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Category:Letter type:CNL
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 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 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report 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), CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS 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 CNL-24-036, – 10 CFR 50.46 Annual Report2024-04-25025 April 2024 – 10 CFR 50.46 Annual Report 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 CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) CNL-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-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule CNL-24-031, Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-03-18018 March 2024 Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance CNL-24-028, Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-24-027, 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-24-026, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, 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 CNL-24-013, Cycle 22 Reload Analysis Report2024-03-14014 March 2024 Cycle 22 Reload Analysis Report CNL-24-012, Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-02-28028 February 2024 Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance CNL-24-023, Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 CNL-24-011, Application for Subsequent Renewed Operating Licenses, Supplemental Information - Neutron Fluence Analyses Methodology2024-01-22022 January 2024 Application for Subsequent Renewed Operating Licenses, Supplemental Information - Neutron Fluence Analyses Methodology CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 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-23-005, Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011)2023-12-26026 December 2023 Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011) 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-23-068, 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-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan 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-23-061, 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-23-059, 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-23-057, 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-23-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472023-07-0303 July 2023 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 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 . 2024-09-24
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Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-15-138 August 28, 2015 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390
Subject:
Tennessee Valley Authority Nuclear Power Group Response to NRC Regulatory Issue Summary 2014-13 Planned Licensing Action Submittals for All Power Reactor Licensees The purpose of this letter is to provide the Nuclear Regulatory Commission (NRC) staff with the Tennessee Valley Authority (TVA) voluntary response to the NRC Regulatory Issue Summary (RIS) 2014-13 that requested power reactor licensees to voluntarily provide information regarding the number of planned licensing actions to be submitted for NRC review in the next three calendar years and the planned power uprates that will be submitted in the next five calendar years.
Enclosures 1, 2, and 3, to this letter provide the estimated licensing actions for Browns Ferry Nuclear Plant Units 1, 2, and 3, Sequoyah Nuclear Plant Units 1 and 2, and Watts Bar Nuclear Plant, Unit 1, respectively. Watts Bar Nuclear Plant, Unit 2 has not received its operating license; therefore planned Watts Bar Unit 2 licensing actions are not included in this submittal. provides the planned power uprate application information for the Browns Ferry Nuclear Plant Units 1, 2, and 3. As noted in RIS 2014-13, licensee responses to this request are not binding and can be updated as needed.
Nuclear Regulatory Commission CNL-15-138 Page2 August 28, 2015 There are no new regulatory commitments contained in this letter. Should you have any questions, please contact Russ Wells at (423) 751-8130 .
. Shea Vice President, Nuclear Licensing ROW: EDS Enclosures
- 1. Tables of Estimated Licensing Actions for Browns Ferry Nuclear Plant, Units 1, 2, and 3
- 2. Tables of Estimated Licensing Actions for Sequoyah Nuclear Plant, Units 1 and 2
- 3. Tables of Estimated Licensing Actions for Watts Bar Nuclear Plant, Unit 1
- 4. Plans for Power Uprates cc (Enclosures):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Senior Resident Inspector- Sequoyah Nuclear Plant NRC Senior Resident Inspector- Watts Bar Nuclear Plant NRR Project Manager - Browns Ferry Nuclear Plant NRR Project Manager- Sequoyah Nuclear Plant NRR Project Manager - Watts Bar Nuclear Plant Tracy Orf, NRC Division of Operating Reactor Licensing Technical Assistant, Mail Stop O-C2
ENCLOSURE 1 Table of Estimated Licensing Actions1 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296 Licensing Licensing Licensing Action Description Projected Outage Comments (As Needed)
Action Action Submittal Related?
Number Date If so, Date Needed 1 Relief Request RR for Unit 2 Reactor Vessel 09/16/2015 No (RR) Circumferential Weld 2 License Revise Technical Specification 09/16/2015 No Amendment (TS) Section 3.3.5.1, Request (LAR) Emergency Core Cooling System (ECCS) Preferred Pump Logic 3 RR RR for Unit 3 Reactor Vessel 09/23/2015 No Circumferential Weld 4 LAR Revise Residual Heat Removal 09/25/2015 No Service Water (RHRSW) TS and Bases for consistency with BFN design bases and rules of usage reflected in TS Section 1.0 5 LAR TS 2.1.1.2, Revise Safety Limit 09/25/2015 Yes, Fall Minimum Critical Power Ratio 2016 (SLMCPR) for BFN Unit 1 6 LAR Revise TS frequency for 10/31/2015 No Augmented IST components 7 LAR Revise TS 5.3.1 related to 12/31/2015 No operator training requirements
- 1. The projected submittal dates are subject to change as discussed periodically with the NRC Project Manager. Also, operational considerations may result in the addition of licensing actions that are not currently listed.
CNL-15-138 E 1 of 5
ENCLOSURE 1 Table of Estimated Licensing Actions1 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296 Licensing Licensing Licensing Action Description Projected Outage Comments (As Needed)
Action Action Submittal Related?
Number Date If so, Date Needed 8 LAR Extend Surveillance 12/31/2015 No Requirement (SR) 3.3.8.2 Channel Calibration from 184 days to 18 months 9 LAR Technical Specification Task 3/31/2016 No Force (TSTF) 523, Managing Gas Accumulation 10 LAR Revise SR 3.1.7.7 re 44 gpm 05/20/2016 No SLC pump flow rate 11 LAR Electric Board Room / Control 05/31/2016 No Bay Chillers 12 LAR TSTF-425, Relocate 06/30/2016 No Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b 13 LAR Add TS 3.0.2 applicability to TS 06/30/2016 No 5.5.2 14 LAR TSTF-522, Ventilation System 06/30/2016 No Surveillance Requirements 15 LAR TS 5.5.12 Primary Containment 09/01/2016 Yes, Spring Applies to all three units Leakage Rate Testing Program 2019
- Change program guideline reference
- 1. The projected submittal dates are subject to change as discussed periodically with the NRC Project Manager. Also, operational considerations may result in the addition of licensing actions that are not currently listed.
CNL-15-138 E 2 of 5
ENCLOSURE 2 Table of Estimated Licensing Actions1 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328 Licensing Licensing Licensing Action Description Projected Outage Comments (As Needed)
Action Action Submittal Related?
Number Date If so, Date Needed 1 LAR Revise TS 6.3.1 related to 12/31/2015 No operator training requirements 2 LAR Revise Emergency Diesel 06/30/2016 No Generator (EDG) Frequency Band
- 1. The projected submittal dates are subject to change as discussed periodically with the NRC Project Manager. Also, operational considerations may result in the addition of licensing actions that are not currently listed.
CNL-15-138 E 3 of 5
ENCLOSURE 3 Table of Estimated Licensing Actions1,2 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390 Licensing Licensing Licensing Action Description Projected Outage Comments (As Needed)
Action Action Submittal Related?
Number Date If so, Date Needed 1 LAR TSTF 372, Addition of LCO 10/30/2015 No 3.0.8, Inoperability of Snubbers 2 LAR ABGTS - TSTF 287 10/30/2015 No 3 LAR TS Tables 3.3.1-1 and 3.3.2-1: 12/31/2015 No Systems 46 and 47 pressure switches 4 LAR Emergency Diesel Generator / 01/31/2016 No Electrical Board TS 3.8.1 Allowed Outage Time 5 LAR TSTF-493, LSSS Setpoint 02/15/2017 No Methodology 6 LAR TSTF-340, AFW Mode 02/17/2017 No Transition 7 LAR Improved TS Rev 4 Upgrade 02/17/2017 No
- 1. The projected submittal dates are subject to change as discussed periodically with the NRC Project Manager. Also, operational considerations may result in the addition of licensing actions that are not currently listed.
CNL-15-138 E 4 of 5
ENCLOSURE 4 Plans for Power Uprates RIS 2014-13 states:
The licensee is requested to address if they plan to apply for a power uprate (please indicate whether it is a measurement uncertainty recapture (MUR), stretch, or extended power uprate (EPU)) in the next 5 calendar years. (If the answer is no, please skip the next four questions.)
x What percent increase in power from the current licensed thermal power (CLTP) limit does the licensee plan to apply for? (Please write N/A in any unit that does not apply or that is not planned for a power uprate.)
Unit 1______% Unit 2______% Unit 3______% Unit 4______%
x What is the planned increase from the CLTP limit in megawatts thermal?
Unit 1______MWt Unit 2______MWt Unit 3______MWt Unit 4______MWt x What is the expected schedule for filing the application (month/year)? (If the month is not known, please provide the quarter and/or year.)
Unit 1______ Unit 2______ Unit 3______ Unit 4______
x What is the expected date for power ascension with uprated conditions (month/year)?
Unit 1______ Unit 2______ Unit 3______ Unit 4______
TVA Response TVA plans to submit an EPU for the Browns Ferry Nuclear Power Plants Units 1, 2, and 3.
Below is the information requested by NRC:
x What percent increase in power from the current licensed thermal power (CLTP) limit does the licensee plan to apply for? (Please write N/A in any unit that does not apply or that is not planned for a power uprate.)
Unit 1_15__% Unit 2_15__% Unit 3_15__%
x What is the planned increase from the CLTP limit in megawatts thermal?
Unit 1__494_MWt Unit 2__494_MWt Unit 3__494_MWt x What is the expected schedule for filing the application (month/year)? (If the month is not known, please provide the quarter and/or year.)
Unit 1_10/2015_ Unit 2__10/2015_ Unit 3__10/2015_
x What is the expected date for power ascension with uprated conditions (month/year)?
Unit 1_10/2018__ Unit 2_03/2019_ Unit 3_03/2018__
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