ML20083H106
| ML20083H106 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/27/1983 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, John Miller Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20083H112 | List: |
| References | |
| 552A, NUDOCS 8401040424 | |
| Download: ML20083H106 (2) | |
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,VIRGIMIA ELECTRIC AND PowEn COMPANY Ricnwown, VIRGINIA 20261 W.L.srswimr vice r..r==='
December 27, 1983 Nucu. nam oFEMATIONS c.
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s Mr. Harold R. Denton, Director Serial No. 552A Office of Nuclear Reactor Regulation N0/JHL: jab Attn: Mr.-James R. Miller, Chief Docket Nos. 50-338 Opefating Reactors Branch No.'3 50-339 Division of Licensing License Nos. NPF-4 U. S. Nuclear Regulatory Commission NPF-7 Washington, D. C.
20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 SUPPLEMENT TO PROPOSED TECHNICAL SPECIFICATIONS CHANGES In our letter dated ' October 7,
1983 (Serial No. 552), Vepco requested an amendment in the form of changes to the Technical Specifications for North
. Anna-Unit Nos. I and 2.
These proposed changes would revise the Technical Specifications to reflect the addition of new fire protection systems.
This submittal will be a supplement to our above mentioned submittal, to add-the statement that hose rack stations are located at the containment entrance.
W This statement should be added to the asterisk note on Table 3.7-7.
The addition of this change will aid in completing the provisions of Appendix A to Branch Technical Position APCSB 9.5-1~and to clarify where the fire hose rack stations are located in relation to the containment.
The proposed Technical Specification change for North Anna Unit No. 1 is provided in Attachment 1.
The proposed Technical Specification change for North Anna Unit No. 2 is provided in Attachment 2.
A discussion of the proposed Technical Specifications change is provided in Attachment 3.
This ~ supplemented request has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff.- It has.been determined that this supplemental request does not involve an-unreviewed safety question as defined in 10CFR50.59 and it does not pose a significant hazards consideration as defined in 10CFR50.92.
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Mr. Harold R. Denton Vaasswu Es.acresc. Awo Powsm Conapawr To LWe'have reviewed.this supplemental request /in accordance with the criteria in 10CFR170.22.
.Since. this request supplements a previous submittal,. no
-additional license amendment fees are required.
Very truly yours,
/
(,sy'p W. L. Stewart Attachments:
1.
Proposed Technical Specification Change - Unit 1
-2.
Proposed Technical Specification Change - Unit 2 3.l Discussion of Proposed Technical Specifications Change cc:
Mr. James P. O'Reilly Regional Administrator Region-II:
.Mr. M. W. Branch
-NRC Resident. Inspector
-North Anna Power Station iMr. Charles Price Department of Health 109 Governor Street-
' Richmond, Virginia 23219 Mr. L. D. Graber LIS S
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