05000316/LER-1978-076, Forwards LER 78-076/03L-0 & LER 78-077/03L-0

Forwards LER 78-076/03L-0 & LER 78-077/03L-0

ML17317A713
Person / Time
Site:	Cook
Issue date:	11/01/1978
From:	Shaller D INDIANA MICHIGAN POWER CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17317A714	List: 05000316/LER-1978-076, Forwards LER 78-076/03L-0 & LER 78-077/03L-0 05000316/LER-1978-077-03, /03L-0 on 781005:main Turbine Stop Valves C & D Closure Limit Switches Found Inoperable.Caused by Excessive Vibration of Stop Valves Due to Poor Design
References
NUDOCS 7811090151
Download: ML17317A713 (8)

LER-1978-076, Forwards LER 78-076/03L-0 & LER 78-077/03L-0

Event date:
Report date:
3161978076R00 - NRC Website

text

2.

REGUIRTO+INFORMATION DISTRIBUTION+STEM

~ ~

DOCKET NBR: 50-316 COOK -2 DOC DATE:

781101 RECIPIENT:

KEPPLER,J.G.

ACCESSXON NBR: 7811090151 ORXGINATOR:SHALLERFD.V.

COPIES RECEIVED:

COMPANY NAME: IN

& MI PNR CO LTR 1

ENCL 1

SUBJECT:

SIZE:

1+2 LERg78-076/03L-0 on 781003:surveillance tests on train-B of sol'id st protec sys showed that several switch positions were bad.

Caused by bad universal logic. card.

Card replaced 6 sys returned to SVC.

LER478-077/03L-0 encl.

DISTRJQUTION CODEt

'BLOOP DISTRIBUTIO~ TITLEi INCIDENT REPORTS NOTARIZED BR CH NRC PDR I

L E

4% I P C I

L C

SYSTE,"S BR

'OQAK/CHECK EEB AD FOR ENG PLANT SYSTEMS BR

'HANAUFR

'., AD FOR PLANT.SYST

'D FOR SYS L

PROJ REACTOR SAFETY BR ENGINEERING BR KREGER/J.'nLLINS i POWER SYS aR E. Jordan LPDR NSIC 4 ACRS TOTAL NUBBER OF ENCL7 w/g ENCL W/ENCL w/ENCL W/g ENCL W/5 ENCL w/FNCL W/ENCi w/ENCL W/ENCL w/ENCL w/ENCL EBS w/ENCL

~/ENCL W/ENCL W/ENCL W/ENCL W/ENCL H/ENCL W/ENCL W/ENCL W/I6 ENCL COPIES REuUTRED>

LTR ENCL 4

I FOR ACTION

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ORB%1 BC q>>

NOTES: SEND 3

CYS OF ALL NATL TO I g

E

DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 November 1, 1978 Mr. J.G.

Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regul.atory Coiliiission 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 the Appendix A Technical Specifications the following reports are submitted:

RO 78-076/03L-0 RO 78-077/03L-0 Sincerely, A>> D.V. Shaller Plant Manager

/bab 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.

Olson J.M. Hennigan PNSRC J.F. Stietzel Dir., I'E (30 copies)

Dir., MIPC (3 copies) yt()Y 3 1978 7S'bio oo is-y ~

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U. S. NUCLEAR REGULATORY COMMISSION NRC FORM 366 p.)~ --'-

LICENSEE EVENT REPORT s

CONTROL BLOCK:

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0 0

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LICENSEE CODE 14

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8 Qg DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES ~10 DURING NORMAL OPERATIONi SURVEILLAN&TESTS ON TRAIN B OF lHE SOLID STATE 3

PRCTiKTION SYSTEM REVEAIZD %PZ SIRERAIs SWITCH POSITIONS TESTED WERE BAD THIS RENDERED THE SYSTEM INOPERABIE IN RESPKT TO T.S.

TABLE 3.3-1 ITEM 22.

THE APPLICABIZ ACI'ION MQQIREMIXTS NEHE FULFIILED~

~OB

~os 7

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8 SYSTEM

CAUSE

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VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

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47 CAUSE DESCRIPTION ANDCORRECTIVE ACTIONS 27 IMMEDIATE TIGUBIZSHOOTMG THAT THIS FAILURE WAS DUE TO A BAD UNIVERSAL IOGIC CARD. (WESTINGHOUSE PART NO. 6056D2lGOl). 'le DEFECTIVE IOGIC CARD WAS REPLACED AND AI.IER TESTING THE NEW CARDi THE SYSTEM WAS REZURNED TO SERVICE.

NO FURLER ACTIONS ARE REQUIRED AS A RESULT OF THIS EVICT.

. CD ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITYQ 6

~Z Q33 Z Q34 NA 7

8 9

10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q3g o ~00 0

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11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 [ii~] ~oo o

Qo NA LOCATIONOF RELEASE Q 45 7

8 9

FACILITY

~3P METHOD OF STATUS

% POWER OTHER STATUS ~

DISCOVERY DISCOVERY DESCRIPTION Q32 s

E Qos ~10 0

Qos NR

~BQsl SOROEZLZRNCE TEST 7

8 9

10 12 13 44 45 46 80 80 80 80 7

8 g

7 8

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8 9

10 PUBLICITY ISSUED DESCRIPTION Q4 L~JQ44 9

10 NAME OF PREPARER 9

11

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12 LOSS OF OR DAMAGETO FACILITYQ43 TYPE

DESCRIPTION

Z Q42 Jack Rischlin 68 69 PHONE'RC USE ONLY 80 80 80 g 0

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NRg FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7-"fP:~

LlCENSEE EVENT REPORT 8

CP NTR0L BLOCK:

Ql (PLEASE PRINT OR TYPE ALLREQUIRED INFORMATION)

I 6

~oi II I

0 C

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QE 0

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LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T

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8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES QIO

~02 DURING NORMAL OP ERAT ION THE MAIN TURBINE S

II II II II

~O3 LIMIT SWITCHES WERE FOUND INOPERABLE.

THESE SWITCHES PROVIDE A TRIP SIGNAL AS LISTED IN T.S.

TABLE 3.3-1 ITEM 18.b.

THE APPLICABLE ACTION RE UIREMENTS

~OS WERE FULFILLED.

PREVIOUS OCCURRENCES INCLUDE: 050-316/78-29.

~os

~os 7

8 80

~Os 7

8 VIBRATION OF THE STOP VALVES, WHICH I'S ATTRIBUTED TO POOR DESIGN.

BOTH SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

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8 QEE

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CODE TYPE NO.

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QW

~03

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+0 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

~FQEE ~FQls

~2Q28

~ZQEl 0

0 0

0

~N Q23

~YQ23 LJLIQ28 Qs 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27

~1O INVESTIGATION REVEALED THAT THESE FAILURES WERE CAUSED BY THE EXCESS IVE LIMIT SWITCHES WERE 'REPAIRED'iAND!RETURNED:TO SERVICE'THESE PROBLEMS ARE 3

4 PRESENTLY UNDER STUDY AS A DESIGN CHANGE (02-2248)

HAS BEEN INITIATED TO FIND A SUITABLE REPLACEMENT INSTRUMENT.

METHOD OF DISCOVERY WQ31 44 45 46 QBS 44 45 OF PREPARER

~Ck Ri SChl in 7

8 9

FACILITY STATUS

% POWER OTHER STATUS 8

8 Q28 LDD 9~0 Q28 7

8 9

10 12 13 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITY ZZ Z

Q33

~~Q34 NA 7

8 9

10 11 PERSONNEL EXPOSURES NUIABER TYPE

DESCRIPTION

~l7 ~00 0

QET ~ZQ38 NA 7

8 9

11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 8

~00 0

QEE NA 7

8 9

11 12 LOSS OF OR DAMAGETO FACILITY 43 TYPE

DESCRIPTION

2 Q42 NA 7

8 9

10 PUBLICITY ISSUED DESCRIPTION~

KZ LNJS 7

8 9

10 80 LOCATION OF RELEASE Q 80 80 80 80 PHONE:

68 69 80 NRC USE ONLY ESa 8

80 Es 0

DISCOVERY DESCRIPTION Q32

I P

I

. ~

DONALD C. COOK NUCLEAR PLANT P.O. Box 468, Bridgrnan, Michigan 49106 November 1, 1978 Mr. J.G.

Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Coranission 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 the Appendix A Technical Specifications the following reports are submitted:

RO 78-076/03L-0 RO 78-077/03L-0 Sincerely, R~ D.Y. Shaller Plant Manager

/bab 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.

Olson J.M. Hennigan PNSRC J. F. Stietzel Dir., I'E (30 copies)

Dir., MIPC (3 copies) 7f(ID' 5/

RFGL>L,II I~~~(I g,

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