ML20128G751
| ML20128G751 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/04/1996 |
| From: | Rosalyn Jones NRC (Affiliation Not Assigned) |
| To: | Taylor J BABCOCK & WILCOX CO. |
| References | |
| NUDOCS 9610090119 | |
| Download: ML20128G751 (1) | |
Text
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October 4, 1996 Mr. J. H. Taylor, Manager i
Licensing Services j
Framatome Technologies 1
3315 Old Forest Road P.O. Box 10935 Lynchburg, VA 24506-0935
Dear Mr. Taylor:
J In a letter of August 28, 1996 (JHT/96-57), Framatome Cogema Fuels-(FCF) requested that the SIMULATE-3 neutronics code calculational uncertainty of 5.5% be approved for use with the NRC-approved TAC 03 and GDTAC0 fuel thermal analysis codes for Three Mile Island, Unit 1 (TMI-1) reload licensing analyses.
FCF has previously received approval from the NRC to utilize the NEMO code calculational uncertainty of 4.8% as the fuel rod power history uncertainty when performing fuel thermal performance analyses with either the l
TAC 03 or the GDTACO code.
GPU Nuclear (GPUN) has recently received NRC approval of their SIMULATE-3 code, which has a calculational uncertainty of 5.5%, for TMI-l reload 2
i applications.
Therefore, the NRC staff finds the SIMULATE-3 calculational uncertainty of 5.5%, as the power history uncertainty for use with the TAC 03 j
and GDTAC0 codes, acceptable for TMI-l reload licensing analyses.
This uncertainty applies only to TMI-l and may not be used generically.
GPUN will provide the fuel rod power history obtained with SIMULATE-3 to FCF for use with TAC 03 or GDTACO.
This letter may be referenced by GPUN as an NRC approved methodology for performing reload analyses.
4 Sincerely,
/
R bert C. Jones, Chief Reactor Systems Branch Division of Systems Safety and Analysis l
Contact:
L. Kopp, SRXB DISTRIBUTION 415-2879 Central Files RJones PDR EWeiss SRXB R/F LKopp i
LKopp R/F RHernan
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