Braidwood NRC End-of-Cycle Slide PresentationML12227A533 |
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Braidwood ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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08/14/2012 |
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NRC/RGN-III |
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Download: ML12227A533 (33) |
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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 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 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 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 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 ML13224A2922013-08-0808 August 2013 2012 Braidwood Station End-of-Cycle Public Meeting NRC Presentation ML13107A0532013-04-23023 April 2013 Pre-Submittal Meeting MSIV Actuators Slides ML12227A5332012-08-14014 August 2012 NRC End-of-Cycle Slide Presentation 2024-01-08
[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 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 ML13224A2882013-08-12012 August 2013 2012 Braidwood Station End-of-Cycle Public Meeting Licensee Presentation ML13224A2922013-08-0808 August 2013 2012 Braidwood Station End-of-Cycle Public Meeting NRC Presentation ML13107A0532013-04-23023 April 2013 Pre-Submittal Meeting MSIV Actuators Slides ML12227A5172012-08-14014 August 2012 Licensee End-of-Cycle Public Meeting Slides ML12227A5332012-08-14014 August 2012 NRC End-of-Cycle Slide Presentation 2024-01-08
[Table view] |
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Braidwood Station Annual Assessment Mti 1 M ee ti ngReactor Oversight Process -2011Nuclear Regulatory Commission -Region IIILisle, IllinoisAugust 15, 2012 Purpose of Today's Meeting*A public forum for discussion of the licensee's performance in 2011*NRC will address the performance 2issues identified in the annual assessment letter*Licensee will be given the opportunity to respond and inform the NRC of new
or existing programs to maintain or
improve performance Agenda*Introduction *Review of Reactor Oversight Process
- National Summary of Plant PerformanceDiifPlPfRl 3*Di scuss i on o f Pl ant P er f ormance R esu l ts*Licensee Response and Remarks
- NRC Available to Address Public Questions Region III OrganizationCharles CastoRegional AdministratorCynthia PedersonDeputy Regional AdministratorGary ShearActing Director, Division of Reactor ProjectsSteven Reynolds Director, Division of Reactor Safety 4Kenneth O'BrienActing Deputy DirectorRichard SkokowskiActing Deputy DirectorEric DuncanBranch ChiefRegional SpecialistsBraidwood StationResident InspectorsJamie BenjaminAlex GarmoeRegional StaffRaymond NgTravis DaunHudson Rowland Our Mission*To license and regulate the nation's civilian use of byproduct, source, and special nuclearmaterialsto 5 nuclear materials to ensure adequate protection of public health and safety, promote the common defense and security, and protect the
environment.
Some Nuclear Facts*104 nuclear power plants supply about 20 percent of the electricity in the U.S.*Nuclear materials are used inmedicinefordiagnosis 6 in medicine for diagnosis and cancer treatment.*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 7*Nuclear waste-transportation, storage and disposal of nuclear material and waste, decommissioning of nuclear facilities*Nuclear security-physical security of nuclear facilities and materials from sabotage or attacks What We Don't Do*Regulate nuclear weapons, military reactors, or space vehicle reactors 8*Own or operate nuclear power plants*Regulate some radioactive materials, such as x-rays and naturally occurring
radon How We Regulate*Establish rules and regulations*Issue licenses
- Provide oversight through inspection, ftdltif 9 en f orcemen t , an d eva l ua ti on o f 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 10*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 11 casks-Any national spent fuel storage site What We Do -Nuclear Security*NRC Requires:-Well-armed and well-trained security forces-Surveillance and perimeter patrols 12 perimeter patrols-State-of-the-art site access equipment and
controls-Physical barriers and detection zones-Intrusion detection systems and alarm
stations NRC Performance Goals*Safety: Ensure adequate protection of public health and safety and the
environment 13*Security: Ensure adequate protection in the secure use and management of
radioactive materials Reactor Oversight ProcessStrategic Performance AreasSafety Cornerstones Inspection Results Performance Indicator Results 14 Significance Evaluation Significance EvaluationAction MatrixRegulatory Response Examples of Baseline Inspections*Equipment Alignment ~80 hrs/yr *Operator Response ~125 hrs/yr
- Emergency Preparedness ~80 hrs/yr 15*Worker Radiation Protection ~95 hrs/yr*Corrective Action Case Reviews ~60 hrs/yr*Corrective Action Program ~250 hrs every 2 yrs*RadRelease Controls ~110 hrs every 2 yrs
- Triennial Fire Protection ~250 hrs every 3 yrs Significance Threshold Performance Indicators Green:Only Baseline InspectionWhite:Increases NRC oversight
Yellow:Increases NRC oversight Red:IncreasesNRCoversight 16 Red: Increases NRC oversight Inspection Findings Green:Very low safety issueWhite:Low to moderate safety issue
Yellow:Substantial safety issue Red:High safety issue Action Matrix ConceptLicenseeResponseRegulatoryResponseDegradedCornerstoneMultiple/Rep.DegradedCornerstoneUnacceptablePerformance 17Increasing Safety SignificanceIncreasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions National Summary of Plant Performance Status as of 12/31/2011Licensee Response 88 Regulatory Response 11DegradedCornerstone 3 18 Degraded Cornerstone 3Multiple/Repetitive Deg. Cornerstone1 Unacceptable 0 IMC 0350 Oversight1 Total104 National Summary*Performance Indicator Results for 2011 1-Green 6585-White9
-Yellow 0 Red 0 19-Red 0*Total Inspection Findings in 2011 2-Green 846-White13
-Yellow 2-Red 01PIs are counted per plant per quarter2Finding data does not include security findings Braidwood Station Assessment ResultsJanuary 1 -December 31, 2011*Unit 1 was in the Licensee Response column throughout 2011 20*Unit 2 was in the Licensee Response column throughout 2011*There was no substantive cross-cutting issue identified during 2011 Safety Significant Findings or PIs*One White Performance Indicator for Unit 2 was submitted for the 2 ndquarter of 2012*The White Performance Indicator was associated with the 21Cooling Water System of the Unit 2 Mitigating Systems Performance Index*Unit 2 transitioned to the Regulatory Response column in 2 nd quarter 2012*A 95001 Supplemental Inspection will be performed Braidwood Station Inspection ActivitiesJanuary 1 -December 31, 2011Examples of Major Inspection Activities in 2011:*Special Inspection (March 31 to May 4) 22*Temp. Inst. 183 (April 1 to April 21)
- Unit 2 Refueling Outage (April 17 to May 12)
- Initial Licensed Operators Examination (June 20 to June 30)
- Modification / 50.59 Inspection (September 12 to September 30)
- ISFSI Inspection (October 27 to December 23)
- Triennial Heat Sink Inspection (November 28 to December 2)
Braidwood StationAnnual Assessment SummaryJanuary 1 -December 31, 2011*Exelon operated Braidwood Station in a manner that p reserved public health and 23 pp safety*All cornerstone objectives were met January 1 -December 31, 2011*No substantive cross-cutting issue was identified at Braidwood Station Braidwood StationAnnual Assessment Summary 24*NRC plans to perform baseline inspections at Braidwood Station for 2012 for both units*NRC also plans to perform a 95001 supplemental inspection for Unit 2 (Not yet scheduled)
Licensee Response and Remarks Dan Enright 25 Dan EnrightSite Vice President, Braidwood Exelon Nuclear Open to the Public*The NRC places a high priority on keeping the public and stakeholders informed of its
activities 26*At www.nrc.gov, you can:-Find public meeting dates and transcripts-Read NRC testimony, speeches, press releases, and policy decisions-Access the agency's Electronic Reading Room to find NRC publications and documents Contacting the NRC*Report an emergency-(301) 816-5100 (call collect)*Report a safety concern 27-(800) 695-7403 -Allegation@nrc.gov*General information or questions-www.nrc.gov
-Select "What We Do" for Public Affairs Actions in Response to the Japan Nuclear Accident*Actions in response to Japan Nuclear Accident Website: http://www.nrc.gov/japan/japan-info.html*Mailbox for comments on staff actions:
28 JLD_Public.Resource@nrc.gov*Office of Public Affairs Point of Contact:
OPA.resource@nrc.gov or 301-415-8200 NRC Representatives*Gary Shear, Acting Director, Division of Reactor Projects -(630) 829-9600*Kenneth O'Brien, Acting Deputy Division Director, DRP-(630) 829-9602*Joel Wiebe, Project Manager, NRR
-(301) 415-6606 29 ()*Jamie Benjamin, Senior Resident Inspector-(815) 458-2852*Alex Garmoe, Resident Inspector-(815) 458-2852*Raymond Ng, Project Engineer-(630) 829-9574*Eric Duncan, Branch Chief-(630) 829-9620 NRC Representatives*Christine Lipa, Chief, Decommissioning Branch (ISFSI)-(630) 829-9834
- Viktoria Mitlyng, Public Affairs Officer-(630) 829-9662 30*Prema Chandrathil, Public Affairs Officer-(630) 829-9663*NRC Region III Office Switchboard-(630) 829-9500; (800) 522-3025 NRC Social Media Channels*Blog:http://public-blog.nrc-gateway.gov/
31*Flickr: http://www.flickr.com/photos/nrcgov/*Twitter: http://twitter.com/#!/nrcgov*YouTube:http://www.youtube.com/user/NRCgov*RSS: http://www.nrc.gov/public-involve/listserver.html#rss Reference Sources*Reactor Oversight Process-http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/in dex.html 32*Public Electronic Reading Room-http://www.nrc.gov/reading-rm.html*Public Document Room-1-800-397-4209 (Toll Free)
Braidwood Station Annual Assessment Mti 33 M ee ti ngReactor Oversight Process -2011Nuclear Regulatory Commission -Region IIILisle, IllinoisAugust 15, 2012