... __._. . _ _ _ _ _ _ _ .

~ ' _,.

'.

'

EPIP-11Page 1 of 401-31-80

@-

VIRGINIA ELECTRIC AND POWER COMPAhTNORnl ANNA P0b7.R STATION f

ESTIMATING REI. EASE FROM RADIATION MONITORING SYSTEM DATA

1.0 Operations Response

2.0 Heal h Physics Response

Appendix 1, Significance and Evaluation of Release EstimatesBased on Radiation Monitoring System Data

Appendix 2, Black Forms EPIP 11.1, RMS Relea.e Data Worksheet

Appendix 3, Procedure for Determining Release Rates and Doses RatesUsing High Range Effluent Mocitors

.

NOT A CONTROREDDOCUMENT

F B 3 51980~

NOR NECESSARILY THEMTEST REylsicN

-

, '! fV 880fRECOMMEND APPROVAL:APPROVED BY: -l $ %

CHAIRtCTATION NUCLEAR SAFETY'

AND OPERATING CCMMITTEE

d> L -.:Q 7 977' I7 DATE:01-31-80GL.:.7 7 m'['*.p)u1*L .!. .u

,

8002 290387

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...

EPIP-11Page 2 of 401-31-80

ESTIMATING RELEASE FROM RADIAT!ON MONITORING SYSTEM DATA

1.0 Overations Response

1.1 Obtain, from Appendix 2 of this procedure, a FORM EPIP 11.1,

"RMS Release Data Worksheet".

NOTE: IF LOW RANGE !"ONITORS ARE OFT SCALE THEN TO D3TERMINE .RELEASE RATES AND/OR DOSE RATES USING THE HIGH RANGEEFFLL'ENT MONITORS, REFER TO APPENDIX 3. OPERATIONSSHOULD IMMEDIATELY POST AN INDIVIDUAL TO RECORD DATA ONA FIVE !iINUTE FREQUENCY USING THE APPROPRIATE HIGHRANGE RADIATION MONITOR. FOLLCWING THE INS" RUCTIONS INAPPENDIX 3, CALCULATE THE RELEASE RATES.

1.2 Gotain the count rate of the monitor of interest from the

radiation system panels as appropriate, and enter the monitor

type (or number) and the count rate in CPM which is to be

evaluated on FORM EPIP 11.1.(

NOTE: Refer to last PT-37 for background subtraction, priorto calculating release data.

1.3 Obtain from Table EPIP 11.1, " Response of Potential Release

Path Radiation Monitors", the Ci per Hr Released per CIM value

and the Selected Flow Rate for each monitor of interest and

enter on FORM EPIP 11.1.

1.4 Obtain, by appropriate methods, the flow rate of the path being

monitored (in the same units as entered on FORM EPIP 11.1) and

enter on FORM EPIP 11.1. If this is not practical or desired,

a " default" value equal :o the Selected Flow Rate (design) may

be used.

1.5 Perform the indicated math to obtain the gross curies of ac-

tivity indicated as being released per hour. The total amount

of activity released can then be estimated based on the knowns

or expected time durar. ion of the release.

-. _ _ _

_

,

'

.

EPIP-11Page 3 of 401-31-80

.

1.0 Operations Response

1.6 Use these results for preliminary evaluation, forward the

completed FORM EPIP 11.1 to HP for use in determining the need

for further monitoring. The release data to initiate any

offsite action will come from hP on a FORM EPIP 2.1.

2.0 Health Physics Response

2.1 If a release point has a continuous in line radiation sampler

(such as process or ventilation) vent, remove the filter (s)

and/or obtain a sample (s) and count using the appropriate count

room equipment.

2.2 If the filter removed or the sample taken will affect the

routine records of the Power Stations radioactive effluents,

( use the appropriate Release Pecord as described in the 3.2

series of HP Procedures concerning radioactive waste and cal-

culate the release accordingly.

2.3 Based on the information shown on FORM EPIP 11.1, determine the

need for obtaining additional samples or other monitoring.

.

%.

.-

.

.*

EPIP-11'

Page 4 of 401-31-80

.

.

TABLE EPIP 11.1

RESPONSE OF POTENTIAL RELEASE PATH RADIATION MONITORS

REFERENCE pCi/ml SELECTED Ci ner Hr ReleasedMONITOR * NUCLIDE CPM FLOW RATE CPM

SGBD Cs-137 3.3 E-7 67 GPM 5.0 E-6

DsTun Cs-137 3.3 E-8 985800 GPM 7.5 E-3

CCWSW Cs-137 2.9 E-7 13000 GPM 8.7 E-4

RSCSW Cs-137 4.0 E-7 4500 GPM 4.1 E-1

SW Cs-137 2.9 E-7 23000 GPM 1.5 E-3

Clf D Cs-137 2.0 E-7 300 GPM 1.3 E-5

PVG Xe-133 9.1 E-7 310 CFM 4.8 E-4

PVP Cs-137 7.7 E-13 31C CFM 4.1 E-10

VAG Xe-133 9.1 E-7 143900 CFM 2.2 E-1

VAP Cs-137 7./ E-13 143900 CFM 1.9 E-7

V3G Xe-133 3.0 E-8 108700 CFM 5.5 E-3

V3P Cs-137 1.2 E-12 108700 CFM 2.2 E-7

CAE Xe-133 2.9 E-2 25 CFM 1.3 E+0- _ ___ _ __ _

*SGBD - Steam Generator Blowdown: SS-122, 123, 123, 222, 223, 224

DsTun - Discharge Tunnel Liquid: SW-130, 230.

CCWSW - Cocrponent Cooling Water Ex Service Water: SW-107.

RSC1 'ecire. Spray Cooling Service Water Outlet: SW-124, 125, 126,127, 224, 225, 226, 227.

SW - Service Water Discharge: SW-108. .

Clf D - Clairfier Discharge: LW-lll.

PVG - Process Vent Radiogas: GW-102.

PVP - Process Vent Air Particulate: GW-101.

VAG - Ventilation Vent A Radiogas: VG-104.

VAP - Ventilation Vent A Air Particulate: VG-103.

VBG - Ventilation Vent B Radiogas: VG-ll3.

V3P - Ventilation Vent 3 Air Particulate: VG-112.

C.E - Condenser Air Ej ector Radiogss: SV-121, 221.

.

. .

*EPIP-11Appendix 1Page 1 of 201-31-80

-

ESTIMATING RFTFASE FROM RADIATION MONITORING SYSTEM DATA

APPENDIX 1

SIGNITICANCE AND EVALUATION OF RELEASE ESTIMATESBASED ON RADIATION MONITORING SYSTEM DATA

Part Subject

1.0 Consideration on the RMS

( 2.0 Estimating Release of Airborne Activity Exceeding Monitor'sk Range

s

. .

: .-'

*

EPIP-11-

Appendix 1Page 2 of 201-31-80

-

1.0 Considerations on the RMS

The detectors in the RMS respond to gross activity and for this

reason the response of the monitor must be interpreted using know-

ledge of the system involved. For instance, liquid monitors will

detect any gamma emitters, which includes dissolved radiogases which

do not necessarily present the radiation hazard the monitor could be

implying.

Air particulate monitors have detectors which are NaI scintillation

devices and therefore count essentially only gamma enitting parti-

cles. It should not be assumed radioiodines car,be collected and

counted on the filter paper. Air radiogas monitors have relative

2thick (30 mg/cm ) walled G-M detectors, and therefere have a much

lower ef ficiency for weak beta emitters , for instance the Xe-133

( cpm / Ci is more than 10 less than that for Kr-85.

The electronics used in the RMS are designed in a maaner which should

prevent a meter from reading low even if that channel's G-M detector

is in continuous discharge.

2.0 Estimating Release of Airborne Activitv Exceeding Monitor's Range'

If activity collected by the monitor results in full scale reading

tue activity released can be estimated by count room methods as

described in Step 2.0 of this procedure or if a quick estimate is

considered essential the following method may be used.

Measure the dose rate one foot from the actual collection point of

the monitor. Esticate the curies released using the following

equation.

Ci = 0.00624 x ER CFM of Monitored Pathxbr CFM of Sacpling Rate

-

.__ _

.

'

EPIP-11-Appendix 2Page 1 of 201-31-80

ESTIMATING RELEASE FROM RADIATION MONITORING SYSTEM DATA

APPENDIX 2

BLANK FORMS EPIP 11.1

R".S PFLEASE DATA '40RKSHEET

__ -

,*

. ,

, -

' EPIP-11Appendix 2Page 2 of 2Form EPIP-11.101-31-80

RMS RELEASE DATA WORKSHEET

Date/ Time:

Ci per HrRELEASED SELECTED ACTUAL Ci per Hr

MONITOR CPM CPM FLOW RATE FLOW RATE RELEASED

: X X ='

: X X ='

: X X ='

_ X X ='-

: X X ='

: _ X X ='

Ci per Hr Estimated or Known Estimated CuriesReleased Number of Hours of Release Released

X

X

X

X

X

X

NOTE: Refer to last 7-37 for background subtraction, prior to calcula-ting release data.

-.

' EPIP-11Appendix 3Page 1 of 1901-31-80

ESTIE\ TING REI. EASE FROM RADIATION MONITORING SYSTEM DATA

APPE:QIX 3

ESTIMATING RELEASE AND/OR DOSE RATES FROMHIGH RANGE RADIATION EFFLUENT MONITORS

Part Subject

1.0 Determing 'n' hole Body Dose Using Kr-85Equivalent

k

.

h "*

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-.

.,,

EPIP-11Appendix 3Page 3 of 1901-31-80

CUTLINE OF THE PROCLFTRE FOR DETERMININGREIIASE RATES AND D0fi RATES DURING THE

INTERIM HIGH RANGE EFFLUENT MONITORS

The following is for determining the whole body gamma dose using a Kr-85equivalent.

1. Concentration (pCi/ce)

The concentration in the effluent stream is determined as a Kr-85equivalent. A graph is utilized which displays dose rate (MREM /Hr)vs Kr ',5 equivalent concen- cation (pCi/cc) . The Kr-85 equivalentconcentration is read directly from the graph at the point on thecurve corresponding to the dose rate reading from the monitor.(Table I lists the figures and their appropriate application.)

2. Flow Rate (cc/Sec)

See procedure in Section 2.

3. Release Rate (pCi/Sec)

The release rate is calculated by =ultiplying the concentration (pCi/ce),determined in Section 1, by the flow rate (cc/sec), determined in-,

(_ Section 2. This is the release rate of Kr-85 equivalent.

R = Releasif Rate (pci/sec) Kr-85 equivalent

C = Concen: ration (pCi/ce) Kr-85 equivalent

F = Flaw Rate (cc/sec)

R = CF

pCi/ rec = pCi/cc x cc/sec

4. Whole Body Gamma Dose Rate (nREM/Hr)

The dose rate at any location may be calculated using the release rate(pCi/sec) of Kr-85 equivalent from Section 3, the dose rate conversionfactor for Kr-85, and the X/Q for the location of interest- from currentMET data. The dose rate is calculated as follows, where

D = Dose Rate (= REM /Hr)

X/Q - Atmospheric Diffusion Factor (sec/M ) = 2.0 x 10 '~

K = Cose Rate Conversion Factor for Kr-85 = 1.8 x 10~ MREM /ErpCi/M~

R = Release Rate 'rCi/sec) (see 3 above)s

. _ _ _ _

_

-.

'

.

EPIP-11Appendix 3Page 4 of 1901-31-80

-

D = K x R x X/Q~

D = 1.80 x 10 R X/Q

MREM /Hr = MREM-M x pCi x secHr-pCi see M"

2. Flow Rate Conversion (cc/sec)

A. Main Steam Lines ,F, = m (2.8317 x 10")

p 3600

where:

F = Volume Flow Rate Main Steam, cc/sec

M = Mass Flow Rate Main Steam, LBM/Hr (see Table 2)

P = Density of fluid (main steam @ Sgeam t neratortemperature and pressure) LBM/FT = 2.3625 @ 1050psia

B. Vent Stacks and Process Vents4F = SCFM x (2.8317 x 10 )s .

eos,

where:

F, = Volume Flow Rate of Gas, cc/see

SCFM = Measured volume flow rate of gas at std. conditions(NOTE: difference between actual and std. con-ditions are negligible), SCFM (see Table 2)

NOTE: Due to the shielding effect of the main steam safetyvalve riser pipe thickness, the detector response toXe-133 will significantly under estimate the po'.m - 'al.offsite dose due to Xe-133. However, for relief valveoperations immediately af ter reactor trip, this willnot significantly effect the accuracy of the totalpotential whole body dose projection.

(

.. . _ _ _ . _ _

-.

.

.

EPIP-11Appendix 3Page 5 of 1901-31-80

TABLE 1

LIST OF FIGURES

FIGURE 1 - Unit 1 - Main Steam Safety Line 32"-SHP-22, RM-MS170

FIGURE 2 - Unit 1 - Main Steam Safety Line 32"-SHP-23, RM-MS171

FIGURE 3 - Unit 1 - Main Steam Safety Line 32"-SHP-24, RM-MS172

FIGURE 4 - Units 1 & 2, Process Vent, RM-GE 73Units 1 & 2, Vent Stack A, RM-VG174l'rti * a 1 & 2, Vent Stack B, RM-VG175

FIGURE 5 - Unit 2 - Main Steam Safety Line 32"-SHP-422, RM-MS270

FIGURd 6 - Unit 2 - Main Steam Safety Line 32"-SHP-423, RM-MS271

F. CURE 7 - Unit 2 - Main Steam Safety Line 32"-SHP-424, RM-MS272

s

.. . ,, . . . - . . -

-

..,

EPIP-11Appendix 3Page 6 of 1901-31-80

TABLE 2

FLOW RATE DETERMINATION

Source of Flow Min. Flow for Accurate Ref.Monitor Service Measurement Measurement (MF) Notes

RM-MS 170 Main Steam Safety ET-1474 30% Llov* 1, 2Line (32"-SHP-22)

RM-MS 172 Main Steam Safety FT-1484 30% Flow * 1, 2Line (32"-SHP-23)

RM-MS 172 Main Steam Safety FT-1494 30% Flow * 1, 2Line (32"-SHP-23)

RM-GW 173 Process Vent FT-GW 108 100 cfm* 1, 3

RM-VG 174 Vent Stack A l'"-HV 1212A 100,000 cfm 1, 4

RM-VG 175 Vent Stack B FT-HV 1212B 80,000 cfm I, 4

Notes:* or as determined by operating data

( 1. If flow rate indicated is less than minimum flow fcr accurates measurement (MF), the flow must be determined using the methodsoutlines in Notes 2 through 4, as applicable, or a flow of MFmay be assumed.

2. Based on values determined open by inspection for a givenperiod of time, determine total flow using design flow rates of855,084 lb/hr for each safety valve, 690,000 lb/hr for eachatmospheric steam dump valve (PCV-MS 101A, B, C), and 181,000lb/hr for the decay heat release valve (HCV-MS 104)

3. An evaluation of paths open to process vent must be performedto determine total flow.

4. Based on fans operating, determine total flow based on thefollowing design flows:

Fan Area Design Flow (Cfm each_)_

HV-F-5A, B Reactor Containment Purge 11,000

HV-F-7A, B Fuel Building 17,500

HV-F-8A, B, C Aux. Building, Central' Area 20,200

HV-F-9A. B, C Aux. Building, General Area 24,700

. HV-F-40A, B Safeguards ?.rea 12,700

HV-F-56A, B Decontamination Building 13,150

_ . - - . -- -

- -,

:.

.*

EPIP-11Appendix 3Page 7 of 1901-31-80

TABLE 2Continued

FISPONSE

Each steam generato. is protected with five safety valves as follows:

Capacity, each Capacity, each Set PressureMark No. Set Press at Set Press at 1,135 Psig Tolerance

SV-MS101A,B,C 1,C85 817,883 855,084 ! 1%

SV-MS102A,B,C 1,095 825,323 855,084 1%

SV-MSIO3A,B,C 1,110 836,483 855,084 1 1%

SV-MS104A,B,C 1,120 843,924 855,084 1%

SV-MS105A,B,C 1,135 855,084 855,084 1 1%

Actual Total capacity for 5 valves - 4,275,420 lb/hr

Required total capacity for 5 valves - 4,252,439 lb/hr

Excess capacity - 22,981 lb/hr

.

.

- . EPIP 11*FIGURE 1 p3ge a of 13

01-31-80' NIT 1 MAIN STEAM SAFETY LINE 32" - SHP -22 P& MS170 t

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-

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.

s

EPIP 11'FICURE 1. Page 9 of 13

(continued) 01-31-60

UNIT 1 MAIN STEAM SMm LINE 32" - SHP-22 RM-MS170. - - 2 - - ____.____,2

---t-. ,.a%, -s . _ - - a.. .._qu . - r 7 ____3L 1 - r - _. t -_- -- y'"---:7n_ _ - . - - -3

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. . ___ . _ _ _ _ ._-.._: " . ~ _ _ _ = = = 2

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