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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
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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:Technical Specifications
MONTHYEARNLS2024025, License Amendment Request to Revise Technical Specifications Table 3.3.2.1-1, Control Rod Block Instrumentation2024-05-0909 May 2024 License Amendment Request to Revise Technical Specifications Table 3.3.2.1-1, Control Rod Block Instrumentation ML24096A1202024-04-0505 April 2024 Issuance of Amendment No. 275 Revision to Technical Specification 3.3.1.1 (Emergency Circumstances) NLS2024027, Response to NRC Request for Additional Information Regarding Application for the Emergency License Amendment Request to Revise Technical Specifications 3 .3 .1.1, Reactor Protection (RPS) Instrumentation2024-04-0303 April 2024 Response to NRC Request for Additional Information Regarding Application for the Emergency License Amendment Request to Revise Technical Specifications 3 .3 .1.1, Reactor Protection (RPS) Instrumentation NLS2024024, Emergency License Amendment Request to Revise Technical Specifications 3.3.1.1, Reactor Protection (RPS) Instrumentation2024-04-0101 April 2024 Emergency License Amendment Request to Revise Technical Specifications 3.3.1.1, Reactor Protection (RPS) Instrumentation 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 NLS2023029, License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks2023-09-0606 September 2023 License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks NLS2021041, Request for Exception from Leak Testing Requirement of the Primary Containment Leakage Rate Testing Program2021-07-20020 July 2021 Request for Exception from Leak Testing Requirement of the Primary Containment Leakage Rate Testing Program ML20314A2352020-12-0202 December 2020 Issuance of Amendment No. 268 Revision to Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, Using the Consolidated Line Item Improvement Process ML19238A0072019-10-30030 October 2019 Issuance of Amendment No. 263 Adoption of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation ML18218A4832018-09-0606 September 2018 Issuance of Amendment No. 261 Safety Limit Minimum Critical Power Ratio ML18137A2102018-05-10010 May 2018 License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio NLS2016010, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2016-03-22022 March 2016 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program ML15343A3012016-01-22022 January 2016 Issuance of Amendment No. 253 to Technical Specifications to Add Residual Heat Removal System Containment Spray Function ML16021A3222016-01-12012 January 2016 Correction to License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function ML15216A2592015-08-27027 August 2015 Issuance of Amendment No. 252, Revise Technical Specification 3.5.2, ECCS - Shutdown, to Delete Condensate Storage Tank as Alternate Source of Makeup Water ML15168A1712015-07-14014 July 2015 Issuance of Amendment No. 251, Request to Move Linear Heat Generation Rate (LHGR) and Single Loop Operation LHGR Limit from Technical Requirements Manual to Technical Specifications ML15135A0052015-05-29029 May 2015 Issuance of Amendment No. 250, Adopt Technical Specification Task Force (TSTF) Traveler TSTF-413, Elimination of Requirements for a Post Accident Sampling System (PASS) NLS2014087, License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function2015-01-15015 January 2015 License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function ML14055A0232014-04-29029 April 2014 Issuance of Amendment No. 248, Adopt National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants ML13191A1052013-09-12012 September 2013 Issuance of Amendment No. 247, Revise License Condition 2.E to Require All License Renewal Commitments Will Be Incorporated Into the Updated Safety Analysis Report 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 ML12157A2062012-05-30030 May 2012 License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio ML1136302582012-01-31031 January 2012 Issuance of Amendment No. 240, Revise Technical Specification 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs), to Reduce Number of Required SRVs for Overpressure Protection NLS2011086, Supplement to License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves2011-10-0606 October 2011 Supplement to License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves NLS2011071, License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a2011-09-16016 September 2011 License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a ML1101002912011-01-0505 January 2011 Cooper - License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves NLS2009034, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process2009-06-0202 June 2009 Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process ML0906207232009-02-26026 February 2009 Corrected Technical Specification Pages Regarding Reactor Equipment Cooling System Margin Amendment ML0815402852008-06-30030 June 2008 Technical Specifications, Measurement Uncertainty Recapture Power Uprate ML0812202892008-05-12012 May 2008 Technical Specification Pages for Issuance of Amendment No. 230 Control Room Habitability, TSTF-448 NLS2008046, Response to Request for Additional Information for License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate2008-05-0909 May 2008 Response to Request for Additional Information for License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate NLS2007079, Corrected Technical Specification Pages2007-11-0505 November 2007 Corrected Technical Specification Pages NLS2007048, License Amendment Request for a One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve2007-08-16016 August 2007 License Amendment Request for a One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve ML0630405382006-10-31031 October 2006 Tech Spec Pages for Amendment 226 Regarding MSIV Leakage Exemption from 10 CFR Part 50, Appendix J ML0629602942006-10-23023 October 2006 Technical Specification, Revised Limiting Condition for Operation (LCO) 3.10.1, Scram Time Testing Activities ML0627700902006-10-0303 October 2006 Technical Specification Pgs Amd #224 - Issuance of Amendment Additional Extension of Appendix J, Type a Integrated Leakage Rate Test Interval ML0625003012006-09-0606 September 2006 Technical Specifications, Technical Specification (TS) Changes Associated with Inservice Testing Program, Section 5.5.6, Under TS Programs and Manuals, MD0335 ML0624900372006-09-0505 September 2006 Technical Specifications, Application of the Alternative Source Term for Reevaluation of the Fuel Handling Accident Dose Consequences and Related Technical Specification Changes, MC8566 NLS2006042, License Amendment Request for Revision of Technical Specification 3.10.1, Inservice Leak and Hydrostatic Testing Operation2006-06-16016 June 2006 License Amendment Request for Revision of Technical Specification 3.10.1, Inservice Leak and Hydrostatic Testing Operation ML0612403772006-05-0303 May 2006 Correction to Amendment No. 218, Technical Specification Page 3.1-12 ML0612304692006-05-0202 May 2006 Technical Specifications, Changes to TS Leakage Limit for the Main Stream Isolation Valves ML0611802442006-04-27027 April 2006 Technical Specifications, Revised Pressure Vessel Fluence and Pressure Temp Curve Applicability to 30 Effective Full-Power Years of Operation ML0611001622006-04-18018 April 2006 Corrected Technical Specification Page 3.9-1 Re Refueling Operations NLS2006039, Corrected Technical Specification Page from Amendment No. 2182006-04-17017 April 2006 Corrected Technical Specification Page from Amendment No. 218 ML0609004412006-03-30030 March 2006 Technical Specification Pages, Change Request for Various Sections ML0628404572006-03-10010 March 2006 Tech Spec Pages for Amendment 217 Regarding Revise Technical Specifications Instrumentation Definitions NLS2006013, License Amendment Request to Update the American Society of Mechanical Engineers Code Referenced in TS Section 5.5.6, Inservice Testing Program2006-03-0707 March 2006 License Amendment Request to Update the American Society of Mechanical Engineers Code Referenced in TS Section 5.5.6, Inservice Testing Program NLS2006001, Application for TS Change to Add LCO 3.0.8 on Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2006-01-30030 January 2006 Application for TS Change to Add LCO 3.0.8 on Inoperability of Snubbers Using the Consolidated Line Item Improvement Process NLS2006002, License Amendment Request for a One-Time Extension of Containment Integrated Leakage Rate Test Interval2006-01-30030 January 2006 License Amendment Request for a One-Time Extension of Containment Integrated Leakage Rate Test Interval ML0602002922006-01-16016 January 2006 Cooper Nuclear Station - Revised and Supplemental Pages to License Amendment Request for Application of the Alternative Source Term for Reevaluation of the Fuel Handling Accident Dose Consequences 2024-05-09
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 29, 2013 Mr. Oscar A. Limpias Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION -CORRECTION TO TECHNICAL SPECIFICATION AND SAFETY EVALUATION PAGES FOR AMENDMENT NO. 245 RE: REVISIONS TO TECHNICAL SPECIFICATION 3.4.9, "RCS PRESSURE AND TEMPERATURE (PrT) LIMITS," FOR 32 EFFECTIVE FULL POWER YEARS (TAC NO. ME7324)
Dear Mr. Limpias:
By letter dated February 22, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13032A526), the U.S. Nuclear Regulatory Commission (NRC, the Commission) issued Amendment No. 245 to Renewed Facility Operating License No. DPR-46 for the Cooper Nuclear Station, in response to your application dated September 22, 2011, as supplemented by letters dated March 30, September 10, and September 28,2012, and January 3, 2013 (ADAMS Accession Nos. ML11272A057, ML12094A118, ML12258A072, ML12278A138, and ML13008A181, respectively). The amendment revised Cooper Nuclear Station's Technical Specification (TS) 3.4.9, "RCS [Reactor Coolant System] Pressure and Temperature (PrT) Limits," regarding the current 28 effective full power year (EFPY) pressure temperature (P-T) limit curves with new curves that are valid for 32 EFPY. The proposed 32 EFPY P-T limit curves were developed based on the consideration of a measurement uncertainty recapture power uprate that was approved with the issuance of Amendment No. 231 dated June 2,2008 (ADAMS Accession No. ML081540278).
As noted in discussions with your staff, the safety evaluation issued with the amendment cited 3 incorrect P-T limit curves. The safety evaluation cites the P-T curves in Figures 3.4.9-1,3.4.9-2, and 3.4.9-3 that were submitted by letter dated September 28,2012. By letter dated January 3, 2013, the licensee withdrew the aforementioned P-T curves and requested the NRC to approve the original license amendment request submitted on September 22, 2011. The NRC staff did evaluate and issue Amendment No 245 based upon the P-T curves in the September 22, 2011, submittal, as requested, and this was an administrative oversight by the NRC staff and does not affect the NRC staffs overall conclusions associated with Amendment No. 245.
Enclosed are the corrected TS pages 3.4-23, 3.4-24, and 3.4-25 for Figures 3.4.9-1, 3.4.9-2, and 3.4.9-3, respectively, and page 5 of the safety evaluation to be included with the issued amendment. We regret any inconvenience this may have caused.
O. Limpias - 2 In addition, by email datedMarch27.2013.Mr. Edward McCutchen of your staff requested a 30 day extension, from the date of this letter, to implement Amendment 245 due to competing activities associated with License Renewal implementation efforts. The NRC staff concludes that this extension is acceptable.
If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea. wilkins@nrc.gov.
Sincerely, d --I i /
' '\J-/l'-""./~( I
.~
.' Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosure:
Revised TS and SE pages cc w/encl: Distribution via Listserv
ENCLOSURE REVISED TECHNICAL SPECIFICATION PAGES 3.4-23, 3.4-24, AND 3.4-25, AND SAFETY EVALUATION PAGE 5 FOR AMENDMENT NO. 245 DATED FEBRUARY 22,2013
RCS PIT limits 3.4.9 Cooper Heatup/Cooldown, Core Not Critical Curve (Curve B), 32 EFPY Safe Operating o ~~~~-+~~-+~~~~~~~~~~~~~~~~~~
., 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEl METAL TEMPERATURE (Of)
Figure 3.4.9-1 PressurelTemperature limits* for Non-Nuclear Heatup or Cooldown Following Nuclear Shutdown Valid Through 32 EFPY Cooper 3.4-23 Amendment No. 245
Res PIT Limits 3.4.9 Cooper Pressure Test Curve (Curve A), 32 EFPY 300 8oI-up Temp:
>70 F 200 100 0
0 20 40 80 80 100 120 140 180 180 200220 240 260 280 300 320 340 MINIMUM REACTOR VESSel METAl TEMPERAllJRE rFJ Figure 3.4.9-2 PressurelTemperature Limits for Inservice Hydrostatic and Inservice leakage Tests Valid Through 32 EFPY Cooper 3.4-24 Amendment No. 245
RCS PfT Limits 3.4.9 Cooper Haatup/Cooldown, Core Critical Curve (Curve C), 32 EFPY 1.100 +-to-+
1,000 +-1-+--+-+-+
- i
.I m~ ~-+~~~~+-~~+-
~800 +----+-+--+
~700 i
...1600 +-+-+-1
..I i~500 f--+-,o+-+-+
~ ~~~+-~~+-~-+~~-+~~~
MintmumCore CritIcal Temperature:
- > serF ~,-J;:f:t::f:
~~~80~m~~~~m~~_B~~
MINIMUM REACTOR VESSEL METAl TEMPERATURE (OF)
Figure 3.4.9-3 PressurefTemperature Limits for Criticality Valid Through 32 EFPY Cooper 3.4-25 Amendment No. 245
-5 shall reflect consideration of service temperatures and other conditions of the boundary material under operating, maintenance, testing, and postulated accident conditions and the uncertainties in determining (1) material properties, (2) the effects of irradiation on material properties, (3) residual, steady state and transient stresses, and (4) size of flaws.
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes By letter dated September 22, 2011, as supplemented by letter dated September 28, 2012, the licensee proposed the following revisions to TS 3.4.9 requirements for the RCS P-T limits:
- TS Figure 3.4.9-1, "PressurelTemperature limits for Non-Nuclear Heatup or Cooldown Following Nuclear Shutdown," will be revised to include new P-T limits for heat-up and cool-down operations with the core not critical that are valid through 32 EFPY. For a markup of proposed changes to TS Figure 3.4.9-1. see Attachment 2 of the licensee's letter dated September 22, 2011.
- TS Figure 3.4.9-2, "PressurelTemperature limits for Inservice Hydrostatic and Inservice Leakage Tests," will be revised to include new P-T limits for pressure test conditions that are valid through 32 EFPY. For a markup of proposed changes to TS Figure 3.4.9-2. see Attachment 2 of the licensee's letter dated September 22, 2011.
- TS Figure 3.4.9-3. "PressurelTemperature limits for Criticality," will be revised to include new P-T limits for heat-up and cool-down operations, with the core critical that are valid through 32 EFPY. For a markup of proposed changes to TS Figure 3.4.9-3, see Attachment 2 of the licensee's letter dated September 22, 2011.
- SRs 3.4.9.5,3.4.9.6, and 3.4.9.7 will be revised to reflect the decrease in the minimum bolt-up temperature value from 80 OF to 70 OF, as specified for the proposed 32 EFPY P-T limits for pressure test and core not critical conditions.
The NOTES in SR 3.4.9.6 and SR 3.4.9.7 for MODE 4 (cold shutdown) will also be changed to reduce by 10°F the points at which the surveillances are required to be performed in order to maintain the same margins from the minimum operating parameters.
Specifically, current SRs 3.4.9.5, 3.4.9.6, and 3.4.9.7 state that Verify reactor vessel flange and head flange temperatures are
> 80°F.
O. limpias -2 In addition, by email datedMarch27.2013.Mr. Edward McCutchen of your staff requested a 30 day extension, from the date of this letter, to implement Amendment 245 due to competing activities associated with License Renewal implementation efforts. The NRC staff concludes that this extension is acceptable.
If you have any questions, please contact me at 301-415-1377 orvia e-mail at Iynnea. wilkins@nrc.gov.
Sincerely, IRA!
Lynnea E. Wilkins, Project Manager Plant licensing Branch IV Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosure:
Revised TS and SE pages cc w/encl: Distribution via listserv DISTRIBUTION:
PUBLIC RidsNrrLAJBurkhardt Resource LPLIV r/f RidsNrrPMCooper Resource RidsAcrsAcnw_MailCTR Resource RidsRgn4MailCenter Resource RidsNrrDorlDpr Resource BParks, NRR/DSS/SRXB RidsNrrDorlLpl4 Resource RGrover, NRRIDSS/STSB RidsNrrDssSrxb Resource JPoehler, NRR/DE/EVIB RidsNrrDeEvib Resource CSydnor, NRR/DE/EVIB RidsNrrDssStsb Resource ADAMS Accession No. ML13085A096 OFFICE NRR/DORlILPL4/PM NRR/DORlILPL4/LA NRRlDORULPL4/BC NRR/DORULPL4/PM MMarkley (JPolickoski NAME LWilkins JBurkhardt for) LWilkins DATE 3/27113 3127/13 3129/13 3/29/13 OFFICIAL RECORD COpy