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MONTHYEARML18270A3642018-09-27027 September 2018 Topics NRC Staff Would Like Exelon to Address at Calvert Cliffs 50.69 LAR Pre-submittal Meeting Project stage: Meeting ML18276A0712018-10-0404 October 2018 Exelon'S Presentation for October 4, 2018 Public Pre-Submittal Meeting on Planned Calvert Cliffs 10CFR50.69 LAR Project stage: Meeting ML18292A8202018-10-24024 October 2018 October 4, 2018, Summary of Pre-Application Meeting with Exelon Generation Co., LLC on Planned Submittal of Licensing Action for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, Risk-Informed Categorization and Treatment Project stage: Meeting 2018-10-04
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML23033A6672023-01-30030 January 2023 Public Call with Constellation January 30, 2023 (Slides) ML22013A3942022-01-13013 January 2022 Presentation Information for Pre-Submittal Meeting Regarding Relief Request to Use the Carbon Fiber Reinforced Polymer (Cfrp) Composite System ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21144A0172021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request Pre-Submittal Meeting ML21134A0162021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request - NRC Pre-submittal Meeting Telecon May 24, 2021 (EPID L-2021-LRM-0051) (Slides) ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20246G8772020-09-0303 September 2020 Licensee'S Presentation for September 3, 2020 Public Telephone Conference ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation ML19318F9512019-11-20020 November 2019 Presentation Slides for November 20, 2019, Pre-Application Meeting - Request for Revision to Quality Assurance Program Internal Audit Frequency ML19317C9952019-11-12012 November 2019 In-Service Testing Supplemental Position Indication Relief Request NRC Pre-Application Meeting November 18, 2019 ML19246B7162019-08-29029 August 2019 Meeting Between NRC and Exelon Regarding Calvert Cliffs-2 LAR to Use Framatome ATF LTAs ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19151A6602019-05-31031 May 2019 BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19022A2002019-01-23023 January 2019 Request for Use of ASME Code Case N-879 for Exelon Nuclear Power Plants ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18276A0712018-10-0404 October 2018 Exelon'S Presentation for October 4, 2018 Public Pre-Submittal Meeting on Planned Calvert Cliffs 10CFR50.69 LAR ML18171A0842018-06-21021 June 2018 GSI-191 Program Use of Risk Metrics for Containment Sump Tech Spec Operability Determination June 21, 2018 Public Meeting Slides (MF8521, MF8522; L-2016-LRM-0001) ML18190A3922018-06-14014 June 2018 Licensee Presentation Material for June 14, 2018 Public Meeting ML18136A4932018-05-16016 May 2018 Licensee'S Slides for Pre-Application Meeting W/Exelon Re Planned GSI-191 LAR for Calvert Cliffs (L-2016-LRM-0001) ML18096A0222018-04-0404 April 2018 Annual Assessment Meeting 04/04/2018 Handouts ML18096A9902018-03-12012 March 2018 NRC Pre-Submittal Call Briefing Notes, Calvert Cliffs Emergency Planning Future Licensing Actions ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML17143A1612017-05-23023 May 2017 Annual Assessment Meeting Handout and Sign in Sheet ML16274A0012016-09-30030 September 2016 PWR MSIP Analysis and Measurements ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML15321A3702015-12-0101 December 2015 GSI-191 Program Strainer Head Loss Testing and Option 2b Closure Approach ML15308A1072015-11-0505 November 2015 TSTF-505 LAR - NRC Pre-Submittal, November 5, 2015 Meeting Slides ML15282A0832015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application - Final ML15279A4992015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application ML15222A5472015-08-31031 August 2015 GSI 191 Program Chemical Effects Testing Update Option 2b Closure Approach ML15152A0822015-06-0404 June 2015 Presentation for the June 4, 2015 Public Meeting Regarding the National Fire Protection Association Standard 805 License Amendment Request ML14230A9132014-08-18018 August 2014 Enclosure - Fuel Performance and Cask Internals - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L ML14230A9112014-08-18018 August 2014 Enclosure - Example AMP - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 ML14230A9102014-08-18018 August 2014 Enclosure - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 2024-01-30
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides NEI 99-01, Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides2023-02-21021 February 2023 Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML23033A6672023-01-30030 January 2023 Public Call with Constellation January 30, 2023 (Slides) ML22124A1492022-05-10010 May 2022 (Ccnpp) Control Element Assembly (CEA) Recovery Time Improvement Project LAR Pre-Submittal Non-Proprietary (Public) ML22124A1482022-05-10010 May 2022 (Ccnpp) Control Element Assembly (CEA) Recovery Time Improvement Project LAR Pre-Submittal Redacted (Public) ML22013A3942022-01-13013 January 2022 Presentation Information for Pre-Submittal Meeting Regarding Relief Request to Use the Carbon Fiber Reinforced Polymer (Cfrp) Composite System ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs ML21144A0172021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request Pre-Submittal Meeting ML21134A0162021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request - NRC Pre-submittal Meeting Telecon May 24, 2021 (EPID L-2021-LRM-0051) (Slides) ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20246G8772020-09-0303 September 2020 Licensee'S Presentation for September 3, 2020 Public Telephone Conference ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20163A6542020-06-18018 June 2020 2020 NRC Annual Assessment Webinar Presentation - Pennsylvania and Maryland Facilities (Beaver Valley, Calvert Cliffs, Limerick, Peach Bottom, Susquehanna) ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation ML19246B7162019-08-29029 August 2019 Meeting Between NRC and Exelon Regarding Calvert Cliffs-2 LAR to Use Framatome ATF LTAs ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18276A0712018-10-0404 October 2018 Exelon'S Presentation for October 4, 2018 Public Pre-Submittal Meeting on Planned Calvert Cliffs 10CFR50.69 LAR ML18171A0842018-06-21021 June 2018 GSI-191 Program Use of Risk Metrics for Containment Sump Tech Spec Operability Determination June 21, 2018 Public Meeting Slides (MF8521, MF8522; L-2016-LRM-0001) ML18136A4932018-05-16016 May 2018 Licensee'S Slides for Pre-Application Meeting W/Exelon Re Planned GSI-191 LAR for Calvert Cliffs (L-2016-LRM-0001) ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML16328A2832016-11-18018 November 2016 Supplemental Presentation Slides for 10/25/2016 Public Meeting Via E-mail from K.Greene to R.Guzman Calvert Cliffs GSI-191 Resolution Update ML16307A4902016-10-25025 October 2016 Presentation Slides from Public Meeting Calvert Cliffs GSI-191 Resolution Update ML16274A0012016-09-30030 September 2016 PWR MSIP Analysis and Measurements ML16242A1782016-09-0101 September 2016 Presentation Slides from Public Meeting Regarding Calvert Cliffs GSI-191 Resolution Update ML16198A0012016-07-18018 July 2016 Presentation Slides from Public Meeting Regarding Calvert Cliffs GSI-191 Resolution Update ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML15321A3702015-12-0101 December 2015 GSI-191 Program Strainer Head Loss Testing and Option 2b Closure Approach ML15308A1072015-11-0505 November 2015 TSTF-505 LAR - NRC Pre-Submittal, November 5, 2015 Meeting Slides ML15279A4992015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application ML15282A0832015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application - Final ML15222A5472015-08-31031 August 2015 GSI 191 Program Chemical Effects Testing Update Option 2b Closure Approach ML15152A0822015-06-0404 June 2015 Presentation for the June 4, 2015 Public Meeting Regarding the National Fire Protection Association Standard 805 License Amendment Request ML14230A9132014-08-18018 August 2014 Enclosure - Fuel Performance and Cask Internals - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L ML14230A9112014-08-18018 August 2014 Enclosure - Example AMP - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 ML14230A9102014-08-18018 August 2014 Enclosure - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 ML14230A9092014-08-18018 August 2014 Enclosure - Generic Concrete AMP CC ISFSI - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 ML14230A9082014-08-18018 August 2014 Enclosure - Elements of an AMP CC ISFSI - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 2024-01-30
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Calvert Cliffs 10CFR50.69 LAR Pre-Submittal Meeting October 4, 2018
Agenda
- Discuss NRC questions on Seismic approach
- Get alignment on level of detailed need in the LAR
- Staff Questions & Concerns 1 Calvert Cliffs 50.69 LAR Pre-submittal meeting
Calvert Cliffs and Industry Attendees
- Shannon Rafferty-Czincila - Exelon Senior Manager, Risk Management
- Barry Sloane - Exelon Risk Management
- Phil Tarpinian - Exelon Risk Management
- Enrique (Rick) Villar - Exelon Corporate Licensing
- Rob Cavedo - Exelon Risk Management
- James Landale - Exelon Risk Management
- John Koelbel - Exelon Risk Management
- David Passehl - Exelon Risk Management
- John Richards - EPRI 2 Calvert Cliffs 50.69 LAR Pre-submittal meeting
Calvert Cliffs 10CFR50.69 - The Rule
- 10 CFR 50.69 allows adjustment of the scope of equipment subject to special treatment controls (e.g., quality assurance, testing, inspection, condition monitoring, assessment, and evaluation).
- Allows licensees to focus resources on SSCs that make a significant contribution to plant safety.
- Allows licensees to categorize SSCs using a risk-informed process.
- The risk-informed categorization process determines the safety significance of SSCs and place the SSCs into one of four Risk-Informed Safety Class (RISC) categories.
3 Calvert Cliffs 50.69 LAR Pre-submittal meeting
Calvert Cliffs 10CFR50.69
- The NEI 00-04 provides 2 options for considering seismic risks:
- An SPRA can be used with specified risk ranking and sensitivity studies to determine seismic related HSS SSCs
- An IPEEE Seismic Margins Assessment (SMA) equipment list can be used where all of the SSCs on the equipment list are designated HSS.
- Calvert Cliffs cannot submit 50.69 LAR without an alternative approach to characterize seismic risks
- Industry developed EPRI TR 3002012988 Alternative Approaches for Addressing Seismic Risk in 10CFR50.69 Risk-Informed Categorization
- Calvert Cliffs will submit using this approach 4 Calvert Cliffs 50.69 LAR Pre-submittal meeting
NRC Questions and Discussion Application of Seismic Risk Insights Using a Risk Informed Approach RIDM is a top regulatory priority
- SECY-17-0112, Plans for Increasing Staff Capabilities to Use Risk Information in Decision-making Activities
- SECY-18-0060, Achieving Modern Risk Informed Regulation Use of this approach is consistent with the a recommendation from SECY-18-0060 (Staff Response to EDO Transformation Letter)
- expanding the use of qualitative and quantitative risk insights to scale the scope and depth of licensing reviews depending on the safety and security significance of the matter being reviewed The application of a seismic alternative approach to inform the 50.69 categorization process is an example of RIDM
- The incorporation of insights from contemporary seismic PRAs provide a perspective on the seismic risk contribution to the 50.69 categorization decision making process 6 Calvert Cliffs 50.69 LAR Pre-submittal meeting
1 - Describe the integrated, systematic process being used to support the risk-informed categorization and treatment of SSCs
- The requirements of 10CFR50.69(c) apply to the entire categorization process, not new approaches to screening a hazard. However EPRI Seismic Alternative approach:
- Considers the results and insights from the plant-specific PRA.
- Employs a systematic process to evaluated the seismic hazard which is integrated into the overall categorization process.
- The EPRI systematic process:
- Considers the likelihood and magnitude of the seismic hazard.
- Considers margin to the site specific seismic design basis.
- Uses insights from categorization trials performed using detailed seismic PRAs, at high seismic hazard sites, to determine the degree to which seismic importance measures contribute to the 50.69 categorization decisions.
- Using those risk-informed insights, a graded implementation process was developed to consider the site-specific contributions of seismic risks in the full NEI 00-04 categorization process in concert with insights from other risk evaluations, Defense-in-Depth considerations, and Integrated Decision-making Panel considerations.
7 Calvert Cliffs 50.69 LAR Pre-submittal meeting
2 - Describe whether the case studies in the EPRI report are bounding for Calvert Cliffs
- The Case Studies in the EPRI Report are representative and risk-informed for the industry, including Calvert Cliffs.
- The trials in the EPRI report are performed at sites with high seismic hazards relative to their design basis and are therefore more likely to challenge the seismic capability of the plant and produce unique seismic insights.
- At Calvert Cliffs, and other Tier 1 plants, the seismic hazard is less challenging compared to the seismic design basis and therefore, the expected unique seismic insights are much less likely.
- The graded seismic process developed in the EPRI report focuses specifically on 50.69 categorization insights, and consistent with other risk-informed applications recommends focusing efforts where unique insights are more likely to occur and less efforts where they are unlikely.
8 Calvert Cliffs 50.69 LAR Pre-submittal meeting
3 - Describe how the proposed approach addresses the discussion in Section II.1.2 of the statements-of-consideration for 10 CFR 50.69
- 1. The industry commenters stated that additional PRA requirements were not necessary because the other categorization requirements in § 50.69(c) addressed other modes and events not addressed by the PRA and as a result, all sources of risk were addressed
- The EPRI report addresses this explicitly. The results of the 4 example sites demonstrate that all sources of risk are adequately address by either the results of the other elements of the categorization process (Tier 1 sites), or a combination of the other categorization methods combined with additional correlated failure investigations (Tier 2 sites).
- 2. and where non-PRA methods are used, the requirements and associated implementation guidance account for this situation by requiring a process that tends to conservatively categorize SSCs into RISC-1 and RISC-2
- NEI 00-04 was written prior to the development of many of the risk-informed processes in use today, and as such the non-PRA processes invoked do tend to produce conservative results.
- The method described in the EPRI report is a risk-informed process based on PRA results, and is demonstrated to produce results equivalent to seismic PRAs 9 Calvert Cliffs 50.69 LAR Pre-submittal meeting
4 - Identify any differences between the approved Limerick 50.69 LAR and the planned Calvert Cliffs 50.69 LAR
- Calvert will apply the same methodology and implementation of NEI 00-04 as Limerick
- The only deviation from the NEI 00-04 (and the Limerick 50.69 LAR) is the approach to the screening assessment for the seismic external hazard 10 Calvert Cliffs 50.69 LAR Pre-submittal meeting
5 - Identify which portions of the EPRI report (or information in the EPRI report) will be included in the submittal
- The entire EPRI report will be submitted as part of the Calvert LAR
- The LAR will indicate that only those portions of the report that support the Tier 1 approach are applicable to Calvert Cliffs
- Note: the Tier 2 plant will have the same approach 11 Calvert Cliffs 50.69 LAR Pre-submittal meeting
6 - Identify which portions of the EPRI report that Exelon will be using as the technical justification for the planned amendment
- The entire EPRI report will be submitted as part of the Calvert LAR
- The LAR will indicate that only those portions of the report that support the Tier 1 approach are applicable to Calvert Cliffs
- This includes the majority of the report (excludes Sections 2.3 and 2.4) 12 Calvert Cliffs 50.69 LAR Pre-submittal meeting
7 - Describe whether the alternative approach described in the EPRI report can be considered a bounding approach
- Approach defined in EPRI Report is a risk-informed, graded process.
- Graded seismic process focuses specifically on 50.69 categorization insights
- Consistent with other risk-informed applications, focuses on where unique insights are more likely to occur rather than where they are unlikely
- Examined sites with high seismic hazards relative to their design basis that are more likely to challenge the plant seismic capability and produce unique seismic insights.
- At Tier 1 and Tier 2 plants, seismic hazard is less challenging compared to design basis, so expectation of unique seismic insights is even less likely.
- Seismic hazard at Tier 1 plants is sufficiently low that it is unlikely the 50.69 Integral Importances would be driven by seismic risk.
- Integral Importance assessment weighs component importance from each contributor (hazard) by the fraction of the total CDF for that contributor.
- Therefore unlikely that the 50.69 Integral Importance of any component would have a required HSS outcome due to seismic risk for Tier 1.
- Other, non-PRA elements of the 50.69 categorization process provide reasonable confidence that SSC design requirements, including earthquake response, are adequately considered in HSS determination 13 Calvert Cliffs 50.69 LAR Pre-submittal meeting
8 - For the PRAs used in the case studies, state whether the PRAs have been used to support NRC approval of licensing actions comparable to the planned 50.69 LAR PLANT NSSS Containment RG 1.174 Risk-Informed LARs, Comparable to 50.69 LARs, Using RG 1.200 PRAs FPIE FPRA SPRA (INTERNAL)
Mark I (Steel (NS) 50.69 (NS) 50.69 A GE / BWR 4 Drywel and -
Wetwell) (App X) (App X)
(NS) ILRT Westinghouse / Large Dry, B N/A -
3-loop Subatmospheric (no App X)
(NS) 50.69, RICT (NS) 50.69, RICT (NS) 50.69, Westinghouse /
C Large Dry (NR) TMRE,ILRT, # (NR) TMRE,ILRT, # (NR) TMRE,ILRT, #
4-loop (no App X) (no App X) (no App X)
SFCP *, 50.69
Westinghouse / Wet, Ice D N/A 4-loop Condenser (App X) (App X)
Legend:
- October 2018 # GSI-191 (NS) NRC SER Issue (NR) NRC review in progress 14 Calvert Cliffs 50.69 LAR Pre-submittal meeting
9 - For the SPRAs used in the case studies in the EPRI report, describe whether peer-review findings have been appropriately addressed for risk-informed licensing actions and whether SPRA peer-review findings have been closed out using an NRC-approved process PLANT NSSS Containment RG 1.200 SPRAs Peer NTTF Rec. 2.1 SPRA App. X Review Closure Status Findings ^ Review Mark I (Steel Submitted A GE / BWR 4 Drywel and YES (NR)
ALL NO Wetwell)
Large Dry, Westinghouse Submitted B
/ 3-loop Subatmo- YES (NR)
ALL NO spheric Westinghouse Submitted C
/ 4-loop Large Dry YES (NS)
ALL NO Westinghouse Wet, Ice Submitted D
/ 4-loop Condenser YES (NS)
OPEN YES Legend: ^ Finding Resolutions Reported (NS) NRC SER Issue (NR) NRC review in progress 15 Calvert Cliffs 50.69 LAR Pre-submittal meeting
10 - Discuss the relevance of the Near Term Task Force 2.1 evaluations in determining the appropriate tier for the proposed alternative approaches considering the differences in scope and purpose
- The 50.69 Seismic Alternate approach uses the best estimate seismic hazard for the site along with the seismic design basis.
- The site seismic hazard was developed in response to the NRCs NTTF 50.54(f) letter and was reviewed and accepted by the NRC.
- The site seismic hazards reflect the site, for any purpose.
- The site hazard is the same for all risk informed applications.
- Threshold for Tier 1 sites has no association with NTTF 2.1 evaluations.
- At Tier 1 sites, GMRS is either very low or within the range of the SSE such that unique seismic categorization insights not expected.
16 Calvert Cliffs 50.69 LAR Pre-submittal meeting
11 - Discuss why correlated failures that are evaluated for Tier 2 plants are not considered for Tier 1 plants (i.e., why Tier 2 evaluations are not performed for Tier 1).
- At the low seismic hazard sites in Tier 1, the likelihood of identifying a unique seismic condition that would cause an SSC to be designated HSS is very low.
- Based on the trial cases for plants with high seismic ground motions compared to their design basis and detailed SPRAs, few if any SSCs would be designated HSS for seismic unique reasons.
- This same philosophy would apply to seismic correlated fragilities similarly as seismically independent fragilities.
17 Calvert Cliffs 50.69 LAR Pre-submittal meeting
12 - Describe how risk significant SSCs identified by fire PRA will be addressed considering the incorporation of a new approach that relies on fire PRA models to identify SSCs that are important to safety
- The approach is not completely reliant on fire PRA models to identify SSCs important to safety
- EPRI report shows the large majority of seismic risk HSS SSCs are overlaid by FPIE HSS determination; Impacts of fire risk evaluations are limited.
- It is possible that even these few SSCs would be captured by other portions of the NEI 00-04 categorization process including:
- Defense-in-Depth, Shutdown, IDP qualitative considerations that do not permit downgrading an HSS SSC categorization
- Inclusion of a non-overlapping component in a function that is otherwise HSS and not able to be performed without the individual SSC.
Number of HSS HSS Seismic Fragility HSS Seismic Fragility Trial Plant Seismic Fragility Groups Overlaid ONLY by Groups Overlaid by FPIE Groups Fire Risk Plant A 23 22 1 Plant B 38 38 0 Plant C 28 17 6 Plant D 59 28 3 18 Calvert Cliffs 50.69 LAR Pre-submittal meeting
13 - Describe - how Exelon will address the potential hazard changes that may change the current proposed Tier 1 classification in the future and therefore, the categorization approach with respect to seismic risk
- NRC Process for Ongoing Assessment of Natural Hazards Information (POANHI)
- Enhances Safety, Integrated w/ existing process, provides stability & predictability (Ref. NRC SECY-15-0137, SECY-16-0144 )
- NRC staff proactively and routinely aggregates and assesses new natural hazard info
- NRC will use existing processes (e.g. GIP, identification of future research)
- 10CFR50.69(e) (1) - Licensee shall review changes to the plant, operational practices, applicable plant & industry operational experience and update the SSC categorization &
treatment process every 2 refueling outages.
- 1. INPO post-Fukushima actions (IER 13-10) o Sites have implemented a process to formally evaluate challenges to design basis assumptions for external events, i.e. credible new hazard information
- 2. EPRI o Compiles and analyzes new information annually related to specific External Events, including seismic (Ref. NEI 12-06)
- Exelon specific OPEX processes
- Several procedures incorporate the INPO/EPRI Processes
- External NSRB review annually 19 Calvert Cliffs 50.69 LAR Pre-submittal meeting
LAR Wording Section 3.2.3
- CCNPP proposes to apply an alternative seismic approach to those listed in NEI 00-04 sections 1.5 and 5.3. This alternative approach is specified in EPRI 3002012988.
- CCNPP meets the Tier 1 criteria for Low Seismic Hazard/High Seismic Margin.
- Tier 1: Plants where the GMRS [Ground Motion Response Spectrum]
peak acceleration is at or below approximately 0.2g or where the GMRS is below or approximately equal to the SSE [Safe Shutdown Earthquake]
between 1.0 Hz and 10 Hz. Examples are shown in Figures 2-1 and 2-2.
At these sites, the GMRS is either very low or within the range of the SSE such that unique seismic categorization insights are not expected.
- For CCNPP, the 1st criterion is met
- See handout for exact wording 20 Calvert Cliffs 50.69 LAR Pre-submittal meeting
Review
- Discuss NRC questions on Seismic approach
- Get alignment on level of detailed need in the LAR
- Staff Questions & Concerns 21 Calvert Cliffs 50.69 LAR Pre-submittal meeting