Letter Sequence Response to RAI |
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TAC:MD8314, Clarify Application of Setpoint Methodology for LSSS Functions, Control Room Habitability, Steam Generator Tube Integrity (Open) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement
Results
Other: CNL-14-154, Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 12 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 12, CNL-15-137, Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 13 (TAC No. MD6311) and Status of Generic Communications for Unit 2 - Revision 13, CNL-15-150, Pressurizer PORV Block Valves - Dynamic Testing Alternative, ML080370185, ML081490110, ML081490118, ML082140238, ML082560373, ML082750019, ML101200204, ML101260469, ML101680561, ML101760222, ML102170077, ML102290258, ML102700527, ML103010299, ML110210486, ML11213A130, ML11362A056, ML12234A688, ML13023A315, ML13213A194
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MONTHYEARML0803701852008-02-0101 February 2008 Request to Use American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Code Case N-520-2, Alternative Rules for Renewal of Active or Expired N-Type Certificates for Plants Not in Active Construction. Project stage: Other ML0813008092008-05-22022 May 2008 Request for Additional Information, Renewal of Active or Expired N-Type Certificates for Plants Project stage: RAI ML0814901182008-05-28028 May 2008 NRC Review: Generic Communications Status for TVA Watts Bar Unit 2 Project stage: Other ML0814901102008-05-28028 May 2008 Status of Generic Communications for Review (Tac No. MD8314) Project stage: Other ML0818504592008-07-0202 July 2008 Response to Request for Additional Information Project stage: Response to RAI ML0821402382008-07-29029 July 2008 Generic Communications Status, Revision 1 Project stage: Other ML0827500192008-09-26026 September 2008 Regulatory Framework for the Completion of Construction and Licensing Activities for Unit 2 - Corrective Action and Special Programs, and Unresolved Safety Issues Project stage: Other ML0825603732008-10-0202 October 2008 Request for Relief Regarding Alternative Rules for Renewal of Active or Expired N-Type Certificates Project stage: Other ML1001204872009-11-12012 November 2009 Application for Special Nuclear Material License in Accordance with 10 CFR 70, Domestic Licensing of Special Nuclear Material Project stage: Request ML1001916842010-01-11011 January 2010 Final Safety Analysis Report, Amendment 97, Section 3 - Design of Structures, Components, Equipment, and Systems, Page 3.8.5-1 Through Page 3.11-9 Project stage: Request ML1001914212010-01-11011 January 2010 Final Safety Analysis Report, Amendment 97 Project stage: Request ML1012002042010-04-20020 April 2010 Preservice Inspection Program Plan and Additional Information Project stage: Other ML1012604692010-04-29029 April 2010 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 2, and Status of Generic Communications for Unit 2 - Revision 2 Project stage: Other ML1016805612010-06-17017 June 2010 Preservice Inspection Program Plan and Additional Information Project stage: Other ML1019402362010-06-18018 June 2010 Instrumentation and Controls Staff Information Requests Project stage: Request ML1017602222010-06-25025 June 2010 Request to Use ASME Boiler and Pressure Vessel Code, Code Case N-520-3, Alternative Rules for Renewal of Active or Expired N-Type Certificates for Plants Not in Active Construction, Section III, Division 1 Project stage: Other ML1021700772010-07-30030 July 2010 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 3, and Status of Generic Communications for Unit 2 - Revision 3 Project stage: Other ML1022902582010-07-31031 July 2010 Final Safety Analysis Report - Response to Preliminary Requests for Additional Information and Requests for Additional Information Project stage: Other ML1025001712010-09-0101 September 2010 OL - TVA Letter to NRC - WBN U2 FSAR A100 Project stage: Request ML1027005272010-09-29029 September 2010 Request for Relief Regarding Alternative Rules for Renewal of Active or Expired N-Type Certification Project stage: Other ML1030102992010-10-28028 October 2010 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 4, and Status of Generic Communications for Unit 2 - Revision 4 Project stage: Other ML1031207112010-10-29029 October 2010 Instrumentation and Controls Staff Information Requests Project stage: Request ML1031207122010-10-29029 October 2010 Edcr 52321 Draft Scope and Intent, Unit Difference and Technical Evaluation, Enclosure 2, Attachment 1 Project stage: Request ML1031403142010-11-0101 November 2010 OL - TVA Letter to NRC_10-29-10_WBN U2 FSAR 101 Project stage: Request ML1032001462010-11-0909 November 2010 Final Safety Analysis Report (FSAR) - Response to Requests for Additional Information Project stage: Response to RAI ML1032106442010-11-17017 November 2010 Revision of Commitment for Implementation of the Maintenance Rule Project stage: Request ML1035405602010-12-17017 December 2010 Safety Evaluation Report Supplement 22 (SSER22) - Response to Requests for Additional Information Project stage: Supplement ML1102104862011-01-21021 January 2011 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 5 and Status of Generic Communications for Unit 2 - Revision 5 Project stage: Other ML1106202192011-02-25025 February 2011 Instrumentation and Controls Staff Information Requests Project stage: Request ML1110500092011-04-0808 April 2011 OL - FW: Updated OI List Project stage: Request ML11136A0532011-04-18018 April 2011 OL - TVA Letter to NRC_04-15-11_I&C RAI Response Project stage: Request ML11129A2052011-05-0606 May 2011 Instrumentation and Controls Staff Information Requests Project stage: Request ML11178A1552011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104 Project stage: Request ML11167A1102011-06-10010 June 2011 Instrumentation and Controls Staff Information Requests Project stage: Request ML11213A1302011-07-27027 July 2011 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 6 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 6 Project stage: Other ML11213A2612011-07-28028 July 2011 Results from Cost-Benefit Analysis of Radwaste System Enhancements Project stage: Request ML11292A1992011-10-17017 October 2011 Revision of Commitment for Unit 2's Implementation of the Maintenance Rule Project stage: Request 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 Project stage: Other ML12234A6882012-08-15015 August 2012 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 8 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 8 Project stage: Other ML12249A1952012-08-30030 August 2012 Instrumentation and Controls Staff Request for Additional Information (RAI) Related to Supplemental Safety Evaluation Report (Sser) Open Item 80 Project stage: Supplement ML12284A5132012-10-0404 October 2012 NRC Bulletin No. 88-08, Thermal Stresses in Piping Connected to Reactor Coolant System (RCS) - Clarification Project stage: Request ML12284A5142012-10-0404 October 2012 Revision of Commitment for Unit 2's Implementation of the Maintenance Rule Project stage: Request ML12312A1672012-10-25025 October 2012 Unit 1 & 2, Watts Bar, Units 1 & 2, 90-Day Response to NRC Bulletin 2012-01, Design Vulnerability in Electric Power System. Project stage: Request ML12349A3792012-12-10010 December 2012 Instrumentation and Controls Staff Request for Additional Information (RAI) Related to Supplemental Safety Evaluation Report (Sser) Open Item 80 Project stage: Supplement ML13023A3152013-01-17017 January 2013 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 9 (TAC No. MD6311), and Status of Generic Communications for Unit 2 -Revision 9 Project stage: Other ML13030A0322013-01-24024 January 2013 Documentation of Liability Insurance Coverage Requested Per Supplemental Safety Evaluation Report (Sser) Open Item 25 Project stage: Request ML13213A1942013-07-25025 July 2013 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 10 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 10 Project stage: Other CNL-13-149, Updated Inservice Test (IST) Program (Unit 1) and Ist/Preservice Test (Pst) Program2013-12-12012 December 2013 Updated Inservice Test (IST) Program (Unit 1) and Ist/Preservice Test (Pst) Program Project stage: Request CNL-14-154, Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 12 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 122014-09-0202 September 2014 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 12 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 12 Project stage: Other CNL-15-063, Supplement Safety Evaluation Report - Open Item 33 - Completion of Dcns 53421 and 546362015-04-0707 April 2015 Supplement Safety Evaluation Report - Open Item 33 - Completion of Dcns 53421 and 54636 Project stage: Request 2010-09-01
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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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Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 July 2, 2008 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Gentlemen:
In the Matter of ) Docket No. 50-391 Tennessee Valley Authority )
WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 - REQUEST TO USE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) BOILER AND PRESSURE VESSEL CODE, CODE CASE N-520-2, "ALTERNATIVE RULES FOR RENEWAL OF ACTIVE OR EXPIRED N-TYPE CERTIFICATES FOR PLANTS NOT IN ACTIVE CONSTRUCTION, SECTION III, DIVISION 1" - RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MD8314)
References:
- 1. NRC letter dated May 22, 2008, "Watts Bar Nuclear Plant, Unit 2 - Request for Additional Information Regarding Renewal of Active or Expired N-Type Certificates for Plants Not in Active Construction (TAC NO. MD8314)"
- 2. TVA letter dated February 1, 2008, 'Watts Bar Nuclear Plant (WBN) Unit 2 -
Request to Use American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Code Case N-520-2, "Alternative Rules for Renewal of Active or Expired N-Type Certificates for Plants Not in Active Construction, Section III, Division 1" The purpose of this letter is to respond to the NRC request for additional information (Reference 1) regarding the use of provisions of ASME Section III Code Case N-520-2, "Alternative Rules for Renewal of Active or Expired N-Type Certificates for Plants Not in Active Construction." Code Case N-520-2 would allow TVA to obtain a temporary Certificate of Authorization from ASME to complete and transfer documentation of the partially completed ASME Section III systems and components to the jurisdiction of a subcontractor, who will be an ASME Section III N-Certificate holder. TVA's original request for approval to use the Code Case was submitted on February 1, 2008 (Reference 2). provides the NRC requests and TVA's responses.
U.S. Nuclear Regulatory Commission Page 2 July 2, 2008 If you have any questions in this matter, please contact Gordon Arent, Manager of Watts Bar Unit 2 Nuclear Licensing and Industry Affairs at (423) 365-2004.
Sincerely, W'soud estan ,i Watts B r nit 2 Vice President Enclosure cc (Enclosure):
Lakshminarasimh Raghavan U.S. Nuclear Regulatory Commission MS 08H4A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Patrick D. Milano, Senior Project Manager, Watts Bar Special Projects Branch U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Loren R. Plisco, Deputy Regional Administrator for Construction U. S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center, Suite 23T85 61 Forsyth Street, SW, Atlanta, Georgia 30303-8931 U. S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381
Enclosure 1 Response to Request for Additional Information ASME Code Case N-520-2 NRC request 1:
In paragraph(c) of the ASME Code Case N-520-2 it is stated that:" [tjhe Quality Assurance program previously accepted by the society shall be continually implemented (NCA-8140) and any revisions to the programshall be acceptable to the Authorized Nuclear Inspection Agency." However in the second paragraphof page 1 of Enclosure I to the application,it notes that the ASME Section III Quality Assurance (QA) Manual was applied to WBN-2 only through October 25, 1996. It appearsthat the code case requiresthat the ASME Section III QA manual should have been applied post October 25, 1996, to such items as layup, maintenance, and removal of components for use on the other unit.
Clarify whether the QA manual was applied after October 25, 1996, for such items as /ayup, maintenance and removal of components.
TVA response:
TVA's Nuclear Quality Assurance Plan (NQAP) (TVA-NQA-PLN89-A) defines and describes the nuclear quality assurance (QA) requirements for TVA and establishes the responsibilities for their implementation. The NQAP has been continuously applied to WBN Unit 2. Among other things, that plan applied to items such as layup, maintenance, and removal of components for use on WBN Unit 1. Changes to the NQAP comply with the requirements for approval and submittal of 10 CFR 50.55 (f) (3) (construction permits) for WBN Unit 2 and with 10 CFR 50.54 for the operating units. The current revision of the NQAP was submitted December 4, 2007 (Reference 1).
Associated with the NQAP is the TVA ASME Section III Quality Assurance Manual (ASME III QAM). The ASME III QAM is a self-contained manual that describes specific QA requirements for the control of items and activities subject to the ASME Section II1. Revisions to the ASME Ill QAM are coordinated with the Authorized Inspection Agency for review and acceptance prior to implementation.
As discussed in Reference 2, the ASME Ill QAM was revised on October 25, 1996, to reflect the fact that WBN Unit 1 was completed and that there was, at the time, no current plan for completing WBN Unit 2. ASME Section III activities associated with the design, construction, and installation of ASME Ill systems and components in WBN Unit 2 were no longer being performed. TVA allowed the Owner's Certificate and the N-type Certifications to expire, and the issued Code Symbol Stamps were returned to the Society.
On March 10, 2008, the ASME Ill QAM was revised (Revision 32) to comply with the provisions of ASME Section III Code Case N-520-2 and specifically N-520-2 (f)(4) with respect to the QA Program. This revision was coordinated with and accepted by the Authorized Inspection Agency.
Enclosure 1 Response to Request for Additional Information ASME Code Case N-520-2 NRC request 2:
In Enclosure 1, the section entitled "ProposedAlternative and Basis for Use" states in Item No. 2 that "[t]heSociety will perform a survey of the limited scope quality assuranceprogram and processes to ensure that the proceduresare in place to accomplish the code data transferin accordance with the provisions of the Code Case".
Since NRC staff has not yet reviewed this revised code case, nor has it approved its generic use by the industry through the usualprocesses of incorporation(i.e.,
Regulatory Guides, Title 10 of the Code of FederalRegulations, Section 50.55a),
the staff's position is that a FULL ASME survey, and not a limited survey, should be performed.
Clarify your definition of a "limitedscope survey" to provide, in more detail, the scope of the survey of the QA program to be performed.
TVA response:
The survey will be a full survey of the ASME program invoked by TVA's limited scope QA program. TVA's ASME III QAM is limited in scope in that no ASME Code activities other than completion of documentation, Code Data Reports, and Stamping are allowed under the provisions of ASME Section III Code Case N-520-
- 2. The current TVA ASME III QAM meets the requirements of ASME Section III Code Case N-520-2. Under the provisions of Code Case, WBN Unit 2 will complete documentation and Code Data Reports and Stamping for those portions of the plant that are suitable for use. In addition, WBN Unit 2 project will identify those items that are not complete to the Authorized Inspection Agency and the N-Certificate Holder having overall responsibility for completion of construction and installation of ASME III systems and components in WBN Unit 2.
NRC request 3:
In Enclosure 1, Item No. 6 of the section entitled "ProposedAlternative and Basis for Use" states that the term length of the temporary certificates will be of limited duration. Paragraph(f)(7) of the code case has specific requirementsfor the term of the temporary certificates and for renewals.
Clarify your definition of "limitedduration"to a more detailed timeframe, and describe how this will comply with requirements of the code case.
TVA response:
Code Case N-520-2 allows use of the temporary certificates for one year with allowance for one extension for an additional period not to exceed one year. TVA will comply with the requirements of the Code Case.
Enclosure 1 Response to Request for Additional Information ASME Code Case N-520-2
References:
- 1. TVA letter dated December 4, 2007, "TVA Nuclear Quality Assurance (NQA) Plan (TVA-NQA-PLN89-A) - Browns Ferry, Sequoyah and Watts Bar nuclear Plants - Update"
- 2. TVA letter dated February 1, 2008, 'Watts Bar Nuclear Plant (WBN) Unit 2
- Request to Use American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code, Code Case N-520-2, "Alternative Rules for Renewal of Active or Expired N-Type Certificates for Plants Not in Active Construction, Section III, Division 1"