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MONTHYEARNLS2011015, License Amendment Request to Revise Technical Specification Pressure/Temperature Limit Curves and Surveillance Requirements2011-09-22022 September 2011 License Amendment Request to Revise Technical Specification Pressure/Temperature Limit Curves and Surveillance Requirements Project stage: Request ML1130815502011-11-0404 November 2011 Acceptance Review Email, License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature Limits Project stage: Acceptance Review ML1204503792012-02-14014 February 2012 Request for Additional Information, License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and Surveillance Requirements Project stage: RAI ML1204503532012-02-14014 February 2012 Email, Request for Additional Information, License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and Surveillance Requirements Project stage: RAI ML1205900852012-02-29029 February 2012 Request for Additional Information, License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and Surveillance Requirements Project stage: RAI NLS2012023, Response to Request for Additional Information License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (Pit) Limits2012-03-30030 March 2012 Response to Request for Additional Information License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (Pit) Limits Project stage: Response to RAI ML1212901232012-05-0707 May 2012 Round 2, Draft Request for Additional Information, License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and SRs Project stage: Draft RAI ML1212900812012-05-0707 May 2012 Email, Round 2, Draft Request for Additional Information, License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and SRs Project stage: Draft RAI ML12205A2162012-08-10010 August 2012 Request for Additional Information, Round 2, License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and Surveillance Requirements Project stage: RAI ML12278A1382012-09-28028 September 2012 Supplement to License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits Project stage: Supplement ML12338A2642012-12-0303 December 2012 Email, Round 3, Request for Additional Information, License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and SRs Project stage: RAI ML13032A5262013-02-22022 February 2013 Issuance of Amendment No. 245, Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and Surveillance Requirements Project stage: Approval ML13085A0962013-03-29029 March 2013 Corrected Technical Specification (TS) and Safety Evaluation Pages for Amendment No. 245, Revise TS 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and Surveillance Requirements Project stage: Approval 2012-03-30
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Category:Request for Additional Information (RAI)
MONTHYEARML24010A1172024-01-10010 January 2024 NRR E-mail Capture - Cooper Nuclear Station - LAR Dfo Tank Inspection RAI Issuance ML24010A0902024-01-0404 January 2024 RAI - 10120-R1 - Final Dfo Tank Inspections LAR ML23352A2472023-12-18018 December 2023 NRR E-mail Capture - Cooper Nuclear Station - Relief Request RC3-02 Drywell Head Inspection RAI Issuance ML23257A2192023-09-14014 September 2023 NRR E-mail Capture - Cooper - Final RAI LAR to Adopt TSTF-551, Revision 3 ML22276A1562022-10-0505 October 2022 Notification of Commercial Grade Dedication Inspection 05000298/2023011 and Request for Information ML22208A0642022-07-26026 July 2022 Notification of Inspection and Request for Information for NRC Inspection Report 05000298/2022004 ML22179A3152022-06-28028 June 2022 Notification of Post-Approval Site Inspection for License Renewal (Phase 4) (NRC Inspection Report 05000298/2022011) and Request for Information ML22010A2632022-01-10010 January 2022 NRR E-mail Capture - Cooper - Final RAI Relief Request RR5-01 Revision 1 ML21321A3742021-11-10010 November 2021 NRR E-mail Capture - Cooper - Final RAI Alternative Request RI5-02 Revision 3 ML21258A2632021-09-15015 September 2021 NRR E-mail Capture - Cooper - Final RAI Alternative Request RS-01 ML21109A2222021-04-15015 April 2021 Email with RFI Document for CNS PIR 2021012 ML21026A3112021-01-27027 January 2021 Notification of NRC Design Bases Assurance Inspection (Team) (NRC Inspection Report 05000298/2021010) and Initial Request for Information ML20315A3922020-11-10010 November 2020 Email 11-10-2020 - Cooper EP Prog Insp RFI ML20203M3692020-07-21021 July 2020 NRR E-mail Capture - Cooper - Final RAI License Amendment Request for Approval of EAL Scheme Change (EPID L-LLA-2020-0028) ML18306A5582018-10-30030 October 2018 Notification of Cyber Security Inspection(Nrc Inspection Report 05000298/2019410) and Request for Information ML18060A0272018-02-28028 February 2018 Enclosurequest for Additional Information (Letter to J. Shaw Request for Additional Information Regarding Nebraska Public Power District'S Decommissioning Funding Plan Update for Cooper Nuclear Station ISFSI) ML18037B0002018-02-0606 February 2018 NRR E-mail Capture - Cooper Nuclear Station - Final RAI Relief Requests RR-02 and RR-03 (EPIDs L-2017-LRR-065 and -066) ML18025C0042018-01-25025 January 2018 Notification of NRC Design Bases Assurance Inspection (Teams) (05000298/2018011) and Initial Request for Information ML18024A3752018-01-24024 January 2018 NRR E-mail Capture - Cooper Nuclear Station - Final RAI LAR to Adopt TSTF-542 (CAC MG0138; EPID L-2017-LLA-0290) IR 05000298/20170032017-11-13013 November 2017 NRC Integrated Inspection Report 05000298/2017003 and Independent Spent Fuel Storage Installation Inspection Report 07200066/2017001 ML17177A2432017-06-26026 June 2017 Notification of NRC Design Bases Assurance Inspection (Programs) (05000298/2017007) and Initial Request for Information ML17024A3292016-12-15015 December 2016 NRR E-mail Capture - Rec 2.1 Seismic: Cooper'S SFP Evaluation ML16335A0152016-11-29029 November 2016 NRR E-mail Capture - Cooper Nuclear Station - Formal Request for Additional Information Concerning License Amendment Request to Adopt TSTF-425 Revision 3 ML16112A2732016-04-21021 April 2016 Notification of NRC Triennial Fire Protection Baseline Inspection (05000298/2016008) and Request for Information ML15107A2542015-05-0404 May 2015 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Hazard and Screening Report ML15051A4872015-02-20020 February 2015 Notification of NRC Component Design Bases Inspection 05000298/2015007 and Initial Request for Information ML13323A1052013-12-0404 December 2013 Interim Staff Evaluation and Request for Additional Information, Overall Integrated Plan in Response to 3/12/12 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13256A0822013-09-12012 September 2013 Request for Additional Information Email, Overall Integrated Plan in Response to 3/12/12 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) ML13246A3482013-08-29029 August 2013 Draft Request for Additional Information Email, Overall Integrated Plan in Response to 3/12/12 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) NLS2013082, Letter Requesting Information from the United States Army Corps of Engineers to Provide Response to March 12, 2012 Letter Regarding Enclosure 2, Recommendation 2.1, Flooding2013-08-22022 August 2013 Letter Requesting Information from the United States Army Corps of Engineers to Provide Response to March 12, 2012 Letter Regarding Enclosure 2, Recommendation 2.1, Flooding ML13155A0112013-06-0303 June 2013 Request for Additional Information Email, 2013 Decommissioning Funding Status Report ML13144A5202013-05-24024 May 2013 Request for Additional Information Email, Decommissioning Funding Status Report ML13133A0802013-05-24024 May 2013 (Redacted) - Request for Additional Information, Review of License Renewal Commitment NLS2009100-1 - Core Rim Plate Bolts ML13095A1602013-04-0404 April 2013 Email, Draft Request for Additional Information - Review of License Renewal Commitment NLS2009100-1 - Core Rim Plate Bolts ML13059A3452013-03-0808 March 2013 Request for Additional Information, License Amendment Request to Revise the Updated Safety Analysis Report to Reflect Changes to Fuel Handling Accident Dose Calculation ML13053A3422013-02-22022 February 2013 E-mail, Draft Request for Additional Information, License Amendment Request to Revise the Updated Safety Analysis Report to Reflect Changes to Fuel Handling Accident Dose Calculation ML12338A2642012-12-0303 December 2012 Email, Round 3, Request for Additional Information, License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and SRs ML12312A2812012-11-14014 November 2012 Request for Additional Information, License Amendment Request to Adopt National Fire Protection Agency (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants ML12283A4002012-10-0909 October 2012 Email, Draft Request for Additional Information, License Amendment Request to Adopt National Fire Protection Agency (NFPA)-805 Performance-Based Standard for Fire Protection for LWR Electric Generating Plants ML12251A0582012-09-0606 September 2012 Request for Additional Information, License Amendment Request, Round 2, Revise Technical Specifications to Implement a 24-Month Fuel Cycle and Adopt TSTF-493, Revision 4, Option a ML12235A2522012-09-0505 September 2012 Request for Additional Information License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio ML12205A2162012-08-10010 August 2012 Request for Additional Information, Round 2, License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and Surveillance Requirements ML1217400512012-06-21021 June 2012 List of Questions for Supplement to Complete Acceptance Review, License Amendment Request to Adopt NFPA-805 Performance-Based Standard for Fire Protection for LWR Electric Generating Plants ML12157A5412012-06-11011 June 2012 Second Request for Additional Information Request for Relief for the Fourth 10-Year Pump and Value Inservice Testing Program ML12159A2992012-06-11011 June 2012 Request for Additional Information, Relief Request RI-07 from ASME Code Requirements for Residual Heat Removal Shell Circumferential and Nozzle to Head Welds, Fourth 4th 10-Year Inservice Inspection Interval ML12153A0642012-05-31031 May 2012 Notification of Inspection (NRC Inspection Report 05000298/2012005) and Request for Information ML1213905092012-05-18018 May 2012 Email, Draft Request for Additional Information, Second Round, Relief Request Nos. RV-07 and RV-01, Revision 1, Fourth 10-Year Inservice Testing Program Interval ML1213905112012-05-18018 May 2012 Draft Request for Additional Information, Second Round, Relief Request Nos. RV-07 and RV-01, Revision 1, Fourth 10-Year Inservice Testing Program Interval ML1213205752012-05-11011 May 2012 Request for Additional Information, Relief Request RI-07 from ASME Code Requirements for Residual Heat Removal Shell Circumferential and Nozzle to Head Welds, Fourth 4th 10-Year Inservice Inspection Interval 2024-01-04
[Table view] Category:Letter
MONTHYEARML23334A2012024-01-0303 January 2024 Issuance of Amendment No. 274 Revision to Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements ML23311A1122023-11-0909 November 2023 Project Manager Assignment ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000298/20230032023-11-0202 November 2023 Integrated Inspection Report 05000298/2023003 IR 05000298/20234012023-11-0101 November 2023 Cyber Security Report 05000298/2023401 Public ML23264A8052023-10-11011 October 2023 Issuance of Amendment No. 273 Revision to Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23233A1882023-09-0505 September 2023 Regulatory Audit Plan in Support of Relief Request RC3-02 Regarding Drywell Head Bolting IR 05000298/20243012023-09-0101 September 2023 Notification of NRC Initial Operator Licensing Examination 05000298/2024301 IR 05000298/20230052023-08-21021 August 2023 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2023005)- Mid Cycle Letter IR 05000298/20230022023-08-0808 August 2023 Integrated Inspection Report 05000298/2023002 IR 05000298/20234022023-08-0303 August 2023 NRC Security Inspection Report 05000298/2023402 ML23214A2742023-08-0303 August 2023 Nuclear Station - Notification of Inspection (NRC Inspection Report 05000298/2023004) and Request for Information IR 05000298/20234202023-08-0101 August 2023 Security Baseline Inspection Report 05000298/2023420 ML23173A0862023-06-26026 June 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000298/2023401 IR 05000298/20230102023-05-17017 May 2023 Biennial Problem Identification and Resolution Inspection Report 05000298/2023010 IR 05000298/20234032023-05-0404 May 2023 Security Baseline Inspection Report 05000298/2023403 ML23129A2822023-04-20020 April 2023 Submittal of Revision 31 to Updated Safety Analysis Report ML23102A0282023-04-19019 April 2023 U.S. Nuclear Regulatory Commission Presentation at the May 8, 2023, Brownville Village Meeting IR 05000298/20230012023-04-17017 April 2023 Integrated Inspection Report 05000298/2023001 ML23060A1582023-03-0808 March 2023 Design Basis Assurance Inspection (Programs) Inspection Report 05000298/2023001 IR 05000298/20220062023-03-0101 March 2023 Annual Assessment Letter for Cooper Nuclear Station Report 05000298/2022006 ML23041A1622023-02-10010 February 2023 Licensed Operator Positive Fitness-for-Duty Test Request for Additional Information IR 05000298/20220042023-01-30030 January 2023 Integrated Inspection Report 05000298/2022004 IR 05000298/20220112022-12-23023 December 2022 License Renewal Phase 4 Inspection Report 05000298/2022011 ML22286A2072022-11-30030 November 2022 Issuance of Amendment No. 272 Revision to Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements IR 05000298/20220032022-10-27027 October 2022 Integrated Inspection Report 05000298/2022003 ML22304A0052022-10-26026 October 2022 Surveillance Capsule Location (Re-insertion Into the Reactor Vessel) IR 05000298/20223022022-10-20020 October 2022 NRC Initial Operator Licensing Examination Approval 05000298/2022302 ML22276A1562022-10-0505 October 2022 Notification of Commercial Grade Dedication Inspection 05000298/2023011 and Request for Information IR 05000298/20224022022-09-29029 September 2022 NRC Security Inspection Report 05000298/2022402 (Full Report) IR 05000298/20220052022-08-18018 August 2022 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298 2022005) IR 05000298/20223012022-08-10010 August 2022 NRC Examination Report 05000298/2022301 IR 05000298/20220022022-07-28028 July 2022 Integrated Inspection Report 05000298/2022002 ML22200A2772022-07-21021 July 2022 Correction to Proposed Inservice Testing Alternative RS-01, Revision of Error in Safety Evaluation ML22152A1232022-07-18018 July 2022 Issuance of Amendment No. 271 Request for Exception from Certain Primary Containment Leak Rate Testing Requirements IR 05000298/20224012022-06-29029 June 2022 Security Baseline Inspection Report 05000298/2022401 IR 05000298/20224032022-06-28028 June 2022 Security Baseline Inspection Report 05000298/2022403 IR 05000298/20220102022-06-16016 June 2022 Triennial Fire Protection Inspection Report 05000298/2022010 ML22140A1612022-06-0808 June 2022 Proposed Inservice Inspection Alternative RR5-01 Revision 1 ML22147A1122022-06-0101 June 2022 NRC Initial Operator Licensing Examination Approval 05000298/2022301 ML22111A1382022-05-13013 May 2022 Proposed Inservice Testing Alternative RS-01, Revision 0 IR 05000298/20220012022-04-28028 April 2022 Integrated Inspection Report 05000298/2022001 IR 05000298/20224042022-04-13013 April 2022 Material Control and Accounting Program Inspection Report 05000298/2022404 - (Public) ML22084A6032022-04-0404 April 2022 Notification of NRC Evaluations of Changes, Tests and Experiments Inspection 05000298/2022002 and Request for Information ML22090A2892022-04-0101 April 2022 John Larson'S Invitation to Participate in the 8th Nuclear Regulatory Commission'S Workshop on Vendor Oversight ML22045A0012022-03-31031 March 2022 Proposed Inservice Inspection Alternative RI5- 02 Revision 3 IR 05000298/20210062022-03-0202 March 2022 Annual Assessment Letter for Cooper Nuclear Station (Report 05000298/2021006) IR 05000298/20210042022-01-24024 January 2022 Integrated Inspection Report 05000298/2021004 ML21350A0582021-12-21021 December 2021 Withdrawal of an Amendment Request ML21340A2362021-12-20020 December 2021 Issuance of Amendment No. 270 Adoption of Technical Specifications Task Force Traveler TSTF-582, Revision 0, RPV WIC Enhancements 2024-01-03
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 February 29, 2012 Mr. Brian J. OGrady 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. OGrady:
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. The U.S. Nuclear Regulatory Commission staff has reviewed your submittal and determined that additional information is needed for the staff to complete its evaluation.
The request for additional information was transmitted via e-mail to Mr. Edward McCutchen of your staff on February 14, 2012. Mr. McCutchen indicated via e-mail on February 15, 2012, that the response would be provided within 30 days of receipt of this letter.
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. 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 (Cooper).
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 (RV) flange and RV head flange temperatures are greater than the revised minimum operating temperature (70 degrees Fahrenheit (OF>> specified for the proposed 32 EFPY P-T limits. The U.S. Nuclear Regulatory Commission (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 proposed 32 EFPY P-T limits for all operating conditions, including pressure test conditions, are based, in part, on the adjusted Reference Temperature of Nil-Ductility Transition (adjusted RT NDT (ART>> for the limiting RV beltline shell material at 32 EFPY. The NRC staff noted discrepancies among the various parts of the submittal regarding the limiting beltline shell ART value. Specifically, Section 3.3 of the LAR (page 5 of 11) states, in part, that U[t]he most limiting beltline material is the Lower Longitudinal Weld with an ART value of 103.5 of. Cooper Calculation No. NEDC 07-048 (Enclosure to the LAR, page 5 of 7), states, in part, that "[t]he limiting beltline material has an ART value of 1 03.2°F and 123.5°F for 32 and 54 EFPY, respectively." Also, Structural Integrity Associates (SIA) Calculation Package 1100445.303 (Enclosure to the LAR, page 10 of 40) states, in part that, "the limiting beltline material is the Lower/Intermediate shell plate, which has an ART value of 105.8°F for 32 EFPY and 131.2°F for 54 EFPY." Please identify the correct limiting beltline shell material and corresponding ART value for this material at 32 EFPY. Please provide the inputs necessary for calculating this ART value, based on NRC Regulatory Guide (RG) 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," May 1988 (ADAMS Accession No. ML003740284), procedures (initial RT NDT, CU content, Ni content, chemistry factor calculations, 32 EFPY fluence, and margin term calculations).
Enclosure
-2 The 32 EFPY P-T limits for core not critical and pressure test conditions are based, in part, on the fracture mechanics calculations for the limiting N16 instrument nozzle. Specifically, SIA Calculation Package 1100445.303 identifies the N16 nozzles as being located in the extended beltline region. The SIA calculation report (Enclosure to the LAR, page 6 of 40) states, in part, that, "[t]he nozzle material is not ferritic and does not need to be specifically evaluated.
However, the effect of the [nozzle] penetration on the adjacent [RV beltline]
shell must be considered." Accordingly, the SIA report documents P-T limit calculations for the limiting N16 nozzle based on thermal and pressure stress intensity factors, which are determined based on nozzle configuration/geometry and finite element analyses, and a 32 EFPY ART value of 52.4 of. Please identify the RV beltline shell material which contains the N16 nozzle penetrations. Please confirm that a 32 EFPY ART value of 52.4 of is the correct value for the RV plate with the embedded N16 nozzles. Please provide the inputs necessary for calculating this ART value, based on RG 1.99, Revision 2 procedures (initial RT NOT, CU content, Ni content, chemistry factor calculations, 32 EFPY fluence, and margin term calculations). The proposed 32 EFPY P-T limits for heat-up and cool-down operations with the core not critical show a reduction in the minimum operating (bolt-up) temperature requirement from 80 OF (as specified in the current TS P-T limits) to 70 of. While the NRC staff notes that the new minimum temperature requirement of 70 of will continue to remain acceptable per the minimum temperature requirements specified in Table 1 of Appendix G, "Fracture Toughness Requirements," to Part 50 of Title 10 of the Code of Federal Regulations (10 CFR), the NRC staff could not find an explanation for the change. Please discuss the technical basis for the reduction in the minimum operating (bolt-up) temperature requirement.
B. O'Grady -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
_MaiICTR Resource RidsNrrDeEvib Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMCooper Resource RidsOgcRp Resource RidsRgn4MailCenter Resource CSydnor, NRRlDE/EVIB ADAMS Accession No.: ML 120590085 Sincerely, IRA! Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- via memo dated [@'frICE NRRlLPL4IPM NRR/LPL4/LA NRR/DE/EVIB/BC NRRlLPL4/BC NRR/LPL4/PM NAME LWilkins JBurkhardt SRosenberg*
MMarkley LWilkins (NKalyanam for) DATE 2/28/12 2/28/12 1/30/12 2/29/12 2/29/12 OFFICIAL RECORD