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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 ML24003A1812024-01-0808 January 2024 Handout - Byron-Braidwood Core Monitoring and Support System LAR Pre-Submittal Meeting January 8,2024 ML23345A0362023-12-11011 December 2023 ATWS Uet December 11, 2023 Pre-submittal Meeting Slides 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) ML23272A0622023-09-29029 September 2023 Ultimate Heat Sink Temperature Tech Spec Limit Change ML23229A0132023-08-17017 August 2023 Relief Request for Alternative Requirements for Byron Unit 1 Reactor Pressure Vessel Inservice Inspection Intervals NRC Meeting Handout ML23229A1722023-08-17017 August 2023 RR Pen-75 Pre-Submittal NRC Meeting Handout ML23229A4832023-08-17017 August 2023 RR 20-Year ISI Pre-Submittal NRC Meeting Handout ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23163A1642023-06-12012 June 2023 2022 Braidwood/Byron End-of-Cycle Meeting Presentation 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) ML22159A3332022-06-0909 June 2022 Presentation Slides for Braidwood and Byron 2021 End of Cycle Meeting ML22098A0512022-04-11011 April 2022 2 Cycle 25 High Burnup Lead Test Assembly NRC Pre-Submittal Meeting on April 22, 2022 (EPID L-2022-LRM-0022) (Slides) ML21320A0672021-11-17017 November 2021 NRC Pre-Submittal Meeting - 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U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach 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 ML20091L0432020-04-0101 April 2020 Public Meeting Handout for Braidwood, Unit 2, April 1, 2020 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 ML18218A1122018-08-0808 August 2018 Reactor Pressure Vessel Head Penetration Nozzle Post Peening Follow-up Inspection Relief Requests for Byron Unit 2 and Braidwood Unit 1 ML18086A8432018-03-27027 March 2018 NUREG-1021, Revision 11 Implementation 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 ML17291B0282017-10-17017 October 2017 Submittal of Slide Package Westinghouse Encore Lead Test Rod Program Byron Unit 2 (Proprietary/Non-Proprietary) ML17296A2032017-10-0303 October 2017 Accident Tolerant Fuel Lead Test Assembly Deployment ML17132A1772017-05-25025 May 2017 LAR for Control Room Cooling at Byron and Braidwood Stations ML16334A4452016-12-0505 December 2016 Pre-submittal Meeting Byron UT RR Presentation ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16062A4222016-03-0202 March 2016 Meeting Slides for March 7, 2016 Public Meeting to Discuss Backfit Appeal ML15342A1012015-12-0909 December 2015 TORMIS Computer Code Methodology Public Meeting Slides ML15232A6832015-08-27027 August 2015 Stations Auxiliary Feedwater System - Unit Cross-tie License Amendment Request ML15209A9722015-07-30030 July 2015 Alloy 600 PWSCC Mitigation Plan for Reactor Vessel Head Penetration Nozzles Utilizing Cavitation Peening at Byron and Braidwood ML15204A5052015-07-23023 July 2015 EPRI Tech Basis for Brd-Byr Head RR ML15204A4932015-07-23023 July 2015 Bb Station Requests for Relief for Alternate Examination Frequency ML15133A4732015-05-20020 May 2015 Digital Upgrades of the Non-Safety Related NSSS Control Systems at Byron and Braidwood Stations 2024-01-08
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Braidwood Station and Byron Station Requests for Relief for Alternate Examination Frequency Under ASME Code Case N-729-1 for Reactor Vessel Head Penetration Welds in accordance with 10 CFR 50.55a (a)(3)(i)
Scot Greenlee, Sr. VP Engineering and Technical Services David Gullott, Manager Corporate Licensing July 27, 2015
Purpose
- Provide a brief history of B/B Relief Request related to the RPV Head Nozzles
- Provide technical basis for Re-examination interval requested of every other cycle for Braidwood and Byron Station
-MRP-395
-New sensitivity analyses performed at 95th percentile
- Understand technical questions that may exist on Relief Request 1 Braidwood Station and Byron Station Requests for Relief for Alternate Examination Frequency
B/B RPV Head Nozzle History
- During Byron Station Unit 2 Refueling Outage in Spring 2007 (B2R13) a PWSCC flaw was identified in penetration 68 and it associated J-groove weld
- ASME Code Case N-729-1 was incorporated into 10 CFR 50.55a as an augmented ISI program in September 2008 and allowed volumetric or surface examination every second refueling outage, even with detected flaws
- However, in a final rule action published in the Federal Register (FR) at 73 FR 52730, dated September 10,2008, 10 CFR 50.55a(g)(6)(ii)(D)(5) added a condition modifying ASME Code Case 729-1, Note (8) indicating that if flaws attributed to PWSCC had been identified, the re-inspection interval must be each refueling outage
- Thus, volumetric and/or surface examinations are conducted every outage 2 Braidwood Station and Byron Station Requests for Relief for Alternate Examination Frequency
B/B RPV Head Nozzle History
- In 2010, NRC authorized inspection frequency of every other outage for Byron Station Unit 2 under RR I3R-16, SE also included the statement that if future indications were found, would change inspection frequency to every outage
- Volumetric and/or surface examinations of all penetrations with the exception of penetration 68
- Exelon submitted I3R-20 for Byron Station Units 1 and 2 and I3R-09 for Braidwood Station Units 1 and 2 for use of Westinghouse weld overlay method on reactor vessel head penetration housing and J-groove welds, April 2011
- Included that future indications found would change inspection frequency to every outage
- NRC approved I3R-09 and I3R-20 Revision 1 as a repair method, March 2012
- All repaired nozzle penetrations examined with UT and Surface Examinations (PT) every outage
- Exelon submitted a Revision to the Relief Request for I3R-09 and I3R-20 which requests relief to eliminate surface examinations after successful examinations, September 2014
- Exelon recently provided a revision to the previously submitted Relief Request for I3R-09 and I3R-20, changing the frequency of surface examinations to every other cycle after successful examinations have been obtained 3 Braidwood Station and Byron Station Requests for Relief for Alternate Examination Frequency
Proposed Relief Request
- Requests UT examination inspection frequency interval of every other outage for all reactor vessel closure head penetrations (inclusive of repaired penetrations) for Braidwood Station Unit 1 and Byron Stations Unit 1 and Unit 2
-Effectiveness of current inspection requirements, including recent indications found in cold heads (i.e., reactor vessels operating at reactor cold-leg temperature (Tcold) including Braidwood Station and Byron Station)
-Deterministic crack growth rate analysis
-Probabilistic Monte Carlo simulation analysis
-Margin to leakage for flaws detected in cold heads 4 Braidwood Station and Byron Station Requests for Relief for Alternate Examination Frequency
Proposed Relief Request
- Personnel exposure reduced approximately 500-1000 mRem each outage an inspection is not required to be performed
- Implement approved Relief Request to support Byron Station Fall Outage 2015 (B1R20)
- Continued implementation of UT Inspection Frequency Relief Post-Peening application
-Peening application planned for Byron Station Unit 2 Spring 2016 outage (B2R19)
-Inspection Frequency Relief for all nozzles 5 Presentation Title
Technical Basis for Re-examination Interval of Every Second Refueling Outage for PWR Reactor Vessel Heads Operating at Tcold with Previously Detected PWSCC Craig Harrington, EPRI Glenn White, Dominion Engineering 6 Braidwood Station and Byron Station Requests for Relief for Alternate Examination Frequency