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MONTHYEARML24003A1812024-01-0808 January 2024
Handout - Byron-Braidwood Core Monitoring and Support System LAR Pre-Submittal Meeting January 8,2024
Project stage: Meeting
ML24009A0552024-01-24024 January 2024
Summary of January 8, 2024, Presubmittal Meeting Between the U.S. Nuclear Regulatory Commission and Constellation Energy Generation, LLC, Regarding Removal of the Power Distribution Monitoring System from Technical Specifications
Project stage: Meeting
2024-01-24
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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
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
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
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
ML21320A0672021-11-17017 November 2021
NRC Pre-Submittal Meeting - Braidwood, Unit 2, LAR for Removal of Unit 2 License Condition for Closure Stud Hole Location No. 35 (EPID L-2021-LRM-0089) (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
ML21166A3722021-06-15015 June 2021
End-of-Cycle Meeting Presentation
ML21130A6252021-05-12012 May 2021
NRC Pre-Submittal Meeting - Braidwood LAR for Ultimate Heat Sink (EPID L-2021-LRM-0040) (Slides)
ML21078A0952021-03-0808 March 2021
Session W20 - James Petty - Slide Deck 3
ML20258A0302020-09-22022 September 2020
Decommissioning Licensing Action Submittal Plan for Byron and Dresden Stations Early Shutdowns
ML20261G7322020-09-16016 September 2020
Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a
ML20209A5322020-07-24024 July 2020
2019 Braidwood and Byron End-of-Cycle Presentation
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
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)
ML20091L0432020-04-0101 April 2020
Public Meeting Handout for Braidwood, Unit 2, April 1, 2020
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
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
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
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
ML18018B4432018-01-25025 January 2018
Summary of December 17, 2017, Closed Meeting with Exelon Generation Company, LLC, Regarding Tvel Lead Test Assemblies to Be Placed in the Braidwood Reactor (EPID 000976/05000456/L-2017-LRM and 000976/05000457/L-2017-LRM-0047
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
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
ML16334A4642016-12-0505 December 2016
Westinghouse Pre-Application Meeting: License Amendment Request to Modify Byron Station Facility Operating License in Support of the Molybdenum-99 Isotope Production Project - December 5, 2016
ML16327A3702016-11-25025 November 2016
Enclosure 3: Exelon Byron Station Design (Meeting Handout)
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
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
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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Category:Slides and Viewgraphs
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Text
Braidwood and Byron Core Monitoring and Support System January 8, 2024
Agenda
- References 2 Byron-Braidwood - Core Monitoring and Support System Pre-submittal Meeting 01/08/2024
Purpose and Background
- On February 13, 2001, Byron and Braidwood received NRC approval of license amendment (Reference 1) allowing for the relaxation of several Technical Specifications when the Best Estimate Analyzer for Core Operations Nuclear (BEACON) power distribution monitoring system (PDMS) is Operable.
- PDMS is a component within Westinghouses BEACON Core Monitoring System which allows for the relaxation of several Technical Specifications.
- Currently, the Byron and Braidwood Technical Specifications are written such that Limiting Conditions for Operations (LCOs) can be completed satisfactory in the event PDMS becomes INOPERABLE.
3 Byron-Braidwood - Core Monitoring and Support System Pre-submittal Meeting 01/08/2024
License Amendment Request Scope
- Constellation proposes to remove the current PDMS relaxations from Byron and Braidwood Technical Specifications, reverting to its previous licensing bases which aligns with industry Standard Technical Specifications (STS), NUREG 1431 Revision 1.
- This proposal would revert changes made to incorporate PDMS that was issued on 13 February 2001.
- TS 3.2.3 - Axial Flux Difference (AFD) was revised and approved for both Braidwood and Byron stations in 2018 (Reference 2) to remove any association with PDMS. Therefore, the proposed changes as part of this upcoming request will not include a revision to TS 3.2.3.
4 Byron-Braidwood - Core Monitoring and Support System Pre-submittal Meeting 01/08/2024
License Amendment Request Scope (continued)
- Technical Specification Sections impacted:
TS Section Notes Remove references to inoperable PMDS and restore action to perform Surveillance Requirements 3.1.4 - Rod Group Alignment Limits (SRs).
Clarify Required Actions (RAs) to verify position of the rods with inoperable Digital Rod Position 3.1.7 - Rod Position Indication Indications (DRPIs) indirectly. Completion Time (CT) of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> added.
Set RAs, CT , and SRs to ensure compliance and monitoring to FQ(Z) limit. Remove references to 3.2.1 - Heat Flux Hot Channel Factor PDMS (to align with STS 3.2.1B from NUREG 1431).
3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor State specific SR for FNH (SR 3.2.2.1) and remove references to PDMS.
Remove reference for inoperable PDMS as QPTR TS ensures QPTR limit is met so the gross radial 3.2.4 - Quadrant Power Tilt Ratio (QPTR) power distribution remains consistent with Safety Analysis.
3.2.5 - Departure from Nucleate Boiling Ratio (DNBR) Delete from TS Restore Condition D to TS LCO which involves One Power Range Neutron Flux-High Channel 3.3.1 - Reactor Trip System (RTS) inoperable. Ensure that under specific unit status of TS applicability that all instrumentation performing a RTS function is operable.
5.6.5 - Core Operating Limits Report (COLR) Remove text LCO 3.2.5, Departure from Nucleate Boiling Ratio (DNBR) from 5.6.5.a list 5 Byron-Braidwood - Core Monitoring and Support System Pre-submittal Meeting 01/08/2024
Reason for the change
- Standard Technical Specifications (STS) for Westinghouse Plants (NUREG-1431) are agnostic to the specific core monitoring system software used to satisfy LCOs and Surveillance Requirements (SRs).
- Byron and Braidwood are currently outliers in the U.S. PWR fleet by referencing a specific core monitoring system (i.e., PDMS) in Technical Specifications.
- Constellation desires to align Byron and Braidwood closer to industry STS to position itself for future projects.
6 Byron-Braidwood - Core Monitoring and Support System Pre-submittal Meeting 01/08/2024
Key Milestones
- Pre-Submittal Meeting - 08 January 2024
- Expected Submittal Date -29 March 2024
- Requested Approval Date - 30 April 2025 7 Byron-Braidwood - Core Monitoring and Support System Pre-submittal Meeting 01/08/2024
References
- 1. Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 - Issuance of Amendments to Technical Specifications for Implementation of the Best Estimate Analyzer for Core Operations Nuclear Power Distribution Monitoring System (TAC Nos. MA8254, MA8255, MA8252, and MA8253), February 13, 2001
- 2. Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2 - Issuance of Amendments Regarding Axial Flux Difference Technical Specifications (EPID L-2018-LLA-0098), December 12, 2018 8 Byron-Braidwood - Core Monitoring and Support System Pre-submittal Meeting 01/08/2024
Questions 9
