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| {{#Wiki_filter:Pre-Submittal Teleconference Millstone Power Station Unit 2 License Amendment Request for Spent Fuel Pool Heat Load Analysis in Response to Confirmatory Order EA-13-188 December 17, 2015 Pg. 2 Agenda Purpose of LAR Scope of LAR Schedule Pg. 3 Purpose of LAR LAR required by Confirmatory Order EA-13-188 (8/26/15) Compliance Item #5: amendment request seeking NRC approval of the spent fuel pool heat load analysis and any associated technical specification changes. This DNC has determined no change to the TS is required Request approval of the SFP heat load analyses, TS Bases Section 3/4.9.3 and FSAR Section 9.5 LAR meets regulatory criteria and will preserve health and safety of the public Pg. 4 Scope of LAR LAR will request NRC review and approval of proposed changes to TS Bases Section 3/4.9.3 to remove spent fuel pool decay heat load Proposed bases change is based on the TS prior to the 2009 Bases change made by DNC under 10 CFR 50.59 Change will remove reference to Spent Fuel Pool Decay Heat Load The change is consistent with 10 CFR 50.36 and previous License Amendments 240 (2/10/2000) and 315 (6/4/2013) | | {{#Wiki_filter:Pre-Submittal Teleconference Millstone Power Station Unit 2 License Amendment Request for Spent Fuel Pool Heat Load Analysis in Response to Confirmatory Order EA-13-188 December 17, 2015 |
| Pg. 5 Scope of LAR (Continued) LAR will request NRC review and approval of proposed changes to FSAR Section 9.5 Proposed changes are based on the FSAR prior to the 2010 change made by DNC under 10 CFR 50.59 Proposed FSAR change reflects revisions to: Spent fuel movement decay time Cooling water temperatures (RBCCW) Spent fuel movement rate Scope of LAR (Continued) LAR will provide a summary of the analysis results supporting fuel movement starting at 100 hours after reactor shutdown at a rate of 6 assemblies per hour. LAR will include the proprietary analyses performed by Holtec International submitted under 10 CFR 2.390 Holtec Report No. HI-971778, Rev. 2 "Heat Load from the Spent Fuel Holtec Report No. HI-2094491, Rev. 0, "Thermal- Hydraulic Analysis of Millstone Unit 2 Spent Fuel Pool with Increased Fuel Transfer Rate and Reduced In- Holtec Report No. HI-981901, Rev. 0 including Addenda A & B, "Spent Fuel Pool Thermal- Pg. 6 Pg. 7 Schedule DNC will submit the LAR by February 15, 2016 Request review of this LAR within one year of submittal To maintain compliance with the Confirmatory Order, Standing Order 14-21 is in place prohibiting fuel movement prior to 150 hours after shutdown. This will remain in place until NRC makes a final determination on the LAR. | | |
| QUESTIONS? Pg. 8 Acronym List CFR Code of Federal Regulations DNC Dominion Nuclear Connecticut FSAR Final Safety Analysis Report LAR License Amendment Request MPS2 Millstone Power Station, Unit 2 RBCCW Reactor Building Closed Cooling Water system TS Technical Specifications Pg. 9 Pre-Submittal Teleconference Millstone Power Station Unit 2 License Amendment Request for Spent Fuel Pool Heat Load Analysis in Response to Confirmatory Order EA-13-188 December 17, 2015 Pg. 2 Agenda Purpose of LAR Scope of LAR Schedule Pg. 3 Purpose of LAR LAR required by Confirmatory Order EA-13-188 (8/26/15) Compliance Item #5: amendment request seeking NRC approval of the spent fuel pool heat load analysis and any associated technical specification changes. This DNC has determined no change to the TS is required Request approval of the SFP heat load analyses, TS Bases Section 3/4.9.3 and FSAR Section 9.5 LAR meets regulatory criteria and will preserve health and safety of the public Pg. 4 Scope of LAR LAR will request NRC review and approval of proposed changes to TS Bases Section 3/4.9.3 to remove spent fuel pool decay heat load Proposed bases change is based on the TS prior to the 2009 Bases change made by DNC under 10 CFR 50.59 Change will remove reference to Spent Fuel Pool Decay Heat Load The change is consistent with 10 CFR 50.36 and previous License Amendments 240 (2/10/2000) and 315 (6/4/2013) | | Agenda |
| Pg. 5 Scope of LAR (Continued) LAR will request NRC review and approval of proposed changes to FSAR Section 9.5 Proposed changes are based on the FSAR prior to the 2010 change made by DNC under 10 CFR 50.59 Proposed FSAR change reflects revisions to: Spent fuel movement decay time Cooling water temperatures (RBCCW) Spent fuel movement rate Scope of LAR (Continued) LAR will provide a summary of the analysis results supporting fuel movement starting at 100 hours after reactor shutdown at a rate of 6 assemblies per hour. LAR will include the proprietary analyses performed by Holtec International submitted under 10 CFR 2.390 Holtec Report No. HI-971778, Rev. 2 "Heat Load from the Spent Fuel Holtec Report No. HI-2094491, Rev. 0, "Thermal- Hydraulic Analysis of Millstone Unit 2 Spent Fuel Pool with Increased Fuel Transfer Rate and Reduced In- Holtec Report No. HI-981901, Rev. 0 including Addenda A & B, "Spent Fuel Pool Thermal- Pg. 6 Pg. 7 Schedule DNC will submit the LAR by February 15, 2016 Request review of this LAR within one year of submittal To maintain compliance with the Confirmatory Order, Standing Order 14-21 is in place prohibiting fuel movement prior to 150 hours after shutdown. This will remain in place until NRC makes a final determination on the LAR. | | * Purpose of LAR |
| QUESTIONS? Pg. 8 Acronym List CFR Code of Federal Regulations DNC Dominion Nuclear Connecticut FSAR Final Safety Analysis Report LAR License Amendment Request MPS2 Millstone Power Station, Unit 2 RBCCW Reactor Building Closed Cooling Water system TS Technical Specifications Pg. 9}} | | * Scope of LAR |
| | * Schedule Pg. 2 |
| | |
| | Purpose of LAR |
| | * LAR required by Confirmatory Order EA-13-188 (8/26/15) |
| | Compliance Item #5: |
| | By no later than February 15, 2016, DNC will submit a license amendment request seeking NRC approval of the spent fuel pool heat load analysis and any associated technical specification changes. This will be treated as a high priority review by the NRC. |
| | * DNC has determined no change to the TS is required |
| | * Request approval of the SFP heat load analyses, TS Bases Section 3/4.9.3 and FSAR Section 9.5 |
| | * LAR meets regulatory criteria and will preserve health and safety of the public Pg. 3 |
| | |
| | Scope of LAR |
| | * LAR will request NRC review and approval of proposed changes to TS Bases Section 3/4.9.3 to remove spent fuel pool decay heat load |
| | - Proposed bases change is based on the TS prior to the 2009 Bases change made by DNC under 10 CFR 50.59 |
| | - Change will remove reference to Spent Fuel Pool Decay Heat Load |
| | - The change is consistent with 10 CFR 50.36 and previous License Amendments 240 (2/10/2000) and 315 (6/4/2013) |
| | Pg. 4 |
| | |
| | Scope of LAR (Continued) |
| | * LAR will request NRC review and approval of proposed changes to FSAR Section 9.5 |
| | - Proposed changes are based on the FSAR prior to the 2010 change made by DNC under 10 CFR 50.59 |
| | - Proposed FSAR change reflects revisions to: |
| | * Spent fuel movement decay time |
| | * Cooling water temperatures (RBCCW) |
| | * Spent fuel movement rate Pg. 5 |
| | |
| | Scope of LAR (Continued) |
| | * LAR will provide a summary of the analysis results supporting fuel movement starting at 100 hours after reactor shutdown at a rate of 6 assemblies per hour. |
| | * LAR will include the proprietary analyses performed by Holtec International submitted under 10 CFR 2.390 |
| | - Holtec Report No. HI-971778, Rev. 2 "Heat Load from the Spent Fuel Pool for 3 Core Unload Scenarios |
| | - Holtec Report No. HI-2094491, Rev. 0, "Thermal- Hydraulic Analysis of Millstone Unit 2 Spent Fuel Pool with Increased Fuel Transfer Rate and Reduced In-core Hold Time |
| | - Holtec Report No. HI-981901, Rev. 0 including Addenda A & B, "Spent Fuel Pool Thermal- Hydraulic Analysis for Millstone Unit 2 Pg. 6 |
| | |
| | Schedule |
| | * DNC will submit the LAR by February 15, 2016 |
| | * Request review of this LAR within one year of submittal |
| | * To maintain compliance with the Confirmatory Order, Standing Order 14-21 is in place prohibiting fuel movement prior to 150 hours after shutdown. This will remain in place until NRC makes a final determination on the LAR. |
| | Pg. 7 |
| | |
| | QUESTIONS? |
| | Pg. 8 |
| | |
| | Acronym List |
| | * CFR Code of Federal Regulations |
| | * DNC Dominion Nuclear Connecticut |
| | * FSAR Final Safety Analysis Report |
| | * LAR License Amendment Request |
| | * MPS2 Millstone Power Station, Unit 2 |
| | * RBCCW Reactor Building Closed Cooling Water system |
| | * TS Technical Specifications Pg. 9 |
| | |
| | Pre-Submittal Teleconference Millstone Power Station Unit 2 License Amendment Request for Spent Fuel Pool Heat Load Analysis in Response to Confirmatory Order EA-13-188 December 17, 2015 |
| | |
| | Agenda |
| | * Purpose of LAR |
| | * Scope of LAR |
| | * Schedule Pg. 2 |
| | |
| | Purpose of LAR |
| | * LAR required by Confirmatory Order EA-13-188 (8/26/15) |
| | Compliance Item #5: |
| | By no later than February 15, 2016, DNC will submit a license amendment request seeking NRC approval of the spent fuel pool heat load analysis and any associated technical specification changes. This will be treated as a high priority review by the NRC. |
| | * DNC has determined no change to the TS is required |
| | * Request approval of the SFP heat load analyses, TS Bases Section 3/4.9.3 and FSAR Section 9.5 |
| | * LAR meets regulatory criteria and will preserve health and safety of the public Pg. 3 |
| | |
| | Scope of LAR |
| | * LAR will request NRC review and approval of proposed changes to TS Bases Section 3/4.9.3 to remove spent fuel pool decay heat load |
| | - Proposed bases change is based on the TS prior to the 2009 Bases change made by DNC under 10 CFR 50.59 |
| | - Change will remove reference to Spent Fuel Pool Decay Heat Load |
| | - The change is consistent with 10 CFR 50.36 and previous License Amendments 240 (2/10/2000) and 315 (6/4/2013) |
| | Pg. 4 |
| | |
| | Scope of LAR (Continued) |
| | * LAR will request NRC review and approval of proposed changes to FSAR Section 9.5 |
| | - Proposed changes are based on the FSAR prior to the 2010 change made by DNC under 10 CFR 50.59 |
| | - Proposed FSAR change reflects revisions to: |
| | * Spent fuel movement decay time |
| | * Cooling water temperatures (RBCCW) |
| | * Spent fuel movement rate Pg. 5 |
| | |
| | Scope of LAR (Continued) |
| | * LAR will provide a summary of the analysis results supporting fuel movement starting at 100 hours after reactor shutdown at a rate of 6 assemblies per hour. |
| | * LAR will include the proprietary analyses performed by Holtec International submitted under 10 CFR 2.390 |
| | - Holtec Report No. HI-971778, Rev. 2 "Heat Load from the Spent Fuel Pool for 3 Core Unload Scenarios |
| | - Holtec Report No. HI-2094491, Rev. 0, "Thermal- Hydraulic Analysis of Millstone Unit 2 Spent Fuel Pool with Increased Fuel Transfer Rate and Reduced In-core Hold Time |
| | - Holtec Report No. HI-981901, Rev. 0 including Addenda A & B, "Spent Fuel Pool Thermal- Hydraulic Analysis for Millstone Unit 2 Pg. 6 |
| | |
| | Schedule |
| | * DNC will submit the LAR by February 15, 2016 |
| | * Request review of this LAR within one year of submittal |
| | * To maintain compliance with the Confirmatory Order, Standing Order 14-21 is in place prohibiting fuel movement prior to 150 hours after shutdown. This will remain in place until NRC makes a final determination on the LAR. |
| | Pg. 7 |
| | |
| | QUESTIONS? |
| | Pg. 8 |
| | |
| | Acronym List |
| | * CFR Code of Federal Regulations |
| | * DNC Dominion Nuclear Connecticut |
| | * FSAR Final Safety Analysis Report |
| | * LAR License Amendment Request |
| | * MPS2 Millstone Power Station, Unit 2 |
| | * RBCCW Reactor Building Closed Cooling Water system |
| | * TS Technical Specifications Pg. 9}} |
Letter Sequence Meeting |
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MONTHYEARML15353A0022015-12-17017 December 2015 /12/17 Presentation Slides for Pre-Submittal Teleconference - Proposed LAR for Spent Fuel Pool Heat Load Analysis in Response to Confirmatory Order EA-13-188 Project stage: Meeting ML16004A4732016-01-0404 January 2016 Teleconference Memo to File: Summary of December 17, 2015 - Pre-submittal Call with the NRC Related to Confirmatory Item IV.5 Project stage: Meeting 2015-12-17
[Table View] |
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Category:Meeting Briefing Package/Handouts
MONTHYEARML23254A0562023-09-13013 September 2023 Presentation Material for 9/13/23 Pre-Submittal Meeting License Amendment Request to Support Cycle Reloads Using Framatome Gaia Fuel ML22277A8412022-10-18018 October 2022 Presentation Material for 10/18/22 Pre-Submittal Meeting Licensing Requests to Implement Framatome Gaia Fuel ML22243A0322022-09-0707 September 2022 Presentation Material for 9/7/22 Pre-Submittal Meeting Supplement to the Spent Fuel Pool Criticality Safety Analysis ML22236A0602022-08-29029 August 2022 Presentation Material for 8/29/22 Pre-Submittal Meeting Reactor Pressure Vessel Head Peening Follow-Up Exam Deferral ML22215A2872022-08-0909 August 2022 Presentation Material for 8/9/22 Pre-Submittal Meeting Containment Recirc Spray System Flow Test Alternative Request ML22082A1482022-03-23023 March 2022 Annual Assessment Meeting for Millstone Power Station - Webinar Presentation (NRC) ML21076A3322021-03-18018 March 2021 3/18/21 - Annual Assessment Meeting for Millstone Power Station - Presentation Slides ML20226A4112020-08-19019 August 2020 Presentation Material for 8/19/20 Pre-Submittal Meeting Biennial Emergency Preparedness Exercise Date Change Exemption Request ML20176A2762020-06-29029 June 2020 Presentation Material for 6/29/20 Pre-Submittal Meeting Proposed License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML20143A0772020-05-26026 May 2020 Presentation Material for 5/26/20 Pre-Submittal Meeting Steam Generator Examination Frequency Alternative Request ML20111A0352020-04-20020 April 2020 Annual Assessment Meeting for Millstone Power Station - NRC Presentation Slides ML19143A4722019-06-0303 June 2019 Presentation Material for 6/03/19 Pre-Submittal Meeting Integrated Leak Rate Test Extension License Amendment Request ML19128A4072019-05-0909 May 2019 Presentation Material for 5/09/19 Pre-Submittal Meeting TS Coolant Activity Changes, License Amendment Request ML19063D9452019-03-0707 March 2019 Presentation Material for 3/07/19 Pre-Submittal Meeting License Amendment Request to Revise Technical Specification 3.8.1.1 ML19022A2432019-01-22022 January 2019 Presentation Material for 1/22/19 Pre-Submittal Meeting Fillet Weld Preheat Alternative Request ML18320A2502018-11-20020 November 2018 50.90 License Amendment Request - Dominion Fleet EAL Scheme Changes, November 20, 2018 Public Meeting ML18310A1812018-11-0808 November 2018 Presentation Material for 11/08/18 Pre-Submittal Meeting 10 CFR 50.69 Risk Informed Approach License Amendment Request ML18108A2072018-04-10010 April 2018 04/10/2018 Public Teleconference Meeting Slides MPS3 C Charging Pump ML17230A1282017-08-31031 August 2017 Connecticut, Inc. Presentation Slides for Pre-submittal Meeting on August 31, 2017 ML17200C9572017-07-18018 July 2017 Connecticut, Inc. Presentation Slides for Pre-submittal Meeting on July 18, 2017 ML16272A3462016-08-10010 August 2016 08/10/2016 - NEI Supplemental Material 2 (Estimate of BADGER System Uncertainty Using Millstone Unit 1 2013) ML16272A3472016-08-10010 August 2016 08/10/2016 - NEI Supplemental Material 1 (BADGER Measurement of Carborundum B-10 Areal Density) ML16125A0092016-05-0303 May 2016 2016/05/03 Presentation Slides for Pre-Submittal Teleconference for Realistic Large Break LOCA License Amendment Request ML15353A0022015-12-17017 December 2015 /12/17 Presentation Slides for Pre-Submittal Teleconference - Proposed LAR for Spent Fuel Pool Heat Load Analysis in Response to Confirmatory Order EA-13-188 ML15344A2942015-12-10010 December 2015 /12/10 Presentation Slides for Pre-Submittal Teleconference - Proposed LAR for Charging System in Response to Confirmatory Order EA-13-188 ML15314A1022015-10-20020 October 2015 2015/10/20 Pre-Submittal Teleconference Meeting Slides: Proposed License Amendment Request for EAL Changes, RCS Sampling Methodology Revision ML15198A3432015-06-22022 June 2015 2015/06/22 Pre-Submittal Teleconference Meeting Slides: LOCA Analyses Supporting MPS2 Upgrade to Areva Standard CE14 Htp Fuel Assembly ML15155B3692015-05-21021 May 2015 Connecticut, Inc. Presentation Slides for Pre-submittal Meeting on May 21, 2015 ML14176A0922014-06-25025 June 2014 6/25/2014, Dominion Public Meeting Presentation for Surry GMRS Profile ML13305A1442013-10-31031 October 2013 Rlbloca, Revision 3 - Post-Submittal Meeting, Areva, Oct. 31, 2013S, Lides ML1014101592010-05-21021 May 2010 April 22, 2010 Summary of Meeting with Connecticut Nuclear Energy Advisory Council ML0910506232009-04-23023 April 2009 NRC & Neac Meeting Concerning Millstone Annual Assessment, 2008 Reactor Oversight Process, Slides ML0909800642009-04-0808 April 2009 Slides for Millstone Annual Assessment Meeting, 2008 Reactor Oversight Process ML0808800832008-03-28028 March 2008 Slides - NRC & Neac Meeting Concerning Millstone Station Performance, 2007 Reactor Oversight Program ML0734708412007-12-11011 December 2007 Drop-In Visit from Dominion (Millstone) ML0730400332007-11-0101 November 2007 Public Meeting Slides for Meeting with Dominion Nuclear ML0730502942007-11-0101 November 2007 TSTF Status Spreadsheet for 11-01-2007 Meeting ML0729806642007-10-24024 October 2007 Meeting Presentation on Update on Generic Safety Issue 191 Plant Audits ML0608300792006-03-24024 March 2006 NRC Slides for Public Meeting with Nuclear Energy Advisory Council (Neac) to Discuss Cy 2005 Annual Assessment of Millstone Station ML0532501622005-11-22022 November 2005 Att. 4 Millstone Power Station Appeal Faq 55.2 ML0524300932005-08-18018 August 2005 Att. 6, FAQ Log ML0527701902005-08-16016 August 2005 Mantg Conference, 8/16/05 - Plenary - Welcoming Speech on Predictability by J. Alan Price, Site Vice President Millstone Power Station, Dominion Nuclear ML0515304782005-05-18018 May 2005 NRC Slides for Public Meeting with Nuclear Energy Advisory Council (Neac) Ref: Special Inspection Team Results of April 17, 2005 Event ML0507303932005-03-14014 March 2005 NRC Slides for Public Meeting with Dominion Nuclear Connecticut, Inc. (Millstone Station) Ref: Annual Assessment Performance ML0331604212003-11-21021 November 2003 Meeting Handouts for 9/24/03 Public Meeting Re. Discussion of Planned Consolidation of Quality Assurance Programs ML0309003222003-03-20020 March 2003 Notice of Meeting EOC Slides Annual Assessment of Safety Performance of Millstone Unit 2 and Unit 3. Region I Presentation on Reactor Oversight Program - 2002 ML0309003542003-03-20020 March 2003 Notice of Meeting Neac Slides Annual Assessment of Safety Performance of Millstone Unit 2 and Unit 3. Region I Presentation on Reactor Oversight Program - 2002 ML17252A1571977-09-14014 September 1977 Summary of Meeting Held with Representatives of the Mark I Owner'S Group to Discuss the Structural Acceptance Criteria for the Mark I Containment Long Term Program 2023-09-13
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24135A0812024-05-14014 May 2024 5/16/2024, Annual Assessment Meeting for Millstone Power Station - NRC Presentation Slides ML23254A0562023-09-13013 September 2023 Presentation Material for 9/13/23 Pre-Submittal Meeting License Amendment Request to Support Cycle Reloads Using Framatome Gaia Fuel ML23073A0042023-03-14014 March 2023 Annual Assessment Meeting for Millstone Power Station - NRC Presentation Slides ML22277A8412022-10-18018 October 2022 Presentation Material for 10/18/22 Pre-Submittal Meeting Licensing Requests to Implement Framatome Gaia Fuel ML22243A0322022-09-0707 September 2022 Presentation Material for 9/7/22 Pre-Submittal Meeting Supplement to the Spent Fuel Pool Criticality Safety Analysis ML22236A0602022-08-29029 August 2022 Presentation Material for 8/29/22 Pre-Submittal Meeting Reactor Pressure Vessel Head Peening Follow-Up Exam Deferral ML22215A2872022-08-0909 August 2022 Presentation Material for 8/9/22 Pre-Submittal Meeting Containment Recirc Spray System Flow Test Alternative Request ML22082A1482022-03-23023 March 2022 Annual Assessment Meeting for Millstone Power Station - Webinar Presentation (NRC) ML21076A3322021-03-18018 March 2021 3/18/21 - Annual Assessment Meeting for Millstone Power Station - Presentation Slides ML20226A4112020-08-19019 August 2020 Presentation Material for 8/19/20 Pre-Submittal Meeting Biennial Emergency Preparedness Exercise Date Change Exemption Request ML20176A2762020-06-29029 June 2020 Presentation Material for 6/29/20 Pre-Submittal Meeting Proposed License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML20143A0772020-05-26026 May 2020 Presentation Material for 5/26/20 Pre-Submittal Meeting Steam Generator Examination Frequency Alternative Request ML19143A4722019-06-0303 June 2019 Presentation Material for 6/03/19 Pre-Submittal Meeting Integrated Leak Rate Test Extension License Amendment Request ML19128A4072019-05-0909 May 2019 Presentation Material for 5/09/19 Pre-Submittal Meeting TS Coolant Activity Changes, License Amendment Request ML19022A2432019-01-22022 January 2019 Presentation Material for 1/22/19 Pre-Submittal Meeting Fillet Weld Preheat Alternative Request ML18108A2072018-04-10010 April 2018 04/10/2018 Public Teleconference Meeting Slides MPS3 C Charging Pump ML18086A7742018-02-21021 February 2018 LOR Program Biennial Inspection 71111.11B Exam Overlap Issues ML17230A1282017-08-31031 August 2017 Connecticut, Inc. Presentation Slides for Pre-submittal Meeting on August 31, 2017 ML17200C9572017-07-18018 July 2017 Connecticut, Inc. Presentation Slides for Pre-submittal Meeting on July 18, 2017 ML16272A3472016-08-10010 August 2016 08/10/2016 - NEI Supplemental Material 1 (BADGER Measurement of Carborundum B-10 Areal Density) ML16272A3462016-08-10010 August 2016 08/10/2016 - NEI Supplemental Material 2 (Estimate of BADGER System Uncertainty Using Millstone Unit 1 2013) ML16125A0092016-05-0303 May 2016 2016/05/03 Presentation Slides for Pre-Submittal Teleconference for Realistic Large Break LOCA License Amendment Request ML15353A0022015-12-17017 December 2015 /12/17 Presentation Slides for Pre-Submittal Teleconference - Proposed LAR for Spent Fuel Pool Heat Load Analysis in Response to Confirmatory Order EA-13-188 ML15344A2942015-12-10010 December 2015 /12/10 Presentation Slides for Pre-Submittal Teleconference - Proposed LAR for Charging System in Response to Confirmatory Order EA-13-188 ML15314A1022015-10-20020 October 2015 2015/10/20 Pre-Submittal Teleconference Meeting Slides: Proposed License Amendment Request for EAL Changes, RCS Sampling Methodology Revision ML15198A3432015-06-22022 June 2015 2015/06/22 Pre-Submittal Teleconference Meeting Slides: LOCA Analyses Supporting MPS2 Upgrade to Areva Standard CE14 Htp Fuel Assembly ML15155B3692015-05-21021 May 2015 Connecticut, Inc. Presentation Slides for Pre-submittal Meeting on May 21, 2015 ML14176A0922014-06-25025 June 2014 6/25/2014, Dominion Public Meeting Presentation for Surry GMRS Profile ML13305A1442013-10-31031 October 2013 Rlbloca, Revision 3 - Post-Submittal Meeting, Areva, Oct. 31, 2013S, Lides IR 05000336/20110102011-08-0808 August 2011 EA-11-047, Millstone - Final Significance Determination for White Finding, W/Assessment Follow-up;Notice of Violation and Results of Regulatory Conference (NRC Special Inspection Report No. 05000336/2011010) ML1120005362011-07-19019 July 2011 EA-11-047, Millstone Regulatory Conference-July 19, 2011-Dominion Slides ML1120005282011-07-19019 July 2011 EA-11-047, Millstone Regulatory Conference-July 19, 2011 NRC Slides ML1118800642011-07-0707 July 2011 NRC Slides - Millstone/Neac Public Meeting on May 25, 2011 ML1118800332011-07-0707 July 2011 NRC Slides - Millstone 2011 Annual Assesssment Meeting ML1019505052010-07-13013 July 2010 MPS3 RAI 6 ML1014101592010-05-21021 May 2010 April 22, 2010 Summary of Meeting with Connecticut Nuclear Energy Advisory Council ML1005009822010-02-17017 February 2010 Spent Fuel Pool Criticality Presentation for Feb 17 Public Meeting ML0910506232009-04-23023 April 2009 NRC & Neac Meeting Concerning Millstone Annual Assessment, 2008 Reactor Oversight Process, Slides ML0909800642009-04-0808 April 2009 Slides for Millstone Annual Assessment Meeting, 2008 Reactor Oversight Process ML0911200622009-03-31031 March 2009 Post Exam Comment Miscellaneous References (Folder 1) ML0808801002008-04-0202 April 2008 Slides - NRC Annual Performance Assessment of Millstone, 2007 Reactor Oversight Process ML0808800832008-03-28028 March 2008 Slides - NRC & Neac Meeting Concerning Millstone Station Performance, 2007 Reactor Oversight Program ML0734708412007-12-11011 December 2007 Drop-In Visit from Dominion (Millstone) ML0730400332007-11-0101 November 2007 Public Meeting Slides for Meeting with Dominion Nuclear ML0729806642007-10-24024 October 2007 Meeting Presentation on Update on Generic Safety Issue 191 Plant Audits ML0707907302007-03-20020 March 2007 2006 NRC and Neac Public Meeting Slides to Discuss Millstone Station Annual Assessment Performance EOC 2006-07 ML0707907132007-03-20020 March 2007 2006 Millstone Annual Assessment Meeting Slides 2006-07 EOC ML0615106012006-05-23023 May 2006 EPRI HRA Users Group Review of Draft NUREG-1842 ML0608300792006-03-24024 March 2006 NRC Slides for Public Meeting with Nuclear Energy Advisory Council (Neac) to Discuss Cy 2005 Annual Assessment of Millstone Station ML0608202022006-03-23023 March 2006 NRC Slides for Public Meeting with Dominion Nuclear (Millstone) to Discuss CY2005 Performance 2024-05-14
[Table view] |
Text
Pre-Submittal Teleconference Millstone Power Station Unit 2 License Amendment Request for Spent Fuel Pool Heat Load Analysis in Response to Confirmatory Order EA-13-188 December 17, 2015
Agenda
Purpose of LAR
Compliance Item #5:
By no later than February 15, 2016, DNC will submit a license amendment request seeking NRC approval of the spent fuel pool heat load analysis and any associated technical specification changes. This will be treated as a high priority review by the NRC.
- DNC has determined no change to the TS is required
- Request approval of the SFP heat load analyses, TS Bases Section 3/4.9.3 and FSAR Section 9.5
- LAR meets regulatory criteria and will preserve health and safety of the public Pg. 3
Scope of LAR
- LAR will request NRC review and approval of proposed changes to TS Bases Section 3/4.9.3 to remove spent fuel pool decay heat load
- Proposed bases change is based on the TS prior to the 2009 Bases change made by DNC under 10 CFR 50.59
- Change will remove reference to Spent Fuel Pool Decay Heat Load
- The change is consistent with 10 CFR 50.36 and previous License Amendments 240 (2/10/2000) and 315 (6/4/2013)
Pg. 4
Scope of LAR (Continued)
- LAR will request NRC review and approval of proposed changes to FSAR Section 9.5
- Proposed changes are based on the FSAR prior to the 2010 change made by DNC under 10 CFR 50.59
- Proposed FSAR change reflects revisions to:
- Spent fuel movement decay time
- Cooling water temperatures (RBCCW)
- Spent fuel movement rate Pg. 5
Scope of LAR (Continued)
- LAR will provide a summary of the analysis results supporting fuel movement starting at 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after reactor shutdown at a rate of 6 assemblies per hour.
- LAR will include the proprietary analyses performed by Holtec International submitted under 10 CFR 2.390
- Holtec Report No. HI-971778, Rev. 2 "Heat Load from the Spent Fuel Pool for 3 Core Unload Scenarios
- Holtec Report No. HI-2094491, Rev. 0, "Thermal- Hydraulic Analysis of Millstone Unit 2 Spent Fuel Pool with Increased Fuel Transfer Rate and Reduced In-core Hold Time
- Holtec Report No. HI-981901, Rev. 0 including Addenda A & B, "Spent Fuel Pool Thermal- Hydraulic Analysis for Millstone Unit 2 Pg. 6
Schedule
- DNC will submit the LAR by February 15, 2016
- Request review of this LAR within one year of submittal
- To maintain compliance with the Confirmatory Order, Standing Order 14-21 is in place prohibiting fuel movement prior to 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> after shutdown. This will remain in place until NRC makes a final determination on the LAR.
Pg. 7
QUESTIONS?
Pg. 8
Acronym List
- CFR Code of Federal Regulations
- FSAR Final Safety Analysis Report
- LAR License Amendment Request
- MPS2 Millstone Power Station, Unit 2
- RBCCW Reactor Building Closed Cooling Water system
- TS Technical Specifications Pg. 9
Pre-Submittal Teleconference Millstone Power Station Unit 2 License Amendment Request for Spent Fuel Pool Heat Load Analysis in Response to Confirmatory Order EA-13-188 December 17, 2015
Agenda
Purpose of LAR
Compliance Item #5:
By no later than February 15, 2016, DNC will submit a license amendment request seeking NRC approval of the spent fuel pool heat load analysis and any associated technical specification changes. This will be treated as a high priority review by the NRC.
- DNC has determined no change to the TS is required
- Request approval of the SFP heat load analyses, TS Bases Section 3/4.9.3 and FSAR Section 9.5
- LAR meets regulatory criteria and will preserve health and safety of the public Pg. 3
Scope of LAR
- LAR will request NRC review and approval of proposed changes to TS Bases Section 3/4.9.3 to remove spent fuel pool decay heat load
- Proposed bases change is based on the TS prior to the 2009 Bases change made by DNC under 10 CFR 50.59
- Change will remove reference to Spent Fuel Pool Decay Heat Load
- The change is consistent with 10 CFR 50.36 and previous License Amendments 240 (2/10/2000) and 315 (6/4/2013)
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Scope of LAR (Continued)
- LAR will request NRC review and approval of proposed changes to FSAR Section 9.5
- Proposed changes are based on the FSAR prior to the 2010 change made by DNC under 10 CFR 50.59
- Proposed FSAR change reflects revisions to:
- Spent fuel movement decay time
- Cooling water temperatures (RBCCW)
- Spent fuel movement rate Pg. 5
Scope of LAR (Continued)
- LAR will provide a summary of the analysis results supporting fuel movement starting at 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after reactor shutdown at a rate of 6 assemblies per hour.
- LAR will include the proprietary analyses performed by Holtec International submitted under 10 CFR 2.390
- Holtec Report No. HI-971778, Rev. 2 "Heat Load from the Spent Fuel Pool for 3 Core Unload Scenarios
- Holtec Report No. HI-2094491, Rev. 0, "Thermal- Hydraulic Analysis of Millstone Unit 2 Spent Fuel Pool with Increased Fuel Transfer Rate and Reduced In-core Hold Time
- Holtec Report No. HI-981901, Rev. 0 including Addenda A & B, "Spent Fuel Pool Thermal- Hydraulic Analysis for Millstone Unit 2 Pg. 6
Schedule
- DNC will submit the LAR by February 15, 2016
- Request review of this LAR within one year of submittal
- To maintain compliance with the Confirmatory Order, Standing Order 14-21 is in place prohibiting fuel movement prior to 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> after shutdown. This will remain in place until NRC makes a final determination on the LAR.
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QUESTIONS?
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Acronym List
- CFR Code of Federal Regulations
- FSAR Final Safety Analysis Report
- LAR License Amendment Request
- MPS2 Millstone Power Station, Unit 2
- RBCCW Reactor Building Closed Cooling Water system
- TS Technical Specifications Pg. 9