ML20097F328

Suppl to 871109 & 880331 Applications for Amends to Licenses NPF-4 & NPF-7,revising TS 3.10.3 & 3.10.4 to State That Reactor Trip Setpoints for intermediate-range Channels Set at Plus or Minus 35% of Rated Thermal Power

ML20097F328
Person / Time
Site:	North Anna
Issue date:	06/08/1992
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20097F331	List: ML20097F328 ML20097F334
References
92-086, 92-86, NUDOCS 9206150252
Download: ML20097F328 (2)

Text

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VIHOINIA F.u:cri<ic Axn Pown:it Coxi .tny M ICit MON D, YlllOINI A 20061 June 8, 1992 United States Nuclear Regulatory Commission Serial No.92-086 Attention: Document Control Desk NL&P/JYR:Jm)

Washington, D.C. 20555 Docket Nos. 50-338 50 339 License Nos. NPF-4 NPF-7 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPAtD' NOBTH ANNA POWER STATION UNITS _1 AND 2 ADMINISTR ATIVE ,QQHRECTION TO PROPO_SXQ TECHNICAL SPECIFIC ATION CH ANGE Our letters dated November 9,1987 and March 31,1988 proposed changes to the Technical Specificatlans for North Anna Units 1 and 2 associated with the intermV. ate range neutron flux trip setpoints. Specifically, the changes were to revise the inethod by which the nominal and allowable intermediate range 1eutron flux 1:ip setpoints were specified, and reformat the operability and surveillanco requirements to be consistent with Standard Technical Specifications. Howeve, cue to an administrative oversight, the submittals were incomplete. The proposed increase from 25% to 35% of rated thermal power for the intermediate range Oux trip setpoints was not addressed in two specifications. ,

Technical Specifications 310.3 (Physics Tests) and 3.10.4 (Reactor Coolant Loops) address special test exceptions. In the current wording, ;he reactor trip setpoints for both the intermediate and power range changes are the came. The wording should have been revised to differentiate between power levels with respect to the intermediate and power range channels. Proposed revisions to those specifications were not included _in the submittals, but were addressed within the scope of the original safety evaluation.

Spedhcally, Technical Specification 3.10.3 and 3.10.4 shou ci be re 'ised to state that the reactor trip setpoints for the intermediate range channels are set at s 35% of rated thermal power, and the power range channels are set at s.25% of rated thermal power. This will make the intermediate range trip setpoint in those two specifications consistent with the setpcint proposed for Table 2.2-1 (Reactor Trip System Instrumentation Setpoints) which was previously submitted.

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Att' ached are the revised Technical Specli, cation 3.10.3 and 3.10.4 pages for North >

Anna Units 1 and 2. The safety evaluation providing the basis for our determinat!on that this proposed change does not involve a significant hazard consideration previously submitted remains unchanged. The conclusion that the proposed changes do not involve an unrevieweu safety question as defined in 10 CFR 50.59 or a significant hazaros consideration as defined in 10 CFR 50.92 remains valid.

Should you have any questions or require additional information, please contact us.

Very truly yours, dLSch 4 W. L Stewart Senior Vice President - Nuclear Attachments cc; United States Nuclear Regulatory Commir%t Region 11

.i01 Marietta Street, N.W.

Suite 2900 Atlanta, GA 30320 Mr. M. S. Lesser NRC Senior Resident inspector North Anna Power Station

< Commissioner -

Department of Health '

Room 400 109 Governor Street Richmond, Virginia 23219 i

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