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Category:Inspection Plan
MONTHYEARML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant 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 ML24087A1822024-03-28028 March 2024 Notification of Target Set Inspection and Request for Information NRC Inspection Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 ML24052A1472024-02-28028 February 2024 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023006, 05000260/2023006 and 05000296/2023006 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 05000259/20220062023-03-0101 March 2023 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 Report 05000259/2022006, 05000260/2022006 and 05000296/2022006 ML23020A0602023-01-20020 January 2023 Long Term Steam Dryer Inspection Plan 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 ML22210A1342022-07-20020 July 2022 Requalification Inspection Notification Letter ML22174A2722022-06-24024 June 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection 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 ML22091A1942022-03-0808 March 2022 2022 BFN POV Inspection Information Request 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 ML22025A4132022-01-25025 January 2022 RP Inspection Doc Request ML22018A0292022-01-18018 January 2022 Region 2 RFI - 2022 Program Inspections ML21343A4232021-12-0909 December 2021 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000259/2022010, 05000260/2022010, and 05000296/2022010) and Request for Information (RFI) 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 IR 05000259/20200062021-03-0303 March 2021 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2020006, 05000260/2020006 and 05000296/2020006 ML21047A4732021-02-16016 February 2021 Notification of Browns Ferry Nuclear Power Plant Design Bases Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000259/2021010, 05000260/2021010, and 05000296/2021010 ML20338A3682020-12-0303 December 2020 Notification of Inspection and Request for Information ML20266G4472020-09-22022 September 2020 Notification of Inspection and Request for Information IR 05000259/20200052020-08-18018 August 2020 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2020005, 05000260/2020005, and 05000296/2020005 ML20191A2232020-07-0909 July 2020 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000259/20190062020-03-0303 March 2020 Annual Assessment Letter for Browns Ferry Nuclear Plant Units 1,2,and 3 - NRC Report 05000259/2019006, 05000260/2019006, and 05000296/2019006 ML19108A1682019-04-18018 April 2019 EP Exercise Inspection RFI IR 05000259/20180062019-03-0404 March 2019 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2018006, 05000260/2018006 and 05000328/2018006 ML19030A6712019-01-25025 January 2019 U2 ISI RFI ML19024A4112019-01-24024 January 2019 Transmittal of RP Baseline Inspection Document Request 2019 ML18264A2052018-09-21021 September 2018 U1 ISI Emailed RFI Notification ML18059A1052018-02-28028 February 2018 EOC Assessment Letter ML18029A4672018-01-29029 January 2018 Notification of Browns Ferry Nuclear Plant Design Bases Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000259/2018010, 05000260/2018010, and 05000296/2018010 ML18029A2552018-01-29029 January 2018 U3 RFI Email Request ML17236A1972017-08-24024 August 2017 Updated Inspection Plan ML17156A1612017-06-0202 June 2017 Notification of Inspection and Request for Information IR 05000259/20160062017-03-0101 March 2017 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2, and 3 (Report 05000259/2016006, 05000260/2016006 and 05000296/2016006) IR 05000259/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Browns Ferry Nuclear Plant Units 1, 2 and 3, NRC Inspection Reports 05000259/2016005, 05000260/2016005 and 05000296/2016005 ML16243A2242016-08-30030 August 2016 Notification of Inspection and Request for Information ML16120A1182016-04-27027 April 2016 Notification of Conduct of a Triennial Fire Protection Baseline Inspection - U.S. Nuclear Regulatory Commission Inspection Report Nos. 05000259/2016011, 05000260/2016011 and 05000296/2016011 IR 05000259/20150062016-03-0202 March 2016 Annual Assessment Letter for Browns Ferry Nuclear Plant Units 1, 2 and 3 NRC Inspection Reports 05000259/2015006, 05000260/2015006 and 05000296/2015006 ML16013A0812016-01-12012 January 2016 Browns Ferry Nuclear Plant, Unit 3 - Notification of Inspection and Request for Information ML15348A1802015-12-14014 December 2015 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000259/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for the Browns Ferry Nuclear Plant Units 1, 2 and 3, NRC Inspection Report 005000259/2015005, 005000260/2015005, and 005000296/2015005 IR 05000259/20140012015-03-0404 March 2015 Annual Assessment Letter for Browns Ferry Nuclear Plant Units 1, 2 and 3 - NRC Inspection Reports 05000259/2014001, 05000260/2014001 and 05000296/2014001 IR 05000259/20140062014-09-0202 September 2014 Mid-Cycle Assessment Letter for Browns Ferry Nuclear Plant Units 1, 2 and 3 (NRC Inspection Reports 05000259/2014006, 05000260/2014006 and 05000296/2014006) ML14063A1092014-03-0404 March 2014 2013 Annual Assessment Letter for Browns Ferry ML14031A4122014-01-31031 January 2014 U3 2014002 ISI RFI Final - Copy ML13353A5852013-12-19019 December 2013 PIR Notification Letter 2014 ML13246A1842013-09-0303 September 2013 Mid Cycle Assessment Letter ML13084A0052013-03-25025 March 2013 Emergency Preparedness Inspection Notification and Request for Information 2024-09-24
[Table view] Category:Letter
MONTHYEARML24289A1232024-10-24024 October 2024 Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 ML24270A2162024-09-27027 September 2024 Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075 ML24262A1502024-09-24024 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) 05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-07-0303 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) 05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-24024 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) ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 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 05000296/LER-2024-002, Breaker Trip Automatically Started an Emergency Diesel Generator2024-04-24024 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 2024-09-03
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Text
March 4, 2013
Mr. Joseph Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402-2801
SUBJECT: ANNUAL ASSESSMENT LETTER FOR BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 (NRC INSPECTION REPORT 05000259, 260, 296/2012001)
Dear Mr. Shea:
On February 14, 2013, the NRC completed its end-of-cycle performance review of Browns Ferry Nuclear Plant, Units 1, 2, and 3. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from January 1, 2012, through December 31, 2012. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility.
The NRC determined the performance at Browns Ferry Nuclear Plant, Unit 1, during the most recent quarter was within the Multiple/Repetitive Degraded Cornerstone column (Column 4) of the NRC's Reactor Oversight Process (ROP) Action Matrix, beginning the fourth quarter 2010, based on the issuance of one finding classified as having a high safety significance (Red) in the mitigating systems cornerstone. This was detailed in Final Significance Determination of a Red Finding, Notice of Violation, and Assessment Follow-Up Letter (NRC Inspection Report No. 05000259/2011008, (ML111290482)) for Browns Ferry Nuclear Plant, dated May 9, 2011.
On November 30, 2012, the NRC issued NRC Supplemental Inspection Report 05000259/2012015, (ML12335A380) for completion of an inspection pursuant to IP 95001,
"Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area," for a White Unit 1 Mitigating System Performance Index, High Pressure Injection Systems (HPCI) performance indicator. The inspection was completed satisfactorily and the performance indicator has returned to Green. On February 15, 2013, your staff notified the NRC of your readiness for it to conduct a supplemental inspection to review the actions taken to address the performance issues.
Therefore, in addition to ROP baseline inspections, the NRC plans to conduct a supplemental inspection in accordance with Inspection Procedure (IP) 95003, "Supplemental Inspection for Repetitive Degraded Cornerstones, Multiple Degraded Cornerstones, Multiple Yellow Inputs, or One Red Input, beginning on May 13, 2013. The supplemental inspection will include inspection and assessment activities to provide the NRC additional information to be used in deciding whether the continued operation of the facility is acceptable and whether additional regulatory actions are necessary to arrest declining plant performance; to provide an independent assessment of the extent of risk significant issues to aid in the determination whether an adequate level of margin of safety exists; and to evaluate the licensee's third-party safety culture assessment and conduct a graded assessment of the licensee's safety culture based on the results of the evaluation.
The NRC determined the performance at Browns Ferry Nuclear Plant, Units 2 and 3, during the most recent quarter was within the Regulatory Response Column (Column 2) of the NRC's Reactor Oversight Process Action Matrix. As detailed in Final Significance Determination Of A White Finding, Notice Of Violation, And Assessment Follow-Up Letter (NRC Inspection Reports 05000259,260,296/2012013, (ML12226A647)) for Browns Ferry Nuclear Plant, dated Aug 13, 2012, Units 2 and 3 were determined to be in the Regulatory Response Column beginning in the second quarter 2012.
On November 23, 2012, the NRC issued NRC Supplemental Inspection Report 05000259/2012014, 05000260/2012014, 05000296/2012014, (ML12331A180) for completion of an inspection pursuant to IP 95001, "Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area," for the White finding. The inspection was completed satisfactorily and the performance issue will remain open for consideration in the NRC's assessment program until the end of the first quarter 2013.
On November 30, 2012, the NRC issued NRC Supplemental Inspection Report 05000296/2012016, (ML12335A371) for completion of an inspection pursuant to IP 95001,
"Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area," for a White Unplanned Scrams performance indicator for Unit 3. The inspection was completed satisfactorily and the performance indicator has returned to Green.
The NRC identifies substantive cross-cutting issues (SCCIs) to communicate a concern with the licensee's performance in a cross-cutting area and to encourage the licensee to take appropriate actions before more significant performance issues emerge. The NRC identified a cross-cutting theme in the Resources component of the Human Performance & Error Prevention cross-cutting area. Specifically, six Green inspection findings for the current 12-month assessment period, each with a documented cross-cutting aspect of "Complete Documentation and Component Labeling" (H.2.(c)) were identified. The NRC determined that an SCCI existed because the NRC has a concern with your staff's scope of effort and progress in addressing the cross-cutting theme. Although you identified and implemented a range of actions to address the cross-cutting theme; these actions had not yet proven effective in substantially mitigating the cross-cutting theme, even though a reasonable duration of time has passed. This SCCI will remain open until the NRC has reviewed your other actions to address this SCCI, based on the following: 1) an appropriate and comprehensive range of actions identified by the Corrective Action Program, which will effectively address the cross-cutting theme; 2) no significant increase in the number of findings with the cross-cutting aspect of "Complete Documentation and Component Labeling" (H.2.(c)) during the previous six month assessment period; and 3) an increased level of confidence in your ability to deal effectively with operational and equipment issues as related to the cross-cutting theme of "Complete Documentation and Component Labeling" (H.2.(c)) during the previous six month assessment period. In its Annual Assessment Letter, dated March 4, 2011, (ML11063042), the NRC opened a SCCI with the aspect of "appropriate and timely corrective actions" (P.1(d)). The NRC determined that an SCCI existed because the NRC had a concern with your staff's scope of effort and progress in addressing the cross-cutting theme (NRC Inspection Report No. 05000259,260, 296/2010005 ML110400431). Although you identified and implemented a range of actions to address the cross-cutting theme; these actions had not yet proven effective in substantially mitigating the cross-cutting theme, even though a reasonable duration of time has passed. In its Mid-Cycle Assessment Letter, dated August 29, 2011, (ML112411450), the NRC requested that this SCCI be addressed during your third party safety culture assessment which will be reviewed as part of the Independent NRC Safety Culture Assessment per IP 95003,
"Supplemental Inspection for Repetitive Degraded Cornerstones, Multiple Degraded Cornerstones, Multiple Yellow Inputs, or One Red Input." Therefore this SCCI will continue to remain open pending completion of these assessments and until the NRC has reviewed your other actions to address this SCCI, based on the following: 1) a comprehensive range of actions are identified in your Corrective Action Program that effectively demonstrate you will address the cross-cutting theme; 2) no significant increase in the number of findings with the cross-cutting aspect of "appropriate and timely corrective actions" (P.1(d)) during the previous twelve month assessment period; and 3) the NRC has an increased level of confidence in your ability to deal effectively with operational/equipment issues as related to this cross-cutting theme during the previous six months assessment period. This letter is the fifth consecutive assessment letter documenting an SCCI with the same cross-cutting aspect.
In its Annual Assessment Letter, dated March 3, 2010, (ML100620960), the NRC opened a SCCI with the aspect of "thorough evaluation of identified problems" (P.1(c)). The NRC determined that an SCCI existed because the NRC had a concern with your staff's scope of effort and progress in addressing the cross-cutting theme (NRC Inspection Report No.
05000259,260,296/2010005). Although you identified and implemented a range of actions to address the cross-cutting theme; these actions had not yet proven effective in substantially mitigating the cross-cutting theme, even though a reasonable duration of time has passed. In its Mid-Cycle Assessment Letter, dated August 29, 2011, (ML112411450), the NRC requested that this SCCI be addressed during your third party safety culture assessment which will be reviewed as part of the Independent NRC Safety Culture Assessment per IP 95003,
"Supplemental Inspection for Repetitive Degraded Cornerstones, Multiple Degraded Cornerstones, Multiple Yellow Inputs, or One Red Input." Therefore this SCCI will continue to remain open pending completion of these assessments and until the NRC has reviewed your other actions to address this SCCI, based on the following: 1) an appropriate and comprehensive range of actions identified by the Corrective Action Program, which will effectively address the cross-cutting theme; 2) no significant increase in the number of findings with the cross-cutting aspect of "thorough evaluation of identified problems" (P.1(c)) during the previous twelve month assessment period; and 3) an increased level of confidence in your ability to deal effectively with operational and equipment issues as related to this cross-cutting theme during the previous six month assessment period. This letter is the seventh consecutive assessment letter documenting an SCCI with the same cross-cutting aspect.
The enclosed inspection plan lists the inspections scheduled through June 30, 2014. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the mid-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes. This inspection plan does not include security related inspections, which will be sent via separate, non-publicly available correspondence.
In addition to the baseline inspections at your facility, we also plan on conducting infrequently performed inspections which include: IP 92702, Follow up On Traditional Enforcement Actions Including Violations, Deviations, Confirmatory Action Letters, Confirmatory Orders, And Alternative Dispute Resolution Confirmatory Orders, initial reactor operator licensing examinations, TI 2515/182, "Review of the Implementation of the Industry Initiative to Control Degradation of Underground Piping and Tanks," and IP 71003, "Post-Approval Site Inspection For License Renewal."
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice", a copy of this letter 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). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Please contact Eugene Guthrie at 404-997-4662 with any questions you may have regarding this letter or the inspection plan.
Sincerely,/RA/ Victor M. McCree Regional Administrator Docket No.: 50-259, 50-260, 50-296 License No.: DPR-33, DPR-52, DPR-68
Enclosure:
Browns Ferry Inspection/ Activity Plan (03/01/2013 - 06/30/2014)
cc w/encl: (See page 5)