05000316/LER-1981-013-03, /03L-0:on 810428,all Charging Pumps Were Removed from Svc Contrary to Tech Spec Requirements.Caused by Leak on East Pump Discharge Isolation Valve CS-300E.Valve Repacked.Drain Valve CS-349 Also Repacked

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/03L-0:on 810428,all Charging Pumps Were Removed from Svc Contrary to Tech Spec Requirements.Caused by Leak on East Pump Discharge Isolation Valve CS-300E.Valve Repacked.Drain Valve CS-349 Also Repacked
ML17319A846
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 05/05/1981
From: Wizner D
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17319A839 List:
References
LER-81-013-03L, LER-81-13-3L, NUDOCS 8105120378
Download: ML17319A846 (9)
v • d • e


LER-1981-013, /03L-0:on 810428,all Charging Pumps Were Removed from Svc Contrary to Tech Spec Requirements.Caused by Leak on East Pump Discharge Isolation Valve CS-300E.Valve Repacked.Drain Valve CS-349 Also Repacked
Event date:
Report date:
3161981013R03 - NRC Website
v • d • e

text

REGULATO INFORMATION DISTRIBUTION STEM (RIDS)

SUB JECT:

LER 81 013/03L-0: on 810428'l 1

char ging pumps were. removed from svc contrary to Tech Spec requirements. Caused by leak.

on east pump discharge isolation valve CS~300 ED Yalve repackediDrain valve Cs 349 also

repacked, DISTRIBUTION CODE:

A002S COPIES RECEIVED:LTR J "ENCL T-ITLE!; Inc i dent Repor t s SIZEe

~

ACCESSION NBR: 8105120378 DOC ~ DATE: 81/05/05 NOTARIZED:

NO DOCKET' FACIL':50 3ib Donald C',

Cook Nuclear Power Plantr Unit 2~ Indiana 8

05000316 AUTH BYNAME AUTHOR AFF'Il IATION WIZNERgD.G ~

Indiana 8 Michigan Electric Co ~

REC IP ~ NAME~

RECIPIENT AFFILIATION Region 3<Chicago~

Office, of the Director NOTEStSend 3 copies of al 1 mater ial to I8,E ~

05000316 EXTERNAL: ACRS NSIC 46 05 RECIPIENT IO CODE/NAME~

ACTION; VARGArS ~

04 INTERNAL: A/D COMPLSTRU06 A/0>> NATL 8

QU08 A/0 PLANT SYS10 A/0 SFTY ASSE12 AEOD ASLBP/J ~ HARD CHEN KNG BR 16 CORE PERF BR 18 DIR g HUM FAC S21 EFf'R SYS BR23 GEOSCIENCES 26

I86, 05 LI C GUID BR 30 MECH ENG BR 33.

OR ASSESS BR 35'AD ASSESS BR39 REG F ILE 01 SFTY PROG KYA42:

COPIES LTTR ENCL 3

1 1

1 1

1 1

1 3

3 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

16 1

1 RECIPIENT ID CODE/NAME A/D ENV TECH 07 A/D OP REACT009 A/D RAD PROT 11 ACC EVAL BR 14 AEOD/DMU

'UX SYS BR 15 CONT SYS BR 17 DIRg ENGINEERI20 DIRzSYS INTEG22 EQUIP QUAL BR25 I8C SYS BR 29 JORDANgE ~ /IE MATL ENG BR 32 NRC PDR 02 POKER SYS'R 36 REACT SYS BR 40 REL 8

RISK A 41 STRUCT ENG BR44 LPDR 03 COPIES LTTR-KNCL 1

1 1

1 1

1 1

3 3

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1-=

1 1

1 1

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TOTAL NUMBER OF COPIES REQUIRED:

LTTR ENCL

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1 1

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ar-aalaan

+laatrla

~owar yste INDIANA& MICHIGANElECTRIC CDMPANY DONALDC. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 (616) 4654901 May 5, 1981 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 Operating License DPR-74 Docket No. 50-316

Dear Mr. Keppler:

Pursuant to the requirements of the Appendix A Technical Specifications, the following report/s are submitted:

RO 81-010/03L-0 RO 81-011/03L-0 RO 81-012/03L-0 RO 81-013/03L-O.

Sincerely, D.V. Shaller Plant Manager

/bab cc:

J.E.

Dolan R.S. Hunter R.W. Jurgensen R.F. Kroeger R.W. Kilburn E.

Swanson/N.

DuBry RO:III R.C. Callen MPSC G. Charnoff, Esq.

J.M. Hennigan W. Lavallee EPRI PNSRC J.F. Stietzel E.L. Townley Dir., IE (30 copies)

Dir., MIPC (3 copies)

MAy 7 ~98'

gl ll

~

c

NRC FORM 866 (7.77)

U. S. NUCLEAR REGULATORY COMMISSION LlCENSEE EVENT REPORT

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8 CON'T

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I M

I D

C C

2 Q20 0

9 LICENSEE CODE 14 15

,Q (PLEASE PRINT OR TYPE ALI.REQUIRED INFORMATION) 0 0

0 0

0

0 0Q34 1

1 1 1Q4~pg LICENSE NUMBER 25 26 I ICENSE TYPE 30 57 CAT 58 soURGE MLQB 0

5 0

0 0

3 1

6 Q7 0

4 1

1 8

1 QB 0

5 0

5 8

1 OB 60 61 DOCKET NUMBER 68 69 EVENT DATE 74

'75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABL.E CONSEQUENCES Q10 DURING SURVEILLANCE INSPECTION OF INACCESSIBLE HYDRAULIC SNUBBERS PER T.S. 4.7.7.1A,

~03 SNUBBERS IIO.

1 AND iNO.

29 WfRE FOUND INOPERABLE.

SNUBBER NO.

29 HAD A FLUID LEAK AT

~o4 THE CYLIiNDER END CAP.

SNUBBER NO.

1 WAS FOUND UPSIDE DOWN.

SNUBBER NO.'1 WAS ALSO

~os SCHEDULED FOR FUNCTIONAL TEST PER T.S. 4.7.7.1C AND FAILED THE TEST.

11 SNUBBERS IN

~OB ADDITION TO THE INITIALll WERE TESTED AS RE UIRED WITH NO FAILURES.

PUBLIC HEALTH AND

~O7 SAFETY WERE NOT AFFECTED.

SIMILAR OCCURRENCES INCLUDE:

RO 78-086 03L-0 AND FOR DOCKET'OB NO. 050-0315:

RO 79-019/03L-0 AND'O 78-029 03L-O.

7 8

9 80 SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~OB

~ZZ Qis E

Qn

~BQ>3 3

0 P

0 R

T Q>4

~OQI6

~Z Q6 7

8 9

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

CODE TYPE NO.

Qi7>>eo>>

~81

~

~ol 0

~w

~03

~L

+

~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 O22 SUBMITTED FORM SUB.

SUPPLIER MANUFACTURER

~AQ18 ~ZQ19

~ZQ2o

~2Q2' 0

N Q23

~YQ24

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I 2

0 Q>>

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

THE LEAK OiV SNUBBER NO.

29 WAS DUE TO SEPARATION OF A GLUED JOINT OF THE EiND SEAL 0-.

RINGs GRINNELL NO.

150ES007250400.

THE 0-RING HAS BEEN REPLACED WITH A MOLDED 0-RING WITHOUT A GLUED JOINT.

THE EXTENSION ROD LOCKNUT ON SNUBBER NO.

1 HAD LOOSENED, ALLOW-3 ING THE SNUBBER TO FLIP OVER.

THE LOCKNUT WAS TIGHTENED AND STAKED.

BOTH SNUBBERS WERE 4

RETESTED.

INSPECTION FREQUENCY CHANGED TO ONCE PER 6 MONTHS PER T.S.

TABLE 4.7-9.

DISCOVERY DESCRIPTION Q32 8

MONTH INSPECTION LOCATIONOF RELEASE 45 NRC USE ONLY 68 69 616-465-5901 NAME OF PREPARER DAVID G.

WIZNER 7

8 9

FACILITY

~3O METHOD OF STATUS

% POWER OTHER STATUS Q DISCOVERY

~15

~H Q28 ~00 0

Qzs NA LBJQ>>

1 7

8 9

10 12 13 44 45

'6 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITYQ36

~Z Q33 Z

Q34 NA NA 7

8 9

10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 o oQ>>zp>>

7 8

9 11 12 13 PERSONNEL INJURIES pIg IZEDJaJQ LOSS OF OR DAMAGETO FACILITY 43 TYPE

DESCRIPTION

~e Z

P~~

NA 7

8 9

10 PUBLICITY ISSUED DESCRIPTIONQ

~2O L~JQ44 NA 8

9 10 80 80 80 80 80 80

'O l4 r

80 ~ o 0

AS

NRC FORM 366

{777)

LlCENSEE EVENT REPORT U. S. NUCLEAR REGULATORYCOMMISSION

~O 7

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9 LICENSEE CODE Q1

{PLEASE PRINT OR TYPE ALLREQUIRED INFORMATION) 6 2Q2 0

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QE 25 26 LICENSE TYPE 30 57 CAT 58 REPDRT ~LQB 0

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5 8 i Q'0 61 DOCKETNUMBER 68 69 EVENT DATE 74 75 REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 DURING A REFUELING OUTAGE, SURVEILLANCE TEST DATA REVEALED THAT STEAM LINE PRESSURE

~Os 4

TRANSMITTER (MPP-21'0)

AS FOUND DATA WAS AT A VALUE WHICH EXCEEDS THE LCO VALUE FOR DIFFERENTIAL PRESSURE BETWEEN STEAM LINES, T.S.

TABLE 3. 3-4 ITEM I. E.

THE DIFFEREN-TIAL PRESSURE ALARM WOULD HAVE ACTUATED AT 114.6 PSI.

PREVIOUS OCCURRENCES OF A

~OB SIMILAR NATURE INCLUDE:

050-316/80-20.

~O7

~OB 80 7

8 R

[OO~]

7 8

SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~SQ11 E

Q12

~EQ73 I

N S

T R

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~TQ18

~Z Q1' 10 11 12 13 18 19 20 SEOUENTIAL OCCURRENCE REPORT REVISION LER)RO EVENT YEAR REPORT NO.

CODE TYPE NO.

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~81

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THE TRANSMITTER (FOXBOR09 EllGM HSAEl)

WAS RECALIBRATED TO WITHIN ALLOWABLE VALUES THE CAUSE OF THIS EVENT IS CONSIDERED TO BE INSTRUMENT DRIFT.

7 8

9 FACILITY STATUS

'4 POWER OTHER STATUS Q H

s 0

0 0

29 NA 45 NRC USE ONL'Y METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32

~BPE, SURVEILLANCE TEST 7

8 9

10 12 13 44 45 46 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITYQ LOCATIONOF RELEASE 8

~Z Q33

~ZQ34 NA NA 7

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10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION QSB

~77 ~00 0

Q37 ~ZQ38 NA 7

8 9

11 12 13 PERSONNEL INJURIES 7

8 9

11 12 LOSS OF OR DAMAGETO FACILITY 43 TYPE

DESCRIPTION

~79 Z

Q42 NA 8

9 10 PUBLICITY ISSUED

DESCRIPTION

KK iree

'. NA 7

8 9

10 68 69 J.

L. Rischling 616-465-.5901 NAME OF PREPARER PHONE:

80 80 80 80 80 80 EEa 80 a

0L0

NRC FORM 866 (7 77)

I4.

S. NUCLEAR REGULATORY COMMISSION l

LICENSE E EVENT R EPORT

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{PLEASE PRINT OR TYPE ALLREQUIRED INFORMATION)

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60 61 DOCKET NUMBER 68 69 EVENT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 DURING SURV.-"'IISP.".::PER T 'S'4.,6,;5..9; CRACKS WERE IDENTIFIED..IN DIVIDER. BARRIER SEAL.

THE CRACKS DID NOT PENETRATE THE SEAL AND THE SEAL INTEGRITY REMAINED 'NTACT.

THE 4

EVENT DID NOT AFFECT'UBLIC HEALTH AND SAFETY ~

SIMILAR EVENTS WERE REPORTED AS RO 79-6 043/03X-1 AND FOR DOCKET 05000315, 80-014/03L-0 AND 79-029/03L-O.

~06

~07

~OB 7

8 9

80 7

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Q4

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

CODE TYPE NO.

QTT REPoRT

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~

~OI 2

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~03

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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 LaJQIB LZJQ19

~Q20 L>JQ" 0

0 0

~NQ23

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0 6

6 Q26 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 o

THE DEFECTIVE PORTIONS OF THE SEAL APPROX.

35 LINEAR FEET WERE REPLACED.

THE SPECIF-IC CAUSE FOR THE CRACKS COULD NOT BE DETERMINED.

HOWEVER, DUE TO THE NUMBER OF PREVI-OUS FAILURES, THE UNIROYAL 3807 MATERIAL WAS REPLACED WITH UNIROYAL 41300 MATERIAL IN THE AREAS WHICH HAD CRACKS.

4 7

8 9

FACILITY STATUS BE POWER 4

IJLIQEE

~ilLLJLJQEE 7

8 9

10 12 13 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITYQ Z

Q33 Z Q34 NA 7

8 9

10 PERSONNEL EXPOSURES NUMBER TYPE

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~00 0

QET 2

Qss NA 7

8 9

11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 EKE ~00 0

Q4o NA 7

8 9

11 12 LOSS OF OR DAMAGETO FACILITY 43 TYPE

DESCRIPTION

9 Z

Q2 NA 8

9 10 PUBLICITY ISSUED DESCRIPTION~

KZ QQQ44 7

8 9

10 80 80 LOCATIONOF RELEASE Q NA 45 44 80 80 80 80 NRC USE ONLY 80 ~ o 0

68 69 PHONE.

616-465-5901 NAIvIE OF PREPARER DAVID G.

WIZNER METHOD OF OTHERSTATUS ~

DISCOVERY DISCOVERY DESCRIPTION Q32

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SURVEILLANCE INSPECTION 44 45 46

NRC RORMB66 17-77)

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68 69 EVENT DATE 74

'75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 WHILE IN MODE 5 ALL CHARGING PUMPS WERE REMOVED FROM SERVICE IN ORDER TO REPACK THE

~o3 EAST PUMP DISCHARGE ISOL.

VALVE TO THE SEAL INJECTION FILTERS.

NO CHARGING PUMPS WERE

~o4

OPERABLE, GONTRARY TO REQUIREMENTS OF T.S. 3.1.2.3.

THE ACTION REQUIREMENTS WERE MET.

~O6 PUBLIC HEALTH AND SAFETY WERE NOT AFFECTED.

THIS WAS THE FIRST OCCURENCE OF THIS TYPE.

~OB

~OB 7

8 9

80 7

8 SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~PC Qil E

Q1s

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V A

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Q4

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~81

+

~<>

3 QH

~03

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0 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDX PRIME COMP.

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

SUPPLIER MANUFACTURER

~DQis ~Z Qls

~ZPss

~ZPs 0

0 0

0 N

Qss

~N Qg4

~N Qss V

0 B

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

VALVE CS-300E HAD A PACKING LEAK AND THERE WAS NO MORE ADJUSTMENT OF THE PACKING GLAND 1

REMAINING.

CS-300E WAS REPACKED.

ALSO THE EAST CHARGING PUMP DRAIN VALVE CS-349 WAS REPACKED.

THE PUMPS WERE THEN RETURNED TO SERVICE; 3

4 7

8 9

FACILITY STATUS BG POWER OTHER STATUS QBO

~ls H

Pss ~00 0

Qss NA 7

8 9

10 12 13 44 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITY

~Z Q33

~ZQ34 NA 7

8 9

10 11 44 PERSONNEL EXPOSURES NUMBER TYPE

DESCRIPTION

7 ~00 0 Qs'pss NA 7

8 9

11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 LOOOOJQ4s NA 7

8 9

11 12 LOSS OF OR DAMAGETO FACILITY 43 TYPE

DESCRIPTION

B Z

Q42 NA 7

8 9

10 PUBLICITY ISSUED DESCRIPTION~

~2O

~Q44 8

9 10 OF PREPARER DAVID G

~

WIZNER METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32

~APsi OBSERVATION OF PACKING LEAK 45 46 LOCATIONOF RELEASE 36 NA 45 NRC USE ONLY 68 69 PP NE 616 465 5901 80 80 80 80 80 80 C!

ssa 80' 0

0.

LS

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