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Category:Meeting Briefing Package/Handouts
MONTHYEARML24302A2422024-10-29029 October 2024 ECCS Compensated Level System Replacement Project Pre-Submittal Meeting Slides ML24200A2312024-07-22022 July 2024 Constellations Pre-Submittal Meeting Presentation About Peach Bottom ECCS Compensated Level System Replacement Project - July 22, 2024 ML24137A1882024-05-16016 May 2024 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML24134A2032024-05-14014 May 2024 Lessons Learned for ECCS Digital I&C License Amendment - Rev 0 ML24131A1282024-05-14014 May 2024 Lessons Learned for ECCS Digital I&C License Amendment ML24121A1862024-05-14014 May 2024 Attachment 3: Peach Bottom ECCS Compensated Level System Replacement Project Presentation Material (Non-Proprietary Information) ML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24029A1742024-01-30030 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 ML23170A0082023-06-29029 June 2023 Decommissioning Presentation for NRC Pre-submittal Meeting, June 29, 2023 ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23094A1492023-04-11011 April 2023 Licensee Presentation on Whr Exemption Request for Public Meeting on April 11, 2023 ML23076A0442023-03-16016 March 2023 Pb U2 Scram Barrier Presentation KT Session 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) ML21095A0162021-04-0505 April 2021 2021 RIC Session T12 - DOE-Sponsored Light Water Reactor Sustainability Program ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a 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 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 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) 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 ML19308B9262019-11-0505 November 2019 ACRS Plant License Renewal Subcommittee - Peach Bottom Atomic Power Station Units 2 and 3 Subsequent License Renewal Safety Evaluation Report (SER) with Confirmatory Item ML19256E3522019-09-12012 September 2019 Slides - Peach Bottom SLRA Dseis Public Meeting - Sep 12 2019 ML19256E3852019-09-12012 September 2019 SLR Dseis Public Meeting Sept 12 2019 - Scott Portzline - Former Three Mile Island Alert Presentation ML19157A0542019-06-0606 June 2019 Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - NRC Presentation Slides 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 ML19084A0982019-03-22022 March 2019 Potential Topics for Pre-Application Meetings for Peach Bottom SLRA 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 ML18144A6932018-05-31031 May 2018 License Amendment Request for Expanded Actions for LEFM Flow Meter Conditions - NRC Pre-Submittal Meeting May 31, 2018 ML18141A3072018-05-21021 May 2018 18 - SLR Status 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 ML17320A2002017-11-15015 November 2017 Insights from Implementing FLEX in the Peach Bottom Seismic PRA Model ML17257A1612017-09-19019 September 2017 September 19, 2017 Pre-application Public Meeting Presentation on Peach Bottom Subsequent License Renewal Application 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 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 ML12159A2662012-06-11011 June 2012 County Generating Station Pre-Application Meeting Extended Power Uprate: Replacement Steam Dryers. June 11, 2012 ML12130A0992012-05-0909 May 2012 Annual Assessment Meeting Slides Presentation Rev. 0, 2012 ML12130A1172012-05-0909 May 2012 Pb 2012 Public Mtg Attendance Sheet April 2012 2024-07-22
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24310A0672024-11-0505 November 2024 Constellation NRC Pre-Submittal Meeting Slides - Proposed Alternative for Reactor Vessel Closure Stud Exam Optimization ML24302A2422024-10-29029 October 2024 ECCS Compensated Level System Replacement Project Pre-Submittal Meeting Slides ML24200A2312024-07-22022 July 2024 Constellations Pre-Submittal Meeting Presentation About Peach Bottom ECCS Compensated Level System Replacement Project - July 22, 2024 ML24137A1882024-05-16016 May 2024 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML24131A1282024-05-14014 May 2024 Lessons Learned for ECCS Digital I&C License Amendment ML24121A1862024-05-14014 May 2024 Attachment 3: Peach Bottom ECCS Compensated Level System Replacement Project Presentation Material (Non-Proprietary Information) ML24134A2032024-05-14014 May 2024 Lessons Learned for ECCS Digital I&C License Amendment - Rev 0 ML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24029A1742024-01-30030 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) ML23251A0782023-09-0606 September 2023 DRE1 Decom Pre-Submittal Slides ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23170A0082023-06-29029 June 2023 Decommissioning Presentation for NRC Pre-submittal Meeting, June 29, 2023 ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23094A1492023-04-11011 April 2023 Licensee Presentation on Whr Exemption Request for Public Meeting on April 11, 2023 ML23076A0442023-03-16016 March 2023 Pb U2 Scram Barrier Presentation KT Session 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 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 ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a 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 ML19308B9262019-11-0505 November 2019 ACRS Plant License Renewal Subcommittee - Peach Bottom Atomic Power Station Units 2 and 3 Subsequent License Renewal Safety Evaluation Report (SER) with Confirmatory Item ML19256E3522019-09-12012 September 2019 Slides - Peach Bottom SLRA Dseis Public Meeting - Sep 12 2019 ML19256E3852019-09-12012 September 2019 SLR Dseis Public Meeting Sept 12 2019 - Scott Portzline - Former Three Mile Island Alert Presentation ML19157A0542019-06-0606 June 2019 Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - NRC Presentation Slides 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 ML18275A3712018-09-25025 September 2018 Subsequent License Renewal Environmental Scoping Meeting 9-25-18 ML18141A3072018-05-21021 May 2018 18 - SLR Status 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 ML18017A1172018-01-18018 January 2018 NRC PBAPS SLRA Pre-Submittal Meeting Jan 2018 PM Copy ML17320A2002017-11-15015 November 2017 Insights from Implementing FLEX in the Peach Bottom Seismic PRA Model ML17257A1612017-09-19019 September 2017 September 19, 2017 Pre-application Public Meeting Presentation on Peach Bottom Subsequent License Renewal Application ML16106A2792016-04-15015 April 2016 Meeting Slides for License Amendment Request for Measurement Uncertainty Recapture Uprate NRC Pre-Submittal Meeting April 26, 2016 ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML13255A3762013-09-16016 September 2013 Soarca Peach Bottom Uncertainty Analysis (UA) Acrc Briefing - Sept 2013 ML12159A2662012-06-11011 June 2012 County Generating Station Pre-Application Meeting Extended Power Uprate: Replacement Steam Dryers. June 11, 2012 ML12130A0992012-05-0909 May 2012 Annual Assessment Meeting Slides Presentation Rev. 0, 2012 ML12124A0782012-04-26026 April 2012 Power Point Presentation: Peach Bottom - Timing and Criteria for RCS Failure ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR 2024-07-22
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DISCLAIMER
This training session is being recorded for future use in the NRCs knowledge management program. As such, please note that the recorded contents of the session, including any questions posted by audience members, will be preserved in accordance with the NRCs record management program and, moreover, subject to FOIA disclosure. Please refrain from including any sensitive information (i.e., SUNSI) in any questions that you may ask.
- Frank Arner, Senior Reactor Analyst PEACH BOTTOM UNIT 2 MAY 16 SCRAM 19 The Unexpected 40 Plans are Made for a Reason, Time Pressure, Commitment 19 Purpose Plan commitments, Just in 20 Time Training, Walkthroughs, Procedures
Planning and Setup19 19 Training and Crew Dynamics 19 Two Heads Partial Procedure vs 10 50 Lineup Awareness, Plans 80 Stop Work Criteria, Peer Temporary Change and and Purpose, Training Checks, Human Integrate Risk Management Standards Performance Tools
Questions Turnover and Briefings19 19 and Answers Quality of Turnover, Review 30 70 Ask, Listen, Understand, of Actions, Communication Reply, Communication Must and Purpose Flow Both Ways
19 When It Really Matters 60 Best Laid Plans 4KV EMERGENCY POWER BUS ALIGNMENT NORMAL LINEUP LINEUP DURING 2EA OUTAGE LINEUP WITH 2SU LINKS REMOVED NORMAL RPS POWER SUPPLY ALIGNMENT ALTERNATE RPS POWER SUPPLY ALIGNMENT
OFFSITE TRANSIENT A RPS TRIPPED ERROR RESULTS IN BOTH U2 RPS BUSSES TRIPPED
PLANNING AND SETUP COMMITMENT TURNOVER AND BRIEFINGS
THE UNEXPECTED TRAINING AND CREW DYNAMICS WHEN IT REALLY MATTERS
QUESTIONS AND ANSWERS TWO HEADS 3 TAKEAWAYS FROM THIS EVENT
- If you think something is not a credible potential scenario, this one is a reminder that anything can happen. There were at least 5 actions that happened which typically would not occur (This shows the powerful effect of group think or dependency within each human task which can drastically increase all failure rates in a sequence of events)
- Resident Inspectors continue to be the eyes and ears for the agency - never underestimate the importance of each and every observation you have during post event response
- Initiating Events such as MSIV closure events can result in an increase in risk (impulse) which is equivalent to TWICE the entire baseline internal event risk expected over the course of the entire year - (With no other failures of mitigating equipment for event)
HUMAN ERRORS PRIOR TO EVENT
- EO asked the CRS if the partial procedure still needed to carried, CRS stated they would look into it and never got back to the EO. 1E-1 1 in 10 failure?
- 4th RO (tasked to reset 2A RPS) pulled a clean copy of procedure. 1 in 2 0.5?
- EO had the partial procedure and asked 4 th RO if it should be used instead of clean copy. 4th RO told the EO to use the clean copy. Recovery Chance 1E-1?
- EO spoke with CRS and was directed to operate A components only, no B components. CRS told EO to N/A step 4.3 but gave no direction for steps 4.4 to 4.9 which is for lining up the alternate feed. N OT C L E A R,
STO P ? 1 E-1
- EO called MCR to verify alarm was in per step 4.4 and 4 th RO mistakenly said alarm was in, when it was not.
1 in 100 failure, simple verification alarm 1E-2?
- EO noted the output breakers for alternate feed were closed and step 4.5 would trip them. EO asked 4th RO if they should continue with step 4.5 and was told to continue. CLEARLY NORMALLY RESULTS IN STOP 1 in 10 failure 1E-1
- Incredible that perhaps ANY 1 of the above may have stopped this Event - above exceeds 1 in a million chance...Clearly shows how dependency among crew thinking or among group think takes place. Easy to have said if asked to evaluate the above-not credible POST EVENT MCR OBSERVATIONS
- Noted that SRVs seemed to be cycling quite a bit. As it turned out, the residents provided the SRA with computer information showing there were up to 33 SRV cycles within the 1st hour post event. An SRV failing open can then be estimated considering the high number of cycles and core damage cutsetsused to keep the current value in the model which increased the risk outcome due to higher probability of a stuck open SRV
- Residents were wondering 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> into the event why the opening of the MSIVs was not being pursued. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in, it was apparent there were issues which were causing procedure limits to be exceeded (i.e. 50 psid limit for re-opening of inboard MSIVs) Thus Reactor Feedpumps, high pressure source and Turbine Bypass Valves (Heat sink) could not be used.
- While Operators were following standard EOPs, there were steps to consider re-opening MSIVs but this did not occur until around 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> later - Thus the SRA could NOT credit early MSIV recovery based on the challenges that were observed - Licensee denied challenges existed which did not comport w observations (Credit would have lowered risk)
26 WHY WAS RESIDENT INSPECTOR PRESENCE POST EVENT IN MCR CRITICAL IN RISK EVALUATION?
MSIV CLOSURE EVENT RISK
- PB Model of record indicated a CCDP for MSIV closure of 1E-5
- PB claimed their PRA MOR for this event would not be accurate and would overestimate the risk - stated SPAR model with proposed major revision decreasing operator failure rates by up to 25x to 125x should be used (So in essence they wanted incredible Human Error Probability reductions even after all of the PRE Event errors that occurred
- With a MSIV closure event frequency changing from 1/25/ yr to 1.0/yr this drives the risk even with no other failures of other mitigating equipment such as HPCI or RCIC, remember we are not calculating what happenedBUT what COULD happen, i.e. MSIVs closed, x prob. Of HPCI failing, Prob. Of RCIC failing and failure to depressurize leading to core damage for example.
So If the PB internal event risk is 3E -6/yr including internal flooding, this ICDP risk increase was 6E-6 or basically equivalent to 2 times the risk of operating the plant over the entire year..Initiating Events create a spike in CDP and have a large impact to the Plant risk profile!
28 QUESTIONS The Office of Nuclear Reactor Regulation (NRR), Division of Reactor Oversight (DRO), will conduct an Inspector Town Hall meeting on Thursday, March 9, 2023, from 2:00 pm - 3:30 pm.
OPERATING The purpose of the meeting is to update inspectors on important developments impacting the Reactor Oversight Process (ROP) and their inspection activities.
REACTOR Topics for the meeting will include the following:
INSPECTOR
- Inspection sample changes and guidance for calendar year 2023 - Manuel Crespo, Operations Engineer, NRR/DRO
- Resident Inspector Recruitment and Retention Status Update - Zack Hollcraft, Senior Operations Engineer, NRR/DRO