ML20091A690
| ML20091A690 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/21/1992 |
| From: | Shelton D CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2027, NUDOCS 9203300115 | |
| Download: ML20091A690 (3) | |
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@ CIENTERIOR V
ENERGY Donald C. Shelton 300 Madison Avenue Vice President Nuclear Toledo, OH 43652-0001 Davs Besse (419)249 2300 Doci:e t Number 50-346 1.icense Number NPF-3 Serial Number 2027 March 21, 1992 linited States Nuclear Regulatory Commission Document Control Desk Vashingion, D.C.
20555 Sr5}ect: Nuclear Regulatory Commission Review of Current Babcock and Vilcox Fuel Company Topical Report Submittals Gentlemen:
In September 1991, the Babcock.and Vilcox Fuel Company (BWFC) submitted and requested Nuclear Regulatory Commission (NRC) review and appro/al of three topical reports: NEMO, FRGPC, and CROV8.
The NRC's approval of these topical reports is very important to Toledo Edison's (TE) immediate and long term fuel management objectives for the Davis-Besse Nuclear Power Station (DBNPS), Unit Number 1.
A description of these three topical reports and their specific application to the DBNPS is attached. The benefits associated with the implementation of these irnpi oved met hodologies are significan t to the DBNPS.
Any delay in the NRC's review and approval of these topical reports vould be of serious concern to TE as core design for Cycle 9 vill soon commence at the BVFC using NEMO. Toledo Edison understands, from conversations with the BVFC, that the NRC review of NEMO is scheduled for completion in May 1992.
This date matches fairly well with the needs of TE.
Toledo Edison also understands that the NRC intends to hegin the review of FRCPC and CROV8 after October 1, 1992. This also meets TE's needs,ssuming that these reviews are completed by March 31, 1993.
Dite to their importance to TE's fuel management objectives and upcoming core design decisions, TE requests that the-NRC confirm by March 31, 1992 the NhC's review schedule for these topical reports, o :-f o.
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Operahng Compan:es Chweiend E;ectnc lHuminating Toledo Ed' son
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1 Docket Number 50-346 License Number NPF-3' Serial Number 2027
.. Page 2 If you have any questions, please contact Mr. R. V. Schrauder, Manager - Nuclear Licensing, at (419) 249-2366.
Very truly yours, i
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6 KBR/dlm Attachment cc:
A. B. Davis, Regional Administrator, NRC Region III J. B. Hopkins, NRC/NRR DB-1 Senior Project Manager V. Levis, NRC Region III, DB-1 Senior Resident Inspector Utility Radiological Safety Board l
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Docket Number 50-346 a
License Number NPF-3 Serial Number 2027 Attachment Page 1 Babcock and Vilcox Fuel Company Computer Codes under NRC Reviev NEMO is BVFC's new advanced nodal code.- BVFC expects to use NEMO for the Davis-Besse Nuclear Power Station (DBNPS) Cycle 9. reload safety analysis. Therefore, the core design vill be done on this basis.
Since NEMO provides different results than the old PD0 methodology, a design developed for Cycle 9 based on the NEMO code vould not be i
acceptable when analyzed with PDO.
Overall, NEMO allows a significantly better core design than PDQ, such that if NEMO vere not-to be topically approved by the NPC in time for the Cycle 9 design, it vould be very difficult to meet the design requirements for the Cycle 9 reload as it is currently being planned, FRGPC refers to a fuel burnup limit based on internal fuel pin pressure. This limit is one of the greatest constraints on reload design. The Cycle 9 design vill require the existing pin pressure burnup limit, which is based on TACO 2 and limited by syucem pressure, to be extended using TACO 3 and ERL.'C if the desired cycle length is to i
be licensed.
CROV8 is BVFC's improved fuel rod cladding creep collapse predictor code. This code vill allow internal fuel pin prepressure to be reduced, thereby allowing a higher burnup limit.
The implementation of both CROV8 and FRGPC is required to achieve the DBNPS's minimur desired burnups in the near term.
If CROV8 is not topically approved by the NRC prior to the fabrication of the Cycle 9 reload fuel, currently scheduled to begin in September 1992, then a higher prepressure, with an associated loss of burnup capability for that reload batch of fuel, vill occur. While a lover burnup limit for this batch of fuel vill probably be acceptable for the Cycle 9 reload, the lover prepressure is certainly requiced for the Cycle 10 reload and beyond.
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