05000244/LER-2077-007, Bus 14 Breaker for C Safety Injection Pump

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)

LER-2077-007, Bus 14 Breaker for C Safety Injection Pump

Event date:
Report date:
2442077007R00 - NRC Website

text

REGULATORY INFORMATION DISTRIBUTlON SYSTEM (RIDS)

DISTRIBUTION FOR 1NCOMING MATERIAL 50-244 REC:

BRIER B H NRC ORG:

WHITE L D ROCHESTER GAS 8( ELEC DOCDATE: 07/27/77 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:

XJM DISTRIBUTOR INITIAL:

N

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

(DISTRIBUTION CODE F00i)

INTERNAL:

EG FILE44W/ENC I

NRC PDR+4W/ENCL EXTERNAL:

LPDR S ROCHESTERr NY4'+W/ENCL TIC+4W/ENCL ACRS CAT B~4W/0 ENCL COPIES VOT SUB".(ITTED PFR REGULATORY GUIDE 10.1 DISTRIBUTION:

LTR 6 SIZE:

iP+iP ENCL 6 CONTROL NBR:

7809500i8 4%%%4% 4%%4 %%4 % 4%% 4 4 %%%%%%4%%%%%%%%%

THE END

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g1 Q( 0 ! 'h s 'I kifPlllIJL ROCHESTER GAS At(0 ELECTRIC CORPORATIOII

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<1+It o~..89 EAST A'VEIIUE, ROCHESTER, N.Y. 14649 LFON O. WHITE. JR.

VICC PRESIDKNt Mr. Boyce H. Grier, Director U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 TCI.CP>i04C

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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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~05 0 0 2

4 4

7 8

57 58 59 60 61 Igg~I During test C Sl pump faA d"to s art froin bus 4

EVENT DATE REPORT DATE

~QQ P, 0

7 7

0 7

2 7

.7 7"

74 75 BC breaker on 2 attempts.

The pump was j 7

8 9 BC [QQ3) started successfully with the bus 1 6 breaker.

Subsequently bus 14 breaker started 7

8 9 80 I=

and 1 event w'ith the bus 14 breaker.

Replacement breaker tvas tested and installed!

7 89 80 toO~]

pump successfully.

This incident is similar to 7 events involvin the bus 16 breaker I

7 8 9 COOg 80 7

8 9 SYSTEM

CAUSE

CODE CODE

~or ~SF B

C 7

8 9 10 11 12 CAUSE DESCRIPTION 80 PRBAE COMPONENT SUPPUER COht PONEf/T MAI4UFACTUlFM W

1 2

0 COMPONENT CODE K

T B

R K

N 17 43 44 47 v

/

Inspection of circuit breaker revealed no a arent cause for [ODB]

A 7

8 9 80 Iaaf ~failure.

Circuit breal;er is Westinghouse Model DB-50, 500 tr It.C. lt willbe~

7 89'ACILITY STATUS 55 POWER Jig B

~10 0

7 8

9 10 12 13 FORM OF ACTIVITY CONTENT RELEASEO OF RELEASE AMOUNT OF Q~g H

NA 7

8 9

10 11 PERSONNEL EXPOSURES NUMBER TYPE

DESCRIPTION

Q~g ~00 0

~B NA 7

89 11 12 13 PERSONNEL INJURIES NUMBER

DESCRIPTION

Iitg ~o0 o

NA 7

89 11 12 OTHER STATUS ACTIVITY OFFSITE CONSEQUENCES

[<is]

7 89 LOSS OR DAMAGE TO FACILITY TYPE

DESCRIPTION

'Qg p,

7 89 10 PUBLICITY

@~7 7

89 ADDITIONAL FACTORS METHOD OF DISCOVERY b

44 45 46 44 45 7.'. 9.,

. ~so

~return'ed tb Westinghouse for further investigation.

NA LOCATION OF RELEASE DISCOVERY DESCRIPTION Test 80 80 80 80'0 80 7

89 80 7

89 J. T. St. Martin 80 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 chan the sensitized stainless steel has occurred.

A Technical Specificat'e,has been recommended to eliminate the requirement for a water phase ic, ion 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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