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{{#Wiki_filter:4'REGULATORY DJ.STBj:9UTI ON FOR REC: KEPPLER J G NRC DOCDATE: 06/30/78 DATE RCVD: 07/06/78 I/FORMAT'I'ON'ISTRIBUTION SYSTEM (RIDS')'INCOMING'ATERI'AL
., 50-316'I ORG: SHALLER D V IN 5 MI PWR 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...Wf ATT LERS 78-039'8-040 AND 7g 0+<PLANT NAME: COOK-UNIT 2 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:~lt Il<<+<~<<<<<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: INTERNAL: EXTERNAL: BR CHI-LWRN2'C54W/4 ENCL EG..~W/ENCL E+4~W/2 ENCL 8.C SYSTEMS BR4l+W/ENCL NOVAK/CHECK+4FW/
ENCL AD FOR ENG4twM/ENCL HANAUER~~~W/ENCL AD FOR SYS 5 PROJ<<W/ENCL ENGINEERING BR4F4W/ENCL KREGER/J.COLLINSQ+M/ENCL K SEYFRI T/IE~~~~W/ENCL LPDR S ST.JOSEPH'I<<W/ENCL TIC~~~W/ENCL NS I C~~~W/ENCL ACRS CAT B~F+W/16 ENCL NRC PDR<<W/ENCL MIPC<<W/3 ENCL EMERGENCY PLAN BR<<M/ENCL EEB<<I Jf ENCL PLANT SYSTEMS BR<<W/ENCL AD FGR PLANT SYSTEMS+<M/ENCL REACTOR SAFETY BR<<W/ENCL VOLLMER/BUNCH<<W/ENCL POWER SYS BR<<M/ENCL DISTRIBUTION:
LTR 45 S I ZE: 1P+1 P+3P ENCL 45 CONTROL NBR: 781870119<<%0HM 4%%8M<<%9M 4%%%%%0$<<%084%0E%HF0F<<THE FND MASTER ROSTER PUBLICATIONS ISION I----D ISTRIBUT ION CODES 1 LE I------DISTR ABUT ION QTY.Y ST ZIP I----DISTR IBUT ION CODES 18-I-----D I STR.I BUT ION CODES 35-I------DISTR I BUT ION QTY 35-8 17-~17-----I 3~----I RD OF SUPERVISGRS LR IRNOMAN SAN DIEGO CO BD SUP 1'4 DIEGO CA 92101 BRARI AN N D I EGO 1 CA 92101 N DIEGO CA 92101 SN SR SF SE SM SO ST SA SG NB NU 1 1 CL EAR PHARMAC I ST N DIEGO CA 92103 SF SE SM SP ST SO SA SG 1 1 1 1 1 1 1 1 N D IEGO CA 92108 J OLLA CA 9203 7 SN SF SE SM ST SG CH 1 AN DIEGO SN SR SF SE ST SG 1 1 1 1,1 1 CA 92110 AN DIEGO CA 92110 1 1 1 1 1 1 1 li AN DIEGO iM CA 92112 SN SR SF SE SM SP ST SO SA SG CM
~Xi er4oen 7'O'NDIANA
&MICHIGAN POWER COMPANY DONALD C.COOK NUCLEAR PLANT P.O.Box 458, Bridgman, Michigan 49106 June 30, 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 V7 r;j 1~C"3~>cv~7 Kl C/7 c 7 7 f f'7 C"7 Cr~'f'7.4 C iC9 7"7 Cl7 C77 C.M CD CD 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)Dir., MIPC (3 copies)JUL 03 1978 Y.
LP ll U.S.NUCLEAR REGULATORY COMMISSION Qi (PLEASE PRINT OR TYPE ALL REOUIRED INFORMATION) 6 0-0 0 0 0-p 0 Qs 4 1 1 1 1 QE~QE 25 26 LICENSE TYPE 30 57 CAT 58 LICENSE NUMBER NRC FORM 366 (7.77)LICE NT REPORT CONTROL BLOCK: I[os)M I D D C 2 Q2 0 7 8 9 LICENSEE CODE 14 15 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 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 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~O4~OS~OB~O7~OB 7 8 specif ic gravi ty of 1~195 whi ch is below the 1~200 minimum speci f ic gravity allowed per T.S.4.8.2.3.2a, 2, which.-constituted an inoperable battery.AB battery was operable.DC loads were shifted to AB battery for a period of 1 6 mi nutes whi-1 e cell 889 was jumpered.CD battery was returned to service a f ter being inoperable for 80 minutes.This event had no,effect upon public health and safety.80~og i s being developed to attempt to restore the cell.Also, a repl acement cell has SYSTEM CAUSE CAUSE COMP.VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~EC Q>>E Q LAJQ73 8 A.T T R Y 8 LZJQEE L2J Q 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LF R(RO EVENT YEAR REPORT NO.CODE TYPE NO.Q17 REPoRT~78 U L0038 I L~J LLJ UL Q 0 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 HOURS Q22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER LXJQER LCJQ>>LZJQ23 LZJQ>>O O O O~NQ23~YQ24~AQEE E 3 5 5 Q23 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 f i c ravi t could not be determi ned~A rocedure 3 been ordered incase restorati on is not possible.Remaining cel 1 s in CD battery show no similar problems~OTHER STATUS QBO NA METHOD OF DISCOVERY~BQ31 NA 46 44 45 NA 45 44 NAMF oF PREPARER Dave Wizner 4 7 8 9 FACILITY STATUS~%POWER~BQ23~pg p Qs 7 8 9 10 12 13 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q~Z Q33 Z Q34 NA 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 Q37 MZQ33 NA 7 8 9 11 12 13 PERSONNEL INJURIES 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION g Z Q42 NA 7 8 9 10 PUBLICITY ISSUED DESCRIPTION Q~Ze NA 7 8 9 10 DISCOVERY DESCRIPTION Q32 80 LOCATION OF RELEASE Q 80 80 ((ygg5'.80 80 NRC USE ONLY 80 o 2 68 69 BOP g 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 N I 0 C C ZJOO 0-0 0 0 0 0 0 DQ 1 1 1 1Q~00 , 7 8 9 LICENSEE'ODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T~01 soosos LUQs 0 5 0 0 0 3 1 6 Q 0 6 1 5 7 8 Qs0 6 3 0 7 8 Q 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 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~p4~OS~ps~O7', specificJgravity of 1.197 which is below the 1.200 minimum specific gravity allowed per T.S.4.8.2.3.2a, 2 which constituted an inoperable battery.CD battery was operable.DC loads were shifted to CD battery for a period of 13 minutes while cell 7II35 was jumpered.AB battery was returned to service after being inoperable for 29 minutes.This event had no effect on:publ.ic I health and safety.Reference similar LER No.78-038/03L-O.
~08 80 7 8 9 4 7 8 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 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LF R(RO EVENT YEAR REPORT NO.CODE TYPE NO.Q>>ssso>>[zan++~03 9+w~03~L-0 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDR PRIME COMP.COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER Q15~CQ13~ZQ25~ZQ>>0 0 0 0~NQ23~YQ24 A Q25 5 3 5 5 Qss 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.OTHER STATUS QSO NA NAME OF PREPARER 4 7 8 9 FACILITY STATUS 51 POWER 5~8 Q25~05 0 Q25 7 8 9 10 , 12 13 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q 6~Z Q33~ZQ34 NA 7 8 9 10 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39~00 0 Q31 Z Qss 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION Q41~15~OO O Q45 NA 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION z Q4.NA 8 9 10 PUBLICITY ISSUED DESCRIPTION Q~2O~ZQ4 NA 8 9 10 METHOD OF DISCOVERY~BQ" NA 44 45 46 NA 45 44 DISCOVERY DESCRIPTION Q32 LOCATION OF RELEASE Q 80 80 80 80 80 NRC USE ONLY 80 PHONE 2 68 69 80~45 616 465 5901 3 EXT 4 398 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)[D C C 2 Q o o o 0 0 0 0 0 o Q 4 I I I QE~QE 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE T)[PE 30 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~O4 FOR CONTROL ROD H-8 DID NOT INDICATE THAT H-8 WAS FULLY INSERTED.THE ACTION RE(UIREMENT OF T.S.3.1.1.1 WAS FULFILLED BY EMERGENCY BORATING FOR 5 MINUTES.~O6~O7~OB 80 7'9 SYSTEM CAUSE CAUSE CODE CODE SUBCODE 0 Q UxQ UxQ 9 10 11 12 13 SEQUENTIAL LF RIRP EVENT YEAR REPORT NO.Q17 REPoRT I778J U~04 0 21 22 23 24 ACTION FUTURE EFFECT SHUTDOWN TAKEN ACTION ONPLANT-METHOD HOURS Ql!I Ux Qlg Uz Q20 Uz Q21 0 0 0 33 34'5 36 37 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o NA COMPONENT CODE 7.8 COMP.VALVE.SUBCODE SUBCODE Q14 U[Q15~Z Q16 18 19 20 OCCURRENCE REPORT REVISION CODE TYPE NO.U~M>UL-laJ 27 28 29 30 31 32 Q ATTACHMENT NPRDQ PRIME COMP.COMPONENT 22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER 0 N Q23~Q24 L[LI Q25 I I I 2 0 Q25 40 41 42 43 44 47 3 4 7 8 9 FACILITY~3P METHOD OF STATUS 39 POWER OTHER STATUS~=DISCOVERY 5 UD Q25~OG 0 Q29 NA L[LJ Q31 7*8 9 10 12 13 44 45 46 ACTIVITY CONTENT~RELEASED OF RELEASE AMOUNT OF ACTIVITY~QQQ~Z Q3 Z Q3 NA 7 8 9 10 11 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7~<<0 Q37 2 Q35 NA 7 8 9'1 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION Q[ii~j~00 0 Q49 NA 7 8 9 511 12 LOSS OF OR DAMAGE TO FACILITY Q43~IB~<Q42 NA 7 8 9 10 PUBLICITY ISSUED DESCRIPTION Q o~NQ44 N 7 8 9 10 NAME OF PREPARER JaCk RlsChlln I 80 LOCATION OF RELEASE Q 80 80 80 80 PHONE: 68 69 80 NRC USE ONLY 44 o 80 o 0 DISCOVERY DESCRIPTION Q32 I'RC FORM 366 I7.77),, LICENSEE EVENT REPORT 7 8 CON'T 7 8~O3~O4~OS CONTROL BLOCK: QI 1 6 M I D C C 2 Q2 0 0 0 0 0 0 0 0 0 0 Q34 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 1 1 1 Q4~QE LICENSE TYPE 30 57 CAT 58 S IMILAR NATURE INCLUDE: RO-050/316-78-31,22,08,07'.~,'RO-050/315-78-.07,04.
77-34,33,28,27,76-54,44,13.
"'""'LJQBO 5 0 0 0 3 I 6 Q70 6 0 2 7 8 QB 0 6 3 0 7 8'0 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 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~O6~O7~Os 80 7 8 9 SYSTEM CAUSE CAUSE COMP.VALVE.CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~IE Qll E Q12~ZQ13 I N 5 T R 0 Q4~IQ19~Z QTE 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT LF R IRO EVENT YEAR REPORT NO.CODE TYPE Q11 REPORT[77J~O<I~~~OS 21 22 23 24 26 27 28 29 30 31 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDR PRIME COMP.TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.SUPPLIER~EQTE~Z QEE~Z Q20~Z Q 0 0 0~N Q23 LE)Q24 IJL)QEE 33 34 35 36 37 40 41 42 43 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27~1O INVESTIGATION REVEALED THAT THE SIGNAL CONDITIONING MODULE OUTPUT VOLTAG REVISION+o COMPONENT MANUFACTURER 47 44 AFTER THE ROD'S SECONDARY COIL VOLTAGE WAS MEASURED TO VERIFY THA QE 3 THE CORRECT POSITION, THE SIGNAL CONDITIONING MODULE WAS RECALIBRATED AND PLACED BACK IN SERVICE RETURNING RPI TO WITHIN THE 12 STEP LIMIT 4 NA 7,8 9 FACILITY~3PMf THDD OF STATUS%POWER OTHER STATUS~<<DISCOVERY DISCOVERY DESCRIPTION Q32~lE~E Q29~06 5 Q29 NA~AQ31 OPERATOR OBSERVATION 7 8 9 10 12 13 44 45 46 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY~LOCATION OF RELEASE Q Q33 Z Q34 NA 7 8 9 10 11 44 45 PERSONNEI.
EXPOSURES NUMBER TYPE DESCRIPTION Q39 1~00 0 QET Z Q39 NA 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION 41 9~00 0 Q49 QIIA 80 80 80 80 7 8 7 8 O 9 11 12 LOSS OF OR DAMAGE TO FACILITY Q43 TYPE DESCRIPTION Z Q4, NA.9 10 PUBLICITY ISSUED DESCRIPTION~
LNJQ4" 7 8 9 10 Jack Risch]ing NAME OF PREPARER 80 68 69 616-465-5901 80 NRC USE ONLY 44 O 80 g 0}}

Revision as of 13:30, 31 July 2019

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  American Electric Power icon.png
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

4'REGULATORY DJ.STBj:9UTI ON FOR REC: KEPPLER J G NRC DOCDATE: 06/30/78 DATE RCVD: 07/06/78 I/FORMAT'I'ON'ISTRIBUTION SYSTEM (RIDS')'INCOMING'ATERI'AL

., 50-316'I ORG: SHALLER D V IN 5 MI PWR 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...Wf ATT LERS78-039'8-040 AND 7g 0+<PLANT NAME: COOK-UNIT 2 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:~lt Il<<+<~<<<<<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: INTERNAL: EXTERNAL: BR CHI-LWRN2'C54W/4 ENCL EG..~W/ENCL E+4~W/2 ENCL 8.C SYSTEMS BR4l+W/ENCL NOVAK/CHECK+4FW/

ENCL AD FOR ENG4twM/ENCL HANAUER~~~W/ENCL AD FOR SYS 5 PROJ<<W/ENCL ENGINEERING BR4F4W/ENCL KREGER/J.COLLINSQ+M/ENCL K SEYFRI T/IE~~~~W/ENCL LPDR S ST.JOSEPH'I<<W/ENCL TIC~~~W/ENCL NS I C~~~W/ENCL ACRS CAT B~F+W/16 ENCL NRC PDR<<W/ENCL MIPC<<W/3 ENCL EMERGENCY PLAN BR<<M/ENCL EEB<<I Jf ENCL PLANT SYSTEMS BR<<W/ENCL AD FGR PLANT SYSTEMS+<M/ENCL REACTOR SAFETY BR<<W/ENCL VOLLMER/BUNCH<<W/ENCL POWER SYS BR<<M/ENCL DISTRIBUTION:

LTR 45 S I ZE: 1P+1 P+3P ENCL 45 CONTROL NBR: 781870119<<%0HM 4%%8M<<%9M 4%%%%%0$<<%084%0E%HF0F<<THE FND MASTER ROSTER PUBLICATIONS ISION I----D ISTRIBUT ION CODES 1 LE I------DISTR ABUT ION QTY.Y ST ZIP I----DISTR IBUT ION CODES 18-I-----D I STR.I BUT ION CODES 35-I------DISTR I BUT ION QTY 35-8 17-~17-----I 3~----I RD OF SUPERVISGRS LR IRNOMAN SAN DIEGO CO BD SUP 1'4 DIEGO CA 92101 BRARI AN N D I EGO 1 CA 92101 N DIEGO CA 92101 SN SR SF SE SM SO ST SA SG NB NU 1 1 CL EAR PHARMAC I ST N DIEGO CA 92103 SF SE SM SP ST SO SA SG 1 1 1 1 1 1 1 1 N D IEGO CA 92108 J OLLA CA 9203 7 SN SF SE SM ST SG CH 1 AN DIEGO SN SR SF SE ST SG 1 1 1 1,1 1 CA 92110 AN DIEGO CA 92110 1 1 1 1 1 1 1 li AN DIEGO iM CA 92112 SN SR SF SE SM SP ST SO SA SG CM

~Xi er4oen 7'O'NDIANA

&MICHIGAN POWER COMPANY DONALD C.COOK NUCLEAR PLANT P.O.Box 458, Bridgman, Michigan 49106 June 30, 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 V7 r;j 1~C"3~>cv~7 Kl C/7 c 7 7 f f'7 C"7 Cr~'f'7.4 C iC9 7"7 Cl7 C77 C.M CD CD 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)Dir., MIPC (3 copies)JUL 03 1978 Y.

LP ll U.S.NUCLEAR REGULATORY COMMISSION Qi (PLEASE PRINT OR TYPE ALL REOUIRED INFORMATION) 6 0-0 0 0 0-p 0 Qs 4 1 1 1 1 QE~QE 25 26 LICENSE TYPE 30 57 CAT 58 LICENSE NUMBER NRC FORM 366 (7.77)LICE NT REPORT CONTROL BLOCK: I[os)M I D D C 2 Q2 0 7 8 9 LICENSEE CODE 14 15 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 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 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~O4~OS~OB~O7~OB 7 8 specif ic gravi ty of 1~195 whi ch is below the 1~200 minimum speci f ic gravity allowed per T.S.4.8.2.3.2a, 2, which.-constituted an inoperable battery.AB battery was operable.DC loads were shifted to AB battery for a period of 1 6 mi nutes whi-1 e cell 889 was jumpered.CD battery was returned to service a f ter being inoperable for 80 minutes.This event had no,effect upon public health and safety.80~og i s being developed to attempt to restore the cell.Also, a repl acement cell has SYSTEM CAUSE CAUSE COMP.VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~EC Q>>E Q LAJQ73 8 A.T T R Y 8 LZJQEE L2J Q 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LF R(RO EVENT YEAR REPORT NO.CODE TYPE NO.Q17 REPoRT~78 U L0038 I L~J LLJ UL Q 0 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 HOURS Q22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER LXJQER LCJQ>>LZJQ23 LZJQ>>O O O O~NQ23~YQ24~AQEE E 3 5 5 Q23 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 f i c ravi t could not be determi ned~A rocedure 3 been ordered incase restorati on is not possible.Remaining cel 1 s in CD battery show no similar problems~OTHER STATUS QBO NA METHOD OF DISCOVERY~BQ31 NA 46 44 45 NA 45 44 NAMF oF PREPARER Dave Wizner 4 7 8 9 FACILITY STATUS~%POWER~BQ23~pg p Qs 7 8 9 10 12 13 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q~Z Q33 Z Q34 NA 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 Q37 MZQ33 NA 7 8 9 11 12 13 PERSONNEL INJURIES 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION g Z Q42 NA 7 8 9 10 PUBLICITY ISSUED DESCRIPTION Q~Ze NA 7 8 9 10 DISCOVERY DESCRIPTION Q32 80 LOCATION OF RELEASE Q 80 80 ((ygg5'.80 80 NRC USE ONLY 80 o 2 68 69 BOP g 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 N I 0 C C ZJOO 0-0 0 0 0 0 0 DQ 1 1 1 1Q~00 , 7 8 9 LICENSEE'ODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T~01 soosos LUQs 0 5 0 0 0 3 1 6 Q 0 6 1 5 7 8 Qs0 6 3 0 7 8 Q 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 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~p4~OS~ps~O7', specificJgravity of 1.197 which is below the 1.200 minimum specific gravity allowed per T.S.4.8.2.3.2a, 2 which constituted an inoperable battery.CD battery was operable.DC loads were shifted to CD battery for a period of 13 minutes while cell 7II35 was jumpered.AB battery was returned to service after being inoperable for 29 minutes.This event had no effect on:publ.ic I health and safety.Reference similar LER No.78-038/03L-O.

~08 80 7 8 9 4 7 8 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 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LF R(RO EVENT YEAR REPORT NO.CODE TYPE NO.Q>>ssso>>[zan++~03 9+w~03~L-0 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDR PRIME COMP.COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER Q15~CQ13~ZQ25~ZQ>>0 0 0 0~NQ23~YQ24 A Q25 5 3 5 5 Qss 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.OTHER STATUS QSO NA NAME OF PREPARER 4 7 8 9 FACILITY STATUS 51 POWER 5~8 Q25~05 0 Q25 7 8 9 10 , 12 13 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q 6~Z Q33~ZQ34 NA 7 8 9 10 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39~00 0 Q31 Z Qss 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION Q41~15~OO O Q45 NA 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION z Q4.NA 8 9 10 PUBLICITY ISSUED DESCRIPTION Q~2O~ZQ4 NA 8 9 10 METHOD OF DISCOVERY~BQ" NA 44 45 46 NA 45 44 DISCOVERY DESCRIPTION Q32 LOCATION OF RELEASE Q 80 80 80 80 80 NRC USE ONLY 80 PHONE 2 68 69 80~45 616 465 5901 3 EXT 4 398 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)[D C C 2 Q o o o 0 0 0 0 0 o Q 4 I I I QE~QE 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE T)[PE 30 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~O4 FOR CONTROL ROD H-8 DID NOT INDICATE THAT H-8 WAS FULLY INSERTED.THE ACTION RE(UIREMENT OF T.S.3.1.1.1 WAS FULFILLED BY EMERGENCY BORATING FOR 5 MINUTES.~O6~O7~OB 80 7'9 SYSTEM CAUSE CAUSE CODE CODE SUBCODE 0 Q UxQ UxQ 9 10 11 12 13 SEQUENTIAL LF RIRP EVENT YEAR REPORT NO.Q17 REPoRT I778J U~04 0 21 22 23 24 ACTION FUTURE EFFECT SHUTDOWN TAKEN ACTION ONPLANT-METHOD HOURS Ql!I Ux Qlg Uz Q20 Uz Q21 0 0 0 33 34'5 36 37 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o NA COMPONENT CODE 7.8 COMP.VALVE.SUBCODE SUBCODE Q14 U[Q15~Z Q16 18 19 20 OCCURRENCE REPORT REVISION CODE TYPE NO.U~M>UL-laJ 27 28 29 30 31 32 Q ATTACHMENT NPRDQ PRIME COMP.COMPONENT 22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER 0 N Q23~Q24 L[LI Q25 I I I 2 0 Q25 40 41 42 43 44 47 3 4 7 8 9 FACILITY~3P METHOD OF STATUS 39 POWER OTHER STATUS~=DISCOVERY 5 UD Q25~OG 0 Q29 NA L[LJ Q31 7*8 9 10 12 13 44 45 46 ACTIVITY CONTENT~RELEASED OF RELEASE AMOUNT OF ACTIVITY~QQQ~Z Q3 Z Q3 NA 7 8 9 10 11 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7~<<0 Q37 2 Q35 NA 7 8 9'1 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION Q[ii~j~00 0 Q49 NA 7 8 9 511 12 LOSS OF OR DAMAGE TO FACILITY Q43~IB~<Q42 NA 7 8 9 10 PUBLICITY ISSUED DESCRIPTION Q o~NQ44 N 7 8 9 10 NAME OF PREPARER JaCk RlsChlln I 80 LOCATION OF RELEASE Q 80 80 80 80 PHONE: 68 69 80 NRC USE ONLY 44 o 80 o 0 DISCOVERY DESCRIPTION Q32 I'RC FORM 366 I7.77),, LICENSEE EVENT REPORT 7 8 CON'T 7 8~O3~O4~OS CONTROL BLOCK: QI 1 6 M I D C C 2 Q2 0 0 0 0 0 0 0 0 0 0 Q34 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 1 1 1 Q4~QE LICENSE TYPE 30 57 CAT 58 S IMILAR NATURE INCLUDE: RO-050/316-78-31,22,08,07'.~,'RO-050/315-78-.07,04.

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

"'""'LJQBO 5 0 0 0 3 I 6 Q70 6 0 2 7 8 QB 0 6 3 0 7 8'0 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 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~O6~O7~Os 80 7 8 9 SYSTEM CAUSE CAUSE COMP.VALVE.CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~IE Qll E Q12~ZQ13 I N 5 T R 0 Q4~IQ19~Z QTE 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT LF R IRO EVENT YEAR REPORT NO.CODE TYPE Q11 REPORT[77J~O<I~~~OS 21 22 23 24 26 27 28 29 30 31 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDR PRIME COMP.TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.SUPPLIER~EQTE~Z QEE~Z Q20~Z Q 0 0 0~N Q23 LE)Q24 IJL)QEE 33 34 35 36 37 40 41 42 43 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27~1O INVESTIGATION REVEALED THAT THE SIGNAL CONDITIONING MODULE OUTPUT VOLTAG REVISION+o COMPONENT MANUFACTURER 47 44 AFTER THE ROD'S SECONDARY COIL VOLTAGE WAS MEASURED TO VERIFY THA QE 3 THE CORRECT POSITION, THE SIGNAL CONDITIONING MODULE WAS RECALIBRATED AND PLACED BACK IN SERVICE RETURNING RPI TO WITHIN THE 12 STEP LIMIT 4 NA 7,8 9 FACILITY~3PMf THDD OF STATUS%POWER OTHER STATUS~<<DISCOVERY DISCOVERY DESCRIPTION Q32~lE~E Q29~06 5 Q29 NA~AQ31 OPERATOR OBSERVATION 7 8 9 10 12 13 44 45 46 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY~LOCATION OF RELEASE Q Q33 Z Q34 NA 7 8 9 10 11 44 45 PERSONNEI.

EXPOSURES NUMBER TYPE DESCRIPTION Q39 1~00 0 QET Z Q39 NA 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION 41 9~00 0 Q49 QIIA 80 80 80 80 7 8 7 8 O 9 11 12 LOSS OF OR DAMAGE TO FACILITY Q43 TYPE DESCRIPTION Z Q4, NA.9 10 PUBLICITY ISSUED DESCRIPTION~

LNJQ4" 7 8 9 10 Jack Risch]ing NAME OF PREPARER 80 68 69 616-465-5901 80 NRC USE ONLY 44 O 80 g 0