ML20205S114

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{{#Wiki_filter:__ [d(*M% fg UNITED STATES g g NUCLEAR REGULATORY COMMISSION j WASHINGTON, D. C. 20555 5 7 %...../ SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO GENERIC LETTER 83-28, ITEM 4.5.2 REACTOR TRIP SYSTEM RELIABILITY ON-LINE TESTING PUBLIC SERVICE COMPANY OF COLORADO FORT ST.-VRAIN NUCLEAR GENERATING STATION DOCKET NO. 50-267

1.0 INTRODUCTION

AND SUMARY Generic Letter 83-28 was issued by NRC on July 8, 1983, indicating actions to be taken by applicants and licensees based on the generic implications of the Salem ATWS events. Item 4.5 states a staff position which requires on-line functional testing including independent testing of the diverse trip features of the reactor trip breakers of the reactor trip system for all plants. Item 4.5.2 requires applicants and licensees with plants not currently designed to permit periodic on-line testing to justify not making modifications to permit such testing. By {{#if: 

| {{#if:{{#show:ML20205S114|?site|limit=1|link=none}}
  | [[letter::{{#ask:from::[[site::{{#show:ML20205S114|?site|limit=1|link=none}}]]Issue date::November 4, 1983|limit=1|link=none|searchlabel=}}|letter dated November 4, 1983]]
  | {{#ask:from::Issue date::November 4, 1983|limit=0|searchlabel=letter dated November 4, 1983 }}
  }}
| {{#if:{{#show:ML20205S114|?site|limit=1|link=none}}
  | {{#if:{{#ask:[[site::{{#show:ML20205S114|?site|limit=1|link=none}}]]Issue date::November 4, 1983!~Information Notice*!~Press Release*}}
    | [[letter::{{#ask:[[site::{{#show:ML20205S114|?site|limit=1|link=none}}]]Issue date::November 4, 1983!~Information Notice*!~Press Release*|limit=1|link=none|searchlabel=}}|letter dated November 4, 1983]]
    | letter dated November 4, 1983
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  | letter dated November 4, 1983
  }}

}}, Public Service Company of Colorado (the licensee) responded to the staff position regarding Item 4.5.2 of. Generic Letter 83-28. Our review of this response finds it to be acceptable. 2.0 EVALUATION The licensee states that Fort St. Vrain is designed to allow on-line testing of the reactor trip system. The staff's review of the licensee's response and the FSAR' indicates that the design uses four independent contactors instead of reactor trip breakers which can be independently tested at power.

3.0 CONCLUSION

The staff finds that the Fort St. Vrain Nuclear Generating Station is designed to permit on-line functional testing of the reactor _ trip system, including independent testing of the reactor trip contactors. Thus, the licensee meets the staff position of Item 4.5.2 of Generic Letter 83-28. Principal Contributor: A. Toalston Dated: MAR 311987 'B704060525 870331 PDR ADOCK 05000267 P PDR}}

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