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Category:Letter type:PNP
MONTHYEARPNP 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 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 2023-025, 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 2023-023, Special Report High Range Noble Gas Monitor Inoperable2023-08-0909 August 2023 Special Report High Range Noble Gas Monitor Inoperable PNP 2023-018, 2022 Annual Non-Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Non-Radiological Environmental Operating Report 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 PNP 2023-002, 6 to Updated Final Safety Analysis Report2023-03-31031 March 2023 6 to Updated Final Safety Analysis Report 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 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 PNP 2022-037, Report of Changes to Security Plan, Revision 192022-12-14014 December 2022 Report of Changes to Security Plan, Revision 19 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 2022-026, 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 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 2022-031, License Amendment Request, Revise License Condition to Eliminate Cyber Security Plan Requirements2022-09-14014 September 2022 License Amendment Request, Revise License Condition to Eliminate Cyber Security Plan Requirements PNP 2022-025, Report of Changes to Palisades Nuclear Plant Security Plan, Revision 182022-09-12012 September 2022 Report of Changes to Palisades Nuclear Plant Security Plan, Revision 18 PNP 2022-032, 2022 Evacuation Time Estimate Report2022-09-0707 September 2022 2022 Evacuation Time Estimate Report PNP 2022-023, Report of Changes to Palisades Nuclear Plant Security Plan, Revision 172022-08-15015 August 2022 Report of Changes to Palisades Nuclear Plant Security Plan, Revision 17 PNP 2022-014, Report of Changes to Palisades Nuclear Plant Site Emergency Plan, Revision 342022-07-13013 July 2022 Report of Changes to Palisades Nuclear Plant Site Emergency Plan, Revision 34 PNP 2022-016, License Amendment Request: Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-07-12012 July 2022 License Amendment Request: Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-017, Request for Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47(b); 10 CFR 50.47(c)(2); and 10 CFR Part 50, Appendix E2022-07-11011 July 2022 Request for Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47(b); 10 CFR 50.47(c)(2); and 10 CFR Part 50, Appendix E PNP 2022-019, & Big Rock Point - Notification of Expected Date of Transfer of Ownership of Nuclear Plants to Holtec Palisades, LLC; and Notification of Receipt of All Required Regulatory Approvals2022-06-24024 June 2022 & Big Rock Point - Notification of Expected Date of Transfer of Ownership of Nuclear Plants to Holtec Palisades, LLC; and Notification of Receipt of All Required Regulatory Approvals PNP 2022-011, Termination of the Emergency Response Data System (Eros) Link2022-06-13013 June 2022 Termination of the Emergency Response Data System (Eros) Link PNP 2022-010, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2022-06-13013 June 2022 Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel PNP 2022-004, 2021 Radiological Environmental Operating Report2022-05-12012 May 2022 2021 Radiological Environmental Operating Report PNP 2022-003, and Big Pock Point Plant - 2021 Annual Radioactive Effluent Release and Waste Disposal Report2022-04-25025 April 2022 and Big Pock Point Plant - 2021 Annual Radioactive Effluent Release and Waste Disposal Report PNP 2022-007, 2021 Annual Non-Radiological Environmental Operating Report2022-04-21021 April 2022 2021 Annual Non-Radiological Environmental Operating Report PNP 2022-012, Response to Request for Additional Information Regarding License Amendment Request to Revise Facility Operating License and Technical Specifications for a Permanently Defueled Condition2022-04-21021 April 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Facility Operating License and Technical Specifications for a Permanently Defueled Condition PNP 2022-002, Annual Report of Changes in Emergency Core Cooling System Models2022-03-24024 March 2022 Annual Report of Changes in Emergency Core Cooling System Models PNP 2021-012, Report of Changes, Tests and Experiments, and Summary of Commitment Changes2021-10-0707 October 2021 Report of Changes, Tests and Experiments, and Summary of Commitment Changes PNP 2021-029, Pre-Notice of Disbursement from Decommissioning Trust2021-09-0202 September 2021 Pre-Notice of Disbursement from Decommissioning Trust PNP 2021-013, Request for Rescission of Interim Compensatory Measure from Order EA-02-0262021-07-21021 July 2021 Request for Rescission of Interim Compensatory Measure from Order EA-02-026 PNP 2021-020, Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.122021-06-15015 June 2021 Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.12 PNP 2021-005, License Amendment Request to Revise Renewed Facility Operating License and Technical Specifications for Permanently Defueled Condition2021-06-0101 June 2021 License Amendment Request to Revise Renewed Facility Operating License and Technical Specifications for Permanently Defueled Condition PNP 2021-026, Pre-Notice of Disbursement from Decommissioning Trust2021-05-27027 May 2021 Pre-Notice of Disbursement from Decommissioning Trust PNP 2021-016, 2020 Radiological Environmental Operating Report2021-05-12012 May 2021 2020 Radiological Environmental Operating Report PNP 2021-022, 2020 Annual Non-Radiological Environmental Operating Report2021-04-27027 April 2021 2020 Annual Non-Radiological Environmental Operating Report PNP 2021-015, and Big Rock Point, Submittal of 2020 Annual Radioactive Effluent Release and Waste Disposal Report2021-04-21021 April 2021 and Big Rock Point, Submittal of 2020 Annual Radioactive Effluent Release and Waste Disposal Report PNP 2021-017, Schedule Change to Open Phase Condition Detection Implementation2021-04-0101 April 2021 Schedule Change to Open Phase Condition Detection Implementation PNP 2021-003, 2020 Steam Generator Tube Inspection Report2021-03-25025 March 2021 2020 Steam Generator Tube Inspection Report PNP 2021-010, Annual Report of Changes in Emergency Core Cooling System Models2021-03-19019 March 2021 Annual Report of Changes in Emergency Core Cooling System Models PNP 2021-004, Report - Changes to Palisades Nuclear Plant Technical Specifications Bases2021-03-10010 March 2021 Report - Changes to Palisades Nuclear Plant Technical Specifications Bases PNP 2021-006, Pre-Notice of Disbursement from Decommissioning Trust2021-03-0808 March 2021 Pre-Notice of Disbursement from Decommissioning Trust PNP 2021-001, ASME Section XI 90-Day Owner'S Activity Report2021-01-12012 January 2021 ASME Section XI 90-Day Owner'S Activity Report 2023-09-28
[Table view] Category:Report
MONTHYEARPNP 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 ML23087A0392023-05-0202 May 2023 PSDAR Comment Resolution PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023 Regulatory Path to Reauthorize Power Operations CNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021 Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L PNP 2020-039, 10 CFR 71.95 Report Involving 3-608 Cask2020-11-20020 November 2020 10 CFR 71.95 Report Involving 3-608 Cask 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, ML20267A3912020-09-22022 September 2020 Attachment 4, Framatome Document No. 51-9292503-002, Palisades CEDM Nozzle Idtb Repair - Life Assessment Summary PNP 2019-001, Request for Deferral of Actions Related to a Beyond-Design-Basis External Seismic Event2019-03-20020 March 2019 Request for Deferral of Actions Related to a Beyond-Design-Basis External Seismic Event ML18354B1332019-01-17017 January 2019 Staff Assessment of Flood Focused Evaluation ML18330A1432018-11-26026 November 2018 Relief Request Number RR 5-7, Proposed Alternative to ASME Section Xi Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations ML18330A1462018-11-24024 November 2018 Framatome, Document No. 51-9292503, Palisades CRDM & Ici Nozzle Idtb Repair - Life Assessment Summary ML18270A3232018-09-27027 September 2018 Attachment 2: Probabilistic Risk Assessment Technical Adequacy PNP 2018-036, Revised Mitigating Strategies Assessment for Flooding Pursuant to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1: Flooding of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2018-09-25025 September 2018 Revised Mitigating Strategies Assessment for Flooding Pursuant to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1: Flooding of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident PNP 2018-041, Focused Evaluation Pursuant to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1: Flooding of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2018-09-25025 September 2018 Focused Evaluation Pursuant to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1: Flooding of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident PNP 2016-066, Special Report for Inoperability of High Range Noble Gas Monitor2016-12-20020 December 2016 Special Report for Inoperability of High Range Noble Gas Monitor PNP 2016-042, Annual Status Notification in Response to Confirmatory Order, EA-14-0132016-06-16016 June 2016 Annual Status Notification in Response to Confirmatory Order, EA-14-013 ML16048A3442016-02-10010 February 2016 Annual Fatigue Reporting Form 2015 ML15351A3522015-12-16016 December 2015 Attachment 1, Compliance with Order EA-12-049 ML15351A3532015-12-16016 December 2015 Attachment 2, Order EA-12-049 Compliance Elements Summary ML15351A3542015-12-16016 December 2015 Attachment 3, Audit Open Item Responses ML15351A3552015-12-16016 December 2015 Attachment 4, Interim Staff Evaluation Open Item and Confirmation Item Responses ML15351A3622015-12-16016 December 2015 Attachment 6, System Operating Procedure 23, Plant Heating System, Attachment 14, Actions When Outside Temperatures Are Less than 20 Degrees Fahrenheit. ML15351A3602015-12-16016 December 2015 Attachment 5, Final Integrated Plan PNP 2015-066, Submittal of Report on the 8-120B Cask2015-08-20020 August 2015 Submittal of Report on the 8-120B Cask PNP 2015-058, Technical Specification Required Report2015-08-0404 August 2015 Technical Specification Required Report PNP 2015-037, Appendix a, Computer Files Listing, File No. 1200895.306, Revision 12015-05-22022 May 2015 Appendix a, Computer Files Listing, File No. 1200895.306, Revision 1 ML15147A6192015-05-22022 May 2015 Enclosure 2, Corrected Documentation for Relief Request Number RR 4-18 ML15147A6182015-05-22022 May 2015 Appendix a, Computer File Listing, File No. 1400669.323, Revision 0 ML15147A6172015-05-22022 May 2015 Enclosure 1, Relief Request Number RR 4-21 Proposed Alternative, in Accordance with 10 CFR 50.55a(z)(2), Hardship Without a Compensating Increase in Level of Quality and Safety PNP 2015-018, Areva, Inc., 51-9226987-000, Palisades Nuclear Plant Flooding Hazard Re-Evaluation Report.2015-02-25025 February 2015 Areva, Inc., 51-9226987-000, Palisades Nuclear Plant Flooding Hazard Re-Evaluation Report. PNP 2014-108, Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.2014-12-18018 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima. PNP 2014-051, Response to May 1, 2014 Request for Additional Information for License Amendment Request to Revise Emergency Response Organization Staff Augmentation Response Times2014-07-16016 July 2014 Response to May 1, 2014 Request for Additional Information for License Amendment Request to Revise Emergency Response Organization Staff Augmentation Response Times PNP 2014-038, Special Report for Inoperability of High Range Noble Gas Monitor2014-04-14014 April 2014 Special Report for Inoperability of High Range Noble Gas Monitor PNP 2014-033, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from The.2014-03-31031 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from The. ML13365A2642014-02-10010 February 2014 Interim Staff Evaluation Regarding Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14030A2072014-02-0606 February 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Palisades Nuclear Plant, TAC No.: MF0768 PNP 2013-072, Report of Changes, Tests and Experiments and Summary of Commitment Changes2013-10-14014 October 2013 Report of Changes, Tests and Experiments and Summary of Commitment Changes PNP 2013-063, Unsatisfactory Laboratory Testing Report2013-09-18018 September 2013 Unsatisfactory Laboratory Testing Report ML13242A1592013-08-29029 August 2013 Addendum to the Results of Independent Samples Collected by the NRC at Palisades Nuclear Plant Storm Drain Outfall ML13295A4502013-07-31031 July 2013 WCAP-15353-Supplement 2-NP, Rev. 0, Palisades Reactor Pressure Vessel Fluence Evaluation. PNP 2013-046, Updated Palisades Nuclear Plant Reactor Vessel Fluence Evaluation2013-06-25025 June 2013 Updated Palisades Nuclear Plant Reactor Vessel Fluence Evaluation PNP 2013-027, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2013-04-10010 April 2013 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application ML14316A2082013-02-28028 February 2013 Attachment 5 - Westinghouse WCAP-17651-NP, Revision 0, Palisades Nuclear Power Plant Reactor Vessel Equivalent Margins Analysis ML13295A4512013-02-28028 February 2013 WCAP-17651-NP, Rev. 0, Palisades Nuclear Power Plant Reactor Vessel Equivalent Margins Analysis. ML13038A4402013-02-0707 February 2013 BADGER Test Campaign at Palisades Nuclear Plant ML13295A4492013-01-31031 January 2013 WCAP-17403-NP, Rev. 1, Palisades Nuclear Power Plant Extended Beltline Reactor Vessel Integrity Evaluation. ML14316A1992013-01-31031 January 2013 Attachment 3 - Westinghouse WCAP-17403-NP, Revision 1, Palisades Nuclear Power Plant Extended Beltline Reactor Vessel Integrity Evaluation ML12334A0962012-11-27027 November 2012 PLP-RPT-12-00141, Rev. 0, Palisades Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 1 of 3 PNP 2012-101, Flooding Walkdown Report - Response to NRC Request for Information Pursuant to 10CFR50.54(f) the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-27027 November 2012 Flooding Walkdown Report - Response to NRC Request for Information Pursuant to 10CFR50.54(f) the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML12334A0972012-11-27027 November 2012 PLP-RPT-12-0041, Rev. 0, Palisades Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 2 of 3 2023-09-28
[Table view] Category:Miscellaneous
MONTHYEARML23087A0392023-05-0202 May 2023 PSDAR Comment Resolution PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023 Regulatory Path to Reauthorize Power Operations CNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021 Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L PNP 2019-001, Request for Deferral of Actions Related to a Beyond-Design-Basis External Seismic Event2019-03-20020 March 2019 Request for Deferral of Actions Related to a Beyond-Design-Basis External Seismic Event ML18354B1332019-01-17017 January 2019 Staff Assessment of Flood Focused Evaluation PNP 2016-066, Special Report for Inoperability of High Range Noble Gas Monitor2016-12-20020 December 2016 Special Report for Inoperability of High Range Noble Gas Monitor PNP 2016-042, Annual Status Notification in Response to Confirmatory Order, EA-14-0132016-06-16016 June 2016 Annual Status Notification in Response to Confirmatory Order, EA-14-013 ML16048A3442016-02-10010 February 2016 Annual Fatigue Reporting Form 2015 ML15351A3542015-12-16016 December 2015 Attachment 3, Audit Open Item Responses ML15351A3622015-12-16016 December 2015 Attachment 6, System Operating Procedure 23, Plant Heating System, Attachment 14, Actions When Outside Temperatures Are Less than 20 Degrees Fahrenheit. ML15351A3602015-12-16016 December 2015 Attachment 5, Final Integrated Plan ML15351A3552015-12-16016 December 2015 Attachment 4, Interim Staff Evaluation Open Item and Confirmation Item Responses ML15351A3522015-12-16016 December 2015 Attachment 1, Compliance with Order EA-12-049 ML15351A3532015-12-16016 December 2015 Attachment 2, Order EA-12-049 Compliance Elements Summary PNP 2015-066, Submittal of Report on the 8-120B Cask2015-08-20020 August 2015 Submittal of Report on the 8-120B Cask ML15147A6192015-05-22022 May 2015 Enclosure 2, Corrected Documentation for Relief Request Number RR 4-18 ML15147A6182015-05-22022 May 2015 Appendix a, Computer File Listing, File No. 1400669.323, Revision 0 ML15147A6172015-05-22022 May 2015 Enclosure 1, Relief Request Number RR 4-21 Proposed Alternative, in Accordance with 10 CFR 50.55a(z)(2), Hardship Without a Compensating Increase in Level of Quality and Safety PNP 2015-037, Appendix a, Computer Files Listing, File No. 1200895.306, Revision 12015-05-22022 May 2015 Appendix a, Computer Files Listing, File No. 1200895.306, Revision 1 PNP 2014-033, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from The.2014-03-31031 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from The. PNP 2013-072, Report of Changes, Tests and Experiments and Summary of Commitment Changes2013-10-14014 October 2013 Report of Changes, Tests and Experiments and Summary of Commitment Changes PNP 2013-063, Unsatisfactory Laboratory Testing Report2013-09-18018 September 2013 Unsatisfactory Laboratory Testing Report PNP 2013-046, Updated Palisades Nuclear Plant Reactor Vessel Fluence Evaluation2013-06-25025 June 2013 Updated Palisades Nuclear Plant Reactor Vessel Fluence Evaluation PNP 2013-027, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2013-04-10010 April 2013 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application PNP 2012-101, Flooding Walkdown Report - Response to NRC Request for Information Pursuant to 10CFR50.54(f) the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-27027 November 2012 Flooding Walkdown Report - Response to NRC Request for Information Pursuant to 10CFR50.54(f) the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML12334A0962012-11-27027 November 2012 PLP-RPT-12-00141, Rev. 0, Palisades Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 1 of 3 ML12334A0972012-11-27027 November 2012 PLP-RPT-12-0041, Rev. 0, Palisades Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 2 of 3 PNP 2012-102, PLP-RPT-12-0041, Rev. 0, Palisades Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 3 of 32012-11-27027 November 2012 PLP-RPT-12-0041, Rev. 0, Palisades Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 3 of 3 PNP 2012-094, 2012 Steam Generator Tube Inspection Report2012-11-0101 November 2012 2012 Steam Generator Tube Inspection Report PNP 2012-059, 60-Day Reports Per Bulletin 2004-01 and CAL No NRR-07-023 Pressurizer Inspection Results for the 2012 Refueling Outage2012-07-11011 July 2012 60-Day Reports Per Bulletin 2004-01 and CAL No NRR-07-023 Pressurizer Inspection Results for the 2012 Refueling Outage IR 05000255/20110192012-02-14014 February 2012 Final Significance Determination of Yellow and White Findings with Assessment Followup and Notice of Violation NRC Inspection Report Nos. 05000255-11-019 and 05000255-11-020 Palisades Nuclear Plant ML12023A1872012-01-17017 January 2012 EA-PSA-SDP-D11-2-11-07, Rev. 2, SDP Assessment of DC Panel D11-2 Fault, Cover Through Appendix a ML12023A1882012-01-17017 January 2012 EA-PSA-SDP-D11-2-11-07, Rev. 2, SDP Assessment of DC Panel D11-2 Fault, Appendix B Through End ML12006A0712012-01-0505 January 2012 SDP Assessment of DC Panel D-11-2 Fault Palisades ML1134205122011-12-19019 December 2011 Review of the 2010 Steam Generator Tube Inspections During Refueling Outage 21 ML12006A0722011-10-17017 October 2011 Plant Trip During D-11-2 Maintenance Root Cause ML1128705702011-10-14014 October 2011 Report of Changes, Tests and Experiments and Summary of Commitment Changes ML12006A0672011-09-28028 September 2011 SDP Assessment of Service Water Pump P-7C Coupling Failures Part 3 ML1031603372010-11-0909 November 2010 Unsatisfactory Laboratory Testing Report ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1020301642010-04-28028 April 2010 E-Mail. from Dotson to Cassidy, GZA 2007 Report ML0929505252009-10-22022 October 2009 Generator Tube Inspection Report ML0928903362009-10-15015 October 2009 Report of Facility Changes, Tests and Experiments and Summary of Commitment Changes ML0901402872008-07-16016 July 2008 E-mail from Ellegood to M. Chawla Et Al. Palisades SFP Racks with Attachment: Report on Resolution of Outstanding Concerns on Spent Fuel Pit Rack Localized Swelling Palisades Nuclear Plant ML0810000792008-04-0808 April 2008 Request for Enforcement Discretion - Technical Specification 3.8.1 Required Actions F.1 and F.2 ML0717802162007-06-19019 June 2007 Revised Steam Generator Tube Integrity Assessment from the 2006 Refueling Outage ML0719400912006-09-15015 September 2006 Request for Relief from ASME Section Xl Code Requirements for Repair of Pressurizer Nozzle Penetrations (Non-Proprietary) ML0619803382006-07-20020 July 2006 Review of the 2004 Steam Generator Tube Inspection Reports ML0617301112006-06-21021 June 2006 Day Report Per First Revised Order EA-03-009 ML0608203512006-03-20020 March 2006 License Amendment Request: Removal of TSP from Palisades Containment 2023-05-02
[Table view] |
Text
Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant Iiterf bY 27780 Blue Star Memorial Highway Covert, Ml 49043-9530 Tel 269 764 2000 Anthony J. Vitale Site Vice President PNP 2013-046 June 25, 2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Updated Palisades Nuclear Plant Reactor Vessel Fluence Evaluation Palisades Nuclear Plant Docket 50-255 License No. DPR-20
References:
- 1. Entergy Nuclear Operations, Inc. letter, Updated Palisades Reactor Vessel Pressurized Thermal Shock Evaluation, dated December 20, 2010 (ADAMS Accession No. ML110060692)
- 2. NRC letter, Updated Reactor Pressure Vessel Pressurized Thermal Shock Evaluation for Palisades Nuclear Plant (TAC No.
ME5263), dated December 7, 2011 (ADAMS Accession No. ML112870050)
Dear Sir or Madam:
As documented in Reference 1, Entergy Nuclear Operations, Inc. (ENO) submitted an updated reactor vessel pressurized thermal shock (PTS) evaluation for Palisades Nuclear Plant (PNP). The submittal included an updated reactor vessel fluence evaluation, WCAP-1 5353 Supplement I NP, Revision 0, Palisades Reactor Pressure Vessel Fluence Evaluation, that calculated fluence based on actual plant operation through Cycle 20 and the finalized design for Cycle 21, with future fluence based on planned future operations. Using data from the fluence calculation, the PTS evaluation concluded that the PNP reactor vessel would not reach the 10 CFR 50.61 PTS screening criteria limit until April2017, during Cycle 26.
In Reference 2, the Nuclear Regulatory Commission (NRC) concluded that the updated PNP PTS evaluation was in accordance with 10 CFR 50.61 and that the PTS screening criteria limit would not be reached until April 2017.
PNP 2013-046 Page 2 ENO has re-calculated PNP reactor vessel fluence, based on actual reactor operation through Cycle 22, and future fluence based on planned operations through Cycle 26.
This is documented in the attached Palisades Reactor Pressure Vessel Fluence Evaluation, WCAP-1 5353 Supplement 3 NP, Revision 0. The evaluation concludes that the PNP reactor vessel would not reach the 10 CFR 50.61 PTS screening criteria limit until August 2017.
The attachment contains no proprietary information.
This letter identifies no new commitments and no revisions to existing commitments.
ENO requests that, by December 31, 2013, the NRC complete review and approval of the attached fluence evaluation, and endorse the new date at which the PNP reactor vessel is estimated to reach the PTS screening criteria limit.
I declare under penalty of perjury that the foregoing is true and correct. Executed on June 25, 2013.
Sincerely, ajv/Jse
Attachment:
- 1. Palisades Reactor Pressure Vessel Fluence Evaluation, WCAP-1 5353 Supplement 3 NP, Revision 0 cc: Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC
ATTACHMENT I PALISADES REACTOR PRESSURE VESSEL FLUENCE EVALUATION WCAP-I 5353 SUPPLEMENT 3 NP REVISION 0 18 pages follow
Westinghouse Non-Proprietary Class 3 WCAP-15353 - Supplement 3 - NP June 2013 Revision 0 Palisades Reactor Pressure Vessel Fluence Evaluation
Westinghouse Non-Proprietary Class 3 WCAP-15353 - Supplement 3 - NP, Revision 0 Palisades Reactor Pressure Vessel Fluence Evaluation Stanwood L. Anderson*, Fellow Engineer Radiation Engineering & Analysis June 2013 Reviewed:
Benjamin W. Amiri*, Senior Engineer Radiation Engineering & Analysis Approved:
Laurent P. Houssay*, Acting Manager Radiation Engineering & Analysis Work Performed Under Shop Order 450 Sales Order No. 94483 Prepared by Westinghouse for Entergy Nuclear Operations Inc WESTINGHOUSE ELECTRIC COMPANY LLC 1000 Westinghouse Drive Cranberry Township, PA 16066
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Westinghouse Non-Proprietary Class 3 EXECUTIVE
SUMMARY
In early 2000, WCAP-15353, Revision 0[1] describing the methodology used in the fluence evaluations for the Palisades plant was submitted to the NRC staff for review. Following that review and a further exchange of information documented in Reference 2, the methodology described in WCAP-15353, Revision 0 was approved for application to the Palisades reactor pressure vessel[3]. Subsequent to that approval, additional submittals[4,5] in support of the benchmarking of this fluence methodology were reviewed and approved by the NRC Staff as being in compliance with the requirements of Regulatory Guide 1.190[6].
The fluence analysis described in WCAP-15353, Revision 0[1] included cycle-specific evaluations through fuel Cycle 14 (the then-current operating cycle). In mid 2010, Supplement 1 to WCAP-15353, Revision 0[10] was issued to provide an updated neutron fluence assessment for the Palisades pressure vessel that included cycle-specific analysis for additional operating cycles for which the design had been finalized (Cycles 15 through 21). Supplement 1 included fluence projections for future operation through approximately 44 effective full power years (EFPY). The results of the evaluation documented in Supplement 1 were used as input to vessel materials studies that included updates to surveillance capsule credibility analysis, material chemistry factor determination, Pressurized Thermal Shock (PTS) evaluation, and generation of Pressure-Temperature (PT) limit curves.
In December of 2010, Entergy Nuclear Operations Inc submitted a request to revise the Palisades PTS evaluation to include new information on surveillance data for the limiting RPV welds (axial welds) fabricated with weld wire heat number W5214 (Weld W5214). Neutron fluence data documented in Supplement 1 to WCAP-15353, Revision 0[10] were used in support of this submittal. In December of 2011, the request for the revised PTS evaluation was approved by the USNRC Staff[14] and a limiting fluence of 1.685e19 n/cm2 (E > 1.0 MeV) was established for Weld W5214. Based on the fluence projections provided in Supplement 1 to WCAP-15353, Revision 0[10] the limiting fluence was expected to be reached in April 2017.
In this supplement, the neutron fluence accrued by Weld W5214 during cycles 21 through 26 has been re-evaluated based on actual fuel cycle designs, fuel cycle lengths, and refueling outage schedules. The result of that re-evaluation is a movement in the date at which the fluence limit (1.685e19 n/cm2) for Weld W5214 corresponding to the PTS screening criterion of 270° F is anticipated to be reached from April 2017 to August 2017.
WCAP-15353 - Supplement 3 - NP, Revision 0 June 2013
Westinghouse Non-Proprietary Class 3 i TABLE OF CONTENTS Page TABLE OF CONTENTS i LIST OF TABLES ii LIST OF FIGURES iii
1.0 INTRODUCTION
1-1 2.0 NEUTRON TRANSPORT CALCULATIONS 2-1 2.1 Method of Analysis 2-1 2.2 PTS Limit Re-Evaluation 2-5
3.0 REFERENCES
3-1 WCAP-15353 - Supplement 3 - NP, Revision 0 June 2013
Westinghouse Non-Proprietary Class 3 ii LIST OF TABLES Table Title Page 2.2-1 Comparison of Fast Neutron Flux Values and Fuel Cycle Lengths used in 2-6 the PTS Limit Analysis - Weld W5214 2.2-2 Comparison of Fast Neutron Fluence Accrued at the Conclusion of 2-7 Cycles 21 through 26 - Weld W5214 2.2-3 Fast Neutron Fluence Accumulation as a Function of Irradiation Time 2-8 During Cycle 26 - Weld W5214 WCAP-15353 - Supplement 3 - NP, Revision 0 June 2013
Westinghouse Non-Proprietary Class 3 iii LIST OF FIGURES Figure Title Page 2.1-1 Palisades r, Reactor Geometry 2-3 2.1-2 Palisades r,z Reactor Geometry 2-4 WCAP-15353 - Supplement 3 - NP, Revision 0 June 2013
Westinghouse Non-Proprietary Class 3 1-1 SECTION
1.0 INTRODUCTION
In the assessment of the state of embrittlement of light water reactor (LWR) pressure vessels, an accurate evaluation of the neutron exposure of each of the materials comprising the beltline region of the vessel is required. In Section II F of 10 CFR 50[7] Appendix G, the beltline region is defined as:
the region of the rea ctor vessel shell m aterial (including welds, heat affected zones, and plates or forgings) that directly sur rounds the effective height of the reactor cor e and adja cent region s of the re actor vesse l that are predicted to experience sufficient neutron radiation damage to be considered in the selection of the most limiting material with regard to radiation damage.
Each of the materials that is anticipated to experience a neutron exposure that exceeds this fluence threshold must be considered in the overall embrittlement assessments for the pressure vessel.
Regulatory Guide 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence [6], describes state-of-the-art calculation and measurement procedures that are acceptable to the NRC staff for determining pressure vessel fluence. Also included in Regulatory Guide 1.190 is a discussion of the steps required to qualify and validate the methodology used to determine the neutron exposure of the pressure vessel wall.
In early 2000, WCAP-15353, Revision 0[1] describing the methodology used in the fluence evaluations for the Palisades plant was submitted to the NRC staff for review. Following that review and a further exchange of information documented in Reference 2, the methodology described in WCAP-15353, Revision 0 was approved for application to the Palisades reactor pressure vessel (RPV)[3]. Subsequent to that approval additional submittals[4,5] in support of the benchmarking of this fluence methodology were reviewed and approved by the NRC Staff as being in compliance with the requirements of Regulatory Guide 1.190[6].
The fluence analysis described in WCAP-15353, Revision 0[1] included cycle-specific evaluations through fuel Cycle 14 (the then-current operating cycle). In mid 2010, Supplement 1 to WCAP-15353, Revision 0[10] was issued to provide an updated neutron fluence assessment for the Palisades pressure vessel that included cycle-specific analysis for additional operating cycles for which the design had been finalized (Cycles 15 through 21). At that time, Cycle 21 was in operation, but not completed.
WCAP-15353 - Supplement 3 - NP, Revision 0 June 2013
Westinghouse Non-Proprietary Class 3 1-2 Supplement 1 to WCAP-15353, Revision 0[10] included fluence projections for future operation through approximately 44 effective full power years (EFPY). The results of the evaluation documented in Supplement 1 were used as input to vessel materials studies that included updates to surveillance capsule credibility analysis, material chemistry factor determination, Pressurized Thermal Shock (PTS) evaluation, and generation of Pressure-Temperature (PT) limit curves.
In December of 2010, Entergy Nuclear Operations Inc submitted a request to revise the Palisades PTS evaluation to include new information on surveillance data for the limiting RPV welds (axial welds 2-112A/C & 3-112A/C) fabricated with weld wire heat number W5214 (Weld W5214). Neutron fluence data documented in Supplement 1 to WCAP-15353, Revision 0[10]
were used in support of this submittal. In December of 2011, the request for the revised PTS evaluation was approved by the USNRC Staff[14] and a limiting fluence of 1.685e19 n/cm2 (E > 1.0 MeV) was established for Weld W5214 corresponding to when the PTS screening criterion of 270° F would be reached. Based on the fluence data provided in Supplement 1 to WCAP-15353, Revision 0[10] the limiting fluence was expected to be reached in April 2017. This date corresponds to a time during operation of Palisades Cycle 26.
Since the approval of the revised PTS evaluation, Cycles 21 and 22 have been completed and a design for Cycle 23 has been implemented and is currently in operation. Therefore, it became possible to evaluate the neutron fluence accrued during these fuel cycles based on the more accurate data obtained from actual rather than projected reactor operation.
In this supplement, the neutron fluence accrued by the limiting Weld W5214 during Cycles 21 through Cycle 26 is re-evaluated using revised neutron flux calculations and fuel cycle lengths and based on this re-evaluation an updated time at which the PTS screening limit will be reached is determined.
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Westinghouse Non-Proprietary Class 3 2-1 SECTION 2.0 NEUTRON TRANSPORT CALCULATIONS As noted in Section 1.0 of this report, the exposure of the Palisades pressure vessel was developed based on a series of fuel cycle-specific neutron transport calculations validated by comparison with plant-specific measurements. Measurement data used in the validation process were obtained from both in-vessel and ex-vessel capsule irradiations. These comparisons along with the benchmarking information described in References 4 and 5 demonstrate that the transport methodology provides results that meet the requirements of Regulatory Guide 1.190[6]. In this section, the neutron transport methodology is discussed in some detail, and the calculated results applicable to the PTS limit re-evaluation are provided.
2.1 - Method of Analysis In performing the fast neutron exposure evaluations for the Palisades reactor, plant-specific forward transport calculations were carried out using the three-dimensional flux synthesis technique described in Section 1.3.4 of Regulatory Guide 1.190. In particular, the following single channel synthesis approach was employed for all fuel cycles:
(r, z )
(r, , z) = (r, ) *
(r )
where (r,,z) is the synthesized three-dimensional neutron flux distribution, (r,) is the transport solution in r, geometry, (r,z) is the two-dimensional solution for a cylindrical reactor model using the actual axial core power distribution, and (r) is the one-dimensional solution for a cylindrical reactor model using the same source-per-unit-height as that used in the r, two-dimensional calculation.
For the Palisades analysis, all of the transport calculations were carried out using the DORT two-dimensional discrete ordinates code Version 3.2[8] and the BUGLE-96 cross section library[9]. The BUGLE-96 library provides a 67-group coupled neutron-gamma ray cross-section data set produced specifically for light water reactor applications. In these analyses, anisotropic scattering was treated with a P5 Legendre expansion and the angular discretization was modeled with an S16 order of angular quadrature. Energy and space dependent core power distributions as well as system operating conditions were treated on a fuel cycle-specific basis.
The geometry used for the Palisades transport analysis is discussed in some detail in Reference 1 and the geometric model established for Cycle 15 and beyond was also used for the current evaluations. A plan view of the r, model of the reactor geometry at the core midplane is shown in Figure 2.1-1. This model depicts a single quadrant of the reactor. A WCAP-15353 - Supplement 3 - NP, Revision 0 June 2013
Westinghouse Non-Proprietary Class 3 2-2 section view of the r,z model of the Palisades reactor is shown in Figure 2.1-2. The r,z model extended radially from the centerline of the reactor core out to a location interior to the primary biological shield and over an axial span from an elevation one foot below the active fuel to an axial elevation one foot above the active fuel. The one-dimensional radial model used in the synthesis procedure consisted of the same radial mesh intervals included in the r,z model.
Thus, radial synthesis factors could be determined on a meshwise basis throughout the entire geometry.
The core power distributions used in the plant-specific transport analysis for the reactor were provided by Entergy[11]. The data used in the source generation included fuel assembly-specific initial enrichments, beginning-of-cycle burnups and end-of-cycle (EOC) burnups. Appropriate axial burnup distributions were also used.
For each fuel cycle of operation, the fuel assembly-specific enrichment and burnup data were used to generate the spatially dependent neutron source throughout the reactor core. This source description included the spatial variation of isotope-dependent (U-235, U-238, Pu-239, Pu-240, Pu-241, and Pu-242) fission spectra, neutron emission rate per fission, and energy release per fission based on the burnup history of individual fuel assemblies. These fuel assembly-specific neutron source strengths derived from the detailed isotopics were then converted from fuel pin Cartesian coordinates to the [r,], [r,z], and [r] spatial mesh arrays used in the DORT discrete ordinates calculations.
WCAP-15353 - Supplement 3 - NP, Revision 0 June 2013
Westinghouse Non-Proprietary Class 3 2-3 Figure 2.1-1 Palisades r, Reactor Geometry WCAP-15353 - Supplement 3 - NP, Revision 0 June 2013
Westinghouse Non-Proprietary Class 3 2-4 Figure 2.1-2 Palisades r,z Reactor Geometry WCAP-15353 - Supplement 3 - NP, Revision 0 June 2013
Westinghouse Non-Proprietary Class 3 2-5 2.2 - PTS Limit Re-evaluation The limiting RPV axial welds (Weld W5214) are exposed to the neutron flux characteristic of the 60° azimuthal location. A summary of the neutron flux and cycle time data used in both the prior analysis and the current re-evaluation is given in Table 2.2-1. Note that the updated data include new neutron flux values for Cycles 21, 22, and 23, as well as new cycle lengths for Cycles 21, 22, 23, and 24. The projected neutron flux for Cycles 24, 25, and 26 and the projected cycle lengths for Cycles 25 and 26 remain the same as those used in Reference 10.
The updated data included in Table 2.2-1 were provided via References 11 through 13.
In Table 2.2-2, a comparison of the calculated neutron fluence at the end of Cycles 20 through Cycle 26 is given for both the prior analysis and the current re-evaluation. From Table 2.2-2, it is noted that, in both cases, the limiting weld fluence of 1.685e19 n/cm2 is reached during Cycle 26.
In Table 2.2-3, the accrued neutron fluence at the limiting Weld (W5214) is provided as a function of irradiation time through Cycle 26 for the updated irradiation conditions. In developing this exposure profile, Cycle 26 was assumed to initiate at 11:00 on November 15, 2016 and to run at 100% capacity during the cycle up to the point at which the limiting fluence is reached.
Based on these projections, the limiting fluence at Weld W5214 is calculated to be reached after 11.99 days of irradiation in August 2017.
WCAP-15353 - Supplement 3 - NP, Revision 0 June 2013
Westinghouse Non-Proprietary Class 3 2-6 Table 2.2-1 Comparison of Fast Neutron Flux Values and Fuel Cycle Lengths used in the PTS Limit Analysis Weld W5214 Reference 10 Current Analysis Cycle Flux1 Cycle Time Cycle Flux1 Cycle Time Cycle [n/cm2-s] [EFPD] [n/cm2-s] [EFPD]
21 1.172e10 519 1.169e10 508 22 1.128e10 499 1.101e10 495 23 1.172e10 499 1.021e10 527 24 1.172e10 477 1.172e10 4202 25 1.172e10 504 1.172e10 504 26 1.172e10 504 1.172e10 504 1- Limiting RPV axial welds (Weld W5214) are exposed to the neutron flux characteristic of the 60° azimuthal location.
2 - Cycle 24 length is based upon a spring 2015 refueling outage. That outage might be changed to Fall 2015 and the subsequent refueling outages delayed to maintain 18-month refueling cycles. Three refueling outages are still planned before reaching the limiting fluence.
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Westinghouse Non-Proprietary Class 3 2-7 Table 2.2-2 Comparison of Fast Neutron Fluence Accrued at the Conclusion of Cycles 21 Through 26 Weld W5214 Reference 10 Current Analysis Cumulative Cumulative Cycle Exposure EOC Exposure EOC Time Fluence1 Time Fluence1
[EFPY] [n/cm2] [EFPY] [n/cm2]
20 22.0 1.419e19 22.0 1.419e19 21 23.4 1.472e19 23.3 1.471e19 22 24.7 1.520e19 24.7 1.518e19 23 26.1 1.571e19 26.1 1.564e19 24 27.4 1.619e19 27.3 1.607e19 25 28.8 1.670e19 28.7 1.658e19 26 30.2 1.721e19 30.1 1.709e19 1- Limiting RPV axial welds (Weld W5214) are exposed to the neutron flux characteristic of the 60° azimuthal location.
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Westinghouse Non-Proprietary Class 3 2-8 Table 2.2-3 Fast Neutron Fluence Accumulation as a Function of Irradiation Time During Cycle 26 Weld W5214 Current Analysis Monthly Month Exposure Accumulated Time Fluence
[EFPD] [n/cm2]
Nov. 2016 14.54 1.659e19 Dec. 2016 31 1.662e19 Jan. 2017 31 1.665e19 Feb. 2017 28 1.668e19 Mar. 2017 31 1.671e19 Apr. 2017 30 1.674e19 May 2017 31 1.678e19 Jun. 2017 30 1.681e19 Jul. 2017 31 1.684e19 Aug. 2017 11.99 1.685e19 Notes: 1 - Assumed Cycle Start Nov. 11/15/2016 at 11:00 2 - Cycle flux = 1.172e10 n/cm2-s (E > 1.0 MeV) 3 - Cycle 26 Capacity Factor is assumed to be 100% to the point at which the limiting fluence is reached.
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Westinghouse Non-Proprietary Class 3 3-1 SECTION
3.0 REFERENCES
- 1. WCAP-15353, Revision 0, Palisades Reactor Pressure Vessel Neutron Fluence Evaluation, G. K. Roberts et al., January 2000.
- 2. LTR-REA-00-630, Transmittal of Responses to Requests for Additional Information on WCAP-15353 in Support of the Palisades Pressure Vessel Fluence Evaluation, G. K. Roberts, July 13, 2000.
- 3. NRC Safety Evaluation Report (SER), Darl S. Hood (NRC) to Nathan L. Haskell (Palisades), Palisades Plant - Reactor Vessel Neutron Fluence Evaluation and revised Schedule for Reaching Pressurized Thermal Shock Screening Criteria, November 14, 2000.
- 4. WCAP-14040-NP-A, Revision 4, Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves, May 2004.
- 5. WCAP-16083-NP-A, Revision 0, Benchmark Testing of the FERRET Code for Least Squares Evaluation of Light Water Reactor Dosimetry, S. L. Anderson, May 2006.
- 6. Regulatory Guide 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence, U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, March 2001.
- 7. Code of Federal Regulations Title 10 Part 50, Domestic Licensing of Production and Utilization Facilities, Appendix G, Fracture Toughness Requirements and Appendix H, Reactor Vessel Materials Surveillance Requirements, January 1992.
- 8. CCC-650, DOORS 3.2, One-, Two-, and Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System, April 1998. Available from the Radiation Safety Information Computational Center, Oak Ridge National Laboratory.
- 9. DLC-185, BUGLE-96, Coupled 47 Neutron, 20 Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications, March 1996. Available from the Radiation Safety Information Computational Center, Oak Ridge National Laboratory.
- 10. WCAP-15353, Supplement 1 - NP, Palisades Reactor Pressure Vessel Fluence Evaluation, Stanwood L. Anderson, May 2010.
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Westinghouse Non-Proprietary Class 3 3-2
- 11. Palisades Design Input Record for Input to a Contingent Calculation, Thomas W. Allen, May 20, 2013.
- 12. Westinghouse Project Letter CPAL-11-20, Pressure Vessel Flux Update - Cycles 21 and 22, Edward P. Shields, July 29, 2011.
- 13. Westinghouse Project Letter CPAL-12-14, Pressure Vessel Inner Radius Fluence Following Cycle 23, Anthony L. Dietrich, August 21,2012.
- 14. NRC Safety Evaluation Report (SER), Mahesh Chawla (NRC) to Vice President Operations, Entergy Nuclear Operations Inc, Palisades Nuclear Plant, Updated Reactor Pressure Vessel Pressurized Thermal Shock Evaluation for Palisades Nuclear Plant (TAC NO. ME5263), December 7, 2011.
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