ML17335A448

LER 98-053-00:on 981130,discovered Use of Inoperable Substitute Subcooling Margin Monitor.Caused by Condition Existing Since Installation of Plant Process Computer in 1992.Updated LER Will Be Submitted.With 981230 Ltr

ML17335A448
Person / Time
Site:	Cook
Issue date:	12/30/1998
From:	Sampson J, Rich Smith INDIANA MICHIGAN POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-98-053, LER-98-53, NUDOCS 9901060076
Download: ML17335A448 (4)

Text

CATEGORY ly REGULATORY INFORMATION DISTRIBUTION SYSTEM (RXDS)

ACCESSION NBR:9901060076 DOC.DATE: 98/12/30 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1,'Indiana M 05000315 AUTH.N2&K AUTHOR AFFILIATION SMITH,R. Indiana Michigan Power Co.

SAMPSON,J.R. Indiana Michigan Power Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 98-053-00:on 981130,discovered use of inoperable substitute subcooling margin monitor. Caused by condition existing since installation of plant process computer in 1992.Updated LER will be submitted. With 981230 ltr.

D1STRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE:

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

RECIPIENT COPIES RECIPIENT COPIES ZD CODE/NAME LTTR ENCL XD CODE/NAME LTTR ENCL PD3-3 PD 1 1 STANG, J 1 1 XNTERNAL: AEOD/SPD/RAB 2 2 AEOD/S PD/RRAB 1 1 1 1 NRR/DE/ECGB 1 1 m/ivy NRR/DRCH/HICB 1

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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 0 NRC PDR 1 1 NUDOCS FULL TXT 1 1 U

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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 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

Indiana Michigan Powet Company Cookthttaat Rant

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6164655901 INDIANA NICHIOiAN POIVKR December 30, 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 LER 315/98-053-00, "Use of Inoperable Substitute Subcooling Margin Monitor" No commitments were identiTied'in this submittal.

Sincerely, J. R. Sampson Site Vice President Imbd Attachment 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 990i060076 98i230 PDR ADOCK 050003i5 S PDR t ~ l

.RFPt.itt(erica'a'netpl larlner "

NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB No. 0150%104 EXPIRES 06/SOI2001 (6-1998) ESTSIATEO IK24DEN PER RESPONSE TO COMPLY WAN TISS IIANOATORY SPORMATION COLIECDOH REOIJEST: $ 0AI ISA REPORTED LESSONS LENIIIEDARE HCCRPCIIATED SIIO TI% UCEN5040 PROCESS AIEI FED SACK TO SEXISTRY.

LICENSEE EVENT REPORT (LER) FORWARD COMMENTS REINRDINO 8424OEN ESISIATE TO llC <<FORMATION ANO RECORDS MANAOEMEIIT SRANCN IT4 FssL ILS. IAKSEAR RECIAATORY COMIRSSKNL WASINIOTOH. OC 205550001. AMI TO THE PAPERWORK IDICTCCNN PRCJEOT 4$ 1500104), CFNCE CF MNIACEMENT AN) SvocET, wAsleNCTCIL Dc (See reverse for required number of 20503 digits/characters for each block)

FACIUTY NAME II) DOCKET NUMBER I2) PAGE I3)

Cook Nuclear Plant Unit 1 05000-315 1 of1 Interim LER - Use Of Inoperable Substitute Subcooling Margin Monitor EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED(8)

A I SEQUENTIAL REVISION DC Cook Unit 2 05000-316 MONTH DAY YEAR YEAR NUMBER NUMBER MONTH DAY YEAR A I I NAM D NUMB 11 30 1998 1998 053 00 12 30 1998 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR I): (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) 000 20.2203(a)(3)(ii) 50.73(a)(2)(iii) 73.71 20.2203(a)(2)(i) 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)

Specrir in Abstract below 20.2203(a)(2)(iv) . 50.36(c)(2) 50.73(a)(2)(vii) or n NRC Form 36BA LICENSEE CONTACT FOR THIS LER (12)

TELEPHONE NUMBER (Inc4de Area Code)

Mr. Robert Smith, Nuclear Information Systems Manager 616/697-5103 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 02 16 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 9, 1998, plant Instrument and Control (l&C) personnel performing cross-calibration checks on core exit thermocouple indications for the Plant Process Computer (PPC) found that all points were indicating 30 to 35 degrees F too high. Investigation by plant personnel has revealed that the PPC inputs for core exit thermocouples were calibrated as linear signals as opposed to calibration to a thermocouple curve. This resulted in the erroneous PPC indication. This condition has existed since installation of the PPC in 1992.

Technical Specification (TS) 3.3.3.8, "Post-Accident Instrumentation," allows the PPC subcooling margin indication to be substituted for the TS required subcooling monitor. TS surveillance Requirement 4.3.3.8, Table 4.3-7, Item 11 requires a monthly channel check and an 18 month channel calibration on the Reactor Coolant System Subcooling Margin Monitor.

In the past, the PPC subcooling margin indication has been substituted for the TS required instrumentation. No TS surveillance testing was performed on the PPC core exit thermocouple input to the PPC subcooling margin monitors prior to substituting the PPC subcooling margin indication for TS required instrumentation. On November 30, 1998, this condition was determined to be reportable in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by the plant's Technical Specifications due to missed surveillance testing.

Investigation into this condition is continuing, and is expected to be complete by February 1, 1999. An update to this interim LER will be submitted by February 16, 1998.

NRC FORM 366 (6-1998)