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Category:Letter
MONTHYEARCNL-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 CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems 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 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 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation IR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 ML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate 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 ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS 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) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 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 IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information 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 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) 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 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 ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule ML24081A0262024-03-21021 March 2024 Emergency Plan Implementing Procedure Revisions ML24079A0312024-03-19019 March 2024 Wb 2024-301, Corporate Notification Letter (210-day Ltr) CNL-24-031, Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-03-18018 March 2024 Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance CNL-24-028, Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 IR 05000390/20240102024-03-0808 March 2024 Age-Related Degradation Inspection Report 05000390/2024010 and 05000391/2024010 CNL-24-012, Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-02-28028 February 2024 Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance IR 05000390/20230062024-02-28028 February 2024 Annual Assessment Letter for Watts Bar Nuclear Plant Units 1 and 2 - Report 05000390/2023006 and 05000391/2023006 CNL-24-023, Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 ML24009A1712024-02-16016 February 2024 Environmental Assessment and Finding of No Significant Impact Related to an Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods (EPID L-2023-LLA-0039) - Letter ML24019A0722024-02-14014 February 2024 Request for Withholding Information from Public Disclosure IR 05000390/20230042024-02-13013 February 2024 Integrated Inspection Report 05000390/2023004 and 05000391/2023004 and Apparent Violation 2024-09-05
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE SUITE 1200 ATLANTA, GEORGIA 30303
-1257 April 11, 2011 Mr. William R. Campbell, Jr. Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402
-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT UNITS 1 AND 2 MULTI
-UNIT OPERATOR TRAINING AND CERTIFICATION PROGRAM, REVISION 1
Dear Mr. Campbell,
Jr.:
In a letter dated November 18, 2010, the Tennessee Valley Authority (TVA) provided changes to its initial approach for ensuring that a sufficient number of licensed operators will be available to operate Watts Bar Nuclear Plant (WBN), Units 1 and 2
, prior to Unit 2 initial fuel load. The changes to the proposed initial training and certification program submittal also addressed comments that members of your staff received from Region II Operations Branch during a meeting on November 4, 2010. The reviewed training plan from TVA dated November 18, 2010, is attached.
The purpose s of the Region II Operator Licensing staff's review of the proposed training plan and the planned inspection activities are to: Evaluate the differences between Unit 1 and Unit 2 and provide insight to the office of Nuclear Reactor Regulation (NRR), headquarters Operator Licensing Branch , to identify if currently licensed operators on Unit 1 who will be requesting Watts Bar Unit 2 (dual) licenses have had sufficient operating experience at a comparable facility as required by 10 CFR 55.47 (a)(1), that is on Watts Bar Unit 1
, and that this operating experience has occurred within two years prior to Unit 2 initial fuel load.
Evaluate the content of the proposed "differences
" training provided to operators who are currently licensed on Unit 1
, to identify if training include s comprehensive "differences" written examination s, JPM operating test s, and simulator modifications, training that meets the requirement s of 10 CFR 55.47 (a)(3) in that each applicant "has learned the operating procedures for and is qualified to operate competently and safely
" Watts Bar Unit 2
. Additionally, the purpose of the evaluation is to ensure that incumbent operators, as well as initial operator license applicants
, have startup training using Unit 2 initial criticality procedures on the plant reference simulator using a simulator model that approximates Unit 2 core design.
Evaluate the adequacy of the Unit 1 simulator for administering operating test s to initial operator applicants, in accordance with 10CFR 55.46, during the same time frame that the simulator will be used to train licensed operators on the Unit
-2 modifications.
TVA 2 Evaluate the content of the proposed "differences" training including the proposed evaluation methods that will be administered to initial operator license applicants who will only be issued Unit 1 operating license s prior to obtaining a dual unit license.
Based on Region II Operator Licensing's review of the available Unit 2 modifications
, the proposed differences between Unit 1 and Unit 2 are not so significant that they would affect the operator's ability to operate each unit safely and competently.
Approximately ten percent of the required modifications are yet to be issued. The final determination of whether the operators who are currently licensed on Unit 1 meet the written and operating test waiver requirements, in accordance with 10CFR55.47 and NUREG 1021, Revision 9, Supplement 1, ES
-204, Section D.2, on Unit 2 is contingent upon Region II Operator Licensing inspections, and completion of the proposed training plan "Multi-Unit Operator Training and Certification Program, Revision 1.
" Sincerely, / RA / Malcolm T. Widmann
, Chief Operations Branch 1 Division of Reactor Safety
Docket No(s).: 50
-390, 50-391 License No(s)
.: NPF-90, CPPR-92
Enclosure:
As stated cc w/encl: (See page
- 3)
ML 111010586 X SUNSI REVIEW COMPLETE OFFICE RII:DRS RII:DRS RII:DRS SIGNATURE RA RA RA NAME R. Baldwin M. Widmann M. Franke DATE 04/11/2011 04/11/2011 04/11/2011 E-MAIL COPY?
YES NO YES NO YES NO YES NO YES NO YES NO YES NO TVA 3 cc w/encl:
D. E. Grissette Site Vice President Watts Bar Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution G. A. Boerschig Plant Manager Watts Bar Nuclear Plant, MOB 2R
-WBN Tennessee Valley Authority Electronic Mail Distribution C. J. Riedl Acting Manager, Licensing Watts Bar Nuclear Plant, ADM 1L
-WBN Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381
J. W. Shea Manager, Corp. Nuclear Licensing
- WBN Tennessee Valley Authority Electronic Mail Distribution E. J. Vigluicci Assistant General Counsel Tennessee Valley Authority Electronic Mail Distribution
W. D. Crouch Licensing Manager, Unit 2 Watts Bar Nuclear Plant, EQB 1B
-WBN Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381 County Mayor P.O. Box 156 Decatur, TN 37322
County Executive 375 Church Street Suite 215 Dayton, TN 37321 Tennessee Department of Enviornment & Conservation Division of Radiological Health 401 Church Street Nashville, TN 37243 Senior Resident Inspector U.S. Nuclear Regulatory Commission Watts Bar Nuclear Plant U.S. Nuclear Regulatory Commission 1260 Nuclear Plant Road Spring City, TN 37381
-2000 Ann Harris 341 Swing Loop
Rockwood, TN 37854 R. Krich Vice President, Nuclear Licensing 1101 Market Street, LP 3R Chattanooga, TN 37402
-2801 William W. Thompson Training Manager Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381
Letter to William R. Campbell, Jr. from Malcolm T. Widmann dated April 11, 2011.
SUBJECT:
WATTS BAR NUCLEAR PLANT UNITS 1 AND 2 MULTI
-UNIT OPERATOR TRAINING AND CERTIFICATION PROGRAM, REVISION 1 V. McCree Distribution w/encl:
L. Wert C. Casto J. Munday H. Christensen M. Franke R. Croteau W. Jones G. Guthrie C. Kontz R. Baldwin B. Caballero P. Capehart C. Evans L. Douglas J. McHale, NRR/DIRS/IOLB P. Milano, NRR OE Mail RIDSNRRDIRS PUBLIC