05000339/LER-1989-003, Advises of Change in Reportability for LER 89-003-00 Re 10 Containment Isolation Valves W/Excessive Leak Rates

Advises of Change in Reportability for LER 89-003-00 Re 10 Containment Isolation Valves W/Excessive Leak Rates

ML20216K024
Person / Time
Site:	North Anna
Issue date:	11/14/1990
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-697, NUDOCS 9011200012
Download: ML20216K024 (2)

LER-1989-003, Advises of Change in Reportability for LER 89-003-00 Re 10 Containment Isolation Valves W/Excessive Leak Rates

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vi)
3391989003R00 - NRC Website

text

.

j VINGINIA EuiCTRIC AND POWER COMPANY Hicunoxo,VinatwiA cues:

November 14,1990 U.S. Nuclear Regulatory Commission Serial No.

90 697 Attention: Document Control Desk NAPS /RCS:rcs R2 Washington, DC 20555 Docket No.

50-339 License No.

NPF 7 Gentlemen:

ylRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2

~ CHANGE IN REPORTABILITY

~ On March 23,1989, Virginia Electric and Power Company submitted Licensee Event Report (LER) 89-003-00 for North Anna Unit 2. This LER documented ten containment.

Isolation-valves which exceeded the acceptable "as-found" leak rates for Type C testing. The LER treated the event as reportable pursuant to 10 CFR 50.73(a)(2)(ii) for an "... event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded...." However, upon further consideration, we have determined this event to be not reportable. In the case of each valve which exceeded the 0.6 La acceptance criterion, either closed system '

1 integrity or one operable isolation device existed which would have prevented direct leakage to the environment. Therefore, the penetrations remained operable and the containment isolation capability was not seriously degraded.

in addition, we have evaluated the event with respect to other relevant reporting criteria of 10- CFR-50.73 and have determined them also to be not applicable.

Specifically,10 CFR 50.73(a)(2)(v)(C) states that any ev_ent or condition that alone

..could.have prevented the ful.fillment of the safety function of structures or systems that are needed to control the release of radioactive materialis reportable. However,10

1 CFR 50.73(a)(2)(vi) allows that-Individual' component failures need not be reported pursuant to paragraph 50.739i)(2)(v)(C) if redundant equipment in the same system' R

was operable and available to perform the required safety function. As stated above, either closed system Integrity or one operable isolation device existed to prevent i

leakage though each' penetration. Therefore, this reporting requirement also does not apply to this event.

Due to this change in reportability, no supplemental report will be made as indicated on the LER submitted March 23,1989. Henceforth, similar events will be treated as not reportable. This change in reportability has been reviewed by the Station Nuclear S

I' h

9

c Safety and Operating Committee and has been discussed with the NRC Senior Resident inspector at North Anna.

Very truly yours, Dk' W. L. Stewart Senior Vice President - Nuclear cc:

U.S. Nuclear Regulatory Commission Region ll -

101 Marietta Street, N.W.

Suite'2900 Atlanta, Georgia - 30323 Mr. M. S. Lesser NRC Senior Resident inspector North Anna Power Station

, (.-