ML20134A519
| ML20134A519 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/22/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20134A518 | List: |
| References | |
| TAC-59060, TAC-59061, NUDOCS 8511070183 | |
| Download: ML20134A519 (2) | |
Text
- Q Ktt k UNITED STATES
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p, NUCLEAR REGULATORY COMMISSION 5
'j WASHINGTON, 0. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS.98 AND 102TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 WISCONSIN ELECTRIC POWER COMPANY POINT BEACH NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-266 AND 50-301 Introduction In a letter from C. W. Fay to H. R. Denton dated June 17, 1985 the Wisconsin Electric Power Company (the licensee) requested amendments to Facility Operating Licenses DPR-24 and DPR-27 for Point Beach Nuclear Plant, Units 1 and 2 (PBhP),
respectively. The changes would revise the capsule removal schedule in the PBNP reactor vessel material surveillance program. The PBNP reactor vessel material surveillance program must meet the requirements of Appendix H,10 CFR 50, which became effective on July 26, 1983. Appendix H,10 CFR 50 requires that the surveillance program meet the requirements of ASTM E 185-82 to the extent prac-tical.
Evaluation ASTM E 185-82 requires that the PBNP reactor vessel surveillance program have a minimum of five capsules and the last capsule should be withdrawn when the capsule neutron fluence is between one and two times the peak vessel end-of-life value. Other capsules are to be withdrawn at earlier times in the vessel's life in order to detennine the exter.t of neutron irradiation damage to the PBNP reactor vessel beltline materials.
The change in schedule requested would extend the removal dates for the final capsule in Unit I to a period corresponding to 110% of the peak vessel end-of-life neutron fluence and would extend the removal dates for the last two capsules in Unit 2 to the periods corresponding to 90% and 110% of the peak vessel end-of-life neutron fluence. Capsules have been previously withdrawn from the PBNP reactor vessels at earlier times to determine the extent of neutron irradiation damage.
The staff has detennined that the proposed reactor vessel surveillance capsule withdrawal schedules meet the requirements of ASTM E 185-82 as incorporated by reference into 10 CFR Part 50 Apoendix H and are, therefore, acceptable.
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. ENVIRONMENTAL CONSIDERATION These amendments involve a change in the 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 amendments involve 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 individuel or cumulative occupational radiation exposure. The Commission has previously published a proposed finding that these amendments involve no significant hazards consideration and there has been no public comment on such finding. Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 651.22(c)(9).
Pursuant to 10 CFR 951.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Date: October 22, 1985 Principal Contributor:
B. Elliot T. Colburn 0
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