ML20247E255
| ML20247E255 | |
| Person / Time | |
|---|---|
| Site: | Millstone |
| Issue date: | 03/27/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247E248 | List: |
| References | |
| NUDOCS 8904030012 | |
| Download: ML20247E255 (2) | |
Text
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%l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 32 TO FACILITY OPERATING LICENSE NO. NPF-49 NORTHEAST NUCLEAR ENERGY COMPANY, ET AL.
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 DOCKET NO. 50-423 INTRODtlCTION By application for license amendment dated January 6,1989 as supplemented by letter dated January 20, 1989, Northeast Nuclear Energy Company, et al.
(the licensee), requested changes to Millstone Unit 3 Technical Specification (TS) 4.7.10b, " Snubbers", to allow an approximate two month extension in the snubber visual inspection interval, to permit continued operation until the next refueling outage.
DISCUSSION AND EVALUATION Technical Specification 4.7.10b requires that snubbers on safety-related components and piping be visually inspected at various intervals depending upon snubber failure rate determined by the previous inspection. An increased number of snubber failures would decrease the surveillance intervals from as great as 18 months 25% to as little as 31 days 25%. The current inspection interval for Millstone Unit 3 is 18 months for all snubbers except for Type PSA-1/2 and PSA-1/4, which have a 12 month interval. During the last round of inspections, the licensee found all snubbers operable which enabled the licensee to increase the inspection interval for the Type PSA-1/2 and PSA-1/4 snubbers to 12 months. The next required inspection interval would end April 30,1980. The licensee has requested that the surveillance interval be extended to allow snubber inspection during the next refueling outage, which is scheduled to begin on May 20, 1989. The proposed change to the TS would also have the effect of restarting the inspection interval so that the subsequent inspection intervel will not be unduely short.
In reviewing the licensee's proposed TS change, the NRC staff notes that it is unlikely that a one time extension of approximately 20% of the snubber inspection interval will appreciably increase the incidence of undetected snubber failure. Moreover, although there may be small, localized, reductions in safety margins with regard to seismic resistance of safety systems due to undetected snubber failures, the overall reduction in safety margin will not be significant. Accordingly, the proposed change to TS 4.7.10b is acceptable.
8904030012 890327 PDR ADOCK 05000423 P
ENVIRONMENTAL CONSIDERATION This amendment changes a requirement with respect to installation or use 1
of a facility canponent located within the restricted area as defined in 4
10 CFR Psrt 20. We have determined that the amendment involves no j
significant increase in the amounts, and no significant change in the types, of any effluents that may be released.offsite, and that there is j
i no significant increase in individual or cumulative occupational radiation exposure. The staff has previously published a proposed finding that the amendment involves no significant hazards consideration and there has been no i
public comment on such finding. Accordingly, the amend-ment 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.
l 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 (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated:
March 27, 1989 Principal Contributor: D. Jaffe l
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