ML19254D822

LER 79-130/03L-0:on 790925,operation Personnel Noted Steam Driven Auxiliary Feedwater Pump 1-FW-P-2 Turning Due to Steam Leak Through Steam Inlet Trip Valve.Valve Will Be Repaired During Refueling Outage

ML19254D822
Person / Time
Site:	North Anna
Issue date:	10/23/1979
From:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19254D819	List: ML19254D818 ML19254D822
References
LER-79-130-03L, LER-79-130-3L, NUDOCS 7910300210
Download: ML19254D822 (2)

Text

NRC FORM 366 - -

(747) .

LICENSEE EVENT REPORT (PLEASE PRINT OR TYPE ALL REQUlflED INFORMATION)

CONTROL BLOCK: l 1

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7 o i 8 9 IvlAlNlAlSl LICENSEE CODE 1 l@l 0 l 0 l- l 0LICENSE 14 lb l0 l0NUMBEHl0 l0 l- l0 lo l@[4 LICENSE 25 26 h h hTYPE h JOl@lbl CATl 58l@

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8 5$uRCE 60 L l@l61015 l 0DOCKET l 0 l0 l 3 l 3 l868@l0 NUMBER 69 19 EVE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h 2 l While to Mode 3. operation oersonnel noted thn a t oni, Artunn ,,,v411, vy fe+ne r I O

l IO1311 pump 1-W-_P- 2 was turning due to a steam leak thru a stenn inior trin unlun l The steam supply to 1-W-P-2 was isolated using nantially nnornenA icnt oinn I O 4 O s Ivalves rendering it inoperable. This event is contrarv tn T M. 1.7.1 ? nnA l lOisl l reportable pursuant to T.S. 6.9 .1. 9 .b . Twn bn1f-ni w nuvil in ey f neAuenv p pr l 10171 l were operational: therefore the oublic health nnd snfory unro nne nfforenA hy I

O a Ithis event. 80 7 8 9 SYSTEM CAUSE CAUSE COVP. VALVE CODE CODE SUSCODE COYPONENT CODE SUBCODE SUBCODE O 9 9

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10 11 12 13 vl^ t l v l e l x l@ tr_l@ liLJ 18 19 20 7 8 REVISION SEQUENTIAL OCCURRENCE REPORT EVENT YEAR REPORT NO. CODE TYPE NO.

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_ 21 22 AK N AC ON PL NT ET HOURS S B IT EO FOR SUS. SUPPLIE t'AN FACTURER l_z.1@l zi@ Lzl@ IL JO lo DDDI LO 41

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33 34 35 3ti 3/ 40 42 43 44 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l 110 l l Isolation of steam to 1-FW-P-2 became necessary due to a leak thru a sten, inint l I

li11J l trip valve. The plant was in the Hot Shutdown condition (Modo O within 1A k mire i 2 lof the event due to a shutdown that was in progress for a nianned refueline outnge. I Therefore, the dictates of the action statement of T.S. 3.7.1.2 were net. The I iil3l i 4 l valve will be repaired during the refuelinn outane.

80 7 8 9 ST S  % POWER OTHER STATUS DISCO RY OtSCOVERY DESCRIPTION li l s l [X_J@ l 0 l 0 l 0 l@hergency Shutdown l Operator Observation l Al@l ACTIVITY CO TENT RELEASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION Oi RELEASE l1 l6 l [ @ y@l 7 8 9 10 11 NA 44 l l 45 NA 80 PERSONNEL E XPOSURES NUVBE R TTPE DESCRIPTION

[,1 l 7 [ l 0 l 0 l 0 l@l Z l@l NA l PE RSONNE t iN;uYiES 7

NUM8ER DESCRIPTION 0 NA l 7

i a 8 9 0 l0 l@l 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION 1 9 (z j@l NA 80 l

7 8 9 10 7910300}(O NRC uSE ONa 2 O ISSUED

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@ DESCRIPTION @ lllllllllllll2 10 68 69 80=%

7 8 9 NAME OF PREPARER ". D, Ca r t gr Qh t PHONE: 703_ y _313;

Virginia Electric and Power Company North Anna Power Station, Unit #1

Attachment:

Page 1 of 1 Docket No. 50-338 Report No. LER 79-130/03L-0 Description of Event On September 25, 1979, steam was observed leaking past the seat of trip valve TV-MSillB. During Mode 3 operation, TV-MS-IllB was isolated for repair.

This valve is located on the steam line leading to the steam driven steam generator auxiliary feedwater pump 1-FW-P-2.

Probable Consequences of Occurrence The steam supply line to the auxiliary feedwater pump required isolation thereby bringing into ef fect the ACTION statement of T.S. 3.7.1.2. This calls for one of three auxiliary feedwater pumps to be powered by an operable steam supply within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Since both motor driven auxiliary feed pumps were available for operation, the health and safety of the general public were not af fected by this event.

Potential generic implications for Unit 2 exist because of past problems en-countered with these valves.

Cause of Occurrence The steam leak was caused by the valve not seating properly.

Immediate Corrective Action The unit was taken to Cold Shutdown for a scheduled refueling outage.

Scheduled Corrective Action The valve will be repaired during the refueling outage.

Actions Taken To Prevent Recurrence Causes of failure are being evaluated. The vendor has been contacted and his recommendation will be evaluated and implemented, as appropriate, during the refueling outage.

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