ML19350C749

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LER 81-015/03L-0:on 810306 & 07,RHR Return Valve E11-F015A,core Spray Pump Min Flow Valve E21-F031A & RHR Min Flow Valve E11-F007A Exceeded Tech Spec Local Leak Rate Limit.Cause Unknown.Investigation Continuing
ML19350C749
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 03/31/1981
From: Coggin C
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19350C743 List:
References
LER-81-015-03L-01, LER-81-15-3L-1, NUDOCS 8104060659
Download: ML19350C749 (2)


Text

U. S. NUCLE AR REGUL ATORY CO*.1 MISSION , m{

HRC FORM 36G

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C , LICENSEE EVENT REPORT coNTRot stoco l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) l l ] l l @

lo I tj l G l A ! E l I l H l 1 l@l 0 l 0 l - 10 l 0 l 0 l 010,l- l 0 l 0 l@l 2s 4 l 1ticENst 2s 11 11 l 1 l@l37 cAtsc-@

l l i a 3, uqsEE CooE i4 :s ucENst NuvseR 13 Pe as COYT lo111 'C l L60]@l 0151010101312 S l 1 l@l 0131016 (O l 8 l 1 l@l 0 l 313 74 75 PEPORTlCATE 1 l 811 eJ l@

1 6 61 DOCKET NLVBER 6d EVENT O ATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h 10121l0n 3-6-81 and 3-7-81, wi th Uni t I shutdown for a refueling / torus modif- 1 10131 i cati on outage the following LLRTs were performed: RHR return valve E11-1 1o 141 IF015A. CS numo minimum flow valve E21-F031 A, and RHR minimum fita valve I lo i s t I E11-F007A. Reviewed (on 3-6-81, and 3-9-81) by the LLRT coordinator i lo lo l Idetermined that they were leaking such that the .60 La overall limit of I l o_lLJ I T e c h S p e c s 4. 7 . A . E . G c o u l d b e e x c e e d e d . Event posed no threat to publici lem1thealth or safety.

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Repetitive event - refer to LER 50-321/1981-014. I 80 SYSTEM CAUSE CAUSE C OV P. VAL %E CODE CCCE SUBCODE COMPONENT CODE SU8CCDE SL8 COLE lo191 lC l F l @ LE_j@ l X j @ l V l A I L l V l E l X l@ LEj @ [D_J zu

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8 9 to 11 12 13 16 v3 7

OCCURRENCE HEPORT H EVISION SEQUE NTI AL EVENT YE AR REPORT NO, CODE TYPE N O.

LER RO O,agjy; a 1811 l l--J 101115l l/l l 0131 lLl l-l l 0l

_, 21 22 23 24 26 27 28 29 30 31 32 AKE A TG ON PLANT t T HOURS S 9 i FO L B. S' PPLIE MA A T PER LLJ@l x l@ lZl@ Lz_j@

36 3 1010l010l lY l@ 4a 41 lY 42 l@ l43 Al@ lW l0 13 1047 l@

4g J3 J4 35 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS lijolIThe cause of the valves' leaking is unknown at the present time. An in-1 11 1 1 Ivestigation is underway. The valves will be repaired and successfully I Iilli Iretested prior to startup following the outage. An update report will I l

li 131 l be submitted.

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, l i i41 I SO T 8 9 S TUS  % PCnER OTHER STATUS DISC F DISCOVERY DESCRIPTION Performed LLRT l liI5i Lcl@ l 01010 l@l NA l l Bl@l A TlVITY CONTENT RELE ASED OF RE LE ASE AMOiNT OF ACTIVITY LOCATION OF RELEASE NA l l NA l l i I G8 l9l Z ] @ [ 10Z_ J @11 l F 44 45 6J PERSONNEL FXPOSLHES NUYtM R TYPE D ESCHiP TION -

1i I 71 1010 10 l@Lzj@l NA i S

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nRsONNd'~ULS NUV9ER DESCn PTtON 1

1 a 8 9 lolo10l@l 11 12 NA 80 l

LO% OF CR DA.VAGE TO F ACIUTY TYPE CESCRiPTION l 3 l 9 l (,Z_j@l NA l go 7 8 9 10 e

E SC RIP TION 2 9 IS5UEfhl DL NA l llll1ll!!!Ii15

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'810~.'4 0 6"0659 NA*. E ar PREoARtn C. L. Coggirdnt. Pl t. Eng. Serv. gnoyg. 912-367-7851

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s LER #: 50-321/1981-015 L

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' Licensec: Georgia Power Company

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Facility Name: Edwin I. llatch Docket f: 50-321 i .

S i Narrative Report

-for LER 50-321/1981-015 l

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l , ' On 3 -.6 - 81, with-Unit 1 shutdown for a refueling / torus modific- '

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c ation~ outage, local leak rate tests, per llNP-1-3952, Primary

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Containment Periodic Type B and Type C Leakage Tests, of the RilRD return valve E11-F015A and the. core spray pump minimum o

F flow valvo E21-F031A were performed. On 3-6-R1, the LLRT coordinator . reviewed - the . data sheets, and it w..s determined

. , that'. thcivalves wcrc- Icaking - excessively (as found: would not pressurize) .such that. it would' cause the .60 La overall allow-(able leakagc ~ por ' Tech Specs '4 ; 7. A. 2-.G to be exceeded. On 3- E 81', f an 1 LLRT . o f1_ the. RI!R pump. minimum flow valve E11-F007A s

. wa s L per formed. -_0_n '3-9-81, tho' LLRT coordinator reviewed the

data 1 sheet,, and_ ite was ' dctermined that the valve was leaking

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-(as' .found: greater ' than 2200 acem) such that it could cause 1

thel .60: La overalliallowabic Icakage per Tech Specs 4.7. A.2.G toibe ' exceeded. . -These are repetitive occurrences ' - refer to

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' LER f50-321/1981~-014. - There.were noc cf fect.3 on _ public health for safety.

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The : cause l'ofi the valves' 1' caking is unknown at the present

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tim'c ; 'an' investigation .is underway.

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The+ valves -will be s . repaired 0and" satisfactorily rctested prior to startup follow- -

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Ja< ing (the outage. , An' upda te : report will : bc. . submitticd.

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