ML19270G367

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LER 79-033/01T-0 on 790518:RHR Return Valves E11-F015B & E11-F017B & RHR Pump Suction Valves Leaked During Local Leak Rate Testing.Cause Unknown.Corrective Maint Will Be Performed to Allow Satisfactory Leakage Rate
ML19270G367
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 05/24/1979
From: Thomas Greene
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19270G366 List:
References
LER-79-033-01T, LER-79-33-1T, NUDOCS 7906060222
Download: ML19270G367 (3)


Text

LICENSEE EVENT REPORT coNTnot BLOCK: I l l l l l lh (PLEASE PnlNT on TYPE ALL HEOUIRED INFOHMATioN) 1 6 Tl]8IG 9 I ALICENSEE I E liCODE lH l1 l@[0 14 15 101010 10 1010 10 10 lo 10 LICENSE hvP.*uEH 23 l@l aLICEP.:et 2h l 11 l14l PE il JJll@lbi L Al I *sel@

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@ l While sht>1hn for refunling_.on c;-19 79 ; rinrinn the_pnrfnmnce_ of Local Leak Rate  !

@ l Testino per procedure HNP-1-3957. it was discovered that RHR r_e_ turn valves Ell-F015B I

@ l and E11-F0178. and RHR pump suction valves were leakino in excess of scecif *ed crit- I ,

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@ l eria. Since these valves are the inboard and outuvard containment isolation valve I

@ l pairs for primary containment penetration X138 and X2048 resoectivelv. a of tential I

@ I' leakage path from primary containment to secondary containment exists. Refer to: 1 E I LERs 76-28, 77-34, 78-17, 79-27, 79-28. -

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DE COCE SLBCO E COMPONENT CODE SUSC^ E N

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8 9 10 11 12 IJ 18 19 20 SEQUENTI AL OCCUR R E NCE REPORT REVISION E E R /810 CVENT YE AR REPORT NO. CODE TYPE N O.

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3G 40 42 43 44 CAUSE oESCnlPTION AN0 CORRECTIVE ACTIONS h

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Valve maintenance is not comolete at this time. In order te ccmoly with Tech. Snec. I pl 4.7. A.2 9, corrective maintenance will be performed as reauired to allow a satisfac- 1 El tory leakage rate for each containment isolation valve. The *as found" leakafe for I

. g i each valve that requires maintenance will be (continued) I g 9 80 STA 5  % POWER OTHER STATUS iO RY DeSovtRV OESCRIPTION M LtLj @ l 01 Olu l @ l N/A l lB l@l Local Leak Rate Test I

' JuviTY CO0 TENT REtEaSE AVOUNT OF ACTIVITY LOCnacN or RELEASE

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PERSONNE L ExPOSOES NOVBER TYPE DESCRIPTION *

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Georgia Power Company Plant E. I. Hatch Baxicy, Georgia

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Cause Description and Corrective Actions (continued) recorded and will be reported in the Leak Rate Report. required by Appen- .,

dix J of 10CFR50. .

9 2274 273 s

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I NARRATIVE

SUMMARY

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, Durins the 1979 Refueling Outage, Type B and C Local Leak Rate Tests (LLRT) will Le performed to ccmply with Tech. Specs. Sections 4.7.A.2.e and 4.7.A.2.F and Appendix J to 10CFR50. This will involve subjecting potential leak paths, j i.e. containment penetrations (Type B Test) and containment isolation valves (Type C Tests) to the same test conditions that would occur post-LOCA.

Conducting local leak rate test (LLRTs) allow discovery and elimination of leak paths thru the containment without performing the Integrated Leak ,

Rate Test (Type A Test) each. refueling outage. ,

Since the primary concern in the containment leakage test program is tot-al containment leakage, no specific acceptance ' criteria is defined for an ' individual Type B or Type C LLRT (excluding MSIVs). However, the logis-tics used in determining an unsatisfactory LLRT encompasses several factors.

The valve design, size, service, etc. are considered in order to maintain .

the total containment penetration leakage within the acceptance criter- ,

ia without imposing an unrealistic -leakage rate limit on an individual valve.

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