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Category:Letter
MONTHYEARIR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) 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 IR 05000390/20243012024-10-17017 October 2024 Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301 ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24261C0062024-10-0404 October 2024 Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 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 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 05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024 Inoperability of Both Trains of Unit 2 Low Head Safety Injection 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 05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024 Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO 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-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 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 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 05000391/LER-2024-001, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-03-27027 March 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation 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) 2024-09-05
[Table view] Category:Schedule and Calendars
MONTHYEARWBL-23-026, Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2023-01 - Preparation and Scheduling of Operator Licensing Examinations2023-05-18018 May 2023 Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2023-01 - Preparation and Scheduling of Operator Licensing Examinations ML22018A0292022-01-18018 January 2022 Region 2 RFI - 2022 Program Inspections WBL-21-023, Preparation and Scheduling of Operator Licensing Examination2021-04-20020 April 2021 Preparation and Scheduling of Operator Licensing Examination ML15110A4052015-05-21021 May 2015 Summary of Category 1 Public Meeting with Tennessee Valley Authority on the Fire Protection Report for Watts Bar Nuclear Plant, Unit 2 IR 05000391/20146062014-09-0303 September 2014 Mid-Cycle Assessment Letter Watts Bar Nuclear Plant, Unit 2 (NRC Inspection Report 05000391/2014606) ML12307A1042012-10-29029 October 2012 Tennessee Valley Authority - Initial Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML0921705872009-08-14014 August 2009 Confirmation of Schedule for Submission of Information to Support Operating Licence Application Review ML0916106382009-06-12012 June 2009 Confirmation of Schedule for Submission of Information to Support Operating License Application Review ML0821206382008-07-28028 July 2008 NRC Regulatory Issue Summary (RIS) 2008-16 - Preparation and Scheduling of Operator Licensing Examinations 2023-05-18
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 14, 2009 Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SUB~IECT: WATTS BAR NUCLEAR PLANT, UNIT 2 - CONFIRMATION OF SCHEDULE FOR SUBMISSION OF INFORMATION TO SUPPORT OPERATING LICENSE APPLICATION REVIEW
Dear Mr. Bhatnagar:
The Tennessee Valley Authority (TVA) has recently updated its schedule reflecting the remaining topics to be submitted in support of the operating license application for Watts Bar Nuclear Plant, Unit 2. The schedule provides the anticipated dates that TVA will provide information amending the final safety analysis report to the Nuclear Regulatory Commission (NRC). On the basis of its review of the schedule, the NRC anticipates receiving information on the topic sections listed in the enclosure to this letter before October 31, 2009. Therefore, the NRC staff requests that TVA verifies the Safety Evaluation Report sections to be provided on November 27,2009, and includes all anticipated items.
If you should have any questions, please contact Ayanna Rice at 301-415-5490.
Sincerely, Patrick D. Milano, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391
Enclosure:
Status of Submittal Items for September - November 2009 cc w/encl: Distribution via Listserv
Expected Submittal of Topic Items Related to the Safety Evaluation Report (SER)
Between Septem ber an d Novem ber 2009 SER Section Title Expected Due Date 1.5.0
SUMMARY
OF PRINCIPAL REVIEW MATTERS 11/27/2009 1.9.0 LICENSE CONDITIONS 11/27/2009 2.4.6 ULTIMATE HEAT SINK 11/27/2009 3.0.0 DESIGN OF STRUCT, COMP, EQUIP, & SYS 11/27/2009 3.
1.0 INTRODUCTION
11/27/2009 3.1.1 CONFORMANCE W/ GEN DESIGN CRITERIA 11/27/2009 3.1.2 CONFORMANCE W/ INDUST CODES & STAND 11/27/2009 3.2.0 CLASS OF STRUCT, SYS, & COMP 11/27/2009 3.2.1 SEISMIC CLASSIFICATIONS 11/27/2009 3.2.2 SYS QUALITY GROUP CLASSIFICATIONS 11/27/2009 3.5.0 MISSILE PROTECTION 11/27/2009 3.5.1 MISSILE SELECTION & DESCRIPTION 11/27/2009 3.5.2 STRUCT, SYS, COMP TO BE PROTECTED 11/27/2009 3.5.3 BARRIER DESIGN STRUCTURES 11/27/2009 3.6.0 PROTECT AGAINST EFFECTS PIPE RUPTURE 11/27/2009 3.6.1 PLANT DESIGN PROTECT FROM PIPE FAIL 11/27/2009 3.6.2 DETERMINE BRK LOCATION PIPE RUPTURES 11/27/2009 3.6.3 LEAK-BEFORE-BREAK EVALUATION PROCED 11/27/2009 3.10.0 SEISMIC & DYNAMIC QUAL OF EQUIP 11/27/2009 4.0.0 REACTOR 11/27/2009 4.
1.0 INTRODUCTION
11/27/2009 4.2.0 FUEL SYSTEM DESIGN 11/27/2009 4.
2.1 DESCRIPTION
11/27/2009 4.2.2 THERMAL PERFORMANCE 11/27/2009 4.2.3 MECHANICAL PERFORMANCE 11/27/2009 4.2.4 SURVEILLANCE 11/27/2009 4.2.5 FUEL DESIGN CONSIDERATIONS 11/27/2009 4.3.0 NUCLEAR DESIGN 11/27/2009 4.3.1 DESIGN BASIS 11/27/2009 4.3.2 DESIGN DESCRIPTION 11/27/2009 4.3.3 ANALYTICAL METHODS 11/27/2009 4.3.4
SUMMARY
OF EVALUATION FINDINGS 11/27/2009 4.4.0 THERMAL-HYDRAULIC DESIGN 11/27/2009 4.4.1 PERFORMANCE IN SAFETY CRITERIA 11/27/2009 4.4.2 DESIGN BASES 11/27/2009 4.4.3 THERMAL-HYDRAULIC DESIGN METHODOLOGY 11/27/2009 4.4.4 OPERATING ABNORMALITIES 11/27/2009 4.4.6 THERMAL-HYDRAULIC COMPARISON 11/27/2009 4.4.7 N-1 LOOP OPERATION 11/27/2009 4.4.9
SUMMARY
& CONCLUSION 11/27/2009 4.6.0 FUNCTIONAL DESIGN OF REACTIVITY SYS 11/27/2009 5.2.1 COMPLIANCE W/ CODES & CODE CASES 11/27/2009 5.4.2 STEAM GENERATORS 11/27/2009 Enclosure
5.4.4 PRESSURIZER RELIEF TANK 11/27/2009 6.2.5 COMBUSTIBLE GAS CONTROL SYSTEMS 11/27/2009 6.2.7 FRACTURE PREVENTION OF CONTAINMENT 11/27/2009 6.3.0 EMERGENCY CORE COOLING SYSTEM 11/27/2009 6.3.1 SYSTEM DESIGN 11/27/2009 6.3.2 EVALUATION 11/27/2009 6.3.3 TESTING 11/27/2009 6.3.4 PERFORMANCE EVALUATION 11/27/2009 6.
3.5 CONCLUSION
S 11/27/2009 6.6.0 INSERVICE INSPECT OF CLASS 2 & 3 COMP 11/27/2009 7.3.0 ENGINEERED SAFETY FEATURES SYSTEM 11/27/2009 7.3.1 SYSTEM DESCRIPTION 11/27/2009 7.3.2 CONTAINMENT SUMP LEVEL MEASUREMENT 11/27/2009 7.3.3 AUX FEEDWATER INITIAION & CONTROL 11/27/2009 7.3.4 FAILURE MODES & EFFECTS ANALYSIS 11/27/2009 7.3.5 IE BULLETIN 80-06 11/27/2009 7.
3.6 CONCLUSION
S 11/27/2009 7.4.0 SYSTEMS REQUIRED FOR SAFE SHUTDOWN 11/27/2009 7.4.1 SYSTEM DESCRIPTION 11/27/2009 7.4.2 SAFE SHUTDOWN FROM AUX CONTROL ROOM 11/27/2009 7.
4.3 CONCLUSION
S 11/27/2009 7.7.3 VOLUME CONTROL TANK LVL CONTROL SYS 11/27/2009 8.1.0 GENERAL 11/27/2009 8.2.1 COMPLIANCE WITH GDC 5 11/27/2009 8.2.2 COMPLIANCE WITH GDC 17 11/27/2009 8.2.3 COMPLIANCE WITH GDC 18 11/27/2009 8.2.4 EVALUATION FINDINGS 11/27/2009 8.3.0 ONSITE POWER SYSTEMS 11/27/2009 8.3.1 ONSITE AC PWR SYS COMPLIANCE W/ GDC17 11/27/2009 8.3.2 ONSITE DC SYS COMPLIANCE WITH GDC 17 11/27/2009 8.3.3 EVALUATION FINDINGS 11/27/2009 8.4.0 STATION BLACKOUT 11/27/2009 9.1.1 NEW FUEL STORAGE 11/27/2009 9.1.2 SPENT FUEL STORAGE 11/27/2009 9.2.0 WATER SYSTEMS 11/27/2009 9.2.1 ERCW & RCWS 11/27/2009 9.2.2 COMPONENT COOLING SYSTEM 11/27/2009 9.2.3 DEMINERALIZED WATER MAKEUP SYSTEM 11/27/2009 9.2.4 POTABLE & SANITARY WATER SYSTEMS 11/27/2009 9.2.5 ULTIMATE HEAT SINK 11/27/2009 9.2.6 CONDENSATE STORAGE FACILITIES 11/27/2009 9.3.3 EQUIP & FLOOR DRAINAGE SYSTEM 11/27/2009 9.4.4 TURBINE BUILDING ARE VENT SYS 11/27/2009 9.5.2 COMMUNICATIONS SYSTEM 11/27/2009 9.5.3 LIGHTING SYSTEMS 11/27/2009 9.5.4 EMERG DIESEL GEN FUEL OIL STORAGE 11/27/2009 9.5.5 EMERG DIESEL GEN COOLING WATER SYS 11/27/2009
9.5.6 EMERG DIESEL GEN STARTING SYS 11/27/2009 9.5.8 EMERG DIESEL GEN INTAKE & EXHAUST SYS 11/27/2009 10.1.0
SUMMARY
DESCRIPTION 11/27/2009 10.2.0 TURBINE GENERATOR 11/27/2009 10.2.1 TURBINE GENERATOR DESIGN 11/27/2009 10.2.2 TURBINE DISC INTEGRITY 11/27/2009 10.3.0 MAIN STEAM SUPPLY SYSTEM 11/27/2009 10.3.1 MAIN STEAM SUPPLY SYS INCLUDE VALVES 11/27/2009 10.3.2 MAIN STEAM SUPPLY SYS 11/27/2009 10.3.3 STEAM & FEEDWATER SYS MATERIALS 11/27/2009 10.3.4 SECONDARY WATER CHEMISTRY 11/27/2009 10.4.1 MAIN CONDENSER 11/27/2009 10.4.2 MAIN CONDENSER EVACUATION SYS 11/27/2009 10.4.4 TURBINE BYPASS SYSTEM 11/27/2009 11.0.0 RADIOACTIVE WASTE MANAGEMENT 11/27/2009 11.1.0
SUMMARY
DESCRIPTION 11/27/2009 11.2.0 LIQUID WASTE MANAGEMENT 11/27/2009 11.3.0 GASEOUS WASTE MANAGEMENT 11/27/2009 11.4.0 SOLID WASTE MANAGEMENT 11/27/2009 11.5.0 PROCESS & EFFLUENT RADIOLOGICAL MON 11/27/2009 11.6.0 EVALUATION FINDINGS 11/27/2009 11.7.0 NUREG-0737 ITEMS 11/27/2009 11.7.1 WIDE RANGE NOBLE GAS & IODINE 11/27/2009 11.7.2 PRIMARY COOLANT OUTSIDE CONTAINTMENT 11/27/2009 12.0.0 RADIATION PROTECTION 11/27/2009 12.1.0 GENERAL 11/27/2009 12.2.0 ASSURING THAT OCCUP RADIATION EXPOSE 11/27/2009 12.3.0 RADIATION SOURCES 11/27/2009 12.4.0 RADIATION PROTECT DESIGN FEATURES 11/27/2009 12.5.0 DOSE ASSESSMENT 11/27/2009 12.6.0 HEALTH PHYSICS PROGRAM 11/27/2009 12.7.0 NUREG-0737 ITEMS 11/27/2009 12.7.1 PLANT SHIELDING 11/27/2009 12.7.2 HIGH RANGE INCONTAINMENT MONITOR 11/27/2009 12.7.3 INPLANT RADIOIODINE MONITOR 11/27/2009 13.1.0 ORG STRUCTURE OF THE APPLICANT 11/27/2009 13.1.1 MANAGEMENT & TECHNICAL ORG 11/27/2009 13.1.2 CORPORATE ORG & TECH SUPPORT 11/27/2009 13.1.3 PLANT STAFF ORGANIZATION 11/27/2009 13.2.0 TRAINING 11/27/2009 13.2.1 LICENSED OPERATOR TRAINING PROGRAM 11/27/2009 13.2.2 TRAINING FOR NONLICENSED PERSONNEL 11/27/2009 13.3.0 EMERGENCY PREPAREDNESS EVALUATION 11/27/2009 13.
3.1 INTRODUCTION
11/27/2009 13.3.2 EVALUATIONS OF THE EMERGENCY PLAN 11/27/2009 13.
3.3 CONCLUSION
S 11/27/2009 13.4.0 REVIEW & AUDIT 11/27/2009 15.3.6 ANTICIPATED TRANSIENT WITHOUT SCRAM 11/27/2009
Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 2 - CONFIRMATION OF SCHEDULE FOR SUBMISSION OF INFORMATION TO SUPPORT OPERATING LICENSE APPLICATION REVIEW
Dear Mr. Bhatnagar:
The Tennessee Valley Authority (TVA) has recently updated its schedule reflecting the remaining topics to be submitted in support of the operating license application for Watts Bar Nuclear Plant, Unit 2. The schedule provides the anticipated dates that TVA will provide information amending the final safety analysis report to the Nuclear Regulatory Commission (NRC). On the basis of its review of the schedule, the NRC anticipates receiving information on the topic sections listed in the enclosure to this letter before October 31, 2009. Therefore, the NRC staff requests that TVA verifies the Safety Evaluation Report sections to be provided on November 27, 2009, and includes all anticipated items.
If you should have any questions, please contact Ayanna Rice at 301-415-5490.
Sincerely, IRAI Patrick D. Milano, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391
Enclosure:
Status of Submittal Items for September - November 2009 cc w/encl: Distribution via Listserv DISTRIBUTION: RidsOgcRp Resource A. Rice PUBLIC RidsNrrDorlLpwb Resource RidsNrrDorlDpr Resource LPWB Reading File RidsNrrLABClayton Resource RidsAcrsAcnw_MailCTR Resource RidsNrrPMWattsBar2 Resource RidsRgn2MailCenter Resource ADAMS Accession No*.. ML092170587 OFFICE DORLlCPAlPPM LW/LA LPWB/PM LPWB/PM LPWB/BC NAME ARiee BClayton PMilano JWiebe LRaghavan DATE 08/14/09 08/13/09 08/14/09 08/14/09 08/14/09 OFFICIAL AGENCY RECORD