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| | issue date = 12/18/2014 | | | issue date = 12/18/2014 |
| | title = IR 05000456/2014502, 05000457/2014502, on 11/17/2014 - 11/21/2014, Braidwood Station, Units 1 and 2, Baseline Emergency Preparedness Exercise Evaluation - Hostile Action Event, Exercise Evaluation Scenario Review; Performance Indicator Veri | | | title = IR 05000456/2014502, 05000457/2014502, on 11/17/2014 - 11/21/2014, Braidwood Station, Units 1 and 2, Baseline Emergency Preparedness Exercise Evaluation - Hostile Action Event, Exercise Evaluation Scenario Review; Performance Indicator Veri |
| | author name = Orth S K | | | author name = Orth S |
| | author affiliation = NRC/RGN-III/DRS/PSB | | | author affiliation = NRC/RGN-III/DRS/PSB |
| | addressee name = Pacilio M J | | | addressee name = Pacilio M |
| | 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:UNITED STATES mber 18, 2014 |
| [[Issue date::December 18, 2014]]
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| Mr. Michael Senior VP, Exelon Generation Co., LLC President and CNO, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
| | ==SUBJECT:== |
| | BRAIDWOOD STATION, UNITS 1 AND 2, BASELINE EMERGENCY PREPAREDNESS BIENNIAL EXERCISE INSPECTION REPORT 05000456/2014502; 05000457/2014502 |
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| SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2, BASELINE EMERGENCY PREPAREDNESS BIENNIAL EXERCISE INSPECTION REPORT 05000456/2014502; 05000457/2014502
| | ==Dear Mr. Pacilio:== |
| | On November 21, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Braidwood Station, Units 1 and 2. The enclosed report documents the results of this inspection which were discussed on November 21, 2014, with Mr. M. Kanavos and other members of your staff. |
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| | 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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| | The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. No findings were identified during this inspection. |
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| ==Dear Mr. Pacilio:==
| | In accordance with Title 10, Code of Federal Regulations (CFR), Section 2.390 of the NRC's |
| On November 21, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Braidwood Station, Units 1 and 2. The enclosed report documents the results of this inspection which were discussed on November 21, 2014, with Mr. M. Kanavos and other members of your staff. The inspection examined activities conducted under your license as they relate to safety and compliance 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. No findings were identified during this inspection. In accordance with Title 10, Code of Federal Regulations (CFR), Section 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any), will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
| | "Rules of Practice," a copy of this letter, its enclosure, and your response (if any), will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management 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/ | | Sincerely, |
| Steven K. Orth, Chief Plant Support Branch Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77 | | /RA/ |
| | Steven K. Orth, Chief Plant Support Branch Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77 |
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| ===Enclosure:=== | | ===Enclosure:=== |
| IR 05000456/2014502; 05000457/2014502 | | IR 05000456/2014502; 05000457/2014502 w/Attachment: Supplemental Information |
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| ===w/Attachment:===
| | REGION III== |
| Supplemental Information cc w/encl: Distribution via LISTSERV Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION III Docket No: 50-456; 50-457 License No: NPF-72; NPF-77 Report No: 05000456/2014502; 05000457/2014502 Licensee: Exelon Generation Company, LLC Facility: Braidwood Station, Units 1 and 2 Location: Braceville, IL Dates: November 17 through 21, 2014 Inspectors: R. Jickling, Senior Emergency Preparedness Inspector J. Benjamin, Senior Resident Inspector J. McGhee, Senior Resident Inspector J. Beavers, Emergency Preparedness Inspector D. Funk, Senior Project Specialist Approved by: S. Orth, Chief Plant Support Branch Division of Reactor Safety 2
| | Docket No: 50-456; 50-457 License No: NPF-72; NPF-77 Report No: 05000456/2014502; 05000457/2014502 Licensee: Exelon Generation Company, LLC Facility: Braidwood Station, Units 1 and 2 Location: Braceville, IL Dates: November 17 through 21, 2014 Inspectors: R. Jickling, Senior Emergency Preparedness Inspector J. Benjamin, Senior Resident Inspector J. McGhee, Senior Resident Inspector J. Beavers, Emergency Preparedness Inspector D. Funk, Senior Project Specialist Approved by: S. Orth, Chief Plant Support Branch Division of Reactor Safety Enclosure |
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| =SUMMARY OF FINDINGS= | | =SUMMARY OF FINDINGS= |
| IR 05000456/2014502, 05000457/2014502, 11/17/2014 - 11/21/2014, Braidwood Station, Units 1 and 2, Baseline Emergency Preparedness Exercise Evaluation - Hostile Action Event, Exercise Evaluation Scenario Review; Performance Indicator Verification. This report covers a 1-week period of announced baseline inspection by three regional inspectors and two resident inspectors. The significance of most findings is indicated by their color (i.e., Green, White, Yellow, and Red) using Inspection Manual Chapter 0609, "Significance Determination Process (SDP)." Findings for which the SDP does not apply may be Green or be assigned a severity level after NRC management review. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 5, dated February 2014. | | IR 05000456/2014502, 05000457/2014502, 11/17/2014 - 11/21/2014, Braidwood Station, Units and 2, Baseline Emergency Preparedness Exercise Evaluation - Hostile Action Event, |
| | Exercise Evaluation Scenario Review; Performance Indicator Verification. |
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| ===A. NRC-Identified===
| | This report covers a 1-week period of announced baseline inspection by three regional inspectors and two resident inspectors. The significance of most findings is indicated by their color (i.e., Green, White, Yellow, and Red) using Inspection Manual Chapter 0609, Significance Determination Process (SDP). Findings for which the SDP does not apply may be Green or be assigned a severity level after NRC management review. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 5, dated February 2014. |
| and Self-Revealed Findings
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| ===Cornerstone: Emergency Preparedness No findings were identified. | | ===NRC-Identified=== |
| | and Self-Revealed Findings |
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| ===B. Licensee-Identified Violations=== | | ===Cornerstone: Emergency Preparedness=== |
| None===
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| | No findings were identified. |
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| | ===Licensee-Identified Violations=== |
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| | None |
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| =REPORT DETAILS= | | =REPORT DETAILS= |
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| ==REACTOR SAFETY== | | ==REACTOR SAFETY== |
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| ===Cornerstone:=== | | ===Cornerstone: Emergency Preparedness=== |
| Emergency Preparedness
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| {{a|1EP7}} | | {{a|1EP7}} |
| ==1EP7 Exercise Evaluation - Hostile Action Event== | | ==1EP7 Exercise Evaluation - Hostile Action Event== |
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| ====a. Inspection Scope==== | | ====a. Inspection Scope==== |
| Title 10, Code of Federal Regulations (CFR), Part 50, Appendix E, Section IV.F.2.j, requires, in part, that nuclear power reactor licensees, in each eight calendar year exercise cycle, provide the opportunity for their Emergency Response Organization (ERO) to demonstrate proficiency in the key skills necessary to respond to a Hostile Action (HA) event directed at the plant site. Braidwood Station designed the November 19, 2014, exercise to satisfy this requirement, and the NRC inspected the Braidwood Station HA event exercise to assess the licensee's ability to effectively implement their Emergency Plan during a HA event and adequately protect public health and safety. The exercise evaluation consisted of the following reviews and assessments: The adequacy of the licensee's performance in the biennial exercise conducted on November 19, 2014, regarding the implementation of the Risk-Significant Planning Standards in 10 CFR 50.47 (b)(4), (5), (9), and (10), which address emergency classification, offsite notification, radiological assessment, and Protective Action Recommendations (PAR), respectively. The overall adequacy of the licensee's emergency response facilities with regard to NUREG-0696, "Functional Criteria for Emergency Response Facilities," and Emergency Plan commitments. The facilities assessed were the Control Room Simulator, Alternative Emergency Response Facility, Incident Command Post, Simulated Central Alarm Station, and the Emergency Operations Facility. A review of other performance areas such as the licensee ERO's recognition of abnormal plant conditions; command and control, including interactions with site security staff; intra and inter-facility communications; prioritization of mitigating activities; utilization of repair and field monitoring teams; interface with offsite agencies, including local law enforcement agencies; staffing and procedure adequacy; and the overall implementation of the Emergency Plan and its implementing procedures. Past performance issues from NRC inspection reports to determine the effectiveness of corrective actions, as demonstrated during this exercise, to ensure compliance with 10 CFR 50.47(b)(14). | | Title 10, Code of Federal Regulations (CFR), Part 50, Appendix E, Section IV.F.2.j, requires, in part, that nuclear power reactor licensees, in each eight calendar year exercise cycle, provide the opportunity for their Emergency Response Organization (ERO) to demonstrate proficiency in the key skills necessary to respond to a Hostile Action (HA) event directed at the plant site. Braidwood Station designed the November 19, 2014, exercise to satisfy this requirement, and the NRC inspected the Braidwood Station HA event exercise to assess the licensees ability to effectively implement their Emergency Plan during a HA event and adequately protect public health and safety. |
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| The adequacy of the licensee's post-exercise critiques, to evaluate Braidwood Station's self-assessment of its ERO performance during the November 19, 2014, exercise and to ensure compliance with 10 CFR Part 50, Appendix E, Section IV.F.2.g. The inspectors reviewed various documents that are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the exercise evaluation on a biennial basis. | | The exercise evaluation consisted of the following reviews and assessments: |
| | * The adequacy of the licensees performance in the biennial exercise conducted on November 19, 2014, regarding the implementation of the Risk-Significant Planning Standards in 10 CFR 50.47 (b)(4), (5), (9), and (10), which address emergency classification, offsite notification, radiological assessment, and Protective Action Recommendations (PAR), respectively. |
| | * The overall adequacy of the licensees emergency response facilities with regard to NUREG-0696, Functional Criteria for Emergency Response Facilities, and Emergency Plan commitments. The facilities assessed were the Control Room Simulator, Alternative Emergency Response Facility, Incident Command Post, Simulated Central Alarm Station, and the Emergency Operations Facility. |
| | * A review of other performance areas such as the licensee EROs recognition of abnormal plant conditions; command and control, including interactions with site security staff; intra and inter-facility communications; prioritization of mitigating activities; utilization of repair and field monitoring teams; interface with offsite agencies, including local law enforcement agencies; staffing and procedure adequacy; and the overall implementation of the Emergency Plan and its implementing procedures. |
| | * Past performance issues from NRC inspection reports to determine the effectiveness of corrective actions, as demonstrated during this exercise, to ensure compliance with 10 CFR 50.47(b)(14). |
| | * The adequacy of the licensees post-exercise critiques, to evaluate Braidwood Stations self-assessment of its ERO performance during the November 19, 2014, exercise and to ensure compliance with 10 CFR Part 50, Appendix E, Section IV.F.2.g. |
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| | The inspectors reviewed various documents that are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the exercise evaluation on a biennial basis. |
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| This exercise evaluation inspection constituted one sample as defined in Inspection Procedure (IP) 71114.07-06. | | This exercise evaluation inspection constituted one sample as defined in Inspection Procedure (IP) 71114.07-06. |
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| ====b. Findings==== | | ====b. Findings==== |
| No findings were identified. | | No findings were identified. {{a|1EP8}} |
| {{a|1EP8}} | |
| ==1EP8 Exercise Evaluation - Scenario Review== | | ==1EP8 Exercise Evaluation - Scenario Review== |
| {{IP sample|IP=IP 71114.08}} | | {{IP sample|IP=IP 71114.08}} |
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| ====a. Inspection Scope==== | | ====a. Inspection Scope==== |
| Prior to the inspection activity, the inspectors conducted an in-office review of the exercise objectives and scenarios submitted to the NRC using IP 71114.08, "Exercise Evaluation - Scenario Review," to determine if the exercise would test major elements of the Emergency Plan as required by 10 CFR 50.47(b)(14). This inspection activity represents one sample on a biennial cycle. The inspectors reviewed various documents that are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the exercise evaluation on a biennial basis. This review of the exercise objectives and scenario constituted one sample as defined in IP 71114.08-06. | | Prior to the inspection activity, the inspectors conducted an in-office review of the exercise objectives and scenarios submitted to the NRC using IP 71114.08, Exercise Evaluation - Scenario Review, to determine if the exercise would test major elements of the Emergency Plan as required by 10 CFR 50.47(b)(14). This inspection activity represents one sample on a biennial cycle. |
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| | The inspectors reviewed various documents that are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the exercise evaluation on a biennial basis. |
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| | This review of the exercise objectives and scenario constituted one sample as defined in IP 71114.08-06. |
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| ====b. Findings==== | | ====b. Findings==== |
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| ==OTHER ACTIVITIES== | | ==OTHER ACTIVITIES== |
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| ===Cornerstone:=== | | ===Cornerstone: Emergency Preparedness=== |
| Emergency Preparedness
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| {{a|4OA1}} | | {{a|4OA1}} |
| ==4OA1 Performance Indicator Verification== | | ==4OA1 Performance Indicator Verification== |
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| ====a. Inspection Scope==== | | ====a. Inspection Scope==== |
| The inspectors sampled licensee submittals for the Drill/Exercise Performance (DEP) Performance Indicator (PI) for the period from the first quarter 2013 through the third quarter 2014. To determine the accuracy of the DEP data reported during those periods, PI definitions and guidance contained in the Nuclear Energy Institute (NEI) document NEI 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7, was used. The inspectors reviewed the licensee's records associated with 5 the PI to verify that the licensee accurately reported the indicator in accordance with relevant procedures and the NEI guidance. Specifically, the inspectors reviewed licensee records and processes, including procedural guidance on assessing opportunities for the PI, assessments of PI opportunities during pre-designated control room simulator training sessions, and performance during other drills. Documents reviewed are listed in the Attachment to this report. This inspection constituted one DEP sample as defined in IP 71151-05. | | The inspectors sampled licensee submittals for the Drill/Exercise Performance (DEP) |
| | Performance Indicator (PI) for the period from the first quarter 2013 through the third quarter 2014. To determine the accuracy of the DEP data reported during those periods, PI definitions and guidance contained in the Nuclear Energy Institute (NEI)document NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7, was used. The inspectors reviewed the licensees records associated with the PI to verify that the licensee accurately reported the indicator in accordance with relevant procedures and the NEI guidance. Specifically, the inspectors reviewed licensee records and processes, including procedural guidance on assessing opportunities for the PI, assessments of PI opportunities during pre-designated control room simulator training sessions, and performance during other drills. Documents reviewed are listed in the Attachment to this report. |
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| | This inspection constituted one DEP sample as defined in IP 71151-05. |
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| ====b. Findings==== | | ====b. Findings==== |
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| ====a. Inspection Scope==== | | ====a. Inspection Scope==== |
| The inspectors sampled licensee submittals for the ERO Drill Participation PI for the period from the first quarter 2013 through the third quarter 2014. To determine the accuracy of the PI data reported during those periods, PI definitions and guidance contained in NEI 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7, was used. The inspectors reviewed the licensee's records associated with the PI to verify that the licensee accurately reported the indicator in accordance with relevant procedures and the NEI guidance. Specifically, the inspectors reviewed licensee records and processes including procedural guidance on assessing opportunities for the PI, performance during the 2013 and 2014 drills, and revisions of the roster of personnel assigned to key ERO positions. Documents reviewed are listed in the Attachment to this report. | | The inspectors sampled licensee submittals for the ERO Drill Participation PI for the period from the first quarter 2013 through the third quarter 2014. To determine the accuracy of the PI data reported during those periods, PI definitions and guidance contained in NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7, was used. The inspectors reviewed the licensees records associated with the PI to verify that the licensee accurately reported the indicator in accordance with relevant procedures and the NEI guidance. Specifically, the inspectors reviewed licensee records and processes including procedural guidance on assessing opportunities for the PI, performance during the 2013 and 2014 drills, and revisions of the roster of personnel assigned to key ERO positions. Documents reviewed are listed in the Attachment to this report. |
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| This inspection constituted one ERO Drill Participation sample as defined in IP 71151-05. | | This inspection constituted one ERO Drill Participation sample as defined in IP 71151-05. |
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| ====a. Inspection Scope==== | | ====a. Inspection Scope==== |
| The inspectors sampled licensee submittals for the Alert and Notification System (ANS) PI for the period from the first quarter 2013 through the third quarter 2014. To determine the accuracy of the PI data reported during those periods, PI definitions and guidance contained in NEI 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7, was used. The inspectors reviewed the licensee's records associated with the PI to verify that the licensee accurately reported the indicator in accordance with relevant procedures and the NEI guidance. Specifically, the inspectors reviewed licensee records and processes including procedural guidance on assessing opportunities for the PI and results of periodic scheduled ANS operability tests. Documents reviewed are listed in the Attachment to this report. | | The inspectors sampled licensee submittals for the Alert and Notification System (ANS) |
| | PI for the period from the first quarter 2013 through the third quarter 2014. To determine the accuracy of the PI data reported during those periods, PI definitions and guidance contained in NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7, was used. The inspectors reviewed the licensees records associated with the PI to verify that the licensee accurately reported the indicator in accordance with relevant procedures and the NEI guidance. Specifically, the inspectors reviewed licensee records and processes including procedural guidance on assessing opportunities for the PI and results of periodic scheduled ANS operability tests. |
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| | Documents reviewed are listed in the Attachment to this report. |
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| This inspection constituted one ANS sample as defined in IP 71151-05. | | This inspection constituted one ANS sample as defined in IP 71151-05. |
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| ====b. Findings==== | | ====b. Findings==== |
| No findings were identified. | | No findings were identified. |
| {{a|4OA6}} | | {{a|4OA6}} |
| ==4OA6 Management Meetings== | | ==4OA6 Management Meetings== |
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| ===.1 Exit Meeting Summary On November 21, 2014, the inspectors presented the biennial exercise inspection results to Mr. M. Kanavos and other members of the licensee's staff.=== | | ===.1 Exit Meeting Summary=== |
| The licensee acknowledged the issues presented. The inspectors confirmed that none of the potential report input discussed was considered proprietary. ATTACHMENT: | | |
| | On November 21, 2014, the inspectors presented the biennial exercise inspection results to Mr. M. Kanavos and other members of the licensees staff. The licensee acknowledged the issues presented. |
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| | The inspectors confirmed that none of the potential report input discussed was considered proprietary. |
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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== |
| Licensee | | |
| : [[contact::M. Kanavos]], Site Vice President | | Licensee |
| : [[contact::M. Marchionda]], Plant Manager | | : [[contact::M. Kanavos]], Site Vice President |
| : [[contact::J. Bashor]], Engineering Manager | | : [[contact::M. Marchionda]], Plant Manager |
| : [[contact::B. Bergman]], Outage Manager | | : [[contact::J. Bashor]], Engineering Manager |
| : [[contact::J. Cady]], Radiation Protection Manager | | : [[contact::B. Bergman]], Outage Manager |
| : [[contact::A. Daniels]], MidWest Emergency Preparedness Manager | | : [[contact::J. Cady]], Radiation Protection Manager |
| : [[contact::T. Elam]], Projects | | : [[contact::A. Daniels]], MidWest Emergency Preparedness Manager |
| : [[contact::A. Ferko]], Operations Manager | | : [[contact::T. Elam]], Projects |
| : [[contact::T. Fisk]], Nuclear Oversight | | : [[contact::A. Ferko]], Operations Manager |
| : [[contact::T. Gardner]], Nuclear Oversight Assessor | | : [[contact::T. Fisk]], Nuclear Oversight |
| : [[contact::C. Ingold]], Site Chemical Environment & Radwaste Manager | | : [[contact::T. Gardner]], Nuclear Oversight Assessor |
| : [[contact::J. Lizalek]], Security | | : [[contact::C. Ingold]], Site Chemical Environment & Radwaste Manager |
| : [[contact::S. McKinney]], Emergency Preparedness Coordinator | | : [[contact::J. Lizalek]], Security |
| : [[contact::D. Poi]], Emergency Preparedness Manager | | : [[contact::S. McKinney]], Emergency Preparedness Coordinator |
| : [[contact::P. Raush]], Regulatory Assurance Manager | | : [[contact::D. Poi]], Emergency Preparedness Manager |
| : [[contact::R. Schlessmann]], Regulatory Assurance | | : [[contact::P. Raush]], Regulatory Assurance Manager |
| : [[contact::B. Sparr]], Maintenance Director | | : [[contact::R. Schlessmann]], Regulatory Assurance |
| : [[contact::D. Stiles]], Site Training Director Nuclear Regulatory Commission | | : [[contact::B. Sparr]], Maintenance Director |
| : [[contact::J. Benjamin]], Senior Resident Inspector | | : [[contact::D. Stiles]], Site Training Director |
| : [[contact::B. Boston]], Acting Resident Inspector | | Nuclear Regulatory Commission |
| | : [[contact::J. Benjamin]], Senior Resident Inspector |
| | : [[contact::B. Boston]], Acting Resident Inspector |
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| ==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== | | ==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== |
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| ===Opened, Closed, and Discussed=== | | ===Opened, Closed, and Discussed=== |
| None | | |
| | None |
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| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| The following is a partial list of documents reviewed during the inspection.
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| : Inclusion on this list does not imply that the NRC inspectors reviewed the documents in their entirety, but rather that selected sections or portions of the documents were evaluated as part of the overall inspection effort.
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| : Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report.
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| : 1EP7 Exercise Evaluation (71114.07)
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| : EP-AA-1000; Exelon Nuclear Standardized Radiological Emergency Plan; Revision 25
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| : EP-AA-1001; Radiological Emergency Plan Annex for Braidwood Station; Revision 32
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| : EP-AA-110; Assessment of Emergencies; Revision 9
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| : EP-AA-111; Emergency Classification and PARs; Revision 18
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| : EP-AA-112; ERO/ERF Activation and Operation; Revision 16
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| : EP-AA-113; Personnel Protective Action; Revision 11
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| : EP-AA-114-100; Midwest Region Offsite Notifications; Revision 14
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| : EP-AA-122; Drills and Exercise Program; Revision 15 0Bw0A; Security Threat; Revision 17 Two Year List of Drill and Exercise Corrective Action Program Issues; December 5, 2012 - August 29, 2014 Two Years of Drill and Exercise Timelines; December 5, 2012 - August 27, 2014
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| : IR 2416846.2; Exercise-Alternate ERF Confusion Regarding Multiple Priority Ones; November 24, 2014
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| : IR 2416846.4; Exercise-Alternative ERF Determined Cell Phone Communications With Mitigation Teams Was Not Adequate In the Plant; November 24, 2014
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| : IR 2416839; Exercise-Alternative ERF Mitigation Team Movement On-Site Did Not Adhere to Restrictions; November 24, 2014
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| : IR 2415811; Exercise-Over-Simulation Contributed to Confusion With Mitigation Team Status Communications; November 21, 2014
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| : IR 2415803; Exercise-Mitigative Action Planning at the ICP and Alternative ERF Needs to be Improved and Alternative ERF Communications With ICP and Mitigation Teams Needs to be Improved; November 21, 2014
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| : IR 2415733.1; Exercise-EOF Failed to Notify the NRC Within One Hour of the Emergency Classification; November 21, 2014
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| : IR 2415733.2; Exercise-EOF Significant Events Log Lacked Information and Contained Errors; November 21, 2014
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| : IR 2415733.3; Exercise-EOF Top Priorities Not Established But Had Three Priority Ones; November 21, 2014
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| : 1EP8 Exercise Evaluation - Scenario Review (71114.08) Braidwood Station 2014 HAB Exercise 60 Day Submittal; September 15, 2014 4OA1 Performance Indicator Verification (71151)
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| : LS-AA-2110; Monthly Data Elements for NRC ERO Drill Participation; January 2013 - September 2014
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| : LS-AA-2120; Monthly Data Elements for NRC Drill/Exercise Performance; March 2013 - September 2014
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| : LS-AA-2130; Monthly Data Elements for NRC ANS Reliability; January 2013 - September 2014
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| : AR 01678496; Siren Failure; July 3, 2014
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| : AR 01678295; Siren Failures; July 2, 2014
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| : AR 01677436; Siren Outage; July 1, 2014
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| ==LIST OF ACRONYMS==
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| : [[USED]] [[]]
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| : [[ADAMS]] [[Agencywide Documents Access and Management System]]
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| : [[ANS]] [[Alert and Notification System]]
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| : [[CFR]] [[Code of Federal Regulations]]
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| : [[DEP]] [[Drill and Exercise Performance]]
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| : [[DRS]] [[Division of Reactor Safety]]
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| : [[ERO]] [[Emergency Response Organization]]
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| : [[HA]] [[Hostile Action]]
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| : [[IP]] [[Inspection Procedure]]
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| : [[NEI]] [[Nuclear Energy Institute]]
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| : [[NRC]] [[U.S. Nuclear Regulatory Commission]]
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| : [[PAR]] [[Protective Action Recommendation]]
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| : [[PARS]] [[Publicly Available Records System]]
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| PI Performance Indicator SDP Significance Determination Process
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| Mr. Michael
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| : [[J.]] [[Pacilio Senior]]
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| : [[VP]] [[, Exelon Generation Co.,]]
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| : [[LLC]] [[President and]]
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| : [[CNO]] [[, Exelon Nuclear 4300 Winfield Road Warrenville,]]
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| : [[IL]] [[60555]]
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| : [[SUBJEC]] [[T: BRAIDWOOD STATION,]]
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| : [[UNITS]] [[1]]
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| : [[AND]] [[2, BASELINE EMERGENCY PREPAREDNESS BIENNIAL EXERCISE INSPECTION]]
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| : [[REPORT]] [[05000456/2014502; 05000457/2014502 Dear Mr. Pacilio: On November 21, 2014, the U.S. Nuclear Regulatory Commission (]]
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| : [[NRC]] [[) completed an inspection at your Braidwood Station, Units 1 and 2. The enclosed report documents the results of this inspection which were discussed on November 21, 2014, with Mr.]]
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| : [[M.]] [[Kanavos and other members of your staff. The inspection examined activities conducted under your license as they relate to safety and compliance 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. No findings were identified during this inspection. In accordance with Title 10, Code of Federal Regulations (]]
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| : [[CFR]] [[), Section 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any), will be available electronically for public inspection in the]]
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| : [[NRC]] [[Public Document Room or from the Publicly Available Records System (]]
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| : [[PARS]] [[) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the]]
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| : [[NRC]] [[Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Sincerely, /]]
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| : [[RA]] [[/ Steven]]
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| : [[K.]] [[Orth, Chief Plant Support Branch Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos.]]
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| : [[NPF]] [[-72; NPF-77 Enclosure:]]
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| : [[IR]] [[05000456/2014502; 05000457/2014502 w/Attachment: Supplemental Information cc w/encl: Distribution via]]
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| : [[LISTSE]] [[RV DOCUMENT NAME:]]
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| : [[BRA]] [[2014 502 (]]
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| : [[RDJ]] [[).docx Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy]]
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| : [[OFFICE]] [[]]
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| : [[RIII]] [[]]
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| : [[RIII]] [[]]
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| : [[RIII]] [[]]
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| : [[RIII]] [[]]
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| : [[NAME]] [[RJickling:ls DFunk SOrth]]
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| : [[DATE]] [[12/17/14 12/18/14 12/18/14]]
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| : [[OFFICI]] [[AL]]
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| : [[RECORD]] [[]]
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| : [[COPY]] [[Letter to Michael]]
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| : [[J.]] [[Pacilio from Steven K. Orth dated December 18, 2014.]]
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| : [[SUBJEC]] [[T: BRAIDWOOD STATION,]]
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| : [[UNITS]] [[1]]
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| : [[AND]] [[2,]]
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| : [[UNITS]] [[1]]
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| : [[AND]] [[2 BASELINE EMERGENCY PREPAREDNESS BIENNIAL EXERCISE INSPECTION REPORT 05000456/2014502; 05000457/2014502]]
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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
UNITED STATES mber 18, 2014
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2, BASELINE EMERGENCY PREPAREDNESS BIENNIAL EXERCISE INSPECTION REPORT 05000456/2014502; 05000457/2014502
Dear Mr. Pacilio:
On November 21, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Braidwood Station, Units 1 and 2. The enclosed report documents the results of this inspection which were discussed on November 21, 2014, with Mr. M. Kanavos 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. No findings were identified during this inspection.
In accordance with Title 10, Code of Federal Regulations (CFR), Section 2.390 of the NRC's
"Rules of Practice," a copy of this letter, its enclosure, and your response (if any), will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Steven K. Orth, Chief Plant Support Branch Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77
Enclosure:
IR 05000456/2014502; 05000457/2014502 w/Attachment: Supplemental Information
REGION III==
Docket No: 50-456; 50-457 License No: NPF-72; NPF-77 Report No: 05000456/2014502; 05000457/2014502 Licensee: Exelon Generation Company, LLC Facility: Braidwood Station, Units 1 and 2 Location: Braceville, IL Dates: November 17 through 21, 2014 Inspectors: R. Jickling, Senior Emergency Preparedness Inspector J. Benjamin, Senior Resident Inspector J. McGhee, Senior Resident Inspector J. Beavers, Emergency Preparedness Inspector D. Funk, Senior Project Specialist Approved by: S. Orth, Chief Plant Support Branch Division of Reactor Safety Enclosure
SUMMARY OF FINDINGS
IR 05000456/2014502, 05000457/2014502, 11/17/2014 - 11/21/2014, Braidwood Station, Units and 2, Baseline Emergency Preparedness Exercise Evaluation - Hostile Action Event,
Exercise Evaluation Scenario Review; Performance Indicator Verification.
This report covers a 1-week period of announced baseline inspection by three regional inspectors and two resident inspectors. The significance of most findings is indicated by their color (i.e., Green, White, Yellow, and Red) using Inspection Manual Chapter 0609, Significance Determination Process (SDP). Findings for which the SDP does not apply may be Green or be assigned a severity level after NRC management review. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 5, dated February 2014.
NRC-Identified
and Self-Revealed Findings
Cornerstone: Emergency Preparedness
No findings were identified.
Licensee-Identified Violations
None
REPORT DETAILS
REACTOR SAFETY
Cornerstone: Emergency Preparedness
1EP7 Exercise Evaluation - Hostile Action Event
Main article: IP 71114.07
.1 Exercise Evaluation
a. Inspection Scope
Title 10, Code of Federal Regulations (CFR), Part 50, Appendix E,Section IV.F.2.j, requires, in part, that nuclear power reactor licensees, in each eight calendar year exercise cycle, provide the opportunity for their Emergency Response Organization (ERO) to demonstrate proficiency in the key skills necessary to respond to a Hostile Action (HA) event directed at the plant site. Braidwood Station designed the November 19, 2014, exercise to satisfy this requirement, and the NRC inspected the Braidwood Station HA event exercise to assess the licensees ability to effectively implement their Emergency Plan during a HA event and adequately protect public health and safety.
The exercise evaluation consisted of the following reviews and assessments:
- The adequacy of the licensees performance in the biennial exercise conducted on November 19, 2014, regarding the implementation of the Risk-Significant Planning Standards in 10 CFR 50.47 (b)(4), (5), (9), and (10), which address emergency classification, offsite notification, radiological assessment, and Protective Action Recommendations (PAR), respectively.
- The overall adequacy of the licensees emergency response facilities with regard to NUREG-0696, Functional Criteria for Emergency Response Facilities, and Emergency Plan commitments. The facilities assessed were the Control Room Simulator, Alternative Emergency Response Facility, Incident Command Post, Simulated Central Alarm Station, and the Emergency Operations Facility.
- A review of other performance areas such as the licensee EROs recognition of abnormal plant conditions; command and control, including interactions with site security staff; intra and inter-facility communications; prioritization of mitigating activities; utilization of repair and field monitoring teams; interface with offsite agencies, including local law enforcement agencies; staffing and procedure adequacy; and the overall implementation of the Emergency Plan and its implementing procedures.
- Past performance issues from NRC inspection reports to determine the effectiveness of corrective actions, as demonstrated during this exercise, to ensure compliance with 10 CFR 50.47(b)(14).
- The adequacy of the licensees post-exercise critiques, to evaluate Braidwood Stations self-assessment of its ERO performance during the November 19, 2014, exercise and to ensure compliance with 10 CFR Part 50, Appendix E, Section IV.F.2.g.
The inspectors reviewed various documents that are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the exercise evaluation on a biennial basis.
This exercise evaluation inspection constituted one sample as defined in Inspection Procedure (IP) 71114.07-06.
b. Findings
No findings were identified.
1EP8 Exercise Evaluation - Scenario Review
Main article: IP 71114.08
a. Inspection Scope
Prior to the inspection activity, the inspectors conducted an in-office review of the exercise objectives and scenarios submitted to the NRC using IP 71114.08, Exercise Evaluation - Scenario Review, to determine if the exercise would test major elements of the Emergency Plan as required by 10 CFR 50.47(b)(14). This inspection activity represents one sample on a biennial cycle.
The inspectors reviewed various documents that are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the exercise evaluation on a biennial basis.
This review of the exercise objectives and scenario constituted one sample as defined in IP 71114.08-06.
b. Findings
No findings were identified.
OTHER ACTIVITIES
Cornerstone: Emergency Preparedness
4OA1 Performance Indicator Verification
.1 Drill/Exercise Performance
a. Inspection Scope
The inspectors sampled licensee submittals for the Drill/Exercise Performance (DEP)
Performance Indicator (PI) for the period from the first quarter 2013 through the third quarter 2014. To determine the accuracy of the DEP data reported during those periods, PI definitions and guidance contained in the Nuclear Energy Institute (NEI)document NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7, was used. The inspectors reviewed the licensees records associated with the PI to verify that the licensee accurately reported the indicator in accordance with relevant procedures and the NEI guidance. Specifically, the inspectors reviewed licensee records and processes, including procedural guidance on assessing opportunities for the PI, assessments of PI opportunities during pre-designated control room simulator training sessions, and performance during other drills. Documents reviewed are listed in the Attachment to this report.
This inspection constituted one DEP sample as defined in IP 71151-05.
b. Findings
No findings were identified.
.2 Emergency Response Organization Drill Participation
a. Inspection Scope
The inspectors sampled licensee submittals for the ERO Drill Participation PI for the period from the first quarter 2013 through the third quarter 2014. To determine the accuracy of the PI data reported during those periods, PI definitions and guidance contained in NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7, was used. The inspectors reviewed the licensees records associated with the PI to verify that the licensee accurately reported the indicator in accordance with relevant procedures and the NEI guidance. Specifically, the inspectors reviewed licensee records and processes including procedural guidance on assessing opportunities for the PI, performance during the 2013 and 2014 drills, and revisions of the roster of personnel assigned to key ERO positions. Documents reviewed are listed in the Attachment to this report.
This inspection constituted one ERO Drill Participation sample as defined in IP 71151-05.
b. Findings
No findings were identified.
.3 Alert and Notification System
a. Inspection Scope
The inspectors sampled licensee submittals for the Alert and Notification System (ANS)
PI for the period from the first quarter 2013 through the third quarter 2014. To determine the accuracy of the PI data reported during those periods, PI definitions and guidance contained in NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7, was used. The inspectors reviewed the licensees records associated with the PI to verify that the licensee accurately reported the indicator in accordance with relevant procedures and the NEI guidance. Specifically, the inspectors reviewed licensee records and processes including procedural guidance on assessing opportunities for the PI and results of periodic scheduled ANS operability tests.
Documents reviewed are listed in the Attachment to this report.
This inspection constituted one ANS sample as defined in IP 71151-05.
b. Findings
No findings were identified.
4OA6 Management Meetings
.1 Exit Meeting Summary
On November 21, 2014, the inspectors presented the biennial exercise inspection results to Mr. M. Kanavos and other members of the licensees staff. The licensee acknowledged the issues presented.
The inspectors confirmed that none of the potential report input discussed was considered proprietary.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- M. Kanavos, Site Vice President
- M. Marchionda, Plant Manager
- J. Bashor, Engineering Manager
- B. Bergman, Outage Manager
- J. Cady, Radiation Protection Manager
- A. Daniels, MidWest Emergency Preparedness Manager
- T. Elam, Projects
- A. Ferko, Operations Manager
- T. Fisk, Nuclear Oversight
- T. Gardner, Nuclear Oversight Assessor
- C. Ingold, Site Chemical Environment & Radwaste Manager
- J. Lizalek, Security
- S. McKinney, Emergency Preparedness Coordinator
- D. Poi, Emergency Preparedness Manager
- P. Raush, Regulatory Assurance Manager
- R. Schlessmann, Regulatory Assurance
- B. Sparr, Maintenance Director
- D. Stiles, Site Training Director
Nuclear Regulatory Commission
- J. Benjamin, Senior Resident Inspector
- B. Boston, Acting Resident Inspector
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened, Closed, and Discussed
None
LIST OF DOCUMENTS REVIEWED