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{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 August 10, 2012 Mr. Brian J. O'Grady Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321 COOPER NUCLEAR STATION -REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION 3.4.9, "RCS PRESSURE AND TEMPERATURE (PIT) LIMITS" (TAC NO. ME7324) Dear Mr. O'Grady: By letter dated September 22, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 11272A057), Nebraska Public Power District (the licensee) submitted a license amendment request (LAR) to revise the Technical Specifications (TSs) for Cooper Nuclear Station. The proposed LAR would revise TS 3.4.9, "RCS [Reactor Coolant System] Pressure and Temperature (PIT) Limits," to include new pressure-temperature (P-T) limits for heat-up and cool-down operations with the core critical and core not critical, as well as for pressure test conditions. The proposed P-T limits would be valid for 32 effective full power years (EFPY) of facility operation. The proposed revisions to TS 3.4.9 also would revise surveillance requirements for verifying that the reactor vessel flange and reactor vessel head flange temperatures are greater than the revised minimum operating temperature (70 degrees Fahrenheit) specified for the proposed 32 EFPY P-T limits. By letter dated February 29, 2012 (ADAMS Accession No. ML 120590085), the U.S. Nuclear Regulatory Commission (NRC) issued a request for additional information (RAI). By letter dated March 30, 2012 (ADAMS Accession No. ML 12094A 119), the licensee provided its RAt response. The NRC staff has reviewed your submittals and determined that additional information is needed for the staff to complete its evaluation. A portion of the RAls were transmitted via e-mail to Mr. Edward McCutchen of your staff on May 7, 2012. The additional RAls were discussed with Mr. McCutchen and others of your staff on June 5, 2012. Mr. McCutchen indicated via telephone on July 20,2012, that the licensee's response would be provided within 30 days of receipt of this letter. | {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 August 10, 2012 Mr. Brian J. O'Grady Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321 COOPER NUCLEAR STATION -REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION 3.4.9, "RCS PRESSURE AND TEMPERATURE (PIT) LIMITS" (TAC NO. ME7324) | ||
B. O'Grady -If you have any questions, please contact me at 301-415-1377 or via e-mail at Lynnea.Wilkins@nrc.gov. Lynnea E. Wilkins, Project Manager Plant licensing Branch IV Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-298 Enclosure: Request for Additional Information cc w/encl: Distribution via listserv REQUEST FOR ADDITIONAL INFORMATION NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298 By letter dated September 22, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 11272A057), Nebraska Public Power District (the licensee) submitted a license amendment request (LAR) to revise the Technical Specifications (TSs) for Cooper Nuclear Station. The proposed LAR would revise TS 3.4.9, "RCS [Reactor Coolant System] Pressure and Temperature (PfT) Limits," to include new pressure-temperature (P-T) limits for heat-up and cool-down operations with the core critical and core not critical, as well as for pressure test conditions. The proposed P-T limits would be valid for 32 effective full power years (EFPY) of facility operation. The proposed revisions to TS 3.4.9 also would revise surveillance requirements for verifying that the reactor vessel flange and reactor vessel head flange temperatures are greater than the revised minimum operating temperature (70 degrees Fahrenheit) specified for the proposed 32 EFPY P-T limits. By letter dated February 29,2012 (ADAMS Accession No. ML 120590085), the U.S. Nuclear Regulatory Commission (NRC) issued a request for additional information (RAI). By letter dated March 30, 2012 (ADAMS Accession No. ML 12094A119), the licensee provided its RAI response. The NRC staff has reviewed and evaluated the information provided by the licensee and has determined that the following information is needed in order to complete its review: The regulations in Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix G, "Fracture Toughness Requirements," state, in part, that This appendix specifies fracture toughness requirements for ferritic materials of pressure-retaining components of the reactor coolant pressure boundary of light water nuclear power reactors to provide adequate margins of safety ... In addition, 10 CFR Part 50, Appendix G, paragraph IV.A states, in part, that The pressure-retaining components of the reactor coolant pressure boundary that are made of ferritic materials must meet the requirements of the ASME Code [American Society of Mechanical Engineers Boiler and Pressure Vessel Code], supplemented by the additional requirements set forth below [paragraph IV.A.2, "Pressure-Temperature Limits and Minimum Temperature Requirements"] ... Enclosure | |||
==Dear Mr. O'Grady:== | |||
By letter dated September 22, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 11272A057), Nebraska Public Power District (the licensee) submitted a license amendment request (LAR) to revise the Technical Specifications (TSs) for Cooper Nuclear Station. The proposed LAR would revise TS 3.4.9, "RCS [Reactor Coolant System] Pressure and Temperature (PIT) Limits," to include new pressure-temperature (P-T) limits for heat-up and cool-down operations with the core critical and core not critical, as well as for pressure test conditions. The proposed P-T limits would be valid for 32 effective full power years (EFPY) of facility operation. The proposed revisions to TS 3.4.9 also would revise surveillance requirements for verifying that the reactor vessel flange and reactor vessel head flange temperatures are greater than the revised minimum operating temperature (70 degrees Fahrenheit) specified for the proposed 32 EFPY P-T limits. By letter dated February 29, 2012 (ADAMS Accession No. ML 120590085), the U.S. Nuclear Regulatory Commission (NRC) issued a request for additional information (RAI). By letter dated March 30, 2012 (ADAMS Accession No. ML 12094A 119), the licensee provided its RAt response. The NRC staff has reviewed your submittals and determined that additional information is needed for the staff to complete its evaluation. A portion of the RAls were transmitted via e-mail to Mr. Edward McCutchen of your staff on May 7, 2012. The additional RAls were discussed with Mr. McCutchen and others of your staff on June 5, 2012. Mr. McCutchen indicated via telephone on July 20,2012, that the licensee's response would be provided within 30 days of receipt of this letter. | |||
B. O'Grady -If you have any questions, please contact me at 301-415-1377 or via e-mail at Lynnea.Wilkins@nrc.gov. Lynnea E. Wilkins, Project Manager Plant licensing Branch IV Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-298 | |||
==Enclosure:== | |||
Request for Additional Information cc w/encl: Distribution via listserv REQUEST FOR ADDITIONAL INFORMATION NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298 By letter dated September 22, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 11272A057), Nebraska Public Power District (the licensee) submitted a license amendment request (LAR) to revise the Technical Specifications (TSs) for Cooper Nuclear Station. The proposed LAR would revise TS 3.4.9, "RCS [Reactor Coolant System] Pressure and Temperature (PfT) Limits," to include new pressure-temperature (P-T) limits for heat-up and cool-down operations with the core critical and core not critical, as well as for pressure test conditions. The proposed P-T limits would be valid for 32 effective full power years (EFPY) of facility operation. The proposed revisions to TS 3.4.9 also would revise surveillance requirements for verifying that the reactor vessel flange and reactor vessel head flange temperatures are greater than the revised minimum operating temperature (70 degrees Fahrenheit) specified for the proposed 32 EFPY P-T limits. By letter dated February 29,2012 (ADAMS Accession No. ML 120590085), the U.S. Nuclear Regulatory Commission (NRC) issued a request for additional information (RAI). By letter dated March 30, 2012 (ADAMS Accession No. ML 12094A119), the licensee provided its RAI response. The NRC staff has reviewed and evaluated the information provided by the licensee and has determined that the following information is needed in order to complete its review: The regulations in Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix G, "Fracture Toughness Requirements," state, in part, that This appendix specifies fracture toughness requirements for ferritic materials of pressure-retaining components of the reactor coolant pressure boundary of light water nuclear power reactors to provide adequate margins of safety ... In addition, 10 CFR Part 50, Appendix G, paragraph IV.A states, in part, that The pressure-retaining components of the reactor coolant pressure boundary that are made of ferritic materials must meet the requirements of the ASME Code [American Society of Mechanical Engineers Boiler and Pressure Vessel Code], supplemented by the additional requirements set forth below [paragraph IV.A.2, "Pressure-Temperature Limits and Minimum Temperature Requirements"] ... Enclosure | |||
-2 Therefore, 10 CFR Part 50, Appendix G requires that P-T limits be developed for the entire reactor coolant pressure boundary (RCPB), consisting of ferritic RCPB materials in the reactor vessel (RV) beltline (neutron fluence <:: 1 x 1017 n/cm2, E> 1 MeV), as well as ferritic RCPB materials not in the RV beltline (neutron fluence < 1 x 1017 n/cm2, E> 1 MeV). P-T limit calculations for ferritic RCPB components that are not RV beltline shell materials, may define curves that are more limiting than those calculated for the RV beltline shell materials. This may be due to the following factors: RV nozzles, penetrations, and other discontinuities have complex geometries that may exhibit significantly higher stresses than those for the RV beltline shell region. These higher stresses can potentially result in more restrictive P-T limits, even if the reference temperature (RT NDT) for these components is not as high as that of RV beltline shell materials that have simpler geometries. Ferritic RCPB components that are not part of the RV may have initial RTNDT values, which may define a more restrictive lowest operating temperature in the P -T limits than those for the RV beltline shell materials. Please describe how the P-T limit curves, and the methodology used to develop these curves considered all RV materials (beltline and non-beltline) and the lowest service temperature of all ferritic RCPB materials, consistent with the requirements of 10 CFR Part 50, Appendix G. Linear Elastic Fracture Mechanics (LEFM) evaluation of the N16 Water Level Instrument Nozzles: The licensee's LAR submittal, which includes Structural Integrity Associates (SIA) calculation package 1100445.303, provides a reference to the generic LEFM methodology used for calculating the applied stress intensity factor values for the N 16 instrument nozzles. For Cooper, the N16 nozzles define part of the bounding beltline region P-T curves at low temperatures. The generic LEFM methodology for boiling-water reactor instrument nozzles, provided in SIA Report No. 0900876.401, Revision 0, "Linear Elastic Fracture Mechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzles for Pressure-Temperature Curve Evaluation," November 2011 (ADAMS Accession No. ML 11325A074), is currently under review by NRC staff. Please provide an alternate methodology for the stated instrument nozzles. | -2 Therefore, 10 CFR Part 50, Appendix G requires that P-T limits be developed for the entire reactor coolant pressure boundary (RCPB), consisting of ferritic RCPB materials in the reactor vessel (RV) beltline (neutron fluence <:: 1 x 1017 n/cm2, E> 1 MeV), as well as ferritic RCPB materials not in the RV beltline (neutron fluence < 1 x 1017 n/cm2, E> 1 MeV). P-T limit calculations for ferritic RCPB components that are not RV beltline shell materials, may define curves that are more limiting than those calculated for the RV beltline shell materials. This may be due to the following factors: RV nozzles, penetrations, and other discontinuities have complex geometries that may exhibit significantly higher stresses than those for the RV beltline shell region. These higher stresses can potentially result in more restrictive P-T limits, even if the reference temperature (RT NDT) for these components is not as high as that of RV beltline shell materials that have simpler geometries. Ferritic RCPB components that are not part of the RV may have initial RTNDT values, which may define a more restrictive lowest operating temperature in the P -T limits than those for the RV beltline shell materials. Please describe how the P-T limit curves, and the methodology used to develop these curves considered all RV materials (beltline and non-beltline) and the lowest service temperature of all ferritic RCPB materials, consistent with the requirements of 10 CFR Part 50, Appendix G. Linear Elastic Fracture Mechanics (LEFM) evaluation of the N16 Water Level Instrument Nozzles: The licensee's LAR submittal, which includes Structural Integrity Associates (SIA) calculation package 1100445.303, provides a reference to the generic LEFM methodology used for calculating the applied stress intensity factor values for the N 16 instrument nozzles. For Cooper, the N16 nozzles define part of the bounding beltline region P-T curves at low temperatures. The generic LEFM methodology for boiling-water reactor instrument nozzles, provided in SIA Report No. 0900876.401, Revision 0, "Linear Elastic Fracture Mechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzles for Pressure-Temperature Curve Evaluation," November 2011 (ADAMS Accession No. ML 11325A074), is currently under review by NRC staff. Please provide an alternate methodology for the stated instrument nozzles. | ||
B. O'Grady -2 If you have any questions, please contact me at 301-415-1377 or via e-mail at Lynnea.wilkins@nrc.gov. Docket No. 50-298 Request for Additional cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPLIV r/f RidsAcrsAcnw_MailCTR Resource RidsNrrDeEvib Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMCooper Resource RidsOgcRp Resource RidsRgn4MailCenter Resource CSydnor, NRRlDE/EVIB JPoehler, NRRlDE/EVIB ADAMS Accession No.: ML 12205A216 Sincerely, IRA! Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation OFFICE NRR/LPL4/PM NRR/LPL4/LA NRRlDE/EVIB/BC NRR/LPL4/BC NRRlLPL4/PM NAME LWilkins JBurkhardt SRosenberg (CSydnor for) MMarkley LWilkins DATE 7/24/12 7/24112 7/26112 8/10/12 8110112 OFFICIAL RECORD | B. O'Grady -2 If you have any questions, please contact me at 301-415-1377 or via e-mail at Lynnea.wilkins@nrc.gov. Docket No. 50-298 Request for Additional cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPLIV r/f RidsAcrsAcnw_MailCTR Resource RidsNrrDeEvib Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMCooper Resource RidsOgcRp Resource RidsRgn4MailCenter Resource CSydnor, NRRlDE/EVIB JPoehler, NRRlDE/EVIB ADAMS Accession No.: ML 12205A216 Sincerely, IRA! Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation OFFICE NRR/LPL4/PM NRR/LPL4/LA NRRlDE/EVIB/BC NRR/LPL4/BC NRRlLPL4/PM NAME LWilkins JBurkhardt SRosenberg (CSydnor for) MMarkley LWilkins DATE 7/24/12 7/24112 7/26112 8/10/12 8110112 OFFICIAL RECORD | ||
}} | }} | ||
Revision as of 12:59, 5 April 2018
| ML12205A216 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/10/2012 |
| From: | Wilkins L E Plant Licensing Branch IV |
| To: | O'Grady B J Nebraska Public Power District (NPPD) |
| Wilkins L E | |
| References | |
| TAC ME7324 | |
| Download: ML12205A216 (5) | |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 August 10, 2012 Mr. Brian J. O'Grady Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321 COOPER NUCLEAR STATION -REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION 3.4.9, "RCS PRESSURE AND TEMPERATURE (PIT) LIMITS" (TAC NO. ME7324)
Dear Mr. O'Grady:
By letter dated September 22, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 11272A057), Nebraska Public Power District (the licensee) submitted a license amendment request (LAR) to revise the Technical Specifications (TSs) for Cooper Nuclear Station. The proposed LAR would revise TS 3.4.9, "RCS [Reactor Coolant System] Pressure and Temperature (PIT) Limits," to include new pressure-temperature (P-T) limits for heat-up and cool-down operations with the core critical and core not critical, as well as for pressure test conditions. The proposed P-T limits would be valid for 32 effective full power years (EFPY) of facility operation. The proposed revisions to TS 3.4.9 also would revise surveillance requirements for verifying that the reactor vessel flange and reactor vessel head flange temperatures are greater than the revised minimum operating temperature (70 degrees Fahrenheit) specified for the proposed 32 EFPY P-T limits. By letter dated February 29, 2012 (ADAMS Accession No. ML 120590085), the U.S. Nuclear Regulatory Commission (NRC) issued a request for additional information (RAI). By letter dated March 30, 2012 (ADAMS Accession No. ML 12094A 119), the licensee provided its RAt response. The NRC staff has reviewed your submittals and determined that additional information is needed for the staff to complete its evaluation. A portion of the RAls were transmitted via e-mail to Mr. Edward McCutchen of your staff on May 7, 2012. The additional RAls were discussed with Mr. McCutchen and others of your staff on June 5, 2012. Mr. McCutchen indicated via telephone on July 20,2012, that the licensee's response would be provided within 30 days of receipt of this letter.
B. O'Grady -If you have any questions, please contact me at 301-415-1377 or via e-mail at Lynnea.Wilkins@nrc.gov. Lynnea E. Wilkins, Project Manager Plant licensing Branch IV Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosure:
Request for Additional Information cc w/encl: Distribution via listserv REQUEST FOR ADDITIONAL INFORMATION NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298 By letter dated September 22, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 11272A057), Nebraska Public Power District (the licensee) submitted a license amendment request (LAR) to revise the Technical Specifications (TSs) for Cooper Nuclear Station. The proposed LAR would revise TS 3.4.9, "RCS [Reactor Coolant System] Pressure and Temperature (PfT) Limits," to include new pressure-temperature (P-T) limits for heat-up and cool-down operations with the core critical and core not critical, as well as for pressure test conditions. The proposed P-T limits would be valid for 32 effective full power years (EFPY) of facility operation. The proposed revisions to TS 3.4.9 also would revise surveillance requirements for verifying that the reactor vessel flange and reactor vessel head flange temperatures are greater than the revised minimum operating temperature (70 degrees Fahrenheit) specified for the proposed 32 EFPY P-T limits. By letter dated February 29,2012 (ADAMS Accession No. ML 120590085), the U.S. Nuclear Regulatory Commission (NRC) issued a request for additional information (RAI). By letter dated March 30, 2012 (ADAMS Accession No. ML 12094A119), the licensee provided its RAI response. The NRC staff has reviewed and evaluated the information provided by the licensee and has determined that the following information is needed in order to complete its review: The regulations in Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix G, "Fracture Toughness Requirements," state, in part, that This appendix specifies fracture toughness requirements for ferritic materials of pressure-retaining components of the reactor coolant pressure boundary of light water nuclear power reactors to provide adequate margins of safety ... In addition, 10 CFR Part 50, Appendix G, paragraph IV.A states, in part, that The pressure-retaining components of the reactor coolant pressure boundary that are made of ferritic materials must meet the requirements of the ASME Code [American Society of Mechanical Engineers Boiler and Pressure Vessel Code], supplemented by the additional requirements set forth below [paragraph IV.A.2, "Pressure-Temperature Limits and Minimum Temperature Requirements"] ... Enclosure
-2 Therefore, 10 CFR Part 50, Appendix G requires that P-T limits be developed for the entire reactor coolant pressure boundary (RCPB), consisting of ferritic RCPB materials in the reactor vessel (RV) beltline (neutron fluence <:: 1 x 1017 n/cm2, E> 1 MeV), as well as ferritic RCPB materials not in the RV beltline (neutron fluence < 1 x 1017 n/cm2, E> 1 MeV). P-T limit calculations for ferritic RCPB components that are not RV beltline shell materials, may define curves that are more limiting than those calculated for the RV beltline shell materials. This may be due to the following factors: RV nozzles, penetrations, and other discontinuities have complex geometries that may exhibit significantly higher stresses than those for the RV beltline shell region. These higher stresses can potentially result in more restrictive P-T limits, even if the reference temperature (RT NDT) for these components is not as high as that of RV beltline shell materials that have simpler geometries. Ferritic RCPB components that are not part of the RV may have initial RTNDT values, which may define a more restrictive lowest operating temperature in the P -T limits than those for the RV beltline shell materials. Please describe how the P-T limit curves, and the methodology used to develop these curves considered all RV materials (beltline and non-beltline) and the lowest service temperature of all ferritic RCPB materials, consistent with the requirements of 10 CFR Part 50, Appendix G. Linear Elastic Fracture Mechanics (LEFM) evaluation of the N16 Water Level Instrument Nozzles: The licensee's LAR submittal, which includes Structural Integrity Associates (SIA) calculation package 1100445.303, provides a reference to the generic LEFM methodology used for calculating the applied stress intensity factor values for the N 16 instrument nozzles. For Cooper, the N16 nozzles define part of the bounding beltline region P-T curves at low temperatures. The generic LEFM methodology for boiling-water reactor instrument nozzles, provided in SIA Report No. 0900876.401, Revision 0, "Linear Elastic Fracture Mechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzles for Pressure-Temperature Curve Evaluation," November 2011 (ADAMS Accession No. ML 11325A074), is currently under review by NRC staff. Please provide an alternate methodology for the stated instrument nozzles.
B. O'Grady -2 If you have any questions, please contact me at 301-415-1377 or via e-mail at Lynnea.wilkins@nrc.gov. Docket No. 50-298 Request for Additional cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPLIV r/f RidsAcrsAcnw_MailCTR Resource RidsNrrDeEvib Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMCooper Resource RidsOgcRp Resource RidsRgn4MailCenter Resource CSydnor, NRRlDE/EVIB JPoehler, NRRlDE/EVIB ADAMS Accession No.: ML 12205A216 Sincerely, IRA! Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation OFFICE NRR/LPL4/PM NRR/LPL4/LA NRRlDE/EVIB/BC NRR/LPL4/BC NRRlLPL4/PM NAME LWilkins JBurkhardt SRosenberg (CSydnor for) MMarkley LWilkins DATE 7/24/12 7/24112 7/26112 8/10/12 8110112 OFFICIAL RECORD