ML17335A314

LER 98-044-00:on 981001,offsite Power Availability Was Not Verified as Required by TS Surveillance.Caused by Inadequate Procedure That Governed Document Changes.Revised Appropriate Surveillance Procedures.With 981102 Ltr

ML17335A314
Person / Time
Site:	Cook
Issue date:	11/02/1998
From:	Sampson J, Weber L INDIANA MICHIGAN POWER CO., INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-98-044, LER-98-44, NUDOCS 9811090049
Download: ML17335A314 (7)

Text

CA'TEGORY 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR-9811090049 DOC.DATE: 98/11/02 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Po~er Plant, Unit 1, Xndiana M 05000315 AUTH. NAME AUTHOR AFFILIATION WEBERIL. Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele SAMPSON,J.R. Indiana Michigan Power Co. (formerly Indiana E Michigan Ele RECIP.NAME RECXPIENT AFFILIATION

SUBJECT:

LER 98-044-00:on 981001,offsite power availability was not verified as required by TS surveillance.Causedb by inadequate procedure that governed document changes. Revised appropriate surveillance procedures. With 981102 ltr.

DXSTRZBUTZON CODE: IE22T COPXES 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 ID CODE/NAME LTTR ENCL PD3-3 PD 1 1 STANG, J 1 1 INTERNAL: AEOD RAB 2 2 AEOD/SPD/RRAB 1 1 LE CE 1 1 NRR/DE/ECGB 1 1

~'EELB 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HZCB 1 1 NRR/DRCH/HOHB 1 . 1 NRR/DRCH/HQMB 1' NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 RES/DET/EZB 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 E,

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 j ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 22

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Indiana Michigan Power Company ~

Cook Nudear ftn One Ceca Ran1 Bridgmn Ml49106 Z

61 6 465 5901 INDQlllM NlCHlCRAN POWER November 2, 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 fll i ibig i d.'ER 98-04I4-00, "Offsite Power Availability Not Verified as Required by Technical Specification Surveillance".

Sincerely,

.J. R. Sampson Site Vice President

.4Imbd 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 98ii090049 98ii02 PDR ADOCK 050003i5 S PDR

.NP:Anrerica's Eaeg> Ibrlller-

NRC Form 366 U.S. NUCLEAR REGUIATORY COMMISSION APPROVED SY OMS NO. 51 5041 05 (4-95) EXPIRES 04M(le KSTSAATKO SVROKN PER RESPONSE TO COMPLY WITH TleS MAJCATORY LICENSEE EVENT REPORT (LER) ARE ~TKO MORMATTONCOLLECTIGN REOVEST: 50 0 lelS. RfPORTKD lESSONS lEARNEO PJTO llew UCKNSNO PROCESS ANO FEO SACK TO WOVSTRY. FORFMAO COMMKNTS RECARDWC SIJROKJI ESTSAATK TO THE INFORMATION AJCJ RECORDS MMIACKAMNTBRANCH (T4 F55), V.S. NVCIEAR RKCIAATORY COMASSSCeL WASISNCTOIL OC 105554001. AIKI TO TNE (See reverse for required number of PAPERWORK REOVCTION PROJECT (51504101K OFFICE OF MANAGEMENTAJKT SvOCET. wASISNCTOK DC 10505 digitslcharacters for each block)

FACIUTYNAME (1) DOCKET NUMBER(1) PAGE (5)

Cook Nuclear. Plant Unit 1 50-315 1of3 Offsite Power Availability Not Verified as Required by Technical Specification Surveillance EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED(6)

MONTH DAY YEAR SEQUENTIAL REVISION MONTH DAY YEAR 11 NUMBER NUMBER Cook Unit 2 50-316 NU 10 01 98 98 044 00 02 98.

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) S0.73(a)(2)(vili)

POWER 20.2203(a)(1) 2O 2203(a)(3)(0 50.73(a)(2)(ii) 50.73(a)(2)(x)

LEVEL (10) 20.2203(a)(2)(i) 20.2203(a)(3}(ii) 50.73(a}(2)(iii) 73.71 20.2203(a)(2)(li) 20.2203(a)(4) 50.73(a)(2)iiv) OTHER el ADSVsct below or 20.2203(a)(2}(iii) 50,36(c)(1) 50.73(a)(2)(v) l1 NRC FCITII SBS 20.2203(a)(2)(iv) S0.36(c)(2) 50.73(a)(2)(v(0 LICENSEE CONTACT FOR THIS LER (12)

TELEPHONE NUMBER (iodude Ares Code)

Mr. Larry Weber, Operations Manager (616) 465-5901, x2443 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

SYSTEM COMPONENT MANUFACTURER REPORTABLE TO CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE NPROS TO NPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED YES NO SUBMISSION X DATE (15)

(If Yes, complete EXPECTED SUBMISSION DATE).

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

On October 1 1998, during a review of Technical Specification (TS) surveillance requirements for the offsite electrical

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power sources by engineering, it was discovered that the availability of the preferred offsite power source was not being verified in accordance with TS 4.8.1.1.1.a. Specifically, the surveillance procedure did not require verification of breaker alignment and voltage reading for the preferred offsite power source. The TS requires that each of the circuits between the offsite electrical power sources, preferred and alternate offsite power sources, and the onsite 4 kV electrical distribution system be determined operable at least once per 7 days by verifying correct breaker alignments and indicated power availability. In accordance with 10CFR50.73(a)(2)(i)(B), this LER is being reported as a condition prohibited by the plant's Technical Specifications.

The root cause for this condition was an inadequate procedure that governed document changes. The instruction that governed the procedure change process in 1992 did not provide adequate guidance and expectations to the Opefations personnel for the review of changes made to plant procedures and their supporting documentation. The appropriate surveillance procedures have been revised. Recent improvements in the procedure revision process have been made which include the issuance of an Operations Department document revision procedure.

The failure to perform the required surveillance was evaluated. It was determined that not verifying the breaker alignment and voltage availability of the preferred offsite source had no safety significance.

NR FORM 366 (4-95}

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (4-95)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITYNAME (1) DOCKET NUMBER(2) LER NUMBER (6) PAGE (3)

YEAR SEQUENTIAL . REVISION Cook Nuclear Plant Unit 1 50-315 NUMBER NUMBER 2 of 3 98 044 00 TEXT (lfmore spece is rectrrired, use additfonel copies of NRC Form (366A) (12)

Conditions Prior to Event Unit 1 was in Mode 5, Cold Shutdown Unit 2 was in Mode 5, Cold Shutdown Descrl tlon of Event On October 1, 1998, during a review of Technical Specification (TS) surveillance requirements for the offsite electrical power sources by System Electrical Engineering, it was discovered that the availability of the preferred offsite power source was not being verified in accordance with TS 4.8.1.1.1.a. Specifically, surveillance procedures 1/2 OHP 4030.STP.031, "Operation Weekly Surveillance Checks," did not require verification of breaker alignment and voltage reading for the preferred offsite power source. The TS requires that each of the circuits between the offsite electrical power sources, 34.5 kilovolt (kV) preferred and alternate 69 kV offsite power sources, and the onsite 4 kV electrical distribution system be determined operable at least once per 7 days by verifying correct breaker alignments and indicated power availability.

An investigation discovered that prior to 1992, surveillance procedures1/2 OHP 4030.STP.031did not include steps to verify correct breaker alignment and power availability for either the preferred or alternate offsite power sources, as required by TS 4.8.1.1.1.a. A revision of the surveillance procedures in 1992 added steps to verify correct breaker alignment and power availability for the offsite power sources. However, the procedure revision only included verification of correct breaker alignment and power availability for the alternate offsite power source. The same requirements for the preferred offsite power source were not added. As a result, the requirements of TS 4.8.1.1.1.a were not fully met.

Cause of Event .

The root cause for this condition was an inadequate document change procedure. The instruction that governed the procedure change process in 1992, Procedure Group Guideline 003.002, "Procedure Change Sheets," did not provide adequate guidance and expectations to the Operations Department for reviewing changes made to plant procedures and their supporting documentation. Additionally, no formal documentation of completed procedure change reviews was required.

The surveillance requirement has existed since the TS were originally issued. It could not be determined why the verification steps were never included in the surveillance procedure up until 1992.

Anal sis of Event This LER is submitted in accordance with 10CFR50.73(a){2){i){B), as a condition prohibited by plant Technical Specifications.

The 4 kV electrical distribution system design at D.C. Cook consists of two subsystems: the 4 kV safety-related and non-safety related distribution systems. The safety-related system is designed to ensure a continuous supply of electrical power to all essential plant equipment during normal operation and under abnormal plant conditions. The 4 kV safety-related system buses can receive power from four sources: the non-safety related unit auxiliary transformers (UAT), the 34.5 kV preferred offsite power, the emergency diesel generator system, or the 69 kV alternate offsite power source.

During normal operations, the main generator supplies power to the 4 kV non-safety related buses through the UATs.

During plant start-up or shutdown, the 34.5 kV preferred offsite source supplies power to the 4 kV non-safety related buses through the reserve auxiliary transformers 101/201AB and 101/201CD. The non-safety related buses then supply power to the four 4 kV safety-related buses.

NRC FORM 366A (4.95)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (4-95)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITYNAME (1) DOCKET NUMBER(2) LER NUMBER (6) PAGE (3)

YEAR SEQUENTIAL REVISION Cook Nuclear Plant Unit 1 50-315 NUMBER NUMBER 3of3 044 00 TEXT (ifmole spaceis required, use eddilionel copies of NRC Form (366AJ (17)

Analysis of Event (cont'd)

To ensure the availability of these offsite power sources, TS 4.8.1.1.1.a requires that each of the circuits between the offsite power sources and the onsite 4 kV electrical distribution system be determined operable at least once per 7 days by verifying correct breaker alignments and indicated power availability. Although procedures 1/2 OPH 4030.STP.031 did not include a step to verify the availability of the 34.5 kV preferred offsite power source, there are indication lights on the control room electrical panels which indicate power available to the 101/201AB and 101/201CD reserve auxiliary transformers. When these lights are lit, they provide indication that power is available from the 34.5 kV preferred offsite source. During shift turnover, control room panel walkdowns are conducted between the oncoming and offgoing shifts.

Also, as part of regular control room operator duties, walkdowns of these panels are performed once per shift. It is reasonable to assume that the operators would have identified this condition during panel walkdowns.

Based on the above, it was determined that not verifying the breaker alignment and voltage availability of the preferred offsite source had no safety significance.

Corrective Actions Procedures 1/2 OHP 4030.STP.031, "Operation Weekly Surveillance Checks," were revised to include verification of the voltage upstream of the offsite reserve auxiliary transformers 101/201AB and 101/201 CD, as required by TS 4.8.1.1.1.a.

Recent improvements in the procedure revision process have been made which include the issuance of OPM.001, "Operations Department Document Revision Manual." This manual provides detailed instruction regarding the procedure change, review and approval process. Recent additions to the manual have included the addition of a procedure revision checklist, which is required to be completed for all procedure changes and revisions. The checklist requires the procedure reviewer to address specific questions related to the document change and to formally document the results of the review.

A comprehensive assessment of the plant's surveillance program is currently being performed as part of the Restart Plan.

This assessment will be completed prior to restart of either unit. Specific actions that arise from this assessment will be communicated to the NRC during the restart process.

Failed Com onent Identification Not Applicable Previous Similar Events None NRC FORM 366A (4-95)