ML18219B572

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Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-034/03L-1, RO 78-044/03L-0, RO 78-045/03L-0, RO 78-046/03L-0)
ML18219B572
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 07/11/1978
From: Shaller D
American Electrtic Power System, Indiana Michigan Power Co
To: James Keppler
NRC/RGN-III
References
LER 1978-034-03L, LER 1978-044-03L, LER 1978-045-03L, LER 1978-046-03L
Download: ML18219B572 (12)


Text

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REGULATORY INFORMATION DISTRIBUTION SYSTEM < RIDS)

DISTRIBUTION FOR INCOMING 'MATERIAL 50-316 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 07/11/78 NRC lN 5 Ml PWR DATE RCVD: 07/14/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-316/78-034) ON 05/15/78 CONCERNING DURING SURVEILLANCE TESTS ON 05/15/78 8. 06/20/78) THE HYDROGEN SKIMMER RECIRCULATION FANS (2HV-CEQi 8( 2-HV-CEQ2) FAILED TO START WITHIN TECH SPEC REQUIREMENT 4. 6. 5. 6. A... W/ATT LER 7Q -Q9"f ] '7B" ~V+ >

+ 7

>~k'LANT NAME: COOK UNIT 2 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:

++++~>+++++++4+4l+> DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS +4>+>>~+>>>>+>>>+>

NOTES:

1. SEND 3 COPIES OF ALL MATERIAL TO lhE ED REEVES-1 CY ALL MATERIAL INCIDENT REPORTS (DISTRIBUTION CODE A002)

FOR ACTION: BR CHIE W ¹2 BC+4W/4 ENCL INTERNAL: R G FILE+4W/E NRC PDR++W/ENCL I 5 E~~ ENCL, MIPC~~W/3 ENCL I 8( C SYSTEMS BR+%W/ENCL EMERGENCY PLAN BR++W/ENCL NOVAK/CHECK~+W/ENCL EEB++W/ENCL AD FOR ENG~~~~W/ ENCL PLANT SYSTEMS BR<<W/ENCL HANAUER++W/ENCL AD FOR PLANT SYSTEMS+>W/ENCL AD FOR SYS 8( PROJ+4W/ENCL REACTOR SAFETY BR<+W/ENCL ENGINEERING BR++W/ENCL VOLLMER/BUNCH++M/ENCL KREGER/J. COLLINS<~W/ENCL POWER SYS BRwmW/ENCL K SEYFRIT/IE++W/ENCL EXTERNAL: LPDR'8 ST. JOSEPH' I +4 WfENCL

'ERA>+W/ENCL NSIC~~W/ENCL ACRS CAT B++W/16,ENCL DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 7819500 4 SIZE: 1P+1P+3P

',%%%0f%%%%%%%%%%%%4 SH8%%%%%%%%%%%%%%%% THE END

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y>ccI IND/ANA & NICHIGAN PD %EH COMP N Y C7 DONALD C. COOK NUCLEAR PLANT C+

r'a P.O. Box 458, Bridgman, Michigan 49106 t C.> "!

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%CD July 11, 1978 >~a rC-C CD CA CO C/)CD D Pl C".. X Mr. J.G. Keppler, Regional Director C/l CD Office of Inspection and Enforcement United States Nuclear Regulatory Commission 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 78-034/03L-1 RO 78-044/03L-0 RO 78-045/03L-0 RO 78-046/03L-0 Sincerely, D.V. Shaller Plant Manager

/bab CC: J.E. Dolan R.W. Jur gensen 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.

PNSRC J.F. Stietzel JUP ].g 1978 R.S. Keith Dir., IE (30 copies)

Dir., MIPC (3 copies)

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( NRC FOR0/I 366

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(7') "UPDAT~EPORT - PREVIOUS REPORT DATE LICENSE E EV EN T R E PORT 6/ I CONTROL BLOCK:

1 ,Q (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

~oi 7 8 9 M I D I.ICENSEE CODE C C 2 14 2

15 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 0 25 Q 3 26 4 1 1 LICENSE TYPE 1 1 30 Q4~QE 57 CAT 58 CON'T

~O REPoRT

~LQ6 P 5 P P P 3 1 6 Q7 0 5 1 5 7 8 QB 0 / I I / 8 Q 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES +10 DURING SURVEILLANCE TESTS ON 5-15-78 END 6-20-78, THE HYDROGEN SKIMMER RECIRCULATION

~O3 FANS (2HV-CEQl and 2-HV-CEQ2) FAILED TO START WITHIN THE TIME LIMIT SPECIFIED BY T.S.

SURVEILLANCE REQUIREMENT 4.6.5.6.a. IN BOTH CASES THE AGASTAT TIMERS WERE RESET TO

~O6 WITHIN SPECIFICATIONS. PREVIOUS OCCURRENCES OF A SIMILAR NATURE INCLUDE: RO-050-315/75

~O6 -'.15.

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

CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~SC Q>> ~Q\2 ~Z Q13 R 2 L A Y S Q14 ~NQ1s ~Z Q16 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION Q11 LER]RO REPQRT ACTION FUTURE EVfNT YEAR

~S8 21 22 EFFECT Q

23 SHUTDOWN

~03 24 REPORT N Q.

4 26 Q~

27

~03 28 ATTACHMENT CODE 29 NPRDP TYPE QL 30 g

PRIME COMP.

31 NO.

Ql 32 COMPONENT.

TAKEN ACTION

~2Q15 ~Z 33 34 Qls ON PLANT "

~Z 35 Q20 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 METHOD

~Z 36 Q21 37 0

HOURS Q22 0 0 0 40

~

SUBMITTED 41 Q23 FORM SUB.

LJLIQ24 42 SUPPLIER

~A 43 Q25 44 MANUFACTURER A 1 0 9 47 Q26 o NA 3

~14 7 8 9 80, FACILITY STATUS 91 POWER OTHER STATUS Q METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32 EIH 7 8.9 E Q26 ~~Q29 10 12 13 44 MQ31 45 46 80

~16 ACTIVITY

~Z Q33 CONTENT RELEASED OF RELEASE Z Q34 AMOUNT OF ACTIVITY NA

~ NA LOCATION OF RELEASE Q 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

~00 0 Z NA 7

7 8 9 11 Q37 PERSONNEL INJURIES 12 QEs 13 "

Iyqh 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 Z Q4. NA 7 8 9 10 80 PUBLICITY NRC USE ONLY o

7 8 9 10 68 69 80 o 0

NAME OF PREPARER PH NE, 61 6 465 5901

L' l

NRC FORM 366 S. NUCLEAR REGULATORY,COMMISSION (7'7PJ LICENSEE EVENT REPORT CONTROL BLOCK:

I 6 Q (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

~01 7 8 9 N I D C LICENSEE CODE C 2 14 Q2'0 15 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 OQE 25 26 4 1 1 LICENSE TYPE 1 1QR~QE 30 57 CAT 58

'1 CON'T

~01 ~LQB 0 5 0 0 0 3 1 6 Q70 6 1 8 7 8QBO 7 1 I 7 8 QB 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 DURING NORMAL OPERATION PRESSURI'ZER LEVEL CHANNEL III NL - 53 1

MODEL 8764) WAS DECLARED INOPERABLE DUE TO EXCESSIVELY HIGHER INDICATION THAN THE

~O4 OTHER TWO CHANNELS. THE APPLICABLE ACTION RE UIREMENTS OF T.S. TABLE 3.3-1 ITEM ll

~OS AND T.S. TABLE 3.3-3 ITEN 18d MERE FULFILLED. PREVIOUS OCCURRENCES OF A SIMILAR

~os NATURE INCLUDE: RO 05 316-78-6 050 315-78-10 77-41 76-41 40 75-76.

~OB 80 7 8 9 3 SYSTEM CAUSE CAUSE COMP. VALVE.

CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 8

~IA 9 10 Q11 ~X 11 Q72 ~2 12 Q73 13 I N S T R U 18 PR ~T 19 Q78 ~2 20 Q18 SEQUENTIAL OCCURRENCE REPORT REVISION Q17 LERIRO REPQRT ACTION FUTURE EVENT YEAR

~78 21 22 EFFECT

+

23 SHUTDOWN

~04 24 REPORT NO.

4 26 QZ 27

~03 28 ATTACHMENT CODE 29 NPRDR TYPE QL 30

~

PRIME COMP.

Q 31 32 NO.

[JO COMPONENT TAKEN ACTION ON PLANT ~

METHOD HOURS +22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~BQ78 ~2 Q78 ~2 QEP ~2 Q27 0 0 0 0 ~N Q23 ~YQ24 ~L QEE B 0 0 0 Q28 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 8 INVESTIGATION REVEALED THAT A LEAK HAD DEVELOPED AT A PLUGGED TEE FITTING IN THE REFERENCE LEG. THE LEAK WAS REPAIRED AND THE REFERENCE LEG WAS REFIL E .

P AFFECTED CHANNEL WAS RETURNED TO OPERATION WITH INDICATION WITHIN 3'5 OF THE OTHER TWO CHANNELS.

9 80

~

7 8 FACILITY 3P METHOD OF

, STATUS BG POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Q32 8 F Q28 ~04 0 Q28 NA ~AQ37 OPERATOR OBSERVATION 7 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT 6

RELEASED OF RELEASE Z

AMOUN1'F ACTIVITY NA NA LOCATION OF RELEASE Q

~Z Q33 Q34 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

~00 0QZ Q38 NA 80 7 8 9 11 12 13 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY ~43 TYPE DESCRIPTION Z Q42 NA 7 8 9 10 80 O N PUBLICITY ISSUED Q44 DESCRIPTION ~ NA NRC USE ONLY O

7 8 9 10 68 69 80 ER Jack Rischling 616-465-5901 0

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NRC FORM 366 (7.77)

LICENSEE EVENT REPORT U. S. NUCLEAR REGULATORY COMMISSION CONTROL BLOCK: Ol (PLEASE PRINT OR TYPE ALI. REQUIRED INFORMATION)

I 6

~p M I D C C 2 14 QO IS 0 0 0 0 0'0 LICENSE NUMBER 0 0 0 OQ3 25 26 4 1 1 LICENSE TYPE 1 1Q ~Qs 30 57 CAT 7 8 9 LICENSEE CODE CON'T

~01 ~LQ6 0 5 0 0 0 3 1 6 Q70 6 1 2 7 8 Qs 0 7 I I 7 8 Qe 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Qlp DURING NORMAL OPERATION, FOLLOWING AN ADDITION OF BORIC ACID TO THE BORATED WATER

~o3 SYSTEMIS. "THE BORON INJECTION TANK BORON CONCENTRATION WAS FOUND TO BE 19,780 PPM.

~o4 THIS WAS BELOW THE 20,000 PPM LIMIT OF T. S. 3.5.4.1. THE ASSOCIATED BORIC ACID

~os STORAGE TANK SOLUTION WAS FOUND TO CONTAIN 18,705 PPM BORON, WHICH IS BELOW THE LIMIT

~o6 SPECIFIED BY T.S. 3.1.2.8. THE ACTION REQUIREMENTS OF BOTH T.S. WERE FULFILLED.

~os 80 7 8 9

'3 SYSTEM CAUSE CAUSE COMP. VALVE.

CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~oe ~SF Q11 A Q12 ~X Q13 Z Z Z Z Z Z Q14 ~Z Q13 ~Z 20 Q13 7 8 9 10 12 18 19 SEQUENTIAL OCCURRENCE REPORT REVISION Q11 LERIRO REPoRT ACTION FUTURE EVENT YEAR

~78 21

~

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~

23 SHUTDOWN

~0~

24 REPORT NO.

8 26

~~

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~03 28 CODE 29 NPRDQ TYPE

~L 30 PRIME COMP.

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31 NO.

32 0

COMPONENT TAKEN ACTION ON PLANT 4 METHOD HOIJRS Q22 SUBMITTED FORM SUB. SUPPLIEII MANUFACTURER

~NQPE ~ZQER ~ZQER ~ZQ>> 0 0 0 0 ~NQEE ~NQ34 ~ZQEE Z 9 9 9 Qss 33 34 35 36 37 40 41 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 INVESTIGATION REVEALED THAT A CHEMICAL TECHNICIAN HAD THE BORIC ACID EVAPORATOR p

BOTTOMS PUMPED TO THE SOUTH BORIC ACID STORAGE TANKS(S-BAST) WITH A LOWER THAN DESIRED BORIC ACID CONCENTRATION. THE S-BAST IS RECIRCULATED THROUGH THE BORON 3 INJECTION TANK, CAUSING ITRJAS LOW BORIC ACI D CONCENTRATION ~

7,8 9 80 FACILITY

~

~3P METHOD OF

'7 8 9

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STATUS Q26 10 99POWER

$ ~9~Q2e 12 13 OTHERSTATUS NA 44 DISCOVERY

'BQ31 45 46 ROUTINE SAMPLES DISCOVERY DESCRIPTION 80 EK izJO33 ACTIVITY RELEASED OF RELEASE CONTENT z Q34 AMOUNTQF ACTIVITY ~ NA LOCATION OF RELEASE 036 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

~lT ~00 0 QET Z Q33 NA 7 8 9 11 12 13 80 PERSONNEI. INJURIES NUMBER DESCRIPTIONO41

[<i~] ~00 0 Qs NA 80 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 z Q42 NA 7 8 9 10 P 80 O

ISSUED L~JQ44 I

PUB L CITY DESCRIPTION ~ NA NRC USE ONLY ES Es 7 8 9 10 68, 69 80 TR 0

NAME OF PREPARER Jack Rischling PHDNE 6 1 6 465 590 1 L 49

t NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION 4

LICENSEE EVENT REPORT CONTROL BLOCK: QI (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6

~O 7 8 9 P

LICENSEE CODE P C 302 14 15 P P P P P LICENSE NUMBER P P, P.P 034 25 26

$ I LICENSE TYPE

$ 3 30 04~03 57 CAT 58 CON'T

~O 7 8 soU'"cE~LQB 60 61 0 5 0 0 0 DOCKET NUMBER 3 1 6Q7 68 69 0 6 1 EVENT DATE 7 7 8QB 74 75 0 7 1 REPORT DATE 1

80 Q

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 DURING NORMAL OPERATIONS, A WELD LEAK WAS DISCOVERED ON THE

~O3 ESSENTIAL SERVICE WATER OUTLET ON 2AB DIESEL LUBE OIL COOLER

~O4 HEAD. TO ACCOMPLISH REPAIRS, IT WAS NECESSARY TO TAKE 2AB

~OB DIESEL GENERATOR OUT OF SERVICE. ALTHOUGH THE COMPANION DIESEL,

~OB 2CD, WAS OPERABLE DURING 2AB REPAIRS, THE UNIT WAS IN A DEGRADED

~O7 MODE AS DELINEATED IN TECH. SPEC. SECTION 3.8.1.1.

~OS 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VAI.VE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~EE Q11 5 Q12 ~C Q13 H T E X C H Q14 ~C QEs ~Z QER 7 8 9 10 11 12 1, 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION Q17 LE RIB REPoRT ACTION FUTURE O

~7" EVENT YEAR 21 22 EFFECT

~

23 SHUTDOWN

~04 24 REPORT NO.

6 26

~~

27

~03 28 ATI'ACHMENT CODE 29 NPRDP TYPE

~L, 30

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PRIME COMP.

31

~0 32 NO.

COMPONENT TAKEN ACTION ON PLANT METHOD HOURS +22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~AQER ~ZQ13 33 34

~Z020 35

~Z027 36 37 0 0 0 11 H Q23 ~Y024 ~AQ25 W 3 I 5 QER 40 41 42 -

43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o THE CAUSE OF THE CRACK WAS MISALIGNMENT STRESS BETWEEN THE COOLER HEAD AND CONNECTING PIPING. A NEW PIPING SPOOL PIECE WAS FABRI-CATED TO ELIMINATE THE MISALIGNMENT. THE FOUR INCH CRACK IN THE 3

COOLER HEAD COULD NOT BE REPAIRED, THEREFORE, THE COOLER HEAD WAS REPLACED.

4 7 8 9 80 FACILITY STATLIS POWE R OTHER STATUS Q METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32 0 LLLJQ 55 CZI 7

6 8 9 B 2B 10 0 6 0 12 2e 13 NA 44

~A 45 Q31 46 ROUTINE INSPECTION 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITYQ36 LOCATION OF RELEASE Q36 6 ~Z Q33 Z Q34 NA NA 7 8 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 037 MZ033 HA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 7

s 8

~00 9

0 Qo 12 NA 11 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 Z Q4. NA 7 8 9 10 80 o

ISSUED uNQ44 PUBLICITY DESCRIPTION ~ NA NRC USF ONLY 7

7 8 9 10 68 69 80 o NAMEOF PRFPARER C AEL S. BRO N 616-465-5901, EXT.