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Category:Inspection Report
MONTHYEARIR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 ML24123A2012024-05-0202 May 2024 NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information IR 05000260/20244012024-04-10010 April 2024 Security Baseline Inspection Report 05000260/2024401 and 05000260/2024401 and 05000296/2024401 IR 05000259/20230062024-02-28028 February 2024 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1, 2 - Report 05000259/2023006, 05000260/2023006 and 05000296/2023006 IR 05000259/20230042024-02-0606 February 2024 Integrated Inspection Report 05000259/2023004; 05000260/2023004 and 05000296/2023004 IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter IR 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 IR 05000259/20234022023-06-12012 June 2023 Material Control and Accounting Program Inspection Report 05000259 2023402, 05000260 2023402 and 05000296 2023402 IR 05000259/20230912023-05-0808 May 2023 Final Significance Determination of a White Finding and Nov and Assessment Followup Letter; NRC Inspection Report 05000259/2023091 IR 05000259/20230012023-05-0303 May 2023 Integrated Inspection Report 05000259/2023001, 05000260/2023001 and 05000296/2023001 IR 05000259/20234402023-03-23023 March 2023 Special Inspection Supplemental Report 05000259 2023440 and 05000260 2023440 and 05000296 2023440 Cover Letter IR 05000259/20234012023-03-0808 March 2023 Security Baseline Inspection Report 05000259 2023401 and 05000260/2023401 and 05000296/2023401 IR 05000259/20230902023-03-0202 March 2023 NRC Inspection Report 05000259/2023090 and 05000260 2023090 and Preliminary White Finding and Apparent Violation IR 05000259/20220062023-03-0101 March 2023 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 Report 05000259/2022006, 05000260/2022006 and 05000296/2022006 IR 05000259/20220042023-02-0707 February 2023 Integrated Inspection Report 05000259/2022004, 05000260/2022004 and 05000296/2022004 IR 05000259/20220032022-11-0909 November 2022 Browns Perry Nuclear Plant - Integrated Inspection Report 05000259/2022003, 05000260/2022003 and 05000296/2022003 IR 05000259/20220122022-09-20020 September 2022 Biennial Problem Identification and Resolution Inspection Report 05000259 2022012, 05000260 2022012 and 05000296 2022012 IR 05000259/20220112022-09-16016 September 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000259/2022011 and 05000260/2022011 and 05000296/2022011 IR 05000259/20224022022-09-0606 September 2022 Security Baseline Inspection Report 05000259/2022402 and 05000260/2022402 and 05000296/2022402 Cover Letter IR 05000259/20220052022-08-30030 August 2022 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 Report 05000259/2022005, 05000260/2022005 and 05000296/2022005 IR 05000259/20220022022-08-0808 August 2022 Integrated Inspection Report 05000259/2022002, 05000260/2022002 and 05000296/2022002 IR 05000259/20224202022-07-19019 July 2022 Security Baseline Inspection Report 05000259/2022420, 05000260/2022420 and 05000296/2022420 ML22181A9562022-06-29029 June 2022 Bf Report 2022-401 Base Public Cover Letter ML22173A1622022-06-21021 June 2022 Replacement Steam Dryer Visual Inspection Results (U3R20) IR 05000259/20220012022-05-12012 May 2022 Integrated Inspection Report 05000259/2022001, 05000260/2022001, 05000296/2022001 and Exercise of Enforcement Discretion IR 05000259/20220102022-03-30030 March 2022 Triennial Fire Protection Inspection Report 05000259/2022010 and 05000260/2022010 and 05000296/2022010 and Apparent Violation IR 05000259/20224012022-03-0808 March 2022 Information Request for the Cyber-Security Baseline Inspection Notification to Perform Inspection 05000259/2022401; 05000260/2022401; 05000296/2022401 IR 05000259/20210062022-03-0202 March 2022 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 (Report No. 05000259/2021006, 05000260/2021006 and 05000296/2021006 IR 05000259/20210042022-01-31031 January 2022 Integrated Inspection Report 05000259/2021004, 05000260/2021004 and 05000296/2021004 IR 05000259/20214032022-01-19019 January 2022 NRC Inspection Report 05000259/2021403, 05000260/2021403 and 05000296/2021403 IR 05000259/20214022022-01-18018 January 2022 Brows Ferry Nuclear Plant - Security Baseline Inspection Report 05000259/2021402 and 05000260/2021402 and 05000296/2021402 IR 05000259/20210032021-11-0909 November 2021 Integrated Inspection Report 05000259/2021003, 05000260/2021003, 05000296/2021003 and 07200052/2021001 IR 05000259/20214012021-08-31031 August 2021 Security Baseline Inspection Report 05000259/2021401 and 05000260/2021401 and 05000296/2021401 IR 05000259/20210112021-08-24024 August 2021 Temporary Instruction 2515/TI-193 Inspection Report 05000259/2021011, 05000260/2021011, and 05000296/2021011 IR 05000259/20210052021-08-23023 August 2021 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2, and 3- Report Nos. 05000259/2021005, 05000260/2021005 and 5000296/2021005 ML21217A2832021-08-0505 August 2021 Resident Integrated Inspection Report 2021-002 IR 05000259/20213012021-07-28028 July 2021 NRC Operator License Examination Report Nos. 05000259/2021301, 05000260/2021301, 05000296/2021301 IR 05000259/20210102021-07-26026 July 2021 Design Basis Assurance Inspection (Teams) Inspection Report 05000259/2021010 and 05000260/2021010 and 05000296/2021010 IR 05000259/20204012021-05-26026 May 2021 Security Baseline Inspection Report 05000259/2020401 and 05000260/2020401 and 05000296/2020401(U) IR 05000259/20210012021-04-28028 April 2021 Integrated Inspection Report 05000259/2021001, 05000260/2021001 and 05000296/2021001 2024-09-03
[Table view] Category:Letter
MONTHYEARML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) ML24190A1292024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints ML24185A1512024-07-0303 July 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure ML24184A1142024-07-0202 July 2024 Site Emergency Plan Implementing Procedure Revision ML24183A3842024-07-0101 July 2024 Registration of Use of Cask to Store Spent Fuel (MPC-364, -365) ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) ML24176A1022024-06-24024 June 2024 Reactor Scram Due to Generator Step-Up Transformer Failure ML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 ML24141A2462024-05-20020 May 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24123A2012024-05-0202 May 2024 NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information ML24122A6852024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual CNL-24-036, – 10 CFR 50.46 Annual Report2024-04-25025 April 2024 – 10 CFR 50.46 Annual Report ML24116A2522024-04-25025 April 2024 Site Emergency Plan Implementing Procedure Revision ML24115A1652024-04-24024 April 2024 Breaker Trip Automatically Started an Emergency Diesel Generator 05000296/LER-2024-001, Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup2024-04-22022 April 2024 Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A2302024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24108A1832024-04-17017 April 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update ML24106A2572024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Yahola, Kialegee Tribal Town ML24102A0422024-04-16016 April 2024 Ltr to State Recognized Tribes-Russell, Cherokee Tribe of Northeast Alabama 2024-09-03
[Table view] |
Text
une 26, 2008
SUBJECT:
BROWNS FERRY NUCLEAR POWER PLANT UNITS 1, 2, AND 3 - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000259/2008501, 05000260/2008501, and 05000296/2008501
Dear Mr. Campbell:
On June 6, 2008, the U. S. Nuclear Regulatory Commission (NRC) completed an Emergency Preparedness inspection at Browns Ferry Nuclear Power Plant. The enclosed inspection report documents the inspection results, which were discussed on June 6, 2008, with Mr. R. West 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 findings of 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 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).
TVA 2 ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety une 26, 2008
SUBJECT:
BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000259/2008501, 05000260/2008501, and 05000296/2008501
Dear Mr. Campbell:
On June 6, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an Emergency Preparedness inspection at Browns Ferry Nuclear Power Plant. The enclosed inspection report documents the inspection results, which were discussed on June 6, 2008, with Mr. R. West 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 findings of 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 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).
_______________________
OFFICE RII: DRS RII:DRP RII:DRS SIGNATURE /RA/ LGarner /RA/ for /RA/
NAME L. Miller R. Musser B. Bonser DATE 06/17/2008 06/25/2008 06/20/2008 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
TVA 3 cc w/encl:
Ashok S. Bhatnagar Michael A. Purcell Senior Vice President Senior Manager Nuclear Generation Development and Nuclear Licensing Construction Tennessee Valley Authority Tennessee Valley Authority Electronic Mail Distribution Electronic Mail Distribution H. Rick Rogers William R. Campbell, Jr. Vice President Chief Nuclear Officer and Executive Vice Nuclear Engineering and Projects President Tennessee Valley Authority Tennessee Valley Authority Electronic Mail Distribution 6A Lookout Place 1101 Market Street Beth A. Wetzel Chattanooga, TN 37402-2801 Manager Corporate Licensing and Industry Affairs (Vacant) Tennessee Valley Authority Vice President Electronic Mail Distribution Nuclear Support Tennessee Valley Authority Senior Resident Inspector 3R Lookout Place Tennessee Valley Authority 1101 Market Street Browns Ferry Nuclear Plant Chattanooga, TN 37402-2801 U.S. NRC 10833 Shaw Road R. G. (Rusty) West Athens, AL 35611-6970 Site Vice President Browns Ferry Nuclear Plant Chairman Tennessee Valley Authority Limestone County Commission Electronic Mail Distribution 310 West Washington Street Athens, AL 35611 D. Tony Langley Manager Dr. D. E. Williamson Licensing and Industry Affairs State Health Officer Tennessee Valley Authority Alabama Dept. of Public Health Electronic Mail Distribution 434 Monroe Street Suite 1552 John C. Fornicola P.O. Box 303017 General Manager Montgomery, AL 36130-1701 Nuclear Assurance Tennessee Valley Authority Kirksey E. Whatley Electronic Mail Distribution Director Office of Radiation Control General Counsel Alabama Dept. of Public Health Tennessee Valley Authority Electronic Mail Distribution Electronic Mail Distribution Larry E. Nicholson General Manager Licensing and Performance Improvement Tennessee Valley Authority Electronic Mail Distribution
TVA 4 Letter to William R. Campbell, Jr. from Brian Bonser dated June 26, 2008 SUBJECT: BROWNS FERRY NUCLEAR PLANT - NRC INTEGRATED INSPECTION REPORT 05000259/2008, 05000260/2008 AND 05000296/2008 Distribution w/encl:
E. Brown, NRR (PM - BF 2, 3)
L. Raghavan, NRR RIDSNRRDIRS PUBLIC
U. S. NUCLEAR REGULATORY COMMISSION
REGION II
Docket Nos: 50-259, 50-260, and 50-296 License Nos: DPR-33, DPR-52, DPR-68 Report Nos: 05000259/2008, 05000260/2008 and 05000296/2008 Licensee: Tennessee Valley Authority Facility: Browns Ferry Nuclear Plant, Units 1, 2, and 3 Location: Athens, AL Dates: June 2-6, 2008 Inspector: Lee Miller, Senior Emergency Preparedness Inspector Approved by: Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Enclosure
SUMMARY OF FINDINGS
IR 05000259/2008501, 05000260/2008501, and 05000296/2008501; 06/01/2008 - 6/06/2008;
Browns Ferry Nuclear Power Plant; Baseline Inspection.
The report covered an announced inspection by one emergency preparedness inspector. The NRC=s program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, AReactor Oversight Process.@
NRC-Identified and Self-Revealing Findings
No findings of significance were identified.
Licensee-Identified Violations
.
None
REPORT DETAILS
REACTOR SAFETY
Cornerstone: Emergency Preparedness
1EP2 Alert and Notification System Testing
a. Inspection Scope
The inspector evaluated the adequacy of licensee=s methods for testing the alert and notification system in accordance with NRC Inspection Procedure 71114, Attachment 02, AAlert and Notification System Evaluation.@ The applicable planning standard 10 CFR Part 50.47(b)(5) and its related 10 CFR Part 50, Appendix E, Section IV.D requirements were used as reference criteria. The criteria contained in NUREG-0654, ACriteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants,@ Revision 1, was also used as a reference.
The inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the alert and notification system on an biennial basis.
b. Findings
No findings of significance were identified.
1EP3 Emergency Response Organization Augmentation
a. Inspection Scope
The inspector reviewed the licensee=s Emergency Response Organization (ERO)augmentation staffing requirements and process for notifying the ERO to ensure the readiness of key staff for responding to an event and timely facility activation. The qualification records of key position ERO personnel were reviewed to ensure all ERO qualifications were current. A sample of problems identified from augmentation drills or system tests performed since the last inspection were reviewed to assess the effectiveness of corrective actions.
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 03, AEmergency Response Organization Staffing and Augmentation System.@
The applicable planning standard, 10 CFR 50.47(b)(2) and its related 10 CFR 50, Appendix E requirements were used as reference criteria.
The inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the ERO staffing and augmentation system on a biennial basis.
b. Findings
No findings of significance were identified.
1EP4 Emergency Action Level and Emergency Plan Changes
a. Inspection Scope
The inspector=s review of revisions to the emergency plan, implementing procedures, and Emergency Action Level (EAL) changes was performed to determine that changes had not decreased the effectiveness of the plan. The inspector evaluated the associated 10 CFR 50.54(q) reviews associated with non-administrative emergency plan, implementing procedures, and EAL changes. The inspector reviewed Tennessee Valley Authority Nuclear Radiological Emergency Plan revision 87, including appendix A:
Browns Ferry Nuclear Plant, and changes to the implementing procedures from June 1, 2007 to June 1, 2008.
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 04, AEmergency Action Level and Emergency Plan Changes.@ The applicable planning standard, 10 CFR 50.47(b)
- (4) and its related 10 CFR 50, Appendix E requirements were used as reference criteria.
The inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the EAL and emergency plan changes on an annual basis.
b. Findings
No findings of significance were identified.
1EP5 Correction of Emergency Preparedness Weaknesses and Deficiencies
a. Inspection Scope
The inspector reviewed the corrective actions identified through the Emergency Preparedness program to determine the significance of the issues and to determine if repeat problems were occurring. The facility=s self-assessments and audits were reviewed to assess the licensee=s ability to be self-critical, thus avoiding complacency and degradation of their EP program. In addition, the inspector reviewed licensee=s self-assessments and audits to assess the completeness and effectiveness of all emergency preparedness related corrective actions.
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 05, ACorrection of Emergency Preparedness Weaknesses.@ The applicable planning standard, 10 CFR 50.47(b)(14) and its related 10 CFR 50, Appendix E requirements were used as reference criteria.
The inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the correction of emergency preparedness weaknesses on a biennial basis.
Findings No findings of significance were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator Verification
a. Inspection Scope
Cornerstone: Emergency Preparedness
The inspector sampled licensee submittals for three Performance Indicators (PI) listed below. For each of the submittals reviewed, the inspector reviewed the period from March 31, 2007 through March 31, 2008. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in Nuclear Energy Institute (NEI) 99-02, ARegulatory Assessment Indicator Guideline,@ Revision 5, were used to verify the basis in reporting for each data element.
$ Emergency Response Organization Drill/Exercise Performance (DEP)
$ Emergency Response Organization Readiness (ERO)
$ Alert and Notification System Reliability (ANS)
The inspectors reviewed portions of the raw PI data developed from monthly performance indicator reports and discussed the methods for compiling and reporting the PIs with cognizant emergency preparedness personnel. The inspector also independently screened drill and exercise opportunity evaluations, drill participation reports, and drill evaluations. Selected reported values were calculated to verify their accuracy. The inspectors compared graphical representations from the most recent PI report to the raw data to verify that the data was correctly reflected in the report.
Reviewed documents are listed in the Attachment to this report.
b. Findings
No findings of significance were identified.
4OA6 Meetings, including Exit
On June 6, 2008, the lead inspector presented the inspection results to Mr. R. West and other members of his staff. The inspector confirmed that proprietary information was not provided during the inspection.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
R. West Site Vice President
S. Douglas Plant General Manager
T. Elms Assistant Plant Manager
M. Palmer Assistant Plant Manager
L. Hughes Operations
T. Brumfield Quality Assurance Manager
B. Marks Emergency Services - Corporate
T. Feltman Emergency Preparedness
R. Waldrep Emergency Preparedness
S. Austin Site Licensing
LIST OF DOCUMENTS REVIEWED