ML18219B562

Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-056/03L-0 and RO 78-057/03L-0)

ML18219B562
Person / Time
Site:	Cook
Issue date:	08/22/1978
From:	Shaller D American Electrtic Power System, Indiana Michigan Power Co
To:	James Keppler NRC/RGN-III
References
LER 1978-056-03L, LER 1978-057-03L
Download: ML18219B562 (9)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FQR INCOMING MATERIAL 50- 316

'REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 08/18/78 NRC IN 8. MI PWR DATE RCVD: 08/24/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-316/78-052> ON 07/19/78 CONCERNING RHR PUMP SUCTION VALVE IMQ-320 CYCLE TIME EXCEEDED MAXIMUM STROKE TIME OF 2 MIN WHILE UNIT WAS IN MODE 1 DURING SURVEILLANCE TESTS... W/ATT LERS78-053 78-54 78-055.

PLANT NAME: COOK UNIT 2 REVIEWER INITIAL: XJM DISTRIBUTOR INITIAL: g5J DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ++4+++<<+++++<<+++

NOTES:

1,. SEND 3 COPIES OF ALL MATERIAL TO ISE INCIDENT REPORTS (DISTRIBUTION CODE A002)

FOR ACTION: BR CHIFF ORB01 BC++W/4 ENCL INTERNAL: EG FI W/ENCL NRC PDR44W/ENCL

/2 ENCL MIPC+4W/3 ENCL I 8c C SYSTEMS BR++W/ENCL EMERGENCY PLAN BR+%W/ENCL NOVAK/CHECK++W/ENCL EEB~~W/ENCL AD FOR ENG%4W/ENCL PLANT SYSTEMS BR~%W/ENCL HANAUER++W/ENCL AD FOR PLANT SYSTEMS+>W/ENCL AD FOR SYS 8( PROJ++W/ENCL REACTOR SAFETY BR+4W/ENCL ENGINEERING BR4~W/ENCL VOLLMER/BUNCH>4W/ENCL KREGER/J. COLL INS~~+W/ENCL POWER SYS BR<+W/ENCL K SEYFRIT/IE++W/ENCL EXTERNAL: LPDR~S ST. JOSEPH MI++M/ENCL T I C r L I Z CARTER++W/ENCL NS I C44 W/ENCL ACRS CAT B~uW/16 ENCL DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBA: "

782360105 SI ZE: 1P+1P+3P

%8l+dl+%%8f+NI%%%%%%%8l%%4%%%% w%%%%%%%%% THE END

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El DONALD C.,COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 August 22, 1978 cn h7 a~ (op wc a~< ~l~

Mr. J.G. Keppler, Regional Director ~~C/7 Office of Inspection and Enforcement Rn r.7>>

~CA United States Nuclear Regulatory Commission Region III R aB lC 799 Roosevelt Road m CA Glen Ellyn, IL 60137 Operating License DPR-74 Docket No. 50-316

Dear Mr. Keppler:

Pursuant to the requirements of the Appendix A Technical Specifications the following reports are submitted:

RO 78-056/03L-0 RO 78-057/03L-O.

Sincerely, D.V. Shaller Plant Manager

/bab cc: J.E. Dolan R.W. Jurgensen R.F ~ Kroeger 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.

J.M. Hennigan G. Olson PNSRC J.F. Stietzel R.S. Keith T.P. Bei lman/J.L. Rischling Dir., IE (30 copies) G ~c ts7S Dir., MIPC (3 copies)

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NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7.27) ..

LICENSEE EVENT REPORT CONTROL BLOCK: Qi lPLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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[0D1]

7 8 9 M 1 0 0 LICENSEE CODE 0 2 14 QE 15 0 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 25 Qs 26 4 1 1 LICENSE TYPE 1 1 30 Q4~ 57 CAT 58 Qs CON'T

~o1., "'" ~LQR 0 5 0 0 0 3 1 6 QTO 7 2 8 7 8 74 Qsp 75 8 2 2 7 8 80 Qs DOCKET NUMBER 68 69 EVENT DATE REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 A SURVEILLANCE TEST ON THE 2 AB DIESEL Gl&ERATOR RESULTED IN AN OVERSPEED TRIP AS THE D 4 ACTION REQUIREMENTS WERE FULFILLED PREVIOUS OF A SIMILAR NATURE INCLUDE 050 315/78 Olg09g AND 77 42 ~

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

~EE QTT E QTE ~EQR E N G I N E QT4 ~ZQ15 ~z Q16 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION QTT LERIRP REPoRT ACTION FUTURE EVENT YEAR

~78 21 22 EFFECT

+

23 SHUTDOWN

~05 24 REPORT NO.

6 26 Q~

27

~03 28 ATTACHMENT CODE 29 NPRDQ TYPE

+L 30 PRIME COMP.

Q 31 QO 32 NO.

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

~AQTR ~XQ16 ~ZQ20 ~ZQRT 0 0 0 0 ~Y Q23 ~NQ24 ~8Q25 W 2 9 0 Q26 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27

~io INVESTIGATION REVEALED THAT THE OVl~PEED TRIP WAS CAUSED BY A LINKAGE CAP SCREW BRFAKING IN HlE GOVlZKOR LINKAGE. AN EXAMINATIONOF THE GOVERNOR LINKAGE FAIL1%

TO HlMM OTHER SIGNS OF WEAR. THE OTHER DIESELS WERE ALSO INSPHCZED. THIS LINKAGE CAP SCREW WAS REPLACED ON EACH. 'IKE BKE1% CAP SCREW IS BEING EVALUATED FOR THE 4

K)DE OF FAILURE AND FURM& PEKVKRZATIVE ACTION IF REQUIRED. SEE SUPPL!~PZ 7 8 9 80 FACILITY METHOD OF STATUS  % POWER OTHER STATUS QSO DISCOVERY DISCOVERY DESCRIPTION Q32 5 ~GQ28 ~00 0 QER NA ~BQ3i SURVEIIIANIM TEST 7 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED" OF RELEASE AMOUNT OF ACTIVITY Q LOCATION OF RELEASE Q 7 8

~zQ 9 10 z Q34 11 NA 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION ~39

~00 0 Q3T ~Z Q36 7 8 9 11 12 13 80 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION Z NA Q4, 7 8 9 10 80 PUBLICITY NRC USE ONLY aN 5

7 8 9 10 68 69 80 g NAME OF PREPARER Jad R'~l'ng 616-465-5901 0

I ATZAQKEÃ2 TO LER 4 78-056/03L-0 SUPPU2KNT 1Q CAUSE DESCRIPTION

'IHE MAINTlRIANCE DEPMGKEPZ WILL BE INSPECTING THE GOVERNOR LINKAGE ON THE DIESIS QUARTERLY< FOR SIGNS OF WEAR

NRC FORM 386 U. S. NUCLEAR REGULATORY COMMISSION (747)

LlCENSEE EVENT REPORT .

CONTROL BLOCK:

,Q (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

~0 7, 8 9 M I D LICENSEE CODE C C 2Q20 14 15 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 0Q34 25 26 1 1 LICENSE TYPE 1 104~05 30 57 CAT 58 CON'T

~01 ~LQB 0 5 0 0 0 3 1 6 Q7 0 7 2 5 7 8 74 Qs 75 0 8 2 2 7 8 80 Qe 7 8 60 61 DOCKETNUMBER 68 69 EVENT DATE REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 DURING A SURVEILLANCE.TEST ON IHE ICE CONDENSER IVER INLET DOORS DOORS 1-R AND 14-L EXCEEDED THE INITIALOPENING  %)RQUE SPECIFIED BY T.S. 4. 6.5. 3. 1 .b. 1 .

PREVIOUS-" OCCURRENCJD INCLUDE: HO-050-,315/75-69, 76-01,24,30,38.

~OS

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~07

~08 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE COMPONENTCODE 0 ~Q CODE CODE SUBCODE SUBCODE SUBCODE

~OB 7- 8 9 10 0 11 12 13 E E E E E E 18 Q14 ~EQE 19

~EQ 20 REVISION SEQUENTIAL OCCURRENCE REPORT Qll LERiRO REPoRT ACTION FUTURE fVENT YEAR

~78, 21 22 EFFECT

~23 SHUTDOWN

~09 24 REPORT NO.

7 26

+~

27

~09 28 ATTACHMENT CODE 29 NPRDP TYPE

+~

30 PRIME COMP.

Q 31 NO.

0 32 COMPONENT TAKEN ACTION ON PLANT METHOD HOURS +22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER LJ018L8018 ~Z020 LIO ~ ~023 ~024 ~i025 9 9 9 9 Q25 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 o INVESTIGATION HEVFM.ED THAT THE DOOR SEALS WERE CAjLICHING ON ROUGH SPOTS ON 1HE

~TED WITH I

1 DOOR FRAMES. THESE ROUGH SPOTS WERE SN3CfKEX) AND THE DOORS WERE

%K INITIALOPENING FOHCE MEETING THE T.S. HEQUIHl&EN1'S. ALL OTHER DOORS WERE 3 CHJXX1K) POR SIMILAR RXJGH AREAS NONE WERE BXJND.

4 7 8 9 80 FACILITY STATUS

~00

% POWER 0'28

' OTHER STATUS ~

~30 METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32 CC] 1 5 8 9 0 028 10 12 13 EEE 44

~B031 45 46 SONVETLIANCE TEST 80 ACTIVITY CONTENT RELEASED OF RELEASE Z

AMOUNT OF ACTIVITY NA Q LOCATION OF RELEASE Q

~Z Q33 Q34 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE'ESCRIPTION Q39

~l7 ~00 0 032 9 Q38 NA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41

~lB ~00 0 Q40 NA 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 Z Q4.

7 8 9 10 80 O

ISSUED LmJQ44 PUBLICITY DESCRIPTION ~ NRC USE ONLY 44 o

8'0 8 10 68 69 o 0

NAME OF PREPARER PHONE:

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