ML18219C209

LER 1978-017-03L & LER 1978-018-03L Re Failure of Inverter Power Supply

ML18219C209
Person / Time
Site:	Cook
Issue date:	03/17/1978
From:	Shaller D Indiana Michigan Power Co
To:	James Keppler NRC/RGN-III
References
LER 1978-017-03L, LER 1978-018-03L
Download: ML18219C209 (7)

Text

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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) t DISTRIBUTION FOR INCOMING MATERIAL 50-315 J REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 03/17/78 NRC IN 4 MI PWR DATE RCVD: 03/22/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 LICENSEE EVENT REPT <RO 50-315/78-017/03L-0) ON 02/15/78 CONCERNING WATER SPRAYED INTO THE INVERTOR FOR THE CD DIESEL GENERATOR SPEED GOVENOR RESULTED IN FAILURE QF THE INVERTER POWER SUPPLY... W/ATT LER 78-018/03L-0.

PLANT NAME: COOK UNIT 1 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:

DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRIBUTION CQDE A002)

FOR ACTION: BR CHIEF b ENCER++W/4 ENCL INTERNAL: EG FILE44W NRC PDR++W/ENCL NCL MIPC4+Wf3 .ENCL SCHROEDER/I PPOL I TO++W/ENCL HGUSTON++W/ENCL NGVAI<fCHECK+4EWlENCL GR IMES4 +W/ENCL KNIGHT+~W/ENCL BUTLER++W/ENCL IHAIWAUER+4W/ENCL TEDESCO~~W/ENCL EI SENHUT++W/ENCL BAER++W/ENCL SHAG~~~~W/ ENCL VOLLMER/BUNCH++W/ENCL KREGERl J. COLL I NS++W/ENCL ROSA++W/ENCL K SEYFRIT/ IE++WfENCL EXTERNAL: LPDR'S ST. JOSEPH'I ++W/ENCL TIC4~+WfENCL NS I C+~W/ENCL ACRS CAT B4+Wf 16 ENCL COPIES NOT SUBMITTED PER REGULATORY GUIDE 10.1 DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 78083007 SIZE: lP+iP+iP THE END

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~erleen Itteotrla lower dO'ONALD QSCd C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 March 17, 1978 Mr., J. G. Keppler, Regional Director .

Office of In specti on and Enforcement United States Nuclear Regulatory Commission 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 reports are submitted:

RO 78-017/03L-0 RO 78-018/03L-O Since rely, D. V. Shaller Plant Manager

/pk 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.

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

Dir., MIPC (3 copies) pf

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NRC FORM 386 U. S. NUCLEAR REGULATORY COMMISSION (7.77) o J e LICENSEE EVENT REPORT oeCONTROL BLOCK: (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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'7 M I D C C 1 14 Q2 15 0 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 OQo4 25 26 1 1 1 LICENSE TYPE 1

30 Q4~Qs 57 CAT 58 8 9 LICENSEE CODE CON'T

[oot) "o,~LOs0 60 61 G 0 0 0 DOCK ET NUMBE R 3 1 5 68 Oo 69 EVENT DATE 74 QB 75 0 3 1 REPORT DATE 7

80 QB EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10

~o~ Iiater s ra ed into the inver ter for the CD D'

~O3 in failure of the inverter power supply. The inverter was switched to the alternate power source and the engine was tested. The Diesel was inoperable for 36 minutest

~OS This is the first occurrence of this type.

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~OB 80 7 8

'9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

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SEQUENTIAL OCCURRENCE REPORT REVISION Q>>o LERIRO ACTION FUTURE Poor EVENT YEAR

~78 21 22 EFFECT

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23 SHUTDOWN

~01 24 REPORT NO.

7 26 Qx 27 ATTACHMENT

~03 28 CODE 29 NPRDX TYPE

+L 30 PRIME COMP.

Q 31 NO.

QO 32 COMPONENT TAKEN ACTION ON PLANT METHOD HOURS 022 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER I A IQ>s ~2Q>e ~ZQoo ~ZQ>> 0 0 0 0 N Qoo ~NQoo ~AQos S 2 33 34 35 36 37 40 41 42 43 44 47 cAUsE DEscRIPTIQN AND coRREGTIYE AGTIQNs 027 o This condition was the result of a water su 1 ho c eanin e The Supervisor responsible for this .cleanin has been instructed not to use ressur ized water .cleaning equipment in the vicinity of any electrical panels ~ ~

3 4

80 7

~l5 8 9 FACILITY STATUS

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% POWER 0 Qoo N/A OTHER STATUS 0 METHOD OF DISCOVERY

~aQ31 N/A DISCOVERY DESCRIPTION Q32 7 8 9 10 12 44 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q LOCATION OF RELEASE Q 6 ~Z Q33 ~ZQ34 N A N A 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION 039

~l7 ~00 0 Q>> ZQs 13 NA 80 7 8 9 11 12 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41

~00 0 Qoo 12 NA 80 7 8 9 11 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION 6 Z Q42 N A 8 9 10 80 PUBLICITY NRC USE ONI Y o

ISSUED DESCRIPTION N/A Q o

~Z 044 r 10 68 69 80' 8 9 0

David G. Mizner PHQNE 616-465-5901 NAME QF PREPARER

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NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7.77) s LICENSEE EVENT REPORT CONTROL BLOCK: Ql (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION1 1 6

~oi 7 8 9 M 10 C LICENSEE CODE C 1 14 Qo 15 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 OQo 25 26 4 1 1 LICENSE TYPE 1 I 30 Qs~Qs 57 CAT 58 CON'T KDi 7

soos~L'..Qs 0 5 0 0 03 1 5 Qo 2 QB 0 3 1 7 7 8 QB 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10

~O2 Durin normal o erations, Ft/I0-212, the motor o crated auxiliar feed um dischar e valve for (51 S/6,'ailed to shut from the Control Room. This constituted degradation

~o4 of an operable flow path required by Technical Specification 3.7.1.2. The failure

~os did not present a substantial safety hazard since the'valve failed in the safest (ful

~06 o en osition and redundant auxiliar feed s stems were o erable. This is the. first

~o 7 event of this nature at the lant.

~OB 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~OS ~CH Q>> 8 Q>> ~C Q13 V A L V 0 P Qls ~AQls ~Z Qls 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION Q>>

LER/RO os ACTION FUTURE osr EVENT YEAR

~78 21 22 EFFECT

+

23 SHUTDOWN

~01 24 REPORT NO.

8 26

+w 27

~03 28 ATTACHMENT CODE 29 NPRDR

+L TYPE 30 Q

PRIME COMP.

31 NO.

+0 32 COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~EQls ~ZQo ~ZQoo ~ZQ>> 0 0 0 0 N Qos ~NQos ~AQos ..L 3 0 0 Qos 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o FMO-212 failed to o crate due to a loose screw at an electrical connection. in. the..

valve's motor o erator control circuit. This connection was robabl not ti htened during initial installation, although previous operations with FMO-212 were success-3 ful . The 1 pose screw'as ti htened and subse uent retest was sati sfactory. No other connections were found to be loose and no further actions are 1 armed.

7 8 9 80 FACILITY STATUS E Qs ~l0

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% POWER 0 Qs OTHER STATUS N/A

~

~3P METHOD OF DISCOVERY

~AQol Operator observation DISCOVERY DESCRIPTION Q32 7 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE

~z Q ~zs ~ A AMOUNT OF ACTIVITY ~ N A LOCATION OF RELEASE Q 7 8 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7 8

~00 9

0 Q>>~Z:.Qss 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 7 8

~00 9

0 Qo 11 12 NA 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 zQ- vA 7 8 9 10 80 PUBLICITY DESCRIPTION ~S NRC USF. ONLY ISSUED ~s ss a

O LILtQ44 7 8 9 10 68 69 80 ~ a Michael S. Brown 616-465-5901 0 a

NAME OF PREPARER PHONE: ss