ML18219C201

LER 1978-025-03L Re Hydraulic Fluid Leakage from Snubber No. 90

ML18219C201
Person / Time
Site:	Cook
Issue date:	04/26/1978
From:	Shaller D Indiana Michigan Power Co
To:	James Keppler NRC/RGN-III
References
LER 1978-025-03L
Download: ML18219C201 (8)

Text

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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-315 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 04/26/78 NRC IN 8c MI PWR 'DATE RCVD: 05/02/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 FORWARDING LICENSEF EVENT REPT (RO 50-315/78-025/03L-0) ON'4/04l78 CONCERNING DURING SURVEILLANCE INSPEC) SNUBBER NO. 19 WAS FOUND TO HAVVE LEAKED ITS HYDRAULIC FLUID AND DRAINED IT RESERVOIR.

PLANT NAME: COOK UNIT 1 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:

DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS +44<++<<<<<+++<+++

INCIDENT REPORTS (DISTRIBUTION CODE A002>

FOR ACTION: ER++W/4 ENCL INTERNAL: REG FILE++W/EN NRC PDR++W/ENCL W- MIPC++W/3 ENCL SCHROEDER/IPPOLITO+~W/ENCL HOUSTON++W/ENCL NOVAK/CHECK+4W/ENCL EEB+oW/ENCL KN I GHT++W/ENCL BUTLER++W/ENCL HANAUER+~W/ENCL TEDESCO+4W/ENCL E I SENHUT++W/ENCL BAER++W/ENCL SHAO+<W/ENCL VOLLMER/BUNCH~4W/ENCL KREGERl J. COLL I NS++W/ENCL ROSA+4W/ENCL K SEYFR I T/IE4 +W/ENCL EXTERNAL: LPDR S ST. JOSEPH) MI++W/ENCL TIC~~W/ENCL NS I C++W/ENCL ACRS CAT B+4W/16 ENCL COPIFS NOT SUJPfITTED PER REGULATORY GUIDE 10. >

DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 78124005 SIZE: iP+2P

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W mooCcon C i~.B'D VO k NIGH G IN POWE4 C~ONPA Y DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 CD c o Cf)

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~O'l carol Cl April 26, 1978 Cl CD WCD.X o ~~C7

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Nr. J.G. Keppler, Regional Director R CD Office of Inspection and Enforcement , CD United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-56 Docket No. 50-315

Dear Nr. Keppler:

Pursuant to the requirements of Appendix A Technical Specifications the 'following report is submitted:

RO 78-025/03L-O.

Sincerely, D.V. 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. MAY 1 'l978 R. Walsh, Esq.

G. Charnoff, Esq.

J.H. Henni gan G. Olson PNSRC J.F. Stietzel Dir., IE (30 copies)

Dir., t1IPC (3 copies)

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U. S. NUCLEAR REGULATORY COMMISSION RC FORM 366 (7.77) n LICENSEE EVENT REPORT CONTROL BLOCK: QI (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) toOQ 7 8 9 M I D LICENSEE CODE C

I C 1Q200-00000-00Qp41111Q4~OS 14 '15 6

LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T REPD p 5 p p p 3 5 Q7 0 4 0 4 7 8 o 6 7 8 Qe

~O ~LQB 1 69 EVENT DATE 74 QB 75 REPORT DATE 80 7 8 60 61 DOCKET NUMBER 68 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES QIO Durin surveillance ins ection snubber number 90 was found to have leaked its h dra-

~03 ulic fluid and drained its reservoir. This constituted an inoperable snubber as de-

~o4 lineated b Technical S ecification 3.7.8.1. Althou h snubber 89 shared the reservoi'os with snubber 90, sufficient hydraulic fluid remained in the tubing from the reservoir

~OB for ro er o eration of snubber 89. This was not a si nificant safet hazard because o seismic activit was recorded durin the snubber ino erabilit . The snubber was

~OB re aired and returned to service the fol 1owin da 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~oe ~SH Ql B Qu ~BQ13 S 0 P 0 R T Q4 ~OQ>> ~2Q'6 8 9 10 11 12 13 18 19 20 7

SEQUENTIAL OCCURRENCE REPORT REVISION EVENT YEAR REPORT NO. CODE TYPE NO.

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~'PD "~ ~78 21 22 Q

23

~02 24 5

26 QA 27

~03 28 29 QL 30 31 PRIME COMP.

QO COMPONENT ATTACHMENT NPRDA

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ACTION FUTURE EFFECT SHUTDOWN TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER 0 0 ~X M 3 2 2 LJZIQ18 ~Z Q>> ~Z Q20 ~Z QÃ 37 0 0 ~N Qn 41 Q24 Q25 44 47 Qgs 33 34 35 36 40 42 43 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o Snubber number 90 h draulic fluid leaka e was the result of nicks in the rod seal and rod wi er art number 6 and 15 res ectivel on Grinnell Cor oration rint. AH 1423 Miller Fluid Power Snubber . The snubber seals and rod wiper were replaced. Stroke 3 velocit settin s were found to meet s ecifications and snubber 90 was returned to 4 service. 'ontinued on attached a e

~O 80 7 8 9 FACILITY METHOD OF STATUS '%OWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Q32 CQ 6 L~JO 2B 1 0 0 2e N A ~BQ31 Surveillance Inspection 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q LOCATION OF RELEASE Q

~ZQ33 Z Q34 N A 80 7 8 9 10 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7

8

~00 0 QÃ 12 2QB 13 N A 80 7 9 11 PERSONNEL INJURIES 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION 7

7 e

O 8

8 9

2 ISSuED 9

Q42 10 PUBLICITY NA DESCRIPTION 10 NAME OF PREPARER

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Mike Brown H NE'0 NRC USE ONLY 80 BOER g 0

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Item 27 continued The nicks in the seals may have occurred during manufacturer's assembly of the snubber by dragging the seals over the shaft end threads. All other Unit 1 safety related snubbers're, b'eing 'inspected, and tested during, 1978 refueling outage.

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