ML18142B221

LER 1977-007-00 for R.E. Ginna, Bus 14 Breaker for C Safety Injection Pump

ML18142B221
Person / Time
Site:	Ginna
Issue date:	03/31/1977
From:	White L Rochester Gas & Electric Corp
To:	Grier B NRC/IE, NRC Region 1
References
LER 1977-007-00
Download: ML18142B221 (8)

Text

REGULATORY INFORMATION DISTRIBUTlON SYSTEM (RIDS)

DISTRIBUTION FOR 1NCOMING MATERIAL 50-244 REC: BRIER B H ORG: WHITE L D DOCDATE: 07/27/77 NRC ROCHESTER GAS 8( ELEC DATE RCVD:

z/s7/vS DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR i ENCL i LICENSEE EVENT REPT (RO 50-244/77-07) ON 06/29/77 CONCERNING DURING TEST C SI PUMP FAILED TO START FROM BUS i4 BREAKER ON 2 ATTEMPTS... W/ENCL.

PLANT NAME:RE GINNA UNIT i REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:

N

+m+++++++++w+++++ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS LER (BACKFIT)

(DISTRIBUTION CODE F00i)

INTERNAL: EG FILE44W/ENC NRC PDR+4W/ENCL I

EXTERNAL: LPDR S ROCHESTERr NY4'+W/ENCL TI C+4W/ENCL ACRS CAT B~4W/0 ENCL COPIES VOT SUB".(ITTED PFR REGULATORY GUIDE 10.1 DISTRIBUTION: LTR 6 ENCL 6 CONTROL NBR: 7809500i8 SIZE: iP+iP 4%%%4% 4%%4 %%4 % 4%% 4 4 %%%%%%4%%%%%%%%% THE END

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<1+It ROCHESTER GAS At(0 ELECTRIC CORPORATIOII o~..89 EAST A'VEIIUE, ROCHESTER, N.Y. 14649 LFON O. WHITE. JR. TCI.CP>i04C =

VICC PRESIDKNt

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~CA Mr. Boyce H. Grier, Director ~@~ w ~g U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

Reportable Occurrence 77-07 (30-day report), Bus 14 breaker for "C" Safety Injection Pump R. E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244

Dear Mr. Grier:

In accordance with Technical Specifications, Article 6.9.2b, the attached report of Reportable Occurrence 77-07, 30-day, is hereby submitted. Two additional copies of this letter and the attachment are enclosed.

N Very truly yours, L. D. White, Jr.

Attachment cc: Dr. Ernst Volgenau (30)

. Mr. William G. McDonald (3) 7809500i8

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I cour TYPE L ~L ~05 0 0 2 4 4 ~QQ P, 0 7 7 0 7 2 7 .7 7" 7 8 . 57 58 59 60 61 74 75 BC Igg~I During test C Sl pump faA d"to s art froin bus 4 breaker on 2 attempts. The pump was j 7 8 9 BC

[QQ3) started successfully with the bus 16 breaker . Subsequently bus 14 breaker started 7 89 80 toO~] pump successfully. This incident is similar to 7 events involvin the bus 16 breaker I 80 I=

7 7

8 9 8 9 and 1 event w'ith the bus 14 breaker. Replacement breaker tvas tested and installed!

80 COOg 7 8 9 PRBAE 80 SYSTEM CAUSE COMPONENT COht PONEf/T CODE CODE COMPONENT CODE SUPPUER MAI4UFACTUlFM

~or ~SF B C K T B R K N W 1 2 0 7 8 9 10 11 12 17 43 44 47 CAUSE DESCRIPTION v

/

A Inspection of circuit breaker revealed no a arent cause for

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7 8 9 Iaaf ~failure. Circuit breal;er is Westinghouse Model DB-50, 500 tr It. C. lt will 7.'. 9.,

be~ 80

~so ~return'ed tb Westinghouse for further investigation.

7 80 89'ACILITY METHOD OF STATUS 55 POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Jig B ~10 0 b Test 7 8 9 10 12 13 44 45 46 FORM OF ACTIVITY CONTENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q~g H NA NA 7 8 9 10 11 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q~g ~00 0 ~B NA 7 89 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION Iitg ~o0 o NA 7 89 11 12 80 OFFSITE CONSEQUENCES

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7 89 LOSS OR DAMAGE TO FACILITY 80'0 TYPE DESCRIPTION

'Qg p, 7 89 10 PUBLICITY

@~7 7 89 80 ADDITIONAL FACTORS 7 89 80 7 89 80 J. T. St. Martin PHDNE716-546-2700, e.'.. 291-21,"

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ATTAC}lf1ENT TQ LER 7i- d2 for Nf/P Pl EVENT DESCRIPTION During a routine refueling outage, a'u(ater phase material sample in the reactor vessel was not inspected as is required by Technical Specification 4.2.2.d. Inspections of the other material samples in steam and steam/water phase areas, and analysis of 'other condition's such as primary coolant chemistry indicate that no deterioration of the sensitized stainless steel has occurred. A Technical ic, ion been recommended to eliminate the requirement for a water phase Specificat'e,has chan material sample inspection for the current outage.

CAUSE DESCRIPTION Due to the location and radioactivity, o.-: the material swnpre packet, it was, not possible to remove,and collect, it with any tools currently available. During the next scheduled refue1ing outage,.

attempts will be made to design a tool for such a purpose, or a new material sample will be placed in the reactor in a location which permits retrieval.

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