ML18219C243

LER-1977-022-00 for Donald C. Cook, Unit 1 - Reactor Trip and Safety Injection Due to Loss of Fourth Inverter Caused by Blown Fuse

ML18219C243
Person / Time
Site:	Cook
Issue date:	06/07/1977
From:	Jurgensen R American Electric Power Service Corp, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To:	James Keppler NRC/IE, NRC/RGN-III
References
LER-1977-022-00
Download: ML18219C243 (7)

Text

Cob'ION NICC FGRIi 196 I2-70)

J U.S. NUCLGAB REGULATORY G-DOCKET NUMOE B FILE NUMIIER NRC DISTRIBUTION roB PART 50 DOCKET MATERIAL INCXDENT REPORT FROM: DATE OF DOCUMENT Indiana 86 Michigan Power Company 6/7/77 Bridgman, Michigan DATE RECEIVED Mr. Ji Gi Keppler S

h R~ Wi Jurgensen 6/15/77 GALETTE B CINOTORIZED PROP INPUT FOAM NUMBER OF COPIES RECEIVED

/ S / /./L/C H

~OB IG INAL ~CLASSIFIED I QCOPY.

DESCRIPTION ENCLOSURE I

1 I

Licensee Event Report (RO 50;315/77-22) on 4/21/77'oncerning a reactor Nrip and safety injection occurring due to a loss of g4 inverter caused by blown fuseo ~ ~ ~~ ~ ~

PLANT NAME:

(1-P) (2-P) gook Unit No. 1 hIJL 6/16/77 NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J, COLLXNS P)pi~~;Q7,/LEDGEDLI FOR ACTION/INFORMATION BRANCH CHIEF:

W 3 CYS FOR ACTION LXC, ASST,:

W CYS AC S j'YS UQQ~~ S 'NT INTERNAL D IST Rl BUTION REG PDR I&E 2 MIPC SCHROEDER/IPPOLXTO'OUSTON NOVAK/CHECK GRIMES BUTLER HANAUER TEDESCO/MACCARY EISENHUT SIIAO VOLLMER/BUNCH KREGER/J COLLXNS EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR:

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+e-INDIANA& MICHIGAIVPDNE8 CDNPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 June 7, 1977 Mr. J.G. Keppler, Regional Director Office of Inspection and,Enforcement United States Nuclear Regulatory Commission gggu,gg GggI I'le MI'1 Operating License DPR-58 Docket No. 50-315

Dear Mr. Keppler:

Pursuant to the requirements of Appendix A Technical Specifications and the United States Nuclear Regulatory Commission Regulatory Guide 1. 16, Revision 4, Section 2.b, the following report is submitted:

RO 50-315/77-22.

Sincerely, q

R.W. Jurgensen Plant Manager g~

o~~'~

/bab cc: J.E. Dolan ;S R.S. Hunter G.E. Lien R. Kilburn R.J. Vollen BPI

'4// ~

K.R. Baker RO: III R.C. Callen MPSC P.W. Steketee, Esq.

R. Walsh, Esq.

G. Charnoff, Esq.

G. Olson J.M. Hennigan PNSRC R.S. Keith Dir., IE (30 copies)

Dir., MIPC (3 copies) ~>>6SO003 JUN 9 i977

'I n~ rs Form No. 4494 LICENSEE EVENT REPORT CONTROL BLOCK: (PLEASE PRIMT ALL REQUIRED IMFORMATIOM) 1 6 UCENSEE LCENSE EVENT NAME LICENSE NUMBER TYPE TYPE foai] M I D C C 1 0 0 0 0 0 0 0 0 0 4 1 1 1 1 ~0033 30 '32

~~~

7 8 9 14 15 25 26 31 REPO+ REPORT OOCKP'UMBER EVENT OATE REPORT OATE CATEGORY TYPE SOURCE QogcooT 0 5 0 0 4 2 1 7 7 6 7 57 58 59 60 61 68 69 74 75 80 7 8 EVENT DESCRIPTION Qo2 WHILE IN MODE 1 AT 58K POWER A REACT 80 7 8 9

~03 A LOSS OF ¹4 I NVERTER CAUSED BY BLOWN FUSE.

7 8 9 80 7 8 9 80

[OO~]

7 8 9 80 RO-50-315 77-22

[OOg 80 7 8 9 PAME SYSTEM CAUSE COMPONENT COMPONENT COMPONENT COBE SUPPUER MANUFACTURER COBE COBE A 6 0 K T 5 R W 1 2 0 N 7 8 8 10 11 . 12 17, 43 47 48 CAUSE DESCRIPTION

~08 THE LOSS OF CR I D ¹4 RESULTED IN T 7 8 9 80

~os REACTOR PROTECTION SYSTEM WHICH G I 7 8 9 80 0 WAS OPEN, WHILE 50K POWER -- CAUSING A REACTOR TRIP. See su 1 ement 7 8 9 80 FACILITY METHOO OF POWER OTHER STATUS OISCOVERY DISCOVERY OESCRIPTION STATUS Qg 5 ~05 3 13 NA 44 45 46 80 7 8 9 10 12 FORM OF AMOUNT OF ACTIVITY LOCATION OF RELEASE NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE. OESCRIPTION o ~00 o z 7 8 9 11, 12 13 80 PERSONNEL INJURIES NUMBER OESCRIPTION

~<< ~00 o 80 7 8 9 11 12 OFFSITE CONSEQUENCES g NA 7 8 9 80 LOSS OR DAMAGE TO FACILITY 7' 9 ~ 10 80 PUBLICITY 7] NA 7 8 9 80 ADDITIONAL FACTORS

~18 NA 7 8 9 80 pgg 7 8 9 80 6 16 ) 46 5- 5 90 1 ( 365 )

NAME J . L . RI SCHL I NG ( GPO 8bl ~ <$ 7

3, H'

SUPPLEMENT TO REPORTABLE OCCURRENCE RO-'50-315 77-'22 SUPPLEMENT TO CAUSE DESCRIPTIONS THE LOSS OF GRID 84 ALSO INITIATES HALF OF THE SAFETY INJECTION SIGNAL, LOW STEAM LINE PRESSURE. IT IS POSTULATED THAT THE OTHER HALF OF THE SAFETY INJECTION SIGNAL, HIGH STEAM FLOW, RESULTED WHEN THE STEAM DUMP SYSTEM OPERATED AFTER THE REACTOR TRIP.

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