ML20065K085
| ML20065K085 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 09/30/1982 |
| From: | Brey H PUBLIC SERVICE CO. OF COLORADO |
| To: | Clark R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20065K087 | List: |
| References | |
| FSV-63, P-82430, NUDOCS 8210060273 | |
| Download: ML20065K085 (2) | |
Text
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public Service Company fP(Cdnndo O
5909 East 38th Avenue, Denver, Colorado 80207 September 30, 1982 Fort St. Vrain Unit No. 1 P-82430 F90-63 Mr. Robert A. Clark Chief, Operating Reactors Branch 3 Division of Licensing Office of Nuclear Reactur Regulation U.S. fluclear Regulatory Commission Washington, D.C.
20533 00CKET NO. 50-267
SUBJECT:
Fort St. Vrain Inservice Inspection and Testing - Additional Surveillance Requirements
REFERENCE:
- 1) PSC Letter, J.K. Fuller to James Miller, P-80064 dated March 31, 1980 l
- 2) PSC Letter, J.K. Fuller to Steven A. Varga, P-80034, dated March 3, 1980 Gentlemen:
PSC has submi tted for your review a preliminary update of the inservir e inspectioa and testing program for all Fort St.
Vrain systems and equipment identified as priority category I.
Following an independent rt. view under the direction of Los Alamos fiational Laboratory, it was agreed at the meeting held on July 29,1982 at Fort St. Vrain that PSC would further investigate the feasibility of additional examinations and tests for:
the PCRV penetrations secondary boundaries, including flow restrictors, restraints and limit stops; and
_ P..
a the steam generator bimetallic welds.
Enclosed for your review are the results of these aduitional investigations, together with draft Technical Speci fications that reflect proposed additional exaniinations and tests.
Enclosure (1) contains an evaluation of the additional surveillance requirements for the PCRV penetrations and is a supplement to PSC Letter P-60034 dated liarch 3,1980.
An attachment to this enclosure provides a draft for a new prr, posed Technical Specification SR5.2.28 PCRV Penetrations and Closures Surveillance - which incorporates the examination requirements for the refueling penetration holddown plates, previously submitted as SR5.2.24 in letter P-80034.
Enclosure (2) contains an evaluation of the additional surveillance requirements for the steam generator bimetallic welds and is a supplement to PSC Letter P-80064 dated March 31, 1980.
An attachment to this enclosure provides a draft for a new proposed Technical Specification SRS.3.11 Steam Generator Bimetallic Welds Surveillance.
These addi tional surveillance requirements will be included in the forthcoming formal submittal for changes to the Technical Specifications to update the Fort St. Vrain inservice inspection and testing program and complete the PSC commitment included in the Safety Evaluation Report of January 20, 1972.
Please direct any questions or comments you n;ay have concerning the submittals o.r PSC ISI program to Mr. M. H. Holmes, (303) 571-6711.
Very truly yours, MC H. L. Brey, Manager i
Nuclear Engineering Division HLB /JRJ:pa Attachment i
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