ML20205P690
| ML20205P690 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 03/31/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205P681 | List: |
| References | |
| NUDOCS 8704030346 | |
| Download: ML20205P690 (2) | |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 99 TO FACILITY OPERATING LICENSE NO. DPR-28 VERMONT YANKEE NUCLEAR POWER CORPORATION VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271
1.0 INTRODUCTION
10 CFR 50.55a(g) requires ASME Code Class 1, 2 and 3 components (including supports) of a boiling water-cooled nuclear reactor facility to meet the requirements set forth in Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, of the ASME Boiler and Pressure Vessel Code.
Each facility is required to have an inspection program plan which is updated every ten years to meet the requirements of the latest approved edition and addenda of Section XI. This program plan is submitted to the NRC for review of the licensee's compliance with the Regulation which entails verifying that the correct systems, sampling plans, and non-destructive examination methods have been incorporated, and evaluating the efficacy of proposed alternative examinations and tests to be performed in lieu of the requirements.
By letter dated January 30, 1979, Vermont Yankee Nuclear Power Corporation proposed a modification to the Technical Specifications for the Vermont Yankee Nuclear Power Station. Amongst the many changes proposed was a change to section 4.6.E which presently requires that the inservice examinations of the piping, components, and their supports be performed in accordance with an early edition of the ASME Code Section XI.
Because this request was included in a group of requests which are still under review, and a delay acting on this request would result in unnecessary and burdensome testing, we are acting on this request separately from the other requests.
2.0 EVALUATION Technical Specification 4.6.E for the Vermont Yankee Nuclear Power Station requires an inservice inspection program which essentially conforms to the requirements of the 1974 Edition ASME Section XI, up to and including the 1975 Summer Addenda except piping examinations (Cat. F & J) shall be per the requirements of ASME Code Section XI,1974 Edition,1976 Summer Addenda, Appendix III. The regulation 10 CFR 50.55a(b requires that the plant be examined in accordance with the 1977 Edition of Section XI with Addenda to Summer of 1979. Since the Technical Specification examination is to a different edition of the ASME Code than the regulation requirements, the plant must examine to both sets of requirements with the inherent conflicts and extra overlapping examinations. Examination to both sets of requirements, provides marginal or no extra benefits considering the burden of doing the extra examination.
8704030346 870331 PDR ADOCK 05000271 P
O t The licensee proposes to modify the requirements of 4.6.E to require that the inservice inspection of the plant be performed in accordance with Section XI of the Code Edition required by the regulation 10 CFR 50.55a(g).
This will keep the Technical Specification requirement in accordance with the regulations as modified throughout the life of the plant without the extra burden of conforming to two different editions of the ASME Boiler and Pressure Vessel Code Section XI. This change is in accordance with the regulations and is acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
S This amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The staff has determined that the amendment involves 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. 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.
4.0 CONCLUSION
We have 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, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
B. Turov11n Dated March 31, 1987