05000338/LER-1981-069-03, /03L-0:on 810819,found Two Containment Isolation Valves Were Not Leak Tested After Maint.Caused by Valve Repair Using General Valve Mechanical Maint Procedures Which Omit Leak Test.Maint Procedure Revised

/03L-0:on 810819,found Two Containment Isolation Valves Were Not Leak Tested After Maint.Caused by Valve Repair Using General Valve Mechanical Maint Procedures Which Omit Leak Test.Maint Procedure Revised

ML20010G649
Person / Time
Site:	North Anna
Issue date:	09/14/1981
From:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20010G643	List: 05000338/LER-1981-069, Forwards LER 81-069/03L-0 05000338/LER-1981-069-03, /03L-0:on 810819,found Two Containment Isolation Valves Were Not Leak Tested After Maint.Caused by Valve Repair Using General Valve Mechanical Maint Procedures Which Omit Leak Test.Maint Procedure Revised
References
LER-81-069-03L, LER-81-69-3L, NUDOCS 8109220353
Download: ML20010G649 (2)

LER-1981-069, /03L-0:on 810819,found Two Containment Isolation Valves Were Not Leak Tested After Maint.Caused by Valve Repair Using General Valve Mechanical Maint Procedures Which Omit Leak Test.Maint Procedure Revised

Event date:
Report date:
3381981069R03 - NRC Website

text

'

U.S. NUCLEAR REGULATORY COMMISSION LIC "CE 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

/L/ (6)

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

/0/8/1/9/8/1/ (8) h / 94 / /i A / (9)

OUR E DOCKET NUMBER EVENT DATE REPORT DATE EVENT DESCRIPTION AND F20BABIE CONSEQUENCES (10)

/0/2/

/ On May 28, 1980, with Unit I at cold shutdown it was discovered that two contain-/

/0/3/

/ ment isolation valves were not leak tested after maintenance. This condition is /

/0/4/

/ not consistent with AShE Section XI Subsection IWV-3200.

In both cases the re-

/

/0/5/

/ dundant valves were operable aqd, the as found leakages were satisfactory; there- /

/0/6/

/ fore, the heelth and safety of the general public were not affected. This is

/

/0/7/

/ reportable pursuac. Le T.S 3.6.3.1 and 6.9.1.9.c.

/

/0/8/

/

/

SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

/0/9/

/S/D/ (11) /D/ (12) /2/ (13) /V/A/L/V/E/X/ (14) [X/ (15)

LX/ (16)

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

CODE TYPE NO.

(17) REPORT NUMBER

/8/1/

/-[ /0/6/9/

/\\/

/0/3/

/L/

/-/

[0/

ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACT.ON 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) /W/ (25) /M/1/2/0/ (26)

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)

/1/0/

/ The general valve maintenance procedure did not verify surveillarce requirements /

/1/1/

/ after maintenance was performed. The general valve procedure has been changed

/

/1/2/

/_t_o include verification of valve testing requirements upon completion of main-

/

/1/3/

/ tenance.

/

/1/4/

/

/

FACILITY METHOD OF STATU3

% POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION (32)

/1/5/

/G/ (28)

/0/0/0/ (29) /

NA

/ (33) /B/ (31) / QC INSPECTOR OBSERVATION /

ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY (35)

LOCATION OF RELEASE (36)

/1/6/

/Z/ (33)

/Z/ (34) /

KA

/

/

NA

/

FERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION (39)

/1/7/ /0/0/0/ (37) /2/ (38) /

NA

/

i PERSONNEL INJURIES NUMBER DESCRIPTION (41)

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

NA

/

LOSS OF OR DAMAGE TO FACILITY (43)

TYPE

DESCRIPTION

/1/9/

/Z/ (42) /

NA

/

PUBLICITY ISSUED DESCRIPTION (45)

NRC USE ONLY

/2/0/

/N/ (44) /

NA

/////////////

NAME OF PREPARER W. R. CARTWRIGHT PHONE (703) 894-5151 g922ossaago,g4 g

ADOCK o5000338 PDR

Virginia Electric and Power Company North Anna Power Station, Unit #1 Attachment: Page 1 of 1 Docket No. 50-338 Report No. LER 81-069/03L-0

Description of Event

On May 28, 1980 with Unit I at cold shutdown it was discovered that FCV-1160 and TV-IM-101C were not type "C" tested after maintenance.

Initially this event was determined to be non-reportable On August 19, 1981 the deviation was reviewed by the Station Nuclear Safety and Operat-ing Committee and the classification was changed to reportable pursuant to T.S. 6.9.1.9.c.

Probable Consequences of Occurrence The redundar.t containment isolation valves for both of these valves were operable with acceptable leak rates. Both valves had acceptable as found leak rates; therefore, the health a.nd safety of the general public were not affected.

Cause of Event

I The valves were repaired using a general valve mechanical mainten$nce procedure. This procedure did not reference the required leakage surveill-ance test.

Immediate Corrective Action

Both valves were tested satisfactorily.

Scheduled Corrective Action No scheduled corrective action is require.d.

Actions Taken to Prevent Recurrence The valve maintenance procedure was chaaged to verify that valve leakage is performed on all valves that require type "C" testing.

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

f' a