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Category:Meeting Briefing Package/Handouts
MONTHYEARML23215A1922023-08-0707 August 2023 – August 7, 2023 Presubmittal Meeting Presentation - Relocation of Technical Specification 3.9.3 Nuclear Instrumentation to a Licensee Controlled Document (EPID: L?2023?LRM-0052) ML23215A1652023-08-0404 August 2023 – August 8, 2023 Presubmittal Meeting Presentation - Technical Specification 3.8.1 AC Sources - Operating Required Action B.4, 14-hour Completion Time (EPID: L?2023?LRM-0053) ML23094A2722023-04-0606 April 2023 – April 6, 2023 Presubmittal Meeting Presentation - Extension Request for Thermal Relief Valves (EPID: L?2023?LRM-0023) ML23081A0252023-03-22022 March 2023 – March 28, 2023 Pre-submittal Meeting Presentation - LAR for Exception to RG 1.81 (EPID L?2023?LRM-0015) ML23045A1552023-02-14014 February 2023 Public Meeting February 23, 2023 - Presentation Slides ML23011A0872023-01-10010 January 2023 License Renewal Scoping Meeting, Comanche Peak Nuclear Power Plant, Units 1 and 2 - Meeting Slides ML22140A1082022-05-31031 May 2022 (CPNPP) First License Renewal (60 Years) Application Pre-Application Submittal Meeting 2, Meeting Slides ML21259A0312021-09-30030 September 2021 Initial License Renewal Pre-Application Submittal Meeting Sept 2021 - Safety ML21259A0292021-09-16016 September 2021 Initial License Renewal - NRC Presubmittal Meeting Slides - Safety ML21259A0352021-09-16016 September 2021 License Renewal Pre-Application Submittal Meeting Sept 2021 Environmental Report ML21259A0332021-09-16016 September 2021 Initial License Renewal Application - NRC Presubmittal Meeting Slides - Environmental ML21097A0522021-04-0707 April 2021 NRC Talking Points - 4/7/2021 Meeting with Vistra Operations Company LLC Proposed COVID-19 Related Exemption Request to Defer the Annual Force-on-Force Exercise for Comanche Peak ML21068A0292021-03-0909 March 2021 Presentation - 3/24/2021 Meeting with Vistra Operations Company LLC Proposed License Amendment Request to Adopt TSTF-505, Revision 2, to Provide Risk-Informed Extended Completion Times at Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 ML21007A2562021-01-12012 January 2021 Luminant-CPNPP License Renewal SAMA January 12 2021 Public Mtg ML20314A3422020-11-12012 November 2020 NRC Teleconference with Comanche Peak Regarding a Proposed Exigent License Amendment Request (LAR) 20-007 TS 3.7.8 Station Service Water System TS 3.8.1 AC Sources - Operating ML20097B2852020-04-0606 April 2020 April 7, 2020, Presubmittal Teleconference Discussion Topics - Proposed Relief Requests for Deferral of Several Inspections and Tests from 2RF18 (Spring 2020) to 2RF19 (Fall 2021) ML20097C2662020-04-0606 April 2020 April 6, 2020, Presubmittal Teleconference Presentation - License Amendment Request Revise Technical Specification 5.5.9 ML20036D4102020-02-12012 February 2020 Pre-Submittal Meeting for: Comanche Peak Nuclear Power Plant Docket Nos. 50-445 and 50-446 February 12, 2020 - License Amendment Request for Changes to Certain Emergency Action Levels ML19296D5592019-10-24024 October 2019 Pre-Submittal Meeting with NRC for Proposed License Amendment Request (LAR) 15-001 TS 3.8.1, AC Sources - Operating, Presentation ML14077A2872014-03-18018 March 2014 Transcript of the 612th ACRS Meeting, March 6, 2014 (Open) Pages 1-317 ML13059A1812013-02-28028 February 2013 Licensee Slides for 2/28/13 Meeting Via Conference Call with Luminant Generation Company, LLC, ML12328A1252012-11-20020 November 2012 Licensee Slides from 11/20/12 Pre-Submittal Meeting to Discuss LAR for Spent Fuel Criticality ML12229A5042012-09-19019 September 2012 8/6/2012 Summary of Conference Call with Luminant to Discuss Proposed License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, to Support Installation of Backup Transformer at Comanche Peak, Units 1 and 2 ML12236A3322012-08-23023 August 2012 Non-proprietary - Presentation for September 13, 2012, Proposed License Amendment Request for Spend Fuel Pool Criticality Analysis ML12188A6972012-07-18018 July 2012 6/26/12 Summary of Meeting with Luminant Generation Company LLC to Discuss Proposed License Amendment Request to Revise TS 3.8.1, AC Sources - Operating, to Support Installation of Backup Transformer at Comanche Peak, Units 1 and 2 (TAC ME8 ML12156A2052012-05-31031 May 2012 Presentation to NRC for LAR 12 ML1125702582011-09-13013 September 2011 Licensee Slides from 9/13/11 Meeting with Luminant Generation Company, LLC Regarding Proposed License Amendment Request for Risk-Informed Technical Specification Task Force Initiative... ML1114003142011-05-19019 May 2011 Summary of Public Meeting with Luminant Generation Company on Comanche Peak Nuclear Power Plant, Units 1 and 2, to Discuss 2010 End of Cycle Performance Assessment ML0924401642009-09-14014 September 2009 Meeting Summary, Pre-Application Meeting on with Luminant Generation Company LLC to Dicuss Future Amendment Request to Revise Comanche Peak Units 1 and 2 Startup Transformer Completion Times ML0919400842009-07-0909 July 2009 Luminant RAI 22 and 23 SBLOCA, Vortex, Air Ingestion, Void Fraction and Flashing Issues ML0919402772009-07-0909 July 2009 Luminant Holistic Overview: Presentation Will Cover Information Related to RAIs 1 - 5, 7, 12 - 14,16 - 19, 21, 25 - 36 and Overall Response to GL 2004-02 ML0919400832009-07-0909 July 2009 Pci RAI 8, Test Protocol, Erosion Issue, RAI 15, Test Protocol, Latent Fiber Issue, Areva RAI 20, Test Flume, Fiberglass Larges Question ML0919400852009-07-0909 July 2009 Luminant RAI 24 and 37, Secondary Line Breaks, Debris Load and Testing ML0919604492009-07-0808 July 2009 Alion Meeting Presentations on RAI 9 - Pool Fill Transport, & RAI 6 - Fiber Erosion Testing ML0828204232008-10-0707 October 2008 Meeting Handout - Comanche Peak Col Application Public Orientation Meeting ML0817100272008-06-12012 June 2008 Second Handout for Comanche Peak Public Outreach Meeting on June 12, 2008 ML0816201432008-06-10010 June 2008 End-of-Cycle Meeting Summary 6/5/08 ML0729204682007-10-29029 October 2007 09/25/2007, Summary of Meeting Between the U.S. Nuclear Regulatory Commission Staff and Strategic Teaming and Resource Sharing Representatives to Discuss License Renewal Activities ML0717200702007-06-20020 June 2007 Summary of Meeting with Txu Power Regarding Comanche Peak Steam Electric Stations End-of-Cycle Assessment for 2006 ML0720101702007-05-23023 May 2007 Enclosure 3 - 5/23/07 P.M. Meeting Slides - Comanche Peak Steam Electric Station, Units 1 and 2 - Summary of Meeting Held on 5/23/07 with Txu Generation Company LP to Discuss the Plans for Methodology Transition and Power Uprate ML0720101742007-05-23023 May 2007 Enclosure 2 - 5/23/07 A.M. Meeting Slides - Comanche Peak Steam Electric Station, Units 1 and 2 - Summary of Meeting Held on 5/23/07 with Txu Generation Company LP to Discuss the Plans for Methodology Transition and Power Uprate ML0707202502006-12-12012 December 2006 12/12-13/2006 Slides, Txu Power Comanche Peak Site, NRC Onsite Review, Site Geotechnical Investigation Activities. ML0435101002004-11-10010 November 2004 Meeting Slides - Nrc/Stars Plant Aging Management Center of Business Meeting ML0330402882003-10-30030 October 2003 Meeting Handout Materials Regarding STARS-IRAG/NRC Meeting to Discuss Topics Taken from the June 10.11, 2003, Workshop ML0324812782003-09-10010 September 2003 Agenda and Handout for Public Meeting Between NRC and Firstenergy Nuclear Operating Company Davis-Besse Nuclear Power Station ML0319206482003-06-10010 June 2003 Meeting Handouts for STARS-IRAG/NRC Workshop to Discuss Selected Topics Listed in the Agenda Attached to Meeting Notice ML0234504632002-12-10010 December 2002 05000445; Txu Energy, Comanche Peak, Public Exit Meeting - December 10, 2002-Licensee Handouts ML0231200242002-11-0707 November 2002 Meeting Handouts - Meeting with Strategic Teaming and Resources Sharing - Integrated Regulatory Affairs Group ML0208705662002-04-15015 April 2002 Meetingsummary with Stars and the NRC to Inform the NRC About Current Stars Activities ML0208107562002-03-19019 March 2002 Operator Licensing Workshop Meeting Summary 2023-08-07
[Table view] Category:Slides and Viewgraphs
MONTHYEARML23332A2772023-11-0707 November 2023 CPNPP Dseis Slide for 12/7/23 Public Meetings_112223 ML23215A1922023-08-0707 August 2023 – August 7, 2023 Presubmittal Meeting Presentation - Relocation of Technical Specification 3.9.3 Nuclear Instrumentation to a Licensee Controlled Document (EPID: L?2023?LRM-0052) ML23215A1652023-08-0404 August 2023 – August 8, 2023 Presubmittal Meeting Presentation - Technical Specification 3.8.1 AC Sources - Operating Required Action B.4, 14-hour Completion Time (EPID: L?2023?LRM-0053) ML23094A2722023-04-0606 April 2023 – April 6, 2023 Presubmittal Meeting Presentation - Extension Request for Thermal Relief Valves (EPID: L?2023?LRM-0023) ML23081A0252023-03-22022 March 2023 – March 28, 2023 Pre-submittal Meeting Presentation - LAR for Exception to RG 1.81 (EPID L?2023?LRM-0015) ML23045A1552023-02-14014 February 2023 Public Meeting February 23, 2023 - Presentation Slides ML23011A0872023-01-10010 January 2023 License Renewal Scoping Meeting, Comanche Peak Nuclear Power Plant, Units 1 and 2 - Meeting Slides ML22140A1082022-05-31031 May 2022 (CPNPP) First License Renewal (60 Years) Application Pre-Application Submittal Meeting 2, Meeting Slides ML21259A0312021-09-30030 September 2021 Initial License Renewal Pre-Application Submittal Meeting Sept 2021 - Safety ML21259A0292021-09-16016 September 2021 Initial License Renewal - NRC Presubmittal Meeting Slides - Safety ML21259A0332021-09-16016 September 2021 Initial License Renewal Application - NRC Presubmittal Meeting Slides - Environmental ML21259A0352021-09-16016 September 2021 License Renewal Pre-Application Submittal Meeting Sept 2021 Environmental Report ML21095A3052021-04-0707 April 2021 4/7/2021 Presubmittal Meeting Presentation - Comanche Peak, Units 1 and 2 - Request for a Temporary Exemption from 10 CFR 73, Appendix B, Section VI, Subsection A.7 and Subsection C.3(l)(1) (L-2021-LRM-0039) ML21097A0522021-04-0707 April 2021 NRC Talking Points - 4/7/2021 Meeting with Vistra Operations Company LLC Proposed COVID-19 Related Exemption Request to Defer the Annual Force-on-Force Exercise for Comanche Peak ML21068A0292021-03-0909 March 2021 Presentation - 3/24/2021 Meeting with Vistra Operations Company LLC Proposed License Amendment Request to Adopt TSTF-505, Revision 2, to Provide Risk-Informed Extended Completion Times at Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 ML21007A2562021-01-12012 January 2021 Luminant-CPNPP License Renewal SAMA January 12 2021 Public Mtg ML20314A3422020-11-12012 November 2020 NRC Teleconference with Comanche Peak Regarding a Proposed Exigent License Amendment Request (LAR) 20-007 TS 3.7.8 Station Service Water System TS 3.8.1 AC Sources - Operating ML20036D4102020-02-12012 February 2020 Pre-Submittal Meeting for: Comanche Peak Nuclear Power Plant Docket Nos. 50-445 and 50-446 February 12, 2020 - License Amendment Request for Changes to Certain Emergency Action Levels ML19337A6622019-12-0303 December 2019 Revised Comanche Peak Pre-Submittal Meeting with NRC for Proposed License Amendment Request (LAR) 15-001 TS 3.8.1, AC Sources -- Operating ML19324D3482019-11-0505 November 2019 December 3, 2019 Pre-Submittal Meeting Presentation - Proposed License Amendment Request (LAR) 15-001 TS 3.8.1, AC Sources - Operating (L-2019-LRM-0072) ML14077A2872014-03-18018 March 2014 Transcript of the 612th ACRS Meeting, March 6, 2014 (Open) Pages 1-317 ML13059A1812013-02-28028 February 2013 Licensee Slides for 2/28/13 Meeting Via Conference Call with Luminant Generation Company, LLC, ML12229A5042012-09-19019 September 2012 8/6/2012 Summary of Conference Call with Luminant to Discuss Proposed License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, to Support Installation of Backup Transformer at Comanche Peak, Units 1 and 2 ML12236A3322012-08-23023 August 2012 Non-proprietary - Presentation for September 13, 2012, Proposed License Amendment Request for Spend Fuel Pool Criticality Analysis ML12188A6972012-07-18018 July 2012 6/26/12 Summary of Meeting with Luminant Generation Company LLC to Discuss Proposed License Amendment Request to Revise TS 3.8.1, AC Sources - Operating, to Support Installation of Backup Transformer at Comanche Peak, Units 1 and 2 (TAC ME8 ML1125702582011-09-13013 September 2011 Licensee Slides from 9/13/11 Meeting with Luminant Generation Company, LLC Regarding Proposed License Amendment Request for Risk-Informed Technical Specification Task Force Initiative... ML1114003142011-05-19019 May 2011 Summary of Public Meeting with Luminant Generation Company on Comanche Peak Nuclear Power Plant, Units 1 and 2, to Discuss 2010 End of Cycle Performance Assessment ML1101908002011-01-18018 January 2011 Summary of Meeting with Luminant Generation Company LLC Regarding a Preliminary Finding with Moderate Safety Significance ML11161A1552009-11-30030 November 2009 Enclosure 4 to TXX-11056, Jp Morgan'S Long-Term Capital Market Returns ML0924401642009-09-14014 September 2009 Meeting Summary, Pre-Application Meeting on with Luminant Generation Company LLC to Dicuss Future Amendment Request to Revise Comanche Peak Units 1 and 2 Startup Transformer Completion Times ML0919402762009-07-0909 July 2009 NRC Opening Remarks Discuss the Draft Us Nuclear Regulatory Commission Request for Additional Information for Generic Letter GL-2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressur ML0919604492009-07-0808 July 2009 Alion Meeting Presentations on RAI 9 - Pool Fill Transport, & RAI 6 - Fiber Erosion Testing ML0918303012009-07-0202 July 2009 Summary of Annual Performance Assessment Meeting for Comanche Peak Steam Electric Stations ML0828204232008-10-0707 October 2008 Meeting Handout - Comanche Peak Col Application Public Orientation Meeting ML0720101742007-05-23023 May 2007 Enclosure 2 - 5/23/07 A.M. Meeting Slides - Comanche Peak Steam Electric Station, Units 1 and 2 - Summary of Meeting Held on 5/23/07 with Txu Generation Company LP to Discuss the Plans for Methodology Transition and Power Uprate ML0720101702007-05-23023 May 2007 Enclosure 3 - 5/23/07 P.M. Meeting Slides - Comanche Peak Steam Electric Station, Units 1 and 2 - Summary of Meeting Held on 5/23/07 with Txu Generation Company LP to Discuss the Plans for Methodology Transition and Power Uprate ML0707202502006-12-12012 December 2006 12/12-13/2006 Slides, Txu Power Comanche Peak Site, NRC Onsite Review, Site Geotechnical Investigation Activities. ML0702304012006-10-20020 October 2006 Pre-DBA and Post DBA Pictures ML0530801972005-10-18018 October 2005 Slides 46 Pages - Comanche Peak -Summary of Meeting with Txu Generation Company, LP, to Discuss Application of Accident Analysis Methodologies ML0435101002004-11-10010 November 2004 Meeting Slides - Nrc/Stars Plant Aging Management Center of Business Meeting ML0429905152004-10-19019 October 2004 Presentation by Txu on 10/19/04 - Comanche Peak Steam Electric Station, Unit 1 - Steam Generator Replacement Project ML0422602762004-08-12012 August 2004 Meeting Summary of the August 8, 2004 Public Workshop - Region IV Operator Licensing Feedback ML0404104602004-02-10010 February 2004 2/4/2004 Meeting Summary with Txu for Comanche Peak, Units 1 and 2 to Discuss Plans for Digital Modifications ML0316806212003-07-17017 July 2003 Licensee'S Handouts, Slides and Viewgraphs, 53 Pages, S107210 ML0316806062003-07-17017 July 2003 NRC Handout, Slides and Viewgraphs, 103 Pages, S107211 ML0234504632002-12-10010 December 2002 05000445; Txu Energy, Comanche Peak, Public Exit Meeting - December 10, 2002-Licensee Handouts ML0234504962002-12-10010 December 2002 05000445-TXU Energy-Comanche Peak; Public Exit Meeting Slides (Nrc); December 10, 2002 ML0211400792002-04-22022 April 2002 Attachment 15, E-Mailed on April 22, 2002 (Docket Nos. 50-445 and 50-446). Slides for Zirlo Meeting ML0210801292002-03-0505 March 2002 March 5, 2002 - RIC 2002 Presentation - T3 Lance Terry - Policy Focus Safeguards/Security Issues ML0204200522002-02-0505 February 2002 Regulatory Conference - January 23 2002 2023-08-07
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Comanche Peak Nuclear Power Plant (CPNPP)
P re -Submittal Meeting with the NRC for Proposed License Amendment Request (LAR) 23- 002, Application Regarding General Design Criteria 5 (GDC-5) Shared System Requirements
Licensee Amendment to Receive NRC Approval for an Exception to Regulatory Guide (RG) 1.81, Revision 1, Regulatory Positions C.1 and C.3 Agenda
- Reason the LAR is Necessary
- Applicable Regulatory Requirements
- Proposed Change to the CPNPP Position Towards RG 1.81, Revision 1
- Existing Configuration of Applicable Loads
- Questions Reason the LAR is Necessary CPNPP has received a Notice of Violation (NOV) based on not resolving a previous Non-Cited Violation (NCV) in a timely manner. The NOV reads in-part:
The previous violation identified the licensee's failure to obtain a license amendment or perform a written evaluation demonstrating the basis for not obtaining a license amendment prior to making a change to the facility as described in the Final Safety Analysis Report. Specifically, the licensee revised the Final Safety Analysis Report to change the facility's commitments to NRC Regulatory Guide 1.81, which demonstrated compliance with General Design Criterion 5, without obtaining a license amendment.
In the required NOV response to the NRC, CPNPP made a commitment to the NRC that reads:
A 10CFR50.59 evaluation will be performed, and a license amendment will be submitted to address CPNPP' s commitments to NRC Regulatory Guide (RG) 1.81.
Based on this, the upcoming LAR is necessary to resolve the NRC concern with CPNPP s commitment to RG 1.81 Applicable Regulatory Requirements - GDC 5 and GDC 17
General Design Criteria 5 - Sharing of Structures, Systems, and Components Structures, systems, and components important to safety shall not be shared among nuclear power units unless it can be shown that such sharing will not significantly impair their ability to perform their safety functions, including, in the event of an accident in one unit, an orderly shutdown and cooldown of the remaining units.
General Design Criteria 17 - Electric Power Systems An onsite electric power system and an offsite electric power system shall be provided to permit functioning of structures, systems, and components important to safety. The safety function for each system (assuming the other system is not functioning) shall be to provide sufficient capacity and capability to assure that (1) specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded as a result of anticipated operational occurrences and (2) the core is cooled and containment integrity and other vital functions are maintained in the event of postulated accidents.
Applicable Regulatory Requirements - RG 1.81, Regulatory Positions C.1 & C.3
Regulatory Guide 1.81, Revision 1, Regulatory Position C.1 D.C. systems in multi-unit nuclear power plants should not be shared.
Regulatory Guide 1.81, Revision 1, Regulatory Position C.3 In the case of multi -unit nuclear power plants for which the construction permit application was made on or after June 1, 1973, each unit should have separate and independent onsite emergency and shutdown electric systems, both a.c. and d.c., capable of supplying minimum ESF loads and the loads required for attaining a safe and orderly cold shutdown of the unit, assuming a single failure and loss of offsite power.
Applicable Regulatory Requirements - RG 1.6, RG 1.9, and RG 1.47 Summaries
Regulatory Guide 1.6, Revision 0, describes an acceptable degree of independence between redundant standby (onsite) power sources and between their distribution systems.
Regulatory Guide 1.9, Revision 0, describes an acceptable basis for the selection of diesel generator sets of sufficient capacity and margin to implement GDC 17.
Regulatory Guide 1.47, Revision 0, describes an acceptable method of complying with the requirements of IEEE Standard 279-1971 and Appendix B to 10 CFR Part 50 with regard to indicating the inoperable status of a portion of the protection system (as defined in IEEE Standard 279-1971),
systems actuated or controlled by the protection system, and auxiliary or supporting systems that must be operable for the protection system and the systems it actuates to perform their safety-related functions.
CPNPP Current Position To w a r d s RG 1.81, Revision 1 The CPNPP design is in compliance with the provisions of Regulatory Guide 1.81 with an exception to Regulatory Position C1 as described below.
Safet y-related loads shared between both units are powered from common MCCs, 120- VAC panels, 118-VAC panels, and 125-VDC panels as described in Subsections 8.3.1.1.9, 8.3.1.1.13 and 8.3.2.1. Indication of source of power associated with the common electrical equipment mentioned above is provided on a common panel located in the Control Room and accessible to both unit operators.
A single failure at the system level will not affect the capability to automatically supply minimum ESF loads in any one unit and safely shutdown the other unit assuming a loss of off-site power because the redundancy of common buses is maintained the same as redundancy for Unit 1 and Unit 2 buses.
On-site power capacity to energize sufficient seismic Category I equipment to attain a safe and orderly cold shutdown of both the units, assuming the loss of off-site power and most severe design basis event and a single failure in the on-site electrical system, is not compromised as a result of common buses because each unit system is designed to have sufficient capacity to feed common bus loads in addition to the unit specific loads.
The CPNPP design is controlled such that only common loads are fed from common buses except for some DC / 118-VA C common panels which feed Unit 1 loads also and the normal source of power for the panels is Unit 1. This does not affect the capability of any unit to feed these loads adequately. Because the unit specific loads of only one unit are fed from a common panel and the common panel normal power source is the same unit, therefore, under normal operation, the interaction between the units for maintenance and test operation will be no different than what is required for a common panel. The time when such common panel is aligned to the unit other than the one whose specific loads it feeds will be limited, therefore, any additional interaction needed for maintenance and test activities will be limited also.
Proposed Change to the CPNPP Position Towards RG 1.81, Revision 1 The CPNPP design represents a deviation of Regulatory Guide 1.81, Regulatory Positions C.1 and C.3, as approved in Amendments [xxx] and [xxx] to the Unit 1 and Unit 2 facility licenses, respectively (Reference 49). Regulatory Position C.1 states that D.C. systems in multi-unit nuclear power plants should not be shared. Regulatory Position C.3 states that each unit should have separate and independent onsite emergency and shutdown electric systems (i.e., vital power should not be shared between units). The CPNPP design includes some safety related common loads, which is a deviation from Regulatory Guide 1.81, Regulatory Positions C.1 and C.3. The acceptability of this design is described below and is in compliance with GDC 5 in that the sharing of these loads does not significantly impair the ability to perform the necessary safety functions, assuming an accident in one unit and an orderly shutdown and cooldown of the remaining unit.
Safet y-related loads shared between both units are powered from common MCCs, 120- VAC panels, 118-VAC panels, and 125-VDC panels as described in Subsections 8.3.1.1.9, 8.3.1.1.13 and 8.3.2.1. Indication of source of power associated with the common electrical equipment mentioned above is provided on a common panel located in the Control Room and accessible to both unit operators.
A single failure at the system level will not affect the capability to automatically supply minimum ESF loads in any one unit and safely shutdown the other unit assuming a loss of off-site power because the redundancy of common buses is maintained the same as redundancy for Unit 1 and Unit 2 buses.
On-site power capacity to energize sufficient seismic Category I equipment to attain a safe and orderly cold shutdown of both the units, assuming the loss of off-site power and most severe design basis event and a single failure in the on-site electrical system, is not compromised as a result of common buses because each unit system is designed to have sufficient capacity to feed common bus loads in addition to the unit specific loads.
The CPNPP design is controlled such that only common loads are fed from common buses except for some DC / 118-VA C common panels which feed Unit 1 loads also and the normal source of power for the panels is Unit 1. This does not affect the capability of any unit to feed these loads adequately. Because the unit specific loads of only one unit are fed from a common panel and the common panel normal power source is the same unit, therefore, under normal operation, the interaction between the units for maintenance and test operation will be no different than what is required for a common panel. The time when such common panel is aligned to the unit other than the one whose specific loads it feeds will be limited, therefore, any additional interaction needed for maintenance and test activities will be limited also.
Background
The CPNPP Unit 1 and Unit 2 design includes some common loads which can be powered from either unit, including receiving power from Class 1E vital AC and DC sources.
The DC Power System sharing of common loads was noted in CPNPP SER, NUREG -0797 Supplement 22:
"There are no bus ties or sharing of power supplies between redundant trains. Class 1E equipment associated with systems shared by both units receives power from panel boards having an incoming automatic transfer switch which can select power from either unit. Transfer switch design is such that power cannot be supplied from both units simultaneously. Train separation is maintained by supplying these shared panel boards from the same train of both units. Sharing of these power sources in this manner does not significantly impair the ability of these sources to perform their safety function and, as such, this arrangement is in accordance with GDC 5."
"On the basis of its review of the dc power system as described in the FSAR, the staff concludes that two fully redundant Class 1E dc systems are provided. The systems are testable, independent, and conform to the requirements of Regulatory Guides 1.6 and 1.32. These systems meet the requirements of GDC 5, 17, and 13 and are, therefore, acceptable."
Background (cont.)
The AC Power Systems ability to share common loads was noted in NUREG- 0797, Supplement 22:
Nuclear -safety-related loads common to both units are powered from Class 1E MCCs [motor control centers] and distribution panels which have supplies from each unit. Class 1E MCCs and distribution panels common to both units shall be aligned to be powered from Unit 1 only until Unit 2 design, installation, and testing are complete. These dual -unit supplies are interlocked to preclude supplying power to one MCC or distribution panel from both units simultaneously. Incoming feeders to train A MCCs or distribution panels common to both units are supplied only from train A power systems of both units (a similar arrangement exists for train B equipment and incoming feeders). This ensures the proper train separation between equipment common to both units.
However, NUREG-0797, Supplement 22 later notes that:
There is no sharing of emergency power sources between units, which is in accordance with RG 1.81.
Technical Evaluation - 118 VAC 118 VAC instrument distribution panels XEC1-1 and XEC2-1 provide power to common and Unit 1 specific safety-related loads. Associated inverters feed supply power to these panels and are normally powered from vital 480 VAC sources but will automatically transfer to the associated 125 VDC battery if AC power is lost. CPNPP has administratively disallowed powering XEC1-1 and XEC1-2 from Unit 2 unless Unit 1 is defueled, due to the potential for some relays to not function properly when these panels were powered from the Unit 2 source, following a loss of the Unit 2 power source with coincident Unit 1 safety injection (SI) signal. The failure of these relays to actuate would prevent some automatic SI functions from occurring (such as some required load shedding,
fan starts, valve re-positionings, etc.) following a Unit 1 SI signal.
Technical Evaluation - 125 VDC 125 VDC distribution panels XED1 and XED2 are normally aligned to Unit 1 through automatic transfer switches, and supply power to common and Unit 1 specific safety-related loads. Evaluations confirmed that the power sources, from both units, feeding the common buses have sufficient capacity and capability to adequately feed all the common bus loads, as stated in the FSAR.
Nevertheless, procedures maintain the panels normally powered from Unit 1 and limit the time power is supplied from Unit 2 by limiting the time of maintenance and testing activities.
Technical Evaluation - Unit 2 Specific Loads With respect to Unit 2, no Unit 2 specific loads are powered from the subject common panels (XEC1-1 / XEC 1-2/XED1/XED2). With no Unit 2 specific loads powered from a Unit 1 source, no further adverse impacts on safety function performance were identified.
Technical Evaluation - Single Failure Considerations Due to the sharing of systems being train-separated (Train A common system loads are fed ONLY from Unit 1 and Unit 2 Train A sources, and Train B common system loads are fed ONLY from Unit 1 and Unit 2 Train B sources), and being limited to only two units, a single failure at the system level would not preclude the capability to automatically supply minimum ESF loads in any one unit and safely shutdown the other unit, assuming a loss of off -site power (LOOP).
Technical Evaluation - Summary
- 1. The design does not significantly impair the ability to perform the specified safety functions, including an assumption of an accident in one unit and coincident orderly shutdown and cooldown of the remaining unit, and, therefore, meets the requirements of 10 CFR 50, Appendix A, GDC 5, " Sharing of structures, systems, and components.
- 2. For common vital 118 VAC buses/panels supplying Unit 1 specific loads, administrative controls require these buses/panels to be aligned from Unit 1 power sources, except when Unit 1 is defueled.
- 3. The shared power sources from both units (DC and AC) feeding the common buses have sufficient capacity and capability to adequately feed all the common bus loads, as stated in the FSAR.
- 4. The sharing of the electrical power supplies is limited between two units only.
- 5. Because redundancy for common systems is maintained consistent with that of unit -specific safety related trains, a single failure at the system level will not preclude the capability to automatically supply minimum safety -related loads in any one unit and safely shutdown the other unit assuming a loss of offsite power.
- 6. The design of the common 125 VDC and 118 VAC system panels conforms to the requirements of GDC 17, "Electrical Power Systems" (Reference 9), RG 1.6 (Reference 6), RG 1.9 (Reference 7), and RG 1.47 (Reference 8).
LAR Schedule P re-Submittal Meeting on 03/28/23 Submittal of LAR by 04/22/23 Request Approval of LAR by 05/29/24 Implementation of LAR by 06/28/24 - Committed to in NOV response Questions?