Letter Sequence Approval |
---|
TAC:ME2439, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) TAC:ME2440, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) |
|
MONTHYEARML0929503402009-10-20020 October 2009 License Amendment Request for Adoption of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 - Browns Ferry TS Change 469; Sequoyah Change 09-04; and Watts Change 09-19 Project stage: Request ML0933800952009-12-0303 December 2009 TSTF-511 LAR Acceptance Review Project stage: Acceptance Review ML0931600842010-02-0202 February 2010 Issuance of Amendments 327 and 320, Regarding Adoption of TSTF- 511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.1 to Support Compliance with 10CFR Part 26 (Tac Nos. ME2439 and ME2440) Project stage: Approval 2009-12-03
[Table View] |
|
---|
Category:Letter
MONTHYEARCNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems 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 ML24267A0402024-09-19019 September 2024 Cycle 27 Core Operating Limits Report Revision 0 ML24185A1742024-09-18018 September 2024 Cover Letter - Issuance of Exemption Related to Non-Destructive Examination Compliance Regarding Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation 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 ML24253A0152024-09-0808 September 2024 Emergency Plan Implementing Procedure Revisions ML24247A2212024-08-29029 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-21-160, NEI 03-08 Needed Guidance: PWR Lower Radial Support Clevis Insert X-750 Bolt Inspection Requirements, September 1, 2021 ML24247A1802024-08-28028 August 2024 Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation for Sequoyah Nuclea IR 05000327/20240052024-08-26026 August 2024 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2024005 and 05000328/2024005 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 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), IR 05000327/20240022024-07-31031 July 2024 Integrated Inspection Report 05000327/2024002 and 05000328/2024002 ML24211A0542024-07-29029 July 2024 Operator License Examination Report ML24211A0572024-07-29029 July 2024 Submittal of Emergency Plan Implementing Procedure Revision ML24211A0412024-07-26026 July 2024 Unit 1 Cycle 26 Refueling Outage - 90-Day Inservice Inspection Summary Report 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 ML24191A4652024-07-0909 July 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24177A0282024-06-25025 June 2024 Emergency Plan Implementing Procedure Revisions ML24176A0222024-06-24024 June 2024 Retraction of Interim Report of a Deviation or Failure to Comply – Transducer Model 8005N 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) ML24145A0852024-05-30030 May 2024 1B-B Diesel Generator Failure - Final Significance Determination Letter ML24145A1052024-05-29029 May 2024 301 Exam Approval Letter ML24134A1762024-05-13013 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report 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 ML24128A0352024-05-0707 May 2024 Providing Supplemental Information to Apparent Violation ML24120A0582024-04-26026 April 2024 10 CFR 50.46 Annual Report for Sequoyah Nuclear Plant Units 1 and 2 ML24116A2612024-04-25025 April 2024 Interim Report of a Deviation or Failure to Comply - Transducer Model 8005N ML24114A0482024-04-23023 April 2024 Annual Radioactive Effluent Release Report for 2023 Monitoring Period 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 ML24144A2322024-04-20020 April 2024 Tennessee Multi-Sector Permit (Tmsp), 2024 Annual Discharge Monitoring Report for Outfalls SW-3, SW-3, and SW-9 ML24144A2362024-04-20020 April 2024 Discharge Monitoring Report (Dmr), March 2024 ML24102A1212024-04-18018 April 2024 Summary of Conference Call with Tennessee Valley Authority Regarding Sequoyah Nuclear Plant, Unit 1 Spring 2024 Steam Generator Tube Inspections ML24089A0882024-04-18018 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 IR 05000327/20240012024-04-17017 April 2024 Integrated Inspection Report 05000327/2024001 and 05000328/2024001 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 ML24109A0272024-04-16016 April 2024 Cycle 27 Core Operating Limits Report Revision 0 CNL-23-006, Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03)2024-04-15015 April 2024 Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03) ML24106A0502024-04-12012 April 2024 Discharge Monitoring Report (Dmr), February 2024 ML24100A0162024-04-11011 April 2024 Request for Regulatory Conference (Tennessee Valley Authority - Sequoyah Nuclear Plant) 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 ML24088A0332024-03-28028 March 2024 Request for Regulatory Conference (Tennessee Valley Authority) 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-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report ML24040A2062024-03-26026 March 2024 Issuance of Amendment Nos. 367 and 361 Regarding Changes to the Hydrologic Analyses (EPID L-2020-LLA-0004) - Public IR 05000327/20240902024-03-19019 March 2024 NRC Inspection Report 05000327-2024090 and 05000328-2024090 and Preliminary Greater than Green Finding and Apparent Violation CNL-24-027, Response to Request for Additional Information Regarding Sequoyah 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 Sequoyah 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 2024-09-08
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML24247A1752024-08-28028 August 2024 Enclosure 1: Description and Assessment of the Proposed Changes ML24247A1802024-08-28028 August 2024 Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation for Sequoyah Nuclea CNL-23-006, Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03)2024-04-15015 April 2024 Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03) CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-22-030, Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03)2022-07-27027 July 2022 Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03) CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04) CNL-22-071, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08)2022-07-13013 July 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08) ML22165A1052022-07-12012 July 2022 Issuance of Amendment Nos. 357 and 351 Regarding Revision to Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation CNL-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022 and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) ML22115A0022022-05-17017 May 2022 Correction to Amendment No. 350 Regarding One-Time Change to Technical Specification3.4.12, Low Temperature Overpressure Protection System, CNL-22-034, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03)2022-05-13013 May 2022 Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03) ML22125A1272022-05-0404 May 2022 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases CNL-22-023, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf2022-04-28028 April 2022 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf CNL-22-001, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08)2022-04-0404 April 2022 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08) CNL-21-085, License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07)2022-02-24024 February 2022 License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07) CNL-21-001, Application to Modify the Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation (SQN-TS-21-01)2021-11-29029 November 2021 Application to Modify the Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation (SQN-TS-21-01) CNL-21-091, Exigent License Amendment Request to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System (SQN-TS-21-06)2021-10-22022 October 2021 Exigent License Amendment Request to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System (SQN-TS-21-06) CNL-21-026, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03)2021-08-0505 August 2021 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03) CNL-21-045, Bellefonte Nuclear Plant, Units 1 and 2; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN82021-04-29029 April 2021 Bellefonte Nuclear Plant, Units 1 and 2; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN89- CNL-20-014, Application to Modify the Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09)2020-09-23023 September 2020 Application to Modify the Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09) CNL-20-041, License Amendment Request to Remove Licensee Control (BFN TS-527, SQN-TS-20-08, and WBN-TS-20-016)2020-08-14014 August 2020 License Amendment Request to Remove Licensee Control (BFN TS-527, SQN-TS-20-08, and WBN-TS-20-016) CNL-20-047, Brown Ferry Nuclear Plant, Sequoyah Nuclear Plant & Watts Bar Nuclear Plant - Tennessee Valley Authority License Amendment Request to Revise Radiological Emergency Plan Regarding On-shift Emergency Medical Technician and Onsite Ambulance2020-07-31031 July 2020 Brown Ferry Nuclear Plant, Sequoyah Nuclear Plant & Watts Bar Nuclear Plant - Tennessee Valley Authority License Amendment Request to Revise Radiological Emergency Plan Regarding On-shift Emergency Medical Technician and Onsite Ambulance Re CNL-20-042, Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-20-05)2020-04-17017 April 2020 Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-20-05) CNL-20-010, Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01)2020-02-24024 February 2020 Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01) CNL-19-066, Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02)2020-01-14014 January 2020 Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02) CNL-19-116, Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05)2019-11-16016 November 2019 Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05) CNL-19-005, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program (SQN-TS-19-01)2019-02-0101 February 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program (SQN-TS-19-01) CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays2018-11-19019 November 2018 Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays CNL-18-085, License Amendment Request to Change the Implementation Date for License Amendments to Upgrade Emergency Action Level Scheme2018-06-15015 June 2018 License Amendment Request to Change the Implementation Date for License Amendments to Upgrade Emergency Action Level Scheme CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06)2018-03-16016 March 2018 Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) CNL-17-150, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise the Updated Final Safety Analysis Report (SQN-TS-17-04)2018-03-0909 March 2018 Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise the Updated Final Safety Analysis Report (SQN-TS-17-04) CNL-18-021, Supplement to Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plants, Units 1 and 2 License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 2.4, QPTR, and TS 3.3.1, 'Reactor Trip System (RTS)2018-02-0808 February 2018 Supplement to Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plants, Units 1 and 2 License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 2.4, QPTR, and TS 3.3.1, 'Reactor Trip System (RTS) .. NL-18-021, Supplement to Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plants, Units 1 and 2 License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 2.4, Qptr, and TS 3.3.1, 'Reactor Trip System (RTS) .2018-02-0808 February 2018 Supplement to Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plants, Units 1 and 2 License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 2.4, Qptr, and TS 3.3.1, 'Reactor Trip System (RTS) .. CNL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power Syste2017-11-17017 November 2017 Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System. NL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System2017-11-17017 November 2017 Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System. NL-17-008, Sequoyah and Watts Bar - License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, Qptr, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014)2017-08-0707 August 2017 Sequoyah and Watts Bar - License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, Qptr, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014) CNL-17-008, License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, QPTR, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014)2017-08-0707 August 2017 License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, QPTR, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014) CNL-16-051, Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04)2017-03-13013 March 2017 Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04) CNL-16-121, Supplemental Information Regarding Proposed Technical Specification Change to Extend the Allowed Completion Time to Restore Essential Raw Cooling Water System Train to Operable Status from 72 Hours to 7 Days2016-07-22022 July 2016 Supplemental Information Regarding Proposed Technical Specification Change to Extend the Allowed Completion Time to Restore Essential Raw Cooling Water System Train to Operable Status from 72 Hours to 7 Days CNL-16-001, Application to Modify Sequoyah Nuclear Plant, Units 1 and 2 Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02)2016-05-26026 May 2016 Application to Modify Sequoyah Nuclear Plant, Units 1 and 2 Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02) CNL-16-018, License Amendment Request (SQN-TS-16-03) to Change the Completion Date of Cyber Security Plan Implementation Milestone 82016-05-16016 May 2016 License Amendment Request (SQN-TS-16-03) to Change the Completion Date of Cyber Security Plan Implementation Milestone 8 CNL-15-178, License Renewal Application - Clarifications (TAC Nos. MF0481 and MF0482)2015-08-28028 August 2015 License Renewal Application - Clarifications (TAC Nos. MF0481 and MF0482) CNL-15-164, Second Annual Update, License Renewal Application2015-08-14014 August 2015 Second Annual Update, License Renewal Application CNL-14-075, Redacted Version of License Amendment Request (SQN-TS-14-01) to Change the Completion Date of Cyber Security Plan Implementation Milestone 82014-05-27027 May 2014 Redacted Version of License Amendment Request (SQN-TS-14-01) to Change the Completion Date of Cyber Security Plan Implementation Milestone 8 ML13329A7172013-11-22022 November 2013 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) ML13281A8062013-08-0606 August 2013 Operating License Renewal, Site 40HA22 and Revision to Phase I Cultural Resources Survey Final Report, Hamilton County, Tn ML13199A2812013-07-0303 July 2013 Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04) 2024-08-28
[Table view] |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 February 2, 2010 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vic.e President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 -ISSUANCE OF AMENDMENT REGARDING ADOPTION OF TSTF-511, REVISION 0, "ELIMINATE WORKING HOUR RESTRICTIONS FROM TS 5.2.2 TO SUPPORT COMPLIANCE WITH 10 CFR PART 26" (TAC NOS. ME2439 AND ME2440)
Dear Mr. Swafford:
The U.S. Nuclear Regulatory Commission (NRC or Commission) has issued the enclosed Amendment No. 327 to Facility Operating License No. DPR-77 and Amendment No. 320 to Facility Operating License No. DPR-79 for the Sequoyah Nuclear Plant, Units 1 and 2, respectively.
The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated October 20, 2009. The amendments revise TS 6.2.2, "Facility Staff," to eliminate working hour restrictions in paragraph g to support compliance with the revisions to Title 10 of the Code of Federal Regulations (10 CFR), Part 26, "Fitness for Duty Programs." The changes are consistent with guidance contained in the NRC-approved Technical Specifications Task Force (TSTF) change traveler, TSTF-511, Revision 0, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26." The availability of this improvement was announced in the Federal Register on December 30, 2008 (73 FR 79923), as part of the consolidated line item improvement process.
P. -2 A copy of our related Safety Evaluation is also enclosed.
The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Sincerely, \t' Siva Project M'anager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328
Enclosures:
- 1. Amendment No. 327 to License No. DPR-77 Amendment No. 320 License No. 3. Safety Evaluation cc w/encls: Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 327 License No. DPR-77 1. The Nuclear Regulatory Commission (the Commission) has found that: The application for amendment by Tennessee Valley Authority (the licensee) dated October 20, 2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR) Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
-Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows: Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 327 ,are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. This license amendment is effective as of its date of issuance, to be implemented no later than 30 days after issuance.
FOR NUCLEAR.2fGULATORY COMMISSION ,{O'L homas H. Boyce., Chief t Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License and Technical Specifications Date of Issuance:
February 2, 2010 ATTACHMENT TO LICENSE AMENDMENT NO. FACILITY OPERATING LICENSE NO. DOCKET NO. 50-327 Replace Page 3 of Operating License DPR-77 with the attached page. Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change. REMOVE INSERT 6-2 6-2
-Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis, instrument calibration or associated with radioactive apparatus or components; and Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the Sequoyah and Watts Bar Unit 1 Nuclear Plants. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: Maximum Power Level The Tennessee Valley Authority is authorized to operate the facility at reactor core power levels not in excess of 3455 megawatts thermal. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 327 are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications. Initial Test Program The Tennessee Valley Authority shall conduct the post-fuel-loading initial test program (set forth in Section 14 of Tennessee Valley Authority's Final Safety Analysis Report, as amended), without making any major modifications of this program unless modifications have been identified and have received prior NRC approval.
Major modifications are defined as: Elimination of any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as being essential; Modification of test objectives, methods or acceptance criteria for any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as being essential; Performance of any test at power level different from there described; and Facility Operating License No. DPR-77 Amendment No. 327 ADMINISTRATIVE CONTROLS c. A Radiological Control technician#
shall be onsite when fuel is in the reactor. d. DELETED e. DELETED f. The Operations Superintendent shall hold a Senior Reactor Operator license. g. DELETED An individual shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift. #The Radiological Control technician may be offsite for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided immediate action is taken to fill the required positions.
SEQUOYAH -UNIT 6-2 Amendment No. 32, 58, 74,152,156,178, 227,233,240,266,281, 327 UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 320 License No. DPR-79 The Nuclear Regulatory Commission (the Commission) has found that: The application for amendment by Tennessee Valley Authority (the licensee) dated October 20, 2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR) Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
-2 Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as follows: Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 320 ,are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. This license amendment is effective as of its date of issuance, to be implemented no later than 30 days after issuance.
REGULATORY COMMISSION
...
II /;)'A-hL Thgmas H. Boyce., Chief 1 Plant Licensing Branch 11-2 iJ Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License and Technical Specifications Date of Issuance:
February 2, 2010 ATTACHMENT TO LICENSE AMENDMENT NO. FACILITY OPERATING LICENSE NO. DOCKET NO. Replace Page 3 of Operating License DPR-79 with the attached page. Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change. REMOVE INSERT 6-2 6-2 (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the Sequoyah and Watts Bar Unit 1 Nuclear Plants. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: Maximum Power Level The Tennessee Valley Authority is authorized to operate the facility at reactor core power levels not in excess of 3455 megawatts thermal. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 320 are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications. Initial Test Program The Tennessee Valley Authority shall conduct the post-fuel-loading initial test program (set forth in Section 14 of Tennessee Valley Authority's Final Safety Analysis Report, as amended), without making any major modifications of this program unless modifications have been identified and have received prior NRC approval.
Major modifications are defined as: Elimination of any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as being essential; Modification of test objectives, methods or acceptance criteria for any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as being essential; Performance of any test at power level different from there described; and Facility Operating License No. DPR-79 Amendment No. 320 ADMINISTRATIVE CONTROLS A Radiological Control technician#
shall be onsite when fuel is in the reactor. DELETED DELETED The Operations Superintendent shall hold a Senior Reactor Operator license. DELETED An individual shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift. #The Radiological Control technician may be offsite for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence proVided immediate action is taken to fill the required positions.
SEQUOYAH -UNIT 2 6-2 Amendment No. 50,66,142, 145, 169,218, 223, 230, 257, 272, 320 UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 327 TO FACILITY OPERATING LICENSE NO. DPR-77 AND AMENDMENT NO. 320 TO FACILITY OPERATING LICENSE NO. DPR-79 TENNESSEE VALLEY AUTHORITY SEOUOYAH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328
1.0 INTRODUCTION
By application dated October 20, 2009 (Agencywide Documents Access and Management System Accession No. ML092950340), Tennessee Valley Authority (TVA, the licensee) requested changes to the Technical Specifications (TSs) for the Sequoyah Nuclear Plant (SON), Units 1 and 2. The proposed changes would delete paragraph g of TS 6.2.2, "Facility Staff," to eliminate working hour restrictions in the TSs, as similar requirements are sufficiently imposed by Title 10 of the Code of Federal Regulations (10 CFR), Part 26, Subpart I. The licensee stated that the application is consistent with the U.S. Nuclear Regulatory Commission (NRC, Commission)-approved Technical Specifications Task Force (TSTF) change traveler, TSTF-511, Revision 0, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26." The availability of this TS improvement was announced in the Federal Register on December 30, 2008 (73 FR 79923), as part of the consolidated line item improvement process.
2.0 REGULATORY EVALUATION
The history of NRC regulations pertaining to prevention of worker impairment is summarized in the Federal Register notice containing the final rule that amended 10 CFR Part 26 (73 FR 16966, March 31,2008).
Subpart I, "Managing Fatigue," of 10 CFR Part 26 provides the regulatory requirements for managing worker fatigue at nuclear power plants. The NRC regulatory requirements related to the content of the TSs are contained in 10 CFR Part 50, Section 50.36, "Technical specifications." The regulations in 10 CFR 50.36 require that the TSs include items in the following categories:
(1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls.
The administrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner.
-2 The NRC guidance for the format and content of the licensee TSs can be found in NUREG-1431, Revision 3, "Standard Technical Specifications
-Westinghouse Plants," referred to as Standard Technical Specifications (STSs). Section 5 of STSs contains administrative controls.
Paragraph d of Section 5.2.2 of STSs contains requirements for administrative procedures to limit the working hours of personnel who perform safety-related functions.
This paragraph represents NRC guidance on how licensees TS requirements should address hour controls.
Licensees adhere to the guidance to varying degrees due to minor administrative differences and differences in each licensee's current licensing basis. The inconsistent level of adherence to NRC guidance has led to inconsistent TS interpretation and implementation.
This has also made it difficult for NRC to enforce the requirements.
The new requirements of 10 CFR Part 26, Subpart I supersede TS requirements for limiting the working hours of personnel as described in paragraph d of Section 5.2.2 of STSs. Subpart I of 10 CFR Part 26 distinguishes between work-hour controls and fatigue management and strengthens the requirements for both. Subpart I of 10 CFR Part 26 requires nuclear power plant licensees to ensure against worker fatigue adversely affecting public health and safety and the common defense and security by establishing clear and enforceable requirements for the management of worker fatigue. Licensees are required to implement Subpart I of 10 CFR Part 26 by October 1, 2009, as announced in the final rule that revised 10 CFR Part 26 (73 FR 16966, March 31,2008).
TSTF-511, Revision 0, proposed a change to STSs that would delete paragraph d of STS 5.2.2. This change was approved in the Federal Register notice on December 30, 2008 (73 FR 79923). 2.1 Adoption of TSTF-511, Revision 0, by SON, Units 1 and 2 Proper adoption of TSTF-511 and implementation of 10 CFR Part 26, Subpart I by TVA will provide reasonable assurance that TVA will maintain limits on the working hours of personnel who perform safety-related functions at SON, Unit 1 and 2. TVA stated the following:
TVA implemented 10 CFR Part 26 requirements for working hour restrictions on October 1, 2009. The 10 CFR Part 26 requirements are more restrictive than the current TS requirements and as such does not require a commitment.
TVA will implement the proposed TS changes within 30 days after approval is received.
This does represent a deviation from the consolidated line item improvement process (CLlIP). However, this will have no impact on the NRC staff's model safety evaluation (SE) published on December 30, 2008 (73 FR 79923). 3.0 TECHNICAL EVALUATION Controls on work hours for personnel at nuclear power plants are necessary to prevent worker fatigue from adversely affecting public health and safety and the common defense and security.
Work-hour controls for SON, Units 1 and 2 are currently located in paragraph g of TS 6.2.2. When the TS change is implemented, the regulatory requirements of 10 CFR 26, Subpart I will effectively replace the plant-specific TS requirements currently found in SON, Units 1 and 2 TS 6.2.2, paragraph
- g.
-3 The licensee proposed deleting paragraph g of TS 6.2.2. Since the new requirements of 10 CFR Part 26, SUbpart I took effect on October 1, 2009, TVA must follow its requirements on work-hour controls.
The NRC staff evaluated the licensee's proposed change against the applicable regulatory requirements listed in Section 2.0 of this safety evaluation.
The NRC staff also compared the proposed change to the change made to STSs by TSTF-511, Revision O. There is reasonable assurance that the licensee will comply with the regulations for work-hour controls through the requirements of 10 CFR Part 26, Subpart I, at all times at SON Units 1 and 2. TVA must comply with both the SON Units 1 and 2 TSs and the regulations in 10 CFR Part 26, until the TS change is implemented.
Therefore, the licensee will continue to prevent worker fatigue from adversely affecting public health and safety and the common defense and security.
Therefore, the NRC staff concludes that the proposed change is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Tennessee State official was notified of the proposed issuance of the amendments.
The State official had no comments.
5.0 ENVIRONMENTAL
CONSIDERATION The amendments change recordkeeping, reporting, or administrative procedures.
The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (74 FR 62837, December 1, 2009). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR51.22(c)(10).
Pursuant to 10 CFR51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributor:
V. Cusumano Date: February 2, 2010 P.
-A copy of our related Safety Evaluation is also enclosed.
The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Sincerely, IRA! Siva Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328
Enclosures:
- 1. Amendment No. 327 to License No. DPR-77 Amendment No. 320 License No. 3. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL2-2 r/f RidsAcrsAcnw
_MailCTR Resource RidsNrrDirsltsb Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl2-2 Resource RidsNrrPMSequoyah Resource RidsNrrlACSola Resource RidsOgcRp Resource RidsRgn2MailCenter Resource MHamm, NRRlDIRS/ITSB ADAMS Accession No ML093160084 NRR-058 OFFICE NRRlWBSP/PM NRR/LPL2-2/PM NRR/LPL2-2/LA DIRS/ITSB/BC OGC-not required NRR/LPL2-2/BC NAME JLamb SLingam CSoia RElliott EWiliiamson EBrown for TBoyce DATE 11/23/09 11/23/09 12/22/09 12/23/09 02/02/10 OFFICIAL AGENCY RECORD