ML20080Q601
| ML20080Q601 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 03/03/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080Q598 | List: |
| References | |
| NUDOCS 9503080419 | |
| Download: ML20080Q601 (2) | |
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- NUCLEAR REGULATORY COMMISSION '
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,v SAFETY EVALUATION BY'THE OFFICE-OF NUCLEAR REACTOR REGULATION l
-RELATED TO'AMENOMENT N0; 142 TO~ FACILITY OPERATING: LICENSE NO. DPR-28 w
' VERMONT YANKEE NUCLEAR POWER CORPORATION 1
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VERMONT YANKEE NUCLEAR POWER STATION l
DOCKET N0.:50-271L i
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1.0 INTRODUCTION
By letter dated December!14, 1994, the Vermont Yankee Nuclear' Power Corporation (the licensee) submitted a request for changes to the Vermont Yankee Nuclear Power Station. Technical. Specifications'(TSs).. The requested:
changes would revise the identification of low reactor pressure instrument trip card from a " slave" trip card designation to a " master" trip card designation.
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l 2.0 EVALUATION The proposed changes to instrument identifications in Tables 3.2.1 and'4.2.1 revise' the identification of low reactor pressure instrument trip cards fros'a -
" slave" trip card designation to a;" master" trip card designation. The licensee plans to install a modification during the:1995' refueling outage to R
satisfy the instrument diversity requirements of the Anticipated Transient Without Scram Rule. As.a result of the modification, the emergency core cooling system low reactor pressure circuitry will be comprised of." master"
. trip cards only. Therefore, the " slave" designation in the current TSs wouldi become ' obsolete.
The licensee has reviewed the design change pursuant to 10 CFR 50;59(a)(2) and-concluded that the change does not involve an unreviewed safety question.
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' Additionally, neither the proposed TS amendment nor the modification change-o o
the design basis, protective function, redundancy, trip point, or logic of the system.
i The change of identification of a. low reactor pressure instrument in Table 4.2.1 from PT-2-128A/B to PS-2-128A/B corrects a typographical error,-is' consistent with designation of that instrument in Table.3.2.1 on Page 39 of the TS, and is purely administrative.
Therefore, the NRC staff concludes that the proposed changes are acceptable.
9503090419 950 3 PDR ADOCK O 271 P
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3.0 STATE CONSULTATION
In accordance with' the Commission's regulations, the Vermont ~ State official was notified of'the proposed issuance of.the amendment. The State official
- had no comments ~.
4.0 ENVIRONMENTAL CONSIDERATION
The amen' ment changes a requirement with respect to installation'or use of a' d
i facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no
- significant increase in the amounts, and no significant change-in the types, of. any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that the amendment involves.no significant hazards consideration, and there has been no public comment on such finding (60 FR 6315). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR. 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
The Commission has concluded,. based'on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of-the public will not be endangered by operation in the proposed manner, (2) such activities.will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common s
defense and security or to the health and safety of.the public.
3 Principal Contributor: D. Dorman Date:
March 3, 1995 7
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