ML18219B542

D.C. Cook - Submit Licensee Event Reports: RO 78-004/03L-1, RO 78-007/03L-0, RO 78-008/03L-0, RO 78-009/03L-0, for Unit 2

ML18219B542
Person / Time
Site:	Cook
Issue date:	04/11/1978
From:	Shaller D American Electrtic Power System, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To:	James Keppler NRC/RGN-III
References
LER 1978-004-03L-1, LER 1978-007-03L-0, LER 1978-008-03L-0, LER 1978-009-03L-0
Download: ML18219B542 (14)

Text

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REGULATORY INFORIIATIQII DISTRIBUTION SYSTEI'I (RIDS)

DISTRIBUTION FOR INCONING I IATERIAL 50-3i6 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 04/ii/78 NRC IN 5 NI PWR DATE RCVD: 04/i7/78 DGCTYPE: LETTER IWQTAR IZED: NO COPIES RECEIVED SUBJFCT: LTR i ENCL i FORWARDING LICENSEE EVENT RFPT <RO 50-3ib/78-004) ON 02/27/78 CONCERNING ROUTINE COOLANT SYSTEI"I LEAK RATE TEST CONDUCTED REVEALED LEAK RATE OF 5. 29 GPIR UNIDENTIFIED LEAKAGE IN VIOLATION OF APPENDIX A TECH SPEC

3. 4. 6. 2B... W/ATT LERS78-007'8-008 AND 78-06$ /b3I -0 PLANT MAIRE: COOK UI4IT 2 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL: ~

DISTRIBUTION OF THIS HATERIAL IS AS FOLLOWS NOTES:

SEND 3 COPIES OF ALL NATERIAL TO IhE iblCIDENT REPORTS (DISTRIBUTION CODE A002)

FGR ACTION: EL~~W/4 ENCL INTERNAL: RE .E+4 NRC PDR++W/ENCL I 5 E4s+ gCL NIPC~~~W/3 ENCL SCHROEDER/I PPO NCL HOUSTON~~W/ENCL IWOVAIC/CHECI<<~~~lj/ENCL EEB~I~W/ENCL KNIGHT++W/ENCL BUTLER4~+W/ENCL HANAUER~>+W/EIACL TEDESCO+%W/ENCL E I SEIAHUT+~~W/ENCL BAER4~+W/ENCL SHAO~~W/ENCL VOLLNER/BUNCH4+W/ENCL KREGER/J. COLLINS~>W/ENCL ROSA++W/ENCL I SEYFR IT/I E<H~W/ENCL EXTERNAL: LPDR S ST. JOSEPH, I"II )l +W/ENCL TI C+~W/EIWCL NS I C++W/ENCL ACRS CAT B~~~W/i6 FNCL COPIES NOT SUB!IITTED PER REGULATORY GUIDE 10.1 DISTRIBUTION: LTR 45 ENCI 45 CONTROL NBR: 78i0 0l SIZE: iP+iP+4P

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INDIANA8r MICHIGANPON'ER COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 April 11, 1978 Hr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-74 Docket No. 50-316

Dear Hr. Keppler:

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

RO 78-004/03L-1 RO 78-007/03L-0 RO 78-008/03L-0 RO 78-009/03L-O.

Sincerely, D.V. Shaller Plant Manager

/bab cc: J.E. Dolan RE W. Jurgensen R.F. Kroeger R. Kilburn R.J. Vollen BPI R.C. Callen HPSC K.R. Baker RO: III P.W. Steketee, Esq.

R. Walsh, Esq.

G. Charnoff, Esq.

G. Olson J.H. Hennigan PNSRC APR 3.3 tST8 J.F. Stietzel Dir., IE (30 copies)

Dir., MIPC (3 copies)

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NRC FORM 366 -

(7-77) "UPDATE REPORT PREVIOUS REPORT DATE EVENT REPORT 3/PlJI75'tCENSEE CONTROL BLOCK: I QI tPLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6

~o 7 8 9 M I D LICENSEE CODE C C 2Qs 14 15 0 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0Qs4 I I 25 26 LICENSE TYPE I I 30 Q" ~Qs 57 CAT 58 CON'T

~01 soURGE MLQ6 0 5 0 0 0 3 1 6 68 Q7 69 EVENT DATE 74 QB032178QB 75 REPORT DATE 80 7 8 60 61 DOCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 UNIT 2 WAS AT 'NORMAL TEMPERATURE AND PRESSURE IN MODE 3. A ROUTINE REACTOR COOLANT s SYSTEM LEAK RATE TEST CONDUCTED BETWEEN 0300 AND 0600 HOURS REVEALED A LEAK RATE

~o

~o v OF 5.29 GPM UNIDENTIFIED LEAKAGE IN VIOLATION OF APPENDIX A TECH. SPEC. 3.4.6.2b.

~o s AFTER LEAK WAS FOUND THE SUBSEQUENT LEAK RATE TEST REVEALED A REACTOR COOLANT SYSTEM

~os LEAK RATE OF 0.016 GPM.

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~08 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 8 LcllaJQ 9 10 MQ 11 L~JQ 12 13 18 Q14 ~F 19 Q15 ~D 20 Q16 REVISION SEQUENTIAL OCCURRENCE REPORT EVENT YEAR REPORT NO. CODE TYPE NO.

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32 ATTACHMENT NPRDP PRIME COMP. COMPONENT ACTION FUTURE TAKEN ACTION EFFECT ON PLANT SHUTDOWN METHOD HOURS 'Q SUBMITTED FORM SUB. SUPPI.IER MANUFACTURER

~AQls Lf]Qls ~ZQoo ~ZQol O O O Z ~NQos ~NQo4 ~NQos V O 5 5 Qos 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o THE EXCESSIVE UNIDENTFIED LEAKAGE WAS CAUSED BY LEAKAGE PAST THE PACKING To ATMOS-PHERE AND TO THE STEAM LEAKOFF SYSTEM. THE VALVE WAS REPACKED AND THE STEAM SYSTEM WAS CAPPED OFF. NO FURTHER ACTIONS ARE PLANNED AT THIS TIME.

3 7 8 9 80 FACILITY METHOD OF QBO DISCOVERY . DISCOVERY DESCRIPTION +32 STATUS 56 POWER OTHER STATUS 5 B Qos ~00

'IO 0

12 Qoo NA 44

~BQ31 45 46 DURING LEAK RATE SURVEILLANCE TEST 80 7 8 9 13 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q NA LOCATION OF RELEASE Q Z Q33 ~ZQ34 NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION 7 8

~00 9

DQ 11 12 2 Qss 13 NA 80 PERSONNEI. INJURIES NUMBER DESCRIPTIONQ41 LOOOOJQso NA 7 8 9 11 12 80 LOSS OF OR DAMAGE.TO FACILITY ~43 TYPE DESCRIPTION

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ISSUED PUBLICITY LJZQ44 DESCRIPTION ~ NRC USE ONLY cv a

7 8 9 10 68 69 80 o 0

NAME OF PREPARER R S KEITH (616) 465-5901

5'f, Q' NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION I7.V77)

LICENSEE EVENT REPORT CONTROL BLOCK: QI {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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~os N I D C C 2 Q20 0 0 0 0 0 0 0 0 0 Op 4 1O~Qs 1 1 1 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T

~ei L Qs 0 5 0 0 0 3 1 6 Qr 0 3 1 5 7 5 Qs. 0 4 I I 7 5 Qe DOCKET NUMBER 68 69 EVENT DATE, 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES ~10 DURING 0 POWER PHYSICS TESTING, WHICE SHUTDOI'I BANK "C" WAS BEING I'IITHDRAI'IN FROM 214 STEPS TO 225 STEPS, ROD POSITION INDICATION FOR ROD L-13 WAS READING 205 STEPS, WITH VIS ICORDER INDICATION SHOWING THE ROD HAD ACTUALLY DROPPED 37 STEPS. THIS INCIDENT EXCEEDED THE + 12 STEP LIMIT OF T. S. 3.1.3.2. PREVIOUS REPORTABLE

~06 OCCURRENCES OF A S IMILAR NATURE INCLUDE RO 050/31 5 78 07 04 77 34 33 28 27 76-54,44, 1 3 ~

~08 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE ~

CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 8 GRUB'S 9

~i~ 10 p ~X@ UZpe 12 SEQUENTIAL 13 I N S T R U 18 OCCURRENCE Q4 UKQs 19 UZQs 20 REVISION

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REPORT EVENT YEAR U Ll U LERiRO REPORT NO. CODE TYPE NO.

Qlr REPoRT L77(

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27 LLJ 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDQ PRIME COMP. COMPONENT 7738KEN ACT@)N ONJELANT METHOD HOURS Ozz SUBMITTED FORM SUB. SUPPLIER MANUFACTURER U

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Ulpee UQEE " Q33 UQE UNQEE Qrs 33, 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 8 INVESTIGATION REVEALED THAT THERE IIAS NO APPARENT REASON FOR THIS CONDITION, INNEDIATE ACTION INCLUDED DISCONNECTING OTHER RODS IN BANK "C" AND WITHDRAWING ROD L-13. ROD 2 CONTROL WAS THEN RECONNECTED TO INCLUDE L-13 IN BANK "C", WITH THE,. ENTIRE BANK CYCLED 3 BETWEEN 21 4 STEPS AND 228 STEPS WITH NO PROBLEMS. FURTHER INVESTIGATING INCLUDED 4 REPULLING ROD L-13 WITH EACH ROD IN IT'S BANK, ( SEE ATTACHED SUPPLEMENT) 7 .8 9 80 FACILITY ~30 METHOD OF STATUS 5(P POWER OTHERSTATUS QP DISCOVERY DISCOVERY DESCRIPTION Q32 8 9 B Q>> ~00 10 0

12 Qee NA 44

'JL(psr 45 80 7 13 46

.ACTIVITY CONTENT 6

RELEASED OF RELEASE AMOUNT OF ACTIVITYQ36 LOCATION OF RELEASE Q

~Z Q33 ~ZQ34 NA l 7 8 9 10 44 45 80 PERSONNEL EXPOSURES e NUMBER TYPE DESCRIPTION ~39

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~00 9

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PERSONNEL INJURIES 12 2 Q38 13 NA 80 NUMBER DESCRIPTIONQ41 8 ~00 0 Q48 NA 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 e Uz, Q43 NA 7 8 9 10 80 PUBLICITY NRC USE ONLY O

7 8 9 10 68 69 80 48 NAME OF PREPARER lack Ri,schljng 616-.465-5901 0

A SUPPLEMENT TO LER 5'8-007/03L-0 CAUSE DESCRIPTION VERIFYING BY VISICORDER TRACES THAT NO STEPS MERE MISSED. VOLTAGE READING OF THE L-13 COIL STACK SHOWED NORMAL RESISTANCE FOR L-13

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NRC FORM 366 (7.77) g'g CONTROL BLOCK:

I i L[CENSEE EVENT REPORT 6

Qi U. S. NUCLEAR REGULATORY COMMISSION (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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7 8 9 N I D LICENSEE CODE C C 2 14 Qg 15 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 OQs 25 26 41 1 LICENSE TYPE 1 1Q4~Qg 30 57 CAT 58 CON'T

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~LQg p 5 p p p 3 1 6 Qg 0 3 1 9 7 8 Qs 0 4 I I 7 8 Qs 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES +10 DURING PHYSICS TESTING CONTROL ROD F-T4 ROD POSITION INDICATION WAS 18 STEPS FROM DEI<AND POSITION. THIS EXCEEDED THE + 12 STEP LII1IT OF T. S. 3.1.3.2. PREVIOUS

~p g OCCURRENCE NUMBERS INCLUDE: RO-050/315-78-07,04,77-34,33,28,27,76-54,44,13

~p g 050/316-78 -007/03L-0

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

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~Ebs 12 13 I N S T R U 18 Qlg ~YOlg 19

~ZOls 20 SEQUENTIAL OCCURRENCE REPORT REVISION 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD.4 PRIME COMP. COMPONENT TA(EN

~QiBLIQIB 33 ACTI)N 34 ON 35 P/ANT

~Q>>. '6 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 METHOD LJQ21 37 0

HOURS Q22 0 0 0 40 SUBMITTED 41 N Q'JQ24 FORM SUB.

42 SUPPLIER L~JQ26 43 44 MANUFACTURER W ' 0 47 Q

INVESTIGATION'REVEA'L'CDTHAT THE COIL STACK VOLTAGE OF R-14 WAS IDENTICAL TO OTHER RODS IN THIS BANK. THE SIGNAL CONDITIONING NODULE WAS ADJUSTED FOR PROPER RPI ALIGNMENT. THE ACTION REQUIREMENTS OF T. S. WERE FULFILLED.

3 4

7 8 9 80

~lg FACILITY STATUS B

LJOgs ~Ogg 56 0

POWER 0 4 OTHERSTATUS ~

~SO METHOD OF DISCOVERY

~Q31 OPERATOR 0 h SE NNNh 7 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED OF RQ.EASE AMOUNMIFACTIVITYQ36 LOCATION OF RELEASE Q36 OZ 7 8 L'J Q>>

9 L'JQ3 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION l ~00 OO Z Oos NA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41

~ls ~OO 7 8 9 0 Qo 11 12 NA 80 LOSS OF OR DAMAGE TO FACILITY ~43 TYPE DESCRIPTION WQ42 8 9 10 80

~oo ISSUED

~ZQ44 PUBLICITY DESCRIPTION ~  : NRC USE ONLY o

7 8 9 10 68 69 80 o NAME OF PREPARER Jack R j schl ing 616-465-5901 0 IL 0

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[os] MI.IDCC 7 8 9 LICENSEE CODE 2

14 Q20 15 0 0 0 0 0'0 0 0 0 OQ3 25 26 6 11 LICENSE TYPE I IQ~Q5 30 57 CAT 58 CON'T

~o ~LQB 0 5 0 0 0 3 " 6 Qj0 3 1' 7 8 QB 0 4 I I 7 8 Q 7 8 DOCKET NUMBER 68 69 EVENT PA'f f 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES QIO WHILE REVIEWING SURVEILLANCE TEST DATA ON MARCH 13 1 DURING THE PERFORMANCE OF SURVEILLANCE TEST PROCEDURES ON "POWER RANGE-NUCLEAR INSTRUMENTATION SYSTEM", CHANGES WERE 11ADE TO THESE PROCEDURES Al'ID PERFORMED I'IITHOUT PROPER APPROVED DOCUI1ENTATION. THE CHANGES AFFECTED THE OVERPOWER TRIP AND RESET POINTS. THIS IS CONTRARY To T. S. 6.8.3.C.

~OB 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE.

CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE A Q>> A Q12 ~CQ13 Z Z Z Z Z Z Q14 ~ZQ15 ~Z Qis 7 8 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION Q12 LF R(RP 95PORP ACTION FUTURE EVENT YEAR

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~00 24 REPORT NO.

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27 ATTACHMENT

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28 CODE 29 NPRDP TYPE QL 30 PRIME COMP.

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~QisLJQis 33 34 gJQ29 35

~ZQ 36 37 o o o o 40

~NQ23 41

~NQ24 42

~ZQ25 43 44 z 8 8 8 47 Q

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 2 7 INVESTIGATION REVEALED THAT THE TRTP AND RESET VALUES HERE CHANGED IN THE PROCEDURES.

THE PERS NNEL RUNNING THE TEST SHOULD NOT HAVE USED THESE VALlJES WITHOUT A TEMPORARY CHANGE SHEET. TO PREVENT RECURRENCE, THE INSTRUMENT MAINTENANCE GROUP HAS RECEIVED TRAINING COVERING THE USE OF TEMPORARY CHANGE SHEETS.

4 7,8 9 80 5

FACILITY STATUS G, Q25 ~00 36 POWER 0 Q29 OTHER STATUS NA

~'~GQ31 3P

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METHOD OF DISCOVERY SURVEILLANCE DATA REVIEW DISCOVERY DESCRIPTION Q32 7 8 9 10 12 13 44 45 46 4 80 ACTIVITY CONTENT

~16 RELEASED OF REI.EASE AMOUNTOF ACTIVITY LOCATION OF RELEASE Q

~Z Q33 ~ZQ34 NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 2 ~00 0 Q 2 Qss NA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 s ~OO 0 Q4o NA 7 8 9 11 12 80 9

LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q Z Q4. NA 7 8 9 10 80 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION Ps o

o ~Q44 NA 8 9 10 68 69 80 o Jack Ri,schl ~no 616-465-5901 0 L

NAME OF PREPARER 4P

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