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MONTHYEARML0822102102008-08-19019 August 2008 Supplemental Information Needed for Acceptance Requested Licensing Action Relief Request and Supporting Amendment to Extend Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examination Project stage: Other 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 Project stage: Acceptance Review ML0902204422009-02-11011 February 2009 Issuance of Amendment Change to In-Service Inspection Interval. Project stage: Approval 2008-09-19
[Table View] |
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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:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23236A0042023-12-27027 December 2023 Issuance of Amendment 274 Re Changes to Perm Defueled Emergency Plan and Perm Defueled Emergency Action Level Scheme ML22173A1762022-06-28028 June 2022 Enclosure 2 - Holtec Palisades, LLC and Holtec Decommissioning International, LLC - Palisades Nuclear Plant Amendment to Renewed Facility Operating License ML22173A1752022-06-28028 June 2022 Enclosure 1 - Holtec Palisades, LLC and Holtec Decommissioning International, LLC - Big Rock Point Plant Amendment to Facility Operating License ML22039A1982022-05-13013 May 2022 Issuance of Amendment No. 272 Permanently Defueled Technical Specifications 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) 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 ML19317D8552019-12-30030 December 2019 Issuance of Amendment No. 271 Regarding Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B 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) ML19107A0532019-05-13013 May 2019 Issuance of Amendment No. 268 Regarding Revision to Diesel Generator Undervoltage Start Surveillance Requirement PNP 2019-004, License Amendment Request Resubmittal to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b2019-03-28028 March 2019 License Amendment Request Resubmittal to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b ML18346A2872018-12-12012 December 2018 Appendix a to Provisional Operating License DPR-20, Technical Specifications for the Palisades Plant, Consumers Power Company, Docket No 50-255 PNP 2018-052, Supplement to License Amendment Request -Application to Revise Technical Specifications to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force.2018-11-16016 November 2018 Supplement to License Amendment Request -Application to Revise Technical Specifications to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force. 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) ML18114A4102018-06-0404 June 2018 Issuance of Amendment Regarding Administrative Controls for Permanently Defueled Condition (CAC No. MG0021; EPID L-2017-LLA-0266) 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) ML17128A4462017-06-21021 June 2017 Correction to License Amendment No. 235 to Correct an Error Introduced During Issuance of Renewed Facility Operating License 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 ML16078A0682016-05-0202 May 2016 Issuance of Amendment Cyber Security Plan Implementation Schedule ML15209A7912015-11-23023 November 2015 Issuance of Amendment License Amendment Request to Implement 10 CFR 50.61a, Alternative Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events ML15106A6822015-11-23023 November 2015 Issuance of Amendment License Amendment Request for Approval of Palisades Nuclear Plant 10 CFR 50 Appendix G Equivalent Margins Analysis 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) 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 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 ML12279A1572012-12-0505 December 2012 Issuance of Amendment Revised Cyber Security Plan Implementation Schedule Milestone 6 ML1207400812012-04-23023 April 2012 Issuance of Amendment to Extend the Containment Type a Leak Rate Test Frequency to 15 Years ML11362A4682012-01-27027 January 2012 License Amendment, Issuance of Amendment No. 246 to Revise TS Sections 3.7.16 and 4.3 Regarding Fuel Storage Criticality ML1134803032012-01-19019 January 2012 Issuance of Amendment Primary Coolant System Pressure-Temperature Limits ML1132203702012-01-19019 January 2012 Issuance of Amendment Revise Calculated Peak Containment Internal Pressure ML1118012432011-07-28028 July 2011 Issuance of Amendment Regarding Cyber Security Plan ML1115701362011-07-26026 July 2011 License Amendment, Emergency Diesel Generator Fuel Oil and Lube Oil Systems ML1101005992011-01-25025 January 2011 Issuance of Amendment Change to License Section 2.E ML1020901372010-08-23023 August 2010 License Amendment, Issuance of Amendment One-time Extension to the Integrated Leak Rate Test Interval ML1013805342010-06-0202 June 2010 License Amendment, Issuance of Emergency Amendment Control Rod Drive Exercise Surveillance ML0902204422009-02-11011 February 2009 Issuance of Amendment Change to In-Service Inspection Interval. ML0901602382009-02-0606 February 2009 Issuance of Amendment Spent Fuel Pool Region I Storage Requirements ML0833700592008-12-19019 December 2008 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Hearing ML0829100562008-12-12012 December 2008 Issuance of Amendment Request to Support Use of M5 Alloy ML0827404452008-11-20020 November 2008 Issuance of Amendment Eliminate License Condition 2.F ML0725500572007-10-0404 October 2007 Issuance of Amendment 228 Proposal to Revise Containment Sump Surveillance Requirement to Verify Strainer Integrity ML0725307352007-10-0202 October 2007 License Amendment, Issuance of Amendment Replacement of Containment Sump Buffer (Tac No. MD5893) ML0724706672007-09-28028 September 2007 License Amendment, Implemented Alternative Radiological Source Term ML0721800242007-08-0909 August 2007 Revised Pages of Renewed Facility Operating License No. DPR-20 2023-12-27
[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
[Table view] |
Text
\-<.1'\\ REGU,_ UNITED STATES "V "'{r NUCLEAR REGULATORY COMMISSION
",<1' _~ _> 0""...
WASHINGTON, D.C. 20555*0001
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of "0
~ \-I i
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Y/.~~ ,,0*' February 11, 2009 Vice President, Operations Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530
SUBJECT:
PALISADES PLANT - ISSUANCE OF AMENDMENT RE: CHANGE TO IN SERVICE INSPECTION INTERVAL (TAC NO. MD9266)
Dear Sir or Madam:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 237 to Renewed Facility Operating License No. DPR-20 for the Palisades Plant. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated July 21, 2008 .
The amendment supports a proposed change to the in-service inspection program that is based on topical report WCAP-16168-NP-A, Revision 2, "Risk-Informed Extension of the Reactor Vessel In-Service Inspection Interval. " In the referenced safety evaluation of the topical report ,
the NRC required licensees to amend their licenses to require that the information and analyses requested in Section (e) of the final 10 CFR 50.61 a (or the proposed 10 CFR 50.61 a, given in 72 FR 56275 prior to issuance of the final 10 CFR 50.61 a) be submitted for NRC staff review and approval within one year of completing the required reactor vessel weld inspection. Entergy Nuclear Operations, Inc., added a new license condition to provide this information.
A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Comm ission's biweekly Federal Register notice .
Sincerely, Mahesh L. Chawla , Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-255
Enclosures:
- 1. Amendment No. 237 to DPR-20
- 2. Safety Evaluation cc w/encls : Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-255 PALISADES PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 237 License No. DPR-20
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Entergy Nuclear Operations, Inc. (the licensee),
dated July 21, 2008, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application , the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
-2
- 2. Accordingly, the license is amended by adding new license condition 2.C.(8) to the operating license of Renewed Facility Operating License No. DPR-20 as indicated in the attachment to this license amendment, as follows:
(8) Upon implementation of Amendment 237 ,within one year: of completing each of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Category B-A and B-D reactor vessel weld inspections, submit information and analyses requested in Section (e) of the final 10 CFR 50.61a (or the proposed 10 CFR 50.61a, given in 72 FR 56275 prior to issuance of the final 10 CFR 50.61a) to the NRC.
- 3. This license amendment is effective as of the date of issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Lois M. James, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License Date of Issuance: February 11, 2009
ATTACHIV1EI\JT TO LICENSE AMENDMENT NO. 237 RENEWED FACILITY OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 Replace the following page of the Renewed Facility Operating License No. DPR-20 with the attached revised page. The changed area is identified by a marginal line.
REMOVE INSERT Page 3 Page 3 Add the following page of the Appendix C Additional Conditions. The page contains marginal line indicating the change.
REMOVE INSERT NA Operating License, Page 5b
-3 (1) Pursuant to Section 104b of the Act, as amended, and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," (a) ENP to possess and use, and (b) ENO to possess, use and operate, the facility as a utilization facility at the designated location in Van Buren County, Michigan, in accordance with the procedures and limitation set forth in this license; (2) ENO, pursuant to the Act and 10 CFR Parts 40 and 70, to receive, possess, and use source and special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended; (3) ENO, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use byproduct, source, and special nuclear material as sealed sources for reactor startup, reactor instrumentation, radiation monitoring equipment calibration, and fission detectors in amounts as required ;
(4) ENO, pursuant to the Act and 10 CFR Parts 30,40, and 70, to receive , possess, and use in amounts as required any byproduct, source, or special nuclear material for sample analysis or instrument calibration, or associated with radioactive apparatus or components; and (5) ENO, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess , but not separate, such byproduct and special nuclear materials as may be produced by the operations of the facility.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations in 10 CFR Chapter I and is subject to all applicable provisions of the Act; to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) ENO is authorized to operate the facility at steady-state reactor core power levels not in excess of 2565.4 Megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2) The Technical Specifications contained in Appendix A, as revised through Amendment No.237, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. ENO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) ENO shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SERs dated 09/01/78, 03/19/80 , 02/10/81, OS/26/83, 07/12/85, 01/29/86, 12/03/87, and 05/19/89 and subject to the following provisions:
Renewed License No. DPR-20 Amendment No. 237
5b (8) Upon implementation of Amendment 237, within one year of completing each of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Category B-A and B-D reactor vessel weld inspections, submit information and analyses requested in Section (e) of the final 10 CFR 50.61 a (or the proposed 10 CFR 50.61 a, given in 72 FR 56275 prior to issuance of the final 10 CFR 50.61a) to the NRC.
Renewed License No. DPR-20 Amendment No. 237
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 237 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-20 ENTERGY NUCLEAR OPERATIONS, INC.
PALISADES PLANT DOCKET NO. 50-255
1.0 INTRODUCTION
By letter dated July 21,2008 (Reference 3), the Entergy Nuclear Operations. Inc. (the licensee),
submitted a request for changes to the Palisades Nuclear Plant (PNP , Palisades) operating license. The requested changes would introduce a new license conditions that will require the licensee to submit information and analyses requested in Section (e) of the final 10 CFR 50.61 a (or the proposed 10 CFR 50 .61a, given in 72 FR 56275 prior to issuance of the final 10 CFR 50.61a) to the Nuclear Regulatory Commission (NRC), within one year of completing each of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),
Section XI, Category B-A and B-D reactor vessel weld inspections.
2.0 REGULATORY EVALUATION
This amendment request is a required part of a code relief request submitted to extend the Palisades reactor vessel (RV) Inservice Inspection (lSI) 10-year inspection interval. Reference 4 provides the requirements a station must meet in order for the NRC to approve such an alternative to Section XI of the ASME Code. This amendment request meets the requirement, listed in Section 3.4 of Reference 5, that the licensee will submit identified information and analyses to the NRC.
The proposed change, to report results from RV examinations required by Section XI of the ASME code, is being submitted in support of demonstrating Palisades's ability to justify extending its RV lSI interval frequency.
3.0 TECHNICAL EVALUATION
This letter requests an amendment to Renewed Operating License DPR-20 for Palisades. The proposed change will insert into the operating license a requirement involving the reporting of specified RV lSI information and analyses as specified in Reference 1. This amendment request is a required element of a code relief request (Reference 2) to extend the RV lSI 10-year inspection interval. The code relief request is based on the analysis contained within Reference 4. The methodology in Reference 4 was evaluated by the NRC, in Reference 5, as Enclosure
-2 being acceptable for referencing in license amendment requests. Reference 5 requires that licensees desiring to extend the frequency of the RV lSI interval, which do not implement 10 CFR 50.61 a, must amend their licenses to require the submittal of information and analyses requested in paragraph (e) of the final 10 CFR 50.61a [or the proposed 10 CFR 50.61a , as listed in Reference 1 prior to the issuance of the final 10 CFR 50.61a]. Currently, the licensee has not implemented 10 CFR 50.61 a because the final rule has not yet been approved . Therefore, in accordance with Reference 3, the licensee is requesting to amend the license as described below.
The licensee proposed to add new paragraph (8) to Section 2.C of the operating license to read as follows:
(8) Upon implementation of Amendment 237, within one year of completing each of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Category B-A and B-D reactor vessel weld inspections, submit information and analyses requested in Section (e) of the final 10 CFR 50.61a (or the proposed 10 CFR 50.61a, given in 72 FR 56275 prior to issuance of the final 10 CFR 50.61a) to the NRC.
This proposed change implements the requirement to submit a license amendment request at the time of submitting a relief request as specified in Reference 5. The relief request to extend the RV lSI interval is separate from this license change and is being reviewed separately.
The proposed change is administrative in nature because it adds a reporting requirement to the operating license. The justification for the information requested, and the scope and frequency of the lSI examinations is given in Reference 2. This proposed amendment only addresses the reporting of results following the described lSI examination. Submittal of the data required by 10 CFR 50.61 a is necessary to demonstrate the RV maintains its ability to meet code fracture toughness requirements and is used to justify continued use of the approved code relief request for an extended RV lSI interval. Since the proposed change involves only a requirement for the submittal of information, it clearly does not have any impact on the operation of the plant or any design basis accident, is not related to a margin of safety, and is acceptable to the NRC staff.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Michigan State official was notified of the proposed issuance of the amendment. The Michigan State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment relates to changes in record keeping , reporting, or administrative procedures or requirements. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (73 FR 65690). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
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6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
- 1. Federal Register Notice (72 FR 56275), dated October 3, 2007, Alternative Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events.
- 2. Letter from ENO to NRC, dated July 21, 2008 - Request for Authorization to Extend the Third 1O-Year Inservice Inspection Interval for Reactor Vessel Weld Examination (ADAMS Accession No. ML082040342).
- 3. Letter from ENO to NRC, dated July 21,2008 - License Amendment Request for License Condition to Support Implementation of Extended In-Service Inspection Interval (ADAMS Accession No. ML082030796).
- 4. WCAP-16168-NP, Revision 2, dated June 2008, Risk-Informed Extension of the Reactor Vessel In-Service Inspection Interval.
- 5. Letter from H. K. l'Jieh (NRC) to G. Bischoff (PWROG), dated May 8,2008, Final Safety Evaluation for Pressurized Water Reactor Owners Group (PWROG) Topical Report (TR)
WCAP-16168-NP, Revision 2, "Risk-Informed Extension of the Reactor Vessel In Service Inspection Interval" (TAC No. MC9768) (ADAMS Accession No. ML081060045)
Principal Contributor: Mahesh Chawla, NRR Date: February 11, 2009
ML090220442 OFFICE LPL3-1/PM LPL3-1/LA CVIB/BC OGC LPL3-1/BC NAME MChawla BTully MMitcheli BMizuno LJames DATE 01/29/09 01/29/09 02/15/09 02/04/09 02/11/09