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| | number = ML12205A216 | | | number = ML12205A216 |
| | issue date = 08/10/2012 | | | issue date = 08/10/2012 |
| | title = Cooper Nuclear Station - 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 (TAC ME | | | title = 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 |
| | author name = Wilkins L E | | | author name = Wilkins L |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = O'Grady B J | | | addressee name = O'Grady B |
| | addressee affiliation = Nebraska Public Power District (NPPD) | | | addressee affiliation = Nebraska Public Power District (NPPD) |
| | docket = 05000298 | | | docket = 05000298 |
| | license number = DPR-046 | | | license number = DPR-046 |
| | contact person = Wilkins L E | | | contact person = Wilkins L |
| | case reference number = TAC ME7324 | | | case reference number = TAC ME7324 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#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 STATES NUCLEAR REGULATORY COMMISSION 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 |
| 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. | | ==SUBJECT:== |
| 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
| | 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. ML11272A057), 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. ML120590085), the U.S. Nuclear Regulatory Commission (NRC) issued a request for additional information (RAI). By letter dated March 30, 2012 (ADAMS Accession No. ML12094A119), 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 - 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. ML11272A057), 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. ML120590085), the U.S. Nuclear Regulatory Commission (NRC) issued a request for additional information (RAI). By letter dated March 30, 2012 (ADAMS Accession No. ML12094A119), 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: |
| | : 1. 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/cm 2 , E> 1 MeV), as well as ferritic RCPB materials not in the RV beltline (neutron fluence < 1 x 10 17 n/cm 2 , |
| | 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: |
| | : a. 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. |
| | : b. Ferritic RCPB components that are not part of the RV may have initial RT NDT 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. |
| | : 2. 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. ML11325A074), is currently under review by NRC staff. Please provide an alternate methodology for the stated instrument nozzles. |
| | |
| | ML12205A216 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRRlDE/EVIB/BC NRR/LPL4/BC NRRlLPL4/PM SRosenberg NAME LWilkins JBurkhardt (CSydnor for) MMarkley LWilkins DATE 7/24/12 7/24112 7/26112 8/10/12 8110112}} |
Letter Sequence RAI |
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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
NLS2012062, Response to Request 2 for Additional Information License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits.2012-09-10010 September 2012
Response to Request #2 for Additional Information License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits.
Project stage: Request
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
NLS2013001, Response to Request 3 for Additional Information License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits2013-01-0303 January 2013
Response to Request #3 for Additional Information License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits
Project stage: Request
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
2012-05-07
[Table View] |
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Category:Letter
MONTHYEARIR 05000298/20240032024-11-0505 November 2024
Integrated Inspection Report 05000298/2024003
ML24250A2052024-10-0808 October 2024
Issuance of Amendment No. 278 Regarding Revision to Technical Specification Table 3.3.2.1-1 and Transfer of Minimum Critical Power Ratio Values to Core Operating Limit Report
ML24227A0822024-09-0303 September 2024
Summary of Regulatory Audit in Support of License Amendment Request to Modify the High Pressure Coolant Injection Low Flow Value
IR 05000298/20240052024-08-22022 August 2024
Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2024005)
IR 05000298/20240022024-07-25025 July 2024
Integrated Inspection Report 05000298/2024002
ML24183A1722024-07-17017 July 2024
Issuance of Amendment No. 277 to Adopt TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil
ML24197A1462024-07-15015 July 2024
NRC Region IV Ltr to Cooper Nuclear Station Re FEMA Level 1 Finding
ML24134A1782024-07-0303 July 2024
Issuance of Amendment No. 276 Revision to Technical Specification 3.8.3, Diesel Fuel Oil, Lube Oil and Starting Air, to Allow for Cleaning, Inspection and Any Needed Repairs During Refuel Outage 33
ML24197A0682024-06-24024 June 2024
FEMA Ltr to Missouri State Emergency Management Agency - Level 1 Finding, 24 June 2024
ML24192A0112024-06-13013 June 2024
2024-06-Post Exam Comments
05000298/LER-2023-002-01, Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications2024-06-0606 June 2024
Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications
IR 05000298/20244012024-06-0404 June 2024
Security Baseline Inspection Report 05000298/2024401
ML24151A1082024-05-30030 May 2024
NRC Initial Operator Licensing Examination Approval 05000298/2024301
ML24137A0942024-05-17017 May 2024
Regulatory Audit Plan in Support of License Amendment Request to Modify Allowable Value Regarding Technical Specification for High Pressure Coolant Injection Pump Discharge Low Flow
05000298/LER-2024-005, High Pressure Coolant Injection Pressure Switch Installation Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited B Technical2024-05-13013 May 2024
High Pressure Coolant Injection Pressure Switch Installation Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited B Technical.
05000298/LER-2024-004, Main Turbine Stop Valve Position Switches Do Not Meet Channel Independence Criteria Results in Two Channels Being Declared Inoperable and a Condition Prohibited by Technical Specifications2024-05-0909 May 2024
Main Turbine Stop Valve Position Switches Do Not Meet Channel Independence Criteria Results in Two Channels Being Declared Inoperable and a Condition Prohibited by Technical Specifications
IR 05000298/20240012024-05-0303 May 2024
Integrated Inspection Report 05000298/2024001
ML24129A0952024-04-25025 April 2024
Preparation and Scheduling of Operator Licensing Examinations
IR 05000298/20240102024-04-24024 April 2024
Comprehensive Engineering Team Inspection Report 05000298/2024010
05000298/LER-2024-003, High Pressure Coolant Injection Steam Leak Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited by Technical Specifications2024-04-22022 April 2024
High Pressure Coolant Injection Steam Leak Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited by Technical Specifications
ML24096A1202024-04-0505 April 2024
Issuance of Amendment No. 275 Revision to Technical Specification 3.3.1.1 (Emergency Circumstances)
ML24093A2282024-04-0202 April 2024
Notice of Enforcement Discretion for Cooper Nuclear Station
IR 05000298/20240902024-04-0101 April 2024
– Notice of Violation, NRC Inspection Report 05000298/2024090
05000298/LER-2024-001, Inoperable Turbine Stop Valve Limit Switch Causes Condition Prohibited by Technical Specifications2024-03-0404 March 2024
Inoperable Turbine Stop Valve Limit Switch Causes Condition Prohibited by Technical Specifications
05000298/LER-2024-002, Technical Specifications Prohibited Condition for Inoperable Service Water Booster Pump2024-03-0404 March 2024
Technical Specifications Prohibited Condition for Inoperable Service Water Booster Pump
IR 05000298/20230062024-02-28028 February 2024
Annual Assessment Letter for Cooper Nuclear Station - Report 05000298/2023006
IR 05000298/20230042024-02-12012 February 2024
Integrated Inspection Report 05000298/2023004
ML24033A3092024-02-12012 February 2024
Summary of Regulatory Audit Regarding the Relief Request RC3-02 Regarding Drywell Head Bolting
IR 05000298/20230122024-02-12012 February 2024
NRC Inspection Report 05000298/2023012
ML23334A2012024-01-0303 January 2024
Issuance of Amendment No. 274 Revision to Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements
05000298/LER-2023-002, Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications2023-12-20020 December 2023
Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications
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
ML23311A1122023-11-0909 November 2023
Project Manager Assignment
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
05000298/LER-2022-002-01, Manual Core Spray Injection to Restore Skimmer Surge Tank Level2023-06-29029 June 2023
Manual Core Spray Injection to Restore Skimmer Surge Tank Level
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
05000298/LER-2022-004-01, 1 for Cooper Nuclear Station, Manual Reactor Scram and Group I Isolation Due to Main Turbine Bypass Valve Failing Open2023-05-11011 May 2023
1 for Cooper Nuclear Station, Manual Reactor Scram and Group I Isolation Due to Main Turbine Bypass Valve Failing Open
05000298/LER-2023-001, Valve Test Failures Result in Condition Prohibited by Technical Specifications2023-05-0808 May 2023
Valve Test Failures Result in Condition Prohibited by Technical Specifications
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
2024-09-03
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24094A2462024-04-0303 April 2024
NRR E-mail Capture - Cooper Nuclear Station - RAI Emergency LAR Turbine Stop Valve Limit Switch TS 3.3.1.1
ML24032A2382024-02-0101 February 2024
NRR E-mail Capture - Cooper Nuclear Station - LAR Dfo Tank Inspection RAI Issuance
ML24010A1172024-01-10010 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
ML13133A0802013-05-24024 May 2013
(Redacted) - Request for Additional Information, Review of License Renewal Commitment NLS2009100-1 - Core Rim Plate Bolts
ML13144A5202013-05-24024 May 2013
Request for Additional Information Email, Decommissioning Funding Status Report
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
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
ML12157A5412012-06-11011 June 2012
Second Request for Additional Information Request for Relief for the Fourth 10-Year Pump and Value Inservice Testing Program
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
2024-04-03
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION 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
SUBJECT:
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. ML11272A057), 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. ML120590085), the U.S. Nuclear Regulatory Commission (NRC) issued a request for additional information (RAI). By letter dated March 30, 2012 (ADAMS Accession No. ML12094A119), 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 - 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. ML11272A057), 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. ML120590085), the U.S. Nuclear Regulatory Commission (NRC) issued a request for additional information (RAI). By letter dated March 30, 2012 (ADAMS Accession No. ML12094A119), 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:
- 1. 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/cm 2 , E> 1 MeV), as well as ferritic RCPB materials not in the RV beltline (neutron fluence < 1 x 10 17 n/cm 2 ,
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:
- a. 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.
- b. Ferritic RCPB components that are not part of the RV may have initial RT NDT 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.
- 2. 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. ML11325A074), is currently under review by NRC staff. Please provide an alternate methodology for the stated instrument nozzles.
ML12205A216 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRRlDE/EVIB/BC NRR/LPL4/BC NRRlLPL4/PM SRosenberg NAME LWilkins JBurkhardt (CSydnor for) MMarkley LWilkins DATE 7/24/12 7/24112 7/26112 8/10/12 8110112
