'Reactor Containment Bldg Integrated Leak Rate Test.' · 2VC5 was exposed to t~e containment test...

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REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST FOR PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM UNIT II

PURPOSE

The purpose of this report is to vresent a description and analysis of the Third Period, Fi~st Interval, Reactor Containment Building Integrated Leak Rate Test (CILRT) conducted on Public Service Electric and Gas Company Salem Nuclear Generating Station Unit II Containment during the 6th

·refueling outage.

T~is report is submitted as required by 10-CFR-50, Appendix J, paragraph VB.

2.0 REFERENCES

1. 10-CFR-50 Appendix J - Primary Reactor Containment Leakage Testing for Water-cooled Power Reactors, January 1, 1990.

2. ANSI N 45.4 (1972) - Leakage Rate Testing of Containment Structures for Nuclear Reactors (Technical Specifications commitment)

3. ANSI 56.8 (1987) - Containment System Leakage Testing Requirements.

4. PSE&G Nuclear Site Services Department Procedure S2.SS-IS.ZZ-0005(Q) Reactor Containment Building Integrated Leak Rate Test (Type 11 A11 Test) Salem Unit II.

5. Salem Unit II Technical Specification 4.6.1.2 (a), ( b) , and ( c) .

3.0 LIST OF ATTACHMENTS

1. Attachment 17 of S2.SS-IS.ZZ-0005(Q) 11 A11 Test log of events.

2. Attachment 24 of S2.SS-IS.ZZ-0005(Q)· Weather prior to and during the 11 A11 Test.

3. Containment gas release permit.

4. PSE&G Research & Testing Laboratory repor~~

5 . Type II B II & II c II running summary.

Salem unit Ir Page 1 of 11

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4.0 SUMMARY OF TEST

The Containment Integrated Leak Rate Test (CILRT) was directed and coordinated by the Inservice Inspection Department (ISI) and performed in accordance with PSE&G Nuclear Site Services D~partment Procedure S2.SS-IS.ZZ-0005 (Q), Reactor Building Containment Building Integrated Leak Rate Test - Salem Unit II. The CILRT is divided into the following:

4.1

4.1 Preparation

4.2 Pressurization

4.3 Stabilization

4.4 Test Period

4.5 Depressurization

4.6 Restoration

PREPARATION

a. The test log, Attachment 17 of S2.SS-IS.ZZ-0005(Q), commenced on 2/21/92 at 0915 to record events of the CILRT .

b. A temporary pressurization facility was established IAW Attachment 16 of S2.SS-IS.ZZ-0005(Q), which consisted of portable Atlas Copco diesel driven air compressors. The air compressors supplied·l00% oil free air a~ 58-100 PSIG. The air compressors discharged through an af tercooler and air dryer to supply the containment with clean dry air for pressurization.

c. A temporary enclosure was erected in the 78' Electric Penetration area to house the Data Acquisition Center to maintain electronic and computer equipment within desired calibrated temperature range.

d. A temporary CILRT Command Center was established in the Salem Quality Assurance Conference room. This site was chosen because of its central location in the plant which provided easy access to the Control Room, Auxiliary Building and Containment.

e. Temporary telephone communications were established between the Pressurization Facility, Data Acquisition Center and CILRT Command Center located on elevation 113' in the SQA conference room .

Salem Unit II Page 2 of 11

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4.1 PREPARATION - Continued

f. The ISI department performed a general inspection of the accessible interior and exterior surfaces of the containment IAW Attachment 19 of S2.SS-IS.ZZ-0005(Q). The Inspection of the exterior surf ace was satisfactory with no indications found. The Inspection of the interior surface revealed indications of minor corrosion on the liner located on the 78' el. A deficiency report was initiated by the ISI Group IAW Nuclear Department Administrative Procedure NC.NA-AP.ZZ-0020, Nonconformance Program, and was evaluated by the Technical Department System Engineer. The disposition referenced Engineering Evaluation S-2-ZZ-SEE-0676-0. The identified condition does not constitute a deficiency and no immediate actions are required.

g. Weather conditions were monitored for approximately three days prior to and during the CILRT IAW Attachment 24 of S2.SS-IS.ZZ-0005(Q). Weather conditions for the performance of the CILRT were excellent.

The following temporary modifications and valve lineup were performed IAW Site Services procedure S2.SS-IS.ZZ-0005(Q) for the performance of the Type A Test .

h. The Operations department performed the valve lineup for the CILRT IAW Attachment 2 of S2.SS-IS.ZZ-0005 (Q). This included administrative control of valves out of their normal position by clearing and tagging IAW Nuclear Department Administrative Procedure NC.NA-AP.ZZ-0015, Safety Tagging Program. The valve lineup and tagging was performed to ensure all tested components were vented to the containment atmosphere and subjected to post accident differential pressure IAW 10CFR50 APP.J, Section III.d for the Test. The Operations department performed a second verification of all tagged components.

In addition, the ISI department performed an independent verification of the valve lineup IAW Attachment 2 of S2.SS-IS.ZZ-0005(Q).

During the clearing and tagging of 22 Control Air Header IAW Attachment 2 of S2.SS-IS.ZZ-0005(Q), control of the containment fan coil units service· water outlet flow control valves, 21, 22, 23, 24 and 25SW223 was lost. After evRluation of the situation by the Test Director, which included input from System Engineering, the Test Director de~ided to perform a limited revision to the Test Procedure which allowed the 22 Control Air Header to remain inservice outside the containment in the mechanical


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penetration area during the test to ensure adequate control of service water fo~ proper CFCU's operation.

This was a deviation of the normal CILRT valve lineup and removed penetration #23 and #56 from the Test. A penalty was taken for these penetrations in Attachment 17 Section 6.3. This revision provided instruction for the new valve alignment with the · addition of Attachment 33 to ensure there would be no in leakage of air into the containment during the CILRT.

The Maintenance Department performed the following temporary modifications:

1. Temporarily modified. containment penetration # 20 (2VC5 and 2VC6) !AW Attac~ment 3 of S2.SS-IS.ZZ-0005'(Q) to provide a flow path from the Pressurization Facility to the containment building for pressurization and a flow path from the containment building to the atmosphere to for depressurization. ·

A penalty was taken for penetration #20 (2VC5 & 2VC6) and incorporated into the measured CILRT result due to not being aligned in the required test position. This penalty was conservative because 2VC5 was closed and vented once the containment was pressurized to CILRT pressure. 2VC5 was exposed to t~e containment test volume and any leakage was measured in the actual CILRT results.

2. Blocked open 2PR1 & 2PR2, !AW Attachment 3 of S2.SS-IS.ZZ-0005(Q), which provided a vent path to the Reactor Coolant System Pressurizer and vented the Pressurizer Relief Tank by removing one of two pressurizer relief tank rupture disks.

3. Adjusted the CFCU's inlet guide vanes from their normal setting to 25 degrees open IAW Attachment 4 of S2.SS-IS.ZZ-0005(Q), to prevent motor overcurrent and tripping of CFCU's during test pressure conditions due to high air density.

j. The Instrumention·and Control/Electrical (I&C) support group performed the following temporary modifications:

1. Blocked open containment isolation valve 2VC6 !AW Attachment 5 of S2.SS-IS.ZZ-0005(Q), by the


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use df a mechanical blocking device on the actuator. This prevented 2VC6 from failing to the closed position due to loss of control air once the control air system was cleared and tagged for the CILRT valve alignment. This was required due to 2VC6 being in the pressurization flow path.

2. Installed a temporary N2 supply to the 2VC5 actuator IAW Attachment 5 of S2.SS-IS.ZZ-0005(Q). This prevented 2VC5 from failing to the closed position due to loss of control air once the control air system was cleared and tagged for the CILRT valve alignment. This was required due to 2VC5 being the control valve in the pressurization and depressurization flow path. The method of installation allowed the Control Room to maintain

·control of the 2VC5.

3. Vented various lighting fixtures IAW Attachment 5 of S2.SS-IS.ZZ-0005(Q) to prevent them from being damaged .during the CILRT.

4. Installed amperage recorders on the containment fan coil unit breakers to record current demand during CILRT IAW Attachment 5 of 52.SS-IS.ZZ-0005 (Q) .

k. The Site Protection Fire Department installed jumpers to block the fire alarms on the reactor coolant pumps and CFCUs IAW Attachment 10 of S2.SS-IS.ZZ-0005(Q), This modification enabled all other fire alarms within the same group to remain operable during the CILRT.

Equipment located within the containment, protected by fire suppression systems made inoperable for the CILRT valve lineup and not needed during the CILRT, were made inoperable by clearing and tagging to prevent operation.

1. The Radiation Protection Department installed a portable radiation monitor IAW Attachment 12 of S2.SS-IS.ZZ-0005(Q), to monitor the containment air that was released during the depressurization of the containment.

m. The Research and Test Lab monitored, collected and analyzed the CILRT data. The ·Research and Test Lab performed the setup and installation of the Data Acquisition center in accordance with Research and Test Lab procedure PEP-19A .


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n. The Site Security Department established access controlled areas within 30 feet of the containment building for the safety of employees and in areas designated vital to the CILRT. These boundaries were established IAW Attachment 13 of S2.SS-IS.ZZ-0005(Q).

4.2 PRESSURIZATION

When all prerequisites were completed, ISI performed a final walkdown of the containment building IAW Attachment 22 of S2.SS-IS.ZZ-0005(Q), and verified that the containment was evacuated of all personnel. The containment building was then secured and ready for pressurization.

Pressurization of the containment building commenced at 2132 on 3/22/92

At 2320 on 3/22/92 the pressurization control valve 2VC5 went closed and pressurization was stopped. Investigation of the problem revealed excessive instrument tubing leaks which caused the temporary N2 supply to deplete.

The Test Directqr decided to release the normal control air supply v~lve and restore 2VC5 to normal. This had no impact on the Test or the Test results. A work request was initiated for the repair of the 2VC5 instrument tubing.

Pressurization of the containment building recommenced at 2132 on 3/22/92

During pressurization, inspection teams made tours of the containment penetration areas to look for any problems which may have arisen.

The containment building reached test pressure at 1352 on 3/23/92 and pressurization was terminated.

4.3 Stabilization

The stabil~zation began at 1352 on 3/23/92 and ended at 1810 with temperature stable at a rate of change of .18 degree.

Removed 22 containment fan coil unit from service at 1749 on 3/23/92 to help stabilize containment temperature.

4.4 TEST PERIOD

The 24 hour test period began at 1815 on 3/23/92 and ended at 1815 om 3/24/92. The measured result is .02% per day of containment net free volume.


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After the test period was complete, a successful intrumentation verification test was performed IAW Attachment 14 of S2.SS-IS.ZZ-0005(Q).

4.5 DEPRESSURIZATION

Depressurization began -at-21-1;8 on--3/-24-/9z--and-was---terminated at 0917 on 3/24/92.

4.6 RESTORATION

Immediatly after depressurization, ISI performed a general inspection of the interior and exterior surf aces of the containment structure IAW Attachment 30 of S2.SS-IS.ZZ-0005(Q). The interior containment inspection revealed three bolts located at 6 o'clock on the equipment hatch had moved. One bolt located exactly at ~ o'clock had dropped from the hatch and two adjacent bolts, one on each side, dropped about 1/2 inch. A deficiency report was initiated by the ISI Group IAW Nuclear Department Administrative Procedure NC.NA-AP.ZZ-0020, Nonconformance Program, and was evaluated by the Technical Department. System Engineer. An as found locai leak rate test was performed and the result was 11 seem with an allowable of 1900 seem. An inspection of the gap between the hatch and the frame indicated that the hatch was not properly installed. A revision to maintenance procedure SC.MD-EU.CAN-OOOl(Q) was initiated to clarify hatch installation requirements. The hatch was retorqued and an as left local leak rate test was performed with the results 8 seem. The deficiency report was dispositioned as acceptable and not a deficiency.

The Test Director requested all departments to perform the required restorations IAW CILRT procedure S2.SS-IS.ZZ-0005(Q).

7. Edited Log of Events

2/24/92 at 0840 - Officially made notifications to: US NRC Salem resident inspector, Salem QA (Vincent) _and ANII (Hewitt).

2/27/92 ISI conducted a meeting with Salem General Manager Cal Vondra, ISI Engineer R. Brandt, Operations Engineer L. Curran, Senior ISI Supervisors C. J. Conner and w. Treston, ISI Supervisors E. Obert and R. Rinaldi. GM Cal Vondra appointed L. Curran as Test Manager. Senior ISI Supervisor C. J. Conner appointed R. Rinaldi and E. Obert as Type A Test Direct~rs. Meeting held IAW


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7. Edited Log of Events - continued

Nuclear Department Administrative Procedure NC.NA-AP.ZZ-0005 (Q) for special tests.

3/22/92 at 2132 - Salem Unit II was in Mode 5 with RCS filled and vented and RHR inservice. Commenced pressurization of the containment at a rate of approximately 3.0 PSI/HR.

3/22/92 - at 2320 Salem- Unit- II- control- room informed the Test Director the 2VC5 valve went closed.

3/23/92 at 0130 2VC5 released and recommenced containment pressurization of Unit II containment.

3/23/92 at 0255 - At 25 PSIA Inspection teams were sent out in the field to inspect areas around the containment. Subsequent inspections were performed at the following pressures: 35 PSIA, 45 PSIA, and 55 PSIA, No abnormalities were reported.

3/23/92 at 0320 Control Room informed the' Test Director the containment pocket sumps were at overflow.· This sump overflows into the main containment sump which has a wide range level indication on it. Will keep an eye on it .

3/23/92 0655 Containment Sump level was 41% at th~ start of pressurization and is still 41%.

3/23/92 1352 Terminated pressurization at 63.199 psia. Commenced minimum 4 hour stabilization period. Data Acquisition center commenced data collection.

3/23/92 1810 Containment reached temperature stabilization with a rate of change of .18 degrees.

3/23/92 1815 24 hour Test start. Control Room notified.

3/24/92 1815 24 hour test period complete, Results .02% per day Dispatched crew to perform instrumentation verification test.

3/24/92 2100 Instrument verification test complete, preparing to depressurize containment.

3/24/92 2118 Begin containment depressurization.

3/24/92 0917 Containment depressurization complete .


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SUMMARY OF TEST RESULTS AND TECHNICAL DATA .

A. Containment net free volume 2,620,000 cuft

B. Normal operating pressure : Atmospheric

C. Calculated peak accident pressure: 47 psig

D. Normal operating temperature : 120 degrees F

E. Calculated peak accident temperature : 271 degrees F

The Salem Unit II CILRT was performed during the sixth refueling outage.

The level indications of liquid containing vessels within the containment were recorded prior to the test and immediately after completion of the test. Only the vessels with level changes are listed below. Containment sump ullage was calculated using the overflow alarm ~etpoint (alarm received during pressurization) to the top of the sump divider plate. This calculation is cons~rvative because this is the maximum amount of water that could be in the containment pocket sump prior to overflow to the main containment sump. The level in the main containment sump did not increase during the Test .

VESSEL

Pressurizer

Accumulator #21

Containment Sump

Salem Unit II

PRETEST POST TEST VALUE IN CU FT

63.8% 60.5% 40.11

70.8% 72.1% + 3.34

overflow top of + 61.875 setpoint divider plate

Total difference @ 63 psia

50 deg F

Total difference @ 14.7 psia

68 deg F

Page 9 of 11

+ 25.105 CU FT

= 111.77 STD CU FT

= 2197.89 SCCM

= .01% I La

= .001% I day

SUMMARY OF TEST RESULTS AND TECHNICAL DATA - CONTINUED

• Type "B" and "C" leakage to be added. (PENALTY FACTORS)

Valve No. Leakage SCCM

2VC5 - 2VC6 2520.0

2SA268 - 2SA270 2.0

- - - - - -- -- 2SA-265- -- -2SA26'7- - ----0.0-

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2SA262 - 2SA264

2WL190 - 2SF36

2CA1715

2CA1714

2CS900, 901, 903

22CA330, 22CA360

REFUELING CANAL FLANGE

ELEC~RICAL PENETRATIONS

Total

0.0

2.6

1.0

1.0

6.0

65.0

432.0

13.5

3043.1

Type "B 11 and "C 11 leakage to be added to the measured CILRT results.

A. As found "B 11 and "C" leakage

B. As-left 11 B" and "C" leakage

C. Difference added to the CILRT

Measured CILRT results Penalty factor Tank and sumps levels As found type "B" & II c II

Total

Convert seem to %/Day

+ +

+

40,064.8

19,425.2

20,639.6

43,250.0 3,043.1 2,197.89

20,639.6

69,130.59

seem

seem

seem

seem seem seem seem

seem

Calculated as-found containment leakage at 95% UCL

69,130.59 seem x .1%/Day I 216,250 seem= .03196%/Day


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SUMMARY OF TEST RESULTS AND TECHNICAL DATA - CONTINUED

Results were within the limit of .1-%/Day

Calculated as-left containment leakage at 95% UCL

Measured CILRT results Penalty factor Tank and sumps levels

Convert seem to %/Day

Total

+ +

43,250.0 seem 3,043.1 seem 2,197.89 seem

48,490.99 seem

48,490.99 seem x .1%/Day I 216,250 seem= .0224 %/Day

Results were within the limit of 0.075 %/Day

END


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REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST FOR PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM UNIT II

THE CURRENT RUNNING SUMMERY LEAKAGE AS OF 6/12/92 IS 31427.3.

THIS IS 0.15 La

THIS IS WITHIN ALLOWABLE TECHNICAL SPECIFICATION LIMITS .

Salem Unit II - i

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S2.SS-IS.ZZ-0005(Q)

ATTACHMENT 17

1.0 REQUIRED DATA

1.1 The log shall consist of, but is not limited to, the following information:

NOTE Attachment 17

All entries shall be designated by the date, time and initials of the individual who makes the entry. Entries shall be made only by the Test Director or his Desiqnee.

Salem

1.1.1 Document any prerequisite, limiting condition and/or precaution not completed or obtained, and the justification for continuing on with the test in Attachment 17, section 3.0.

1.1.2 Document any equipment unavailable for the test and justification for continuing on with the test in Attachment 17, section 3.0.

1.1.3 Record the time and date of the start and com-pletion of the Type "A" Test in Attachment 17, section 2.0.

1.1.4 Record any deviations from the test procedure including all ACN's and OTSC's and justification for the deviation in Attachment 17, Section 3.0.

1.1.5 Record any deviations from the suggested valve lineup in Attachment 17, Section 4.0, Valve Lineup Deviations.

1.1.6 Record any unplanned events or unusual condi-tions not expected or anticipated during the test in Attachment 17, Section 3.0.

1.1. 7 Record the results of inspections in Attachment 17, section s.o.

1.1. 8 Summarize the CILRT results in Attachment 17, section 6.0 .

Unit 2 Page 178 of 266 Rev o

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S2.SS-IS.ZZ-0005(Q) Attachment 17 continued

1.1.9 Record the personnel that performed work in Attachment 17, Section 7.0.

2.0 RECORD THE CILRT START AND FINISH= TIME AND DATE

3.0

Log

Log

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Start Time

Finish Time ~~'~£~'-~"--~~~

Date

Date

3- J.,3-q:z.,.

3-J4-9J..

_.;;...~.......,.:{L::..=J...,e;..;~~--· _· _/ 3-~4-f;.2 Test Director Date

If more space is needed to record information in the test loq, attach multiple copies of this section 3.0, and append them to Attachment 17. section 9.0 is available to trend any data the Test Director deems necessary •

COMMENTS SECTION

Start: Time 09/f' Date

Terminated: Time t:.tJ/70 Date

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Page 180 of 266 Rev o


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Atc.t.pTAl!>~t. f u.. -ns1 t>;ucme..

?Alt\£ ~\ - Zl +h~u.wil1 2~ SJ 20-'BfU.LS Ac:ldt:d ~ lAk"1i"1'1

~t:QU£.C:."T" .a, 01 ~7q3 j ..i -\-ht c\ostl> &s.,4-'io..J' A-S PU.

.\-\.\f.. ~tQ'-'(Sr o~ ~f S°ALtt't\ Wo4U'.~I ~ -~

Ac.~t.PT'A'BL't AS Ql£a.. ~ })\Uc.Ttifl •


••

••

•

, 12S5 G-H S' .I 6357 y~ , I

~·

OWG NQ~ ZQ5'344-A• 87{0~ SHe I REV Cf DCP NO. 2ec- ·~x:J57-.

C::::D NO: ~D~~74 . PAGE""B. of ~3 ·

•

•

•

S2.SS-IS.ZZ-0005(Q) Attachment 17 cont.inued

4.0 VALVE LINEUP DEVIATIONS

u .

3·Pl?·CZ:i Po.cae tt4- ~· 55 ~~ vc:.lve-s a.re o.ll +o.g9~J opEI\ foC" :Z: 1 C.. Tke. bool\dory vJ ves fGI" -lie. Cls~ +b_ G5~b vo.lve.s ~s /\of-N?-9.1d. lJ. ~-:2~-~~

3-j.'d-·'l:l. Pa5e'.s 4

•

•

•

52.55-IS.ZZ-OOOS(Q) Attachment 17 continued

4.0 VALVE LINEUP DEVIATIONS

~~e~ ~u- o

Attachment 17 continued s2.ss-rs.zz-ooqs(Q)

• 5.0 RECORD THE RESULTS OF THE INSPECTIONS

•

•

;

rA-.±19-tzJJ O.R. c:.uL ,-

•

•

•


NOTE 6.0

Data from Attachment 17, Section 6.0 shall be included in the NRC Report.

6.0 TEST RESULTS SUMMARY

Those sections that are not applicable (N/A) to the proce-dure performed, shall be .marked by the Test Director.

6.1 Temperature Stabilization Results

6.1.1 Start of stabilization :J -.z J • 9 .2. I 1.3 > 2.. Date Time

Completion of Stabilization 3-.:i3_,~ / Ill' ID Date Time·

Time criteria satisfied -:) -2J-"1 ~ I I 7 \.:>-Date Time

h~ M"' ..

•

•

•


6.2 Level Corrections

6.2.1 Obtain the Test Start and Test Finish levels from the control roam or Section e.o of this Attachment, and calculate the volumetric differ-ence in cubic feet and enter results in Attach-ment 17, section 6.2.2.

Tank, Vessel or sump

PRESSURIZER COLO CALIB. 2LI 462

21 STEAM GENERATOR 2LA3977 2RP4

22 STEAM GENERATOR 2LA1557RB 2RP4

23 STEAM GENERATOR 2LA 6978 2RP4

24 STEAM GENERATOR 2LA 15576RB 2RP4

RCOT 2LA 4144-A 2RP1

PRT 2LI 470

21 ACCUMULATOR 2LI 934A & 935A

22 ACCUMULATOR 2LI 934B & 935B

23 ACCUMULATOR 2LI 934C & 935C

24 ACCUMULATOR 2LI 9340 & 9350

RWST 2LI 960

CONT. SUMP . (ULLAGE) OYC'.A £!£.'4> fl~A"'t

REACTOR VESSEL LEVEL {RVLIS)

CONTAINMENT SUMP (LVL A 2LA2445) \

CONTAINMENT SUMP (LVL.B 2LA2448)

Salem Unit 2 Page 184 of 266

Test Start

~3. z 9

•

•

•


NOTE 6.2.2

control Room tank qraphs will be needed to calculate volume difference. Record required data form Section a.o Attachment 17

6.2.2 Level Corrections

VESSEL TEST START TEST FINISH ± CU/FT LEVEL LEVEL

PRESSURIZER ~3.~ ~o.S- - 'fo.11

RCDT l'i Ii 0 PRT 3q,q 3~.'1 C> ACCUMULATOR #21 70.~ 7.:;;. . I + 3.3Y ACCUMULATOR #22 ,

•

•

•


6.3 Penalty Factors

6.3.1 The penetrations that were not in their normal isolation mode during the test and whose Type "B" or "C" leakage must be added to the "A" Test results are:

PENETRATION L~G~ SCCM - ---

2VC5 - 2VC6 (PEN. 40) ;)._ S'":;.. 0 6,._,...:z,o /-S".o .5. l". c:..'"'

TOTAL 304~. I

6.4 Calculate the Type "B" and "C" leakage to be added to the measured CILRT results/ r:='ott.. T'4.... A.s. ..cov .... o( ~~ .. ff.

A. As found "B" and "C" leakage ~oo(, 'I. I seem

B. Subtract the as-left "B" and "C" leakage 1q i.os.;;. seem

C. Add Chemistry sample Attachment 31, Step seem

(~ D. Equals the total to be added to the CILRT results ;i,o ~ .3.~. G,, seem

E. Convert the total to . ooq,r % / day

F. Convert the total to . 09$"" % La

-~__.......-) ~-...,,....-...,£/'-...,..-/ ___ /

• • • Attachment 17 r.r·11Linued

S2.SS-IS.ZZ-0005(Q)

6.5 Calculate the penalty factor for the penetrations isolated prior to and during the CILRT to be added to the measured CILRT results.

A. Type "B" and "C" leakage (Actual as-found leakage for penetrations isolated prior to the CILRT)

C.t.1 B. Type "B" and "C" leakage (Actual as-found leakage for penetrations isolated during the CILRT)

6.6 Tank and sump level correction factor (Attachment 17, Section 6.2.2)

6.7 Add 6.4(C), 6.5(A), 6.5(B) and 6.6 to get the total leakage to be added to the measured CILRT results

6.8 Measured CILRT results

6.9 Add 6.7 and 6.8 to calculate the total CILRT results

6.10 Total CILRT results:

3043,/_ seem .001:1 % I day ~ (St;Qp Ei 4 D} (S'tep 6.4 E) ,,., ,;t:JI(

N Lll. seem ~% I day •

;it 'i7. 89 seem .oo I % / day

S" :i. 'i o. '!q seem .oo;l..'"( % I day

4'3/ ::i.s-o •

seem . 0 ;i % I day

'{8 L/ClJV. 't_~ seem .;f;o;2..:l

4.-')"/ % '?bl Lg. -W( ? b) ?S bS ·o £. I b? v ::>?S b b ' 0 b h 8 h

_L"?).-,:X? 17~0:::1 "> (;/

~.; ";? -p r:>7 7)"" n r 61-=> 1rl tf 'l'~V "">i ~ ~fl VN?d "W"::>?S /. b~ ~ o"e

•

• --+

•

•

•

. S2.SS-IS.ZZ-0005{Q) Attachment 17 continued

6.12 CILRT report summary .

6.12.1 List the reportable Type "B" and "C" penetra-tions and their as-found and their as-left leakage that were isolated during the Type "A" Test.

P~tion # as-found as-left ( A.

( ) B.

( ) c.

( ) o.

( ) . E •


•

•

•


7.0 RECORD THE NAMES, SIGNATURE AND INITIALS OF THE PERSONNEL THAT PERFORMED WORK

PRINT NAME SIGNATURE INITIALS COMMENTS

:r: S:L 5uPG12.v ,5ue_

;.//.!;/)'?_

. .. ~- ~,

Salem Unit 2 Page 189 of 266 Rev O

~S.lh( .

•

•

•

s2.ss-rs.zz~ooo5(Q)


7.0 RECORD fBI NAMES, SIGNATURE AND INITIALS OF THE PERSONNEL THAT PERFORMED !QB.I

PRINT NAME

f>1 ~ ~ I ~ ..J (';g ,( f._ c.J

•

•

•

S2.SS-IS.ZZ-0005{Q) Attachment 17 continued

~- I . ' 0 ('. . 'i .. q REACTOR LEVEL ~elf Cf 4- q7 'l ?- ]J q7 q"T

(RVLIS) ~fPr- ~.5' 1g 9~ 7Z tt5 q8 CONTAINMENT SUMP (LVL A 2LA 2445) 4-1 JI I 'ii t; I 41 41 CONTAINMENT SUMP (LVL B 2LA 2448) 4/ L( t "{I '1 I 41 4\ 21 ACCUMULATOR

70.t:, 10.t.o 70Jf 71.. l 7i.1 2LI 934A t'f, 1 2LI 935A l

• 52.SS-IS.ZZ-OOOS(Q)


To record more data than available on this paqe, make copies of this, section 9.0 and attach each sheet to this Attachment 17.

9.0 This section is for trending any data which the Test Direc-tor deems as necessary for the Type A Test.

DAD

TIME

c

0 ... p

0

. H

B

H I

I

I

• End of Attachment Salem Unit 2 Page 191 of 266 Rev O

I

--

DR # FORM NC.NA-AP.ZZ-0020-1 DEFICIENCY REPORT WO/WR # 910921013

IDENTIFICATION Sl_ S2~ SC HC_

~omponent Equipment Hatch Sys/Code Serial #

Model # ASME Code Item? Y ~ N Description of Nonconforming Item:

During the post CILRT liner inspection IAW S2.SS-IS.ZZ-0005(Q) three bolts located at 6:00 on the equipment hatch were revealed to have moved during the CILRT. One bolt located at exactly 6:00 dropped from the hatch and the two adjacent bolts dropped approximately 1/2 'inch. An as found LLRT was performed and the result was 11 seem. The allowable is 1~00 seem. The hatch·was retorqued and an as left-LLRT was performed and t~qresult is 8 seem. An inspection performed before the retorquing revealed the hatch to frame was not metal to metal in the ~oved bolt area. Is thpis co ition acceptable. fl ..., / :Jc, R. Rinaldi 3/26/92 I.Ji- )JIJ= Ng., /4 ?------- ,.,->~ -?.?--

supvr/Planner Date LCO # Exp'. Date Time ...-SNSS/NSS Date

DISPOSITION

REPAIR USE-AS-IS OTHER

NUC. CODE COMP. REPAIR NUC. CODE COMP. REPLACMNT

lOCFRS0.59 Applies? Design Change/Temp Mod Req'd? 'uture Item Replacement Req'd?

.nstructions:

REVIEW:

y N y N

y N

NUC. CODE COMP. MODIFICATION ASME VESSEL REPAIR (NON-NUC.)~-

10CFR21 Applies? Change Pkg/Temp Mod #

WO #

5'=·~ System Eng.

y N

*Req'd for ASME Code items~--------------~ SQA DATE covered by the NR Manual ANII* Date

tlliCTION COMPLETE: Cause Code:

Job Supervisor Date SQA Date ANII* Date

Nuclear Common Page of 11-07-90

•

•

•

Disposition:

DR # NA, WO # 910921013, Equipment Hatch

The as left condition is acceptable and is not a deficiency as defined in NAAP-20. The as left condition is in accordancs with design documents (with the bolts reinstalled).

__ The as found condition demonstrated acceptable leak tightness-during both the Type A test and the LLRT. The bolts have been retorqued through the WO process as part of the test · evolution.

Note that the hatch seal is designed to utilize the pressure on the hatch to further seat the hatch. The pressure on the hatch was unavailable during the LLRT. The LLRT is a more conservative test than the Type A test for this hatch.

The gap between the hatch and the frame is an indication that the hatch was not properly installed on the frame. A revision to Maintenance Procedure SC.MD-EU.CAN-OOOl(Q) has been · initiated to clarify hatch installation requirements .

FORM NC.NA-AP.ZZ-0020-1 DEFICIENCY REPORT

IDEN'l'IFICATION

~omponent CONTAINMENT LINER

Model # Description of Nonconforming

Sys/Code c_ A>-J

Item:

DR # ____;.\)~A.__ __ WO/WR # 900418001

Sl S2x SC_ HC

Serial #

ASME Code Item? Y ~ N

DURING ISI INSPECTION OF THE UNIT II INTERIOR CONTAINMENT LINER, CORROSION WAS IDENTIFIED AT VARIOUS LOCATIONS ON ELEVATION 78', WHERE THE LINER MEETS THE CONCRETE FLOOR. PLEASE EVALUATE.

RICH RINALDI 3/11/92 Supvr/Planner Date LCO # Exp. Date Time SNSS/NSS

DISPOSITION

REPAIR USE-AS-IS OTHER

NUC. CODE COMP. REPAIR NUC. CODE COMP. REPLACMNT

10CFR50.59 Applies? Design Change/Temp Mod Req'd? Future Item Replacment Req'd? Instructions:

REVIEW:

y y y

N N N

~ *Req'd for ASME QA DATE covered by the 1'.CTION COMPLETE:

• Job ¥u~rvisor ~ Date "tSQA Nuclear Common

NUC. CODE COMP. MODIFICATION ASHE VESSEL REPAIR (NON-NUC.)

10CFR21 Applies? Change Pkg/Temp Mod # WO #

Code items NR Manual

Date

a..-P-t-cr-

-fh is

-1/Je

J·~t)-- Sys tern Eng.

~~II* Cause Code:

-h ~ANII*

y

11-07-90

N

31t1 /q l_ Date

Date

Date

I J PSl~G · \ .: : S-2-ZZ-SE!· 676-0 ~ Page 1 i if 8 Pi.:blic Serv~·ce Etectnc al')d ~asi Jomba~y P.b

1 . Sox 236 t-Jar'!icks ~,;dgo. l.w J< oy 08038

. P , I : 1 Nuclear Deoartment . . . 1 i · ; !

TITLE: EVALUATION OF CONTAINMENT LINER PLATE CORROSION RELEVANT T0°NRC

1

IPAT QUES~ON ~

l.O

2.0

i.0' r •.

Nos.·: 50~212/~11-'.90-s1-Qoos SALEM GENERAT!NG STATION IT #2

, , • ~ I , I•• ' ' t '• '

I ~ I.:

P!IRPOS! 'l.'.~ ! ' ~· I l '· ~ j -- -- t i - - -

To perform a yisual inspection walkdow~ of the containment steel ~iner 'pla~e and evaluate lits exiS,ting conditions for evidence· of.degradation, due to corrosion, such as, water stains, loo~~ i~sula~ion mater(al, rus~ stains, mineral deposits, pi~ti~qs, etc., to address NRC IPAT Question 272/3ll-90-~~~QQ057. l

; I !

SCOPE

Scope of work irlvolves the steel liner plate attached to the inside .surf~p~ ~f the containmert co~cr~te shell, in the Salem Statiort: R~actof Containmert bu1ld~in9 'Unit #2 from elevati.on 7~i· ··to. 110', upper elevations to dome and containm~nt l o\:1tside concrete wa~ls. Th~ visual inspect'ion/evaluation consists of the followinn items:

! .. . . I 1 1' 2 .1 Lin~r ar e~evations 78 '-0"1· and 110 I -O"' as seen in ' "o I l_ I

recess:~;e~s (A~tachment 7(' 2). 1 · ; l ; . I

2.2 Test channel at·bottom of nsulation.

2.3 Li~er p~it~ ~ithout insulalion, atl·elevations above 11~~-oii~o ~ome~. I

. I l t : , , , J 1

. 2.4 Top ot la9q1nq qonnection, to liner p ate at elevation

1·10 f-Qll J ·t ' 1 . I ;

I :1t. : .i 2.s out~ide·qoncrete walls, fr·m Auxil ary Building at al~V,atf1~qs ~4 • -()" and 100' O", south side of containra?-e. nt:.

l ! 1!1 : l)l:SCVSS*Q!I

1

a 11

· r: l d ..

NRC Inspe,cti,C!n Rrport 272/311-9 disclosed visible signs of corr No. 2 c9ntai'.rlirient st~el liner p report ~ome ~ust!was :visible th

; ; I I ~ I studs, ;n,d or

~ \ .

''

' \ ~ ' l 2 of a

S-2·-~Z-SEE•0676-0 ': Page

3.1

3.2

l •

: \ I l.: J ~ Background , . I

~ ~ i I J The interior cyl,indrical s rface of the containment is li~e~ w,i~h a carpon steel ~ea~ tig~t steel membrane which is l/~" thick for the loW'er 21 feet 4 inches and 3/8 11 ' thick for the remainde1r and is' anchored to the reinforc~? ~o·ncr~te cylinder ~ith l~/2" dic;tmeter hooked studs. In areas where there is an excessive number of

· " ~ ' I o penetrat~9n~ and at the knuckle pla~e at the bottom of th• cylip~e~, the liner is ~ncrease~ to 3/4" for reinforcement. The lower 34 feet of the containment lin.er is\ bovered on the ins1ide by insulation. The insulati?fi ~s provided to p~event b~ckling of the liner due to restricted growth under a rise in temperature exp~~ieq9.~d during a LOCA.·rThe ins?lation is attached to the liner at intervals, ith stu~s, in panels approxi:~~ely 6' wide x 10' high. I Leak te~~·c~annels are welded to pottions of the liner behind i~4 ~nsulation laggi~g. . l

I j ', J • Initial '

1

fnsp'ection Walkdown and Evaluations · l ~ I l

3. 2. l L{b.~r :Plate at Elevation§ 78 '.-on and 110' -0"

i I

: , .. - : I , I. ,

A~: Walkdown f; 1

i,~Th~ liner plate 1 coverel wit~ insulati~n '. ·wh~ch consists of 1a stainless steel lagging, ' a vapor barrier and ins~lAtion material " ri9idly attached io the llner plate. This i ·insulation laggin9 runs atound the entire :i·pe~ime~er of the liner plAte, from elevations I l ·78;1 -0 11 :tO 110 1 -0 11 except at the recess areas, : . r'Where the liner p ate is 4xposed behind 1.· :el~ctrical cabineij-s, and t/C instrumentation 1 j pa~els ., See ~ttaqhments 1 · l and 7. 2. Some l1)c~ttered stains n insul~tion laqqinq at '·.Elev. 78 '-0 11 were observed. ) . :; ~ l I L;soine 1/4" diamete stud heads, attaching the It

l 3 of s

S-2-ZZ-SEE-0676-0. I ! .:: I j

P~ge I

J

3.2.2

\.

f,l~ki9g, especlaI1y· at the right of column 1i lirie B-11 (Elev. 78') (Altachment 7.6).

I I ~ I I ! 1 l ! I 1: Tp~ l~ner below he test; channel exhibited a ! ~ degree of rust a d deterioration and some · i ·~ Y:':ater ~ accumulatif n was o9served at the floor i~ J~nct~on, at a c uple of1locations. (See 1 Attachment 7.6.) ~

: [ •. A~ elevation 100 water ~tains were observed ·: •.· b~hind the contalnment spray system (right of

personne~ hatch ~nd simi~arly at left of column line? B-sTand B-9~.

; · Ai though some ru l t stain~ were observed on ,, . insul~tion la99i~:(9, rust~at the junction of

insulation and f oor are~due to the very hUmid conditionst1that pr~vail inside the containment, esp cially in elevation 78 11 • T~e condition of the lin~r plate can only be opserved at the 1ecess. JThese areas were

; " . r~garded as a pr totype of the unseen area~. Ir 1 B~ ·· tvaluation i 1p I

B~sed on the obs rved depth and amount of c9rrosion we con·lude that the loss of liner

.,. p~ate material my be es~imated to be less than 1/16", is irlsi9nificant and does not

· · d~mprqmise its structurai' or leak tight i~tegrity.

l

; . i . Test Chan el at Bott m o iner

' • ! J l ~f, w~lkdo'wn - oiscu tion j ;J3 T~e bottom test dhannel attached to the liner 1 •' I i I I ( h r: was nspected at the rec~ss areas (were 1

: insul~tion is in errupted) and it exhibited some rust combin d with dirt and rubbish on 1 t~ t~e to~ flange, special\y near column lines

; B;S, B9, B-14, B 16 and ,-17. (Attachments

B.: .; :l:: u:~ :o:nd 7 • 6 j. ) \ ·1' ~ Nb wat\er leakaqe were oJserved but it may be i ! ;~: a~sumed that som~ water r&ay have migrated i ~ ,. ftom l'eaks in th~ service water system by : : . c61umn lines B-1 and B-i7, to the bottom of ! j -~ th~ liner where ome of the corrosion exists. l :' i t 1· l . . . ~ 1 • l I • l J I : . ' I I I 2 ! : ."·

I I .

\~ I !

j. I

P)r: e 4 Of 8 S-2-ZZ-SEE-067.6-0 I I

· .; .~ Ir.i • adc . .1..;=t"f'i=o-n....,..t""'o....,,t~1'"9if"'s-,-t .. h•a-""'~a-c-c""'um-u'"i!'l-a-tsii-o-n-o-f...-• ~ ~ di~1 gr~ase, du~t ~nd p~int ~ay hava · c6nl ·ibuted to the appearance of rusting and

'; flakin1q on the channel surfaces.

. ' I : I I 3.2.3 · er. Plate Without ±nsulation at Elev tions

ioo•-on to Dome . ! .~. ~

A.! W~lkdown - Discussion • ~ . I : J •

________ ;__· __ At ~l~y_t\tion _ll~'l_a11ci abqve, the l_iner:_ !_s_ -~n '. · qc?od c.ondi tion w~th minor stains in isolated : .. areas above _130'-lO" ·1

3.2.4 ~dp of Lagging Insul tion atJElevation 110• ~.! :' Walkdown - OiscuJsioo l

: : :: I I ' j '. .: Tl)e in'sulation la99inc; a.t. elevation 110'

. : •· consis.ts of a st~el angld welded to the liner

. . .. I • : 't ,~ plate (and to thEj test channels} along the l:: e*tire l~ner per~meter. :1t i~ protected with : j: a 1 meta.llic enclosure or 1lashinq to ensure a 1 1 ~ t7qht water seal i I l • o . ! ·• Portions of the flashinq. (about 3 to 4 feet) ,:· a*e m~ssinq at s~veral idcations or are loose : ' p.eft Of COlUIIlll l,ine B•3 ;1 B~lO and B-13) • : , · (~ee A.ttachment ?. • 6.) 1

B.: . Evaiua'tion '

i'

'' '. Tl:le. in'trusion of water i9 the ; · ~ ii;isula'tion/liner lconnect~on is not possible

due to the adequate construction detail ! : . ptovided. The f~ashing at elevation 110' :. protects the top

1angle ptovided at the

! . '. connec'tion and t e anqle :itself is welded to I : . t~e li.ner plate o ensur~ a tight water. seal. ! " · .J) • Therefore, ·t is co~cluded that the ! '. ·:. i~Qlat,ed rusted on~i tioqs of the exposed I :: metal .surtaces a e due tq the extremely humid

I e~viromnent prev ilinq durinq plant·

. or·eration. l I . I, . : . I. I. ''. I.'

l '

I ~ :u •, '

·1 " l I If I I;;· ~ I; .. I ~ . ! 1 ~· ~ l

' I

! I I I

L9 I

I

i

J o.: a I i

PU;e I

5 S-2-ZZ-SEE-067 6-o'

!

4.0

... , It,

; .. ·. 1 I ! I ·: I 3.2.5 Visu~l Inspection of :ontainment outside

C6~cr~te Surfaces J' ' ·. ~ l ~ : . . ~i ·~ Walkd~wn

. I M I • i . I

.~~A ~or~ion of the1exterio surface of the ·j~ r~acttjr containm,nt wallJ below grade is 1

1'.. acces~ible from the Auxiliary Building, the

il: h~lf ~outh side, :eleyati4n 84 1 -0" and 100 1 -::: o~. ~he walls;w~re 1nsp,cted-for evi~ence of : l~ach1n9, scalin , spall1ng, rust stains,

· j' '. prelinq or 9rack ng. . ' I

~1.: Eya1u~tion I !! Accessible areas showed no evidence of : j . Concrete SUrfaCe degradation I Cracking r nor , .. signs of water 1 akage.

4.2 Test Ch~pne~ at Bottom of J:L

1•iner. Elev. 78'-0"

ThQ rust stains on the sur ace of the test channel are due :to ~li·e ~ccumulation of dust, dirt, paint and extr.emelY' humid ·Conditions~that pr~vail inside the contai~~nt: duri.ng operati n and nC? significant loss of metal thickness was observ d on the channel. . . ' l !l j l . . I ·~1 :

i ..:J. I • q · i I • 4. 3 L ner Plate W thout Insulation, at ;·Elevations above iio~. •;-9n,;l ·}t"g ~ome t · ]

l ·.~ } . Th :lin~~ pl~te ;is in good cor:iditi

4t i

'-• l i

·, '

j Page 6 of S

S-2-ZZ-SEE-067~-0 t ~ I

'; ! i . · : 1 I l I : l I Revi,ew !=>f o~~oul1a.tion of R4fa~ence~ 5. 3 "ld 5. 4, revealeq that local thinninq·of the cont~inment liner

: ' ' ' . ! 1 1 I ~ 3 t pl~te d.o.Yin ~Q l/

16 11 minunum 1th~ckne~s is acceptable to withstand LO.CA and all other desig1 basis loadings. ·

l ·: I I Below ele~va~ion 110 1 insulation of. the liner is required,·· even a't the recess areas 'under the current allowable liner stresses specified~in the Salem Gene.rat{nq $tation UFSAR, ~nless t~e UFSAR is updated to the c:u:.rr~nt version of ~he 1989 , 1A~M~ ~oiler an~ Pressure Vessel .Code, Sectlion III, Division I, which would al.low; an uninsulated lliner plate below elevation 11q '· This' change wil-1 be ipart of ~a different project in the ne'ar: futu.re. j j

: : 11 ,. . l ' • 1 . : • 4.4 Cont~1nm~nt'Outs1de Wall S rface

Ac~e.ssi~~·e ~~eas showed no !evidenc q of degradation nor si~n~ of ·leakage, and the wall is considered stru~tu~~11r safe. l ] In s.ummk

1ry, J ~nspection of 1;he different components of th~ :lin~r'. p~ate ·showed nominal amo~nt of degradation in seyerali:~~e~s w~ich pose n4 siqnif~cant danqer to the st:i;u:ctur.a .. l function of the I liner p~ate as per Referende~ 5.3 and 5.4. G,neral housekeeping and clea·nli~e.ss; of the lagging A channels, floors and walls is· requir_ed · to preserve th~ life of these elements. At this ti~e it is concluded ~hat alt~ough corrosion is present', it is not severe inough nor prevalent enough to inhibit ~he liner platedfrom performing its design

S. O REFER:::.:ior:: as: stated in the esign ba

1~ sis.

5. l NRC 0

IPA~ .··2,k/311-90-81-QOO 7' date. 5/21/90. I I I I ~ ! _I '1 i

• I I lo i 1 5.2 NR~ ·Infpr:mat: .on :Notice No. s~-79. ·~Degraded Coatings

and Corrosi9n of Steel Contaitunentjvessels, dated De

!

I

I I

~ I

I i I I

! • I

! I

I l '

j Page 7 of 8

S-2-ZZ-SEE-067~-0 J ·: I

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6.0

5.6 Fi~l~ o~~ec~lve :s-c-2110-s~o-~s~, 'ev. o - "Inspectio~ and Restoration of the Int~rnal Liner Plate Surface ano Coatinq' ·in the Reactor Buil.dinq ·- dated June 30, 1986. ·. . . I I

S. 7 Or~w.ing. ;N:o. 207~~0-A-8797 i Salem Nuclear Generating Station No. 2 Unit - Reactor Conta!nment Floor Plan El. 1a 1 -·o" a;~d ~1 1 0 11 - Archite,tural. j ·

5. 8 Draw.inc; N,o.; 201167-A-8709 1 Salem ~uclear .Generating Station i...; Reactor Containment Slab at El. 78'-0" and 81~~0" ~·cohcrete. l j

5. 9 Draw.inq !~fo.: 201170-A-S709. SNGS Unit No. 2 - Reactor Containme'nt: Slab El. 78 '-o• and 81 i-0 11 Sectioris -conc

1rete.· 1 5.10 Dr~~ing ~o.i201177-A-8710 Salem Juclear Generating

• I I • I I 41 St~tion 1~ N~. 1 & 2 Units. Reacto~ Containment Cylindrica1:wa11 Liner - Q adrant "A" - Structural ..

YENDQR TECHNic·AL1 DOCUMENT (VOT) I IMPACT I 1 I

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7·. 0 ATTAClnf,ENTS l • I '

~ ; j : I 1.1 Containment· Liner and Insu ation Elev. 78'.

·~ ' '.< I\ ~ : ; ~ 7.2 Liner Typical Recess Area Section A-A.

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7.3 Se9tio~;~-B; - Bqttom of Li er Plat1.

1. 4 Top .of ~t:aif les~ ~teel Lag]ing Detail. 7.5 RuS~ Gr~qe ferc~ntage. l 7.6 Co~~ain~~ntf Lin~r Plate In pection'Record.

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l,-1,-, ,t.. Civil/Str~ctural ' Date Supervisqr

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---------· ~ -s._,2 .. zz. J6·7·6-o·--·----~---·-~--~---'-~-----·-- ··• ------CONTAINMENT LINER· PLATE INSPECTION··

SALEM UNIT #2 Date: 2/19/92 By: J. E. Maldanado & J. Buza

Checked By: a~ 1

lnspection--started clockwise from Quadrant-D. Column B-5, (see Attachment 7. t) --- ··- ·-· .. --··· .. - ·- - - . ---- ·---···· .... Attachment 7.6 Paoe 1-..

LINER PlATE WllHOUT I .. QUADRANT OOlUM .. ·-· ----· INSULATION.(RECESS LINER PLATE BELOW . - . FLOOR .. .. - .-.,. __ lELI .. " INSUt.ATION -AREA) . · - TEST CHANNEl (TC! . NLINE·-· TEST CHANNEL · · ·CONDITION· · ·PHOTOGRAPH COMMENTS ·- - ·-

B-6 . 2"'SWAed Oelul Covered ·Covered 6% Dirty Panel 245 • T. L Valve• ------ ___ Q ___ . . ·-· .... ..,, __ ..,.. __ . - . -~--- -- ....... . . . .. - .. ---· ·- . - ... -- ..... .- -----· .. . ....... {181

8--4 1~Stalned 0.6'Ki Dirty 5% Rust 10% Rust

--- ----- -- ... Fairly Clean .. - ------· 8-3 0.6% Dirty Reoesa at Be00lc1111 5'r» Ruat Na T•d Ch•nnel Clean

Pallel ' -6-2 CINn 1cnlo Rust 15% Rusi 10% Oirtv Ruat Clean Recess at ptirl1tl 235 • 2 X

lnaulatian 00\/9Ald w/mutlc tape (a 2'll3"

I •r ... l 1lnht of S.2 B:.1. __ _(;.IHI\__ _ _ Contlnuo1.11Jnaulalion --- _ Qorilinu~ _ lnsu!ation Contlnuou1 Clean L S.18 NoReona

-· -ln11Uta11on -- -- ------...

c S..17 3%Staln 10"'Allat 15% Rust Dirt 1~Rust Dirt Falfly Clean #1 l.attot B-16 Pfilftal ~~--- I. (181 . - - . '"'-&'le- ~'-Sta------ -~-Ru11·· - ~-Oirty··- -· -- .... 16%~ .,faldy.Qean . ..__~ . .#2~ .Recell&ollt

--.. --- • ·-------- -- -------- ......... --·-- - ·-- -·- •.. __ ..;_ .... _.::...-_________ - ...... ----=·-=·· =="'-=-=-=··=--=-=·-=···=· =-=·-=·-=··=--=-~· ·=-=··-=·-=--=--=·~--=· ==~-~.~-~-.~. -=---~-~-~-~---

---------------s-2-zz·· 67'6-0--···--·--·-----·--------·--- ••• ·CONT Al N MENT·LINER· PLATE· INSPECTION

SALEM UNII#2 Ode: 2/19/92 By: J. E. Malldonado & J. Buz.a

Qiodced By..aer-·lnepactlon started clockwise from Quadrant D. Column B-5 (see Attachment 7.1)

LINER Pl.ATE WITHOUT ---- -- ... QUADRANT-- -COLUM- -------- -INSULATION(RECES$..._ UNERPlATEBELOW.

-····-. :··-- :- - . !ELI ... - NUNE" ·-INSUl.ATIOH". ·ARE.ll·· · TESTCHANNELrTQ . - . - e a.1a Clean ~

- --- -- (78') ____ -- -- -- ----·. --- . ---· - - --·- .. .•. . ·-- .(Cont'd)

&-12 Ctean Covered with lnaulatlon Cowred wllh in1Ula1ion ----------·-·

.. 8-11 10% ftlSt 25'l. rusted liner 70'1. ruin and dirty

at>ove8w. 8(1

TEST CHANNEL Covwed

Cuwredwith lnwlatlon

~rust

__ .FLOOR CONDITION

· 15'l!. Stain, Dirty

Falrly Clean

30%Dirt

PHOTOGRAPH .,.

#5

Attachment 7 6 Paae 2 . --

·COMMENTS

Stud1 mlsalng M I.rt uf - · ··Column B-13 · · - -- ·

Behnid Pressurizer Relief Tank ···--- ··-- --·- -

Recess at panel 232. Behnid B-11

&-10 ReONaat 10%Rust Coveredw/lnaulation cowftld 30'1!.Dkty, #6 Al•ashieldedbVateel A Becwlclll w/lnlldatlun Stained · encloaure. ----·•--va;-- ----- -P.neerat1on- ------------- ------------ ------ ·· ·-··-· -- --· ------ -------·--···-··- -a.se·p1aw·ar.nd-or---

··-- ··~·----~........__~ •nclouure i1 totally rusted.

B-9 11' Dirt .. Mnot Aul~ 200' Auat Dirt 10% Ruat Dirt Dirty At. ri~ht of B-9

Fal~Cleen falll~CIMn

....__ .................... ~--- ... -~------=:.aw-__ ..

17

At. leh Of B-8

Siuda missing behind I DCalr RC-1 ..,d I con1alnment IUAlp and elevator aha.ft

Eapoud llnet' hN.vl~ corroded, right of Column B-9

. -·· ---·--· -··-----·-----~ ·----- ------=-=-~~ .. _..--·-···'"'·---..---:-~:-:~=--"'!~~~:'~~-.;--- ... ---·-·- ... ·:-·--~!9"'-·- ! .... __ .. _.,,,.. .•• ~ ·--~-:~:·:~·~:---:- -~-=· :·.,..-- - . -·-...----· -

- - . -QUADRANT COWM

- - . - tELT ___ - NLINE -. ·- - - -- . 8-6 ------- -

., ............

-·---- M

0 8-3 (1001

·- -. - - 8-2

... ....._ ... -- ~ .. --· .. ___ .,

·- - - ... 81

__________ s-.2_-zz. _6.7.6-0. __ , __________ _

CONTAINMENT {IN ER PLATE ... NSPECTION SALEM UN IT #2.

DI .. : 2/19/92 By: J. E. Maldonado & J. Buza

0iecked By:C?e'~

Inspection started clock.wise_ from Quadrant D. Column B-5 (see Attachment 7 .1)

LINER PLATE WITHOUT INSUL\T&ON (RECESS LINER PLATE BELOW FLOOR

· 1NSUlATION-- -AREA) TEST CHANNEL CTCl - - !EST CHANNEL CONOmON PHOTOGRAPH 20'la~ 10% "'at. 15% Rust- 15%.Rlm - 15% "'st Dirt

.. - ---· ···- .... . . . ..... - .. ·-. -- ... - --

·-Cldn -No A9ce61I Cowrad-with Insulation ~d.with Faitly.aee.n C.OV.red with lnsuhlllon Insulation

Clean NoReCHS Covered wltll k\sulatlon (;oye,..d wilh Fal1lyON11 #8 Co11ered wltll lnl4.lldon lnauldon

---- - - -- -· --- ... ·--· - . -· -- - ......... a.an NoReoeas Cowred with lnaulation Covered with Fal1lyClean

Cov.red with Insulation ln1ulatJon.

CINt'I No·Raceaa Covered with lnsulatlon CoveNdwilh fal1lyOean Covltted with lnlUlallon lnaulatlon

•

A h ttac menl 76 ~ age 3

·· - COMMENTS -·-Pd right of p.l'M>Mel -- -

naticn, 1111.lda mhialng on ·· lnauliition ----·--·- - --·

·--·- ----- ---- ----

. Top tluhing, at 110' - 3' long aectloo is looM, left of 8-3

. - . ---- -- -

--·--· - . -S1ulh mlaalng rigtlt of 8-1

------~· --- ·c...;a_:-~·4 ~ ••• --..:-=-o=-...=r\•.--..~~ r, c-.*-- ... -- ... • - - ,.,.., .... , •.. •, - :"' ..... ~ .. "! ... - •• - ~~-----. - . ·-· - - -- ·---- -- -- ··-

8-18 Clean NoR8()1tQ Covered with lnsulatLon 0ov&Ndwilh Clean Studs missing c Covefed with !n11Ulation lftsulatlon

{100') Studs mlSllng lett of B-17

8-17 aean No Reoeaa Covered with lnat.llldion CovelHwith Clean Cowred with ln&ulation lft1ulatlon

8-16 aean NoRec»sa Covered with Insulation CoYeNdwilh Clean Covered with lnsulaticm lnaulatlon -

B 8-15 Cl tan No r.oe .. ooverod Covefed W/lnsul&1ion C.OV.red falrly Oean 1119 Top flaaliing loc;:,e right (100') W/lnsulatlon 15'lb Rust W/nulatlon oflH5

-·

---

I

---· -

-- --

. -- --- ----- . - -- ---------··----... -------·--------~-·----------- ... -------- -·-----····----··----... ·-------------.... ..-.. -.

-·

----· ·-···· ..

.. .. ·- ..... . . .· OUADRAHT. COLUM" -- ·----(EL) NLINE

·- -

. -·· .

:--·-:·--·--s-t-z-z·· . 676-o------

CONTAINMENT LINER PLATE INSPECTION SALEM UNIT #2

Oa~: 2/19/92 OV: J. E. Maldonado & J. Bw:a

c ....... ~""Q'~ · · · .. Inspection stanecf clockwise· from Quadrant D:- Column·e-s· (see Attachment-7; 1 )· ·

. ·- ·---· ·-· . ·- - - -·- ..... ··-- -. ... ~ - ~ - ... . - LINER PLAlEwrTHOUT - ._LINER Pl.ATE BELOW·-· . . . ..... .. · - :FLOOR . - --- . INSULATION wst.U.ATION (RECESS TEST CHAHNEL (TC} TESf CHANNEL CONDITION PHOTOGRAPH ---- --·-· ----· ... _.. - -- --- .. , ·AAEM·- . ..... ------ ------· -- ----·--·. . - --- ····· ·--- . .. - .

- - .. . ···a . B-14 Clean R9ceu lelt of B-14 Cove,.cl with Insulation Cowled with FaltlyCiean (1001 Cle•n Olean !Aeulation

--(Coft'!I)-' • .. .aean.

B-13 CiNn NoR9ceu Covered with lnaulatlon Cowredwlth Falrlv Clean #10 CowMd with lnaulallOA lnautlllion

8-12 Qean NoRoceu C.Ove111d with Insulation Cowenld with Fa1r11 Clean CoveNMt with lrniulation IJnavldan

- ---- -----··-~---

- . ~~ .. -.-.-- ... 8-11 . Qlun. .No.Aeoess C.Overed.lllilh.!Mul.OOn Coveredwhh Fairly Cle•n : Cowfed with lnaulatlon IMulation .. - . -

~--.-... .. ·A- · · e10- · ·C111n-.. . . -NoReona- ... O>vefed wittt lnlUl1tion-- ·-\41d,,RMM9d ~ -Fald~-C!Nn--- - ·•· '"-• (100't Ccwered with Insulation

B-9 Sbllned NoReceu Cove..a wfth ln1ulatlon \Mii. l\.iated 20% FaldyCINn #11 Oov•,.d with Jnaolatloo

B-8 QNn NolWoeu Qwered wllh ln1Ulatian v.rt.Ar1o1Wld Fairly Clean C.OV.red wtlh ltl1>1.1latlot1 20%

8-7 Clean Alena right ol B-7 Covered with Insulation Coll9ted wtth Fairly Clean lnullation

••••

;-;-;:.·

na me ·aoe A ch nt76P 4 I .. ......

- -- .. ·-. ·-COMMENTS

.. ---· -..

------- -· 4" of 11•slling at 110" is missing - top .ngle 30% 111118d

Saud missing righl of B-12

-~-· ..

-4'.of lluhln/l..i.UO'.-~- - --mlaUng - ugl• rusted 30'lli

F/,~I.;,,~ Top portion lmng, rlghl olB-fl"'f

Studs mlulng right of 8-3

----------. --~-···----·:-----··----.·-- .. -~-------------.:-------___ · ·~-~----s-2~zz~·-"67~-~~~~----~--------~~-· ---· ~-.----==--.

---- ------------

·coNTAINMENILINER-PLATE-INSPECTION·~

SALEM UNIT #2 DMI: 2/19~2 By: J. E. Ml.tdonadO I. J. Buza

Checbd By-t:

-------------------------- WORK REQUEST DESCRIPTION --------------------TCM2121 COMMAND INPUT ===> CREATE MdDE

PAGE 1 OF 2 WORK REQ NO 920317173 AR STATUS-DATE: INITED l ~ INITIATED: OJ/17 /92 LAST UPDATE 03/17 /92 RlR

R· DEPT SSP_ __ PRIORITY 01 ~~· DEPT NSS SMT INITIATOR R. RINALDI 2038

AR YPE CM_ C.R. INST N MUC: SYSTEM: UNIT-CMPNT ID S2 NEUTRON SOURCE FEG NO: F/CMP DESCR: NUCLEAR INSTRUMENTATION SYSTEM NEUTRON SOURCE S-132 _______ _ LOCATION UNIT II REACTOR CAVITY------------------~ ACTION STATMNT: A S DATE-TIME : REFER WO/ACT 910921013 01 EMIS HUNG? : N EMIS TAG NO: SUMMARY : VENT NEUTRON SOURCE ______________ _ A DESC: THE NUCLEAR INSTRUMENTATION SYSTEM SOURCE S-132 NEEDS TO BE

VENTED DUE TO IT REMAINING IN THE CONTAINMENT DURING THE TYPE A TEST. PLEASE_ VENT IAW SMD SEAT 92-163 SEE ATTACHED·-------------------~

MESSAGE: PF4 TO COMMIT; 'CAN' TO CANCEL; 'NEXT' FOR NEXT SCREEN

•

•

•

IJq) lll'l' LOG I 91~/lr:J .

SYSTEM ENGINEERING ASSISTANCE ·TRANSMITTAL .

QUESTION/PROBLEM DESCRIPTION

., ... ~---

..... _. . ~ f'.OHFOlL\Tlo~·

. ,, • 1°U:-1il'.'I..~'\' I • ' H ,\ .~ T ti · .. en t:r:r-AnTM[HT ;: it·;in !'. i' ~- ·~l".l!l. "~"- 4!1•l'i7 USAr:C L1ccn:.r. llo. S~f .. .5G7 Tet.•11hom: :r,5;;769 Ato.:.1 Code '..ll

l!;i::, r;:C! r,, -. ,,QA!J, D.:.~~c:i. l.:'.:: . .:~ . .Ji!

: .: ~· t i :~ ~ : 1 o ~.: ~ r• E 1 cc tr 1 c Co r n o r ~ t i fJ n .: ucn_-ci?" ~i: ~ rcw Sys terns · - - - -- -P. L'. ~nx ~!j;j Pf ttsburq, PA 15230

L _J

-···- -··-·· ..... s·::r-~--sHir ?iNG DATA FORM

---- -----------------t.iAT" ul • .ur r.•f.Nl

-·- ------~- 1-2 6-76 ~· .O.lJ · 01 .. 1

l~------n~v~nn. n.h..iMft'--~-~---VIA

Co 11 cc t. 10190

Public Service El~ctr1c & Gas Co c/o United Engineers &

Cons trl!ctors, , J\tt.11: Construction Sup~r1ntenden

-------------------------t Slllc::i ~lucl cJr Gc.icrating Stat1cn Artific1l I~land.

: Purch.:::!e Orc~r N~. ~r i.i Cl'n $P. No.

S 1l4-csr:-1~-11;; 1-Xil l i RC ~ 9 -1 S 0 l~ 2 - 0 1

~-:it t·:;ri nl r !~rr.·:bor =r CEi:O'; PT~°" I

ii any):

>urcc Ho.

ilcnitrc~ Arn-241

U er y 11 i 11111

Am't of Isotope

3.37 C1 or 0.984 gms

Chemical Fonn: ft.mo 2

10.0 gms

.) c •••• , Dl?scription:

"~"" 1lP~s steel. 1.25• o.o. x 2.ss• O.L.-< '. ·l•'1••·11-.i.>n'\, window lhickno-;s, ii .1ny) '~--)

i~.o. 1011-a 176-tAt

Lot·!i:>r :~ 11 cv:ays Ci"eek Town sh 1 ;:> Salem County, Ne~ Jersey

PRICE UNITS OROERED QTY. SHIPPEC

SHIPPING COofTAINER DESCRIPTION

30 ga 11 on dru•

USA DOT . 7~ •• Tvnfl! A Particle Energy Emission Rate-Date

n.m. 8.35 X 10s n/sec

P!ice ~I S.:>urce(s)

Conl&iincr deposll/prico

Total

$ ____ _

'-----$ ____ _ ~-

---~--

IS.-.. J·,;lUN ;:, ., .-J~TS

DAT .·i'i1 OHIO

• .~ i. ~.~~;~HI~I SUR'iEY RECORD ,JSTOMER ~4 --~~ DATE /-~/-// PRODUCT NO(S). -~)7!,~~~~·~c.=~~--L.L.-.M..l.~~~~~~~~~-~~~~-~~~-Type of Source~....,.,-_/--""- Quantity I Type Radiation Emitted )l~

Source Number

hJ!?C- /Jn'} g _/I.Ji

SH.IP PI NG PACKAGE:

Se r i a 1 No • H- 3o9A S i z e_~,lu.itJ~p-P-4-"dmJ...........,~A pp ox. Wt. ./# 1' . L.T Type: A. A,_B S lding: 0 Paraffin

RADIOLOGICAL CONTROL: Conte- 1er Survey

(Contan 1ation, µCi) Outer S_rface~f11D-b Inner Cont(s)/9JJo·' Ho 1 de r ( s ) i 9 x 10 - 6 Other~----~~~~-

SEALED SOURCE TEST

Emission Amount Surface Contamination

J..ls ~/,!) J' ..JL J?..!~ el'· ./S ~10"' '~"/I· -

OUTER INNER SPECIAL

~Metal Drum 0 Pipe'Nipple O Mod. 2501 0 Steel Pot 0 Tin Can D Mod. 2511 0 Fiber Box 0 6M or 11 8"11 cntr. D Overpack· __ _ 0 Other_· __ D Other_.____ O Other ___ _ c~rw.E.P. D Lead/Steel D Other ___ 0 None

Container Survey (Radiation) at Surface at 3 Feet

Gamma /,,0 mrem/hr Gamma - O. 6 mrem/hr Neutrons - /ZO mrem/hr Neutrons - tl.2 · mrem/hr

Total - /.:J .() mrem/hr Total - .J . .l ~•rem/hr *Transport Index

SURVEY INSTRUMENTS USED

[]Helium Mass Spectrometer leak Test

[] External Pressure Test PSIG

~Final Bubble Test

~Gamma

~Neutron

D Other

-Eber·l ine R0-2

-Eberline PHR-4

[] Other~~~~~~~~~~~~~

--.,MENTS:

• Shi pm~t approved·~:

I/ . /? .. ~ .. ~_,,

• NOTlCE -

I.

• < •

-:,:.,,.· ..

-.,_ - ) ~

··-:.·~ •:!... ... -~ •· ..

••

Removable Drumhead .

MONSANTO RESEAR~CORPORATION ENGINEERED PRODUCTS

DAYTON, OHIO

• NEUTRON SOURCE UNLOADING INSTRUCTIONS

·1. Remove security seal,· release bolt rin~ and remove drum head.

w i t~ .Bo 1 t Lock R 1 nng ---,---==:::s-----~ 2. Remove pipe cap from center pipe.

Center Pipe with

Source Holder

Neutron Source

.. • • r

,lltll CllAIA•CIS llAIGllATID.111 ILLWITIATlll rwaPlllS

I

3. Using wire loop, withdraw source holder . until neutron source 1s clear of top of center pipe.

4. Using long tongs or other handling tool, transfer source from holder to shielded storage.

·NOTE: DO NOT TOUCH RADIOACTIVE SCL~CES BY HANOI KEEP EXPOSED SOURCES AT ARMS LENGTH OR MORE FROM THE BODY.

5. Replace source holder 1n center p1pe.

6. Replace center pipe cap.

7. Replace drum head and bolt ring.

8. Remove or cover rad1oact1ve labels.

9. Label drum "EMPTY".

10. Return container to: Monsanto Research Corporation 1515 Nicholas Road Dayton, Oh1o 45407

-------~~----i==:=.--~~~~.-----._,_____ ......... . • ZONE SY. Oi:5CRIPTION . DATE-

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UNLESS OTHERWISE SPECIFIED DIMENSIONS ARE IN INCHES

APPD

TOLERANCES: APPO MONSANTO RESEARC.H CORPORATION

DAYTON LA.110.R.ATOl\Y

DAYTON, OHIO DECIMALS FRACTIONS ._ __ _,_ ___ ,.__-t

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MATERIAL ....}Q.i. ~ u-. cHEcKm e.E. ~- 1-10-7' 4 C\. Ain "Be. souRcE. ~AMMA $HlELDE.D ------...... -~~-+-----. ANISH=S!E-==== PRAWN (\}',~J. l\-S·7! CALC --i:....- - - - .-_ ...- 1----------t---1 SCALE NDNf WT 61GNATUR1t DATE .-.cT.

OWG NO.

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•

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ML ,,\ . .iL.."1;,"'ol \,,v~PORATION

ENGINEERED PRODUCTS

DAYTON, OH I 0

.. .. . " SH I PP E R 1 S CE R TI F I CAT I 0 N F 0 R RA 0 I 0 ACT IV E MATER I Al S -·- --. - . -

{To be completed fn triplicate)

We hereby certify that the named articles are properly classified, described, packaged, marked and labeled, and are 1n proper.~-\fondition for transportation, according to the applicable regulatio"S' of the De p a rt me n t of T rans po rt at i on .·-:-J.$.~

1-26-76

Name of Radionuclide

.... ~ ·z-

MQNSANTQ RESEARCH CORPORATIOl:, 1515 Nicholas Road Day ton, o·h 1 o 45407 · J"",i :·::.,.'.O .. (slJ) 268-6769 ~r ~--,o~·-· -

~~~· Harold L. Coleman ""

Manager. Manufacturing SuppoP~

-~

•

•

••

Sim 101' LOG # 9 2- \ lo5

SYSTEM ENGINEERING ASSISTANCE TRANSMITTAL

QUESTION/PROBLEM DESCRIPTION

WORK OIU)IJll. I C\ \OC\ 2. \ 0\ 30 PROILE>h T'fvt: Nt;.:.,iSa.o"-3 Son g_ce.. \$ \10 -\'\.\..e Q..\e.. "to L~a\Je

,.,._, 2.oSL

RESPONSE

DOI.llm ---------- PllOld I --~- __ D\'!-' ----

•

•

•

S2.SS~IS.ZZ-0005(Q) Attachment 24 contiuued

2.0 SITE METEOROLOGY PRIOR TO CILRT

·Record the weather conditions every four (4) hours for a minimum of three (3) days prior to the CILRT.

i

~/92 10:09 15-MIN AVERAGES ETER REFO REFl T-IN PRES. RAIN· SOL -TEMB( TEGG DWPT· DTUL

UNITS VOLT Mv c INHG INCH LY/M c F F c ..:.. :

DTML ·wsL WDL SIGL SIGA WSM WDM SIGM wsu WDU c MPli DEG. DEG DEG MPH DEG DEG MPH . DEG

SIGU DEG

03/20/92 00:15 2. 4.89 2.50 31.3 29.77:'1 o.oo 0.01 0.6: 34.4 32.3 0.05 ·- ..... ~ ....

-o.~;:,63 4.4 324 g- ·1 lLO 7.2 329 5.6 9.2 109 . ~ . >11. 3 '";: .. .... ·

·-~-:

03/20/92 00:30 2.489 2.50 31. 7· ,29. 7W 0 • 0 0 . : ·~. ! 01 0.6 34.3 32.5 0.15 ' , J

5 .·1. -0.49 4.5 30·7 7.3 14.5 7. 0 . 331.· 8.7 110

14.8

03/20/92 0:0:.45 ·2.489 2.50 (-~~ .1 29. 7& 0.00·.o.01 o.~. 34.3 32 • .t-1 0.00

-0.50 4.6 313 7.1 19. 9•· 7.2 323 3.5 8.5 86

• HIGH 84.6 .' ~· .. ·~ ,_ .. 03/20/92 01:00· 2.;489 2.50 ~~--4 .29.79~ 0.00 0.01 . o. 6-;i 34.3 32.4 -0.07 1•

-0.55 4.5 319 7.9 9.1 7.5 323 3. 7· 8.8 335 • ¢· HIGH

6.4 . !-":"". " .. . ... , ..

03/20/92 ~1;15 r 1 2.489 2~50 32.7 29.79 0.00 0.01 0.7 34.3 32.1 -0.04 I .

-0.5.3 4.9 307 7.9 4.5 8.0 320 4.1 9.0 334

6.3 -03/20/92 01:30 2.489 2.50 32.9 29.79 0.00 0.01 0.8 34~4 32.1 -0.29

-0.64 4.7 295 9.8 4.6 7.2 311 6.4 8 .·3 325 ... ~. ~

t·"r'p '·

03/20/92 02:00 2.489 2.50 33.4 29.79 0.00 0.01 0.8 34.2 32.5 -0.25 • -0.64 5.0 300 9.0 4.3 7.0 311 5.1 8.9 328 5.0 03/20/92 02:15 2.489 2.50 33.5 29.79 0.00 0.01 0.6 34.0 32.9 0.10

-0.45 5.1 307 6.8 2.3 7.8 317 3.0 9.7 335

3.0

03/20/92 02:30 20489 2o50 33.7 29.79 0.00 0.01 0.6 33.9 32.9 0.37

-0.29 4.8 321 7.1 2.1 8.2 324 2.6 10.4 341

2.4

03/20/92 02:45 2.489 2.50 33.8 29.79 0.00 0.01 0.5 33.7 32.9 0.60

-0.15 5.6 325 5.7 1. 8 9.0 326 2.2 11. 4 344

2o2

03/20/92 03:00 2.489 2.50 33.8 29.79 0.00 0.01 0.4 33.6 32.7 0.80

• -Oo04 5.3 327 5.7 1. 8 9.4 331 1.8 11. 4 348 2.2 03/20/92 03:15 20489 2.50 33.9 29.79 0.00 0.01 0.3 33.5 32.8 0.90

0.01 4.3 340 5.2 1. 2 8.0 333 2.8 11. 2 347

1. 4

03/20/92 03:30 2.489 2.50 34.1 29.79 0.00 0.01 0.6 34.1 32.9 0.74

0.01 5.4 340 3.3 12.2 8.8 346 4.3 10.1 356 HIGH

15.6

03/20/.92 03:45 2.489 2.50 34.1 29.79 0.00 0.01 0.8 34.2 32.7 0.71

0.45 5.7 336 3.6 N/A 7.7 349 3.6 8.9 37 HIGH

84.6

03/20/92 04:00 2.489 2.50 34.2 29.79 0.00 0.01 0.9 34.3 32.9 0.58

0.40 5.2 340 3.2 N/A 7.5 350 2.9 9.3 359 HIGH •• 25.4

03/20/92 04:15 2.489 2.50 34.4 29.79 o.oo 0.01 1. 0 34.7 33.0 0.10

• 0.13 4.0 336 5.3 N/A 7.0 345 4.9 9.3 356 HIGH 22.2 03/20/92 04:30 2.489 2.50 34.5 29.79 0.00 0.01 0.7 34.3 32.5 0.20

0.30 4.7 331 7.3 6.9 8.2 341 4.9 9.6 350 HIGH

15.7

03/20/92 04:45 2.489 2.50 34.6 29.79 0.00 0.01 0.5 34.0 32.7 0.22

0.26 4.1 344 7.5 16.2 7.2 341 8.7 9.1 347 HIGH

13.9

03/20/92 05:00 2.489 2.50 34.6 29.80 0.00 0.01 0.0 33.1 32.2 0.58

0.66 5.0 332 4.2 16.5 9.7 339 3.8 10.8 349 HIGH

14.5

03/20/92 05:15 2.489 2.50 34.7 29.80 0.00 0.01 -0.3 33.0 32.0 0.63

• 0.69 5.4 320 6.4 7.6 9.6 334 2.7 10.5 344 HIGH 2.7 03/20/92 05:30 2.489 2.50 34.7 29.81 0.00 0.01 -0.2 33.1 31. 9 0.54

0.59 5.1 319 5.2 3.1 9.0 333 3.6 10.8 344

4.5

03/20/92 05:45 2.489 2.50 34.7 29.81 0.00 0.01 -0.5 32.5 31. 8 0.84

0.80 3.5 342 24.6 3.1 8.3 335 3.3 10.6 345

3.3 ,, '

03/20/92 06:00 2.489 2.50 34.7 29.82 o.oo 0.01 -0.3 33.2 32.0 0.41 ;~

0.25 3.6 352 9.2 2.3 . 6.4 339 5.1 9.2 344 2.7

03/20/92 06:15 2.489 2.50 34.7 29.82 0.00 0.01 0.1 33.3 31. 6 0.23 LOW

0.09 4.9 334 6.7 2.1 8.1 335 3.6 10.2 343

• 2.4

03/20/92 06:30 2.489 2.50 34.7 29.82 0.00 0.04 -0.6 32.1 30.6 0.79

• 0.80 5.2 329 9.1 2.2 10.0 335 1.7 11.2 344 2.7 03/20/92 06:45 2.489 2.50 34.7 29.82 0.00 0.07 -0.5 32.1 30.5 0.71

0.70 4.9 334 13.7 2.0 10.1 336 1.9 11. 9 346

2.4

03/20/92 07:00 2.489 2.50 34.5 29.82 0.00 0.11 -0.l 32.6 31. 0 0.31

0.37 4.8 325 8.7 2.4 9.9 334 2.6 11. 6 343

3.4

03/20/92 07:15 2.489 2.50 33.7 29.82 0.00 0.12 0.5 33.4 31.1 -0.21

-0.10 5.0 328 10.2 2. ,6 8.7 335 3.5 10.7 345

3.1

03/20/92 07:30 2.489 2.50 32.9 29.82 o.oo 0.16 0.8 33.7 31. 7 -0.41

-0.32 4.3 335 1-2. 3 6.1 7.2 342 6.3 11. 2 354

• HIGH 18.1 03/20/92 07:45 2.489 2.50 32.7 29.83 o.oo 0.21 1. 2 34.3 31. 6 -0.68 -0.47 4.2 338 13.0 19.4 6.5 343 7.9 9.9 351

HIGH 9.3

03/20/92 08:00 2.489 2.50 32.6 29.83 0.00 0.26 1. 6 34.8 31. 3 -o. 93 .

-0.59 5.3 336 14.5 23.0 7.3 346 7.4 9.8 346

14.3

03/20/92 08:15 2.489 2.50 32.0 29.83 0.00 0.30 1. 9 35.3 30.7 -1. 05

-0.64 6.8 342 14.2 N/A 8.7 351 8.0 9.7 350 HIGH

23.4

03/20/92 08:30 2.489 2.50 31. 3 29.85 0.00 0.34 2.0 35.4 30.2 -1.05

-0.64 8.1 339 10.9 18.9 9.1 346 6.2 9.7 350

• 11.1

n1/20/92 08:45 2.489 2.50 31. 0 29.85 0.00 0.41 2.3 35.8 29.7 -1.13

• -0.71 7. 7; 341 13.5 19.5 8.6 349 7.8 9.3 347 HIGH 19.4 03/20/92 09:00 2. 48.9 2.50 30.7 29.85 0.00 0.45 2.8 36.5 29.7 -1. 30

-0.77 6.9 340 14.2 N/A 7.9 349 8.1 8.9 348 HIGH

26.8

03/20/92 09:15 2.489 2.50 30.4 29.85 0.00 0.51 3.1 37.0 29.2 -1. 36

-0.79 6.9 345 16.7 N/A 7.3 357 15.8 8.4 347 HIGH

25.0

03/20/92 09:30 2.489 2.50 30.1 29.85 0.00 0.47 3.0 36.8 28.8 -1. 27

-0.74 7.0 332 15.8 14.3 7.3 343 11. 5 8.4 341

9.8

03/20/92 09:45 2.489 2.50 30.3 29.85 o.oo 0.39 2.9 36.8 29.1 -1. 28

-0.74 6.7 334 15.5 9.2 7.1 336 10.5 7.9 337 • 8.7 03/20/92 10:00 2.489 2.50 30.2 29.85 0.00 0.46 3.0 36.9 28.1 -1.18

-0.71 5.8 331 19.6 11.8 6.5 341 11. 8 7.3 337

10.7

03/20/92 10:15 2.489 2.50 30.1 29.85 0.00 0.58 3.6 37.6 27.5 -1. 39

-0.81 6.0 339 22.2 15.3 6.7 341 15.2 7.3 334

14.4

03/20/92 10:30 2.489 2.50 29.9 29.85 0.00 0.54 3.7 37.8 27.6 -1. 28

-0.80 5.1 338 32.4 29.8 5.8 344 19.7 7.4 336 HIGH

18.5

03/20/92 10:45 2.489 2.50 30.1 29.85 0.00 0.72 4.1 38.2 27.9 -1. 51

-0.96 5.5 316 26.1 17.6 5.6 327 17.8 6.4 333

• 16.2

"~/20/92 11:00 2.489 2.50 30.5 29.85 o.oo 0.60 4.0 38.2 27.2 -1. 37 • -0.85 4.6 303 27.7 29.2 4.8 330 22.2 6.0 331 21.3 03/20/92 11:15 2.489 2.50 30.5 29.85 0.00 0.57 4.0 38.2 24.8 -1.28

. -o. 79 5.1 348 26.0 30.0 5.7 353 21.1 6.6 338 HIGH

22.4

03/20/92 11:30 2.489 2.50 30.4 29.84 0.00 0.61 4.2 38.6 23.3 -1.41

-0.84 5.4 3 24.8' N/A 6.2 7 15.9 6.9 333 HIGH

27.6

03/20/92 11:45 2.489 2.50 30.3 29.84 0.00 0.61 4.3 38.9 24.5 -1.43

-0.90 6.6 344 22.3 28.4 7.4 353 14.9 8.4 339 HIGH

18.1

03/20/92 12:00 2.489 2.50 30.l 29.83 0.00 0.51 4.3 39.1 25.2 -1.35

• -0.84 5.8 340 25.7 32.3 6.5 349 17.9 7.5 341 HIGH 20.1 03/20/92 12:15 2.489 2.50 30.1 29.83 0.00 0.48 4.5 39.3 24.7 -1. 36

-0.81 4.7 352 32.6 N/A 5.2 354 19.1 6.0 337 HIGH

18.2

03/20/92 12:30 2.489 2.50 30.4 29.83 0.00 0.52 4.7 39.7 23.6 -1. 35

-0.72 5.5 10 21. 6 N/A 6.0 5 16.4 6.9 339 HIGH

24.8

03/20/92 12:45 2.489 2.50 30.4 29.83 0.00 0.63 5.3 40.5 22.8 -1. 51

-0.86 6.0 334 34.6 N/A 6.3 345 23.7 7.3 331 ·HIGH

21.9

03/20/92 i3:00 2.489 2.50 30.3 29.83 0.00 0.61 5.5 41. 0 20.5 -1. 58

-0.99 6.2 325 27.1 27.6 7.3 336 21. 9 8.5 331

• 18.9

"1/20/92 13:15 2.489 2.50 30.1 29.81 o.oo 0.57 5.3 40.9 19.7 -1.54 • -0.94 8.8 352 14.8 24.7 10.0 0 10.9 10.8 344 HIGH 25.9 03/20/92 13:30 2.489 2.50 29.8 29.81 0.00 0.54 5.6 41.4 22.8 -1.76

-1. 09 8.9 349 16.8 N/A 10.6 356 11.4 11. 9 342 HIGH

25.7

03/20/92 13:45 2.489 2.50 29.9 29.81 o.oo 0.58 5.6 41. 5 22.3 -1. 47

-0.93 9.0 312 17.1 13.8 9.8 321 12.7 10.5 320

\._ 11.7

03/20/92 14:00 2.489 2.50 29.8 29.80 0.00 0.56 5.9 41. 8 22.8 -1. 58

-1. 08. 8 .. 9 308 20.5 9.7 10.3 322 15.0 11. 4 . 319

13.7

03/20/92 14:15 2.489 2.50 29.7 29.79 0.00 0.47 5.7 41. 6 23.5 -1.49

• -1. 00 9.4 328 1·7. 4 10.4 ·10. 9 335 12.9 12.2 334 11. 3 03/20/92 14:30 2.489 2.50 29.6 29.79 0.00 0.51 6.0 42.2 22.8 -1. 56

-0.98 9.0 318 18.2 11. 7 . 10. 5 328 13.4 11.8 324

12.2

03/20/92 14:45 2.489 2.50 29.6 29.79 0.00 0.49 5.9 42.1 22.2 -1. 49

-1.00 10.2 329 27.0 17.2 11. 8 336 21. 0 12.6 332

19.3

03/20/92 15:00 2.489 2.50 29.6 29.79 0.00 0.42 5.8 42.2 21.5 -1.47

-0.94 10.1 314 19.6 11. 6 11. 9 324 14.6 13.2 322

12.7

03/20/92 15:15 2.489 2.50 29.5 29.79 0.00 0.40 5. 6 . 41. 9 21. 6 -1.46

-0.96 10.6 307 12.6 4.6 12 .1 317 7.5 13.1 317

• 6.1

f'1/20/92 15:30 2.489 2.50 29.4 29.79 o.oo 0.36 5.6 41.9 21.8 -1. 37 • -0.92 10.5 309 14.4 5.5 12.1 321 6.7 13.l 318 6.1 03/20/92 15:45 2.489 2.50 29.4 29.79 0.00 0.29 5.3 41. 6 21. 0 -1.26

-0.79 9.6 317 13.5 5.3 11. 6 325 8.0 12.6 323

8.7

03/20/92 16:00 2.489 2.50 29.5 29.79 0.00 0.24 5.3 41.7 21.6 -1. 30

-0.79 9.3 322 14.4 7.4 11.4 329 8.0 13.5 327

6.8

03/20/92 16:15 2.489 2.50 29.2 29.79 0.00 0.18 4.9 41. 2 22.6 -1.15

-0.71 10.5 323 12.4 5.1 13.0 331 6.5 14.8 329

5.9

03/20/92 16:30 2·. 489 2. 50. .29. 0 29.79 o.oo 0.15 4.7 40.9 23.1 -1. 04

• -0.64 10.4 319 12.2 4.3 13.5 328 7.0 15.7 326 5.5 03/20/92 16:45 2.489 2.50 29.2 29.80 o.oo 0.13 4.6 40.8 23.6 -1. 01

-0.61 9.9 321 13.8 5.5 12.7 327 8.1 14.9 326

6.4

OJ/20/92 17:00 2.489 2.50 29.0 29.80 0.00 0.12 4.5 40.7 23.5 -0.97

-0.59 9.2 316 12.9 5.4 12.2 322 7.0 14.6 317

6.4

03/20/92 17:15 2.489 2.50 28.9 29.80 o.oo 0.09 4.3 40.4 23.3 -0.83

-0.49 10.2 316 12.9 3.3 13.9 323 5.3 16.7 318

3.4

03/20/92 17:30 2.489 2.50 29.2 29.80 0.00 0.07 4.1 40.1 22.6 -0.75

-0.44 10.9 315 12.5 3.5 15.2 324 6.6 18.1 321

• 6.9

l""l/20/92 17:45 2.489 2.50 28.9 29.81 o.oo 0.04 3.8 39.7 21.0 -0.66 • -0.38 11. 5 320 11. 4 3.3 16.0 328 5.8 19.6 326 3.7 03/20/92 18:00 2.489 2.50 28.7 29.81 0.00 0.03 3.6 39.3 22.0 -0.59

-0.33 11. 8 315 11.1 3.1 16.5 323 6.0 19.7 321

4.6

03/20/92 18:15 2.489 2.50 29.0 29.81 0.00 0.01 3.4 39.1 23.3 -0.51

-0.28 9.9 312 12.1 3.7 13.9 319 5.9 17.2 316

4.9

03/20/92 18:30 2.489 2.50 28.8 29.82 o.oo 0.01 3.3 38.8 23.2 -0.39

-0.21 8.4 318 10.8 2 .·9 11. 9 324 5.5 14.9 320

3.3

03/20/92 18:45 2.489 2.50 28.9 29.82 0.00 0.01 2.8 ;37. 9 23.7 0.01

• 0.07 6.5 326 8.8 2.6 10.8 326 4.4 14.2 320 3.2 03/20/92 19:00 2.489 2.50 29.5 29.82 0.00 0.01 2.6 37.7 23.1 0.09

0.18 7.2 319 10.3 3.9 11. 6 323 5.0 14.9 320

5.4

03/20/92 19:15 2.489 2.50 29.9 29.83 0.00 0.01 2.7 37.9 22.2 -0.07

0.06 8.8 323 9.7 3.8 13.7 327 4.9 16.9 326

4.4

03/20/92 19:30 2.489 2.50 29.6 29.83 o.oo 0.01 2.5 37.6 22.1 -0.07

0.04 7.9 320 11.4 4.1 12.7 325 5.8 16.2 325

4.1

03/20/92 19:45 2.489 2.50 29.4 29.83 0.00 0.01 2.5 37.5 22.3 -0.13

0.04 7.9 318 10.6 2.7 13.4 323 4.3 16.5 319

• 4.4

1"'1/20/92 20:00 2.489 2.50 29.8 29.84 o.oo 0.01 2.4 37.2 23.0 -0.11 • 0.02 7.5 315 10.3 3.0 12.1 320 4.5 16.l 316 3.3

03/20/92 20:15 2.489 2.50 30.3 29.85 0.00 0.01 2.1 36.9 23.7 -o. 0·6

0.05 7.9 311 10.1 3.0 13.0 318 3.8 17.0 315

3.2

03/20/92 20:30 2.489 2.50 30.7 29.85 0.00 0.01 1. 9 36.6 23.8 0.40

0.18 9.1 311 9.8 1. 7 14.5 318 3.9 20.0 316

2.0

03/20/92 20:45 2.489 2.50 30.6 29.85 0.00 0.01 2.0 36.7 23.3 0.18

0.12 9.2 311 10.7 1.8 14.3 318 3.8 19.1 314

2.6

03/20/92 21:00 2.489 2.50 30.1 29.85 o.oo 0.01 1. 9 36.4 23.3 0.06

• 0.04 9.4 309 9.6 2.1 14.0 314 5.2 19.0 311 2.9 03/20/92 21:15 2.489 2.50 30.0 29.85 0.00 0.01 1. 7 36.2 23.5 0.36

0.08 9.9 305 9.4 2.6 15.0 313 4.2 20.8 313

2.9

03/20/92 21:30 2.489 2.50 30.3 29.85 0.00 0.01 1. 7 36.2 23.7 0.44

0.05 10.4 306 10.7 2.3 14.9 313 5.9 21. 0 312

3.0

03/20/92 21:45 2.489 2.50 30.4 29.86 o.oo 0.01 1. 7 36.3 23.8 0.55 ' . ~,-

0.12 9.6 307 11. 5 2.7 13.9 312 6.1 20.1 310

3.5

03/20/92 22:00 2.489 2.50 29.9 29.86 o.oo 0.01 1. 5 35.9 23.7 0.76

0.28 8.7 307 10.0 2.5 13.4 312 5.9 19.5 309

• 3.0

"~/20/92 22:15 2.489 2.50 29.9 29.86 0.00 0.01 1. 6 36.1 23.7 0.97 • 0.31 8.5 303 10.7 1. 9 . 13. 6 312 5.6 19.7 310 2.1 03/20/92 22:30 2.489 2.50 30.3 29.86 0.00 0.01 1. 4 35.6 24.0 1.13

0.42 6.7 306 8.2 1.8 11. 4 312 5.1 17.4 310

2.6

03/20/92 22:45 2.489 2.50 30.8 29.86 0.00 0.01 1. 2 35.4 24.3 1. 42

0.66 5.7 307 7.8 1.3 11.4 314 4.4 16.l 311

1. 3

03/20/92 23:00 2.489 2.50 31. 2 29.86 o.oo 0.01 1.1 35.3 24.2 1. 40

0.56 5.4 304 7.3 1. 6 9.2 310 5.2 14.8 311

2.9

03/20/92 23:15 2.489 2.50 31. 6 29.86 o.oo 0.01 1. 2 35.4 24.3 0.96

• 0.46 4.7 303 9.0 4.8 7.3 306 7.6 12.4 307 5.9 03/20/92 23:30 2.489 2.50 32.0 29.86 0.00 0.01 1. 0 35.1 24.6 1. 25

0.51 4.0 305 5.4 2.7 7.4 309 6.5 12.3 311

3.0

03/20/92 23:45 2.489 2.50 32.3 29. 8·6 0.00 0.01 1. 2 35.5 24.7 0.88

0.45 4.7 296 6.1 2.9 7.3 308 6.9 11. 3 310

5.0

03/21/92 00:00 2.489 2.50 32.6 29.86 0.00 0.01 1. 3 35.7 24.4 0.28

0.27 4.3 294 9.0 7.4 6.2 296 8.8 ·8. 8 300

8.1

03/21/92 00:15 2.489 2.50 32.8 29.86 0.00 0.01 1. 3 35.8 24.4 0.08

0.15 4.2 293 8.3 6.9 5.6 297 6.6 8.1 301

• 7.3

.1/92 00:30 2.489 2.50 33.0 29.86 o.oo 0.01 1. 0 35.~ 24.6 0.18

0.26 2.6 283 10.4 7.6; 4.6 295 9.1 6.9 300

8.1

03/21/92 00:45 2.489 2.50 33.2 29.86 0.00 0.01 1.1 35.4 24~2 0.08

0.16 2.7 290· 7.9 8.2 4.0 293 6.6 6.4 302

10.l

03/21/92 01:00 2.489 2.50 33.3 29.86 o.oo 0.01 1.1 35.5 23.7 0.11

0.18 3.0 289 13.l 9.2 4.5 295 9.8 7.1 301

9.9

03/21/92 01:15 2.489 2.50 33.4 29.86 0.00 0.01 1.2 35.6 23.4 0.03

0 .16 . 4.5 276 12.1 7.6 5.5 292 8.6 8.1 298

8.7

03/21/92 01:30 2.489 2.50 33.5 29.86 0.00 0.01 1.4 35.9 24.1 -0.24

• -0.10 5.0 269 8.7 10.0 5.7 289 9.2 8.3 297 11.0 03/21/92 01:45 2.489 2.50 33.7 29.86 o.oo 0.01 1.1 35.4 25.8 -0.13

-0.10 5.3 266 8.7 10.4 6.0 283 9.3 8.1 292

10.7

03/21/92 02:00 2.489 2.50 33.8 29.86 o.oo 0.01 0.9 35.2 25.3 -0.14

0.01 4.9 262 7.6 12.0 5.6 281 11. 2 7.4 292

13.2

03/21/92 02:15 2.489 2.50 34.0 29.86 o.oo . 0. 01 0.9 35.0 24.9 -0.10

0.00 5.3 282 16.9 8.9 7.2 298 14.7 10.4 305

9.3

03/21/92 02:30 2.489 2.50 34.1 29.86 0.00 0.01 0.9 34.8 24.4 -0.10

-0.03 5.3 291 10.9 3.4 7.6 305 7.8 10.4 308

• 3.9

f\"l /21/92 02:45 2.489 2.50 34.1 29.86 o.oo 0.01 0.8 34.6 24.6 -0.22

• -0.12 4.4 297 11.5 5.2 6.2 308 a.4 a.a 315

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