ML18330A143
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| ML18330A143 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 11/26/2018 |
| From: | Entergy Nuclear Operations |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18330A141 | List: |
| References | |
| PNP 2018-054 | |
| Download: ML18330A143 (32) | |
Similar Documents at Palisades | |
|---|---|
Category:Report
MONTHYEARPNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.822023-09-28028 September 2023
[Table view]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. 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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 Category:Technical MONTHYEARPNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.822023-09-28028 September 2023
[Table view]Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82 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 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 2018-041, 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 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 2015-058, Technical Specification Required Report2015-08-0404 August 2015 Technical Specification Required Report 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 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 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. ML13295A4512013-02-28028 February 2013 WCAP-17651-NP, Rev. 0, Palisades Nuclear Power Plant Reactor Vessel Equivalent Margins Analysis. ML14316A2082013-02-28028 February 2013 Attachment 5 - Westinghouse WCAP-17651-NP, Revision 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 ML12061A2892012-02-28028 February 2012 Attachment 6, Holtec International Report No. HI-2115004, Licensing Report for Replacement of the Palisades Region 1 Spent Fuel Pool Storage Racks. (Non-Proprietary Version) ML1201005032012-01-0505 January 2012 Regulatory Conference Supporting Documentation for Apparent Violations EA-11-241 and EA-11-243, Attachment 1. Root Cause Evaluation-Service Water Pump P-7C Coupling Failure, Rev 0, Part 2.3 of 7 ML1201004962012-01-0505 January 2012 Regulatory Conference Supporting Documentation for Apparent Violations EA-11-241 and EA-11-243, Attachment 1. Root Cause Evaluation-Service Water Pump P-7C Coupling Failure, Rev 0, Part 2 of 7 ML1201004992012-01-0505 January 2012 Regulatory Conference Supporting Documentation for Apparent Violations EA-11-241 and EA-11-243, Attachment 1. Root Cause Evaluation-Service Water Pump P-7C Coupling Failure, Rev 0, Part 2.2 of 7 ML1201005062012-01-0505 January 2012 Regulatory Conference Supporting Documentation for Apparent Violations EA-11-241 and EA-11-243, Attachment 1. Root Cause Evaluation-Service Water Pump P-7C Coupling Failure, Rev 0, Part 2.4 of 7 ML1201005092012-01-0505 January 2012 Regulatory Conference Supporting Documentation for Apparent Violations EA-11-241 and EA-11-243, Attachment 2. SDP Assessment of Service Water Pump P-7C Coupling Failures, Part 2 of 7 Completed ML1201005112012-01-0505 January 2012 Regulatory Conference Supporting Documentation for Apparent Violations EA-11-241 and EA-11-243, Attachment 2. SDP Assessment of Service Water Pump P-7C Coupling Failures, Part 4.1 of 7 ML1201005142012-01-0505 January 2012 Regulatory Conference Supporting Documentation for Apparent Violations EA-11-241 and EA-11-243, Attachment 2. SDP Assessment of Service Water Pump P-7C Coupling Failures, Part 4.2 of 7 ML1201005162012-01-0505 January 2012 Regulatory Conference Supporting Documentation for Apparent Violations EA-11-241 and EA-11-243, Attachment 2. SDP Assessment of Service Water Pump P-7C Coupling Failures, Part 4.4 of 7 ML1201005442012-01-0505 January 2012 Regulatory Conference Supporting Documentation for Apparent Violations EA-11-241 and EA-11-243, Attachment 2. SDP Assessment of Service Water Pump P-7C Coupling Failures, Part 5.2 of 7 ML1201005472012-01-0505 January 2012 Regulatory Conference Supporting Documentation for Apparent Violations EA-11-241 and EA-11-243, Attachment 2. SDP Assessment of Service Water Pump P-7C Coupling Failures, Part 6.1 of 7 ML1201005482012-01-0505 January 2012 Regulatory Conference Supporting Documentation for Apparent Violations EA-11-241 and EA-11-243, Attachment 2-End and Attachment 3, Root Cause Evaluation-Plant Trip During Panel ED-11-2 Maintenance, Rev 2, Part 6.2 of 7 ML1201005502012-01-0505 January 2012 Regulatory Conference Supporting Documentation for Apparent Violations EA-11-241 and EA-11-243, Attachment 3, Root Cause Evaluation-Plant Trip During Panel ED-11-2 Maintenance, Rev 2, Part 6.3 of 7 ML1201005582012-01-0505 January 2012 Regulatory Conference Supporting Documentation for Apparent Violations EA-11-241 and EA-11-243, Attachment 3, Root Cause Evaluation-Plant Trip During Panel ED-11-2 Maintenance, Rev 2, Part 7.1 of 7 ML1201005592012-01-0505 January 2012 Regulatory Conference Supporting Documentation for Apparent Violations EA-11-241 and EA-11-243, Attachment 3, Root Cause Evaluation-Plant Trip During Panel ED-11-2 Maintenance, Rev 2, Part 7.2 of 7 ML1201005622012-01-0505 January 2012 Regulatory Conference Supporting Documentation for Apparent Violations EA-11-241 and EA-11-243, Attachment 3, Root Cause Evaluation-Plant Trip During Panel ED-11-2 Maintenance, Rev 2 - End, Part 7.4 of 7 ML1201005602012-01-0505 January 2012 Regulatory Conference Supporting Documentation for Apparent Violations EA-11-241 and EA-11-243, Attachment 3, Root Cause Evaluation-Plant Trip During Panel ED-11-2 Maintenance, Rev 2, Part 7.3 of 7 ML1201005402011-12-0505 December 2011 Regulatory Conference Supporting Documentation for Apparent Violations EA-11-241 and EA-11-243, Attachment 2. SDP Assessment of Service Water Pump P-7C Coupling Failures, Part 5.1 of 7 ML11339A1012011-11-14014 November 2011 EA-PSA-SDP-P8B-11-05, Rev. 1, Assessment of Steam Driven Auxiliary Feedwater P-8B Trip on May 10, 2011, Attachment 3 ML12006A0492011-09-0808 September 2011 P-7C Coupling Failure Root Cause ML14316A2072011-07-31031 July 2011 Attachment 4 - Westinghouse, WCAP-15353, Supplement 2-NP, Revision 0, Palisades Reactor Pressure Vessel Fluence Evaluation ML1103800922011-01-31031 January 2011 Areva Np Inc. Technical Report, Document No. ANP-2858NP-003, Palisades SFP Region 1 Criticality Evaluation with Burnup Credit. ML1100606942010-11-12012 November 2010 Attachment 2, Structural Integrity Associates, Inc., Report No. 1000915.401, Revised Pressurized Thermal Shock Evaluation for the Palisades Reactor Pressure Vessel ML1107300842010-11-12012 November 2010 1001026.401, Rev 1, Basis for Period of Validity of the Palisades Pressure-Temperature (P-T) Limit Curves, Attachment 6 to Pnp 2011-016 ML1015403862010-06-0202 June 2010 Documentation for Pressurized Thermal Shock Evaluation Meeting ML1100606952010-05-31031 May 2010 Attachment 3, WCAP-15353-NP, Revision 0, Supplement 1, Palisades Reactor Pressure Vessel Fluence Evaluation ML1100606932010-04-20020 April 2010 Attachment 1, Structural Integrity Associates, Inc., Report No. 0901132.401, Evaluation of Surveillance Data for Weld Heat No. W5214 for Application to Palisades PTS Analysis 2023-09-28 |
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