05000316/LER-2078-064-03, Letter Enclosure of Licensee Event Report

Letter Enclosure of Licensee Event Report

ML18219B520
Person / Time
Site:	Cook
Issue date:	09/27/1978
From:	Shaller D American Electrtic Power System, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To:	James Keppler NRC/RGN-III
References
LER 1978-064-03L
Download: ML18219B520 (6)

LER-2078-064, Letter Enclosure of Licensee Event Report

Event date:
Report date:
3162078064R03 - NRC Website

text

REGULATORY'NFORMATION 13ISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50 -316 REC:

KEPPLER J G

NRC ORG:

SIIALLER D V IN 5 MI PWR DOCD ATE: 09/27/78 DATE RCVD:

10/03/78 DOCTYPE:

LETTER NOTARIZED:

NO COPIES RECEIVED

SUBJECT:

LTR 1

ENCL 3 FORWARDING LICENSEE EVENT REPT (RO 50-316f78-064)

ON 09/05/70 CONCERNING 13URI NG NORMAL OPERATION ROD INDICATION FOR ROD C-9 INDICATED A DEVIATION OF GREATER THAN 12 STEPS FROM DEMAN POSITION>

EXCEEDING TECH SPEC LIMIT OF 3.'. 3. 2.

PLANT NAME: COOK UNIT 2 REVIEWER INITIAL:

X DISTRIBUTOR INITIAL: ]Q

~~HH~<<<e>>>>>>~~~.~-

DISTRIBUTION Ol= THIS MATERIAL IS AS FOLLOWS>>~~>>~~>>~>>>>~~~

NOTES:

i.

SEND 3 COPIE OF ALL MATERIAL TO IhE INCIDENT REPORTS (DISTRIBUTION CODE A0023 FOR ACTION:

BR CI-IIEF ORB61 BC~~~W/4 ENCL INTERNAL:

EXTERNAL:

iEG F

<<+W/ENCL

--k4WJ ENCL I 5 C SYSTEMS BR>>W/ENCL NOVAK/CHECIB4W/ENCI AD FOR ENG<+W/ENCL HANAUER>>W/ENCL AD FOR SYS 0 PROJ~+W/ENCL ENGINEERING BR<4 W/ENCL KREGER/J.

COLLINS4>> ~ W/ENCL l'EYI=RITlIE>>W/ENCL LPDR S ST.

JOSEPH MI N. wW/ENCL NSIC>>W/ENCL ACRS CAT B~4~W/16 ENCL NRC PDR>>W/ENCL MIPC44~W/3 ENCL EMERGENCY PLAN BR>>W/ENCL EEB4~~W/ENCL PLANT SYSTEMS BR+4W/ENCL AD FOR PLANT SYSTEMS~<W/ENCL REACTOR SAFETY BR>>W/ENCL VOLLMER/BUNCH44~W/ENCL POWER SYS BR~>>W/ENCL DISTRIBUTION:

LTR 44 ENCL 44 S I ZE:

1P+2P

% 3<<l 5 $f>>% Ã 0fSHf+ 3fSHHH5%>> k0t")I>>6>>>> SHHl k THE END CONTRQL NBR:

780680 88 Hl>>4 5 3I %4% k%>>>>%%%>>>>4%4 %>>>>>>>>%

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/

DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgrnan, Michigan 49106 September 27, 1978 kIi1Ãii7~7i llIIl,'I(f7i fj[I:.IIIitt la(

A)-I

~~CD C7 Mr. J.G.

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

C)

C7 C)

C r'~

IR

~CO C)

Dear Mr. Keppler:

Operating License DPR-74 Docket No. 50-316 Pursuant to the requirements of the Appendix A Technical Specifications the following report is submitted:

RO 78-064/03L-O.

Sincerely, D.V. Shaller Plant Manager

/bab cc:

J.E.

Dolan R.W. Jurgensen REF.

Kroeger R.

Ki 1 burn R.J.

Vollen BPI K.R. Baker RO: III R.C. Callen MPSC P.W. Steketee,'sq.

R. Walsh, Esq.

G. Charnoff, Esq.

G. Olson J.M. Hennigan PNSRC J.F. Stietzel R.S. Keith T.P. Beilman/J.L. Rischling Dir., IE (30 copies)

Dir., MIPC (3 copies)

Ill,ygag(

<<EI tf 780680188

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NRC FORM 366 I7-77) t

~ NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT 0 Qo4 1

1 1

1 Q<~Oo 25 26 LICENSE TYPE 30 57 CAT 58 CONTROL BLOCK:

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{PLEASE PRINT OR TYPE ALLREQUIRED INFORMATION)

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LICENSEE CODE 14 IS LICENSE NUMBER CON'T

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7 8 Q DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABI.E CONSEQUENCES Qlo

~02 DURING NOBMAL OPERATION CN SEPTIM3ER 5, BOD PCSITION INDICATION (BPI)

FOR BOO 3

C-9 INDICATED A DISVIATION OF GREATER THAN 12 STEPS FBDM DEMAND POSITION.

THIS

~04 EZC1XDED T S

3 1 3 2 ALSO'N SEPTEMFKoR 14 7 WHILE INCREASING PC%& BPI FOR 6

H-8 EXCEED THE T.S. LIMIT.

THE APPLICABLE T. S.

ECTION REQUIBI2KÃZS HEBE FULE'ILLED.

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6 SIMILAR INCLUDE 050 0315/76 13 t 44 i54 77 27 28 7 33 7 34 78 04 z 07 i38 I46

~07 050 0316/78 07 i08 g 22 g 31 7 41

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CAUSE

CAUSE COMP VALVE CODE CODE4-SUBCODE COMPONENT CODE SUBCODE SUBCODE

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10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LF RIRO EVENT YEAR REPORT NO.

CODE TYPE O.

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+

~08 4

21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDP PRIME COMP.

COMPONENT TAKEN ACTION ON PLANT METHOD HOUR(. +22 SUBMLTTED FORM SUB.

SUPPLIER MANUFACTURER Qle

~Q20 ~ Q2

~ Q23 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o

INVESTIGATICN BEVfMZD THAT TSE SI~ CC5DITICNING M)DULE HAD DRIFTED HIGH FOR C 9 ~

AFZER VEBIFYZlG 'ISE POSITION OF BOD C-9 BY MEASURING 'iSE ROD'S SECCNDABY COIL VOLTAGE THE SI~ CCNDITICNING N3DULE HAS RECAl2ZBATED AND PUV ED BACK IN SERVICE INDICATING 7

8 9

FACILITY STATUS

% POWER OTHERSTATUS Q F

26 0

9 2

29 NA 80 METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32 O~O

~BQ31 SURVEZZZmCE TEST 7

8 9

10 12 13 44 45 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITY~

LOCATIONOF RELEASE Q36

~Z Q33

~ZQ3 NA NA 7

8 9

10 44 PERSONNEL EXPOSURES NUI'ABER TYPE DESCRIPTION Q39 l ~00 0

Qo~

Z Qoo NZ 7

8 9

11 12 13 PERSONNEI. INJIJRIES NUMBER DESCRIPTIONQ41 [i']~pQ4o NA 80 45 80 80 9

11 12 LOSS OF OR DAMAGETO FACILITYQ TYPE

DESCRIPTION

~ZQ42 9

10 PUBLICITY ISSUED DESCRIPTION~

~Q44 9

10 7

8 80 9

80 NRC USE ONLY o

t 80 o 0

7 8

O 68 69 7

8 PHONE:

NAME OF PREPARER 3

THE CORRECT BOD POSITION 'PI FOR H 8 REZUEKED K) WITHIN THE + 12 STEP LIMIT7 WITHOUZ 4

ANY CORRECTS PCTICNo THE CONZBDL BANK WAS BEING NITHDimI {SEE SUPPLIMÃZ)

4

SUP~em TO ZZR 578-064/03L-0 CAUSE DESCRIPTION SUPPL1HPKZ hMZZ INCREASING PGNER.

M ENGINEERING HWEEW IS IN 'PEERESS TO IXTlPM1NE 'JHE KGT CMICE OF THIS HECUKUNG PEGBZZN.