ML20086H855

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Safety Evaluation Supporting Amends 189 & 71 to Licenses DPR-66 & NPF-73,respectively
ML20086H855
Person / Time
Site: Beaver Valley
Issue date: 06/27/1995
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20086H845 List:
References
NUDOCS 9507180298
Download: ML20086H855 (2)


Text

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.f 'E009 y-1 UNITED STATES a

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NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. 20555-0001

'+9.....,o SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 189 AND 71 TO FACILITY OPERATING LICENSE NOS. OPR-66 AND NPF-73 DV0VESNE LIGHT COMPANY OHI0 EDIS0N COMPANY PENNSYLVANIA POWER COMPANY THE CLEVELAND ELECTRIC ILLVMINATING COMPANY THE TOLEDO EDIS0N COMPANY BEAVER VALLEY POWER STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-334 AND 50-412

1.0 INTRODUCTION

By letter dated June 8, 1993, as supplemented June 15, 1995, the Duquesne Light Company (the licensee) submitted a request for changes to the Beaver Valley Power Station, Unit Nos. I and 2 (BV-1 and BV-2), Technical Specifications (TSs).

The requested changes would revise item 2 of TS 6.9.1.14, " Core Operating Limits Report," for Unit I and Unit 2, to specify the use of the BASH methodology instead of an earlier Westinghouse methodology.

The June 15, 1995, letter provided typed final TS pages for issuance of these amendments and included minor editorial changes that did not change the initial proposed no significant hazards consideration determination or expand the scope of the original Federal Reaister notice.

2.0 EVALVATION Generic Letter (GL) 88-16, " Removal of Cycle-Specific Parameter Limits From Technical Specifications," provided guidance for modifying TSs that have cycle-specific parameter limits.

This guidance included the addition of TS 6.9.1.14, " Core Operating Limits Report," to the Administrative Controls

.section of the BV-1 and BV-2 TSs. The Core Operating Limits Report (COLR) specifies the values of cycle-specific parameter limits that are applicable for the current fuel cycle.

The COLR for each reload cycle shall be submitted to the NRC before each reload cycle and before operation with a new parameter limit if the limit is changed during a reload cycle.

TS 6.9.1.14 also requires that the values of the cycle-specific parameter limits shall be established using NRC-approved methodology and shall be consistent with all applicable limits of the safety analysis.

The current list of analytical methods specified in items 1 through 5 of TS 6.9.1.14 were implemented on April 26, 1990, by License Amendment Nos. 154 and 31 for BV-1 and BV-2 respectively.

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. 4 The BASH methodology is a Westinghouse improved and updated methodology which can be used to evaluate a large break loss-of-coolant accident.

The specific change would revise item 2 of TS 6.9.1.14 for Unit I and Unit 2 to specify the use of the BASH methodology which is described in WCAP-10266-P-A, Revision 2, and WCAP-ll524-NP-A, Revision 2, instead of WCAP-9220-P-A, Revision 1, which described an earlier Westinghouse methodology.

The BASH methodology was approved by the NRC staff on November 13, 1986; therefore,.we find the proposed change of updating TS 6.9.1.14 to reference use of the BASH methodology acceptable.

3.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendments. The State official had no comments.

4.0 ENVIRONMENTAL CONSIDERATION

The 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 NRC 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 individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (58 FR 36433).

The amendments also relate to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (c)(10).

Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

5.0 CONCLUSION

The Commission has 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, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) 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: Donald S. Brinkman Date:

June 27, 1995

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