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Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump 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 ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 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 ML23233A0432023-08-18018 August 2023 Enforcement Action EA-22-122 Inspection Readiness Notification ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23228A1642023-08-16016 August 2023 Site Emergency Plan Implementing Procedure Revision ML23228A0202023-08-15015 August 2023 (BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23201A2182023-07-20020 July 2023 Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299) ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23199A3072023-07-18018 July 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 2024-02-01
[Table view] |
See also: IR 05000259/2011301
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
February 17, 2011
Tennessee Valley Authority
ATTN: Mr. Jeff Morris
Training Manager
Browns Ferry Nuclear Plant
P. O. Box 2000
Decatur, AL 35609-2000
SUBJECT: REVISED - BROWNS FERRY NUCLEAR POWER PLANT - OPERATOR LICENSING
WRITTEN EXAMINATION APPROVAL 05000259/2011301, 05000260/2011301 AND
05000296/2011301
Dear Mr. Morris:
The purpose of this letter is to confirm the final arrangements for the upcoming operator licensing written
examination at Browns Ferry Nuclear Power Plant.
The U.S. Nuclear Regulatory Commission (NRC) has completed its review of the operator license
applications submitted in connection with this examination and separately provided a list of approved
applicants to your office. The NRC staff administered the operating tests to individuals, as applicable,
during the weeks of February 7, 2011, and February 14, 2011. Note that any examination waivers and
application denials have been addressed in separate correspondence.
The NRC has re-approved the subject written examination since changes were made after original
approval. I hereby authorize you to administer the written examination in accordance with Revision 9,
Supplement 1, of NUREG-1021, Operator Licensing Examination Standards for Power Reactors, on
February 18, 2011.
This examination has undergone extensive review by my staff and representatives responsible for
operator training at your facility. Based on this review I have concluded that the examination meets the
guidelines of NUREG-1021 for content, operational, and discrimination validity. By administering this
examination, you also agree that it meets NUREG-1021 guidelines, and is appropriate for measuring the
qualifications of licensed operators at your facility. If you determine that this examination is not
appropriate for licensing operators at your facility, do not administer the examination and contact me at
(404) 997-4550.
Please contact the Chief Examiner, Mr. Ronald F. Aiello, at (404) 997-4641 if you have any questions or
identify any errors or changes in license level (RO or SRO) or type of examination (partial or complete
written examination and/or operating test) specified for each applicant on the list of approved applicants.
Sincerely,
/RA/
Malcolm T. Widmann, Chief
Operations Branch
Division of Reactor Safety
Docket Nos.: 50-259, 50-260, 50-296
License Nos.: DPR-33, DPR-52, DPR-68
Tennessee Valley Authority
ATTN: Mr. Jeff Morris
Training Manager
Browns Ferry Nuclear Plant
P. O. Box 2000
Decatur, AL 35609-2000
SUBJECT: REVISED - BROWNS FERRY NUCLEAR POWER PLANT - OPERATOR LICENSING
WRITTEN EXAMINATION APPROVAL 05000259/2011301, 05000260/2011301 AND
05000296/2011301
Dear Mr. Morris:
The purpose of this letter is to confirm the final arrangements for the upcoming operator licensing written
examination at Browns Ferry Nuclear Power Plant.
The U.S. Nuclear Regulatory Commission (NRC) has completed its review of the operator license applications
submitted in connection with this examination and separately provided a list of approved applicants to your office.
The NRC staff administered the operating tests to individuals, as applicable, during the weeks of February 7, 2011,
and February 14, 2011. Note that any examination waivers and application denials have been addressed in
separate correspondence.
The NRC has re-approved the subject written examination since changes were made after original approval. I
hereby authorize you to administer the written examination in accordance with Revision 9, Supplement 1, of
NUREG-1021, Operator Licensing Examination Standards for Power Reactors, on February 18, 2011.
This examination has undergone extensive review by my staff and representatives responsible for operator training
at your facility. Based on this review I have concluded that the examination meets the guidelines of NUREG-1021
for content, operational, and discrimination validity. By administering this examination, you also agree that it meets
NUREG-1021 guidelines, and is appropriate for measuring the qualifications of licensed operators at your facility. If
you determine that this examination is not appropriate for licensing operators at your facility, do not administer the
examination and contact me at (404) 997-4550.
Please contact the Chief Examiner, Mr. Ronald F. Aiello, at (404) 997-4641 if you have any questions or identify
any errors or changes in license level (RO or SRO) or type of examination (partial or complete written examination
and/or operating test) specified for each applicant on the list of approved applicants.
Sincerely,
/RA/
Malcolm T. Widmann, Chief
Operations Branch
Division of Reactor Safety
Docket Nos.: 50-259, 50-260, 50-296
License Nos.: DPR-33, DPR-52, DPR-68
X PUBLICLY AVAILABLE G NON-PUBLICLY AVAILABLE G SENSITIVE X NON-SENSITIVE
ADAMS: Yes ACCESSION NUMBER: ML110480888 X SUNSI REVIEW COMPLETE
OFFICE RII:DRS RII:DRS
SIGNATURE RFA MTW
NAME RAIELLO MWIDMANN
DATE 2/17/11 2/17/11 2/ /2011 2/ /2011 2/ /2011
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO
O:\Browns Ferry Examinations\BF 2011-301 Initial Exam (Ron)\Correspondence\BF Exam 2011-301 Revised Approval Letter.docx