ML20207G478
| ML20207G478 | |
| Person / Time | |
|---|---|
| Issue date: | 06/08/1999 |
| From: | Carpenter C NRC (Affiliation Not Assigned) |
| To: | Rickard I ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| Shared Package | |
| ML20207G482 | List: |
| References | |
| TAC-MA5282, NUDOCS 9906110184 | |
| Download: ML20207G478 (2) | |
Text
'
Mr. lin C. Rickird, Dirzctor June' 8, 1999-Nucle:r Licensing
. t ABB-Combustion Engineering, Inc.
Post Office B:x 500 2000 Day Hill Road c Windsor, Connecticut 06095-0500
SUBJECT:
SAFETY EVALUATION OF ABB-CENP REPORT, " APPLICATION OF A DIT CROSS SECTION LIBRARY BASED ON ENDF/B-VI" (TAC NO. MA5282)
The NRC staff has completed its review of the subject report requested by ABB Combustion Engineering Nuclear Power (ABB-CENP) by letter of March 11,1999, and subsequent teleconference between the staff and ABB-CENP. The staff has found that this report is acceptable for referencing in licensing applications to the extent specified and under the limitations delineated in the report and in the associated NRC safety evaluation, which is enclosed.. The safety evaluation define,s the basis for acceptance of the report.
The subject report describes modifications made relative to the DIT computer code. These modifications include the generation of a new fine-group DIT neutron cross section library based on data from ENDF/B-VI as well as a change in the number of fine-mesh groups.
employed and in the number of isotopes explicitly modeled. The staff concludes that these cross sections can be utilized in the ROCS code as well as in the HERMITE space-time couts the MC fine-mesh code, and supporting boundary condition constant processing codes.
The staff will not repeat its review of the matters described in the subject report, when the report appears as a refereace in license applications, except to ensure that the material presented applies to the specific plant involved. If the NRC's criteria or regulations change so
~ that its conclusion that the submittalis acceptable are invalidated, ABB-CENP and/or the applicant referencing the report will be expected to revise and resubmit its respective documentation, or submit justificat,on for the continued applicability of the report without revision of the respective documentation.
- Should you have any questions or wish further clarification, please call me at (301) 415-1282 or Larry Kopp at (301) 415-2879.
Sincerely, Original Signed By:
Cynthia A. Carpenter, Chief Generic issues, Environmental, Financial Q Qy gE U
C PDR Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation,
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June 8,1999 Mr. lan C. Rickard, Director Nuclear Licensing ABB-Combustion Engineering, Inc.
l Post Office Box 500 l
2000 Day Hill Road Windsor, Connecticut 06095-0500
SUBJECT:
SAFETY EVALUATION OF ABB-CENP REPORT, " APPLICATION OF A DIT j
CROSS SECTION LIBRARY BASED ON ENDF/B-VI" (TAC NO. MA5282)
The NRC staff has completed its review of the subject report requested by ABB Combustion Engineering Nuclear Power (ABB-CENP) by letter of March 11,1999, and subsequent teleconference between the staff and ABB-CENP. The staff has found that this report i-s acceptable for referencing in licensing applications to the extent specified and under the limitations delineated in the report and in the associated NRC safety evaluation, which is enclosed. The safety evaluation defines the basis for acceptance of the report.
J The subject report describes modifications made relative to the DlT computer code. These modifications include the generation of a new fine-group DIT neutron cross section library based on data from ENDF/B-VI as well as a change in the number of fine-mesh groups employed and in the number of isotopes explicitly modeled. The staff concludes that these cross sections can be utilized in the ROCS code as well as in the HERMITE space-time code, the MC fine-mesh code, and supporting boundary condition constant processing codes.
The staff will not repeat its review of the matters described in the subject report, when the report appears as a reference in license applications, except to ensure that the material presented applies to the specific plant involved. If the NRC's criteria or regulations change so that its conclusion that the submittal is acceptable are invalidated, ABB-CENP and/or the applicant referencing the report will be expected to revise and resubmit its respective documentation, or submit justification for the continued applicability of the report without i
revision of the respective documentation.
Should you have any questions or wish further clarification, please call me at (301) 415-1282 or Larry Kopp at (301) 415-2879.
Sincerely, 4
0 wA O fp Cy thia A. Carpenter, Chief Generic issues, Environmental, Financial and Rulemaking Branch Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/ enc: See next page