ML17335A496

LER 98-057-00:on 981228,discovered That AFW Valves Were Not Tested IAW Inservice Testing Program.Caused by Failure to Recognize Design Bases Features Re Afws by Personnel. Updated LER Will Be Submittted by 990415.With 990127 Ltr

ML17335A496
Person / Time
Site:	Cook
Issue date:	01/27/1999
From:	Gebbie J, Sampson J INDIANA MICHIGAN POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-98-057, LER-98-57, NUDOCS 9902040026
Download: ML17335A496 (3)

Text

~ CATEGORY 1 ~

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9902040026 DOC.DATE: 99/01/27 NOTARIZED: NO DOCKET I FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH s '.AME. AUTHOR AFFILIATION GEBBIE, J. Indiana Michigan Power Co.

SAMPSON,J.R. Indiana Michigan Power Co.

RECIP.NAME RECIPIENT AFFILIATION,

SUBJECT:

LER 98-057-00:on 981228,discovered that AFW valves were not tested IAW inservice testing program. Caused by failure to recognize design bases features re AFWS by personnel.

Updated LER will be submittted by 990415.With 990127 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ( ENCL i 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

'NTERNAL: AEOD SPD RAB 2 2 AEOD/SPD/RRAB 1 1 CENTE 1 1 NRR/DE/ECGB 1 1 NRR E 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 L1TCO BRYCE, J H 1 1 NOAC POORE,W. 1 1 NOAC QUEENER,DS 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 N

NOTE TO ALL NRIDSs RECIPIENTS:

PLEASE HELP US TO R=DU~E NASTE. TO HAVE YOUR NAME OR ORGANZZATTON REMOVED ERCM DZSTREBUT-ON :STS OR REDUCE THE NLTMBER O": COPTES R=C=

ESZ (BCD> CN EX -NS: N ~B".

V=" BY YO: OR YCUR ORGY':.EAT:CN, CON'ACT AH= -CC-".rEN FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 22

Indiana Michigan Power Company Cook Nudear Aaa One Cook Ran BridgnnN49106 616466 6901 INWANA NICHIGiAN POWER January 27, 1999 I

United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 hagi 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 p i i 1 i d.'ER 315/98-057-00,"Auxiliary Feedwater Valves Not Tested In Accordance With Inservice Testing Program" 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 S,

'airai02040026 eaI90%27 PDR ADQCK 0500C3i5 PDR g AEP: America's EnegI'nrlner

NRC Form 366 U.S. NUCLEAR REGULA Y COMMISSION APPROVED B OMB NO. 3150-0104 EXPIRES 06)30)2001 (6-1998) ESTIMATED SVRDEN I'ER RESPONSE TO COMPLY WITH THIS MANDATORY orFORMATION COLLECTION REOVESTI 500 HRS. REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FED SACK TO INDVSTRY LICENSEE EVENT REPORT (LER) FORWARD COMMENTS REG*RIANG 8VRDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (TA FSII, V S NUCLEAR RECVLATORY COIIIMISSION WASHINGTON. DC 20555.0001, AND TO THE PAPERWORK REDV"TION PROJECT (515OSIIH). OFFICE OF MANAGEMENT AND SVOCET, WASHINGTON. OC (See reverse for required number of 20505 digits/characters for each block)

FACILITYNAME (I) OOCKETNUMBER(2) PAGE (2)

Cook Nuclear Plant Unit 1 05000-315 1 of 1 Auxiliary Feedwater Valves Not Tested ln Accordance With Inservice Testing Progam EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED(8)

A ILITYNAM NUMB R SEQUENTIAL REVISION DC Cook - Unit 2 05000-316 MONTH DAY YEAR YEAR NUMBER NUMBER MONTH DAY A ILITYNAME DOCKET NUMB R 12 28 1998 1998 057 00 01 27 1999 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) 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)

Speafy in Abstrar2 below 20.2203(a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(vii) or n NRC Form 366A LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER (Inoarde Area Code)

Mr. Joel Gebbie, Safety Related Mechanical Engineering Supervisor 616/465-5901 x1543 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 OAY X YES SUBMISSION 04 15 1999 (If Yes, complete EXPECTED SUBMISSION DATE) NO DATE (15)

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

During an Inservice Testing (IST) Program assesment performed in December 1998, plant personnel identified several valves in the Auxiliary Feedwater (AFW) System that should have been tested in accordance with American Society of Mechanical Engineers (ASME)Section XI but were not tested as required. The specific valves include the Auxiliary Feedwater Pump Suction Check Valves and the Auxiliary Feedwater Pump Emergency Leakoff Valves.

As a result of the missed IST Program testing, the requirements for Technical Specification (TS) 4.0.5 were not satisfied.

On December 28, 1998, this condition was determined to be reportable. Therefore, this interim report is being submitted in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by plant Technical Specifications.

I The proximate cause of this event is failure to recognize design bases features related to the AFW System by personnel who developed the ASME Section XI program requirements. The AFW Pump Suction Check valves were not included in the testing program because personel did not recognize that the valves were a barrier between a safety-related and non-safety-related system. The AFW Pump Emergency Leakoff Valves were previously included in the program, but were incorrectly considered to have a passive safety function when testing requirements were established. Therefore, the valves were not tested in the closed direction. Further review has shown that the emergency leakoff valves may be required to perform an active closure function and should be tested in the closed direction.

Investigation into this condition is continuing, and is expected to be complete by March 31, 1999. An update to this interim LER will be submitted by April 15, 1999.

NRC FORM 366 (6-1998)