ML18219C210

LER 1978-016-03L. Re Removal of Emergency Diesel Generator from Service for Maintenance

ML18219C210
Person / Time
Site:	Cook
Issue date:	03/14/1978
From:	Shaller D Indiana Michigan Power Co
To:	James Keppler NRC/RGN-III
References
LER 1978-016-03L
Download: ML18219C210 (9)

Text

REGULATORY I NFORI"IATION DISTRIBUTION, SYSTEN ( R IDS)

DISTRIBUTION FOR INCONING NATERIAL 50-315 REC: NRC QRG: SHALLER D V DOCDATE: 03/14/78 NRC IN 8c NI PWR DATE RCVD: 03/ 20/ 78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 LICENSEE EVENT REPT (RO 50-315/78-016l03L-0) ON 02/15/78 CONCERNING 1AB ENERGENCY DIESEL GENERATOR WAS REI"IOVED FROM SERVICE FOR MAINTENANCE AND THE BREAKER ALIGNMENT VERIFICATION AS REQUIRED BY TECH SPEC 4. 8. 1. 1. 1A WAS NOT PERFORNED WITHIN ONE HOUR.

PLANT MANE: COOK UNIT 1 REVIEWER INITIAL: X JN DISTRIBUTOR INITIAL: g, A

+~~~~~~~~~HI ~~~~~~~ DISTR I BUT ION OF THIS NATERIAL IS AS FOLLOWS +++~~~~~~~~~~~~~~~

INCIDENT REPORTS (DISTRIBUTION CODE A002)

FOR ACTION: EI4CER++W/4 ENCL INTERNAL: REG FILE4+W NCL NRC PDR++Wf ENCL NIPC++4f/3 ENCL SCHRQEDER/ IPPQL I TO+4 M/ENCL HOUSTQN4+W/ENCL NQVAK/CHECK++W/ENCL GRINES++W/ENCL KNIGHT44W/ENCL BUTLER++W/ENCL HANAUER++W/ENCL TEDESCO++W/ENCL EI SENHUT~+W/ENCL BAER44 WfENCL SHAO++W/ENCL VOLLMER/BUNCH++W/ENCL KREGER/ J. COLL INS4 +I Jf ENCL ROSA'WfENCL K SEYFRIT/IE++W/ENCL EXTERNAL: LPDR S ST. JOSEPH'I ++l JlENCL TIC++W/ENCL NSIC+4l J/ ENCL ACRS CAT B+4 W/1 6 ENCL I COPIES NOT SUBMITTED PER REGUIATORY GUIDE 10. 1 DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 780810 5 SIZE: iP+iP THE END

0 I 1

IIyO i

Mmertoan OI HA 8 NICHIGAIlIPOIEER CONPAIIIY DONALD C. COOK NUCLEAR PLANT IE>gQig)P P()

~li ~f'I'frn

'8 P.O. Bov 458, Bridgman, Michigan 49106 u,s '"mc p 79pg March 14, 1978 COAIAIEGGEO

'~~ESS Qa l~

Hr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Comnission Region III 799 Roosevelt, Road Glen Ellyn, IL 60137 C'perating License DPR-58 Docket No. 50-315

Dear Hr. Keppler:

Pursuant to the requirements of Appendix A Technical Specifications the following report is submitted:

RO 78-016/03L-O.

Sincerely, D.V. Shaller Plant Manager

/bab cc: J.E. Dolan R.W. Jurgensen G.E. Lien R. Kilburn R.J. Vollen BPI K. R. Baker RO: I I I R.C. Callen HPSC P.W. Steketee, Esq.

R. Walsh, Esq.

G. Charnoff, Esq.

G. Olson J.M. Hennigan 780810015 PNSRC J.F. Stietzel Dir., IE (30 copies)

Dir., HIPC (3 copies)

]gooa./~ %

/ji

R NRC FRORhl 366 I7.77)

LlCENSEE EVENT REPORT CONTROL BLOCK: {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6

~01 8 9 N I 0 C C LICENSEE CODE 1QE 14 15 0 0 0 0 0 0 0 LICENSE NUhIBER 0 0 0 0 25 QE4 26 1 1 1 LICENSE TYPE 1

30 OR~OR 57 CAT 58 CON'T

~01 7 8 SOU CE L~JQG 60 61 0

DOCKET NUMBER 68 Q 69 EVENT DATE 74 QB 75 REPORT DATE 80 OB EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 UNIT WAS OPERATING NORMALLY IN M D 1. T

~03 FROM SERVICE AT 0130 HOURS ON 2 15 78 FOR MAIf]TENANCE. H R TION AS RE UIRED BY APPENDIX A TECH. SPEC. 4... W

~OG HOUR. THE CORRECT BREAKER ALIGNMENT WAS VERIFIED AT 10 5 H UR

~OG REMAINED AT STEADY

~07 CALLED UPO . T

~OB 80 7 8 SYSTE'M CAUSE CAUSE COMP. VALVE.

CODE CODE SUBCODE COMPOiVENTCODE SUBCODE SUBCODE 8

~ZZ 9 10 Q>> ~AQ>>

11

~AQ>>

12 13 Z Z Z Z Z Z 18 Qi ~ZQEE 19

~Z 20 Q's 7

SEQUENTIAL OCCURRENCE REPORT REVISION Q17 LER)RO RERRRE ACTION FUTURE EVENT YEAR

~78 21 22 EFFECT

~

23 SHUTDOWN

~01 24 REPORT NO.

6 26

~~

27

~03 28 ATTACHMENT CODE 29 NPRDX TYPE

~L 30 31 PRIME CohIP.

~P NO.

32 COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~22 SUBMITTED FORM'SUB. SUPPLIER MAiNUFACTURER

~HS~ZQ 33 34 L~JQ20 35 LZJO 36 37 40

~023 41

~Q24 42 MQ26 43 44 47 Q26 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 027 o THE EVENT WAS CAUSED BY THE UNIT SUPERVISOR FAILING TO RE UIRE HAVING THE BREAKER ALIGNMENT VERIFIED. THE SHIFT OPERATING ENGINEER REINSTRUCTED THE UNIT P THE REQUIREMENTS FOR REMOVING VITAL EQUIPMENT FROM SERVICE WITH RESPECT TO PERFORM-3 ING SURVEILLANCE AS DIRECTED BY THE TECH. SPECS. AND OPERATING DEPARTMENT INSTRUCTIONS 4

80 7 8 9 FACILITY STATUS 6 Oss ~io

% POWER o OE>>A OTHER STATUS ~

~30 hIETHOO OF DISCOVERY

~AQ>> P ANT STAT DISCOVERY DESCRIPTION Q32 Y

8 9 10 12 13 44 45 Bo 7

ACTIVITY CONTENT ENG INEER RELEASED OF REI.EASE AhIOUNT OF ACTIVITY~36 LOCATION OF RELEASE Q Z Q33 ~ZQ34 NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES 0

NUi4IBER TYPE DESCRIPTION Q3B

~77 8

~00 0 12 Z Oss 13 NA 80 7 9 11 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR OAhIAGE TO FACILITY TYPE DESCRIPTION Q43

~IB 80 7 8 9 10 ISSUED

~O44 PUBLICITY DESCRIPTION ~ NRC USE ONLY 7 8 9 10 68 69 80 ER 0

NAME OF PREPARER R. S. Keith PHDNE. 61 6 465 5901

h ~.

RECEIVEO OOCUVFN~

CO>CIRCE BESIDE U.S. NRC DIS TRIBUTION SERVICES BRANCH

CoP /

/W>ee~

L, i~Nolcw I

~

NIGHIG 8 PDIYE4 coN IN DONALD C. COOK NUCLEAR PLANT P.O. Box 456, Bridgman, Michigan 49106 March 14, 1978 Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Comnission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-58 Docket No. 50-315

Dear Mr. Keppler:

Pursuant to the requirements of Appendix A Technical Specifications the following report is submitted:

RO 78-016/03L-O.

Sincerely, D.V. Shaller Plant Manager

/bab cc: J.E. Dolan R.W. Jurgensen G.E. Lien R. Kilburn R.J. Vollen BPI K.R. Baker RO: III R.C. Callen MPSC P.W. Steketee, Esq.

R. Walsh, Esq.

G. Charnoff, Esq. i~~ ~l, )S78 G. Olson J.M. Hennigan PNSRC J.F. Stietzel Dir., IE (30 copies)

Dir., MIPC (3 copies)

I t

'I ~

II

~

I'

'li

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION

{7-77) +~~ ~-

LICENSEE EVENT REPORT CONTROL BLOCK: O1 {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6

~0 7 8 M I D LICENSEE CODE C C 1Qs 14 15 0 0 0 0 0 0 0.0 0 0 0 25 Qs4 26 1 1 1 I.ICENSE'TYPE 1

30 Q4~Qs 57 CAT 58 CON'T

~0 7 8 SOURCE L~JQ 60 61 DOCKET NUMBER 68 0 69 EVENT DATE 74 75 REPORT DATE 80 0

EVENT DESCRIPTION AND PROBABI.E CONSEQUENCES QIO UNIT WAS OPERATING NORMALLY IN ODE 1.

~03 FROM SERVICE AT 01 30 HOURS ON 2 1 5 78 FOR MAIl TENANCE. THE

~04 TION AS RE UIRED BY APPENDIX A TECH. SPEC

~os HOUR. THE CORRECT BREAKER ALIGNMENT WAS VERIFIED AT 1 5 UR

~06 REMAINED AT STE D

~0 7 CALLED UP

~OB 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE.

CODE CODE SUBCODE COMPONENT CODE SVBCODE SUBCODE 7

g 8

~ZZ 9 10 Q>>

11 A Q>> ~AQ>>

12 l3 Z Z Z Z Z Z 18 Qs ~ZQs 19

~ZQs 20 SEaUENTIAL OCCURRENCE REPORT REVISION EVENT YEAR REPORT NO. CODE TYPE NO.

Q17 LERIRP REpoRT ~78 21 22 Q

23

~01 24 6

26 Qx 27

~03 28 29 QL 30

[J 31 QQ 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDP PRIME COMP. COMPONENT TAKEN ACTION ON PLANT ~

METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~HO>>~ZO>> ~ZO20 &O21 MQss LzLIQ4 [zJQss O26 33 34 35 36 37 40 41 42 43 44 47

, CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 027 o THE EVENT WAS CAUSED BY THE UNIT SUPERVISOR FAILING TO RE UIRE HAVING THE BREAKER ALIGNMENT VERIFIED. THE SHIFT OPERATING ENGINEER REINSTRUCTED THE UNIT S P THE REQUIREMENTS FOR REMOVING VITAL EQUIPMENT FROM SERVICE WITH RESPECT TO PERFORM 1 3 ING SURVEILLANCE AS DIRECTED BY THE TECH. SPECS. AND OPERATING DEPARTMENT INSTRUCTIONS 4

80 7 8 9 FACILITY STATUS 6 Q>> ~l0

% POWER 0 Qss NA OTHER STATUS 0 M30 METHOD OF DISCOVERY

'AQ>i PLA T T DISCOVERY DESCRIPTION 032 R

8 9 10 12 13 44 45 46 80 ENGINEER ACTIVITY CONTENT RELEASED OF REI.EASE Z Q33 Z Q34 NA AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE Q 7 8 9 10 44 45 80 PERSONNEL EXPOSURES TYPE DESCRIPTION Q3g 7 8

~00 9

NUMBER 0$11 12 ZQss 13 NA 80 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 7 8 IrJQs 9 10 80 PUB L I CITY NRC USE ONLY ISSUED DESCRIPTION ~4.

o ~Q44 7 8 9 10 68 69 80 o 0

R" S ~ Ke'I th PHoNE'16 465-5901 L NAMF PF PREPARER 0

I 4,

.IW I