ML20210K070
| ML20210K070 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 01/31/1986 |
| From: | Haroldsen R, Vanderbeek R EG&G IDAHO, INC. |
| To: | NRC |
| Shared Package | |
| ML20210K074 | List: |
| References | |
| CON-FIN-D-6001 TAC-53002, TAC-53840, NUDOCS 8604070522 | |
| Download: ML20210K070 (8) | |
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Enclosura 2 CONFORMANCE TO GENERIC LETTER 83-28 ITEMS 3.1.3 AND 3.2.3 FORT ST. VRAIN UNIT NO. 1 R. VanderBeek/R. Haroldsen i
Published January 1986 EG1G Idaho, Inc.
Prepared for the U.S. Nuclear Regulatory Comission Washington, D.C.
20555 der DOE Contract No. OE-AC07-761001570 FIN No. 06001 O '( h
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ABSTRACT This EG&G Idaho, Inc., report reviews the Fort St. Vrain Unit No.1 submittal for conformance to Generic Letter 83-28, items 3.1.3 and 3.2.3.
FOREWORD This report is supplied as part of the program for evaluating licensee / applicant conformance to Generic Letter 83-28 " Required Actions based on Generic Implications of Salem ATWS Events." This work is conducted for the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of System Integration by'EG&G Idaho, Inc., NRC Licensing Support Section.
The U.S. Nuclear Regulatory Commission funded the work under the authorization, B&R 20-19-19-11-3, FIN NO. 06001.
Docket No. 50-267 TAC Nos. 53002 and 53840 11
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CONTENTS A B ST RA CT..............................................................
11 FOREWORD..............................................................
11 T.
INTRODUCTION.....................................................
1 2.
REVIEW REQUIREMENTS..............................................
2 3.
REVIEW RESULTS FOR FORT ST. VRAIN UNIT NO. 1.....................
3 3.1 Evaluation 3
3.2 Conclusion 3
4.
REFERENCES........................................................
4 8
111
CONFORMANCE TO GENERIC LETTER 83-28 ITEMS 3.1.3 AND 3.2.3 FOR FORT ST. VRAIN UNIT N0. I 1.
INTRODUCTION I
On July 8, 1983, Generic Letter No. 83-28 was issued by D. G. Eisenhut, Director of the Division of Licensing, Nuclear Reactor Regulation, to all licensees of operating reactors, applicants for operating licenses, and holders of construction permits. This letter included required actions based on generic implications of the Salem ATWS events. These requirements have been published in Volume 2 of NUREG-1000,
" Generic Implications of ATWS Events at the Salem Nuclear Power Plant".2 This report documents the EG&G Idaho, Inc. review of the submittal from Fort St. Vrain Unit No. 1 for conformance to items 3.1.3 and 3.2.3 of Generic Letter 83-28. The submittal and other documents utilized in this evaluation are referenced in section 4 of this report.
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REVIEW REQUIREMENTS Item 3.1.3 (Post-Maintenance Testing of Reactor Trip System Components) requires licensees and applicants to identify, if applicable, any post-maintenance test requirements for the reactor trip system (RTS) in existing technical specifications which can be demonstrated to degrade rather than enhance safety.
Item 3.2.3 extends this same requirement to include all other safely-related components. Any proposed technical specification changes resulting from this action shall receive a pre-implementations review by NRC.
The relevant submittal from the Fort St. Vrain Unit No. I was reviewed to determine compliance with items 3.1.3 and 3.2.3 of the Generic Letter.
First, the submittal from this plant was reviewed to determine that these two items were specifically addressed. Second, the submittal was checked to determine if there were any post-maintenance test items specified by the technical specifications that were suspected to degrade rather than enhance safety. Last, the submittal was reviewed for evidence of special conditions or other significant information relating to the two items of Concern.
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3.
REVIEW RESULTS FOR FORT ST. VRAIN UNIT NO. 1 3.1 Evaluation Public Service Company of Colorado, the licensee for the Fort St. Vrain High Temperature Gas-Cooled Reactor (HTGR), provided an initial response to items 3.1.3 and 3.2.3 of Generic Letter 83-28 on November 4, 1983.3 The contents of the initial response was inconclusive respecting the concerns of items 3.1.3 and 3.2.3.
A letter requesting clarifying information was sent to the licensee on May 8,1985. The 5
licensee responded with a submitta1 dated June 12, 1985.
In the submittal the licensee states that no post maintenance testing requirements have been found in the technical specifications that degrade safety for either the RTS components or thr non-RTS safety-related components.
3.2 Conclusion The licensee's response meets the requirements of items 3.1.3 and 3.2.3 and is acceptable.
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REFERENCES 1.
NRC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits,
" Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28)", July 8, 1983.
2.
Generic Implications of ATWS Events at the Salem Nuclear Power Plant, NUREG-1000, Volume 1, April 1983; Volume 2, July 1983.
3.
Public Service Company of Colorado letter to NRC, O. R. Lee to D. G. Eisenhut, Director, Division of Licensing, NRC, " Response to Generic Letter 83-28", November.4,1983, P-83359.
4 NRC Letter, E. H. Johnson to 0. R. Lee, Public Service Company of Colorado, " Request for Additional Information or Indicated Items of Generic Letter 83-28", May 8, 1985.
5.
Public Service Company of Colorado letter to NRC, J. W. Gahm to E. H. Johnson, Regional Administrator, Region IV, NRC, " Response to Generic Letter 83-28", June 12, 1985, P85204.
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This EG&G Idaho, Inc. report provides a review of the submittals for Fort St. Vrain Unit No. I for conformance to Generic Letter 83-28 Items 3.1.3 and 3.2.3.
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