|
|
| (5 intermediate revisions by the same user not shown) |
| Line 1: |
Line 1: |
| {{Adams|number = ML100990411}} | | {{Adams |
| | | number = ML100990411 |
| | | issue date = 04/08/2010 |
| | | title = IR 05000456-10-502, 05000457-10-502, on 03/22/2010 - 03/26/2010, Braidwood Station, Units 1 and 2, Baseline Emergency Preparedness Biennial Exercise Inspection |
| | | author name = Peterson H |
| | | author affiliation = NRC/RGN-III/DRS/OB |
| | | addressee name = Pardee C |
| | | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear |
| | | docket = 05000456, 05000457 |
| | | license number = NPF-072, NPF-077 |
| | | contact person = |
| | | document report number = IR-10-502 |
| | | document type = Inspection Report, Letter |
| | | page count = 11 |
| | }} |
|
| |
|
| {{IR-Nav| site = 05000456 | year = 2010 | report number = 502 }} | | {{IR-Nav| site = 05000456 | year = 2010 | report number = 502 }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION |
| [[Issue date::April 8, 2010]]
| |
|
| |
|
| Mr. Charles Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville IL 60555 | | ==REGION III== |
| | 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 April 8, 2010 Mr. Charles Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville IL 60555 SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2 BASELINE EMERGENCY PREPAREDNESS BIENNIAL EXERCISE INSPECTION REPORT 05000456/2010502(DRS); 05000457/2010502(DRS) |
|
| |
|
| SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2 BASELINE EMERGENCY PREPAREDNESS BIENNIAL EXERCISE INSPECTION REPORT 05000456/2010502(DRS); 05000457/2010502(DRS)
| | ==Dear Mr. Pardee:== |
| | On March 26, 2010, the U. S. Nuclear Regulatory Commission (NRC) completed a Baseline Emergency Preparedness Biennial Exercise inspection at your Braidwood Station, Units 1 and 2. The enclosed report documents the inspection results, which were discussed on March 26, 2010, with Mr. A. Shahkarami 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. |
|
| |
|
| ==Dear Mr. Pardee:==
| | Based on the results of this inspection, no NRC-identified and no self-revealed findings of very low safety significance were identified. |
| On March 26, 2010, the U. S. Nuclear Regulatory Commission (NRC) completed a Baseline Emergency Preparedness Biennial Exercise inspection at your Braidwood Station, Units 1 and 2. The enclosed report documents the inspection results, which were discussed on March 26, 2010, with Mr. A. Shahkarami 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. Based on the results of this inspection, no NRC-identified and no self-revealed findings of very low safety significance were identified. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be made 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).
| | |
| | In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs 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/ | | Sincerely, |
| Hironori Peterson, Chief Operations Branch Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77 | | /RA/ |
| | Hironori Peterson, Chief Operations Branch Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77 |
|
| |
|
| ===Enclosure:=== | | ===Enclosure:=== |
| Inspection Report 05000456/2010502; 05000457/2010502 | | Inspection Report 05000456/2010502; 05000457/2010502 w/Attachment: Supplemental Information |
|
| |
|
| ===w/Attachment:===
| | REGION III== |
| Supplemental Information cc w/encl: Distribution via ListServ U. S. NUCLEAR REGULATORY COMMISSION REGION III Docket Nos: 50-456; 50-457 License Nos: NPF-72; NPF-77 Report No: 05000456/2010502(DRS) and 05000457/2010502(DRS) Licensee: Exelon Generation Company, LLC Facility: Braidwood Station, Units 1 and 2 Location: Braceville, Illinois Dates: March 22 through 26, 2010 Inspectors: Robert Jickling, Senior Emergency Preparedness Inspector Regina Russell, Emergency Preparedness Inspector Raymond Walton, Senior Operations Engineer Approved by: Hironori Peterson, Chief Operations Branch Division of Reactor Safety Enclosure Enclosure
| | Docket Nos: 50-456; 50-457 License Nos: NPF-72; NPF-77 Report No: 05000456/2010502(DRS) and 05000457/2010502(DRS) |
| | Licensee: Exelon Generation Company, LLC Facility: Braidwood Station, Units 1 and 2 Location: Braceville, Illinois Dates: March 22 through 26, 2010 Inspectors: Robert Jickling, Senior Emergency Preparedness Inspector Regina Russell, Emergency Preparedness Inspector Raymond Walton, Senior Operations Engineer Approved by: Hironori Peterson, Chief Operations Branch Division of Reactor Safety Enclosure |
|
| |
|
| =SUMMARY OF FINDINGS= | | =SUMMARY OF FINDINGS= |
| IR 05000456/2010502, 05000457/2010502; 03/22/2010 - 03/26/2010; Braidwood Station, Units 1 and 2; Baseline Emergency Preparedness Biennial Exercise Inspection. This report covers a one week period of announced baseline inspection by two regional inspectors and one operations engineer. The significance of most findings is indicated by their color (Green, White, Yellow, Red) using Inspection Manual Chapter (IMC) 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 4, dated December 2006. | | IR 05000456/2010502, 05000457/2010502; 03/22/2010 - 03/26/2010; Braidwood Station, |
| | |
| | Units 1 and 2; Baseline Emergency Preparedness Biennial Exercise Inspection. |
| | |
| | This report covers a one week period of announced baseline inspection by two regional inspectors and one operations engineer. The significance of most findings is indicated by their color (Green, White, Yellow, Red) using Inspection Manual Chapter (IMC) 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 4, dated December 2006. |
|
| |
|
| ===A. NRC-Identified=== | | ===NRC-Identified=== |
| and Self-Revealed Findings | | and Self-Revealed Findings |
|
| |
|
| ===Cornerstone: Emergency Preparedness=== | | ===Cornerstone: Emergency Preparedness=== |
| | |
| No findings of significance were identified. | | No findings of significance were identified. |
|
| |
|
| ===B. Licensee-Identified Violations=== | | ===Licensee-Identified Violations=== |
| | |
| No violations of significance were identified. | | No violations of significance were identified. |
|
| |
|
| Line 39: |
Line 68: |
| ==REACTOR SAFETY== | | ==REACTOR SAFETY== |
|
| |
|
| ===Cornerstone:=== | | ===Cornerstone: Emergency Preparedness=== |
| Emergency Preparedness
| |
| {{a|1EP1}} | | {{a|1EP1}} |
| ==1EP1 Exercise Evaluation== | | ==1EP1 Exercise Evaluation== |
| Line 47: |
Line 75: |
|
| |
|
| ====a. Inspection Scope==== | | ====a. Inspection Scope==== |
| The inspectors reviewed the March 24, 2010, biennial emergency preparedness exercise'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 inspectors also reviewed records of other drills and exercises conducted in 2008, 2009, and 2010, to verify that those drills' scenarios were sufficiently different from the scenario used in the March 24, 2010, exercise. The inspectors evaluated the licensee's exercise performance, focusing on the risk significant activities of emergency classification, notification, and protective action decision making, implementation of accident mitigation strategies, and correction of past exercise weaknesses in the following emergency response facilities: Control Room Simulator (CRS); Technical Support Center (TSC); 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 with offsite officials, readiness of emergency facilities and related equipment, and overall implementation of the licensee's emergency plan. The inspectors attended post-exercise critiques in the CRS, TSC, and EOF to evaluate the licensee's initial self-assessment of its exercise performance. The inspectors later met with the licensee's lead exercise evaluators and managers to obtain the licensee's findings and 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 exercise performance. Documents reviewed are listed in the Attachment to this report. This exercise evaluation inspection constituted one sample as defined in Inspection Procedure (IP) 71114.01-05. | | The inspectors reviewed the March 24, 2010, 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 other drills and exercises conducted in 2008, 2009, and 2010, to verify that those drills scenarios were sufficiently different from the scenario used in the March 24, 2010, exercise. |
| | |
| | The inspectors evaluated the licensees exercise performance, focusing on the risk significant activities of emergency classification, notification, and protective action decision making, implementation of accident mitigation strategies, and correction of past exercise weaknesses in the following emergency response facilities: |
| | * Control Room Simulator (CRS); |
| | * Technical Support Center (TSC); 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, and EOF to evaluate the licensees initial self-assessment of its exercise performance. The inspectors later met with the licensees lead exercise evaluators and managers to obtain the licensees findings and 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. Documents reviewed are listed in the Attachment to this report. |
| | |
| | This exercise evaluation inspection constituted one sample as defined in Inspection Procedure (IP) 71114.01-05. |
|
| |
|
| ====b. Findings==== | | ====b. Findings==== |
| No findings of significance were identified.Enclosure 3 | | No findings of significance were identified. |
|
| |
|
| ==OTHER ACTIVITIES== | | ==OTHER ACTIVITIES== |
| Line 59: |
Line 98: |
|
| |
|
| ====a. Inspection Scope==== | | ====a. Inspection Scope==== |
| The inspectors sampled licensee submittals for the Drill/Exercise Performance PI for the period from the third quarter 2009 through fourth quarter 2009. To determine the accuracy of the PI data reported during those periods, PI definitions and guidance contained in the Nuclear Energy Institute (NEI) Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 6, were used. The inspectors reviewed the licensee's records associated with the performance indicator 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 drill/exercise performance sample as defined in IP 71151-05. | | The inspectors sampled licensee submittals for the Drill/Exercise Performance PI for the period from the third quarter 2009 through fourth quarter 2009. To determine the accuracy of the PI data reported during those periods, PI definitions and guidance contained in the Nuclear Energy Institute (NEI) Document 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 6, were used. The inspectors reviewed the licensees records associated with the performance indicator 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 to this report. |
| | |
| | This inspection constituted one drill/exercise performance sample as defined in IP 71151-05. |
|
| |
|
| ====b. Findings==== | | ====b. Findings==== |
| Line 67: |
Line 108: |
|
| |
|
| ====a. Inspection Scope==== | | ====a. Inspection Scope==== |
| The inspectors sampled licensee submittals for the Emergency Response Organization (ERO) Drill Participation PI for the period from the third quarter 2009 through fourth quarter 2009. To determine the accuracy of the PI data reported during those periods, PI definitions and guidance contained in the NEI Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 6, were 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 2009 exercises and drills; and revisions of the roster of personnel assigned to key emergency response organization 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. | | The inspectors sampled licensee submittals for the Emergency Response Organization (ERO) Drill Participation PI for the period from the third quarter 2009 through fourth quarter 2009. To determine the accuracy of the PI data reported during those periods, PI definitions and guidance contained in the NEI Document 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 6, were 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 2009 exercises and drills; and revisions of the roster of personnel assigned to key emergency response organization positions. Documents reviewed are listed in the to this report. |
| | |
| | This inspection constituted one ERO drill participation sample as defined in IP 71151-05. |
|
| |
|
| ====b. Findings==== | | ====b. Findings==== |
| No findings of significance were identified. Enclosure 4 5.3 Alert and Notification System | | No findings of significance were identified. |
| | |
| | ===.3 Alert and Notification System=== |
|
| |
|
| ====a. Inspection Scope==== | | ====a. Inspection Scope==== |
| The inspectors sampled licensee submittals for the Alert and Notification System (ANS) PI for the period from the third quarter 2009 through fourth quarter 2009. To determine the accuracy of the PI data reported during those periods, PI definitions and guidance contained in the NEI Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 6, were 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. This inspection constituted one alert and notification system sample as defined in IP 71151-05. | | The inspectors sampled licensee submittals for the Alert and Notification System (ANS) |
| | PI for the period from the third quarter 2009 through fourth quarter 2009. To determine the accuracy of the PI data reported during those periods, PI definitions and guidance contained in the NEI Document 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 6, were 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 alert and notification system sample as defined in IP 71151-05. |
|
| |
|
| ====b. Findings==== | | ====b. Findings==== |
| No findings of significance were identified. | | No findings of significance were identified. |
| {{a|4OA6}} | | {{a|4OA6}} |
| ==4OA6 Management Meetings== | | ==4OA6 Management Meetings== |
|
| |
|
| ===.1 Exit Meeting Summary On March 26, 2010, the inspectors presented the inspection results to Mr. A. Shahkirami, and other members of the licensee 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 March 26, 2010, the inspectors presented the inspection results to Mr. A. Shahkirami, and other members of the licensee staff. The licensee acknowledged the issues presented. The inspectors confirmed that none of the potential report input discussed was considered proprietary. |
| | |
| | ATTACHMENT: |
|
| |
|
| =SUPPLEMENTAL INFORMATION= | | =SUPPLEMENTAL INFORMATION= |
|
| |
|
| ==KEY POINTS OF CONTACT== | | ==KEY POINTS OF CONTACT== |
| Licensee | | |
| : [[contact::A. Shahkarami]], Site Vice President | | Licensee |
| : [[contact::K. Appel]], Corporate Emergency Preparedness Manager | | : [[contact::A. Shahkarami]], Site Vice President |
| : [[contact::S. Butler]], Emergency Preparedness Manager | | : [[contact::K. Appel]], Corporate Emergency Preparedness Manager |
| : [[contact::P. Daly]], Radiation Protection Manager | | : [[contact::S. Butler]], Emergency Preparedness Manager |
| : [[contact::R. Gaston]], Regulatory Assurance Manager | | : [[contact::P. Daly]], Radiation Protection Manager |
| : [[contact::J. Lizalek]], Nuclear Oversight | | : [[contact::R. Gaston]], Regulatory Assurance Manager |
| : [[contact::M. Marchionda]], Operations Director | | : [[contact::J. Lizalek]], Nuclear Oversight |
| : [[contact::T. Mattson]], NRC Coordinator | | : [[contact::M. Marchionda]], Operations Director |
| : [[contact::T. McCool]], Operations Manager | | : [[contact::T. Mattson]], NRC Coordinator |
| : [[contact::S. McKinney]], Emergency Preparedness Coordinator | | : [[contact::T. McCool]], Operations Manager |
| : [[contact::M. Smith]], Engineering Manager | | : [[contact::S. McKinney]], Emergency Preparedness Coordinator |
| : [[contact::W. Waznis]], Nuclear Oversight Nuclear Regulatory Commission | | : [[contact::M. Smith]], Engineering Manager |
| : [[contact::N. Shah]], Acting Senior Resident Inspector | | : [[contact::W. Waznis]], Nuclear Oversight |
| : [[contact::A. Garmoe]], Resident Inspector | | Nuclear Regulatory Commission |
| | : [[contact::N. Shah]], Acting Senior Resident Inspector |
| | : [[contact::A. Garmoe]], Resident Inspector |
| | |
| ==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== | | ==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== |
| Opened, Closed, and Discussed None
| |
|
| |
|
| 2
| | ===Opened, Closed, and Discussed=== |
| | |
| | None Attachment |
| | |
| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| The following is a list of documents reviewed during the inspection.
| | |
| : Inclusion on this list does not imply that the NRC inspectors reviewed the documents in their entirety, but rather, that selected sections of portions of the documents were evaluated as part of the overall inspection effort.
| |
| : Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report. 1EP1 Exercise Evaluation
| |
| : EP-AA-1001; Radiological Emergency Plan Annex for Braidwood; Revision 22
| |
| : EP-AA-112-100; Control Room Operations; Revision 9
| |
| : EP-AA-112-200; TSC Activation and Operation; Revision 7
| |
| : AR 01047918; Exercise:
| |
| : OSC Operator Dispatched without Briefing or Tracking; March 25, 2010
| |
| : AR 01047913; Exercise:
| |
| : TSC Dose Ass't Used Incorrect Conditions; March 25, 2010
| |
| : AR 01047898; Exercise:
| |
| : Initial Dose Ass't Air Sample Analysis Incorrect; March 25, 2010
| |
| : AR 01047890; Exercise:
| |
| : TSC Core Damage Ass't Objective Failure; March 25, 2010
| |
| : AR 01047653; Exercise:
| |
| : NOS Identified OSC Team Briefing Problems; March 25, 2010
| |
| : AR 01047638; Exercise:
| |
| : NOS Identified TSC Habitability Problems; March 25, 2010 4OA1 Performance Indicator Verification
| |
| : LS-AA-2110; Monthly Data Elements for NRC ERO Drill Participation; September - December 2009
| |
| : LS-AA-2120; Monthly Data Elements for NRC ERO Drill/Exercise Performance; July - December 2009
| |
| : LS-AA-2130; Monthly Data Elements for NRC Alert and Notification System Reliability; July - December 2009 Braidwood Monthly Siren Availability Report Records; July - December 2009
| |
| ==LIST OF ACRONYMS==
| |
| : [[USED]] [[]]
| |
| : [[ADAMS]] [[Agency-wide Documents Access and Management System]]
| |
| : [[ANS]] [[Alert and Notification System]]
| |
| CFR Code of Federal Regulations
| |
| CR Condition Report
| |
| CRS Control Room Simulator
| |
| : [[EOF]] [[Emergency Operations Facility]]
| |
| : [[EP]] [[Emergency Preparedness]]
| |
| : [[ERO]] [[Emergency Response Organization IMC Inspection Manual Chapter]]
| |
| : [[IP]] [[Inspection Procedure]]
| |
| : [[KI]] [[Potassium Iodide]]
| |
| : [[NEI]] [[Nuclear Energy Institute]]
| |
| : [[NRC]] [[]]
| |
| : [[U.]] [[S. Nuclear Regulatory Commission]]
| |
| OSC Operations Support Center
| |
| : [[PAR]] [[Protective Action Recommendation]]
| |
| : [[PA]] [[]]
| |
| : [[RS]] [[Publicly Available Records]]
| |
| : [[PI]] [[Performance Indicator]]
| |
| : [[SDP]] [[Significance Determination Process]]
| |
| : [[TI]] [[Temporary Instruction]]
| |
| : [[TSC]] [[Technical Support Center]]
| |
| : [[C.]] [[Pardee -2-]]
| |
| : [[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/
| |
| Hironori Peterson, Chief Operations Branch
| |
| Division of Reactor Safety Docket Nos. 50-456; 50-457
| |
| License Nos.
| |
| : [[NPF]] [[-72;]]
| |
| : [[NPF]] [[-77 Enclosure: Inspection Report 05000456/2010502; 05000457/2010502 w/Attachment: Supplemental Information cc w/encl: Distribution via ListServ]]
| |
| }} | | }} |
|
|---|
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 NUCLEAR REGULATORY COMMISSION
REGION III
2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 April 8, 2010 Mr. Charles Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville IL 60555 SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2 BASELINE EMERGENCY PREPAREDNESS BIENNIAL EXERCISE INSPECTION REPORT 05000456/2010502(DRS); 05000457/2010502(DRS)
Dear Mr. Pardee:
On March 26, 2010, the U. S. Nuclear Regulatory Commission (NRC) completed a Baseline Emergency Preparedness Biennial Exercise inspection at your Braidwood Station, Units 1 and 2. The enclosed report documents the inspection results, which were discussed on March 26, 2010, with Mr. A. Shahkarami 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.
Based on the results of this inspection, no NRC-identified and no self-revealed findings of very low safety significance were identified.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs 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/
Hironori Peterson, Chief Operations Branch Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77
Enclosure:
Inspection Report 05000456/2010502; 05000457/2010502 w/Attachment: Supplemental Information
REGION III==
Docket Nos: 50-456; 50-457 License Nos: NPF-72; NPF-77 Report No: 05000456/2010502(DRS) and 05000457/2010502(DRS)
Licensee: Exelon Generation Company, LLC Facility: Braidwood Station, Units 1 and 2 Location: Braceville, Illinois Dates: March 22 through 26, 2010 Inspectors: Robert Jickling, Senior Emergency Preparedness Inspector Regina Russell, Emergency Preparedness Inspector Raymond Walton, Senior Operations Engineer Approved by: Hironori Peterson, Chief Operations Branch Division of Reactor Safety Enclosure
SUMMARY OF FINDINGS
IR 05000456/2010502, 05000457/2010502; 03/22/2010 - 03/26/2010; Braidwood Station,
Units 1 and 2; Baseline Emergency Preparedness Biennial Exercise Inspection.
This report covers a one week period of announced baseline inspection by two regional inspectors and one operations engineer. The significance of most findings is indicated by their color (Green, White, Yellow, Red) using Inspection Manual Chapter (IMC) 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 4, dated December 2006.
NRC-Identified
and Self-Revealed Findings
Cornerstone: Emergency Preparedness
No findings of significance were identified.
Licensee-Identified Violations
No violations of significance were identified.
REPORT DETAILS
REACTOR SAFETY
Cornerstone: Emergency Preparedness
1EP1 Exercise Evaluation
Main article: IP 71114.01
.1 Exercise Evaluation
a. Inspection Scope
The inspectors reviewed the March 24, 2010, 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 other drills and exercises conducted in 2008, 2009, and 2010, to verify that those drills scenarios were sufficiently different from the scenario used in the March 24, 2010, exercise.
The inspectors evaluated the licensees exercise performance, focusing on the risk significant activities of emergency classification, notification, and protective action decision making, implementation of accident mitigation strategies, and correction of past exercise weaknesses in the following emergency response facilities:
- Control Room Simulator (CRS);
- 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, and EOF to evaluate the licensees initial self-assessment of its exercise performance. The inspectors later met with the licensees lead exercise evaluators and managers to obtain the licensees findings and 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. Documents reviewed are listed in the Attachment to this report.
This exercise evaluation inspection constituted one sample as defined in Inspection Procedure (IP) 71114.01-05.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator (PI) Verification
.1 Drill/Exercise Performance
a. Inspection Scope
The inspectors sampled licensee submittals for the Drill/Exercise Performance PI for the period from the third quarter 2009 through fourth quarter 2009. To determine the accuracy of the PI data reported during those periods, PI definitions and guidance contained in the Nuclear Energy Institute (NEI) Document 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 6, were used. The inspectors reviewed the licensees records associated with the performance indicator 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 to this report.
This inspection constituted one drill/exercise performance sample as defined in IP 71151-05.
b. Findings
No findings of significance were identified.
.2 Emergency Response Organization Drill Participation
a. Inspection Scope
The inspectors sampled licensee submittals for the Emergency Response Organization (ERO) Drill Participation PI for the period from the third quarter 2009 through fourth quarter 2009. To determine the accuracy of the PI data reported during those periods, PI definitions and guidance contained in the NEI Document 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 6, were 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 2009 exercises and drills; and revisions of the roster of personnel assigned to key emergency response organization positions. Documents reviewed are listed in the to this report.
This inspection constituted one ERO drill participation sample as defined in IP 71151-05.
b. Findings
No findings of significance 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 third quarter 2009 through fourth quarter 2009. To determine the accuracy of the PI data reported during those periods, PI definitions and guidance contained in the NEI Document 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 6, were 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 alert and notification system sample as defined in IP 71151-05.
b. Findings
No findings of significance were identified.
4OA6 Management Meetings
.1 Exit Meeting Summary
On March 26, 2010, the inspectors presented the inspection results to Mr. A. Shahkirami, and other members of the licensee 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
- A. Shahkarami, Site Vice President
- K. Appel, Corporate Emergency Preparedness Manager
- S. Butler, Emergency Preparedness Manager
- P. Daly, Radiation Protection Manager
- R. Gaston, Regulatory Assurance Manager
- J. Lizalek, Nuclear Oversight
- M. Marchionda, Operations Director
- T. Mattson, NRC Coordinator
- T. McCool, Operations Manager
- S. McKinney, Emergency Preparedness Coordinator
- M. Smith, Engineering Manager
- W. Waznis, Nuclear Oversight
Nuclear Regulatory Commission
- N. Shah, Acting Senior Resident Inspector
- A. Garmoe, Resident Inspector
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened, Closed, and Discussed
None Attachment
LIST OF DOCUMENTS REVIEWED
