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 NRC ORG: SHALLER D V IN 8(MI PWR DOCDATE: 08/02/78 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: INTERNAL: EXTERNAL: BR I.F ORBN1 BC<+W/4 ENCL EG FII d~~~~W/ENCL I h E~~W/g ENCL I 8.C SYSTEMS BR++W/ENCL NOVAK/CHECK++W/ENCL AD FOR ENG+%W/ENCL HANAUER4~~W/ENCL AD FOR SYS 5 PROJ~4W/ENCL ENGINEERING BR++W/ENCL KREGER/J.COLLINS+>W/ENCL K SEYFR IT/IE4H~W/ENCL LPDR S ST.JOSEPHI M I+~W/ENCL TICz LIZ CARTER+<W/ENCL NSI C~~~W/ENCL ACRS CAT B%~W/16 ENCL NRC PDR<+W/ENCL MIPC++W/3 ENCL EMFRGENCY PLAN BR>>W/ENCL EEB++W/ENCL PLANT SY TEMS BR>+W/ENCL AD FOR PLANT SYSTEMS+<W/ENCL REACTOR SAFETY BR>+W/ENCL VOLLMER/BUNCH++W/ENCL POWER SYS BR4~W/ENCL DISTRIBUTION:

LTR 45 ENCL 45 SIZE: i P+1 P+2P TIRE END CONTROL NBR: 7822301 V fl If I kl, h P II~1, I I I er4oen eo p-(~c yg(~III/DIA IVA&II/IICHIGA IV POI/I/ER COMPA ItI Y DONALD C.COOK NUCLEAR PLANT P.O.Box 458, Bridgman, Michigan 49106 August 2, 1978 Mr.J.G.Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission

'egion III 799 Roosevelt Road Glen Ellyn, IL 60137 ,ti Clk M7 Ca~I E," I'7~)<M C,.Q C3 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 Dir., IE (30 copies)Dir., MIPC (3 oopiys)AQ Q d.)978

'I e I NRC FORM 366 NITgut-~" 4~o3 VALVE"D" CLOSURE L IMIT SWITCH BECAME INOPERABLE

.THI S SWITCH PROV I 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.

U.S.5VCLEAR REGULATORY COMMISSION Upda Report Previous Report Date 06-2-/u LICENSEE EVENT REPORT CONTROL BLOCK: Q1 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 4 6~sl H I 0 C C 2 QE 0 0 0 0 0 0 0 0 0 0 0 Qs 4 1 1 1 1 Q4~Qs 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T~LQR 0 5 0 0 0 3 1 6 QTO 5 1 1 7 8 Qs 0 8 0 2 7 8 Ql!DOCKET NUMBER 68 69 EVENT DATE'74 75 REPORT DATE EVENT DESCRIPTION AND PROBABlE CONSEQUENCES QIO DURING HORIIAL OPERATION, ON MAY 11 AND 14, 1978 THE t1AIN TURBINE STOP~DB 7 8 9 80 zz 7 8 VIBRATION OF)THE SWITCH HOUNTING BRACKETS AND OPERATING DISCS INDUCED BY SYSTEM CAUSE CAUSE COMP.VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE A Q11 8 Q12~AQ13 I N S T R U 64 MSQEE~ZQ 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER7RO EVENT YEAR REPORT NO.CODE TYPE NO.Q11 REPoRT~78 Q~02 9 Q~~03+L Q Ql 21 22 23 24 26 27 28 29 30 31 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 COMBINED STOP AND CONTROL VALVES.THE MOUNTING BRACKETS BEINGI, INSTALLED.

DESIGN CHANGE NO.RFC-DC-02-2248.

7 8 9 FACILITY~3O METHOD OF STATUS Ss POWER~OTIIER STATUS~DISCOVERY Q26 0 6 9 029~NA~,~.-~BQ31 OPERA 7 8 9 10 12" 13 44 45 46 ACTIVITY COI)TENT RELEASED OF RELCASE I'MOUItT OF ACTIVITY~36 3~ZQ33~ZQ34L',"'NA.'<<<HA 7 8 9~10)11 44M 45 PERSONNEL+XtgoURES j 1-", MAUMBERK'~~

'YPEDESCIIIPTION

~39 1 1~00..;0'Q31 L/ZQTs'4 j HA 7r.'3'7=.,'112 4(-13'."'OSSQO~OR OAMAGETOFACILITY Q43 si~1~3~lQ43',, ((', NA P DISCOVERY DESCRIPTION Q32 TOR OBSERVATION LOCATION OF RELEASE Q 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 I S PRESENTLY 80 80 80 80 80 PHONE: 68 69 80 NRC USE ONLY 44 a 80 o 0 oc/I I f 33 vtOI7ifU'[

!'0 tel)I I'<)jets.]s:~~, t.r 33jJ'5(i~,lI,)!I 1 If ,e I, 0 f.f, J f I J a)f U.S.NUCLEAR REGULATORY COMMISSION NT REPORT (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONl NRC FORM 366 P477 l>>LlCENSEE EVE ,Q QE o'o o o o o o 0 0 0 Q34>>I I Q~QE 14'15 26 LICENSE TYPE 30 57 CAT 58 CCQTROL BLOCK: I I~O 7 8 CON'T~O M I D C C 9 LICENSEE CODE 7 8 REPDRT~LQB 0 5 0 1 6 0 o 7 o 6 7.8 QB 0 8 0 2 7 8 Q 60 A 61 DOCKET NUMBER 68 69 EVENTDATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES

~10 AFTER REACTOR TRIPS ON MARCH 25, JUNW4,19, JULY6',7 14, 1978, ROD POSITION~o3'N D I CAT I 0 N 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 AT E TH AT H-8 W A S F U L L Y I N S E RT E 0.T H E 4 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[oO~]7 8 SYSTEM CAUSE CAUSE COMP.VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~10 QI X QIR~XQIG.I N S T R 0 Q4~IQIR~Z QIR 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LERJRP EVENT YEAR REPORT NO.CODE TYPE NO.Q17 REPORT~78+~04 8 QM~03+L Q~0 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDMI PRIME COMP.COMPONENT TAKEN ACTION ON PLANT METHOD HOURS+22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER

~XQIR~XQIR~ZQEO~ZQEI 0 0 0 0~YQEG~NQ34~NQER W I 2 0 QER 33 34 35 36 37 40 41 42 43 44 47 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 3 A L S 0 I N D I CAT E D T H AT H-8 I S N OT F U L L Y I N S E R T E D.H 0 W E V E R, H-8 D 0 E S D R I F T I N SLOWLY AFTER 10-15 MINUTES.SEE ATTACHED SUPPLEMENT.

7 8 9 FACILITY STATUS 14 POWER OTHER STATUS QBO 1 5 D 28 0 0 0 29 NA 9 11 12 4 13 PERSONNEL INJUIlIES 8 CCI LlQ~Q ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIV ITY Q35[gg~zO F03" NA 7 8 9 10 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

~39 7~00 0 Q37 2 Q33 NA METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32~A Q31 OPERATOR OBSERVATION 45 46 LOCATION OF RELEASE Q 45 80 80 80 80 7 8 7 8 o 7'8 9 11 12 LORE OF OR DAMAGE TO FACILITY Q43 9 10 PUBLICITY ISSUED DESCRIP~TION Q LxlQ44 9 10 NAME OF PR)PARER PHONE: 68 69 80 80 NRC USE ONLY o 80 o 0 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.