ML17335A428

LER 98-051-00:on 981122,reactor Trip Signal from Manual Safety Injection Not Verified as Required by TS Surveillance,Was Discovered.Maintenance Currently Evaluating Significance & Cause of Event

ML17335A428
Person / Time
Site:	Cook
Issue date:	12/22/1998
From:	Boesch J, Sampson J INDIANA MICHIGAN POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-98-051, LER-98-51, NUDOCS 9812300352
Download: ML17335A428 (3)

Text

CATEGORY 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9812300352 DOC.DATE: 98/12/22 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana 05000315 AUTH i NAME 'UTHOR AFFILIATION BOESCH,J.'ndiana Michigan Power Co.

M SAMPSON,J.R. Indiana Michigan Power Co.

RECXP.NAME RECIPIENT AFFILIATION SUB JECT: LER 98-051-00: on 981122, reactor trip signal from, manual safety injection not verified as required by TS surveillance,was discovered. Maintenance currently evaluating significance 6 cause of event.

DXSTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE:

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

NOTES'.

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 PD 1 1 STANG, J 1 1 INTF)RNAL: A RAB 2 2 AEOD/SPD/RRAB 1 1 FILE CE E 1 1 NRR/DE/ECGB 1 '1 NRR DE EELB 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 DZSTRIBUTION LZSTS OR REDUCE THE NUMBER OF COPIES'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

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616 466 6901 INOIANA Ir/tICHIGAN PMAR December 22, 1998 United States Nuclear Regulatory Commis'sion Document Control Desk Washington, DC 20555

• Operating License DPR-58 Docket No. 50-315 Document Control Manager:

<<h In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event f"I i i i ~ p i'b'i'g i d:

LER 315/98-051-00 No commitments were identified in this submittal.

Sincerely, 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 E

'ar812300352 4118i222 PDR ADOCK 050003i5 S PDR AFP ~1 rnerr'ca's Em 1 plarlrrer."

NRC Form 366 U.S. NUCLEAR REGUIATORY COMMISSION APPROVED BY OMB No. 31504104 EXPIRES 05/30/2001 6-1998)

KSTSIATED BURDEN PER RESPONSE TO COMPLY WITH TISS MANDATORY BrFORMATlON COUECTCN RKGVESn 50.0 HRS. REPORTED lESSONS LEARNED ARE INCORPORATED SITO THK UCENSING PROCESS ANO FKD BACK TO INOVSTRY.

LICENSEE EVENT REPORT (LER) FORWARD COMMENTS RKGARDSIG BURDKN ESTSIIATE TO THE IIFORMATION AND RECORDS MaGKMENT BRANCH IT4 F55). U.S. NVClEAR REGULATORY COMMISSION. WASISNGTON. OC 205554001. AND TO THE PAPERWORK RKDVCTION PROJECT (51504101). OFRCE OF MANAGEMENT AND BUDGET. WASHL'4GTON DC (See reverse for required number of 20505 digits/characters for each block)

FACILITYNAME (I) DOCKET NUMBER (2) PAGE (5)

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

Reactor Trip Signal from Manual Safety Injection Not Verified as Required by Technical Specification Surveillance EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED(8)

FA ILITYNAM 0 C NUMB R SEQUENTIAL REVISION Cook Unit 2 05000-316 MONTH DAY YEAR YEAR NUMBER NUMBER MONTH DAY YEAR A ILI NAM 0 CK NUMB 22 1998 1998 051 00 12 22 1998 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR (I: (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 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(iii) 73.71 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)

Specity SI Abstract below 20.2203(a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(vii) or nNRCForm366A LICENSEE CONTACT FOR THIS LER (12)

TELEPHONE NUMBER (IIKIvde Area Code)

Mr. John Boesch, Maintenance Manager (616) 465-5901, x2634 COMPLETE ONE LINE FOR EACH CONIPONENT 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 OAY X YES SUBMISSION 01 12 1999 (If Yes, complete EXPECTED SUBMISSION DATE) NO DATE (15)

Abstract (Limit to 1400 spaces, I.e., approximately 15 single-spaced typewritten lines) (16)

On November 22, 1998, during a review of Technical Specification (TS) surveillance requirements for the engineered safety feature actuation system instrumentation by engineering, it was discovered that in Modes 3 and 4 the, reactor trip signal from a manual initiation of a safety injection (Sl) had not been verified in accordance with TS 4.3.2.1.1, Table 4.3-2, Item 9.a. The TS requires the Sl tests be performed for Modes 1, 2, 3 and 4 on a refueling frequency. Normally'during preparations for unit restart from refueling, the reactor trip breakers are required to be open in Modes 3 and 4 for other TS surveillance testing. The tripping of the reactor trip breakers from manual Sl initiation cannot be verified with the reactor trip breakers open. Therefore the reactor trip portion of the manual Sl test has not normally been performed for Modes 3 and 4. In accordance with 10CFR50.73(a)(2)(i)(B), this interim LER is being reported as a condition prohibited by the plant's TS.

Maintenance is currently evaluating the significance and cause of this event. Corrective actions will be developed based on the results of the evaluation. It is anticipated that an update to this LER will be submitted by January 12, 1999.

NRC FORM 366 (6-1998)