ML19318B654

LER 80-053/03L-0:on 800601,w/unit in Cold Shutdown,Rhr Pumps de-energized for More than 1-h.Caused by Need to Repair Valve Packing Leak Resulting from Personnel Error.Pump Returned to Svc Following Repair

ML19318B654
Person / Time
Site:	North Anna
Issue date:	06/20/1980
From:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19318B653	List: ML19318B652 ML19318B654
References
LER-80-053-03L, LER-80-53-3L, NUDOCS 8006270265
Download: ML19318B654 (2)

Text

v e U.S. NUCLEAR REGULATORY COMMISSION p 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/ /L/ (6) /0/5/0/0/0/3/3/8/ (7) /0/6/0/1/8/0/ (8) /o /6 /2 /0 /8 /0 (9)

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

/0/2/ / On June 1, 1980, with the Unit at Cold Shutdown and no reactor coolant pumps /

/0/3/ / operating, the residual heat removal (RHR) pumps were de-energized for greater /

/0/4/ / than one hour. This is contrary to the Action Statement of T.S. 3.4.1.1 and /

/0/5/ / reportable by T.S. 6.9.1.9.b. The health and safety of the public were not /

/0/6/ / affected. /

&/7f, / /

/0/8/ / /

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

/0/9/ /C/F/ (11) /A/ (12) /C/ (13) /V/A/L/V/E/X/ (14) /_B/ (15) /G/ (16)

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

(17) REPORT NUMBER /S/0/ /-/ /0/5/3/ /\/ /0/3/ /L/ /-/ /_0/

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

/B/ (18) /Z/ (19) /C/ (20) /Z/ (21) /0/0/0/0/ (22) [Y/ (23) /N/ (24) /N/ (25) /F/1/2/5/ (26)

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)

/1/0/ / The RHR pumps were secured for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 43 minutes to repair a valve packing leak /

/1/1/ / which developed as a result of personnel error in loosening a valt . packing nut /

/1/2/ / on HCV-1758 in the RHR system. The incore thermocouple temperatures were /

/1/3/ / monitored and the valve was repacked. The RHR system was returned to service /

/1/4/ / following repairs. /

FACILITY METHOD OF STATUS  % POWER OTHER STATUS DISCOERY DESCRI m 0N (32)

/1/5/ /C/ (28) /0/0/0/ (29) / NA / (30)DISCOERY

/A/ (31) / Operator Observation /

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

/1/6/ /2/ (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 OF OR TYPE DAMAGE TO FACILITY (43)

DESCRIPTION

/1/9/ /2/ (42) / NA /

ISSUED PUBLICITY DESCRIPTION kkh)062 70 1 f NRC USE ONLY

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

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

4 .

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

Attachment:

Page 1 of 1 Docket No. 50-338 Report No. LER 80-053/03L-0 Description of Event On June 1, 1980, with the Unit at Cold Shutdown and with the reactor coolant system (RCS) pressure of approximately 140 psig, a mechanic was making packing measurements on valve HCV-1758 in the residual heat removal (RHR) system. In order to check the size of the packing gland in the stuffing box, the packing nut was loosened. When no leakage was observed, the mechanic loosened the nut further and started taking measurements. Unknown to the mechanic, the RCS pressure was being increased. While the mechanic was still taking readings, the valve packing came loose, dislodging the packing nut and leaking primary water into the containment.

To reduce RHR pressure, the operating RHR pump was secured for 34 minutes and the RCS pressure reduced while the packing nut was temp-orarily installed. After the packing nut was installed, one RHR pump was operated for 54 minutes. During this time it was decided that the valve should be repacked. The pump was secured and the valve repacked, however, neither the reactor coolant pumps nor the RHR pumps were oper-ated for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 43 minutes while the valve was being repacked. This l is contrary to the Action Statement of T.S. 3.4.1.1.

Probable Consequences of Occurrence The health and safety of the public were not affected since the incore temperatutres were monitored and verified to be well below satura-tion temperature.

Cause of Event The cause of the event was the need to repack HCV-1758 in the RHR system which required securing the RHR pumps and the reactor coolant pumps for greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Immediate Corrective Action The incore temperatures were monitored while the valve was being repaired. Following repair, a RHR pump was restarted. While the RER pumps were secured, no operations were permitted which could have caused a dilution of the reactor coolant system boron concentration.

Scheduled Corrective Action l None scheduled.

Actions Taken to Prevent Recurrence The mechanic involved realized his error. The incident was dis-cussed with this mechanic and other mechanics who are involved with valve repair.

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