ML20217Q033
| ML20217Q033 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/03/1998 |
| From: | Jeffery Wood CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2516, NUDOCS 9803110324 | |
| Download: ML20217Q033 (2) | |
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- nr Davis-Besse Nuclear Power Station g gg M 5501 North State Route 2 m
Oak Harbor Ohio 43449-9760 Docket Number 50-346 License Number NPF-3 i
Serial Number 2516 March 3. 1998 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 S sject:
Framatome Cogema Fuels Topical Repons LAW-10227P and BAW-10231P Ladies and Gentlemen:
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. The purpose of this letter is to convey Toledo Edison's interest in the NRC's review and approval of two Framatome Cogema Fuels (FCF) Topical Reports which were recently submitted to the NRC by FCF. As described below, NRC approval of these reports would be significantly beneficial to the Davis-Besse Nuclear Power Station (DBNPS).
i On September 30,1997, FCF submitted Topical Report BAW-10227P entitled " Evaluation of Advanced Cladding and Structural Material (M5)in PWR Reactor Fuel" to the NRC. This report provides the physical properties of the "M5" advanced alloy and the analyses that have been performed to demonstrate its suitability as a fuel cladding and structural component material.
Use of this advanced alloy as a cladding material would provide significant improvements relative to the Zircaloy cladding presently in use at the DBNPS.
Toledo Edison stronaly supports FCF's efforts to obtain NRC approval for use of this advanced p
cladding material, 'd intends to utilize MS-clad fuel rods during Cycle 13. Use of the M5 advanced alloy yields improved margins in several design analyses. Fuel rod corrosion for Zin:aloy cladding is currently the limiting burnup factor for fuel at the DBNPS. Use of M5
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cladding at the DBNPS will provide substantially greater margin to the current 100 micron fuel l
clad corrosion limit than is afforded by Zircaloy. Inability to obtain reload fuel utilizing M5 cladding for DBNPS will result in significantly larger reload batches in future operating cycles and may restrict cycle lengths to less than the currently NRC-approved twenty-four months. The M5 advanced alloy also provides a significant benefit in reducing fuel assembly irradiation growth and distortion, since the M5 alloy exhibits considerably less radiation-induced growth relative to Zircaloy.
9803110324 980303 PDR ADOCK 05000346 P
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7 Docket Number 50-346 License Number NPF-3 Serial Number 2516 l
. Page,2 l-It is noted that Title 10 of the Code of Federal Regulations (CFR), Section 50.44, " Standards for j
Combustible Gas Control System in Light-Water-Cooled Power Reactors," Section 50.46, "Accep-(
tance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors," and I
associated Appendix K, "ECCS Evaluation Models," presume the use of Zircaloy or ZIRLO cladding. Since the chemical composition of the M5 alloy differs from the specifications for Zircaloy or ZIRLO, a plant-specific exemption would be required to allow the use of the M5 alloy as a cladding material at the DBNPS, unless these 10 CFR sections are modified to permit the use of other zirconium-based alloys such as the M5 alloy. In addition, a License Amendment would be l
required to revise Technical Specification Section 5.3.1, " Design Features, Reactor Core, Fuel Assemblies," which presently specifies Zircaloy or ZIRLO clad fuel rods.
Pending NRC approval of Topical Report BAW-10227P and the necessary plant-specific exemption and License Amendment, Toledo Edison intends to use the M5 alloy in DBNPS l
operating Cycle 13. Fuel assemblies for Cycle 13 are presently scheduled to be delivered to the j.
DBNPS in February of 2000. In order to complete the design and analysis activities associated i
with this schedule, Toledo Edison requests that the NRC complete their review and approval of BAW-10227P by December 31,1998. If this milestone is not met, the DBNPS will have to utilize Zircaloy-clad reload fuel in Cycle 13, which will have a significant adverse impact on DBNPS fuel management and clad corrosion margins.
In addition, on January 22,1998, FCF submitted Topical Report BAW-10231P entitled i
"COPERNIC - Fuel Rod Design Computer Code." The COPERNIC code is based upon an expanded data base of fuel rod perfc,mance measurements and contains features and improvements, relative to the currently-used TACO 3 code, specific to the M5 alloy. While NRC approval of this Topical Report is not required for the initial use of the M5 alloy-based cladding, Toledo Edison supports an expedited NRC review and approval process for this Topical Report j
so that the full benefits of the M5 alloy can be realized for the DBNPS.
Should you have any questions or require additional information, please contact Mr. James L. Freels, Manager - Regulatory Affairs, at (419) 321-8466.
Very truly yours, V
RJB/MKL/laj cc:
A. B. Beach, Regional Administrator, NRC Region III A. G. Hansen, DB-1 NRC/NRR Projcct Manager S. J. Campbell, DB-1 NRC Senior Resident Inspector Utility Radiological Safety Board
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