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| {{#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) | | {{#Wiki_filter:ust 22, 2006 |
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| | ==SUBJECT:== |
| | BRAIDWOOD STATION, UNITS 1 AND 2 NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000456/2006010(DRS); 05000457/2006010(DRS) |
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| ==Dear Mr. Crane:== | | ==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. | | On August 11, 2006, the NRC completed an inspection at your Braidwood Station, Units 1 and 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. |
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| 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. | | The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license. |
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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). | | The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Specifically, this inspection focused on emergency preparedness, including your staffs determinations of performance indicators for the Emergency Preparedness Cornerstone. |
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| | On the basis of the results of this inspection, no findings of significance were identified. |
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| | In accordance with 10 CFR Part 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room, or from the Publicly Available Records (PARS) component of NRC's 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, | | 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) | | /RA/ |
| 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 | | Kenneth Riemer, Chief Plant Support Branch Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77 Enclosure: Inspection Report 05000456/2006010(DRS); |
| | 05000457/2006010(DRS) |
| | w/Attachment: Supplemental Information cc w/encl: Site Vice President - Braidwood Station Plant 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= |
| 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. | | IR 05000456/2006010(DRS); 05000457/2006010(DRS); 08/07/2006 - 08/11/2006; |
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| ===B.Licensee-Identified Violations=== | | Braidwood Station; Emergency Preparedness Specialist Report. |
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| | The report covers a 1 week baseline inspection by two regional emergency preparedness inspectors, 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. |
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| | The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 3, dated July 2000. |
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| | A. Inspector-Identified and Self-Revealed Findings None. |
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| | ===Licensee-Identified Violations=== |
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| ===Cornerstone: Emergency Preparedness=== | | ===Cornerstone: Emergency Preparedness=== |
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| 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. | | One violation of very low safety significance, which was identified by the licensee, was reviewed by the inspectors. Corrective actions taken by the licensee were entered into the licensees corrective action program and were adequately completed. This violation is listed in Section 4OA7 of this report. |
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| | =REPORT DETAILS= |
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| | ==REACTOR SAFETY== |
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| =REPORT DETAILS= | | ===Cornerstone: Emergency Preparedness=== |
| 1.REACTOR SAFETYCornerstone: Emergency Preparedness1EP1Exercise Evaluation (71114.01)
| | {{a|1EP1}} |
| | ==1EP1 Exercise Evaluation== |
| | {{IP sample|IP=IP 71114.01}} |
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| ====a. Inspection Scope==== | | ====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); | | The inspectors reviewed the August 8, 2006, biennial emergency preparedness exercises objectives and scenario to ensure that the exercise would acceptably test major elements of the licensees emergency plan and to verify that the exercises simulated problems provided an acceptable framework to support demonstration of the licensees capability to implement its plan. The inspectors also reviewed records of two emergency preparedness drills, which were conducted in 2005 and 2006, to verify that those drills scenarios were sufficiently different from the scenario used in the August 8, 2006 exercise. |
| *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. | | The inspectors evaluated the licensees exercise performance, focusing on the risk-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). |
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| | The inspectors also assessed the licensees recognition of abnormal plant conditions, transfer of responsibilities between facilities, internal communications, interfaces with offsite officials, readiness of emergency facilities and related equipment, and overall implementation of the licensees emergency plan. |
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| | The inspectors attended post-exercise critiques in the CRS, TSC, OSC, and EOF to evaluate the licensees initial self-assessment of its exercise performance. The inspectors later met with the licensees lead exercise evaluators to obtain the licensees refined assessments of its exercise participants performances. These self-assessments were then compared with the inspectors independent observations and assessments to assess the licensees ability to adequately critique its exercise performance. |
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| | These activities completed one inspection sample. |
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| ====b. Findings==== | | ====b. Findings==== |
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| ==4OA1 Performance Indicator (PI) Verification== | | ==4OA1 Performance Indicator (PI) Verification== |
| {{IP sample|IP=IP 71151}} | | {{IP sample|IP=IP 71151}} |
| Cornerstone: Emergency Preparedness.1Reactor Safety Strategic Area | | ===Cornerstone: Emergency Preparedness=== |
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| | ===.1 Reactor Safety Strategic Area=== |
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| ====a. Inspection Scope==== | | ====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 | | The inspectors reviewed the licensees records associated with each of the three emergency preparedness PIs to verify that the licensees 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 Drill 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 PIs were reviewed: |
| *ANS*ERO Drill Participation | | Common |
| *DEPThese activities completed three PI samples. | | * ANS |
| | * ERO Drill Participation |
| | * DEP These activities completed three PI samples. |
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| ====b. Findings==== | | ====b. Findings==== |
| No findings of significance were identified.4OA6Meetings.1Exit MeetingAn exit meeting was conducted for: | | No findings of significance were identified. |
| *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.
| | {{a|4OA6}} |
| | ==4OA6 Meetings== |
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| 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
| | ===.1 Exit Meeting=== |
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| 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: | | An exit meeting was conducted for: |
| | * Emergency Preparedness with Mr. G. Boerschig and other members of licensee management and staff at the conclusion of the inspection on August 11, 2006. |
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| | The licensee acknowledged the information presented. No proprietary information was identified. |
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| | ===.2 Public and Media Briefing=== |
| | * On August 11, 2006, an inspector summarized NRCs preliminary exercise inspection conclusions at a public and media briefing hosted by Department of Homeland Security Region V Field Office staff in Joliet, Illinois. |
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| | {{a|4OA7}} |
| | ==4OA7 Licensee Identified Violations== |
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| | ===Cornerstone: Emergency Preparedness=== |
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| | The following violation of very low significance was identified by the licensee and is a violation of NRC requirements which met the criteria of Section VI of the NRC Enforcement Manual, NUREG-1600, for being dispositioned as a Non-Cited Violation (NCV). |
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| | Title 10 CFR 50.54(q) requires, in part, that a licensee shall follow and maintain in effect emergency 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. |
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| | The licensees implementation of the change to EAL HU-5 on January 17, 2006, decreased the effectiveness of the emergency plan without prior NRC approval, and consequently 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. |
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| | Because the violation was entered into the licensees corrective action program and adequate corrective action was completed, it is being treated as a Severity Level IV NCV. |
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| | ATTACHMENT: |
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| =SUPPLEMENTAL INFORMATION= | | =SUPPLEMENTAL INFORMATION= |
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| ==KEY POINTS OF CONTACT== | | ==KEY POINTS OF CONTACT== |
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| Licensee | | Licensee |
| : [[contact::K. Aleshire]], Emergency Preparedness Manager | | : [[contact::K. Aleshire]], Emergency Preparedness Manager |
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| : [[contact::R. Leasure]], Radiation Protection Manager | | : [[contact::R. Leasure]], Radiation Protection Manager |
| : [[contact::S. McCain]], Corporate Emergency Preparedness Manager | | : [[contact::S. McCain]], Corporate Emergency Preparedness Manager |
| : [[contact::W. Waznis]], Nuclear Oversight SpecialistIllinois Emergency Management Agency | | : [[contact::W. Waznis]], Nuclear Oversight Specialist |
| | Illinois Emergency Management Agency |
| : [[contact::M. Perry]], Engineer | | : [[contact::M. Perry]], Engineer |
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| ==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== | | ==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== |
| Opened, Closed, and | | |
| ===Discussed===
| | ===Opened, Closed, and Discussed=== |
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| None. | | None. |
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| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| The following is a list of documents reviewed during the inspection.
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| : Inclusion on this list doesnot imply that the NRC inspectors reviewed the documents in their entirety but rather that
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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
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[Table view] |
Text
ust 22, 2006
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2 NRC 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 1 and 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 and compliance with the Commissions 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 staffs 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 letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room, or from the Publicly Available Records (PARS) component of NRC's 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, Chief Plant Support Branch Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77 Enclosure: Inspection Report 05000456/2006010(DRS);
05000457/2006010(DRS)
w/Attachment: Supplemental Information cc w/encl: Site Vice President - Braidwood Station Plant 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 preparedness inspectors, 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 NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 3, dated July 2000.
A. Inspector-Identified and Self-Revealed Findings None.
Licensee-Identified Violations
Cornerstone: Emergency Preparedness
One violation of very low safety significance, which was identified by the licensee, was reviewed by the inspectors. Corrective actions taken by the licensee were entered into the licensees corrective action program and were adequately completed. This violation is listed in Section 4OA7 of this report.
REPORT DETAILS
REACTOR SAFETY
Cornerstone: Emergency Preparedness
1EP1 Exercise Evaluation
Main article: IP 71114.01
a. Inspection Scope
The inspectors reviewed the August 8, 2006, biennial emergency preparedness exercises objectives and scenario to ensure that the exercise would acceptably test major elements of the licensees emergency plan and to verify that the exercises simulated problems provided an acceptable framework to support demonstration of the licensees capability to implement its plan. The inspectors also reviewed records of two emergency preparedness drills, which were conducted in 2005 and 2006, to verify that those drills scenarios were sufficiently different from the scenario used in the August 8, 2006 exercise.
The inspectors evaluated the licensees exercise performance, focusing on the risk-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);
- Operations Support Center (OSC); and
- Emergency Operations Facility (EOF).
The inspectors also assessed the licensees recognition of abnormal plant conditions, transfer of responsibilities between facilities, internal communications, interfaces with offsite officials, readiness of emergency facilities and related equipment, and overall implementation of the licensees emergency plan.
The inspectors attended post-exercise critiques in the CRS, TSC, OSC, and EOF to evaluate the licensees initial self-assessment of its exercise performance. The inspectors later met with the licensees lead exercise evaluators to obtain the licensees refined assessments of its exercise participants performances. These self-assessments were then compared with the inspectors independent observations and assessments to assess the licensees ability to adequately critique its exercise performance.
These activities completed one inspection sample.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator (PI) Verification
Cornerstone: Emergency Preparedness
.1 Reactor Safety Strategic Area
a. Inspection Scope
The inspectors reviewed the licensees records associated with each of the three emergency preparedness PIs to verify that the licensees 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 Drill 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 PIs were reviewed:
Common
- DEP These activities completed three PI samples.
b. Findings
No findings of significance were identified.
4OA6 Meetings
.1 Exit Meeting
An exit meeting was conducted for:
- Emergency Preparedness with Mr. G. Boerschig and other members of licensee management and staff at the conclusion of the inspection on August 11, 2006.
The licensee acknowledged the information presented. No proprietary information was identified.
.2 Public and Media Briefing
- On August 11, 2006, an inspector summarized NRCs preliminary exercise inspection conclusions at a public and media briefing hosted by Department of Homeland Security Region V Field Office staff in Joliet, Illinois.
4OA7 Licensee Identified Violations
Cornerstone: Emergency Preparedness
The following violation of very low significance was identified by the licensee and is a violation of NRC requirements which met the criteria of Section VI of the NRC Enforcement 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 effect emergency 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 licensees implementation of the change to EAL HU-5 on January 17, 2006, decreased the effectiveness of the emergency plan without prior NRC approval, and consequently 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 licensees 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 Specialist
Illinois Emergency Management Agency
- M. Perry, Engineer
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened, Closed, and Discussed
None.
LIST OF DOCUMENTS REVIEWED
