ML17335A411

LER 98-047-00:on 981117,potential for Increase Leakage from Reactor Coolant Pump Seals Was Identified.Util Is Working with W to Resolve Issue.Current Expectations Are to Submit Update to LER by 990215.With 981217 Ltr

ML17335A411
Person / Time
Site:	Cook
Issue date:	12/17/1998
From:	Brassart G, Sampson J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-98-047, LER-98-47, NUDOCS 9812230013
Download: ML17335A411 (3)

Text

REGULATO INFORMATION DISTRIBUTION YSTEM (RIDS)ACCEEETON NER:9812230013 DOC.DATE: 98/12/17 NOTARTEED:

NO DOCKET¹FACIL:50-315 Donald, C.Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH.NAME.AUTHOR AFFILIATION BRASSART,"G.

Indiana Michigan Power Co.(formerly Indiana 5 Michigan Ele SAMPSON,J.R.

Indiana Michigan Power Co.(formerly Indiana&, Michigan Ele RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 98-047-00:on 981117,potential, for increase leakage from reactor coolant pump seals was identified.

Util is working with W to resolve issue.Current expectations are to submit update to LER by 990215.With 981217 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED'.LTR ENCL SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: RECIPIENT ID CODE/NAME PD3-3 PD INTERNAL: AEOD/SPD RAB~FILE CENTE~R/DE7EELB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RGN3 FILE 01 EXTERNAL: L ST LOBBY WARD NOAC POORE,W.NRC PDR COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME STANG, J AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HOHB NRR/DRPM/PECB RES/DET/EIB LITCO BRYCE, J H NOAC QUEENER,DS NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D G NOTE TO ALL NRZDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROE DESK (DCD)ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 22 One Cook Rare Biidgnsn.@491 06 616 465 5901 Z INOIAMA NICHIGIN POMfKR December 17, 1998 United States Nuclear Regulatory Commissi'on Document Control Desk Washington, DC 20555 Operating License DPR-58 Docket No.50-315 Document Control Manager: In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event f II LER 315/98-047-00,"Interim-Potential for Increase Leakage from Reactor Coolant Pump Seals Identified" No commitments were identified in this preliminary submittal J.R.Sampson Site Vice President/mbd Attachment c: J.L.Caldwell (Acting), Region III R.P.Powers P.A.Barrett J.B.Kingseed R.Whale D..Hahn Records Center, INPO NRC Resident Inspector 98i22300i3 98i2i7 PDR ADQCK 050003i5 S PDR t NRC Form 366 U.S.NUCLEAR REGULATORY COMMISSION (6-1998)LICENSEE EVENT REPORT (LER)(See reverse for required number of digits/characters for each block)APPROVED BY OMB NO.3150-0104 EXPIRES 06/30/2001 ESTSJATED BVRDEN PER RESPONSE TO COMPLY WITH TISS MANDATORY INFORMATION COLLECTION RKOVKST;$0.0 HRS.REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSNG PROCESS ANO FED BACK TO PIDVSTRY.FORWARD COMMENTS REGARDING BVRDEN ESTBJATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH rr4 F33), V.S.NUCLEAR REGVLATORY COMMISSION, WASHINGTON.

DC 205550001.

AND TO THK PAPERWORK REDVCTION PROJECT o1504101).

OFFICE OF MANAGEMENT AND BVDGEf, WASHINGTON, DC 20503 FACIUTY NAME I1)TITLE (4)Cook Nuclear Plant Unit 1 OOCKETNUMBERI2) 05000-315 PAGE I3)1 of1 Interim-Potential for Increase Leakage from Reactor Coolant Pump Seals Identified MONTH DAY YEAR EVENT DATE (5)LER NUMBER (6)SEQUENTIAL NUMBER REVISION NUMBER REPORT DATE (7)MONTH DAY YEAR A ILITY HAM DC Cook-Unit 2 NUMB 05000-316 OTHER FACILITIES INVOLVED (8)17 1998 1998-047-00 12 17 1998 A ILI N K T NUM OPERATING MODE (9)POWER LEVEL (10)00 20.2201 (b)20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(v) 20.2203(a)(3)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(i) 50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(viii) 50.73(a)(2)(x) 73.71 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR Ii: (Check one or more)(11)20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(4) 50.36(c)(1) 50.36(c)(2)

LICENSEE CONTACT FOR THIS LER (12)50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii)

OTHER SpeoEy n Aberracr beIow or n NRC Form 366A Mr.Gary Brassart, Nuclear Safety Analysis Supervisor TELEPHONE NUMBER (BICSJde Area Code)616/697-5106 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO EPlX CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO EPIX SUPPLEMENTAL REPORT EXPECTED (14)X YES (If Yes, complete EXPECTED SUBMISSION DATE NO EXPECTED SUBMISSION DATE (15 MONTH 02 DAY 15 98 Abstract (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)(16)On November 17, 1998, with Units 1 and 2 in Mode 5, Cold Shutdown, it was identified that in some cases the Reactor Coolant Pump (RCP)thermal barrier heat exchanger might not be able to maintain seal leak-off temperatures below the 235 degree Fahrenheit (F)limit during a loss of seal injection.

The Cook UFSAR states that the RCPs can be operated"indefinitely since the thermal barrier cooler has sufficient capacity to cool the reactor coolant flow which would pass through the thermal barrier cooler and seal leakoff from the pump volute".This implies that the Component Cooling Water (CCW)flow to the thermal barrier heat exchanger provides redundant cooling for the RCP seals.As a result of questions asked by plant personnel regarding the range of allowable CCW flow rates to the thermal barrier heat exchanger for the range of seal leakoff flows permitted by Cook operating procedure, Westinghouse determined that if the RCP seal leakoff flow were less than 2 gallons per minute, and the CCW temperature were above 95 degrees F, the seal leakoff temperature could potentially flash to steam and cause damage to the RCP number 1 seal.The postulated RCP number 1 seal damage due to flashing may degrade the ability to perform its function of RCS pressure boundaryAt this time it is not known if the potential seal damage would be extensive enough to allow increased leakage along the RCP shaft.Westinghouse has been informed of this issue, the Westinghouse Safety Review committee has begun their investigation, and Westinghouse has put this issue into their Part 21 review process.As Cook has operated in the past with seal leak-off flow less than 2 gpm, this potential condition was determined to be reportable in accordance with 10 CFR 50.73(a)(2)(ii)(B), as a condition which resulted in the nuclear power plant being in a condition that was outside the design basis of the plant, as the plant was designed to have a certain amount of leakage along the shaft.Cook is working with Westinghouse to resolve this issue.Current expectations are to submit an update to this LER by February 15, 1999.NRC FORM 366 (6-1998)