ML17335A463

LER 98-054-00:on 981202,discovered That at Least One MSSV Had Not Been Reset as Required by Ts.Engineering Is Continuing Review of Extent of Condition for Event.Updated LER Will Be Submitted by 990129.With 990104 Ltr

ML17335A463
Person / Time
Site:	Cook
Issue date:	01/04/1999
From:	Pisarsky F, Sampson J INDIANA MICHIGAN POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-98-054, LER-98-54, NUDOCS 9901120098
Download: ML17335A463 (5)

Text

CATEGORY .ly REGULATORY INFORMATION DISTRIBUTION SYSTEM (RZDS)

ACCESSION NBR:9901120098 DOC.DATE: 99/01/04 NOTARIZED: NO DOCKET FACZL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH.NAME . AUTHOR AFFILIATION PISARSKY, P. Indiana Michigan Power Co.

SAMPSON,J.R. Indiana Michigan Power Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 98-054-00:on 981202,discovered that at least one MSSV had not been reset as required by TS.Engineering is continuing review of extent of condition for event. Updated LER will be submitted by 990129.With 990104 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR 1 ENCL l SIZE: 2J TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ZD CODE/NAME LTTR ENCL PD3-3 PD 1 1 STANG, J 1 1 INTERNAL: AEOD S 2 2 AEOD/SPD/RRAB 1 1 CENTE 1 1 NRR/DE/ECGB 1 1 E 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 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 LZQTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROI DESK (DCD) ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 22

Indiana Michigan powar Company Cook Nudoar Rani One Cook Pan nrkkrnan, M149106 616 465 5901 Z

INDlAMA NICHfOAN POWER January 4, 1999 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 LER 315/98-054-00, "Main Steam Safety Valve Not Reset as Required by Technical Specifications".

S No commitments were identified in this submittal.

Sincerely, J. R. Sampson Site Vice President

/mbd Attachment J. L. Caldwell (Acting), Region III R. P. Powers P. A. Barrett D. F. Kunsemiller R. Whale D. Hahn Records Center, INPO NRC Resident Inspector 990ii20098 990i04 PDR ADOCK 050003i5 8 PDR

NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150%104 EXPIRES 06/30/2001 (6-1998) ESTSlATEO IKSeEN PER RESPONSE TO COMPLY WITH TISS MANDATORY PPORMATION COLIECOON REOUEsh lo.o HRS. REPORTED LESSONS LEARNED ARE NCORPORATEO NTO THE LCENSSIO PROCESS ANO FED SACK TO SIDUSTRY.

LICENSEE EVENT REPORT (LER) FORWARD COMMENTS RECARDWO BURDEN ESTSIATE TO THE IIPORMATlON AND RECORDS LIANACEMENT SRANCH IT4 FIJL UA. NUCLEAR RECIAATORY COMMISSeN. WASHWOTON. DC 205554001. AIEI TO THE PAPERWORK REDUCTION PRoJEcT I51504150. CFFIcE DF MANAGEMENT AI4) sUDGET, wAsleNCToN, Dc (See reverse for required number of digits/characters for each block)

FACILITYNAME (I) DOCKET NUMBER (2) PAGE (2)

Cook Nuclear Plant Unit 1 05000-315 1 of1 TITLE(4)

Interim - Main Steam Safety Valve Not Reset as Required by Technical Specifications EVENT DATE (5) LER NUMBER (6), REPORT DATE (7) OTHER FACILITIES INVOLVED(8)

A I NUMB SEQUENTIAL REVISION Cook Unit 2 MONTH DAY YEAR NUMBER NUMBER MONTH DAY YEAR 05000-316 NUM 12 02 1998 1998 054 00 01 04 1999 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) 000 73.71 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(iii) 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv) OTHER 20.2203(a)(2)(iii) 50.36(c)(1) 50.73(a)(2)(v)

Speo/F eI Abelrerl De)err 20.2203(a)(2)(lv) 50.36(c)(2) 50.73(a)(2)(vil) or n NRC Form 366A LICENSEE CONTACT FOR THIS LER (12)

TELEPHONE NUMBER (IIKSJde Aree Code)

Mr. Frank Pisarsky, Production Engineering Manager (616) 465-5901, x2607 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

REPORTABLE REPORTABLE TO CAUSE SYSTEM COMPONENT MANUFACTURER TO EPIX CAUSE SYSTEM COMPONENT MANUFACTURER EPIX SUPPLEMENTAL REPORT EXPECTED 14 EXPECTED MONTH DAY X YES SUBMISSION 01 29 1999 (If Yes, complete EXPECTED SUBMISSION DATE). NO DATE (15)

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

On December 2, 1998, with Units 1 and 2 in Mode 5, Cold Shutdown, Engineering determined that the procedures used for controlling the main steam safety valve (MSSV) set points had allowed at least one MSSV to be left in operation without adjusting its set point as required by Technical Specifications (TS) Surveillance Requirement 4.7.1.1. The TS requires that an MSSV set point be reset (as-left) if, during testing (as-found), it is not within 1 per cent of its nominal set point value. TS Table 4.7-1 establishes that an MSSV is operable if its set point is within 3 percent of its nominal value. When the TS requirements were incorporated into the set point control procedures, the set point values were rounded using normal arithmatic rounding methods. Thus for some of the MSSVs the procedures allowed as-left set point deviations of as much as 0.35 pounds per square inch gage (psig), and unreported as-found deviations of as much as 0.45 psig.

MSSV testing data recorded since September 1994 was reviewed. This review Identified that, during the period of review, only one safety valve had been found or left with a set point outside of TS requirements. MSSV 1-SV-1A-3 had been left with a set point of 1076 psig, above the maximum allowed set point of 1075.65 psig. This was within the range of set points required for operability of 1033.05 to 1096.95 psig. Similar incorrect allowable ranges of set points were identified in several LERs as old as 1987. Engineering is continuing its review of the extent of condition for this event. In accordance with 10CFR50.73(a)(2)(i)(B), this condition is being reported as a condition prohibited by the plant's TS. Current expectations are to submit an update to this LER by January 29, 1999.

NRC FORM 366 (6-1998)