ML18219C208

LER 1978-020-03L Re Train of Heat Tracing Was Removed During Normal Operation of Mode 1

ML18219C208
Person / Time
Site:	Cook
Issue date:	03/21/1978
From:	Shaller D Indiana Michigan Power Co
To:	James Keppler NRC/RGN-III
References
LER 1978-020-03L
Download: ML18219C208 (8)

Text

ji REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-315 REC: KEPPLER J G QRG: SHALLER D V DQCDATE: 03/21/78 NRC IN 8c l'lI PWR DATE RCVD: 03/24/76 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 t L ICENSEE EVENT REPT (RO 50-315/78-020/03L-0) ON 02J24/78 CONCERNING DURING NORMAL OPFRATION OF I"IODE 1, A TRAIN OF HEAT TRACING WAS REMOVED FORM SVC> AND READING FOR HEAT TRACE TRAIN B WAS NOT TAKEN WITHIN REQUIRED TECH SPEC LII"I ITS.

PLANT NAl"IE: COOK UNIT 1 DISTRIBUTION OF THIS MATER1AL IS AS FOLLOWS REVIEWER DISTRIBUTOR INITIAL:~

INITIAL: X JM INCIDENT REPORTS (DISTRIBUTIQN CODE A002)

FOR ACTION: BR C WENCER++W/4 ENCL INTERNAL: REG FILE~~+W/ENCL NRC PDR~~4W/ENCL MIPC~H~W/3 ENCL I

SCHROEDER J IPPOL TO+4~W /ENCL HQUSTOhl4l 4 W/ENCL NQVAK/CHECK~H~W/ENCL 6RIMES~H~W/ENCL KNIGHT~~~W/ENCL BUTLER+~~W/ENCL HANAUER~~W/ENCL TEDESCO4~+W/ENCL I

E SENHUT~~~W/ENCL BAER~+W/ENCL SHAQ++W/ENCL VOLLMER/BUNCH+4FW/ENCL KREGER/J. COLL INS~H~W/ENCL ROSA++W/ENCL K SEYFRIT/IE~~4~W/ENCL EXTERNAL: LPDRiS ST. JOSEPH, MI~~4l W/ENCL Tl C~F<~W/ENCL NS I C++W/ENCL ACRS CAT B~~~~W/16 ENCL h

COPIES NOT SUBMITTED PER

. REGULATORY GUIDE 10.1 1'ISTRIBUTION:

LTR 45 ENCl 45 CONTROL NBR: 78083 13 SIZE: 1P+1P sssHsssssssss<a%+sse++w++ssww+++w+w++<HI wesw<Ht THE END

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g3Lmorhen Y i INDIANAEr NICHIGANPDNER CONPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 March 21, 1978 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 Operating Li cense DPR-58 Docket No. 50-315

Dear Mr. Keppler:

Pursuant to the requirements of Appendix A Technical Specifications the following report is submitted:

RO 78-020/03L-O.

Sincerely, D.V. Shaller Plant Manager

/bab cc: J.E. Dolan R.W. Jurgensen G.E. Lien 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. Olson J.M. Hennigan PNSRC MAR 23 1978 J.F. Stietzel Dir., IE (30 copies)

Dir., MIPC.(3 copies)

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION I

g7.77I LICENSEE EVENT REPORT

'CONTROL BLOCK: Q1 (PLEASE PRINT OR TYPE ALI. REQUIRED INFORMATION) 1 6 7

~O 8 9 M I D C LICENSEE CODE C 1 14 Q2 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 0 25 Qo 26 4 I I I LICENSE TYPE IQ4~Qs 30 57 CAT 58 CON'T

~01 7 8 REPORT

~LQ 60 61 DOCKET NUMBER 68 7

69 EVENT DATE 74 QB 75 REPORT DATE 80 QB EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 UNIT WAS OPERATING NORMALLY IN MODE 1 ~ THE A TRAIN 0 HEAT T CI A ED FR

~03 SERVICE AT 1000 HOURS ON 2/24/78. READI'NG FOR HEAT TRACE TRAIN B WAS NOT TAKEN WITHIN

~04 8 HOURS IN VIOLATION OF APPENDI'X A TECH. SPEC. 3.5.4.2. WHEN READINGS WERE TA HEAT TRACE TRAIN B WAS MAINTAINING TEMPERATURE WITHIN RE UIRED BAND. THIS IS THE

~O6 FIRST EVENT OF THIS TYPE FOR THE HEAT TRACE SYSTEM ~

~O7

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

CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCOOE 7 8 9 10 Q>>

11 A Q>> ~AQ>>

12 13 Z Z Z Z Z Z 18 Q>< ~ZQ>>

19

~Zoo 20 SEQUENTIAL OCCURRENCE REPORT REVISION LfR/RP nssoov ACTION FUTURE EVENT YEAR

~jg 2I 22 EFFECT

~

23 SHUTDOWN

~OZ 24 REPORT NO.

0 26 27 28 ATTACHMENT CODE o

29 NPRD 4 TYPE 30 31 PRIME COMP.

LoJ COMPONENT TAKEN ACTION ON PLANT

• METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER lpJOs~zOa ~zOso ~Q2> LILIQ23 ~Q24 LZ-IQ25 Q26 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o THIS EVENT WAS CAUSED BY THE UNIT SUPER IS TO. RECORD THE PART OF THE HEAT TRACE TO REVIEW TECH. SPEC. TO DETERMINE ADDITIONAL SURVEILLANCE RE VIREO 3 PERSONS WERE REINSTRUCTED IN THE SURVEILLANCE RE UIREMENTS WHE R MENT FOR SERVICE.

.8 80 7

~ls 9

FACILITY STATUS E Qss ~IO

% POWER 0 Qo NA OTHER STATUS

~

~3P ~

METHOD OF DISCOVERY

'BQoi OPERATOR OBSERVATION DISCOVERY DESCRIPTION Q32 7 8 9 10 12 13 44 45 46 80 6

ACTIVITY RELEASED OF Z Q33 CONTENT RELEASE,

'Z Q34 NA AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE Q 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION LOOOOJOoo ~zQ>> NA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 Loaoo JOoo 12 80 7 8 9 11 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 Z Q42 7 '8 9 10 80 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION 4 KZ 8 LNJQ44 9 10 NA 68 69 80 o s

0 NAME OF PREPARER R. S. Kei th PHDNF 616 465-5901.

~ V h

JULmomsn

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NDIANA 8 MICHIGANPDNER CDMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 March 21, 1978 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 Operating License DPR-74 Docket No. 50-316

Dear Mr. Keppler:

Pursuant to the requirements, of Appendix A Technical Specifications the following report is submitted:

RO 78-004/03L-O.

Sincerely, D.V. Shaller Plant Manager

/bab cc: J.E. Dolan R.W. Jurgensen G.E. Lien 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. Olson J.M. Hennigan PNSRC J,F. Stietzel Dir., IE (30 copies)

Dir., MIPC (3 copies)

'Y f

/ j\

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION 47-77)'

4 1 LICENSEE EVENT REPORT 4

CONTROL BLOCK: QI (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

~O 7 8 9 M I D C LICENSEE CODE C IQ20000000000004 14 15 6

25 26 I Z>>0~OR LICENSE TYPE 30 57 CAT 58 CON'T

~O ~LQG 0 5 0 0 0 3 1 '6f Q7 0 2 2 QS QB soUROE 75 80 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 REPORT DATE EVENT DESCRIPTION,AND PROBABI.E CONSEQUENCES Q10 UNIT 2 WAS AT NORMAL TEMPERATURE AND PRESSURE IN'MODE 3. A ROUTINE REACTOR COOLANT

~o 3 SYSTEM LEAK RATE TEST CONDUCTED . BETWEEN 0300 AND 0600 HOURS REVEALVED A LEAK RATE

~o4 OF 5.29 GPM UNIDENTIFIED LEAKAGE IN VIOLATION OF APPENDIX A TECH. SPEC. 3.4.6.2b.

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

~OG LEAK RATE OF 0.016 GPM.

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

CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~Os 7 8 9 10 Qll 11 5 Q12 ~FQ13 12 13 A L 5 x 04 18 LJFOEE 19 LoJ 20 O

SEQUENTIAL OCCURRENCE REPORT REVISION Qll LF RIRO REPORT ACTION FUTURE

~~ ~

EVENT YEAR 21 22 EFFECT 23 SHUTDOWN

~00 24 REPORT NO.

4 26 27 ATTACHMENT 28 CODE 29 NPRD-4 TYPE 30 PRIME COMP.

31 32 NO.

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

~AO13 ~FQ15 ~ZQ2o .~ZQ21 0 0 0 0 ~NQ23 ~NQ24 ~NORE V 0 8 5 p2.

33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 o THE EXCESSIVE UNIDENTIFIED LEA PHERE AND TO THE STEM LEAKOFF SYSTE . THE VALVE WAS P SYSTEM WAS CAPPED OFF. NO FURTHER ACTIONS ARE PLANNED AT THIS TIME.

3 80 8 9

~

7 FACILITY ~3O METHOD OF STATUS  % POWER OTHER STATUS = DISCOVERY DISCOVERY DESCRIPTION Q32 5

8 9 8 Q23 ~00 10 0

12 Q25 13 NA 44

~BQ31 45 46 D R 80 7

ACTIVITY CONTENT RELEASED OF RELEASE LJt Q>> ~ZQ4 NA AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE Q 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q3B EE 7 8 LOO 9

~JQ>>LZlQ3s 11 12 13 '4 80 PERSONNEL INJURIES NUMBER DESCRIPTION 41 EZ 7 8 9

~00 0 11 Q45 12 NA 80 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION

~o 8 9 Z P42 10 NA 80 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION Q 44 KK L~JO 10 8 9 NA 68 69 80 43 0

NAMF OF PREPARER R.'S. Kei th PHONE: -5 1 L

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