· Enclosure PG8 E Letter DCL 99-055 DIABLOCANYON POWER PLANT Annual Radioactive Effluent Release...
Transcript of · Enclosure PG8 E Letter DCL 99-055 DIABLOCANYON POWER PLANT Annual Radioactive Effluent Release...
EnclosurePG&E Letter DCL 99-055
DIABLOCANYON POWER PLANT -—
1998 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT
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January 1 - December 31, 1998
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EnclosurePG8E Letter DCL 99-055
DIABLOCANYON POWER PLANT
ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT
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JANUARY 1 - DECEMBER 31, 1998
EnclosurePG8 E Letter DCL 99-055
DIABLOCANYON POWER PLANT
Annual Radioactive Effluent Release ReportJanuary 1, 1998 Through December 31, 1998
Table of Contents
Introduction
Supplemental Information 4
II.
III.
IV.
V.
VI.
VII.
VIII
IX.
XI.
XII
Major Changes to Liquid, Gaseous, and Solid Radwaste Systems ..........
Changes to the Radiological Monitoring and Controls Program (RMCP) ...
Changes to the Radiological Effluent Controls Program (RECP) ............
Changes to the Environmental Radiological Monitoring (ERMP) ...........
Changes to the Off-Site Dose Calculation Procedure (ODCP) .
Changes to the Process Control Program (PCP)
Land Use Census
Gaseous and Liquid Effluents
TABLE 1 - GASEOUS EFFLUENTS - SUMMATIONOF ALLRELEASES
TABLE2 - GASEOUS EFFLUENTS - GROUND-LEVELRELEASES
TABLE3 - GASEOUS EFFLUENTS - LOWER LIMITSOF DETECTION .
TABLE4 - LIQUIDEFFLUENTS - SUMMATIONOF ALLRELEASES
TABLE5 - LIQUIDEFFLUENTS - NUCLIDES RELEASED
TABLE6 - LIQUID EFFLUENTS - LOWER LIMITSOF DETECTION (LLD) ...
Solid Radwaste Shipments
Radiation Dose Due to Gaseous and Liquid Effluents
TABLE7 - RADIATIONDOSE DUE TO THE RELEASE OF RADIOACTIVELUQUID
EFFLUENTS
TABLE8 - RADIATIONDOSE DUE TO THE RELEASE OF RADIOACTIVEGASEOUS
EFFLUENTS
TABLE9 - PERCENT OF TECHNICALSPECIFICATION LIMITSFOR RADIOACTIVELIQUID
EFFLUENTS
TABLE 10 - PERCENT OF TECHNICALSPECIFICATION LIMITSFOR RADIOACTIVE
GASEOUS EFFLUENTSTABLE 11 - ON-SITE DOSE TO MEMBERS OF THE PUBLIC .
Meteorological Data .
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10
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EnclosurePGSE I etter DCL 99-055
DIABLOCANYON POWER PLANT
Annual Radioactive Effluent Release ReportJanuary 1, 1998 Through December 31, 1998
Attachments
1. Corrections to 1997 Annual Radioactive Effluent Release Report
2. Radiological Monitoring And Controls Program (RMCP), CY2 Revision 2A
3. Radioactive Effluent Control Procedure (RECP), IDAP CY2.ID1 Revision 3A
4. Off-Site Dose Calculation Procedure (ODCP), CAP A-8 Revision 22I
5. Process Control Program, RP2. DC2 Revision 4
6. Process Control Program, RP2. DC2 Revision 5
7. Mobile Service Operating Procedures for Low Level Radioactive Waste Processing,RP2. DC4 Revision 9
8. Land Use Census
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EnclosurePG8E Letter DCL 99-055
DIABLOCANYON POWER PLANT
1998 Annual Radioactive Effluent Release Report
Introduction
The 1998 Annual Radioactive Effluent Release Report summarizes gaseous and liquideffluent releases from Diablo Canyon Power Plant's (DCPP) Units 1 and 2. The reportincludes the dose due to release of radioactive liquid and gaseous effluents-andsummarizes solid radwaste shipments. The report contains information required by Units 1
and 2 Technical Specification (TS) 6.9.1.6 and 6.14 and is presented in the general formatof Regulatory Guide 1.21, Appendix B. Procedure revisions which implement theRadiological Monitoring and Controls Program (RMCP), Radioactive Effluent ControlProcedure (RECP), Off-Site Dose Calculation Procedure (ODCP), and Process ControlProgram (PCP) and three diskettes containing meteorological data are attached.
In all cases, the plant effluent releases were well below TS limits for the report period.
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EnclosurePG8E Letter DCL 99-055
I. Supplemental Information
A. Regulatory Limits
1. Gaseous Effluents
a. Noble Gas Dose Rate Limit
The dose rate in areas at or beyond the site boundary-due to radioactivenoble gases released in gaseous effluents is limited to less than or equal to500 millirem (mR) per year to the total body and less than or equal to 3000mR per year to the skin. [Radioactive Effluent Control Procedure (RECP)[6.1.6.1.a].
b. Particulate and Iodine Dose Rate Limit
The dose rate in areas at or beyond the site boundary due to iodine-131,iodine-133, tritium, and all radionuclides in particulate form with half livesgreater than 8 days in gaseous effluents, is limited to less than or equal to1500 mR per year to any organ. (RECP 6.1.6.1.b).
c. Noble Gas Dose Limit
The air dose due to noble gases released in gaseous effluents from eachreactor unit to areas at or beyond the site boundary is limited to the following:
Radiation Type
GammaBeta
Calendar Quarter LimitRECP 6.1.7.1.a
5 millirad10 millirad
Calendar Year LimitRECP 6.1.7.1.b
10 millirad20 millirad
d. Particulate and iodine Dose Limit
The dose to an individual from iodine 131, iodine 133, tritium, and allradionuclides in particulate form with half lives greater than 8 days in gaseouseffluents released from each reactor unit to areas at or beyond the siteboundary is limited to less than or equal to 7.5 mR to any organ in anycalendar quarter and less than or equal to 15 mR to any organ during acalendar year. (RECP 6.1.8.1).
EnclosurePG8E Letter DCL 99-055
2. Liquid Effluents
a. Concentration
The concentration of radioactive material released from the site is limited tothe concentrations specified in 10 CFR Part 20, Appendix B, Table 2,Column 2, for radionuclides other than dissolved or entrained noble gases.For dissolved or entrained noble gases, the concentration is limited to 2 x 10microcuries/milliliter (pCi/ml) total activity. -(RECP 6:1:3;1).
b. Dose
The dose or dose commitment to a member of the public from radioactivematerials in liquid effluents released from each reactor unit to areas at orbeyond the site boundary is limited to the following:
Dose Type
Total BodyAny Organ
Calendar QuarterLimitRECP 6.1.4.1
1.5 millirem5 millirem
Calendar Year LimitRECP 6.1.4.1
3 millirem10 millirem
B. Maximum Permissible Concentrations
1. Gaseous Effluents
Maximum permissible concentrations are not used for determining allowablerelease rates for gaseous effluents at DCPP.
2. Liquid Effluents
The concentrations listed in 10 CFR 20, Appendix B, Table 2, Column 2, forradionuclides other than dissolved or entrained noble gases are used fordetermining the allowable release concentration at the point of discharge from thesite for liquid effluents. For dissolved or entrained noble gases, the allowablerelease concentration at the point of discharge is limited to 2 x 10~ pCi/ml totalactivity for liquid effluents.
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EnclosurePG8E Letter DCL 99-055
C. Measurements and Approximations of Total Radioactivity
1. Gaseous Effluents
Fission and Activation Gases
The gaseous radioactivity released from the plant vent is monitored by a pairof off-line monitors equipped with beta scintillator detectors. The monitorreadings are correlated to isotopic concentration based on. laboratory isotopicanalysis of grab samples using a germanium detector.
When plant vent measurements, as indicated by the process monitors, arebelow the lower limitof detection, grab samples results are used to quantifyreleases. The individual batch release data are used to quantify theradioactivity discharged from the gas decay tanks and containment.
A noble gas grab sample is obtained and analyzed at least weekly. Theisotopic mixture is assumed to remain constant between grab sampleanalyses.
Containment purges, gas decay tank releases, and air ejector discharges arereleased via the plant vent.
The gaseous radioactivity released from the steam generator blowdown tankvent is measured by analyzing liquid or steam condensate grab samples witha germanium detector. A factor R, a ratio of unit masses between waterflashing to steam and water entering the tank, is used to calculate the activity.The isotopic concentrations are assumed to remain constant between grabsamples.
Other potential pathways for releasing gaseous radioactivity are periodically. monitored by collecting grab samples and analyzing these samples with a
germanium detector system.
b. lodines
Radioiodines released from the plant vent are monitored by continuoussample collection on silver zeolite cartridges. The cartridges are changed atleast weekly and analyzed with a germanium detector. The radioiodinereleases are averaged over the period of cartridge sample collection.
Other potential pathways for releasing radioiodines are periodically monitoredby collecting samples using charcoal cartridges and analyzing with agermanium detector.
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EnclosurePG8 E Letter DCL 99-055
Radioactive materials in particulate form released from the plant vent aremonitored by continuous sample collection on particulate filters. The filtersare changed at least weekly and analyzed with a germanium detector. Theparticulate radioactivity is averaged over the period of particulate filtersamplecollection. Each filter is analyzed for alpha emitters using an internalproportional counter. Plant vent particulate filters collected during a quarterare used for the composite analysis for strontium-89 and -90 which is countedon an internal proportional counter after chemical separation.
Other potential pathways for releasing radioactive particulate are periodicallymonitored by collecting samples using particulate filters and analyzing thesefilters with a germanium detector.
Tritium
Tritium released from the plant vent is monitored by passing a measured'olumeof plant vent sample through a water column and determining the
tritium increase in the water. An aliquot of the water is counted in a liquidscintillation spectrometer. The minimum'routine sample frequency for tritiumis weekly. The tritium concentration is assumed to remain constant betweensamples.
Estimations of Overall Error
Sources of error considered for batch release are: (1) calibration source; (2)calibration counting; (3) sampling; (4) sample counting; and (5) gas decaytank pressure gauge / containment exhaust fan flow rate.
Sources of error for continuous release are: (1) calibration source; (2)calibration counting; (3) sampling; (4) sample counting; (5) process monitor(RE-14) reading (fission gases only); and (6) plant vent exhaust fan flow rate.
'Total error = (@2< + a 2 + ac 3+ a
Where cz, = error associated with each component.
2. Liquid Effluents
Batch Releases
Each tank of liquid radwaste is analyzed for principal gamma emitters using agermanium detector prior to release. A monthly prerelease analysis includesdissolved and entrained gases. Volume proportional monthly and quarterlycomposites are prepared from aliquots of each tank released. The monthlycomposite is analyzed for tritium using a liquid scintillation spectrometer and
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EnclosurePG8E Letter DCL 99-055
gross alpha radioactivity using an internal proportional counter. The quarterlycomposite is analyzed for iron-55 using a liquid scintillation spectrometer andfor strontium-89 and -90 using an internal proportional detector followingchemical separations.
b. Continuous releases
For the continuous liquid releases of the steam generator blowdown tank andturbine building sump oily water separator;-daily-grab samples are collectedand aliquots are proportioned for weekly, monthly, and quarterly composites.
The oily water separator weekly composite is analyzed for principal gammaemitters using a germanium detector. The steam generator blowdown tankweekly composite is analyzed for principal gamma emitters and iodine-131.
The steam generator blowdown tank monthly composite is analyzed for tritiumusing a liquid scintillation spectrometer and for gross alpha using an internalproportional counter.
The steam generator blowdown tank quarterly composite is analyzed for iron-55 using a liquid scintillation spectrometer and for strontium-89 and strontium-90 using an internal proportional counter following chemical separation. Theresults for each of the composites are averaged over the period of thecomposite.
In addition, one grab sample of the steam generator blowdown tank isanalyzed monthly for dissolved and entrained gases using a germaniumdetector. The results of this analysis are assumed to remain constant overthe period of one month.
c. Estimation of Overall Error
Sources of error considered are: (1) calibration source error; (2) calibrationcounting error; (3) sampling error; (4) sample counting error;.and (5) volumeof waste release error.
These sources of error are independent; thus the total error is calculatedaccording to the following formula:
Total error = (a', + a', + a', + ... a',) '"
Where o; = error associated with each component
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EnclosurePG8E Letter DCL 99-055
D. Batch Releases
1. Liquida. Number of batch releasesb. Total time period for batch releasesc. Maximum time period for a batch released. Average time period for a batch releasee. Minimum time period for a batch releasef. Average saltwater flow during batch releases
6471541.38 hours
48.00 hours2.38 hours0.03 hours
— - 1.63E+6 GPM
2. Gaseousa. Number of batch releasesb. Total time period for batch releasesc. Maximum time period for a batch released. Average time per'iod for a batch release,e. Minimum time period for a batch release
135926.82 hours
72.00 hours6.87 hours0.12 hours
E. Abnormal Release (Gaseous and Liquid
From December 24, 1998, through December 31, 1998, an unplanned, butmonitored, release of Unit 1 condensate occurred due to a leak on the CondensateDischarge Overboard Valve CND-1-128. During this event, 3.09E-2 curies of tritiumwere released. The percent of effluent concentration limitwas 5.11 E-4 percent ofthat specified in RMCP IDAP CY2.ID1, step 6.1.3.1.
F. Effluent Monitoring Instrumentation
On March 25, 1998, RE-18 (Liquid Effluent Monitor) alarmed. The alarm was mostlikely due to activated corrosion product accumulation in the piping dead legs sharedby the liquid radwaste system discharge and process pathways. The activatedcorrosion products were transported to the RE-18 monitor during the beginning ofdischarge causing a RCV-18 trip which terminated the release. The residue in theline was then flushed back to the liquid radwaste system after a sample was obtainedand analyzed. The percent of effluent concentration limitwas 1.65 E+0 percent ofthat specified in RMCP IDAP CY2.ID1, step 6.1.3.1.
II. Major Changes to Liquid, Gaseous and Solid Radwaste Treatment System
There were no major changes to liquid, gaseous, and solid radwaste treatment systemsduring the report period.
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EnclosurePG&E Letter DCL 99-055
III. Changes to the RMCP
CY2, "Radiological Monitoring And Controls Program," was revised during the reportperiod. Revision 2A made the following change.
Organizational name was changed from "Chemistry and Environmental Operations" to"Chemistry."
The change was reviewed by the Plant Staff Review Committee (PSRC) and approvedby the Plant Manager on March 26, 1998. (See Attachment 2).
IV. Changes to the RECP
CY2.ID1, "Radioactive Effluent Controls Program," was revised during the report period.Revision 3A made the following change.
Organizational name was changed from "Chemistry and Environmental Operations" to"Chemistry."
The change was reviewed by the PSRC and approved by the Plant Manager onMarch 24, 1998. (See Attachment 3).
V. Changes to the ERMP
There were no changes to RP1.ID11, "Environmental Radiological MonitoringProcedure," during the report period.
Vl. Changes to the ODCP
CAP A-8, "Off-Site Dose Calculations," was revised during the report period. Revision22 made the following changes.
A. The methodology for direct radiation determination using environmental TLDs wasadded.
B. Table 10.2 was updated with the most recent 5-year meteorology data.
These changes were reviewed by the PSRC and approved by the Plant Manager onApril 3, 1998. (See Attachment 4).
Vll. Changes to the Process Control Program
RP2.DC2, "Process Control Program," Revision 4, adopted a revised polymersolidification vendor data sheet.
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EnclosUrePG8E Letter DCL 99-055
March 13, 1998. (See Attachment 5).
RP2.DC2, Revision 5, adopted vendor procedure revisions to change the name of thevendor.
The change was reviewed by the PSRC and approved by the Plant Manager onOctober 2, 1998. (See Attachment 6).
RP2.DC4, "Mobile Service Operating Procedures For Low-level Radioactive WasteProcessing," Revision 9, adopted vendor procedure revisions to change the name ofthe vendor.
The change was reviewed by the PSRC and approved by the Plant Manager onFebruary 27, 1998. (See Attachment 7).
Vill. Land Use Census
Changes to the Land Use Census Program are included as Attachment 8.
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EnclosurePG8 E Letter DCL 99-055
IX. Gaseous and Liquid Effluents
Table 1a
Gaseous Effluents - Summation of All Releases
Units First SecondQuarter Quarter
A. Fission and activation gases
Est. TotalError, %
1. Total release
2. Average release rate for period
3. Percent of technical specification limit"
Ci
pCi/sec
6.38E+0
8.20E-1
1.03E-3
1.16E-1
1.48E-2
4.58E-5
5.98E+1
B. Iodines
1. Total iodine-131
2. Average release rate for period
3. Percent of technical specification limit"
Ci
pCi/sec
1.39E-4
1.78E-5
1.04E-4
MDA
MDA
MDA
2.35E+1
C. Particulate
1. Particulate with half-lives >8 days Ci 1.84E-3 MDA 2.35E+1
2. Average release rate for period
3. Percent of technical specification limit"
ijCi/sec 2.37E-4
9.37E-5
MDA
MDA
4. Gross alpha radioactivity Ci 9.73E-8 1.58E-7
D. Tritium
1. Total release
2. Average release rate for period
3. Percent of technical specification limit"
Ci 7.72E+1
pCi/sec 9.93E+0
2.30E-5
3.28E+1
4.17E+0
9.65E-6
1.30E+1
MDA= Less than the "a posteriori" minimum detectable activity (microcuries per unit mass orvolume). This note applies to all tables.
" RECP 6.1.6.1 Limit
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EnclosurePG&E Letter DCL 99-055
Table 1b
Gaseous Effluents - Summation of All Releases
Units Third FourthQuarter Quarter
Est. TotalError%
A. Fission & activation gases
1. Total release
2. Average release rate for period
3. Percent of technical specification limit"
Ci
ijCi/sec
1.09E-1
1.37E-2
3.96E-5
4.49E+0
5.64E-1
2.10E-4
5.98E+1
B. lodines
1. Total iodine-131
2. Average release rate for period
3. Percent of technical specification limit"
Ci MDA
pCi/sec MDA
MDA
MDA
MDA
MDA
2.35E+1
C. Particulate
1. Particulate with half-lives >8 days
2. Average release rate for period
3. Percent of technical specification limit"
Ci MDA
pCi/sec MDA
MDA
MDA
MDA
MDA
2.35E+1
4. Gross alpha radioactivity Ci 2.98E-7 3.28E-7
D. Tritium
1. Total release
2. Average release rate for period
3. Percent of technical specification limit"
Ci
pCi/sec
3.80E+1 2.93E+1
4.78E+0 3.68E+0
1.10E-5 8.52E-6
1.30E+1
MDA= Less than the "a posteriori" minimum detectable activity (microcuries per unit mass orvolume). This note applies to all tables.
" RECP 6.1.6.1 Limit.
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EnclosurePG8E Letter DCL 99-055
Table 1c
Gaseous Effluents - Summation of All Releases
A. Fission & activation gases
1. Total release
Units
Ci
AnnualTotal
1.11E+1
2. Average release rate for period
3. Percent of technical specification limit"
pCi/sec 3.52E-1
3.28E-4
B. lodines
1. Total iodine-131 Ci 1.39E-4
2. Average release rate for period
3. Percent of technical specification limit"
pCi/sec 4.40E-6
2.57E-5
C. Particulate
1. Particulate with half-lives >8 days
2. Average release rate for period
3. Percent of technical specification limit"
4. Gross alpha radioactivity
Ci
pCi/sec
Ci
1.84E-3
5.84E-5
2.31E-5
'.81E-7
D. Tritium
1. Total release
2. Average release rate for period
3. Percent of technical specification limit"
Ci
ijCi/sec
1.77E+2
5.62E+0
1.30E-5
" RECP 6.1.6.1 Limit.
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EnclosurePG8 E Letter DCL 99-055
Table 2a
Gaseous Effluents - Ground-Level Releases
Nuclides Released Unit
First Quarter
Continuous BatchMode Mode
Second Quarter
Continuous BatchMode Mode
1. Fission gases
argon-41
krypton-85
krypton-85m
krypton-87
krypton-88
xenon-1 31m
xenon-1 33
xenon-133m
xenon-135
xenon-1 35m
xenon-1 38
Total For Period
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
MDA
MDA
MDA
MDA
MDA
MDA
4.52E+0
MDA
MDA
MDA
MDA
4.52E+0
6.66E-1
6.72E-1
3.98E-6
MDA
MDA
MDA
5.18E-1
2.02E-3
1.09E-3
MDA
MDA
1.86E+0
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
3.73E-2
7.63E-2
MDA
MDA
MDA
MDA
2.34E-3
MDA
4.61E-5
MDA
MDA
1.16E-1
2. lodines
iodine-131
iodine-133
iodine-135
Total For Period
Ci
Ci
Ci
Ci
1.39E-4
MDA
MDA
1.39E-4
MDA
MDA
MDA
MDA
MDA= Less than the "a posteriori" minimum detectable activity (microcuries per unit mass or
volume). This note applies to all tables.
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EnclosurePG8 E Letter DCL 99-055
Table 2a (Continued)
Gaseous Effluents - Ground-Level Releases
Continuous Mode
Nuclides Released Unit First Quarter Second Quarter
3. Particulate
barium-140
cesium-134
cesium-137
cerium-141
cerium-144
chromium-51
cobalt-57
cobalt-58
cobalt-60
iron-59
lanthanum-1 40
manganese-54
molybdenum-99
niobium-95
ruthenium-103
strontium-89
strontium-90
zinc-65
zirconium-95
Total For Period
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
MDA
MDA
MDA
MDA
MDA
2.33E-5
MDA
1.82E-3
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
1.84E-3
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA= Less than the "a posteriori" minimum detectable activity (microcuries per unit mass orvolume). This note applies to all tables.
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EnclosurePGLE Letter DCL 99-055
Table 2b
Gaseous Effluents - Ground-Level Releases
Third Quarter Fourth Quarter
Nuclides Released Unit Continuous Batch ModeMode
Continuous BatchMode Mode
1 ~ Fission gases
argon-41
krypton-85
krypton-85m
krypton-87
krypton-88
xenon-131m
xenon-1 33
xenon-1 33m
xenon-135
xenon-135m
xenon-1 38
Total For Period
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
3.22E-2
6.00E-2
MDA
MDA
MDA
MDA
1.64E-2
MDA
1.65E-5
MDA
MDA
1.09E-1
MDA
MDA
MDA
MDA
MDA
MDA
4.36E+0
MDA
MDA
MDA
MDA
4.36E+0
2.58E-2
MDA
MDA
MDA
MDA
MDA
9.96E-2
MDA
3.71E-4
MDA
MDA
1.26E-1
2. lodines
iodine-1 31
iodine-133
iodine-135
Total for period
Ci
Ci
Ci
Ci
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA= Less than the "a posteriori" minimum detectable activity (microcuries per unit mass orvolume). This note applies to all tables.
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EnclosurePGSE Letter DCL 99-055
Table 2b (Continued)
Gaseous Effluents - Ground-Level Releases
Nuclides Released Unit
Continuous Mode
Third Quarter Fourth Quarter
3. Particulates
barium-140
cesium-134
cesium-137
cerium-141
cerium-144
chromium-51
cobalt-57
cobalt-58
cobalt-60
iron-59
lanthanum-140
manganese-54
molybdenum-99
niobium-95
ruthenium-103
strontium-89
strontium-90
zinc-65
zirconium-95
Total For Period
Ci
Ci
Ci
,Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
'MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA= Less than the "a posteriori" minimum detectable activity (microcuries per unit mass orvolume). This note applies to ail tables.
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Table 3
Gaseous Effluents - Lower Limits of Detection
Batch Mode
Nuclide ~ Unit ContinuousMode
ContainmentPurge
Gas DecayTank
1 ~ Fission gases
argon-41
krypton-85
krypton-85m
krypton-87
krypton-88
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
2.05E-S
2.99E-6
6.91E-9
3.18E-8
2.80E-8
2.05E-8
2.99E-6
6.91E-9
3.18E-S
2.80E-S
6.91E-8
7.84E-6
1.54E-8
5.74E-S
5.54E-S
xenon-131m
xenon-133
xenon-133m
xenon-1 35
pCi/ml
pCi/ml
pCi/ml
pCi/ml
xenon-1 35m pCi/ml
2.59E-7
2.14E-8
6.84E-8
6.84E-9
1.41E-7
2.59E-7
2.14E-8
6.84E-8
6.84E-9
1.41E-7
5.32E-7
5.06E-S
1.48E-7
1.48E-S
4.79E-7
xenon-138 pCi/mi 4.94E-7 4.94E-7 1.11E-6
2. Tritium
, hydrogen-3 pCi/ml 4.74E-9 4.74E-9
3. lodines
iodine-131
iodine-1 33
iodine-1 35
pCi/ml
pCi/ml
pCi/ml
5.19E-13
6.00E-13
3.27E-12
-19-
EnclosurePG&E Letter DCL 99-055
Table 3 (Continued)
Gaseous Effluents - Lower Limits of Detection
Nuclide Unit Continuous Mode
4. Particulate
barium-140
cerium-141
cerium-144
cesium-134
cesium-137
chromium-51
cobalt-57
cobalt-58
cobalt-60
iron-59
lanthanum-140
manganese-54
molybdenum-99
ruthenium-1 03
strontium-89
strontium-90
zinc-65
gross alpha
pCi/ml
pCi/ml
pCi /m
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/m
pCi/ml
1.93E-12
4.30E-13
1.44E-12
3.50E-13
4.70E-13
2.96E-12
2.06E-13
6.92E-13
1.03E-12
1.01E-12
6.71E-13
4:63E-13
1.95E-13
4.35E-13
4.70E-15
1.78E-15
1.30E-12
1.36E-15
-20-
EnclosurePG&E Letter DCL 99-055
Table 4a
Liquid Effluents - Summation of All Releases
Unit FirstQuarter
SecondQuarter
Est. TotalError, %
A. Fission and activation products
1. Total release (not includingtritium, gases, alpha)
2. Average diluted concentrationduring period
3. Percent of applicable limit"
Ci
pCi/ml
3.20E-1
1.43E-10
9.22E-4
1.14E-1
4.19E-11
2.58E-4
2.35E+1
B. Tritium
1. Total release
2. Average diluted concentrationduring period
3. Percent of applicable limit"
Ci
pCi/ml
5.16E+2
2.31E-7
2.31E-2
2.78E+2
1.02E-7
1.02E-2
1.30E+1
C. Dissolved and entrained gases
1. Total release
2. Average diluted concentrationduring period
3. Percent of applicable limit"
Ci
pCi/ml
6.69E-4
3.00E-13
1.50E-7
4.77E-6
1.75E-15
8.75E-10
2.35E+1
D. Gross alpha radioactivity
1. Total release Ci MDA MDA 6.10E+1
MDA= Less than the "a posteriori" minimum detectable activity (microcuries per unit mass orvolume). This note applies to all tables.
'RECP 6.1.6.1 Limit
-21-
EnclosurePGSE Letter DCL 99-055
Table 4a (Continued)
Liquid Effluents - Summation of All Releases
Unit FirstQuarter
SecondQuarter
Est. TotalError, %
E. Volume of waste released(prior to dilution)
liters 7.74E+7 8.12E-7 5.0E+0
F. Volume of circulating saltwater litersused during the release
2.23E+12 2.73E+12 6.5E+0
-22-
EnclosurePG8E Letter DCL 99-055
Table 4b
Liquid Effluents - Summation of All Releases
Unit ThirdQuarter
FourthQuarter
Est. TotalError, %
A. Fission and activation products
1. Total release (not includingtritium, gases, alpha)
2. Average diluted concentrationduring period
3. Percent of applicable limit"
Ci
pCi/ml
2.72E-2
1.02E-11
8.93E-5
7.50E-2
2.83E-11
3.53E-4
2.35E+1
B. Tritium
1. Total release
2. Average diluted concentrationduring period
3. Percent of applicable limit"
Ci
pCi/ml
2.17E+2
8.14E-8
8.14E-3
2.74E+2
1.03E-7
1.03E-2
1.30E+1
C. Dissolved and entrained gases
1. Total release
2. Average diluted concentrationduring period
3. Percent of applicable limit"
Ci
pCi/ml
2.66E-5
1.00E-14
5.00E-9
7.20E-4
2.72E-13
1.36E-7
2.35E+1
D. Gross alpha radioactivity
1. Total release Ci MDA MDA 6.10E+1
MDA= Less than the "a posteriori" minimum detectable activity (microcuries per unit mass orvolume). This note applies to all tables.
" RECP 6.1.6.1 Limit
-23-
EnclosurePG8 E Letter DCL 99-055
Table 4b (Continued)
Liquid Effluents - Summation of All Releases
Unit ThirdQuarter
FourthQuarter
Est. TotalError, %
E. Volume of waste released(prior to dilution)
liters 8.04E+7 8.27E+7 5.0E+0
F. Volume of circulating saltwater liters 2.66E+12used during release
2.65E+12 6.5E+0
i
-24-
EnclosurePG8 E Letter DCL 99-055
Table 4c
Liquid Effluents - Summation of All Releases
Unit Annual Total
A. Fission and activation products
1. Total release (not including tritium,gases, alpha)
2. Average diluted concentrationduring period
3. Percent of applicable limit"
Ci
pCi/ml
'5.36E-1
5.22E-11
3.83E-4
B. Tritium
1. Total release
2. Average diluted concentrationduring period during period
3. Percent of applicable limit"
Ci
pCi/ml
1.28E+3
1.25E-7
1.25E-2
C. Dissolved and entrained gases
1. Total release
2. Average diluted concentrationduring period during period
3. Percent of applicable limit"
Ci
pCi/ml
1.42E-3
1.38E-13
6.92E-8
D. Gross alpha radioactivity
1. Total release Ci MDA
" RECP 6.1.3.1 Limit
MDA= Less than the "a posteriori" minimum detectable activity (microcuries per unit mass orvolume). This note applies to all tables.
-25-
EnclosurePG8E Letter DCL 99-055
Table 4c (Continued)
Liquid Effluents - Summation of All Releases
Unit Annual Total
E. Volume of waste released (prior todilution)
liters 3.22E+8
F. Volume of circulating saltwater usedduring release
liters 1.03E+13
-26-
J
EnclosurePG8 E Letter DCL 99-055
Table 5a
Liquid Effluents - Nuclides Released
First Quarter Second Quarter
Nuclides Released
antimony-1 22
antimony-124
antimony-1 25
barium-140
beryllium-7
bromine-82
cerium-141
cerium-143
cerium-144
cesium-134
cesium-136
cesium-1 37
cesium-1 38
chromium-51
cobalt-57
cobalt-58
cobalt-60
iron-55
iron-59
lanthanum-140
Unit
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
ContinuousModeMDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
2.20E-4
MDA
MDA
MDA
MDA
Batch Mode
1.63E-3
5.60E-3
6.16E-2
7.83E-7
MDA
MDA
9.30E-6
MDA
MDA
MDA
MDA
1.06E-3
3.17E-5
2.73E-2
4.82E-4
1.71E-1
1.87E-2
1.77E-2
2.28E-3
1.75E-4
ContinuousModeMDA
'DA'DA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
'DA
MDA
MDA
MDA
MDA
MDA
Batch Mode
MDA
1.39E-3
2.19E-2
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
8.70E-5
MDA
3.05E-3
2.25E-4
7.20E-2
6.05E-3
6.39E-3
1.93E-4
MDA
MDA= Less than the "a posteriori" minimum detectable activity (microcuries per unit mass orvolume). This note applies to all tables.
-27-
EnclosurePG8E Letter DCL 99-055
Table 5a (Continued)
Liquid Effluents - Nuclides Released
First Quarter Second Quarter
Nuclides Released
lanthanum-142
manganese-54
manganese-56
molybdenum-99
niobium-95
niodymium-147
rubidium-89
ruthenium-1 03
silver-110m
sodium-24
strontium-89
strontium-90
strontium-91
strontium-92
tellurium-129m
tellurium-1 31
tellurium-1 32
tin-113
Unit
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
ContinuousModeMDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA"
MDA'DA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
Batch Mode
MDA
1.86E-3
MDA
2.15E-4
3.27E-3
1.82E-5
MDA
1.44E-4
8.09E-5
5.76E-5
MDA
MDA
MDA
MDA
5.61E-4
MDA
1.42E-3
4.61E-4
ContinuousNlodeMDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
Batch Mode
MDA
6.54E-4
MDA
2.96E-5
9.91E-4
MDA
MDA
6.86E-6
3.97E-4
4.20E-6
MDA
MDA
MDA
MDA
MDA
MDA
MDA
5.37E-5
MDA= Less than the "a posteriori" minimum detectable activity (microcuries per unit mass orvolume). This note applies to all tables.
-28-
EnclosurePG8E Letter DCL 99-055
Table 5a (Continued)
Liquid Effluents - Nuclides Released
First Quarter Second Quarter
Nuclides Released
tin-117m
tungsten-1 87
zinc-65
zirconium-95
iodine-1 31
iodine-1 32
iodine-133
iodine-134
iodine-135
Total For Period
Unit
,Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
ContinuousModeMDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
2.20E-4
BatchMode
1.65E-4
MDA
MDA
1.95E-3
6.38E-4
1.24E-3
3.63E-4
2.33E-7
3.72E-5
3.20E-1
ContinuousNlodeMDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
BatchMode
3.31E-5
MDA
7.60E-5
4.56E-4
1.38E-4
MDA
5.08E-5
MDA
MDA
1.14E-1
Dissolved And Entrained Gases
xenon-133
xenon-1 33m
xenon-1 35
krypton-85
krypton-87
krypton-88
Total For Period
Ci
Ci
Ci
Ci
Ci
Ci
MDA
MDA
MDA
MDA
MDA
MDA
MDA
5.60E-4
MDA
1.10E-4
MDA
MDA
MDA
6.69E-4
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
4.77E-6
MDA
MDA
MDA
4.77E-6
MDA= Less than the "a posteriori" minimum detectable activity (microcuries per unit mass orvolume). This note applies to all tables.
-29-
0'I
I
EnclosurePG8 E Letter DCL 99-055
Table 5b
Liquid Effluents - Nuclides Released
Third Quarter Fourth Quarter
Nuclides Released
antimony-122
antimony-124
Unit
Ci
Ci
ContinuousModeMDA
MDA
Batch Mode
MDA
ContinuousModeMDA
4.94E-5 'DABatch Nlode
MDA
MDA
antimony-1 25
barium-140
. beryllium-7
bromine-82
cerium-141
cerium-143
cerium-144
cesium-1 34
cesium-136
cesium-1 37
cesium-1 38
chromium-51
cobalt-57
cobalt-58
cobalt-60
iron-55
iron-59
lanthanum-1 40
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
5.82E-3
MDA
MDA
MDA
MDA
MDA
MDA
5.21E-6
MDA
1.46E-4
MDA
MDA
6.66E-5
1.11E-2
2.54E-3
6.24E-3
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
1.02E-2
MDA
MDA
MDA
MDA
MDA
MDA
7.67E-6
MDA
2.06E-4
MDA
MDA
1.35E-4
8.37E-3
1.59E-2
3.50E-2
MDA
MDA
MDA= Less than the "a posteriori" minimum detectable activity (microcuries per unit mass orvolume). This note applies to all tables.
- 30-
EnclosurePG8E Letter DCL 99-055
Table 5b (Continued)
Liquid Effluents - Nuclides Released
Third Quarter Fourth Quarter
Nuclides Released
lanthanum-1 42
manganese-54
manganese-56
molybdenum-99
niobium-95
neodymium-147
rubidium-89
ruthenium-103
silver-110m
sodium-24
strontium-89
strontium-90
strontium-91
strontium-92
tellurium-129m
tellurium-1 31
tellurium-132~
tin-113
tin-117m
tungsten-187
zinc-65
Unit
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
Ci
ContinuousModeMDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
Batch Mode
1.17E-6
2.35E-4
MDA
2.65E-5
1.61E-4
MDA
MDA
MDA
6.16E-6
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
2.58E-6
MDA
MDA
5.51E-5
ContinuousModeMDA
- MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
MDA
Batch Mode
MDA
6.54E-4
MDA
1.17E-4
1.18E-4
MDA
MDA
MDA
1.18E-4
MDA
MDA
MDA
MDA
MDA
MDA
MDA
2.73E-6
1.64E-5
MDA
MDA
1.32E-3
-31-
EnclosurePG8 E Letter DCL 99-055
Table 5b (Continued)
Liquid Effluents - Nuclides Released
Third Quarter Fourth Quarter
Nuclides Released
zirconium-95
iodine-1 31
iodine-1 32
iodine-1 33
iodine-1 34
iodine-1 35
Total For Period
Unit
Ci
Ci
Ci
Ci
Ci
Ci
Ci
ContinuousModeMDA
MDA
MDA
MDA
MDA
MDA
MDA
Batch Mode
5.80E-5
5.08E-4
MDA
1.35E-4
MDA
MDA
2.72E-2
ContinuousModeMDA
MDA
MDA
MDA
MDA
MDA
MDA
Batch Mode
MDA
2.34E-3
MDA
4.65E-4
MDA
MDA
7.50E-2
Dissolved And Entrained Gases
xenon-133
xenon-1 33m
xenon-1 35
krypton-85
krypton-87
krypton-88
Total For Period
Ci
Ci
Ci
Ci
Ci
Ci
Ci
MDA
MDA
MDA
MDA
MDA
MDA
MDA
2.01E-5
MDA
6.51E-6
MDA
MDA
MDA
2.66E-5
MDA
MDA
MDA
MDA
MDA
MDA
MDA
7.10E-4
MDA
1.93E-5
MDA
MDA
MDA
7.20E-4
MDA= Less than the "a posteriori" minimum detectable activity (microcuries per unit mass orvolume). This note applies to all tables.
-32-
k
EnclosurePG8 E Letter DCL 99-055
Nuclide
antimony-1 22
antimony-124
antimony-1 25
barium-140
beryllium-7
bromine-82
cerium-141
cerium-143
cerium-144
cesium-1 34
cesium-1 36
cesium-137
cesium-1 38
chromium-51
cobalt-57
cobalt-58
cobalt-60
iron-55
iron-59
lanthanum-140
lanthanum-142
manganese-54
manganese-56
molybdenum-99
Table 6
Liquid Effluents - Lower Limits of Detection (LLD)
Unit
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
LLD
5.71E-8
1.04E-7
8.55E-8
1.73E-7
3.34E-7
5.11E-8
3.73E-8
7.53E-8
1.89E-7
3.93E-8
5.14E-8
5.51E-8
3.00E-7
3.04E-7
2.28E-8
4.41E-8
5.80E-8
3.00E-7
9.66E-8
6.40E-8
1.19E-7
5.84E-8
3.52E-7
2.06E-8
-33-
EnclosurePG8 E Letter DCL 99-055
niobium-95
Nuclide
Table 6 (Continued)
Liquid Effluents - Lower Limits of Detection (LLD)
Unit
pCi/ml
LLD
4.86E-8
neodymium-147
rubidium-89
ruthenium-1 03
silver-110m
sodium-24
strontium-89
strontium-90
strontium-91
strontium-92
tellurium-1 29m
tellurium-1 31
tellurium-1 32
tin-113
tin-117m
tungsten-1 87
zinc-65
zirconium-95
gross alpha
hydrogen-3
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
1.20E-7
1.56E-6
4.13E-8
4.89E-S
7.56E-S
4.20E-S
1.50E-8
8.05E-8
8.41E-S
1.32E-6
1.65E-7
3.30E-8
4.52E-S
2.21E-S
1.17E-7
1.18E-7
7.05E-S
9.17E-8
4.47E-6
-34-
EnclosurePG8 E Letter DCL 99-055
Table 6 (Continued)
Liquid Effluents - Lower Limits of Detection (LLD)
iodine-131
iodine-1 32
iodine-1 33
iodine-1 34
iodine-1 35
xenon-133
Nuclide Unit
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
LLD
3.65E-8
5.78E-8
4.16E-8
8.60E-8
2.61E-7
, 1.01E-7
xenon-1 33m
xenon-135
krypton-85
krypton-87
krypton-88
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
2.29E-7
2.60E-8
1.29E-5
9.64E-8
1.13E-7
-35-
EnclosurePG8 E Letter DCL 99-055
X. Solid Radwaste Shipments
Solid Waste and Irradiated fuel Shipment
A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)
1. Type of Waste Unit 12 Month Period Est. Total Error,
a. Spent Resins, Filter Sludges,Evaporator Bottoms, etc.
b. Dry Compressible Waste,Contaminated Equipment, etc.
c. Irradiated Components, ControlRods, etc.
d. Other
m3Ci
m3Ci
m3Ci
m3Ci
9.20E+0
3.77E+2'.62E+1
5.01E+0
0.00E+00.00E+0
0.00E+00.00E+0
0.00E+04.92E+0
0.00E+01.00E+1
0.00E+00.00E+0
0.00E+00.00E+0
2. Estimate of Major Nuclide Composition (by type of waste)
Fe-55
Co-60
Ni-63
Cs-137
Mn-54
43
30
17
b. Fe-55
Co-58
Co-60
Zr-95
Ni-63
Sb-125
H-3
C-14
Cr-51
41
10
Not Applicable N/A
Not Applicable N/A
-37-
EnclosurePG8 E Letter DCL 99-055
Solid Waste and Irradiated Fuel Shipment (Continued)
3. Solid Waste Disposition
Number of Shipments
36
Mode ofTransportation
Truck
Truck
Rail
Destination
BURNWELL, SC
ENVIROCARE, UT
ENVIROCARE, UT
4. Supplemental Information Required by TS 6.9.1.6
Solidification Agent
CementMetalVESNoneNone
Type of Container
Strong TightType A, Metal HIC
Strong TightType A, Poly HIC
Strong Tight
No. ofContainers
97
10 CFR 61WasteClass
ASAU
AU
Shipping Type
LSA II
LSA II
LSA II
LSA II (LSA Cask)LSA II
B. Irradiated Fuel Shipments (Disposition)
Number of Shipments
None
Mode of Transportation
N/A
Destination
N/A
-38-
EnclosurePG&E Letter DCL 99-055
XI. Radiation Dose Due to Gaseous and Liquid Effluents
Radiation Doses
A. Radiation doses from radioactive liquid effluents
The radiation dose contributions due to releases of radioactive liquid effluents to thetotal body and each individual organ for the maximum exposed adult have beencalculated in accordance with the methodology in the ODCP;-Dose contributionslisted in Table 7 show conformance to RECP 6.1.4.1.
B. Radiation doses from radioactive gaseous effluents
The radiation dose contributions due to radioactive gaseous effluents at the siteboundary for the land sectors have been calculated in accordance with thecalculation meth'odology in the ODCP. Each unit's dose contribution has beencalculated separately. The latest five year historical average meteorologyconditions were used in these calculations. In addition to the site boundary doses,the dose to an individual (critical receptor) due to radioiodines, tritium, andparticulates released in gaseous effluents with half-lives greater than,8 days isdetermined in accordance with the methodology in the ODCP based on themethodology described in NUREG 0133. Dose contributions listed in Table 8,which represents the maximum dose for age groups, organs, and geographiclocations for the report period, show conformance to RECP 6.1.6.1, 6.1.7.1, and6.1.8.1.
C. Radiation Doses from Direct Radiation (Line-of-Sight Plus Sky-Shine)-Closest Site Boundary (800 m)
For the report period, the radiation dose is evaluated to be 8.72E-2 mrem due tothe presence of radioactive waste containers outside of plant buildings and thestorage of contaminated tools and equipment inside plant buildings.
D. Radiation Doses from Chemistry Laboratory Radioactive Gaseous Effluents-Closest Site Boundary (800m)
The radiation doses due to chemistry laboratory radioactive gaseous effluents forthe report period is evaluated to be 2.31E-6 mrem.
E. Radiation Doses from Post-accident Sampling System Radioactive GaseousEffluents - Closest Site Boundary (800m)
The radiation doses due to post-accident sampling system radioactive gaseouseffluents for the report period is evaluated to be 2.29E-6 mrem.
- 39-
EnclosurePG8E Letter DCL 99-055
F. 40CFR190 Considerations
The release of radioactivity in liquid and gaseous effluents during 1998 resulted indoses that are small percentages of the TS limits as shown in Tables 9 and 10.This, coupled with the fact that there are no other uranium fuel cycle sources withineight kilometers of the DCPP, shows conformance to 40CFR190.
G. Radiation Doses from Radioactive Liquid And Gaseous Effluents to Membersof the Public Due To Their Activities Inside The Site Boundary..
1. Liquid Effluents
The radiation dose to members of the public within the site boundary due to therelease of radioactive liquid effluents is negligible because the discharge piping forliquid radwaste is mostly imbedded in concrete, located in remote or inaccessibleareas, or is underground. In addition, the quantity of radioactivity released was verylow during 1998.
2. Gaseous Effluents
The radiation dose to members of the public within the site boundary due to therelease of radioactive gaseous effluents are listed in Table 11 for the year of 1998.
-40-
EnclosurePG8E Letter DCL 99-055
Table 7
Radiation Dose Due to the Release of Radioactive Liquid Effluents
INillirem
Total Body
Bone
Liver
Thyroid
Kidney
Lung
G.l. LLI
FirstQuarter5.86E-4
9.05E-4
1.07E-3
1.21E-4
7.67E-5
4.54E-4
7.85E-3
SecondQuarter1.28E-4
1.85E-4
2.07E-4
2.97E-5
3.77E-5
9.39E-5
1.61E-3
ThirdQuarter6.47E-5
1.71E-4
1.54E-4
4.48E-5
2.84E-5
8.20E-5
3.38E-4
FourthQuarter3.80E-4
1.09E-3
1.07E-3
1A8E-4
2.59E-4
4.04E-4
1.11E-3
AnnualTotal
1.16E-3
2.36E-3
2.51E-3
3.43E-4
4.02E-4
1.03E-3
1.09E-2
-41-
nclosurePG8 E Lette L 99-055
Table Sa
Radiation Dose Due to the Release of Radioactive Gaseous Effluents (Unit 1)
Site Boundary
First Second Third Fourth AnnualQuarter Dose Quarter Dose Quarter Dose Quarter Dose Total Dose
Noble GasGamma Air DoseBeta Air Dose
mradmrad
3.87E-51.89E-4
4.16E-54.02E-5
2.82E-53.00E-5
2.18E-57.80E-6
1.30E-42.67E-4
Nearest Residence - NNNP
First Second Third Fourth AnnualQuarter Dose Quarter Dose Quarter Dose Quarter Dose Total Dose
I P TCritical Receptor (Highest
Organ)mrem 3.55E-4 2.05E-4 2.34E-4 1.97E-4 9.90E-4
Nearest Vegetable Garden-ESE"
First Second Third Fourth AnnualQuarter Dose Quarter Dose Quarter Dose Quarter Dose Total Dose
I
PT'ritical Receptor (HighestOrgan)
mrem 2.94E-4 1.70E-4 1.94E-4 1.63E-4 8.22E-4
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0 V
—nclosurePG8 E Lette L 99-055
Table Sb
Radiation Dose Due to the Release of Radioactive Gaseous Effluents (Unit 2)
Site Boundary
First Second Third Fourth AnnualQuarter Dose Quarter Dose Quarter Dose Quarter Dose Total Dose
Noble GasGamma Air DoseBeta Air Dose
mradmrad
1.30E-31.30E-3
1.83E-56.85E-6
2.45E-51.12E-5
2.90E-48.12E-4
1.64E-32.13E-3
Nearest Residence -NNW'irst Second Third Fourth Annual
Quarter Dose Quarter Dose Quarter Dose Quarter Dose Total Dose
I P TCritical Receptor (HighestOrgan)
mrem 1.50E-3 2.41E-4 2.81E-4 2.01E-4 2.22E-3
Nearest Vegetable Garden-ESE'irst Second Third Fourth Annual
Quarter Dose Quarter Dose Quarter Dose Quarter Dose Total Dose—
I
PT'ritical Receptor (HighestOrgan)
mrem 1.17E-3 2.00E-4 2.33E-4 1.67E-4 1.77E-3
-43-
EnclosurePG8E Letter DCL 99-055
Notes for Tables Sa And Sb
1. This represents the maximum dose of age groups, organs, and geographic locations for the quarterand the year.
'. Radioiodines, radioactive material in particulate form and radionuclides other than noble gases withhalf-lives greater than eight days.
3. The inhalation and ground plane pathways are included for this-location.
4. The inhalation, ground plane, and vegetable pathways are included for this location. An occupancyfactor of 0.5 was used for the inhalation and ground plane pathways. The teen age group had thehighest calculated dose for this location.
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EnclosurePG8 E Letter DCL 99-055
Table 9
Percent of Technical Specification Limits for Radioactive Liquid Effluents
ORGAN FirstQuarter
SecondQuarter
Percent
ThirdQuarter
FourthQuarter
AnnualTotal
Total Body 3.91E-2 8.55E-3 4.31E-3 2.54E-2 3.87E-2
Bone
Liver
Thyroid
Kidney
Lung
G.l. LLI
1.81E-2
2.15E-2
2.42E-3
1.53E-3
9.07E-3
1.57E-1
3.71E-3
4.13E-3
5.93E-4
7.54E-4
1.88E-3
3.23E-2
3.41E-3
3.08E-3
8.96E-4
5.67E-4
1.64E-3
6.76E-3
2.19E-2
2.15E-2
2.95E-3
5.18E-3
8.08E-3
2.22E-2
2.36E-2
2.51E-2
3A3E-3
4.02E-3
1.03E-2
1.09E-1
NOTE:
" RECP 6.1.4.1.
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0
nclosurePG8 E Lett L 99-055
Table 10a
Percent of Technical Specification Limits'for Radioactive Gaseous Effluents (Unit 1)
Site Boundary
First SecondQuarter % of Quarter% of
TS Limit TS Limit
Third FourthQuarter% of Quarter% of
TS Limit TS Limit
AnnualTotal % ofTS Limit
Noble GasGamma Air DoseBeta Air Dose
mradmrad
7.74E-41.89E-3
8.32E-44.02E-4
5.63E-43.00E-4
4.37E-47.80E-5
1.30E-31.34E-3
Nearest Residence - NNW
First SecondQuarter % of Quarter% of
TS Limit TS Limit
Third FourthQuarter% of Quarter% of
TS Limit TS Limit
AnnualTotal % ofTS Limit
I PTCritical Receptor (Highest
Organ)mrem 4.73E-3 2.73E-3 3.12E-3 2.63E-3 6.60E-3
Nearest Vegetable Garden - ESE
FirstQuarter % of
TS Limit
Second ThirdQuarter% of Quarter% of
TS Limit TS Limit
FourthQuarter % of
TS Limit.
AnnualTotal % ofTS Limit
I PTCritical Receptor (Highest
Organ)mrem 3.92E-3 2.27E-3 2.59E-3 2.18E-3 5.48E-3
NOTE:'ECP 6.1.6.1, 6.1.7.1, and
6.1.8.1
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s I
nclosurePG8 E Lette L 99-055
Table 10b
Percent of Technical Specification Limits'forRadioactive Gaseous Effluents (Unit 2)
Site Boundary
First Second Third Fourth AnnualQuarter% of Quarter% of Quarter% of Quarter% of Total % of
TS Limit TS Limit TS Limit TS Limit TS Limit
Noble GasGamma Air DoseBeta Air Dose
mradmrad
2.61E-21.30E-2
3.67E-46.85E-5
4.89E-41.12E-4
5.80E-38.12E-3
1.64E-21.07E-2
Nearest Residence - NNW
First Second ThirdQuarter% of Quarter% of Quarter% of
TS Limit TS Limit TS Limit
FourthQuarter % of
TS Limit
AnnualTotal % ofTS Limit
I PTCritical Receptor (Highest Organ) mrem 2.00E-2 3.21E-3 3.74E-3 2.68E-3 1.48E-2
Nearest Vegetable Garden - ESE
First SecondQuarter% of Quarter% of
TS Limit TS Limit
Third FourthQuarter% of Quarter% of
TS Limit TS Limit
AnnualTotal % ofTS Limit
IPTCritical Receptor (Highest Organ) mrem 1.56E-2 2.67E-3 3.11E-3 2.23E-3 1.18E-2
NOTE:'ECP 6.1.6.1, 6.1.7.1, and6.1.8.1
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I P
nclosurePG8 E Lette L 99-055
Table 11a
Radiation Dose Due to Release of Radioactive Gaseous EffluentsFirst Quarter, 1998
On-Site Dose to Members of the Public(Special Interest Groups)
External Dose (mrem)
Noble Gas
Internal Dose(m rem)
lodines, Particulate, and Tritium
Specific ActivityExposureLocation(Sectors)
Exposure ExposureClosest TimeDistance (Hours)
Whole Body Skin Ground Plane Inhalation
Police at ShootingRangeTour Participants
(a) Simulator Bldg.
(b) Bio Lab
(c) OverlookAmerican Indiansat Burial GroundsRanch hands drivingcattle around site
SE
S
SSE
NWNNWNW
NNWN
NNENE
700m
310m
460m
210m200m200m250m350m320m450m630m
52
1.0
1.5
252424.25.25.25.25.25
4.73E-5
6.20E-7
9.30E-7
4.31E-71.71E-41.20E-41.19E-64.58E-73.04E-71.19E-76.05E-S
8.33E-5
'.09E-6
1.64E-6
7.60E-73.02E-42.11E-42.11E-68.06E-75.36E-72.10E-71.07E-7
4.19E-5
2.91E-7
6.61E-7
9.50E-S4.33E-52.47E-53.18E-71.07E-75.40E-S
— 2.33E-S1.43E-S
3.44E-4
4.51E-6
6.76E-6
3.14E-61.24E-38.71E-48.69E-63.33E-62.21E-68.65E-74.40E-7
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nclosurePG8 E Lette L 99-055
Table 11b
Radiation Dose Due to Release of Radioactive Gaseous EffluentsSecond Quarter, 1998
On-Site Dose to Members of the Public(Special Interest Groups)
External Dose (mrem)
Noble Gas
Internal Dose(mrem)
lodines, Particulate, and TritiumSpecific Activity
Police at ShootingRangeTour Participants
(a) Simulator Bldg.
(b) Bio Lab
(c) OverlookAmerican Indiansat Burial GroundsRanch hands drivingcattle around site
ExposureLocation(Sectors)
SE
SSE
NWNNWNW
NNWN
NNENE
ExposureClosestDistance
700m
310m
460m
210m200m200m250m350m320m450m630m
ExposureTime
(Hours)52
1.0
1.5
252424.25.25.25.25.25
Whole Body
2.13E-6
2.79E-S
4.18E-S
1.94E-S7.70E-65.39E-65.37E-82.06E-81.37E-85.34E-92.72E-9
Skin
3.76E-6
4.93E-S
7.39E-S
3.43E-S1.36E-59.53E-69.50E-S3.64E-82.42E-S9.45E-94.81E-9
Ground Plane
0.00E+0
0.00E+0
0.00E+0
0.00E+00.00E+00.00E+00.00E+00.00E+00.00E+00.00E+00.00E+0
Inhalation
1.34E-4
1.76E-6
2.64E-6
1.23E-64.87E-43.41E-43.40E-61.30E-68.64E-73.38E-71.72E-7
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0
nclosurePG8 E Lett L 99-055
Table 11c
Radiation Dose Due to Release of Radioactive Gaseous EffluentsThird Quarter, 1998
On-Site Dose to Members of the Public(Special Interest Groups)
External Dose (mrem)
Noble Gas
Internal Dose, (mrem)
lodines, Particulate, and TritiumSpecific Activity
Police at ShootingRangeTour Participants
(a) Simulator Bldg.
(b) Bio Lab
(c) OverlookAmerican Indiansat Burial GroundsRanch hands drivingcattle around site
ExposureLocation(Sectors)
SE
SSE
NWNNWNW
NNWN
NNENE
ExposureClosestDistance
700m
310m
460m
210m200m200m250m350m320m450m630m
ExposureTime
(Hours)52
1.0
1.5
252424.25.25.25.25.25
Whole Body
1.01E-5
1.32E-7
1.98E-7
9.19E-S3.65E-52.55E-52.55E-79.75E-S6.47E-S2.53E-S1.29E-8
Skin
2.26E-5
2.97E-7
4.45E-7.
2.07E-78.20E-55.74E-55.72E-72.19E-71.46E-75.69E-S2.90E-S
Ground Plane
0.00E+0
0.00E+0
0.00E+0
0.00E+00.00E+00.00E+00.00E+00.00E+00.00E+00.00E+00.00E+0
Inhalation
1.56E-4
2.04E-6
3.06E-6
1 42E-65.64E-43.94E-43.93E-61.51E-61.00E-63.91E-71.99E-7
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nclosurePG&E Lett L 99-055
Table 11d
Radiation Dose Due to Release of Radioactive Gaseous EffluentsFourth Quarter, 1998
On-Site Dose to Members of the Public(Special interest Groups)
External Dose (mrem)
Noble Gas
Internal Dose(mrem)
lodines, Particulate, and TritiumSpecific Activity
Police at ShootingRangeTour Participants
(a) Simulator Bldg.
(b) Bio Lab
(c) OverlookAmerican Indiansat Burial GroundsRanch hands drivingcattle around site
ExposureLocation(Sectors)
SE
SSE
NWNNWNW
NNWN
NNENE
ExposureClosestDistance
700m
310m
460m
210m200m200m250m350m320m450m630m
ExposureTime
(Hours)52
1.0
1.5 *
252424.25.25.25.25.25
Whole Body
9.86E-6
1.29E-7
1.94E-7
9.00E-S3.57E-52.50E-52.49E-79.55E-S6.34E-S2.48E-S1.26E-S
Skin
2.20E-5
2.88E-7
4.32E-7
2.00E-77.95E-55.57E-55.55E-72.13E-71.41E-75.52E-S2.81E-S
Ground Plane
0.00E+0
0.00E+0
0.00E+0
0.00E+00.00E+00.00E+00.00E+00.00E+00.00E+00.00E+00.00E+0
Inhalation
1.20E-4
1.57E-6
2.36E-6
1.10E-64.35E-43.04E-43.03E-61.16E-67.72E-73.02E-71.54E-7
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nclosurePG8 E Lett L 99-055
Table 11e
Radiation Dose Due to Release of Radioactive Gaseous EffluentsAnnual Total 1998
On-Site Dose to INembers of the Public(Special Interest Groups)
External Dose (mrem) Internal Dose(mrem)
Noble Gas lodines, Particulate, and TritiumSpecific Activity
Police at ShootingRangeTour Participants
(a) Simulator Bldg.
(b) Bio Lab
(c) OverlookAmerican Indiansat Burial GroundsRanch hands drivingcattle around site
ExposureLocation(Sectors)
SE
S
SSE
NWNNWNW
NNWN
NNENE
ExposureClosestDistance
700m
310m
. 460m
210m200m200m250m350m320m450m630m
ExposureTime
(Hours)208
4.0
6.0
1.0
96961.01.01.01.01.0
Whole Body
6.93E-5
9.09E-7
1.36E-6
6.33E-72.51E-41.76E-41.75E-66.71E-74.46E-71.74E-78.87E-8
Skin
1.32E-4
1.73E-6
2.59E-6
1.20E-64.77E-43.34E-43.33E-61.27E-68.46E-73.31E-71.68E-7
Ground Plane
4.19E-5
2.91E-7
6.61E-7
9.50E-84.33E-52.47E-53.18E-71.07E-75.40E-82.33E-81.43E-8
Inhalation
7.54E-4
9.89E-6
1.48E-5
6.88E-62.73E-31.91E-31.91E-57.30E-64.85E-61.90E-69.64E-7
-52-
0
I
EnclosurePG8E Letter DCL 99-055
Meteorological Data
The hour-by hour listing of wind speed, wind direction, atmospheric stability, andprecipitation is contained on disks with this submittal in accordance with TS 6.9.1.6.
-54-
Attachment 1
PG8 E Letter DCL 99-055
Corrections to 1997 AnnualRadioactive Effluent Release Report
(Total Error, % for Fission and ActivationGases changed from 23.5E+1 to 2.35E+1)
Attachment 1
PG&E Letter DCL 99-055
IX. Gaseous and Liquid Effluents
Table 1a
Gaseous Effluents - Summation of All Releases
A. Fission and activation gases
1. Total release
Units
Ci
FirstQuarter
4.40E-2
SecondQuarter
2.01E+0
Est. TotalError, %
2.35E+1
2. Average release rate for period
3. Percent of technical specification limit"
pCi/sec 5.66E-3
5.12E-5
2.55E-1
1.52E-3
B. lodines
1. Total iodine-131
2. Average release rate for period
3. Percent of technical specification limit"
Ci MDA
pCi/sec MDA
MDA
MDA
MDA
MDA
2.35E+1
C. Particulate
1. Particulate with half-lives >8 days
2. Average release rate for period
3. Percent of technical specification limit"
4. Gross alpha radioactivity
Ci
pCi/sec
Ci
MDA
MDA
MDA
4.05E-7
. 2.79E-5
3.55E-6
1.38E-6
1.40E-7
2.35E+1
D. Tritium
1. Total release Ci 2.71E+1 4.97E+1 1.30E+1
2. Average release rate for period
3. Percent of technical specification limit"
pCi/sec 3.48E+0
7.79E-6
6.32E+0
1.41E-5
MDA = Less than the "a posteriori" minimum detectable activity (microcuries per unit massor volume). This note applies to all tables.
" RECP 6.1.6.1 Limit
Attachment 1
PG8 E Letter DCL 99-055
Table 1b
Gaseous Effluents - Summation of All Releases
A. Fission 8 activation gases
Units Third FourthQuarter Quarter
Est. TotalError%
1. Total release Ci 3.08E-2 1.54E-1 2.35E+1
2. Average release rate for period
3. Percent of technical specification limit"
pCi/sec 3.88E-3
3.39E-5
1.93E-2
5.10E-5
B. lodines
1. Total iodine-131
2. Average release rate for period
3. Percent of technical specification limit"
Ci
ljCi/sec
MDA
MDA
MDA
MDA
MDA
MDA
2.35E+1
C. Particulate
1. Particulate with half-lives >8 days
2. Average release rate for period
3. Percent of technical specification limit"
4. Gross alpha radioactivity
Ci
pCi/sec
Ci
MDA
MDA
MDA
3.75E-7
MDA
MDA
MDA
6.43E-8
2.35E+1
D. Tritium
1. Total release
2. Average release rate for period
3. Percent of technical specification limit"
Ci 2.47E+1 3.68E+1
pCi/sec 3.10E+0 4.64E+0
6.94E-6 1.04E-5
1.30E+1
MDA = Less than the "a posteriori" minimum detectable activity (microcuries per unit massor volume). This note applies to all tables." RECP 6.1.6.1 Limit.
Attachment 2PG8 E Letter DCL 99-055
Radiological Monitoring And Controls Program (RMCP)
(CY2 Revision 2A)
~ ~* ISSUED FOR USE BKPACIFIC GAS AND ELECTRIC COMPANYNUCLEAR POWER GENERATIONPROGRAM DIRECTIVE
DATE: EXPIRES:NUMBERREVISION 2A
PAGE 1 OF 12
TITLE: RADIOLOGICALMONITORINGAND CONTROLSPROGRAM
EFFECTIVE DATE
SPONSORING ORGANIZATION: CHEMISTRYCLASSIFICATION: QUALITYRELATED
SECTION
PROGRAM OVERVIEW.APPLICABILITY.................DEFINITIONS.
TABLEOF CONTENTS
PAGE
~ ~ ~ ~ ~ ~ ~ 3
I
PROGRAM OBJECTIVES AND RE UIREMENTS.Program ObjectivesProgram Requirements .
Radiological Environmental Monitoring Program ...........Radioactive Effluent Control Prograin . ~ ..Offsite Dose Calculation Procedures .
Environmental Radiological Monitoring Procedure .
Radwaste Treatment Systems........~.........~................~....Quality Assurance Requirements.
RESPONSIBILITIES .....KEY IMPLEMENTINGDOCUMENTS.
Inter-Departmental Administrative Procedures (IDAPs) .
Department-Level Administrative Procedures (DLAPs)CLOSELY RELATED PROGRAMS .
RECORDS.....APPENDICES .
ATTACHMENTS.
REFERENCES .
PONSOR ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~S
3
. .. ... 4...4
.. 10
..... 10
......... 10
PROGRAM OVERVIEW
It is the policy of Nuclear Power Generation (NPG) that the release of radioactive materials to theenvironment be in compliance with Federal regulations and be "As Low As ReasonablyAchievable" (ALARA). The overall objectives are to protect the health and safety of the publicfrom undue radiation exposure and to minimize the amount of radioactive effluents resulting fromthe operation of the Diablo Canyon Power Plant.
This PD defines the overall policies and general requirements related to the RadiologicalMonitoring and Controls Program (RMCP). This includes the Radiological EnvironmentalMonitoring Program, and the Radioactive Effluent Controls Program.
01317002.DOE 1A 1 1 0324.0631
I,
PACIFIC GAS AND ELECTRIC COMPANYNUCLEAR POWER GENERATION
TITLE: RADIOLOGICALMONITORINGAND CONTROLSPROGRAM
NUMBER CY2REVISION 2APAGE 2 OF 12
The scope of this PD is focused on the control of releases of radioactive material to theenvironment, and minimizing radiological impact on the general public. Radiation protection ofplant workers and visitors within the restricted area of the plant is within the scope of RP1,"Radiation Protection."
Figure 1 illustrates the hierarchy of procedures associated with this PD.
FIGURE 1
CY2Hierarchy of Procedures
CY2
Radiological Monitoring and Controls Program
Radioactive Effluent Control ProgramEnvironmental Radiological Monitoring Procedure
DLAPs
Department Specific Administrative Controls
01317002.DOE IA 2 0324.063 t
PACIFIC GAS AND ELECTRIC COMPA~NUCLEAR POWER GENERATION
TITLE: RADIOLOGICALMONITORINGAND CONTROLSPROGRAM
NUMBER CY2REVISION 2APAGE 3 OF 12
2. APPLICABILITY
This PD is applicable to all persons involved in radioactive effluent control, monitoring, and
management activities. This includes all NPG personnel, personnel matrixed to NPG from otherPG&E organizations, personnel in other PG&E organizations that are engaged in activities in
support of NPG, and contractor personnel that are working under NPG supervision.
DEFINITIONS
3.1 ALARA(acronym for "as low as reasonably achievable" ) - A term that means making
every reasonable effort to maintain exposures to radiation as far below the dose limitsof 10 CFR 20 as is practical consistent with the purpose for which the licensed activityis undertaken,'aking into account the state of technology, the economics ofimprovements in relation to state of technology, the economics of improvements inrelation to benefits to the public health and safety, and in relation to utilization ofnuclear energy and licensed materials in the public interest. The specific objectives ofachieving ALARAeffluents are based on those described in 10 CFR 50, Appendix I.
The Radiological Monitoring and Controls Program (RMCP) - Contains the RadioactiveEffluent Controls and Radiological Environmental Monitoring Programs required byTechnical Specification 6.8.4 and descriptions of the information that should be
included in the Annual Radiological Environmental Operating and Annual RadioactiveEffluent Release Reports required by Technical Specifications 6.9.1.5 and 6.9.1.6.
3.3 Offsite Dose Calculation Procedure (ODCP) - Contains the methodology and
parameters used in the calculation of offsite doses due to radioactive gaseous and liquideffluents and in the calcuhtion of gaseous and liquid effluent monitoring Alarm/TripSetpoints.
3.4 Environmental Radiological Monitoring Procedure (ERMP) - Contains a description ofsample locations, types of sample locations, methods and frequency of analysis, and
reporting requirements.
PROGRAM OBJECTIVES AND UIREMENTS
4.1 Program Objectives
The NPG Radiological Monitoring and Controls Program is established to meet the
following objectives:
4.1.1 Ensure that systems, methods, and controls are established to meet applicableregulatory requirements and objectives for release of radioactive effluents.
Liquid and gaseous radioactive waste processing systems provide the means
for controlling radioactive releases. It is also important to establishadministrative controls with clear delineation of responsibilities to ensure that
monitoring, measurement, and release activities are properly sequenced,
authorized, and controlled.
01317002.DOE 1A 3 I 0324.0631
PACIFIC GAS AND ELECTRIC COMPANYNUCLEARPOWER GENERATION
TITLE: RADIOLOGICALMONITORINGAND CONTROLSPROGRAM
NUMBER CY2REVISION 2APAGE 4 OF 12
4.2 Program Requirements
The basic requirement for the Radiological Monitoring and Controls Program shall beto maintain radioactive releases to the unrestricted areas surrounding the plant inconformance with applicable Federal regulations and ALARA. The following
sections'rovide
additional requirements for various elements of the program.
4.2.1 Changes to the RMCP (including ODCP, ERMP and RECP) shall beprocessed in accordance with the requirements of DCPP TechnicalSpecification Section 6. 14.2.
4.2.2
4.2.3
Radiological Environmental Monitoring Program
a. A Radiological Environmental Monitoring Program (REMP) shall beestablished and maintained to comply with the DCPP TechnicalSpecification 6.8.4.h, Radiological Environmental Monitoring Programrequirements. The program shall be provided to monitor the radiationand radionuclides in the environs of the plant, and shall address thefollowing:
1. Monitoring, sampling, analysis, and reporting of radiation andradionuclides in the environment in accordance with themethodology and parameters in the Environmental RadiologicalMonitoring Procedure (ERMP),
2. A Land Use Census to ensure that changes in the use of areas atand beyond the SITE BOUNDARYare identified and thatmodifications to the monitoring program are made ifrequired bythe results of this census, and
3. Participation in an Interlaboratory Comparison Program to ensurethat independent checks on the precision and accuracy of themeasurements of radioactive materials in the environmentalsample matrices are performed as part of the quality assurance
program for environmental monitoring.
Radioactive Effluent Control Program
a. Monitoring requirements shall be established and maintained for allmajor and potentially significant paths for release of radioactivematerial during normal plant operation, including anticipatedoperational occurrences, to comply with Regulatory Guide 1.21,Revision 1, June 1974, requirements.
Ol317002.DOE 1A 4 I 0324.0631
PACIFIC GAS AND ELECTRIC COMPANYNUCLEAR POWER GENERATION
TITLE: RADIOLOGICALMONITORINGAND CONTROLSPROGRAM
NUMBER CY2REVISION 2APAGE 5 OF 12
b. Procedures shall be established and maintained to define the methodsand requirements for control of liquid and gaseous radioactivedischarges within the limits of DCPP Technical SpecificationSections 6.8.4.g. These procedures shall address the following:
1. Limitations on the operability of radioactive liquid and gaseousmonitoring instrumentation including surveillance requirementsand setpoint determination in accordance with methodology in theOff-site Dose Calculation Procedure, (ODCP).
2. Limitations on the concentrations of radioactive material releasedin liquid effluents to UNRESTRICTED AREAS conforming to10 CFR Part 20, Appendix B, Table 2, Column 2,
Monitoring, sampling, and analysis of radioactive liquid andgaseous effluents in accordance with 10 CFR 20.1302 and withthe methodology and parameters in the ODCP,
i
4.
5.
6.
Limitations on the annual and quarterly doses or dose commitmentto a MEMBER OF THE PUBLIC from radioactive materials inliquid effluents released from each unit to UNRESTRICTEDAREAS conforming to Appendix I to'10 CFR Part 50,
Determination of cumulative and projected dose contributionsfrom radioactive effluents for the current calendar quarter andcurrent calendar year in accordance with the methodology andparameters in the ODCP at least every 31 days,
Limitations on the operability and use of the liquid and gaseouseffluent treatment systems to ensure that the appropriate portionsof these systems are used to reduce releases of radioactivity whenthe projected doses in a 31-day period would exceed 2 percent ofthe guidelines for the annual dose or dose commitmentconforming to Appendix 1 to 10 CFR Part 50,
7. Limitations on the dose rate resulting from radioactive materialreleased in gaseous effluents from the site to areas at or beyondthe SITE BOUNDARYshall be limited to the following:
a)
b)
For noble gases: Less than or equal to a dose rate of500 mrem/yr to the whole body and less than or equal to a
dose rate of 3000 mrem/yr to the skin, and
For Iodine-131, for Iodine-133, for tritium, and for allradionuclides in particulate form with half-lives greater than8 days: Less than or equal to a dose rate of 1500 mrem/yrto any organ.
0) 317002.DOE iA 5 0324.0631
PACIFIC GAS AND ELECTRIC COMPANYNUCLEAR POWER GENERATION
TITLE: RADIOLOGICALMONITORINGAND CONTROLSPROGRAM
NUMBER CY2REVISION 2APAGE 6 OF 12
C.
d.
8. Limitations on the annual and quarterly air doses resulting fromnoble gases released in gaseous effluents from each unit to areas
beyond the SITE BOUNDARYconforming to Appendix I to10 CFR Part 50,
9. Limitations on the annual and quarterly doses to MEMBERS OFTHE PUBLIC from Iodine-131, Iodine-133, tritium, and allradionuclides,in particulate form with half-lives greater than 8
days in gaseous effluents released from each unit to areas beyondthe SITE BOUNDARYconforming to Appendix I to 10 CFR Part50, and
10. Limitations on the annual dose or dose commitment to anyMEMBER OF THE PUBLIC due to releases of radioactivity andto radiation from uranium fuel cycle sources conforming to 40CFR Part 190.
Sampling and analysis methods associated with effluent monitoringactivities shall be controlled in accordance with CY1.DC4, " Control ofMaterial and Equipment Used For Analysis for Chemistry andRadiochemistry Program."
Systems that are known pathways for radioactive releases shall beexplicitly addressed. Periodic sampling of systems with the potential ofbecoming radioactively contaminated should also be addressed.
An onsite meteorological program shall be established and maintainedin accordance with the requirements of Regulatory Guide 1.23,February 1972, to provide sufficient data for the performance of doseassessments.
The collection and processing of technical data required to support theAnnual Radioactive Effluent Release Report and non-routine reports tothe NRC to comply with DCPP Technical SpecificationsSections 6.9.1.6 shall be defined as part of this program. Theprocessing of these reports shall be performed in accordance withXI1, "Regulatory Interface."
4.2.4 Offsite Dose Calculation Procedures
a. Offsite Dose Calculation Procedures (ODCP) shall be established andmaintained to define and control the methods for determining offsitedoses. NRC Regulatory Guide 1. 109, Revision 1, October 1977, as
well as its interpretation through NUREG 0133, should be used as
guidance for establishing acceptable methods. These procedures shalladdress the following:
1. Methods for determining monitoring instrumentation alarmsetpoints are addressed in accordance with a Department-LevelAdministrative Procedure (DLAP) under CY2.
013i 7002.DOE lA 6 0324.0631
PACIFIC GAS AND ELECTRIC COMPANYNUCLEAR POWER GENERATION
TITLE: RADIOLOGICALMONITORINGAND CONTROLSPROGRAM
NUMBER CY2REVISION 2APAGE 7 OF 12
4.2.5
4.2.6
4.2.7
2. Methods for determining effluent concentrations.
3. Methods for calculating doses to persons in unrestricted areas
surrounding the plant from all exposure pathways.
b. Changes to the ODCP shall be processed in accordance with the„requirements of CF4, "Modification Control."
Environmental Radiological Monitoring Procedure
a. An Environmental Radiological Monitoring Procedure (ERMP) shall be
established and shall contain a description of sample locations, types ofsample locations, methods and frequency of analysis, and reportingrequirements.
Radwaste Treatment Systems
a. Radwaste Treatment Systems shall be provided to control the processingand release of radioactive materials in gaseous and liquid effluent incompliance with Technical Specification requirements. The design ofthese systems shall be controlled in accordance with CF3, "DesignControl," and the requirements of Regulatory Guide 1. 143, October1979.
b. Approval of changes to the Radwaste Treatment Systems shall beprocessed in accordance with the requirements of CF4, "ModificationControl."
Quality Assurance Requirements
In addition to requirements specified in earlier sections and thoserequirements utilizing procedures in the section 6.2 of this PD, the ControlProgram shall be subject to the Quality Assurance requirements specified inCY1, "Chemistry/Radiochemistry."
RESPONSIBILITIES
5.1 'he Senior Vice President and General Mana er NPG - is responsible for establishingthe policy and general requirements for the Radiological Monitoring and ControlsProgram, for providing management support and guidance for the program'simplementation, and ensuring compliance with all regulatory requirements is
maintained.
5.2 The Vice President and Plant Mana'r P&PM - is responsible for the overalldevelopment, implementation, and maintenance of the Radiological Monitoring and
Controls Program in accordance with the requirements of this PD.
01317002.DOE IA 7 I 0324.0631
0
PACIFIC GAS ANDELECTRIC COMPANYNUCLEAR POWER GENERATION
TITLE: RADIOLOGICALMONITORINGAND CONTROLSPROGRAM
NUMBER CY2REVISION 2APAGE 8 OF 12
5.3
5.4
5.5
5.6
5.7
The Vice President Nuclear Technical Services NPG - is responsible for ensuring thatsupport from reporting departments is provided for the Radiological Monitoring andControls Program.
The Mana er - DCPP erations Services - is responsible for the direct implementationof the Radiological Monitoring and Controls Program with the exception of the designof radwaste treatment and effluent monitoring systems.
The Mana er - En ineerin Services and the Mana er Re lato and Desi n ServicesQ<&D~S - are responsible for maintaining the design bases for installed plant radwastetreatment and effluent monitoring systems, structures, and components and providingtechnical support to the plant for the operation and maintenance of these systems.
The Mana er - Technical and Ecolo ical Services TES - is responsible for performingradiological laboratory analysis for the Radiological Environmental MonitoringProgram and preparing and reviewing the Annual Radiological EnvironmentalOperating Report.
Other PG&E De artments - called upon to support NPG activities associated with theRadioactive Effluent Control program are responsible for performing their activities inaccordance with the requirements of this PD.
5.8
5.9
The Mana er - Nuclear ali Services N S - is responsible for auditing theRadiological Monitoring and Controls Program at least once every 12 months.
The Mana er - Maintenance Services - is responsible for maintaining the radiationmonitoring systems and the hardware and software for the Rad Effluent program.
KEY IMPLEMENTINGDOCUMENTS
6.1
6.2
Inter-Departmental Administrativ'e Procedures (IDAPs)
Inter-Department Administrative Procedures shall be developed to address the followingaspects of the Radiological Monitoring and Controls Program:
6.1.1 An IDAP shall be developed to define the requirements and responsibilitiesassociated with the Radioactive Effluent Control Program.
6.1.2 An IDAP shall be developed to define the requirements and responsibilitiesassociated with the Environmental Radiological Monitoring Procedure.
Department-Level Administrative Procedures (DLAPs)
Departments responsible for performing activities related to the Radioactive EffluentControl program shall develop DLAPs as appropriate to control program activities.
Ol317002.DOE 1A 8 0324.0631
0
PACIFIC GAS AND ELECTRIC COMPANYNUCLEARPOWER GENERATION
TITLE: RADIOLOGICALMONITORINGAND CONTROLSPROGRAM
NUMBER CY2REVISION 2APAGE 9 OF 12
7. CLOSELY RELATED PROGRAMS
7.1 Interfaces
This section describes each of the principal interfaces and boundaries between this
Program Directive and other management processes.
7.1.1 AD10, "Records"
7.1.2
"Records" provides for the retention of Radiological Monitoring and ControlsProgram records.
CF3, "Design Control"
"Design Control" addresses the implementation of design activities forinstalled radwaste treatment and effluent monitoring systems in accordancewith the requirements of NRC Regulatory Guide 1.143.
7.1.3 CF4, "ModificationControl"
"Modification Control" addresses the implementation of modificationactivities for installed effluent monitoring systems.
7.1.4 CY1, "Chemistry/Radiochemistry"
7.1.5
7.1.6
"Chemistry/Radiochemistry" addresses the methods forchemistry/radiochemistry sampling and analysis of liquid and gaseousradioactive effluents in support of this PD.
OM7, "Problem Resolution"
"Problem Resolution" addresses deficiencies identified during theimplementation of the. radioactive effluent control program. OM7 alsoaddresses evaluating nonconformances for reportability in accordance withTechnical
Specifications.'Q1,
"Personnel Training and Qualification"
"Personnel Training and Qualification" identifies training and qualificationrequirements for personnel.
7.1.7 XI1, "Regulatory Interface"
"Regulatory Interface" addresses the process for required reporting andcommunication with outside agencies.
7.1.8 CY2.ID1, "Radioactive Effluent Controls Program"
l
8. RECORDS
None
"Radioactive Effluent Controls Program" contains the general programrequirements to ensure the requirements of 10 CFR Part 20 and10 CFR Part 50, Appendix I, are met.
Oi317002.DOE 1A 9 0324.0631
0
PACIFIC GAS ANDELECTRIC COMPANYNUCLEARPOWER GENERATION
TITLE: RADIOLOGICALMONITORINGAND CONTROLSPROGRAM
NUIHBER CY2REVISION 2APAGE 10 OF 12
9. APPENDICES
9.1 Graded Quality Assurance Requirements for Radiological Monitoring and ControlsProgram
10. ATTACHMENTS
None
11. REFERENCES
11.1 Title 10, Code of Federal Regulations,
11.1.1 Part 20, ."Standards for Protection Against Radiation"
11.2
11.3
11.4
11.5
11.6
11.7
11.1.2 Part 50, Appendix I,
11.1.3 Part 50, Appendix A, GDC 60, 64,
Title 40, Code of Federal Regulations, "Environmental Radiation Protection Standardsfor Nuclear Power Operations."
Regulatory Guide 1.109, Revision 1, October 1977, "Calculation of Annual Doses to, Man From Routine Releases of Reactor Effluents for the Purpose of EvaluatingCompliance with 10 CFR Part 50 Appendix I."
Regulatory Guide 1.143, October 1979, "Design Guidance for Radioactive WasteManagement Systems, Structures, and Components Installed in Light-Water-CooledNuclear Power Plants."
Regulatory Guide'1.21, Revision 1, June 1974, "Measuring, Evaluating, and ReportingRadioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid andGaseous Effluent from Light-Water-Cooled Nuclear Power Plants."
Regulatory„Guide 1.23, February 1972, "Onsite Meteorological Programs."
Regulatory Guide 4.15, Revision 1, February 1979, "Quality Assurance ForRadiological Monitoring Programs (Normal Operations) - Effluent Streams and theEnvironment."
11.8 Regulatory Guide 4.1, Revision 1, April 1975, "Programs for Monitoring Radioactivityin the Environs of Nuclear Power Plants."
11.9 Diablo Canyon Nuclear Power Plant Facility Operating Licenses (Unit 1, Unit 2)
12. SPONSOR
David Chen
01317002.DOE 1A 10 1 0324.0631
PACIFIC GAS AND ELECTRIC COMPANYNUCLEARPOWER GENERATION
TITLE; RADIOLOGICALMONITORINGAND CONTROLSPROGRAM
NUMBER CY2REVISION 2APAGE 11 OF 12
APPENDIX 9.1
GRADED QA REQUIREMENTSFOR RADIOLOGICALMONITORINGAND CONTROLS PROGRAM
The basis for these Graded QA requirements is to comply w'ith the regulations of 10 CFR 20, 10 CFR 50,
40 CFR 190, the Technical Specifications and Regulatory Guides 1.21; and 4:15.
1. GRADED ITEMS
Radioactive Effluent monitoring instruments are classified as Category 2 or Category 3 items per
Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess
Plant and Environs Conditions During and Following an Accident." These instruments are used
for detection and assessment of releases and possibly detection of containment breach with
accomplishment of mitigation of the breach. These items fall under Graded QA requirements.
GRADED ACTIVITIES
3.
2.3
2.1 Installed radiation monitors required per the Technical Specifications 3/4.3.3.6, and
6.8.4.b for monitoring radioactive effluents during plant operations or accidents shall be
calibrated at prescribed intervals.
2.2 Sampling and analysis of liquid and gaseous effluents shall be performed in accordance
with CY1, "Chemistry/Radiochemistry."
Calculations, computer programs, and procedures for evaluating the dose associated
with radioactive effluents shall be performed in accordance with approved quality
related procedures.
GRADED RE UIREMENTS
3.1
3.2
3.3
3.4
3.5
Effluent releases shall be maintained ALARAand shall be performed in accordance
with the requirements of this Program Directive (CY2) to limit the concentrations,
doses and doserates as specified in DCPP Technical Specifications 6.8.4,NRC regulations 10 CFR 20,.10 CFR 50 Appendix I, and EPA regulation 40 CFR 190.
The Annual Radiological Environmental Operating Report shall be developed in
accordance with Technical Specification 6.9.1.5.
The Annual Radioactive Effluent Release Report shall be developed in accordance withTechnical Specification 6.9.1.6.
Records that support and document radioactive effluent releases and dose evaluations
shall be controlled in accordance with AD10, "Records."
Personnel involved in direct implementation of Chemistry/Radiochemistry, Operations,
or Radiation Protection activities in support of the Radiological Monitoring and
Controls Program are qualified in accordance with the requirements of TQ1,"Personnel Training and Qualification."
Ol317002.DOE iA ii i 0324.063l
k
PACIFIC GAS AND ELECTRIC COMPANYNUCLEAR POWER GENERATION
TITLE: RADIOLOGICALMONITORINGAND CONTROLSPROGRAM
NUMBER CY2REVISION 2APAGE 12 OF 12
3.6
3.7
3.8
3.9
APPENDIX 9.1 Continued
NotiTications and reports 'to and correspondence with regulatory agencies shall be donein accordance with XI1, "Regulatory Interface."
Written plans, procedures and instructions for implementing Radiological Monitoringand Controls Program shall be prepared, processed, and controlled in accordance withAD1, "Administrative Control Program."
Procurement of quality-related equipment or services shall be in accordance withwritten procedures. Applicable regulatory requirements, design bases, and any otherrequirements necessary to assure adequate quality shall be included in or invoked byreference in documents for procurement of items or services. Test or acceptancerequirements and documentation to be submitted by the supplier shall be identified inthe procurement documents. Receipt inspection requirements, ifrequired, shall beidentified in the procurement documents.
Deficiencies identified during implementation of this program shall be documented andcontrolled in accordance with OM7, "Problem Resolution."
3.10 Periodic assessments shall be performed at least annually to review the content andimplementation of the Radiological Monitoring and Controls Program.
013 l7002.DOE iA 12 i 0324.063 I
fC
0
0
Attachment 3PG&E Letter DCL 99-055
Radioactive Effluent Control Program (RECP)
(CY2.ID1 Revision 3A)
~ ~ ~
PACIFIC GAS AND ELECTRIC COMPANYNUCLEARPOWER GENERATIONINTER-DEPARTMENTALADMINISTRATIVEPROCEDURE
I'UMBERCY2.ID1REVISION 3A
PAGE 1 OF 37
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
03/24/98EFFECTIVE DATE
SPONSORING ORGANIZATION: CHEMISTRYPROCEDURE CLASSIFICATION: QUALITYRELATED
REVIEW LEVEL: "A"
SECTION
SCOPE .......................DISCUSSION.RESPONSIBILITIESINSTRUCTIONSRECORDSAPPENDICES .
REFERENCESSPONSOR.
1. SCOPE
TABLEOF CONTENTS
PAGE
~ ~ ~ ~ ~ ~ 0 ~ 23
....... 6
....... 6
....... 6.6
This procedure contains the general program requirements of the Radioactive EffluentControls Program. This program ensures that the requirements of 10 CFR Part 20 and10 CFR Part 50 Appendix I are met.
DISCUSSION
2.1
2.2
This procedure provides the general requirements for Radioactive Effluent ControlsProgram in accordance with the Technical Specifications and the implementationGeneric Letter 89-01, "Implementation of Programmatic Controls for RadiologicalEffluent Technical Specifications in the Administrative Controls Section of theTechnical Specifications and the Relocation of Procedural Details of RETS to theOff-Site Dose Calculation Manual or to the Process Control Program."
The following Technical Specification definitions are applicable.
2.2.1 The OFF-SITE DOSE CALCULATIONPROCEDURE (ODCP) shallcontain the methodology and parameters used in the calculation of off-sitedoses resulting from radioactive gaseous and liquid effluents, in thecalculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints.
01192903. DOC 1A 1
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k
' UNCONTROLLEDPROCEDURE-DO NOTUSE TO'PERFORN NORKorISSUEFOR USE-,'ACIFICGAS ANDELECTRIC COMPANY
NUCLEAR POWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.IDlREVISION 3APAGE 2 OF 37
2.3 The specific methodology and parameters used in the calculation of off-site doses
resulting from radioactive gaseous and liquid effluents and in the calculation of gaseousand liquid effluent monitoring Alarm/Trip Setpoints, is contained in CAP A-8,"Off-Site Dose Calculations Procedure (ODCP)." As such, CAP A-8 is incorporated inthis procedure by reference. Therefore, the requirements for revisions to thisprocedure also apply to CAP A-8.
2.3.1 The procedural requirements that ensure compliance with TechnicalSpecification 6.8.4.g are contained in CAP A-5, CAP A-6, and CAP A-8,"Off-Site Dose Calculation Procedure (ODCP)."
RESPONSIBILITIES
3.1
3.2
3.3
The Director, Chemistry is responsible for:
3.1.1 Implementation'of the Off-Site Dose Calculation Procedure in a manner thatmeets regulatory requirements and preparing the Annual RadiologicalEffluent Release Report.
3.1.2 Providing direction to the Operations Staff in the processing of radioactivewaste streams.
3.1.3 Ensuring preparation, review and approval of the Nonroutine RadiologicalEnvironmental Operating Report when required by Appendix 6.1 ~ 11.1. TESnotifies DCPP in accordance with 3.5.
3.1.4 Ensuring that a comparison of the Annual Radioactive Effluent ReleaseReport and the Annual Radiological Environmental Operating Report isperformed.
3.1.5 Ensuring that dose commitment increases due to the Land Use Census inaccordance with Appendix 6.1. 12.1 are determined and communicatedpromptly to RP.
The Director, Radiation Protection is responsible for:
3.2.1 Ensuring the performance of the annual land use census and that the resultsare provided to Chemistry so that Chemistry can established the doserequirements of Appendix 6.1.12.1.
3.2.2 Ensuring that the results of the annual Land Use Census are provided to TESfor inclusion in the Annual Radiological Environmental Operating Report.
3.2.3 Ensuring that changes to the Environmental Radiological MonitoringProcedure are provided to Chemistry for inclusion in the Annual RadiologicalEffluent Release Report.
The Director, Chemical and Environmental, TES is responsible for ensuring that REMPsample results exceeding the criteria of Appendix 6.1.11.1 are communicated promptlyto the Director, Chemistry and the Director, RP at DCPP.
01192903.DOC 1A 2
I! ~ v lf l ~ . I ii h ~ ll i
t
...'.. UNCONTROElEDPROCEDURE=-DO NOT'VSE TOPERFORM O'ORKorISSVEFOR VSE ":,
PACIFIC GAS AND ELECTRIC COMPANYNUCLEARPOWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 3 OF 37
INSTRUCTIONS
4.1 Administrative Requirements
4.1.1 Appendix 6.1 of this procedure contains the operational requirements of theRadioactive Effluent Controls Program.
4.1.2 The operational requirements are implemented by equipment controlguidelines (reference OP1.DC16), CAP A-8, and XI1.ID2, "RegulatoryReporting Requirements and Reporting Process."
a. The Equipment Control Guidelines implement those requirements thatare related to equipment and have specific allowed outage times oroperator actions.
b. CAP A-8 includes the methodology and parameters used in thecalculation of off-site doses resulting from radioactive gaseous andliquid effluents and in the calculation of gaseous and liquid effluentmonitoring alarm/trip setpoints.
c. XI1.ID2 implements the reporting requirements.
4.2 Reporting Requirements
4.2.1 Annual Radioactive Effluent Release Report
a. Report Schedule
1. Annual Radioactive Effluent Release Reports covering theoperation of the unit during the previous calendar year shall besubmitted before May 1 of each year.
b. The Annual Radioactive Effluent Release Reports shall include:
1. A summary of the quantities of radioactive liquid and gaseouseffluents and solid waste released from the unit as outlined inRegulatory Guide 1.21, "Measuring, Evaluating, and ReportingRadioactivity in Solid Wastes and Releases of RadioactiveMaterials in Liquid and Gaseous Effluents fromLight-Water-Cooled Nuclear Power Plants," Revision 1, June1974, with data summarized on a quarterly basis following theformat of Appendix B thereof. For solid wastes, the format forTable 3 in Appendix B shall be supplemented with three additionalcategories; class of solid wastes (as defined by 10 CFR Part 61),type of container (e.g., LSA, Type A, Type B, Large Quantity)and SOLIDIFICATIONagent or absorbent (e.g., cement, ureaformaldehyde);
01192903. DOC lA 3
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PACIFIC GAS AND ELECTRIC COMPANYNUCLEARPOWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAMI
NUMBER CY2.ID1REVISION 3APAGE 4 OF 37
2. A list and description of unplanned releases from the site toUNRESTRICTED AREAS of radioactive materials in gaseousand liquid effluents made during the reporting period;
3. Any changes made during the reporting period to the PCP,RMCP, ERMP, and ODCP, pursuant to Specifications 6.13 and6. 14, respectively.
NOTE: An FSAR update may be used in lieu of the ARERR forcommunicating changes to the NRC, regarding the PCP.
A listing of new locations for dose calculations and/orenvironmental monitoring identified by the Land Use Censuspursuant to Appendix 6.1.
An explanation as to why the inoperability of liquid or'gaseouseffluent monitoring instrumentation was not corrected within thetime specified in Appendix 6.1; and
Description of the events leading to liquid holdup tanks or gasstorage tanks exceeding the limits of Technical Specifications3.11.1.4 or 3.11.2.6.
c. A discussion of major changes to the Radwaste Treatment Systems(liquid, gaseous and solid). The discussion of each change shallcontain:
A summary of the evaluation that led to the determination that thechange could be made in accordance with 10 CFR 50.59;
Sufficient detailed information to totally support the reason for thechange without benefit of additional or supplemental information;
A detailed description of the equipment, components andprocesses involved and the interfaces with other plant systems;
An evaluation of the change which shows the predicted releases ofradioactive materials in liquid and gaseous effluents and/orquantity of solid waste that differ from those previously predictedin the License application and amendments thereto;
An evaluation of the change which shows the expected maximumexposures to a MEMBER OF THE PUBLIC in theUNRESTRICTED AREA and to the general population that differfrom those previously estimated in the License application andamendments thereto;
6. A comparison of the predicted releases of radioactive materials, inliquid and gaseous effluents and in solid waste, to the actualreleases for the period prior to when the changes are to be make;
01192903.DOC IA 4
ac l 4 I % 1 =+a t'l '4 'I ills 1 5 -. e 0 8
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P 1% P
PACIFIC GAS AND ELECTRIC COMPANYNUCLEARPOVVER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 5 OF 37
7. An estimate of the exposure to plant operating personnel as a
result of the change; and
8. Documentation of the fact that the change was reviewed and foundacceptable by the PSRC.
Otherwise the above information may be submitted as part of theannual FSAR update.
d. In addition, the Annual Radioactive Effluent Release Report shall alsoinclude:
1. An annual summary of hourly meteorological data collected overthe previous year. This annual summary may be either in theform of an hour-by-hour listing on magnetic tape/hard disk orother media of wind speed, wind direction, atmospheric stability, =
and precipitation (ifmeasured), or in the form ofjoint frequencydistributions of wind speed, wind direction, and atmosphericstability or the licensee has the option of retaining this summary ofrequired meteorological data on site in a file that shall be providedto the NRC upon request;
2. An assessment of the radiation doses due to the radioactive liquidand gaseous effluents released from the unit or station during theprevious calendar year;
3. An assessment of the radiation doses from radioactive liquid andgaseous effluents to MEMBERS OF THE PUBLIC due to theiractivities inside the SITE BOUNDARY (see TechnicalSpecification Figure 5.1-3) during the report period;
4. - Allassumptions used in making these assessments, i.e., specificactivity, exposure time and location. The meteorologicalconditions concurrent with the time of release of radioactivematerials in gaseous effluents, as determined by samplingfrequency and measurement, shall be used for determining thegaseous pathway doses. The assessment of radiation doses shallbe performed in accordance with the methodology and parametersin the OFF-SITE DOSE CALCULATIONPROCEDURE(ODCP); and
5..An assessment of radiation doses to the likely most exposedMEMBER OF THE PUBLIC from reactor releases and othernearby uranium fuel cycle sources, including doses from primaryeffluent pathways and direct radiation, for the previous calendaryear to show conformance with 40 CFR Part 190, "EnvironmentalRadiation Protection Standards for Nuclear Power Operation."Acceptable methods for calculating the dose contribution fromliquid and gaseous effluents are given in Regulatory Guide 1.109,Rev. 1, October 1977.
01192903.DOC 1A 5
"t
UN!CONTROLLEDPROCEDVRE-, DO:NOTVSE TO PERFORM;O'ORKor ISSUEFOR USEPACIFIC GAS AND ELECTRIC COMPANYNUCLEAR PONER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 6 OF 37
4.3
4.4
e. A single submittal may be made for a multiple unit plant. The submittalshould combine those sections that are common to all units at the plant;however, for units with separate radwaste system, the submittal shallspecify the releases of radioactive material from each unit.
Revisions to the RECP
4.3.1 The requirements for revision to the RECP also apply to CAP A-8.
4.3.2 The requirements are provided in Technical Specification 6.14.2.
Major changes to Liquid, Gaseous, and Solid Radwaste Treatment Systems
4.4.1 Major changes to the liquid, gaseous, and solid radwaste treatment systemsshall become effective upon review and acceptance by the PSRC provided thechange could be made in accordance with 10 CFR 50.59.
5. RECORDS
5.1 Data Sheets and records willbe maintained in the Records Management System (RMS)in accordance with CY1.DC1, "Analytical Data Processing Responsibilities."
APPENDICES
6.1 Operational Requirements of the Radioactive Effluent Controls Program
REFERENCES
7.1 CAP A-8, "Off-site Dose Calculation Procedure (ODCP)."
7.2 CAP A-5, "Liquid Radwaste Discharge Management."
7.3 CAP A-6, "Gaseous Radwaste Discharge Management."
7.4 RP1.ID11, "Environmental Radiological Monitoring Procedure."
7.5 OP1.DC16, "Control of Plant Equipment Not Required by the TechnicalSpecifications."
7.6 XI1.ID2, "Regulatory Reporting Requirements and Reporting Process."
7.7 Regulatory Guide 1.21, Revision 1, June 1974.
7.8 Regulatory Guide 1.109, Revision 1, October 1977.
7.9 License Amendment Request 93-04.
SPONSOR
David Chen
0l 192903.DOC lA 6
' UilfCONTROI.IEIJ:PROCEOURE-OO NOMSE TOPERFORM'kYORKorISSUEFOR 'USE,,"PACIFIC GAS ANDELECTRIC COMPANYNUCLEARPOWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAMl
NUMBER CY2.IDIREVISION 3APAGE 7 OF 37
APPENDIX 6.1OPERATIONALREQUIREMENTS OF THE RADIOACTIVEEFFLUENT
CONTROLSPROGRAM
6.1.1 Radioactive Li uid Effluent Monitorin Instrumentation (Also covered by ECG 39.3)
Commitment for 0 eration
6.1.1.1 The radioactive liquid effluent monitoring instrumentation channels shown inTable 6.1.1-1 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure thatthe limits of Commitment 6.1.3.1 are not exceeded. The Alarm/Trip Setpoints of thesechannels shall be determined in accordance with the methodology and parameters in theOFF-SITE DOSE CALCULATIONPROCEDURE (ODCP).
~Aticebitit: At eii times.
Action:
With a radioactive liquid effluent monitoring instrumentation channelAlarm/Trip Setpoint less conservative than required by the aboveCommitment, immediately suspend the release of radioactive liquid effluentsmonitored by the affected channel or declare the channel inoperable.
With less than the minimum number of radioactive liquid effluent monitoringinstrumentation channels OPERABLE, take the ACTION shown inTable 6.1.1-1. Restore the inoperable instrumentation to OPERABLE statuswithin the time specified in the ACTION, or explain in the next AnnualRadioactive Effluent Release Report why this inoperability was not correctedwithin the time specified.
Surveillance Re uirements
6.1.1.2 Each radioactive liquid effluent monitoring instrumentation channel shall bedemonstrated OPERABLE by performance of the CHANNELCHECK, SOURCECHECK, CHANNELCALIBRATIONand CHANNELFUNCTIONALTEST at thefrequencies shown in Table 6.1.1-2.
6.1.1.3 At least one saltwater pump shall be determined operating and providing dilution to thedischarge structure at least once per 4 hours whenever dilution is required to meet thelimits of Commitment 6.1.3.1.
0l 192903.DOC IA 7
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"'NCONITROllEDPROCEDVRE-DONOTUSE TO PERFORM OORKor ISSVEFOR USE "PACIFIC GAS AND ELECTRIC COMPANYNUCLEAR POWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 8 OF 37
APPENDIX 6.1 Continued
TABLE6.1.1-1RADIOACTIVELI UID EFFLUENT MONITORINGINSTRUMENTATION
INSTRUMENT
a. Liquid Radwaste Effluent Line (RM-18)¹
b. Steam Generator Blowdown Tank (RM-23)
2. Flow Rate Measurement Devices
a. Liquid Radwaste Effluent Line (FR-20)¹
b. Steam Generator Blowdown Effluent
Lines (FR-53)
Oily Water Separator EffluentLine (FR-251)¹
adioactivity Monitor Not Providing AutomaticTermination of Release
c,Oily Water Separator Effluent Line (RM-3)¹
1. Radioactivity Monitors Providing Alarm and AutomaticTermination of Release
MINIMUMCHANNELS'OPERABLE ACTION
¹ This Radioactive Liquid Effluent Monitoring Instrumentation is common to both units.
01192903.DOC 1A 8
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, 'NCONT80II.EDPROCEDURE-DO NOTUSE 70'PERFORM 5'08/For ISSUE:FOR USE "PACIFIC GAS ANDELECTRIC COMPANYNUCLEAR POWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAMI
NUMBER CY2.ID1REVISION 3APAGE 9 OF 37
ACTION 1
ACTION 2
ACTION 3
ACTION4
APPENDIX 6.1 Continued
TABLE6.1.1-1 ContinuedACTION STATEMENTS
With the number of channels OPERABLE less than required by the Minimum ChannelsOPERABLE requirement, effluent releases via this pathway may continue for up to 14
days provided that prior to initiating a release:
At least two independent samples are analyzed in accordance withCommitment 6.1.3.2.
At least two technically qualified members of the facility staff independentlyverify the release rate calculations and discharge line valvings.
Otherwise, suspend release of radioactive effluents via this pathway.
With the number of channels OPERABLE less than required by the Minimum ChannelsOPERABLE requirement, effluent releases via this pathway may continue for up to 30days provided grab samples are analyzed for radioactivity (beta or gamma) at a lowerlimit of detection of no more than 107 microcuries/ml:
At least once per 12 hours when the specific activity of the secondary coolantis greater than 0.01 microcuries/gram DOSE EQUIVALENTI-131, or
b. At least once per 24 hours when the specific activity of the secondary coolantis less than or equal to 0.01 microcuries/gram DOSE EQUIVALENTI-131.
With the number of channels OPERABLE less than required by the Minimum ChannelsOPERABLE requirement, effluent releases via this pathway may continue for up to 30days provided that, at least once per 12 hours, grab samples are collected and analyzedfor radioactivity (beta or gamma) at a lower limitof detection of no more than
10'icrocuries/mlor transfer the oily water separator effluent to the Liquid RadwasteTreatment System.
With the number of channels OPERABLE less than required by the Minimum ChannelsOPERABLE requirement, effluent releases via this pathway may continue for up to 30days provided the flow rate is estimated at least once per 4 hours during actual releases.Pump performance curves may be used to estimate flow.
01192903.DOC 1A 9
VNCONTROI.I.EDPROCEDURE- DONPACIFI AND ELECTRIC COMPANYNUCLEARPOWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
E TO PERFORM O'ORKorISSUE FOR USE':.=':NUMBER CYREVISION 3APAGE 10 OF 37
APPENDIX 6.1. Continued
TABLE6.1.1-2RADIOACTIVELI UID EFFLUENT MONITORINGINSTRUMENTATIONSURVEILLANCERE UIREMENTS
INSTRUMENT1. Radioactivity Monitors Providing Alarm and Automatic Termination
of Release
a. Liquid Radwaste Effluent Line (RM-18)
b. Steam Generator Blowdown Tank (RM-23)
2. Flow Rate Measurement Devices
a. Liquid Radwaste Effluent Line (FR-20)
b. Steam Generator Blowdown Effluent Line (FR-53)
c. Oily Water Separator Effluent Line (FR-251)
3. Radioactivity Monitor Not Providing Automatic Termination ofRelease
Oily Water Separator Effluent Line (RM-3)
CHANNELCHECK
D
D
D(4)
D(4)
Daily(4)
D
SOURCECHECK
N.A.
N.A.
N.A.
CHANNELCALIBRATION
R(3)
R(3)
R(3)
CHANNELFUNCTIONAL
TEST
Q(1)
Q(1)
Q
Q
Q
Q(2)
01192903.DOC 1A 10
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" 'NCONTROIIEDPROCEDURE-DO NOTUSE TO PERFORM O'ORKorISSUEFOR USE "PACIFIC GAS AND ELECTRIC COMPANYNUCLEAR POWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAMI
NUMBER CY2.ID1REVISION 3APAGE 11 OF 37
(2)
(y (3)
(4)
(5)
APPENDIX 6.1 Continued
TABLE6.1.1-2TABLENOTATION
The CHANNELFUNCTIONALTEST shall also demonstrate that automatic isolation of thispathway and Control Room alarm annunciation occurs ifany of the following conditions exits:
a. Instrument indicates measured levels above the Alarm/Trip Setpoint (isolation and alarm),or
b. Relay control circuit failure (isolation only), orc. Instrument indicates a downscale failure (alarm only), ord. Instrument controls not set in operate mode (alarm only).
The CHANNELFUNCTIONALTEST shall also demonstrate that Control Room alarmannunciation occurs ifany of the following conditions exist:
a. Instrument indicates measured levels above the Alarm Setpoint, orb. Circuit failure, orc. Instrument indicates a downscale failure, ord. Instrument controls not set in operate mode.
The initial CHANNELCALIBRATIONshall be performed using one or more of the referencestandards certified by the National Bureau of Standards (NBS) or using standards that have beenobtained from suppliers that participate in measurement assurance activities with NBS. Thesestandards shall permit calibrating the system over its intended range of energy and measurementrange. For subsequent CHANNELCALIBRATION,sources that have been related to the initialcalibration shall be used.
CHANNELCHECK shall consist of verifying indication of flow during periods of release.CHANNELCHECK for FR-251 shall be made once per calendar day*, and for FR-20 and FR-53shall be made at least once per 24 hours on days on which continuous, periodic, or batch releasesare made.
Fre uenc Notation
NotationDDailyMQRpN.A.
FrequencyAt least once per 24 hoursAt lease once per calendar day*At least once per 31 daysAt least once per 92 daysAt least once per 18 monthsCompleted prior to each releaseNot Applicable
* The frequency "once per calendar day" could result in two successive channel checks nearly 48 hoursapart over a two day period. This frequency is different from and should not be confused with thefrequency notation "D" (at least once per 24 hours) defined in Technical Specifications.
01192903.DOC lA 11
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PACIFIC GAS AND ELECTRIC COMPANYNUCLEAR POWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 12 OF 37
APPENDIX 6.1 Continued
6.1.2 Radioactive Gaseous Effluent Monitorin Instrumentation (Also covered by ECG 39.4)
Commitment for 0 eration
6.1.2.1 The radioactive gaseous effluent monitoring instrumentation channels shown inTable 6.1.2-1 shall be OPERABLE with their.Alarm/Trip Setpoints set to ensure thatthe limits of Commitment 6.1.6.1 is not exceeded. The Alarm/Trip Setpoints of thesechannels meeting Commitment 6.1.6.1 shall be determined and adjusted in accordancewith the methodology and parameters in the ODCP.
~Aplicability: As shown in Table 6.1.2-1.
Action:
a. With a radioactive gaseous effluent monitoring instrumentation channelAlarm/Trip Setpoint less conservative than required by the aboveCommitment, immediately suspend the release of radioactive gaseouseffluents monitored by the affected channel, or declare the channelinoperable.
b. With the number of OPERABLE radioactive gaseous effluent monitoringinstrumentation channels less than the Minimum Channels OPERABLE, takethe ACTION shown in Table 6.1.2-1. Restore the inoperable instrumentationto OPERABLE status within the time specified in the ACTIONor explain inthe next Annual Radioactive Effluent Release Report why this inoperabilitywas not corrected within the time specified.
Surveillance Re uirements
6.1.2.2 Each radioactive gaseous effluent monitoring instrumentation channel shall bedemonstrated OPERABLE by performance of the CHANNELCHECK, SOURCECHECK, CHANNELCALIBRATIONand CHANNELFUNCTIONALTEST at thefrequencies shown in Table 6.1.2-2.
01192903.DOC 1A 12
UNCUNTRUilED PRUCFOURE -00 NPACIFI AND ELECTRIC COMPANYNUCLEARPOWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
E 7OPERFORM O'ORKor ISSVEFOR VSE- '.-.'-
NUMBER CYREVISION 3APAGE 13 OF 37
APPENDIX 6.1 Continued
TABLE6.1.2-1RADIOACTIVEGASEOUS EFFLUENT MONITORINGINSTRUMENTATION
INSTRUMENT1. Gaseous Radwaste System
Noble Gas ActivityMonitor - Providing
Alarm and Automatic Termination of Release (RM-22)
2. Plant Vent System
a. Noble Gas ActivityMonitor Providing Alarm (RM-14 orRM-14R)
b. Iodine Sampler
c. Particulate Sampler
d. Flow Rate Monitor (FR-12)
e. Iodine Sampler Flow Rate Monitor
3. Containment Purge System
Noble Gas ActivityMonitor - Providing Alarm and AutomaticTermination of Release (RMMAor 44B)
MINIMUMCHANNELOPERABLE
2n)
APPLICABILITY ACTION
2 channels required in Modes 1, 2, 3 and 4. Only 1 channel required in Mode 6 during Core Alterations or movement of irradiated fuel withincontainment.
01192903.DOC 1A 13
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,:" . VNCONTROLIEIJPROCEOVRE-DO NOTVSE TO PERFORM OORKor JSSVEFOR VSEPACIFIC GAS ANDELECTRIC COMPANYNUCLEAR POWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 14 OF 37
APPENDIX 6.1 Continued
TABLE 6.1.2-1 ContinuedTABLENOTATIONS
At all times.MODES 1-4; also MODE 6 during CORE ALTERATIONSor movement of irradiated fuel withincontainment.
ACTION 5
ACTION 6
ACTION7
ACTION 8
ACTION 9
With the number of channels OPERABLE less than required by the Minimum ChannelsOPERABLE requirement, the contents of the tank(s) may be released to theenvironment for up to 14 days provided that prior to initiating the release:
a. At least two independent samples of the tank's contents are analyzed, andb. At least two technically qualified members of the facility staff independently
verify the release rate calculations and discharge valve lineup.
Otherwise, suspend release of radioactive effluents via this pathway.
With the number of channels OPERABLE less than required by the Minimum ChannelsOPERABLE requirement, effluent releases via this pathway may continue for up to 30days provided the flow rate is estimated at least once per 4 hours.
With the number of channels OPERABLE less than required by the Minimum ChannelsOPERABLE requirement, effluent releases via this pathway may continue for up to 30days provided grab samples are taken at least once per 12 hours and these samples areanalyzed for radioactivity within 24 hours.
With the number of channels OPERABLE less than required by the Minimum ChannelsOPERABLE requirement, immediately suspend containment PURGING of radioactiveeffluents via this pathway.
With the number of channels OPERABLE less than required by the Minimum ChannelsOPERABLE requirement, effluent releases via the affected pathway may continue forup to 30 days provided samples are continuously collected with auxiliary samplingequipment as required in Commitment Table 6.1.6-1.
NOTE FOR ACTION 9: To respond to the low flow alarm, determine that a simplefixcannot be made and that an auxiliary sampler is needed. Move the sampler in, hookup and verify operation, a maximum of two hours is considered a reasonable time.Over two hours should be considered as exceeding the time limitation of thecommitment for operation (PSRC Interpretation 85-07).
01192903.DOC IA 14
J
I~ 4
",«; UllfCOJITROIIEDPROCEDURE-DOllf E TOPERFORN lYORKorJSSUEFOR USE""PACIFI ANDELECTRIC COMPANY NUMBER CYNUCLEARPOWER GENERATION REVISION 3A
PAGE 15 OF 37TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
APPENDIX 6.1 Continued
TABLE6.1.2-2RADIOACTIVEGASEOUS EFFLUENT MONITORINGINSTRUMENTATIONSURVEILLANCERE UIREMENTS
INSTRUMENT
1. Gaseous Radwaste System
Noble Gas ActivityMonitor - Providing
Alarm and Automatic Termination of Release (RM-22)
2. Plant Vent System
a. Noble Gas ActivityMonitor Providing Alarm (RM-14 or RM 14R)
b. Iodine Sampler
c. Particulate Sampler
d. Flow Rate Monitor (FR.12)
e. Iodine Sampler Flow Rate Monitor
3. Containment Purge System
Noble Gas ActivityMonitor - Providing Alarm and Automatic Termination of Release
(RM44A or 44B)
CHANNEL
CHECK
W(4)
W(4)
SOURCE
CHECK
M
N.A.
N.A.
N.A.
N.A.
CHANNEL
CALIBRATION
R(3)
R(3)
N.A.
R(3)
CHANNEL
FUNCTIONAL
TEST
Q(1)
Q(2)
Q(1)
MODES FOR
WHICH
SURVEILLANCE
IS REQUIREO
01 192903.DOC IA 15
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PACIFIC GAS AND ELECTRIC COMPANYNUCLEARPOWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 16 OF 37
APPENDIX 6.1 Continued
TABLE6.1.2-2 ContinuedTABLENOTATIONS
At all times.** MODES 1-4; also MODE 6 during CORE ALTERATIONSor movement of irradiated fuel within
containment.
(1) The CHANNELFUNCTIONALTEST shall also demonstrate that automatic isolation of thispathway and control room alarm annunciation occurs ifany of the following conditions exists:
(2)
a. Instrument indicates measured levels above the Alarm/Trip Setpoint (isolation andalarm), or
b. Instrument indicates a downscale failure (alarm only), orc. Instrument controls not set in operate mode (alarm only).
The CHANNELFUNCTIONALTEST shall also demonstrate that control room alarmannunciation occurs ifany of the following conditions exist:
a. Instrument indicates measured levels above the Alarm Setpoint, orb. Circuit failure, orC. Instrument indicates a downscale failure, ord. Instrument controls not set in operate mode.
(3) The initial CHANNELCALIBRATIONshall be performed using one or more of the referencestandards certified by the National Bureau of Standards (NBS) or using standards that have beenobtained from suppliers that participate in measurement assurance activities with NBS. Thesestandards shall permit calibrating the system over its intended range of energy and measurementrange. For subsequent CHANNELCALIBRATION,sources that have been related to the initialcalibration shall be used.
(4) The CHANNELCHECK shall consist of verifying that the iodine cartridge and particulate filterare installed in the sample holders.
Fre uenc Notation
NotationDWMQRPN.A.
FrequencyAt least once per 24 hoursAt least once per 7 daysAt least once per 31 daysAt least once per 92 daysAt least once per 18 monthsCompleted prior to each releaseNot Applicable
01192903.DOC 1A 16
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PACIFIC GAS AND ELECTRIC COMPANYNUCLEAR POWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 17 OF 37
APPENDIX 6.1 Continued
6.1.3 Li uid Effluents - CONCENTRATION
Commitment for 0 eration
6.1.3.1 The concentration of radioactive material released in liquid effluents toUNRESTRICTED AREAS (see TS Figure 5.1-.3) shall be. limited to theconcentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2for radionuclides other than dissolved or entrained noble gases. Fordissolved or entrained noble gases, the concentration shall be limited to2 x 10 microcurie/ml total activity.
~Alicabilit: At all times.
Action:
With the concentration of radioactive material released in liquid effluents toUNRESTRICTED AREAS exceeding the above limits, immediately restorethe concentration to within the above limits.
Surveillance Re uirements
6.1.3.2 Radioactive liquid wastes shall be sampled and analyzed according to thesampling and analysis program of Table 6.1.3-1.
6.1.3.3 The results of the radioactivity analyses shall be used in accordance with themethodology and parameters in the ODCP to assure that the concentrations atthe point of release are maintained within the limits of Commitment 6.1.3.1.
01192903.DOC IA 17
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PACIFIC GAS ANDELECTRIC COMPANYNUCLEAR POWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 18 OF 37
APPENDIX 6.1 Continued
TABLE6.1.3-1RADIOACTIVELI UID WASTE SAMPLING AND ANALYSISPROGRAM
LIQUIDRELEASETYPE
1. Batch WasteReleaseTanks
'4'.
ContinuousReleases'"
Steam GeneratorBlowdown Tank
3. ContinuousReleases'"
Oily WaterSeparator Effluent
SAMPLINGFREQUENCY
pEach Batch
pOne Batch/M
Each Batch
Each Batch
DGrab Sample
Grab Sample
D
Grab Sample
D
Grab Sample
D
Grab Sample
MINIMUMANALYSIS
FREQUENCYp
Each Batch
M
Composite"'omposite"'
Composite"'omposite"i
Composite"i
W
Composite"'YPE
OFACTIVITYANALYSIS
Principal GammaEmitters t@
I-131
Dissolved andEntrained Gases
(Gamma emitters)
H-3
Gross Alpha
Sr-89, Sr-90
Fe-55
Principal GammaEmitters
"'-131
Dissolved andEntrained Gases
(Gamma emitters)
H-3
Gross Alpha
Sr-89, Sr-90
Fe-55
Principal GammaEmitters'@
LOWER LIMITOFDETECTION
(LLD)(pCi/ml)"
Sx10'x104
lx105
lx10'x10'x10
lx10~
Sx10'xl0~
lxl0~
ix10~
lx10'x10-s
lx10+
Sx10'
1 l92903.DOC 1A ts
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TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAMI
NUMBER CY2.ID1REVISION 3APAGE 19 OF 37
APPENDIX 6.1 Continued
TABLE6.1.3-1 ContinuedTABLENOTATIONS
(1) The LLD is defined, for the purposes of these specifications, as the smallest concentration ofradioactive material in a sample that willyield a net count, above system background, that willbedetected with 95% probability with only 5% probability of falsely concluding that a blankobservation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
LLD— 4.66 sb
E + V + 2.22 x 10 + Y + exp(-Mt)
Where:
LLDSb
EV
2.22 x 10'
ht
the "a priori" lower limitof detection (microcuries per unit mass or volume),the standard deviation of the background counting rate or of the counting rateof a blank sample as appropriate (counts per minute),the counting efficiency (counts per disintegration),the sample size (units of mass or volume),the number of disintegrations per minute per microcurie,the fractional radiochemical yield, when applicable,the radioactive decay constant for the particular radionuclide (sec'), andthe elapsed time between the midpoint of sample collection and the time ofcounting (sec).
(2)
(3)
(4)
Typical values of E, V, Y, and ht should be used in the calculation.
It should be recognized that the LLD is defined as an ~ariori (before the fact) limit representingthe capability of a measurement system and not as an ~aosterior (atter the fact) limit for a
particular measurement.
A composite sample is one in which the quantity of liquid sampled is proportional to the quantityof liquid waste discharged and in which the method of sampling employed results in a specimenwhich is representative of the liquids released.
To be representative of the quantities and concentrations of radioactive materials in liquideffluents, samples shall be composited in proportion to the rate of flow of the effluent stream.Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for thecomposite sample to be representative of the effluent release.
A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling foranalyses, each batch shall be isolated, and then thoroughly mixed, by a method described in theODCP, to assure representative sampling.
01192903.DOC 1A 19
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1
PACIFIC GAS AND ELECTRIC COMPANYNUCLEAR POWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 20 OF 37
(5)
(6)
APPENDIX 6.1 Continued
TABLE6.1.3-1 ContinuedTABLENOTATIONS
A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a
volume of system that has an input flow, during the continuous release.
The principal gamma emitters for which the LLD specification applies include the followingradionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141.Ce-144 shall also be measured but with an LLDof Sx10~. This list does not mean that only thesenuclides are to be considered. Other gamma peaks that are identifiable, together with those of theabove nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent ReleaseReport.
(7) Frequency Notation:
Notation FrequencyD At least once per 24 hours.W At least once per 7 days.M At least once per 31 days.
Q At least once per 92 days.P Completed prior to each release.
6.1.4 Li uid Effluents - Dose
Commitment for 0 eration
6.1.4.1 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactivematerials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (seeTS Figure 5.1-3) shall be limited:
During any calendar quarter to less than or equal to 1.5 mrem to the wholebody and to less than or equal to 5 mrem to any organ, and
During any calendar year to less than or equal to 3 mrem to the whole bodyand to less than or equal to 10 mrem to any organ.
~Atieebitit: At eii times.
Action:
With the calculated dose from the release of radioactive materials in liquideffluents exceeding any of the above limits, prepare and submit to theCommission within 30 days, pursuant to Technical Specification 6.9.2, a
Special Report that identifies the cause(s) for exceeding the limit(s) anddefines the corrective actions that have been taken to reduce the releases andthe proposed corrective actions to be taken to assure that subsequent releaseswillbe in compliance with the above limits.
01192903.DOC 1A 20
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'. " UIVC'OJVTROllED.PROCEDURE- DOIVOTUSE TO PERFORATE 'O'ORKorISSUEFOR USE "PACIFIC GAS AND ELECTRIC COMPANYNUCLEARPOWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 21 OF 37
Surveillance Re uirements
APPENDIX 6.1 Continued
6.1.4.2 Cumulative dose contributions from liquid effluents for the current calendar quarter andthe current calendar year shall be determined in accordance with the methodology andparameters in the ODCP at least once per 31 days.
6.1.5 Li uid Radwaste Treatment S stem
Commitment for 0 eration
6.1.5.1 The Liquid Radwaste Treatment System* shall be OPERABLE and appropriate portionsof the system shall be used to reduce the radioactive materials in liquid wastes prior totheir discharge when the projected doses due to the liquid effluent, from each unit, toUNRESTRICTED AREAS (see TS Figure 5.1-3) would exceed 0.06 mrem to thewhole body or 0.2 mrem to any organ in a 31-day period.
~Alicabilit: At aii times.
Action:
With any portion of the Liquid Radwaste Treatment System not in operationand with radioactive liquid waste being discharged without treatment and inexcess of the above limits, prepare and submit to the Commission within30 days, pursuant to Technical Specification 6.9.2, a Special Report whichincludes the following information:
Explanation of why liquid radwaste was being discharged withouttreatment, identification of any inoperable equipment or subsystems,and the reason for the inoperability,
Action(s) taken to restore the inoperable equipment to OPERABLEstatus, and
3. Summary description of action(s) taken to prevent a recurrence.
Surveillance Re uirements
6.1.5.2 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall beprojected at least once per 31 days, in accordance with the methodology and parametersin the ODCP when Liquid Radwaste Treatment Systems are not being fullyutilized.
6.1.5.3 The installed Liquid Radwaste Treatment System shall be considered OPERABLE bymeeting Commitments 6.1.3.1 and 6.1.4.1.
* The Liquid Radwaste Treatment System is common to both units.
01192903.DOC 1A 21
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PACIFIC GAS ANDELECTRIC COMPANYNUCLEAR POWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 22 OF 37
6.1.6 Gaseous Effluents - Dose Rate
Commitment for 0 eration
APPENDIX 6.1 Continued
6.1.6.1 The dose rate due to radioactive materials released in gaseous effluents from the site toareas at or beyond the SITE BOUNDARY (see TS Figure 5.1.-3).shall be limited to thefollowing:
a. For noble gases: Less than or equal to 500 mrem/yr to the whole body andless than or equal to 3000 mrem/yr to the skin, and
b. For Iodine-131, for Iodine-133, for tritium, and for all radionuclides inparticulate form with half-lives greater than 8 days: Less than or equal to1500 mrem/yr to any organ.
~Attcabtttt: At all times.
Action:
With the dose rate(s) exceeding the above limits, immediately decrease the release rateto within the above limit(s).
Surveillance Re uirements
6.1.6.2 The dose rate due to noble gases in gaseous effluents shall be determined to be withinthe above limits in accordance with the methodology and procedures of the ODCP.
6.1.6.3 The dose rate due to Iodine-131, Iodine-133, tritium, and all radionuclides in particulateform with half-lives greater than 8 days in gaseous effluents shall be determined to bewithin the above limits in accordance with the methodology and procedures of theODCP by obtaining representative samples and performing analyses in accordance withthe sampling and analysis program specified in Table 6.1.6-1.
01192903.DOC IA 22
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PAGE 23 OF 37TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
APPENDIX 6.1 Continued
TABLE6.1.6-1RADIOACTIVEGASEOUS WASTE SAMPLING AND ANALYSISPROGRAM
GASEOUS RELEASE TYPE
1. Waste Gas Decay Tank
2. Containment Purge
3. Plant Vent
SAMPLINGFREQUENCY
PEach TankGrab Sample
PEach
Purge"'rab
Sample
M<'>
Grab Sample
MP) (8
Grab Sample
MINIMUMANALYSIS
FREQUENCY
Each Tank
PEach
Purge"'r>
TYPE OFACTIVITYANALYSIS
Principal Gamma Emitters+(noble gases)
Principal Gamma Emitters+(noble gases)
I-131, I-133
Principal Gamma Emitters(particulates)
H-3
Principal Gamma Emitters+(noble gases)
H-3
LOWER LIMITOFDETECTION (LLD)
(pCi/ml) <'>
Ix10~
Ixl04
1x10 ~
1x10
Ix10~
1x10
1x10
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PAGE 24 OF 37TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
APPENDIX 6.1 Continued
TABLE6.1.6-1 Continued
4. AllRelease Types as listed in 1., 2.,3., above, at the plant vent
Continuous'
CharcoalSample
W'1 I-131
I-133
1x10'x10
5. Steam Generator Blowdown Tank Vent
Continuous'@
Continuous'@
Continuous'@
M1'0
w<'>
ParticulateSample
MCompositeParticulateSample
CompositeParticulateSample
M(8)
Principal Gamma Emitters+
Gross Alpha
Sr-89, Sr-90
Principal Gamma Emitters+(noble gases)
1x10"
1x10"
1x10"
Ix10~
01192903.DOC 1A 24
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PACIFIC GAS ANDELECTRIC COMPANYNUCLEARPOWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 25 OF 37
APPENDIX 6.1 Continued
TABLE 6.1.6-1 ContinuedTABLENOTATIONS
(1) The LLD is defined, for purposes of these specifications, as the smallest concentration ofradioactive material in a sample that willyield a net count, above system background, that willbedetected with 95% probability with only 5% probability of falsely concluding that a blankobservation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
I.LD = '
E V 2.22x10 Y exp(-Xb,t)
Where:
LLD
EV
2.22 x 10'
the "a priori" lower limitof detection (microcuries per unit mass or volume),the standard deviation of the background counting rate or of the counting rateof a blank sample as appropriate (counts per minute),the counting efficiency (counts per disintegration),the sample size (units of mass or volume),the number of disintegrations per minute per microcurie,the fractional radiochemical yield, when applicable,the radioactive decay constant for the particular radionuclide (sec'), andthe elapsed time between the midpoint of sample collection and the time ofcounting (sec).
Typical values of E, V, Y, and ht should be used in the calculation.
It should be recognized that the LLD is defined as an ~ariort (before the fact) limit representingthe capability of a measurement system and not as an ~aosterior (after the fact) limit for a
particular measurement.
(2) Sampling and analyses shall also be performed following shutdown, startup, or a THERMALPOWER change exceeding 15% of the RATED THERMALPOWER within a 1-hour period.
(3) Tritium grab samples shall be taken a least once per 24 hours when the refueling canal is flooded.
01192903. DOC lA 25
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TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.IDlREVISION 3APAGE 26 OF 37
APPENDIX 6.1 Continued
TABLE6.1.6-1 ContinuedTABLENOTATIONS Continued
(4) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hoursafter changing or after removal from sampler. Sampling shall also be performed at least once per24 hours for at least 7 days following each shutdown, startup or THERMALPOWER 'change
exceeding 15% of RATED THERMALPOWER within a 1-hour period and analyses shall becompleted within 48 hours of changing. When samples collected for 24 hours are analyzed, thecorresponding LLD's may be increased by a factor of 10. This requirement does not apply if: (1)analysis shows that the DOSE EQUIVALENTI-131 concentration in the reactor coolant has notincreased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity hasnot increased more than a factor of 3.
(5)
(6)
(7)
(8)
(9)
Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from thespent fuel pool area, whenever spent fuel is in the spent fuel pool.
The ratio of the sample flow rate to the sampled stream flow rate shall be known for the timeperiod covered by each dose or dose rate calculation made in accordance with Commitments6.1.6.1, 6.1.7.1, and 6.1.8.1.
The principal gamma emitters for which the LLD specification applies include the followingradionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases andMn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141, and Ce-144 inIodine and particulate releases. This list does not mean that only these nuclides are to beconsidered. Other gamma peaks that are identifiable, together with those of the above nuclides,shall also be analyzed and reported in the Annual Radioactive Effluent Release Report.
Grab samples shall be taken and analyzed at least once per 31 days whenever there is fiowthrough the steam generator blowdown tank. Releases of radioiodines shall be estimated based onsecondary coolant concentration and partitioning factors during releases or shall be measured.
Fre uenc Notation
NotationWMQP
FrequencyAt least once per 7 daysAt least once per 31 daysAt least once per 92 daysCompleted prior to each release
0l 192903.DOC lA 26
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NUCLEARPOWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 27 OF 37
6.1.7 Dose - Noble Gases
Commitment for 0 eration
APPENDIX 6.1 Continued
6.1.7.1 The air dose due to noble gases released in gaseous effluents, from each unit, to areasat or beyond the SITE BOUNDARY(see TS Figure 5.1-3).shall be limited to thefollowing:
During any calendar quarter: Less than or equal to 5 mrad for gammaradiation and less than or equal to 10 mrad for beta radiation, and
b. During any calendar year: Less than or equal to 10 mrad for gammaradiation and less than or equal to 20 mrad for beta radiation.
~Aticabiltt: At all times
Action:
With the calculated air dose from radioactive noble gases in gaseous effluentsexceeding any of the above limits, prepare and submit to the Commissionwithin 30 days, pursuant to Technical Specification 6.9.2, a Special Reportthat identifies the cause(s) for exceeding the limit(s), defines the correctiveactions that have been taken to reduce the releases and the proposedcorrective actions to be taken to assure that subsequent releases willbe incompliance with the above limits.
Surveillance Re uirements
6.1.7.2 Cumulative dose contributions for the current calendar quarter and current calendaryear for noble gases shall be determined in accordance with the methodology andparameters in the ODCP at least once per 31 days.
6.1.8 Dose - Iodine-131 Iodine-133 Tritium and Radioactive Material in Particulate Form
Commitment for 0 eration
6.1.8.1 The dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium andall radionuclides in particulate form with half-lives greater than 8 days in gaseouseffluents released, from each unit, to areas at and beyond the SITE BOUNDARY (seeTS Figure 5.1-3) shall be limited to the following:
During any calendar quarter: Less than or equal to 7.5 mrem to any organand,
b. During any calendar year: Less than or equal to 15 mrem to any organ.
~Aticabilit: At all times.
i
01192903.DOC 1A 27
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PACIFIC GAS AND ELECTRIC COMPANYNUCLEARPOWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 28 OF 37
Action:
APPENDIX 6.1 Continued
With the calculated dose from the release of Iodine-131, Iodine-133, tritium,and radionuclides in particulate form with half-lives greater than 8 days, ingaseous effluents exceeding any of the above limits, prepare and submit tothe Commission within 30 days, pursuant to Technical Specification 6.9.2, a
Special Report that identifies the cause(s) for exceeding the limit(s), definesthe corrective actions that have been taken to reduce the releases and theproposed actions to be taken to assure that subsequent releases willbe incompliance with the above limits.
Surveillance Re uirements
6.1.8.2 Cumulative dose contributions for the current calendar quarter and current calendaryear for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form withhalf-lives greater than 8 days shall be determined in accordance with the methodologyand parameters in the ODCP at least once per 31 days.
6.1.9 Gaseous Radwaste Treatment S stem
Commitment for 0 eration
The GASEOUS RADWASTE SYSTEM and the VENTILATIONEXHAUSTTREATMENTSYSTEM shall be OPERABLE. The appropriate portions of thesesystems shall be used to reduce releases of radioactivity when the projected doses in 31days due to gaseous effluent releases, from each unit, to areas at and beyond the SITEBOUNDARY (see TS Figure 5.1-3), would exceed 0.2 mrad to air from gammaradiation or Oe4 mrad to air from beta radiation or 0.3 mrem to any organ of a
MEMBER OF THE PUBLIC.
~Alicabiltt: At all times.
Action:
With radioactive gaseous waste being discharged without treatment and inexcess of the above limits, prepare and submit to the Commission within 30days, pursuant to Technical Specification 6.9.2, a Special Report thatincludes the following information:
1. Identification of the inoperable equipment or subsystems and the reasonfor inoperability,
2. Action(s) taken to restore the inoperable equipment to OPERABLEstatus, and
3. Summary description of action(s) taken to prevent a recurrence.
01192903.DOC iA 28
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; ", ',:UNCONTROllEDPROCEDURE-DO NOTUSE TO PERFORM 5'08ICorISSUEFOR USEPACIFIC GAS AND ELECTRIC COMPANYNUCLEARPOWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 29 OF 37
Surveillance Re uirements
APPENDIX 6.1 Continued
6.1.9.2 Doses due to gaseous releases from each unit to areas at and beyond the SITEBOUNDARYshall be projected at least once per 31 days, in accordance with themethodology and parameters in the ODCP when Gaseous Radwaste Treatment Systemsare not being fullyutilized.
6.1.9.3 The installed VENTILATIONEXHAUST TREATMENTSYSTEM and GASEOUSRADWASTE SYSTEM shall be considered OPERABLE by meeting Commitments6.1.6.1 and 6.1.7.1 or 6.1.8.1.
6.1.10 Total Dose
Commitment for 0 eration
6.1. 10.1 The annual (calendar year) dose or dose commitment to any MEMBER OF THEPUBLIC due to releases of radioactivity and to radiation from uranium fuel cyclesources shall be limited to less than or equal to 25 mrems to the whole body or anyorgan, except the thyroid, which shall be limited to less than or equal to 75 mrems.
~Aplicabilitlr, At all times.
Action:
With the calculated doses from the release of radioactive materials in liquidor gaseous effluents exceeding twice the limits of Commitments 6.1.4.1.a,6.1.4.1.b, 6.1.7.1.a, 6.1.7.1.b, 6.1.8.1.a, or 6.1.8.1.b, calculations shall bemade including direct radiation contributions from the units and from outsidestorage tanks to determine whether the above limits of RegulatoryCommitment 6.1.10.1 have been exceeded. Ifsuch is the case, prepare andsubmit to the Commission within 30 days, pursuant to Technical Specification6.9.2, a Special Report that defines the corrective action to be taken toreduce subsequent releases to prevent recurrence of exceeding the abovelimits and includes the schedule for achieving conformance with the abovelimits. This Special Report, as defined in 10 CFR 20.2203(a), shall includean analysis that estimates the radiation exposure (dose) to a MEMBER OFTHE PUBLIC from uranium fuel cycle sources, including all effluentpathway and direct radiation, for the calendar year that includes the release(s)covered by this report. It shall also describe levels of radiation andconcentrations of radioactive material involved, and the cause of the exposurelevels or concentrations. Ifthe estimated dose(s) exceeds the above limits,and ifthe release condition resulting in violation of 40 CFR Part 190 has notalready been corrected, the Special Report shall include a request for a
variance in accordance with the provisions of 40 CFR Part 190. Submittal ofthe report is considered a timely request, and a variance is granted until staffaction on the request is complete.
01192903.DOC IA 29
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TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 30 OF 37
Surveillance Re uirements
APPENDIX 6.1 Continued
6.1.10.2 Cumulative dose contributions from liquid and gaseous effluents shall be determined inaccordance with Commitments 6.1.4.2, 6.1.7.2, and 6.1.8.2, and in accordance withthe methodology and parameters in the ODCP.
6.1.10.3 Cumulative dose contributions from direct radiation from the units and from outsidestorage tanks shall be determined in accordance with the methodology and parametersin the ODCP. This requirement is applicable only under conditions set forth inACTION a. of Commitment 6.1.10.1.
6.1.11 Radiolo ical Environmental Monitorin
6.1.11.1 Commitment for 0 eration - The Radiological Environmental Monitoring Programshall be conducted as specified in RP1.ID11, "Environmental Radiological MonitoringProcedure."
~Aticabitit: At all times.
Action:
With the confirmed level of radioactivity as the result of plant effluents in anenvironmental sampling medium at a specified location exceeding the"Reporting Levels for Nonroutine Operating Reports" in RP1.ID11 whenaveraged over any calendar quarter, prepare and submit to the Commissionwithin 30 days from the end of the quarter, pursuant to Specification 6.9.2, aNonroutine Radiological Environmental Operating Report that identifies thecause(s) for exceeding the limit(s) and defines the corrective actions to betaken to reduce radioactive effluents so that the potential annual dose to a
MEMBER OF THE PUBLIC is less than the calendar year limits ofCommitment 6.1.4.1, 6.1.7.1, or 6.1.8.1. A confirmatory reanalysis of theoriginal, a duplicate, or a new sample may be desirable, as appropriate. Theresults of the confirmatory analysis shall be completed at the earliest timeconsistent with the analysis, but in any case within 30 days. When more thanone of the radionuclides from "Reporting Levels for Nonroutine OperatingReports" in RP1.ID11 are detected in the sampling medium, this report shallbe submitted if:
concentration (1) concentration (2)+ + ...a 1.0reporting level (1) reporting level (2)
01 l92903.DOC 1A 30
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lJNCONTROLL-EDPROCEDlJRE- DO NOT'USE TO PERFORM,NOR/C'oi 'ISSUEFOR USE '-"PACIFIC GAS AND ELECTRIC COMPANYNUCLEAR POWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 31 OF 37
t
APPENDIX 6.1 Continued
When radionuclides other than those in the "Reporting Levels for NonroutineOperating Reports" in RP1.ID11 are detected and are the result of planteffluents, a Nonroutine Radiological Environmental Operating Report shallbe submitted ifthe potential annual dose to a MEMBER OF THE PUBLICfrom all radionuclides is equal to or greater than. the calendar year limits ofCommitment 6.1.4.1, 6.1.7.1, or 6.1.8.1. This report shall include anevaluation of any release conditions, environmental factors, or other aspectsnecessary to explain the anomalous result.
6.1.12 LAND.USE CENSUS
6.1.12.1 A Land Use Census shall be conducted as specified in RP1.ID11, "EnvironmentalRadiological Monitoring Procedure."
~Aticabitit: At aii times.
Action:
With a Land Use Census identifying a location(s) that yields a calculated doseor dose commitment greater than the values currently being calculated inCommitment 6.1.8.2, identify the new location(s) in the next AnnualRadioactive Effluent Release Report.
With a Land Use Census identifying a location(s) that yields a calculated doseor dose commitment (via the same exposure pathway) 20% greater than at a
location from which samples are currently being obtained in accordance withCommitment 6.1.11.1, add the new location(s) within 30 days to theRadiological Environmental Monitoring Program given in the ERMP. Thesampling location(s), excluding the control station location, having the lowestcalculated dose or dose commitment(s), via the same exposure pathway, maybe deleted from this monitoring program after October 31 of the year inwhich this Land Use Census was conducted. Submit in the next AnnualRadioactive Effluent Release Report documentation for a change in theERMP including a revised figure(s) and table(s) for the ERMP reflecting thenew location(s) with information supporting the change in sampling locations.
Bases
6.1.1 Radioactive Li uid Effluent Monitorin Instrumentation
The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable,the releases of radioactive materials in liquid effluents during actual or potential releases of liquideffluents. The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted inaccordance with the methodology and parameters in the ODCP to ensure that the alarm/trip willoccur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITYand use of thisinstrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 ofAppendix A to 10 CFR Part 50.
01192903.DOC 1A 31
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TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAMt
NUMBER CY2.ID1REVISION 3APAGE 32 OF 37
6.1.2
6.1.3
APPENDIX 6.1 Continued
Radioactive Gaseous Effluent Monitorin Instrumentation
The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable,the releases of radioactive materials in gaseous effluents during actual or potential releases ofgaseous effluents. The Alarm/Trip Setpoints for these instruments shall be calculated and adjustedin accordance with the methodology and parameters in the ODCP to ensure that the alarm/trip willoccur prior to exceeding the limits of NUREG 0133. The OPERABILITYand use of thisinstrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 ofAppendix A to 10 CFR Part 50. The sensitivity of any noble gas activity monitors used to showcompliance with the gaseous effluent release requirements of Regulatory Commitment 6.1.7.1shall be such that concentrations as low as 1 x 10~ pCi/ml are measurable.
Li uid Effluents - Concentration
This Regulatory Commitment is provided to ensure that the concentration of radioactive materialsreleased in liquid waste effluents to UNRESTRICTED AREAS willbe less than the concentrationlevels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. This limitation providesadditional assurance that the levels of radioactive materials in bodies of water inUNRESTRICTED AREAS willresult in exposures within: (1) the Section II.Adesign objectivesof Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of10 CFR 20.1301(e) to the population. The concentration limit for dissolved or entrained noblegases is based upon the assumption that Xe-135 is the controlling radioisotope and its EffluentConcentration Limit (ECL) in air (submersion) was converted to an equivalent concentration inwater using the methods described in International Commission on Radiological Protection (ICRP)Publication 2.
This Regulatory Commitment applies to the release of radioactive materials in liquid effluentsfrom all units at the site.
The required detection capabilities for radioactive materials in liquid waste samples are tabulatedin terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and otherdetection limits can be found in Currie, L.A., "Lower Limitof Detection: Definition andElaboration of a Proposed Position for Radiological Effluent and Environmental Measurements,"NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300 (revisedannually).
01192903.DOC lA 32
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PACIFIC GAS AND ELECTRIC COMPANYNNUCLEARPOWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.IDlREVISION 3APAGE 33 OF 37
6.1.4 Li uid Effluents - Dose
APPENDIX 6.1 Continued
6.1.5
This Regulatory Commitment is provided to implement the requirements of Sections II.A, III.Aand IV.Aof Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements theguides set forth in Section II.Aof Appendix I. The ACTION statements provide the requiredoperating flexibilityand at the same time implement the guides set forth in Section IV.AofAppendix I to assure that the releases of radioactive material in liquid effluents toUNRESTRICTED AREAS willbe kept "as low as is reasonably achievable." The dosecalculation methodology and parameters in the ODCP implement the requirements in Section HI.Aof Appendix I that conformance with the guides of Appendix I be shown by calculationalprocedures based on models and data, such that the actual exposure of a MEMBER OF THEPUBLIC through appropriate pathways is unlikely to be substantially underestimated. Theequations specified in the ODCP for calculating the doses due to the actual release rates ofradioactive materials in liquid effluents are consistent with the methodology provided inRegulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of ReactorEffluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents fromAccidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April1977.
This Regulatory Commitment applies to the release of radioactive materials in liquid effluentsfrom each unit at the site. For units with shared Radwaste Treatment Systems, the liquid effluentsfrom the shared system are to be proportioned among the units sharing that system.
Li uid Radwaste Treatment S stem
The OPERABILITYof the Liquid Radwaste Treatment System ensures that this system willbeavailable for use whenever liquid effluents require treatment prior to release to the environment.The requirement that the appropriate portions of this system be used when specified providesassurance that the releases of radioactive materials in liquid effluents willbe kept "as low as isreasonably achievable." This specification implements the requirements of 10 CFR 50.36a,General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given inSection II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use ofappropriate portions of the Liquid Radwaste Treatment System were specified as a suitablefraction of the dose design objectives set forth in Section II.Aof Appendix I, 10 CFR Part 50, forliquid effluents.
This Regulatory Commitment applies to the release of radioactive materials in liquid effluentsfrom each unit at the site. For units with shared Radwaste Treatment Systems, the liquid effluentsfrom the shared system are to be proportioned among the units sharing that system.
01192903. DOC 1A 33
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PACIFIC GAS AND ELECTRIC COMPANYNUCLEAR POWER GENERATION
~ TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 34 OF 37
6.1.6 Gaseous Effluents - Dose Rate
APPENDIX 6.1 Continued
This Regulatory Commitment is provided to ensure that the dose at any time at and beyond theSITE BOUNDARYfrom gaseous effluents from all units on the site willbe within the annual dose
limits of NUREG 0133 to UNRESTRICTED AREAS. The annual dose limits are the doses to beassociated with the concentrations of 10 CFR Part 20, Appendix'B, Table 2, Column 1. Theselimits provide reasonable assurance that radioactive material discharged in gaseous effluents willnot result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA,either within or outside the SITE BOUNDARY, to average concentrations exceeding the limits tobe specified in Appendix B, Table 2 of 10 CFR Part 20 (10 CFR Part 20.1302(c)). ForMEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, theoccupancy of that MEMBER OF THE PUBLIC willusually be sufficiently low to compensate forany increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examplesof calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors,shall be given in the ODCP. The specified release rate limits of NUREG 0133 restrict, presently,the corresponding gamma and beta dose rates above background to a MEMBER OF THEPUBLIC at or beyond the SITE BOUNDARYto less than or equal to 500 mrems/year to thewhole body or to less than or equal to 3000 mrems/year to the skin. These release rate limits alsorestrict, at all times, the corresponding thyroid dose rate above background to a child via theinhalation pathway to less than or equal to 1500 mrems/year.
This Regulatory Commitment applies to the release of radioactive materials in gaseous effluentsfrom all units at the site.
The required detection capabilities for radioactive material in gaseous waste samples are tabulatedin terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and otherdetection limits can be found in Currie, L.A., "Lower Limitof Detection: Definition andElaboration of a Proposed Position for Radiological Effluent and Environmental Measurements,"NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASI 300 (revisedannually).
01192903.DOC 1A 34
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TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 35 OF 37
6.1.7 Dose - Noble Gases
APPENDIX 6.1 Continued
This Regulatory Commitment is provided to implement the requirements of Sections II.B, III.Aand IV.Aof Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements theguides set forth in Section II.B of Appendix I. The ACTION statements provide the requiredoperation flexibilityand at the same time implement the guides set'forth in Section IV.AofAppendix I to assure that the releases of radioactive material in gaseous effluents toUNRESTRICTED AREAS willbe kept "as low as is reasonably achievable." The SurveillanceRequirements implement the requirements in Section III.Aof Appendix I that conformance withthe guides of Appendix I be shown by calculational procedures based on models and data suchthat the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways isunlikely to be substantially underestimated. The dose calculation methodology and parametersestablished in the ODCP for calculating the doses due to the actual release rates of radioactivenoble gases in gaseous effluents are consistent with the methodology provided in RegulatoryGuide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluentsfor the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1,October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport andDispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"Revision 1, July 1977. The ODCP equations provided for determining the air doses at andbeyond the SITE BOUNDARYare based upon the historical average atmospheric conditions.
This Regulatory Commitment applies to the release of radioactive materials in gaseous effluentsfrom each unit at the site. For units with shared Radwaste Treatment Systems, the gaseouseffluents from the shared system are proportioned among the units sharing the system.
01192903.DOC lA 35
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I
' UilfCONTROl'lEDPROCEOl/8E-'DONOTIJSE TOPERFORN 5'ORA'oI...JSSLIE:FOR USE'PACIFIC GAS AND ELECTRIC COMPANYNUCLEARPOWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 36 OF 37
6.1.8
APPENDIX 6.1 Continued
Dose - Iodine-131 Iodine-133 Tritium and Radioactive Material in Particulate Form
This Regulatory Commitment is provided to implement the requirements of Sections II.C, III.A,and IV.Aof Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guidesset forth in Section II.C of Appendix I. The ACTION statements provide the required operatingflexibilityand at the same time implement the guides set forth in Sections.A of Appendix I toassure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREASwillbe kept "as low as is reasonably achievable." The ODCP calculational methods specified inthe Surveillance Requirements implement the requirements in Section III.Aof Appendix I thatconformance with the guides of Appendix I be shown by calculational procedures based onmodels and data, such that the actual exposure of a MEMBER OF THE PUBLIC throughappropriate pathways is unlikely to be substantially underestimated. The ODCP calculationalmethodology and parameters for calculating the doses due to the actual release rates of the subjectmaterials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculationof Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose ofEvaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 andRegulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion ofGaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,: Revision 1, July1977. These equations also provide for determining the actual doses based upon the historicalaverage atmospheric conditions. The release rate specifications for Iodine-131, Iodine-133,tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependentupon the existing radionuclide pathways to man in the areas at and beyond the SITEBOUNDARY. The pathways that were examined in the development of the calculations were:(1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafyvegetation with subsequent consumption by man, (3) deposition onto grassy areas where milkanimals and meat-producing animals graze with consumption of the milk and meat by man, and
(4) deposition on the ground with subsequent exposure of man.
This Regulatory Commitment applies to the release of radioactive materials in gaseous effluentsfrom each unit at the site. For units with shared Radwaste Treatment Systems, the gaseouseffluents from the shared system are proportioned among the units sharing that system.
01192903.DOC IA 36
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PACIFIC GAS AND ELECTRIC COMPANYNUCLEARPOWER GENERATION
TITLE: RADIOACTIVEEFFLUENT CONTROLS PROGRAM
NUMBER CY2.ID1REVISION 3APAGE 37 OF 37
APPENDIX 6.1 Continued
6.1.9 Gaseous Radwaste Treatment S stem
The OPERABILITYof the GASEOUS RADWASTE SYSTEM and the VENTILATIONEXHAUST TREATMENTSYSTEM ensures that the systems willbe available for use whenevergaseous effluents require treatment prior to release to the environment. The requirement that theappropriate portions of these systems be used, when specified, provides reasonable assurance thatthe releases of radioactive materials in gaseous effluents willbe kept "as low as is reasonablyachievable." This specification implements the requirements of 10 CFR 50.36a, General DesignCriterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section II.D ofAppendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions ofthe systems were specified as a suitable fraction of the dose design objectives set forth in SectionsII.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
This Regulatory Commitment applies to the release of radioactive materials in gaseous effluentsfrom each unit at the site. For units with shared Radwaste Treatment Systems, the gaseouseffluents from the shared system are proportioned among the units sharing that system.
6.1 ~ 10 Total Dose
This Regulatory Commitment is provided to meet the dose limitations of 40 CFR Part 190 thathave been incorporated into 10 CFR Part 20 by 46 FR 18525. The specification requires thepreparation and submittal of a Special Report whenever the calculated doses due to releases ofradioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole bodyor any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. Forsites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OFTHE PUBLIC willexceed the dose limits of 40 CFR Part 190 ifthe individual reactors remainwithin twice the dose design objectives of Appendix I, and ifdirect radiation doses from the unitsand from outside storage tanks are kept small. The Special Report willdescribe a course of actionthat should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to withinthe 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that thedose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources isnegligible, with the exception that dose contribution from other nuclear fuel cycle facilities at thesame site or within a radius of 8 km must be considered. Ifthe dose to any MEMBER OF THEPUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a
request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and10 CFR 20.2203(a), is considered to be a timely request and fulfillsthe requirements of40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of10 CFR Part 20, as addressed in Regulatory Commitment 6.1.3.1 and 6.1.6.1. An individual isnot considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged incarrying out any operation that is part of the nuclear fuel cycle.
01192903.DOC lA 37
ci
Attachment 4PG8 E Letter DCL 99-055
Off-Site Dose Calculation Procedure (ODCP)
(CAP A-8 Revision 22)
***ISSUED FOR USE BY:PACIFIC GAS AND ELECTRIC COMPANYNUCLEAR POWER GENERATIONDIABLOCANYONPOWER PLANTCHEMICALANALYSISPROCEDURE
DATE: EXPIRES:NUMBER CAP A-8
REVISION 22
PAGE 1 OF 64
UNITS
TITLE: OFF-SITE DOSE CALCULATIONS
EFFECTIVE DATE
PROCEDURE CLASSIFICATION: QUALITYRELATED
SECTION
SCOPE ...DISCUSSIONRESPONSIBILITIES ...PRERE UISITES
TABLEOF CONTENTS
PRECAUTIONSINSTRUCTIONS
Liquid Effluents.Liquid Effluents - Dose Calculation.10 CFR 20, Appendix B, Table 2, Column 2, Effluent (liquid) Concentration Limit (ECL)Calculation.Liquid Effluent Radiation Monitor Set Point MethodologyDose Projection (for Liquid Effluents) .
Liquid LimitingFlow Rate Methodology - ECL Based.Liquid Limiting Flow Rates - LLD Based.
Gaseous Effluents.Plant Vent Noble Gas Monitor - RE-14 HASPContainment Purge - RE-44 HASP .
Dose To Critical Receptor Due To Radioiodines, Tritium and Particulates Released in GaseousEffluents.
40 CFR 190 Dose CalculationsACCEPTANCE CRITERIA .
REFERENCESRECORDSAPPENDICESATTACHMENTSSPONSOR .
PAGE
23
3
3
3
444
67
13
15
16
18
2128
3442474747484848
Table 6.1 - Typical Liquid Effluent Discharge Pathway Allocation Factors.Table 6.2 - Typical Gaseous Effluent Discharge Pathway Allocation Factors ..............Table 6.3 - Expected On-Site Distance and Visitation Times for Members of the Public.
Figure 6.1 - Liquid Discharges (LRW) Monitored for RadioactivityFigure 6.2 - Gaseous Discharges (GRW) Monitored for Radioactivity
8
20.. 46
4950
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UNITS I AND 2
SCOPE
This procedure describes the methodology for the following:
EffluentType
Liquids
Gases
RECP orTech Spec
6.1.1.1 (RECP)6.1.3.1 (RECP)
6.1.2.1 (RECP)6.1.6.1 (RECP)
RECP or Tech Spec Surveillance Requirement
Determination of alarm/trip setpoints for RE-18;RE-23, and RE-3
Determination of alarm/trip setpoints for RE-22,RE-14, and RE-14R
Implements
10 CFR 20 App. BTable 2, Col. 2
NUREG 0133
Liquids
Liquids
Liquids
Gases
6.1.3.2 (RECP) Prerelease analyses of effluents6.1.3.3 (RECP)
Postrelease analysis of effluents
6.1.4.2 (RECP) Dose calculations
6.1.5.2 (RECP) Dose projections
6.1.6.2 Dose Rate calculations, Noble Gases, Total Body andSkin
10 CFR20 App. BTable 2, Col. 2
10 CFR 50 App. I
10 CFR 50 App. I
NUREG 0133
Gases 6.1.6.3 Dose Rate calculations, Iodines, Particulates and, NUREG 0133Radionuclides other than Noble Gases, per organ, perage group
Gases
Gases
Gases
6.1.7.2 (RECP) Noble Gas AirDose Calculations
6.1.8.2 (RECP)
6.1.9.2 (RECP)
Iodines, Particulates, and Radionuclides other thanNoble Gases Organ Dose Calculations per age group
Noble Gases, Iodines, Particulates, and Radionuclidesother than Noble Gases, Dose Projection
10 CFR 50 App. I
10 CFR 50 App. I
10 CFR 50 App. I
LiquidsandGases
DirectRadiation
6.1.10.2(RECP)4.4.2.b.l(RECP)
6.1.10.3(RECP)
Cumulative Dose from: Liquids, Noble Gases,Iodines, Particulates, and Radionuclides other thanNoble Gases per age group, per organ
Direct Radiation Dose Rate and Dose Calculations tounrestricted areas due to plant and high radwastestorage sky-shine
40 CFR 190
40 CFR 190
The calculational methodology for doses are based on models and data that make it unlikely tosubstantially underestimate the actual exposure of an individual through any of the appropriatepathways. Tables containing the values for the various parameters used in these expressions arealso included.
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UNITS 1 AND 2
2. DISCUSSION
This procedure is used in support of the Radiological Monitoring and Controls Program (RMCP),and Radioactive Effluent Controls Program (RECP), and the portion that deals with routineradioactive liquid and gaseous releases to the unrestricted area. Limits are based on the'dose
commitment to a member of the general public related to the release of radionuclides througheither direct or indirect exposure (e.g., submersion in a cloud'of radioactive Noble Gases,
radionuclides deposited on the ground, direct radiation from radionuclides stored on-site,inhalation of radionuclides or ingestion of radionuclides via a food pathway such as milk, meat,vegetable or fish, etc.).
Further, the conduct of the Environmental Radiological'Monitoring Procedure (ERMP) is foundin RP1.ID11.
3. RESPONSIBILITIES
3.1 The Director, Chemistry is the overseeing authority of responsibility for ensuring thatthe off-site dose calculational procedure (ODCP) meets all RECP and Tech Specrequirements with regards to calculated doses delivered by the plant to the unrestrictedarea surrounding the site.
3.2
3.3
3.4
3.5
3.6
The Senior Radiochemistry Engineer assumes the overall responsibility for ensuringthat this procedure's program is followed and implemented where appropriate,especially in regards to RECP or Tech Spec requirements.
The Radiochemistry Effluents Engineer has the responsibility of correct and timelyimplementation of all the procedure's calculational methodology, where appropriate, foreach radioactive effluent released. Furthermore this engineer is responsible for:reviewing the results; cross (spot) checking the calculations; and maintaining an updatedarchive of post release calculated doses for annual report purposes.
The Senior Engineer Tech Maintenance Computer Group assures that any supportingcomputer software is maintained current and compatible with the procedure'scalculational methodology and that the computer hardware is maintained operable at alltimes.
The Radiochemistry staff engineer provides an oversight of the effluents program'sODCP to: confirm compliance with RECP or Tech Specs; provide technical support;recommend or design improvements to the dose calculational methodology and theeffluent program control; and investigate long-term planning toward effluent related
'ctivitiesand their associated dose calculations.
Responsibilities as described in CY1, " Chemistry and Radiochemistry," andCY1.DC1, "Analytical Data Processing Responsibilities," apply.
Not Applicable
PRECAUTIONS
Not Applicable
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NUMBER CAP A-8REVISION 22PAGE 4 OF 64
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INSTRUCTIONS
6.1 Liquid Effluents
6.1.1 Liquid Effluents - Dose Calculation
The dose contributions to the total body and each individual organ (bone,liver, thyroid, kidney, lung and GI-LLI)of the maximum exposed individual(adult) due to consumption of saltwater fish and saltwater invertebrate is
calculated for all radionuclides identified in liquid effluents released tounrestricted areas using the following expression:
D, = F, 6t gA,,C,. eI
Where:
Do The dose commitment to organ, o, in mrem.
Fc Near field average dilution factor during the period of therelease. It is defined as:
Where:
Waste FlowDilutionFlow x Z
(2)
C;
Z is the site specific factor for the mixing effect of thedischarge structure. Specifically, it is the credit taken fordilution which occurs between the discharge structure andthe body of water which contaminates fish or invertebratesin the liquid ingestion pathway. For DCPP Z = 5.
The time period for the release in hours.
The site specific ingestion dose commitment factor toorgan, o, due to radionuclide, i, in mrem/hr per pCi/ml as
defined by Equation 3.
Concentration of radionuclide, i, in the undiluted liquideffluent, in pCi/ml.
Decay constant of radionuclide, i.
Time interval between end of sampling and midpoint ofrelease.
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The site specific ingestion dose commitment factor, A;„ is defined as:
A. =1c U„BF. +U,BI. DF.
Where:
Units conversion factor of 1. 14x10- in units ofpCi/pCi x ml/1 x yr/hr.
(3)
UF —— Saltwater fish consumption rate in kilograms of fish peryear. DCPP value for this parameter is 21 kg/yr and istaken from NUREG 0133, Section 4.3.1.
BFi
BI;
DF;
Saltwater bioaccumulation factor for nuclide, i, in fishflesh in units of pCi/Kg per pCi/1. Values for BF; aretaken from Table A-1 of Reg. Guide 1.109.
Saltwater invertebrate consumption rate in kilograms peryears. DCPP value for this parameter is 5 kg/yr and istaken from NUREG 0133, Section 4.3.1.
Saltwater bioaccumulation factor for nuclide, i, ininvertebrate flesh in units of pCi/Kg per pCi/1. Values forBI; are taken from Table A-1 of Reg. Guide 1.109.
Adult ingestion dose conversion factor for nuclide, i, inmrem per pCi ingested, from Table E-11 of RegulatoryGuide 1.109, with the following exceptions: H-3, Br-82,Sb-124 and Sb-125 ingestion dose conversion factors aretaken from NUREG/CR-4013. As-76, Sn-113, Sn-117mand Sb-122 ingestion dose conversion factors werecalculated by ORNL using ICRP-2 methodology.
The site specific values for A;, are listed in Table 10.1.
Units 1 and 2 share a common liquid radwaste (LRW) treatment system. Theeffluent doses due to releases discharged via the common LRW areapportioned between the units with 50% credited to Unit 1 and 50% creditedto Unit 2.
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UNITS I AND 2
6.1.2 10 CFR 20, Appendix B, Table 2, Column 2, Effluent (liquid) ConcentrationLimit (ECL) Calculation
a. The ECL for the identified mixture of radionuclides in the "j " batch ofliquids is calculated as follows:
Where:
pc.„.ECL =
ECL
(4)
ECL1
C0
ECL0
The unrestricted area, total undiluted ECL for the"j " particular mixture of identified radionuclides,in pCi/ml.
The concentration of radionuclide "i," in pCi/mlfor the "j "mixture.
The ECL in unrestricted area water forradionuclide "i," in general, in pCi/ml (from10 CFR 20, Appendix B, Table 2, Column 2).
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b. The overall ECL for simultaneous discharges is given by Equation 5.
Where:
ECLovcrall
C;
ECLJ
ge,.c,.j~l
overall n
,, ECL;
The unrestricted area ECL for the current radionuclidemixture for concurrent "j"discharges (in pCi/ml).
The total activity concentration for the "j " individualstream in pCi/ml.
The total ECL for the "j " individual mixture (orstream) determined as defined in Equation 4, inpCi/ml.
The ratio of an individual discharge "j " pathwayflowrate to the sum total of all individual undilutedpathway flowrates as defined by:
Where:
fjJ
J
fj = Undiluted effluent flowrate for pathway, "j".
6.1.3 Liquid Effluent Radiation Monitor Set Point Methodology
Introduction
The DCPP radiological effluent controls program requires that theliquid effluent monitors be operable with their alarm/trip set points set
to ensure that the effluent concentration limits of 10 CFR 20 are notexceeded.
The alarm/trip set point for the liquid effluent radiation monitors is
derived from the concentration limitset forth in Appendix B, Table 2,Column 2 of 10 CFR 20.1001-2404.
The alarm/trip set points are applied at the unrestricted area boundary.The set points take into account appropriate factors for dilution,dispersion, or decay of radioactive materials that may occur betweenthe point of discharge and the unrestricted area boundary.
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b. Allocation and Safety Factors
The limits of RCMP 6.1.3.1 are site limits which require that the set
point methodology must ensure simultaneous releases do not exceed the
liquid effluent concentration limits of 10 CFR 20 in the unrestrictedarea. The DCPP High Alarm Set Point (HASP) methodology makesuse of an Allocation Factor (AF) to limit'he effluent concentrationsfrom simultaneous liquid discharges. The Allocation Factors can be
adjusted based upon, operational requirements with the restriction thatthe sum of the Allocation Factors must be less than or equal to 1.
Typical Allocation Factors are shown Table 6. 1.
Table 6. 1
Typical Liquid Effluent Discharge Pathway Allocation Factors
Discharge PathwayOily Water Separator RE-3 0.01
Rad Monitor Allocation Factor (AF)
Liquid Radwaste SystemSteam Generator Blow Down (Unit 1)
Steam Generator Blow Down (Unit 2)Miscellaneous
RE-18RE-23 (U1)RE-23 (U2)
none
0.900.040.040.01
An additional level of conservatism in the HASP methodology is
implemented by the use of a Safety Factor (SF). The Safety Factor is
defined as 0.9 and provides for a High Alarm Set Point at 90% of the10 CFR 20 concentration limits.
Tritium Correction Factor „
As result of an aggressive liquid radwaste treatment program, the liquideffluents at DCPP typically contain very low levels, of gamma emitters.In order to reduce the over all volume of liquid waste discharged,DCPP also recycles waste water. This recycling results in highertritium concentration in liquid effluents when compared with the lowgamma emitter concentrations. As a result, standard HASPmethodology results in very low set points. In some cases thecalculated set points are barely above the monitor background.
The liquid HASP methodology used by DCPP uses a TritiumCorrection Factor (TCF) which assumes a constant, but conservativetritium concentration in the liquid effluent. This results in an
operationally reasonable set point while ensuring that the liquid effluentconcentrations released to the unrestricted areas do not exceed the limitsof 10 CFR 20.
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The Tritium Correction Factor is defined as shown in Equation 7.
H3I C H3
@if (7)
Where:
ECLii3 = effluent concentration limitof tritium
CH3 = concentration of tritium in the release mix,pre-dilution (pCi/ml)
conservative dilution flow rate (gpm)
conservative undiluted effluent flow rate (gpm)
The concentration of tritium, Cio, is conservatively estimated.
d. Liquid Effluent Radiation Monitor Set Point Calculations
The High Alarm Set Point (HASP) are calculated to ensure that theliquid effluent concentration limits of 10 CFR 20 are not exceeded.The set points represent the maximum operational set point. The actualset point used by operations willbe equal to or less than the actualvalue as determined by the HASP methodology described in thissection.
1. Set Point Methodology for RE-3 HASP: Oily Water Separator
Under normal conditions, the Oily Water Separator stream does
not contain any radioactive material. Only in the event that thereis primary to secondary leakage does this become a potentialliquid effluent discharge point. In order to insure that nounplanned or unmonitored releases take place by way of the OilyWater Separator, RE-3 serves to monitor the discharge even whenno activity has been identified in the effluent. When no significantprimary to secondary leakage is taking place or when no activityhas been identified in the Oily Water Separator, the High AlarmSet Point for RE-3 is calculated as shown in Equation 8.
HASP~ 3= 3 X BEGD~ 3 (8)
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In the event that primary to secondary leakage results in activitybeing detected in the Oily Water Separator, Equation 9 willbeused to calculate a High Alarm Set Point value. The greaterHASP value as determined by Equation 8 or Equation 9 willbeused.
HASP~, = BKGD„~, + (AF)(SF) x gk„C gc, zcl.,IwH3
x TCF (9)
Where:
HASPRE.3
BKGDRa.3
(AF)
high alarm setpoint for RE-3 (cpm)
background reading for RE-3 (cpm)
allocation factor for the oily water separatoreffluent system from Table 6. 1 (0.01)
(SF) safety factor for RE-3 (0.9)
monitor response factor (cpm/pCi/ml)
concentration of gamma emitting isotopes in therelease mix, pre-dilution (pCi/ml)
dilution flow rate (gpm)
undiluted effluent flow rate (gpm)
C; concentration of isotope "i," in the release mix,pre-dilution (pCi/ml)
ECL;
TCF
effluent concentration limitof isotope "i"
tritium correction factor as defined by Equation 7.
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UNITS 1 AND 2
2. Set Point Methodology for RE-18 HASP: Liquid Radwaste
System
The High Alarm Set Point for the RE-18 Liquid Radwaste Systemliquid effluent radiation monitor is calculated as shown inEquation 10.
HASP'8 BICGDI ia + (AF)(SF) x g k> C|,gC, ECI,,islt3
x TCF (IP)
Where:
HASPRE.is high alarm setpoint for RE-18 (cpm)
BKGDRE.is —— background reading for RE-18 (cpm)
(AF)
(SF)
C;
ECL;
TCF
allocation factor for the liquid radwasteeffluent system from Table 6. 1 (0.9)
safety factor for RE-18 (0.9)
monitor response factor (cpm/NCi/ml)
concentration of gamma emitting isotopes inthe release mix, pre-dilution (pCi/ml)
dilution flow rate (gpm)
undiluted effluent flow rate (gpm)
concentration of isotope "i," in the release
mix, pre-dilution (pCi/ml)
effluent concentration limitof isotope "I"
tritium correction factor as defined byEquation 7.
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UNITS 1 AND 2
3. Set Point Methodology for RE-23 HASP: Steam GeneratorBlowdown Tank
The High Alarm Set Point for the RE-23, Steam GeneratorBlowdown Tank liquid effluent radiation monitor, is calculated as
shown in Equation 11.
HASP~ „= BKGD~ „+(AF)(SF) x gk, C„gC, ECL,
iwH3
x TCF (11)
Where:
HASPaE.23 high alarm setpoint for RE-23 (cpm)
BKGDaE.23= background reading for RE-23 (cpm)
(AF)
(SF)
allocation factor for the steam generatorblowdown effluent system for each unit fromTable 6. 1 (0.04)
safety factor for RE-23 (0.9)
monitor response factor (cpm/pCi/ml)
concentration of gamma emitting isotopes inthe release mix, pre-dilution (pCi/ml)
dilution flow rate (gpm)
undiluted effluent flow rate (gpm)
C;
ECL;
TCF
concentration of isotope "i," in the release
mix, pre-dilution (pCi/ml)
effluent concentration limitof isotope "i"
tritium correction factor as defined byEquation 7.
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UNITS 1 AND 2
6.1.4 Dose Projection (for Liquid Effluents)
The projected dose contributions from each reactor unit due to liquideffluents for the current calendar month, quarter and current calendar yearmust be determined in accordance with the methodology and parameters inthe ODCP at least every 31 days.
The purpose of this is to determine ifappropriate treatment of liquidradioactive materials in relation to maintaining releases "as low as reasonablyachievable," is necessary.
Projections willbe made, at least by the end of each month with attention tothe frequency requirement contained in the radiological effluent controlsprogram.
The projected dose from each reactor unit is given by:
Where:
P P,U 2 P,Coo> (12)
D„= Projected Dose.
DP U= Projected dose attributed to reactor unit, U.
DP c,„, = Projected dose common to both reactor units.
The 31-day projected dose is calculated by Equation 13.
Phf Chf CBDh' 31
D„+d„+ dP
(T+ t)(13)
Where:
Dphil= Monthly projected Dose
D~" = Previous Month's Actual Dose
d~' Current Month Actual Dose to date
dp —— Projected Dose from Current Batch Release
T = Number of days in the previous month
t = Number of days into the present month
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UNITS 1 AND 2
Projected quarterly doses are determined by Equation 14.
D" d dz)CQ dCQ (9 )
A A P+ 2-t( )
Where:
(14)
g)CQP Projected dose for the current calendar
quarter.
Current quarter to date actual dose.
g) QPrevious quarter's actual dose.
dCBP Projected dose as a result of the current
batch release.
T = Number of days in the previous quarter.
t = Number of days into the present quarter.
Projected yearly doses are determined by Equation 15.
a" =d" +(366-i) "(15)
Where:
ICYP Projected dose for the current calendar
year.
dCY Current year to date actual dose.
g) PY Previous year's actual dose.
dCBP Projected dose as a result of the current
batch release.
T = Number of days in the previous year.
t = Number of days into the presentyear.
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6.1.5 Liquid Limiting Flow Rate Methodology - ECL Based
The maximum effluent flow rate through monitors RE-3, RE-18, and RE-23as well as for releases from the Condensate Demineralizer Regenerate wastetank or miscellaneous release points is established in order to provide furthercontrol over the effluent releases. The release rate limit is determined by the
effluent concentration and the 10 CFR 20 Effluent Concentration Limits(ELCs) as shown in Equation 16.
Where:
F (AF) (SF) (TCF)CiZ —,'
«-3 J-'Cli
(16)
Maximum operational undiluted liquid radwaste effluentdischarge flow rate (gpm)
AF
Expected dilution flow rate (gpm)
allocation factor for the liquid radwaste effluent sourcefrom Table 6. 1.
TCF
safety factor (0.9).
tritium correction factor as defined by Equation 7.
C; concentration of isotopes "i" in the release mix,pre-dilution (pCi/ml)
ECL; effluent concentration limit.of isotope "i" (pCi/ml)
When the term g —='0 then the Limiting Flow Rate is calculated by:CI
„„3ECI-I
f= F(AF)(SF)(TCF)
Where the terms are as previously defined.
(17)
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6.1.6 Liquid Limiting Flow Rates - LLDBased
When there is no primary to secondary leakage, the Oily Water Separatorand various miscellaneous release points are assumed to be uncontaminated.Furthermore, in order to establish practical operational flow rate limits forany sources when they are considered uncontaminated, Equation 18 is used.While no activity may be present, Equation 18 assumes a concentration equalto the Lower Limitof Detection for the nuclides listed in CY2.ID1,Appendix 6.1, Table 6.1.3-1.
Where:
F (~F) (Sr)4.3
(18)
Maximum operational undiluted liquid radwaste effluentdischarge flow rate (gpm)-
Expected dilution flow rate (gpm)
AF allocation factor for the liquid radwaste effluent sourcefrom Table 6. 1.
SF
4.3
safety factor (0.9).
Total ECL fraction as given by:
Z—'LD(
I ECL,
Where:
LLD; = Lower limitof detection for isotope "i" from CY2.ID1,Appendix 6.1, Table 6.1.3-1. (pCi/ml)
ECL; =. effluent concentration limitof isotope "i" (pCi/ml)
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6.1.7 Unplanned Liquid Releases
An unplanned release is an unexpected and potentially unmonitored release tothe environment due to operational error or equipment malfunctions.
a. Unmonitored unplanned releases shall have a report written by theRadiochemistry Effluents Engineer describing the event with a
calculation, ifpossible, of the percent of Tech Spec release rate limit.This will then be forwarded to PSRC for review and then forwarded toNSOC for review.
b. Monitored unplanned releases which exceed 1% of the RMCP release
rate limitwillalso have a report written describing the event and mustbe forwarded to the PSRC for review, and then forwarded to NSOC forreview.
c. Describe these unplanned releases in the Annual Radioactive EffluentRelease Report. This report willalso be forwarded to PSRC andNSOC for review.
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6.2 Gaseous Effluents
The only significant path for gaseous radioactive releases to the environment duringnormal operations is via the plant vent. This source is used for calculating dose rates
and real-time doses to the unrestricted area due to noble gases, vaporous radioiodinesand airborne radio-particulates. The plant vent also has redundant monitoring for these
types of gaseous releases.
Other paths such as the steam generator blowdown tank vent, the chemistry lab fumehood, the main condenser Nash vacuum pump discharge, hot machine shop vent, etc.,'are considered miscellaneous release sources. These miscellaneous release sources arenot continuously monitored but can have dose rates and dose calculated for their path tothe unrestricted area.
6.2.1 Meteorological Methodology
The equations for determining gaseous effluent concentration limits, highalarm setpoints, dose rates, and critical receptor doses make use of thehistorical average atmospheric conditions in accordance with methodologiesof Regulatory Guides 1.109 and 1.111 and NUREGs 0133 and 0472. Thehistorical average dispersion (X/Q) and deposition (D/Q) values are derivedfrom the methodology of Regulatory Guide 1.111 as implemented byNUREG 2019 (computer code XOQDOQ). The DCPP dispersion anddeposition values are based on the latest five years of meteorological data andare updated when the value of X/Q or D/Q changes by more than ten percent.The present values are listed in Table 10.2.
Long-term releases are characterized as those that are generally continuousand stable in release rate, such as normal ventilation systems effluents.Doses due to long-term releases are modeled using historical annual averagedispersion and deposition values in accordance with the guidance ofRegulatory Guide 1.109, Regulatory Guide 1.111, NUREG 0133 andNUREG 0472.
Short-term releases are defined as those which occur for a total of 500 hoursor less in a calendar year but not more than 150 hours in any quarter. Inaccordance with NUREG 0133 and based upon an operational history thathas demonstrated short term gaseous releases can be characterized as randomin both time of day and duration, historical average atmospheric dispersionand deposition values are used to model doses due to short-term releases.
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6.2.2 Gas Effluent Concentration Limits
a. Philosophy of Concentration Limits .
The radiological effluent controls restrict at all times the dose rate dueto radioactive materials released in gaseous effluents from the site toareas at or beyond the site boundary for noble gases to less than orequal to 500 mrem/yr to the total body and 3000 mrem/yr to the skin.For iodine-131, iodine-133, tritium and for all radionuclides inparticulate form with half-lives greater than 8 days, the dose rate is
limited to less than or equal to 1500 mrem/yr to any organ.
These dose rate limits act to restrict at all times the instantaneousconcentrations of radionuclides in gaseous effluents at the siteboundary.
l. Allocation and Safety Factors
The limits set forth by RCMP 6.1.6.1 are site limits which requirethat the set point methodology must ensure simultaneous releasesdo not exceed the off-site dose rate limits set forth by RCMP6.1.6.1(a) and 6.1.6.1(b). The DCPP High Alarm Set Pointmethodology makes use of an Allocation Factor (AF) to limit thenoble gas effluent dose rate from simultaneous atmosphericreleases.
The Allocation Factors can be adjusted based upon operationalrequirements with the following restrictions:
The sum of the Allocation Factors for RE-14, the SGBDtank vents, and miscellaneous release points from both unitsmust be less than or equal to 1.
The Allocation Factors for RE-22 (Waste Gas Decay Tanks)and RE-44 (Containment Purge) can also be adjusted based
upon operational requirements with restriction that the sum'of the Allocation Factors for RE-22 and RE-44 must be less
than or equal to the Allocation Factor for RE-14.
The Allocation Factors for RE-24 (Plant Vent IodineMonitor) and RE-28 (Plant Vent Particulate Monitor) are set
equal to the Allocation Factor for RE-14.
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~ Typical Allocation Factors are shown in Table 6. 2.
Table 6. 2
Typical Gaseous Effiuent Discharge Pathway Allocation Factors
Discharge PathwayPlant Vent - NG MonitorPlant Vent Iodine MonitorPlant Vent Part MonitorWaste Gas Decay TankContainment PurgeSGBD Tank VentMiscellaneous
Rad MonitorRE-14RE-24RE-28RE-22RE-44
Allocation Factor (AF)0.480.480.480.100.380.010.01
An additional level of conservatism in the HASP methodology is
implemented by the use of a Safety Factor (SF). The SafetyFactor is defined as 0.9 and provides for a High Alarm Set Pointat 90% of the dose rate limits.
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b. Gaseous Effluent Radiation Monitor Set Points
1. PLANT VENT NOBLE GAS MONITOR - RE-14 HASP
The Plant Vent effluent stream is monitored by rad monitorRE-14. RE-14 provides alarm function only.The High Alarm Set Point methodology for RE-14 is given byEquation 19.
" ' (NG) = AF SF472x F „x (Xig) x 294
Where:
(19)
4M'"C (NG) the maximum allowable total concentration of noble gas inthe plant vent, in pCi/cc
AF the allocation factor for the plant vent for one unit fromTable 6. 2 (0.48)
SF = a safety factor to ensure that dose rate limits of theradiological effluent controls are not exceeded (0.9)
500 = (mrem/yr) the site Total Body dose rate limit forinstantaneous releases
472 = the conversion constant to cc/sec from cfm
Fpp = total flow rate in the plant vent, in cfm (maximum plant ventflow rate is 263,000 cfm)
(xigi = the maximum historical site boundary dispersion factor,Sam
based on 5 year averages derived from the meteorologicaldata base, from Table 10.2.
294 = the whole body dose factor (mrem/yr/pCi/m ) for Xe-133 as
presented in Table 10.3, (for the plant vent HASP, therelease is assumed to be all Xe-133)
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2. PLANT VENT NOBLE GAS MONITOR - RE-14 SCALING
In order to correlate the readings of RE-14 to noble gasconcentration during periods between samplings, the concentrationis scaled according to Equation 20.
CPMT
CPM(2o)
Where:
CPMT = RE-14 time weighted arithmetic mean (cpm).
CPMs = RE-14 gross count rate at the time of sampling (cpm).
Cs Concentration of noble gas corresponding to CPMs,based upon noble gas grab sample (pCi/cc).
Scaled concentration of noble gas (pCi/cc).
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3. PLANT VENT IODINEMONITOR - RE-24
The Plant Vent Iodine concentration is monitored by rad monitorRE-24. RE-24 provides alarm function only. The alarm setpointmethodology is based upon the assumption that RE-24 responds
only to I-131. The methodology also presumes a release mixturebased upon the RCS source term.
The High Alarm Set Point methodology of RE-24 is given byEquation 21.
"""C (Iodine) =SFx AFx f 1500Y '''472xF x X/Q .gP"f (21)
PY Max . i iI
Where:
'"CT(iodine) the maximum allowable concentration ofI-131 in the plant vent
AF The allocation factor for the plant vent forone unit from Table 6. 2 (0.48)
SF
ft-131
A safety factor to insure that the dose ratelimits of the radiological effluent controlsare not exceeded (0.9).
fraction of the total non-noble gasconcentration that is due to 1-131. Definedas:
f CI }31I-1 31
I
(22)
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1500 = (mrem/yr) the site organ dose rate limit forradioiodines and for all radioactivematerials in particulate form andradionuclides other than noble gases withhalf-lives greater than 8 days.
472 = the conversion constant to cc/sec from cfm
FP„ total flowrate in the plant vent, in cfm(maximum plant vent flowrate is
263,000 cfm)
x/g) = maximum historical site boundaryIhfar
dispersion factor, based on 5 year averagesderived from the meteorological database,from Table 10.2.
i
PW Inhalation dose factor for nuclide "i"(mrem/yr/pCi/m ) for child age group forworst case organ, from Table 10.4. Dosefactors are based upon NUREG 0133methodology. Inhalation dose conversionfactors are taken from Reg. Guide 1.109,Rev 1, Table E-9, with the followingexceptions: H-3, Sb-124 and Sb-125inhalation dose conversion factors takenfrom NUREG/CR-4013.
fraction of total non-noble gas concentration(excluding tritium) that is due to nuclide, i,and defined as:
C,f=-pc, (23)
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4. PLANT VENT PARTICULATEMONITOR - RE-28
The Plant Vent Particulate concentration is monitored by radmonitor RE-28. The alarm setpoint methodology is based uponthe assumption of a 5% cross talk from the iodine channel. Thisis due to the retention of a small portion of iodine on the
particulate filter. A release mixture based upon the RCS sourceterm is also assumed.
The High Alarm Set Point methodology for RE-28 is given byEquation 24.
C (Particulates) = AFxSFx 0.05x f . + flodines Particulates
1500x
472xF x y/Q gP fI
(24)
Where:
'"Cr(Particulate) Maximum allowable particulate concentration inthe plant vent
AF The allocation factor for the plant vent for oneunit from Table 6. 2 (0.48)
SF A safety factor to insure that the dose rate limitsof the radiological effluent controls are notexceeded (0.9).
0.05
fiodines
Fraction of total iodine activity retained onparticulate filter.
Fraction of the total non-noble gas concentrationthat is due to iodines.
fParticuhtes Fraction of the total non-noble gas concentrationthat is due to particulates.
1500
472
FP„
(mrem/yr) the site organ dose rate limit forradioiodines and for all radioactive materials inparticulate form and radionuclides other thannoble gases with half-lives greater than 8 days.
Conversion constant to cc/sec from cfm
Total flowrate in the plant vent, in cfm (maximumplant vent flowrate is 263,000 cfm)
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(x/g) = Maximum historical site boundary dispersionIhfax
factor, based on 5 year averages derived from themeteorological database, from Table 10.2
PW Inhalation dose factor for nuclide "i"(mrem/yr/NCi/m3) for child age group for worstcase organ, from Table 10.4. Dose factors arebased upon NUREG 0133 methodology.Inhalation dose conversion factors are taken fromReg. Guide 1.109, Rev 1, Table E-9, with thefollowing exceptions: H-3, Sb-124 and Sb-125inhalation dose conversion factors taken fromNUREG/CR-4013.
Fraction of total non-noble gas concentration(excluding tritium) that is due to nuclide, i, as
defined by Equation 23.
5. WASTE GAS DECAYTANKMONITOR - RE-22 HASP
Effluent releases from the Waste Gas Decay Tank are monitoredby rad monitor RE-22. RE-22 provides alarm and automaticrelease termination functions.
The High Alarm Set Point methodology for RE-22 is given byEquation 25.
'"'r(NG)= AFxSFx472 x F~ x (XiQ) x 1.34x10'25)
Where:
22M-C,(NG) the maximum allowable total concentration ofnoble gas in the gas decay tank exhaust line, inpCi/cc
472
F6d1
the conversion constant to cc/sec from cfm
maximum flow rate for the gas decay tank system(31 cfm)
AF = the allocation factor for the waste gas decay tankfor one unit from Table 6. 2 (0.10)
SF = safety factor to ensure that dose rate limits of theradiological effluent controls are not exceeded
(0.9)
3000 = (mrem/yr) the site Skin dose rate limit forinstantaneous releases
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(y,/gl = the maximum historical site boundary dispersionIhoax
factor, based on 5 year averages derived from themeteorological data base from Table 10.2.
1.34x10 = -. the skin dose factor for Kr-85 (mrem/yr/ pCi/m,from Table 10.3.
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6. CONTAINMENTPURGE - RE-44 HASP
The Containment Purge is monitored by rad monitor R&44.RE-44 provides alarm and automatic release terminationfunctions.
The HASP for RE-44 must limit the noble gas dose rate for skinand total body exposure. In order to address this, two set pointsare calculated. One set point is calculated based upon limiting thetotal body dose rate and the other limits the skin dose rate. Themore limiting set point is used. The High Alarm Set Pointmethodology for RE-44 is given by Equations 26 and 27.
a) Limiting Concentration Based on Total Body Dose
44AIEMmg (gG) gF gF472x Fg x(X/Qj x QKifi(NG)
(26)
Where: .
'"CT(NG) = the maximum allowable total co'ncentrationof noble gas in the containment purgeexhaust line, in pCi/cc
AF the allocation factor for the containment purgefor one unit from Table 6. 2 (0.38)
SF safety factor to ensure that dose rate limits ofradiological effluent controls are not exceeded
(0 9)
500 (mrem/yr) the site Total Body dose rate limit forinstantaneous releases
472 = the conversion constant to cc/sec from cfm
F„= maximum flow rate in the containment purgesystem (maximum containment purge flowrate is
55,000 cfm)
the maximum historical site boundary dispersion
factor, based on 5 year averages derived from themeteorological data base averages, fromTable 10.2.
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K; = whole body dose factor (mrem/yr/pCi/m ) forisotope "i." Dose factors are presented inTable 10.3.
f; = the fraction of the concentration of the individualnoble gas radionuclide, "i," in the total mix ofnoble gas effluents in the containment purge line.
b) Limiting Concentration Based on Skin Dose
Skin dose should be calculated whenever an RCS samplecontains a significant fraction of Kr-85.
The concentration limitcalculated by this method shouldthen be compared to the concentration limitcalculated fortotal body dose. The smaller concentration should beselected as the limiting concentration for the HASP.
44~////,'~C (NG) = AF SF3000
(2'7)472 x F„x (X/Q) xg(L +11M') fj(7VG)
/
Where:
44A/BMaxc (NG) the maximum allowable total concentration ofnoble gas in the plant vent in pCi/cc
AF the allocation factor for the containment purgefor one unit from Table 6. 2 (0.38)
SF safety factor to ensure that dose rate limits of theradiological effluent controls are not exceeded
(0 9)
3000 = (mrem/yr) the site Total Body dose rate limit forinstantaneous releases.
472 = the conversion constant to cc/sec from cfm
F« = total flow rate in the containment purge system,in cfm (maximum containment purge flow rate is
55,000 cfm)
the maximum historical site boundary dispersion
factor, based on 5 year averages derived from themeteorological data base averages, fromTable 10.2.
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L; = the skin dose factor (mrem/yr per pCi/m ) forisotope "i." Dose factors are presented inTable 10.3.
1.1 = Conversion factor mrem/mrad. Converts airdose to skin dose.
M; = the beta dose factor (mrad/yr per pCi/m ) forisotope 'i." Dose factors are presented inTable 10.3.
f; = the fraction of the concentration of the individualnoble gas radionuclide, "i," in the total mix ofnoble gas effluents in the containment purge line.
Mode 6 Particulate activity.
The HASP calculation specified in this section based upon Noble Gas
effluent limitations conservatively bounds the Tech. Spec. requirementfor particulate activity in Mode 6. The FSAR expected case accidentfor Mode 6 is a containment fuel handling accident which does notinclude a particulate release. Therefore, the HASP for RM-44 in thissection conservatively satisfies the Tech. Spec. (Ref.: 8.15)
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6.2.3 Gaseous Dose Rate Calculation Methodology
a. Total Body Noble Gas Dose Rate Methodology
The dose rate to the total body due to immersion in a cloud of noblegases is given by:
(y/Q), gK,.Q,.(500 mrem/yearI
Where:
(28)
Q/ The release rate of radionuclide i in units ofpCi/sec.
Allother terms are as previously defined.
b. Skin Dose Rate Methodology
The dose rate to the skin due to immersion in a cloud of noble gases is
given by:
(y/Q) g(L.,+1.1M.,)Q.,<3000mrem/yearI
Where the terms are as previously defined.
(29)
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c. Radioiodine, Tritium and Particulate Dose Rate Methodology
The dose rate to organ, o, due to radioiodines, tritium and particulatesreleased in gaseous effluents is given by:
(yiQ) gP,. Q, <1500 mrem/yearI
Where:
P;, = K'BR) DFA;,
and
(30)
K' 10 pCi/pCi
BR = The breathing rate of the a child age group inm /yr. The default value of 3700 m /yr is takenfrom Table E-5 of Reg. Guide 1.109.
DFA; The inhalation dose factor for organ o, for thechild age group for radionuclide, i, fromTable E-9 of Reg. Guide 1.109 in mrem/pCi, withthe following exceptions: H-3, Sb-124 and Sb-
125 inhalation dose conversion factors taken fromNUREG/CR4013.
Allother terms are as previously defined.
Values for P;, are listed in Table 10.6.
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6.2.4 Noble Gas Air Dose Calculation Methodology
a. Gamma Air Dose
The gamma air dose due to immersion in a cloud of noble gases is
given by:
D = 3.17 x10 (X/Q), gM,Q,I
Where:
D,„= Gamma air dose in mrad.
3. 17x10 = Conversion constant yr/sec.
(31)
M; = Gamma air dose factor for nuclide i, in mrad/yrper pCi/m . Values are listed in Table 10.3.
Q, = Total release of noble gas radionuclide, i, in pCi.
Allother terms are as previously defined.
b. Beta AirDose
The beta air dose due to immersion in a cloud of noble gases is givenby:
D~
——3.17x10 '(X/Q)„, gN,Q,I
Where:
(32)
D,ti = Beta air dose in mrad.
N; = Beta air dose factor for nuclide i, in mrad/yr perNCi/m . Values are listed in Table 10.3.
Allother terms are as previously defined.
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6.2.5 Dose To Critical Receptor Due To Radioiodines, Tritium and ParticulatesReleased in Gaseous Effluents
a. Calculation Methodology
The dose to an individual (critical receptor) due to radioiodines, tritiumand particulates released in gaseous effluents with half-lives greater than8 days is determined based upon the methodology described inNUREG 0133. This methodology makes use of the maximumindividual concept described in Regulatory Guide 1.109. Themaximum individual is characterized as maximum with regard to foodconsumption, occupancy, and other usage parameters. This concepttherefore models those individuals within the local population withhabits representing reasonable deviations from the average. In allphysiological and metabolic respects, the maximum individual isassumed to have those characteristics that represent the average for the
age group of interest.
The concept of critical receptor is introduced as a further refinement ofthe maximum individual. The critical receptor is defined as thatindividual that receives the largest dose based upon the combination ofdose pathways that have been shown to actually exist. The criticalreceptor concept is applied at that location where the combination ofdispersion'(X/Q), deposition (D/Q), existing pathways, occupancy time,receptor age group, and effluent source term indicates the maximumpotential exposure. The inhalation and ground plane exposurepathways are considered to exist at all locations. The grass-cow-milk,grass-cow-meat, and vegetation pathways are considered based on theiractual existence in the vicinityof the plant.
The dose pathways that have been shown to actually exist at DCPP arethe ground plane, inhalation and the vegetation pathways. These dose
pathways are reviewed yearly and updated based upon the annual landuse census survey in order to insure that actual exposure to anindividual willnot be substantially underestimated.
The locations of the pathways and descriptions are listed in Table 10.2.
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b. Dose Calculation
The dose contributions to the total body and each individual organ(bone, liver, thyroid, kidney, lung and GI-LLI)of the maximumexposed individual (Critical Receptor) due to radioactive gaseouseffluent releases is calculated for all radionuclides identified in gaseous
effluents released to unrestricted areas using the followin'g expression:
D,~ = 3.17 x 10 'c„QR,. Q,.I
(33)
Where:
Dapo Dose to the critical receptor for age group a,pathway p, and organ o, in mrem.
WcR Critical receptor X/Q for immersion, inhalation and
all tritium pathways (seconds/m ) from Table 10.2.
Critical receptor D/g for ground plane and allingestion pathways (1/m ) from Table 10.2.
Raipo Site specific dose factor for age group a, radionuclidei, pathway p, and organ j (mrem/yr per pCi/m forinhalation and tritium pathways - mrem/yr perpCi/(sec m ) for ground plane and ingestionpathways). These dose factors are listed inTable 10.6.
The site specific dose factors are calculated based
upon NUREG 0133 methodology. Alldoseconversion factors are taken from Reg. Guide 1.109,Rev 1, Tables E6-E14, with the following exceptions:H-3, Sb-124 and Sb-125 dose conversion factors
taken from NUREG/CR-4013.
Qi = The total release of radionuclide i, in units of pCi.
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6.2.6 Noble Gas Gaseous Radioactive Waste (GRW) Batch Release Percent Release
Rate Limits (PRRLs) and Expected Reading (ER)
The Percent Release Rate Limit (PRRL) for noble gas releases for each
unit is calculated based upon the 500 mrem/yr whole body dose rate limit,and is given by Equation 34.
(XIQ)„ZI:iQiPRRL — ' 100%
(048) (500 mreinl yr)(34)
Where:
X/Ql = The maximum site boundary dispersion factor based on/hfdf
5 year averages from Table 10.2.
Whole body dose factor (mrem/yr per lhCi/m ) forisotope "i." Dose factors are presented in Table 10.3.
Total release rate of isotope "i" from all sources
discharged through this release point in pCi/sec.
0.48 Plant vent allocation factor for one unit from Table 6.2.
500 mrem/yr = Site noble gas dose rate limit.
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The Expected Reading (ER) is the anticipated monitor response based uponthe known plant vent concentration and the monitor response factors. TheExpected Readings for RE-22, RE-44, RE-14 are given by Equations 35, 36,aild 37.
BR(~ „) = BKG(~ „)+gk())F „)) C())) „),I
(35)
Where:
ER(RE-22)
BKG(RE.22) =
k(RE-22) i
Expected reading on monitor RE-22 in pCi/cc.
Monitor background.
Noble gas monitor response factor for nuclide "i" formonitor RE-22.
C(RE 22»= Concentration of nuclide "i" seen by RE-22.
ER(~ )4)——BKG(~ „) +CCSP(~ 44)gk(~ 4)), C(~ ~)) (36>
I
Where:
ER(REg4)
BKG(RE~4) =
Expected reading on monitor RE-44 in pCi/cc.
Monitor background.
CCSP(RE~4) = Conversion constant setpoint for monitor RE-44.
k(RE44)i Noble gas monitor response factor for nuclide "i" formonitor RE-44.
C(REM)i Concentration of nuclide "i" seen by monitor RE-44.
ER())) )4>—BKG(() )))+ CCSP())E ))>gk())) )))) C())) ))))
I(37)
Where:
ER(RE-14)
BKG(RE.i4) =
CCSP(RE-14)
Expected reading on monitor RE-14 in pCi/cc.
Monitor background.
Conversion constant setpoint for monitor RE-14.
CAPA8.DOC 08 37
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TITLE: OFF-SITE DOSE CALCULATIONS
NUMBER CAP A-8REVISION 22PAGE 38 OF 64
UNITS 1 AND 2
ktRE-14) i Noble gas monitor response factor for nuclide "i" formonitor RE-14.
C<RE i4i;—— Concentration of nuclide "i" seen by monitor RE-14.
Generally ifthe Expected Reading (ER) is greater than the existing HASPsetting (an "administrative limit" as set by CY2.DC1) then no release shouldbe made until a calculation shows that the HASP (Admin Limit)can be raised
so the release can be legally discharged. On the other hand should the ER be
less than the existing HASP (Admin Limit), then the release can be
discharged.
6.2.7 IPT - PRRL
The Percent Release Rate Limit (PRRL) for radioiodines, tritium andparticulates for each unit is calculated based upon the 1500 mrem/yr organdose rate limit. The dose rate is calculated for the inhalation pathway to thechild age group using the highest (worst case) organ dose factor for nuclide.The Percent Release Rate Limitbased on the worst case organ is given byEquation 38.
(x/Q)„,„Z11" QII'RRL, = x 100%
(0.48) (1500 >nrem/ yr)(38)
Where:
(x/Q)„=PW'he
maximum site boundary dispersion factor based on 5
year averages from Table 10.2.
Inhalation dose factor for nuclide "i" (mrem/yr/pCi/m3) forchild age group for worst case organ, from Table 10.4.Dose factors are based upon NUREG 0133 methodology.Inhalation dose conversion factors are taken from Reg.Guide 1.109, Rev 1, Table E-9, with the followingexceptions: H-3, Sb-124 and Sb-125 inhalation doseconversion factors taken from NUREG/CR-4013.
Q/ Release rate of isotope "i" in pCi/sec.
0.48 = Plant vent location factor for one unit from Table 6. 2.
1500 mrem/yr = Site radioiodine, tritium and particulate dose rate limit.
CAPA8.DOC 08 38
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TITLE: OFF-SITE DOSE CALCULATIONS
NUMBER CAP A-8REVISION 22PAGE 39 OF 64
UNITS 1 AND 2
6.2.8 Alternate Dose Methodologies
For purposes of routine gaseous effluent dose assessment, the methodology ofNUREG 0133 (described in Section 6.2.5) willbe used. However, DCPPmay elect to utilize the dose methodologies of Regulatory Guide 1.109 or theGASPAR computer code for special purposes such as evaluation of potentialnew gaseous effluent dose pathways or critical receptors.
6.2.9 Gas Effluent Dose Projection
The projected dose contributions from each reactor unit due to gaseous
effluents for the current calendar month, quarter and current calendar yearmust be determined in accordance with the methodology and parameters inthe ODCP at least every 31 days.
The purpose of this is to determine ifappropriate treatment of gaseousradioactive materials in relation to maintaining releases "as low as reasonablyachievable," is necessary.
Projections willbe made, at least by the end of each month with attention tothe frequency requirement contained in radiological effluent controlsprogram.
The projected dose from each reactor unit is given by:
Where:
>p = >p,v +is>p,c... (39)
Dp = Projected Dose.
Dp U Projected dose attributed to reactor unit, U.
Dp c Projected dose common to both reactor units.
CAPAS. DOC 08 39
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TITLE: OFF-SITE DOSE CALCULATIONS
NUMBER CAP A-8'REVISION 22PAGE 40 OF 64
UNITS 1 AND 2
The 31 day projected dose is calculated by Equation 40.
Dhi 31DA"+ dA '+dP
(T+ i)(40)
Where:
Projected Dose for the next 31 day period.
@Phd Previous Month's Actual Dose
Current Month Actual Dose to date
dcB Projected Dose from Current Batch Release
Number of days in the previous month
Number of days into the present month
Projected quarterly doses are determined by Equation 41.
a"Q+d" +d"gCQ dCQ (92 )
A A P(41)
Where:
L)CQProjected dose for the current calendar quarter.
d Current quarter to date actual dose.
g)PQPrevious quarter's actual dose.
dcBProjected dose as a result of the current batch release.
T = Number of days in the previous quarter.
t = Numberofdays,into thepresentquarter.
CAPA8.DOC 08 40
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TITLE: OFF-SITE DOSE CALCULATIONS
NUMBER CAP A-8REVISION 22PAGE 41 OF 64
UNITS 1 AND 2
Projected yearly doses are determined by Equation 42.
D""+1 Y+1D Y =1 -Y+(366-t)
P A (y+()(42)
Where:
g)CY Projected dose for the current calendar year.
1CY
DPY
Current year to date actual dose.
Previous year's actual dose.
1cBProjected dose as a result of the'current batch release.
T = Number of days in the previous year.
t = Number of days into the present year.
6.2.10 Unplanned Gaseous Releases
An unplanned release is an unexpected and potentially unmonitoredrelease to the environment due to operational error or equipmentmalfunctions.
1. Unmonitored unplanned releases shall have a report written by theRadiochemistry Effluents Engineer describing the event with a
calculation, ifpossible, of the percent of RMCP release rate limit.This will then be forwarded to PSRC for review and thenforwarded to NSOC for review.
2. Monitored unplanned releases which exceed 1% of the RMCPrelease rate limitwillalso have a report written describing theevent and must be forwarded to the PSRC for review, and thenforwarded to NSOC for review. For purposes of classificationonly, unplanned release puffs through the plant vent may use onehour integrated resolution times.
3. Describe these unplanned releases in the Annual radioactiveeffluent release report. This report willalso be forwarded toPSRC and NSOC for review.
CAPA8.DOC 08 41
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TITLE: OFF-SITE DOSE CALCULATIONSI
NUMBER CAP A-8REVISION 22PAGE " 42 OF 64
UNITS 1 AND 2
6.3 40 CFR 190 Dose Calculations
6.3.1 Pathways
Calculation of total uranium fuel cycle dose for purposes of demonstratingcompliance with 40 CFR 190 requires the contributions from liquid and
gaseous effluent as well as direct radiation from the units and outside storagetanks to be considered. The total uranium fuel cycle dose to any member ofthe public willbe calculated by summing the following doses:
~ Direct Radiation Dose
~ Liquid Effluent Dose
~ Noble Gas Dose
~ Radioiodine, Tritium and Particulate Gaseous Effluent Dose
6.3.2 Methodology
Direct Radiation Dose
Determination of direct radiation dose from the reactor units and fromoutside storage tanks may be made by direct survey measurements,derived from environmental TLD data, or calculated by shielding code.
The direct radiation dose willalso take into account residence timesnear the site based upon land use census information.
The direct radiation determination using environmental TLD is given byequation 43.
2
b + X 9/7 X e-6.38 (43)
where:
D', b= the dose rate at the site boundary
D'~ = the dose rate from the dosimetry reading
r„, = the distance from the point source to the dosimetry
CAPA8.DOC 08 42
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TITLE: OFF-SITE DOSE CALCULATIONS
NUMBER CAP A-8REVISION 22PAGE 43 OF 64
UNITS 1 AND2
b. Noble Gas Dose
The noble gas skin dose and total body dose contributions to the totaluranium fuel cycle dose to a member of the public willbe determinedas shown in Equations 44 and 45.
Noble Gas Total Body Dose = 3.17 x 10'(X/L7) g K,g, (44)I
Noble Gas Skin Dose = 3.17x)0'(X/Q) g(L, +1)M ) g, (aS)R
I
Where:
3.17x10 Conversion constant yr/sec.
(x/())„
K;
Maximum historical dispersion factor forreceptor of interest, based on 5 year averagesfrom Table 10.2.
Gamma air dose factor for nuclide i, in mrem/yrper pCi/m . Values are listed in Table 6.3.
Gamma air dose factor for nuclide i, in mrem/yrper pCi/m . Values are listed in Table 6.3.
Conversion factor mrem/mrad. Converts airdose to skin dose.
M; = Gamma air dose factor for nuclide i, in mrad/yrper pCi/m . Values are listed in Table 10.3:
QI Total release of noble gas radionuclide, i, inNCi/sec.
CAPA8.DOC 08 43
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TITLE: OFF-SITE DOSE CALCULATIONS
NUMBER CAP A-8REVISION 22PAGE 44 OF 64
UNITS 1 AND 2
Liquid and Gaseous Effluent Dose
The doses from liquid effluents and radioiodines, tritium and
particulates in gaseous effluents willbe determined by Equations 1 and
33, respectively.
For purposes of calculating the dose required by the radiologicaleffluent controls, more realistic assumptions concerning the liquid and
gaseous effluent dose pathways willbe used, based upon the mostrecent land use census data as well as the latest environmentalmonitoring information.
These assumptions may include, but not be limited to: more realisticliquid dilution factors; location and age of actual individuals, sitespecific food pathway parameters, and documentation of true foodconsumption. Other assumptions may be used provided they can besubstantiated by census or direct measurement.
CAPAS.DOC 08 44
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TITLE: OFF-SITE DOSE CALCULATIONSi
j
NUMBER CAP A-8REVISION 22PAGE 45 OF 64
UNITS 1 AND 2
6.4 On-Site Dose to Members of the Public
Members of the public are occasionally granted access within the site boundary, butonly in the owner controlled area up to the protected area boundary. The mostcommon public access activities are: tours to the simulator (training building) or BioLab, policemen using the shooting range (most frequent activity), cattle drives throughto adjacent properties, and visits of American Indians to on-site burial grounds (closestto the plant).
Exposure to members of the public due to liquid releases while on-site is highly unlikelyand therefore not addressed. Exposure due to gaseous releases and direct radiation arecredible and therefore are considered.
The dose to members of the public during on-site activities willbe primarily determined
by the duration of the on-site visitation time and by the closest proximity to the plant.
For gaseous releases the doses are calculated using Equations 44, 45 and 33. The R s
in Equation 33 consider only the inhalation and ground plane pathway and exclude theinfant age group.
The X/Q and D/Q values are modified using logarithmic extrapolation from the siteboundary to the on-site location of interest as shown in Equations 46 and 47.
log [X/Q ]
log [X/Q ]> >—log [X/Q ]ttoe [log (dist on - site.) —iog (dist S tt)]..
log (dist.S.B.) —log (dist. loc.)
+ log [X/Q ]
log [D/Q]
log [D//Q]» —log [D/Q],"'log (dist on - site) —iog (dt'st g tt)]..log (dist.S./3.) —log (dist. loc.)
+ log [D/Q]
(47)
Based upon Regulatory Guide 1.111, these equations can be expected to providereasonable dispersion and deposition estimates for distances as close as 200 meters.
Determination of direct radiation dose from the reactor units and from outside storagetanks may be made by direct survey measurements, derived from environmental TLDdata, or calculated by shielding code.
A distance of 200 meters from the plant (both units) equidistant from the plant vent is
arbitrarily selected as the closest perimeter for which on-site doses willbe calculated.
CAPAS.DOC 08 45
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TITLE: OFF-SITE DOSE CALCULATIONS
NUMBER CAP A-8REVISION 22PAGE 46 OF 64
UNITS 1 AND 2
The activities of the members-of-the-public while on-site (described above), are at orbeyond 200 meters. Table 6. 3 details the types of on-site activities thatmembers-of-the-public might be expected to participate in at DCPP. The sectors andclosest distances in which they may visit as well as expected visitation duration are alsoshown (based on Security Section information).
Table 6. 3
Expected On-Site Distances and Visitation Times for Members of the Public
ONSITE MEMBEROF THE PUBLIC
Police atshooting range
Tour Participants
Simulator Bldg
Bio Lab
Overlook
American Indiansat burial grounds
Ranch hands drivingcattle around site
SECTOROF
VISITATION
SE
S (SE)
SSE (SE)
E
NWNNW
NWNNWNNNENE
CLOSEST POINTOF APPROACH
TO PLANT
700m
310m
460m
210m
200m200m
250m350m320m450m630m
AVERAGE EXPECTEDVISITATION
TIME PER YEAR
208 hours
4 hours
6 hours
1 hours
96 hours96 hours
1 hour1 hour1 hour1 hour1 hour
i
CAPAS.DOC 08 46
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TITLE: OFF-SITE DOSE CALCULATIONS
NUMBER CAP A-8REVISION 22PAGE 47 OF 64
UNITS 1 AND 2
7. ACCEPTANCE CRITERIA
7.1 There is no quantitative acceptance for this procedure. Ifthe task or analysis has been
accomplished within the bounds of this procedure, it is considered acceptable.
8. REFERENCES
8.1
8.2
8.3
8.4
8.5
8.6
8.7
Draft Radiological Tech Specs for PWRs, NUREG No. 0472; May 1978;
Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for, the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I, Regulatory
Guide 1.109, Rev. 0, March 1976.
Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents forthe Purpose of Evaluating Compliance with 10 CFR 50, Appendix I, Regulato'ryGuide 1.109, Rev. 1, October 1977.
Preparation of Radiological Effluent Tech Specs for Nuclear Power Plants,NUREG No. 0133, October 1978.
LADTAPII - Technical Reference and User Guide, NUREG/CR-4013.
Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel CycleStandard 40 CFR 190, NUREG No. 0543, January 1980.
Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents inRoutine Releases from Light-Water-Cooled Reactors, Regulatory Guide, 1.111, Rev. 1,
July, 1977.
8.8 Radioactive Decay Data Tables, David C. Kocher. DOE/TIC-11026, 1981.
8.9 CAP A-6, "Gaseous Radwaste Discharge Management."
8.10 CAP A-S, "Liquid Radwaste Discharge Management."
8.11 CAP D-15, "Steam Generator Leak Rate Determination."
8.12 CAP D-19, "Correlation of Rad Monitors to Radioactivity."
8.13 CY2.DC1, "Radiation Monitoring System High Alarm Setpoint Control Procedure."
8.14 CY2.ID1, "Radiological Monitoring and Controls Program" (RMCP)
8.15 "Setpoint Calculation for Containment Ventilation Exhaust Monitor,"Calc ¹ NSP-18'-39-44, 10/92 and 11/92 and AR A0430610.
RECORDS
9.1 Data Sheets and records willbe maintained in the Records Management System (RMS)in accordance with CY1.DC1, "Analytical Data Processing Responsibilities."
CAPAS.DOC 08 47
PACIFIC GAS AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: OFF-SITE DOSE CALCULATIONS
NUMBER CAP A-8REVISION 22PAGE 48 OF 64
UNITS I AND 2
10. APPENDICES
10.1 Tables
11. ATTACHMENTS
None
12. SPONSOR
Jeff Gardner
CAPA8.DOC 08 48
PACIFI AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: OFF-SITE DOSE CALCULATIONS
NUMBER CREVISION 22PAGE 49 OF 64UNITS I AND 2
FIGURE 6.1LIQUIDDISCHARGES (LRW) MONITORED FOR RADIOACTIVITY
LIQUIDRADWASTE SYSTEM CONDENSATE DEMINERALIZER STEAM GENERATORREGENERATE TANKS BLOWDOWN
BA EVAPFEED DEMONS
HIGH LOWCONDVCllVITY CONDVCTMlY
MOBAERADWASTE TANK TANKPROCESSING SYSTEM(MRPSj
SGRDTANK
STEAM CENERATO
PRIMARYSYS.PRIMARY
WATER STORATANK
WASTE BORIC ACID
RETURN TOCONDENSOR
CLOSED DRAINS
MEOT
SCBT
EDR
SURFACECAPACITY
FOR EDR/FBA
LAUNDRYDISTAIATE
TANK
OILYWATERSEPARATOR
DEMWREGENRECVR
CARMEIXAFATER
MIXEDBED
OEM/NB
PROCESSWASTE
RECEIVER
OILYWATER
SEPARATOR
RES
EOIAPMENTDRAW
RECEIVER
P A
LAUNDRYdHOT
I~ F F
FCV4IT RCV-Id
RE Id
ONCE THROVGH COOUNG WATER
DIABLOCOVE
00692302
CAPA8.DOC 08 49
PACIFIC AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: OFF-SITE DOSE CALCULATIONS
NUMBER CAPREVISION 22PAGE 50 OF 64UNITS 1 AND 2
FIGURE 6.2GASEOUS RELEASES (GRW) MONITORED FOR RADIOACTIVITY
II PZR
REVEFTANK
II r-II II I REACTII
DRAWTANKII
I II II II IIIIlIIIII II II II II II II II II II II II IIIII
I VOL
I
R
SURGE TANKI
~Qm
.0
I uaUID
I I I
I I I
WASTE1.'I
COMPRESSORMCNSTSEP.
WASTE01
COMPRESSORMOISTSEP.
HOLDUP
N1 I
@ --Q.-gVGISD
TANK I
--g-'GVO
IHOLDUP
TAIJK I01
II
ISSCEGVPDRASITANK
N2
okCOMPONENT
I I WATERHEAD 'fARK
XD P.
Qmaav +DECAY
HEPAFILTER
GASDECAYTANK
ppppppSIG 14~
I~SIG14
I DVMPTO ATMOSPHERE DVMP 'fO ATMOSPHERE DVMPTO ATMOSPHERE
~:„pxog P P P,",". xoxoxoxo pxoxoxoxo"„".".'=,
I II
@n. 22.TS.S T4I I I
ISJG ATMOS.1.1
v UNIT2
III VNIT2II
II
GASDECAYTANK
L 24 I
15R IS
PIANTVENTTO
ATMOSPHERE
14/14R24J24R24J2SRST20
44A
ATMOS.44B
FUEL HANDVNGBLDG. VENT
III
SJG BD TANKI GIANDSTEAM
ATMOS.
00692319
CAPA8.DOC 08 50
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NUMBER CAP A-8REVISION 22PAGE 51 OF 64
TITLE: OFF-SITE DOSE CALCULATIONS UNITS 1AND2
Nuclide Tot Body
TABLE 10.1
LRW COMPOSITE DOSE FACTORS A'<)
FOR ADULTS AT A SALTWATERSITE(mrem/hour per pCi/ml)
organ "o"
Thyroid Kidney Lung GI-LLI Bone LiverH-3Na-24Cr-51Mn-54Mn-56Fe-55Fe-59Co-57Co-58Co-60Ni-65CU-64Zn-65Zn-69As-76Br-82Br-84Rb-86Rb-88Rb-89Sr-89Sr-90Sr-91Sr-92Y-90Y-91mY-92Zr-95Zr-97Nb-95Mo-99Tc-101Ru-103Ru-105Ru-106Ag-110mSn-113Sn-117mSb-122Sb-124
1.61E-01 1.61E-01 1.61E-01 1.61E-01 1.61E-01 0.00E+00 1.61E-014.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01-5.58E+00 3.34E+00 1.23E+00 7.40E+00 1.40E+03 O.OOE+00 0.00E+001.35E+03 O.OOE+00 2.10E+03 O.OOE+00 2.16E+04 0.00E+00 7.06E+033.15E+01 0.00E+00 2.26E+02 0.00E+00 5.67E+03 0.00E+00 1.78E+028.23E+03 0.00E+00 O.OOE+00 1.97E+04 2.03E+04 5.11E+04 3.53E+047.27E+04 0.00E+00 0.00E+00 5.30E+04 6.32E+05 8.06E+04 1.90E+052.36E+02 0.00E+00 O.OOE+00 O.OOE+00 3.59E+03 0.00E+00 1.42E+021.35E+03 O.OOE+00 O.OOE+00 0.00E+00 1.22E+04 O.OOE+00 6.03E+023.82E+03 O.OOE+00 0.00E+00 0.00E+00 3.25E+04 O.OOE+00 1.73E+031.20E+01 0.00E+00 0.00E+00 0.00E+00 6.65E+02 2.02E+02 2.62E+011.01E+02 0.00E+00 5.40E+02 0.00E+00 1.83E+04 0.00E+00 2.14E+022.32E+05 O.OOE+00 3.43E+05 O.OOE+00 3.23E+05 1.61E+05 5.13E+054.56E+01 O.OOE+00 4.26E+02 O.OOE+00 9.85E+Ol 3.43E+02 6.56E+024.42E+01 O.OOE+00 8.72E+01 0.00E+00 O.OOE+00 0.00E+00 4.62E+014.07E+00 0.00E+00 O.OOE+00 0.00E+00 4.67E+00 0.00E+00 O.OOE+009.39E-02 0.00E+00 0.00E+00 0.00E+00 7.37E-07 0.00E+00 0.00E+00
2.91E+02 0.00E+00 O.OOE+00 0.00E+00 1.23E+02 O.OOE+00 6.24E+029.49E-01 0.00E+00 0.00E+00 0.00E+00 2.47E-11 0.00E+00 1.79E+008.34E-01 0.00E+00 0.00E+00 0.00E+00 6.89E-14 0.00E+00 1.19E+001.43E+02 0.00E+00 O.OOE+00 0.00E+00 8.00E+02 4.99E+03 0.00E+002.83E+03 0.00E+00 0.00E+00 0.00E+00 3.55E+03 1.41E+05 O.OOE+003.71E+00 0.00E+00 0.00E+00 0.00E+00 4.37E+02 9.18E+01 O.OOE+001.51E+00 0.00E+00 0.00E+00 0.00E+00 6.90E+02 3.48E+01 0.00E+001.63E-01 0.00E+00 O.OOE+00 0.00E+00 6.42E+04 6.06E+00 0.00E+002.22E-03 0.00E+00 O.OOE+00 O.OOE+00 1.68E-01 5.73E-02 0.00E+001.56E-02 0.00E+00 0.00E+00 0.00E+00 9.32E+03 5.32E-01 0.00E+00
3.46E+00 0.00E+00 8.02E+00 0.00E+00 1.62E+04 1.59E+01 5.11E+008.13E-02 0.00E+00 2.68E-01 0.00E+00 5.51E+04 8.81E-01 1.78E-011.34E+02 0.00E+00 2.46E+02 0.00E+00 1.51E+06 4.47E+02 2.49E+022.43E+01 0.00E+00 2.89E+02 O.OOE+00 2.96E+02 0.00E+00 1.28E+021.88E-01 0.00E+00 3.46E-01 9.81E-03 5.77E-14 1.33E-02 1.92E-02
4.60E+01 O.OOE+00 4.07E+02 0.00E+00 1.25E+04 1.07E+02 O.OOE+003.51E+00 0.00E+00 1.15E+02 0.00E+00 5.44E+03 8.89E+00 0.00E+002.01E+02 0.00E+00 3.06E+03 O.OOE+00 1.03E+05 1.59E+03 0.00E+008.60E+02 O.OOE+00 2.85E+03 0.00E+00 5.91E+05 1.56E+03 1.45E+033.53E+03 9.85E+02 O.OOE+00 0.00E+00 O.OOE+00 6.06E+04 1.66E+038.76E+02 2.52E+02 O.OOE+00 0.00E+00 O.OOE+00 3.02E+03 3.41E+026.65E+00 3.09E-01 0.00E+00 1.18E+01 O.OOE+00 2.19E+01 4.47E-011.09E+02 6.70E-01 0.00E+00 2.15E+02 7.84E+03 2.76E+02 5.22E+00
Sb-125 4.20E+01h
1.79E-01 O.OOE+00 1.36E+02 1.94E+03 1.77E+02 1.97E+00
CAPA8.DOC 08 51
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NUMBER CAP A-8REVISION 22PAGE 52 OF 64
UNITS 1 AND 2
Nuclide
LRW COMPOSITE DOSE FACTORS, A;„FOR ADULTS AT A SALTWATERSITE
(mrem/hour per pCi/ml)organ "o"
Tot Body Thyroid Kidney Lung GI-LLI Bone . LiverTe-129mTe-129Te-131mTe-131Te-132I-131I-132I-133I-134I-135Cs-134Cs-136Cs-137Cs-138Ba-139Ba-140Ba-141La-140La-142Ce-141Ce-143Ce-144Pr-144Nd-147
'-187N -239
1.47E+02 3.20E+02 3.89E+03 0.00E+00 4.69E+03 9.31E+02 3.47E+026.19E-01 1.95E+00 1.07E+01 0.00E+00 1.92E+00 2.54E+00 9.55E-01
5.71E+01 1.08E+02 6.94E+02 O.OOE+00 6.80E+03 1.40E+02 '6.85E+015.03E-01 1.31E+00 6.99E+00 0.00E+00 2.26E-01 1.59E+00 6.66E-011.24E+02 1.46E+02 1.27E+03 0.00E+00 6.24E+03 2.04E+02 1.32E+021.79E+02 1.02E+05 5.35E+02 0.00E+00 8.23E+01 2.18E+02 3.12E+029.96E+00 9.96E+02 4.54E+01 0.00E+00 5.35E+00 1.06E+01 2.85E+013.95E+01 1.90E+04 2.26E+02 0.00E+00 1.16E+02 7.45E+01 1.30E+025.40E+00 2.62E+02 2.40E+01 0.00E+00 1.32E-02 5.56E+00 1.51E+012.24E+01 4.01E+03 9.75E+01 0.00E+00 6.87E+01 2.32E+01 6.08E+011.33E+04 0.00E+00 5.27E+03 1.75E+03 2.85E+02 6.84E+03 1.63E+042.04E+03 0.00E+00 1.57E+03 2.16E+02 3.21E+02 7.16E+02 2.83E+037.85E+03 O.OOE+00 4.07E+03 1.35E+03 2.32E+02 8.77E+03 1.20E+045.94E+00 0.00E+00 8.81E+00 8.70E-01 5.12E-05 6.07E+00 1.20E+012.30E-01 O.OOE+00 5.23E-03 3.17E-03 1.39E+01 7.85E+00 5.59E-031.08E+02 O.OOE+00 7.02E-01 1.18E+00 3.38E+03 1.64E+03 2.06E+001.29E-01 O.OOE+00 2.68E-03 1.63E-03 1.80E-09 3.81E+00 2.88E-032.10E-01 0.00E+00 O.OOE+00 0.00E+00 5.83E+04 1.57E+00 7.94E-019.13E-03 0.00E+00 0.00E+00 0.00E+00 2.68E+02 8.06E-02 3.67E-022.63E-01 O.OOE+00 1.08E+00 0.00E+00 8.86E+03 3.43E+00 2.32E+004.94E-02 0.00E+00 1.97E-01 0.00E+00 1.67E+04 6.04E-01 4.46E+029.59E+00 O.OOE+00 4.43E+01 0.00E+00.6.04E+04 1.79E+02 7.47E+019.64E-04 O.OOE+00 4.44E-03 0.00E+00 2.73E-09 1.90E-02 7.87E-032.74E-01 O.OOE+00 2.68E+00 0.00E+00 2.20E+04 3.96E+00 4.58E+00
2.68E+00 O.OOE+00 0.00E+00 0.00E+00 2.51E+03 9.16E+00 7.66E+001.91E-03 0.00E+00 1.08E-02 0.00E+00 7.11E+02 3.53E-02 3.47E-03
Dose factors are based upon NUREG 0133 methodology.
CAPA8.DOC 08 52
0
PACIFIC GAS AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: OFF-SITE DOSE CALCULATIONS
NUMBER CAP A-8REVISION 22PAGE 53 OF 64
UNITS '1 AND 2
TABLE10.2SUMMARYOF LANDUSE CENSUS EVALUATION
Sector
N
NNE
NE
ENE
SE
SSE
SSW
SW
WSW
WNW
NNW
ReceptorDescription
none
residence
residence
residence
residence
residence
residence
residence
residence +garden
oat hay andsugar peas
none
none
none
none
none
none
none
none
highest siteboundary
dispersion value
residence
residence
residence
Distance(miles)
443.3
4.9
4.4
5.0
4.0
3.7
4.5
3.3
0.5
1.2
3.6
1.5
5.56E-08
8.55E-08
4.39E-08
4.94E-08
3.58E-08
4.86E-08
5.92E-08
4.10E-08
1.88E-07
5.24E-06
1.57E-06
2.19E-07
5.89E-07
D/Q
1.00E-10
1.67E-10
8.10E-11
1.02E-10
6.80E-11
1.30E-10
1.65E-10
1.05E-10
1.20E-09
2.00E-08
6.31E-09
7.10E-10
1.85E-09
Comments
no receptors within 5 miles
unknown use
cabin - limited use
full'time occupancy
full time occupancy
full time occupancy
cabin - unknown use
part time occupancy
full time occupancy
field workers present only during the
day - critical receptor ground plane,inhalation, and vegetation ingestiondose assessed at this location
no receptors within 5 miles
over water
over water
over water
over water
over water
over water
over water
Gas effluent dose rates. PRRLs andHASPs evaluated at this location.
cabin - very limited use
full time occupancy
full time occupancy (trailer) - criticalreceptor ground plane and inhalationdose assessed at this location
CAPA8.DOC 08 53
PAC S AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: OFFNITE DOSE CALCULATIONS
NUMBER CAREVISION 22PAGE 54 OF 64UNITS 1 AND 2
TABLE 10.3
GRW DOSE FACTORS FOR NOBLE GASES
Radionuclide
Kr-83mKr-85mKr-85Kr-87Kr-88Kr-89Kr-90Xe-131mXe-133mXe-133Xe-135mXe-135Xe-137Xe-138Areal
Whole BodyDose Factor
K;(mrem/yr per pCi/m )
7.56E-021.17E+031.61E+015.92E+031.47E+041.66E+041.56E+049.15E+012.51E+022.94E+023.12E+031.81E+031.42E+038.83E+038.84E+03
Skin Dose FactorL;
(mrem/yr per pCi/m )
1.46E+031.34E+039.73E+032.37E+031.01E+047.29E+034.76E+029.94E+023.06E+027.11E+021.86E+031.22E+044.13E+032.69E+03
Gamma AirDose Factor
M;(mrad/yr per pCi/m )
1.93E+011.23E+031.72E+016.17E+03
- 1.52E+041.73E+041.63E+041.56E+023.27E+023.53E+023.36E+031.92E+031.51E+039.21E+039.30E+03
Beta AirDose Factor
N;(mrad/yr per pCi/m )
2.88E+021.97E+031.95E+031.03E+042.93E+031.06E+047.83E+031.11E+031.48E+031.05E+037.39E+022.46E+031.27E+044.75E+033.28E+03
From Table B-1 of Regulatory Guide 1.109 (Rev. 1, Oct. 1977)
CAPA8.DOC 08 54
PACIFIC GAS AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: OFF-SITE DOSE CALCULATIONS
NUMBER CAP A-8REVISION 22PAGE 55 OF 64
UNITS 1 AND 2
TABLE 10.4
CHILD INHALATIONPATHWAYDOSE FACTORS FOR WORST CASE ORGAN
RadionuclideH-3CR-51MN-54FE-59CO-58CO-60ZN-65RB-86SR-89Y-90SR-90ZR-95NB-95RU-103RU-106AG-110MSB-124SB-125TE-129MI-131I-133CS-134CS-136CS-137BA-140CE-141CE-144ND-147
p 1Y
i
6.40E+021.70E+041.58E+061.27E+061.11E+067.07E+069.95E+051.98E+052.16E+062.68E+053.85E+072.23E+066. 14E+056.62E+051.43E+075.48E+063.24E+062.32E+061.76E+061.62E+073.85E+061.01E+061.71E+059.07E+051.74E+065.44E+051.20E+073.28E+05
CAPA8.DOC 08 55
PACIFIC GAS ANDELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: OFF-SITE DOSE CALCULATIONS
NUMBERREVISIONPAGE
UNITS
CAP A-82256 OF 64
1AND2
Nuclide
TABLE 10.5
GROUND PLANE DOSE FACTORS
GRW DOSE PARAMETERS Ri.ot FOR RADIOIODINES, RADIOACTIVEPARTICULATES, AND ANYRADIONUCLIDEOTHER THAN
NOBLE GAS (IPT), GASEOUS EFFLUENTS(GRW),'NY
AGE GROUP, GROUND PLANE PATHWAY(mrem/yr per pCi/(sec m'))
Bone Liver T Body Thyroid Kidney Lung GI-LLIH-3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00CR-51 4.65E+06 4.65E+06 4.65E+06 4.65E+06 4.65E+06MN-54 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09FE-59 2.73E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08CO-58 3.80E+08 3.80E+08 3.80E+08 3.80E+08 3.80E+08
0.00E+004.65E+061.38E+092.73E+083.80E+08
0.00E+004.65E+061.38E+092.73E+083.80E+08
CO-60ZN-65RB-86SR-89Y-90SR-90 0.00E+00 O.OOE+00ZR-95 2.45E+08 2.45E+08NB-95 1.37E+08 1.37E+08RU-103 1.08E+08 1.08E+08RU-106 4.20E+08 4.20E+08
0.00E+002.45E+081.37E+081.08E+084.20E+08
2.15E+10 2.15E+10 2.15E+107.46E+08 7.46E+08 7.46E+088.98E+06 8.98E+06 8.98E+062.16E+04 2.16E+04 2.16E+044.50E+03 4.50E+03 4.50E+03
2.15E+107.46E+088.98E+062.16E+044.50E+03
2.15E+107.46E+088.98E+062.16E+044.50E+03
0.00E+00 0.00E+002.45E+08 2.45E+081.37E+08 1.37E+081.08E+08- 1.08E+084.20E+08 4.20E+08
2.15E+107.46E+088.98E+062.16E+044.50E+030.00E+002.45E+081.37E+081.08E+084.20E+08
2.15E+107.46E+088.98E+062.16E+044.50E+030.00E+002.45E+081.37E+081.08E+084.20E+08
AG-110M 3.45E+09 3.45E+09 3.45E+09 3.45E+09 3.45E+09SB-124 5.99E+08 5.99E+08 5.99E+08 5.99E+08 5.99E+08SB-125 2.34E+09 2.34E+09 2.34E+09 2.34E+09 2.34E+09TE-129M 1.98E+07 1.98E+07 1.98E+07 1.98E+07 1.98E+07I-131 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07I-133 2.45E+06 2.45E+06 2.45E+06 2.45E+06 2.45E+06CS-134 6.90E+09 6.90E+09 6.90E+09 6.90E+09 6.90E+09CS-136 1.51E+08 1.51E+08 1.51E+08 1.51E+08 1.51E+08CS-137 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10BA-140 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07CE-141 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07CE-144 6.96E+07 6.96E+07 6.96E+07 6.96E+07 6.96E+07ND-147 8.39E+06 8.39E+06 8.39E+06 8.39E+06 8.39E+06
3.45E+095.99E+082.34E+091.98E+071.72E+072.45E+066.90E+091.51E+081.03E+102.05E+071.37E+076.96E+078.39E+06
3.45E+095.99E+082.'34E+091.98E+071.72E+072.45E+066.90E+091.51E+081.03E+102.05E+071.37E+07„6.96E+078.'39E+06
Dose factors are based upon NUREG 0133 methodology.
CAPAS.DOC 08 56
PACIFIC GAS AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE OFF-SITE DOSE CALCULATIONS
NUMBER CAP A-8REVISION 22PAGE 57 OF 64
UNITS 1 AND 2
TABLE 10.6
GRW DOSE PARAMETERS FOR RADIOIODINES, RADIOACTIVEPARTICULATES, ANDANYRADIONUCLIDEOTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW)
CAPA8.DOC 08 57
PACIFIC GAS AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: OFF-SITE DOSE CALCULATIONS
NUMBER CAP A-8REVISION 22PAGE 58 OF 64
UNITS 1 AND 2
TABLE 10.6.1
GRW DOSE PARAMETERS FOR RADIOIODINES, RADIOACTIVEPARTICULATES, AND ANYRADIONUCLIDEOTHER THANNOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), INFANT
AGE GROUP, INHALATIONPATHWAYORGAN "0" (mrem/yr per pCi/m ) Rg ( y t
Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLIH-3 O.OOE+00 3.68E+02 3.68E+02CR-51 0.00E+00 0.00E+00 8.95E+01MN-54 O.OOE+00 2.53E+04 4.98E+03FE-59 1.36E+04 2.35E+04 9.48E+03CO-58 O.OOE+00 1.22E+03 1.82E+03
3.68E+025.75E+010.00E+000.00E+000.00E+00
3.68E+02 3.68E+02 3.68E+021.32E+01 1.28E+04 3.57E+024.98E+03 1.00E+06 7.06E+030.00E+00 1.02E+06 2.48E+040.00E+00 7.77E+05 1. 11E+04
CO-60ZN-65RB-86SR-89Y-90
0.00E+00 8.02E+03 1.18E+041.93E+04 6.26E+04 3.11E+04O.OOE+00 1.90E+05 8.82E+043.98E+05 O.OOE+00 1. 14E+043.29E+03 O.OOE+00 8.82E+01
0.00E+000.00E+000.00E+000.00E+000.00E+00
0.00E+00 4.51E+06 3.19E+043.25E+04 6.47E+05 5.14E+040.00E+00 0.00E+00 3.04E+030.00E+00 2.03E+06 6.40E+040.00E+00 2.69E+05 1.04E+05
SR-90ZR-95NB-95RU-103RU-106
1.55E+071.15E+051.57E+042.02E+038.68E+04
0.00E+00 3.12E+052.79E+04 2.03E+046.43E+03 3.78E+03O.OOE+00 6.79E+020.00E+00 1.09E+04
O.OOE+000.00E+000.00E+00O.OOE+00O.OOE+00
O.OOE+00 1.12E+07 1.31E+053.11E+04 1.75E+06 2.17E+044.72E+03 4.79E+05 1.27E+044.24E+03 5.52E+05 1.61E+041.07E+05 1.16E+07 1.64E+05
AG-110M 9.98E+03 7.22E+03SB-124 3.79E+04 5.56E+02SB-125 5.17E+04 4.77E+02TE-129M 1.41E+04 6.09E+03I-131 3.79E+04 4.44E+04
5.00E+031.20E+041.09E+042.23E+031.96E+04
0.00E+001.01E+026.23E+015.47E+031.48E+07
1.09E+04 3.67E+060.00E+00 2.65E+060.00E+00 1.64E+063.18E+04 1.68E+065.18E+04 O.OOE+00
3.30E+045.91E+041.47E+046.90E+041.06E+03
I-133CS-134CS-136CS-137BA-140
1.32E+043.96E+054.83E+045.49E+055.60E+04
1.92E+04 5.60E+037.03E+05 7.45E+041.35E+05 5.29E+046.12E+05 4.55E+045.60E+01 2.90E+03
3.56E+060.00E+000.00E+00O.OOE+000.00E+00
2.24E+04 0.00E+00 2.16E+031.90E+05 7.97E+04 1.33E+035.64E+04 1.18E+04 1.43E+031.72E+05 7.13E+04 1.33E+031.34E+01 1.60E+06 3.84E+04
CE-141 2.77E+04 1.67E+04 1.99E+03CE-144 3.19E+06 1.21E+06 1.76E+05ND-147 7.94E+03 8.13E+03 5.00E+02
0.00E+000.00E+000.00E+00
5.25E+03 5.17E+05 2.16E+04 .
5.38E+05 9.84E+06 1.48E+053.15E+03 3.22E+05 3.12E+04
Dose factors are based upon NUREG 0133 methodology.
cApAs.Doc 08 58
PACIFIC GAS ANDELECTRIC COMPANYDIABLOCANYONPOWER PLANT
NUMBER CAP A-8REVISION 22PAGE 59 OF 64
TITLE:t OFF-SITE DOSE CALCULATIONS UNITS 1 AND 2
TABLE 10.6.2
GRW DOSE PARAMETERS FOR RADIOIODINES, RADIOACTIVEPARTICULATES, AND ANYRADIONUCLIDEOTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), CHILD AGE
GROUP, INHALATIONPATHWAYORGAN "0" (mrem/yr per pCi/m ) R»„„.,
NuclideH-3CR-51MN-54FE-59CO-58
Bone Liver T Body Thyroid0.00E+00 6.40E+02 6.40E+02 6.40E+020.00E+00 0.00E+00 1.54E+02 8.55E+010.00E+00 4.29E+04 9.51E+03 0.00E+002.07E+04 3.34E+04 1.67E+04 0.00E+000.00E+00 1.77E+03 3.16E+03 0.00E+00
Kidney Lung GI-LLI6.40E+02 6.40E+02 6.40E+022.43E+01 1.70E+04 1.08E+031.00E+04 1.58E+06 2.29E+040.00E+00 1.27E+06 7.07E+040.00E+00 1.11E+06 3.44E+04
CO-60ZN-65RB-86SR-89Y-90
0.00E+004.26E+040.00E+005.99E+054.11E+03
1.31E+04 2.26E+041.13E+05 7.03E+041.98E+05 1.14E+050.00E+00 1.72E+040.00E+00 1.11E+02
0.00E+000.00E+000.00E+000.00E+000.00E+00
0.00E+00 7.07E+06 9.62E+047.14E+04 9.95E+05 1.63E+040.00E+00 0.00E+00 7.99E+030.00E+00 2.16E+06 1.67E+050.00E+00 2.62E+05 2.68E+05
SR-90ZR-95NB-95RU-103RU-106AG-110MSB-124SB-125TE-129MI-131
3.85E+07 0.00E+00 7.66E+051.90E+05 4.18E+04 3.70E+042.35E+04 9.18E+03 6.55E+032.79E+03 0.00E+00 1.07E+031.36E+05 0.00E+00 1.69E+041.69E+04 1.14E+04 9.14E+035.74E+04 7.40E+02 2.00E+049.84E+04 7.59E+02 2.07E+041.92E+04 6.85E+03 3.04E+034.81E+04 4.81E+04 2.73E+04
0.00E+000.00E+00O.OOE+00O.OOE+000.00E+000.00E+001.26E+029.10E+016.33E+031.62E+07
0.00E+00 1.48E+07 3.43E+055.96E+04 2.23E+06 6.11E+048.62E+03 6.14E+05 3.70E+047.03E+03 6.62E+05 4.48E+041.84E+05 1.43E+07 4.29E+052.12E+04 5.48E+06 1.00E+050.00E+00 3.24E+06 1.64E+050.00E+00 2.32E+06 4.03E+045.03E+04 1.76E+06 1.82E+057.88E+04 0.00E+00 2.84E+03
I-133CS-134CS-136CS-137BA-140
1.66E+046.51E+056.51E+049.07,E+057.40E+04
2.03E+041.01E+061.71E+058.25E+056.48E+01
7.70E+032.25E+051.16E+051.28E+054.33E+03
3.85E+060.00E+000.00E+000.00E+000.00E+00
3.38E+04 0.00E+003.30E+05 1.21E+059.55E+04 1.45E+042.82E+05 1.04E+052.11E+01 1.74E+06
5.48E+033.85E+034.18E+033.62E+031.02E+05
CE-141CE-144ND-147
3.92E+04 1.95E+04 2.90E+03 0.00E+006.77E+06 2.12E+06 3.61E+05 0.00E+001.08E+04 8.73E+03 6.81E+02 0.00E+00
8.55E+03 5.44E+05 5.66E+041.17E+06 1.20E+07 3.89E+054.81E+03 3.28E+05 8.21E+04
Dose factors are based upon NUREG 0133 methodology.
cApAs.Doc 08 59
t1
PACIFIC GAS AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT
NUMBER CAP A-8REVISION 22PAGE 60 OF 64
TITLE: OFF-SITE DOSE CALCULATIONS UNITS 1 AND2
TABLE 10.6.3
GRW DOSE PARAMETERS FOR RADIOIODINES, RADIOACTIVEPARTICULATES, AND ANYRADIONUCLIDEOTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), TEEN AGE
GROUP, INHALATIONPATHWAYORGAN "0" (mrem/yr per pCi/m ) R, t p,
Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLIH-3CR-51MN-54FE-59CO-58
0.00E+00 7.25E+02 7.25E+02 7.25E+02 7.25E+02 7.25E+02 7.25E+020.00E+00 0.00E+00 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.00E+030.00E+00 5.11E+04 ~ 8.40E+03 0.00E+00 1.27E+04 1.98E+06 6.68E+041.59E+04 3.70E+04 1.43E+04 0.00E+00 0.00E+00 1.53E+06 '.78E+050.00E+00 2.07E+03 2.78E+03 0.00E+00 0.00E+00 1.34E+06 9.52E+04
CO-60ZN-65RB-86SR-89Y-90
0.00E+003.86E+040.00E+004.34E+052.98E+03
1.51E+04 1.98E+041.34E+05 6.24E+041.90E+05 8.40E+040.00E+00 1.25E+040.00E+00 8.00E+01
0.00E+000.00E+000.00E+000.00E+000.00E+00
0.00E+00 8.72E+068.64E+04 1.24E+060.00E+00 0.00E+000.00E+00 2.42E+060.00E+00 2.93E+05
2.59E+054.66E+041.77E+043.71E+055.59E+05
SR-90ZR-95NB-95RU-103RU-106AG-110MSB-124SB-125TE-129MI-131
3.31E+07 0.00E+001.46E+05,4.58E+041.86E+04 1.03E+042.10E+03 0.00E+009.84E+04 0.00E+001.38E+04 1.31E+044.30E+04 7.94E+027.38E+04 8.08E+021.39E+04 6.58E+033.54E+04 4.91E+04
6.66E+053.15E+045.66E+038.96E+021.24E+047.99E+031.68E+041.72E+042.25E+032.64E+04
O.OOE+000.00E+000.00E+000.00E+000.00E+000.00E+009.76E+017.04E+Ol4.58E+031.46E+07
0.00E+00 1.65E+076.74E+04 2.69E+061.00E+04 7.51E+057.43E+03 7.83E+051.90E+05 1.61E+072.50E+04 6.75E+060.00E+00 3.85E+060.00E+00 2.74E+065.19E+04 1.98E+068.40E+04 O.OOE+00
7.65E+051.49E+059.68E+041.09E+059.60E+052.73E+053.98E+059.92E+044.05E+056.49E+03
I-133CS-134CS-136CS-137,BA-140CE-141CE-144ND-147
1.22E+04 2.05E+04 6.22E+03 2.92E+065.02E+05 1.13E+06 5.49E+05 0.00E+005.15E+04 1.94E+05 1.37E+05 0.00E+006.70E+05 8.48E+05 3.11E+05 '.00E+005.47E+04 6.70E+01 3.52E+03 0.00E+002.84E+04 1.90E+04 2.17E+03 0.00E+004.89E+06 2.02E+06 2.62E+05 0.00E+007.86E+03 8.56E+03 5.13E+02 0.00E+00
3.59E+04 0.00E+003.75E+05 1.46E+051.10E+05 1.78E+043.04E+05 1.21E+052.28E+01 2.03E+068.88E+03 6.14E+051.21E+06 1.34E+075.02E+03 3.72E+05
1.03E+049.76E+031.09E+048.48E+032.29E+051.26E+058.64E+051.82E+05
Dose factors are based upon NUREG 0133 methodology.
CAPA8.DOC 08 60
PACIFIC GAS ANDELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: OFF-SITE DOSE CALCULATIONS
NUMBER, CAP A-8REVISION 22PAGE 61 OF 64
UNITS 1 AND 2
Nuclide Bone Liver T Body GI-LLI
TABLE 10.6.4
GRW DOSE PARAMETERS FOR RADIOIODINES, RADIOACTIVEPARTICULATES, AND ANYRADIONUCLIDEOTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), ADULT
AGE GROUP, INHALATIONPATHWAYORGAN "0" (mrem/yr per pCi/m ) Ri jh It
Thyroid Kidney LunH-3 O.OOE+00 7.18E+02 7.18E+02CR-51 0.00E+00 0.00E+00 1.00E+02MN-54 0.00E+00 3.96E+04 6.30E+03FE-59 1.18E+04 2.78E+04 1.06E+04CO-58 0.00E+00 1.58E+03 2.07E+03
7.18E+025.95E+01O.OOE+00O.OOE+00O.OOE+00
7.18E+02 7.18E+02 7.18E+022.28E+01 1.44E+04 3.32E+039.84E+03 1.40E+06 7.74E+040.00E+00, 1.02E+06 1.88E+050.00E+00 9.28E+05 1.06E+05
CO-60ZN-65RB-86SR-89Y-90SR-90ZR-95NB-95RU-103RU-106
0.00E+00 1.15E+04 1.48E+043.24E+04 1.03E+05 "4.66E+04O.OOE+00 1.35E+05 5.90E+043.04E+05 0.00E+00 8.72E+032.09E+03 0.00E+00 5.61E+012.87E+07 O.OOE+00 5.77E+051.07E+05 3.44E+04 2.33E+041.41E+04 7.82E+03 4.21E+031.53E+03, 0.00E+00 6.58E+026.91E+04 0.00E+00 8.72E+03
O.OOE+000.00E+00O.OOE+000.00E+000.00E+000.00E+000.00E+00O.OOE+000.00E+000.00E+00
0.00E+00 5.97E+06 2.85E+056.90E+04 8.64E+05 5.34E+040.00E+00'.OOE+00 1.66E+04O.OOE+00 1.40E+06 3.50E+05O.OOE+00 1.70E+05 5.06E+050.00E+00 9.60E+06 7.22E+055.42E+04 1.77E+06 1.50E+057.74E+03 5.05E+05 1.04E+055.83E+03 5.05E+05 1.10E+051.34E+05 9.36E+06 9.12E+05
AG-110MSB-124SB-125TE-129MI-131
1.08E+043.12E+045.34E+049.76E+032.52E+04
1.00E+04 5.94E+035.89E+02 1.24E+045.95E+02 1.26E+044.67E+03 1.58E+033.58E+04 2.05E+04
O.OOE+007.55E+015.40E+013.44E+031.19E+07
1.97E+040.00E+000.00E+003.66E+046.13E+04
4.63E+06 3.02E+052.48E+06 4.06E+051.74E+06 1.01E+051.16E+06 3.83E+05O.OOE+00 6.28E+03
I-133CS-134CS-136CS-137BA-140
8.64E+03 1.48E+04 4.52E+033.73E+05 8.48E+05 7.28E+053.90E+04 1.46E+05 1.10E+054.78E+05 6.21E+05 4.28E+053.90E+04 4.90E+01 '.57E+03
2.15E+060.00E+000.00E+000.00E+000.00E+00
2.58E+04 0.00E+00 8.88E+032.87E+05 9.76E+04 1.04E+048.56E+04 1.20E+04 1.17E+042.22E+05 7.52E+04 8.40E+031.67E+01 1.27E+06 2.18E+05
CE-141 1.99E+04 1.35E+04 1.53E+03CE-144 " 3.43E+06 1.43E+06 1.84E+05ND-147 5.27E+03 6.10E+03 3.65E+02
0.00E+000.00E+00O.OOE+00
6.26E+03 3.62E+05 1.20E+058.48E+05 7.78E+06 8.16E+053.56E+03 2.21E+05 1.73E+05
Dose factors are based upon NUREG 0133 methodology.
CAPA8.DOC 08 61
PACIFIC GAS AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: OFF-SITE DOSE CALCULATIONS
NUMBER CAP A-8REVISION 22PAGE 62 OF 64
UNITS 1 AND 2
TABLE 10.6.5
GRW DOSE PARAMETERS'OR RADIOIODINES, RADIOACTIVEPARTICULATES, AND ANYRADIONUCLIDEOTHER THANNOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), CHILD AGE
GROUP, VEGETATIONPATHWAYORGAN "0" (mrem/yr per pCi/(sec m')) R, p's(
Nuclide Bone Liver T Body Thyroid Kidney Lun GI-LLI'-3
CR-51MN-54FE-59CO-58CO-60ZN-65RB-86SR-89Y-90
0.00E+00 2.29E+03 2.29E+03 2.29E+030.00E+00 0.00E+00 1.17E+05 6.49E+040.00E+00 6.65E+08 1.77E+08 0.00E+003.97E+08 6.42E+08 3.20E+08 0.00E+000.00E+00 6.45E+07 1.97E+08 0.00E+000.00E+00 3.78E+08 1.12E+09 0.00E+008.12E+08 2.16E+09 1.35E+09 0.00E+000.00E+00 4.54E+08 2.79E+08 0.00E+003.59E+10 0.00E+00 1.03E+09 0.00E+002.31E+04 0.00E+00 6.18E+02 0.00E+00
2.29E+03 2.29E+03 2.29E+031.77E+04 1.18E+05 6.20E+061.86E+08 0.00E+00 5.58E+080.00E+00 1.86E+08 6.69E+080.00E+00 0.00E+00 3.76E+080.00E+00 0.00E+00 2.10E+091.36E+09 0.00E+00 3.80E+080.00E+00 0.00E+00 2.92E+070.00E+00 0.00E+00 1.39E+090.00E+00 0.00E+00 6.57E+07
SR-90ZR-95NB-95RU-103RU-106
1.87E+123.86E+064.12E+051.53E+077.45E+08
0.00E+00 3.77E+ 10 0.00E+008.50E+05 7.56E+05 0.00E+001.61E+05 1.15E+05 0.00E+000.00E+00 5.89E+06 0.00E+000.00E+00 9.30E+07 0.00E+00
0.00E+00 0.00E+00 1.67E+101.22E+06 0.00E+00 8.86E+081.51E+05 0.00E+00 2.97E+083.86E+07 0.00E+00 3.96E+081.01E+09 0.00E+00 1.16E+10
AG-110M 3.21E+07SB-124 3.52E+08SB-125, 4.99E+08TE-129M 8.40E+08I-131 1.43E+08
2.17E+074.57E+063.85E+062.35E+081.44E+08
1.74E+071.23E+081.05E+081.30E+088.17E+07
0.00E+007.78E+054.62E+052.71E+084.75E+10
4.04E+07 0.00E+00 2.58E+090.00E+00 1.96E+08 2.20E+090.00E+00 2.78E+08 1.19E+092.47E+09 0.00E+00 1.02E+092.36E+08 0.00E+00 1.28E+07
I-133CS-134CS-136CS-137BA-140
3.52E+061.60E+ 108.18E+072.39E+102.77E+08
4.36E+062.63E+102.25E+082.29E+102.43E+05
1.65E+06 8.09E+085.55E+09 0.00E+001.46E+08 0.00E+003.38E+09 0.00E+001.62E+07 0.00E+00
7.26E+068.16E+091.20E+087.46E+097.90E+04
0.00E+00 1.76E+062.93E+09 1.42E+081.79E+07 7.90E+062.68E+09 1.43E+081.45E+05 1.40E+08
CE-141 6.55E+05 3.27E+05 4.85E+04CE-144 1.27E+08 3.98E+07 6.78E+06ND-147 . 7.27E+04 5.89E+04 4.56E+03
0.00E+000.00E+00O.OOE+00
1.43E+05 0.00E+00 4.08E+082.21E+07 0.00E+00 1.04E+103.23E+04 O.OOE+00 9.33E+07
Dose factors are based upon NUREG 0133 methodology.
For Tritium the units of the dose parameters are mrem/yr per pCi/m for all pathways, and they must'e
multiplied by X/Q.
cApAs.Doc 08 62
4
PACIFIC GAS AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: OFF-SITE DOSE CALCULATIONS
NUMBER CAP A-8REVISION 22PAGE 63 OF 64
UNITS 1 AND 2
TABLE 10.6.6
GRW DOSE PARAMETERS FOR RADIOIODINES, RADIOACTIVEPARTICULATES, AND ANYRADIONUCLIDEOTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), TEEN AGE
GROUP, VEGETATIONPATHWAYORGAN "0" (mrem/yr per pCi/(sec m')) R,<,,
Nuclide Bone Liver T Body Thyroid Kidney Lun GI-LLIH-3 0.00E+00 1.47E+03 1.47E+03 1.47E+03, 1.47E+03 1.47E+03 1.47E+03CR-51 0.00E+00 0.00E+00 6.16E+04 3.42E+04 1.35E+04 8.79E+04 1.03E+07MN-54 0.00E+00 4.54E+08 9.01E+07 0.00E+00 1.36E+08 0.00E+00 9.32E+08FE-59 1.79E+08 4.18E+08 1.61E+08 0.00E+00 0.00E+00 1.32E+08 9.89E+08CO-58 0.00E+00 4.37E+07 1.01E+08 0.00E+00 0.00E+00 0.00E+00 6.02E+08CO-60ZN-65RB-86SR-89Y-90
0.00E+004.24E+08O.OOE+001.51E+101.24E+04
2.49E+08 5.60E+081.47E+09 6.86E+082.75E+08 1.29E+080.00E+00 4.33E+080.00E+00 3.35E+02
0.00E+000.00E+000.00E+000.00E+000.00E+00
0.00E+00 0.00E+00 3.24E+099.41E+08 0.00E+00 6.23E+080.00E+00 0.00E+00 4.06E+070.00E+00 0.00E+00 1.80E+090.00E+00 0.00E+00 1.02E+08
SR-90 9.22E+11 0.00E+00 1.84E+10 0.00E+00ZR-95 1.72E+06 5.44E+05, 3.74E+05 0.00E+00NB-95 1.93E+05 1.07E+05 5.90E+04 0.00E+00RU-103 6.82E+06 0.00E+00 2.91E+06 0.00E+00RU-106 3.09E+08 0.00E+00 3.90E+07 0.00E+00AG-110M 1.52E+07 1.44E+07 8.73E+06 0.00E+00SB-124 1.55E+08 2.85E+06 6.03E+07 3.51E+05SB-125 2.14E+08 2.34E+06 5.01E+07 2.05E+05TE-129M 3.61E+08 1.34E+08 5.72E+07 1.17E+08I-131 7.68E+07 1.08E+08 5.78E+07 3.14E+10
0.00E+00 0.00E+00 2.11E+107.99E+05 0.00E+00 .1.26E+091.04E+05 O.OOE+00 4.58E+082.40E+07 0.00E+00 5.69E+085.97E+08 0.00E+00 1.48E+102.74E+07 0.00E+00 4.03E+090.00E+00 1.35E+08 3.11E+090.00E+00 1.88E+08 1.67E+091.51E+09 0.00E+00 1.36E+091.85E+08 0.00E+00 2.13E+07
I-133CS-134CS-136CS-137BA-140
1.93E+067.10E+094.35E+071.01E+ 101.38E+08
3.28E+061.67E+101.71E+081.35E+101.69E+05
1.00E+067.75E+091.15E+084.69E+098.90E+06
4.58E+080.00E+000.00E+000.00E+000.00E+00
5.75E+06 O.OOE+005.31E+09 2.03E+099.31E+07 1.47E+074.59E+09 '.78E+095.74E+04 1.14E+05
2.48E+062.08E+081.38E+071.92E+082.13E+08
CE-141 2.83E+05 1.89E+05 2.17E+04 0.00E+00CE-144 5.27E+07 2.18E+07 2.83E+06 0.00E+00ND-147 3.67E+04 .4.00E+04 2.39E+03 0.00E+00
8.89E+04 0.00E+00 5.40E+081.30E+07 0.00E+00 1.33E+102.35E+04 0.00E+00 1.44E+08
Dose factors are based upon NUREG 0133 methodology.2 For Tritium the units of the dose parameters are mrem/yr per pCi/m for all pathways, and they must
be multiplied by X/Q.
CAPA8.DOC 08 63
PACIFIC GAS AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: OFF-SITE DOSE CALCULATIONS
NUMBER CAP A-8REVISION 22PAGE 64 OF 64
UNITS j. AND 2
TABLE 10.6.7
GRW DOSE PARAMETERS FOR RADIOIODINES, RADIOACTIVEPARTICULATES, AND ANYRADIONUCLIDEOTHER THANNOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), ADULT
AGE GROUP VEGETATIONPATHWAYORGAN 0 (mrem/yr pcI'Ci/(sec m )) Rl yy
Nuclide Bone Liver T Body Thyroid Kidney Lun GI-LLIH-3CR-51MN-54FE-59CO-58
0.00E+000.00E+000.00E+001.26E+080.00E+00
1.29E+03 1.29E+03 1.29E+03 1.29E+03 1.29E+03 1.29E+030.00E+00 4.64E+04 2.77E+04 1.02E+04 6.15E+04 1.17E+073.13E+08 5.97E+07 O.OOE+00 9.31E+07 0.00E+00 9.5SE+082.96E+08 1.13E+08 0.00E+00 0.00E+00 8.27E+07 9.87E+083.08E+07 6.90E+07 0.00E+00 0.00E+00 0.00E+00 6.24E+08
CO-60ZN-65 *
RB-86SR-89Y-90
0.00E+00 1.67E+08 3.69E+083.17E+08 1.01E+09 4.56E+080.00E+00 2.20E+08 1.03E+OS9.95E+09 0.00E+00 2.86E+081.33E+04 0.00E+00 3.57E+02
0.00E+00 O.OOE+00 0.00E+00 3. 14E+090.00E+00 6.75E+OS O.OOE+00 6.36E+080.00E+00 O.OOE+00 0.00E+00 4.34E+070.00E+00 0.00E+00 O.OOE+00 1.60E+090.00E+00 O.OOE+00 0.00E+00 1.41E+08
SR-90 6.95E+11 0.00E+00 1.40E+10 0.00E+00 O.OOE+00ZR-95 1.18E+06 3.77E+05, 2.55E+05 O.OOE+00 5.92E+05NB-95 1.43E+05 7.95E+04 4.27E+04 O.OOE+00 7.86E+04RU-103 '.77E+06 0.00E+00 2.05E+06 0.00E+00 1.82E+07RU-106 1.93E+08 0.00E+00 2.44E+07 0.00E+00 3.72E+08
0.00E+00 1.75E+100.00E+00 1.20E+090.00E+00 4.83E+080.00E+00 5.57E+08O.OOE+00 1.25E+10
AG-110M 1.05E+07SB-124 1.04E+08SB-125 1.37E+08TE-129M 2:51E+08I-131 8.07E+07
9.75E+06 5.79E+06 0.00E+001.96E+06 4.11E+07 2.52E+051.53E+06 3.25E+07 1.39E+059.37E+07 3.97E+07 8.62E+071.15E+08 6.62E+07 3.78E+10
1.92E+07, 0.00E+00 3.98E+090.00E+00 8.08E+07 2.95E+090.00E+00 1.05E+08 1.50E+091.05E+09 0.00E+00 1.26E+091.98E+08 O.OOE+00 3.05E+07
I-133CS-134CS-136CS-137BA-140
2.08E+064.67E+094.25E+076.36E+091.29E+08
3.62E+06 1.10E+06 5.32E+OS 6.31E+06 0.00E+00 3.25E+061.11E+10 9.08E+09 0.00E+00 3.59E+09 1.19E+09 1.94E+081.68E+08 - 1.21E+08 0.00E+00 9.33E+07 1.28E+07 1.90E+078.70E+09 5.70E+09 O.OOE+00 2.95E+09 9.81E+08 1.68E'+081.61E+05 8.42E+06 0.00E+00 5.49E+04 9.24E+04 2.65E+08
CE-141CE-144ND-147
1.97E+05 1.33E+05 ~ 1.51E+04 0.00E+00 6.19E+04 0.00E+00 5.09E+083.29E+07 1.38E+07 1.77E+06 0.00E+00 8.16E+06 0.00E+00 1.11E+103.37E+04 3.90E+04 2.33E+03 O.OOE+00 2.28E+04 0.00E+00 1.87E+08
Dose factors are based upon NUREG 0133 methodology.
For Tritium the units of the dose parameters are mrem/yr per pCi/m for all pathways, and they mustbe multiplied by X/Q.
cApAs.Doc 08 64
Attachment 5PG&E Letter DCL 99-055
Process Control Program
(RP2. DC2 Revision 4)
*~*ISSUED FOR USE BY:PACIFIC GAS ANDELECTRIC COMPANYNUCLEAR POWER GENERATIONDIABLOCANYONPOWER PLANTADMINISTRATIVEPROCEDURE
DATE: EXPIRES: 4>k8
NUMBER RP2.DC2
REVISION 4
PAGE 1 OF 6
'ITLE: PROCESS CONTROL PROGRAM
EFFECTIVE DATESPONSORING ORGANIZATION:RADIATIONPROTECTION
PROCEDURE CLASSIFICATION: QUALITYRELATEDREVIEW LEVEL: "A"
SCOPE
DISCUSSION
2.1 Solidification is the conversion of wet radioactive wastes into a form that meets
shipping and burial ground requirements.
This procedure implements the requirements of 10 CFR 50.36a and General DesignCriterion 60 of Appendix A to 10 CFR Part 50. The process parameters included inestablishing the PROCESS CONTROL PROGRAM may include, but are not limited to,waste type, waste pH, waste/liquid/SOLIDIFICATION agent/catalyst ratios, waste oilcontent, waste principal chemical constituents, and mixing and curing times.
This procedure contains the individual procedures necessary to perform PCP samplesolidifications.
2.2
2.3
Cement Solidification willnot be utilized to stabilize resin or floor drain sludges. OnlyNRC approved binders (e.g., bitumen, VinylEster Styrene, Aztec) may be used tosolidify resin or floor drain sludges to meet waste form stability.
RESPONSIBILITIES
2.4
1.1 ~ The purpose of the Process Control Program (PCP) is to define the necessary programguidance used at DCPP to ensure that SOLID RADIOACTIVEWASTEMANAGEMENTactivities, in solidifying wet radioactive waste for disposal, conformto the Code of Federal and State Regulations and the Waste Burial Site License Criteria.
3.1
3.2
3.3
3.4
3.5
Plant Manager has the overall responsibility for the Solid Radioactive Waste activities atDCPP.
Director, Radiation Protection is responsible for the implementation of the requirementsof this procedure.
Radwaste Engineer is responsible for the development and review of proceduresrelating to the requirements of this procedure.
.The Radwaste Foreman is responsible for the implementation of procedures relating tothe requirements of this procedure.
The Quality Control Section is responsible for verification of compliance with the
Quality requirements.
RP2DC2.DOC
PACIFIC GAS AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: PROCESS CONTROL PROGRAM
NUMBER RP2.DC2REVISION 4PAGE- 2OF6
4.2
5.1 GENERAL
It is the policy of Pacific Gas and Electric Company to conscientiously apply emphasisand attention to those activities associated with generation, processing, packaging,storage and disposal of radioactive waste generated at the Diablo Canyon Power Plantand to maintain a high level of assurance that radioactive waste products meet or exceed
the applicable Federal and State regulations and the Radioactive Waste Burial SiteLicense Criteria.
4.1 This procedure with the attachments and any changes thereto requires review by thePlant Staff Review Committee and submission to the US NRC in the Annual EffluentReport for the period in which the changes were made.
Any major change to the Solid Radwaste Treatment System shall be'reported to the USNRC in the Annual Effluent Report for the period in which the evaluation was reviewed
by the PSRC. The discussion of each change shall contain the items listed inAttachment 7.2. This information may be submitted as part of the annual FSAR updatein lieu of the Annual Effluent Report.
INSTRUCTIONS
5.2 WET WASTE
5.2.1 LIQUID/WETWASTE
5.2.2
Liquid/Wet wastes at DCPP are processed to a condition meeting shipping-and disposal criteria. These criteria include requirements for immobilization,stability and limits on Free Standing Water (FSW). Specific instructions onprocessing and required FSW limits are contained in plant procedures and/orqualified vendor procedures.
CONTAINERS, SHIPPING CASKS AND PACKAGING
Solid radioactive waste is processed, packaged and shipped in accordancewith DCPP procedures and/or qualified vendor procedures. Theseprocedures provide specific instructions which ensure the container, shippingcasks, and packaging methods comply with the applicable Code of FederalRegulations, State Regulations and the Radioactive Waste Burial Site LicenseCriteria.
5.2.3 SHIPPING AND DISPOSAL
Solid radioactive waste is prepared, loaded and shipped to a Federal and/orState Licensed Radioactive Waste Disposal Facility (Burial Ground) inaccordance with DCPP procedures and/or qualified vendor procedures.These procedures provide specific instructions which ensure the shipmentsmeet the intended Burial Site License Requirements as well as'pplicableFederal and State Regulations.
RP2DC2.DOC 1B
'V
PACIFIC GAS ANDELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: PROCESS CONTROL PROGRAM
NUMBER RP2.DC2REVISION 4PAGE 3 OF 6
5.2.4
5.2.5
5.2.6
LABORATORYMIXINGOF SAMPLES
Qualified vendor procedures reviewed by the PSRC and approved by thePlant Manager provide written instructions on sampling, processing and
handling waste for the determination of process parameters prior to the actualfull scale solidification. These procedures contain the description of thelaboratory mixing methods used for these samples.
SOLIDIFICATIONPROCESS
Qualified vendors used by DCPP for radioactive waste solidification are
required to provide the Process Control Program and written procedures.These procedures and changes thereto must be reviewed by the PSRC and
approved by the Plant Manager prior to use. Further, the vendors arerequired to have a topical report, as referenced, on the waste forms whichwillbe solidified at DCPP. This topical report should demonstratecompliance with the NRC requirements for waste form. These documentsshould include:
a. Description of the solidification process.
b. Type of solidification used.
c. Process control parameters.
d. Parameter boundary conditions.
e. Proper waste form properties.
f. Specific instructions to ensure the systems are operated withinestablished process parameters.
SAMPLING PROGRAM FOR SOLIDIFICATION
Vendors, utilized by DCPP for radioactive waste solidification, are requiredto include in their approved procedures, requirements to sample at least everytenth batch of the same waste type to ensure solidification and to provideactions to be taken ifa sample fails to verify solidification. After a test
specimen failure, initial test specimens from three consecutive batches of thatwaste type must demonstrate solidification before testing requirements ofevery tenth batch can be resumed. Verification of such sampling is to beaccomplished by completing Form 69-10350, "Processing Control Program(PCP) Verification." (See Attachment 7.1.) These forms willbe maintainedin the Radiation Protection Section and the Records Management System(RMS). These procedures and changes thereto must be reviewed by thePSRC and approved by the Plant Manager prior to use.
RP2DC2.DOC
PACIFIC GAS AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: PROCESS CONTROL PROGRAM
NUMBER RP2.DC2REVISION 4PAGE 4 OF 6
5.3
5.4
5.2.7 WASTE FORM VERIFICATION
Vendors utilized by DCPP to process wet wastes are required to include intheir procedures provisions to verify that the solidification and/or FSWCriteria in the Federal and State regulations and the Burial Site License aremet for the specific type of waste being processed.
5.2.8 CORRECTIVE ACTIONS FOR FREE STANDINGWATER
Vendors utilized by DCPP to process wet wastes are required to include intheir approved procedures provisions for correcting processed waste in whichfree standing water in excess of the FSW Criteria is detected.
5.2.9 EXOTHERMIC PROCESSES
Vendors utilized by DCPP for radioactive waste solidification that utilize an
exothermic solidification method are required to include in their approvedprocedures:
a. Waste/binder temperature monitoring to mitigate the consequence ofadverse exothermic reactions which may occur in the full scale
solidification but might not be noticeable in the specimen tests.
b. Specific process control parameters that shall be met before capping thecontainer.
OILYWASTE
Oily wastes at DCPP are processed in accordance with approved vendor procedures.These procedures specify the proper methods to treat oily wastes to comply withFederal and State regulations and applicable Burial Site License Criteria.
SPECIAL CASES
Based upon previous industry experience, DCPP foresees the potential for situationsarising that may be beyond existing plant capabilities. Anticipating this possibility,provisions are made herein to accommodate such situations in a timely manner by usingspecial techniques or processes. These special cases would be controlled as follows:
5.4.1 Implementing procedures would be developed comparable to those used fornormal plant solid waste activities based on the guidance of this PCP andincorporating the applicable provisions for process control and testing.
5.4.2 The implementing procedure would receive PSRC review and Plant Managerapproval prior to use.
5.4.3 Use of this provision and supporting information would be included in thenext Annual Effluent Report to the NRC.
RP2DC2. DOC 1B
PACIFIC GAS ANDELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: PROCESS CONTROL PROGRAMti
A
NUMBER RP2.DC2REVISION 4PAGE 5 OF 6
5.5 REMEDIALACTIONS
5.5.1
5.5.2
For waste forms which do not meet Federal, State and burial site regulationsand requirements, suspension of shipment of the inadequately processed
waste and correction of the PCP, procedures or processing equipment shallbe performed as necessary to prevent recurrence.
For waste forms not prepared in accordance with the PCP, testing of thewaste to verify shipping and burial site requirements shall be performed and
appropriate administrative action taken to prevent recurrence.
5.6 VENDOR PROCEDURES AND REPORTS
5.6.1 The following are maintained in Document Control Master File, Catalog No.TK 9400/SEG-1.
a. Scientific Ecology Group, Inc., Procedure SS-042, Process ControlProgram for Radwaste Solidification Service at Diablo Canyon PowerPlant, Rev. F
b. Topical Report TR-002, 10 CFR 61 Qualified Radioactive WasteForms, Rev. 1
Scientific Ecology Group, Inc., Procedure GS-007, "TemperatureIndicating Device Comparison Test," Rev. E
Scientific Ecology Group, Inc., Procedure GS-006, "Calibration for a
Triple Beam Balance," Rev. D
e. Scientific Ecology Group, Inc., Procedure SS-049, "PenetrometerCheck Procedure," Rev. D
5.6.2 The following are maintained in Document Control Master File, Catalog No.TK 94001 DTI-1.
Diversified Technologies, Procedure DT-DCPP-10, PCP for VERISolidification, Rev 14
Topical Report DTI-VERI-100-NP-A. VERI (VinylEster Resin InSitu) Solidification Process for Low-Level Radioactive Waste, Rev 1
c. Diversified Technologies, Procedure QIP 20-17, pH Meter Calibration,Rev. 3
d. Diversified Technologies, Procedure QIP 20-18,,Conductivity MeterCalibration, Rev. 2
e. Diversified Technologies, Procedure QIP-20-16, ThermocoupleCalibration, Rev 1
f. Diversified Technologies, Procedure DT-DCPP-VES-14, PCP for VESSolidification, Rev B.
RP2DC2.DOC
PACIFIC GAS AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: PROCESS CONTROL PROGRAM
NUMBER RP2.DC2REVISION 4PAGE 6 OF 6
6. RECORDS
g. Topical Report DNS-RSS-200-NP, The Dow Waste SolidificationProcess for Low-Level Radioactive Waste (Docket Number WM-82).
6.1 Records of PCP specimen results and Form 69-10350 shall be submitted to the RecordsManagement System on a shipment basis by container per RCP RW-4.
7. ATTACHMENTS
7.1 Form 69-10350, "Process Control Program (PCP) Verification," 06/03/93
7.2 "Major Change to the Solid Radwaste Treatment System Evaluation," 06/03/93
REFERENCES
8.1 Title 10 Code of Federal Regulations.
8.2 NUREG 0472 and 0473.
8.3 NUREG-0800, 11.4 US NRC Standard Review Plan Solid Waste ManagementSystems.
8.4
8.5
8.6
8.7
8.8
RCP.DC3, "Dewatering Control Program."
RP2.DC4, "Mobile Service Operating Procedure for Low-Level Radioactive WasteProcessing."
NRC Information Notice 88-08, Chemical Reactions with Radioactive WasteSolidification Agents.
Scientific Ecology Group, Inc., Quality Management System Manual, Rev. 5,Document Control Master File, Catalog No. TK-9400/SEG-3.
Technical Position on Waste Form, Revision 1, US NRC, January 1991.
SPONSOR
C. Clint Miller
RP2DC2.DOC 1B
69-10350 06/03/93DIABLOCANYONPOWER PLANT
RP2.DC2
Page 1 of 1
TITLE: PROCESS CONTROL PROGRAM (PCP) VERIFICATION
WASTE BATCH PCPDATE
Number Type Passed FailedNOTES OPERATOR VERIFIER
RP2DC2. DOC
06/03/93DIABLOCANYONPOWER PLANT
RP2.DC2ATTACHMENT7.2
Page 1 of 1
TITLE: MAJOR CHANGE TO THE SOLID RADWASTE TREATMENTSYSTEMEVALUATION
1. A summary of the evaluation that led to the determination that the change could be made inaccordance with 10 CFR 50.59;
2. Sufficient detailed information to totally support the reason for the change without benefit ofadditional or supplemental information;
3. A detailed description of the equipment, components and processes involved and the interfaces withother plant systems;
4. An evaluation of the change which shows the predicted releases of radioactive materials in liquid andgaseous effluents and/or quantity of solid waste that differ from those previously predicted in theLicense application and amendments thereto;
5. An evaluation of the change which shows the expected maximum exposures to a MEMBER OF THEPUBLIC in the UNRESTRICTED AREA and to the general population that differ from those
previously estimated in the License application and amendments thereto;
6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluent and insolid waste, to the actual releases for the period prior to when the changes are to be made;
7. An estimate of the exposure to plant operating personnel as a result of the change; and
8. Documentation of the fact that the change was reviewed and found acceptable by the PSRC.
RP2DC2.DOC
Attachment 6PG8E Letter DCL 99-055
Process Control Program
(RP2. DC2 Revision 5)
~~~ ISSUED FOR USE BY:PACIFIC GAS ANDELECTRIC COMPANYNUCLEARPOWER GENERATIONDIABLOCANYONPOWER PLANTADMINISTRATIVEPROCEDURE
DATE: EXPIRES:NUMBER RP2.DC2
REVISION 5
PAGE 1 OF 6
TITLE: PROCESS CONTROL PROGRAM
(o-EFFECTIVE DATE
SPONSORING ORGANIZATION:RADIATIONPROTECTIONPROCEDURE CLASSIFICATION:QUALITYRELATED
REVIEW LEVEL: "A"
l. SCOPE
The purpose of the Process Control Program (PCP) is to define the necessary programguidance used at DCPP to ensure that SOLID RADIOACTIVEWASTEMANAGEMENTactivities, in solidifying wet radioactive waste for disposal, conformto the Code of Federal and State Regulations and the Waste Burial Site License Criteria.
DISCUSSION
2.1
2.2
2.3
SolidiTication is the conversion of wet radioactive wastes into a form that meetsshipping and burial ground requirements.
This procedure implements the requirements of 10 CFR 50.36a and General Design, Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in
establishing the PROCESS CONTROL PROGRAM may include, but are not limited to,waste type, waste pH, waste/liquid/SOLIDIFICATION agent/catalyst ratios, waste oilcontent, waste principal chemical constituents, and mixing and curing times.
This procedure contains the individual procedures necessary to perform PCP samplesolidifications.
2.4 Cement Solidification willnot be utilized to stabilize resin or floor drain sludges. OnlyNRC approved binders (e.g., bitumen, Vinyl Ester Styrene, Aztec) may be used tosolidify resin or floor drain sludges to meet waste form stability.
RESPONSIBILITIES
3.1
3.2
3.3
3.4
3.5
Plant Manager has the overall responsibility for the Solid Radioactive Waste activities atDCPP.
Director, Radiation Protection is responsible for the implementation of the requirementsof this procedure.
Radwaste Engineer is responsible for the development and review of proceduresrelating to the requirements of this procedure.
The Radwaste Foreman is responsible for the, implementation of procedures relating tothe requirements of this procedure.
NQS is responsible for verification of compliance with the Quality requirements.
01180405.DOA 1B I I 0806.08l3
PACIFIC GAS AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: PROCESS CONTROL PROGRAM
NUMBER RP2.DC2REVISION 5PAGE 2 OF 6
4,
5.
PRERE UISITES
4.2
4.1 This procedure with'the attachments and any changes thereto requires review by thePlant Staff Review Committee and submission to the US NRC in the Annual EffluentReport for the period in which the changes were made.
Any major change to the Solid Radwaste Treatment System shall be reported to the USNRC in the Annual Effluent Report for the period in which the evaluation was reviewedby the PSRC. The discussion of each change shall contain the items listed inAttachment 7.2. This information may be submitted as part of the annual FSAR updatein lieu of the Annual Effluent Report.
INSTRUCTIONS
5.1
5.2
GENERAL
It is the policy of Pacific Gas and Electric Company to conscientiously apply emphasis ~
and attention to those activities associated with generation, processing, packaging,storage and disposal of radioactive waste generated at the Diablo Canyon Power Plantand to maintain a high level of assurance that radioactive waste products meet or exceedthe applicable Federal and State regulations and the Radioactive Waste Burial SiteLicense Criteria.
WET WASTE
5.2.1 LIQUID/WETWASTE
5.2.2
5.2.3
Liquid/Wet wastes at DCPP are processed to a condition meeting shippingand disposal criteria. These criteria include requirements for immobilization,stability and limits on Free Standing Water (FSW). Specific instructions onprocessing and required FSW limits are contained in plant procedures and/orqualified vendor procedures.
CONTAINERS, SHIPPING CASKS AND PACKAGING
Solid radioactive waste is processed, packaged and shipped in accordancewith DCPP procedures and/or qualified vendor procedures. Theseprocedures provide specific instructions which ensure the container, shippingcasks, and packaging methods comply with the applicable Code of FederalRegulations, State Regulations and the Radioactive Waste Burial Site LicenseCriteria.
SHIPPING AND DISPOSAL
Solid radioactive waste is prepared, loaded and shipped to a Federal and/orState Licensed Radioactive Waste Disposal Facility (Burial Ground) inaccordance with DCPP procedures and/or qualified vendor procedures.These procedures provide specific instructions which ensure the shipmentsmeet the intended Burial Site License Requirements as well as applicableFederal and State Regulations.
01180405.DOA IB 2 I 0806.08i3
PACIFIC GAS ANDELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: PROCESS CONTROL PROGRAM
NUMBER RP2.DC2REVISION 5PAGE 3 OF 6
5.2.4
5.2.5
5.2.6
LABORATORYMIXINGOF SAMPLES
Qualified vendor procedures reviewed by the PSRC and approved by thePlant Manager provide written instructions on sampling, processing and
handling waste for the determination of process parameters prior to the actualfull scale solidification. These procedures contain the description of thelaboratory mixing methods used for these samples.
SOLIDIFICATIONPROCESS
Qualified vendors used by DCPP for radioactive waste solidification are
required to provide the Process Control Program and written procedures.These procedures and changes thereto must be reviewed by the PSRC and
approved by the Plant Manager prior to use. Further, the vendors arerequired to have a topical report, as referenced, on the waste forms whichwillbe solidified at DCPP. This topical report should demonstratecompliance with the NRC requirements for waste form. These documentsshould include:
a. Description of the solidification process.
b. Type of solidification used.
c. Process control parameters.
d. Parameter boundary conditions.
e. Proper waste form properties.
Specific instructions to ensure the systems are operated withinestablished process parameters.
SAMPLING PROGRAM FOR SOLIDIFICATION
Vendors, utilized by DCPP for radioactive waste solidification, are requiredto include in their approved procedures, requirements to sample at least everytenth batch of the same waste type to ensure solidification and to provideactions to be taken ifa sample fails to verify solidification. After a testspecimen failure, initial test specimens from three consecutive batches of thatwaste type must demonstrate solidification before testing requirements ofevery tenth batch can be resumed. Verification of such sampling is to beaccomplished by completing Form 69-10350, "Processing Control Program(PCP) Verification." (See Attachment 7.1.) These forms willbe maintainedin the Radiation Protection Section and the Records Management System(RMS). These procedures and changes thereto must be reviewed by thePSRC and approved by the Plant Manager prior to use.
01180405.DOA tB 3 I 0806.0813
PACIFIC GAS ANDELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLEi PROCESS CONTROL PROGRAM
NUMBER RP2.DC2REVISION 5PAGE 4 OF 6
5.2.7
5.2.8
5.2.9
WASTE FORM VERIFICATION
Vendors utilized by DCPP to process wet wastes are required to include intheir procedures provisions to verify that the solidification and/or FSWCriteria in the Federal and State regulations and the Burial Site License aremet for the specific type of waste being processed.
CORRECTIVE ACTIONS FOR FREE STANDING WATER
Vendors utilized by DCPP to process wet wastes are required to include intheir approved procedures provisions for correcting processed waste in whichfree standing water in excess of the FSW Criteria is detected.
EXOTHERMIC PROCESSES
Vendors utilized by DCPP for radioactive waste solidification that utilize anexothermic solidification method are required to include in their approvedprocedures:
a. Waste/binder temperature monitoring to mitigate the consequence ofadverse exothermic reactions which may occur in the full scalesolidification but might not be noticeable in the specimen tests.
b. Specific process control parameters that shall be met before capping thecontainer.
5.3 OILYWASTE
Oily wastes at DCPP are processed in accordance with approved vendor procedures.These procedures specify the proper methods to treat oily wastes to comply withFederal and State regulations and applicable Burial Site License Criteria.
5.4 SPECIAL CASES
Based upon previous industry experience, DCPP foresees the potential for situationsarising that may be beyond existing plant capabilities. Anticipating this possibility,provisions are made herein to accommodate such situations in a timely manner by usingspecial techniques or processes. These special cases would be controlled as follows:
5.4.1 Implementing procedures would be developed comparable to those used fornormal plant solid waste activities based on the guidance of this PCP andincorporating the applicable provisions for process control and testing.
5.4.2 The implementing procedure would receive PSRC review and Plant Managerapproval prior to use.
5.4.3 Use of this provision and supporting infor'mation would be included in thenext Annual Effluent Report to the NRC.
01 i80405.DOA 1B 4 I 0806.08l3
PACIFIC GAS ANDELECTRIC COMPANYDIABLOCANYONPOWER PLANT
NUMBER RP2.DC2REVISION 5PAGE 5 OF 6
TH'LE: PROCESS CONTROL PROGRAM
5.5
5.6
REMEDIALACTIONS
5.5.1 For waste forms which do not meet Federal, State and burial site regulations
and requirements, suspension of shipment of the inadequately processed
waste and correction of the PCP, procedures or processing equipment shall
be performed as necessary to prevent recurrence.
5.5.2 For waste forms not prepared in accordance with the PCP, testing of the
waste to verify shipping and burial site requirements shall be performed and
appropriate administrative action taken to prevent recurrence.
VENDOR PROCEDURES AND REPORTS
5.6.1 The following are maintained in Document Control Master File, Catalog No.
TK 9400/MMT-1.
ao
b.
Molten Metal Technology of Tennessee, Inc., ProcedurePG01-PCP-05-001, Process Control Program for MMT-TNRadwaste
Solidification at Diablo Canyon Power Plant, Rev. 0
Topical Report TR402, 10 CFR 61 Qualified Radioactive Waste
Forms, Rev. 1
c. Molten Metal Technology of Tennessee, Inc., ProcedureMMT-P-01-035, "Temperature Indicating Device Comparison Test,"Rev. 0
d. Molten Metal Technology of Tennessee, Inc., ProcedureMMT-P-01-020, "Calibration for a Triple Beam Balance," Rev. 0
e. Molten Metal Technology of Tennessee, Inc., ProcedureMMT-P-01-024, "Penetrometer Check Procedure," Rev. 0
5.6.2 The following are maintained in Document Control Master File, Catalog No.TK 94001 DTI-1.
a.
b.
Diversified Technologies, Procedure DT-DCPP-10, PCP for VERISolidification, Rev 14
Topical Report DTI-VERI-100-NP-A. VERI (VinylEster Resin InSitu) Solidification Process for Low-Level Radioactive Waste, Rev 1
c. Diversified Technologies, Procedure QIP 20-17, pH Meter Calibration,Rev. 3
d. Diversified Technologies, Procedure QIP 20-18, Conductivity MeterCalibration, Rev. 2
01180405.DOA IB 5 I 0806.0813
PACIFIC GAS ANDELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: PROCESS CONTROL PROGRAM
NUMBER RP2.DC2REVISION 5PAGE 6 OF 6
6. RECORDS
e. Diversified Technologies, Procedure QIP-20-16, ThermocoupleCalibration, Rev 1
f. Diversified Technologies, Procedure DT-DCPP-VES-14, PCP for VESSolidification, Rev B.
g. Topical Report DNS-RSS-200-NP, The Dow Waste SolidificationProcess for Low-Level Radioactive Waste (Docket Number WM-82).
7.
8.
6.1 Records of PCP specimen results and Form 69-10350 shall be submitted to the Records
Management System on a shipment basis by container per RCP RW4.
ATTACHMENTS
7.1 Form 69-10350, "Process Control Program (PCP) Verification," 06/03/93
7.2 "Major Change to the Solid Radwaste Treatment System Evaluation," 06/03/93
REFERENCES
8.1 Title 10 Code of Federal Regulations.
8.2 NUREG 0472 and 0473.
8.3 NUREG-0800, 11.4 US NRC Standard Review Plan Solid Waste ManagementSystems.
8.4
8.5
8.6
8.7
8.8
RCP.DC3, "Dewatering Control Program."
RP2.DC4, "Mobile Service Operating Procedure for Low-Level Radioactive WasteProcessing."
NRC Information Notice 88-08, Chemical Reactions with Radioactive WasteSolidification Agents.
Molten Metal Technology of Tennessee, Inc., Quality Assurance Program DescriptionNo. 71-0870, Rev. 0.
Document Control Master File, Catalog No. TK-9400/MMT-3.
Technical Position on Waste Form, Revision 1, US NRC, January 1991.
01180405.DOA 1B' I 0806.0813
rt
69-10350 06/03/93DIABLOCANYONPOWER PLANT.
RP2.DC2
Page 1 of 1
TITLE: PROCESS CONTROL PROGRAM (PCP) VERIFICATION~1
WASTE BATCH PCPDATE
Number T)g)e Passed F I dNOTES OPERATOR
01180405.DOA 1B 7 I 0806.0813
06/03/93DIABLOCANYONPOWER PLANT
RP2.DC2ATTACHMENT7.2
Page 1 of 1
TITLE: MAJOR CHANGE TO THE SOLID RADWASTE TREATMENTSYSTEMEVALUATION
1. A summary of the evaluation that led to the determination that the change could be made inaccordance with 10 CFR 50.59;
2. Sufficient detailed information to totally support the reason for the change without benefit ofadditional or supplemental information;
3. A detailed description of the equipment, components and processes involved and the interfaces withother plant systems;
4. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and
gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the
License application and amendments thereto;
5. An evaluation of the change which shows the expected maximum exposures to a MEMBER OF THEPUBLIC in the UNRESTRICTED AREA and to the general population that differ from those
previously estimated in the License application and amendments thereto
6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluent and insolid waste, to the actual releases for the period prior to when the changes are to be made;
7. An estimate of the exposure to plant operating personnel as a result of the change; and
8. Documentation of the fact that the change was reviewed and found acceptable by the PSRC.
0118040S.DOA 1B 8 I 0806.0813
Attachment 7PG8E Letter DCL 99-055
Mobile Service Operating Proceduresfor Low-Level Radioactive Waste Processing
(RP2. DC4 Revision 9)
***ISSUED FOR USE BY:PACIFIC GAS AND ELECTRIC COMPANYNUCLEAR POWER GENERATIONDIABLO.CANYONPOWER PLANTADMINISTRATIVEPROCEDURE
DATE: EXPIRES:NUMBER RP2.DC4
REVISION 9
PAGE 1 OF 4
TITLE: MOBILESERVICE OPERATING PROCEDURES FORLOW-LEVELRADIOACTIVEWASTE PROCESSING
EFFECTIVE DATESPONSORING ORGANIZATION: RADIATIONPROTECTION
PROCEDURE CLASSIFICATION: QUALITYRELATEDREVIEW LEVEL: "A"
2.
SCOPE
1.1 This procedure discusses the use of Mobile Service equipment for the proper, safe andeffective processing and/or preparation of radioactive waste for disposal.
DISCUSSION
2.2
RESPONSIBILITIES
2.1 This procedure contains the individual Operating Procedures necessary to operate themobile processing and solidification equipment.
The processing conditions necessary to assure that packaged radioactive wastes meet thevarious governmental and Burial Site Facility Waste Form requirements are addressedin RP2.DC2, "Process Control Program."
3.1
3.2
The Mobile Service Contractor is responsible for:
3.1.1 Setup of the processing equipment,
3.1.2 Operation of the processing equipment,
3.1.3 Dismantling of the processing equipment.
Radiation Protection is responsible for:
3.2.1
3.2.2
Performing surveys on the equipment prior to receipt,
Assuring that the DOT requirements have been met prior to the release of theequipment.
3.3 The Radwaste Engineer is responsible for:
3.3.1 Assuring the most current revisions of the Operating Procedures are on file,
3.3.2 Assuring that the requirements (ifany) for effluent monitoring have beendiscussed with the Chemistry Engineer for radioactive effluents and theimplementation of such requirements is conducted.
3.4
3.5
The Chemistry Engineer for radioactive effluents is responsible for evaluating andreporting effluents from mobile low-level radwaste processing equipment in the AnnualEffluent Report as necessary.
NQS is responsible for the verification that operations have been conducted inaccordance with the appropriate Operating Procedures.
RP2DC4.DOC 18 1
0
PACIFIC GAS AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: MOBILESERVICE OPERATING PROCEDURES FORLOW-LEVELRADIOACTIVEWASTE PROCESSING
NUMBER RP2.DC4REVISION 9PAGE — 2 OF 4
Changes to the dewatering and solidification procedures contained herein due to changes inequipment which would affect any waste form parameters require submission to the US NRC inthe Annual Effluent Report for the period in which the changes were made.
INSTRUCTIONS
Follow the appropriate steps in the individual Operating Procedures as listed below:
5.1 Liquid Waste Processing
NOTE: Copies of the following procedures are maintained in Document ControlMaster File, Catalog No. TK-9400/DTI-3.
5.1.1 Diversified Technologies, Procedure DT-DCPP-01, WPS WasteProcessing, Rev. 0.
5.1.2 Diversified Technologies, Procedure DT-DCPP-02, WPS Adding Media,Rev. 0.
5.1.3 Diversified Technologies, Procedure DT-DCPP-03, WPS Sluicing Media,Rev. 0.
5.1.4 Diversified Technologies, Procedure DT-DCPP-04, WPS Leak Check,Rev. 0.
5.1.5 Diversified Technologies, Procedure DT-DCPP-08, RO-NF Operations,Rev. 0.
NOTE: A copy of the following procedure is maintained in Document Control MasterFile, Catalog No. TK-9400/SEG-2.
5.1.6 Molten Metal Technology of Tennessee, Inc., Procedure PG01-P-10-001,Procedure For Processing Sluice Water In A NUHIC-80B or Resin ExpressContainer at Diablo Canyon, Rev. 0.
NOTE: A copy of the following procedure is maintained in Document Control MasterFile, Catalog No. TK-9400/CNS-3.
5.1.7 Chem Nuclear Systems, Inc., WI-CNSI-96-020, Work Instruction forLoading a CNS-21-300 Thermex Liner at PG&E Diablo Canyon PowerPlant, Rev. 0.
5.2 Dewatering
NOTE: Copies of the following procedures are maintained in Document ControlMaster File, Catalog No. TK-9400/SEG-2.
5.2.1
5.2.2
Scientific Ecology Group, Inc., Procedure DW-008, Dewatering Procedurefor 182 Ft3 Liners at Diablo Canyon Power Plant, Rev. D.
Molten Metal Technology of Tennessee, Inc., Procedure PG01-P-06-001,"Transfer and Dewatering Activated Carbon and/or Bead Resin at DiabloCanyon for Offsite Processing," Rev 0.
RP2DC4.DOC 18 2
PACIFIC GAS ANDELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: MOBILESERVICE OPERATING PROCEDURES FORLOW-LEVELRADIOACTIVEWASTE PROCESSING
NUMBER RP2.DC4REVISION 9PAGE 3 OF 4
5.2.3
5.2.4
5.2.5
5.2.6
5.2.7
5.2.8
Molten Metal Technology of Tennessee, Inc., Procedure PG01-P-03-001,Procedure for Dewatering Bead Resin, Filter Sludge, Zeolites, or CarbonMedia with the MMT-TNDewatering System at Diablo Canyon, Rev. 0.
Scientific Ecology Group, Inc., Procedure HC-001, Procedure for Using theSEG Barrier-Plus High Integrity Container, Rev. 4.
Scientific Ecolog Group, Inc., Procedure HC-002, Procedure for Sealingthe Barrier Plus High Integrity Container for DCPP, Rev. 0.
Scientific Ecology Group, Inc., Procedure DC-P-03-002, Procedure ForFilter Packaging Using the HIC Overpack Assembly at Diablo Canyon,Rev. 0.
TFC Nuclear Associates, Inc., Procedure For Handling and Storage of HighIntegrity Containers, Rev. 4.
TFC Nuclear Associates, Inc., Procedure For Sealing High IntegrityContainers, Rev. 4.
NOTE: The following manual is maintained in Document Control Master File,Catalog No. TK-9400/SEG-2A.
5.2.9 Scientific Ecology Group, Inc., Rad Services Manual for RADLOKHighIntegrity Containers, RSM-014, Rev 0.
5.3 Solidification
NOTE: Copies of the following procedures are maintained in Document ControlMaster File, Catalog No. TK-9400/SEG-2.
5.3.1 Scientific Ecology Group, Inc., Procedure SS-039, Setup/Removal ProcedureFor SEG Radwaste Solidification System No. 8960 for use at Diablo CanyonPower Plant, Rev. D.
5.3.2 Scientific Ecology Group, Inc., Procedure SS-038, Operating Procedure forSEG Radwaste Solidification System No. 8960 for use at Diablo CanyonPower Plant, Rev. E.
5.3.3
5.3.4
Scientific Ecology Group, Inc., Procedure SS-054, Procedure for Using theL-80GE Filter Encapsulation Liner at Diablo Canyon, Rev. 0.
Scientific Ecology Group, Inc., Procedure SS-040, Contamination BibInstallation/Removal, Rev. C.
5.3.5 Scientific Ecology Group, Inc., Procedure SS-041, Procedure for RemoteLid Closure, Rev. C.
NOTE: Copies of the following procedures are maintained in Document ControlMaster File, Catalog No. TK-94001 DTI-2.
5.3.6 Diversified Technologies, Procedure DT-DCPP-09, Waste Transfer, Rev. 9.
5.3.7 Diversified Technologies, Procedure DT-DCPP-11, Filter Loading, Rev. 9.
RP2DC4.DOC 18 3
PACIFIC GAS AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT
TITLE: MOBILESERVICE OPERATING PROCEDURES FORLOW-LEVELRADIOACTIVEWASTE PROCESSING
NUMBER RP2.DC4REVISION 9PAGE 4 OF 4
5.3.8 Diversified Technologies, Procedure DT-DCPP-12, Media Treatment,Rev. 11.
5.3.9 Diversified Technologies, Procedure DT-DCPP-13, VERI Solidification,Rev. 15.
5.3.10 Diversified Technologies, Procedure DT-DCPP-15, VES Solidification,Rev. B.
5.4 Dry Active Waste Processing
NOTE: The following procedure is maintained in Document Control Master File,Catalog No. TK-9400/SEG-2.
Scientific Ecology Group, Inc., Procedure DC-P-28-001, Procedure for using the SEGBarrier Plus ™Container with Foam Lining at Diablo Canyon, Rev. A.
'ECORDS
Records of dewatering and solidification operations shall be submitted to the Records ManagementSystem on a shipment basis by container per RCP RW-4.
7. REFERENCES
7.1 Scientific Ecology Group, Inc., Quality Management System Manual, Rev. 5,Document Control Master File, Catalog No. TK-9400/SEG-3.
7.2 RP2.DC2, "Process Control Program."
7.3 RP2.DC3, "Dewatering Control Program."
7.4 Diversified Technologies, Procedure QIP 20-09, Operator Training Procedure, Rev. 1.
SPONSOR
C. Clint Miller
RP2DC4.DOC lB 4
Attachment 8PG8 E Letter DCL 99-055
1998 Land Use Census
DCPP Radiation Protection personnel conducted a land use census in the vicinity of
DCPP for 1998. The land use census is based on Nuclear Regulatory Commission
(NRC), Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear
Power Plants", and required by DCPP Program Directive CY2, "Radiological
Monitoring and Controls Program." The census is conducted at least once per year
during the growing season for the Diablo Canyon environs.
The land use census identifies the nearest milk animal and garden greater
than 50 square meters (500 square feet), producing broadleaf vegetation, in each ofthe landward meteorological sectors within a distance of 8 kilometers (5 miles) of the
plant. DCPP IDAP RP1.ID11 "Environmental Radiological Monitoring Program",
requires that the nearest residence be identified in each of the landward sectors
within a distance of 5miles.'he
land use census was performed by directly contacting individual landowners or
tenants, or by aerial surveys. The landowners or tenants were contacted between
July 7 and August 31, 1998. The aerial survey was done on August 5, 1998.
The census identified one household garden in the east sector at 4.5 miles, greaterthan 50 square meters (500 square feet) that produces broadleaf vegetation. No
milk animals were identified within the first 5 miles in any sector. Much of the area
surrounding the plant site is used for cattle grazing. Goats were used for weed
abatement for approximately 7 months within the area surrounding the plant site. Afarm is located on the coastal plateau in the east southeast (ESE) sector, along the
site access road. The farm starts at approximately 3.3 miles and extends to 4.5
miles from the plant, but produces only legumes and cereal grass (grains).
A total of 13 residences were identified within the 5-mile radius of the plant that were
confirmed to be, or appeared to be, occupied during 1998. The nearest residence is
1.2 miles north-west (NW) of the plant. Table 1 summarizes the results of the land
use census and Figure 1 shows the locations of the farm and residences in the
vicinity of DCPP.
Attachment 8PG8 E Letter DCL 99-055
Table 1
Land Use Census
Distance in Miles from the Unit 1 Center Line to theNearest MilkAnimal, Residence, Vegetable Garden
2p/'egree(a) Nearest Nearest
Radial Sector MilkAnimal Residencekm (mi)
ResidenceAzimuthDegree
NearestVegetable
Gardenkm (mi)
NW None 1.93 (1.2) 319.5 None
NNW None 2.41 (1.5) 331 None
None None None
NNE
NE
ENE
None
None
None
None
5.3 (3.3)
7.89 (4.9)
7.08 (4.4)
5.95 (3.7)
018.5
036
063.5
097.5
None
None
None
None
ESE
SE
None
None
None
7.24 (4.5)
None
None
098 7.24 (4.5)
5.28(3.3)"'one
Table Notation:
Sectors not shown contain no land beyond the site boundary, other thanislets not used for the purposes indicated in this table.
'" The vegetable garden indicated is the farm along the site access road; however,it does not grow broadleaf vegetation.
To Monterey To Paso Robics
CAYUCOS ~ ATASCADERO
MORRO BAY
~ SANTAMARGARITA
NW
NNW
A
Osp so NE
eV+o ENE
C n.Rd.pre<+
SAN LUIS OBISBO
A
PacificOcean
UNITS 1 AND 2DIABLOCANYON SITE
0 Gardens or Farm
A Residences
5 Mile
ESE
0+
e~+
.g+ SE
@0co
0 1 2 3 4 5
SCALE IN MILES
8~~~0,
GROVER ~reCITY <e
Figure L Units 1 and 2 Diablo Canyon Power Plant-Land Use Census.
970338/landuso/pc19
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