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MONTHYEARLR-N20-0049, LR-N20-0049 COVID-19 Email Exemption Request Security FOF - NRC for Salem Generating Station, Units 1 & 2 and Hope Creek Generating Station2020-07-21021 July 2020 LR-N20-0049 COVID-19 Email Exemption Request Security FOF - NRC for Salem Generating Station, Units 1 & 2 and Hope Creek Generating Station Project stage: Other ML20219A4482020-08-0606 August 2020 NextEra Energy Point Beach, LLC (NextEra) Requests NRC Approval for Alternative Work Hour Controls Delineated in the NRC Letter of 3/28/2020 Project stage: Request NRC 2020-0024, Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements2020-08-17017 August 2020 Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements Project stage: Response to RAI ML20233A8142020-08-20020 August 2020 Incoming Request from FitzPatrick Re COVID-19 Exemption from Part 26 Work Hours Requirements Project stage: Other ML20267A3862020-09-22022 September 2020, 23 September 2020 Relief Request Number RR 5-8, Proposed Alternative to ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations Project stage: Request ML20267A3912020-09-22022 September 2020 Attachment 4, Framatome Document No. 51-9292503-002, Palisades CEDM Nozzle Idtb Repair - Life Assessment Summary Project stage: Request PNP 2020-031, Attachment 3 - Framatome, Inc. Affidavit Supporting Withholding of Proprietary Information2020-09-22022 September 2020 Attachment 3 - Framatome, Inc. Affidavit Supporting Withholding of Proprietary Information Project stage: Request ML20243A0002020-09-23023 September 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for August 2020 Project stage: Approval ML20272A0112020-09-26026 September 2020 Request for Additional Information - Palisades Relief Request RR 5-8 (Proposed Alternative) for Reactor Pressure Vessel Head Penetration Repairs Project stage: RAI PNP 2020-034, Attachment 2 - Framatome, Inc. Affidavit Supporting Withholding of Proprietary Information2020-09-27027 September 2020 Attachment 2 - Framatome, Inc. Affidavit Supporting Withholding of Proprietary Information Project stage: Request ML20272A1622020-09-27027 September 2020, 28 September 2020, 30 September 2020 Response to Request for Additional Information Regarding Relief Request Number RR 5-8, Proposed Alternative to ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations Project stage: Request ML20269A3452020-09-28028 September 2020 Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides Project stage: Meeting ML20275A3432020-10-0101 October 2020 Verbal Authorization for Proposed Alternative (RR 5-8) Reactor Vessel Closure Head Penetration Repairs Project stage: Other ML20288A5562020-10-16016 October 2020 Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant- Relief Request 5-8 for Alternate Repair of Reactor Closure Head Penetration Nozzles Project stage: Withholding Request Acceptance ML20282A7642020-10-16016 October 2020 Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant - Relief Request 5-8 for Alternate Repair of Reactor Closure Head Penetration Nozzles Project stage: Withholding Request Acceptance ML20365A0012021-01-19019 January 2021 Relief Request 5-8 Related to ASME Code Case N-729-4 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles Project stage: Approval 2020-08-06
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Category:Code Relief or Alternative
MONTHYEARML21299A0032021-10-28028 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 ML20365A0012021-01-19019 January 2021 Relief Request 5-8 Related to ASME Code Case N-729-4 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles ML20282A7642020-10-16016 October 2020 Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant - Relief Request 5-8 for Alternate Repair of Reactor Closure Head Penetration Nozzles ML20275A3432020-10-0101 October 2020 Verbal Authorization for Proposed Alternative (RR 5-8) Reactor Vessel Closure Head Penetration Repairs ML20272A1662020-09-30030 September 2020 Attachment 3 - Framatome Document No. ANP-3876, Revision 1Q1NP, Response to NRC Request for Additional Information of Palisades Relief Request Number RR 5-8, Repair of Reactor Pressure Vessel Head Penetration, Inservice Inspection Program, ML20267A3872020-09-23023 September 2020 Relief Request Number RR 5-8, Proposed Alternative to ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations ML20267A3882020-09-23023 September 2020 Attachment 1 - Relief Request Number RR 5-8, Proposed Alternative to ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations 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) 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 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 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 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 ML21067A4982017-09-0707 September 2017 Relief Request No. RR 5-4 Proposed Alternative, Weld Reference System ML17194A8072017-08-14014 August 2017 Relief Request No. RR 4-25 Limited Coverage Examinations During the Fourth 10-Year Inservice Inspection Interval ML17137A0282017-06-29029 June 2017 Relief Request Number RR 5; 5 Proposed Alternative, Under-Vessel Leakage Examination 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 ML16022A1072016-02-0101 February 2016 Relief Request Number RR 4-23- Proposed Alternative Concerning ASME Code Depth Sizing Requirement ML15320A2442015-11-25025 November 2015 Relief Request Number 5-1, Proposed Alternative, Extend the Current ASME Code of Record Into the Fifth 10-Year ISI Interval for ISI Related Activities PNP 2015-073, Forwards Response to Request for Additional Information Regarding Relief Request Number RR 4-22 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination2015-09-17017 September 2015 Forwards Response to Request for Additional Information Regarding Relief Request Number RR 4-22 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination PNP 2015-075, Submittal of Relief Request Number RR 4-23, Proposed Alternative Concerning ASME Code Depth Sizing Requirement2015-09-16016 September 2015 Submittal of Relief Request Number RR 4-23, Proposed Alternative Concerning ASME Code Depth Sizing Requirement 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 PNP 2015-024, Requests Relief of Proposed Alternatives for the Fifth 10-Year Inservice Test Interval2015-05-19019 May 2015 Requests Relief of Proposed Alternatives for the Fifth 10-Year Inservice Test Interval PNP 2015-022, Relief Request Number RR 5-1, Proposed Alternative, Extend the Current ASME Code of Record Into the Fifth 10-year ISI Interval for ISI Related Activities2015-04-29029 April 2015 Relief Request Number RR 5-1, Proposed Alternative, Extend the Current ASME Code of Record Into the Fifth 10-year ISI Interval for ISI Related Activities ML14199A5572014-08-13013 August 2014 Relief Request Number RR-4-19, Proposed Alternative to the Requirements of ASME Code Case N-638-4 ML12258A3522012-09-26026 September 2012 Relief from Certain Requirements of the ASME Code Case N-77-1 for the Fourth 10-Year Inservice Inspection Interval CNRO-2008-00035, Follow-up to Request for Extension of Discretion for the Interim Enforcement Policy for Fire Protection Issues on 10CFR50.48(c), National Fire Protection Association Standard NFPA 8052008-11-20020 November 2008 Follow-up to Request for Extension of Discretion for the Interim Enforcement Policy for Fire Protection Issues on 10CFR50.48(c), National Fire Protection Association Standard NFPA 805 ML0824801002008-09-19019 September 2008 Acceptance of Requested Licensing Action Relief Request and Supporting Amendment to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examination ML0726304272007-09-21021 September 2007 Relief, Request Relief No. 1 - from Requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Requirements for Repair of Pressurizer Nozzle Penetrations ML0719002512007-09-12012 September 2007 Relief Request 1 for the Repair of Reactor Vessel Closure Head Penetrations ML0716201362007-09-12012 September 2007 Relief Request 2 for ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations ML0716302482007-05-31031 May 2007 Request for Relief from ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Vent Line Penetration ML0709200292007-04-30030 April 2007 Request for Relief from ASME Code Regarding Weld Reference System, Relief Request No. RR 4-11 ML0617103642006-07-0303 July 2006 Monticello Nuclear Generating Plant, Palisades Nuclear Plant, Point Beach Nuclear Plant Units 1 and 2, Prairie Island Nuclear Generating Plant, Units 1 and 2 - Use of ASME Code Case N-513-2 ML0607902512006-04-0303 April 2006 Request for Relief from ASME Code, Section XI, Requirements for Repair of Pressurizer Nozzle Penetrations ML0607900612006-04-0303 April 2006 Request for Authorization to Use Alternatives to ASME Code, Section XI, IWA-3300, IWBb-3142.4, IWB-3420, and IWB-3613 for Reactor Pressure Vessel Head Penetration Repair ML0608003192006-04-0303 April 2006 Request for Authorization to Use Alternatives to ASME Code, Section XI, IWA-4120 for Reactor Pressure Vessel Head Penetration Repair ML0605800602006-03-21021 March 2006 Request for Authorization of Relief Request Number 1 for Certain Requirements in ASME Code, Section XI, Code Case N-638-1 ML0601201042006-01-27027 January 2006 Request for Authorization to Extend the Third 10-Year ISI Interval for Reactor Vessel Visual Examination, MC6546 ML0532002962005-11-29029 November 2005 Request for Authorization to Extend the Third Inservice Inspection Interval for Reactor Vessel Weld Examination ML0520706392005-08-17017 August 2005 Revised Relief Requests 28, 30, and 31 for 3rd 10-year Pump and Valve Inservice Testing ML0436504802005-01-18018 January 2005 Relief Request to Use Code Case N-661, and Safety Evaluation ML0430901912004-11-0808 November 2004 Relief, ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations ML0430605712004-11-0303 November 2004 Verbal Authorization of Relief from ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations ML0419103642004-09-14014 September 2004 Relief, Third 10-Year Interval Inservice Inspection Program Plan ML0422402492004-08-0909 August 2004 Request for Relief from ASME Section XI Code Requirements for Repair of Pressurizer Nozzle Penetrations ML0401607382004-02-26026 February 2004 Prairie, Units 1 and 2, Kewaunee, Point Beach, Units 1 and 2, Palisades, Re Request for Alternatives to ASME Section XI, Appendix Viii, Supplement 10 ML0311505002003-05-19019 May 2003 Risk-Informed Inservice Inspection Program TAC No. MB4420 ML0306906292003-03-20020 March 2003 3/20/2003, Palisades, Relief, Re Third Inservice Inspection Interval Program ML0207202292002-03-0101 March 2002 Relief Code, Relief Request for Alternate ASME Code, Section XI, Risk-Informed Inservice Inspection Program ML0207201452002-02-27027 February 2002 Code Relief, Request for Relief from ASME Code Requirements for Inservice Inspection Pressure Test Program (Relief Request PR-07) 2021-10-28
[Table view] Category:Letter
MONTHYEARML24022A1172024-01-23023 January 2024 Acceptance of Requested Licensing Action Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML24012A2422024-01-16016 January 2024 Acceptance of Requested Licensing Action License Transfer Request ML23236A0042023-12-27027 December 2023 Issuance of Amendment 274 Re Changes to Perm Defueled Emergency Plan and Perm Defueled Emergency Action Level Scheme ML23355A1242023-12-26026 December 2023 Withdrawal of an Amendment Request Re License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML23192A0772023-12-26026 December 2023 Letter Exemption from the Requirements of 10 CFR 140.11(a)(4) Concerning Offsite Primary and Secondary Liability Insurance ML23191A5222023-12-22022 December 2023 Exemption Letter from the Requirements of 10 CFR 50.54(W)(1) Concerning Onsite Property Damage Insurance (EPID - L-2022-LLE-0032) ML23263A9772023-12-22022 December 2023 Exemption from Certain Emergency Planning Requirements and Related Safety Evaluation ML23354A2602023-12-21021 December 2023 Reference Simulator Inspection Request for Information L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 PNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations PNP 2023-035, Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements2023-12-12012 December 2023 Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements PNP 2023-028, Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments2023-12-0606 December 2023 Application for Order Consenting to Transfer of Control of License and Approving Conforming License 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 ML23291A4402023-11-0303 November 2023 Acceptance of Requested Licensing Action Request for Exemption from 10 CFR 50.82(a)(2) to Support Reauthorization of Power Operations IR 05000255/20230032023-10-0404 October 2023 NRC Inspection Report No. 05000255/2023003(DRSS)-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23275A0012023-10-0202 October 2023 Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant PNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.822023-09-28028 September 2023 Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82 PNP 2023-026, Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations2023-09-28028 September 2023 Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations PNP 2023-023, Special Report High Range Noble Gas Monitor Inoperable2023-08-0909 August 2023 Special Report High Range Noble Gas Monitor Inoperable ML23215A2302023-08-0303 August 2023 Notice of Organization Change - Chief Nuclear Officer IR 05000255/20230022023-07-19019 July 2023 NRC Inspection Report 05000255/2023002 DRSS-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23087A0362023-05-0202 May 2023 PSDAR Review Letter ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment PNP 2023-018, 2022 Annual Non-Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Non-Radiological Environmental Operating Report L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 PNP 2023-007, and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports2023-04-19019 April 2023 and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports PNP 2023-008, 2022 Radiological Environmental Operating Report2023-04-18018 April 2023 2022 Radiological Environmental Operating Report L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations PNP 2023-002, 6 to Updated Final Safety Analysis Report2023-03-31031 March 2023 6 to Updated Final Safety Analysis Report ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance PNP 2023-006, Report of Changes to Security Plan, Revision 202023-03-29029 March 2023 Report of Changes to Security Plan, Revision 20 PNP 2023-012, Presentation on Regulatory Path to Reauthorize Power Operations2023-03-16016 March 2023 Presentation on Regulatory Path to Reauthorize Power Operations ML23038A0982023-03-15015 March 2023 Request for Withholding Information from Public Disclosure ML23095A0642023-03-14014 March 2023 American Nuclear Insurers, Notice of Cancellation Rescinded PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023 Regulatory Path to Reauthorize Power Operations PNP 2023-004, Report of Changes to Palisades Nuclear Plant Technical Specification Bases2023-03-0808 March 2023 Report of Changes to Palisades Nuclear Plant Technical Specification Bases PNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023 Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23052A1092023-02-17017 February 2023 FEMA Letter to NRC, Proposed Commission Paper Language for Palisades Nuclear Plant Emergency Plan Decommissioning Exemption Request ML23032A3992023-02-0101 February 2023 Regulatory Path to Reauthorize Power Operations IR 05000255/20220032022-12-28028 December 2022 NRC Inspection Report No. 05000255/2022003(DRSS); 07200007/2022001 (Drss) Holtec Decommissioning International, LLC, Palisades Nuclear Plant L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 PNP 2022-037, Report of Changes to Security Plan, Revision 192022-12-14014 December 2022 Report of Changes to Security Plan, Revision 19 ML22321A2852022-11-17017 November 2022 LLC Master Decommissioning Trust Agreement for Palisades Nuclear Plant IR 05000255/20224012022-11-0909 November 2022 Decommissioning Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2022401 PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022 Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-035, International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations2022-11-0202 November 2022 International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations PNP 2022-024, Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance PNP 2022-026, Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance ML22292A2572022-10-25025 October 2022 Permanently Defueled Emergency Plan License Amendment RAI Letter 2024-01-23
[Table view] Category:Safety Evaluation
MONTHYEARML23263A9772023-12-22022 December 2023 Exemption from Certain Emergency Planning Requirements and Related Safety Evaluation ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML22039A1982022-05-13013 May 2022 Issuance of Amendment No. 272 Permanently Defueled Technical Specifications ML21292A1482021-12-13013 December 2021 Safety Evaluation Related to Request for Direct and Indirect Transfers of Control of Facility Operating License DPR-6 for Big Rock Point and Renewed Facility Operating License DPR-20 for Palisades Nuclear Plant and ISFSI (EPID L-2020-LLM-00 ML21292A1472021-12-13013 December 2021 Draft Conforming License Amendments - Palisades Nuclear Plant Renewed Facility Operating License DPR-20 and ISFSI and Big Rock Point Facility Operating License DPR-6 and ISFSI (EPID L-2020-LLM-0003) (Enclosure 2) ML20365A0012021-01-19019 January 2021 Relief Request 5-8 Related to ASME Code Case N-729-4 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI ML19317D8552019-12-30030 December 2019 Issuance of Amendment No. 271 Regarding Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML19318E3942019-12-0202 December 2019 Reactor Vessel Material Surveillance Capsule Withdrawal Schedule 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 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 ML19198A0802019-08-20020 August 2019 Issuance of Amendments No. 269 Regarding Changes to NFPA 805 Modifications and Change to Full Compliance Implementation Date for the Fire Protection Program (Epids L-2018-LLA-0296 and L-2019-LLA-0049) ML19135A0502019-05-21021 May 2019 Correction to Safety Evaluation for Amendment No.268 Regarding Revision to Diesel Generator Undervoltage Start Surveillance Requirement ML19107A0532019-05-13013 May 2019 Issuance of Amendment No. 268 Regarding Revision to Diesel Generator Undervoltage Start Surveillance Requirement ML19112A3172019-04-26026 April 2019 Approval of Alternative for Repair of Reactor Pressure Vessel Head Penetrations ML18170A2192018-09-24024 September 2018 Issuance of Amendment Changes to the Emergency Plan for Permanently Defueled Condition (CAC No. MG0198; EPID L-2017-LLA-0305) 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 ML18114A4102018-06-0404 June 2018 Issuance of Amendment Regarding Administrative Controls for Permanently Defueled Condition (CAC No. MG0021; EPID L-2017-LLA-0266) ML18135A2632018-05-21021 May 2018 Relief Request No. RR 5-6 Alternate to the Reexamination Frequency for a Relevant Condition ML18039A2442018-02-27027 February 2018 Issuance of Amendment License Amendment Request to Change the Full Compliance Implementation Date for the Fire Protection Program Transition License Condition for Required Modifications ML17328B0332017-12-15015 December 2017 Issuance of Amendment Cyber Security Plan Implementation Schedule (CAC No. MF9523; EPID L-2017-LLA-0199) ML21067A4982017-09-0707 September 2017 Relief Request No. RR 5-4 Proposed Alternative, Weld Reference System ML17151A3502017-08-21021 August 2017 Approval of Certified Fuel Handler Training and Retraining Program ML17194A8072017-08-14014 August 2017 Relief Request No. RR 4-25 Limited Coverage Examinations During the Fourth 10-Year Inservice Inspection Interval ML17137A0282017-06-29029 June 2017 Relief Request Number RR 5; 5 Proposed Alternative, Under-Vessel Leakage Examination ML17121A5102017-06-0808 June 2017 Issuance of Amendment License Amendment Request for Editorial and Administrative Changes to Technical Specifications ML17082A4652017-05-30030 May 2017 Issuance of Amendment 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 ML16300A0302016-12-19019 December 2016 Issuance of Amendment Revision to the Requirements for Steam Generator Tube Inspections and Repair Criteria in the Cold Leg Tube Sheet Region ML16281A4982016-10-28028 October 2016 Issuance of Amendment No. 260, Revise License Condition 2.C.(4) and Technical Specifications Related to Control Rod Drive Exercise Surveillance ML16251A6202016-09-13013 September 2016 Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097) ML16014A3182016-08-22022 August 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 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 ML16093A0282016-05-31031 May 2016 Entergy Services, Inc., Proposed Alternative to Utilize ASME Code Case N-789-1, Relief Request RR-EN-15-1, Revision 1 ML16078A0682016-05-0202 May 2016 Issuance of Amendment Cyber Security Plan Implementation Schedule ML16043A4852016-03-14014 March 2016 Relief Request Number RR 4-24 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination ML16022A1072016-02-0101 February 2016 Relief Request Number RR 4-23- Proposed Alternative Concerning ASME Code Depth Sizing Requirement ML15334A3072015-12-22022 December 2015 Relief Request Numbers RR 5-2 and 5-3, Proposed Alternative to the Requirements of the ASME OM Code for the Fifth 10-Year Inservice Test Interval ML15320A2442015-11-25025 November 2015 Relief Request Number 5-1, Proposed Alternative, Extend the Current ASME Code of Record Into the Fifth 10-Year ISI Interval for ISI Related Activities ML15103A0592015-05-18018 May 2015 Issuance of Amendment Adoption of TSTF-426, Revision 5, Revise or Add Actions to Preclude Entry Into Limiting Condition for Operation 3.0.3 - RITSTF Initiatives 6B and 6C. ML15055A1062015-04-22022 April 2015 Issuance of Amendment License Amendment Request to Revise Emergency Response Organization Staff Augmentation Response Times ML15007A1912015-02-27027 February 2015 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) ML14237A1442014-12-0808 December 2014 Issuance of Amendment Cyber Security Plan Implementation Schedule ML14283A2872014-10-22022 October 2014 Issuance of Amendment Application for Technical Specification Change (TSTF-427) to Add Limiting Condition for Operation 3.0.9 Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process ML14223B2262014-09-0404 September 2014 Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination ML14199A5572014-08-13013 August 2014 Relief Request Number RR-4-19, Proposed Alternative to the Requirements of ASME Code Case N-638-4 ML14210A2662014-08-0808 August 2014 Arkansas, Units 1 & 2, Big Rock Point, James A. Fitzpatrick, Grand Gulf, Unit 1, Indian Point, Units 1, 2 & 3, Palisades, Pilgrim, River Bend, Unit 1, Vermont Yankee, Waterford, Safety Evaluation Quality Assurance Program Manual, Rev. 24 & ML13312A4232013-11-26026 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13129A2192013-05-29029 May 2013 Staff Assessment in Response to Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13025A3062013-03-14014 March 2013 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Correction to Amendments Issued on 12/28/12, Revise QA Program Manual and Staff Qualification Technical Specifications ML13056A5142013-02-28028 February 2013 Non-Proprietary Issuance of Amendment Regarding Replacement of Spent Fuel Pool Region 1 Storage Racks 2023-05-01
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January 19, 2021 Vice President, Operations Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530
SUBJECT:
PALISADES NUCLEAR PLANT - RELIEF REQUEST 5-8 RELATED TO ASME CODE CASE N-729-4 SUPPLEMENTAL EXAMINATION REQUIREMENTS OF REACTOR VESSEL CLOSURE HEAD PENETRATION NOZZLES (EPID L-2020-LLR-0128)
Dear Sir or Madam:
By letter dated September 23, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20267A386), as supplemented by letter dated September 28, 2020 (ADAMS Accession No. ML20272A162), Entergy Nuclear Operations, Inc. (Entergy, or the licensee) submitted Relief Request (RR) 5-8, to the U.S. Nuclear Regulatory Commission (NRC) for the use of an alternative to certain requirements in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Rules for lnservice Inspection of Nuclear Power Plant Components, and Code Case N-638-7 Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW Temper Bead Technique, related to the repair of degraded reactor vessel closure head (RVCH) penetration numbers 17 and 34 at Palisades Nuclear Plant (PNP).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a(z)(1), Acceptable level of quality and safety, the licensee requested to use the proposed alternative in RR 5-8 on the basis that the proposed alternative will provide an acceptable level of quality and safety.
On October 1, 2020 (ADAMS Accession No. ML20275A343), the NRC verbally authorized the use of RR 5-8 at PNP for one cycle of operation, not to exceed 20 months of operation or May 31, 2022, when PNP will permanently cease power operations. The enclosed safety evaluation (SE) describes the technical basis for the NRCs verbal authorization.
The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed SE, that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1). Therefore, the NRC staff authorizes the proposed alternative in RR 5-8 for one cycle of operation, not to exceed 20 months of operation or May 31, 2022, when the PNP will permanently cease power operations.
All other ASME Code,Section XI, requirements for which relief was not specifically requested and approved in the subject request for relief remain applicable, including the third-party review by the Authorized Nuclear Inservice Inspector.
If you have any questions, please contact Scott P. Wall, at 301-415-2855 or via e-mail at Scott.Wall@nrc.gov.
Sincerely, Digitally signed by Nancy L. Nancy L. Salgado Date: 2021.01.19 Salgado 08:27:28 -05'00' Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-255
Enclosure:
Safety Evaluation cc: Listserv
ML20365A001 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DNRL/NPHP/BC NRR/DORL/LPL3/BC NAME SWall SRohrer MMitchell NSalgado DATE 01/14/21 01/04/21 01/13/21 1/19/21 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST 5-8 REGARDING ALTERNATIVE REPAIR OF REACTOR VESSEL CLOSURE HEAD PENETRATION NOZZLES ENTERGY NUCLEAR OPERATIONS, INC.
PALISADES NUCLEAR PLANT DOCKET NO. 50-255
1.0 INTRODUCTION
By letter dated September 23, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20267A386), as supplemented by letter dated September 28, 2020 (ADAMS Accession No. ML20272A162), Entergy Nuclear Operations, Inc. (Entergy, or the licensee) submitted Relief Request (RR) 5-8, to the U.S. Nuclear Regulatory Commission (NRC) for the use of an alternative to certain requirements in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Rules for lnservice Inspection of Nuclear Power Plant Components, and Code Case N-638-7 Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW Temper Bead Technique, related to the repair of degraded reactor vessel closure head (RVCH) penetration numbers 17 and 34 at Palisades Nuclear Plant (PNP).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a(z)(1), Acceptable level of quality and safety, the licensee requested authorization of its proposed alternative on the basis that the proposed alternative will provide an acceptable level of quality and safety.
On October 1, 2020 (ADAMS Accession No. ML20275A343), the U.S. Nuclear Regulatory Commission (NRC) staff verbally authorized the use of RR 5-8 at PNP for one cycle of operation, not to exceed 20 months of operation, or May 31, 2022, when the PNP will permanently cease power operations. The enclosed safety evaluation describes the technical basis for the NRCs verbal authorization
2.0 REGULATORY EVALUATION
Repair and Replacement activities for ASME Code Class 1, 2, and 3 components is to be performed in accordance with ASME Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, and applicable editions and addenda as required by 10 CFR 50.55a(g), Preservice and inservice inspection requirements, except where specific written relief has been granted by the NRC.
Enclosure
Section 50.55a(z), Alternatives to codes and standards requirements, of 10 CFR states, in part, that Alternatives to the requirements of [paragraph (g) of 10 CFR 50.55a] or portions thereof may be used, when authorized by the Director, Office of Nuclear Reactor Regulation.
A proposed alternative must be submitted and authorized prior to implementation. The licensee must demonstrate that: (1) the proposed alternatives provide an acceptable level of quality and safety, or (2) compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request the use of an alternative and the NRC to authorize the proposed alternative.
3.0 TECHNICAL EVALUATION
3.1 ASME Code Components Affected
The RVCH penetration numbers 17 and 34. The nozzles were examined in accordance with ASME Code Case N-729-4, Alternative Examination Requirements for PWR [Pressurized Water Reactor] Reactor Vessel Upper Heads with Nozzles Having Pressure-Retaining Partial-Penetration WeldsSection XI, Division 1.
3.2 ISI Interval and Applicable Code Edition and Addenda PNP is currently in its fifth 10-year ISI interval, which began December 13, 2015, and was originally scheduled to end on December 12, 2025. The ASME Code of record for the fifth 10-year ISI interval is the 2007 Edition through the 2008 Addenda.
3.3 Code Requirement for Which Relief is Requested ASME Code,Section III, Rules for Construction of Nuclear Facility Components, Paragraph NB-5245 and subparagraph NB-5331(b).
ASME Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, subsubarticle IWB-3420 and subparagraph IWB-3132.3.
ASME Code Case N-638-7, Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW [Gas Tungsten Arc Welding] Temper Bead Technique,Section XI, Division 1.
3.4 Licensees Proposed Alternative The licensee is proposing to perform a modified half-nozzle repair of the RVCH penetration numbers 17 and 34. The proposed alternative uses inside-diameter temper bead (IDTB) welding in accordance with the requirements of the ASME Code, Sections III and XI, and ASME Code Case N-638-7, and Code alternatives discussed below.
Proposed alternative RR 5-8 has the following deviations from ASME Code:
- 1) Alternate in-process examination requirements of ASME Code,Section III, paragraph NB-5245 and subparagraph NB-5331(b);
- 2) Alternate acceptance criteria of ASME Code,Section XI, subsubarticle IWB-3420 and subparagraph IWB-3132.3; and,
- 3) Alternate materials requirements of ASME Code Case N-638-7.
Specific details are provided in the September 23, 2020, application, as supplement by letter dated September 28, 2020.
3.5 Licensees Basis for the Proposed Alternative The licensee has developed alternative examination methods, flaw acceptance criteria, materials requirements, flaw evaluation methods, welding methods, and to implement the IDTB repairs.
The modified examination methods are based on the use of a final penetrant testing (PT) and ultrasonic testing (UT) in lieu of progressive penetrant testing. The combination of performing PT and UT examinations depicted in during the IDTB repair provides assurance of structural integrity.
The alternate acceptance criteria for a possible triple-point anomaly is based on a fracture mechanics analysis that was performed for the design configuration to provide justification, in accordance with ASME Code,Section XI, for operating with the postulated triple point anomaly. The anomaly is modeled as a 0.10-inch-deep crack-like defect, initiating at the triple point location, considering the most susceptible material for propagation.
The basis for the alternative materials requirements, i.e., the lack of fine-grain practice, is based on the EPRI Report 1014351, "Repair and Replacement Applications Center: Topical Report Supporting Expedited NRC Review of Code Cases for Dissimilar Metal Weld Overlay Repairs." This report provides a comparison of the chemical and mechanical properties, heat treatment, and grain refinement practices of SA-302, Grade B Modified to SA-533, Grade B Class 1 materials.
The duration of the proposed alternative is based on the most limiting life predicted by three evaluations: the weld anomaly analysis, the as-left J-groove analysis, and the primary water stress corrosion cracking (PWSCC) evaluation of the original Alloy 600 nozzle. The life expectancy for the IDTB repair is conservatively estimated by the licensee to be 21.8 effective full power months (EFPM).
3.6 Licensees Proposed Duration of Relief Request The licensee proposed this alternative one cycle of operation, not to exceed 20 months of operation, or May 31, 2022, when the PNP will permanently cease power operations.
3.7 NRC Staff Review The NRC staff evaluated the licensees proposed alternative RR 5-8, including the weld design, flaw evaluations, welding, and examinations in accordance with ASME Code, Sections III and XI, and ASME Code Case N-638-7. The NRC staff also evaluated the proposed deviations from the applicable ASME Code requirements included in the proposed alternative. Verbal authorization for proposed alternative RR 5-8 was given on October 1, 2020 (ADAMS Accession No. ML20275A343). This safety evaluation documents the technical basis for the NRC's verbal authorization.
The licensee proposed to use a half-nozzle repair method with IDTB welding to repair and restore the pressure boundary of the degraded nozzle penetrations. To support its repair
option, the licensee is proposing an alternative to: (1) the in-process examination requirements of ASME Code,Section III; (2) the flaw acceptance criteria of ASME Code,Section XI; and, (3) certain materials requirements of ASME Code Case N-638-7. The specific details regarding the above are provided in the submittal dated September 23, 2020. Given the short duration of the proposed alternative, the licensee will also not perform rotary peening on the inner diameter of the repaired nozzles.
3.7.1 Deviations from ASME Code,Section III The use of the construction code for several aspects of repairs and replacement activities is required by ASME Code,Section XI. The licensee requested relief from the ASME Code,Section III, Article NB-5000 so that potential anomalies at the triple point location may remain in service. ASME Code,Section III, subparagraph N--5331(b), prohibits the existence of indications that are characterized as cracks, lack of fusion, or incomplete penetration regardless of length. As an alternative to subparagraph NB-5331(b), the licensee analyzed a postulated crack-like anomaly at the triple point in accordance with the ASME Code,Section XI, sub article IWB-3600, to justify operating with the anomaly left in service. The results of the licensees analyses demonstrate that a postulated 0.10-inch weld anomaly is acceptable for 27 years. The NRC staff finds that the licensee has adequately demonstrated by analysis and by mockup testing that the triple point weld anomaly is acceptable to remain in service without affecting structural integrity of the repaired nozzle and agrees with the licensees analysis.
ASME Code,Section III, 2001 Edition including Addenda through 2003, Paragraph NB-5245, specifies progressive surface examination of partial-penetration welds. The licensee opted to instead perform an ultrasonic volumetric examination of the modified configuration described in ASME Code Case N-638-7. In addition to the UT [ultrasonic testing] examinations, a surface PT [penetrant testing] examination was performed on the entire weld. The NRC staff find that this alternative combination of UT and PT examinations is at least as effective as the required progressive PT examinations and is acceptable.
3.7.2 Deviations from ASME Code,Section XI ASME Code,Section XI, Subsection IWA-3300 specifies requirements for characterization of flaws detected by inservice examination. Subsubsection IWB-3420 states, Each detected flaw or group of flaws shall be characterized by the rules of subarticle IWA-3300 to establish the dimensions of the flaws. These dimensions shall be used in conjunction with the acceptance standards of subarticle IWB-3500. IWB-3132.3 states, A component whose volumetric or surface examination detects flaws that exceed the acceptance standards of Table IWB-3410-1 is acceptable for continued service without a repair/replacement activity if an analytical evaluation, as described in subarticle IWB-3600, meets the acceptance criteria of subarticle IWB-3600. The area containing the flaw shall be subsequently reexamined in accordance with IWB-2420(b) and (c).
In a typical half-nozzle repair the exposed surface undergoes a surface stress improvement via peening. With stress improvement a half-nozzle repair can be expected to last for decades. As this proposed alternative only covers one operating cycle, peening was not performed. Lack of peening reduces the expected lifetime of the repair. A typical flaw analysis for a nickel-alloy weld is to perform a PWSCC growth calculation assuming an initial flaw too small for nondestructive analysis to detect is present. This flaw is sized at 10 percent of the thickness of the component with a variety of aspect ratios. The licensee performed a flaw analysis, which is
detailed in their submittal, and found that the life expectancy of the repair to be 21.8 full power months, or 1.8 years. The proposed alternative covers a period of 20 months.
The NRC staff performed independent flaw evaluations in the roll-expanded region and near the repair weld. Using conservative assumptions, the NRC flaw analyses found that any undetected flaws would reach 75 percent through-wall in depth in times ranging from 22 months to 84 months, depending on the flaw location and flaw aspect ratios. Any possible leakage from these postulated flaws would occur several months later. The NRC has confirmed that the licensees proposed repair method supports 20 months of operation.
3.7.3 Deviations from ASME Code Case N-638-7 Paragraph 1(a) of Code Case N-638-7 prohibits the use of the code case to repair SA-302, Grade B material unless the material has been modified to include 0.4 percent to 1.0 percent nickel, quenching and tempering, and application of fine grain practice. The use of SA-302 Grade B material, modified to include 0.4 percent to 1.0 percent nickel, was originally permitted by ASME Code via ASME Code Case 1339. However, quenching and tempering and fine grain practice was not a requirement of this code case. SA-302 Grade B material specification called for a heat treatment of normalized with or without accelerated cooling. The RVCH is SA-302 Grade B and the licensee stated that the Certified Material Test Reports show that the materials used have been modified to include 0.4 percent to 1.0 percent nickel and have been quenched and tempered. However, there is no conclusive evidence that fine grain practice was used.
The ambient temperature temper bead welding method involves the formation of martensite in the heat affected zone which is tempered by subsequent weld layers. Qualification of the welding procedure in accordance with Code Case N-638-7 ensures that the welding variables used during field weld repairs produce martensite in the HAZ which is later transformed to tempered martensite by subsequent weld passes. There is no technical reason that would prevent the successful application of temper bead welding on SA-302 Grade B modified material that was not manufactured with the application of fine grain practice. In addition, nozzles previously repaired by the licensee have received a UT examination every refueling outage, since their installation in 2004, without the detection of any RVCH base material flaws.
The NRC staff therefore finds that proposed alternative to Paragraph 1(a) acceptable.
Additionally, the licensee performed an analysis of loose parts from the degraded J-groove weld and corrosion of the bore of the RVCH penetration which will be exposed to primary reactor coolant. These evaluations address the safety concerns which could be raised by the licensees proposed alternatives to ASME Code requirements and help to provide reasonable assurance that the proposed repair will provide for protection of public health and safety.
Reasonable assurance of the materials properties is provided by the testing requirements in ASME Code Case N-638-7. If any leakage does occur during operation the licensee has leakage monitoring and radiation air monitoring that would detect significant leakage through the repaired nozzles. The NRC finds the licensees proposed alternative and supporting analyses to be acceptable for the proposed 20-month duration.
3.7.4 Technical Evaluation Summary Based on the above evaluation, the NRC staff finds that the licensees proposed alternative meets the requirements for authorization under 10 CFR 50.55a(z)(1) and provides reasonable assurance of structural integrity of the RVCH and repaired nozzle numbers 17 and 34 at PNP will be maintained for the next operating cycle, not to exceed 20 months of operation, or May 31, 2022, when the PNP will permanently cease power operations.
4.0 CONCLUSION
As set forth above, the NRC staff finds that the proposed alternative described in RR 5-8 provides an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all the regulatory requirements set forth in 10 CFR 50.55a(z)(1). Therefore, the NRC staff authorizes the proposed alternative in RR 5-8, for the next operating cycle, not to exceed 20 months of operation, or May 31, 2022, when the PNP will permanently cease power operations.
All other ASME Code requirements for which relief was not specifically requested and approved in the subject requests for relief remain applicable.
Principal Contributor: S. Cumblidge Date: January 19, 2021