ML20151B204
| ML20151B204 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/31/1988 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20151B206 | List: |
| References | |
| 86-740A, NUDOCS 8804080097 | |
| Download: ML20151B204 (2) | |
Text
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VIHOINIA ELECTRIC ann PownH Coxiwxy Ricunoxn,VinoxxrA uneet W.L.StBWART d'[l"/.'"".
March 31, 1988
[
United States Nuclear Regulatory Commission Serial No.
86-740A Attention:
Document Control Desk N0/DJV:jmj 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 PROPOSED TECHNICAL SPECIFICATIONS CHANGES INTERMEDIATE RANGE NEUTRON FLUX TRIP Virginia Electric and Power Company letter dated November 9, 1987 proposed changes to the North Anna Power Station Units 1 and 2 Technical Specifications regarding the intermediate range neutron flux trip.
The purpose of this letter is to clarify our November 9,
1987 proposal.
Specifically, the proposed surveillance requirements for the intermediate range trip have been revised in order to clarify the modes in which a monthly channel check is required to verify that permissives P-6 and P-10 are in their required state.
In addition, our previous letter proposed a new monthly functional test when operating in Mode 1 below P-10 and Mode 2.
This additional surveillance requirement is consistent with the Standard Technical Specifications and is being mentioned at this time because we failed to do so in the discussion of proposed changes which accompanied our previous letter.
The revised surveillance requirements for North Anna Units 1 and 2 are provided in the attachment, and supersede those in our November 9, 1987 letter.
The proposed Technical Specifications changes, as revised, have been j
reviewed by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff.
It has been determined that the safety l
l evaluation which was submitted with our previous letter remains valid, and I
therefore the conclusion that the proposed Technical Specifications changes do not involve an unreviewed safety question or a
significant hazards consideration is unchanged.
Very truly yours, l
il I
bvl ) khd ok o
W. L. Stewart i
Attachment 8804080097 880331 l
PDR ADOCK 05000338 P
o cc:
U. S. Nuclear Regulatory comission 101 Marietta Street, N.W.
Suite 2900 Atlanta, GA 30323 Mr. J. L. Caldwell i
NRC Senior Resident Inspector North' Anna Power Station 1
l I
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