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| | issue date = 08/22/2006 | | | issue date = 08/22/2006 |
| | title = IR 05000456-06-010(DRS); 05000457-06-010(DRS); on 08/07/2006 - 08/11/2006; Braidwood Station; Emergency Preparedness Specialist Report | | | title = IR 05000456-06-010(DRS); 05000457-06-010(DRS); on 08/07/2006 - 08/11/2006; Braidwood Station; Emergency Preparedness Specialist Report |
| | author name = Riemer K R | | | author name = Riemer K |
| | author affiliation = NRC/RGN-III/DRS/PSB | | | author affiliation = NRC/RGN-III/DRS/PSB |
| | addressee name = Crane C M | | | addressee name = Crane C |
| | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear | | | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear |
| | docket = 05000456, 05000457 | | | docket = 05000456, 05000457 |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:August 22, 2006Mr. Christopher M. CranePresident and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555SUBJECT:BRAIDWOOD STATION, UNITS 1 AND 2NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000456/2006010(DRS); 05000457/2006010(DRS) |
| [[Issue date::August 22, 2006]]
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| Mr. Christopher M. CranePresident and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
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| SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000456/2006010(DRS); 05000457/2006010(DRS)
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| ==Dear Mr. Crane:== | | ==Dear Mr. Crane:== |
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| In accordance with 10 CFR Part 2.390 of the NRC's "Rules of Practice," a copy of this letterand its enclosure will be available electronically for public inspection in the NRC PublicDocument Room, or from the Publicly Available Records (PARS) component of NRC's C. Crane-2-document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | | In accordance with 10 CFR Part 2.390 of the NRC's "Rules of Practice," a copy of this letterand its enclosure will be available electronically for public inspection in the NRC PublicDocument Room, or from the Publicly Available Records (PARS) component of NRC's C. Crane-2-document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
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| Sincerely,/RA/Kenneth Riemer, ChiefPlant Support Branch Division of Reactor SafetyDocket Nos. 50-456; 50-457License Nos. NPF-72; NPF-77 | | Sincerely, |
| | | /RA/Kenneth Riemer, ChiefPlant Support Branch Division of Reactor SafetyDocket Nos. 50-456; 50-457License Nos. NPF-72; NPF-77Enclosure:Inspection Report 05000456/2006010(DRS); 05000457/2006010(DRS) |
| ===Enclosure:===
| | w/Attachment: Supplemental Informationcc w/encl:Site Vice President - Braidwood StationPlant Manager - Braidwood Station Regulatory Assurance Manager - Braidwood Station Chief Operating Officer Senior Vice President - Nuclear Services Vice President - Operations Support Director Licensing Manager Licensing - Braidwood and Byron Senior Counsel, Nuclear, Mid-West Regional Operating Group Document Control Desk - Licensing Assistant Attorney General Illinois Emergency Management Agency State Liaison Officer Chairman, Illinois Commerce Commission W. King, DHS, Region V |
| Inspection Report 05000456/2006010(DRS); 05000457/2006010(DRS) | |
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| ===w/Attachment:===
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| Supplemental Informationcc w/encl:Site Vice President - Braidwood StationPlant Manager - Braidwood Station Regulatory Assurance Manager - Braidwood Station Chief Operating Officer Senior Vice President - Nuclear Services Vice President - Operations Support Director Licensing Manager Licensing - Braidwood and Byron Senior Counsel, Nuclear, Mid-West Regional Operating Group Document Control Desk - Licensing Assistant Attorney General Illinois Emergency Management Agency State Liaison Officer Chairman, Illinois Commerce Commission W. King, DHS, Region V | |
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| =SUMMARY OF FINDINGS= | | =SUMMARY OF FINDINGS= |
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| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| The following is a list of documents reviewed during the inspection. | | The following is a list of documents reviewed during the inspection. |
| : Inclusion on this list doesnot imply that the NRC inspectors reviewed the documents in their entirety but rather that selected sections of portions of the documents were evaluated as part of the overall inspection effort. | | : Inclusion on this list doesnot imply that the NRC inspectors reviewed the documents in their entirety but rather that |
| : Inclusion of a document on this list does not imply NRC acceptance of the document orany part of it, unless this is stated in the body of the inspection report.
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| : 1EP1Exercise EvaluationBraidwood Station August 2006 Exercise Scenario Manual Braidwood Station Draft August 2006 Exercise Findings and Observations Report;
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| undated Braidwood Station June 2006 Pre-Exercise Findings and Observations Report; datedJuly 28, 2006 Braidwood Station 2005 Off-Year Emergency Plan Drill Scenario SummaryBraidwood Station Annex to the Exelon Standardized Emergency Plan; Section 3;Revision 17
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| : 2EP-AA-110; Assessment of Emergencies; Revision 6EP-AA-110-302; Core Damage Assessment - Pressurized Water Reactors; Revision 1
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| : EP-AA-111; Emergency Classification and Protective Action Recommendations;Revision 11EP-AA-112; Emergency Response Organization and Emergency Response FacilityActivation and Operation; Revision 10EP-AA-112-100; Control Room Operation; Revision 7
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| : EP-AA-112-200; TSC Activation and Operation; Revision 5
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| : EP-AA-112-300; OSC Activation and Operation; Revision 5
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| : EP-AA-112-400; EOF Activation and Operation; Revision 6
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| : EP-AA-113; Personnel Protective Actions; Revision 7
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| : EP-AA-114; Notifications; Revision 6
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| : EP-MW-110-200; Dose Assessment; Revision 4
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| : EP-MW-114-100; Midwest Region Offsite Notifications; Revision 5
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| ==4OA1 Performance Indicator VerificationBraidwood Station Emergency Planning Zone Sirens' Daily and Monthly OperabilityReports - July 2005 through June 2006==
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| : LS-AA-2110; Monthly PI Data Elements for ERO Drill Participation - July 2005 throughJune 2006; Revision 5LS-AA-2120; Monthly PI Data Elements for Drill/Exercise Performance - July
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| : 2005through June 2006; Revision 3LS-AA-2130; Monthly PI Data Elements for ANS Reliability - July 2005 throughJune 2006; Revision 4
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| ==4OA7 Licensee Identified ViolationsBraidwood Station Annex to the Exelon Standardized Emergency Plan; Section 3;Category H - Hazards and Other Conditions; Revisions 16 and 17AR
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| : 00467017; Discovery of Non-Conservative==
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| : EAL Change; dated March 16, 2006
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| : 3
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| ==LIST OF ACRONYMS==
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| USEDANSAlert and Notification SystemARAction Request
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| CFRCode of Federal Regulations
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| CRSControl Room Simulator
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| DEPDrill and Exercise PerformanceEALEmergency Action Level
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| EOFEmergency Operations Facility
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| EROEmergency Response Organization
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| NCVNon-Cited Violation
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| NRCUnited States Nuclear Regulatory Commission
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| NUREGNuclear Regulatory GuideOSCOperations Support Center
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| PIPerformance Indicator
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| : [[TSCT]] [[echnical Support Center]]
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| }} | | }} |
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Category:Inspection Report
MONTHYEARIR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 ML24025C7242024-01-29029 January 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002 IR 05000457/20230112024-01-25025 January 2024 2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report IR 05000456/20230102023-10-18018 October 2023 Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010 IR 05000456/20234012023-10-18018 October 2023 Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401 IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 IR 05000456/20230022023-08-0303 August 2023 Integrated Inspection Report 05000456/2023002 and 05000457/2023002 IR 05000456/20230012023-05-0808 May 2023 Integrated Inspection Report 05000456/2023001 and 05000457/2023001 IR 05000457/20214202023-03-22022 March 2023 Reissued - Braidwood Generating Station, Unit 1 and 2, Security Inspection Report Cover Letter 05000456 and 05000457-2021420 IR 05000456/20220062023-03-0101 March 2023 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2022006 and 05000457/2022006) IR 05000456/20220042023-01-26026 January 2023 Integrated Inspection Report 05000456/2022004 and 05000457/2022004 ML22269A4992022-11-0808 November 2022 Review of the Fall 2021 Steam Generator Tube Inspection Report IR 05000456/20220032022-10-25025 October 2022 Integrated Inspection Report 05000456/2022003 and 05000457/2022003 and Exercise of Enforcement Discretion IR 05000456/20224202022-10-24024 October 2022 Cover Letter Braidwood Station Units 1 and 2 Security Baseline Inspection Report 05000456/2022420 and 05000457/2022420 IR 05000456/20224032022-08-23023 August 2022 Material Control and Accounting Program Inspection Report 05000456/2022403 and 05000457/2022403 IR 05000456/20220052022-08-22022 August 2022 Updated Inspection Plan for Braidwood Station Units 1 and 2 (Report 05000456/2022005; 05000457/2022005) IR 05000456/20220022022-07-26026 July 2022 Integrated Inspection Report 05000456/2022002; 05000457/2022002; and 07200073/2022001 IR 05000456/20220112022-07-20020 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000456/2022011 and 05000457/2022011 IR 05000456/20224012022-07-13013 July 2022 Security Baseline Inspection Report 05000456/2022401 and 05000457/2022401 IR 05000456/20224022022-06-30030 June 2022 Cyber Security Inspection Report 05000456/2022402 and 05000457/2022402 IR 05000456/20220102022-06-22022 June 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000456/2022010 and 05000457/2022010 IR 05000456/20220012022-05-0303 May 2022 Integrated Inspection Report 05000456/2022001 and 05000457/2022001 IR 05000456/20223012022-04-0606 April 2022 NRC Initial License Examination Report 05000456/2022301 and 05000457/2022301 IR 05000456/20225012022-03-21021 March 2022 Emergency Preparedness Biennial Exercise Inspection Report 05000456/2022501 and 05000457/2022501 IR 05000456/20210062022-03-0202 March 2022 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2021006 and 05000457/2021006) IR 05000456/20210042022-01-28028 January 2022 Integrated Inspection Report 05000456/2021004 and 05000457/2021004 IR 05000456/20210032021-10-26026 October 2021 Integrated Inspection Report 05000456/2021003 and 05000457/2021003 IR 05000456/20214022021-09-16016 September 2021 Security Baseline Inspection Report 05000456/2021402 and 05000457/2021402 IR 05000456/20210052021-09-0101 September 2021 Updated Inspection Plan for Braidwood Station, Units 1 and 2 (Report 05000456/2021005 and 05000457/2021005) IR 05000456/20210022021-07-22022 July 2021 Integrated Inspection Report 05000456/2021002 and 05000457/2021002 IR 05000456/20210102021-07-19019 July 2021 Triennial Fire Protection Inspection Report 05000456/2021010 and 05000457/2021010 IR 05000456/20214012021-05-20020 May 2021 Security Baseline Inspection Report 05000456/2021401 and 05000457/2021401 IR 05000456/20210012021-04-16016 April 2021 Integrated Inspection Report 05000456/2021001 and 05000457/2021001 IR 05000456/20200062021-03-0404 March 2021 Annual Assessment Letter for Braidwood Station (Report 05000456/2020006 and 05000457/2020006) IR 05000456/20200042021-01-26026 January 2021 Integrated Inspection Report 05000456/2020004; 05000457/2020004; and 07200073/2020001 IR 05000456/20200122020-11-18018 November 2020 Design Basis Assurance Inspection (Programs) Inspection Report 05000456/2020012 and 05000457/2020012 IR 05000456/20200032020-11-10010 November 2020 Integrated Inspection Report 05000456/2020003 and 05000457/2020003 IR 05000456/20204022020-10-0202 October 2020 Security Baseline Inspection Report 05000456/2020402 and 05000457/2020402 IR 05000456/20200052020-09-0101 September 2020 Updated Inspection Plan for Braidwood Station Units 1 and 2 (Report 05000456/2020005 and 05000457/2020005) IR 05000456/20203012020-08-27027 August 2020 NRC Initial License Examination Report 05000456/2020301 and 05000457/2020301 ML20238B8692020-08-25025 August 2020 Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000456/2020004; 05000457/2020004 IR 05000456/20200022020-07-28028 July 2020 Integrated Inspection Report 05000456/2020002 and 05000457/2020002 IR 05000456/20200012020-04-21021 April 2020 Integrated Inspection Report 05000456/2020001 and 05000457/2020001 IR 05000456/20205012020-04-0808 April 2020 Emergency Preparedness Inspection Report 05000456/2020501 and 05000457/2020501 IR 05000456/20204012020-03-31031 March 2020 Security Baseline Inspection Report 05000456/2020401 and 05000457/2020401 IR 05000456/20200102020-03-25025 March 2020 Biennial Problem Identification and Resolution Inspection Report 05000456/2020010 and 05000457/2020010 IR 05000456/20190062020-03-0303 March 2020 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2019006 and 05000457/2019006) ML20056F2972020-02-25025 February 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2020002 2024-02-02
[Table view] Category:Letter
MONTHYEARIR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 ML24025C7242024-01-29029 January 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002 IR 05000457/20230112024-01-25025 January 2024 2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators ML23348A2162023-12-15015 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0030 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference 05000457/LER-2023-001, Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case2023-11-17017 November 2023 Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case ML23321A0442023-11-17017 November 2023 Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds IR 05000456/20234012023-10-18018 October 2023 Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401 IR 05000456/20230102023-10-18018 October 2023 Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 ML23234A2462023-08-25025 August 2023 Confirmation of Initial License Examination IR 05000456/20230022023-08-0303 August 2023 Integrated Inspection Report 05000456/2023002 and 05000457/2023002 ML23188A1292023-07-26026 July 2023 Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink ML23191A8442023-07-10010 July 2023 05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23110A1152023-06-12012 June 2023 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2023-LLA-0042) (Letter) RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. ML23138A1342023-05-18018 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Braidwood Station and Byron Station ML23132A0472023-05-12012 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ML23130A0072023-05-10010 May 2023 Submittal of Core Operating Limits Report Cycle 24, Rev. 16 IR 05000456/20230012023-05-0808 May 2023 Integrated Inspection Report 05000456/2023001 and 05000457/2023001 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23118A0202023-04-28028 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML23095A1292023-04-0505 April 2023 Steam Generator Tube Inspection Report for Refueling Outage 23 ML23094A1352023-04-0404 April 2023 Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010 RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations 2024-02-02
[Table view] |
Text
August 22, 2006Mr. Christopher M. CranePresident and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555SUBJECT:BRAIDWOOD STATION, UNITS 1 AND 2NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000456/2006010(DRS); 05000457/2006010(DRS)
Dear Mr. Crane:
On August 11, 2006, the NRC completed an inspection at your Braidwood Station, Units 1and 2. The enclosed report documents the inspection findings, which were discussed on August 11, 2006, with Mr. G. Boerschig and other members of your staff.The inspection examined activities conducted under your license as they relate to safety andcompliance with the Commission's rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Specifically, this inspection focused on emergency preparedness, including your staff's determinations of performance indicators for the Emergency Preparedness Cornerstone.On the basis of the results of this inspection, no findings of significance were identified.
In accordance with 10 CFR Part 2.390 of the NRC's "Rules of Practice," a copy of this letterand its enclosure will be available electronically for public inspection in the NRC PublicDocument Room, or from the Publicly Available Records (PARS) component of NRC's C. Crane-2-document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/Kenneth Riemer, ChiefPlant Support Branch Division of Reactor SafetyDocket Nos. 50-456; 50-457License Nos. NPF-72; NPF-77Enclosure:Inspection Report 05000456/2006010(DRS); 05000457/2006010(DRS)
w/Attachment: Supplemental Informationcc w/encl:Site Vice President - Braidwood StationPlant Manager - Braidwood Station Regulatory Assurance Manager - Braidwood Station Chief Operating Officer Senior Vice President - Nuclear Services Vice President - Operations Support Director Licensing Manager Licensing - Braidwood and Byron Senior Counsel, Nuclear, Mid-West Regional Operating Group Document Control Desk - Licensing Assistant Attorney General Illinois Emergency Management Agency State Liaison Officer Chairman, Illinois Commerce Commission W. King, DHS, Region V
SUMMARY OF FINDINGS
IR 05000456/2006010(DRS); 05000457/2006010(DRS); 08/07/2006 - 08/11/2006;Braidwood Station; Emergency Preparedness Specialist Report.The report covers a 1 week baseline inspection by two regional emergency preparednessinspectors, a resident inspector, and a licensed operator examiner. The inspection focused on the Emergency Preparedness Cornerstone in the Reactor Safety strategic performance area during the biennial emergency preparedness exercise. This inspection also included a review of records related to the three emergency preparedness performance indicators for the period July 1, 2005, through June 30, 2006.The NRC's program for overseeing the safe operation of commercial nuclear power reactors isdescribed in NUREG-1649, "Reactor Oversight Process," Revision 3, dated July 2000.A.Inspector-Identified and Self-Revealed FindingsNone.
B.Licensee-Identified Violations
Cornerstone: Emergency Preparedness
One violation of very low safety significance, which was identified by the licensee, wasreviewed by the inspectors. Corrective actions taken by the licensee were entered into the licensee's corrective action program and were adequately completed. This violation is listed in Section 4OA7 of this report.
2
REPORT DETAILS
1.REACTOR SAFETYCornerstone: Emergency Preparedness1EP1Exercise Evaluation (71114.01)
a. Inspection Scope
The inspectors reviewed the August 8, 2006, biennial emergency preparednessexercise's objectives and scenario to ensure that the exercise would acceptably test major elements of the licensee's emergency plan and to verify that the exercise's simulated problems provided an acceptable framework to support demonstration of the licensee's capability to implement its plan. The inspectorsalso reviewed records of two emergency preparedness drills, which were conducted in2005 and 2006, to verify that those dr ills' scenarios were sufficiently different from thescenario used in the August 8, 2006 exercise.The inspectors evaluated the licensee's exercise performance, focusing on therisk-significant activities of emergency classification, notification, and protective action decision making, as well as implementation of accident mitigation strategies in the following emergency response facilities:*Control Room Simulator (CRS);*Technical Support Center (TSC);
- Operations Support Center (OSC); and
- Emergency Operations Facility (EOF).The inspectors also assessed the licensee's recognition of abnormal plant conditions,transfer of responsibilities between facilities, internal communications, interfaces withoffsite officials, readiness of emergency facilities and related equipment, and overallimplementation of the licensee's emergency plan.The inspectors attended post-exercise critiques in the CRS, TSC, OSC, and EOFto evaluate the licensee's initial self-assessment of its exercise performance. The inspectors later met with the licensee's lead exercise evaluators to obtain the licensee's refined assessments of its exercise participants' performances. These self-assessments were then compared with the inspectors' independent observations and assessments to assess the licensee's ability to adequately critique its exerciseperformance.These activities completed one inspection sample.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator (PI) Verification
Cornerstone: Emergency Preparedness.1Reactor Safety Strategic Area
a. Inspection Scope
The inspectors reviewed the licensee's records associated with each of the threeemergency preparedness PIs to verify that the licensee's program was implemented consistent with the industry guidelines in the applicable revision of Nuclear Energy Institute Publication No. 99-02, "Regulatory Assessment Performance Indicator Guideline," and related licensee procedures. Specifically, licensee records related to the performance of the Alert and Notification System (ANS), key Emergency Response Organization (ERO) members' drill participation, and Dr ill and Exercise Performance(DEP) were reviewed to verify the accuracy and completeness of the PI data submitted to NRC for the period from July 1, 2005 through June 30, 2006. The following three PIswere reviewed:Common
- ANS*ERO Drill Participation
- DEPThese activities completed three PI samples.
b. Findings
No findings of significance were identified.4OA6Meetings.1Exit MeetingAn exit meeting was conducted for:
- Emergency Preparedness with Mr. G. Boerschig and other members of licenseemanagement and staff at the conclusion of the inspection on August 11, 2006. The licensee acknowledged the information presented. No proprietary information was identified..2Public and Media Briefing*On August 11, 2006, an inspector summarized NRC's preliminary exerciseinspection conclusions at a public and media briefing hosted by Department of Homeland Security Region V Field Office staff in Joliet, Illinois.
44OA7Licensee Identified ViolationsCornerstone: Emergency PreparednessThe following violation of very low significance was identified by the licensee and is aviolation of NRC requirements which met the criteria of Section VI of the NRCEnforcement Manual, NUREG-1600, for being dispositioned as a Non-Cited Violation(NCV).Title 10 CFR 50.54(q) requires, in part, that a licensee shall follow and maintain in effectemergency plans which meet the standards in Section 50.47(b) and requirements in Appendix E of this part. The licensee may make changes to these plans without Commission approval only if the changes do not decrease the effectiveness of the plans. Contrary to the above, Emergency Action Level (EAL) HU-5, which addressed natural or destructive phenomenon inside the protected area or switchyard, was revised in a non-conservative manner. The non-conservative Unusual Event revision, which was implemented on January 17, 2006, erroneously referenced a seismic acceleration value for an Alert emergency classification, and was identified by the licensee to be the result of inadequate technical reviews. The licensee identified and restored EAL HU-5 to the correct wording in a revision implemented on March 17, 2006.The licensee's implementation of the change to EAL HU-5 on January 17, 2006,decreased the effectiveness of the emergency plan without prior NRC approval, andconsequently was a violation of 10 CFR 50.54(q). The finding is not suitable for evaluation using the Significance Determination Process, but has been reviewed by
NRC management and is determined to be a finding of very low safety significance. Because the violation was entered into the licensee's corrective action program and adequate corrective action was completed, it is being treated as a Severity Level IV NCV.ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- K. Aleshire, Emergency Preparedness Manager
- D. Ambler, Regulatory Assurance Manager
- G. Boerschig, Plant Manager
- C. Dunn, Training Department Manager
- J. Gerrity, Emergency Preparedness Coordinator
- D. Gibeaut, Nuclear Oversight Manager
- R. Leasure, Radiation Protection Manager
- S. McCain, Corporate Emergency Preparedness Manager
- W. Waznis, Nuclear Oversight SpecialistIllinois Emergency Management Agency
- M. Perry, Engineer
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened, Closed, and
Discussed
None.
LIST OF DOCUMENTS REVIEWED
The following is a list of documents reviewed during the inspection.
- Inclusion on this list doesnot imply that the NRC inspectors reviewed the documents in their entirety but rather that