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Category:E-Mail
MONTHYEARML24032A2442024-02-0101 February 2024 OEDO-24-00011 - 10 CFR 2.206 Petition Holtec Misuse Decommissioning Fund- Email to Petitioner ML24005A1262024-01-0505 January 2024 Permanently Defueled Emergency Plan Implementation Notification ML23055A1532023-02-24024 February 2023 Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report ML22343A2282022-12-0909 December 2022 Acceptance Review: Palisades Proposed Exemption from 10 CFR 50.54(w)(1) - Onsite Property Damage Insurance ML22343A1902022-12-0909 December 2022 Acceptance Review: Palisades Proposed Exemption from 10 CFR 140.11 (a)(4) Primary and Secondary Liability Insurance ML22284A0502022-10-0707 October 2022 Acceptance Review: License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML22227A0082022-08-12012 August 2022 Acceptance Review: Exemption Request from 10CFR50.47(b), 10 CFR 50.47(c)(2), and 10 CFR Part 50, Appendix E, Section IV ML22227A0092022-08-12012 August 2022 Acceptance Review: License Amendment Request to Revise Emergency Plan and Emergency Action Level Scheme (L-2022-LLA-0099) ML22179A0752022-06-28028 June 2022 E-mail from Entergy Dated June 28, 2022, Notification of Palisades and Big Rock Point License Transfer (EPIDs L-2022-LLM-0002 and L-2020-LLM-0003) ML22159A2672022-06-0202 June 2022 Answers to Your Questions on Palisades ML22159A2652022-05-0303 May 2022 Questions Asked at Palisades Plant Performance Public Meeting April 26, 2022 ML21328A0062021-11-18018 November 2021 NRR E-mail Capture - (External_Sender) State of Michigan Response - Palisades Nuclear Plant and Big Rock Point Plant - Application for Order Consenting to Transfers of Licenses and Conforming License Amendments ML22208A1052021-11-16016 November 2021 NRR E-mail Capture - (External_Sender) State of Michigan Response - Palisades - Preparation for Issuance of Final Environmental Assessment and Finding of No Significant Impact Holtec Exemption Request to Use Dtf ML21309A5152021-11-0505 November 2021 NRR E-mail Capture - Palisades Nuclear Plant - Preparation for Issuance of Final Environmental Assessment and Finding of No Significant Impact Holtec Exemption Request to Use Dtf ML21309A2982021-11-0505 November 2021 NRR E-mail Capture - Palisades Nuclear Plant and Big Rock Point Plant - Application for Order Consenting to Transfers of Licenses and Conforming License Amendments ML21209A9802021-07-28028 July 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of Requested Licensing Action, Rescission of Interim Compensatory Measure from Order EA-02-026 ML21189A2462021-07-0606 July 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of Requested Licensing Action, Proposed Partial Exemption from Record Retention Requirements ML21189A0432021-07-0606 July 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of Requested Licensing Action, Permanently Defueled Technical Specifications ML21054A1822021-02-23023 February 2021 NRR E-mail Capture - Regarding Public Comment on Palisades Request for Relief RR 5-8 ML21028A4092021-01-27027 January 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of Holtec Exemption Request from 10CFR50.82(a)(8)(i)(A) and 10CFR50.75(h)(1)(iv) ML21028A0552021-01-27027 January 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of License Transfer Application ML21007A3752021-01-0707 January 2021 NRR E-mail Capture - Regarding Public Comment on Palisades Nuclear Plant License Transfer (Sierra Club Nuclear Free Michigan) ML21054A1812021-01-0606 January 2021 NRR E-mail Capture - (External_Sender) Regarding Public Comment on Palisades Request for Relief RR 5-8 ML20275A3432020-10-0101 October 2020 Verbal Authorization for Proposed Alternative (RR 5-8) Reactor Vessel Closure Head Penetration Repairs ML20272A0112020-09-26026 September 2020 Request for Additional Information - Palisades Relief Request RR 5-8 (Proposed Alternative) for Reactor Pressure Vessel Head Penetration Repairs ML20262G9622020-09-17017 September 2020 Acknowledgement to Mr. Muhich e-mail, Dated September 15, 2020 (e-mail) ML20241A1802020-08-27027 August 2020 NRR E-mail Capture - Palisades Nuclear Plant- Upcoming Steam Generator Tube Inservice Inspection ML20162A4522020-04-0808 April 2020 Lake Mich Level Correspondence with Ipotter ML19344C7162019-08-25025 August 2019 Response from NEIMA Local Community Advisory Board Questionnaire 08-25-2019 C Ferry ML19344C8072019-08-16016 August 2019 Scanned Response 09-29-2019 I Potter ML19226A2932019-08-14014 August 2019 NRR E-mail Capture - Request for Additional Information Re License Amendment Request to Adopt TSTF-425, Revision 3 for the Palisades Nuclear Plant ML19226A2922019-08-0505 August 2019 NRR E-mail Capture - Draft Request for Additional Information for Palisades License Amendment Request to Adopt TSTF-425 ML19122A4852019-04-29029 April 2019 NRR E-mail Capture - Request for Additional Information for Palisades License Amendment Request to Revise License Conditions Related to NFPA 805 Modifications ML19095A6572019-04-0505 April 2019 NRR E-mail Capture - Acceptance for Review of Application to Revise the Palisades Nuclear Plant License Renewed Facility Operation License Regarding Full Compliance Implementation Date for the Fire Protection Program ML19059A1782019-02-28028 February 2019 Acceptance Review Results for Relief Request No. EN-19-RR-1 to Use ASME Code Case N-831-1 for Entergy Fleet ML19059A0292019-02-27027 February 2019 NRR E-mail Capture - Acceptance Review Results for License Amendment Request to Adopt TSTF-529, Revision 4, Clarify Use and Application Rules, for Entergy Fleet ML19009A5392019-01-0909 January 2019 NRR E-mail Capture - Request for Additional Information for Palisades License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement 3.3.5.2a ML19009A5382018-12-12012 December 2018 NRR E-mail Capture - Draft Request for Additional Information for Palisades License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement 3.3.5.2a ML18337A1382018-11-30030 November 2018 NRR E-mail Capture - Request for Additional Information Related to Palisades Relief Request Number RR 5-7 ML18337A1352018-11-30030 November 2018 NRR E-mail Capture - Acceptance for Review of Application to Revise the Palisades Nuclear Plant License Renewed Facility Operation License Regarding Changes to the Fire Protection Plan ML18337A1402018-11-29029 November 2018 NRR E-mail Capture - Draft Request for Additional Information Related to Palisades Relief Request 5-7 ML18184A2402018-07-0303 July 2018 NRR E-mail Capture - Acceptance for Review of Application to Revise Technical Specification Surveillance Requirement 3.3.5.2a for the Diesel Generator Undervoltage Start ML18101A1132018-04-11011 April 2018 NRR E-mail Capture - Palisades Nuclear Plant - Request for Additional Information Regarding Proposed Alternative for Relevant Condition ML18081A2962018-03-22022 March 2018 NRR E-mail Capture - Palisades Nuclear Plant - Request for Additional Information Regarding Proposed Changes to Site Emergency Plan for Permanently Defueled Condition (CAC MG0198: EPID L-2017-LLA-0305) ML18059A8202018-02-28028 February 2018 NRR E-mail Capture - Palisades Nuclear Plant - Request for Additional Information Regarding Proposed Alternative for Relevant Condition ML17355A0092017-12-20020 December 2017 NRR E-mail Capture - Palisades Nuclear Plant: Acceptance Review for Relief Request No. RR 5-6 - Alternative to the Reexamination Frequency for a Relevant Condition ML17345A0142017-12-0808 December 2017 NRR E-mail Capture - Acceptance Review Results Entergy Request No. EN-17-RR-1 ML17338B1242017-11-30030 November 2017 NRR E-mail Capture - (External_Sender) Palisades Nuclear Plant Flood Hazard Reevaluation Report FHRR Staff Assessment Input ML17335A1042017-11-30030 November 2017 NRR E-mail Capture - Palisades Nuclear Plant - RAI Regarding Proposed Changes to Administrative Controls Section of the Technical Specifications for Permanently Defueled Condition (CAC MG0021; EPID L-2017-LLA-0266) ML17317A0042017-11-0909 November 2017 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance Review for License Amendment Request to Change the Full Compliance Implementation Date for the Fire Protection Transition License Condition 2024-02-01
[Table view] Category:Report
MONTHYEARPNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.822023-09-28028 September 2023 Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82 ML23087A0392023-05-0202 May 2023 PSDAR Comment Resolution PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023 Regulatory Path to Reauthorize Power Operations CNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021 Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L PNP 2020-039, 10 CFR 71.95 Report Involving 3-608 Cask2020-11-20020 November 2020 10 CFR 71.95 Report Involving 3-608 Cask ML20272A1662020-09-30030 September 2020 Attachment 3 - Framatome Document No. ANP-3876, Revision 1Q1NP, Response to NRC Request for Additional Information of Palisades Relief Request Number RR 5-8, Repair of Reactor Pressure Vessel Head Penetration, Inservice Inspection Program, ML20267A3912020-09-22022 September 2020 Attachment 4, Framatome Document No. 51-9292503-002, Palisades CEDM Nozzle Idtb Repair - Life Assessment Summary PNP 2019-001, Request for Deferral of Actions Related to a Beyond-Design-Basis External Seismic Event2019-03-20020 March 2019 Request for Deferral of Actions Related to a Beyond-Design-Basis External Seismic Event ML18354B1332019-01-17017 January 2019 Staff Assessment of Flood Focused Evaluation ML18330A1432018-11-26026 November 2018 Relief Request Number RR 5-7, Proposed Alternative to ASME Section Xi Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations ML18330A1462018-11-24024 November 2018 Framatome, Document No. 51-9292503, Palisades CRDM & Ici Nozzle Idtb Repair - Life Assessment Summary ML18270A3232018-09-27027 September 2018 Attachment 2: Probabilistic Risk Assessment Technical Adequacy PNP 2018-036, Revised Mitigating Strategies Assessment for Flooding Pursuant to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1: Flooding of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2018-09-25025 September 2018 Revised Mitigating Strategies Assessment for Flooding Pursuant to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1: Flooding of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident PNP 2018-041, Focused Evaluation Pursuant to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1: Flooding of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2018-09-25025 September 2018 Focused Evaluation Pursuant to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1: Flooding of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident PNP 2016-066, Special Report for Inoperability of High Range Noble Gas Monitor2016-12-20020 December 2016 Special Report for Inoperability of High Range Noble Gas Monitor PNP 2016-042, Annual Status Notification in Response to Confirmatory Order, EA-14-0132016-06-16016 June 2016 Annual Status Notification in Response to Confirmatory Order, EA-14-013 ML16048A3442016-02-10010 February 2016 Annual Fatigue Reporting Form 2015 ML15351A3522015-12-16016 December 2015 Attachment 1, Compliance with Order EA-12-049 ML15351A3532015-12-16016 December 2015 Attachment 2, Order EA-12-049 Compliance Elements Summary ML15351A3542015-12-16016 December 2015 Attachment 3, Audit Open Item Responses ML15351A3552015-12-16016 December 2015 Attachment 4, Interim Staff Evaluation Open Item and Confirmation Item Responses ML15351A3622015-12-16016 December 2015 Attachment 6, System Operating Procedure 23, Plant Heating System, Attachment 14, Actions When Outside Temperatures Are Less than 20 Degrees Fahrenheit. ML15351A3602015-12-16016 December 2015 Attachment 5, Final Integrated Plan PNP 2015-066, Submittal of Report on the 8-120B Cask2015-08-20020 August 2015 Submittal of Report on the 8-120B Cask PNP 2015-058, Technical Specification Required Report2015-08-0404 August 2015 Technical Specification Required Report PNP 2015-037, Appendix a, Computer Files Listing, File No. 1200895.306, Revision 12015-05-22022 May 2015 Appendix a, Computer Files Listing, File No. 1200895.306, Revision 1 ML15147A6192015-05-22022 May 2015 Enclosure 2, Corrected Documentation for Relief Request Number RR 4-18 ML15147A6182015-05-22022 May 2015 Appendix a, Computer File Listing, File No. 1400669.323, Revision 0 ML15147A6172015-05-22022 May 2015 Enclosure 1, Relief Request Number RR 4-21 Proposed Alternative, in Accordance with 10 CFR 50.55a(z)(2), Hardship Without a Compensating Increase in Level of Quality and Safety PNP 2015-018, Areva, Inc., 51-9226987-000, Palisades Nuclear Plant Flooding Hazard Re-Evaluation Report.2015-02-25025 February 2015 Areva, Inc., 51-9226987-000, Palisades Nuclear Plant Flooding Hazard Re-Evaluation Report. PNP 2014-108, Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.2014-12-18018 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima. PNP 2014-051, Response to May 1, 2014 Request for Additional Information for License Amendment Request to Revise Emergency Response Organization Staff Augmentation Response Times2014-07-16016 July 2014 Response to May 1, 2014 Request for Additional Information for License Amendment Request to Revise Emergency Response Organization Staff Augmentation Response Times PNP 2014-038, Special Report for Inoperability of High Range Noble Gas Monitor2014-04-14014 April 2014 Special Report for Inoperability of High Range Noble Gas Monitor PNP 2014-033, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from The.2014-03-31031 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from The. ML13365A2642014-02-10010 February 2014 Interim Staff Evaluation Regarding Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14030A2072014-02-0606 February 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Palisades Nuclear Plant, TAC No.: MF0768 PNP 2013-072, Report of Changes, Tests and Experiments and Summary of Commitment Changes2013-10-14014 October 2013 Report of Changes, Tests and Experiments and Summary of Commitment Changes PNP 2013-063, Unsatisfactory Laboratory Testing Report2013-09-18018 September 2013 Unsatisfactory Laboratory Testing Report ML13242A1592013-08-29029 August 2013 Addendum to the Results of Independent Samples Collected by the NRC at Palisades Nuclear Plant Storm Drain Outfall ML13295A4502013-07-31031 July 2013 WCAP-15353-Supplement 2-NP, Rev. 0, Palisades Reactor Pressure Vessel Fluence Evaluation. PNP 2013-046, Updated Palisades Nuclear Plant Reactor Vessel Fluence Evaluation2013-06-25025 June 2013 Updated Palisades Nuclear Plant Reactor Vessel Fluence Evaluation PNP 2013-027, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2013-04-10010 April 2013 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application ML14316A2082013-02-28028 February 2013 Attachment 5 - Westinghouse WCAP-17651-NP, Revision 0, Palisades Nuclear Power Plant Reactor Vessel Equivalent Margins Analysis ML13295A4512013-02-28028 February 2013 WCAP-17651-NP, Rev. 0, Palisades Nuclear Power Plant Reactor Vessel Equivalent Margins Analysis. ML13038A4402013-02-0707 February 2013 BADGER Test Campaign at Palisades Nuclear Plant ML13295A4492013-01-31031 January 2013 WCAP-17403-NP, Rev. 1, Palisades Nuclear Power Plant Extended Beltline Reactor Vessel Integrity Evaluation. ML14316A1992013-01-31031 January 2013 Attachment 3 - Westinghouse WCAP-17403-NP, Revision 1, Palisades Nuclear Power Plant Extended Beltline Reactor Vessel Integrity Evaluation ML12334A0962012-11-27027 November 2012 PLP-RPT-12-00141, Rev. 0, Palisades Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 1 of 3 PNP 2012-101, Flooding Walkdown Report - Response to NRC Request for Information Pursuant to 10CFR50.54(f) the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-27027 November 2012 Flooding Walkdown Report - Response to NRC Request for Information Pursuant to 10CFR50.54(f) the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML12334A0972012-11-27027 November 2012 PLP-RPT-12-0041, Rev. 0, Palisades Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 2 of 3 2023-09-28
[Table view] Category:Miscellaneous
MONTHYEARML23087A0392023-05-0202 May 2023 PSDAR Comment Resolution PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023 Regulatory Path to Reauthorize Power Operations CNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021 Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L PNP 2019-001, Request for Deferral of Actions Related to a Beyond-Design-Basis External Seismic Event2019-03-20020 March 2019 Request for Deferral of Actions Related to a Beyond-Design-Basis External Seismic Event ML18354B1332019-01-17017 January 2019 Staff Assessment of Flood Focused Evaluation PNP 2016-066, Special Report for Inoperability of High Range Noble Gas Monitor2016-12-20020 December 2016 Special Report for Inoperability of High Range Noble Gas Monitor PNP 2016-042, Annual Status Notification in Response to Confirmatory Order, EA-14-0132016-06-16016 June 2016 Annual Status Notification in Response to Confirmatory Order, EA-14-013 ML16048A3442016-02-10010 February 2016 Annual Fatigue Reporting Form 2015 ML15351A3542015-12-16016 December 2015 Attachment 3, Audit Open Item Responses ML15351A3622015-12-16016 December 2015 Attachment 6, System Operating Procedure 23, Plant Heating System, Attachment 14, Actions When Outside Temperatures Are Less than 20 Degrees Fahrenheit. ML15351A3602015-12-16016 December 2015 Attachment 5, Final Integrated Plan ML15351A3552015-12-16016 December 2015 Attachment 4, Interim Staff Evaluation Open Item and Confirmation Item Responses ML15351A3522015-12-16016 December 2015 Attachment 1, Compliance with Order EA-12-049 ML15351A3532015-12-16016 December 2015 Attachment 2, Order EA-12-049 Compliance Elements Summary PNP 2015-066, Submittal of Report on the 8-120B Cask2015-08-20020 August 2015 Submittal of Report on the 8-120B Cask ML15147A6192015-05-22022 May 2015 Enclosure 2, Corrected Documentation for Relief Request Number RR 4-18 ML15147A6182015-05-22022 May 2015 Appendix a, Computer File Listing, File No. 1400669.323, Revision 0 ML15147A6172015-05-22022 May 2015 Enclosure 1, Relief Request Number RR 4-21 Proposed Alternative, in Accordance with 10 CFR 50.55a(z)(2), Hardship Without a Compensating Increase in Level of Quality and Safety PNP 2015-037, Appendix a, Computer Files Listing, File No. 1200895.306, Revision 12015-05-22022 May 2015 Appendix a, Computer Files Listing, File No. 1200895.306, Revision 1 PNP 2014-033, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from The.2014-03-31031 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from The. PNP 2013-072, Report of Changes, Tests and Experiments and Summary of Commitment Changes2013-10-14014 October 2013 Report of Changes, Tests and Experiments and Summary of Commitment Changes PNP 2013-063, Unsatisfactory Laboratory Testing Report2013-09-18018 September 2013 Unsatisfactory Laboratory Testing Report PNP 2013-046, Updated Palisades Nuclear Plant Reactor Vessel Fluence Evaluation2013-06-25025 June 2013 Updated Palisades Nuclear Plant Reactor Vessel Fluence Evaluation PNP 2013-027, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2013-04-10010 April 2013 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application PNP 2012-101, Flooding Walkdown Report - Response to NRC Request for Information Pursuant to 10CFR50.54(f) the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-27027 November 2012 Flooding Walkdown Report - Response to NRC Request for Information Pursuant to 10CFR50.54(f) the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML12334A0962012-11-27027 November 2012 PLP-RPT-12-00141, Rev. 0, Palisades Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 1 of 3 ML12334A0972012-11-27027 November 2012 PLP-RPT-12-0041, Rev. 0, Palisades Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 2 of 3 PNP 2012-102, PLP-RPT-12-0041, Rev. 0, Palisades Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 3 of 32012-11-27027 November 2012 PLP-RPT-12-0041, Rev. 0, Palisades Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 3 of 3 PNP 2012-094, 2012 Steam Generator Tube Inspection Report2012-11-0101 November 2012 2012 Steam Generator Tube Inspection Report PNP 2012-059, 60-Day Reports Per Bulletin 2004-01 and CAL No NRR-07-023 Pressurizer Inspection Results for the 2012 Refueling Outage2012-07-11011 July 2012 60-Day Reports Per Bulletin 2004-01 and CAL No NRR-07-023 Pressurizer Inspection Results for the 2012 Refueling Outage IR 05000255/20110192012-02-14014 February 2012 Final Significance Determination of Yellow and White Findings with Assessment Followup and Notice of Violation NRC Inspection Report Nos. 05000255-11-019 and 05000255-11-020 Palisades Nuclear Plant ML12023A1872012-01-17017 January 2012 EA-PSA-SDP-D11-2-11-07, Rev. 2, SDP Assessment of DC Panel D11-2 Fault, Cover Through Appendix a ML12023A1882012-01-17017 January 2012 EA-PSA-SDP-D11-2-11-07, Rev. 2, SDP Assessment of DC Panel D11-2 Fault, Appendix B Through End ML12006A0712012-01-0505 January 2012 SDP Assessment of DC Panel D-11-2 Fault Palisades ML1134205122011-12-19019 December 2011 Review of the 2010 Steam Generator Tube Inspections During Refueling Outage 21 ML12006A0722011-10-17017 October 2011 Plant Trip During D-11-2 Maintenance Root Cause ML1128705702011-10-14014 October 2011 Report of Changes, Tests and Experiments and Summary of Commitment Changes ML12006A0672011-09-28028 September 2011 SDP Assessment of Service Water Pump P-7C Coupling Failures Part 3 ML1031603372010-11-0909 November 2010 Unsatisfactory Laboratory Testing Report ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1020301642010-04-28028 April 2010 E-Mail. from Dotson to Cassidy, GZA 2007 Report ML0929505252009-10-22022 October 2009 Generator Tube Inspection Report ML0928903362009-10-15015 October 2009 Report of Facility Changes, Tests and Experiments and Summary of Commitment Changes ML0901402872008-07-16016 July 2008 E-mail from Ellegood to M. Chawla Et Al. Palisades SFP Racks with Attachment: Report on Resolution of Outstanding Concerns on Spent Fuel Pit Rack Localized Swelling Palisades Nuclear Plant ML0810000792008-04-0808 April 2008 Request for Enforcement Discretion - Technical Specification 3.8.1 Required Actions F.1 and F.2 ML0717802162007-06-19019 June 2007 Revised Steam Generator Tube Integrity Assessment from the 2006 Refueling Outage ML0719400912006-09-15015 September 2006 Request for Relief from ASME Section Xl Code Requirements for Repair of Pressurizer Nozzle Penetrations (Non-Proprietary) ML0619803382006-07-20020 July 2006 Review of the 2004 Steam Generator Tube Inspection Reports ML0617301112006-06-21021 June 2006 Day Report Per First Revised Order EA-03-009 ML0608203512006-03-20020 March 2006 License Amendment Request: Removal of TSP from Palisades Containment 2023-05-02
[Table view] |
Text
,-John Giessner From: John Ellegood.,
Sent: 'Wi-dnesday,July 16, 2008 8:56 AM,;
To: 'Mahesh Cliawla-; Ross Telson; Christine Lipa; John Giessner; Ross Telson; Christine Lipa; Robert Lerch; Frank.Tran; Thomas Taylor; Kent Wood
Subject:
Attachments: nus-assess-doc-,-sf &cl.-pd f I have attached the earlier analysis done by Entergy to determine the effects of absorber loss on Keff. In addition, I attached the results from the first panel of the first cell. Data has been collected from 4 or 5 more panels but the data has not been analyzed. Based on the shape of the curves, the licensee believes those panels will fail as well.
From: Mahesh Chawla Sent: Wednesday, July 16, 2008 9:23 AM To: Ross Telson; Christine Lipa; John Giessner; John Ellegood; Ross Telson; Christine Lipa; Robert Lerch; Frank Tran; Thomas Taylor
Subject:
FW: Palisades SFP racks FYI From: Lambros Lois Sent: Wednesday, July 16, 2008 8:48 AM To: Mahesh Chawla Cc: Gregory Cranston; Kent Wood
Subject:
RE: Palisades SFP racks Mahesh:
Kent Wood of SRXB is in charge of SFPs and he has this project. I'm forwarding this to Kent.
Lambros Lois.
From: Mahesh Chawla Sent: Wednesday, July 16, 2008 8:30 AM To: Lambros Lois Cc: John Giessner; John Ellegood; Ross Telson; Christine Lipa; Robert Lerch; Frank Tran; Thomas Taylor
Subject:
FW: Palisades SFP racks Lambros, Let me know if you need more information or discussion on this issue. Thanks From: John Ellegood Sent: Wednesday, July 16, 2008 7:25 AM To: Ross Telson; Christine Lipa; Mahesh Chawla Cc: John Giessner; Robert: Lerch; Frank Tran; Thomas Taylor
Subject:
Palisades SFP racks The licensee has some preliminary results from the BADGER testing of the SFP racks. The first panel did not meet the density requirements. The data from the next four panels is in analysis but the preliminary evil indicates they will not pass.
The licensee has an analysis that shows Keff is less than .95 with no credit for the racks provided SFP boron is above 2054. It is at 2732.
I'll keep you posted.
Mac- do you who we spoke with on the SFP swelling rack issue?
John Ellegood 2
Report on Resolution of Outstanding Concerns on Spent Fuel Pit Rack Localized Swelling Palisades Nuclear Plant SUBJECT This report addresses concerns raised by the NRC on the reliability of the Palisades Spent Fuel Pit (SFP) Region I storage racks to maintain fuel in a subcritical condition in accordance with the original rack design as identified in Technical Specification (TS)
Section 4.3.1, and in consideration of the effects of potential neutron absorber localized degradation.
SUMMARY
OF CONCLUSIONS Based on a review of Palisades reports and observations made to date, and as corroborated by rack surveillance evidence elsewhere in the industry, reasonable assurance exists to support the position that the neutron absorber has not degraded in the Region I racks. Furthermore, an internal Entergy assessment provides reasonable assurance that, even if the neutron absorber were to be completely degraded, the 1R19 boron concentration in the SFP cooling water would more than compensate for any possible loss of reactivity holddown.
BACKGROUND Fuel assembly binding in Region I of the Palisades SFP has been observed since 1991 (Reference 1). This binding has been attributed to localized swelling of the Region I SFP racks due to gas buildup within the rack structure. In 1995, Palisades performed a re-evaluation (Reference 2) to update and more fully document the analyses associated with the localized rack swelling. As of this writing there are ten (10) fuel assemblies that cannot be extracted from the Region I racks due to localized swelling.
Since the affected assemblies are generally in isolated rack locations, with only two in adjacent.cells, it is possible to access these cells for testing or venting of the buildup gas, once the surrounding fuel assemblies have been removed. The SFP is completely filled at the present time. Therefore, repair activities are not possible until completion of the next dry cask storage program at Palisades, currently scheduled for spring 2008.
An additional concern regarding future repair work is the caution associated with cutting or grinding in the vicinity of a trapped pocket of hydrogen gas, even under water.
Entergy is reviewing possible approaches to rack maintenance and repair that should minimize risk of inadvertent combustion, but, again, this emphasizes the position that adjacent cells must be empty in order to take action to vent the trapped gas.
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The NRC has voiced concern that the affected Palisades rack cells may be experiencing degradation of neutron holddown, due to potential leakage or slumping of the boron carbide (B4C) neutron absorber within the swollen rack areas. As described in the sections that follow, Entergy has reviewed the engineering bases for the racks and performed a criticality assessment to 'determine the potential impact of absorber degradation.
REVIEW OF RACK ENGINEERING BASES An extensive evaluation was completed by Palisades in support of the Condition Report evaluated in Reference 2. This included input from the B4C manufacturer, the Carborundum Company. Some of the general conclusions of the report are:
- There was visible evidence of an unidentified black material leaching through the vent holes. This could represent a small loss of B4C material. However, because the vent holes are near the tops of the cells and the amount of observed material is small, the impact of any B4C material loss is expected to be very slight.
- The Carborundum Co has reviewed the data (as reported in Reference 3) and concluded that the black material is very likely a boron compound but notes that boron leachability over time is relatively low, although there is no test data to document leaching over a 10-15 year time span.
- There are no vent holes at the base of the racks. Thus, a slow discharge of degraded B4C material, with its inherent loss of reactivity holddown, is not considered a credible scenario.
In addition, interviews with Engineering personnel confirm that the actual locations of the vent holes are below the tie plate, but slightly above the active core height.
Therefore, if the all the interior B4C above the vent were to leak through the holes, there would be an insignificant amount of reactivity holddown degradation in the active fuel region.
Because Palisades does not have rack material surveillance coupons, Palisades has requested supporting information from the Kewaunee plant, which uses a similar B4C rack design and Which has an active surveillance plan. Kewaunee responded (Reference
- 4) by stating that other than some possible B4C dust leakage and some observed chipping (most likely due to the effects of handling), there was no visible degradation of the B4C material. However, as Kewaunee does not test for brittleness, they were unable to confirm that B4C would not degrade under long-term temperature and radiation exposure. Therefore, it reasonable and conservative to assume at least some degree of B4C degradation over time.
As noted above, there are no vent holes at the rack base to permit egress of degraded B4C. As the majority of the racks remain in their original configuration, we can conclude that, except for the swollen racks, the B4C remains in place. For the swollen Page 2 of 5
rack locations, it is conceivable to consider a B4C "slumping" effect, in which the degraded neutron absorber, now in powdered form, sinks to a lower level inside the racks, as would a liquid. Realistically, the maximum amount of slumping would reduce the absorber height to no lower than approximately 80% of its original position.
However, because slumping to that degree could remove neutron absorber function in the very top of the affected rack locations, Entergy has elected to perform a criticality assessment, considering the potential for B4C loss and crediting SFP boron concentration to compensate.
CRITICALITY ASSESSMENT In order to provide assurance that k-effective was remaining within the limits of design basis assumptions, Entergy has completed a criticality assessment, with SFP boron concentration credited for reactivity holddown in lieu of B4C. Although the criticality analysis of record (AOR) takes no credit for SFP boron in the Region I rack area, the assessment provides assurance that a k-effective below 0.95 will be maintained until such time as rack repairs may be performed.
The criticality analysis was prepared using the existing model of the Palisades Region I racks from the AOR (Reference 5). Note well: The MONK computer code, used previously for the criticality analysis, is no longer available. Therefore, the racks were modeled using the CASMO series of modeling codes (Reference 6), which are compatible with the rack model used by MONK. CASMO-4 was used for the calculated criticality values, with an independent check on CASMO-3 for each Eigenvalue.
However, Entergy is not licensed to use CASMO for design basis calculations: therefore, the results that follow must be considered as an assessment, suitable for operability determination, rather than a formal calculation.
Assumptions associated with the criticality assessment are as follows:
The model takes no credit for B4C reactivity holddown. In other words, it assumes complete degradation of all neutron absorber and its replacement in the gap by B4C off-gas. This is an extremely conservative position, but is retained as it (1) provides a more straightforward model and (2) bounds the current conditions; Because the U-235 enrichment is a nominal one, several cases were repeated for an actual enrichment of 5.00 w/o, which is the nominal value of 4.95 w/o U-235 plus a manufacturing uncertainty of 0.05 w/o;.
- In order to establish the most conservative conditions, an additional case was run with the gap filled with water instead of gas.
Page 3 of 5
The code was run for a variety of SFP boron concentrations. The most significant of these are 1720 ppm, which is the minimum SFP boron concentration required by the Palisades Technical Specification 3.7.15 (Reference 8) and 2550 ppm, which is the 1R19 refueling boron concentration. 2550 ppm is also a procedural minimum (Reference 9) for normal operation in Modes 1-4, required to ensure core subcriticality after a design basis seismic event. For normal operation in Modes 5 and 6, a procedural minimum SFP boron concentration of 1800 ppm is specified.
With these considerations in mind, the results of the criticality assessment are as follows Results are in units of k-inf, which is criticality in infinite array, and bounds (i.e. is always greater than) k-effective:
- 1. The k-inf for Region 1, crediting a 1720 ppm boron concentration in the SFP, is below 0.98.
- 2. The k-inf for Region 1, crediting an 1800 ppm boron concentration in the SFP, is below 0.98.
- 3. The k-inf for Region 1, crediting a 2550 ppm boron concentration in the SFP, is below 0.92.
- 4. The SFP boron concentration corresponding to a k-inf of 0.95 is approximately 2054 ppm.
- 5. These conclusions remain valid if the gas within the rack is replaced by unborated water.
- 6. Increasing enrichment from 4.95 w/o to 5.00 w/o U-235 results in a slight increase in k-inf, across a range of 0.0015 to 0.0027.
Therefore, based on the engineering review and criticality assessments described above, it is reasonable to conclude that B4C degradation, in the Region 1 affected areas, is likely to be very slight. However, any degree of degradation, up to and including complete loss of neutron absorber, is not expected to result in an increase of k-effective above 0.95 while the SFP boron concentration remains at or above the procedural minimum of 2550 ppm. /
Written by:
Reviewed by:
Page 4 of 5
REFERENCES
- 1. Palisades Deviation Report D-PAL-91-015H
- 2. Palisades Condition Report C-PAL-95-0343
- 3. Consumers Power Co Memorandum SEL94*008, Lucier to Krueger, "NUS Spent Fuel Pool Rack Boron Carbide Neutron Absorber Information," 6/13/94
- 4. E-Mail from Jeffery Ladewig (Kewaunee) to G. T. Wiggins (Palisades) 9/19/07
- 5. Palisades Calculation EA-SFP-97-02, "Region I Fuel Pool Criticality Calculations," 3/27/00
- 6. Computer codes CASMO-4 and CASMO-3
- 7. Palisades Technical Specification 4.3
- 8. Palisades Technical Specification 3.7.15
- 9. Palisades Procedures COP-27, COP-27-Basis, SOP-27, SFPO-3, DWC-11 D, DWC-11 D-Basis, PCSO-5, GOP-2
,1 Page 5 of 5
Pallisades Initial Data Analysis m Qualitative Analysis The following analysis shows the comparison of the calibration scan data with the first scan for the Pallisades neutron absorber test. Preliminary analysis shows that, for the first panel scanned, we must reject the hypothesis that this panel meets the minimum certified areal density value with 95% certainty.
For the individual elevation count rates, the uncertainty is Calculated as +/-
- t where oa- Counts and t Count Time. This bounds the count rate with 95% certainty based upon the counts having a poisson distribution.
Count Time uncertainty is less than 10-6 sec and, as such, is neglected.
The following plot shows the calibration scan count rates as a function of elevation for all 4 detectors.
CalScanl Count Rate, cps 60 1 i 50 40 30:&-
10 Elevation, in.
5 10 15
2 PallisadesAnalysis.nb 2 Palilsades Analysis.nb This plot can be compared with the first panel scanned, "Q6 South".
Q6SS2 Count Rate, cps Elevation, in 20 40 60 80 100 120 140 Both scans appear to have similar count rates in the absorber panel region. However, upon further examination, it can be shown that panel "Q6 South" may show a lower areal density (higher count rate) than the calibration cell which is manufactured at the minimum certified areal density value.
Pallisades Ahalysis.nb3 3 The following plot shows the calibration scan (in blue) for detector-2 overlaid upon the scan of panel Q6 South (in red) for the same detector. To exceed the minimum certified areal density value, we would expect that the average maximum count rate (minimum areal density) in the test panel should be less than the average minimum count rate (maximum areal density) in the calibration cell. For regions around 90" elevation, this is clearly not the case.
CalScanl 30 . . .
25 "
20 0
0 15-15 20 40 60 80 100 120 Elevation, in
4 PallisadesAnalysis.nb m Statistical Analysis A more quantitative analysis can be performed by examining the average minimum and average maximum count rates for the calibration cell and test cell respectively.
SCalibration Cell Selecting data from the panel region of the calibration cell (between 3" and 10" elevation) shows the average minimum count rate and the associated standard deviation.
The following data shows the raw scan data for detector 2. Uncertainty is calculated as specified previously.
Data is in the format "{Elevation, Count Rate, Count Rate Uncertainty}'"
3.451 19.3667 1.13627 3.946 20.65 1.17331 4.442 20.5167 1.16952 4.956 19.9667 1.15374 5.451 20.1833 1.15998 5.947 19.4167 1.13774 6.443 20.2333 1.16142 6.938 20.85 1.17898 7.452 20.05 1.15614 7.948 19.1 1.12842 8.443 19.9167 1.15229 8.939 20.9833 1.18275 9.453 19.6833 1.14552 9.948 19.9667 1.15374 The average minimum count rate for detector-2 in the calibration cell scan is calculated from the above data.
Average Minimum Count Rate:
1 n
- Z (CountRatei - CountRateUncertaintyi) =
ni=1 18.9067 At a minimum, we would expect that a test panel count rate should not go above this value to be assured of conformance with the minimum certified areal density. Note that this does not take into account the standard deviation associated with the above calculation (shown below).
Minimum Count Rate Standard Deviation:
j 2 ((CountRatei - CountRat eUncertainty1 ) -AverageMinimumCountRate) n i.1 2
0.543706
- PallisadesAnalysis.nb 5 Test Panel "Q6 South" Selecting data from the panel region of the "Q62S" test cell (between 3' and 120" elevation) shows the average maximum count rate and the associated standard deviation.
The following data shows the raw scan data for detector 2. Uncertainty 'is calculated as specified previously.
Data is in the format "{Elevation, Count Rate, Count Rate Uncertainty}"
3.946 18.5778 1.28505 5.947 18. 1.26491 7.948 17.8 1.25786 9.948 17. 1.22927 11.949 18.9111 1.29653 13.95 18.7778 1.29195 15.95 17.9333 1.26257 17.951 19.1556 1.30488 19.952 19.1333 1.30412 21.952 19.6667 1.32218 23.953 18.3778 1.27812 25.954 18.3333 1.27657 27..954 17.7111 1.25472 29.955 19.6889 1.32292 31.956 18.4222 1.27966 33.938 18.5333 1.28351 35.939 18.1556 1.27036 37.939 18.9556 1.29805 39.94 18.5333 1.28351 41.941 19.0667 1.30185 43.941 18.9778 1.29881 45.942 18.1-333 1.26959 47.943 18.2 1.27192 49.943 19.2667 1.30866 51.944 19. 1.29957 53.945 18.2667 1.27425 55.945 18.8444 1.29424 57.946 19.2667 1.30866 59.947 18.2667 1.27425 61.947 19.6222 1.32068 63.948 20.5778 1.35246 65.949 19.2222 1.30715 67.949 19.4889 1.31619 69.95 19.5111 1.31694 71.951 18.9778 1.29881 73.951 18.8222 1.29348 75.952 20.7333 1.35756 77.953 20.1778 1.33925 79.953 20.0222 1.33407 81.954 20.9556 1.36481 83.955 22.2 1.40475 85.955 20.2667 1.34219
6 PallisadesAnalysis.nb 87.938 20.4889 1.34953 89.938 21. 1.36626 91.939 22.4 1.41107 93.94 20.7778 1.35901 95.94 20.6 1.35319 97.941 20.2444 1.34146 99.942 21.3333 1.37706 101.942 20.7778 1.35901 103.943 20.9333 1.36409 105.944 21.0444 1.36771 107.944 19.3333 1.31092 109.945 20.2667 1.34219 111.946 20.3111 1.34366 113.946 19.2222 1.30715 115.947 18.6667 1.28812 117.948 20.7333 1.35756 119.948 19.5111 1.31694 The average maximum count rate for detector-2 in the test cell scan is calculated from the above data.
Average Maximum Count Rate:
1n
- Z (CountRatei + CountRateUncertaintyi) =
n i=1 20.7578 This value exceeds the average minimum count rate associated with the calibration cell as established above.
Thus, we must reject the hypothesis that the test panel exceeds the areal density of the calibration panel which is at the minimum certified areal density.
For reference, the standard deviaiton of the maximum test cell count rate is calculated below.
Maximum Count Rate Standard Deviation:
n 2
- ((CountRatei + CountRateUncertainty) - AverageMaximumCountRate)
Z =
n i=1 1.11177
Pa/lisades Analysis. nb7 7 m Reference Material m Calibration Cell Data Palisades 2008 07/14/08,M. Harris,,
0,18,36,60 7/14/2008,10:55 AM,,
0.000,1749.000,2329.000,2355.000,1884.000 0.441,1689.000,2173.000,221-1.000,1748.000 0.954,1295.000,1711.000,1769.000,1461.000 1.450,1131.000,1379.000,1450.000,1257.000 1.946,981.000,1297.000,1385.000,1144.000 2.441,987.000,1155.000,1234.000,1110.000 2.955,996.000,1220.000,1306.000,1093.000 3.451,970.000,1162.000,1285.000,1055.000 3.946,1023.000,1239.000,1236.000,1083.000 4.442,945.000,1231.000,1328.000,1074.000 4.956,916.000,1198.000,1343.000,1070.000 5.451,1014.000,1211.000,1309.000,1154.000 5 .947,1029.000,1165.000,1329.000,1 126.000 6.443,984.000,1214.000,1236.000,1138.000 6.938,998.000,1251.000,127 1.000,11 28.000 7.452,1041.000,1203.000,1281.000,1113.000 7.948,952.000,1146.000,1265.000,1113.000 8.443,981.000,1195.000,1337.000,1108.000 8.939,1015.000,1259.000,1303.000,1115.000 9.453,966.000,1181.000,1265.000,1112.000 9.948,1017.000,1198.000,1254.000,1116.000 10.444,993.000,1212.000,1340.000,1 145.000 10.939,1083.000,1267.000,1369.000,1112.000 11.453,1111.000,1353.000,1430.000,1272.000 11.949,1346.000,1745.000,1766.000,1527.000 12.445,1701.000,2122.000,2171.000,1867.000 12.940,2126.000,2660.000,2741.000,2000.000 13.454,2487.000,3284.000,3230.000,2488.000 13.950,2761.000,3665.000,3508.000,2640.000 14.445,2808 .000,3698.000,3720.000,2623.000 14.941,2890.000,3824.000,3742.000,2649.000 15.455,2795.000,3722.000,3780.000,2752.000 15.950,2773.000,3668.000,3795.000,2619.000 16.446,2742.000,3731.000,3718.000,2632.000 16.941,2864.000,3743.000,3670.000,278 1.000 17.455,2900.000,3766.000,3910.000,2633.000 17.951,2879.000,3783.000,3772.000,2838.000
a 8Palfisades Analysis.nb Panel "Q6 South" Data Palisades 2008 07/14/08,M. Harris,,
0,144,72,45 7/14/2008,2:00 PM,,
0.000,650.000,795.000,831.000,683.000 1.946,645.000,828.000,905.000,742.000 3.946,605.000,836.000,908.000,744.000 5.947,667.000,810.000,930.000,706.000 7.948,636.000,801.000,915.000,747.000 9.948,596.000,765.000,956.000,698.000 11.949,606.000,851.000,955.000,682.000 13.950,652.000,845.000,963.000,724.000 15.950,613.000,807.000,956.000,730.000 17.951,619.000,862.000,878.000,75 1.000 19.952,603.000,861.000,883.000,675.000 21.952,646.000,885.000,918.000,719.000 23.953,610.000,827.000,950.000,709.000 25.954,642.000,825.000,875.000,685.000 27.954,617.000,797.000,904.000,711.000 29..955,635.000,886.000,939.000,683.000 31.956,659.000,829.000,984.000,715.000 33.938,639.000,834.000,914.000,716.000 35.939,628.000,817.000,928.000,738.000 37.939,631.000,853.000,943.000,718.000 39.940,633.000,834.000,904.000,722.000 41.941,686.000,858.000,947.000,754.000 43.941,673.000,854.000,960.000,70 1.000 45.942,688.000,816.000,935 .000,773.000 47.943,655.000,819.000,918.000,701.000 49.943,649.000,867.000,895.000,732.000 51.944,649.000,855.000,958.000,740.000 53.945,71 5.000,822.000,978 .000,759.000 55.945,681.000,848.000,916.000,737.000 57.946,696.000,867.000,1009.000,715.000, 59.947,674.000,822.000,964.000,709.000 61.947,698.000,883.000,972.000,734.000 63.948,725.000,926.000,941.000,693.000 65.949,720.000,865.000,942.000,779.000 67.949,720.000,877.000,1003.000,759.000 69.950,696.000,878.000,998.000,711.000 71.951,671 .000,854.000,888..000,717.000 73.951,705.000,847.000,938.000,656.000 75.952,722.000,933.000,1025.000,720.000 77.953,725.000,908.000,992.000,726.000 79.953,714.000,901.000,969.000,75 1.000
PallisadesAnalysis.nb 9 81.954,777.000,943.000,980.000,801.000 83.955,769.000,999.000,994.000,745.000 85.955,767.000,912.000,941.000,744.000 87.938,718.000,922.000,966.000,738.000 89.938,756.000,945.000,1057.000,757.000 91.939,761.000,1008.000,1028.000,738.000 93.940,772.000,935.000,988.000,769.000 95.940,718.000,927.000,1042.000,757.000 97.941,741.000,91 1.000,995.000,745.000 99.942,761.000,960.000,1025.000,716.000 101.942,784.000,935.000,964.000,684.000 103.943,775.000,942.000,993.000,717.000 105.944,792.000,947.000,958.000,729.000 107.944,700.000,870.000,956.000,695.000 109.945,757.000,912.000,916.000,675.000 111.946,737.000,914.000,918.000,740.000 113.946,739.000,865.000,991.000,706.000 115.947,730.000,840.000,911.000,671.000 117.948,722.000,933.000,940.000,696.000 119.948,716.000,878.000,932.000,696.000 121.949,728.000,878.000,911.000,683.000 123.950,737.000,916.000,949.000,633.000 125.950,673.000,897.000,959.000,677.000 127.951,732.000,890.000,904.000,707.000 129.952,831.000,1014.000,1154.000,842.000 131.952,1882.000,2414.000,2405.000,1889.000 133.953,2118.000,2690.000,2843.000,2145.000 135.954,1768.000,2313.000,2469.000,1909.000 137.954,1804.000,2320.000,2401.000,1840.000 139.955,1997.000,2636.000,2677.000,2031.000 141.956,1613.000,2108.000,2194.000,1604.000 143.938,983.000,1168.000,1257.000,958.000