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Reactor Containment Bldg Integrated Leakage Rate Test Rept
	ML20086E290
Person / Time
Site:	Pilgrim
Issue date:	08/05/1991
From:	Gina Davis, Ellefeuille J, Manderino P; BOSTON EDISON CO.
To:	Murley T; Office of Nuclear Reactor Regulation
References
	BECO-91-148, NUDOCS 9111270159
	Download: ML20086E290 (112)
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vl , BOSTON EDISON 4 Pugnm Nuclear Power Station Rocky Hdl Road I'lymouth Massachusetts 02360 George W. Davis November 7, 1991 sen or v.c. Pres. dent - Nuoear BECo 91- 148 Mr. Thomas E. Hurley Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555 License DPR-35 Docket 50-293 Reaclor_ Containment Buildina Intearated Lanka.ge Rate Test

Dear Sir:

In accordance with 10CFR50 Appendix J, Section V.B. Boston Edison Company is submitting the attached report on the Pilgrim Nuclear Power Station Primary Containnent Integrated Leakage Rate Test which was completed in August 1991.

This report includes a summary of the Periodic Types B and C Local Leak Rate Tests conducted since December 1987.

He understand that due to the "As-Found" Integrated Leak Rate Test results, we are required to follow the accelerated ILRT test schedule in accordance with 10CFR50 Appendix J.III.A.6(b),

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l REACTOR CONTAINMENT BUILDING INTEGRATED LEAKAGE RATE TEST I BOSTON EDISON COMPANY I PILGRIM NUCLEAR POWER STATION UNIT NO.1 I DOCKET NO. 50-293 l OPERATING LICENSE NO. DPR-35 I

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I I BOSTON EDISON COMPANY I PILGRIM NUCLEAR POWER STATION UNIT NO.1 l DOCKET NO. 50-293 l OPERATING LICENSE NO. DPR-35

,I l August 5,1991 i

ll 1esr DiRec10R d#[a P. M AND'ERINO BOSTON EDISON CO.

APPROVED BY N// /h a/

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IlEACTOlt CONTAINA1ENT llUILDING INTEGitATED LEAKAGE ItATE TEST IlOSTON EDISON COS1PANY PILGillSt NUCLEAll POWEll STATION UNIT NO. I DOCKET NO. 50 293 OPERATING LICENSE NO. DPR 35 ,

l August 5,1991

, I i PitEPAllED llY:

I GENERAL PIIYSICS CORPORATION GP R.263118 I

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TAlli.E OF CONTENTS I 1. INTRODUCflON

11. TEST SYNOPSIS l 111. TEST DATA SUhihiARY A. Plant Information B. Technical Data C. Type A Test Results g D. Type B and C Test Results E. Integrated Leakage Rate hicasurement System I F. Information Retained at Plant IV. ANALYSIS AND INTERPRETATION V. REFERENCES g

VI. APPENDICES I A. Stabilization Phase Data l B. 11old Test Data and Plots C. Verification Phase Data and Plots D. Instrument Selection Guide Calculations E. Sensor Locations l F. Description of General Physics ILRT Computer Program G. Local Leakage Test Summaries

11. FAT Root Cause Analysis - Feedwater Check Valves I

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1. INTRODUCTION The Reactor Containment Huilding Integrated 1.cakage Rate " Type A" Test is performed to demonstrate that leakage through the primary teactor containment systems and components penetrating primary containment do not execed the allowable leakage rates specified in the Plant Technical Specifications.

The purpose of this report is to provide information pertinent to the activities related to the preparation, test performance, and reporting of the Pilgrim Nuclear Power Station Integrated Leakage Rate Test (ILRT).

The section of this report entitled Test Synopsis "Section II" presents the highlights of activities and events which occurred prior to and during the ILRT.

l Test Data Summary "Section 111" contains data and results necessary to demonstrate containment atmosphere stabilization, acceptable leakage rate, and successful verification test, in addition, plots provided in Appendices B and C supply a visual history of containment atmospheric conditions beginning with the eight hour test period and ending with the verification test.

Information in Section IV, Analysis and Interpretation, supplies some of the technical detail associated with the ILRT computer program and its associated hardware as well as the instrumentation used during the ILRT.

Section V lists the documents referenced for the conduct of the ILRT.

The successful periodic Type A and verification tests were performed according to the requirements of the Pilgrim Nuclear Power Station, Technical Specifications and 10CFR50, Anpendix J. The test method utilized is the Absolute Method described in ANSl/ANS 56.81987, " Containment System Leakage Testing Requirernents".

Leakage rate was calculated using formulas from BN TOP 1, Revision 1,1972, (Total Time Analysis technique) during the Type A and verification tests.

Formulas from ANSI /ANS 56.81987 (Mass Point Analysis) were run concurrently for informational purposes only. Type A and verification test durations were conducted according to the criteria of Pilgrim Nuclear Power Station, Plant Technical Specifications.

The test results are reported in accordance with the requirements of 10CFR50, g Appendix J,Section V.B.3.

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11. TEST SYNOPSIS A. Failed ILRT I Prior to containment pressurization on July 26, 1991, Pilgrim Nuclear Power Station site test and maintenance personnel were engaged in activities l related to containment leakage. Cor.taintnent leakage was identified through the Type 13 and C localleakage rate testing programs and reduced by repairs to those systems and containment components having excessive leakage.

I The aesults of the localleakage rate tests are given in Appendix G.

I The following discussion highlights some of the most significant activities encountered during test preparation and execution and presents these items in a chronological order.

1. Pre pressurization Activities Pre-pressurization activities included: Completing all Type 13 and Type C testingt Type A test procedure review; final ILRT instrumentation operability checks; final ILRT computer program modifications; containment subvolume weighing factor calculation checks and sensor failure analysis. A few of these items are l discussed below to present pertinent information that impacted on Type A Test activities.

l The Type A test procedure review was conducted to ensure that all references to Plant Technical Specifications; 10CFR50, Appendix J; BN TOP 1, Rev.1,1972; ANSl/ANS 56.81987; and the FSAR were I accurate and current.

g A containment area temperature survey was conducted in 1987 to verify proper sensor placement for the proposed test ventilation as required by ANSI N45.41972 paragraph 7.4 and ANSI /ANS 56.8 l paragraph 5.5.1. The results of this survey were used to validate the ILRT measurement system sensors.

Final ILRT instrumentation operability checks were perforrned to ensure that all instrumentation was operating correctly. An in situ I check, as specified in ANSl/ANS 56.8-1987, Section 4.2.3.1, was conducted to verify that all ILRT instrumentation was working correctly. Calibration records for all ILRT measurement system l component calibrations, in situ loop checks, and for all field standards used are retained at the plant.

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local leakage rate testing at Pilgrim Nuclear Power Station were completed prior to the start of the ll.RT. The results of this program are summarized in Appendix G, " Local 12akage Test Summaries".

2. IlJIT Test Summary Time Line Phase Time Frame Duration Pressurization From: 1744 on 7/26/91 10.05 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months l To: 0347 on 7/27/91 Stabilization From: 0359 on 7/27/91 48.48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months To: 0428 on 7/29/91 I Depress From: 0428 on 7/29/91 To: 1800 on 7/29/91 13.53 hours6.134259e-4 days 0.0147 hours 8.763227e-5 weeks 2.01665e-5 months I 3. Containment Pressurization Containment pressurization started at 1744, on July 26,1991 using two compressors with a total rating of 2100 scfm. Pressurization I proceeded at a rate which did not exceed the procedural limit of 5 psi /hr. Compressor discharge valves were manually throttled to maintain backpressure and flowrate. Aftercooler cooling water flow was manually throttled to maintain compressor air discharge temperature. No fans were running in the containment during the ILRT itself or verification test.

At 1930 hours0.0223 days 0.536 hours 0.00319 weeks 7.34365e-4 months on July 26,1991, a 5 psig containment walkdown was I performed to identify any potentialleaking penetrations. Two minor body to bonnet water leaks were identified at valves CV 9068A and 2301 CK-40. The leakage rate of 2301-CK 40 was measured at 0.357 l gpm and the lmkage at CV 906SA was estimated to be less than 0.125 gpm.

Containment test pressure of 60.959 psia was reached at 0347 hours0.00402 days 0.0964 hours 5.737434e-4 weeks 1.320335e-4 months on July 27,1991 and the compressors secured.

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4. Containment Atmosphere Stabilization Stabilization was commenced at 0359 hours0.00416 days 0.0997 hours 5.935847e-4 weeks 1.365995e-4 months on July 27,1991.

I Ily 0635 on July 27, 1991, the stabilization criteria of 13N TOP 1, Itev.1, and ANSI 56.8-1987, section 5.3.1.6 were met and the l contained air mass had stabilized. The mass point and total time leakage rates were approximately 1.2 9F per day. Walkdowns were started to identify leakage. During the period from 0635 on July 27 until 1800 on July 29,1991, the following actions were taken:

g Date Time Action 7/27 1000 Smallleak identified past instrument Air check valve 31 CK 167.

7/27 1420 One inch union in tubing to differential I pressure transmitters PTD 506713 and valve AO 5059 was leaking.

7/27 1600 Valve 110112 was closed to isolate leak from one inch union.

7/27 1700 Valves 110 2301-107,108, and 41 A were closed to isolate leakage from CV 9063A.

7/27 1730 Relief vahe on non-operating RilR pump C was lifting due to a leaky pump discharge check valve. Operations switched to the "A" RilR pump and I isolated the flowpath to the "C" pump relief valve. Reactor vessel level had been dropping at a rate of approximately 1,5 l inches per hour. This was equivalent to a leakage rate of 0.373 96 per day.

7/27 2228 CRD seal purge was isolated. No change in leakage rate was observed and the seal I- purge was restored at 2346.

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Date Time Action 7/28 0015 Pressurized to 44.5 psig between htSIVs on "A" hiain Steam Line. No change in leakage rate observed.

7/28 0149 Pressurized to 44.5 psig between htSIVs on "B" hiain Steam Line. No change in leakage rate obsened.

7/28 0215 Pressurized to 44.5 psig between hiSIVs on "C" hiain Steam Line. No change in leakage rate obsened.

l 7/28 0320 Pressurized to 44.5 psig between htSIVs on "D" hiain Steam Line. No change in leakage rate obsened.

7/28 0330 12akage observed at pressurization line I vent valve 110-259. Valve 110 259 was closed. No change in leakage rate obsen ed.

7/28 0500 Pressurized to 44 psig between Torus 8 inch purge exSaust valves AU-5042A &

l B. No change in leakage rate.

7/28 0530 Pressurized to 44 psig between Torus 2 inch purge exhaust valves AO-5041A &

B. No change in leakage rate.

7/28 0645 Pressurized to 44 psig between Drywell 8 inch purge exhaust valves AO 5044A &

B. No change in leakage rate.

7/28 0700 Superimposed leak of 7.5 scfm impost d to verify instrumentation.

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Date Tirne Action 7/28 0907 Secured from superimposed test.

Instrumentation responded properly to superimposed leak.

7/28 1055 CRD and RWCU systems placed in service to maintain reactor vessel water level constant.

7/28 1215 1.cakage rate dropped to approximately 0.5 % per day.

7/28 1515 Operations requested to raise water level l to original band of 80-88 inches.

7/28 1805 Reactor vessel water level at 82 inches.

CRD and RWCU secured.

7/28 1830 Pressurized to 44 psig between Drywell 2 inch purge exhaust valves AO 5043A &

H. No g change in leakage rate.

7/28 1850 Isolated CRD min flow bypass. leakage rate decreased from approximately 1.2 %

per day to 0.91 % per day.

7/28 2207 Isolated suction to CRD pumps. Irakage rate decreased from approximately 0.91

% per day to 0.86 % per day.

l 7/28 2245 Inspection of drywell head identified significant leakage.

7/29 0001 Eight bolts on the drywell head were found to be loose.

7/29 0125 Opened CRD pump suction valve and min flow bypass valve.

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Dale Time Action 7/29 0330 lecal leak rate test of drywell head I indicates a leakage rate of 5.25 scfm or 0.73 % per day.

7/29 0428 Depressurization of containment started.

7/29 1800 Depressurization completed.

13. Successful ILRT Following replacement of the drywell head bolt washers and successful completion of the drywell head seal local leak rate test, the ILRT I prerequisites were re-verified and the containment was ready for pressurization. The root cause analysis of the drywell head bolt washer failures will be addressed by lloston Edison Company in a separate icport.

I 1. Test Summary Time l.ine Phase Time Frame Duration Pressurization From: 1908 on 8/4/91 10.65 hours7.523148e-4 days 0.0181 hours 1.074735e-4 weeks 2.47325e-5 months To: 0547 on 8/5/91 I Stabilization From: 0614 on 8/5/91 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months To: 1014 on 8/5/91 11old Test From: 1014 on 8/5/91 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months To: 1814 on 8/5/91 Leak Stab. From: 1820 on 8/5/91 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Verif. Test To: 1950 on 8/5/91 Verification From: 1950 on 8/5/91 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ll Test To: 2350 on 8/5/91 Depress (includes From: 0030 on 8/6/91 13.92 hours0.00106 days 0.0256 hours 1.521164e-4 weeks 3.5006e-5 months performance of To: 1425 on 8/6/91 drywell to torus g vacuum breaker leak rate test )

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2. Containment Pressurization Containment pressurization started at 1908, on August 4,1991 using l two compressors with a total rating of 2100 scfm. Pressurization proceeded at a rate which did not execed the procedural limit of 5 psi /hr. Compressor discharge valves were manually throttled to maintain backpressure and flowrate. Aftercooler cooling water flow was manually throttled to maintain compressor air discharge temperature.

Five and thirty psig containment walkdowns were performed to g identify any potentialleaking penetrations. No measurable leaks were observed from the penetration vents outside containment.

( No fans or area coolers were running in the containment during the ILitT itself or the verification test. The lineups for the second ILitT were identical 10 the first ILitT with the exception of the CitD I system. The CitD system was isolated for this ILitT.

Containment test pressure was reached at 0547 hours0.00633 days 0.152 hours 9.044312e-4 weeks 2.081335e-4 months on August 5, 1991 and the compressors secured. Approximately 27 minutes were allowed for containment atmosphere "springback" before commencing l the stabilization phase. This period was allowed as the compressors were stopped at 61.16 psia due to the upper limit placed on ust pressure by procedure of 60.0 + 2.0, 0.0 psia.

3. Containment Atmosphere Stabilization 13y 1014 on August 5,1991, the stabilization criteria of 13N TOP-1, l Itev.1, and ANSI 56.8 1987, section 5.3.1.6 were met.

4. IIold Test Period I Subsequent to meeting the temperature stabilization criteria, leakage rate analysis began at 1014 on August 5,1991.

l I 13y 1414 hours0.0164 days 0.393 hours 0.00234 weeks 5.38027e-4 months the measured mass point and total time leakage rates had stabilized at approximately 0.31% wt./ day.

l During the stabilization and hold test periods, the instrumentation was continuously monitored.

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,3 The ILRT was successfully completed at 1814 on August 5,1991.

5 The maximum allowable leakage rate (L ) for the primary containment is 1.096 wt./ day of contained air mass at peak test g pressure. The mass point and total time analysis were run concurrently on the General Physics ILRT Data hianagement Computer Program. The containment leakage data met all the l requirements of 11N TOP.1, Rev.1 (except where it conflicts with Appendix J) necessary to end the hold test in less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The leakage rate results follow:

I hiass Point Analysif ._

Total Time Analysis l Calculated leakage Rate fiom regression line 0.3150 0.3122' 9596 Upper Confidence 0.3184' O.3322' Limit 20 Point hican leakage 0.3093 I

Does not include penalties for nonstandard alignments and water level changes.

5. Verification Test g A successful verification flow test was conducted following the ILRT.

At 1820, a leakage of 7.5 scfm was imposed on the primary containment and allowed to stabilize for about one and one-half hour.

l The verification phase started at 1950 hours0.0226 days 0.542 hours 0.00322 weeks 7.41975e-4 months on August 5,1991, and was completed at 2350 hours0.0272 days 0.653 hours 0.00389 weeks 8.94175e-4 months on the same day. The 7.5 scfm leak imposed (L ) on the existing measured leakage was slightly larger than L (1.0 CL wt./ day) at 1.000396 wt./ day. The results stabilized (as shown on the graph contained in Appendix C) within the 12596 L, acceptance critelia and are summarized on the following page:

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i l Mass Point Analysis Total Time Analysis l Imkage Rate (L, ) 0.3150 0.3122 Imposed Leak (L ) 1.0003 1.0003 Lower limit:

L, + L.,,, - 0.25 L, 10652 1.0625 g

Composite Leakage (13 ) 1.5180 1.5115 I Upper limit:

L, + L , + 0.25 L, 1.5652 1.5625 I

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l g 111. TEST DATA SUhihi ARY l A. Plant Information Owner Boston Edison Company Plant Pilgrim Nuc1 car Power Station Unit 1 location Plymouth, hiassachusetts I Containment Type BWR hiark i NSSS Supplier, Type General Electric BWR 4 Date Test Completed August 5,1991 g B. Technical Data

1. Containment l Net Free Air Volume 263,520 cu. ft.

2. Design Pressure, P 56 psig

3. Design Temperature, T 281'F

4. Calculated Peak 45 psig Accident Pressure, P, I 5. Containment ILRT 60-120*F Avg. Temp. Limits

6. Calculated Peak 281*F Accident Temperature jg C. Test Results - Type A Test

1. Test hiethod Absolute

2. Test Pressure 45.99 psig 11 I

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3. Integrated Leakage Rate Total Time Analysis (Calculated per 13N-T0; Test Results:

I a. Calculated Leakage Rate, from regression line, L., 0.3122 wt.7c/ day

b. Upper 95Fe Confidence Limit 0.3322 wt.CF/ day

4. Integrated Leakage Rate Mass Poliit Analysis Test Results (Presented for information only):

a. Calculated Leakage g Rate, from regression line, L., 0.3150 wt.9F/ day

b. Upper 9596 Confidence Limit 0.3184 wt.0F/ day

5. Maximum Allowable 1.000 wt.9F/ day 12akage Rate, L,

6. ILRT Acceptance Criteria 0.750 wt.CF/ day (750F of L )

7. Verification Test imposed 7.5 scfm Leakage Rate (L,) (1,0003 wt.fc/ day)

8. Verification Test Total Time Analysis Results and Limits I a. Upper Limit (I3+ L,, + 0.25 L )

1.5625 wt.7e/ day I b. Verification Test Total Time Results 1.5115 wt.7c/ day

c. Lower Limit 1.0625 wt 9F/ day (13 4 L,, - 0.25 L.)

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I Verification Test hiass Point Analysis Results and Limits (Presented for information only)

a. Upper Limit 1.5652 wt.fc/ day (13 + L,, + 0.25 L )

b. Verification Test 1.5180 wt.96/ day hiass Point Results l c. IAwer Limit (13 + L., - 0.25 L.)

1.0652 wt.9F/ day

10. Report Printouts g The Report Printouts of the Type A and verification test calculations are provided for the Mass Point and Total Time Analysis (Appendices B and C). Stabilization data is also provided (Appendix A).

D. Test Results - Types B and C Tests A summary of local leakage rate test results since the last ILRT in December 1987 are provided in Appendix G.

E. Integrated I.rakage Rate Measurement System

1. Absolute Pressure (2 Sensors)

Type Mensor Quartz Manometer Range 0100 psia I Accuracy 10.010Tc of reading 10.00206 F.S.

15 microns Repeatabili:y 10.00057c F.S.

Sensitivity 10,001 psi Resolution 0.001 psi Calibration Date 3/8/91 l Instrument Numbers: RSP-906, RSP 907 I

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2. Drybulb Temperature (18 Sensors) g Type 100 ohm platinum RTDs Calibrated Range 60-120"F Accuracy 10.5*F Repeatability 10.01 *F Sensitivity 10.001*F Resolution 0.00l*F g Calibration Date 6/29/91 l 3. Dewpoint Temperature (10 Sensors)

Type Foxboro Lithium Chloride Dewcells Calibrated Range 37.5 100"F Accuracy i 1.5*F Repeatebility 10.5"F g Sensitivity 10.001*F Resolution 0.00l*F l Calibration Date 7/11/91

4. Verification Flow (1 Channel plus 1 Spare) g Flow Meter Datametrics Therrnal Mass Flowmeters Range O to 15 sefm l Accuracy Sensitivity i1% FS i .1% FS Repeatability 101G FS Calibration Date 3/15/91 I

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I 5. Overall Instrumentation Selection Guide (1S0) Value from ANSI /ANS 56.81987 based on ILitT instrutnentation configuration at end of II.llT and an eight hour test = 0.0206% wt./ day (sec l Appendix D for calculations).

6. Sensor Locations and Volume Fractions Appendix !!, Sensor Locations contains descriptions of the sensor locations as installed for the 1991 ILitT.

g G. Information Retained at Plant The following infortnation is available for review at the facility:

I 1. Access controls that were established to limit ingress to containment during testing.

2. A listing of all containment penetrations, including the total number g of like penetrations, penetration size, and function.

3. A listing of normal operating instrumentation used for the leakage l rate test.

4. A system lineup (at time of test), showing required valve positions I and status of piping systens.

I 5. A continuous, sequential log of events from initial survey of containment to restoration of all tested systems.

6. Documentation of instrumentation c:dibrations and standards, included with documentation is a failure analysis of instrumentation.

l 7. Data to verify temperature stabilization criteria as established by test procedure (Appendix A).

8. The working copy of tot procedure that includes signature sign off of procedural steps.

9. The procedure and all data that verifies completion of penetrations l and valve testing (B&C type tests), including as-found leak rates, corrective action taken, and final leak rate.

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10. Computer printouts of Integrated Leakage flate Test Data and automated data accumulation along with summary description of computer program.

11. The Quality Assurance st rveillance checklist that was used to monitor llJIT with proper sign offs.

12. A listing of all test exceptions including changes in containtnent I system boundaries instituted by licensee to conclude successful testing.

13. A review of confidence limits of test results with accompanying computer printouts where applicable.

l 14. Dese;iption of method of leakage rate verification of instrument measming system (superimposed leakage), with calibration info.trnation of flowmeters along with calculations that were used to measure the verification leakage rate (Appendix C).

l 15. Plot presenting ILitT data obtained during the test (Appendix II).

16. The P&lDs of pertinent systems.

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i IV. ANA13 SIS AND INTL!RPRETATION Several corrections must be considered for addition to the calculated results of the l ILRT.

A. Type 13&C Penalties The following corrections must be added for valves / penetrations which were not in their normal post accident condition:

Penetration Description leakate (SCCM)

I 9A Feedwater (including 233 RCIC and RWCU) 9 13 Feedwater (including IIPCI) 86 I 12 Residual lleat Removal (Shutdown Cooling) 15 14 Reactor Water Clean 4, 211 23 Reactor Building Closed 37 Cooling Wate: Supply 24 Reactor 13uilding Closed 5 Cooling Water Return 40Dc Jet Pump Sensing - Post 910 Accident Sampling 40Aa Jet Pump Sensing - Post 15 Accident Sampling I 41A Recire Sample 3 46A Reactor Recirc Seal 582 g

46B Reactor Recirc Seal 1915 47 ILRT Instrumentation 276 2280 Post Accident Sampling 216 22811 Post Accident Sampling 7 I which equates to an addition of 0.022 %wt./ day.

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g 13. Volume Change Corrections !

The following cotrections are made for any liquid level changes which l resulted in an decrease in the net free volume of the containment:

1. Reactor vessel volume change: 0 1

2. Equipment Drain Sump volume change: +33.88 cu. ft./ day

3. Floor Drain Surnp volume change: 0

4. Torus volume change: +79.27 cu. ft./ day Total Water Level Change Volume Correction: +113.15 cu. ft./ day This is equivalent to 0.0437c/ day increase in the leakage rate.

I C. Reported "As Left" ILRT Results The results of the ILRT to be reported including all corrections are:

Mass Point Total Time Analysis - Analysis

1. Measured Leakage Rate 0.318496 0.33229h at 957c UCL (9'wt./

c day)

I 2. Final water volume 0.0439h 0.0439h/ day level corrections

3. Corrections for valves 0.0229h 0.0229h not in Accident Positivns

4. "As Left" leakage rate 0.38349h 0.39729h (7 cwt./ day) (Total of items 1 through 4)

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D. "As Found" Evaluation of the Containment The "as found" containment integrated leakage rate (on a minimum pathway basis) exceeded the acceptance criteria of 1% weight per day due to g excessive leakage from Feedwater check valves 6 58A,6 62A,6 588, and 6 62B. The excessive leakage was due to misalignment of the valve discs relative to their seats.This misalignment was most likely a result of previous l maintenance on the valves. The immediate corrective actions taken included:

1. Installing a 1/32 inch radius on the leading edge of the seat rings to minimize the potential for cutting of the soft seat as the disc enters the valve seat.

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2. Replacement of all four discs (including the soft seats).

3. Modification of the hinge pin / cover arrangement with an anti-rotation pin and new hinge pin cover.

4. Machining of the bonnet pressure seal.

Long term corrective action will include the following:

1. Revising the valve drawings to indicate the correct tolerance on the soft seat protrusion.

l 2. Revising the applicable maintenance procedure to provide better guidance on disc alignment and tolerances.

3. Establishing a prewntative maintenance program for the Feedwater check valves.

4. Evaluating alternative means for Feedwater System containment isolation.

I The Feedwater check valve failures were analyzed through Boston Edison Company's LLRT Failure Analysis Team (FAT). The team is multi disciplinary, comprised of members from both the Nuclear Engineering and Nuclear Operations Departments. The FAT is chartered to determine root cause and recommend I corrective actions for each valve that has failed to pass a LLRT. Corrective action includes repair or modification to address the root cause of the excessive leakage, an evaluation of the impact of the root cause on valves of similar design, and a l review of the testing program for adequacy and frequency to detect these valve failures. The FAT Root Cause Analysis is enclosed in Appendix H.

l 19

l V. REFERENCES A. Pilgrim Nuclear Power Station, FSAR.

I B. Pilgrim Nuclear Power Station, Technital Specifications.

I C. Pilgrim Nuclear Pov.er Station, Procedure 8.7.1.4.2 Rev. 9, Integrated leakage Rate Test Surveillance Procedure.

D. Code of Federal Regulations, Title 10, Part 50, Appendix J, Primary Reactor Containment leakage Testing for Water Cooled Power Reactors.

I E. ANSl/ANS 56.81987, Containment System leakage Testing Requirements.

I F. Bechtel Topical Report BN TOP 1, Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants, Revision 1,1972.

I G. ANSI N45.41971, leakage Rate Testing of Containment Structures for Nuclear Reactors I

I I

I I 20 I

I I

I al,1, . iim STAllil.lZATION l'lIASE DATA I

I I

I l I

l STABLIZATION MODE TIME 1014 OPTIO!is MODE

SUMMARY

I - MAliUAL DATA ENTRY # OF DATA POI!1TS : 17 2 - PARAMATER GRAPHS MODE DURATION (114 HRS) : 4 3 - SEliSOR PLOTS TOT TIME MEASURED LEAK : 0.3017 4 - SE!1SOR DIFFERENTIALS TOT TIME CALCULATED LEAK : 0.2519 5 - AliSI STABILIZATION CRITERIA TOT TIME 05% UCL : 0,3501 6 - Bli-TOP-I STAB. CRITERIA MASS PT LEAK : 0,2804 7 - /iliSI CRITERIA PRINTOUT MASS PT Ob% UCL = 0.2943 6 - B!i-TOP-I CRITERIA PRIliTOUT 9 - REPRIliT CURREliT DATA PolllT P - PASS WORD ME!4U 0 - FLASH OFF AllSI PRESSURE /TEMPERATUFE STABLE CRITERIA MET Bli-TOP TEMPERATURE CRITERIA MET DIliT

SUMMARY

CURREliT VALUE/ DIFFERENCE FROM PREVIOUS POI!1T 70.895/ -0.047 AVG PRESS: 00.373/ -0.007 IVG ASS:TEMP: 79734.73/ -2.727 AVG DEW PRESS: 0.4665/-0.0007 9.2363, ,

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I G614/ 217 TIME 1014/ 217 I

i DN-TOP-1 51AELIZATICN CRITERIA TIME 1EMP BN DN di dT2 4.00 78.8954 -0.2537 -0.2305

, 3.75 78.9426 -0.2773 -0.2471 l g 3.50 78.9942 -0.3015 -0.2646 g 3.25 79.0400 -0.3201 -0.2820 3.00 79.1005 -0.3455 -0.3045 2.75 79.1559 -0.3761 -0.3315 2.50 79.2211 -0.4115 -0.3579 2.25 79.2865 -0.4542 -0.3918 2.00 79.3565 -0.b188 -0.4368 i .75 79.4368 0.0000 O.0000 1.50 79.5235 0.0000 0.0000 1.25 79.6119 0.0000 0.0000 1.00 79.7095 0.0000 0.0000 I0.750.50 79.8188 79.9370 0.0000 0.0000 0.0000 0.0000 0.25 80.0702 0.0000 0.0000 0.00 80.2301 0.0000 0.0000 I

I I

I I .

I I

l .

i e

I ETABILIZATICN AN5156.8

'IME TEMP $6.e 56.e 4-1 rREss 56.0 1 HR 4 HR HR dP F/HR F/HR P51/HR I

4.00 70.895 -0.205 -0.334 -0.129 60.373 .0303 70.943 -0.213 0.000 0.213 60.381 .0326 I 3.75 3.50 78.994 -0.'27 0.000 0.227 60.307 .0347 3.25 79.048 -0.239 0.000 0.239 60.397 .0339 3.00 79.101 -0.236 0.000 0.256 60.403 .0373 I2.7S 79.156 -0.281 0.000 0.281 60.413 .0379 2.50 79.221 -0.302 0.000 0.302 60.422 .0389 2.25 79.287 -0.325 0.000 0.325 60.431 .0415 I2.00 1.75 79.356 79.437

-0.353

-0.382 0.000 0.000 0.353 0.382 60.441 60.451

.044S

.04BS 1.b0 79.D24 -0.414 0.000 0.4*4 60.461 .Ob41 79.612 -0.450 0.000 0.458 60.473 .059b I1.25 1.00 79.710 -0.S21 ') . 000 0.521 60.4ES .0600 0.75 79.819 0.000 0.000 0.000 60.S00 0.0000 79.937 0.000 0.000 0.000 60.S15 0.0000 IO.50 O.2S 80.070 0.000 0.000 0.000 60.S32 0.0000 I

I I

I I ,

I I

I

6 1

AVG. DATA VALUES UNIT N 1 DATE TIME T(1) P(l) D1(1) UP(!) Mass (I) 217 0.00 80.230 60.553 78.311 0.479 79774.84 217 0.25 80.070 60.532 70.348 0.400 79770.40 217 0.50 79.937 60. Sib 78.289 0.479 79767.34 l 217 0.75 79.D19 60.SOO 78.225 0.478 79764.01 217 1.00 79.710 60.48b 78.137 0.477 79762.16 i

I 217 217 1.25 1.50 79.612 79.524 60.473 60.461 78.114 78.068 0.476 0.476 79759.77 79757.13 217 1.75 79.437 60.451 77.967 0.474 79757.36 I 217 217 217 2.00 2.25 2.50 79.356 79.287 79.221 60.441 60.431 60.122 77.894 77.029 77.741 0.473 0.472 0.471 79755.64 797S3.10 79750.59 l

. gg 217 217 2.75 3.00 79.156 60.',13 77.676 0.470 79748.89 I

79.101 60.403 77.649 0.469 79744.31 217 3.25 79.048 60.397 77.471 0.466 79743.71 217 3.50 78.994 60.387 77.531 0.467 79738.43 217 3.75 78.943 60.301 77.464 0.466 79737.45 1

217 4.00 78.895 60.373 77.416 0.466 79734.73 f

I I

1I 1I

I

ISTABLIZATION HODE TIME - 1014 OPTIONS MODE

SUMMARY

1 - HANUAL DATA ENTRY # OF DATA POINTS : 17 2 - PARAMATER GRAPHS MODE DURATION (IN HRS) : 4 3 - SEllSOR PLOTS TOT TIME MEASURED LEAK : 0.3017 4 - SENSOR DIFFEREllTI ALS TOT TIME CALCULATED LEAK : 0.2519 5 - ANSI STABILIZATION CRITERIA TOT TIME 95% UCL : 0.3591 6 - DN-TOP-1 STAB. CRITERIA MASS PT LEAK : 0.2904 7 - ANSI CRITERIA PRINTOUT MASS PT 95% UCL : 0.2943 IB9 - REPRINT BN-TOP-1CURRENT CRITERI A PRIt1 TOUT DATA POINT P - EASS WORD MENU 0 - FLASH OFF ANSI PRESSURE / TEMPERATURE STABLE CRITERIA MET BN-TOP TEMPERATURE CRITERIA MET DINT

SUMMARY

CURREliT VALUE/DIFFERE!1CE FROM PREVIOUS POINT 78.895/ -0.047 AVG PRESS: 60.373/ -0.007 IVGTEMP:

ASS: 79734.73/ -2.727 AVG DEW PRESS: 0.4655/-0.0007 I O.2271 6

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G614/ 217 TIME 1914/ 217

e 1

STABLIZATION MODE TIriE -

1014 OPTIONS MODE

SUMMARY

1 - MANUAL DATA ENTRY # OF DATA POINTS : 17 2 - PARAMATER GRAPHS MODE DURATION (IN HRS) =4 13-SENSORPLOTS TOT TIME MEASURED LEAK = 0.3017 4 - SENSOR DIFFERENTIALS TOT TIME CALCULATED LEAK : 0.2519 35 - ANSI STABILIZATION CRITERIA TOT TIME 95% UCL 0.3591 F., - BN-TOP-1 STAB.C;:TFRIA MASS PT LEAK : 0.2804 7 - ANSI CRITERI A i'RI:. C OUT MASS PT 95% UCL = 0.2943 8 - BN-TOP-1 CRITERI A FRINTOUT 19 - REPRINT CURRENT DATA POINT P - PASS WORD MENU 0 - FLASH OFF ANSI PRESSURE / TEMPERATURE STABLE CRITERIA MET

BN-TOP TEMPERATURE CRITERIA MET JINT

SUMMARY

CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT VG TEMP: 78.895/ -0.047 AVG PRESS: 60.373/ -0.007 ASS: 79734.73/ -2.727 AVG DEW PRESS: 0.4655/-0.0007 b.5344: b, llNIT \

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4 0614/ 217 TIME 1814/ 217 I

i STABLIZATION MODE TIME -

1014 OPTIONS MODE

SUMMARY

1 - mat 10AL DATA ENTRY u 0F DATA POINTS : 17 MODE DURATION (IN HRS) : 4 12-PARAMATERGRAPHS 3 - SENSOR PLOTS TOT TIME HEASURED LEAK : 0.3017 4 - SENSOR DIFFERENTIALS TOT TIME CALCULATED LEAK : 0.2519 TOT TIME 95% UCL : 0.3591 MASS PT LEAK 0.2604 IS6 -- BN-TOP-I ANSI STABILIZATION STAB. CRITERIA CRITERI A MASS PT 95% UCL : 0.2943 7 - ANSI CRITERIA PRINTOUT 8 - BN-TOP-1 CRITERIA PRINTOUT 9 - REPRINT CURREllT DATA POINT P - PASS WORD MENU 0 FLASH OFF ANSI PRES 3URE/ TEMPERATURE STABLE CRITERIA MET BN-TOP TEMPERATURE CRITERIA MET DINT

SUMMARY

CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT AVG TEMP: 78.895/ -0.047 AVG PRESS: 60.373/ -0.007 ASS: 79734.73/ -2.727 AVG DEW PRESS: 0.4655/~0.0007 b.4513- j F

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3 0614/ 217 TIME 1014/ 217 l

e iTABLIZATIO!1 MODE TIME -

1014 PTIONS MODE

SUMMARY

1 - MANUAL DATA ENTRY # OF DATA POINTS : 17

- PARAMATER GRAPHS MODE DURATIO!1 (19 HRS) = 4 3 - SENSOR PLOTS TOT TIME MEASURED LEAK : 0.3017

- SENSOR DIFFERENTIALS TOT TIME CALCULATED LEAK 0.2519 5 - A11SI STABILIZATIO!1 CRITERIA TOT TIME 95% UCL : 0.3591 3 - BN-TOP-1 STAB. CRITERIA MASS PT LEAK : 0.2804 R7 - ANSI CRITERI A PRINTOUT MASS PT 95% UCL : 0.2943 8 - BN-TOP-1 CRITERI A PRINTOUT

- REPRINT CURREllT DATA POINT

' - PASS WORD MENU

- FLASH OFF ANSI PRESSURE / TEMPERATURE STABLE CRITERI A MET BN-TOP TEMPERATURE CRITERIA MET INT

SUMMARY

CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT AVG TEMP: 78.895/ -0.047 AVG PRESS: 60.373/ -0.007 SS: 79734.73/ -2.727 AVG CEW PRESS: 0.4055/-0.0007 l 1. 0331 gHiT 1~ N _

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, .q e614/ 217 TINE 1014/ 217 I

I TIME -

1014 I"TADLIZATIONMODE OPTIONS MODE

SUMMARY

I - MANUAL DATA ENTRY # OF DATA POINTS : 17 I2 - PARAMATER GRAPHS MODE DURATION (IN HRS) 4 3 - SENSOR PLOTS TOT TIME MF ASURED LEAK = 0.3017 4 - SENSOR DIFFERENTIALS TOT TIME CALCULATED LEAK : 0.2519 I5-ANSISTABILIZATIONCRITERIA TOT TIME 95% UCL = 0.3591 6 - BN-TOP-1 STAB. CRITERIA MASS PT LEAK : 0.2804 7 - ANSI CRITERIA PRINTOUT MASS PT 95% UCL : 0.2943 IB9 -- REPRINT BN-TOP-1 CURRENT CRITERI A PRINTOUT DATA POINT P - PASS WORD MENU 0 - FLASH OFF ANSI PRESSURE /TEMPEP.ATURE STABLE CRITERIA MET BN-TOP TEMPERATURE CRITERIA MET TOINT

SUMMARY

CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT 78.895/ -0.047 AVG PRESS: 60.373/ -0.007 IVGTEMP:

ASS: 79734.73/ -2.727 AVG DEW PRESS: 0 . 4 6 5 T,/ - 0 . 0 0 0 7 0 . 48 GV'. .

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STABLIZATION MODE TIME -

1014 OPTIONS MODE

SUMMARY

1 - MANUAL DATA ENTRY # OF DATA POINTS : 17 MODE DURATION (IN HRS) = 4 12-PARAMATERGRAPHS 3 - SENSOR PLOTS TOT TIME MEASURED LEAK : 0.3017 4 - SENSOR DIFFERENTIALS TOT TIME CALCULATED LEAK : 0.2519 S - ANSI STABILIZATION CRITERIA TOT TIME 95% UCL = 0.3591 I6 - BN-TOP-1 STAB,CRITERI A MASS PT LEAK : 0.2804 7 - ANSI CRITERI A PRINTOUT MASS PT 95% UCL : 0.2943 8 - BN-TOP-1 CRITERIA PRINTOUT 19P --PASS REPRINT WORD MENU CURRENT DATA POINT 0 - FLASH OFF ANSI PRESSURE / TEMPERATURE STABLE CRITERI A MET BN-TOP TEMPERATURE CRITERIA MET DINT

SUMMARY

CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT ASS 79J4.7N 2.727 A ;ESS: 0465/-0 BOO 7 b.7977~< T llMI T 1:: \, s

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I I

'I E Appetidix 11 I IIOLD TEST DATA AND l' LOTS

I I

I _. ._ _ .. -

7 CST MODE PLEASE SELECT THE OPTION YOU WISH TO USE: TEST DATA 1814 1 -

MANUAL DATA ENTRY tt OF DATA POINTS = 33 2 -

PARAMETER GRAF HS MODE DURATION (IN HOURS) = 8 3 -

SENSOR PLOTS TOT TIME MEASURED LEAK = 0.3168 4 -

TREND ANALYSIS TOT TIME CALCULATED LEAK = 0.3122 5 -

REPRINT CURRENT DATA PT TOT TIME 95% UCL = 0.3322 6 -

SENSOR DIFFERENTIALS MASS POINT LEAK = 0.3150 MASS POINT 95% UCL = 0.3184 75% La = .75 P -

PASS WORD MENU MASS = 79650.52 SELECTED OPTION =

DINT

SUMMARY

CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT AVG TEMP: 78.187 / -0.007 AVG PRESS: 60.230 / -0.003 79650.52 / -2.89B AVG DEW PRESS: O.4561 /-0.0001 I ASS:

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l

ITEST MODE PLEASE SELECT THE OPTION YOU W]SH TO USE: TEST DATA 1814 1 -

MANUAL DATA ENTRY H OF DATA POINTS = 33 2 -

PARAMETER GRAPHS MODE DURAT1ON (IN HOURS) = 8 3 -

SENSOR PLOTS TOT TIME MEASURED LEAK = 0.3168 4 -

TREND ANALYSIS TOT TIME CALCULATED LEAK = 0.3122 5 -

REPRINT CURRENT DATA PT TOT TIME 95'/. UCL = 0.3322 6 -

SENSOR DIFFERENTIALS MASS POINT LFAK = 0.3150 MASS POINT 95*/. UCL = 0.3184 1 7 5'/. L a = .75 P -

PASS WORD MENU MASS = 79650.52 SELECTED OPTION =

OINT

SUMMARY

CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT 78.187 / -0,007 AVG PRESS: 60.230 / -0.003 ASS: 79650.52 / -2.898 AVG DEW PRESS: 0.4561 /-0.0001 IVGTEMP:

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1014/ 217 TIME 1814/ 217 1

e I AVG. DATA VALUES UNIT # 1 I DATE TIME T(I) P(!) DT(1) VP(I) MASS (1) 217 0.00 78.895 60.373 77.416 0.466 79735 217 0.25 78.849 60.366 77.389 0.465 79732 I 217 217 0.50 0.75 78.807 78.766 60.359 60.353 77.350 77.297 0.46S 0.464 79729 79727 217 1.00 78.729 60.347 77.244 0.463 79725 217 1.25 78.692 60.341 77.173 0.462 79722 1 217 1.50 78.658 60.335 77.151 0.461 79720 217 1.75 78.627 60.329 77.179 0.462 79716 217 2.00 78.594 60.324 77.090 0.461 79714 217 2.25 78.567 60.318 77.122 0.461 79711 217 2.50 78.536 60.314 77.054 0.460 79710 217 2.75 78.508 60.309 77.013 0.4S9 79708 I 217 217 3.00 3.25 78.481 78.460 60.305 60.300 76.973 76.984 0.459 0.459 79706 79703 217 3.50 78.438 60.296 76.967 0.459 79700 217 3.75 78.416 60.292 76.931 0.458 79698 l 217 4.00 78.400 60.286 76.983 0.459 79693 l

217 4.25 78.380 60.283 76.989 0.459 79691 l .g 217 4.50 78.363 60.280 76.952 0.458 70690 3 217 4.75 78.350 60.275 76.943 0.458 79686 217 5.00 78.329 60.271 76.955 0.459 79683 g 217 5.25 78.316 60.267 76.944 0.458 79680 (g 217 217 5.50 5.75 78.300 78.286 60.263 60.259 76.899 76.898 0.458 0.45e 79678 79675 l

l 217 6.00 78.270 60.256 76.862 0.457 79672 217 6.25 78.255 60.253 76.851 0.457 79671 217 6.50 78.244 60.249 76.857 0.457 79668 217 6.75 78.232 60.245 76.866 0.457 79663 217 7.00 78.221 60.243 76.762 0.456 79663 217 7.25 78.211 60.239 76.833 0.457 79659 217 7.50 78.200 60.237 76.791 0.456 79657 217 7.75 78.193 60.233 76.802 0.456 79653 217 8.00 78.187 60.230 76.796 0.456 79651 l

I l

I

I I

t TREND REPORT UNIT M 1 LMCALC SL LAM L95 l' DATE 217 TIME 0.00 TTLM 0.0000 0.0000 0.0000 0.0000 0.0000 217 0.25 0.3036 0.0000 0.0000 0.0000 0.0000 I 217 217 0.50 0.75 0.3332 0.3108 0.0000 0.3194 0.0000 0.5248 0.3943 0.3336 0.3160 0.3040 0.4781 0.3519 0.3278 217 1.00 0.3006 0.3073 I 217 217 217 1.25 1.50 1.75 0.2971 0.2991 0.3244 0.2999 0.2973 0.3077 0.3556 0.3395 0.3544 0.2981 0.2961 0.3110 0.3143 0.3069 0.3291 0.3001 0.3221 I 217 217 217 2.00 2.25 2.50 0.3050 0.3226 0.3003 0.3C62 0.3119 0.3081 0.3463 0.3500 0.3437 0.3152 0.3093 0.3286 0.3217 217 2.75 0.2976 0.3045 0.3379 0.3042 0.3157 I 217 217 3.00 3.25 0.2932 0.2984 0.3006 0.2991 0.3323 0.3288 0.3259 0.2992 0.2982 0.2970 0.3101 0.3075 0.3051 217 3.50 0.2984 0.2980 I 217 217 217 3.75 4.00 4.25 0.2948 0.3109 0.3062 0.2963 0.2986 0.2995 0.3228 0.3253 0.3254 0.2953 0.2988 0.3004 0.3026 0.3063 0.3072 217 4.50 0.2988 0.2988 0.3236 0.2995 0.3056 217 4.75 0.3073 0.2998 0.3241 0.3016 0.3073 217 5.00 0.3113 0.3014 0.3256 0.3038 0.3094 217 5.25 0.3145 0.3034 0.3276 0.3063 0.3121 217 5.50 0.3117 0.3046 0.3284 0.3075 0.3130 217 5.75 0.3152 0.3062 0.3297 0.3095 0.3148 217 6.00 0.3131 0.3072 0.3303 0.3108 0.3158 217 6.25 0.3081 0.3074 0.3298 0.3104 0.3151 217 6.50 0.3112 0.3079 0.3299 0.3110 0.3153 217 6.75 0.3194 0.3096 0.3315 0.3129 0.2173 217 7.00 0.3091 0.3097 0.3311 0.3124 0.3166 I 217 217 7.25 7.50 0.3147 0.3104 0.3104 0.3106 0.3315 0.3312 0.3132 0.3133 0.3172 0.3170 217 7.75 0.3158 0.3114 0.3316 0.3141 0.3176

=

217 8.00 0.3168 7.3122 0.3322 0.3150 0.3184 I

I I

0 EST MODE PLEASE SELECT THE OPTION YOU WISH TO USE: TEST DATA 1814 1 -

MANUAL DATA ENTRY *t OF DATA POINTS = 33 2 -

PARAMETER GRAPHS MODE DURATION (IN HOURS) = 8 3 -

SENSOR PLOTS TOT TIME MEASURED LEAK = 0.3168 TREND ANALYSIS TOT TIME CALCULATED LEAK = 0.3122 145 -

REPRINT CURRENT DATA rT 3 TOT TIME 95% UCL = 0.3322 6 -

SENSOR DIFFERENTIALS MASS POINT LEAK = 0.3150 MASS POINT 95'/. UCL = 0.3184 1 75% La = .75 P -

PASS WORD MEf10 MASS r 79650.52 SELECTED OPTION =

DINT

SUMMARY

LURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT AVG TEMP 78.187 / -0.007 AVG PRESS: 60.230 / -0.003 ASS: 79650.52 / -2.898 AVG DEW PRESS: 0.t'561 /-0.0001 k8.8953 t, llHIT 1 : \

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9 TEST MODE l ' LEASE SELECT THE OPTION YOU WISH TO USE: TEST DATA 1814 1

MANUAL DATA ENTRY M OF DATA POINTS = 33 2 -

PARAMETER GRAPHS MODE DURATION (IN HOURS) = 8 3 -

SENSOR PLOTS TOT TIME MEASURED LEAK = 0.3160 TREND ANALYSIS TOT TIME CALCULATED LEAK = 0.3122 5 -

REPRINT CURRENT DATA PT TOT TIME 95*. UCL = 0.3322 6 -

SENSOR DIFFERENTIALS MASS POINT LEAK = 0.3150 I MASS POINT 95*/. UCL 0.3184

=

7 5'/. L a = .75 P -

PASS WORD MENU MASS = 79650.52 SELECTED OPTION =

JINT

SUMMARY

CLWRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT AVG TEMPS 78.187 / -0.007 AVG PRESS: 60.230 / -0.003 SS: 79650.52 / -2.898 AVG DEW PRESS: 0.4561 /-0.0001 Ie.373~. ..

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i TEST MODE PLEASE SELEET THE OPTION YOU WISH TO USE: TEST DATA 1814 1 -

MANUAL DATA ENTRY H OF DATA POINTS = 33 2 -

PARAMETER GRAPHS MODE DURATION (IN HOURS)

8 SENSOR PLOTS TCT TIME MEASURED LEAK = 0.3168 13 4 -

TREND ANALYSIS TOT TIME CALCULATED LEAK = 0.3122 5 -

REPRINT CURRENT DATA PT TOT TIME G5*/. UCL = 0.3322 6 -

SENSOR DIFFERENTIALS MASS POINT LEAK = 0.3150 MASS POINT 95*/. UCL = 0.3184 75*/. La = .75 P -

PASS WORD MENU MASS = 79650.52 SELECTED OPTION =

OINT GUMMARY: CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT VG TEMP: 78.187 / -0.007 AVG PRESS: 60.230 / -0.003 ASS: 79650.52 / -2.898 AVG DEW PRESS: 0.4561 /-0.0001

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l 1G14/ 217 TIME 1814/ 217 I

1 l

I TEST MODE I PLEASE SELECT THE OPTION TEST DATA 1814 YOU WISH TO USE:

1 -

MANUAL DATA ENTRY # OF DATA POINTS : 33 2 -

PARAMETER GRAPHS MODE DURATION (IN HOURS) =8 E3 -

SENSOR PLOTS TOT TIME MEASURED LEAK = 0.3168 E -

TREND ANALYSIS TOT TIME CALCULATED LEAK : 0.3122 5 -

REPRINT CURRENT DATA PT TOT TIME 95% UCL = 0.3322 S -

SENSOR DIFFERENTIALS MASS POINT LEAK = 0.3150 I MASS POINT 95% UCL : 0.3184 75% La : .75 P -

PASS WORD MENU HASS : 79650.52 SELECTED OPTION:

DINT

SUMMARY

- CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT VG TEMP: 78.187 / -0.007 AVG PRESS: 60.230 / -0.003 ASS: 79650.52 / -2.898 AVG DEW PRESS: 0.4561 /-0.0001 IO 4663, llNI T 1"..\ .

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l 1014/ 217 TIME 1814/ 217 I

TEST MODE PLEASE SELECT THE OPTION l YOU WISH TO USE: TEST DATA 1814 I l

1 -

MANUAL DATA ENTRY H OF DATA POINTS = 33 ;

2 -

PARAMETER GRAPHS MODE DURATION (IN HOURS) = 8 !

3 -

SENSOR PLOTS TOT TIME MEASURED LEAK = 0.3160 ,

1A -

TREND ANALYSIS TOT TIME CALCULATED LEAK = 0.3122 S -

REPRINT CURRENT DATA PT TOT TIME 95% UCL = 0.3322 6 -

SENSOR DIFFERENTIALS MASS POINT LEAK = 0.3150 MASS POINT 95% UCL = 0.3184 75% La = .75 P -

PASS WORD MENU MASS = 79650.52 SELECTED OPTION =

OINT

SUMMARY

CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT VG TEMP: 70.187 / -0.007 AVG PRESS: 60.230 / -0.003 ASS: 79650.52 / -2.898 AVG DEW PRESS: 0.4561 /-0.0001 b.7973X IfNIT 1 ~.

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l 1814/ 217 TIME 1814/ 217

'I

I I

I Appendix C VERIFICATION PIIASE DATA AND PLOTS I

I I

e ERIFICATION MODE TIME = 2350 OPTIONS: TEST

SUMMARY

1 -

MANUAL DAiA ENTRY # OF DATA POINTS = 17 2 -

PARAMETER GRAPHS MODE DURATION (IN HOURS) = 4 3 -

SENSOR PLOTS TOT TIME MEASURED LEAK = 1.5343 4 -

TREND ANALYSIS TOT TIME CALCULATED LEAK = 1.5115 s -

REPRINT CURRENT DATA PT MASS PT LEAK = 1.5180 SENSOR DIFFERENTIALS IMPOSED LEAK = 1.0003 TOT T!r.E UPPER LIMIT = 1.5625 P -

PASS WORD MENU TOT TIME LOWER LIMIT = 1.0625 MASS PT UPPER LIMIT = 1.5652

'LECTED OPTION e MASS PT LOWER LIMIT = 1.0652 TOT TIME VERIFICATION CRITERIA HAS BEEN MET MASS PT VERIFICATION CRITERIA HAS BEEN MET INT

SUMMARY

CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT AVG TEMP: 78.009/ --O.008 AVG PRESS: 69.004/ -0.013 SS: 79377.91/ -16.172 AVG DEW PRESS: 0.4537/+0.0020 k.7652;.

$ NIT 1" r._ --

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I= El l

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l 1950/ 21? TIME 235G/ 217 lI

e iERIFICATIONMODE TIME = 2350 OPTIONS: TEST

SUMMARY

1 -

MANUAL DATA ENTRY tt OF DATA POINTS r 17 2 -

PARAMETER GRAPHS MODE DURATION (IN HOURS) = 4 3 -

SENSOR PLOTS TOT TIME MEASURED LEAK = 1.5343 4 -

TREND ANALYSIS TOT TIME CALCULATED LEAK = 1.5115 5 -

REPRINT CURRENT DATA PT MASS PT LEAK = 1.5180 6 SENSOR DIFFERENTI AL S IMPOSED LEAK = 1.0003 I

TOT TIME UPPER LIMIT = 1.5625 P -

PASS WORD MENU TOT TIME LOWER LIMIT = 1.0625 MASS PT UPPER LIMIT = 1.5652 ELECTED OPTION = MASS PT LOWER LIMIT = 1.0652 TOT TIME VERIFICATION CRITERIA HAS BEEN MET MASS PT VERIFICATION CRITERIA HAS BEEN MET DINT

SUMMARY

CURRENT VALUE/DIFFERENEE FROM PREVIOUS POINT

" AVG TEMP: 78.009/ -0.008 AVG PRESS: 60.004/ -0.013 MASS: 79377.91/ -16.172 AVG DEW PRESS: 0.4537/+0.0020

[.7652 MIT 1" MASS "

/

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s b tNbb , , , t 1950 217 TIHE 2350/ 217

AVG. DATA VALUES UNIT 4 1 11MC DT(I) VP(1) MAGE (1)

I DATE T(1) P(I) 217 0.00 78.127 60.171 76.748 0.455 79581.42 217 0.25 78.121 60.161 76.731 0.455 79568.72 217 0.50 78.114 60.1S1 76.630 0.454 79556.96 217 0.75 78.104 60.140 76.705 0.455 79543.66 217 1.00 78.087 60.129 76.703 0.455 79532.09 I 217 217 217 1.25 1.50 1.7S 78.079 78.068 78.064 60.118 60.109 60.099 76.701 76.718 76.693 0.455 0.455 0.455 79518.61 79507.87 79495.05 2.00 78.057 60.089 76.697 0.455 79482.52 I

217 217 2.25 78.051 60.078 76.653 0.434 79469.56 217 2.50 78.04S 60.068 76.663 0.454 79456.92 217 2.7S 70.039 60.058 76.666 0.454 79444.43 217 3.00 70.035 60.048 76.66a O.454 79431.72 217 3.25 78.027 60.037 76.613 0.453 79418.53 _

217 3.50 78.022 60.027 76.622 0.433 79405.76 I 217 217 3.75 4.00 70.017 78.009 60.017 60.004

76. SOS 76.639 0.452 0.454 79394.08 79377.91 I

I I .

I I -

I I

I

IRIFICATION MODE TIME = 2350 OPTIONS: TEST

SUMMARY

I 1 -

MANUAL DATA ENTRY tt OF DATA POINTS =

MODE DURATION (IN HOURS) = 4 17 2 -

PARAMETER GRAPHS 3 -

SENSOR PLOTS TOT TIME MEASURED LEAK = 1.5343 14 -

TREND ANALYSIS TOT TIME CALCULATED LEAK = 1.5115 5 -

REPRINT CURRENT DATA PT MASS PT LEAK = 1.5180 SENSOR DIFFERENTIALS IMPOSED LEAK = 1.0003 IS TOT TIME UPPER LIMIT = 1.562S P -

PASS WORD MENU TOT TIME LOWER LIMIT = 1.062S MASS PT UPPER LIMIT = 1.5652 ILECTED CPTION = MASS PT LOWER LIMIT = 1.0652 TOT TIME VERIFICATION CRITERIA HAS BEEN MET MASS PT VERIFICATION CRITERIA HAS DEEN MET INT

SUMMARY

CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT

.vG TEMP: 78.009/ -0.008 AVG PRESS: 60.004/ -0.013 ASS: 79377.91/ -16.172 AVG DEW PRESS: 0.4537/+0.0020 l8.18T';. ..

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l8, gag 1950/ 217 TIME 2350/ 217 I

I

iIRIFICATIONMODE TIME = 2350 OPTIONS: TEST

SUMMARY

1~ ~

MANUAL DATA ENTRY 4 OF DATA POINTS = 17 2 -

PARAMETER GRAPHS MODE DLIRATION (IN HOURS) = 4 3 -

SENSOR PLOTS TOT TIME MEASURED LEAK = 1.5343 14 -

TREND ANALYSIS TOT TIME CALCULATED LEAK = 1.5115 5 -

REPRINT CURRENT DATA PT MASS PT LEAK = 1.5180 g6 -

SENSOR DIFFERENTIALS IMPOSED LEAK = 1.0003 g TOT TIME UPPER LIMIT = 1.5625 P -

PASS WORD MENU TOT TIME LOWER LIMIT = 1.0625 MASS PT UPPER LIMIT = 1.5652 LECTED OPTION = MASS PT LOWER LIMIT := 1.0652 TOT TIME VERIFICATION CRITERIA HAS BEEN MET MASS PT VERIFICATION CRITERIA HAS BEEN MET INT

SUMMARY

CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT AVG TEMP: 78.009/ -0.008 AVG PRESS: 60.004/ -0.013

" SS: 79377.91/ -16.172 AVG DEW PRESSr O.4537/+0.0020

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.i 8

1950/ 217 TIME 235G/ 217

e iVERIFICATION MODE TIME = 2350 OPTIONS: TEST

SUMMARY

1 -

MANUAL DATA ENTRY # OF DATA POINTS = 17 PARAMETER GRAPHS MODE DURATION (IN HOURS) = 4 123 -

SENSOR PLOTS TOT TIME MEASURED LEAK = 1.S343 4 -

TREND ANALYSIS TOT TIME CALCULATED LEAK = 1.5115 S -

REPRINT CURRENT DATA PT MASS PT LEAK = 1.5100 I6 -

SENSOR DIFFERENTIALS IMPOSED LEAK TOT TIME UPPER LIMIT

=

1.0003 1.5625 PASS WORD MENU TOT TIME LOWER LIMIT = 1.0625 MASS PT UPPER LIMIT = 1.5652

_ LECTED OPTION = MASS PT LOWER LIMIT = 1.06S2 TOT TIME VERIFICATION CRITERIA HAS BEEN MET MASS PT VERIFICATION CRITERIA HAS BEEN MET

^] INT

SUMMARY

CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT AVG TEMP: 78.009/ -0.008 AVG PRESS: 60.004/ -0.013 SSt 79377.91/ -16.172 AVG DEW PRESS: 0.4537/+0.0020 k 6 . 7 487;'.s.

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I VERIFICATION MODE TIME = 2350 OPTIONS: TEST

SUMMARY

MANUAL DATA ENTRY # OF DATA POINTS = 17 PARAMETER GRAPHS MODE DURATION (IN HOURS) = 4 3 -

SENSOR PLOTS TOT TIME MEASURED LEAK = 1.5343 4 -

TREND ANALYSIS TOT TIME CALCULATED LEAK = 1.5115 REPRINT CURRENT DATA PT MASS PT LEAK = 1.5180 SENSOR DIFFERENTIALS IMPOSED LEAK = 1.0003 TOT TIME UPPER LIMIT = 1.5625 PASS WORD MENU TOT TIME LOWER LIMIT = 1.0625 MASS PT UPPER LIMIT = 1.5652 LECTED OPTION = MASS PT LOWER LIMIT = 1.0652 TOT TIMC VERIFICATION CRITERIA HAS BEEN MET MASS PT VERIFICATION CRITERIA HAS EEEN MET JINT

SUMMARY

CUnRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT G TEMP: 78.009/ -0.008 AVG PRESS: 60.004/ -0.013 ASS: 79377.91/ -16.172 AVG DEW PRESS: 0.4537/+0.0020 I O . 45 5~ . . ....

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l 1950/ 21? TIME 235G/ 217

.I

ERIF1 ATION MODE TIMEe 2350 OPTIONS: TEST

SUMMARY

a -

MANUAL DATA ENTRY # OF DATA POINTS = 17 2 -

PARAMETER GRAPHS MODE DURATION (IN HOURS) = 4 3 -

SENSOR PLOTS TOT TIME MEASURED LEAK = 1.5343 4 -

TREND ANALYSIS TOT TIME CALCULATED LEAK = 1.5115 5 -

REPRINT CURRENT DATA PT MASS PT LEAK = 1.5180 6 -

SENSOR DIFFERENTIALS IMPOSED LEAK = 1.0003 TOT TIME UPPER LIMIT = 1.5625 P -

PASS WORD MENU TOT TIME LOWER LIMIT = 1.0625 MASS PT UPPER LIMIT = 1.5652 ELECTED OPTION = MASS PT LOWER LIMIT = 1.0652 TOT TIME VERIFICATION CRITERIA HAS EEEN MET MASS PT VERIFICATION CRITERIA HAS BEEN MET POINT

SUMMARY

CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT VG TEMP: 78.009/ -0.008 AVG PRESS: 60.004/ -0.013 MASS: 79377.91/ -16.172 AVG DEW PRESS: 0.4537/+0.0020 I

,7958-* s.

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I I

I E

Appendix D E INSTRUMENT SELECTION GUIDE CALCULATIONS I

I I

I lI lI I

I

I I Page 1 of 7

"'""'^"'^"

I ' " S'" "" '*'^" " s ' '" " "

l A. Instrument Specifications

1. Total, Absolute Pressure

a. Mensor Quartz Manometer Pressure Gages

b. No. of sensors used in calculation: 2

c. Range: 0-100 psia (direct reading)

d. Accuracy: 10.010% Rdg.; i 0.002% F.S.; i 5 microns g e. Sensitivity: 10.001 psi

f. Repeatability: 10.001% F.S.

l g. Resolution: 0.001 psi

2. Water Vapor Pressure

a. Foxboro Lithium Chloride Dewcells I b. No. of sensors: 10

c. Calibrated range: 37.5 - 100"F

d. Accuracy: 1 1.5 F g e. Sensitivity: i 0.001 F l 3. Drybulb Temperature

a. 1(X) ohm platinum RTD's

b. No. of sensors: 18

c. Calibrated range: 60 - 120 F

d. Accuracy: 05F

e. Sensitivity: 10.001"F I

t Page 2 of 7

4. Data Acquisition System

a. Fluke Model 2285 I

b. Drybulb Signal Conditioning / Readout

1) Repeatability: 10.001*F

2) Resolution: 0.001*F I c. Dewpoint Signal Conditioning / Readout

1) Repeatability: 10.001*F

2) Resolution: 0.001*F I

B. Instrument and Measurement System Errors I

1. Definitions

a. e= the error associated with the measurement of change in a given l parameter.

l b. E= the error associated with the sensitiv..y of the sensor.

c. e= the error associated with the measurement system readout and signal conditioning (excludes sensor), including resolution and l repeatability.

1) Instrumentation errors (e.g., repeatability and resolution) are combined using a root-sum-square formula (per ANSI /.ANS 56.8-1987, Appendix G).

I 2) In cases where repeatability is tested and specified for both the

! sensor and the readout device, the largest source of error is l used to calculate e.

lI l

Page 3 of 7 I

g C. Instrument Errors

1. Total, Absolute Pressure

a. Sensitivity E, = 10.001 psia (per manufacturer spec.)

I b. Resolution and Repeatability cp = i [(0.001)2 + (0.001 psia)2jin

= i [1 x 104+1x10*]2 4

= 1 [2 x 10 ]'8 t, = 1 1.414 x 10'3 psia 1

I

c. Measurement System Error e=p [(7dp)2 , (gp)2)in/[no. of sensors]

= i [(0.001)2 + (1.414 x 10'3)2)i 2j(3)n2

= 1 [1 x 104 + 2 x 104]v2ji,414

= 1 [3 x 10 4]v2ji,434 e=p 1.225 x 10~3 psia I

I I

0 l

I Page 4 of 7 I

l 2. Drybulb Temperature Sensitivity a.

Fy = 10.001'F g

I b. Resolution and Repeatability or = 1 [(0.001)' + (0.01)2]

d g = i [1 x 104 + 1 X 10 ]'S d

= 1 [1.01 X 10 ]tr2 I c1 = 10.010*F I

c. Measurement System Error e2 = i [(E 3)2 , (c1)2] 2/(no. of sensors) '

I = 1 [(0.001): + (0.01)']'*/(18)

f = 1 [1 x 104 + 1 x 10']/4.243

= i [1.01 x 10 "]'*/4.243

= 10.010/4.243 er = 10.002"F I >

I . -

I I Page 5 of 7

3. Water Vapor Pressure

(

a. Sensitivity En= 10.001*F l b. Resolution and Repeatability t

r = 1 [(.5"F)2 + (0.001)2]2 I = i [.25#F + 1 X 10') '

=

1 [.25]

tr = 0.5"F g

l c. At 80#F dewpoint, water vapor pressure change /'F is 0.0167 psiat'F (from the steam tables)

d. Measurement System Error e

r = 1 [(Er)2 + (t r)2]'? /(no. of sensors)

l l = 1 [(.001)2 + (.5)2]/(10) '

= 1 [0.25]/3.162

= 1 5/3.162

= 10.1581'F x 0.0167 psia /'F en= 12.64 x 10* psia g

I I

I Pap,e 6 of 7 I

l D. Instrumentation Selection Guide Formula (24 hr. Test) 2400 isG=.1 2(

)' 4 2( 'l)2 42(h)2 I

j3g ,,2400 2 ( 1.225x10-3)242( 2.64x10-3.)242(0.002)2 24 h 60.2 60.2 545 I

l = 1100 [2(2.035 x 10 )2 + 2(4.385 x 10 )2 + 2(3.670 x 10)']'?

5 5

= 1100 [2(4.141 x 10 "') + 2(1.923 x 10') + 2(1.347 x 10 ")] 2

= 1 100[8.282 x 10 "' + 3.846 x 10' + 2.694 x 10 "]'?

= 11(X) [4.701 x 10*]

l = 1100 [6.856 x 10 ]

5 ISG = + 0.00689/ day I

E. ISG at 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months s:

l ISO = 1 24 0[6.856 x 10 )

4

= 300 [6.856 x 10 ]

g ISG = 10.0204%/ day I

I

I Page 7 of 7 l F. ISG Acceptance Criteria

1. ISO must be s 257c L, I

2. 257c (17e wt/ day) = .257c/ day

3. ISG = 0.0068% 5 0 257c/ day l for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 4, ISG = 0.02047o 5 0 25%/ day g

for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months I

I l

I

!I

.I I

I I

I 2

I i

I 1 I

I I

i 4

Apperidix E i

SENSOlt LOCAT!ONS I

!I I

I I

1

I y , E LEVATION AZiWUT H 100' 3 3/4" 94' ME A 3; ; _g ,/, y,

.[ A*--- ,

1BO' I

f[

,f/ ,/ E L. 81' 6 1/4" N

N

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/

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/

N E L . 5 0'+ 6" ut c ,*,'n, 20el 2 , . , -

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= \\N N E L. 31' 6"

~E % ,l - "' ' ' A's'-

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g 3

\ w ug .n .'E. \

\ ZONES ie0* \ gout 3 /

I paw Y PROFILE VIEW sn gg ,; 120' 9E x h NOT ES:

I 1. ZONE BOUNDARIES ARE APPROKIM ATE, REFERENCE PNPS CALC. No MB 009.

2. INSTRUMENT ELEVATION AND AZtWUTH POSifl0NS ARE APPROXIM ATE.

I ILRT DEWP0lNT TEMPERATURE I SENSOR LOCATIONS PILGRIM NUCLEAR POWER STATION-UNIT No.1 I

I I

E L E V AT IO N

~

A ZIMUT H E L 106'- 3 3/4" 20 I p

// /r[ A'/'s

,/ s EL 91 3 5/4.

TE C ,3g, % s s

I 7g.a 87' # 9N LONE L/pa NhN

.\

ZONEB N TE 05' ,

E L. 81* 6 1/4" 8#

'/ ,

f N TE B 100'

, /,

/,

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60' 90' \.' / ,

/

b

/' , TE-E 2

60 bC ' ZONE EL. 50' 6" TE G 27

ZONE D ZON - 10. K 32 .gg y 180* E L . 31,- 6..

T E J gg- D** w)., . * ==.th L_

I W"

' y y.

2 2 ' __ t, ,

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' EE . /"h IL 'b10"

! 12' .

"'z$* NjDNs j#~~'

QZONE W iife ., ZONE 0, ,

('Miifl;Z0%J,g{sy, Sgs TE a3 6 3

N E L. 9' 2" 1

$,$)h I

l TE-N2 '70*

I \ ZONE J 15, g

\ ZONE J sg/ \g-T PROFILE VIEW TE-0h

- TE $

12 0 '

I NOTES:

1. ZONE BOUND ARIEC ARE APPROXIM ATE, I REFERENCE PNPS CALC No MB-009.

2. INSTRUMENT ELEVATION AND AZiWUTH PostTIONS ARE APPROXIMATE.

I I ILRT RESISTANCE TEMPERATURE DETECTOR LOCATIONS PILGRIM NUCLEAR POWER STATION UNIT No.1 I

I I

I Appemlix F DESCitil' TION OF GENEIRAI,I'lIYSICS II.itT COMPUTElt 1*llOGitAM I

I I

.. - . .- ~ _ - _ - _ _ _ - ___ .

I I DESCRIPTION OF GENEllAL PilYSICS ILitT COMPUTElt PROGRAM l The following paragraphs describe the various features and attributes of the General Physics ILRT Data Management computer program and the process used to certify it each application.

I IEDUNDANCY l The General Physics ILRT team was equipped with two fully operational IBM compatible rnicrocomputers (Samsung S500 and SD700) during the ILRT for on site data reduction and analysis. The computer software and hardware interfaced directly with the Fluke Model 2285B Data Acquisition System for the test, Two computers were brought on site for 100% redundancy, as each computer and its software was capable of independently performing the ILRT. The General Physics ILRT Data Management Software is also capable of accepting manualinput of raw sensor data and performing all required sensor data conversions if the data logger would cease to function. The program installed on each computer was designed to write to the hard drive and the back-up disks in the "A" and "B" drives to protect against the unlikely event of l

l a disk " crash."

The General Physics ILRT Data Management Computer Program is written in IBM's

BASICA. BASICA is a high level programming language which combines programming case with user oriented command functions to create an easy to use and understand lg program. In order to increase speed of operation the program was then compiled into an executable command file. Compiling was accomplished using the IBM Basic Compiler.

l SECURITY l

l In addition to execution speed, compiling has the added benefit of making the program I more secure as compiled programs cannot be edited or changed. Also, as the program does not need to be attended to operate, a password is required to change modes of operation, start times or to enter the data editing routine. The data editing routine itself is purposely designed to be extremely user un-friendly and implementable only by the GP programmers as General Physics believes that the integrity of the raw data files is paramount.

l I

1

FEATURES The program itself is designed to be a menu driven program consisting of five separate, menu driven operating modes. These are the:

1. Pressurization hiode

2. Stabilization hiode

3. Test hiode

4. Verification hiode

5. Depressurization hiode These modes correspond to the phases of the ILRT. hienu driven means that the user is l presented with a list of options that the prograrn can perform and from which the user can choose, it allows for interactive information exchange between the user and the computer and prevents invalid information or user mistakes from crashing the program. Program organization consists of a master menu which controls access to the five operating modes chained to the individual menus which control these modes. The data processing, information display capabilities and function of each mode is as follows:

1. Pressuri7ation hiode: All data reduction, graphic displays of average temperatme, dewpoint,and corrected pressure.

g

2. Stabili7ation biode: All data reduction, automatic comparison of data l against ANSI 56.8 and BN TOP-1 temperature stabilization criteria, notification when criteria is met, graphic displays of average temperature, dewpoint, and corrected pressure.

3. Test hiode: All data reduction, calculation of leakage rates using mass point, total time and point-to point analysis techniques, display of trend report information required by BN-TOP-1, graphic display of average temperature, dewpoint, pressure and mass, as well as graphic display of mass l point measured leakage, 95% UCL; total time measured and calculated leakage and the total time leakage rate at the 95% UCL (as calculated by BN-TOP-1), including a superimposed acceptance criteria line).

4. Verification Test hinde: With input of imposed leakage in SCFM automatically calculates and displays on graph and trend report the I acceptance criteria band, plus all graphics displays available in test mode.

5. Depressuri7ation hiodt : All data and graphics capabilities of Pressurization hiode.

I I

o Other reduction and analysis capabilities of the General Physics ILRT computer program include:

1. Containment total pressure conversion from counts to psia (if requited), and averaging.

I 2. Containment drybulb temperature weighted averaging and conversion to absolute units.

3. Containment dewpoint temperature weighted averaging and conversion to partial pressure of water vapor (psia).

4. Data storage of ILRT measurement system inputs for each data point.

I 5. Weight (mass) point calculations using the ideal gas law.

l 6. Automated Data . Acquisition and/or Manual Data Entry.

Sensor performance and deviation information for sensor failure criteria, I 7.

graphic display of individual sensor performance for selected operating mode.

8. Calculation of ISO formula at beginning of test; acceptance critria based on number of sensors remaining and actual test duration.

I 9. Computer System Error Functions automatically checks for error in incoming data, printer or disk drive faults.

COMPUTER PROGRAM CERTIFICATION l The computer program used by General Physics and has been previously certified for six tests at the San Onofre Nuclear Generating Station and over a dozen other ILRT's.

The initial certification required verification of the program through hand calculations and an independent review by Bechtel Power Corporation. After certification was completed a calibration set of raw data was established from the data which is used to verify l performance of the program prior to usage.

, Additionally, a hand calculated data set was entered into the program to further verify l

l performance, as configured for the ILRT. Acceptable agreement was obtained between the hand calculated results and the computer results, within the limits of truncation and round-off error.

, I Once the computer was linked to the data acquisition device and a complete data stream was available, the input function of each mode of the program was verified by comparing g the data logger's output to the computer's printed data point summary.

General Physics also provided printouts of the installed constants foi the test such as:

I 1. Volume Fractions for IU(T hicasurement System Sensors

2. Installed Calibration Constants The microcomputer hardware and software remains the property of General Physics. l I Genen! Physics supplied Hoston Edison Cornpany with certification documents for the IUlT rnicrocomputer software for the llJtT in accordance with paragraph 4.2 of General Physics Corporation's CLitT Project Procedures hianual and the Purchase Order l requirements.

I I

t 1

I

I I

I Appendix G I LOCAL LEAKAGE TEST SUMMAltlES I

I I

I I 1991 LOCAL 1.EAK RATE

SUMMARY

l TYPE B DOUBLE GASKETED SEALS AS FOUND AS LEIT MAINTENANCE I PEN.

NO. DESCRilTION LEAKAGE (SCCM)

LEAKAGE (SCCM)

IMPROVEMENT (SCCM) COMMENTS N/A GlBS MANWAY 6 0 ,45 ,90 ,135 N/A GIBS MANWAY 6 180",225",270 ,

l 315 N/A DRYWELL llEAD 42 21 21 I 1 EQUIPMENT llATCil 7 8 l 2 AIRLOCK INNER SEAL 2 8 AIRLOCK OUTER SEAL 2 8 I 4 DRYWELL llEAD 132 ACCESS IIATCil 6 CRD REMOVAL IIATCil 4 25 AO 5044A INBOARD FLANGE 4 AO.5044B INBOARD FLANGE 3 4 AC 5044B OUTBOARD FLANGE

TESTED I WITil AO SN4B ND\RD llANGE I

I I

I

1991 LOCAL 1.EAK RATE

SUMMARY

l TYPE 13 DOUBLE GASKETED SliALS AS FOUND AS LEFT MAINTENANCE PEN. LEAKAGE I.EAKAGE IMPROVEMENT NO, DESCRilrrlON (SCCM) (SCCM) (SCCM) COM Ml!NTS 26 AO-503511 INBOARD FLANGE

TESTED WITil AO 5035A NG\RD11NGI I AO 5035 A IN110ARD FIANGE 6 AO 5035A OUTBOARD FLANGE

TESTED WITil AO 5035A l N D\RDllM Gi 35A TIP DRIVII FLANGES 3513 5 INNER 6 35C 35D TIP DRIVE FLANGES 35E 5 OlJrER 30 43 DRYWELL TEST CONN.

FLANGE 5 47 ILRT SUPP TEST COhN. FLANGE 1520 3 1517 200A TORUS ACCESS llATCil.

EAST 5 3 2 I 200B TORUS ACCESS IIATCil.

NORTIl 28 24 4 l

I

I I 1991 LOCAL LEAK RATE

SUMMARY

l TYPE B DOU13LE GASKI:TED SEALS AS FOUND AS LEFF MAINTENANCl!

PEN. LEAKAGE LEAKAGE IMPROVEMENT No. DESCRIPTION (SCCM) (SCCM) ISCCM) COMMENTS 205 AO 5036B INBOARD

TESTED WITil FLANGE AO 5036A I Mn\RD11RCE AO 5036A INI30ARD FLANGE 4 I AO 5036A OLTTI30ARD FLANGE

TESTED WITil AO 5036A ND\RD 11ANGli 223 IIPCI STEAM TO TORUS l INBOARD FLANGE &

OUTBOARD FLANGE 6 3 3 l 223 2301 74 INBOARD &

OUTBOARD FLANGE 5 225 1301-64 INBOARD &

OUTBOARD FLANGE 7 RCIC STEAM TO TORUS INBOARD FLANGE &

OUTI30ARD FLANGE 3 5 I

I I

I 19911.OCAL LEAK RATE

SUMMARY

l TYPE 13 DOUBLE GASKETED SEALS AS FOUND AS LEIT MAINTENANCE PEN, LEAKAGE LEAKAGE IMPROVEMENT b'Oa DESCRirTION (SCCM) ISCCM) (SCCM) COMMENTS 227 AO.5040A INBOARD &

OUTBOARD FLANGE

TESTED WITil I AO 504013 INBOARD &

OUTBOARD FIANGE AO 504013 INBOARD &

OUTBOARD FLANGE 5

TESTED WITil 227A X 212A SEAT FIANGE AO 5040B INBOARD &

OUTBOARD l FLANGE 22713 X 212B SEAT FLANGE

TESTED WITil AO 5040B INBOARD &

OUTBOARD IlANGE 227 AO 5042A INBOARD I FLANGE AO 5042B INBOARD & 8 OUTBOARD FLANGE AO 5025 INBOARD FLANGE 230 TORUS TEST CONN.

FLANGE 3 I

I I

I I 1991 LOCAL LEAR RATE SUhihiARY l TYPE 13 TESTABLE PENETRATIONS AS FOUND AS LEIT hiAINTENANCE I PEN.

NO, DESCRilTION LEAKAGE (SCCM) 1.EAKAGE (SCCM)

IMPROVEMENT (SCCM) COMMENTS 2 AIRLOCK INTEGRATED 725 690 35 I 7A 53 MAIN STEAM &

RCIC STEAM TO TURBINE 17 7B MAIN STEAM (2) 7C 76 7D hiAIN STEAM &

8 MAIN STEAM l DRAIN 333 9A FEEDWATER (2) l 9B 7 12 RilR SUCrlON FROM RECIRC 51A RilR RETURN TO RECIRC 735 14 CLEANUP SUPPLY 16A CORE SPRAY 7 16B CORE SPRAY 4 17 RX VESSEL llEAD SPRAY 625 51B RIIR RETURN 2010 TO RECIRC g VENT LINE 9 52 11PCI STEAM TO l 20111 TURB VENT LINE 8 I

I

O 1991 LOCAL LEAK RATE SUhihfARY TYPE 13 TESTABLE PENETRATIONS AS FOUND AS LEIT hiAINTENANCE I PEN.

NO. DESCRIPTION LEAKAGE (SCCM)

LEAKAGE (SCCM) lhiPROVEhiENT (SCCM) COMAiENTS 100A/13 101B NEUTRON hiON (4) 55 104E 100C 104G/J NEUTRON h10N (4) 12 10513 I 100D 102A NEUTRON hiON (4) 14 103A l 10411 100E l 102B 103B NEUTRON hiON ELECTRICAL (3) 102 105A CRD POSITION (2) l 104A/B/C 101A ELECTRICAL 104D/F CRD POSITION (2) 39 106B DRYWELL IIUhilDITY 101C ELECTRICAL 17 201A VENT LINE 4 201B VENT LINE 7 201C/D VENT LINE (2) 8 1

l g 231E/F VENT LINE (2) 4 202A ELECTRICAL 17 202B ELECTIUCAL 112 II I

. - - . . _ . _ . - . _ _ - = . _- _ .. ._ -

1 i

1991 LOCAL LEAK RATE

SUMMARY

TYPE C TESTS AS FOUND AS 1.EIT MAINTENANCE PEN. 1.EAKAGE LEAKAGE IMPROVEMENT NO. DESCRilrTION (SCCM) (SCCM) (SCCM) COMMENTS 7A MAIN STEAM AO 2031A 101 1

AO 203 2A 629 7B MAlN S'IT:AM AO 2031B 755 AO 203 2B 10930 484 271 I 7C MAIN STEAM AO 2031C 5933 AO 203 2C 824 E 7D MAIN STEAM E AO 2031D 3121 AL a)3 2D 1082 8 MAIN STEAM DRAIN MO 2201 3 MO 220 2 71 I 9A FEEDWATER 6 58A 394000 233 21967 6-62A 22200 820 RWCU RETURN MO 120180 468 RCIC DISCIIARGE MO-1301-49 2 9B FEEDWATER 6 58B 218000 86 217914 I 6-62B 493000 2070 I

I

1991 LOCAL LEAK RATE

SUMMARY

TYPE C TESTS AS l'OUND AS LEFT MAINTENANCli I PEN.

NO. DESCRIPTION LEAKAGE (SCCM) l_EAKAGli (SCCM)

IMPitOVEMl!NT (SCCM) COMMENTS 9 13 IIPCI DISCllARGE MO 2301-8 11 12 RilR SUCrlON 11 TOM RECIRC I MO 1(X11-47 MO.1001 50 6180 15 427 14 RWCU INLET MO 12012 8369 5010 23 MO 1201-5 211 188 15E 110 2 2 ANALYZER l "B" SV 5065 3511 2 SV 5065-31B 2 16A CORE SPRAY TESTED IN TO REACTOR PARALLEL MO 1400 24A 4 MO 1400-25A 16B CORE SPRAY TESTED IN TO REACTOR , PARALLEL I MO-1400-2413 MO 1400 25B 875 ll 17 RX llEAD SPRAY TESTED IN

! 5 MO ;00160 2 PARALLEL l MO 1001-63 l

l I

i

\

l 1991 LOCAL Li!AK RATE

SUMMARY

TYPE C TESTS AS FOUND AS LEFF hiAINTENANCE I PEN.

Q F_O , DESCRIPTION Ll!AKAGE LEAKAGE (SCCM) (SCChj]

lhtPROVEh1ENT (SCChi) Coh1 Nil!NTS 18 DRYWELL FLOOR DRAIN I AO 7017A AO 7017B 1026 28 I 19 DRYWELL EQUIP.

hiENT DRAIN AO 7011A 16 AO 7011B 871 22 INSTRUh1ENT AIR I TO DRYWELL 31 CK 167 812 l 23 RBCCW SUPPLY 30-CK-432 37 l 24 RBCCW RETURN MO 4002 5 25 DRYWELL PURGE EXilAUST AO 5044A 40 I AO 5044B TESTED IN I 25 DRYWELL VENT EXIIAUST AO 5043A 1039 PARALLEL l AO-5043B POST ACCIDENT TESTED IN I PURGB & VENT SV-5082A SV-5081B 4

PARALLEL I

I I 1991 LOCAL LEAK RATE SUhihiARY l TYPE C TESTS AS FOUND AS LEFF hiAINTENANCE PEN. LEAKAGE LEAKAGE lhiPROVEhiENT

& DESCRIPTION (SCChi) (SCChi) (SCChi) COhihiENTS 25 POST ACCIDENT TESTED IN PARALLEL I PURGE & VENT SV 5081 A SV 5082D 2

26 DRYWELL PURGE TESTED IN INLET PARALLEL I AO 5035A AO-5035B 1306 AO 5033B TORUS PURGE TESTED IN INLET (X-205)

PARALLEL I AO 5036A AO 5036B WITH AO 5035A, AO-5035B, &

l AO-5033B POST ACCIDENT TESTED IN l PURGE & VENT SV 5085A 4 PARALLEL SV-5085B I

POST ACCIDENT TESTED IN I PURGE & VENT SV 5086A 2 PARALLEL SV-5086B DRYWELL MAKEUP TESTED IN I GAS 9-CK-340 48 PARALLEL I DRYWELL hiAKEUP GAS TESTED IN PARALLEL AO-5033A 1058 I

I

o 1991 LOCAL LEAK RATE SUhiMARY TYPE C TESTS AS FOUND AS LEFT htAINTENANCE I PEN.

NO. DESCRWTION LEAKAGE LEAKAGE (SCCM) (SCCM)

IMPROVEMENT (SCChD COMMENTS 29E 1102 2 ANALYZER "A"

SV-5065 37A 1998 SV-5065 33A 373 32A C-19 RLTURN TO DRYWELL CV 5065 91 152 CV-5065 92 276 35A TIP BALL VALVE 4 45 300D "6 3 83 35B TIP BALL VALVE 3 45 300C 76 68 8 35C TIP BAl.L VALVE 1 45 300A 180 2 138 I 35D TIP BALL VALVE 2 45-300B 4368 5 4363 35E TIP N2PURGE CHECK 30 l 39A CONTAINMENT SPRAY TESTED IN PARALLEL MO-1001-23A 28 MO-1001-26A 39B CONTAINMENT TESTED IN j I SPRAY MO-1001-23B 4380 PARALLEL MO 100126B i

I

e l

l 1991 LOCAL LEAK RATE

SUMMARY

g TYPE C TESTS AS FOUND AS LEIT hiAINTENANCE !

l PEN.

NO. DESCRI} TION LEAKAGE (SCCM)

LEAKAGE (SCChD IMPROVEMENT (SCCM) COMMENTS 40Aa JET PUMP SENSING LINE-PASS SV-5065 63 15 SV 5065-64 115 I 40Dc JET PUMP SENSING LINE-PASS SV-5065 85 910 SV-5065 86 1342 41 RECIRC PUMP B I DISCil SAMPLE AO 220-44 AO 220-45 3

231 42 STANDBY LIQUID CONTROL 1101 16 9 43 DRYWELL TEST l CONN.

45 110 106 160 46A RECIRC PUMP SEAL 262 F013A 582 262-F017A 37600 1802 46B RECIRC PUMP SEAL 262 F013B 2360 262-F017B 1915 I

I

I I 1991 LOCAL LEAK RATE

SUMMARY

l TYPE C TESTS AS FOUND AS LEFT MAINTENANCE PEN. LEAKAGE LEAKAGE IMPROVEMENT NO. DESCRitTION (SCCM) (SCCM) ffFCM) COM MiiNTS 46F 11:02 ANALYZER

'A" RETURN SV 5065 26A 61 SV 5065 24A 9 47 DRYWELL TEST TESTED IN 45 110 102 167 PARALLEL 45 110 104 45 110 103 109 TESTED IN 45 110 105 PARALLEL SOAd 110 2 2 ANALYZER "B"

SV-5065-13B 166 SV 5065 20B 235 SIA RilR VESSEL RETURN MO 100128A 82 MO 1001-29A 52 51B RIIR VESSEL RETURN MO 1001-28B 5 MO-1001-29B 6 52 11PCI STEAM TESTED IN TO TURBINE PARALLEL MO 2301-4 27 MO 23015 53 RCIC STEAM TESTED IN TO TURBINE PARALLEL i

MO 1301-16 28 MO-1301-17 i

1991 LOCAL LEAK RATE SUhthiARY TYPE C TESTS AS FOUND AS LEIT MAINTENANCE I PEN. LEAKAGE LEAKAGE lh1PROVEhiENT !

NO, DESCRilrrlON (SCChi) (SCChi) (SCCAD COhihiENTS l 106Ab 110 2 2 ANALYZER "A"

I SV 506514A SV-05065-21A 6

2 205 TORUS MAKEUP GAS 9-CK-341 3 AO 5033C 87 POST ACCIDENT TESTED IN I PURGE & VENT SV 5087A 257 PARALLEL SV-5087B POST ACCIDENT TESTED IN PURGE & VENT PARALLEL SV-5088A 265 SV-5088B 211A RIIR TO TORUS TESTED IN SPRAY PARALLEL MO 1001-34A 57 MO-1001-37A 211B RilR TO TORUS TESTED IN t

i I SPRAY h101001-34B 23 PARALLEL l MO 100137B 219 11PCI VACUUM BREAKER MO 230133 391 MO 2301-34 243

e 1991 LOCAL LEAK RATE

SUMMARY

l TYPE C TESTS AS FOUND AS LEFT MAINTENANCE PEN. LEAKAGE LEAKAGE IMPROVEMENTS NO. DESCRIPTION (SCCM) (SCCM] (SCCM) COMMENTS 223 IIPCI EXilAUST 2301-74 1529000 2 431 2301-45 433 2301 218 530 CV-9068A TESTED IN I CV-9068B 530 PARALLEL 227A TORUS VACUUM TESTED IN BREAKERS PARALLEL AO 5040A 41 X-212A 227B TORUS VACUUM TESTED IN BREAKERS PARALLEL AO-5040B 29 X-2128 227 TORUS EXilAUST TESTED IN VALVE BYPASS PARALLEL AO 5041 A 1177 AO-5041B l TORUS MAIN EX11AUST &

TESTED IN PARALLEL DIRECT VENT AO 5042A AO 5042B 1105 AO 5025 POST ACCIDENT TESTED IN PURGE & VENT PARALLEL I SV-5084A SV-5083B 105 I

E I 1991 LOCAL LEAN RNTE

SUMMARY

TYPE C TESTS AS FOUND AS LEFT MAINTENANCE l PEN.

NO. DESCRIPTION LEAKAGE LEAKAGE (SCCNO (SCChD IMPROVEMENTS (SCChD COMMENTS

)

1 227 POST ACCIDENT TESTED IN i PURGE & VENT PARALLEL I SV-5083A 104 I 5.V-5084B H202ANALYZER I 228C "B"

SV-5065-15B 136 SV-5065-22B 156 226E AIR TO TORUS VACUUM BREAKERS CV 5046 2800 31-CK-434 61000 1682 1118 12SG GAS SAMPLu RETURN P ' SF SV-5065-77 449 SV-5065-78 216 228H GAS SAMPLE RETURN-PASS SV-5065-71 7 SV-5065-72 37 228J ILO2ANALYZER "A"

SV-5065-11 A 27 SV-5065-18A 73 228K H202ANALYZER

, "B" RETURN SV-5065-25B 706 SV-5065 ~27B 657 I

I

4

$t N

1988/1989/1990 LOCAL LEAK RATE TEST DATA EQUIPMENT /

PEN. 'ITPE VALVE LEAKAGE (SLM)/

NO. DESCRIPTION TEST TESTED DATE TESTED NOTES N/A GIBS MANWAY B SOUBLE 0.1/6-13-88 0 ,45 ,90 ,135 t.< R N G 0.28/5-7-89 0.005/4 9-90 l N/A GIBS MANWAY 180 ,225 ,270 ,

B DOUBLE 0-RING 0.1/6-13-88 0.28/5-7-89 315 0.025/4-9-90 I N/A DRYWELL B DOUBLE 0.1/11-30-88 HEAD O RING 1 EQUIPMENT B DOUBLE 0.1/6-6-88 HATCH 0 RING 0.28/5-6-89 I ').008/4-3-90 AIRLOCK B DOUBLE TESTED 58 TIMES I 2 INNEk SEAL O-RING FROM 10-30-88 TIIROUGH 9-24-90.

LEAKAGE RANGED FROM 0.001 TO 0.28 I AIRLOCK OUTER SEAL B DOUBLE O-RING TESTED 59 TIMES FROM 10-30-88 THROUGli 9-24 90.

LEAKAGE RANGED FROM 0.001 TO 0.28 AIRLOCK B 0.5/10 30-88 INTEGRATED 0.75/12-30-88 TEST 2.78/4-27-89 2.0/10-14-89 1.913/3 11 90 0.714/4-21-90 1.895/7.10-90 4.21/9-7-90 0.778/3-7-91 I

I

1988/1989/1990 LOCAL LEAK RATE TEST DATA

'I EQUIPMENT /

PEN. TYPE VALVE LEAKAGE (SLM)/

l NO. DESCRil' TION TEST TESTED DATE TESTED NOTES 4 DRYWELL B DOUBLE 0.1/11-29-88 IIEAD l HATCH 5 O RING ACCESS 6 CRD REMOVAL B DOUBLE 0.1/9-9-88 HATCH 0-RING 0.005/3-20-90

. 7A MAIN STEAM B BELLOWS 0.1/8-19-88 0.023/3 17 90 7B MAIN STEAM (2) B BELLOWS 0.1/8-19-88 7C 0.069/3-18-90 7D MAIN STEAM & B BELLOWS 0.1/8-19-88 8 MAIN STEAM 0.329/3-18-90 DRAIN 9A FEEDWATER (2) B BELLOWS 0.1/8-19-88 l 9B 0.003/3-18-90 12 RHR SUCTION B BELLOWS 0.3/8-23-88 l FROM RECIRC 0.726/3-20 90 14 RWCU SUPPLY B BELLOWS 0.1/8-24-88 16A CORE SPRAY 0.003/3-21-90 0.004/3-21-90 l 16B CORE SPRAY B BELLOWS 0.1/8-24-88 RX VESSEL B BELLOWS I 17 HEAD SPRAY 0.1/8-31-88 0.1/5-11-89 I

I I

I

1988/1989/1990 LOCAL LEAK RATE TEST DATA EQUIPMENT /

PEN. TYPE VALVE LEAKAGE (SLM)/

NO. DESCRil' TION TEST TESTED DATE TESTED NOTES 25 AO-5044A B DOUBLE 0.1/9 13-88 INBOARD O RING FLANGE AO-5044B INBOARD FLANGE I AO 5044B OUTBOARD FLANGE AO-5044A B DOUBLE 0.006/3-20-90 INBOARD O-RING FLANGE AO-5044B B DOUBLE 0.004/3-20-90 I INBOARD FLANGE O RING l AO-5044B OUTBOARD B DOUBLE O-RING 0.002/3-20-90 FLANGE 26 AO-5035B B DOUBLE 0.1/9 12-88 INBOARD O RING FLANGE AO-5035A 0.006/3-27-90 INBOARD FLANGE AO-5035A I OUTBOARD FLANGE 35A TIP DRIVE B DOUBLE 0.1/9-7-88 35B FLANGES O-RING 0.320/3-30-90 10 FLANGES 35C 0.009/3-30-90 5 INNER &

I 35D 35E 5 OUTER

~

I I 1988/1989/1990 LOCAL LEAK RATE TEST DATA EQUIPMENT /

PEN. TYPE VALVE LEAKAGE (SLM)/

NO. DESCRil' TION TEST TESTED DATE TESTED NOTES DRYWELL TEST I 43 CONN. FLANGE B DOUBLE O-RING 0.1/9 9-88 0.28/5-9-89 47 ILRT SUPP. B DOUBLE 0.1/9 13-88 TEST CONN. O-RING FLANGE 0.28/5-10-89 51A RIIR RETURN B BELLOWS 0.0/8 23-88 TESTED WITil P12 TO RECIRC 0.003/3-20-90 51B RIIR RETURN B BELLOWS 0.1/8-22-88 l TO RECIRC 52 IIPCI 0.01/3-19-90

' I 53 RCIC STEAM B BELLOWS 0.0/8-19-88 TESTED WITIIP7A TO TURBINE 0.0/3 17-90 TESTED WITIl P7A

, 100A NEUTRON B DOUBLE 0.1/12-14-88 l 100B MONITORING O-RING 0.053/3-21-90 100C NEUTRON MON B DOUBLE 0.1/12-9-88 104G CRD POSITION 0-RING 0.03/3-22 90 g 104J CRD POSITION l u 105B ELECTRICAL l

l 100D NElTTRON MON. B DOUBLE 0.1/12-12-88 102A ELECTRICAL O-RING 0.033/3-22-90 l 103A ELECTRICAL l 104H CRD POSITION I

I I

i 1988/1989/1990 LOCAL LEAK RATE TEST DATA I EQUIPMENT /

PEN. TYPE VALVE LEAKAGE (SLM)/

l NO. DESCRIIrrlON TEST TESTED DATE TESTED NOTES 100E NEUTRON MON. B DOUBLE 0.1/12-8-88 102B ELECTRICAL O-RING 0.002/3 20-90 104B CRD POSITION 105A ELECTRICAL 101A ELECTRICAL B DOUBLE 0.1/12-14-88 104D CRD POSITION 0-RING 0.036/3-21-90 I 104F 106B CRD POSITION DRYWELL HUMIDITY & TEMP 101C ELECTRICAL B DOUBLE 0.1/12-7-88 O RING 0.039/3-21-90 103B ELECTRICAL B DOUBLE 0.1/12-8-88 I 104A 104C CRD POSITION CRD POSITION 0-RING 0.033/3-20 90 200A TORUS ACCESS B DOUBLE 0.1/10-3-88 HATCH-EAST O-RING 0.003/4-6-90 0.008/9-4-90 l 0.002/9-7-90 200B TORUS ACCESS B DOUBLE 0.1/11-18-88 HATCH-NORTH 0-RING 0.28/7-20-89 201A VENT LINE B BELLOWS 0.1/8-23-88 I 0.002/3-19-90 VENT LINE B BELLOWS I 201B 0.1/8-23-88 0.006/3-19 90 I 201C 201D VENT LINE B BELLOWS 0.1/8-23-88 0.011/3-20-90 0.006/3-20-90 201C 201D I

I I

. o I 1988/1989/1990 LOCAL LEAK RATE TEST DATA I EQUIPMENT /

PEN. TYPE VALVE LEAKAGE (SLM)/

l NO. DESCRIITION TEST TESTED DATE TESTED NOTES 201E VENT LINE B BELLOWS 0.1/8-19-88 201F 0.004/3-18-90 201G VENT LINE B BELLOWS 0.1/8-22-88 I 20111 0.002/3-19-90 ELECTRICAL DOUBLE I 202A B O RING 0.1/11-17-88 0.022/4-13 90 I 202B ELECTRICAL B DOUBLE O-RING O.1/11-18-88 0.1/7-21-89 I 205 AO-5036B INBOARD FLANGE B DOUBLE O-RING 0.1/9 12-88 I AO-5036A INBOARD FLANGE 0.007/3-27-90 l AO-5036A OUTBOARD FLANGE I 223 HPCI STEAM B DOUBLE 0.1/10-3-88 TO TORUS O-RING INBOARD 0.008/4-6-90

& OUTBOARD FLANGE 223 2301-74 B DOUBLE 0.1/9-16-88 I INBOARD

& OUTBOARD FLANGE O-RING 0.004/4-3-90 225 1301-64 B DOUBLE 0.1/12-9-88 INBOARD O-RING I & OUTBOARD FLANGE I

I

I I 1988/1989/1990 LOCAL LEAR RATE TEST DATA I EQUIPMENT /

PEN. TYPE VALVE LEAKAGE (SLM)/

I NO. DESCRIPTION TEST 1TG RED DATE TESTED NOTES 225 RCIC STEAM B DOUBLE 0.1/12-9-88 I TO TORUS INBOARD &

O-RING 0.1/10-17-89 I OUTBOARD FLANGE 227 AO-5040A B DOUBLE 0.1/9-9-88 I. INBOARD & 0-RING OUTBOARD 0.007/3-29-90 I FLANGE AO-5040B INBOARD I & OUTBOARD FLANGE l 227 AO-5042A INBOARD B DOUBLE O-RING 0.1/9-16 88 FLANGE l AO-5042B INBOARD FLANGE 0.005/3-29-90

& OUTBOARD FLANGE

^

AO-5025 B DOUBLE 0.1/10-14-88 I INBOARD FLANGE O-RING 227.A X-212A SEAT B DOUBLE 0.5/9-7-88 FLANGE O-RING 227B X-2128 SEAT B DOUBLE 0.1/9-7-88 FLANGE O-RING 0.007/3 29-90 COMBINED 230 TORUS TEST B FLANGE 0.1/11-18-88 CONN. FIANGE 0.28/7-20-89 I

I I

9 I 1988/1989/1990 LOCAL LEAK RATE TEST DATA EQUIPMENT /

PEN. TYPE VALVE LEAKAGE (SLM)/

I NO. DESCRIPTION TEST TESTED DATE TESTED NOTES 7A MAIN STEAM C AO-203-1 A 1.26/5 31-88 TESTED IN AO-203-2A 2.05/3-14 90 PARALLEL MAIN STEAM I 7B C AO-203-1B AO 203-2B 0.13/6-1-88 0.012/3 14-90 TESTED IN PARALLEL 7C MAIN STEAM C AO 203-1C 0.13/6-1-88 TESTED IN AO-203-2C 0.008/3-14-90 PARALLEL 7D hiAIN STEAM C AO-203-1D 1.89/6-1-88 TESTED IN AO-203-2D 4.8/3-14-90 PARALLEL I 8 MAIN STEAM DRAIN C M O-220-1 M O-220-2 0.1/6-8-88 0.28/5-6-89 1.1/7-9 90 l 0.1/6-8-88 2.03/5-6-89 0.045/3-14-90 I 9A FEEDWATER C 6-58A 0.1/6-8-88 460.58/3-13-90 0.035/3-31-90 C 6-62A 0.1/6-10-88 g 16.44/3-16 90 3 0.245/4-3-90 RvVCU RETURN C MO-1201-80 0.1/6-14-88 g 0.1/12-5-88 LE 0.28/5 21-89 l RCIC DISCH C MO-1301-49 0.1/6 10-88

! 0.0/3-16-90 TESTED WITH 6-62A l

I I

I I 1988/1989/1990 LOCAL LEAK RATE TEST DATA EQUIPMENT /

PEN. TYPE VALVE LEAKAGE (SLM)/

I NO. DESCRIPTION TEST TESTED DATE TESTED NOTES

-g 9B FEEDWATER C 6-58B 0.1/6-9-88 5 0.213/3 13 90 C 6-62B 2.5/6-10-88 1,604/3-16-90 12 RHR SUCTION C MO-10rl-47 0.1/6-21-88 I FROM RECIRC C MO-1001-50 0.9/11-28-88 2.5/6-20-88 1.5/11-28-88 I HPCI DISCH C M O-2301-8 0.2/1 20-88 0.1/5-26-88 TESTED 0.0/3-16-90 WITH 6-62B 14 RWCU INLET C M O-1201-2 0.5/6-14-88 TESTED IN MO-1201-5 0.1/12-5-88 PARALLEL 0.28/5-21-89 l 15E H202ANALYZER "B"

C SV-5065-35B 0.1/8-2-88 0.042/3-28-90 SV 5065-31B 0.1/8-2-88 0.050/3-28-90

~

16A CORE SPRAY C MO-1400-24A 0.1/7-1-88 TO REACI'OR 0.1/12-15-83 0.28/5-15-89 TESTED WITII MO-1400-25A C MO-1400-25A 0.1/7-1-88 0.1/12-15-88 16B CORE SPRAY C MO-1400-24B 0.1/7-13-88 I TO REACTOR 0.1/12-15-88 0.28/5-20-88 TESTED WITH I MO-1400-25B 0.1/7-13-88 MO-1400-25B 0.1/12-15-88

4 1988/1989/1990 LOCAL LEAK RATE TEST DATA I EQUIPMENT /

PEN. TYPE VALVE LEAKAGE (SLM)/

l NO. DESCRIPTION TEST TESTED DATE TESTED NOTES 17 RX IIEAD SPRAY C M O-1001-60 0.28/5-11/89 l MO-1001-63 0.1/5-27-88 TESTED IN PARALLEL 18 DRYWELL C AO-7017A 2.9/6-27-88 FLOOR DRAIN 4.0/6 30-88 2.5/12-6-88 I C AO 7017B 6.5/3 19-90 0.2/6 27-88 0.5/12-6-88 2.37/3-19-90 19 DRYWELL C AO-7011 A 0.1/6-27-88 I EQUIPMENT DRAIN C AO-7011B 0.1/12-6-88 0.002/3-19-90 0.1/6-27-88 0.1/12-6-88 0.005/3 19-90 22 INSTRUMENT C 31-CK-167 0.5/6-28-88 AIR TO 0.1/12-2-88 DRYWELL 2.84/3-26-90 I 23 RBCCW SUPPLY C 30-CK-432 0.1/6-17-88 0.1/1'2-19-88 24 RBCCW RETURN C MO-4002 0.1/6-17-88 0.1/12-19-88 l

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1988/1989/1990 LOCAL LEAK RATE TEST DATA I EQUIPMENT /

PEN. TYPE VALVE LEAKAGE (SLM)/

l NO. DESCRIFFION TEST TESTED _DATE TESTED NOTES 25 DRYWELL C AO 5044A 0.1/8-4-88 TESTED IN PURGB AO-5044B 0.038/3-29-90 PARALLEL EXIIAUST DRYWELL VENT C AO-5043A 0.4/8-4-88 TESTED IN EXHAUST AO-5043B 1.167/3-20-90 PARALLEL EXHAUST POST ACCIDENT C SV-5082A 0.1/8 3-88 TESTED IN PURGE & VENT SV-5081B 0.003/3-20-90 PARALLEL POST ACCIDENT C SV-5081A 0.1/8 3-88 TESTED IN PURGE & VENT SV-5082B 0.003/3-20-90 PARALLEL 26 DRYWELL C AO 5035A 1.0/8-1-88 TESTED IN I PURGE INLET AO-5035B AO-5033B 0.775/4-25-89 1.534/4-4 90 PARALLEL POST ACCIDENT C SV-5085A 0.1/8-1-88 TESTED IN I_ PURGE & VENT SV-5086B 0.038/4-4-90 PARALLEL l POST ACCIDENT PURGE & VENT C SV-5086A SV-50S5B 0.1/8-1-88 0.061/4-4-90 TESTED IN PARALLEL l DRYWELL MAKEUP GAS C 9-CK-340 0.1/8-1-88 0.041/4-4-90 l

l DRYWELL MAKEUP GAS C AO-5033A 0.1/8-1-88 1.275/4-4-90 l

29E H2 0 ANALYZER C SV-5065-37A 1.5/8-17-88 "A" 1.94/3-28-90 C SV-5065-33A 0.1/8-17-88 lI l

0.44/3-28-90 1

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I 1988/1989/1990 LOCAL LEAK RATE TEST DATA EQUIPhiENT/

PEN. TYPE VALVE LEAKAGE (SLhi)!

NO. DESCRIPTION TliST T11STED DATil TESTI!D NOTliS 32A C-19 RETURN C CV-5065 91 0.1/8-10-88 l TO DRYWELL C CV 5065 92 0.143/3 27 90 0.1/8-10-88 0.06/3 27-90 35A TIP BALL C 45-300D 0.10 6-88 TESTED IN 3513 VALVES 45-300C 0.825/4 3 90 PARALLEL 35C 45 3(X)A 35D 45 3008 35E TIP N2PURGE C CilECK 0.10-688 0.006/4 3 90 39A CONTAINhiENT C MO 1001-23A 0.1/62388 TESTED IN SPRAY MO-1001-26A 0.1/12-1-88 PARALLEL 0.008/3 15 90 39B CONTAINMENT C MO-1001-23B 0.1/6-21-88 TESTED IN SPRAY MO-1001-26B 1.94/3-22-90 PARALLEL 40Aa JET PUMP C SV-5065-63 0.1D 22-88 l SENSING LINE-PASS C SV-5065-64 0.28/5-9-89 0.lD 22-88 40Dc JET PUMP C SV-5065-85 0.10-26-88 SENSING LINE- 0.28/5-9-89 PASS C SV 5065-86 0.10-26 88 I 0.28/5 9-89 41A RECIRC PUMP B C AO-220-44 0.1/10-3-88 I DISCil SAMPLE 0.1/2-26 89 0.007/3 17 90 C AO 220-45 I 0.1/2-26 89 0.012/3-17 90 I

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I 1988/1989/1990 LOCAL LEAK RATE TEST DATA I EQUIPMENT /

PEN. TYPE VALVE LEAKAGE (SLM)/

NO. DESCRIPTION TEST TESTED DATE TESTED NOTES 42 STANDBY C 1101-16 0.10-29 88 LIQUID 0.007/4-9-90 CONTROL 43 DRYWELL TEST C 1(0-106 0.1,7-7-88 CONN. 0.28/5-9.'N 46A REC 1RC PUMP C 262 F013A 0.1/6-23/88 SEAL 0.005/3-12 90 I C C

262-F017A/B 26217A 0.1/6-15-88 0.012/3-12-90 I 46B RECIRC PUMP SEAL C 262-F013B 3.25/6-16-88 2.68/3-12 90 C 262-F017B 0.007/3-12-90 I 46F 110 2 2 ANALYZER C SV-5065-24A 0.2D 22-88 "A" RETURN 0.057/3 28-90 l C SV-5065 26A 0.2D-22-88 0.081/3 28-90 4_7 DRYWELL TEST C 45-110-102 0.1 9-8-88 TESTED IN 45-110-104 0.28/5-10-89 PARALLEL 45-110-103 0.1R-8-88 TESTED IN 45-110-105 0.28/5-10-89 PARALLEL SOAd 110 2 2 ANA. M C SV-5065-13B 0.1/8-11-88

B

0.107/3-27 90 C SV-5065-20B 0.1/8-11 88 I 0.516/3-27-90 I

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1988/1989/1990 LOCAL LEAK RATE TEST DATA I EQUIPMENT /

PEN. TYPE VALVE LEAKAGE (SLM)/

NO. DESCRITTION TEST T2STED DATE TESTED NOTES 51A RHR VESSEL C MO-1001-28A 0.1/9-8-88 I RETUIU4 0.1/12-1-88 0.035/3-16-90 C MO-1001 29A I 0.1/6 24-88 0.1/12-1-88 0.392/3-15-90 51B RHR VESSEL C MO-1001-28B 4.25/9-2-88 RETURN 2.74/3-23-90 C MO 1001-29B 5.00/9-21-S8 32.82/3-23-90 1.823/4-7 90 52 HPCI STEAM C MO-2301-4 0.1/3-18-88 TESTED IN TO TURBINE MO 2301-5 0.4/12-16-88 PARALLEL l 0.1/2-27-89 0,023/3-17-90 53 RCIC STEAM C MO-1301-16 0.1/6-3-88 TESTED IN TO TURBINE MO-1301-17 0.1/12-16-88 PARALLEL 0.42/3 17-90 106Ab H 2 0, ANALYZER C SV-5065-14A 0.2/7-2248 "A" 0 003/3-28 90 I C SV-05065-21A 0.2/7-22-88 0.003/3-28-90 I

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1988/1989/1990 LOCAL LEAK RATE TEST DATA EQUIPMENT /

PEN. TYPE VALVE LEAKAGE (SLM)/

NO. DESCRINION TEST TESTED DATE TESTED NOTES 205 TORUS MAKEUP C 9-CK-341 0.1 0-29-88 GAS 0.245/4-4 90 C AO-5033C 0.1/9-16-88 0.273/4-4-90 POST ACCIDENT C SV-5087A 0.1/7-29-88 TESTEDIN l PURGE & VENT S\ -5087B PARALLEL POST ACCIDENT C SV-5088A 0.1D-29-83 PURGE & VENT SV-5088B POST ACCIDENT C SV-5087A 0.136/4-4-90 TESTED IN PURGE & VENT SV-5088B PARALLEL POST ACCIDENT C SV-5087B 0.129/4-4-90 PURGE & VENT SV-5088A TORUS PURGE C AO-5036A 0.8/8-1-88 TESTED IN INLET (X-205) AO-5036B 0.850/4-4-90 PARALLEL I 211A RHR TO TORUS

- SPRAY C MO-1001-34A MO-1001-37A 0.1/6-23-88 0.1/10-1-88 TESTED IN PARALLEL 0.029/3-15-90 I 211B RHR TO TORUS C MO-1001-348 0.1/6-22-88 TESTED IN SPRAY MO-1001-37B 0.002/3-22-90 PARALLEL I 219 HPCI VACUUM C MO 2301-33 0.2/5-24-88 BREAKER 0.161/3-17-90 C MO-2301-34 1.5/5-24-88 0.248/3-17-90 lI I

I 1988/1989/1990 LOCAL LEAK RATE TEST DATA EQUIPMENT /

PEN. TYPE VALVE LEAKAGE (SLM)/

NO. DESCRINION TEST TESTED DATE TESTED NOTES 223 HPCI EXHAUST C 2301-74 0.1/9-28-88 0.143/4-1-90 C 2301-45 1.5/9-28-88 I C 2301-218 2.62/4-1-90 0.1/9-28-88 3.39/4-2-90 I C CV-9068A CV-9068B 0.1/9-28-88 0.018/4-3-90 TESTED IN PARALLEL I 227A TORUS VACUUM C BREAKERS AO-5040A X 212A 0.10-28-88 0.1/2-7-89 0.061/3-29-90 TESTED IN PARALLEL 227B TORUS VACUUM C AO-5040B 0.1R-29-88 TESTED IN BREAKERS X-212B 0.1/2 8-89 PARALLEL 0.068/3-29 90 227 TORUS EXHAUST C AO.5041A 0.1/7-26-88 TESTED IN VALVE BYPASS AO-5041B 1.23/3-29-90 PARALLEL TORUS MAIN C AO-5042A 0.1/10-17-88 TESTED IN l EXHAUST &

DIRECT VENT AO 5042B AO-5025 0.74/3-29-90 PARALLEL POST ACCIDENT C SV-5084A 0.1/7-27 88 TESTED IN PURGE & VENT SV-5083B 0.64/3-29-90 PARALLEL POST ACCIDENT C SV-5083A 0.1R-27-88 TESTED IN PURGE & VENT SV-5084B 0.147/3-29-90 PARALLEL 228C H202ANALYZER C SV-5065-15B 0.10-14-88 "B" 0.022/3-27-90 C SV-5065-22B 0.19-14-88 0.048/3-27-90 I

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1988/1989/1990 LOCAL LEAK RATli TEST DNFA I EQUIPMENT /

PEN. TYPE VALVE LEAKAGE (SLM)/

l- NO. DESCRlirrION E.ST TESTED DATE TESTED NOTES 228E AIR TO TORUS C CV 5046 1 M/h.16 88 VACUUM 1.5/12 2-88 BREAKERS 0.005/3 26-90 C 31-CK-434 I 0.1/8 16-88 0.1/12-2-88 0.360/3 26 90 228G GAS SAMPLE C SV 5065-77 0.1/8 9-88 RETURN-PASS 0.28D-19-89 I C SV-5065-78 0.1/8-9-88 0.28R-19-89 I 22811 GAS SAMPLE RETURN-PASS C

C SV-5065-71 0.1/8-9-88 0.28R-19-89 SV-5065-72 0.t/8 9-88 0.28/7 19-89 228J 11:02 ANALYZER C SV-5065-II A 0.1/7-15 88 "A" 0.28R-20-89 C SV-5065-18 A 0.1D-15-88 0.28/7-20-89 I 228K 11:02 ANALYZER C SV-5065-25B 0.lD-12-88 "B" RETURN 0.28R-20-89 C SV-5065 27B 0.1D 12-88 0.28R-20-89 I

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I Appendix 11 I FAT ROOT CAUSE ANALYSIS - FEEDWATER CIIF.CK VALVES I

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d F.A,T. ROOT CAUSE ANAL 151S_SEMMM1 I

FOR FEEDWATER CH[CK VA(y[S Synynary of Ohgrved Problem:

Feedwater check valved 58A, 588, 62A and 62B failed their respective LLRT's (Ref.1) during RF0 #8. Leakage rates were as follows:

58A- 394 SLM 588 - 218 SLM i I 62A -

62B -

22.2 SLM 493 SLM The acceptable leak rate for each of the four valves is 7.89 SLM. Failure and malfunction reports (F&MR)91-241, 236, 254 and 253, respectively, were issued to address the problems. This report will identify root causes of those failures and corrective actions taken to date.

Root Cause Summary:

The primary root cause of the LLRT failures of all four feedwater check valves k , the misalignment of the discs relative to their valve seats. The l misalignment was a result of previous maintenance on the valves (particularly realignment following sof t seat modification and lapping of the seats) and not maintaining proper clearances between hinge pin shoulders and the respective disc bushings. It has been learned that proptr alignment of the discs is I critical to achieving acceptable and repeatable LLRT results.

PrinciDief of Ooeration:

The principle parts of a tilting disc check valve are the body, bonnet, disc and hinge pin assembly. The body, bonnet and hinge pin closures retain the fluid within the system. The disc is supported by, and rotates about the hinge pins, which are contained in thru-body bores. The pivot axis is located above the center line and near the center of gravity of the disc and in such a geometric position to allow the conical seating surface of the disc to rotate into the matching cone of the body seat without interference.

Flow in the narmal direction creates a force on the disc, which because of the offset pivot axis, causes the disc to rotate away from the seat.

Upon cessation of forward flow or reversal of flow, the force holding the disc open is no longer present and the weight of the disc combined with the force of the reverse flow causes the disc to return to the seat.

Page 1 of 4 I

I Sealing between the disc and the seat results solely from the differential I pressure across the disc forcing the cone of the disc into the matching cone of the seat. Hence, the difficulty in maintaining a tight seal at low pressures.

I RgqLfause Discussion:

After failure of the LLRT's, each valve was opened and inspected to determine the failure mechanism. Findings on three of the valvts (58A, 62A and 628) were very similar. All the soft seats were degraded throughout the bottom 257.

I to 507. of the disc seating area. The degradation appeared to be a chipping or cutting of the soft seat material. These findings are indicative of the valve discs being seated slightly low such that they drag as they enter the valve I seat and catch on the sharp edge of the valve seat ring. No evidence of thermal aging damage was observed on the soft seats.

I The other valve (588) showed no signs of soft seat degradation. The disc was misaligned (set back and low) allowing it to over rotate such that the soft seat retaining ring was contacting the valve seat at the bottom. The soft seat was making good contact with the valve seat when initially installeJ I resulting in acceptable LLRT's. As the retaining ring wore, it allowed the disc to travel past the seat resulting in unacceptable contact between the soft seat and the valve seat. These findings were determined based on wear I and corrosion marks evident on both the valve seat and the soft seat retaining ring.

I The misalignment on all four valves was most likely a result of previous maintenance on the valves. Documentation on the original installation of the soft seats on the 62A and 628 valves in 1976 indicates the procedure used then had steps that are now inconsistent with current Anchor Darling alignment I practice. Anchor Darling had developed these alignment practices after the soft seats were installed at PNPS. PNPS was the first plant to utilize the Anchor Darling Soft seat modification. The steps would result in the discs l being seated slightly low and misaligned. No offset'was incorporated to account for the clearance between the hinge pin outside diameter and the disc bushing inside diameter. Also, the alignments were made with the soft seats I installed on the discs. Alignment should be performed with the soft seats removed to ensure optimal seat to disc contact and verified with a light check. Aligning with soft seats installed would mask any slight misalignment. The same steps were included in TP80-38 which was used to I overhaul the check valves and incorporate soft seats on the 58A and 58B valves in 1980. A maintenance hi wry search on the valves also indicates the valves have been repaired numerou, times in the past including lapping of the seats.

After valves are initially aligned with new parts at the factory, whenever the seats are lapped dimensions change and the alignment would be affected.

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Page 2 of 4 lI

I Also contributing to the misalignment were c>ut of specification clearancos between hinge pin shoulders and ditc bushir.gs found on the 58A, 62A and 628 check valves. This was most likely a resu:t of previous fitups and 3.H.4-49 (Ref 4) not specifying the correct position of the valve disc when the I clearances are measured. The disc should be in the closed position fully seated when the clearances are measured.

Additionally, the tolerance in soft seat protrusion above the stellite seat on tae disc was discussed with Anchor Darling (AD). While BECo DWG Hl!7A-33-1 (Ref. 6) and PNPS 3.H.4-49 (Ref. 4) allow a protrusion of 0.030 1 0.010 inches, AD allows a protrusion of 0.030 + 0.005, -0.010 inches and recommends installation at the lower end of the tolerance. This would minimize the potential for the soft seat to drag as it enters valve seat.

Contributina Root Causes:

Contributing root causes for the 58A and 62A check valve LLRT failures were hinge pin cover leaks (one per valve) which were identified during plant operation. Inspection of the cover seating areas showed degraded surfaces due to steam cuts and corrosion which provided leakage paths.

Other Findinos of Note:

The pressure seal areas on the 58A and 62A valves did not meet the tolerance dimensions on the valve drawing (Ref. 2). The diameters were above the specified dimension by 0.020 and 0.033 inches respectively. This was most likely a result of previous machining in the areas during maintenance to clean them up to achieve an acceptable seal. This did not represent a leakage path.

Indications were noted in the stellite surfaces on the 58A, 62A and 628 valve discs. Stellite is a very hard and brittle material and indications are not uncommon on valve seats with stellite facing. This does not appear to be related to the LLRT failures.

Corrective Actions:

1. All valve seats were lapped and blue checked with a true lapping plate to I ensure that they were in the best achievable condition prior to valve rebuild. In addition, a 1/32 inch radius was installed on the leading edge of the seat rings to minimize the potential for cutting of the soft seat as the disc enters the valve seat.

I Page 3 of 4 ID: 557

l I 2. All four discs (including soft seats) were replaced. During the replacement the new discs were installed in the valve seats without the soft seats, gagged in place and the locations for the hinge pin holes were determined (with allowance given for diametral clearance between hinge pin I 0.0. and bushing 1.0.). The fitup of the new discs achieved alignments in accordance with factory tolerances provided with a new valve. The fitup was performed under the direction of the Anchor Darling factory specialist.

3. A modification to the hinge pins / cover arrangement documented in FRN's against PDC 91-03 (Rei. 3) was incorporated. The modification deleted the I pressure seal, increased the length of the hinge pins ar.d installed an anti-rotation pin and a new design hinge pin cover with a fleritallic gasket. Anchor Darling provided tM new design.

4. The hinge pin cover seating surface areas on all four valves were machined to eliminate all steam cuts and corrosion that could affect the sealing capabilities of the gaskets.

5. The bonnet pressure seal areas were machined on three of the four valvn and new pressure seals were installed. Over size seals were required ori the 58A and 62A valves.

6. Revisions to BECo DHG No Mil 7A-33-1 have been initiated to change soft seat protrusion tolerance to 0.030 +0.005, - 0.010 inches and add note I recommending installation at lower end of tolerance.

7. Establishment of a project team to evaluate alternate means of meeting the I containment isolation requirements for Reactor feedwater. The LLRT Failure Analysis Team is of the opinion that the maintenance performed during RF0 #8 was the most complete to date and if the results are not satisfactory, alternate means on containment isolation should be pursued.

I Plant Management has directed that a project team be established to evaluate alternate means of containment isolation for Reactor Feedwater to support implementation during RF0 #10, if required.

References:

I 1. PNPS Procedure 8.7.1.5 " Local Leak Rate iesting of Containment Penetration and Isolation Valves".

I 2. BECo OHG. No, Mil 7A-1-4, SH. 2, " Nuclear Boiler System feedwater Check i'a l v e s ' .

3. Pbc 91-03, " Standing Mechanical PDC".

4. PNPS Procedure 3.H.4-49, "Feedwater Check Valve Maintenance".

I 5. LER 86-017-01, " Local Leak Rate Test Results of Appendix "J" related Valves in Excess of Limits".

I 6. BFCo DHG. No. M117A-33-1 " Disc Mod. for soft seal installation for feedwater Check Valve.18-900 #T/D Check Valve" Page 4 of 4 I

BECO-91-148, Reactor Containment Bldg Integrated Leakage Rate Test Rept

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