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Category:Meeting Briefing Package/Handouts
MONTHYEARML24100A7672024-04-11011 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) ML24060A1692024-03-0707 March 2024 NRC Slides for March 7, 2024 Regulatory Conference with Constellation Nuclear Regarding Braidwood BW240007, Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations2024-02-29029 February 2024 Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations ML24057A3032024-02-26026 February 2024 Attachment 1: Braidwood Station Regulatory Conference Information ML24057A3062024-02-24024 February 2024 Attachment 4: BW-SDP-006 Rev. 0 - Braidwood 2B AF Pump Fuel Oil Leak SOP Sensitivities 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 ML24057A3042024-01-22022 January 2024 Attachment 2: EC 640630 Rev. 000 - Documentation of Test Results with Diluted Lube Oil from Fuel In-Leakage - 28 AF Diesel Engine Past Operability ML24003A1812024-01-0808 January 2024 Handout - Byron-Braidwood Core Monitoring and Support System LAR Pre-Submittal Meeting January 8,2024 ML24057A3052023-12-12012 December 2023 Attachment 3: EC 640287 Rev. 000 - Past Operability Test Plan Acceptance Related to 2AF01PB-K 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 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 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 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 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 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 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 ML17132A1772017-05-25025 May 2017 LAR for Control Room Cooling at Byron and Braidwood Stations 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 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 2024-04-09
[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 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) ML24060A1692024-03-0707 March 2024 NRC Slides for March 7, 2024 Regulatory Conference with Constellation Nuclear Regarding Braidwood ML24057A3032024-02-26026 February 2024 Attachment 1: Braidwood Station Regulatory Conference Information 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 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 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 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 ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs 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 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 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 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 ML17132A1772017-05-25025 May 2017 LAR for Control Room Cooling at Byron and Braidwood Stations 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 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 ML15204A4932015-07-23023 July 2015 Bb Station Requests for Relief for Alternate Examination Frequency ML15204A5052015-07-23023 July 2015 EPRI Tech Basis for Brd-Byr Head RR ML15133A4732015-05-20020 May 2015 Digital Upgrades of the Non-Safety Related NSSS Control Systems at Byron and Braidwood Stations ML15135A4262015-05-19019 May 2015 EOC Public Meeting Slides ML15104A4932015-04-14014 April 2015 Preliminary Site-Specific Results of the Environmental Review for Braidwood Station License Renewal ML14342A8122014-12-10010 December 2014 Presentation Slides for December 10, 2014 Meeting on Alloy 600 PWSCC Mitigation for Rvh Nozzles ML14261A1112014-09-22022 September 2014 2014 NEI Fire Protection Information Forum NRC Public Slides ML14251A4852014-09-10010 September 2014 Byron/Braidwood Auxiliary Feedwater Cross-Tie ML14177A6412014-06-23023 June 2014 UHS Pre-submittal Meeting Presentation ML13249A1892013-09-0404 September 2013 ILRT Extension LAR Pre-submittal Meeting Slides 2024-04-09
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Braidwood Annual Assessment Meeting Reactor Oversight Program - CY 2007 Nuclear Regulatory Commission - Region III Braidwood, IL June 23, 2008
Purpose of Todays Meeting z To provide a public forum for the discussion of Braidwood Stations performance z The NRC will address licensee performance issues identified in the annual assessment letter z The Licensee will be provided an opportunity to respond to any information in the letter and discuss new or existing programs to maintain or improve performance
Agenda z Description of NRC Activities z Introduction z Review of the Reactor Oversight Process (ROP) z National Summary of Plant Performance z Discussion of Plant Performance Results z Licensee Response and Remarks z NRC Closing Remarks z Break z The NRC will be available after the meeting to address any public questions
Our Mission To license and regulate the nations civilian use of byproduct, source and special nuclear materials to ensure adequate protection of public health and safety, promote the common defense and security, and protect the environment.
NRC Goals Safety: Ensure adequate protection of public health and safety and the environment.
Security: Ensure adequate protection in the secure use and management of radioactive materials.
Some Nuclear Facts More than 100 nuclear power plants supply about 20 percent of the electricity in the U.S.
Nuclear materials are used in medicine for cancer treatment and diagnosis.
Nuclear materials are widely used in industry, such as in density gauges, flow measurement devices, radiography devices and irradiators.
The NRC Regulates:
Nuclear reactors - commercial power reactors, research and test reactors, new reactor designs; Nuclear materials - nuclear reactor fuel, radioactive materials for medical, industrial and academic use; Nuclear waste - transportation, storage and disposal of nuclear material and waste, decommissioning of nuclear facilities; and Nuclear security - physical security of nuclear facilities and materials from sabotage or attacks.
What We Dont Do:
Regulate nuclear weapons, military reactors or space vehicle reactors. (These are regulated by other federal agencies.)
Own or operate nuclear power plants.
Regulate some radioactive materials, such as naturally occurring radon, X-rays and material produced in particle accelerators.
(These are regulated by states or other federal agencies.)
How We Regulate Establish rules and regulations Issue licenses Provide oversight through inspection, enforcement, and evaluation of operational experience Conduct research to provide support for regulatory decisions Respond to events and emergencies
Assurance of Plant Safety Require defense-in-depth Require long-term maintenance of equipment Require continual training of operators Verify compliance with regulations
What We Do - Nuclear Waste The NRC regulates:
- Storage of spent reactor fuel in fuel pools or dry storage casks, and
- Any potential national spent fuel storage site.
What We Do - Nuclear Security The NRC Requires:
- Well-armed and well-trained security forces,
- Surveillance and perimeter patrols,
- State-of-the-art site access equipment and controls,
- Physical barriers and detection zones, and
- Intrusion detection systems and alarm stations.
Region III Organization James Caldwell Regional Administrator Mark Satorius Deputy Regional Administrator Cynthia Pederson Steve West Director Division of Reactor Projects (DRP) Director Division of Reactor Safety (DRS)
Gary Shear Anne Boland Deputy Director Deputy Director Richard Skokowski Regional Specialists Branch Chief Braidwood Project Engineer Resident Inspectors Billy Dickson Reactor Engineer Alex Garmoe Jennifer Dalzell
NRC Representatives z Billy Dickson, Senior Resident Inspector
- (815) 458-2853 z Gregory Roach, Senior Resident Inspector - LaSalle
- (815) 358-8611 z Alex Garmoe, Resident Inspector
- (815) 458-2853 z Richard Skokowski, Branch Chief, DRP
- (630) 829-9620 z Marshall David, Project Manager, NRR
- (301) 415-1547
NRC Representatives z Viktoria Mitlyng, Office of Public Affairs
- (630) 829-9662 z Prema Chandrathil, Office of Public Affairs
- (630) 829-9663 z Steve Orth, Branch Chief - Radiation Protection Branch, DRS
- (630) 829-9827 z Stephanie Bush-Goddard, Branch Chief -
Health Effects Branch, RES
- (301) 415-6293
Reactor Oversight Process (ROP)
Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix Regulatory Response
Examples of Baseline Inspections z Equipment Alignment ~80 hrs/yr z Triennial Fire Protection ~250 hrs/3 yrs z Operator Response ~125 hrs/yr z Emergency Preparedness ~80 hrs/yr z Radiological Release Controls ~110 hrs/2 yrs z Worker Radiation Protection ~95 hrs/yr z Corrective Action Program ~250 hrs/2 yrs z Corrective Action Reviews ~60 hrs/yr
Significance Threshold Performance Indicators Green:
Green Baseline Inspection only White:
White May increase NRC oversight Yellow:
Yellow Requires more NRC oversight Red:
Red Requires more NRC oversight Inspection Findings Green:
Green Very low safety significance White:
White Low to moderate safety significance Yellow:
Yellow Substantial safety significance Red:
Red High safety significance
Action Matrix Concept Licensee Regulatory Degraded Multiple/Rep. Unacceptable Response Response Cornerstone Degraded Performance Cornerstone Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions
National Summary of Plant Performance Status at End of CY 2007 Licensee Response 87 Regulatory Response 8 Degraded Cornerstone 8 Multiple/Repetitive Degraded Cornerstone 1 Unacceptable 0 Total 104
National Summary z Performance Indicator Results (End of CY 2007)
Green 1942 White 8 Yellow 1 Red 0 z Total Inspection Findings (CY 2007)
Green 759 White 9 Yellow 2 Red 0
Braidwood Assessment Results (Jan 1 - Dec 31, 2007) z Safety performance for the last 3 quarters of 2007 Braidwood Units 1 and 2 were within the Licensee Response column of the NRC Action Matrix.
z Braidwood Units 1 and 2 were within the Regulatory Response column for the 1st quarter of 2007 due to a White finding in the Public Radiation Safety Cornerstone that occurred in the 1st quarter of 2006.
Safety Significant Findings or PIs z No safety significant findings were identified during this assessment period.
z During the week of January 29, 2007, the NRC conducted a supplemental inspection using Inspection Procedure 95001 for the 1st quarter 2006 White finding in the Public Radiation Safety Cornerstone. No findings of significance were identified.
NRC IP 95001 Evaluation Inspections encompassed activities from the initial response through evaluating Braidwoods root cause evaluation &
corrective actions.
z Initial Response Source of contamination and evaluation Storage of water while repairing the discharge path z Review of remediation actions and resumption of liquid releases Integrity of blowdown line Integrity of modified vacuum breaker valve vaults including leak detection and alarm system z Independent dose calculation z Independent and duplicate analyses of water samples z External communications
Braidwood Inspection Activities (Jan 1 - Dec 31, 2007) z 12 findings during the assessment period:
8 in mitigating systems 2 in barrier integrity 2 in occupational radiation safety z One additional finding was evaluated separately using the traditional enforcement process.
Braidwood Inspection Activities (Jan 1 - Dec 31, 2007) z Unit 1:
- power operations
- automatic reactor trip due to an offsite grid disturbance
- refueling outage z Unit 2:
- power operations
- manual reactor trip due to a loss of condenser vacuum z Independent Groundwater Monitoring Activities:
- Supplemental Inspection 95001 conducted in January 2007
- Walkdowns of the Circulating Water blowdown line quarterly
- Independent validation of groundwater sample results
Braidwood Annual Assessment Summary (Jan 1 - Dec 31, 2007) z Exelon Nuclear operated Braidwood Units 1 and 2 in a manner that preserved public health and safety z All cornerstone objectives were met during this assessment period.
z NRC plans to conduct baseline inspections at Braidwood for the remainder of the current assessment period.
z A supplemental 95001 inspection was conducted during the week of January 29, 2007 with no significant findings.
Licensee Response and Remarks Bryan Hanson Site Vice President Braidwood Generating Station
Contacting the NRC z To Report an emergency (301) 816-5100 (call collect) z To Report a safety concern:
(800) 695-7403 Allegation@nrc.gov z For general information or questions www.nrc.gov Select What We Do for Public Affairs
Reference Sources z Reactor Oversight Process http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.
html z Public Electronic Reading Room http://www.nrc.gov/reading-rm.html z Public Document Room 1-800-397-4209 (Toll Free)