Letter Sequence Response to RAI |
---|
|
|
MONTHYEARML1022104402010-08-0606 August 2010 Final Safety Analysis Report (FSAR) - Response to Requests for Additional Information Project stage: Response to RAI ML1025304642010-09-16016 September 2010 Request for Additional Information Regarding Final Safety Analysis Report Related to Sections 4, 5, 6, and 9 Project stage: RAI ML1025902442010-09-20020 September 2010 Request for Additional Information, Regarding Final Safety Analysis Report Related to Section 15 Project stage: RAI ML1027301842010-09-29029 September 2010 Response to Request for Additional Information (RAI) Regarding the Preservice Inspection Program Plan Project stage: Response to RAI ML1028003472010-10-0404 October 2010 Final Safety Analysis Report (FSAR) - Response to Requests for Additional Information Project stage: Response to RAI ML1028618462010-10-13013 October 2010 Response to Request for Additional Information Regarding the Preservice Inspection Program Plan Project stage: Response to RAI ML1104503172011-02-10010 February 2011 Final Safety Analysis Report (FSAR) - Response to Requests for Additional Information Project stage: Response to RAI ML1118615372011-07-20020 July 2011 Request for Additional Information Regarding Final Safety Analysis Report Related to Section 15 Project stage: RAI ML12311A2962012-11-0101 November 2012 Supplemental Safety Evaluation Report (Sser) Open Item 70 Regarding the Preservice Inspection Program Plan Project stage: Supplement 2010-09-20
[Table View] |
|
---|
Category:Letter
MONTHYEARCNL-24-080, Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011)2024-11-20020 November 2024 Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011) IR 05000390/20240032024-11-13013 November 2024 Integrated Inspection Report 05000390/2024003, 05000391/2024003 & 07201048/2024001 CNL-24-021, Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020)2024-11-12012 November 2024 Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020) IR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) CNL-24-014, License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22)2024-11-0404 November 2024 License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22) CNL-24-064, Response to Request for Additional Information Regarding the Watts Bar Nuclear Plant, Unit 2 Steam Generator Tube Inspection Report for U2R52024-11-0404 November 2024 Response to Request for Additional Information Regarding the Watts Bar Nuclear Plant, Unit 2 Steam Generator Tube Inspection Report for U2R5 CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20243012024-10-17017 October 2024 Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301 ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24261C0062024-10-0404 October 2024 Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation IR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 ML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter 05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024 Inoperability of Both Trains of Unit 2 Low Head Safety Injection ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024 Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-033, 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-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) 2024-09-05
[Table view] |
Text
Tennessee Valley Authority, Post Office Box 2000. Spring City, Tenn,essee 37381-2000 October 13, 2010 10 CFR 50.4(b)(6) 10 CFR 50.34(b) 10 CFR 2.390(d)(1)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 NRC Docket No. 50-391
Subject:
Watts Bar Nuclear Plant (WBN) Unit 2 - Response to Request for Additional Information Regarding the Preservice Inspection Program Plan (TAC Nos.
ME4074 and ME3113)
Reference:
- 1. Letter from NRC to TVA, 'Watts Bar Nuclear Plant, Unit 2 - Request for Additional Information from the Component Performance and Testing Branch Regarding Preservice Inspection Program Plan (TAC No. ME3113)," dated September 28, 2010 [ADAMS Accession No. ML102630535]
By letter dated June 17,2010 (ADAMS Accession No. ML101680561), TVA submitted the Preservice Inspection Program Plan as part of the Final Safety Analysis Report for WBN, Unit 2.
The NRC staff reviewed the information provided by TVA.
In a letter to TVA dated September 28,2010 (Reference 1), the NRC provided a Request for Additional Information (RAI) needed to complete the NRC staff review. This letter provides the response to that RAI. contains the new Regulatory Commitment contained in this submittal. If you have any questions, please contact Bill Crouch at (423) 365-2004.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 13!b. day of October, 2010.
Sincerely, Masoud B W ani Watts Bar Unit 2 Vice President
U.S. Nuclear Regulatory Commission Page 2 October 13, 2010
Enclosure:
- 1. Response to RAI Regarding the Preservice Inspection Program Plan
- 2. List of New Regulatory Commitments cc (Enclosures):
U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381
ENCLOSURE 1 Response to RAI Regarding the Preservice Inspection Program Plan Tennessee Valley Authority - Watts Bar Nuclear Plant - Unit 2, Docket No. 50-391 The Nuclear Regulatory Commission (NRC) staff has reviewed and evaluated the information submitted by Tennessee Valley Authority (the licensee) in its letter dated June 17, 2010 (Agencywide Documents Access and Management System Accession No. ML101680561), in which the licensee proposed its Preservice Inspection (PSI) Program Plan in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a for Watts Bar Nuclear Plant (WBN),
Unit 2. The licensee requested NRC to review its proposed PSI Program Plan for WBN, Unit 2 to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),
Section XI inspection requirements. The applicable ASME Code,Section XI code of record for the WBN, Unit 2 PSI Program Plan is the 2001 Edition through the 2003 Addenda.
In Section 3.4.1.4, the licensee stated that "[t]he IWF-5000 requirements for preservice examination and testing of snubbers will be performed using Subsection ISTD of the ASME/ANSI OM Code 2001 Edition through 2003 OMb Addenda, as permitted by 10 CFR 50.55a(b)(3)(v). Examination shall be performed using the VT-3 visual examination method described in IWA-2213." A similar statement is made in Section 3.18.3.
Please explain what WBN procedures or part of the ASME OM Code Subsection ISTD will be used for snubbers inservice visual examination and testing, because the submittal only includes various WBN procedures for visual examination and nondestructive examination related to ASME Section XI.
Response: TVA will issue a Temporary Change to Nondestructive Examination (NDE)
Procedure N-VT-1 to perform VT-3 examination of snubbers in accordance with the criteria specified in ASME/ANSI OM Code 2001 Edition through 2003 OMb Addenda. The temporary change will implement the preservice examination requirements of ISTD-4100, Preservice Examination. TVA has utilized this process in the past at another nuclear site for performance of VT-3 examination of snubbers.
Testing of mechanical snubbers will be performed by a vendor (to be selected) utilizing their snubber testing program and procedures to meet the criteria specified in ASME/ANSI OM Code 2001 Edition through 2003 OMb Addenda.
The snubber testing requirements will implement ISTD-5100, Preservice Operational Readiness Testing.
E1-1
ENCLOSURE 2 List of New Regulatory Commitments Tennessee Valley Authority - Watts Bar Nuclear Plant - Unit 2, Docket No. 50-391
- 1. By November 19, issue a Temporary Change to Nondestructive Examination (NDE)
Procedure N-VT-1 to perform VT-3 examination of snubbers in accordance with the criteria specified in ASME/ANSI OM Code 2001 Edition through 2003 OMb Addenda. The temporary change will implement the preservice examination requirements of ISTD-4100, Preservice Examination.
E2-1