ML030770832: Difference between revisions
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| issue date = 03/18/2003 | | issue date = 03/18/2003 | ||
| title = Review of TSTF-445 Revision 1 | | title = Review of TSTF-445 Revision 1 | ||
| author name = Beckner W | | author name = Beckner W | ||
| author affiliation = NRC/NRR/DRIP/RORP | | author affiliation = NRC/NRR/DRIP/RORP | ||
| addressee name = Pietrangelo A | | addressee name = Pietrangelo A | ||
| addressee affiliation = Nuclear Energy Institute (NEI) | | addressee affiliation = Nuclear Energy Institute (NEI) | ||
| docket = | | docket = | ||
| Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:}} | {{#Wiki_filter:March 18, 2003 Mr. Anthony Pietrangelo Nuclear Energy Institute 1776 I Street, N. W. | ||
Suite 400 Washington, DC 20006-3708 | |||
==Dear Mr. Pietrangelo:== | |||
The Nuclear Regulatory Commission (NRC) has completed its review of the Nuclear Energy Institute Technical Specification Change Traveler, TSTF-445 Revision 1, Revision to Peak Linear Heat Rate Safety Limit proposed changes to NUREG-1432, Rev. 2, Standard Technical Specifications Combustion Engineering Plants. | |||
TSTF-445 Revision 1 proposes to replace Technical Specification (TS) Safety Limit 2.1.1.2, Peak Linear Heat Rate with a Peak Fuel Centerline Temperature Safety Limit. This change is necessary such that the Safety Limit adequately conforms to 10 CFR 50.36(c)(1)(ii)(A) which requires that Limiting Safety System Settings prevent a Safety Limit from being exceeded during normal operations and Anticipated Operational Occurrences. This proposed change is consistent with the Westinghouse and B&W improved Standard Technical Specifications. The staff finds the proposed changes acceptable and applicable to both analog and digital plants. | |||
The staff issued its safety evaluation approving TSTF-445 for plant-specific license amendment requests and for incorporation into NUREG-1432, Rev. 2, Standard Technical Specifications Combustion Engineering Plants by {{letter dated|date=December 23, 2002|text=letter dated December 23, 2002}}. TSTF-445 Revision 1 provides a minor editorial change to the wording of the Safety Limit which does not result in a change to the staffs safety evaluation. As a matter of efficiency, the staff has chosen not to process TSTF-445 Revision 1 through the Consolidated Line Item Improvement Process (CLIIP) since there are relatively few licensees remaining that have not adopted this change. | |||
Please contact me at (301) 415-1161 or e-mail wdb@nrc.gov if you have any questions or need further information on these proposed changes. | |||
Sincerely, | |||
/RA/ | |||
William D. Beckner, Program Director Operating Reactor Improvements Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation cc: | |||
T. Silko, BWROG D. Bice, CEOG P. Infanger, BWOG S. Wideman, WOG D. Hoffman, EXCEL B. Mann, EXCEL | |||
ML030770832 DOCUMENT NAME: G:\\RORP\\TSS\\KAVANAGH\\TSTF-445 R1 disposition OFFICE TSS:RORP:DRIP TSS:RORP:DRIP BC:PDIV:DLPM SC:TSS:DRIP PD:RORP:DRIP NAME KAKavanagh LAHill HBerkow RLDennig WDBeckner DATE 03/13/2003 03/13/2003 03/13/2003 03/14/2003 03/18/2003}} | |||
Latest revision as of 11:47, 16 January 2025
| ML030770832 | |
| Person / Time | |
|---|---|
| Issue date: | 03/18/2003 |
| From: | Beckner W NRC/NRR/DRIP/RORP |
| To: | Pietrangelo A Nuclear Energy Institute |
| Kavanagh, k. NRR, 415-3743 | |
| References | |
| Download: ML030770832 (4) | |
Text
March 18, 2003 Mr. Anthony Pietrangelo Nuclear Energy Institute 1776 I Street, N. W.
Suite 400 Washington, DC 20006-3708
Dear Mr. Pietrangelo:
The Nuclear Regulatory Commission (NRC) has completed its review of the Nuclear Energy Institute Technical Specification Change Traveler, TSTF-445 Revision 1, Revision to Peak Linear Heat Rate Safety Limit proposed changes to NUREG-1432, Rev. 2, Standard Technical Specifications Combustion Engineering Plants.
TSTF-445 Revision 1 proposes to replace Technical Specification (TS) Safety Limit 2.1.1.2, Peak Linear Heat Rate with a Peak Fuel Centerline Temperature Safety Limit. This change is necessary such that the Safety Limit adequately conforms to 10 CFR 50.36(c)(1)(ii)(A) which requires that Limiting Safety System Settings prevent a Safety Limit from being exceeded during normal operations and Anticipated Operational Occurrences. This proposed change is consistent with the Westinghouse and B&W improved Standard Technical Specifications. The staff finds the proposed changes acceptable and applicable to both analog and digital plants.
The staff issued its safety evaluation approving TSTF-445 for plant-specific license amendment requests and for incorporation into NUREG-1432, Rev. 2, Standard Technical Specifications Combustion Engineering Plants by letter dated December 23, 2002. TSTF-445 Revision 1 provides a minor editorial change to the wording of the Safety Limit which does not result in a change to the staffs safety evaluation. As a matter of efficiency, the staff has chosen not to process TSTF-445 Revision 1 through the Consolidated Line Item Improvement Process (CLIIP) since there are relatively few licensees remaining that have not adopted this change.
Please contact me at (301) 415-1161 or e-mail wdb@nrc.gov if you have any questions or need further information on these proposed changes.
Sincerely,
/RA/
William D. Beckner, Program Director Operating Reactor Improvements Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation cc:
T. Silko, BWROG D. Bice, CEOG P. Infanger, BWOG S. Wideman, WOG D. Hoffman, EXCEL B. Mann, EXCEL
ML030770832 DOCUMENT NAME: G:\\RORP\\TSS\\KAVANAGH\\TSTF-445 R1 disposition OFFICE TSS:RORP:DRIP TSS:RORP:DRIP BC:PDIV:DLPM SC:TSS:DRIP PD:RORP:DRIP NAME KAKavanagh LAHill HBerkow RLDennig WDBeckner DATE 03/13/2003 03/13/2003 03/13/2003 03/14/2003 03/18/2003