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Category:Code Relief or Alternative
MONTHYEARML23142A1062023-05-24024 May 2023 Authorization and Safety Evaluation for Alternative Request No. ANO1-ISI-035 ML22073A0952022-04-0707 April 2022 Approval of Request for Alternative from Certain Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (EPID L-2021-LLR-0084) (NON-PROPRIETARY) ML21293A0962021-10-28028 October 2021 Relief ANO2-R&R-012 Concerning Proposed Alternative for Repair of Reactor Vessel Closure Head Penetration 46 ML21299A0032021-10-28028 October 2021 and Waterford Steam Electric Station, Unit 3 - Approval of Request for Alternative EN-20-RR-003 from Certain Requirements of the ASME Code ML21168A0562021-07-0909 July 2021 Approval of Request for Alternative from Certain Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML21118B0392021-05-19019 May 2021 Approval of Request for Alternative from Certain Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML21054A3302021-02-24024 February 2021 Approval of Alternative IP3-ISI-RR-16 to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement CNRO-2020-00016, Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2020-08-12012 August 2020 Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) ML20121A1932020-05-0606 May 2020 Alternative Requests for the Fifth 10 Year Interval Inservice Testing of Low Pressure Safety Injection Pumps and Service Water Valves ML20119A0732020-04-29029 April 2020 Withdrawal of Requested Alternatives for the Fifth 10-Year Interval Inservice Testing of Service Water Pumps and Visual Examination of Snubbers ML20083J9682020-03-26026 March 2020 Approval of Request for Alternative ANO 2-PT-002 End-of-Internal System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping ML19254A6032019-09-19019 September 2019 Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1 2CAN071902, Request for Alternative ANO 2-PT-002 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping2019-07-25025 July 2019 Request for Alternative ANO 2-PT-002 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping ML19184A5542019-07-15015 July 2019 Request for Relief ANO1-ISI-032 from the ASME Code Section XI Visual Examination Requirements for the Fourth 10-Year Inservice Inspection Interval ML19156A4002019-06-11011 June 2019 Request for Alternative ANO2-ISI-021 to Permit Continued Application of the 2007 Edition Through the 2008 Addenda of ASME Code ML19039A1492019-02-25025 February 2019 Issuance of Relief Request IP3-ISI-RR-14 Alternative Examination Required by ASME Code Case N-724-4 CNRO-2019-00002, Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-01-31031 January 2019 Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 ML18251A0042018-09-18018 September 2018 Safety Evaluation for Relief Request IP3-ISI-RR-11, RR-12, RR-15 Approval of Alternative Associated with Extension of Fourth Interval Reactor Vessel and Piping Weld Inspections (EPID: L-2017-LLR-0124,0127) ML18193B0302018-07-18018 July 2018 Safety Evaluation for Relief Request IP3-ISI-RR-13 Fourth Ten-year Inservice Inspection Interval Extension ML18128A0672018-06-0808 June 2018 Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4 1CAN041801, Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements Fourth 10-Year Interval, Second and Third Period2018-04-23023 April 2018 Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements Fourth 10-Year Interval, Second and Third Period ML18099A3732018-04-0909 April 2018 04/09/2018 E-mail from R. Guzman to R. Walpole, Verbal Authorization for Relief Request IP2-ISI-RR-06 ML18059A1562018-03-0606 March 2018 Safety Evaluation for Relief Request IP2-ISI-RR-05 Alternative Examination Volume Required by ASME Code Case N-729-4 ML18005A0662018-01-23023 January 2018 Safety Evaluation of Relief Requests ISI-RR-20, ISI-RR-21, and ISI-RR-22 Regarding the Fourth 10-Year Interval of the Inservice Inspection Program CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 12017-11-17017 November 2017 Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1 ML17174B1442017-07-12012 July 2017 Relief Request for EN-ISI-16-1 Regarding Use of Later Edition and Addenda of the ASME Code ML17069A2832017-03-16016 March 2017 Relief Request No. IP3-ISI-RR-09, for Alternative to the Depth Sizing Qualification Requirement ML16358A4442017-01-11011 January 2017 Relief from the Requirements of the ASME Code Regarding Alternate IP3-RR-10 to the Full Circumferential Inspection Requirement of Code Case N-513-3 ML16130A4712016-12-0909 December 2016 Request for Alternative Test Plan to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (CAC Nos. MF7537 and MF7538) ML16237A0822016-08-29029 August 2016 Relief Request No. ANO1-ISI-025, Relief from American Society of Mechanical Engineers Section XI Table IWB-2500-1 Requirements ML16167A0812016-07-15015 July 2016 Request for Alternative IP2-ISI-RR-03 to Weld Reference System Examination Required by ASME Code Subarticle IWA-2600 ML16096A2692016-06-0606 June 2016 Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1 ML16053A0252016-03-0303 March 2016 IP2-ISI-44-18, Relief from the Requirements of the ASME Code CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, D2015-06-0505 June 2015 Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, Division ML15070A4282015-03-16016 March 2015 Relief Request ANO2-ISI-017, Alternative to Utilize ASME Code Case N-513-4 for the Fourth 10-Year Inservice Inspection Interval ML15030A2392015-02-0909 February 2015 Correction to Relief Request ANO1-ISI-024 Issued December 23, 2014; Revises 10 CFR 50.55a Citations as a Result of Changes from Final Rule Effective December 5, 2014 ML14330A2072014-12-23023 December 2014 Relief Request ANO1-ISI-024, Alternative from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-1, Fourth 10-year Inservice Inspection Interval ML14282A4792014-10-29029 October 2014 Relief Request ANO1-ISI-023, Volumetric Examination Frequency Requirements, for the Fourth 10-Year Inservice Inspection Interval ML14198A3312014-07-23023 July 2014 Safety Evaluation for Relief Request IP3-ISI-RR-06 for Reactor Vessel Weld Examinations (Tac No. MF3345) ML14150A1632014-06-0606 June 2014 Relief Request ANO2-ISI-004 - Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations ML14099A4522014-04-15015 April 2014 Relief Request ANO2-ISI-016, from ASME Code Case N-770-1 Successive Examination, for the Fourth 10-Year Inservice Inspection Interval ML13179A1162013-07-24024 July 2013 Request for Relief ANO1-ISI-022 from ASME Code Examination Requirements for Pressure-Retaining Welds in Piping; Fourth 10-Year Inservice Inspection Interval ML13179A1102013-07-16016 July 2013 Request for Relief No. ANO1-ISI-021, from ASME Volumetric Requirements for Full Penetration Welded Nozzles in Vessels - Inspection Program B; Fourth 10-Year ISI Interval ML13161A2412013-06-27027 June 2013 Relief Request ANO2-ISI-015, from Pressure Testing Requirements for Reactor Vessel Flange Seal Leak Detection Piping for the Fourth 10-Year Inservice Inspection Interval ML13071A6342013-03-22022 March 2013 Relief Request ANO2-ISI-014, from Volumetric and Surface Exam Requirements for Pressure Retaining Welds in Austenitic Stainless Steel, Third 10-Year Inservice Inspection Interval ML13071A6632013-03-21021 March 2013 Relief Request ANO2-ISI-010, from Volumetric and Surface Exam Requirements for Pressure Retaining Welds in Piping, Third 10-Year Inservice Inspection Interval ML13032A5732013-02-21021 February 2013 Relief Request Nos. ANO2-ISI-009, ANO2-ISI-011, and ANO2-ISI-012, ASME Code Volumetric and Surface Exam Requirements for Integral Attachment and Pressure-Retaining Welds, Third 10-Year Inservice Inspection Interval NL-13-041, Relief Request IP2-ISI-RR-17: Code Case N-770-1 Weld Inspection Frequency Extension2013-02-20020 February 2013 Relief Request IP2-ISI-RR-17: Code Case N-770-1 Weld Inspection Frequency Extension ML12334A3172012-12-0303 December 2012 Relief Request IP2-ISI-RR-15 - Proposed Alternative to the Use of a Weld Reference System ML12319A3672012-11-27027 November 2012 Relief Request ANO2-ISI-007, Alternative to Use ASME Code Case N-770-1 Baseline Examination, Fourth 10-Year Inservice Inspection Interval 2023-05-24
[Table view] 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 ML24011A1982024-01-12012 January 2024 ISFSI, Notice of Organization Change for Site Vice President IR 05000313/20234202024-01-10010 January 2024 Security Baseline Inspection Report 05000313/2023420 and 05000368/2023420 ML23342A1082024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan IR 05000313/20234022024-01-0202 January 2024 Security Baseline Inspection Report 05000313/2023402 and 05000368/2023402 ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23354A0022023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23353A1742023-12-19019 December 2023 ISFSI, Emergency Plan, Revision 23-04 L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection 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 ML23339A0442023-12-0505 December 2023 Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan ML23338A2262023-12-0404 December 2023 Signed Amendment No. 27 to Indemnity Agreement No. B-19 ML23356A0212023-12-0101 December 2023 American Nuclear Insurers, Secondary Financial Protection (SFP) Program ML23242A2772023-11-30030 November 2023 NRC Letter Issuance - IP LAR for Units 2 and 3 Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs ML23338A0482023-11-30030 November 2023 ISFSI, Report of Changes to Physical Security, Training and Qualification, Safeguards Contingency Plan, and ISFSI Security Program, Revision 28 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 ML22339A1572023-11-27027 November 2023 Letter - Indian Point - Ea/Fonsi Request for Exemptions from Certain Emergency Planning Requirements for 10 CFR 50.47 and 10 CFR Part 50, Appendix E IR 05000003/20230032023-11-21021 November 2023 NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003 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 ML23100A1172023-11-17017 November 2023 NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition ML23050A0032023-11-17017 November 2023 Letter - Issuance Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements Following Spent Fuel Transfer to Dry Storage ML23100A1252023-11-17017 November 2023 Letter and Enclosure 1 - Issuance Indian Point Energy Center Units 1, 2, and 3 Exemption for Offsite Primary and Secondary Liability Insurance Indemnity Agreement ML23100A1432023-11-16016 November 2023 Letter - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Exemption Concerning Onsite Property Damage Insurance (Docket Nos. 50-003, 50-247, 50-286) ML23064A0002023-11-13013 November 2023 NRC Issuance for Approval-Indian Point EC Units 1, 2 and 3 Emergency Plan and Emergency Action Level Scheme Amendments L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23313A0962023-11-13013 November 2023 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 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 ML23306A0992023-11-0202 November 2023 and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) ML23063A1432023-11-0101 November 2023 Letter - Issuance Holtec Request for Indian Point Energy Center Generating Units 1, 2, and 3 Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50 ML23292A0262023-10-19019 October 2023 LTR-23-0211-RI Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report-RI ML23289A1582023-10-16016 October 2023 Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit 2024-01-09
[Table view] Category:Safety Evaluation
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 ML23339A0442023-12-0505 December 2023 Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan ML23243A8452023-11-30030 November 2023 Enclosure 3: Issuance - IP LAR for SE Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs ML23275A2072023-11-28028 November 2023 Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23050A0022023-11-17017 November 2023 Enclosure 2 - Safety Evaluation for Indian Point Unit 2 License Amendment Request to Modify Technical Specifications for Staffing Requirements Following Spent Fuel Transfer to Dry Storage ML23100A1172023-11-17017 November 2023 NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition ML23064A0002023-11-13013 November 2023 NRC Issuance for Approval-Indian Point EC Units 1, 2 and 3 Emergency Plan and Emergency Action Level Scheme Amendments ML23067A0822023-11-0101 November 2023 Enclosure 2 - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Safety Exemption Evaluation for Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50 ML23142A2022023-06-29029 June 2023 Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements ML23166B0902023-06-21021 June 2023 Request for Relief ANO1 ISI 036 Regarding Volumetric Examination Requirements ML23142A1062023-05-24024 May 2023 Authorization and Safety Evaluation for Alternative Request No. ANO1-ISI-035 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML22342B1602023-01-10010 January 2023 Requests for Relief ANO2-ISI-023, -024, -025, -026, -027, and -028 to Permit Reduction of Inspection Area Due to Interference (EPIDs L-2022-LLR-0022,-0023, -0024, -0025, -0026, and -0027) ML22263A1912022-12-0909 December 2022 Issuance of Amendment No. 278 Revision to Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations (EPID L-2021-LLA-0181) - Non-Proprietary ML22236A5452022-08-26026 August 2022 Correction to Issuance of Amendment No. 331 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22138A4312022-06-23023 June 2022 Issuance of Amendment No. 277 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22083A1242022-04-28028 April 2022 Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2 ML22039A2822022-03-15015 March 2022 Issuance of Amendment Nos. 274 and 328 One-Time Change to Support Proactive Upgrade of the Emergency Cooling Pond Supply Piping ML21091A3052022-02-28028 February 2022 Issuance of Amendment No. 272 Revision to Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device (EPID L-2020-LLA-0051) (Non-Proprietary) ML22007A3172022-01-18018 January 2022 1, River Bend Station 1, and Waterford Steam Electric Station 3 - Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ML21225A0552021-12-17017 December 2021 Issuance of Amendment No. 327 Addition of Technical Specification Limiting Condition for Operation 3.0.6 and Adoption of Safety Function Determination Program ML21341B2262021-12-13013 December 2021 Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations ML21313A0082021-12-0808 December 2021 Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21208A4492021-09-20020 September 2021 Issuance of Amendment No. 325 Revise Loss of Voltage Relay Allowable Values and Number of Degraded Voltage Channels ML21132A2792021-05-19019 May 2021 Request for Approval of Change to the Entergy Quality Assurance Program Manual ML21074A0002021-04-22022 April 2021 Issuance of Amendment No. 270 Permanently Defueled Technical Specifications ML21083A0002021-04-14014 April 2021 Issuance of Amendment No. 63 Permanently Defueled Technical Specifications 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 ML21040A5132021-03-10010 March 2021 Issuance of Amendment No. 271 Revision to Loss of Voltage Relay Allowable Values ML21054A3302021-02-24024 February 2021 Approval of Alternative IP3-ISI-RR-16 to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement ML20351A1532021-02-0808 February 2021 Issuance of Amendment No. 323 Technical Specification Deletions, Additions, and Relocations ML20297A3332020-11-23023 November 2020 Enclosure 3, Safety Evaluation for Transfer of Renewed Facility Operating Licenses to Holtec International, Owner, and Holtec Decommissioning International, LLC, Operator ML20288A8242020-11-16016 November 2020 Regulatory Audit Summary Concerning License Amendment Request to Replace the Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent NUREG-1432, Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-14322020-10-30030 October 2020 Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-1432 ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI 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 NL-20-050, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-06-24024 June 2020 Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline ML20100H9922020-06-0202 June 2020 Issuance of Amendment No. 269 Proposed Technical Specification Changes to City Water Surveillance Requirement and Condensate Storage Tank Required Action A.1 ML20121A1932020-05-0606 May 2020 Alternative Requests for the Fifth 10 Year Interval Inservice Testing of Low Pressure Safety Injection Pumps and Service Water Valves ML20122A2622020-05-0404 May 2020 Correction to Amendment No. 294 Dated April 28, 2020, Permanently Defueled Technical Specifications ML20081J4022020-04-28028 April 2020 Issuance of Amendment No. 294 Permanently Defueled Technical Specifications ML20107J3172020-04-23023 April 2020 Relief Request ANO1-ISI-033 Related to ASME Code Case N-729-4 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles ML20078L1402020-04-15015 April 2020 Issuance of Amendment Nos. 62, 293, and 268 Changes to Emergency Plan for Post-Shutdown and Permanently Defueled Condition ML20099A1822020-04-13013 April 2020 Issuance of Relief Request IP3-IST-RR-001 - Alternative to Certain Requirements of the ASME Code for Extension of the Fourth 10-Year Inservice Test Interval ML20071Q7172020-04-10010 April 2020 Issuance of Amendment Nos. 292 and No. 267 Changes to Technical Specification Sections 1.1, 4.0, and 5.0 for a Permanently Defueled Condition ML20087L8032020-04-0808 April 2020 Issuance of Amendment No. 320 to Revise Control Element Assembly Drop Times 2024-01-24
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 12, 2017 Mr. Bryan S. Ford Senior Manager, Fleet Regulatory Assurance Entergy Operation, Inc.
1340 Echelon Parkway Jackson, MS 39213
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT 2 AND INDIAN POINT NUCLEAR GENERATING STATION, UNIT NO. 3- RELIEF REQUEST EN-ISl-16-1 REGARDING USE OF LATER EDITION AND ADDENDA OF THE ASME CODE (CAC NOS. MF8905 AND MF8906)
Dear Mr. Ford:
By letter dated December 1, 2016, Entergy Operations, Inc. and Entergy Nuclear Operations, Inc. (Entergy, the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) to use requirements of subsequent editions and addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, for activities associated with repair/replacement, pressure testing, and nondestructive examination (NOE).
The request EN-ISl-16-1 is for the Arkansas Nuclear One, Unit 2 (AN0-2), and the Indian Point Nuclear Generating Station, Unit No. 3 (IP-3).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.55a(g)(4)(iv), the licensee requested to use portions of the 2007 Edition through 2008 Addenda of the ASME Code,Section XI, for inservice inspection (ISi) items of the Class 1, 2, 3, MC, and CC components, component supports, and welds, subject to conditions listed in 10 CFR 50.55a(b).
The NRC staff determined that use of subsequent editions and addenda of the ASME Code,Section XI, requirements is acceptable. Accordingly, the NRC staff concluded that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(4)(iv). Therefore, the NRC staff approves use of the 2007 Edition through 2008 Addenda of the ASME Code,Section XI, for activities related to repair/replacement, pressure testing, and NOE of Class 1, 2, 3, MC, and CC components, component supports, and welds, for the reminder of the fourth 10-year ISi intervals at AN0-2, which is scheduled to end on March 25, 2020, and IP-3, which is scheduled to end on July 20, 2019.
B. Ford If you have any questions, please contact Margaret Watford at (301) 415-1233 or via e-mail at Margaret. Watford@nrc.gov.
Sincerely, Robert J. Pascarelli, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-368 and 50-286
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST EN-ISl-16-1 REGARDING USE OF LATER EDITION AND ADDENDA OF THE ASME CODE ENTERGY OPERATIONS. INC.
ENTERGY NUCLEAR OPERATIONS. INC.
ARKANSAS NUCLEAR ONE. UNIT 2 INDIAN POINT NUCLEAR GENERATING STATION. UNIT NO. 3 DOCKET NOS. 50-368 AND 50-286
1.0 INTRODUCTION
By letter dated December 1, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16337A368), Entergy Operations, Inc. and Entergy Nuclear Operations, Inc. (Entergy, the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC or the Commission) to use requirements of subsequent editions and addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, for activities associated with repair/replacement, pressure testing, and nondestructive examination (NOE). The request EN-ISl-16-1 is for Arkansas Nuclear One, Unit 2 (AN0-2), and Indian Point Nuclear Generating Station, Unit No. 3 (IP-3).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.55a(g)(4)(iv), "Applicable ISi Code: Use of subsequent Code editions and addenda," the licensee requested to use portions of the 2007 Edition through 2008 Addenda of the ASME Code,Section XI, for inservice inspection (ISi) items of the Class 1, 2, 3, MC, and CC components, component supports, and welds, subject to conditions listed in 10 CFR 50.55a(b).
2.0 REGULATORY EVALUATION
Pursuant to 10 CFR 50.55a(a), "Documents approved for incorporation by reference," and 10 CFR 50.55a(a)(1)(ii), "ASME Boiler and Pressure Vessel Code,Section XI," the ASME Code,Section XI, from the 1970 Edition through the 1976 Winter Addenda, and the 1977 Edition through the 2007 Edition with the 2008 Addenda have been approved for incorporation by reference, but limited to those provisions identified in paragraph (b)(2) of 10 CFR 50.55a.
Pursuant to 10 CFR 50.55a(g)(4)(iv), inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (a) of 10 CFR 50.55a, subject to the conditions listed in paragraph (b) of 10 CFR 50.55a, and subject to Commission approval. Portions of Enclosure
editions or addenda may be used, provided that all related requirements of the respective editions or addenda are met.
Based on the above, and subject to the following technical evaluation, the NRG staff determined that regulatory authority exists for the licensee to request and the NRG to approve the use of subsequent editions and addenda of the ASME Code requested by the licensee.
3.0 TECHNICAL EVALUATION
3.1 ASME Code Component Affected The ASME Code components affected by the licensee's request are ASME Code Class 1, 2, 3, MC, and CC components, component supports, and welds, as delineated in a table titled "Proposed ASME Section XI Code of Record for AN0-2 and IP-3" in Enclosure 1, "Proposed ASME Section XI Codes of Record for AN0-2 and IP-3," of the application dated December 1, 2016.
3.2 Applicable Code Edition and Addenda For both AN0-2 and IP-3, the Code of Record for the fourth 10-year ISi interval is the 2001 Edition through 2003 Addenda of the ASME Code.
3.3 Duration of the Request The licensee submitted this request for the remainder of the fourth 10-year ISi interval at AN0-2, which commenced on March 26, 2010, and is scheduled to end on March 25, 2020, and IP-3, which commenced on July 21, 2009, and is scheduled to end on July 20, 2019.
The licensee stated that an extension of up to 1 year could be applied to the duration of the fourth 10-year ISi interval of AN0-2, and IP-3, in accordance with the applicable requirements of IWA-2430, "Inspection Intervals."
3.4 Licensee's Request In its submittal, the licensee requested to use the requirements of the 2007 Edition through 2008 Addenda of the ASME Code,Section XI, for the repair/replacement activities, pressure testing, and NOE in lieu of the current Code of record of AN0-2, and IP-3.
The licensee stated that it will comply with all related requirements in the 2007 Edition through 2008 Addenda. In Section 4, "Related Requirements, in the attachment of its submittal, the licensee stated that it will comply with the following ASME Code,Section XI requirements:
- The licensee stated that it will utilize all "Articles" (e.g., IWA-4000, "Repair/Replacement Activities," IWA-5000, "System Pressure Tests") from every "Subsection" (e.g., IWA, IWB) of the 2007 Edition through 2008 Addenda that could be used or referenced for the performance of repair/replacement, pressure testing, and NOE activities.
- The licensee stated that it will utilize all mandatory appendices, and non-mandatory Appendices A through Q, of the 2007 Edition through 2008 Addenda, since these appendices provide related and supplemental requirements to the articles and paragraphs that are being used from the 2007 Edition through 2008 Addenda.
- For performance of the ISi examinations and tests, the licensee stated that it will continue to select, plan, and schedule the ISi activities (e.g., IWA-, IW8-, IWC-, IWD-,
IWE-, and IWF-2500, and/or the NRC approved ISi alternatives) in accordance with the current ISi program plans for AN0-2 and IP-3 (i.e., the 2001 Edition through 2003 Addenda of Section XI).
In the table provided in Enclosure 1 of its submittal, the licensee listed all applicable Code provisions (e.g., subsections and articles, and appendices) that will be used during implementation of two different editions and addenda of the ASME Code (dual ASME Code). In addition, Enclosure 1 included 11 footnotes that contain specific details to support this request.
The content of these footnotes is summarized below.
- 1. The licensee stated that it will comply with all applicable requirements and conditions mandated by 10 CFR 50.55a.
- 2. The licensee stated that it will use IWA-2100, "General," IWA-2200, "Examination Methods," and IWA-2300, "Qualifications of Nondestructive Examination Personnel," from the 2007 Edition through 2008 Addenda for requirements applicable to authorized inspection, examination methods, and qualification of NOE personnel. However, the 2001 Edition through 2003 Addenda requirements will be used for IWA-2400, "Inspection Program," IWA-2500, "Extent of Examination," and IWA-2600, "Weld Reference System," for the selection, planning, and scheduling of ISi activities.
- 3. For pressure testing, the licensee stated that:
o The NOE provision in IWA-4540, "Pressure Testing of Classes 1, 2, and 3 Items," paragraph (a)(2) of the 2002 Addenda will be applied when performing system leakage tests after repair/replacement activities involving welding or brazing to comply with 10 CFR 50.55a(b)(2)(xx)(8).
o Pressure testing of Class 1, 2, and 3 mechanical joints will be performed in accordance with IWA-4540(c) of the 1998 Edition and no addenda to comply with 10 CFR 50.55a(b)(2)(xxvi).
- 4. The licensee stated that selection, planning, and scheduling of the ISi will comply with the ASME Code,Section XI, articles (e.g., IW8-1000, "Scope and Responsibility," and IW8-2000, "Examination and Inspection,") from the 2001 Edition through 2003 Addenda, or applicable NRG-approved alternatives.
- 5. The licensee stated that IW8-3514, "Standards for Examination Category 8-F, Pressure Retaining Dissimilar Metal Welds in Vessel Nozzles, and Examination Category 8-J, Pressure Retaining Welds in Piping," of Section XI (the 2007 Edition through 2008 Addenda) requires that the acceptance standards for IW8-3514 be applied to planar surface connected flaws in UNS N06600, N06082, or W86182 materials in a pressurized water reactor subject to stress corrosion cracking. Therefore, if a planar flaw is found in these nickel alloy materials, the licensee will either evaluate the acceptability of the flaw in accordance with IW8-3600, "Analytical Evaluation of Flaws," or correct the
flawed condition by performing an approved ASME Code,Section XI, repair/replacement activity.
- 6. The licensee stated that the preservice and inservice examination and testing of snubbers will be performed in accordance with Subsection ISTD of the ASME Code for Operation and Maintenance of Nuclear Power Plants to comply with the requirements of 10 CFR 50.55a(b)(3)(v)(A).
- 7. The licensee stated that Article IWF-5000, "lnservice Inspection Requirements for Snubbers," was deleted from subsection IWF in the 2006 Addenda and later editions and addenda. Therefore, it will not be used.
- 8. The licensee stated that it will comply with the requirements and conditions for reactor vessel head inspections mandated by 10 CFR 50.55a(g)(6)(ii)(D)(4). The regulation requires that ultrasonic examinations performed in accordance with ASME Code Case N-729-1, "Alternative Examination Requirements for PWR
[Pressurized Water Reactor] Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration WeldsSection XI, Division 1," comply with Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems," of the 2004 Edition with no addenda.
- 9. The licensee stated that non-mandatory Appendices F and I do not exist in the 2001 Edition through 2003 Addenda and the 2007 Edition through 2008 Addenda of ASME Code,Section XI. Therefore, non-mandatory Appendices F and I will not be used.
- 10. The licensee stated that non-mandatory Appendix R, "Risk-Informed Inspection Requirements for Piping," has been added into Section XI since the 2005 Addenda of the ASME Code. Non-mandatory Appendix R is referenced in IWB-2500 and IWC-2500, "Examination and Pressure Test Requirements,"
paragraph (c). The licensee will continue to use the 2001 Edition through 2003 Addenda for IWB-2000, IWC-2000 and IWD-2000, "Examination and Inspection."
Therefore, non-mandatory Appendix R will not be used.
- 11. The licensee stated that the system leakage test of the Class 1 pressure retaining components (as required by Table IWB-2500-1, "Examination Categories") will comply with the boundary requirements of IWB-5222, "Boundaries," of the 2007 Edition through 2008 Addenda. The IWB-5222 requirements are as follows:
o The boundary of the system leakage test performed each refueling outage prior to plant start-up shall comply with IWB-5222(a).
o The boundary of the system leakage test performed at or near the end of the inspection interval shall comply with IWB-5222(b).
3.5 Licensee's Basis for Request In its submittal, the licensee stated that while the ISi program plans are controlled in site-specific documents, the ISi program activities specific to repair/replacement, pressure testing, and NOE are controlled in common corporate program procedures and implemented across the entire Entergy nuclear fleet.
The licensee stated that all Entergy's plants including AN0-2, and IP-3, perform the ISi program activities specific to repair/replacement, pressure testing, and NOE in accordance with Entergy's standardized fleet program. This standardized program is based on a common edition and addenda of the ASME Code,Section XI, which is currently the 2001 Edition through 2003 Addenda.
The licensee also stated that on December 1, 2017, it plans to update Entergy's nuclear fleet Code of Record for the activities related to repair/replacement, pressure testing, and NOE programs from the 2001 Edition through 2003 Addenda to the 2007 Edition through 2008 Addenda. If AN0-2 and IP-3 would continue performing the repair/replacement activities, pressure testing, and NOE in accordance with their current Code of record after December 1, 2017, then the licensee would be required to maintain two separate sets of programs. This would mean one set of programs for AN0-2 and IP-3, and another set of programs for the balance of the Entergy nuclear fleet.
The licensee stated that it has process controls in place to track and monitor the implementation of the dual Code, to properly manage dual Code editions and addenda. These process controls are documented in site-specific ISi plans and administrative and program procedures. The licensee summarized these process controls in its application dated December 1, 2016:
Site-specific lnservice Inspection Plans: These documents implement the ASME Section XI lnservice inspection programs at AN0-2 and IP-3. They ensure the selection, planning and scheduling of ISi examinations and tests are performed in accordance with 2001 Edition/2003 Addenda of ASME Section XI as delineated in Enclosure 1 [of this request].
Administrative and Program Procedures: These procedures establish requirements for implementing the ASME Section XI NOE, PT [pressure testing],
and R&R [repair/replacement] programs. These procedures also ensure program requirements comply with applicable requirements in the 2007 Edition/2008 Addenda of ASME Section XI as described in Enclosure 1 [of this request].
The licensee stated that the above process controls will ensure the use of dual Code editions and addenda at AN0-2 and IP-3 are appropriately managed, tracked, and controlled.
3.6 NRC Staff Evaluation The NRC staff has evaluated this request pursuant to 10 CFR 50.55a(g)(4)(iv). The NRC staff's evaluation focuses on whether: 1) the subsequent editions and addenda of the ASME Code as requested for use are incorporated by reference in 50.55a(a); 2) the Code requirements subject to the conditions listed in 50.55a(b) are met; 3) a request is submitted to the NRC for approval; and 4) all related requirements of the respective editions and addenda are met. If these four criteria are met, the NRC staff will conclude that the requirements of 10 CFR 50.55a(g)(4)(iv)
will also be met.
In evaluating the licensee's request EN-ISl-16-1, the N RC staff confirms that,
- 1. The 2007 Edition through 2008 Addenda of Section XI to the ASME Code, as requested for use, is incorporated by reference in 10 CFR 50.55a, and subject to the conditions in paragraph (b)(2) of 10 CFR 50.55a. Therefore, the NRC staff determines that the 2007 Edition through 2008 Addenda is acceptable provided that the conditions in paragraph (b)(2) of 10 CFR 50.55a be also met.
- 2. The licensee has identified and acknowledged that it will comply with all applicable provisions of 10 CFR 50.55a.
- 3. This submittal (request EN-ISl-16-1) serves as the licensee's request for NRC approval of the use of the 2007 Edition through 2008 Addenda of Section XI for performance of repair/replacement activities, pressure testing, and NOE of Class 1, 2, 3, MC, and CC components, component supports, and welds;
- 4. The licensee has identified and acknowledged that it will comply with all related requirements of the 2007 Edition through 2008 Addenda of Section XI.
Based on the above, the NRC staff determines that each of the four required regulatory requirements for the use of a later edition of the Code have been met and that the use of the 2007 Edition through 2008 Addenda of Section XI to the ASME Code for performance of repair/replacement activities, pressure testing, and NOE of Class 1, 2, 3, MC, and CC components is acceptable.
4.0 CONCLUSION
As set forth above, the NRC staff determines that use of subsequent editions and addenda of the ASME Code,Section XI, requirements is acceptable. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(4)(iv). Therefore, the NRC staff approves the use of the 2007 Edition through 2008 Addenda of the ASME Code,Section XI, for activities related to repair/replacement, pressure testing, and NOE of Class 1, 2, 3, MC, and CC components, component supports, and welds, for the reminder of the fourth 10-year ISi interval at AN0-2, which is scheduled to end on March 25, 2020, and IP-3, which is scheduled to end on July 20, 2019.
All other ASME Code,Section XI, requirements for which relief was not specifically requested and approved remain applicable, including the third-party review by the Authorized Nuclear lnservice Inspector.
Principal Contributor: Ali Rezai Date: July 12, 2017
ML171748144 *via memo OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DE/EPNB/BC* NRR/DORL/LPL4/BC NAME MWatford PBlechman DAiiey RPascarelli DATE 06/28/2017 06/28/2017 02/14/2017 07/12/2017