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Category:Drawing
MONTHYEARML23107A0412023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 11, Figures ML23107A0122023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 2, Figures ML23107A0582023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 6, Figures ML23107A0362023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 3, Figures ML23107A0622023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 4, Figures ML23107A0232023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 5, Figures ML23107A0572023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 10, Figures ML23107A0402023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 1, Figures ML23107A0222023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 9, Figures ML21125A3112021-04-14014 April 2021 5 to Updated Final Safety Analysis Report, Chapter 3, Figures ML21125A3292021-04-14014 April 2021 5 to Updated Final Safety Analysis Report, Chapter 6, Figures (Redacted) ML21125A2902021-04-14014 April 2021 5 to Updated Final Safety Analysis Report, Chapter 2, Figures ML21125A3152021-04-14014 April 2021 5 to Updated Final Safety Analysis Report, Chapter 11, Figures (Redacted) ML21125A3142021-04-14014 April 2021 5 to Updated Final Safety Analysis Report, Chapter 1, Figures (Redacted) ML21125A3342021-04-14014 April 2021 5 to Updated Final Safety Analysis Report, Chapter 14, Figures (Redacted) ML21125A2952021-04-14014 April 2021 5 to Updated Final Safety Analysis Report, Chapter 7, Figures (Redacted) ML21125A3032021-04-14014 April 2021 5 to Updated Final Safety Analysis Report, Chapter 4, Figures ML21125A3062021-04-14014 April 2021 5 to Updated Final Safety Analysis Report, Chapter 8, Figures ML21125A2992021-04-14014 April 2021 5 to Updated Final Safety Analysis Report, Chapter 5, Figures ML16120A3442016-04-18018 April 2016 Final Safety Analysis Report Update, Revision 32, Chapter 2 - Site and Environment - Figures ML16120A3592016-04-18018 April 2016 Final Safety Analysis Report Update, Revision 32, Chapter 3 - Reactor - Figures ML16123A3262016-04-18018 April 2016 Final Safety Analysis Report Update, Revision 32, Chapter 15 - Quality Assurance Program - Figures ML16120A5882016-04-18018 April 2016 Final Safety Analysis Report Update, Revision 32, Chapter 8 - Electrical Systems - Figures ML16120A6022016-04-18018 April 2016 Final Safety Analysis Report Update, Revision 32, Chapter 10 - Steam and Power Conversion System - Figures ML16120A3792016-04-18018 April 2016 Final Safety Analysis Report Update, Revision 32, Chapter 4 - Primary Coolant System - Figures ML16120A4152016-04-18018 April 2016 Final Safety Analysis Report Update, Revision 32, Chapter 5 - Design of Structures, Systems and Components - Figures ML16120A5962016-04-18018 April 2016 Final Safety Analysis Report Update, Revision 32, Chapter 9 - Auxiliary Systems - Figures ML15190A2632015-05-14014 May 2015 Report 1400669.401, Rev. 0, Evaluation of the Palisades Nuclear Plant Branch Line Nozzles for Primary Water Stress Corrosion Cracking ML12272A1682012-08-22022 August 2012 E-mail from A. Shaikh to D. Alley, Et Al., Subject: (Untitled) ML0726801882007-06-26026 June 2007 Drawing C-52, Rev. 23, Heating & Ventilation Auxiliary & Containment Plan at Elevation 639'-0 & 649' -0'. ML0725408072007-01-12012 January 2007 Drawing M-15, Rev. 12, Equipment Location Turbine Building Sections. ML0725408022006-11-15015 November 2006 Drawing C-51, Rev. 30, Architectural Auxillary & Reacator Building Floor Plans at 639' - 0 and 649'-0. ML0726801792006-01-12012 January 2006 Drawing C-52, Rev. 15, Architectural Roof Plan. ML0725407902006-01-11011 January 2006 Drawing C-2, Rev. 16, Plant Area and Switchyard Plan. Sheet 1 ML0633901872004-08-0303 August 2004 Drawing No. M-206, Rev. 6, System Diagram Safety Injection, Containment Spray & Shutdown Cooling System. Sheet a ML0633901912004-08-0202 August 2004 Drawing No. M-209, Rev. 7, System Diagram Component Cooling System. Sheet a ML0633901832004-08-0202 August 2004 Drawing No. M-204, Rev. 7, System Diagram Safety Injection, Conatinment Spray & Shutdown Cooling System. Sheet a ML0628304772000-08-14014 August 2000 Drawing C-51, Rev 29, Architectural Auxiliary Reactor Building Floor Plans. ML0628304702000-08-14014 August 2000 Drawing C-51, Rev 29, Architectural Auxiliary Reactor Building Floor Plans. ML18347B2951999-05-13013 May 1999 Submit Revised Dilution Water Increase - Proposed Modification, to Modify Requested Flow Changes & to Respond to Mdnr & Michigan Dept of Environmental Quality Concerns for NPDES Permit No. MI0001457 ML0725408031999-04-0808 April 1999 Drawing C-127, Rev. 2, Containment Vessel Typical Details. ML0725408061998-10-12012 October 1998 Drawing C-141, Rev. 5, Containment Ventilation Stack. ML0725407951998-10-0505 October 1998 Drawing C-38, Rev. 6, Field Erected Tanks. Sheet 2 ML0725407971998-02-25025 February 1998 Drawing C-50, Rev. 20, Architectural Auxiliary & Reactor Buildings Floor Plan at El 625'-0. ML0725500561998-01-14014 January 1998 Drawing M-119, Rev. 8, Heating and Ventilation Mechanical Equipment Room Plan and Sections El. 629' -2. Sheet 4 ML0725408091997-11-0404 November 1997 Drawing M-29, Rev. 13, Piping Drawing Area 2 Plan of El. 625' - 0. ML0725408111997-02-27027 February 1997 Drawing M-40, Rev. 29, Piping Drawing Area 3 Plan of El. 625' - 0 & Sections. ML0725408161997-01-17017 January 1997 Drawing M-65, Rev. 13, Piping Drawing Main Steam System. ML0725408201996-04-24024 April 1996 Drawing M-119, Rev. 7, Heating and Ventilating Mechanical Room Roof Plan Sections and Details. Sheet 3 ML0725408141996-02-23023 February 1996 Drawing M-42, Rev. 32, Piping Drawing Area 3 Sections. 2023-03-31
[Table view] Category:Letter
MONTHYEARML24022A1172024-01-23023 January 2024 Acceptance of Requested Licensing Action Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML24012A2422024-01-16016 January 2024 Acceptance of Requested Licensing Action License Transfer Request ML23236A0042023-12-27027 December 2023 Issuance of Amendment 274 Re Changes to Perm Defueled Emergency Plan and Perm Defueled Emergency Action Level Scheme ML23355A1242023-12-26026 December 2023 Withdrawal of an Amendment Request Re License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML23192A0772023-12-26026 December 2023 Letter Exemption from the Requirements of 10 CFR 140.11(a)(4) Concerning Offsite Primary and Secondary Liability Insurance ML23191A5222023-12-22022 December 2023 Exemption Letter from the Requirements of 10 CFR 50.54(W)(1) Concerning Onsite Property Damage Insurance (EPID - L-2022-LLE-0032) ML23263A9772023-12-22022 December 2023 Exemption from Certain Emergency Planning Requirements and Related Safety Evaluation ML23354A2602023-12-21021 December 2023 Reference Simulator Inspection Request for Information L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 PNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations PNP 2023-035, Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements2023-12-12012 December 2023 Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements PNP 2023-028, Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments2023-12-0606 December 2023 Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23291A4402023-11-0303 November 2023 Acceptance of Requested Licensing Action Request for Exemption from 10 CFR 50.82(a)(2) to Support Reauthorization of Power Operations IR 05000255/20230032023-10-0404 October 2023 NRC Inspection Report No. 05000255/2023003(DRSS)-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23275A0012023-10-0202 October 2023 Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant PNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.822023-09-28028 September 2023 Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82 PNP 2023-026, Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations2023-09-28028 September 2023 Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations PNP 2023-023, Special Report High Range Noble Gas Monitor Inoperable2023-08-0909 August 2023 Special Report High Range Noble Gas Monitor Inoperable ML23215A2302023-08-0303 August 2023 Notice of Organization Change - Chief Nuclear Officer IR 05000255/20230022023-07-19019 July 2023 NRC Inspection Report 05000255/2023002 DRSS-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23087A0362023-05-0202 May 2023 PSDAR Review Letter ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment PNP 2023-018, 2022 Annual Non-Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Non-Radiological Environmental Operating Report L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 PNP 2023-007, and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports2023-04-19019 April 2023 and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports PNP 2023-008, 2022 Radiological Environmental Operating Report2023-04-18018 April 2023 2022 Radiological Environmental Operating Report L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations PNP 2023-002, 6 to Updated Final Safety Analysis Report2023-03-31031 March 2023 6 to Updated Final Safety Analysis Report ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance PNP 2023-006, Report of Changes to Security Plan, Revision 202023-03-29029 March 2023 Report of Changes to Security Plan, Revision 20 PNP 2023-012, Presentation on Regulatory Path to Reauthorize Power Operations2023-03-16016 March 2023 Presentation on Regulatory Path to Reauthorize Power Operations ML23038A0982023-03-15015 March 2023 Request for Withholding Information from Public Disclosure ML23095A0642023-03-14014 March 2023 American Nuclear Insurers, Notice of Cancellation Rescinded PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023 Regulatory Path to Reauthorize Power Operations PNP 2023-004, Report of Changes to Palisades Nuclear Plant Technical Specification Bases2023-03-0808 March 2023 Report of Changes to Palisades Nuclear Plant Technical Specification Bases PNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023 Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23052A1092023-02-17017 February 2023 FEMA Letter to NRC, Proposed Commission Paper Language for Palisades Nuclear Plant Emergency Plan Decommissioning Exemption Request ML23032A3992023-02-0101 February 2023 Regulatory Path to Reauthorize Power Operations IR 05000255/20220032022-12-28028 December 2022 NRC Inspection Report No. 05000255/2022003(DRSS); 07200007/2022001 (Drss) Holtec Decommissioning International, LLC, Palisades Nuclear Plant L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 PNP 2022-037, Report of Changes to Security Plan, Revision 192022-12-14014 December 2022 Report of Changes to Security Plan, Revision 19 ML22321A2852022-11-17017 November 2022 LLC Master Decommissioning Trust Agreement for Palisades Nuclear Plant IR 05000255/20224012022-11-0909 November 2022 Decommissioning Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2022401 PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022 Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-035, International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations2022-11-0202 November 2022 International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations PNP 2022-024, Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance PNP 2022-026, Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance ML22292A2572022-10-25025 October 2022 Permanently Defueled Emergency Plan License Amendment RAI Letter 2024-01-23
[Table view] Category: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:Technical
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 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
[Table view] |
Text
- ENCLOSURE CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 MAY 24, 1999 CONSUMERS ENERGY, PALISADES PLANT NPDES PERMIT No. MI0001457 REVISED DILUTION WATER INCREASE - PROPOSED MODIFICATION 23 Pages
r A CMS Energy Company Environmental & Technical .cax: 511 788 2329 Services Department 1945 West Pama/I Road Jackson. Ml 49201-8643 May 13, 1999 Michigan Department of Environmental Quality 21EPIO.l Surface Water Quality Division, GLEAS 21EP10.l.3 Attn: Mr Jeff Cooper 300 S Washington Street Knapps Centre Lansing, MI 48933 Michigan Department of Environmental Quality Surface Water Quality Division, Permits Section Attn: Mr Barry Burns 300 S. Washington Street Knapps Centre Lansing, MI 48933 CONSUMERS ENERGY COMPANY, PALISADES NUCLEAR PLANT NPDES PERMIT NO. MI0001457 REVISED DILUTION WATER INCREASE - PROPOSED MODIFICATION:
As part of the Palisades Plant's March 30, 1998 NPDES permit renewal application, the Company requested to increase the plant's dilution water flow to generate electricity more efficiently and remain competitive under future electric utility deregulation. The March 30, 1998 request was to increase cooling water withdrawal from Lake Michigan from 68,000 gpm to 138,000 gpm.
The MDNR and MDEQ raised concerns about allowing the increased water withdrawal for reasons of increased impingement of forage fish species, _and whether the thermal loading limit (BTU/hr) would still be met. After further design evaluations by the Plant, it was determined that the initial flow .
increase request could be reduced from 138,000 gpm to 103,000 gpm to better accommodate existing systems and still yield an improved generation efficiency. Therefore, the requested discharge flow increase to Outfall 001 to Lake Michigan is not needed, and we anticipate to maintain the t~ermal loading to Lake Michigan at 2100 x 10 6 Btu/hr. This change in flow and further information regarding the cooling water intake design, operation and impact were discussed with MDNR Fisheries Division on April 2, 1999, and the updated information is included with this revision as Attachment 1.
The purpose of this revision is to modify the requested (3/30/98) flow changes and to respond to the MDNR &MDEQ concerns by:
- 1. More clearly describing the cooling water intake system, 00599-40.JAC
- 2. Providing the background of changes in operati~n of the cooling water system and impacts,
- 3. Providing the rationale for the current request to increase cooling water fl ow,
- 4. Providing the data and basis to show expected continued compliance with the existing heat load limitation, and
- 5. Provide a resolution strategy that will accommodate permitting of the
- requested flow increase and evaluation of monitoring or other mitigative actions.
Permit Application Enclosed as Attachment 2 are marked-up copies of the 3/30/98 permit application pages that are changed as a result of today's proposed dilution water increase modification. These pages report intake, Outfalls OOA, 008, OOF, and 001 flow information. The changes made on the internal outfall pages for Outfalls OOA, 008 and OOF were revised to show more accurate flow rates and are not a necessarily a reflection of the proposed modification.
The plant's flow diagram, Exhibit I-11 has been revised to reflect the proposed modification.
Please replace the plant's 3/30/98 permit application pages with the enclosed copies accordingly. The remaining pages of the 3/30/98 plant permit application are still valid. The renewed NPDES permit for the Palisades Nuclear Plant should be based on the revised information provided in today's packet along with the remaining (unrevised) pages of the 3/30/98 permit application.
SCHEDULE We are available to meet with the Department at your earliest convenience to discuss any subject in the packet or the proposed permit in general. We are looking forward to working with the Department in order that the renewed Palisades Plant NPDES permit is practical yet remains environmentally protective.
If you have any questions on the impingement or thermal subjects please do not hesitate to contact me at (517) 788-1285 or Jenny Crawford at (517) 788-1469.
Sincerel4.
~~ul1.f!.uk~ o~~a.~
& ~nnifer A. Crawford Sr Environmental Planner Sr Environmental Planner CC Bill Gruhn, MDNR, Fisheries Division, Lansing 00599-40.JAC
ATTACHMENT l
- 1. PALISADES NUCLEAR PLANT COOLING WATER INTAKE SYSTEM Cooling water for. the Palisades Plant is withdrawn from Lake Michigan through an intake crib, located 3300 f~t offshore at about the 35-foot water depth (Figure 1 & 2).
The crib is a 57 feet wide, 57 feet long, 12 feet high box with a steel plate for its top and 2-inch vertical bars spaced 10 inches apart around the sides. Water flows horizontally between the vertical bars. The once-through circulating water flow was designed at approximately 400,000 gpm, discharging after condenser cooling, directly at the shoreline. The intake water velocities at the face of the crib structure ranged from 0.69 to 0.95 fps during once-through cooling operation, and were reduced to <0.1 fps with the conversion to cooling tower operation.
- 2. PALISADES COOLING WATER SYSTEl\il CHANGES AND Il\IPACTS The Palisades Nuclear Plant began operation in 1971 as a once through cooling facility with a cooling water intake and discharge flow of 400,000 gpm. The changes in cooling water flow and BTU loading are depicted in Figure 3 and briefly summarized below.
1971-1974: Once-through cooling operation intake flow: 400;000 gpm/. 7 to 1.0 fps intake velocities BTU/hr: 6222 x l Q6 Average thennal plume size 231 acres Fish Impingement 653,890 fish (Jan-72 to Oct-73) (Table 1) 1975-1978: Cooling tower operation Intake flow 78,000 gpm/ < .1 fps intake velocity BTU/hr - 1140 x 1Q6 Fish impingement: 7, 189 fish (90 % alewife & slimy sculpin) 1979-1984 Modified cooling tower operation to reduce dilution water flow, and reroute cooling tower blowdown for increased electrical output.
_ Intal<e_ flow: 58, 000 gpm -- ---
- BTU/hr: 1140 x 1G6 from velocity of < .1 fps Alden Lab thermal plume model of modification to meet the 72 acre, 3 ° F above ambient mixing zone criteria 1981 Camp Dresser & McKee Thennal Discharge study demonstrated that thermal plumes were well within the 72 acre, 3° above ambient
- 2 requirement. (The study showed that thermal plumes were < 3 acres at one meter depth).
1985 Discharge flow modifications were made to more accurately reflect flow volumes maximum cooling tower blowdown.
Intake flow 58,000 gpm; flow velocity of +/- .1 fps BTU: 1300 x 106 1988-1999 Modified cooling tower operation to allow for hot-side blowdown directly to the mixing basin. This increased generation by 2-3
. megawatts and also increased BTU/hr from 1300 x 1Q6 to 2100 x 1Q6 Intake flow: 68,000 gpm, flow velocity of +/- .1 fps BTU/hr: 2100 x 106 Thermal plume was within the 72 acre, 3°F above ambient requirement of 2.5 to 3.5 megawatts Estimated plume size of approximately 4 acres at 146% maximum heat release rate (Table 2).
Proposed 1999 Modified cooling tower operation by increasing dilution water flow for increased electrical generation efficiency of 2.5 to 3.5 megawatts.
Intake flow: 103,000 gpm; increased flow velocity to an estimated
+/- .25 fps BTU/hr: 2100 x 106 Thermal plume within 72 acre, 3°F ambient as predicted from past thermal plume study and model.
- 3. RATIONALE FOR COOLING WATER FLOW INCREASE Under current operation of the plant withdraws from Lake Michigan approximately 68,000 gpm, comprised of 50,000 gpm far dilution water and 18,000 for service water (Figure 4). The associated discharge flow volume is 58,700 gpm at Outfall 001, or 84.5 MGD. The proposed modification (Figure 5) is to increase the dilution volume to 85,000 gpm (maximum), for a total withdrawal rate of 103,000 gpm. Under this operation, the Company estimates that the authorized discharge flow volume of 135.2 MGD at Outfall 001 can be maintained, therefore we are not requesting an increase in discharge for 001.
The concern raised by the MDNR regarding the requested intake flow increase is that without a change in intake dimensions, the intake velocity must be increased. Under those conditions, the rate of impingement will increase, perhaps geometrically, and the
- 3 Department objects to any further loss of fish, especially forage species at the Palisades Plant.
The Company believes that the requested flow increase will result in only a very marginal increase in impingement, or be similar to the level of impingement observed in 1976 (7, 189).
The reasons for this are:
- The intake was designed for a once-through cooling water flow of 400,000 gpm, and the conversion to a cooling tower system substantially reduced the intake flow down to 78,000 gpm for make-up (Figure 3). The combined reduction of intake flow volume and velocity decreased fish impingement from approximately 654,000 to 7 ,200 per year,
- With the larger surface area of the intake for a once-through design, the requested flow increase to a rate of 103,000 gpm is only anticipated to increase flow velocity at the crib face from about 0.1 to 0.25 fps,
- As shown in Figure 3, the requested intake flow of 103,000 gpm represents only a 25,000 gpm increase above the 1975 cooling tower flow rate of 78,000 gpm.
Thus, the Palisades cooling water intake design, coupled with cooling tower operation can safely accommodate the requested flow increase with very minimal adverse impact to the Lake Michigan fisheries.
- Accordingly, the location, design, construction, and capacity of the Palisades Nuclear Plant intake system, still reflects the best technology available for minimizing adverse environmental impact in accordance with Section 316(b) of PL 92-500.
- 4. HEAT ADDITION Lll\flT DISCUSSION Currently, the NPDES permit for the Palisades Plant allows for two types of condenser cooling operation: one as a closed cooling system, and the other under hotside blowdown conditions. The hotside blowdown condition allows the plant (upon demand) the flexibility to cool down the condenser cooling water by about 1°F by blowing down approximately 58,700 gpm of the wanner side condenser water into the cooling tower basin and discharged through Outfall 001 to Lake Michigan. This operation is in compliance with the current heat rate limit of 2100xl06 BTU/hr, and Outfall 001 authorized discharge volume discharge of 135.2 MGD.
Under the proposed operation, the amount of blowdown to the mixing basin will be increased and still be within the authorized discharge volume of 135 .2 MGD at Outfall 001. The additional cooling water and evaporation from the cooling towers will allow the plant to continue to meet the 2100xH1 BTU/hr limit during all but
- 4 during some months under worst case conditions. The BTU calculation results were derived based on a flow if 127.7 MGD at Outfall 001. The flow takes into consideration cooling tower evaporation and less than maximum pump capacities.
The expected heat release rates to Lake Michigan under the proposed operation are shown by month in the attached Table 3. The estimated worst case heat release rates to Lake Michigan under the proposed operation are also shown by month in Table 3. Due to plant outages, operational data from 1997 and 1998 were used to calculate the expected and worst case scenarios for each month. Under the expected conditions, we anticipate being able to continue operating within the 2100Xl06 BTU/hr limit. Under worst case conditions, exceedances are anticipated during cold water months. In these cases, service water flows can be reduced to maintain compliance with the BTU limit. Monitoring will continue as required in
- the permit to demonstrate compliance.
S. PROPOSAL FOR COOLING WATER INTAKE PERMITTING AND RESOLUTION To demonstrate the continued acceptability of the Palisades Nuclear Plant intake the Company proposes to conduct a one year impingement study in consultation with and approved by MDNR and MDEQ.
At our April 2, 1991 meeting with MDNR Fisheries Division (Mr. Bill Gruhn) we discussed the potential option of installing further fish protection to redU:.ce the fish loss in lieu of a study of impingement. At this time, we are not aware of a fish protection modification for this intake that would be cost effective for the estimated amount of impingement. At the conclusions of the one year impingement study, the Company will review the results with MDNR/MDEQ to determine whether the Palisades intake continues to reflect best technology available for minimizing adverse environment impact.
\
..LAKE
- -* MICHIGAN \
MLISADIS MUGLIAR POWmR 'LANT
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INTAKE
-* MEAN*
WATER
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D 1000 ASSUME LAKE LEVEL TO BE 680.5 FT SCALE* FEET FIGURE 3 NEARSHORE BATHVMETRV AT PALISADES NUCLEAR GENERATING STATION
- , *: '.!'J~:.f:~ -r. .: .
- .L' : *, .-!"*,r .. :w:::.~'
TRAVELING SCREENS BEACH TRASH RACKS FENCE ~[;.-----.___
CONDENSERS TO LAKE MICHIGAN STEEL PLATE 3,300 F T . - - - - - - - - - - - - - 1 - - WATER PUMP
~2 IN.BARS
- F I I- ~NTA_KE _CR_i_B 6 fT. ~ \' - **
~~~~-==~~~~~iiiiiiii---~~iii:J II fT. DIAM. INTAKE PIPE INTAKE STRUCTURE
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lO Palisades Plant c:
-s CD N
(SI PALISADES NUCLEAR PLANT 700 (SI
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- Tab 1e 1 page 1 of 2 Total number of fish collected from traveling screens at the Palisades nuclear power plant from 23 January 1972 to 25 October 1973 TOTAL NUMBER PERIOD OF SPECIES
(%) GREATEST IMPINGEMENT
(<1.0) 9 (< 1 .0) young 42,565 ( 6.5) October, 1972; October, 1973 adult 340. 774 ( 52. 1) Apri 1, 1973 3 (<I . 0)
\6 ( <1 .0) Spring bho salmon 26 (< 1 .o) May-June, 1972 and 1973 (1 nook sa \men 29 (<1.0) June-July, 1973 (young) fake trout 86 (<l ,O) January-March, 1973 i,lake whitefish 28 ( <l . 0) August, 1973 i°Round whitefish 1 (<I. 0) fsrown trout I (<1.0) r
- .Bloater 521 (<1.0) May-August, 1972 and 1973
~
Sme It young 874 (<I . 0) June-August, 1973 adult 6,759 ( l. 0) April-May, 1973 Northern pike l8 (' I . 0) October, 1973 Central mudminnow ( < l . 0)
Carp 17 (<I. 0) Winter Longnose dace 5 ( < 1 . 0)
Spotf in shiner I (<I . 0)
.Spottai I shiner 46,897 ( 7 .2) October-April, 1973; 1 ~Dec.(esp.)
Lake chub 3 ( < I . 0)
River chub 2 (<I . O)
Northern redhorse 1 (< 1.o)
White sucker 395 ( < 1
- 0) December-January, 1973 Longnose sucker 1 ,294 ( < 1 . 0) June, 1973 Channel catfish 168 ( < 1
- O) December-January, 1973
Table 1 page 2 of 2 (cont I nued)
TOTAL NUMBER PERIOD OF SPECIES
(%) GREATEST IMPINGEMENT
... *11 ow bu 11 head 2 (<1.0) f'1 ack bu 11 head 76 ( <1.0) April-June, 1972
.trout-perch 3,485 (<1.0) . Aprl 1-June, 1973; May, 1972 Burbot 513 (<1.0) December-March, 1973 Nine-spine stickleback 409 (<1.0) Apr 11-June, 1972, 1973
- Slimy sculpln 180,303 (27.5) March-Apri 1-May
Pumpkinseed 2 (<1.0)
Bluegill 5 (<1.0)
Perch young I ,084 ( < 1
- 0) October-December, esp. Dec. 1972 adult 27,433 ( 4. 1) May-June, 1972, 1973 Logperch {<1.0)
Johnny darter 27 (<1.0) May, 1972, 1973 Bowfin 54 ( < 1 . *o) February-May , 1972 Total 653,890
TABLE 2 EXPECTED THERMAL PLUME SIZES AT THX 1 HITER DE.PTI!
Table 2 page 1 of Palisades Plant, Covert, ~ic:higan Greatest Estimated Greatest Estimated Average Heat Maximum Heat Release Rate Release Rate 3°FAT Increase - 136\
1 2 Iner**** - 146\
Date (Acres) (Acres) (Acres) 4-30-81 2.7 3.7 3.9 6-01-81 1.2 1.6 1.8 8-18-81 0.5 0.7 0.7 8-19-81 0.3 0.4 0.4 NOTE: 3°F~T thermal plume authorized wider the plant's NPDES permit is 72 acres.
1 From Table l for the month of Harch, the 136i represent* the greatesc est1~ated percentage of the currently permitted maximum heat release rate under estimated average heat release condition*.
2 From Table l for the month of March the 146~ repre*enc the*greatest estimated 9
percentage of the currently permitted maximWll heat release rate under estimated maxi.mum heat release condition*.
R L Fobe*
10/86 MI0986-34RLF-EN03
Figure 4 Palisades Nuclear Plant Evaporative Losses Cooling Water System 9,300 gpm Current Operation 13.39 MGD NPDES permit MI0001457 HYPOCHLORITE PAL02 Cooling Tower Output 380,700 gpm Cooling Tower Blowdown 5,000 gpm Cooling Tower Pump Output 390,000 gpm DILUTION 50,000 gpm WATER PUMPS HOUSE SERVICE WATER o m 5000 gpm 50,000 gpm 72.00 MGD 16,000 gpm Exchan Out to Lake 18,000 gpm*
58,700 gpm 25.92 MGD 84.53 MGD HOUSE SERVICE Outfall 001 WATER LAKE MICHIGAN PUMPS.
68,000 gpm 97.92 MGD LAKE MICHIGAN INPUT .gpm MGD Intake gpm MGD Discharge gpm MGD P-40 Flowrate 50,000 72.00 Dilution water 50,000 72.00 Evaporation 9,300 13.39 CT Pump Output 390,000 Service water 18,000 25.92 Outfall 001 58,700 64.53 CT Slowdown Flow 5,000 (Max = 45,000 gpm) Total Intake 68,000 97.92 Total 68,000 97.92 Service Water Flow 18,000 25.92 P-40 Bypass Flow 0 (Max = 45,000 gpm) KFBieszke Eva oration losses 9300 13.39 05/12/99
Figure 5 Palisades Nuclear Plant Evaporative Losses Cooling Water System 9,300 gpm Proposed Modification 13.39 MGD Dilution water increase NPDES permit Ml0001457 HYPOCHLORITE Cooling Tower Output 380,700 gpm Cooling Tower Slowdown 5000 gpm Cooling Tower Pump Output 390,000 gpm WATER 85,000 gpm PUMPS HOUSE SERVICE WATER o m 5000 gpm 85,000 gpm 122.40 MGD 18,000 gpm Out to Lake 18,000 gpm 93,700 gpm 25.92 MGD 134.93 MGD HOUSE SERVICE Outfall 001 WATER LAKE MICHIGAN PUMPS 103,000 gpm 148.32 MGD LAKE MICHIGAN INPUT gpm MGD Intake gpm MGD Discharge gpm MGD P-40 Flowrate 85,000 122.4 Dilution water 85,000 122.40 Evaporation 9,300 13.39 CT Pump Output 390,000 Service water 18,000 25.92 Outfall 001 93,700 134.93 CT Blowdown Flow =
5,000 (Max 45,000 gpm) Total Intake 103,000 148.32 Total 103,000 148.32 Service Water Flow 18,000 25.92 P-40 Bypass Flow o (Max = 45,000 gpm) KFBieszke Eva oration losses 9 300 13.39 05/12199
- TABLE3 Expected Heat Release To Lake Michigan. Under Proposed Modification **.*
Month/yr Outfall 001 Outfall 001 Inlet Temp Temp. DifT. Heat Release Max Flow Temp (F) (F) (Delta T, F) (Million .
(mgd) BTU/Hr)
Jan 98 127.7 82 35 47 2083 Feb 98 127.7 76 36 40 1773 Mar98 127.7 83 37 46 2039 Apr97 127.7 87 42 45 1994 May97 127.7 90 48 42 1862 June 98 127.7 86 61 25 1108 July 98 127.7 97 70 27 1198 Aug98 127.7 100 66 34 1507 Sept 98 127.7 97 67 30 1330 Oct 98 127.7 94 56 38 1684 Nov. 98 127.7 90 49 41 1817 Dec. 98 127.7 63 44 19 842 Worse Case Heat Release To Lake Michigan Under Proposed Mod.
Month/Yr Outfall 001 Outfall 001 Inlet Max Temp DifT. Heat Release Max Flow Max Temp Temp (Ff ( DeltaT, F) (Million (mgd) (F) BTUs/hr)
Jan 98 127.7 92 38 54 2393 Feb 98 127.7 89 42 47 2083 Mar98 127.7 97 46 51 2260 Apr97 127.7 97 51 46 2039 May97 127.7 97 50 47 2083 June 98 127.7 107 75 32 1418
Worse Case Heat Release To Lake Michigan Under Proposed Mod. *\\
July 98 127.7 109 77 32 1418 Aug 98 127.7 108 76 32 1418 Sept 98 127.7 106 67 39 1728 Oct 98 127.7 101 68 33 1463 Nov98 127.7 99 57 42 1862 Dec 98 127.7 99 50 49 2172
ATTACHMENT _2 Consumers Energy Company Palisades Nuclear Plant MARKED UP COPIES OF 3/30/98 PLANT PERMIT APPLICATION PAGES UPDATED PLANT FLOW DIAGRAM
Plant Intake
~ MGD 134. ~to L*ke Mtohl"'
Outfall 001 1
i EXIBIT 1-11 Schematic of Water Flow 1 Consumers Energy company 1 Palisades Nuclear Plant NPDES Permit MI0001457 I 1
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I Plant Intake I I I I Screens I L ___ L __ _ I I I I I I I I I I I I I J Evaporation I Evaporation J I Feedwater I I I 6.7 MGD 6.7 MGD J t Heater Train J_+---
I IO N
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Condensate _l_ _ _ __J I Tank T-2
~I I Make-up I I Water System 1 - - - - - - - - ---~ I
- - - - - - - - - - ---~ ~
I Primary Primary System Demineralized ~~ Utility Water Make-up Storage Water Storage -- Storage Tank T-91 Tank T-90 Tank T-939 Tank T-91 t~-------------------~
Continuous Flow I I Domestic Water I lntermittant Flow - - - -+
Deep well > - I-1 I System
~ Drain Field Revised 4/27/99 KFBieszke
DEl .w:s~gE~A~E~~SC~An~l~E i~~R~el~a;~1~~T~ON 1
SECTION Ill - Industrial and Commercial Wastewater A. Facility Information Section Ill is to be completed by all facilities classified aslndustrial or Commercial facilities. Industrial and Commeroal facilities include facilities that discharge or propose to. discharge a wastewater generated by a production process or service provided or through a remediation pro1ed. Municipal and oublic facilities are not reQuired to complete Section Ill (unless reques!Jng authorization for discharges other than sanitary wastewater).
- >LEASE TYPE OR PRINT i FACILITY NAME NPDES PERMIT or COC NUMBER
- consumers Energv Comoanv. Palisades Nuclear Plant 0001457 I 1.
BUSINESS INFORMATION A. Provide up to four (4) Standard Industrial Claaslftc:atlon (SIC) eodes, in order of economic import.nee, which belt describe the m*jor products or services provided by this t.cility.
- 11. 12. 13. I
._4_9_1_1_ _ _...i..._ _ _ __..._ _ _ _ _...__ _ _ _....i 4.
- a. Indicate if this facility is a primary industry (refer to Table 2 to detennine if this facility is a primary industry).
~
- Yes, Thia facility is a pnmary industry. Indicate tl'le primary industry as identified in Table 2 in the appendix: Stearn Electric Generator 0 No, This hlcility ts not a prinwy industry, continue With Item C.
C. Do you oper9te a concennted miimal feeding opermion or an aquatic *nimlll production t.c:illty?
0 Yea. Contact the *ppropriata district office (see Peges 2 and 3 in the appendix).
S No, Continue below.
- 2. WATER SUPPLY ANO DISCHARGE TYPE A List all water sources and provide average flows. The volume may be estimated from water supply meter readi.ngs. pumo capacities. etc:..
Provide tne name of the source where appropnate (i.e .. Grand River, Lake Michigan. City of Millpond). The units are as follows: MGO (million gallons per day). MGY (million gallons per year). GPO (gallons per day). If you are reporting in another unit, seled the box with the blank following it and provide the units in the underlined area. If necessary, provide I written description as an attachment on 8 112" x 11" i:iaper.
Name of Source A1191'aO* Volume or Flow Ram (Indicate units)
UMGD DMGY Municip*I Supply: NIA 0GPD 0
~MGO WMGY Surface Water Intake: Lake Michigan 148.3 0GPO 0
~MGD UMGY Priv*te Well: Groundwater .053 0GPD 0
~MGD UMGY Other ( spedfy) Sanitary Wastewater .053 0GPD 0 B. Identify water discharged by tl'le facility and provide average flows. If water is first used for one purpose and then is subsequently used for another purpose. indicate the type and amount of the last use. For example, if water is initially used for noncontact cooling water and then for process w1ter. indicate the amount of process water. The amount of water from sources should approximate the amount of water usage. If they are different. provide an explanation Aven1 e Flow Rate Aven1 e Flow Rate Noncontac:t Cooling
- stands for Ground Water Clean-Up, HPTW
- Revised as of Apri 1 29, 1999 15 EQP 4659-C (Rev 1198)
w:s~gE~A~~~~SCH;.:'~'~E'i~~R~1~-;Pt7~~~1ON SECTION Ill - Industrial and Commercial Wastewater
- 8. Outfall Information Complete a separate Section 111.B. *Outfall Information (pages 17-24) for each outfall at the facility. Make copies of this blank section of the application if necessary.
PLEASE TYPE OR PRINT FACILITY NAME Consumers Energv Cornoanv. Palisades Nuclear Plant I NPDES PERMIT or CCC NUMBER MIOOOl457 I OUTFALL NUMBER OOA
- 3. OUTFALL INFORMATION South CT Overtlow Receiving Water NIA (Internal discharge to Mixing Basin)
A. Receiving Water:
B. County/Township:
County Van Buren I Township Covert SE 1,.. I NW 114 I Section 05 ITown 02S I Range 17W I
C. State Planar Coordinates:
Latitude Longitude
- 0. Latitude/Longitude: 42° 19' 23" 86° 18' 56" E. Type of Wastewater Discharged (Chedc all that apply):
D Contact Cooling 0 Sanitary Wastewater 0 Storm Water (regulated) 0 Other
- specify a Noncontact Cooling 0 Proceu Wastewater 0 Storm Water (not ~ulated)
F. Is this a Seasonal Discharge?
0 Yes - List the discharge periods (by month) in the space provided below. ~ No
- Continue with item G 1*~m 1Th-* I From I Through From Through I From I Through I
G. Discharge Schedule (Yearly Average): I 24 hours/day I 365 days/Year I H. Expected or Proposed Dischar'Qlt Flow Rates:
Total Vearty Daily Minimum Daily Average Daily Maximum Maximum Design Flow Rate
- 25000 MGY 8.64 MGD *66.2 MGD *74.2 MGO *74.2 MGD
- 74.2 0 ~ MGD D MGY 0 I. The maximum discharge tlow rate to be authorized In the permit GPO J. Does this discharge contain storm water subject to elTluent guidelines?
0 Yes
- indicate under which category. g No
- Revised as of April 27, 1999 17 EQP 4659-C (Rev 1198)
I Michigan Depart.of Environmental Quality- Surface Water.lity Division WASTEWATER orSCHARGE PERMIT APPLICATION
/ SECTION Ill - Industrial and Commercial Wastewater B. Outfall Information 1' Complete a separate Section 111.B. *Outfall Information (pages 17-24) for each outfall at the facility. Make copies of this blank section of the application if necessary.
PLEASE TYPE OR PRINT FACILITY NAME Consumers Energy Comoanv. Palisades Nuclear Plant I NPDES PERMIT or COC NUMBER MIOOOl457 I OUTFALL NUMBER OOB
- 3. OUTFALL INFORMATION North CT Overflow Receiving Water NIA (Internal discharge to Mixing Basin)
A. Receiving Water:
B. County/Township:
County Van Buren I Township Covert C. State Planar Coordinates: SE 1/41 NW 1141 Section 05 I Town 02S I Range 17W
- 0. Latitude/longitude:
Latitude 42° 19' 23" I Longitude 86° 18' 56" E. Type of Wastew.ter Olsch*rged (Chedc aH that apply):
0 Contact Cooling 0 Sanitary Wastewater 0 Storm Water (regulated) 0 Other* specify 18 Noncontact Cooling 0 Process Wastewater 0 Storm Water (not regulated)
F. Is this a Seasonal Discharge?
0 Yes - List the discharge periods (by month) in the space provided below. 18 No
- Continue with item G IThR>~* I r~ I ThR>~*
From From Through IFrom Thn>"gh I
G. Discharge Schedule (Yearly Average): 1 24 hours/day I 365 days/year I H. Expected or Proposed Discharge Flow Rates:
Total Yearly Daily Minimum Daily Average Daily Maximum Maximum Design Flow Rate
- 74.2 MGD I. The maximum discharge llow rate to be authorized in the permit:
- 74.2 U GPO ~ MGD C MGY 0 --
J. Does this discharge contain storm water subject to effluent guidelines?
0 Yes. indicate under which category. ~No
- Revised as of April 27, 1999 17 EQP 4659-C (Rev 1198)
9 1 1 w:~~ E~ATERt llcHA~ ~E i~-~R~1~a;~Pa*;~~o N
/ SECTION Ill - Industrial and Commercial Wastewater B. Outfall Information implete a separate Section 111.B. - Outfall Information (pages 17-24) for each outfall at the facility. Make copies of
- s blank section of the application if necessary.
EASE TYPE OR PRINT ACIUTY NAME NPDES PERMIT or COG NUMBER OUTFALL NUMBER Consumers Enemv Comoanv. Palisades Nuclear Plant MIOOO 1457 on I OUTFALL INFORMATION M.L'illlg 8 asm Receiving Water A. Receiving Water. Lake Michigan B. County/Township:
County Van Buren I Townshii>
Covert C. Stat* Planar Coordinates: SE 1/4 I NW 1/41 Section 05 I Town 02S l Range 17W
- 0. L.atltude/Long~ude:
Latitude 42° 19' 23" I Longitude 86° 18' 56" E. Type of Wastewater Dlsctiarged (Check all that apply):
~ Contact Cooling 0 Sanury Wastewater ~ Storm Water (regulated) 0 Other - specify ~~~~~~~-
~ Noncontact Cooling ~ Process Wastewater 0 Storm Water (not regulated)
F. I* tl'lia a Seasonal Discharge?
0 Yes - Uat the discharge period* (by month) In the apace provided below. a No - Continue with item G I Througn Through I Through G. Diactlarge Schedule (Yearly Average): 24 hours/day I 365 daystyear I H. E.xoected or Prooosad o*1sc:tiarge Fl ow Rates:
Total 'r'earty Daily Minimum Daily Average Daily Maximum Muimum Design Flow Rate
- 135 .2 *135. 2 MGY MGO MGD MGD MGD
- 135.2 I. The maximum discharge flow rate to be authorized in the permit - - - - - 0 GPO ~ MGD 0MGY 0 J. Does this discharge contain storm water aubjeet to etnuent guidelines?
8l Yes. indicate under which category. Stearn Electric 0 No
- Revised as of Apri 1 29, 1999 17 EQP 4659-C (Rev 1/98)
~I Michigan DepartmeAEnvironmental Quality- Surface Water aA Division WASTEWATE~ISC.HARGE PERMIT APP!iCATION SECTION Ill - Industrial and Commercial Wastewater B. Outfall Information
- omplete a separate Section 111.B. *Outfall lnfonnation (pages 17-24) for each outfall at the facility. Make copies of his blank section of the application if necessary.
"LEASE TYPE OR PRINT FACILITY NAME NPDES PERMIT or COC NUMBER OUTFALL NUMBER Consumers Energv Comoanv. Palisades Nuclear Plant rvnooo 1457 OOF
- 3. OUTFALL INFORMATION me ::iumo Receiving Water NIA (Internal discharge to Mixing Basin)
A. Receiving Water:
B. County/Township:
County Van Buren I Township Covert SE 1'"' I NW 1/41 Section 05 I Town IRange 17W C. State Planar Coordinates:
O. Latitude/Longitude:
Latitude 42° 19' 23" I Longitude 02S 86° 18' 56" E. Type of Wastewater Discharged (Check 111 that apply):
0 Contad Cooling 0 Sanitary Wastewater 0 Storm Water (regulated) 0 Other - specify - - - - - - - -
0 Noncontact Cooling a Proceu Wutawater 0 Storm Water (not regulated)
F. Is this a Seasonal Discharge?
0 Yes - List the diScharge periods (by month) in the space provided below. 8 No - Continue with item G I From IThrough Through I Through G. Oisch*rge Schedule (Yearty Average): 24 hou"'d*y I 365 d*ystye*r I H. Expected or P roposed o*IS charge Flaw Rates:
Total Yearly Daily Minimum Daily Average Daily Maximum Maximum Design Flow Rate 36.5 MGY 0 MGD
- 0.050 MGD 0.1 MGD 0.1 MGD I. The maximum discharge flow rate to be authorized in the permit: _ _o_._l_ __ D GPO ~ MGD D MGY 0 J. Does this discharge contain storm water subjed to effluent guidelines?
0 Y_es ~indicate under which category. ~No
- Revised as of April 27, 1999 17 EQP 4659-C (Rev 1198)