ML20248E558

Forwards SER Supporting Use of Frosstey Fuel Performance Code Described in Topical Rept PECo-FMS-003, Steady-State Fuel Performance Methods Rept. Addl Applications of Subj Code Require NRC Review & Approval

ML20248E558
Person / Time
Site:	Peach Bottom
Issue date:	09/21/1989
From:	Martin R Office of Nuclear Reactor Regulation
To:	Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
Shared Package
ML20247P522	List: ML20248E558
References
TAC-65871, NUDOCS 8910050285
Download: ML20248E558 (3)

Text

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I J eptember 21, 1989' l

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DocketNos..50-277/278 j

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. Mr.; George 'A. Hunger, Jr.

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y ' Director-Licensing, MC 5-2A-5 i

Philadelphia Electric Company-Correspondence Control Desk i.

955 Chesterbrook Boulevard Wayne, Pennsylvania 19087-5691

SUBJECT:

SAFETY EVALUATION OF PECO'S FROSSTEY FUEL PERFORMANCE CODE:

I

_PECO-FMS-0003 (TAC NOS. 65871)

-l RE:

PEACH' BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 l

The' RRC. staff has completed its review of the Philadelphia Electric Company's (PECo) FROSSTEY fuel performance code. The code was described in a PECo-report PECo-FMS-0003 " Steady-State Fuel Performance' Methods Report" submitted l

by letter dated July.13,-1987.

j As. stated in the enclosed evaluation, the staff concludes thatithe use of ti FROSSTEY, as described in the referenced documents, is acceptable for referencing in the evaluation of Peach Bottom critical power ratio (CPR) analyses.in support of reloads. The use of the FROSSTEY code for the l

i evaluation of gadolinia fuel rods is limited to five percent or less by weight of gadolinia.in U02. 'If PECo wishes to apply the FROSSTEY code to other fuel

, design and safety analyses, i.e., other than core average and hot channel gap conductances for CPR analyses in support of reload analyses, then these additional FROSSTEY applications must be submitted to the NRC staff for review and approval.. Subject to these conditions the NRC staff finds the PEco iFROSSTEY code submittals, as evaluated in the enclosure, to be acceptable for referencing in the Peach Bottom CPR analyses in support of reloading analyses.

Sincerely, j

/S/

Robert E. Martin, Project Manager l

Project Directorate I-2 t

Division of Reactor Projects I/II Office of Nuclear Reactor Regulaticn E

Enclosure:

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September 21, 1989 Docket Nos. 50-277/278 Mr. deorge A. Hunger, Jr.

Director-Licensing, MC 5-2A-5 Philadelphia. Electric Company Correspondence Control Desk 955 Chesterbrook Boulevard Wayne, Pennsylvania 19087-5691

SUBJECT:

' SAFETY EVALUATION OF PEC0'S FROSSTEY FUEL PERFORMANCE CODE:

PECO-FMS-0003.(TAC NOS. 65871)

RE:

PEACH BOTTOM ATOMIC F0WER STATION, UNITS 2 AND 3 The NRC staff has completed its review of.the Philadelphia Electric Company's l

(PECo) FROSSTEY fuel performance code. The code was described in a PEco report PEco-FMS-0003 " Steady-State Fuel Performance Methods Report" submitted by letter dated July 13, 1987..

-As stated in the enclosed evaluation, the staff concludes that the use of FROSSTEY, as described in the referenced documents, is acceptable for referencing in the evaluation of Peach Bottom critical power ratio (CPR) analyses in support of reloads. 'The use of the FROSSTEY code for the evaluation of gadolinia fuel rods is limited to five percent or less by weight

.of'gadolinia in UO2.

If PECo wishes to apply the FROSSTEY code to other fuel design and safety analyses, i.e., other than core average and hot channel gap conductances for CPR analyses in support of reload analyses, then these additional FROSSTEY applications must be submitted to the NRC staff for review and approval. Subject to these conditions the NRC staff finds the PECo FROSSTEY code submittals, as evaluated in the enclosure, to be acceptable for referencing in the Peach Bottom CPR analyses in support of reloading analyses.

Sincerely,

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/ Robert E. ifa/]la v

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rtin, Project Manager project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Enclosure:

L As stated cc w/ enclosure:

1 See next page j

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e-9 Mr. George A. Hunger, Jr.

Peach Bottom Atomic Power Station, Philadelphia Electric Company Units 2 and 3 cc:

Troy B. ' Conner, Jr., Esq.

Single Point'of Contact 1747 Pennsylvania Avenue, N.W.

P. O. Box 11880 Washington, D.C.

20006 Harrisburg, Pennsylvania 17108-1880 Philadelphia Electric Company Mr. Thomas M. Gerusky, Director ATTN: Mr. D. M. Smith, Vice President Bureau of Radiation Protection Peach Bottom Atomic Power Station Pennsylvania Department of

. Route 1. Box 208 Environmental Resources Delta, Pennsylvania 17314 P. O. Box 2063 Harrisburg, Pennsylvania 17120 Philadelphia Electric Company

' ATTN: Regulatory Engineer, A1-25 Mr. Albert R. Steel, Chairman Peach Bottom Atomic Power Station Board of Supervisors Route 1 Box 208' Peach Bottom Township Delta, Pennsylvania 17314 R. D. #1 Delta, Pennsylvania 17314 Resident Inspector

.U.S. Nuclear Regulatory Commission Public Service Commission of Maryland Peach Bottom Atomic Power Station Engineering Division P.O.-Box 399 ATTN: Chief Engineer Delta, Pennsylvania 17314 231 E. Baltimore Street Baltimore, MD 21202-3486 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Mr. Tom Magette 475 Allendale Road Power Plant Research Program King of Prussia, Pennsylvania 19406 Department of Natural Resources B-3 Mr. Roland Fletcher Tawes State Office Building Department of Environment Annapolis, Maryland 21401 201 West Preston Street Baltimore, Maryland 21201

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