ML19263C351

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LER 79-011/03L-0 on 790117:during Normal Startup Test & Reactor in Cold Shutdown,Review of HNP-2-3160 (RHR Pump Operability) Revealed Required Flow Not Being Met.Caused by Procedural Error by Personnel
ML19263C351
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 01/29/1979
From: Thomas Greene
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19263C346 List:
References
LER-79-011-03L-01, LER-79-11-3L-1, NUDOCS 7902220023
Download: ML19263C351 (2)


Text

LICENSEE EVENT REPORT l CONTROL DLOCK: l l l l l lh (PLE ASE PRINT OR TYPE ALL REQUIRTO INFORMATION) o i 8 9 l l E I I l H l 2 14l@l 150 LICENSE E CCOE 0

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, LICENSE NUEJEH a 26 l1 l1l1]@l57 LAT58 LaCENSC lvPE Jo lj@ ,

1

ON'T E_ S S$n%60l L l@l015 61 10 10 10 13 16 16 COCK ET NUve ER 6d l@l0 b3 11 11 Il1719l@l011 EV ENT DATE 14 75 12 19 7 19dJl@

REPORT DATE EVENT DESCRIPTION AND PROB A8LE CONSEQUENCES O'o o 2 lDuring normal start-up testing, with the reactor in cold shutdown, a review of  ; .

t i

o 3 ;HNP-2-3160 (RHR Pump Operabiltiy) Data Sheets revealed that a test for RHR pumps A  ; j i

o 4 land C had been ran such that the flow as recuired by both the nrocedure and Tech. I o s ISpecs. was not met (7700 gpm recuired-test ran at 7300 gom); yet the procedure was 1  :

I o c lsigned off as acceptable. There were no probable consecuences the pumos correctly I  ;

o 7 Imet the combined puma requirement of 17,000 gpm. The A and C pumos were declared  !

l o a linoperable per Tech. Specs. (continued) 1 8 9 80 DE CODE SUSC E CO*.*PONENT CODE SL9C dE S COE a 9 8

9 IC IF @ lA l@ lA l@ l P l u l M I P l X I X I@ I B l@ [Z_.j @

10 11 12 13 13 19 20

__ SEQUE NTI AL OCCURRENCE REFCRT REVISION LER RO EVENT YEAR REPORT NO. CODE TYPE NO.

O .ag.;,1 1719 21 22 l-l 23 lOl111l 24 26 l/l 27 10 13_ j 28 29 Ll 30 l-l 10l 31 32 TA E ACTO O PLANT ETH HOURS S B IT D F t B. S 'PPLIE MAP FA TL ER L2J@l 33 J4 HI@ lZ l@

3s l34 Zl@ l0 l010101 31 Lyj@

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40 42 43 44 41 CAUSE GESCRIPTICN AND CCRRECTit E #~TIONS i o lThe cause of the event was n error bv licensed personnel. Personnel inadvertentiv ra_rj t

Ti 1 Ithe test with a flow cf /300 tjom insteaJ of the recuirea 7700 com. The torrective i  !

i 2 l action will be covered by that being imolemented for LER 2-79-004: i.e., a review willi i i 3 lbe made of the pump and valve Test Program and personnel retrained as neeaed. l f  !

1 4 l l 8 9 80

'ST M S sPOwER S'5CCC?iRY OTwE R STATUS OiSCOvERY cEsCRiPTiON Review of Data Sheets

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W@ l0 l 010l@l N/A l l l@l l

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AC TIVI TY CONTENT RELEASED OF RE LE ASE AMOUNT OF ACTIVITY LOCATION OF RELE ASE i 6 N/A N/A 8 9

[Z_] @ l10Zl@ l 11 44 l l 45 80 l ,

PERSONNEL EXPOSURES NUMBE R TYPE CESCRIPTION i 7 101010j@lZl@l N/A l PERSONNE L INJL IES NUHER DESCntPTION i x 8 9 1010101@l 11 12 N/A l ,

80 lor.S OF OH D AMAGE TO FACILITY l

i 1 PE lZl@l once,nioN N/A 7902220r/>$ .

l 1

3 10 80 j lS';U F t E CHiPTION e

- o 8 3 L!LISI 30 N/A I II IIIIIIiiiI!

08 69 e0 ; ,

k N AP.'E OF PREP AREH Oene, t. t. 09 Tv. PHONE. (9 2) 367-7781  !

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7..I

LER 2-79-011 Event Description and Probable Consecuences (Continued)  !

1 On 1-30-79, they were re-tested correctly and found acceptable before  !

being declared operable.  !

G P

  • - eepw