LTR-14-0426 - Response LTR to Diane Curran, Harmon, Curran, Spielberg & Eisenberg, Llp Ltr. Watts Bar Unit 2 Operating License ProceedingML14267A466 |
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Watts Bar |
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Issue date: |
11/21/2014 |
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From: |
Dean W M Division of Operating Reactor Licensing |
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To: |
Curran D J Harmon, Curran, Harmon, Curran, Spielberg & Eisenberg, LLP, Southern Alliance for Clean Energy |
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Dion J |
Shared Package |
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ML14204A785 |
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LTR-14-0426 |
Download: ML14267A466 (4) |
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Category:Letter
MONTHYEARML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML24008A2462024-01-18018 January 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule 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-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) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods 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 IR 05000390/20234412023-12-21021 December 2023 Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public 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) IR 05000390/20234042023-12-14014 December 2023 Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 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) ML23293A0572023-12-0606 December 2023 Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control IR 05000390/20230102023-11-30030 November 2023 RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation 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 IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation ML23312A1432023-11-0808 November 2023 Submittal of Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 5 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 ML23251A2002023-09-11011 September 2023 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Units 1 and 2 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 IR 05000390/20230052023-08-30030 August 2023 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2023005 and 05000391/2023005 ML23233A0042023-08-28028 August 2023 Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds IR 05000390/20230022023-08-16016 August 2023 Reissue - Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2023002 and 05000391/2023002 ML23220A1582023-08-0909 August 2023 Integrated Inspection Report 05000390/2023002 and 05000391/2023002 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) 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 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 IR 05000390/20230112023-07-24024 July 2023 Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011 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 . ML23122A2322023-06-0707 June 2023 Issuance of Amendment Nos. 162 and 69 Regarding Change to Date in Footnotes for Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (Creatcs) 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 IR 05000390/20234032023-05-30030 May 2023 Cyber Security Inspection Report 05000390/2023403 and 05000391/2023403 ML23131A1812023-05-23023 May 2023 Correction to Amendment No. 161 to Facility Operating License No. NPF-90 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 IR 05000390/20220032023-05-0909 May 2023 Reissue Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2022003 and 05000391/2022003 ML23125A2202023-05-0505 May 2023 Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances) IR 05000390/20230012023-05-0404 May 2023 Integrated Inspection Report 05000390/2023001 and 05000391/2023001 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-23-032, 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-23-030, 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-23-033, 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 ML23072A0652023-04-0505 April 2023 Units 1 and 2 Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12 ML23073A2762023-04-0303 April 2023 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (EPID L-2023-LLA-0029) (Letter) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance 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 2024-01-09
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Text
November 21, 2014
Ms. Diane Curran c/o Southern Alliance for Clean Energy
1726 M St., NW. Suite 600 Washington DC 20036-4523
Dear Ms. Curran:
On behalf of the U.S. Nuclear Regulatory Commission (NRC), I am responding to your letter dated June 23, 2014. In your letter, you question the adequacy of the NRC's review of the Tennessee Valley Authority's (TVA's) Watts Bar Nuclear Plant, Unit 2 operating license application. Specifically, you question the following:
- 1. NRC's review of seismic and flooding requirements in the Watts Bar Unit 2 operating license application. 2. NRC's implementation of the Japan Lessons-Learned Near-Term Task Force (NTTF) recommendation to reevaluate seismic and flooding hazards in the Watts Bar Unit 2
operating license review. 3. NRC's practices for allowing opportunity fo r public participation during the Watts Bar Unit 2 licensing process.
In your letter you express concern that the NRC's operating license review of Watts Bar Unit 2 will not adequately address flooding and seismic safety requirements. All power reactors must be designed to safely withstand a set of natural events, including earthquakes, hurricanes,
tornadoes, floods, and tsunami. These are called design-basis events. The NRC is currently completing the review of the Watts Bar Unit 2 operating license application, which includes the review of the site-specific hydrological licensing basis. To maintain site-wide consistency, the NRC is considering the current design-basis hazards of record for Watts Bar Unit 1 in the Watts Bar Unit 2 review. The NRC will not issue an operating license for Watts Bar Unit 2 until there is a reasonable assurance that the licensee can operate the facility safely and meet all applicable
requirements.
In your letter, you also express concern that in its review of the Watts Bar Unit 2 operating license application, the NRC is not applying seismic and flooding recommendations from the July 12, 2011, Japan Lessons-Learned Near-Term Task Force report, "Recommendation for Enhancing Reactor Safety in the 21st Century: The Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident." To fully address your concern, it is necessary to first describe how the NRC is implementing post-Fukus hima regulatory activities. The NRC formed the Japan Lessons-Learned Near-Term Task Force shortly after the Fukushima Dai-ichi accident. The goal of the task force was to determine what lessons the NRC can learn from the accident and to identify recommendations to enhance reactor safety in the United States. The staff prioritized the task force's recommendations in a three-tiered approach and also described the appropriate regulatory mechanisms for implementation (for example, orders, rulemaking, and requests for information). The Commission approved the staff's proposed actions, schedule for completion, and prioritization approach for implementing the Near-Term Task Force recommendations. Staff requirements memoranda (SRMs) for SECY-11-0124 and SECY-11-0137 describe this approach. You can find these memoranda in the Agencywide
Documents Access and Management System (ADAMS) under Accession Nos. ML112911571 and ML113490055, respectively. Overall, the NRC determined that it is prudent for the agency to take additional regulatory action in response to the accident. However, the NRC also concluded that continued plant operation and licensing activities, including the review of the Watts Bar Unit 2 operating license application, can continue because these actions do not pose an imminent risk to public health and safety. Y ou can find more information on how the NRC is implementing lessons learned from the Fukushima Dai-ichi accident at the NRC public Web site at http://www.nrc.gov/reactors/operating/ops-experience/japan-dashboard.html
.
In response to Near-Term Task Force Recommendation 2.1, the NRC requested that licensees and applicants reevaluate the seismic and flooding hazards at their sites. At the Watts Bar nuclear power plant, TVA is implementing Recommendation 2.1 by reevaluating flooding and seismic hazards at both Unit 1 and Unit 2 using present-day methodologies and information, and determining the impact of these updated hazards on their facility. The Near-Term Task Force seismic and flooding reevaluation activi ties and the associated NRC staff assessments are complex and the agency will need several years to complete these tasks. Once the NRC obtains the results of these assessments, the NRC will determine if safe operation requires additional regulatory action. Such regulatory action could include updating the licensing basis or requiring modification of the facility. The Near-Term Task Force concluded that continued licensing activities do not pose an imminent risk to the public health and safety. Given that conclusion, the NRC does not see a need to defer the issuance of the Unit 2 operating license until these reevaluations and any potential followup actions are complete. In addition TVA must implement certain near-term post-Fukushima actions for the Watts Bar site before a license can be issued. This includes the mitigating strategies under Order EA-12-049, which will provide additional protection against beyond design basis events. TVA is required to meet a schedule for Near-Term Task Force-related requests for information that is consistent with the flooding and seismic reevaluation schedule for Watts Bar Unit 1 as well as all other operating reactors.
TVA is scheduled to submit their flooding hazard reevaluation before the NRC expects to make an operating license decision for Unit 2. If the reevaluated flooding hazard is higher than the design basis, TVA will be required to provide their plans for implementing compensatory measures.
In your letter, you express concern about the opportunities for public participation given the late
stages of the Watts Bar Unit 2 operating license application review. The NRC strives to achieve its mission to protect public health and safety in a manner that is transparent and accessible to interested members of the public. The NRC staff is coordinating regular public meetings and teleconferences with TVA to address significant licensing issues. You can find the schedule for
upcoming public meetings and teleconferences at the NRC's public Web site at http://meetings.nrc.gov/pmns/mtg. Furthermore, if the licensing basis is updated by amendment after the Watts Bar Unit 2 operating license is issued as a result of the NRC's assessment of the seismic or flooding hazard reevaluations, the public will have an opportunity to comment and request a hearing.
The NRC takes reactor safety very seriously. To ensure a quality review, the NRC developed a custom-tailored approach for licensing and inspection activities at Watts Bar Unit 2. The NRC is also dedicated to ensuring that nuclear power plants implement recommendations from the Near-Term Task Force in a timely manner and take appropriate actions to enhance reactor safety as needed. You can find more information regarding the licensing review of Watts Bar
Unit 2 here: http://www.nrc.gov/info-finder/reactor/wb/watts-bar.html. The NRC welcomes your participation and feedback. Please feel free to let us know how we can enhance your awareness of ongoing regulatory activities at Watts Bar Unit 2. Justin Poole, the Watts Bar Unit 2 senior project manager, can assist you in answering questions you may have about upcoming Watts Bar Unit 2 meetings, project milestones, and licensing activities. He can be reached at justin.poole@nrc.gov or 301-415-2048.
Sincerely,
/RA/
William M. Dean, Director Office of Nuclear Reactor Regulation
Docket No. 50-391
PKG ML14204A785 Incoming ML14204A784, ML14205A016 Response LTR ML14267A466 *email concurrence OFFICE NRR/LPWB/PM LPWB LPWB/LA QTE* OGC NRR/DORL/LP WB NAME JDion JPoole BClayton CHsu CKanatas NLO JQuichocho DATE 10/15/14 10/17/14 10/15/14 10/28/14 11/04/14 10/06/14 OFFICE NRR/JLD NRR/DORL/D NRR/OD NAME JDavis MEvans WDean DATE 11/07/14 11/17/14 11/21/14