ML20078G828
| ML20078G828 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/06/1983 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078G827 | List: |
| References | |
| TAC-51596, TAC-51597, NUDOCS 8310130205 | |
| Download: ML20078G828 (2) | |
Text
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UNITED STATES g $ -g NUCLEAR REGULATORY COMMISSION z,%gd,jj WASHINGTON. D. C. 20555' Q Rf SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0.
76 TO FACILITY OPERATING LICENSE N0. DPR-24 AND AMENDMENT NO.
80 TO FACILITY OPERATING LICENSE N0. DPR-27 WISCONSIN ELECTRIC POWER COMPANY POINT BEACH NUCLEAR PLANT, UNIT NOS. 1 AND 2 4
DOCKET N05. 50-266 AND 50-301 Introduction By letter dated May 4, 1983 Wisconsin Electric Power Company (licensee) re-4 quested several changes to the Technical Specifications (TS) and related bases. These changes were submitted to clarify and correct specific portions of the specifications and bases.
Discussion and Evaluation A revision to the basis for TS 15.3.1.A at page 15.3.1-3a was proposed to be consistent with the intent of the limiting conditions for operation which require that, when no decay heat removal method is in operation, all operations causing an increase in the reactor decay heat load or a reduction in boron concentration shall be suspended.
A revision to the basis on page 15.3.3-9 has been made to correct an incon-sistency with TS 15.3.3.B regarding operability of containment fan coolers.
Proposed revisions to TS 15.3.10.C(1)(c), 15.3.10.C(1)(d), 15.3.10.D(1) and 15.3.10.D(2) have been submitted to clarify the conditions during which rod control cluster assemblies are considered misaligned or inoperable.
The misalignment has been clarified to refer to a deviation between the rod position indication and the bank demand position.
This is consistent with the wording in the Standard Technical Specifications for Westinghouse Pres-surized Water Reactors.
I The last requested TS change relates to the definition of the surveillance frequency code "R".
The present TS defines "R" as each refueling shutdown i
(but not to exceed 20 months).
The proposed change revises frequency code R to mean each refueling interval (not to exceed 18 months)..
This allows surveillance testing not requiring shutdown conditions to be accomplished at power during the refueling interval and is consistent with the language of the Standard Technical Specifications for Westinghouse Pressurized Water Reactors.
The staff has reviewed the licensee's proposed changes and agrees that they l
are administrative in nature and serve to clarify or correct the intent of the technical specifications and their bases.
The staff, therefore, finds them acceptable.
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8310130205 831006 PDR ADOCK 05000266 P
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Environmental Consideration We have determined that the amendnents do not authorize a change in effluent ' types or total amounts nor an increase in power level and
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will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendments involve an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR {51.5(d)(4), that an environmental, impact statement or negative declaration and environ-mental impact appraisal need not be prepared in connection with the issuance of the 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 these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Date:
October 6, 1983 Principal Contributors:
T. G. Colburn
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