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| Issue date | Title | Topic | |
|---|---|---|---|
| PNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82 | 28 September 2023 | Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82 | Offsite Dose Calculation Manual FLEX Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Annual Radiological Effluent Release Report License Renewal Exemption Request Fuel cladding Biofouling Environmental Justice Siren |
| PNP 2020-039, 10 CFR 71.95 Report Involving 3-608 Cask | 20 November 2020 | 10 CFR 71.95 Report Involving 3-608 Cask | |
| ML20272A166 | 30 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, | |
| ML20267A391 | 22 September 2020 | Attachment 4, Framatome Document No. 51-9292503-002, Palisades CEDM Nozzle Idtb Repair - Life Assessment Summary | Non-Destructive Examination Finite Element Analysis |
| ML18330A143 | 26 November 2018 | Relief Request Number RR 5-7, Proposed Alternative to ASME Section Xi Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations | |
| ML18330A146 | 24 November 2018 | Framatome, Document No. 51-9292503, Palisades CRDM & Ici Nozzle Idtb Repair - Life Assessment Summary | Finite Element Analysis |
| ML18270A323 | 27 September 2018 | Attachment 2: Probabilistic Risk Assessment Technical Adequacy | Hot Short Safe Shutdown Mission time Fire Barrier Internal Flooding Probabilistic Risk Assessment Operator Manual Action Multiple Spurious Operation Surveillance Frequency Control Program Large early release frequency Fire Protection Program |
| 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 Accident | 25 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 | FLEX Fukushima Dai-Ichi Flooding Focused Evaluation |
| 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 Accident | 25 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 | Fukushima Dai-Ichi |
| PNP 2015-058, Technical Specification Required Report | 4 August 2015 | Technical Specification Required Report | Post Accident Monitoring |
| PNP 2015-018, Areva, Inc., 51-9226987-000, Palisades Nuclear Plant Flooding Hazard Re-Evaluation Report. | 25 February 2015 | Areva, Inc., 51-9226987-000, Palisades Nuclear Plant Flooding Hazard Re-Evaluation Report. | Safe Shutdown High winds Ultimate heat sink Hydrostatic Fukushima Dai-Ichi Frazil ice Earthquake |
| 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. | 18 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. | Boric Acid High Radiation Area Safe Shutdown Earthquake Probabilistic Risk Assessment Emergency Lighting FLEX Fukushima Dai-Ichi Earthquake Power-Operated Valves |
| PNP 2014-051, Response to May 1, 2014 Request for Additional Information for License Amendment Request to Revise Emergency Response Organization Staff Augmentation Response Times | 16 July 2014 | Response to May 1, 2014 Request for Additional Information for License Amendment Request to Revise Emergency Response Organization Staff Augmentation Response Times | Safe Shutdown High Radiation Area Severe Accident Management Guideline Minimum staff |
| PNP 2014-038, Special Report for Inoperability of High Range Noble Gas Monitor | 14 April 2014 | Special Report for Inoperability of High Range Noble Gas Monitor | Offsite Dose Calculation Manual |
| ML13365A264 | 10 February 2014 | Interim Staff Evaluation Regarding Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) | Safe Shutdown Boric Acid High winds Shutdown Margin Ultimate heat sink Tornado Missile Time to boil Safe Shutdown Earthquake Internal Flooding Operating Basis Earthquake Emergency Lighting FLEX Fukushima Dai-Ichi Design basis earthquake Frazil ice Earthquake GOTHIC |
| ML14030A207 | 6 February 2014 | Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Palisades Nuclear Plant, TAC No.: MF0768 | Safe Shutdown Boric Acid High winds Shutdown Margin Ultimate heat sink Tornado Missile Time to boil Safe Shutdown Earthquake Internal Flooding Operating Basis Earthquake Emergency Lighting FLEX Fukushima Dai-Ichi Design basis earthquake Frazil ice Earthquake |
| ML13242A159 | 29 August 2013 | Addendum to the Results of Independent Samples Collected by the NRC at Palisades Nuclear Plant Storm Drain Outfall | |
| ML13295A450 | 31 July 2013 | WCAP-15353-Supplement 2-NP, Rev. 0, Palisades Reactor Pressure Vessel Fluence Evaluation. | |
| ML13295A451 | 28 February 2013 | WCAP-17651-NP, Rev. 0, Palisades Nuclear Power Plant Reactor Vessel Equivalent Margins Analysis. | |
| ML14316A208 | 28 February 2013 | Attachment 5 - Westinghouse WCAP-17651-NP, Revision 0, Palisades Nuclear Power Plant Reactor Vessel Equivalent Margins Analysis | |
| ML13038A440 | 7 February 2013 | BADGER Test Campaign at Palisades Nuclear Plant | |
| ML13295A449 | 31 January 2013 | WCAP-17403-NP, Rev. 1, Palisades Nuclear Power Plant Extended Beltline Reactor Vessel Integrity Evaluation. | |
| ML14316A199 | 31 January 2013 | Attachment 3 - Westinghouse WCAP-17403-NP, Revision 1, Palisades Nuclear Power Plant Extended Beltline Reactor Vessel Integrity Evaluation | |
| ML12061A289 | 28 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) | Boric Acid Safe Shutdown Earthquake Hydrostatic Probabilistic Risk Assessment Operating Basis Earthquake Nondestructive Examination Foreign Material Exclusion Earthquake Control of Heavy Loads Fuel cladding Liquid penetrant |
| ML120100503 | 5 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 | |
| ML120100496 | 5 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 | |
| ML120100499 | 5 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 | Biofouling |
| ML120100506 | 5 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 | Finite Element Analysis |
| ML120100509 | 5 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 | Hot Short Safe Shutdown Mission time Internal Flooding Past operability Probabilistic Risk Assessment Seismically rugged Large early release frequency Earthquake Preliminary White Finding |
| ML120100511 | 5 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 | |
| ML120100514 | 5 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 | |
| ML120100516 | 5 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 | Hot Short |
| ML120100544 | 5 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 | Finite Element Analysis |
| ML120100547 | 5 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 | Mission time Past operability Probabilistic Risk Assessment Condition Adverse to Quality Significance Determination Process Earthquake |
| ML120100548 | 5 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 | Mission time Internal Flooding Temporary Modification Arc flash Missed surveillance Significance Determination Process Fatigue Rule |
| ML120100550 | 5 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 | Boric Acid Fitness for Duty High winds Internal Flooding Temporary Modification Condition Adverse to Quality |
| ML120100558 | 5 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 | |
| ML120100559 | 5 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 | Mission time |
| ML120100562 | 5 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 | Emergency Lighting Job Performance Measure |
| ML120100560 | 5 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 | Temporary Modification |
| ML120100540 | 5 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 | Finite Element Analysis |
| ML11339A101 | 14 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 | Hot Short Safe Shutdown Mission time Fire Barrier Internal Flooding Probabilistic Risk Assessment Emergency Lighting Significance Determination Process Job Performance Measure Seismically rugged Large early release frequency B.5.b Mitigating Strategies |
| ML12006A049 | 8 September 2011 | P-7C Coupling Failure Root Cause | Finite Element Analysis Biofouling |
| ML14316A207 | 31 July 2011 | Attachment 4 - Westinghouse, WCAP-15353, Supplement 2-NP, Revision 0, Palisades Reactor Pressure Vessel Fluence Evaluation | |
| ML110380092 | 31 January 2011 | Areva Np Inc. Technical Report, Document No. ANP-2858NP-003, Palisades SFP Region 1 Criticality Evaluation with Burnup Credit. | |
| ML110060694 | 12 November 2010 | Attachment 2, Structural Integrity Associates, Inc., Report No. 1000915.401, Revised Pressurized Thermal Shock Evaluation for the Palisades Reactor Pressure Vessel | |
| ML110730084 | 12 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 | |
| ML101540386 | 2 June 2010 | Documentation for Pressurized Thermal Shock Evaluation Meeting | |
| ML110060695 | 31 May 2010 | Attachment 3, WCAP-15353-NP, Revision 0, Supplement 1, Palisades Reactor Pressure Vessel Fluence Evaluation | |
| ML110060693 | 20 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 |