ML20023D537

LER 83-022/03L-0:on 830412,review of ASME XI Iwv Program Identified 192 Valves Not Exercised &/Or Stroke Timed.Caused by Fragmented Implementation of Testing Program.Programs Upgraded

ML20023D537
Person / Time
Site:	North Anna
Issue date:	05/13/1983
From:	Harrell E VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20023D527	List: ML20023D526 ML20023D537
References
LER-83-022-03L-01, LER-83-22-3L-1, NUDOCS 8305200583
Download: ML20023D537 (3)

Text

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U.S. NUCLEAR RFGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK / / / / / / / (1) (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

'/0/1/ /V/A/N/A/S/1/ (2) /0/0/-/0/0/0/0/0/-/0/0/ (3) /4/1/1/1/1/ (4) / / / (5)

LICENSEE CODE '

LICENSE NUMBER LICENSE TYPE CAT 0/1/ REP URC

/L/ (6)

/0/5/0/0/0/3/3/8/ (7) /0/4/1/2/8/3/ (8) /0/5/1/3/8/3/ (9)

DOCKET NUMBER EVENT DATE REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (10)

/0/2/ / A review of the ASME XI IWV program for Unit 1 identified 192 valves that had not/

/0/3/ / been either exercised and/or stroke timed as necessary; of these 126 had been /

/0/4/ / fully tested but at an incorrect frequency. On Unit 2 139 valves were similarly /

/0/5/ / affected. All T.S. operability requirements had been met, therefore the health /

/0/6/ / and safety of the public were not affected. This is reported pursuant to /

/0/7/ / T.S. 6.9.1.9.c /

/0/8/ / /

SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

/0/9/ /S/D/ (11) /A/ (12) /X/ (13) /V/A/L/V/E/S/ /X/ /X/

SEQUENTIAL OCCURRENCE REPORT REVISION LER/R0 EVENT YEAR REPORT NO. CODE TYPE NO.

(17) REPORT NUMBER /8/3/ /-/ /0/2/2/ / / /0/3/ /L/ /0/ /0/

ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

/X/ (18) /G/ (19) /Z/ (20) /Z/ (21) /0/0/0/0/ (22) /Y/ (23) /N/ (24) /A/ (25) /Z/9/9/9/

(26)

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)

/1/0/ / The IWV testing was inadequate because implementation of testing programs /

/1/1/ / following submissions in September and October of 1981 has been fragmented. /

/1/2/ / Operability of ESF and RP functions on Unit I was verified. Testing will be /

/1/3/ / completed on Unit 2 prior to start-up. /

/1/4/ / /

FACILITY METHOD OF STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION (32)

/1/5/ /E/ (28) /1/0/0/ (29) / N/A / /C/(31) / Engineering Review /

ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY (35) LOCATION OF RELEASE (36)

/1/6/ /Z/ (33) /Z/ (34) / NA / / NA /

PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION (39)

/1/7/ /0/0/0/ (37) /Z/ (38) / NA- /

PERSONNEL INJURIES NUMBER DESCRIPTION (41)

/1/8/ /0/0/0/ (40) / NA /

LOSS TYPE OF OR DAMAGE TO FACILITY (43)

DESCRIPTION

/1/9/ /Z/ (42) / NA /

PUBLICITY ISSUED DESCRIPTION (45) NRC USE ONLY

/2/0/ /N/ (44) '/ NA- /////////////

8305200583 830533*' ^" " NRER E. WAYNE HARRELL PHONE (703) 894-5151 gDRADOCK 05000338 PDR

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Virginia Electric and Power Company North Anna Power Station, Units Nos. I and 2

Attachment:

Page 1 of 2 Docket No. 50-338 50-339 Attachment to LER 83-022/03L-0

. Description of Event on April 12, with Unit 1 at 100% power while conducting a review of the : ASME XI IW program, it was found that 167 valves had not been either exercised and/or stroke time tested as necessary to comply with IW requirements. As the review proceeded the total number of valves affected reached 192, of which 126 had been subject to the necessary testing but at incorrect frequency. A corresponding earlier review of

, Unit 2 showed that 139 valves on that unit were affected. This appears j to be reportable pursuant to T. S. 6.9.1.9. c. This event is applicable to both Units 1 and 2.

Probsble Consequences of Occurrence The review that identified the IW. deficiencies also identified that Technical Specification requirements applicable to operability

testing of valves required for Engineered Safeguards Function (ESF) and i Reactor Protection (RP) had been met. Since at no time were ESF or RP

! functions compromised, the health and safety of the public were not affected.

Cause of Event The IW testing had been incomplete because, following submission of the written IW-IWP programs in September and October of 1981, implementation of the programs at the station had proceeded in a fragmented manner. The error was compounded by incertainty as to the status of requested relief.

Immediate Corrective Action

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When the deficiencies were discovered, an immediate evaluation of the operability of the valves and systems was done. It was determined h that Technical Specification requirements had been met for all ESF and RP _ systems and therefore continued -operation of Unit I was justified.

Immediate action was in progress to correct Unit 2 procedures to ensure that necessary procedures - were approved. implemented and ' the required testing completed prior to unit start-up.

Scheduled Corrective Action I

A total review and upgrade of the station ASME XI IWV programs is in progress and is expected to be completed and implemented by September 30, 1983.

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Attachment:

Page 2 of 2 Action Taken To Prevent Recurrence In addition to the scheduled corrective action noted above, a staff team has been assigned full time to administer and monitor the IW program.

Generic Implications j There are no generic implications of this occurrence.

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