Letter Sequence Other |
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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 February 1, 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" Pursuant to 10 CFR 50.55a(a)(3)(i), TVA requests approval for the use of the provisions of approved ASME 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."
This Code Case will be applied for specific use as part of the construction activities associated with the ASME Section III systems and components in WBN Unit 2. provides TVA's request for relief to use the proposed alternative Code Case. Review of the use of this relief is requested to be completed in a time frame to facilitate preparations for the ASME survey of WBN Unit 2 program and process as part of TVA's application for a temporary Certificate of Authorization to allow for the completion of Code documentation for previously completed work. This survey is currently anticipated for August of 2008. Preparations for the restart of ASME Section III construction, fabrication, and installation activities on WBN Unit 2 and the associated ASME Section III certification surveys are already underway with the award of a contract to a subcontractor who can obtain the appropriate Code Symbol Stamps to complete the construction of WBN Unit 2.
U.S. Nuclear Regulatory Commission Page 2 February 1, 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, Masoud Ba ~stani Watts B r nit 2 Vice President Enclosure cc w/
Enclosure:
Lakshminarasimh Raghavan U.S. Nuclear Regulatory Commission MS 08H4A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Joseph Williams, Senior Project Manager (WBN Unit 2)
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 WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 - REQUEST FOR RELIEF 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" Executive Summary:
Pursuant to 10 CFR 50.55a(a)(3)(i), TVA is requesting approval for the use of the provisions of ASME 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."
This Code Case will be applied for specific use as part of the construction activities associated with the completion of ASME Section III systems and components in WBN Unit 2. Code Case N-520-2 will 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. This will allow the subcontractor to complete the construction of the WBN Unit 2 systems and complete the associated N-5 Code Data Reports to certify that the systems were constructed in accordance with ASME Section III, and will further allow TVA to document completion of Unit 2 as part of the Owner's Section III required responsibilities at the time the unit construction is finished.
Prior to Revision 2 to Code Case N-520-1, the transfer of the ASME Section III system documentation was only allowed between one N-type certificate holder to another N-type certificate holder, both of which had to hold current and effective certificates. Use of Code Case N-520-2 will allow TVA to complete documentation and provide to the subcontracted N Certificate Holder partially completed N-5 Code Data reports for those systems and components which were already installed in accordance with the requirements of the ASME Section III rules. Construction activities in accordance with the ASME Section III rules were allowed at WBN Unit 2 through October 25, 1996, at which time TVA's ASME Section III Quality Assurance Manual was revised to exclude its applicability to Unit 2. Work on the WBN Unit 2 ASME Section III safety-related systems and components, performed prior to this date, was supported by the ASME Section III Accreditation, Certification, and Authorization processes and TVA's quality assurance programs and procedures. However, N-5 Code Data Reports were not completed on most of the Unit 2 systems because the construction activities were not fully completed.
The provisions of Code Case N-520-2 will allow the partially completed work to be properly documented through the issuance of "Partial N-5 Code Data Reports" which will then be transferred to TVA's subcontractor N Certificate Holder's jurisdiction for final completion and documentation of the entire system. TVA is not authorized to perform any physical work or repairs under the temporary Certificate of Authorization.
In this manner TVA, as the Owner of WBN Unit 2, will also be able to complete the N-3 Code Data Report to document the final completion of Unit 2 in accordance with ASME Section Ill, as required by 10 CFR 50.55a.
I. Systems and Components Affected This request to use the ASME Section III Code Case N-520-2 will be applicable to the WBN Unit 2 safety-related systems and components required to be designed, fabricated, and constructed to the rules of the ASME Boiler and Pressure Vessel Code, Section III.
II. Applicable ASME Code Edition and Addenda WBN Unit 2 ASME piping systems and components were designed and constructed to meet the 1971 Edition with addenda through the Summer 1973 Addenda (1971S73) of Section III, as the construction Code-of-Record. TVA's ASME Section III Quality Assurance Manual, in effect at the time Unit 2 construction activities were suspended, was written to meet the administrative, documentation, and quality control program aspects delineated in the 1980 Edition through the Winter 1981 Addenda (1980W81).
TVA's program, processes, and procedures to document the partially completed piping systems will be written to reflect these requirements and Code Case N-520-2.
Ill. Code Requirement At the time of the suspension of construction activities at WBN Unit 2, TVA was the N, NA, and NPT Certificate Holder for the unit. In addition, there were no clear directions in ASME Section III on how to transfer jurisdiction for Code activities from the owner of an incomplete unit to a new ASME Certificate Holder. The wording in Section III basically required these activities to be administered and controlled by N-type certificate holders.
Subsequent to these earlier editions and addenda it was recognized that there may be circumstances where construction was interrupted, prior to the completion of all Code assigned responsibilities, and later resumed under a different subcontract N-type stamp holder. In support of this possibility the ASME Section III Committee created the ASME Section Code Case N-520, "Alternative Rules for Renewal of N-type Certificates for Plants Not in Active Construction, Section III, Division 1." Later, the Nonmandatory Appendix Z to ASME Section III was also created to incorporate the provision of the Code Case. ASME Code Case N-520 was created, approved, and published effective December 9, 1993. Revision 1 to N-520 was approved and published effective October 24, 1994. Appendix Z was created and approved as part of the 2004 Edition of Section III, which was published in July 1, 2004. However, each of these documents still required the transfer of the jurisdiction of the partially completed code data between organizations with existing and effective ASME Section III Certifications.
2
IV. Reason For Request Subsequent to the suspension of construction activities at WBN Unit 2, TVA allowed the Owner's Certificate and the N-type Certifications to expire, and the issued Code Symbol Stamps were returned to the Society. This decision was made as a result of TVA's decision not to complete WBN Unit 2 due to the lack of need for the extra generating capacity. However, TVA still maintained the NRC construction permit for Unit 2 in case additional generating capacity would be needed in the future. TVA also continued to maintain the Unit 2 ASME Section III piping and system documentation, in the event that construction of Unit 2 was resumed.
Due to the projected power demand in the Tennessee Valley region and in order to maximize the use of an existing asset, TVA's August 3, 2007 letter, "Watts Bar Nuclear Plant (WBN) Unit 2 - Reactivation of Construction Activities" (Reference 1), notified the NRC of the intent to resume construction activities on WBN Unit 2. With this resumption of construction activities, TVA needed a means to be able to transfer the partially completed ASME Section III piping systems and components, and their associated documentation, to the N Certificate holder that was subcontracted to complete Unit 2. In this manner the work previously performed under TVA's N Certificates of Authorization could be credited toward the final completion of the unit's ASME Section III systems and components.
V. Proposed Alternative and Basis For Use Pursuant to 10 CFR 50.55a(a)(3)(i), TVA is requesting approval for the use of the provisions of ASME 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,"
on the basis that this alternative will provide an acceptable level of quality and safety for the required quality processes of the construction of WBN Unit 2 to the rules and requirement of ASME Section II1.
With the planned restart of construction activities at WBN Unit 2, TVA approached the ASME Section III committee about a process that could be developed whereby the partially completed documentation and associated Code items could be transferred from TVA jurisdiction to an N-type Certificate Holder and allow the plant systems to be completed in accordance with the rule of ASME Section III. Revision 2 to Code Case N-520-1 was the result of this request to the ASME Section III Committee. The NRC Staff has not yet reviewed this revised Code Case nor approved its generic use by the industry through the usual process of incorporation into regulatory guides (e.g., RG-1.84 or RG-1.147) and incorporation into the 10 CFR 50.55a rule paragraphs.
N-520-2 imposes conditions on the Owner to ensure that the transfer of the documentation and associated Code items, from the organization with the expired Certificates of Authorization to the new subcontractor N-type Certificate Holder, is performed in a quality manner. The following attributes were added to the provisions of the Code Case to ensure that the process conforms to the ASME code requirements.
- 1. Temporary Certificates of Authorization, with limited scope of application, are issued to allow the Owner to transfer the previously completed code data to the subcontractor N-type stamp holder.
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- 2. The Society will perform a survey of the limited scope quality assurance program and processes to ensure that the procedures are in place to accomplish the code data transfer in accordance with the provisions of the Code Case.
- 3. No new ASME Section III Code (physical) work will be allowed to be performed by TVA under this limited-scope authorization.
- 4. The Authorized Nuclear Inspector shall certify all partial Data Reports and authorize the temporary Certificate Holder to stamp the previously completed work with the appropriate Code Symbol Stamp.
- 5. The Quality Assurance Manual previously accepted by the Authorized Nuclear Inspector Supervisor (ANIS) will be implemented with revisions, also accepted by the ANIS, to document and stamp the previously completed work.
- 6. The term length of the temporary certificates will be of limited duration.
- 7. An accredited Authorized Nuclear Inspection Agency shall be contracted to supervise the completion of the documentation for the previously completed work.
This process will ensure continuity between the previously performed ASME Section III work and the additional work that is to be performed by the Subcontractor. The overall process will ensure that the WBN Unit 2 construction activities and this proposed alternative provide an acceptable level of quality and safety.
VI. Duration of the Proposed Alternative Application of the provisions of this request will commence upon approval of this relief request and site approval of implementing instructions and will continue until such time as the WBN Unit 2 N-3 Code Data Report is completed and signed by TVA, as the Owner; or the use of the Code Case is no longer necessary, nor allowed, in accordance with the provisions of the Code Case. Should the NRC impose additional requirements, these will be implemented prior to completion of the N-3 Code Data Report.
VII. Precedents Due to the unique circumstances associated with WBN Unit 2, there are no established precedents for the use of the revised ASME Section III Code Case, N-520-2.
VIII. References
- 1. TVA letter dated August 3, 2007, "Watts Bar Nuclear Plant (WBN) Unit 2 -
Reactivation of Construction Activities" 4
ATTACHMENT 1 APPROVED COPY OF CODE CASE N-520-2
Gal 1 H004025200 11-27-07 15:55:36 Case number: N-520-2 Approval Date: November 1, 2007 The ASME Boiler and Pressure Vessel Standards Committee took action to eliminate Code Case expiration dates effective March 11, 2005. This means that all Code Cases listed in this Supplement and beyond will remain availablefor use until annulled by the ASME Boiler and Pressure Vessel StandardsCommittee.
Case N-520-2 Alternative Rules for Renewal of Active or Expired N-type Certificates for Plants Not in Active Construction Section I1, Division 1 Inquiry: What alternative requirements (NCA-8100) may be used for the renewal of active or expired N-type Certificates held by the Owner/Designee/Certificate Holder of a nuclear power plant where fabrication and installation activities at the Owner's site have been interrupted?
Reply: It is the opinion of the Committee that an active N-type Certificate, or one that has been permitted to expire, as specified in the Inquiry may be renewed at the appli-cant's facilities by the Society, provided the following alternative rules are met:
(a) The applicant shall notify the Society and the Authorized Nuclear Inspection Agency of its intent to use this Code Case.
(b) The applicant is responsible for documenting com-pliance with the provisions of NCA- 1140.
(c) The Quality Assurance Program previously accepted by the society shall be continually implemented (NCA-8140) and any revisions to the program shall be acceptable to the Authorized Nuclear Inspection Agency.
(d) An agreement with an accredited Authorized Nuclear Inspection Agency shall be maintained by N-type Certificate Holder in accordance with NCA-8130.
(e) For active Certificate not later than six months prior to the date of expiration of the N-type Certificate, the applicant shall apply for renewal of the certificate. The renewal application shall reference this Code Case. A letter from the Authorized Nuclear Inspection Agency recom-mending the renewal of the Certificate shall accompany the application.
(f) Where the N-type Certificate Holder has permitted the Certificates to expire, and has returned the Code Symbol Stamps to the Society, and the Owner plans to contract with a new Certificate Holder to complete construction of the nuclear facility, the expired Certificate Holder may apply to the Society for temporary Certificates of Authori-zation and such Certificates and applicable Code Symbol Stamps shall be issued by the Society subject to the follow-ing conditions:
(1) The scope of the certificates shall be limited to the Code Edition and Addenda to which the nuclear plant
Gal 2 H004025200 11-27-07 15:55:36 has been docketed. No new Code work may be performed under these temporary Certificates. Repair welding of material imperfections and existing welds shall not be per-formed.
(2) An Accredited Authorized Nuclear Inspection Agency shall be employed to review the completed work and monitor and verify compilation and completion of all documentation such as Data Report Forms and supporting Data Packages.
(3) The ANI shall certify all partial Data Reports and authorize the temporary Certificate Holder to stamp the previously completed work with the appropriate Code Symbol Stamp.
(4) The Quality Assurance Program previously accepted by the Society shall be implemented (NCA-8140) and any revisions to the program shall be acceptable to the Authorized Nuclear Inspection Agency. All required revisions to the Quality Assurance Manual shall be reviewed and accepted by the ANIS prior to implementa-tion. The revised program shall govern all activities required to document and stamp all previously com-pleted work.
(5) A survey or audit by the Society shall be required for the issuance of the requested Certificates and Stamps to the expired Certificate Holder. Code activities performed prior to the issuance of the temporary Certificates shall be subject to the acceptance of the Inspector (NCA-8153).
(6) The Owner shall apply to the Society for an Own-ers Certificate (NCA-8162), and the evaluation interview by the Society shall include a review of the scope of activi-ties to be performed under the temporary Certificates. A complete list of all work remaining to be documented and stamped shall be provided to the AIA prior to completion of all work. The Regulatory Authority and the Jurisdic-tional and Enforcement Authority (if applicable) shall be notified of the completion of these activities.
(7) The term of the temporary Certificates shall be for one year, and may be extended once by the Society upon receipt of a request submitted by certified mail for an additional period not to exceed one year. Subsequent renewals shall be treated as renewals of active Certificates.
(8) The Owner shall maintain the Owner's Certificate in accordance with existing Code requirements until all Code activity has been completed, and the N-3 Data Report Form has been completed and filed [NCA-8180(c)].
(9) The temporary Certificates and Code Symbol Stamps shall be returned to the Society when all previously completed work has been documented and stamped.
(g) The renewal application shall include a complete listing of any Code activites to be performed. A certificate providing for activities to meet the provisions of NB/NC/
ND/NE/NF/NG-2000, NB/NC/ND/NE/NF/NG-4000, NB/
NC/ND/NE/NF/NG-5000, and NB/NC/ND/NE/NF/
NG-6000 shall not be issued without a survey as required by the Society.
(h) At least six months prior to performance of any Code activities not listed in the last renewal application,
Gal 3x H004025200 11-27-07 15:55:36 to meet the provisions of NX-2000, NX-4000, and NX-5000, and NX-6000 the N-type Certificate Holder shall apply to the Society for a renewal survey.
(i) An audit as required by the Society shall be con-ducted prior to the renewal of the Certificate.
(j) The Code Symbol Stamp shall be returned to the Society prior to issuance of the renewal Certificate.