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Category:Letter
MONTHYEARML23326A0392024-01-24024 January 2024 Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24017A1582024-01-17017 January 2024 Submittal of Emergency Plan Revision 50 IR 05000313/20234202024-01-10010 January 2024 Security Baseline Inspection Report 05000313/2023420 and 05000368/2023420 IR 05000313/20234022024-01-0202 January 2024 Security Baseline Inspection Report 05000313/2023402 and 05000368/2023402 ML23354A0022023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment IR 05000313/20234052023-12-12012 December 2023 Security Baseline Inspection Report 05000313/2023405 and 05000368/2023405 ML23341A0832023-12-11011 December 2023 Material Control and Accounting Program Inspection Report 05000313/368/2023404- Cover Letter ML23305A0922023-12-0707 December 2023 Summary of Regulatory Audit Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23275A2072023-11-28028 November 2023 Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23325A1412023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000313/20230032023-11-21021 November 2023 Revised - ANO Revised Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/ 2023001 ML23243B0452023-11-13013 November 2023 Request for Withholding Information from Public Disclosure ML23313A0962023-11-13013 November 2023 Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/2023001 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 05000313/20230112023-10-10010 October 2023 Commercial Grade Dedication Inspection Report 05000313/2023011 and 05000368/2023011 IR 05000313/20230052023-08-21021 August 2023 Updated Inspection Plan for Arkansas Nuclear One, Units 1 and 2 (Report 05000313/2023005 and 05000368/2023005) - Mid Cycle IR 05000313/20243012023-08-14014 August 2023 Notification of NRC Initial Operator Licensing Examination 05000313/2024301 IR 05000313/20230022023-08-11011 August 2023 Integrated Inspection Report 05000313/2023002 and 05000368/2023002 and Notice of Violation ML23209A6022023-08-0909 August 2023 Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk- Informed Completion Times IR 05000416/20230022023-08-0808 August 2023 Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001 ML23208A2132023-08-0303 August 2023 Regulatory Audit Summary Concerning Review of License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23188A1732023-07-12012 July 2023 Request for Withholding Information from Public Disclosure ML23142A2022023-06-29029 June 2023 Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements IR 05000313/20234032023-06-28028 June 2023 Security Baseline Inspection Report 05000313/2023403 and 05000368/2023403 ML23178A0892023-06-26026 June 2023 August 2023 Emergency Preparedness Program Inspection-Request for Information ML23166B0902023-06-21021 June 2023 Request for Relief ANO1 ISI 036 Regarding Volumetric Examination Requirements ML23180A1082023-06-20020 June 2023 ANO Unit 1 SAR Amendment 31, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report IR 05000313/20234012023-06-13013 June 2023 Cyber Security Inspection Report 05000313/2023401 and 05000368/2023401 ML23130A2972023-05-17017 May 2023 Notification of Inspection (NRC Inspection Report 05000313/2023003) and Request for Information ML23121A3012023-05-10010 May 2023 Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk - Informed Completion Times ML23114A3572023-05-10010 May 2023 Regulatory Audit Summary Concerning Review of Request for Alternative ANO-CISI-002 Regarding Containment Inservice Inspection Frequency ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000313/20230012023-05-0909 May 2023 Integrated Inspection Report 05000313/2023001 and 05000368/2023001 ML23118A3202023-05-0808 May 2023 Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000313;05000368/2023010) IR 05000368/20233012023-05-0101 May 2023 NRC Examination Report 05000368/2023301 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23108A1362023-04-24024 April 2023 Approval of Request for Half-Nozzle Repair of Reactor Vessel Closure Head Penetration No. 46 ML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G 2024-01-24
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23142A2022023-06-29029 June 2023 Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements 2CAN042301, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-04-0505 April 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure2023-03-30030 March 2023 License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure 1CAN122201, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42022-12-22022 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2022-10-31031 October 2022 Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 0CAN082201, License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-08-30030 August 2022 License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements ML21279A2312021-10-0606 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Using the Consolidated Line-Item Improvement 1CAN102101, SAR Amendment 30, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report2021-10-0606 October 2021 SAR Amendment 30, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report 1CAN092101, License Amendment Request Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2021-09-30030 September 2021 License Amendment Request Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations ML21266A1612021-09-23023 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated ML21182A1582021-07-0101 July 2021 Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections 2CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2021-05-26026 May 2021 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2021-05-26026 May 2021 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors 1CAN022102, Supplement Related to License Amendment Request to Replace the Reactor Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate2021-02-22022 February 2021 Supplement Related to License Amendment Request to Replace the Reactor Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate 0CAN022102, Unit 2; License Amendment Request - One-Time Change to Support Proactive Upgrade of the Emergency - Cooling Pond Supply Piping2021-02-0808 February 2021 Unit 2; License Amendment Request - One-Time Change to Support Proactive Upgrade of the Emergency - Cooling Pond Supply Piping 2CAN112004, License Amendment Request - Application to Adopt a Safety Function Determination Program (SFDP)2020-11-17017 November 2020 License Amendment Request - Application to Adopt a Safety Function Determination Program (SFDP) 2CAN092003, License Amendment Request, Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2020-09-24024 September 2020 License Amendment Request, Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions 1CAN072001, Supplemental Information Related to License Amendment Request to Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate2020-07-21021 July 2020 Supplemental Information Related to License Amendment Request to Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate 1CAN022001, License Amendment Request: Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate2020-02-24024 February 2020 License Amendment Request: Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate 1CAN012002, License Amendment Request: Revise Loss of Voltage Relay Allowable Values2020-01-24024 January 2020 License Amendment Request: Revise Loss of Voltage Relay Allowable Values 2CAN121903, License Amendment Request, Revise Control Element Assembly Drop Time2019-12-18018 December 2019 License Amendment Request, Revise Control Element Assembly Drop Time 2CAN121901, License Amendment Request Technical Specification Deletions, Additions, and Relocations2019-12-16016 December 2019 License Amendment Request Technical Specification Deletions, Additions, and Relocations 1CAN101903, Supplement to License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2019-10-23023 October 2019 Supplement to License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO 0CAN091901, Unit 2: License Amendment Request - Change in Implementation Date for Amendments 263 and 3142019-09-0505 September 2019 Unit 2: License Amendment Request - Change in Implementation Date for Amendments 263 and 314 2CAN081903, License Amendment Request Technical Specification (TS) Change Related to Revised Fuel Handling Accident Analysis and Adoption of TS Improvements Consistent with NUREG-14322019-08-29029 August 2019 License Amendment Request Technical Specification (TS) Change Related to Revised Fuel Handling Accident Analysis and Adoption of TS Improvements Consistent with NUREG-1432 1CAN051901, License Amendment Request Application to Revise Technical Specifications to Adopt TSTF 563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program.2019-05-29029 May 2019 License Amendment Request Application to Revise Technical Specifications to Adopt TSTF 563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program. 0CAN041904, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis2019-04-29029 April 2019 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis 1CAN031901, License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an Lco.2019-03-25025 March 2019 License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an Lco. CNRO-2019-00003, Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 42019-01-31031 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 4 1CAN121801, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues2018-12-19019 December 2018 Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues 2CAN121801, License Amendment Request, Add Actions to Address Inoperability of the Containment Building Sump2018-12-19019 December 2018 License Amendment Request, Add Actions to Address Inoperability of the Containment Building Sump 2CAN051801, License Renewal Pressurizer Surge Line and Safety Injection Nozzle Inspection2018-05-24024 May 2018 License Renewal Pressurizer Surge Line and Safety Injection Nozzle Inspection ML18094A1552018-03-29029 March 2018 Enclosures 2 - 6: Proposed EAL Technical Basis Document, NEI 99-01. Rev. 6., Proposed EAL Matrix Chart/Review Table and Supporting Referenced Document Pages 0CAN031801, Unit 2 - License Amendment Request - Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 62018-03-29029 March 2018 Unit 2 - License Amendment Request - Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 1CAN031801, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2018-03-12012 March 2018 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) 2CAN121702, License Amendment Request Post-Accident Instrumentation Technical Specification Revision2017-12-14014 December 2017 License Amendment Request Post-Accident Instrumentation Technical Specification Revision 2CAN111702, License Amendment Request - Updating the Reactor Coolant System Pressure-Temperature Limits2017-11-20020 November 2017 License Amendment Request - Updating the Reactor Coolant System Pressure-Temperature Limits 1CAN101701, License Amendment Request Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves2017-10-0202 October 2017 License Amendment Request Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves ML17268A2132017-09-21021 September 2017 ISFSI, River Bend Station Unit 1 & ISFSI, Waterford 3 Steam Electric Station & ISFSI, Grand Gulf Nuclear Station & ISFSI, Application for Order Approving Transfers of Licenses and Conforming License Amendments 2CAN081701, Application to Revise Technical Specifications to Adopt TSTF-427, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability.2017-08-14014 August 2017 Application to Revise Technical Specifications to Adopt TSTF-427, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability. 1CAN081701, Application to Revise Technical Specifications to Adopt TSTF-427, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability.2017-08-14014 August 2017 Application to Revise Technical Specifications to Adopt TSTF-427, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability. 2CAN071701, License Amendment Request, Application for Technical Specification Improvement to Provide Actions for Emergency Feedwater Pump Inoperability Consistent with NUREG-14322017-07-17017 July 2017 License Amendment Request, Application for Technical Specification Improvement to Provide Actions for Emergency Feedwater Pump Inoperability Consistent with NUREG-1432 1CAN071701, License Amendment Request, Application for Technical Specification Improvement to Revise Actions for Inoperable Using the Consolidated Line Item Improvement Process2017-07-17017 July 2017 License Amendment Request, Application for Technical Specification Improvement to Revise Actions for Inoperable Using the Consolidated Line Item Improvement Process 1CAN061701, Amendment 27 of the SAR, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report2017-06-0707 June 2017 Amendment 27 of the SAR, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report 1CAN041702, License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line.2017-04-24024 April 2017 License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line. 2CAN041702, License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.2017-04-24024 April 2017 License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection. 2CAN101601, License Amendment Request to Revise the National Fire Protection Association (NFPA) Standard 805 Modifications2016-10-27027 October 2016 License Amendment Request to Revise the National Fire Protection Association (NFPA) Standard 805 Modifications 1CAN051602, Update to Tables S-1 and S-2 - Adoption of National Fire Protection Association Standard NFPA-8052016-05-19019 May 2016 Update to Tables S-1 and S-2 - Adoption of National Fire Protection Association Standard NFPA-805 2CAN031602, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, and to Request an Alternative to the Asme..2016-03-25025 March 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, and to Request an Alternative to the Asme.. 2023-07-27
[Table view] Category:Technical Specifications
MONTHYEARML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting 0CAN042301, Radioactive Effluent Release Report for 20222023-04-14014 April 2023 Radioactive Effluent Release Report for 2022 ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML21279A2312021-10-0606 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Using the Consolidated Line-Item Improvement ML21208A4492021-09-20020 September 2021 Issuance of Amendment No. 325 Revise Loss of Voltage Relay Allowable Values and Number of Degraded Voltage Channels ML21088A4332021-04-14014 April 2021 Issuance of Amendment No. 324 Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition ML21027A4282021-03-23023 March 2021 Issuance of Amendment No. 272 Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent 1CAN022102, Supplement Related to License Amendment Request to Replace the Reactor Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate2021-02-22022 February 2021 Supplement Related to License Amendment Request to Replace the Reactor Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate ML20160A1472020-06-30030 June 2020 Issuance of Amendment No. 270 to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML20135H1412020-06-30030 June 2020 Issuance of Amendment Nos. 269 and 321 Request to Incorporate the Tornado Missile Risk Evaluator Into the Licensing Basis ML19232A3792019-09-19019 September 2019 Correction to Issuance of Amendment No. 264 Adoption of Technical Specifications Task Force Traveler TSTF-425, Revision 3 ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML17251A2112017-10-10010 October 2017 Issuance of Amendment No. 307 Revision of Steam Generator Technical Specifications to Reflect Adoption of Technical Specifications Task Force Traveler TSTF-510 (CAC MF9654; EPID L-2017-LLA-0222) ML16165A4232017-03-10010 March 2017 Issuance of Amendment No. 257 Adoption of Technical Specifications Task Force Traveler TSTF-545, Revision 3, ML16027A1092016-02-24024 February 2016 Issuance of Amendment Nos. 255 and 303 Cyber Security Plan Implementation Schedule (CAC Nos. MF6258 and MF6259) ML15096A3812015-04-29029 April 2015 Issuance of Amendment No. 302, Revise Technical Specification Surveillance Requirement 4.1.3.1.2 Note to Eliminate Movement of Control Element Assembly 18 for Remainder of Operating Cycle 24 ML15068A3192015-03-31031 March 2015 Issuance of Amendment No. 301, Request to Adopt Technical Specification Task Force (TSTF)-422, Revision 2, Change in Technical Specifications End States (CE NPSD-1186) ML15023A1472015-03-0303 March 2015 Issuance of Amendment No. 253, Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-431, Revision 3, Change in Technical Specifications End States (BAW-2441) ML14356A2272015-02-18018 February 2015 Issuance of Amendment No. 300, Request to Adopt National Fire Protection Association Standard NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants ML15014A0712015-02-0303 February 2015 Issuance of Amendment No. 252, Request to Revise Technical Specification 5.5.16, Reactor Building Leakage Rate Testing Program, to Extend Type a Test Frequency to 15 Years ML14350B2852015-01-22022 January 2015 Issuance of Amendment No. 299, Revise Technical Specification 6.5.16, Containment Leakage Rate Testing Program, for Requirements for Containment Building Emergency Escape Air Lock Doors ML14254A1332014-11-24024 November 2014 Issuance of Amendment No. 250, Adoption of Technical Specifications Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 1CAN111401, Arkansas Nuclear One, Unit 1, License Amendment Request Update the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits2014-11-21021 November 2014 Arkansas Nuclear One, Unit 1, License Amendment Request Update the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits 1CAN111401, License Amendment Request Update the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits2014-11-21021 November 2014 License Amendment Request Update the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits 1CAN101407, Clarifications to Response to Request for Additional Information Associated with Technical Specification Change to Extend the Type a Test Frequency to 15 Years2014-10-28028 October 2014 Clarifications to Response to Request for Additional Information Associated with Technical Specification Change to Extend the Type a Test Frequency to 15 Years 1CAN031401, License Amendment Request - Revised Pages Extend the Type a Test Frequency to 15 Years2014-03-11011 March 2014 License Amendment Request - Revised Pages Extend the Type a Test Frequency to 15 Years 1CAN121302, License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years2013-12-20020 December 2013 License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years 1CAN081302, Response to Request for Additional Information, Adoption of Technical Specification Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360.2013-08-28028 August 2013 Response to Request for Additional Information, Adoption of Technical Specification Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360. 2CAN061302, License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-4712013-06-18018 June 2013 License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471 1CAN061301, License Amendment Request, Revision to Technical Specification 2.1.1.1 Reactor Core Safety Limits2013-06-11011 June 2013 License Amendment Request, Revision to Technical Specification 2.1.1.1 Reactor Core Safety Limits 1CAN011304, License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-500, Revision 2 DC Electrical Rewrite - Update to TSTF-360.2013-01-28028 January 2013 License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-500, Revision 2 DC Electrical Rewrite - Update to TSTF-360. 2CAN011301, License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-500, Revision 2 DC Electrical Rewrite - Update to TSTF-3602013-01-28028 January 2013 License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-500, Revision 2 DC Electrical Rewrite - Update to TSTF-360 CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications 1CAN061201, License Amendment Request Technical Specification Change Associated with Main Feedwater Valves2012-06-19019 June 2012 License Amendment Request Technical Specification Change Associated with Main Feedwater Valves 1CAN081001, License Amendment Request, Technical Specification Change Associated with Main Feedwater Isolation Valves2010-08-24024 August 2010 License Amendment Request, Technical Specification Change Associated with Main Feedwater Isolation Valves 2CAN051001, Response to Request for Additional Information Associated with Core Operating Limits Report References2010-05-17017 May 2010 Response to Request for Additional Information Associated with Core Operating Limits Report References 1CAN021004, Response to Request for Additional Information, Application for Technical Specification Improvement to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec.2010-02-28028 February 2010 Response to Request for Additional Information, Application for Technical Specification Improvement to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec. ML0930601322009-12-23023 December 2009 License Amendment No. 240, Revised Administrative Changes to Technical Specification 5.5.8, Inservice Testing Program, to Adopt TSTF-479-A and TSTF-497-A ML0931305282009-12-23023 December 2009 License Amendment No. 241, Modified Technical Specification 3.4.9, Pressurizer, to Delete Low Pressurizer Level Limit 1CAN080901, Changes to Reflect Revision to 10 CFR 50.55a Technical Change Travelers - TSTF-479-A and TSTF-497-A2009-08-0505 August 2009 Changes to Reflect Revision to 10 CFR 50.55a Technical Change Travelers - TSTF-479-A and TSTF-497-A 2CAN030901, License Amendment Request, Technical Specification Change to Modify the Mode of Applicability for Emergency Feedwater Actuation Signal2009-03-0202 March 2009 License Amendment Request, Technical Specification Change to Modify the Mode of Applicability for Emergency Feedwater Actuation Signal 1CAN020901, License Amendment Request, Technical Specification Change to Adopt Low Pressure Air Lock Seal Test2009-02-16016 February 2009 License Amendment Request, Technical Specification Change to Adopt Low Pressure Air Lock Seal Test ML0814000372008-09-0808 September 2008 Technical Specifications for Amendment No. 282 Technical Specification Task Force TSTF-490, Rev 0, Deletion of E Bar Definition and Revision to RCS Specific Activity. ML0812203132008-08-28028 August 2008 Tech Spec Pages for Amendment No. 281 Technical Specification Task Force Change TSTF-359, Increased Flexibility in Mode Restraints. ML0823801472008-08-21021 August 2008 License Amendment Request, Technical Specification Change to Extend Integrated Leak Rate Test Interval One-Time ML0814004492008-07-23023 July 2008 Tech Spec Pages for Amendment No. 280 Reactor Coolant System Relocation to TRM (Tac MD8313) 2CAN070805, License Amendment Request Regarding Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers and Relocate TS 3.7.8 to the TRM2008-07-21021 July 2008 License Amendment Request Regarding Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers and Relocate TS 3.7.8 to the TRM 1CAN070804, License Amendment Request Regarding Technical Specification Changes Associated with Adoption of TSTF-3592008-07-21021 July 2008 License Amendment Request Regarding Technical Specification Changes Associated with Adoption of TSTF-359 1CAN070803, License Amendment Request Regarding Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers2008-07-21021 July 2008 License Amendment Request Regarding Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers ML0815402462008-07-0909 July 2008 License Page 3 & Technical Specifications for Issuance of Amendment No. 233 Containment Spray Nozzle Technical Specification Test Requirements 2023-04-14
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d*--- SEntergy Entergy Operations, Inc.1448SR 333 Russellville, AR 72802 Tel 479-8584E;88 Timothy G. Mitchell Acting Vice President Operations ANO 2CANC30602 March 20, 2006 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
License Amendment Request Proposed Technical Specification to Remove Reactor Coolant System Structural Integrity Requirements Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6
Dear Sir or Madam:
Attached for your review and approval is a proposed Technical Specification (TS) change to remove the reactor coolant system structural integrity requirements contained in TS 3.4.10.1 and its associated Bases from the Arkansas Nuclear One, Unit 2 (ANO-2) TSs. Removal of TS 3.4.10.1 is consistent with NUREG-1432 in that it does not meet the criteria of 10 CFR 50.36 for inclusion in the TSs.The proposed change has been evaluated in accordance with 10 CFR 50.91(a)(1) using criteria in 10 CFR 50.92(c) and it has been determined that this change involves no significant hazards considerations.
The bases for these determinations are included in Attachment
- 1. Proposed TS page markups are contained in Attachment 2.There are no new commitments being made as a result of this request.The proposed change is neither exigent nor emergency.
Once approved, the amendment siall be imp emented within 60 days.If you have any questions or require additional information, please contact David Bice at 479-858-4626.
A oei4 4 2CAN030602 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on March 20, 2006.Sincerely, Attachments:
- 1. Analysis of Proposed Technical Specification Change 2. Proposed Technical Specification Changes (mark-up)cc: Dr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P. 0. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Drew Holland MS O-7D1 Washington, DC 20555-0001 Mr. Bernard R. Bevill Director Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street Little Rock, AR 72205 Attachment I 2CAN030602 Analysis of Proposed Technical Specification Change Attachment I to 2CAN030602 Page 1 of 5
1.0 DESCRIPTION
OF PROPOSED CHANGES The proposed change removes the requirements of the Arkansas Nuclear One, Unit 2 (ANO..2)reactor coolant system structural integrity requirements contained in Technical Specifications (TS) 3.4.10.1 and the associated TS Bases from the TSs. The proposed change is consistent with INUREG 1432, Standard Technical Specifications Combustion Engineering Plants, Revision 3.1 (Reference 1).
2.0 PROPOSED CHANGE
The proposed changes to the Arkansas Nuclear One, Unit 2 TSs are as follows:* TS 3.4.10.1, Reactor Coolant System Structural Integrity, is being removed from the ANO-2 TSs.* An administrative change is being made to TS pages 3/4 4-22a, 23, 23a, and 23b to renumber them as TS Pages 3/4 4-23, 24, 25, and 26, respectively.
This change provides for cleaner sequential TS page numbering as a result of the deletion of TS 3.4.10.1.
This portion of the change is administrative in nature and is not discussed further in this transmittal.
The Bases for TS 3.4.10.1 will be deleted. However, this will be performed under the ANO-2 TS Bases Control Program and is not included in this submittal.
3.0 BACKGROUND
The purpose of TS 3.4.10.1, Reactor Coolant System Structural Integrity, is to specify the requirements of maintaining the structural integrity of the ASME Class 1, 2 and 3 components.
This specification was originally intended to support assurance that structural integrity and operational readiness of these components are maintained at an acceptable level throughout the life of the facility.
The specification is applicable in all operational modes. However, the specification does not provide actions for plant shutdown if its Limiting Condition for Operation (LCO) is not met. In addition, the specification contains no surveillance requirements.
This is because the specification addresses the passive pressure boundary function of ASME Code Class. 1, 2 and 3 components as established by compliance with the Inservice Inspection (ISI)program. The ISI program is required pursuant to 10 CFR 50.55a (Reference 2).Furthermore, the specification wording could be misconstrued to conflict with normal outage-related activities, including removal of Reactor Coolant System (RCS) manways and the Reactor Vessel head in preparation for refueling, a time in which the RCS pressure boundary would no longer be intact. This TS does not fulfill any of the criteria of 10 CFR 50.36(c)(2)1ii) for retention in the TSs.Maintaining a program-type requirement within an LCO creates significant interpretation issues for O.:erations personnel.
The RCS structural integrity TS was part of the original TSs and, therefore, no basis history is available regarding its intent. However, the TS 3.4.10.1 appears to have been included to help ensure that plant heatup and startup would not occur until all required portions of the RCS were verified to meet ISI acceptance criteria following inspections performed during a plant outage (normally performed during refueling outages).
Meeting this acceptance criteria helps ensure the integrity of the RCS pressure boundary during all modes of operation, including accident events. However, the RCS pressure boundary is purposely Attachment 1 to 2CAN030602 Page 2 of 5 breached during Mode 5 and 6 operations to support plant outage activities and such openings are not historically considered a violation of TS 3.4.10.1.
Furthermore, TS 3.4.10.1 contains no actions suggesting it was designed to accommodate integrity concerns once plant heatup has commenced.
RCS structural integrity ISI activities are performed only during plant outages when conditions exist that permit access to the RCS pressure boundary and are not monitored or controlled through application of the ISI program during the operational cycle.Other TSs are designed to monitor the structural integrity of the RCS during operation and provide actions to shutdown the unit if compliance is not maintained.
For example, RCS heatup and cooldown rates protect against applying undue stresses as a result of pressure/temperature transients on RCS components and piping. RCS leakage TSs provide a means of protecting the RCS integrity by detecting and monitoring leakage. Therefore, it is not necessary to apply TS 3.4.10.1 when integrity issues become evident during plant operation above cold shutdown.
Because TS 3.4.10.1 is redundant to other regulation, it is acceptable to remove the TS 3.4.10.1 requirements from the TSs.Removal of this specification does not reduce the controls that are necessary to ensure compliance with the ASME Code or the need to maintain the RCS pressure boundaries.
Structural Integrity is maintained by compliance with 10 CFR 50.55a (Reference
- 2) as implemented through the ANO-2 ISI program.4.0 TECHNICAL ANALYSIS The purpose of TS 3.4.10.1, Reactor Coolant System Structural Integrity, is to specify the requirements of maintaining the structural integrity of the ASME Class 1, 2 and 3 components.
However, this is redundant to and does not contain the detail of the requirements contained within 10 CFR 50.55a, Codes and Standards.
10 CFR 50.36(c)(2)(ii) (Reference
- 3) states that a TS LCO of a nuclear reactor must be established for each item meeting one or more of the following criteria: Criterion 1 Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.This specification is not applicable to installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the RCS. This specification does not meet Criterion 1.Criterion 2 A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.This specification is not applicable to a process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. Although the specification is related to the integrity of the RCS pressure boundary, compliance is maintained by meeting the requirements of 10 CFR 50.55a through implementation of the ANO-2 ISI program and is not specifically monitored or controlled during plant operation.
This specification does not meet Criterion
- 2.
Attachment I to 2CAN030602 Page 3 of 5 Criterion 3 A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fisskbn product barrier.No specific TS-related structure, system, or component (SSC) is being revised or removed from the TSs. Each TS SSC must continue to meet the requirements of 10 CFR 50.55a as implemented through the ANO-2 ISI program. This RCS Structural Integrity specification does not meet Criterion 3.Criterion 4 A structure, system, or component which operating experience orprobabilistic risk assessment has shown to be significant to public health and safety.As stated above, no specific TS-related structure, system, or component (SSC)is being revised or removed from the TSs. Each TS SSC must continue to meet the requirements of 10 CFR 50.55a as implemented through the ANO-2 ISI program. This RCS Structural Integrity specification does not meet Criterion 4.The scope of this specification has been evaluated against the criteria of 10 CFR 50.36(c)(2)(ii) and none of these criteria require that the RCS Structural Integrity controls are appropriate for retention in the ANO-2 TSs. This conclusion is consistent with NUREG 1432, Standard Technical Specifications Combustion Engineering Plants, Revision 3.1 In addition to the above, ISI-related requirements were removed from the ANO-2 TSs to be consistent with NUREG 1432 in Amendment 233, dated September 24, 2001 (Reference 4).The removal of these requirements was based on their redundancy to 10 CFR 50.55a. During this process, TS 3.4.10.1 should also have been removed from the TSs since it too is redundant to 10 CFR 50.55a requirements.
As previously mentioned, NUREG 1432 does not contain this specification.
Based on the above discussion, removal of RCS structural integrity requirements contained in TS 3.4.10.1 from the TSs is acceptable.
6.0 REGULATORY
ANALYSIS 5.1 Applicable Reaulatorv Requirements The proposed change has been evaluated to determine whether applicable regulations and requirements continue to be met. Entergy has determined that the proposed change does not require any exemptions or relief from regulatory requirements, other than the TSs, and does not affect conformance with any General Design Criterion (GDC) differently than described in the ANO-2 Safety Analysis Report (SAR).Although the RCS structural integrity controls of ANO-2 TS 3.4.10.1 are being removed from the T-Ss, ANO-2 is still required to comply with the ASME Code requirements in accordance with I 0 CFR 50.55a. Therefore, there is no impact on any regulatory requirement as a result of the proposed change.
Attachment I to 2CAN030602 Page 4 of 5 5.2 Determination of No Significant Hazards Consideration Entergy Operations, Inc. (Entergy) is proposing that the Arkansas Nuclear One Unit 2 (ANO-2)Operating License be amended to revise the Technical Specification (TS) requirements for Reactor Coolant System (RCS) structural integrity.
The proposed changes will remove the RCS Structural Integrity TS 3.4.10.1 from the TSs. This specification is redundant to the ASMEE Code compliance as required by 10 CFR 50.55a. The proposed change is consistent with NUREG 1432, Standard Technical Specifications Combustion Engineering Plants, Revision 3.1.Entergy Operations, Inc. has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CF:R 50.92, "issuance of amendment," as discussed below: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response:
No.The proposed change to remove the RCS structural integrity controls from the TSs does not impact any mitigation equipment or the ability of the RCS pressure boundary to fulfill any required safety function.
Since no accident mitigation or initiators are impacted by this change, no design basis accidents are affected.Therefore, the proposed change does not involve a significant increase in the probability or consequences of any accident previously evaluated.
2:. Does the proposed change create the possibility of a new or different kind of accident from any previously evaluated?
Response:
No.The proposed change will not alter the plant configuration or change the manner in which the plant is operated.
No new failure modes are being introduced by the proposed change.Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed change involve a significant reduction in the margin of safety?Response:
No.Removal of TS 3.4.10.1 from the TSs does not reduce the controls that are required to maintain the RCS pressure boundary for ASME Code Class 1, 2, or 3 components.
No equipment or RCS safety margins are impacted due to the proposed change.Therefore, the proposed change does not involve a significant reduction in the margin of safety.
Attachment 1 to 2CAN030602 Page 5 of 5 Based on the above, Entergy concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of 'no significant hazards consideration" is justified.
5.3 Environmental
Considerations The proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
6.0 PRECEDENCE
The proposed change to remove of TS 3.4.10.1 from the TSs is consistent with NUREG 1432, Standard Technical Specifications Combustion Engineering Plants, Revision 3.1 and is similar to that issued for the Millstone Nuclear Power Station, Unit No. 2 in Amendment 264 dated February 1, 2002 and the Waterford Steam Electric Station, Unit 3 in Amendment 189 dated September 22, 2003.
7.0 REFERENCES
- 1. NUREG 1432, Standard Technical Specifications Combustion Engineering Plants, Revision 3.1 2. 10 CFR 50.55a, Codes and Standards 3. 10 CFR 50.36, Technical Specifications
- 4. ANO-2 Technical Specification Amendment 233, Issuance of Amendment RE: Technical Specification
4.0.5 Transfer
and Modification (TAC No. MB 2551), dated September 24, 2001 Attachment 2 2CAN030602 Proposed Technical Specification Changes (mark-up)
SURVEILLANCE REQUIREMENTS 4.4.9.1.1 The Reactor Coolant System temperature and pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations.
4.4.9.1.2 The reactor vessel material irradiation surveillance specimens shall be removec' and examined, to determine changes in material properties, at the intervals shown in SAR Table 5.2-12. The results of these examinations shall be used to update Figures 3.4-2A, 3.4-28 and 3.4-2C.ARKANSAS -UNIT 2 3/4 42a23 Amendment No. 424,243, l I Figure 3.4-2A HEATUP CURVE -32 EFPY REACTOR COOLANT SYSTEM PRESSURE/TEMPERATURE LIMITS 2500 2000 co._4 n a3 1500 (n L.0 1)a-1D N.y 0 1000 0 L..0M HI 1@Non-Critical Cr t i80 F/hr Critical Cor--Acceptable Crtcltesty Semt e 19 F 4 Ternperature, H ~ I IIS 4 Ttl \ llin~m~oltiip l Criticalib Limit=190OFl
-T_ XTemnperature, 50 F l lll 1 T 500 0 0 100 200 300 400 500 Reactor Coolant Temperature Tc, OF (Curves do not include margins for instrument uncertainties)
ARMkNSAS -UNIT 2 3/4 4-2324 Amendment No. 424,242, l Z1-Figure 3.4-2B COOLDOWN CURVE- 32 EFPY REACTOR COOLANT SYSTEM PRESSURE/TEMPERATURE LIMITS 2500 2000 0 1-a-N 1r 0 41~IL 1500 1000 ACceptable
... Region--Cooldown_Locwes t ,er_ ic e1_ ___t t Minimum Boltup Temperature, 50 F 500 0 0 100 200 300 400 500 Reactor Coolant Temperature Tc, °F (Curves do not include margins for instrument uncertainties)
ARKJtNSAS
-UNIT 2 3/4 4-23a25 Amendment No. 424,242,2,6, l I Figure 3.4-2C INSERVICE HYDROSTATIC TEST CURVE -32 EFPY REACTOR COOLANT SYSTEM PRESSURE/TEMPERATURE LIMITS 2500 2000 0.a 0 0 N 1.r 0~1500 1000 Ia 1H I:_Loet Sevc I- I IXJ III 500 0 0 100 200 300 400 500 Reactor Coolant Temperature Tc, OF (Curves do not include margins for instrument uncertainties)
ARKANSAS -UNIT 2 3/4 4-23b26 K1--+ ---- ;- "VA A 05a Amendment No. 424,2441,263, Z REACTOR COOLANT SYSTEM'31A A IJA C~rTDIlrr IIDAI tIKIt(fDITV ASME CODE CL:ASS 1. 2 rAND 3 COMPONENT-S IUMI1 ING CONDITION FOR OPERATION 341).1 The 6tructural integrity of ASME Code Class 1, 2 and 3 components shall be maintained.
APP-L.ICABILITY:
ALL MODES a. With the structural integrity of any ASME Code Class 1 component(s) not conforming to the above reirnt, restore the 6tructural integr;ty Of the Affected component(s) to within its limit or isolate the affected component(s) prior to incr.easing the Reactor Coolant SysterAm te+mperatulr monre thaen 50F above the minimum temperature required by NDT considerations.
- b. A/th thestructural integrit of any AASME Code lass 2 coimponent(s) not ronf ig to the above requirements, restore the structural integrity of the affected cormponent(s) to within its limit Or isolate the affected cGmponent(s) prir to increasing the ReactoF Coolant System temperature above 200°F.c. With the structural integrity of any ASME Code Class 3 component(s) not confori to the above requirements, restore the structural integrity of the affected component to within its! limit or is-eato the affeGted comoonent from 6ervice.SURVEILLANCE REQUIREMENTS A b1/P .1 A I.. I I&II ll^ I AA ^: A &I- ------ -11 A M*d4~A~ W~ ui I6 af3If 9 7d )~ONHOREmofiNt
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