ML20210M836
| ML20210M836 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 09/23/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210M833 | List: |
| References | |
| NUDOCS 8610060046 | |
| Download: ML20210M836 (2) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS.79 AND 72 TO FACILITY OPERATING LICENSE N05. DPR-42 AND DFR-60 NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT N05. 1 AND 2 DOCKET N05. 50-282 AND 50-306 Introduction By application dated February 21, 1986, Northern States Power Company (NSP) requested amendments to the facility operating licenses for Prairie Island Nuclear Generating Plant, Unit Nos. 1 and 2.
The proposed amendments would change the expiration date for the Unit 1 Facility Operating License, DPR-42, from June 25, 2008 to August 9, 2013, and change the expiration date for the Unit 2 Facility Operating License, DPR-60, from June 25, 2008, to October 29, 2014.
Discussion and Evaluation Section 103.c of the Atomic Energy Act of 1954 provides that a license is to l
be issued for a specified period not exceeding 40 years.
10 CFR 50.51 speci-l fies that each license will be issued for a fixed period of time not to exceed 40 years from date of issuance.
10 CFR 50.56 and 10 CFR 50.57 allow the is-suance of an operating license pursuant to 10 CFR 50.51 after the construction of the facility has been substantially completed, in conformity with the con-j struction permit and when other provisions specified in 10 CFR 50.57 are met. The currently licensed term for the Prairie Island Unit Nos.1 and 2 is 40 years commencing with the issuance of the construction permits (June 25,1968).
Accounting for the time that was required for plant construction, this represents an effective operating license term of 34 years and 11 months for Unit 1 and 33 years and eight months for Unit 2.
Consistent with Section 103.c of the Atomic Energy Act and Sections 50.51, 50.56 and 50.57 of the Commission's regulations, the licensee, by its application of February 21, 1986, seeks extensions of the operating license terms for Prairie Island Units 1 and 2 such that the fixed period of the licenses would be 40 years from the date of operating license issuance.
The licensee's request for extension of the operating licenses is based on the fact that a 40-year service life was considered during the design and construc-tion of the plant. Although this does not mean that some components will not wear out during the plant lifetime, design features were incorporated which maximize the inspectability of structures, systems and equipment.
Surveillunce I
and maintenance practices which were implemented in accordance with the ASME 8610060046 860923 PDR ADOCK 05000282 p
. code and the facility Technical Specifications provide assurance that any un-expected degradation in plant equipment will be identified and corrected.
The design of the reactor vessel and its internals considered the effects of 40 years of operation at full power and a comprehensive vessel material sur-veillence program is maintained in accordance with 10 CFR Part 50, Appendix H.
We have completed our analyses related to the pressurized thermal shock (PTS) rule, 10 CFR 50.61, for both units.
By our letters dated June 23, 1986, the licensee was given results showing that the most critical weld materials for both reactor vessels meet the criterion of 10 CFR 50.61 by a very large margin at the end of the 40-year operating life.
In addition to these calculations, surveillance capsules placed inside the reactor vessels provide a means of monitoring the cumulative effects of power operation.
Aging analyses have been performed for all safety-related electrical equipment in accordance with 10 CFR 50.49, 'Tnvironmental qualification of electrical equipment important to safety for nuclear power plants," identifying qualified lifetimes for this equipment. These lifetimes will be incorporated into plant equipment maintenance and replacement practices to ensure that all safety-related electrical equipment remains qualified and available to perform its safety function regardless of the overall age of the plant.
Based upon the above, it is concluded that extension of the operating licenses for Prairie Island Unit Nos.1 and 2 to allow a 40-year service life is con-sistent with the safety analysis in that all issues associated with plant aging have already been addressed. Accordingly, we find the proposed change to the expiration date of the Prairie Island Unit Nos. I and 2 Facility Operat-ing Licenses to be acceptable.
Environmental Consideration A Notice of Issuance of an Environmental Assessment and Finding of No Significant Impact relating to the proposed extension of facility operating license termination dates for the Prairie Island Unit Nos. 1 and 2 was published in the Federal Register l
on I
l Conclusion
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We have concluded, based on the considerations discussed above, that (1) there is a 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
D. Dilanni Date: September 23, 1986 l
f Distrbution Copies:
Docket File 50-282/306 NRC PDR Local PDR PAD #1 r/f PAD #1 p/f TNovak, Actg Div Dir Glear DDilanni PShuttleworth NThompson, DHFT ELD LHarmon EJordan BGrimes JPartlow EButcher, TSCB TBarnhart(4)
WJones F0B, DPLA RBallard CBerlinger JMilhoan ACRS (10)
OPA LFMB (w/cy of TAC 61079 & 61080 w/Amd No. & dated issued)