ML18219B574

Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-038/03L-0, RO 78-039/03L-0, RO 78-040/03L-0, RO 78-041/03L-0)

ML18219B574
Person / Time
Site:	Cook
Issue date:	06/03/1978
From:	Shaller D American Electrtic Power System, Indiana Michigan Power Co
To:	James Keppler NRC/RGN-III
References
LER 1978-038-03L, LER 1978-039-03L, LER 1978-040-03L, LER 1978-041-03L
Download: ML18219B574 (9)

Text

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'REGULATORY I/FORMAT'I'ON'ISTRIBUTION SYSTEM (RIDS')'

DJ.STBj:9UTI ON FOR INCOMING'ATERI'AL 50-316

'I REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 06/30/78 NRC IN 5 MI PWR DATE RCVD: 07/06/78 DOCTYPE: LETTER NOTARIZED: NG COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-316/78-038) ON 06/07/7S CONCERNING DURING SURVEILLANCE TEST ON CD PLANT BATTERY . CELL 589 WAS FOUND TO HAVE 8 ECIFIC GRAVITY BELOW 1200 MINIMUM SPECI -IC GRAVITY ALLOWED BY TECH SPECS... WfATT LERS78-039'8-040 AND 7g 0+ <

PLANT NAME: COOK UNIT 2 REVIEWER INITIAL: X JM lt DISTRIBUTOR Il INITIAL:~

<<+<~<<<<<H'<<~HH~<<DISTRIBUTION OF THIS MATFRIAL IS AS FOLLOWS NOTES:

SEND 3 COPIES OF ALL MATERIAL TO IS.E ED REEVES-1 CY ALL I'IATERIAL INCIDENT REPORTS (DISTRIBUTION CODE A002)

FOR ACTION: BR CHI - LWRN2'C54W/4 ENCL INTERNAL: EG . .~W/ENCL NRC PDR<<W/ENCL E+4~W/ 2 ENCL MIPC<<W/3 ENCL

8. C SYSTEMS BR4l+W/ENCL EMERGENCY PLAN BR<<M/ENCL NOVAK/CHECK+4FW/ ENCL EEB<<I Jf ENCL AD FOR ENG4twM/ENCL PLANT SYSTEMS BR<<W/ENCL HANAUER~~~W/ENCL AD FGR PLANT SYSTEMS+<M/ENCL AD FOR SYS 5 PROJ<<W/ENCL REACTOR SAFETY BR<<W/ENCL ENGINEERING BR4F4W/ENCL VOLLMER/BUNCH<<W/ENCL KREGER/J. COLLINSQ+M/ENCL POWER SYS BR<<M/ENCL K SEYFRI T/ IE~~~~W/ ENCL EXTERNAL: LPDR S ST. JOSEPH' I <<W/ENCL TIC~~~W/ENCL NS I C~~~W/ENCL ACRS CAT B~F+W/16 ENCL DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 781870119 S I ZE: 1P+ 1 P+3P

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8 ISION LE MASTER ROSTER PUBLICATIONS I

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DISTR D ISTRIBUT ION DISTR IBUT ION ABUT CODES QTY.

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DISTR D I STR.I I

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~Xi er4oen 7'O'NDIANA

& MICHIGANPOWER COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 V7 7 r;j fC"7f'7 c Cr~'

June 30, 1978 1 ~

7 f '7.4 C iC9 "7

7 C"3 Cl7 C77

~>cv C.M Mr. J.G. Keppler, Regional Director ~7 Kl CD Office of Inspection and Enforcement United States Nuclear Regulatory Commission CD Region III C/7 799 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 78-038/03L-0 RO 78-039/03L-0 RO 78-040/03L-0 RO 78-041/03L-O.

Sincerely, D.VS 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. Kennigan PNSRC J.F. Stietzel R.S. Keith Dir., IE (30 copies) JUL 03 1978 Dir., MIPC (3 copies) Y.

LP ll

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7.77)

LICE NT REPORT CONTROL BLOCK: Qi (PLEASE PRINT OR TYPE ALL REOUIRED INFORMATION)

I 6

[os) M I D D C 2 Q2 14 15 0 0 - 0 0 0 0 LICENSE NUMBER

- p 0 25 Qs 26 4 1 1 1 LICENSE TYPE 30 1 QE~QE 57 CAT 58 7 8 9 LICENSEE CODE CON'T

~o1 " ' ~LQB 0 5 '0 0 0 3 1 6 Q7 0 6 0 " 7 8 QB 0 6 3 0 7 8 ee 68 69 EVENT DATE 74 75 REPORT DATE 80 7 8 60 61 DOCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 During survei 11 ance test on CD Plant Battery, cel 1 )I 89 was found to have a

~O3 specif ic gravi ty of 1 ~ 195 whi ch is below the 1 ~ 200 minimum speci fic gravity

~O4 allowed per T. S. 4.8. 2. 3. 2a, 2, which .-constituted an inoperable battery.

~OS AB battery was operable. DC loads were shifted to AB battery for a period of

~OB 16 mi nutes whi-1 e cell 889 was jumpered . CD battery was returned to service a fter

~O7 being inoperable for 80 minutes. This event had no,effect upon public health

~OB and safety.

80 7 8 SYSTEM CAUSE CAUSE COMP. VALVE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~og 7 8

~EC 9

CODE 10 Q>>

CODE 11 E

Q LAJQ73 12 13 8 A .T T R Y 18 8 LZJQEE 19 L2J 20 Q

REVISION SEQUENTIAL OCCURRENCE REPORT REPORT NO. CODE TYPE NO.

U EVENT YEAR Q17 LF R(RO REPoRT ~78 21 22 23 L0038 26I 24 L~J 27 LLJ 28 29 UL 30 Q

31 32 0

ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDP PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER LCJQ>> LZJQ23 LZJQ>> O O O O ~NQ23 ~YQ24 ~AQEE E 3 5 5 Q23 LXJQER 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 The exact cause of the 1 ow speci fi c ravi t could not be determi ned ~ A rocedure i s being developed to attempt to restore the cell . Also, a repl acement cell has been ordered incase restorati on is not possible. Remaining cel 1 s in CD battery 3

show no similar problems ~

4 8 80 7 9 FACILITY METHOD OF OTHER STATUS QBO DISCOVERY DISCOVERY DESCRIPTION Q32 STATUS ~  % POWER 7 8

~BQ23 9

~pg 10 p Qs 12 13 NA 44

~BQ31 45 46 NA 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q NA LOCATION OF RELEASE Q

~Z Q33 Z Q34 NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 Q37 MZQ33 NA 8 11 12 13 80 7 9 PERSONNEL INJURIES '.

((ygg5 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION g Z Q42 NA 8 9 10 80 7

PUBLICITY NRC USE ONLY ISSUED DESCRIPTION Q o 7 8

~Ze 9 10 NA 68 69 BOP 2

g NAMF oF PREPARER Dave Wizner PHONE

NRC FORM 366 U. S. NUCI.EAR REGULATORY COMMISSION 1, LICENSEE EVENT REPORT CONTROL BLOCK: QI {PLEASE PRINT OR TYPE ALL. REQUIRED INFORMATION)

I 6

,

~oi 7 8 9 N I 0 LICENSEE'ODE C C ZJOO 14 15 0 - 0 0 0 0 LICENSE NUMBER 0 0 DQ25 26 1 1 LICENSE TYPE 1 1Q~00 30 57 CAT 58 CON'T

~01 soosos LUQs 0 5 0 0 0 3 1 6 68 Q 69 0 6 1 EVENT DATE 5 7 8 74 Qs0 75 6 3 REPORT DATE 0 7 8 80 Q

60 61 DOCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 During survei 1 1 ance test on AB Pl ant Battery, cell 835 was found to have a

~O3 ', specificJgravity of 1.197 which is below the 1.200 minimum specific gravity

~p4 allowed per T.S. 4.8.2.3.2a, 2 which constituted an inoperable battery. CD

~OS battery was operable. DC loads were shifted to CD battery for a period of

~ps 13 minutes while cell 7II35 was jumpered. AB battery was returned to service after

~O7 being inoperable for 29 minutes. This event had no effect on:publ.ic I health and

~08 safety. Reference similar LER No. 78-038/03L-O.

80 7 8 9 4 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~OS C Q11 ~ZQ12 ~AQ13 8 A T T 8 Y Q4 ~ZQ15 ~Z Qs 8 9 10 11 12 13 18 19 20 7

SEQUENTIAL OCCURRENCE REPORT REVISION Q>>

ACTION FUTURE LF R(RO ssso>>

EVENT YEAR

[zan+22 21 EFFECT

+

23 SHUTDOWN

~03 24 REPORT NO.

9 26

+w 27

~03 28 ATTACHMENT CODE 29 NPRDR TYPE

~L 30 PRIME COMP.

31 32 NO.

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

~CQ13 ~ZQ25 ~ZQ>> 0 0 0 0 ~NQ23 ~YQ24 A Q25 5 3 5 5 Qss Q15 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 p The exact cause of the low s ecific ravit could not be determined. A procedure is being developed to attempt to restore the cell. Also, a replacement cell has been ordered in case restoration is not possible. Remaining cells in 3

AB battery show no similar problems.

4 7 8 9 80 FACILITY METHOD OF STATUS 51 POWER OTHER STATUS QSO DISCOVERY DISCOVERY DESCRIPTION Q32 5 ~8 Q25 ~05 0 Q25 NA 44

~BQ" 45 46 NA 80 7 8 9 10 , 12 13 ACTIVITY RELEASED OF RELEASE CONTENT AMOUNT OF ACTIVITY NA Q NA LOCATION OF RELEASE Q 6 ~Z Q33 ~ZQ34 80 7 8 9 10 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7 8

~00 9

0 11 Q31 12 Z Qss 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION Q41

~15 ~OO O Q45 NA 80 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION z Q4. NA 8 9 10 80 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION Q

~2O ~ZQ4 NA 68 69 80 ~

2 45 8 9 10 616 465 5901 3 EXT 4 398 NAME OF PREPARER PHONE

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION

{7.77) .

LtCENSEE EVENT REPORT CONTROL BLOCK: Ql (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6

[os) 8 9

[ D LICENSEE CODE C C 2 14 Q 15 o o o 0 0 LICENSE NUMBER 0 0 0 o 25 Q 26 4 I I I LICENSE T)[PE 30 QE~QE 57 CAT 58 CON'T ULQE 0 6 0 0 0 3 1 6Q70 6 0 3 7 8QE 0 6 3 0 7 8 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 5

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10

~O2 AFTER THREE REACTOR TRI'PS ON JUNE 3 9 13 1978 ROD BOTTOM POSI'TIO INDICATION

~O3 FOR CONTROL ROD H-8 DID NOT INDICATE THAT H-8 WAS FULLY INSERTED.

~O4 THE ACTION RE(UIREMENT OF T.S. 3.1.1.1 WAS FULFILLED BY EMERGENCY BORATING FOR 5 MINUTES.

~O6

~O7

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

CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 . 8 9 0

10 Q UxQ UxQ 11 12 13 18 Q14 U[

19 Q15 ~Z 20 Q16 SEQUENTIAL OCCURRENCE REPORT REVISION Q17 LF RIRP REPoRT EVENT YEAR I778J U ~04 REPORT NO.

0 U~ M>

CODE TYPE UL NO.

laJ 21 22 23 24 27 28 29 30 31 32

'5 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDQ PRIME COMP. COMPONENT Q

TAKEN ACTION 33 Ql!I Ux 34 Qlg ONPLANT Uz Q20

-

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 METHOD Uz 36 Q21 37 0

HOURS 0 0 0 22 40 SUBMITTED 41 N Q23 ~

FORM SUB.

42 Q24 SUPPLIER L[LIQ25 43 44 MANUFACTURER II I 2 0 Q25 47 o

NA 3

4 7 8 9 80 5

FACILITY STATUS UD Q25 ~OG 39 POWER 0 Q29 OTHER STATUS NA

~

~3P =

METHOD OF DISCOVERY L[LJ Q31 DISCOVERY DESCRIPTION Q32 7* 8 9 10 12 13 44 45 46 80 QQQ ACTIVITY CONTENT RELEASED OF RELEASE

~Z Q3 Z Q3

~

AMOUNTOF ACTIVITY NA

~ LOCATION OF RELEASE Q 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7 ~<< 0 Q37 2 Q35 NA 7 8 9 '1 PERSONNEL INJURIES 12 13 80 NUMBER DESCRIPTION Q

[ii~j ~00 7 8 9 0

511 Q49 12 NA 80 LOSS OF OR DAMAGE TO FACILITY Q43

~IB ~<Q42 NA 7 8 9 10 80 PUBLICITY o

ISSUED

~NQ44 DESCRIPTION Q N NRC USE ONLY o44 7 8 9 10 68 69 80 o 0

NAME OF PREPARER JaCk RlsChlln PHONE:

I

I'RC FORM 366 I7.77),,

LICENSEE EVENT REPORT CONTROL BLOCK: QI (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 7 8 9 M I D LICENSEE CODE C C 2 14 Q2 15 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 25 Q34 26 1 1 LICENSE TYPE 1 1 30 Q4~QE 57 CAT 58 CON'T

"'""'LJQBO 5 0 0 0 3 I 6 Q70 6 0 2 7 8 QB 75 0 6 3 0 7 80 REPORT DATE 8'0 7 8 61 DOCKET NUMBER 68 69 EVENT DATE 74 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 DURING NORMAL OPERATION, ROD POSITION INDICATION FOR CONTRO D-MEF1 THE

+ 12 STEP LIMIT OF T. S. 3.1.3.2. PREVIOUS OCCURRENCES OF A

~O3

~O4 S IMILAR NATURE INCLUDE: RO-050/316-78-31,22,08,07'.~,'RO-050/315-78-.07,04.

~OS 77-34,33,28,27,76-54,44,13.

~O6

~O7

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

CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 8

~IE 9 10 Qll E 11 Q12 ~ZQ13 12 13 I N 5 T R 0 18 Q4 ~IQ19 19

~Z 20 QTE SEQUENTIAL OCCURRENCE REPORT REVISION LF R IRO EVENT YEAR REPORT NO. CODE TYPE Q11 REPORT

[77J 21 22 23

~O< I 24 26

~~

27

~OS 28 29 30 31

+o ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDR PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~EQTE 33

~Z 34 QEE ~Z 35 Q20 ~Z 36 Q 37 0 0 0 40

~N 41 Q23 LE) Q24 42 IJL) QEE 43 44 47 QE CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27

~1O INVESTIGATION REVEALED THAT THE SIGNAL CONDITIONING MODULE OUTPUT VOLTAG AFTER THE ROD'S SECONDARY COIL VOLTAGE WAS MEASURED TO VERIFY THA THE CORRECT POSITION, THE SIGNAL CONDITIONING MODULE WAS RECALIBRATED AND 3 PLACED BACK IN SERVICE RETURNING RPI TO WITHIN THE 12 STEP LIMIT 4

7,8 9 80

~lE FACILITY STATUS

~E Q29 ~06

% POWER 5 Q29 NA OTHER STATUS ~

~3P MfTHDD OF

<<DISCOVERY

~AQ31 OPERATOR OBSERVATION DISCOVERY DESCRIPTION Q32 7 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE Q33 Z Q34 AMOUNTOF ACTIVITY NA

~ NA LOCATION OF RELEASE Q 7 8 9 10 11 44 45 80 PERSONNEI. EXPOSURES NUMBER TYPE DESCRIPTION Q39 1 ~00 0 QET Z Q39 NA 80 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION 41 9

8

~00 9

0 Q49 11 12 QIIA 80 7

LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 Z Q4, NA.

7 8 9 10 80 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION~ 44 O

O LNJQ4" 7 8 9 10 68 69 80 g Jack Risch]ing 616-465-5901 0 NAME OF PREPARER