05000366/LER-1979-039-01, LER-039/01T-0 on 790523:during Shutdown,One Feedwater Check Valve & Three RHR Pump Suction Valves Deemed to Have Excessive Leak Rates.Caused by Change to ASME Criteria. ASME Criteria Reviewed & Found Too Strigent

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LER-039/01T-0 on 790523:during Shutdown,One Feedwater Check Valve & Three RHR Pump Suction Valves Deemed to Have Excessive Leak Rates.Caused by Change to ASME Criteria. ASME Criteria Reviewed & Found Too Strigent
ML19259C282
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 05/30/1979
From: Thomas Greene
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19259C270 List:
References
LER-79-039-01T, LER-79-39-1T, NUDOCS 7906140532
Download: ML19259C282 (3)


LER-1979-039, LER-039/01T-0 on 790523:during Shutdown,One Feedwater Check Valve & Three RHR Pump Suction Valves Deemed to Have Excessive Leak Rates.Caused by Change to ASME Criteria. ASME Criteria Reviewed & Found Too Strigent
Event date:
Report date:
3661979039R01 - NRC Website

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4 63 61 D~.,,CK E T ALMB ER tid C3 EVEP4T QATE 14 lb (4kPORT O ATE SJ EVENT DESCntPTION AriO PRC9ABLE CONSEQUENCE *, h T D l On flay 23, 1979, while shutdown for anchor bolt insocction and recair, it was discov-l Tal I ered that the following valves which were originally judged to have accootable leak

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feedwater check valve 2821-F0108: and RHR ouro I I suction valves 2 Ell-F00aB, 2 Ell-FCoaC, and 2 Ell-F004D.

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i Cause Description and Corrective Action, This review showed that the acceptance criteria as specified in the Long Term Inservice Inspection Pump and Valve Test Plan (based en the suggest-ed values in Table IIN-3420-1 of ASME Section XI,..part IWV) are too string-ent to be realistically used.

This prcepted the licens~ee and Southern i

Company Services, Inc. to develop a new set of acceptance criteria (as per-l mitted by ASME Section XI, part IWV, paragraph IWV-3420, (f)).

This new I

set of acceptance criteria was then reviewed by the Plant Review Board and approved for replacing the old ones in the Pump and Valve Test Plan.

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NARRATIVE

SUMMARY t.

On May 23, 1979, while sh0tdown for anchor bolt inspection and repair, it was discovered that the folicwing valves which were originally judged to have acceptable leak rate values per Tech. Spec. 3.6.1.2 and Appendix J to 10CFR50 (based on overall leakage and concerned with limiting release to public) when tested per Ht:P-2-3952, did not meet the individual valve leak rate criteria per ASME Code,Section XI, part IWV:

feedwater check valve 2821-F010B; and RHR pump suction valves 2 Ell-f0048, 2 Ell-F004C, and 2 Ell-F004D.

It was originally interpreted that the ASME acceptance criteria did not 90 into effect until cc=ercial operation; however, the interpretation that it took effect with issuance of the operating li:ense (6-13-78) meant that any valves tested after 6-13-78 had to meet the ASME acceptance crit-i eria.

The above listed valves were all tested after E-13-78, and the leak-age value for each exceeded the ASME acceptance crite-ia as specified in j

i the HiiP-2 Long Term Inservice Inspection, thus the ASEE acceptance criter-ia was not met.

Follcwing the discovery that the valve leak rates had Exceeded the ASME leak rate acceptance criteria, a' review of the acceptance criteria was made by the licensee and Southern Coreany Services, Int This review showed that the acceptance criteria as specified in the HNP-2 Long Term Inservice Inspection Purp and Valve Test Plant (based on the sug:r-sted leak rate values in Table IWV-3220-1 of ASME -Section XI, Part IW'.1 are too stringent to be realistically used.

This prompted the licensee a:d SCSI to cevelop a new set of acceptance criteria (as permitted by ASME Eeccion XI, part IUV, paragraph IWV-3020, (f)).

Using the concept that the purpose of the ASME testing is to Jetect valve degradation, the license and SCSI were able to prepare rew acceptance criteria that would satisfy both the ASME and the Tech. Spec. and Appendix J testing consideratiers.

This new set of acceptance criteria was then reviewed by the Plant Re/iew Board and was approved for the replacement of the old acceptance c-iteria in the Pump and Valve Test Plan.

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