ML18219B568

Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-029/03L-1 and RO 78-048/03L-0)

ML18219B568
Person / Time
Site:	Cook
Issue date:	08/02/1978
From:	Shaller D American Electrtic Power System, Indiana Michigan Power Co
To:	James Keppler NRC/RGN-III
References
LER 1978-029-03L, LER 1978-048-03L
Download: ML18219B568 (9)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM <RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-316 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 08/02/78 NRC IN 8( MI PWR DATE RCVD: 08/07/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT I',RO 50-316/78-048) ON 07/06/78 CONCERNING AFTER REACTOR TRIPS ON MARCf I 25'UNE 14> 19 i JULY bi 14'978> ROD POSITION INDICATION FOR CONTROL ROD H-8 DID NOT INDICATE THAT H-8 WAS FULLY INSERTED... W/ATT LER 78-029.

, PLANT NAME: COOK UNIT 2 REV I El JER INITIAL: X JM DISTRIBUTOR INITIAL:

DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS NOTES:

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

FOR ACTION: BR I . F ORBN1 BC<+W/4 ENCL INTERNAL: EG FII d~~~~W/ENCL NRC PDR<+W/ENCL I h E~~W/g ENCL MIPC++W/3 ENCL I 8. C SYSTEMS BR++W/ENCL EMFRGENCY PLAN BR>>W/ENCL NOVAK/CHECK++W/ENCL EEB++W/ENCL AD FOR ENG+%W/ENCL PLANT SY TEMS BR>+W/ENCL HANAUER4~~W/ENCL AD FOR PLANT SYSTEMS+<W/ENCL AD FOR SYS 5 PROJ~4W/ENCL REACTOR SAFETY BR>+W/ENCL ENGINEERING BR++W/ENCL VOLLMER/BUNCH++W/ENCL KREGER/J. COLLINS+>W/ENCL POWER SYS BR4~W/ENCL K SEYFR IT/IE4H~W/ENCL EXTERNAL: LPDR S ST. JOSEPHI M I +~W/ENCL TICz LIZ CARTER+<W/ENCL NSI C~~~W/ENCL ACRS CAT B%~W/16 ENCL DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 7822301 SIZE: i P+ 1 P+2P TIRE END

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eo p-( ~c er4oen yg(~ III/DIAIVA & II/IICHIGAIV POI/I/ER COMPA ItIY M7 DONALD C. COOK NUCLEAR PLANT Ca P.O. Box 458, Bridgman, Michigan 49106 E,"

August 2, 1978 ,ti I'7

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C, .Q Mr. J.G. Keppler, Regional Director C3 Office of Inspection and Enforcement Clk United States Nuclear Regulatory Commission III 'egion 799 Roosevelt Road Glen Ellyn, IL 60137 Operating'icense 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 78-029/03L-1'O 78-048/03L-0 Sincerelv,

~ D.V. Shaller Plant Manager

/sjk 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.

G. Olsen" J.M. Hennigan PNSRC J.F. Stietzel R.S. Keith d. )978 Dir., IE (30 copies) AQ Q Dir., MIPC (3 oopiys)

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NRC FORM 366 U. S. 5VCLEAR REGULATORY COMMISSION NITgut-~ "

4 Upda Report Previous Report Date 06- 2-/u LICENSEE EVENT REPORT CONTROL BLOCK: Q1 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 6 Q4~

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

~LQR 0 5 0 0 0 3 1 6 QTO 5 1 1 7 8 Qs

'74 0 8 0 2 7 8 Ql!

DOCKET NUMBER 68 69 EVENT DATE 75 REPORT DATE EVENT DESCRIPTION AND PROBABlE CONSEQUENCES QIO DURING HORIIAL OPERATION, ON MAY 11 AND 14, 1978 THE t1AIN TURBINE STOP VALVE "D" CLOSURE L IMIT SWITCH BECAME INOPERABLE . THI S SWITCH I

~o3 PROV DES A TRI P SIGNAL LISTED IN T. S. TABLE 3.3-1 ITEN 18.8. IN BOTH OCCASIONS THE APPLICABLE 6 ACTION REQUI REMENTS WERE FULFILLED., THEN THE LIMIT SWITCH WAS R P RETURNED TO OPERATION.

~DB 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE zz CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 8 9 A

10 Q11 11 8 Q12 ~AQ13 12 13 I N S T R U 18 64 MSQEE 19

~ZQ 20 SEQUENTIAL OCCURRENCE REPORT REVISION EVENT YEAR REPORT NO. CODE TYPE NO.

Q11 LER7RO REPoRT ~78 21 22 Q

23

~02 24 9

26 Q~

27

~03 28 29

+L 30 Q

31 Ql 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDQ PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD ~ HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~FQ13 ~FQ13 ~ZQEE ~ZQ31 0 0 0 0 Q33 ~YQ34 N Qss K 9 9 9 QEE 33 34 35 36 R37 40 4 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 3 THE...FAILU,EE)OF THE I'1AIN TURBINE STOP VALVE LIMIT SWITCHES IS DUE TO SEVERE VIBRATION OF)THE SWITCH HOUNTING BRACKETS AND OPERATING DISCS INDUCED BY VIBRATION OF (THE COMBINED STOP AND CONTROL VALVES. THE MOUNTING BRACKETS l

3 AND THE OPERAT I NG D I SCS HAVE BEEN RE DES I GNE0 AND THE MOD I F I CAT I ON IS PRESENTLY BEINGI, INSTALLED. DESIGN CHANGE NO. RFC-DC-02-2248.

7 8 9 80 FACILITY STATUS Q26 0 Ss POWER 6 9 029 ~ ~OTIIER STATUS NA ~,

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~3O METHOD OF DISCOVERY

~BQ31 OPERA TOR OBSERVATION DISCOVERY DESCRIPTION Q32 P

7 8 9 10 12 13 44 45 46 80 ACTIVITY COI)TENT 3

RELEASED OF RELCASE

~ZQ33 ~ZQ34L ',I

'MOUItTOF ACTIVITY~36

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'<<< HA LOCATION OF RELEASE Q 7 8 9 ~10 ) 11 44 M 45 80 PERSONNEL+XtgoURES j ", 1-MAUMBERK'~~ 'YPE ' 'DESCIIIPTION ~39 1

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NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION P477 l >>

LlCENSEE EVE NT REPORT CCQTROL BLOCK:

I I ,Q (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONl

~O 7 8 9 M I D LICENSEE CODE C C 14 QE

'15 o' o o o o o o 0 0 0 Q34>> 26 LICENSE TYPE I I 30 Q~QE57 CAT 58 CON'T

~O 7 8 REPDRT

~LQB 60 A 61 0 5 0 DOCKET NUMBER 1 6 68 0 69 o 7 o EVENTDATE 6 7 .8 74 QB 0 75 8 0 2 REPORT DATE 7 8 80 Q

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES ~10 AFTER REACTOR TRIPS ON MARCH 25, JUNW4,19, JULY6',7 14, 1978, ROD POSITION I

N D CAT I0N F 0 R C 0 N T RO L R 0 D H 8 D I D N 0 T I N D I C ATE TH AT H - 8 W AS F U L LY I N S E RT E 0 . TH E

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ACTION RE(UIREMENT OF T.S.3. 1 . 1 . 1 WAS FULFILLED BY EMERGENCY BORATING FOR 5 MINUTES. ~THE "MARCH.',AND.'JUNE':EVENTS;.WE(EL.DISCOVERED WHILEGATHERING OPERATING INFORtlATION CONCERNING OTHER EVENTS. OCCURRENCES OF A SIMILAR NATURE HAVE BEEN IDENTIFIED ON RO-050-0316/78-40.

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

[oO~] ~10 QI X QIR ~XQIG . I N S T R 0 Q4 ~IQIR ~Z QIR 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION Q17 LERJRP REPORT ACTION FUTURE EVENT YEAR

~78 21 22 EFFECT

+23 SHUTDOWN

~04 24 REPORT NO.

8 26 QM 27

~03 28 ATTACHMENT CODE 29 NPRDMI TYPE

+L 30 Q

31 PRIME COMP.

NO.

~0 32 COMPONENT TAKEN ACTION

~XQIR ~XQIR 33 34 ON PLANT

~ZQEO 35 METHOD

~ZQEI 36 37 0

HOURS +22 0 0 0 40 SUBMITTED

~YQEG 41 FORM SUB.

~NQ34 42 SUPPLIER

~NQER 43 44 W

MANUFACTURER I 2 0 47 QER CAUSE DESCRIPTION AND CORRECTIVE ACTIONS &27 THE ROUT cAUsE QF THEsE EYENTs Is ONKNowN AT THIs TIME. AT THE TIME 0F THE REAC'[OR TRI'PS, ROD POSITION INDICATION (RPI) INDICATES THAT ROD H-8 IS STUCK APPROXIMATELY 25-30 STEPS OUT, RPI SECONDARY COIL VOLTAGE MEASUREMENTS HAVE ALS 0 I N D I CAT E D T H AT H 8 IS N OT F U LLY I NS E RTE D . H 0 W E V E R, H -8 D0 ES I DR F T IN 3

SLOWLY AFTER 10-15 MINUTES. SEE ATTACHED SUPPLEMENT.

~Q 7 8 9 80 FACILITY METHOD OF STATUS 14 POWER OTHER STATUS QBO DISCOVERY DISCOVERY DESCRIPTION Q32 CCI1 5 LlQ D 28 0 0 0 29 NA ~A 45 Q31 46 OPERATOR OBSERVATION 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q35 LOCATION OF RELEASE Q

[gg ~zO 7 8 9 F03" 10 NA 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION ~39 7 ~00 0 Q37 2 4

Q33 NA 9 11 12 13 80 PERSONNEL INJUIlIES 8

7 8 9 11 12 80 LORE OF OR DAMAGE TO FACILITY Q43 7 8 9 10 80 PUBLICITY o

ISSUED LxlQ44 DESCRIP~TION Q NRC USE ONLY o

7 8 9 10 68 69 80 o 0

NAME OF PR)PARER PHONE: L

P g C ATTACHMENT TO LER 8 78-048/03L-0 SUPPLEMENT TO CAUSE DESCRIPTION THE PROBLEM APPEARS TO BE PERIODIC IN NATURE AND DOES NOT OCCUR AFTER EVERY REACTOR TRIP, BUT GENERALLY ONLY AFTER REACTOR TRIPS FROM HIGH POWER LEVELS.

INVESTIGATIVE TESTING INCLUDES ROD DROP TESTS AND A CONTROLLED REACTOR TRIP FROM 8/o POWER REACTOR TRIP TEST DATA INCLUDED TAKING VIS I CORDER TRACES OF H-8 RPI PRIMARY COIL VOLTAGE WITH BRUSH RECORDERS MONITORING THE SIGNAL CONDITIONING MODULE FOR H-8 RPI AND ANOTHER ROD USED AS A COMPARATOR. TEST DATA OBTAINED FROM THE REACTOR TRIP WAS A

INCONCLUSIVE SINCE CONTROL ROD H-8 DID NOT HANG-UP. THIS, IS AN INTERIM REPORT AND A REVISION,WILL BE SUPPLIED LATER WHEN A ROOT CAUSE HAS BEEN DETERMINED.