ML18219E160

Submit Licensee Event Report Nos. 1978-043-03L & 1978-044-03L

ML18219E160
Person / Time
Site:	Cook
Issue date:	08/11/1978
From:	Shaller D American Electrtic Power System, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To:	James Keppler NRC/RGN-III
References
LER 1978-043-03L, LER 1978-044-03L
Download: ML18219E160 (5)

Text

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REGULATORY INFORMATION DISTRIBUTION YSTEM <RIDS)

DISTRIBUTION FOR INCOMING I'"lATERIAL 50-315 KEPPLER J 6 SHZllu'r O.K DOCDATE: 08/11/78

'EC:

ORG:

NRC IN 8( MI PWR DATE RCVD: 08/22/78 DOCTYPE: LETTER, NOTAR I ZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT <RO 50,-,315/78-044) ON 07/14/78 CONCERNING UPON UNIT TRIPI THE TURBINE DRIVEN AUXILIARY FEED PUMP DID NOT START AS REQUIRED UPON RECEIPT OF THE AUTOMATIC START SIGNAL) DUE TO BURNED OUT SOLENOID TI.IROTTLE VALVE... W/ATT LER 7 PLANT NAME: COOK UNIT 1 REVIEWER INITIAL: X JM le DISTRIBUTOR INITIAL:PT4J e

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. DISTRIBUTION OF THIS MATERIA IS AS FOLLOWS

~~~~~~~~~~~~~~~~~~,'OR NOTES:

I 0 E 3 CYS Al L MATERIAL INCIDENT REPORTS (DISTRIBUTION CODE A002>

ACTION: BR CHIEF ORBN1 BC+4W/4 ENCL INTERNAL: ES~,.E:veN/ENCL NRC PDR~~N/ENCL I 5 E~i~~W/2 ENCL MIPC4+W/3 ENCL I 5 C SYSTEMS BR4I+N/ENCL EMFRGENCY PLAN BR~~N/ENCL NOVAK/CHECK4~W/ENCL EEB~~W/ENCL AD FOR ENG~~~N/ENCL PLANT SYSTEMS BRwwN/ENCL l.lANAUER~~~W/ENCL AD FOR PLANT SYSTEMS%~W/ENCL AD FOR SYS 5 PROJ+~kW/ENCL REACTOR SAFETY BR%>N/ENCL ENGINEERING BR++W/ENCL VOLLMER/BUNCH44W/ENCL KREGER/J. COLLINSc+W/ENCL POWER SYS BR4+N/ENCL K SEYFR IT/IE<.~W/ENCL EXTERNAL: LPDR 8 ST. JOSEPI-I, MI~~N/ENCL TI C LI2 CARTER~t 4~W/ENCL NSI C++N/ENCL ACRS CAT B4HFW/16 ENCL DISTRIBUTION: LTR, 45 ENCL 45 CONTROL NBR: 7/235 056 SI ZE: 1P+1P~ 1P

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INDIANA& II/IICHIGANPDt/t/ER CDNPANY Ue DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 C

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August ll, 1978 ~Cog

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CD Mr. J. G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Ope rati n g Li cense DP R-58 Docket No. 50-315

Dear Mr. Keppler:

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

RO 78-043/03L-0 RO 78-044/03L-0 Si nce rely, D. V. Shaller Plant Manager

/pmk 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.

G. Charnoff, Esq.

R. Walsh, Esq.

J. M. Menni gan G. Olson PUG ] 5 1978 PNSRC J. F. Stietzel R. S. Kei th T, P. Bielman/J. L. Rischling Dir., IE (30 copies) 782350056 Dir., MI'PC (3 copies) g~((

NRC FOQM 366 U. S. NUCLEAR REGULATORY COMMISSION I7-77)

LICENSEE EVENT REPORT

'ONTROL BLOCK: (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) ~

Q~I Q1 I 6 7

~37 M I 0 C C 1 02 0 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 25 O 26 4 1 1 1 LICENSE TYPE 1

30 57 CAT 58 7 8 9 LICENSEE CODE 14 15 CON'T

~o> " " 0 5 0 0 0 3 1 5 0 7 1 4 7 8 QB GLOR QT Qs 80 7 8 60 61 DOCKET NUM9CR 68 69 EVENT DATE 74 75 REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSE QUENCES ~10 UPON UNIT TRIP F THE ~INE DRIVEN ILIARY FEED I PUMP D D NOT STARP AS REIP4U IRED UPON RECEIPT OF THE MTRRTIC START SIGNAL. THE H3MP I'RS DECLARE) IbRPERABLE PURSUANT %) THE ACTION IMPOSED BY T.S. 3.7.1.2 7 AND UPON REPAIR WAS REIURNIK) TO 6

SERVICE WITHIN APPROX IMATELY F1VE HOURS FRC)M THE START OF THE EVE5T . S IM IIAR

~OB OF THIS TYPE WERE REPORTED UNDER'O-050-'.315/276-35'ND 47.

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

~CH 9 10 Q11 E 11 0>> LJ 12 013 13 M E C F U N 04 18

~ZO13 19

~Z 20 013 SEQUENTIAL OCCURRENCE REPORT REVISION Q17 LF RiRP REPoRT ACTION FUTURE EVENT YEAR

~78 21 22 EFFECT

+

23 SHUTDOWN

~()

24 REPORT NO.

26 4 4 Q~

27

~Q3 ATTACHMENT 28 CODE 29 NPRDR TYPE

+L 30 Q

31 PRIME COMP.

Qo NO.

COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER Q13 pJQER pJQER ~EQ21 0 0 0 0 N Q23 ~YORE +A QEs 0 Q26 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 p THE SOLENOID WHICH OPERATES THE TRIP THROPIXE VALVE MS FOUND BURNED OVP RENDERING THE MECHANISM INOPERABLE. IT APPEARED THAT A SHORT EXISTED B SOLENOID LUGS AND THE CASE ITSELF WHICH CAUSED THE PROBLEM, ALTHOUGH THE ENQUIRE MECHANISM 3

(GEgCR9 5 03B/AG-5 1 ) WAS REPLACED IO ASSURE THAT ANY ADD ITIONAL Uhl)PZlKTH3 PROBLB )S WERE CORRIKTE33.

8 9 80 FACILITY METHOD OF STATUS 58POWER OTHER STATUS QBO DI5 COY E R Y DISCOVERY DESCRIPTION Q32 3 ~X Q23 ~00 0 Q23 UNIT TRIP 44 Q31 OPERATIONAL EVENT 7 8 9 10 12 13 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE z

AMOUNT OF ACTIVITY NA LOCATION OF RELEASE Q Q33 ~ZQ34 7 8 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7 ~00 0 Q37 Z Q33

'3 NR 7 8 9 11 12 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 3 ~OO 0 Q43 NA 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 g ~zQ42 NA.

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7 8 9 10 80 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION Q46 K&38 L~JS 7 9 10 NA 68 69 80 o Cs 0

NAME OF PREPARER 7 0

NRC FOQM 366 U. S. NUCLEAR REGULATORY COMMISSION LlCENSEE EVENT REPORT

" 'ONTROL BLOCK: (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

Q1

~91 I 8 9 M I D C LICENSEE CODE C

I 3

14 Qs 15 0 0 0 6

0 0 0 LICENSE NUMBER 0 0 0 0 0 25 02 26 4 1 3 LICENSE TYPE 1..1 30 04~ 57 CAT 58 Qs CON'T

[oat],"", ~L08 0 5 0 0 0 3 1 5Q2 68 69 0 7 1 EVENT DATE 2 7 8Q8 74 75 REPORT DATE 80 QB DOCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 DURING THE PERFORMANCE OF A SURVEILLANCE TEST PURSUANT TO T,S94 6 l 3 bg THE 650 ELEVATION AIR LOCK LEAKAGE WAS POUND TO BE IN EXCESS OF THE SPECIFIED LIMIT.

~p4 UPON LOCATION AND CORRECTION OF THE CAUSE, A RETEST WAS IMMEDIATELYPERFORMED WITH

~p6 SATISFACTORY RESULTS ~ A SIMILAR OCCURRENCE OF THIS TYPE WAS REPORTED UNDER

~OB RO-'0'50-."315/78.-23.

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

[OO~] ~SD Qll ~A Qls ~X Qls P E N E T R Q14 ~A Qls ~Z Qls 7 8 9 10 11 12 SEQUENTIAL 13 18 OCCURRENCE 19 REPORT 'EVISION 20 LER)RO Qll Rssosl ACTION FUTURE EVENT YEAR

~75 21 22 EFFECT

+

23 SHUTDOWN

~04 24 REPORT NO.

3 26 gP 27

~03 28 ATTACHMENT CODE 29 NPRDA TYPE

~L 30 PRIME COMP.

g 31 NO.

go 32 COMPONENT TAKEN ACTION 33 Qls ~E019 34 ON PLANT

~5020 35 METHOD

~5021 36 37 0

HOURS &22 0 0 0 40 SUBMITTED 41 N Q23 FORM SUB.

~N024 42 SUPPLIER

~L028 43 44 MANUFACTURER W 3 0 2 47 Q28 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 p THE CAUSE OF THE EXCESSIVE LEAKAGE 02tBIS DETERMINED TO BE ST17AMS OF MATlWIALFKM CU!'ANING RAGS WHICH HAD FALLEN ACROSS THE SEAL AREA. THE SIGNS 'PROPOSE.'".AS CORRECTIVE ACZION UNDER:KI-050-315/78-.33:,FIVE'NO'rU BEEN ISDE,AND POSTE33 AT THE'",AIRS

~3 gO'EMIND:,'PERSONNE8L TO INSPECT'HE" ILS E. BEECH'ILL HOPEFULLY PRECLUDE 'ANY FUTURE 4

8 9 80

~

7 FACILITY 3p METHOD OF STATUS 'A POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Q32 8 ~E Q28 ~09 7 Q29 NA 44

~B081 SDRVEZLLANCE TEST 7 8 9 10 12 13 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITY Q ~ LOCATION OF RELEASE Q 7

6 8

~Z 9

Q33

'0 ~ZQ34 PERSONNEL EXPOSURES 11 NA 44 45 80 NUMBER TYPE . DESCRIPTION Q39

~17 ~0000 0Q2 1 5 Q8 8 NA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 9 ~oo o Q4o NK 80 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION Z Q42 NA, 8 9 10 80 PUBLICITY ISSUED

~Q44 DESCRIPTION Q NA NRC USE ONLY 99 o

8 9 10 68 69 80 o 0

NAME OF PREPARER T' e3-111811 PHONE: