ML20212J295

Forwards Corrected Markup & Typed Version of Affected Pages. Requests That Attached Pages for Those Previously Provided in 990506 Submittal Be Replaced & Incorporated Into NRC Review of Proposed TS

ML20212J295
Person / Time
Site:	North Anna
Issue date:	06/22/1999
From:	Christian D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20212J300	List: ML20212J295 ML20212J304
References
99-261A, NUDOCS 9906290120
Download: ML20212J295 (3)

Text

E haisir Ei.e.:cTRIC ANI) POWi:H COMi%NY Ricituoso, huisir 2326:

June 22, 1999 U.S. Nuclear Regulatory Commission Serial No.

99-261A Attention: Document Control Desk NL&OS/ETS R0 Washington, D.C. 20555 Docket Nos.

50-338 50-339 License Nos.

NPF-4 NPF-7 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2

{

REVISED PAGES FOR PROPOSED TECHNICAL SPECIFICATION CHANGE REVISED SURVEILLANCE FREQUENCY AND ACTION TIMES REACTOR TRIP AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEMS l

In a May 6,1999 letter (Serial No.99-261) Virginia Electric and Power Company l

requested amendments, in the form of changes to the Technical Specifications for l

Facility Operating License Numbers NPF-4 and NPF-7 for North Anna Power Station l

Units 1 and 2, respectively.

The proposed changes will revise the surveillance frequency for the Reactor Trip System (RTS) and Engineered Safety Features

]

Actuation System (ESFAS) analog instrumentation channels in addition, the allowed i

outage time and action times for the RTS and ESFAS snalog instrumentation channels l

and the actuation logic are being modified. We have cubsequently identified a potential verbatim compliance issue associated with one of the proposed changes. To eliminate the potential for a compliance issue, we are providing a corrected markup and typed version of the affected pages. Please replace the attached pages for those previously provided in our May 6,1999 submittal and incorporate the changes into your review of the proposed Techi.. cal Specification.

The description of the " Channels to Trip" for the Functional Unit 12, " Loss of Flow," in r

Table 3.3-1, " Reactor Trip Systein Instrumentation," is being revised. The revision includes a description of the channels required for a reactor trip above the permissive P-7 and P-8. The revised pages 3/4 3-3 for Units 1 and 2 Technical Specifications, are provided as a mark-up in Attachment 1 and as a typed version in Attachment 2. The basis for our determination that the changes do not involve a significant hazards consideration provided in our May 6,1999 submittal is not affected by this correction.

\\

f h l-9906290120 990622 DR ADOCK 050003 8

If you have any further questions, please contact us.

Very truly yours, GLA D. A. Christian Vice President-Nuclear Operations Attachments 1.

Revised Markup Technical Specifications Pages 2.

Revised Proposed Technical Specifications Pages Commitments made in this letter:

1.

None.

cc:

U.S. Nuclear Regulatory Commission Region ll Atlanta Federal Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 Mr. M. J. Morgan NRC Senior Resident inspector North Anna Power Station Commissioner Department of Radiological Health Room 104A 1500 East Main Siteet Richmond,VA 23219 Mr. J. A. Reasor Old Dominion Electric cooperative Innsbrook Corporate center 4210 Dominion Blvd.

Glen Allen, Virginia 23260 i

j l

COMMONWEALTH OF VIRGINIA )

)

COUNTY OF HENRICO

)

i The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Mr. D. A. Christian, who is Vice President - Nuclear Operations, of Virginia Electric and Power Company. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.

Acknowledged before me this 2 day of

/6he

.1999.

)

My Commission Expires:

du 3/

.2092

_l

//

Notary Public (SEAL)