ML20054L443
| ML20054L443 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 07/06/1982 |
| From: | Lee O PUBLIC SERVICE CO. OF COLORADO |
| To: | Clark R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20054L444 | List: |
| References | |
| P-82229, NUDOCS 8207080127 | |
| Download: ML20054L443 (2) | |
Text
N O
PUBLIC SERVICE COMPANY OF COLORADO P.
O.
BOX 840 DENVER, COLORADO 80206 05iCAR R. LEE VIC E. PR ESIDE NT July 6, 1982 Fort St. Vrain Unit No. 1 P-82229 Mr. Robert Clark, Chief Operating Reactor Branch Division of Licensing Office of Nuclear Reactor Regulations U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Docket No. 50-267 f
Subject:
Fort St.
Vrain Unit No. 1 Release from 70?s Power
Dear Mr. Clark:
On February 16, 1982, we met with you and various Nuclear Regulatory Commission representatives to present the results of testing up to 100*o power and to set forth our plans in terms of operating philosophy and proposed Technical Specifications for operating above the present 70?; power restriction. We subsequently received your comments (see ORNL letter dated March 15, 1982), and based on these l
comments we have finalized our test report, prepared Technical i
Specification revisions, and the necessary supporting safety l
evaluation.
We are transmitting herewith the following documents:
I i
Attachment A - Response to ORNL Questions (ORNL Letter Dated l
March 15, 1982)
Attachment B - Final Report " Testing and Operations of Fort St.
Vrain Up To 100?; Power" r
Attachment C - Proposed Technical Specifications ll LCO 4.1.7, Core Inlet Orifice Valves SR 5.1.7, Region Peaking Factor Surveillance t
l Definition 2.21, Individual Refueling Region Outlet Temperature
(&M Definition 2.22, Comparison Region 0
t h
- 6) )
8207080127 820706 PDR ADOCK 05000267 i
P PDR l
t F.
r i 1 i - Safety Evaluation Report, Technical Specifications for Operation of Fort St. Vrain With Region Outlet Temperature Measurement Discrepancies 1
l We are transmitting one copy of the above listed documents as attachments to this letter and 39 additional copies under separate cover.
In accordance with the provisions of 10CFR170 we are forwarding under separate cover a draft in the amount of $4,000.00 for a Class III fee payment.
Based on the February 16, 1982, meeting and the subsequent correspondence as well as resolution of all previous 70% restraint items we believe this submittal constitutes and fulfills all I
requirements for the final release from 70% power restriction.
It is l
requested, therefore, that the Nuclear Regulatory Commission release Fort St. Vrain from the present 70% power restriction, and issue the Technical Specifications for routine operation to 100% power under the provisions of the original License.
If you have any questions or need any further information please contact Mr. Don Warembourg at (303) 571-7436 l
Very truly yours, i
i til -
. R. Lee i
Vice President, Production l
l ORL/alk l
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