05000321/LER-1979-033-01, /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

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/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)


LER-1979-033, /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
Event date:
Report date:
3211979033R01 - NRC Website

text

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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 l

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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.

1 8 9 DE COCE SLBCO E COMPONENT CODE SUSC^ E SU E

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10 11 12 IJ 18 19 20 SEQUENTI AL OCCUR R E NCE REPORT REVISION E E R /810 CVENT YE AR REPORT NO.

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@l Valve maintenance is not comolete at this time.

In order te ccmoly with Tech. Snec. I 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

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Cause Description and Corrective Actionsrecorded and will be reported in the Leak Rate Report. required by Appen-dix J of 10CFR50.

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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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