05000339/LER-1980-034-03, /03L-0:on 800711,during Mode 2 Operation,Leak from RCS Occurred in Excess of Tech Spec Limit.Caused by Packing Failure on Valve RHR-MOV-2700.Valve Repaired,Tested & Returned to Svc

/03L-0:on 800711,during Mode 2 Operation,Leak from RCS Occurred in Excess of Tech Spec Limit.Caused by Packing Failure on Valve RHR-MOV-2700.Valve Repaired,Tested & Returned to Svc

ML19331B631
Person / Time
Site:	North Anna
Issue date:	08/07/1980
From:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19331B620	List: 05000339/LER-1980-034, Forwards LER 80-034/03L-0 05000339/LER-1980-034-03, /03L-0:on 800711,during Mode 2 Operation,Leak from RCS Occurred in Excess of Tech Spec Limit.Caused by Packing Failure on Valve RHR-MOV-2700.Valve Repaired,Tested & Returned to Svc
References
LER-80-034-03L-01, LER-80-34-3L-1, NUDOCS 8008120516
Download: ML19331B631 (2)

LER-1980-034, /03L-0:on 800711,during Mode 2 Operation,Leak from RCS Occurred in Excess of Tech Spec Limit.Caused by Packing Failure on Valve RHR-MOV-2700.Valve Repaired,Tested & Returned to Svc

Event date:
Report date:
3391980034R03 - NRC Website

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O t1ctustz tvtur atroar CONTROL BLOCK / / / / / / / (1)

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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LICENSEE CODE LICENSE NUMBER LICENSE TYPE CAT 0/1/

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

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During normal Mu,2 Operation, a leak occurred from the reactor coolant

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system in excess of the limit specified in T.S. 3.4.6.2.

The leak was

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isolated within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> and the unit placed in Mode 5 within 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />.

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Since the unit contrinment was under a vacuum and the unit was shutdown,

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there was no affect on the health and safety of the public. This item is

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reportable pursuant to T.S. 6.9.1.9.b.

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SYSTEM

CAUSE

CAUSE COMP.

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

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)

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It was determined that the leakage resulted from a packing failure on valve

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RHR-MOV-2700. The valve was repaired, tested and returned to service.

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FACILITY METHOD OF STATUS

% POWER OTHER STATUS DISCO M DESCRI MION (32)

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NA

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ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY (35)

LOCATION OF RELEASE (36)

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PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION (39)

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PERSONNEL INJURIES

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PUBLICITY ISSUED DESCRIPTION (45)

NRC USE ONLY

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NAME OF PREPARER W. R. CARTWRIGHT PHONE (703) 894-5151 8008120516

Virginia Electric and Power Company North Anna Power Station, Unit #2 Attachment: Page 1 of 1 Docket No. 50-339 Report No. LER 80-034/03L-0

Description of Event

On July 11, 1980, a primary system leak was observed. The opera-tions personnel noted a decreasing pressurizer level and system pressure and a rise in containment humidity and temperature. A system leak rate test was performed (PT 52.2) in an attempt to quantify the leakage. The results of this test indicated an 18.2 gpm leak rate. A reactor coolant system walkdown was conducted and the packing failure on RHR-MOV-2700 was discovered.

Probable Consequences of Occurrence The unit was tripped and an emergency maintenance request was submitted for the repair of the valve. Since the containment was under a vacuum and the leak was isolated within 10 bours, there was no affect on the health or safety of the public.

Cause of Event

The primary system leakage was caused by a packing failure on RHR-MOV-2700. This valve is the first isolation valve from the loop TH leg to the residual heat removal system.

Immediste Corrective Actions The unit was tripped and the leak isolated within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. The valve was repaired by replacing the packing. A leak rate test (PT 52.2) was performed after the unit was returned to normal system pressure and temperature wits satisfactory results.

Scheduled Corrective Action No further action required. This event is considered an isolated failure.

Actions Taken to Prevent Recurrence No further action required.

Generic Implications There are no generic implications of thi.s event.