ML20054L443

Forwards Application for Amend to App a of License DPR-34 Releasing Facility from 70% Power.Nrc Should Release Facility from 70% Power Restriction & Issue Tech Specs for Routine Operation at 100% Power

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: ML20054L443 ML20054L448 ML20054L451 ML20054L453 ML20054L459
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 Definition 2.22, Comparison Region (&M ,

t h0

8207080127 820706

6) )

! PDR ADOCK 05000267 i

. P PDR l_ __ _ ,_ , - ___ _ . _ _ _ _ _ , , _ _ _ _ _ _ _ _ _ _ _ - . _ . _ _ _ _ _ . . . _ _ . - _ _ . _ . , _

t F.

r i

1

! i Attachment 0 - 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

[

l Attachments l i

i I

l

[

i I

[

! t i

I i

i

_.