ML17335A501

LER 98-060-00:on 981231,identified That Rt Sys Response Time Testing Did Not Comply with TS Definition.Caused by Inadequate Procedures.Corrective Actions Will Be Developed & Update to LER Will Be Submitted by 990415.With 990201 Ltr

ML17335A501
Person / Time
Site:	Cook
Issue date:	02/01/1999
From:	Arent G, Sampson J INDIANA MICHIGAN POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-98-060, LER-98-60, NUDOCS 9902090054
Download: ML17335A501 (5)

Text

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CA,TE GORY 1 ~

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9902090054 . DOC.DATE'- 99/02/01 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH.NAKE AUTHOR AFFILIATION ARENT, G. Indiana Michigan Power Co.

SAMPSON,J.R. Indiana Michigan Power Co.

RECIP..NAME RECIPIENT AFFILIATION

SUBJECT:

LER 98-060-00:on 991231,identified that RT sys response time testing did not comply with TS definition. Caused by inadecpxate procedures. Corrective actions will be developed & A update to LER will be submitted by 990415.With 990201 ltr. T 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 ID CODE/NAME LTTR ENCL. ID CODE/NAME LTTR ENCL PD3-3 PD .1 1 STANG, J 1 1 INTERNAL: AEOD/SPD 3gg3 2 2 AEOD/SPD/RRAB 1 1 FILE CENTE 1-. 1 NRR/DE/ECGB 1 ' 1

/DE/EE 1 1 NRR/DE/EMEB 1 NRR/DRCH/H1CB 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 C NRC PDR 1 1 NUDOCS FULL TXT 1 1 t C

NOTE TO ALL "RIDS" REC1PIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION L1STS 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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Indiana Michigan Sidgman. MI49106 616 465 5901 INOMNA II/IICHIGAN PolYER February 1, 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 E

ig i

LER 315/98-060-00, "Interim - Reactor Trip System Response'Time Testing Does Not Comply With Technical Specification Requirement".

No commitments were identified in this submittal.

Sincerely,

'Am J. R. Sampson Site Vice President

/mbd Attachment c: 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 9902090054 99020i PDR ADQCK 05000315 S PDR

N C Form 366 U.S. NUCLEAR REGU RY COMMISSION APPROV 0)/IB NO. 3150.0104 EXPIRES 06/30/2001 (6-1998) ESTBIATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REOUEST: 50.0 HRS. REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE UCENSWG PROCESS AND FED BACK TO INDUSTRY LiCENSEE EVENT REPORT (LER) FORWARD COMMENTS REGARDNG BURDEN ESTBIATE TO THE INFORMATION AND RECORDS MANAGEMFNT BRANCH IT4 Fll). U S NUCLEAR REGIAATORY COMMISSION. WASHWGTON. DC 205554001. AND TO THE PAPERWORK REDUCTION PRO)ECT Is)500104). OFFICE OF MANAGEMENT AND BUDGET, WASIeNGTOIL DC (See reverse for required number of 20505 digits/characters for each block)

FACIUlYNAME It) DOCKET NUMBER (2) PAGE I3)

Cook Nuclear Plant Unit 1 05000-315 1 of1 TITLE Ia)

Interim - Reactor Trip System Response Time Testing Does Not Comply With Technical Specification Requirement EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED(8)

A ILI NAM Oc NUM R SEQUENTIAL REVISION Cook Unit 2 05000-316 MONTH DAY YEAR YEAR NUMBER NUMBER MONTH DAY YEAR A IL)lYNAM DOCKET NUMBER 12 31 1998 1998 060 00 02 01 1999 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR g: (Check one or mor e) (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) 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)

Speedy h Abstract beknr 20.2203(a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(vii) or n NRC Fons 366A LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER (Inc4de Ares Code)

Mr. Gordon Arent, Licensing Manager (616) 697-5064 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 04 05 1999 (If Yes, complete EXPECTED SUBMISSION DATE). NO DATE (15)

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

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On December 31, 1998, plant personnel identified that Reactor Trip System Reponse Time (RTSRT) testing did not comply with the Technical Specification (TS) definition of RTSRT. Upon further review of the TS requirements for the Reactor Trip System, it was determined on December 31, 1998, that TS surveillance requirements for the RTSRT was not performed in accordance with Technical Specification (TS) 4.3.1.1.3. TS Definition 1.22 states that the RTSRT is considered to be the interval from when a monitored parameter exceeds its trip setpoint at the channel sensor until the loss of stationary gripper coil voltage. TS 4.3.1.1.3 requires that the RTSRT of each reactor trip function be demonstrated to be within its limit at least once per 18 months. The testing to demonstrate compliance with the TS 4.3.1.1.3 surveillance requirement would be accomplished by channel test measurements, as stated in the TS bases. Surveillance test procedures used to comply with the TS surveillance requirement measures the response time from the initiation of the channel sensor trip to the the opening of the reactor trip breakers. However, these procedures do not measure the response time from the opening of the reactor trip breakers to the loss of stationary gripper coil voltage. Therefore, the surveillance requirement of TS 4.3.1.1.3 has not been met. In accordance with 10CFR50.73(a)(2)(i)(B), this interim LER is being submitted as a condition prohibited by the plant's TS.

The proximate cause of this condition is inadequate procedures, which were apparently based on the definition of reactor trip system response time. There is currently an ongoing evaluation of the significance and root 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 April 5, 1999.

NRC FORM 366 (6-1998)