05000316/LER-2078-007, Re Reactor Trip Exceeded Tech Spec Limit

Re Reactor Trip Exceeded Tech Spec Limit

ML18219C216
Person / Time
Site:	Cook
Issue date:	02/13/1978
From:	Shaller D Indiana Michigan Power Co
To:	James Keppler NRC/RGN-III
References
LER 1978-007-00
Download: ML18219C216 (8)

LER-2078-007, Re Reactor Trip Exceeded Tech Spec Limit

Event date:
Report date:
3162078007R00 - NRC Website

text

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REGULATORY Ib.

RMATION DISTRIBUTION SYST (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-315 REC:

KEPPI ER J G

NRC ORG:

SHALLER D V

IN 8c MI PWR DOCDATE: 02/13/78 DATE RCVD: 02/17/78 DOCTYPE:

LETTER NOTARIZED:

NO

SUBJECT:

LICENSEE EVENT REPT.

NO.

50-315/78-07 CONCERNING POSITION II4DICATION FOR SHUTDOWN ROD, K-6 I14DICATING 129 STEPS FOLLOWlNG A REACTOR TRIP WHICH EXCEEDS THE TECH SPEC LIMIT.

COPIES RECEIVED LTR 1

ENCL 1

PLANT NAME: COOK UNIT 1

REVIEWER INITIAL:

XRL DISTRIBUTOR INITIAL:

DISTRIBUTION OF THIS MATERIAL IS AS FOL'LOWS INCIDENT REPORTS (DISTRIBUTION CODE A002)

FOR ACTION:

INTERNAL:

EXTERNAL:

BR CHIEF SCHWENCER++W/4 FNCL EG FILE++W/ENCL I 5 E++W/2 ENCL SCHROEDER/ IPPOL ITO++W/ENCL NOVAK/CHECK++W/ENCL KNIGHT44 W/ENCL HANAUER++W/ENCL EISENHUT++W/ENCL SHAO++W/ENCL KREGER/J.

COLLINS+~W/ENCL L.

CROCKER++W/ENCL LPDRiS ST.

JOSEPH MI++W/ENCL TIC++W/ENCL NSIC++W/ENCL ACRS CAT B++W/16 ENCL NRC PDR44W/ENCL MIPC++W/3 ENCL HOUSTON++W/ENCL GRIMES++A/ENCL BUTLER4+IJ/ENCL TEDESCO++W/ENCL BAER+<W/ENCL VOLLMER/BUNCH>4W/ENCL ROSA~~W/ENCL K SEYFRIT/IE++W/ENCL COPIES NOT SUBMITTED PEP'EGULATORY GUIDE 10. 1 DISTRIBUTION:

LTR 46 ENCL 46 SIZE:

iP+iP THE END CONTROL NBR:

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Qy INOIANA8r MICHIGANPOINER COMPANV DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 February 13, 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

~up~/jl D iS Rfc~io Igy Operating License DPR-58 Docket No. 50-315

Dear Mr. Keppler:

Pursuant to the requirements of Appendix A Technical Specifications and the United States Nuclear Regulatory Comoission Regulatory Guide

1. 16, Revision 4, Section 2.b, the following report is submitted:

RO 50-315/78-07.

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) 780520187

>form No. 4494 CONTROL BLOCK:

UCENSEE NAME jopg N

I 0

c c1 o

7 89 14 15 ICENBEE EVENT REPORT (PLEASE PRINT ALLREQUIRED INFORMATION)

UCENSE NUMBER LICENSE TYPE EVENT TYPE 0 0 0

0 0

0 0 P

A 1

1 I

1 IUD J 30 31

'32 25 26 CATEGORY TYPE'OURCE REPORT REPORT DOCKET NUMBER EVENT DATE REPORT DATE [001]GQNZ~

L

~L p

5 0 p 3

1 5

0 1

1 A 7 8

0 2

I 3

7 8

7 8

57 58 59 60 61 68 69 74 75 80 Qog POS ITION (RO-050-315/78-07 7

8 9 PWAE SYSTEM

CAUSE

COMPONENT CODE CODE COMPONENT CODE SUPPUER MANUFACTURER VIOLATION

~gp ~i<

5 I

N 5

T R

U

~N N

1 2

9 N

7 8 9 10 11 12 17 43 44 CAUSE DESCRIPTION

~08 THE CAUSE WAS TRACED TO THE SIGNAL CONDITIONING MODULE MODEL 'E2-86 W

47 48 7

8 9

~gg WAS FOUND TO HAVE DRIFTED OUT OF SPECIFICATIONS..

THE MODULE WAS RECALIBRATED AND 7

8 9

~10 SATISFACTORILY RETURNED TO SERVICE.

EVENT DESCRIPTION

[oO~]

ON 1-14-78 POSITION INDICATION FOR SHUT WN R

D K-6 INDI 7

8 9 m

A REACTOR TRIP.

THIS EXCEEDS THE -12 STEP LIMIT STATED IN APPENDIX A TECHNICAL 7

89

~04 SPECIFICATION PARAGRAPH 3.1.3.2.

SHUTDOWN ROD K-6's ACTUAL P I

7 8 9 Qo5 THROUGH COIL VOLTAGE MEASUREMENTS TO BE IN THE CORRECT POSITION RELATIVE TO BANK 80 80 80 80 80 80 80 OTHER STATUS N/A AMOUNT OF ACTIVITY 7

8 9 LOSS OR DAMAGE TO FACILITY TYPE

DESCRIPTION

z N/A 7

89 10 PUBLICITY N/A 7

89 7

89 FACIUTY STATUS 35 POWER

~8 LoaooJ 7

8 9

10 12 13 FORM OF 7

8 9

10 11 PERSONNEL EXPOSURES NUMBER TYPE

DESCRIPTION

~s~OO O

Z.

NA 7

8 9 11

.12 13 PERSONNEL INJURIES NUMBER

DESCRIPTION

~4 ~00 0

N/A 7

8 9 11 12 OFFSITE CONSEQUENCES N/A METHOD OF DISCOVERY A

44 45 46 44 45 N/A DISCOVERY DESCRIPTION LOCATION OF RELEASE 80 80 80 80 80 80 80 ADDITIONAL FACTORS

~ Q~g Rod K-6 osition indication was monitored durin unit start-u No further 7

89 80

~1 g discrepancies were noted.

7 89

'T.

P. Beilman PHDNE (616) 465 5901 (368)

GPO 8111 80

RECEIVED DPCUgfqrQ<4)RP(r>ESy

)9(8FEB ~I gl 8 Ig U.S. NRC DIS I RIBUTIOH SERVICE S BRANCH HOIIVUG S30IAU3S ROIIAGIHISIO JIIN'S 0 oI 933 P16l AS 33 'Ip'> i t~ilD ih3Wn~OO O3al3P3u

~o' rlcen yste IlllDIAllfA&'ICHIGAllfPDNER CDt/IPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 February 13, 1978 Mr. J.G.

Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Comnission Region III 799 Roosevelt Road Glen Ellyn, IL 60137

Dear Mr. Keppler:

Operating License DPR-58 Docket No. 50-315

'ursuant to the requirements of Appendix A Technical Specifications and the United States Nuclear Regulatory Coomission Regulatory Guide 1.16, Revision 4, Section 2.b, the following report is submitted:

RO 50-315/78-07.

Sincerely, D.V. Shaller Plant Manager;"

/bab

'c: J. E.

Dol an R.W. Jurgensen G.ED 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)

FEB 151978

Form No. 4494 LICENSEE EVENT REPORl CONTROL BLOCK:

1.

6 LICENSEE NAME LICENSE NUMBER [op~]

M I

D C

C I 0

0 0 0

0 0-0 0 0

7 8 9 14 15 25 REPORT REPORT CATEGORY TYPE'OURCE DOCKET NUMBER

~o~coNv~

L L

0 5

0 0 3

1' 0

7 8

57 58 59 60 61 68 69 (PLEASE PRINT ALLREQUIREO INFORMATION)

EVENT TYPE UCENSE TYPE 4

I I

I 1

[OD3j 26 EVENT DATE 30 31 32 REPORT DATE 1

1 4

7 8

0 2

I 3

7 8

80 74 75 toOg POSITION (RO-050-315/78-07 7

8 9 PRME SYSTEM

CAUSE

~

COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPLER MANUFACTURER VIOIATCN [oaz] ~IE E

I N

3 T

R U

~N I'1 I

2 9

N 7

8 9 10 11 12 17 43 48 CAUSE DESCRIPTION [oOs]

THE

CAUSE

WAS TRACED TO THE SIGNAL CONDITIOf'lING MODULE t10DEL E2-86 W

44 47 7

8 9 toa~]

WAS FOUND TO HAVE DRIFTED OUT OF SPECIFICATIONS.. THE t10DULE WAS RECALIBRATED AND 7

8 9

~10 SATISFACTORILY RETURNED TO SERVICE.

7 89 FACILITY STATUS POWER Hj 0

~oo o

NiA 7

8 9

10 12 13 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY Jig

~Z Z

N/A 7

8 9

10 11 PERSONNEL EXPOSURES NUMBER TYPE

DESCRIPTION

~00 0

Z.

N A 7

8 9 11

.12 13 PERSONNEL INJURIES NUMBER

DESCRIPTION

~~oo o

N/A 7

8 9 '1 12 OFFSITE CONSEQUENCES N/A OTHER STATUS

'7'9 LOSS OR DAMAGE TO FACILITY TYPE

DESCRIPTION

Z N/A

,7 89 10 PUBLICITY N/A 7

8 9 METHOD OF DISCOVERY A

44 45 46 44 45 DISCOVERY DESCRIPTION LOCATION OF RELEASE

EVENT DESCRIPTION

toO~]

ON 1-14-78 POSITION INDICATION FOR SHUT W

R D K-6 INDI 7

8 9 QP3j A REACTOR TRIP.

THIS EXCEEDS THE +-12 STEP LIMIT STATED IN APPENDIX A TECHNICAL 7

89 QP]

SPECIFICATION PARAGRAPH 3.1.3.2.

SHUTDOWN ROD K-6'CTUAL P I

i7 89 Qosj'HROUGH COIL VOLTAGE MEASUREI1ENTS TO BE IN THE CORRECT POSITION RELATIVE TO BANK 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 7

8 9 Q~g]

discrepancies were noted.

7 89 T.

P. Beilman 80 PHDNF, ( 61 6) 465-5901 (368)

GPO Gbt~ OGT ADDITIONAL FACTORS

~18 Rod K-6 osition indication was monitored durin unit start-u No further

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