05000338/LER-1981-017-03, /03L-0:on 810404,unidentified Leakage of Greater than 1 Gpm Limit Detected During Testing.Caused by Packaging Leaks in Two Manual Isolation Valves & One Pressure Control Valve.Valves Closed & Repacked

/03L-0:on 810404,unidentified Leakage of Greater than 1 Gpm Limit Detected During Testing.Caused by Packaging Leaks in Two Manual Isolation Valves & One Pressure Control Valve.Valves Closed & Repacked

ML20003H724
Person / Time
Site:	North Anna
Issue date:	05/01/1981
From:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20003H719	List: 05000338/LER-1981-017, Forwards LER 81-017/03L-0 05000338/LER-1981-017-03, /03L-0:on 810404,unidentified Leakage of Greater than 1 Gpm Limit Detected During Testing.Caused by Packaging Leaks in Two Manual Isolation Valves & One Pressure Control Valve.Valves Closed & Repacked
References
LER-81-017-03L, LER-81-17-3L, NUDOCS 8105070331
Download: ML20003H724 (2)

LER-1981-017, /03L-0:on 810404,unidentified Leakage of Greater than 1 Gpm Limit Detected During Testing.Caused by Packaging Leaks in Two Manual Isolation Valves & One Pressure Control Valve.Valves Closed & Repacked

Event date:
Report date:
3381981017R03 - NRC Website

text

O U.S. STCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK / / / / / / / (1)

(PLEASE PRINT OR TYPE ALL REQUIRED IhTORMATION)

/0/1/

/V/A/N/A/C/1/ (2)

/0/0/-/0/0/0/0/0/-/0/0/ (3)

/4/1/1/1/1/ (4)

/ / / (5)

LICENSEE CODE LICENSE NLMBER LICENSE TYPE CAT

/0/1/

/_L/ (6)

/0/5/0/0/0/3/3/8/ (7)

/0/4/0/4/8/1/ (8) /o /5 /o /1/a /1/ (9)

DOCKET NLWBER EVENT DATE REPORT DATE EVEhT DESCRIPTION AND PROBABLE CONSEQUENCES (10)

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On April 4, 1981, during performance of tha post-refueling Reactor Coolant

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System leak test, an unidentified leakage of greater than the 1 gpm limit was /

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detected. The unit was in a hot standby condition at the time it was

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discovered and the unidentified leak rate was reduced to.26 gpa within 12

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hours. The health and safety of the general public were not affected. This

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occurrence is reportable pursuant to T.S. 6.9.1.9.b.

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SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

/0/9/

/C/B/ (11) /E/ (12) /B/ (13) /V/A/L/V/E/X/ (14) /F/ (15)

/D/ (16)

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

CODE TYPE NO.

(17) REPORT STMBER

/8/1/

/-/ /0/1/7/

/\\/

/0/3/

[L/

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ACTION FLTURE EFFECT SHLTDOWN ATTACHMEh7 NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB. SUPPLIER MANLTACTUPIR

/X/ (18) /Z/ (19) /Z/ (20) g/ (21) /0/0/0/0/ (22) /Y/ (23) /N/ (24) /N/ (25) /V/0/8/5/ (26)

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)

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The high RCS leak rate resulted from packing leaks in two manual isolation

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valves and one pressure control valve within the primary system pressure

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boundary. The valves, which are not required to be open, were closed and the /

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pressure control valve was satisfactorily repacked.

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FACILITY METHOD OF DISCOVERY DESCRIPTION (32)

STATUS

• POWER OTHER STATUS

/ HOT STANDBY / ( 0. DISCOVERY

/1/5/

g/ (28)

/0/0/0/ (29)

/C/ (31)

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RCS LEAK TESTING

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ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY (35)

LOCATION OF RELEASE (36)

/1/6/

/Z/ (33)

/Z/ (34) /

NA

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/

NA

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PERSONNEL EXPOSURES NL3BER TYPE DESCRIPTION (39)

/1/7/ /0/0/0/ (37) [Z/ (38) /

NA

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PERSONNEL INJURIES NLNEER DESCRIPTION (41) 1 '5!

cl0!O: (6C) !

NA

~2: ': CR CAMAGE TJ FACII.ITY,, -

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PUELICITY ISSUED DESCRIPTION (45)

NRC USE ONLY

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Lvl (4:.) /

NA

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NA"I 0F PREPAFER W. R. CART 4RIGHT FHONE (703) 894-5151 8105070 g g

o Virginia Electric and Power Company North Anna Power Station, Unit #1 Attachment: Page 1 of I Docket No. 50-338 Report No. LER 81-017/03L-0

Description of Event

On April 4, 1981, an uaidentified leak rate of greater than the 1 gpm limit was observed during performance of the post-refueling Reactor Coolant System leak test (1-0P-5.3).

This event is contrary to T.S. 3.4.6.2 and reportable pursuant to T.S. 6.9.1.9.b.

Probable Consequences of Occurrence The health and safety of the general public were not affected by this occurrence because the unit was in a hot standby condition when~

the leak test was performed and the unidentified RCS leakage was reduced to an acceptable rate of.26 gpm within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Cause of Event

The high Reactor Coolant System leak rate resulted from leakage past the packing of three valves in the primary system pressure bounda ry.

The valves which were found leaking were the Loop C drain line manual isolation valve (1-RC-100), the Loop C cold leg sample manual root valte (1-RC-101), and the Loop A pressurizer spray line pressure coe'. col valve (PCV-1455A).

Immediate Corrective Action

The packing in both manual valves was adjusted and the valves, which are not required to be open, were closed. The leaking pressurizer spray line pressure control valve was satisfactorily repacked the following day.

Scheduled Corrective Action No scheduled corrective action is required.

Actions Taken to Prevent Recurrence No further actions are required.

Generic Implications There are no generic implications associated with this event.

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