NRC-92-0098, Submits Addl Info Requested by NRC Project Manager for Preparation of Environmental Impact Statement for Power Uprate License Request.Max Fuel Exposure Data for Reload 3/ Cycle 4 Operation Listed

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Submits Addl Info Requested by NRC Project Manager for Preparation of Environmental Impact Statement for Power Uprate License Request.Max Fuel Exposure Data for Reload 3/ Cycle 4 Operation Listed
ML20099G816
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 08/12/1992
From: Orser W
DETROIT EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-92-0098, CON-NRC-92-98 NUDOCS 9208170222
Download: ML20099G816 (2)


Text

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mm August 12, 1992 NRC-92-0098 U. S. Nuclear Regulatory Commission Attn: Documant Control Desk Washington, D.C. 20555

References:

1) Fermi 2 -

NRC Docket No. 50-341 NRC License No. NPF-43

2) Detrc!t Edison Letter, NRC-91-0102, " Proposed License Amendment - Uprated Power Operation," dated September 24, 1991.
3) Detroit Edison Letter, NRC-92-0048, " Revision to Proposed License Amendment for Uprated Power Operation and to the Fermi 2 Power Uprate Safety Analysis (TAC No, M82102), dat.ed April 30, 1992.
4) Federal Register, Volume 53, Number 39, Pgs.

l 6040-6043, Federal Docket 38-4229, dated February 29, 1988.

5) Detroit Edison Letter NRC-92-0018, "Burnup and Enrichment Levels of 10CFR51.52," dated February 24, 1992.

I

Subject:

Additional Information Requested by the NRC Project i Manager for Preparation of an Environmental Impact l Statement for the Fermi 2 Power Uprate License I Amendment Request l

The purpose of this letter is to document information requested by Mr.

l Timothy Colburn, NRC/NRR Project Manager for Fermi 2, for the l development of an Environmental Impact Statement (EIS) for the Reference 2 & 3 Power Uprate (PU) License Amendment request.

Previously, in Reference 5, Detroit Edison had provided the NRC Staff with information stating that the Reference 4 values would be met for maximum Uranium-235 enrichments no greater than 5% and fuel burnup not erceeding maximum average rod bilenup levels of 60 gigawatt-days per metric ton (GWd/Mtu). Therefore, Detroit Edison concluded that the generic evaluation of the type provided in 53 FR 6040 applied to this EMea170222 920312 splj[

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. j USNRC August 12, 1992

  • , NRC-92-0098 Page 2 application for an amendment to the Facility Operating Licensing.

These conclusions are still applicable.

However, in the course of the NRC/NRR Project Manager's review of this matter, he requested actual maximum fuel pellet enrichment data and expected maximum fuel exposure data for Reload 3 / Cycle 4 operation.

The following information is provided, as requested:

o Maximum Fuel Pellet Enrichment = 4.8%.

o Maximun Batch Average Fuel Exposure = 34.0 GWd/MLu.

o Maximum Fuel Pellet (Rod) Exposure = 49.1 GWd/Mtu.

Detroit Edison provided the same information to Mr. Colburn, in advance, via telecopy, on August 10, 1992.

If there are any further questions on this metter, please contact tir.

Terry L. Riley, Supervisor, Nuclear Licensing, at (313) 586.-1684.

Sincerely, f I l

N cc: T. G. Colburn A. B. Davis H. Phillips S. Stasek l H. Stransky Supervisor, Electric Operators, Michigan Public Service Commission - J. R. Padgett l

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