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Category:Letter type:CNL
MONTHYEARCNL-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 CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) CNL-23-069, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) 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 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-23-061, 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 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 CNL-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)2023-08-0707 August 2023 License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) 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-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 CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)2023-06-28028 June 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06) CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . CNL-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023 Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-043, Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)2023-05-0404 May 2023 Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report CNL-23-002, Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Sche2023-03-20020 March 2023 Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Schedu CNL-23-021, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-03-0808 March 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-015, Expedited 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-22-08)2023-02-27027 February 2023 Expedited 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-22-08) CNL-23-003, Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A2023-01-30030 January 2023 Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A CNL-23-009, Response to Request for Additional Information Request to Revise Technical Specification 3.4.122023-01-0404 January 2023 Response to Request for Additional Information Request to Revise Technical Specification 3.4.12 CNL-23-008, Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-12-22022 December 2022 Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-109, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements2022-12-22022 December 2022 Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements CNL-22-101, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative WBN-2-ISI-012022-11-28028 November 2022 American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative WBN-2-ISI-01 CNL-22-106, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operat2022-11-28028 November 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operatio CNL-22-099, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2022-10-31031 October 2022 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-22-098, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 552022-10-17017 October 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 55 CNL-22-085, Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Al2022-09-0202 September 2022 Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alte CNL-22-077, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-08-11011 August 2022 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 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) CNL-22-070, Status Regarding the Improved Flood Mitigation System Project2022-06-30030 June 2022 Status Regarding the Improved Flood Mitigation System Project 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) CNL-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change2022-06-0909 June 2022 Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change CNL-22-068, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-06-0808 June 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-047, Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2022-05-23023 May 2022 Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-22-043, Response to Request for Additional Information and Confirmation of Information Regarding Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specification 3.7.8 to Support Shutdown Board.2022-05-0202 May 2022 Response to Request for Additional Information and Confirmation of Information Regarding Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specification 3.7.8 to Support Shutdown Board. CNL-22-046, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan.2022-04-28028 April 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan. 2024-01-09
[Table view] Category:Report
MONTHYEARCNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods 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 WBL-23-018, Revised Pressure and Temperature Limits Report (PTLR)2023-04-10010 April 2023 Revised Pressure and Temperature Limits Report (PTLR) CNL-23-002, Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Sche2023-03-20020 March 2023 Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Schedu WBL-22-034, Update to Fire Protection Report Figures Redacted2022-08-0101 August 2022 Update to Fire Protection Report Figures Redacted WBL-21-057, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-12-16016 December 2021 Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report CNL-21-018, Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance .2021-12-0909 December 2021 Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance . WBL-21-056, Revised Pressure and Temperature Limits Report (PTLR)2021-12-0909 December 2021 Revised Pressure and Temperature Limits Report (PTLR) ML21244A3452021-09-20020 September 2021 Proposed Alternative IST RR 9 to the Requirements of the ASME OM Code for Test Plan Group 6 Relief Valves CNL-21-055, Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-07-20020 July 2021 Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report CNL-21-040, Supplement to Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002)2021-03-23023 March 2021 Supplement to Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) ML21060A9132021-03-17017 March 2021 Final Environmental Assessment and Finding of No Significant Impact for Initial and Updated Decommissioning Funding Plans for Watts Bar ISFSI CNL-21-011, Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002)2021-02-25025 February 2021 Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) WBL-21-006, Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-02-11011 February 2021 Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report WBL-20-066, Revised Pressure and Temperature Limits Report (PTLR)2020-12-16016 December 2020 Revised Pressure and Temperature Limits Report (PTLR) CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User2020-12-16016 December 2020 10 CFR 71.95 Report for 3-60B Casks User CNL-20-074, Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2020-08-28028 August 2020 Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) WBL-20-004, Analysis of Capsule U from Watts Bar Unit 2 Reactor Vessel Radiation Surveillance Program2020-04-16016 April 2020 Analysis of Capsule U from Watts Bar Unit 2 Reactor Vessel Radiation Surveillance Program CNL-19-082, License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2019-10-10010 October 2019 License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) L-19-034, Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report2019-06-18018 June 2019 Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report L-19-026, Revised Pressure and Temperature Limits Report (PTLR)2019-04-0404 April 2019 Revised Pressure and Temperature Limits Report (PTLR) ML19039A0492019-02-0808 February 2019 Amd 1 to USAR Chapter 9 Auxiliary System NRC Additional Redactions ML19003A5692019-01-16016 January 2019 Review of the Fall 2017 Steam Generator Tube Inspection Report ML18242A0382018-08-30030 August 2018 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report CNL-18-092, Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02)2018-08-0101 August 2018 Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02) CNL-18-007, Seismic Probabilistic Risk Assessment Supplemental Information2018-04-10010 April 2018 Seismic Probabilistic Risk Assessment Supplemental Information ML17356A2692017-12-20020 December 2017 Construction Lessons Learned Report ML17313A1282017-11-0909 November 2017 Revised Pressure and Temperature Limits Report (PTLR) CNL-17-134, Transmittal of WCAP-18191-NP, Watts Bar Unit 2 Heatup and Cooldown Limit Curves for Normal Operation and Supplemental Reactor Vessel Integrity Evaluations2017-10-13013 October 2017 Transmittal of WCAP-18191-NP, Watts Bar Unit 2 Heatup and Cooldown Limit Curves for Normal Operation and Supplemental Reactor Vessel Integrity Evaluations ML17272A0192017-09-29029 September 2017 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report ML17263A1162017-09-20020 September 2017 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report ML17209A5542017-07-28028 July 2017 Cycle 14 Steam Generator Tube Inspection Report CNL-17-050, Submission of Technical Reports to Support a Public Meeting Regarding the Transition to the Reactor Oversight Process for the Mitigating Systems Performance Index2017-05-30030 May 2017 Submission of Technical Reports to Support a Public Meeting Regarding the Transition to the Reactor Oversight Process for the Mitigating Systems Performance Index ML16215A1042016-08-0202 August 2016 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System Report ML16113A0202016-04-22022 April 2016 Submittal of Title 10, Code of Federal Regulations 50.59 Summary Report CNL-16-038, Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information2016-03-31031 March 2016 Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information CNL-16-034, TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program2016-02-19019 February 2016 TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program CNL-15-263, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory2015-12-29029 December 2015 Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory CNL-15-204, Response to NRC Question Regarding the Revised Containment Analysis, Including Enclosure 3, WCAP-17834-NP, Revision 2, Wcobra/Trac Long Term LOCA M&E and Containment Integrity Analysis and Enclosure 4, Affidavit2015-09-21021 September 2015 Response to NRC Question Regarding the Revised Containment Analysis, Including Enclosure 3, WCAP-17834-NP, Revision 2, Wcobra/Trac Long Term LOCA M&E and Containment Integrity Analysis and Enclosure 4, Affidavit CNL-15-165, Submittal of Electromagnetic Interference (EMI) Survey Results2015-08-20020 August 2015 Submittal of Electromagnetic Interference (EMI) Survey Results CNL-15-143, the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report2015-07-31031 July 2015 the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report CNL-15-131, Individual Plant Examination of External Events (IPEEE) Report, Revision 32015-07-15015 July 2015 Individual Plant Examination of External Events (IPEEE) Report, Revision 3 CNL-15-106, 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information2015-07-0808 July 2015 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information CNL-15-097, Flood Hazard Reevaluation Report for Watts Bar Plant, Response to NRC Request for Information Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-06-16016 June 2015 Flood Hazard Reevaluation Report for Watts Bar Plant, Response to NRC Request for Information Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML15121A6562015-05-0101 May 2015 NRC Region II - CIB1 Watts Bar 2 Ip&S 194 Additional Questions Request List CNL-15-039, Severe Accident Management Alternatives for Reactor Coolant Pump Seals2015-04-10010 April 2015 Severe Accident Management Alternatives for Reactor Coolant Pump Seals CNL-15-043, Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc2015-03-25025 March 2015 Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid ML15030A5082015-01-30030 January 2015 Tritium Production Program, Updated Plans for Cycle 13 Operation and Updated Evaluation of the Radiological Impacts of Tritium Permeation Into the Reactor Coolant System CNL-14-212, Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2014-12-30030 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident 2024-01-03
[Table view] Category:Miscellaneous
MONTHYEARML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods WBL-22-034, Update to Fire Protection Report Figures Redacted2022-08-0101 August 2022 Update to Fire Protection Report Figures Redacted ML21244A3452021-09-20020 September 2021 Proposed Alternative IST RR 9 to the Requirements of the ASME OM Code for Test Plan Group 6 Relief Valves ML19003A5692019-01-16016 January 2019 Review of the Fall 2017 Steam Generator Tube Inspection Report ML18242A0382018-08-30030 August 2018 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report CNL-18-092, Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02)2018-08-0101 August 2018 Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02) CNL-18-007, Seismic Probabilistic Risk Assessment Supplemental Information2018-04-10010 April 2018 Seismic Probabilistic Risk Assessment Supplemental Information ML17313A1282017-11-0909 November 2017 Revised Pressure and Temperature Limits Report (PTLR) ML17272A0192017-09-29029 September 2017 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report ML17263A1162017-09-20020 September 2017 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report ML17209A5542017-07-28028 July 2017 Cycle 14 Steam Generator Tube Inspection Report ML16215A1042016-08-0202 August 2016 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System Report ML16113A0202016-04-22022 April 2016 Submittal of Title 10, Code of Federal Regulations 50.59 Summary Report CNL-16-038, Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information2016-03-31031 March 2016 Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information CNL-16-034, TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program2016-02-19019 February 2016 TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program CNL-15-263, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory2015-12-29029 December 2015 Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory CNL-15-165, Submittal of Electromagnetic Interference (EMI) Survey Results2015-08-20020 August 2015 Submittal of Electromagnetic Interference (EMI) Survey Results CNL-15-131, Individual Plant Examination of External Events (IPEEE) Report, Revision 32015-07-15015 July 2015 Individual Plant Examination of External Events (IPEEE) Report, Revision 3 CNL-15-106, 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information2015-07-0808 July 2015 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information ML15121A6562015-05-0101 May 2015 NRC Region II - CIB1 Watts Bar 2 Ip&S 194 Additional Questions Request List CNL-15-043, Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc2015-03-25025 March 2015 Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid CNL-14-212, Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2014-12-30030 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML14163A6582014-09-18018 September 2014 Closeout of Generic Letter, 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML14212A6032014-07-31031 July 2014 WBRD-50-391/86-60 - Final Report and Revised Completion Schedule IR 05000391/19860602014-07-31031 July 2014 WBRD-50-391/86-60 - Final Report and Revised Completion Schedule ML14149A1502014-06-16016 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14133A5422014-05-23023 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13246A0222013-08-28028 August 2013 Submittal of Pre-op Test Instruction ML13178A2812013-06-26026 June 2013 10 CFR 50.59 Summary Report Supplement ML13144A5762013-05-22022 May 2013 Watt Bar, Units 1 & 2, Report of Drug Testing Error in Accordance with 10 CFR 26.719(c)(1) ML13126A2942013-04-29029 April 2013 10 CFR 50.59 Summary Report ML13121A0602013-04-29029 April 2013 Commitment Summary Report ML13080A3632013-03-18018 March 2013 Enclosure 3, Summer 2011 Compliance Survey for Watts Bar Nuclear Plant Outfall Passive Mixing Zone ML13080A3662013-03-18018 March 2013 Enclosure 1, Summer 2010 Compliance Survey for Watts Bar Nuclear Plant Outfall Passive Mixing Zone ML13080A0732013-03-12012 March 2013 Extension Request Regarding the Flooding Hazard Reevaluation Report Required by NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation.. ML13175A1352013-03-0505 March 2013 2-PTI-092-03, Revision 0, Nuclear Instrumentation Source Range Noise Checks During Hot Functional Testing. ML12356A3172012-12-17017 December 2012 Submittal of Pre-op Test Instruction, 2-PTI-063-06, Revision 0, Safety Injection System Check Valve Test. ML12335A3402012-11-27027 November 2012 Tennessee Valley Authority - Fleet Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding the Flooding Walkdown Results of Recommendation 2.3 of the Near-Term Task Force Review of ML13108A2842012-11-12012 November 2012 Unit 1, Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report ML13175A1362012-11-0808 November 2012 2-PTI-099-06, Revision 0, Reactor Protection Setpoint Verification. ML13175A1342012-11-0101 November 2012 2-PTI-082-02, Revision 0, Rod Control - Non Hft. ML13175A1332012-10-22022 October 2012 2-PTI-085-01, Revision 0, Rod Control Functional Test. ML12236A1642012-07-19019 July 2012 Enclosure 1 Evaluation of Proposed Changes Tennessee Valley Authority Watts Bar Nuclear Plant, Unit 1 ML12223A1832012-03-29029 March 2012 Environmental Protection Agency 2012 - Facility Detail Report - Environmental Facts Warehouse Fii - Moccasin Bend Wwtp ML11362A0562011-12-20020 December 2011 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 7 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 7 ML11341A1572011-11-30030 November 2011 Attachments 7 Through 9, WNA-CN-00157-WBT-NP, Revision 1, CAW-11-3316, and WBT-D-3566 Np, Incore Instrument System Signal Processing System Isolation Requirement ML11326A2842011-11-18018 November 2011 Commitment Summary Report ML11257A0502011-08-31031 August 2011 Attachment 7, WCAP-17427-NP, Rev. 1, Watts Bar Nuclear Plant Unit 2 Common Q Post Accident Monitoring System Computer Security Assessment, Attachment 8, Application for Withholding Proprietary Information from Public Disclosure and Attachme ML1104003852011-02-0707 February 2011 Enclosure 2, Appendix a, Hydrothermal Effects on the Ichthyhoplankton from the Watts Bar Nuclear Plant Supplemental Condenser Cooling Water Outfall in Upper Chickamauga Reservoir ML1104003842011-02-0707 February 2011 Enclosure 1, Hydrothermal Effects on the Ichthyoplankton from Watts Bar Nuclear Plant Supplemental Condenser Cooling Water Outfall in Upper Chickamauga Reservoir 2024-01-03
[Table view] |
Text
Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2 Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381 CNL-1 6-034 February 19, 2016 10 CER 50.4(b)(6) 10 CFR 50.34(b) 10 CFR 2.390 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant Unit 2 Facility Operating License No. NPF-96 NRC Docket No. 50-391
Subject:
TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program
References:
- 1. TIVA Letter to NRC, dated July 27, 1983 (ML073530375)
- 2. NUREG-0847 Supplement 15 "Safety Evaluation Report - Related to the Operation of Watts Bar Nuclear Plant, Units land 2," dated June 1995 In Reference 1, the Tennessee Valley Authority (TIVA) committed to provide the Nuclear Regulatory Commission (NRC) with the following information for the Watts Bar Nuclear Plants (WBN) related to the closure of the Action l.D.1 in NUREG-0660, "NRC Action Plan Developed as a Result of the TMI-2 Accident," regarding the control room design review (CRDR) program:
- TIVA will submit the results of the additional noise measurements 120 days after fuel loading. As noted in Table 18.1 of Reference 2, "The NRC will review the results of the sound/noise survey, discussed below, which will be completed by TVA 120 days after fuel load, in relation to NUREG-0700 Guideline 6.1.5.5, 'Auditory Environment'."
TVA will take a complete set of color photographs of all panels located in the main control rooms and auxiliary control rooms after the respective units are operational for submittal to NRC 120 days after fuel loading.
Security Sensitive Information -Withhold This page is decontrolled when separated from Enclosure2 Under 10 CFR 2.390 A1?P,,'
Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2 U.S. Nuclear Regulatory Commission CNL-1 6-034 Page 2 February 19, 2016 provides the results of the WBN Unit 2 main control room noise survey that was performed in accordance with NUREG-0700 Guideline 6.1.5.5, "Auditory Environment,"
requirements. Enclosure 1, Table 3, 'Hazard Assessment Results/Summaries," lists the five WBN Unit 2 main control room locations and the corresponding noise measurement at each location. Page E1-6 depicts the five main control room locations where the noise measurements were taken. Main control room positions 1 and 2 are located behind the horseshoe where normal communications are not performed. Normal control room communications are performed in positions 3, 4, and, 5 and are no more than 7 feet apart. Per NUREG-0700, these background noise levels are within the range where verbal communication should be intelligible using normal to raised voice levels. provides a compact disk (CD) containing the color photographs of the main control room and auxiliary control room panels. The information provided in Enclosure 2 contains security sensitive information in accordance with 10 CFR 73.21(a)(1)(i). Because of the sensitive nature of this submittal, TVA request that this information be withheld from public disclosure in accordance with 10 CFR 2.390.
There are no new regulatory commitments in this letter. If you have any questions, please contact Gordon Arent, Director of Watts Bar Site Licensing, at (423) 365-2004.
Respectfully, J. W. Shea Vice President, Nuclear Licensing
Enclosures:
- 1. Watts Bar Nuclear Plant, Unit 2 Main Control Room Noise Survey
- 2. Watts Bar Nuclear Plant, Unit 2 Main Control Room and Auxiliary Control Room Panel Photographs cc (w/o Enclosures):
NRC Regional Administrator - Region II NRC Senior Resident Inspector, Unit 1 NRC Senior Resident Inspector, Unit 2 Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2
Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2 ENCLOSURE 1 Tennessee Valley Authority Watts Bar Nuclear Plant, Unit 2 Main Control Room Noise Survey CNL-1 6-034 El-i of 6 Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2
SALLIANT Streamlined Assesment Report WBN0-175 Date of Report:
(MM/DD/YY) Date(s) of Assessment: Report No.: ICustomer:
ILocation: Customer Customer
Contact:
Point of [Customer Work Authorization:
021/611/6WBN0-175 TVA Spring City, TN Chad lsaacs 1411167 A. Scope of Assessment:
Alliant Corporation (Alliant) was tasked with conducting an area noise survey of the Unit 2 side of the Main Control Room at Watts Bar Nuclear Plant located in Spring City, TN. The survey was performed to assess where background noise levels met to the requirements of NUREG-0700 paragraph 12.1.2.5-3, which state "Backgroundnoise levels should not exceed 65 dB(A). Additional/Information: Operatorseight feet apart will have to speak loudly to be heard in the presence of a 65 diB(A) backgroundnoise. Therefore, if workstations, display panels, or control interfaces are widely separated in the control room, the background noise limit should be reduced." Alliant placed noise dosimeters in the five locations on the Unit 2 side that are described in Table 3 of this report.
Hazard ifCAS No.,
applicable Assessment Method OELUIM)
(Include Shift-Length Adjusted OEL (Include UIM) Source of OEL Noise NA NA NA NA NA Table 2. Hazard Controls (Check all that apply.)
Engineering PersonalProtective Equipment
[] None [] None El General ventilation El Eye protection; Type:___
El Enclosure of hazards; Type: - El Face protection; Type:
El Barriers to exposure; Type: __ [ Respiratory Protection; Type:.
El Local exhaust ventilation; Type: [El Head protection; Type:___
El Other; Type: __ [ Foot protection; Type:
Administrative El Electrical protective devices; Type:
[] None El Hand Protection; Type:__
El Lengthened rest breaks El Hearing protection; Type:___
El Additional relief workers El Other; Type:
El Exercise breaks to vary body motions Hazard Control Comments:
El Rotating workers El Hazard-specific training; Type: ____
El Other; Type:
B. Findings and Observations
- 1. During thiswould survey, the A-weighted the sameequivalent noise level (LAeq) was measured at the five locations depicted on the attached layout. LAeq is the noise level that represent amount of noise energy as in the actual noise, effectively giving an average level over the measurement period.
- 2. The A-weighting filter covers the full audio range - 20 Hz to 20 kHz, and it is used because it most closely represents the response of the human ear at the lower frequency levels.
- 3. Since area monitoring was performed, not personal monitoring, time-weighted averages are not applicable. The noise levels reported in Table 3 do not represent personal exposures and should not be interpreted as such.
- 4. Sample positions 3, 4 and 5 are located within the main operating area of the Unit 2 control room, and are no further than seven (7) feet apart from one another. Based upon Figure 12.3, Voice/leve/ as a function of distance and ambient noise level in NUREG-0700, these background noise levels are well within the range where verbal communication should be intelligible using normal or raised voice levels.
E. Report Preparation __________________
____________Report Prepared By ,eReport Approved By Signature __ _ __ _ __ _ __ _
Name Carson Vick ierece A. Douglas, CiH, (SP Date 2119/16 2/19/16 F. Disclaimer This report is for the sole use of Customer and Alliant Corporation. Use of this report by any other parties will be at such party's sole risk, and Alliant Corporation disclaims liability for any such use or reliance by third parties. The results presented in this report are indicative of conditions at the time of the survey. This study does not purport to include every health hazard at this location, and only those areas and exposures specifically mentioned were evaluated.
CNL-1 6-034 E1-2 of 6 Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2
SALLIANT Streamlined Assesment Report WBN0-175 Sample DaeArea Sample LengthMesrdLq No. Dae(Minutes)MesrdLq 1 1114116 Corner of Control Counter of Unit 2 246 66.6 2 1/t4116 Corner of Control Counter of Unit 2 245 66.2 3 1/14/16 North Center of Unit 2 Section of Control Room 244 63.6 4 1/14/16 -Center of Unit 2 Section of Control Room 244 64.3 5 1/'14/16 -Shift Managers Desk - West Side of Unit 2 Section of Control Room 243 63.2 rhis information contained in this report is subject to protection under the Privacy Act of 1974.
ND -Not Detected TWA -Time Weighted Average P -Personal Sample NRR - Noise Reduction Rating NA -Not Applicable PEL -Permissible Exposure Limit dBA - decibel A-weighted filter HCP - Hearing Conservation Program
< -Less Than AL -Action Limit LAeq - A-weighted equivalent noise level CNL-1 6-034 E1-3 of 6 Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2
ii +
I-
<C~TF~9QI '4~L~~ ~c - i'l
~iA FO SNoise SampleMonitori Locationng i
1 I
\
/
7, CNL-1 6- E1-4 of 6 Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2
12 WORKPLACE DESIGN 12.1 Control Room 12.1.2 Control Room Environment 12.1.2.5 Auditory Environment 12.1.2.5-1 General The acoustic design of the control room should ensure that verbal communications among personnel are not impaired; auditory signals are readily detected; and auditory distraction, irritation, and fatigue are minimized.0 700 12.1.2.5-2 Background Noise Background noise should not impair verbal communication between any two points in the main operating area.
Additional Information: Verbal communications should be intelligible using normal or slightly raised voice levels. Figure 12.3 shows the voice levels needed for spoken communication over specified distances in the presence of different levels of background noise. Intelligibility of speech in noise is affected by the frequency spectra of the noise and of the speakers' voices and by the speakers' hearing sensitivity.OOso 16 32 00 16 LU w-. I-.
LU C',.-
~w 8 ozU LU C,
'-'C wS~ ~ z'C I.-
'C 00 w 5 2
0.5 1
0.25 30 40 50 60 70 80 90 100 110 AMBIENT NOISE LEVEL, dB (A)
Figure 12.3 Voice level as a function of distance and ambient noise level 12.1.2.5-3 Background Noise Level Background noise levels should not exceed 65 dB(A).
Additional Information: Operators eight feet apart will have to speak loudly to be heard in the presence of a 65 dB(A) background noise. Therefore, if workstations, display panels, or control interfaces are widely separated in the control room, the background noise limit should be reduced. 070 0 CNL-1 6-034 E1-5 of 6 Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2 480
12 WORKPLACE DESIGN 12.1 Control Room 12.1.2 Control Room Environment 12.1.2.5 Auditory Environment 12.1.2.5-4 Further Reductions Where communications between the main operating area and other control room locations are necessary, and voice transmission systems are not provided, further reductions in background noise should be implemented.°0 °° 12.1.2.5-5 Noise Distractions Noise distractions generated either inside or outside the control room should be minimized.°70 0 12.1.2.5-6 Reverberation Time and Sound Absorption The acoustical treatment of the control room should limit reverberation time to 1 second or less.0 7"0' 590 CNL-1 6-034 E1-6of 6 Security Sensitive Information -W\ithhold Under 10 CER 2.390 This page is decontrolled when separated from Enclosure 2 481
Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2 ENCLOSURE 2 Tennessee Valley Authority Watts Bar Nuclear Plant, Unit 2 Main Control Room and Auxiliary Control Room Panel Photographs (see attached CD)
CNL-1 6-034 E2-1 of 1 Security Sensitive Information This page is decontrolled when- Withhold separatedUnder from 10 CFR 2.390 Enclosure 2
Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2 Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381 CNL-1 6-034 February 19, 2016 10 CER 50.4(b)(6) 10 CFR 50.34(b) 10 CFR 2.390 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant Unit 2 Facility Operating License No. NPF-96 NRC Docket No. 50-391
Subject:
TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program
References:
- 1. TIVA Letter to NRC, dated July 27, 1983 (ML073530375)
- 2. NUREG-0847 Supplement 15 "Safety Evaluation Report - Related to the Operation of Watts Bar Nuclear Plant, Units land 2," dated June 1995 In Reference 1, the Tennessee Valley Authority (TIVA) committed to provide the Nuclear Regulatory Commission (NRC) with the following information for the Watts Bar Nuclear Plants (WBN) related to the closure of the Action l.D.1 in NUREG-0660, "NRC Action Plan Developed as a Result of the TMI-2 Accident," regarding the control room design review (CRDR) program:
- TIVA will submit the results of the additional noise measurements 120 days after fuel loading. As noted in Table 18.1 of Reference 2, "The NRC will review the results of the sound/noise survey, discussed below, which will be completed by TVA 120 days after fuel load, in relation to NUREG-0700 Guideline 6.1.5.5, 'Auditory Environment'."
TVA will take a complete set of color photographs of all panels located in the main control rooms and auxiliary control rooms after the respective units are operational for submittal to NRC 120 days after fuel loading.
Security Sensitive Information -Withhold This page is decontrolled when separated from Enclosure2 Under 10 CFR 2.390 A1?P,,'
Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2 U.S. Nuclear Regulatory Commission CNL-1 6-034 Page 2 February 19, 2016 provides the results of the WBN Unit 2 main control room noise survey that was performed in accordance with NUREG-0700 Guideline 6.1.5.5, "Auditory Environment,"
requirements. Enclosure 1, Table 3, 'Hazard Assessment Results/Summaries," lists the five WBN Unit 2 main control room locations and the corresponding noise measurement at each location. Page E1-6 depicts the five main control room locations where the noise measurements were taken. Main control room positions 1 and 2 are located behind the horseshoe where normal communications are not performed. Normal control room communications are performed in positions 3, 4, and, 5 and are no more than 7 feet apart. Per NUREG-0700, these background noise levels are within the range where verbal communication should be intelligible using normal to raised voice levels. provides a compact disk (CD) containing the color photographs of the main control room and auxiliary control room panels. The information provided in Enclosure 2 contains security sensitive information in accordance with 10 CFR 73.21(a)(1)(i). Because of the sensitive nature of this submittal, TVA request that this information be withheld from public disclosure in accordance with 10 CFR 2.390.
There are no new regulatory commitments in this letter. If you have any questions, please contact Gordon Arent, Director of Watts Bar Site Licensing, at (423) 365-2004.
Respectfully, J. W. Shea Vice President, Nuclear Licensing
Enclosures:
- 1. Watts Bar Nuclear Plant, Unit 2 Main Control Room Noise Survey
- 2. Watts Bar Nuclear Plant, Unit 2 Main Control Room and Auxiliary Control Room Panel Photographs cc (w/o Enclosures):
NRC Regional Administrator - Region II NRC Senior Resident Inspector, Unit 1 NRC Senior Resident Inspector, Unit 2 Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2
Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2 ENCLOSURE 1 Tennessee Valley Authority Watts Bar Nuclear Plant, Unit 2 Main Control Room Noise Survey CNL-1 6-034 El-i of 6 Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2
SALLIANT Streamlined Assesment Report WBN0-175 Date of Report:
(MM/DD/YY) Date(s) of Assessment: Report No.: ICustomer:
ILocation: Customer Customer
Contact:
Point of [Customer Work Authorization:
021/611/6WBN0-175 TVA Spring City, TN Chad lsaacs 1411167 A. Scope of Assessment:
Alliant Corporation (Alliant) was tasked with conducting an area noise survey of the Unit 2 side of the Main Control Room at Watts Bar Nuclear Plant located in Spring City, TN. The survey was performed to assess where background noise levels met to the requirements of NUREG-0700 paragraph 12.1.2.5-3, which state "Backgroundnoise levels should not exceed 65 dB(A). Additional/Information: Operatorseight feet apart will have to speak loudly to be heard in the presence of a 65 diB(A) backgroundnoise. Therefore, if workstations, display panels, or control interfaces are widely separated in the control room, the background noise limit should be reduced." Alliant placed noise dosimeters in the five locations on the Unit 2 side that are described in Table 3 of this report.
Hazard ifCAS No.,
applicable Assessment Method OELUIM)
(Include Shift-Length Adjusted OEL (Include UIM) Source of OEL Noise NA NA NA NA NA Table 2. Hazard Controls (Check all that apply.)
Engineering PersonalProtective Equipment
[] None [] None El General ventilation El Eye protection; Type:___
El Enclosure of hazards; Type: - El Face protection; Type:
El Barriers to exposure; Type: __ [ Respiratory Protection; Type:.
El Local exhaust ventilation; Type: [El Head protection; Type:___
El Other; Type: __ [ Foot protection; Type:
Administrative El Electrical protective devices; Type:
[] None El Hand Protection; Type:__
El Lengthened rest breaks El Hearing protection; Type:___
El Additional relief workers El Other; Type:
El Exercise breaks to vary body motions Hazard Control Comments:
El Rotating workers El Hazard-specific training; Type: ____
El Other; Type:
B. Findings and Observations
- 1. During thiswould survey, the A-weighted the sameequivalent noise level (LAeq) was measured at the five locations depicted on the attached layout. LAeq is the noise level that represent amount of noise energy as in the actual noise, effectively giving an average level over the measurement period.
- 2. The A-weighting filter covers the full audio range - 20 Hz to 20 kHz, and it is used because it most closely represents the response of the human ear at the lower frequency levels.
- 3. Since area monitoring was performed, not personal monitoring, time-weighted averages are not applicable. The noise levels reported in Table 3 do not represent personal exposures and should not be interpreted as such.
- 4. Sample positions 3, 4 and 5 are located within the main operating area of the Unit 2 control room, and are no further than seven (7) feet apart from one another. Based upon Figure 12.3, Voice/leve/ as a function of distance and ambient noise level in NUREG-0700, these background noise levels are well within the range where verbal communication should be intelligible using normal or raised voice levels.
E. Report Preparation __________________
____________Report Prepared By ,eReport Approved By Signature __ _ __ _ __ _ __ _
Name Carson Vick ierece A. Douglas, CiH, (SP Date 2119/16 2/19/16 F. Disclaimer This report is for the sole use of Customer and Alliant Corporation. Use of this report by any other parties will be at such party's sole risk, and Alliant Corporation disclaims liability for any such use or reliance by third parties. The results presented in this report are indicative of conditions at the time of the survey. This study does not purport to include every health hazard at this location, and only those areas and exposures specifically mentioned were evaluated.
CNL-1 6-034 E1-2 of 6 Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2
SALLIANT Streamlined Assesment Report WBN0-175 Sample DaeArea Sample LengthMesrdLq No. Dae(Minutes)MesrdLq 1 1114116 Corner of Control Counter of Unit 2 246 66.6 2 1/t4116 Corner of Control Counter of Unit 2 245 66.2 3 1/14/16 North Center of Unit 2 Section of Control Room 244 63.6 4 1/14/16 -Center of Unit 2 Section of Control Room 244 64.3 5 1/'14/16 -Shift Managers Desk - West Side of Unit 2 Section of Control Room 243 63.2 rhis information contained in this report is subject to protection under the Privacy Act of 1974.
ND -Not Detected TWA -Time Weighted Average P -Personal Sample NRR - Noise Reduction Rating NA -Not Applicable PEL -Permissible Exposure Limit dBA - decibel A-weighted filter HCP - Hearing Conservation Program
< -Less Than AL -Action Limit LAeq - A-weighted equivalent noise level CNL-1 6-034 E1-3 of 6 Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2
ii +
I-
<C~TF~9QI '4~L~~ ~c - i'l
~iA FO SNoise SampleMonitori Locationng i
1 I
\
/
7, CNL-1 6- E1-4 of 6 Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2
12 WORKPLACE DESIGN 12.1 Control Room 12.1.2 Control Room Environment 12.1.2.5 Auditory Environment 12.1.2.5-1 General The acoustic design of the control room should ensure that verbal communications among personnel are not impaired; auditory signals are readily detected; and auditory distraction, irritation, and fatigue are minimized.0 700 12.1.2.5-2 Background Noise Background noise should not impair verbal communication between any two points in the main operating area.
Additional Information: Verbal communications should be intelligible using normal or slightly raised voice levels. Figure 12.3 shows the voice levels needed for spoken communication over specified distances in the presence of different levels of background noise. Intelligibility of speech in noise is affected by the frequency spectra of the noise and of the speakers' voices and by the speakers' hearing sensitivity.OOso 16 32 00 16 LU w-. I-.
LU C',.-
~w 8 ozU LU C,
'-'C wS~ ~ z'C I.-
'C 00 w 5 2
0.5 1
0.25 30 40 50 60 70 80 90 100 110 AMBIENT NOISE LEVEL, dB (A)
Figure 12.3 Voice level as a function of distance and ambient noise level 12.1.2.5-3 Background Noise Level Background noise levels should not exceed 65 dB(A).
Additional Information: Operators eight feet apart will have to speak loudly to be heard in the presence of a 65 dB(A) background noise. Therefore, if workstations, display panels, or control interfaces are widely separated in the control room, the background noise limit should be reduced. 070 0 CNL-1 6-034 E1-5 of 6 Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2 480
12 WORKPLACE DESIGN 12.1 Control Room 12.1.2 Control Room Environment 12.1.2.5 Auditory Environment 12.1.2.5-4 Further Reductions Where communications between the main operating area and other control room locations are necessary, and voice transmission systems are not provided, further reductions in background noise should be implemented.°0 °° 12.1.2.5-5 Noise Distractions Noise distractions generated either inside or outside the control room should be minimized.°70 0 12.1.2.5-6 Reverberation Time and Sound Absorption The acoustical treatment of the control room should limit reverberation time to 1 second or less.0 7"0' 590 CNL-1 6-034 E1-6of 6 Security Sensitive Information -W\ithhold Under 10 CER 2.390 This page is decontrolled when separated from Enclosure 2 481
Security Sensitive Information - Withhold Under 10 CFR 2.390 This page is decontrolled when separated from Enclosure 2 ENCLOSURE 2 Tennessee Valley Authority Watts Bar Nuclear Plant, Unit 2 Main Control Room and Auxiliary Control Room Panel Photographs (see attached CD)
CNL-1 6-034 E2-1 of 1 Security Sensitive Information This page is decontrolled when- Withhold separatedUnder from 10 CFR 2.390 Enclosure 2