ML20148D973
| ML20148D973 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/23/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20148D943 | List: |
| References | |
| NUDOCS 9706020206 | |
| Download: ML20148D973 (3) | |
Text
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j NUCLEAR REGULATORY COMMISSION o
f WASHINGTON, D.C. 2065H001 s,...../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS.203 AND 84 TO FACILITY OPERATING LICENSE NOS. DPR-66 AND NPF-73 DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY BEAVER VALLEY POWER STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-334 AND 50-412
1.0 INTRODUCTION
By letter dated March 10. 1997, the Duquesne Light Company (the licensee) submitted a request for changes to the Beaver Valley Power Station. Unit Nos.
1 and 2 (BVPS-1 and BVPS-2). Technical Specifications (TSs). The requested changes would modify BVPS-1 TS 5.2.1 to add ZIRLO as fuel assembly material and add reference to the Nuclear Regulatory Commission (NRC) approved Topical Report WCAP-12610. " Vantage + Fuel Assembly Reference Core Report." to TS 6.9.1.12 for both units.
j 2.0 EVALUATION BVPS-1 TS 5.2.1 requires fuel rods to be constructed with Zircaloy.
Zircaloy or stainless steel filler rods may be substituted in place of fuel rods in accordance with approved applications of fuel rod configurations. The proposed amendment would modify BVPS-1 TS 5.2.1 to also allow fuel rods to be constructed with ZIRLO and allow fuel assembly reconstitution with ZIRLO filler rods.
The NRC staff approved the ZIRLO fuel design in a safety evaluation dated July 1. 1991, to the Westinghouse Topical Report WCAP-12610 " VANTAGE + Fuel Assembly Reference Core Report." The NRC staff also a) proved LOCA methodologies in another safety evaluation, dated Octo3er 9. 1991, to Westinghouse Topical Reports WCAP-12610. Appendices F. "LOCA NOTRUMP Evaluation Model: ZIRLO Modifications." and G. "LOCA Plant Specific Accident Evaluation." The July 1. 1991, safety evaluation concluded that:
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The mechanical design bases and limits for the ZIRLO clad fuel assembly design are the same as those for the previously licensed Zircaloy-4 clad fuel assembly design, except those for clad corrosion.
2.
The neutronic evaluations have shown that ZIRLO clad fuel nuclear design bases are satisfied and that key safety parameter limits are a)plicable.
The nuclear design models and methods accurately describe the 3ehavior of ZIRLO clad fuel.
3.
The thermal and hydraulic design basis for the ZIRL0 clad fuel is unchanged.
4.
The methods and computer codes used in the analysis of the non-loss-of-coolant-accident licensing basis events are valid for ZIRLO clad fuel, and all licensing basis criteria will be met.
In the October 9. 1991 safety evaluation for WCAP-12610. Appendices F (dealing with large-break-loss-of-coolant-accidents) and G (dealing with small-break-loss-of-coolant-accidents), the NRC staff concluded that the loss-of-coolant-accident analyses and methods used, the same methods a) plied to BVPS-1, demonstrated conformance with the criteria given in 10 CFR 50.46 and 10 CFR Part 50. A)pendix K.
That safety evaluation stated that its conclusions were )ased upon the close similarity between the material properties of the ZIRLO alloy of zirconium to those of other zirconium materials that have been previously licensed for use as cladding material.
Based on this similarity, the NRC staff found that it is ap3ropriately conservative to apply the criteria of 10 CFR 50.46 and 10 C R Part 50.
Appendix K. when reviewing VANTAGE + (ZIRLO) fuel applications, including WCAP-12610. Appendices F and G.
Thus, the NRC staff concludes that the use of ZIRLO fuel up to 60.000 mwd /MTU peak rod average is acceptable for BVPS-1.
The licensee has proposed to add "ZIRLO" in the fuel rod design in TS 5.2.1 in the following sentence:
... Each assembly shall consist of a matrix of Zircaloy or ZIRLO fuel rods...
Based on the above NRC staff evaluation. the NRC staff concludes that the proposed change to add ZIRLO to BVPS-1 TS 5.2.1 is acceptable.
The licensee also proposed to add reference to NRC approved Topical Report.
WCAP-12610. " Vantage + Fuel Assembly Reference Core Report." to TS 6.9.1.12 for both BVPS-1 and BVPS-2.
As noted above, the NRC staff approved the analysis methods of WCAP-12610 in a safety evaluation dated October 9, 1991.
l Therefore, referencing this Topical Report in TS 6.9.1.12 is acceptable.
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3.0 STATE CONSULTATION
In accordance with the Comission's regulations the Pennsylvania State official was notified of the proposed issuance of the amendments. The State official had no comments.
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4.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a 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 j
significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the i
amendments involve no significant hazards consideration, and there has been no public comment on such finding (62 FR 17231).
The amendments also relate to changes in recordkeeping, reporting, or administrative procedures or i
requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (10).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment j
need be prepared in connection with the issuance of the amendments.
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5.0 CONCLUS1Q_N l
The Commission has concluded, based on the considerations discussed above.
j 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.
4 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.
a Principal Contributor:
Donald S. Brinkman 4
l Date: May 23, 1997 4
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