Letter Sequence Request |
---|
|
|
MONTHYEARML15155B3692015-05-21021 May 2015 Connecticut, Inc. Presentation Slides for Pre-submittal Meeting on May 21, 2015 Project stage: Request ML15162A8662015-06-16016 June 2015 Summary of May 21, 2015 Meeting with Dominion Nuclear Connecticut, Inc. to Discuss Pre-Submittal of License Amendment Request for Removal of Severe Line Outage Detection at Millstone Power Station Project stage: Meeting 2015-05-21
[Table View] |
|
---|
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 Meeting:
License Amendment Request for Removal of Severe Line Outage Detection (SLOD) at Millstone Power Station Dominion Page 1 Nuclear Safety First
Background
- SLOD in original MP2 and MP3 License Basis (FSAR) as required to be operational to meet GDC-17.
- Eversource replaced double circuit towers (DCTs) with single circuit towers (SCTs) (2012)
- SLOD disabled (December 2012) without prior NRC approval.
- Number of options were evaluated and a License Amendment Request (LAR) was selected.
Dominion Page 2 Nuclear Safety First
Site Description
- Unit 1: Decommissioned.
- Unit 2: Combustion Engineering Design.
- Unit 3: Westinghouse Design.
- Four 345 kV transmission lines.
Dominion Page 3 Nuclear Safety First
Millstone Transmission System and Facilities Dominion Page 4 Nuclear Safety First
Background
Submittal of LAR is necessary for the following:
- Restoring the current license basis in the FSAR to the standards originally considered when the plants were licensed.
- Establishing appropriate controls in the Technical Requirements Manual for periods when one offsite line is not available.
Dominion Page 5 Nuclear Safety First
Summary of Proposed Changes Final Safety Analysis Report (FSAR) Changes
- Reflect elimination of SLOD.
- Address replacing dual circuit towers (DCTs) with single circuit towers (SCTs).
- Address GDC-17 compliance (offsite sources only).
Dominion Page 6 Nuclear Safety First
Basis for FSAR Change Basis of Meeting GDC-17 Without SLOD ISO-New England Current Stability Studies:
Offsite sources reliability is maintained losing either one additional line, a Millstone Unit, or largest other unit under the following:
(1) With either three or four lines available.
OR (2) With two lines available and Millstone Station output < 1650 MWe Net.
Dominion Page 7 Nuclear Safety First
Basis for FSAR Change
==
Conclusion:==
LAR will conclude current plant design meets GDC-17.
- Current plant design has four transmission lines on separate SCTs (SLOD removed).
- All aspects of onsite power system connection to offsite power system remain unchanged.
- Plant design meets GDC-17 based on current ISO-New England stability studies.
Dominion Page 8 Nuclear Safety First
Summary of Proposed Changes Technical Requirements Manual (TRM) Changes
- Specify actions when only three offsite transmission lines are functional.
- Proposed TRM would allow 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with one offsite line removed from service and a provision to allow up to 14 days if specific defense-in-depth measures have been taken.
Dominion Page 9 Nuclear Safety First
Proposed TRM Changes Basis for 14 Day Allowed Outage Time (AOT)
- Avoids multiple shorter line outages resulting in fewer plant and transmission equipment manipulations.
- Similar to current EDG 14 Day AOT.
- Similar to Standard Review Plan (SRP) Branch Technical Position 8-8, Onsite (Emergency Diesel Generators) and Offsite Power Sources Allowed Outage Time Extensions, allowing AOT up to 14 Days.
Dominion Page 10 Nuclear Safety First
Proposed TRM Changes Proposed TRM is based on the following:
Appropriate Defense-In-Depth Measures Traditional Engineering Analysis Configuration Risk Management Insights Dominion Page 11 Nuclear Safety First
Proposed TRM Changes Defense-in-Depth Measures Defense-in-depth measures are proposed for periods when only three transmission lines are available.
- 1. Once per shift, verify the remaining offsite lines to the Millstone Switchyard are FUNCTIONAL.
- 2. Perform an initial weather assessment for the expected line outage duration and then once per shift thereafter.
- 3. Verify that the emergency diesel generators (EDGs) are OPERABLE and the Millstone Unit 3 SBO diesel generator is available and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter.
Dominion Page 12 Nuclear Safety First
Proposed TRM Changes Traditional Engineering Analysis
- No change to onsite power system.
- Offsite transmission lines are designed and operated to assure reliability and efficiency of the New England bulk power system.
- North American Electric Reliability Corporation (NERC) requires each nuclear plant generator operator and its associated transmission entities to establish Nuclear Plant Interface Requirements (NPIRs).
Dominion Page 13 Nuclear Safety First
Proposed TRM Changes Traditional Engineering Analysis
- The NPIR between Millstone Station, ISO-New England, and the local transmission control center (CONVEX), requires the entities to, in part:
Maintain voltage at the Millstone switchyard at or above 345kV and below 362kV.
Coordinate and plan outages of transmission lines serving as a Millstone offsite power source.
Dominion Page 14 Nuclear Safety First
Proposed TRM Changes Traditional Engineering Analysis The following areas of concern remain after replacement of DCTs with SCTs :
- Proximity of Two Lines: At four specific Right-of-Way (ROW) locations, the spacing separation of two of the independent lines are close enough to enable certain types of limiting line-drop type single failures to impact an adjacent line.
- Line Crossovers: At three specific locations at Hunts Brook Junction (part of original design and discussed in FSARs), there exist transmission line crossovers which enable a limiting line-drop type single failure to also impact an adjacent line.
- Tower Failures: There are a number of locations where the towers are in close proximity that the failure of one tower can impact another tower.
Dominion Page 15 Nuclear Safety First
Physical layout of these major transmission lines in the vicinity of Millstone, scaled and overlaid on a satellite photo of Southern Connecticut Dominion Page 16 Nuclear Safety First
First set of towers leaving the switchyard Dominion Page 17 Nuclear Safety First
Simplified Diagram of Connecticuts 345 kV commercial electrical power system in the vicinity of Millstone Dominion Page 18 Nuclear Safety First
Ground-Level View of Hunts Brook Junction (From South Looking North)
Dominion Page 19 Nuclear Safety First
Proposed TRM Changes
- NERC reliability standards considers failure of a single circuit tower or line affecting another tower or line (regardless of proximity) as an extreme contingency for reliability.
- ISO-New England normal contingency stability/transient studies do not include double line-to-ground faults or line-to-line faults if only SCTs are involved.
Dominion Page 20 Nuclear Safety First
Proposed TRM Changes Traditional Engineering Analysis The proposed LAR takes a more conservative approach to areas of concern that could cause the loss of two 345kV lines due to a single event.
- Less than four 345kV transmission lines treated as a degradation of reliability.
- For defense-in-depth purposes, TRM requirements would be implemented whenever station output exceeds 1650 MWe net and only three transmission lines are available.
Dominion Page 21 Nuclear Safety First
Proposed TRM Changes Traditional Engineering Analysis Defenses against Common Cause Failures (CCF) are maintained and the potential for introduction of new CCFs mechanisms are assessed.
- The removal of one 345kV line minimally increases the potential for a loss of offsite power event but this is not a new CCF.
- Proposed defense-in-depth measures reduce the likelihood of a single failure causing the loss of two additional 345kV lines while one line is out of service.
Dominion Page 22 Nuclear Safety First
Proposed TRM Changes Traditional Engineering Analysis Independence of physical barriers is not degraded.
- The physical barriers between the offsite power system to the onsite power system via two connections remain unchanged when one offsite line is removed from service.
Defenses against human errors are maintained.
- Fewer plant and transmission equipment manipulations.
Dominion Page 23 Nuclear Safety First
Proposed TRM Changes Proposed Configuration Risk Program
- Planned transmission line outages are coordinated between ISO-New England and Millstone.
- Transmission Operating Guides will contain Millstone TRM limit.
- During planned transmission line outages, Millstone Station will not remove an emergency diesel generator for an extended maintenance interval.
- Core damage risk associated with performing switchyard work (including transmission line outages and physical work) will be managed under 10CFR50.65(a)(4).
Dominion Page 24 Nuclear Safety First
Final Summary The LAR will document the following:
- Restoring the current license basis to standards originally considered when the plants were licensed.
- Establishing appropriate defense-in-depth measures in the TRM.
- Managing configuration risk.
Dominion Page 25 Nuclear Safety First
Questions??
Dominion Page 26 Nuclear Safety First