ML17335A197

LER 98-018-02:on 980505,use of RCP Seals as Alternate Boron Injection Flow Path Resulted in Unanalyzed Condition.Caused by Maintaining Temp Above Recommended Max Temp.Westinghouse Has Provided Technical Input on issue.W/980831 Ltr

ML17335A197
Person / Time
Site:	Cook
Issue date:	08/31/1998
From:	Sampson J, Schoepf R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-98-018, LER-98-18, NUDOCS 9809040160
Download: ML17335A197 (5)

Text

CATEGORY 1y REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9809040160 DOC.DATE: 98/08/31 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH.NAME AUTHOR AFFILIATION SCHOEPF>R. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele SAMPSON;J.R. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 98-018-02:on 980505,use of RCP seals as alternate Boron C injection flow path resulted in unanalyzed condi.'tion.Caused by maintaining temp above recommended max temp. Westinghouse has provided technical input on issue.W/980831 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

NOTES:

RECIPIENT COPIES RECIPIENT COPIES 0 ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 PD 1 1 STANG, J 1 1 R INTERNAL: AEOD 2 2 AEOD/SPD/RRAB 1 1 Lh CENTER 1 1 NRR/DE/ECGB 1 1 R DE 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOHB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 RES/DET/EIB 1 1 RGN3 FILE 01 1 1 D

EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE,J H 1 1 NOAC POORE,W. 1 1 NOAC QUEENER,DS 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPZES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 22

Indiana Michigan Power Company Codc t4dcar One G6< Plarc

~

Brid9maA. Ml49106 F6 4aa 590>

Z INDIANA AIICHIOiAN POWER August 31, 1998 United States Nuclear Regulatory Commission 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 98-018-02 Sincerely, J. R. Sampson Site Vice President

/mbd Attachment J. L. Caldwell (Acting), Region III R. P. Powers P. A. Barrett J. B. Kingseed R. 'hale D. Hahn Records Center, INPO NRC Resident Inspector 9809040160 980833, PDR ADGCK 05000315 8 PDR r

a

NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVE O BY OMB NO. 255041 05 (4-95) ExpvIEs 04r)erie ESTIMATED BI)ROSH PER RESPONSE TO ODIST.Y WITH TISS MAIS)ATCRY INFORMATIONCOLIECTlON REOIJEST: 50.0 HRS. REPORTED IESSONS lEARNEO LICENSEE EVENT REPORT (LER) ARE NICORPORATED PITO THE JCENNSINO PROCESS ANO FED BACK TO INOVSTRY. FORWARD COMMENTS RECAROSIO IRÃtDEN ESTSlATE TO THE (See reverse for required number of digits/characters for each block)

P~

INFORMATION AIS) RECORDS MMMCEMENT BRANCH IT4 F55). U.S. NUCLEAR RECIAATORY COMMISSION. WASISNOTON. OC 205554001, ANO TO THE REDUCTION PROJECT III504IOI), OFFICE OP MANACEMEJIT ANO BUOCET. WASHNOTON, DC 20505 FACIUTY NAME II) DOCKET NUMBER I2) PAGE IS)

Cook Nuclear Plant Unit 1 50-315 1 of 1 TITLE IS)

Use of Reactor Coolant Pump Seals as Alternate Boron Injection Flow Path Potentially Results in Unanalyzed Condition EVENT DATE (6) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED(6)

A ILI NUMB R MONTH DAY YEAR YEAR SEQUENTIAL REVISION MONTH DAY YEAR NUMBER NUMBER Cook Unit 2 50-316 A ILI NAM 05 05 98 98 018 02 08 31 98 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS. OF 10 CFR g: (Check one or more) (11)

MODE (9) 20.2201 (b) 20.2203(a)(2)(v) 50.73(a)(2)(i) 50.73(a)(2)(viii)

POWER 20.2203(a)(1) 20.2203(a)(3)(i) 50.73(a)(2)(ii) 50.73(a)(2)(x)

LEVEL(10) 00 73.71 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(iii) 12 Moig'- P SPc 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv) OTHER m Abetrscl below or 20.2203(a)(2)(iii) 50.36(c)(1) 50.73(a)(2)(v) 'SI NRC Form 366A 20.2203(a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(vii)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER (Iodvde Ares Code)

Mr. Paul Schoepf, Safety Related Mechanical Engineering Supertintendent 616/465-5901, x2408 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO jgP>I CAUSE SYSTEM COMPONENT, MANUFACTURER REPORTABLE NPRDS TO NPRDS EXPECTED N H SUPPLEMENTAL REPORT EXPECTED (14)

YES NO SUBMISSION X DATE (15) 10 31 98 (If Yes, complete EXPECTED SUBMISSION DATE).

Abstract (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (1 6)

In March, 1998, while. investigating a different issue, Engineering noted a potential problem involving the use of the Reactor Coolant Pump (RCP) seals as an alternate emergency boration flow path, which utilizes the Boric Acid Storage Tank (BAST) as the injection source. The BAST is maintained at a temperature above the vendor's recommended maximum RCP seal water injection temperature, and the extended use of this flow path could result in the seal water injection temperature exceeding the recommended maximum. After evaluation of the potential impact of this condition, it was determined that this represented an unanalyzed condition, reportable under 10CFR50.72(b)(2)(i), and an ENS notification was made on April 1, 1998. This interim LER is therefore submitted under 10CFR50.72(a)(2)(ii).

Operation of the alternate emergency boration flow path utilizing boric acid from the BAST at the high end of its possible temperature range could result in damage to the RCP seals, which in turn, could result in seal leak-off flow rates beyond the seal injection capabilities. Westinghouse has provided technical input on this issue, which clarified the plant design capability with respect to emergency boration. Evaluation of the Westinghouse input is continuing, as is evaluation of the safety significance of this condition.

Due to the complexity of the issue, It is expected that an update to this LER will be issued by October 31, 1998.

NRC FORM 366 (4.95)