ML20072B946
| ML20072B946 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 02/22/1983 |
| From: | Lee O PUBLIC SERVICE CO. OF COLORADO |
| To: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| Shared Package | |
| ML20072B947 | List: |
| References | |
| P-83072, NUDOCS 8303080088 | |
| Download: ML20072B946 (2) | |
Text
PUBLIC SERVICE COMPANY OF COLORADO P.
O.
BOX 840.
DENVER. COLORADO 80201 OSCAR R. LEE February 22, 1983 me mo w.'
Fort St. Vrain Unit No. 1 k((Q(((]
P-83072 l
I i
FEB 28 l983 L
i Mr. John T. Collins, Regional Administrator
^
Region IV
^
Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011 Docket No. 50-267
Subject:
Revised Proposal to Update the In-Service Inspection and Testing Program Technical Specification Requirements
Reference:
P-82436, Lee to Clark, dated October 15, 1982
Dear Mr. Collins:
This letter is to propose changes to the Fort St. Vrain Technical Specifications pursuant to the requirements of the in-service inspection and testing program.
The changes proposed are revised versions of those proposed in the referenced letter and incorporate suggestions made by Mr. Philip Wagner of your staff. This proposal supercedes any previous proposals regarding the same subsect matter.
Sections 2 and 5 of the Technical Specifications are affected by the changes. Those changes to Section 2 are included in Attachment 2 and those to Section 5 in Attachment 3.
Please note that Attachment 3 provides Section 5 in its entirety at the request of Mr. Wagner.
A summary of the individual changes is provided in Attachment 1, and the Safety Analysis Report for the proposed update is provided in.
The Nuclear Regulatory Commission's License Fee Management Branch has Q
tietermined that these changes will involve the consideration of a safety issue, so a youncher for the Class III fee of $4,000 is enclosed.
We request your concurrence with the proposed revisions as socn as possible. An approval date that is later than March 20, 1983, could create a situation (per the present specification, SR 5.2.1) that would require a plant shutdown and depressurization for the purpose 8303080088 830222 PDR ADOCK 05000267 P
PDR j
i Mr. John Collins P-83072 of testing one of the prestressed concrete reactor vessel rupture discs.
In the event that your approval cannot be obtained by this date, we request that the testing described above be deferred according to the newly proposed revision to SR 5.2.1.
If you have any questions, please contact Mr. Don Warembourg at (303) 785-2224.
Very truly yours, O. R. Lee Vice President Electric Production ORL/cls Enclosures a