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Category:Inspection Report
MONTHYEARIR 05000456/20240112024-09-12012 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000456/2024011 and 05000457/2024011 IR 05000456/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005) IR 05000456/20240022024-08-0808 August 2024 Integrated Inspection Report 05000456/2024002 and 05000457/2024002 IR 05000456/20240102024-05-31031 May 2024 License Renewal Phase 1 Report 05000456/2024010 ML24136A2452024-05-15015 May 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004 IR 05000456/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000456/2024301; 05000457/2024301 IR 05000456/20240012024-04-24024 April 2024 Integrated Inspection Report 05000456/2024001 and 05000457/2024001 IR 05000457/20240902024-04-19019 April 2024 Final Significance Determination for 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Dilution Issue - NRC Inspection Report 05000457/2024090 IR 05000456/20244012024-03-0505 March 2024 Cyber Security Inspection Report 05000456/2024401 and 05000457/2024401 (Public) IR 05000456/20230062024-02-28028 February 2024 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2023006 and 05000457/2023006) IR 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 05000456/20234012023-10-18018 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 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 2024-09-12
[Table view] Category:Letter
MONTHYEARRS-24-098, Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality2024-10-23023 October 2024 Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality ML24291A0012024-10-17017 October 2024 Submittal of Core Operating Limits Report, Cycle 25 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024 Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24263A1272024-09-23023 September 2024 – Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary IR 05000456/20240112024-09-12012 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000456/2024011 and 05000457/2024011 ML24164A0032024-09-10010 September 2024 Issuance of Amendment Nos. 235 and 235 Revision of Technical Specifications for the Ultimate Heat Sink ML24227A0522024-08-29029 August 2024 Audit Plan for LAR to Remove ATWS Mtc Limit IR 05000456/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005) ML24225A1112024-08-13013 August 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000456/20240022024-08-0808 August 2024 Integrated Inspection Report 05000456/2024002 and 05000457/2024002 ML24172A1252024-07-26026 July 2024 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2024-LLA-0075) - Transmittal Letter ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) ML24163A3922024-06-25025 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24164A2132024-06-13013 June 2024 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink IR 05000456/20240102024-05-31031 May 2024 License Renewal Phase 1 Report 05000456/2024010 RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24136A2452024-05-15015 May 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004 ML24136A0132024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) ML24122A6522024-05-0101 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests IR 05000456/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000456/2024301; 05000457/2024301 RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML24116A0052024-04-25025 April 2024 Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25 IR 05000456/20240012024-04-24024 April 2024 Integrated Inspection Report 05000456/2024001 and 05000457/2024001 ML24113A1272024-04-22022 April 2024 Audit Plan in Support of Review of LAR Revision of TS 3.7.15, 3.7.16, and 4.3.1 (EPID: L-2023-LLA-0136) (Non-Proprietary) IR 05000457/20240902024-04-19019 April 2024 Final Significance Determination for 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Dilution Issue - NRC Inspection Report 05000457/2024090 ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML24094A2692024-04-0303 April 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report, WCAP-17451-P, Revision 2, Reactor Internals Guide Tube Wear Westinghouse Domestic Fleet Operational Projections RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24057A0372024-03-26026 March 2024 Proposed Alternative from Certain Requirements Contained in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML24067A3252024-03-0707 March 2024 U.S. Department of Energy, Office of Legacy Management, 2023 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites ML24066A0122024-03-0606 March 2024 Operator Licensing Examination Approval Braidwood Station, Units 1 and 2, March 2024 IR 05000456/20244012024-03-0505 March 2024 Cyber Security Inspection Report 05000456/2024401 and 05000457/2024401 (Public) IR 05000456/20230062024-02-28028 February 2024 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2023006 and 05000457/2023006) ML24057A3022024-02-26026 February 2024 Regulatory Conference Supplemental Information ML24047A2382024-02-20020 February 2024 Regulatory Conference to Discuss Risk Associated with 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Leak RS-24-013, Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-02-13013 February 2024 Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators IR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 2024-09-23
[Table view] |
Text
August 22, 2006
Mr. Christopher M. CranePresident and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT: 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-77
Enclosure:
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 selected sections of portions of the documents were evaluated as part of the overall inspection effort.
- 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.
- 1EP1Exercise EvaluationBraidwood Station August 2006 Exercise Scenario Manual Braidwood Station Draft August 2006 Exercise Findings and Observations Report;
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
- 2EP-AA-110; Assessment of Emergencies; Revision 6EP-AA-110-302; Core Damage Assessment - Pressurized Water Reactors; Revision 1
- 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
- EP-AA-112-200; TSC Activation and Operation; Revision 5
- EP-AA-112-300; OSC Activation and Operation; Revision 5
- EP-AA-112-400; EOF Activation and Operation; Revision 6
- EP-AA-113; Personnel Protective Actions; Revision 7
- EP-AA-114; Notifications; Revision 6
- EP-MW-110-200; Dose Assessment; Revision 4
- EP-MW-114-100; Midwest Region Offsite Notifications; Revision 5
4OA1 Performance Indicator VerificationBraidwood Station Emergency Planning Zone Sirens' Daily and Monthly OperabilityReports - July 2005 through June 2006
- 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
- 2005through June 2006; Revision 3LS-AA-2130; Monthly PI Data Elements for ANS Reliability - July 2005 throughJune 2006; Revision 4
==4OA7 Licensee Identified ViolationsBraidwood Station Annex to the Exelon Standardized Emergency Plan; Section 3;Category H - Hazards and Other Conditions; Revisions 16 and 17AR
- 00467017; Discovery of Non-Conservative==
- EAL Change; dated March 16, 2006
- 3
USEDANSAlert and Notification SystemARAction Request
CFRCode of Federal Regulations
CRSControl Room Simulator
DEPDrill and Exercise PerformanceEALEmergency Action Level
EOFEmergency Operations Facility
EROEmergency Response Organization
NCVNon-Cited Violation
NRCUnited States Nuclear Regulatory Commission
NUREGNuclear Regulatory GuideOSCOperations Support Center
PIPerformance Indicator
- TSCT echnical Support Center