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
MONTHYEARIR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) 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 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 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 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-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description 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-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-010, 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-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 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) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report 05000391/LER-2024-001, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-03-27027 March 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule ML24081A0262024-03-21021 March 2024 Emergency Plan Implementing Procedure Revisions ML24079A0312024-03-19019 March 2024 Wb 2024-301, Corporate Notification Letter (210-day Ltr) 2024-09-05
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Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 June 25, 2010 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 NRC Docket No. 50-391
Subject:
WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 - REQUEST TO USE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) BOILER AND PRESSURE VESSEL CODE, CODE CASE N-520-3, ALTERNATIVE RULES FOR RENEWAL OF ACTIVE OR EXPIRED N-TYPE CERTIFICATES FOR PLANTS NOT IN ACTIVE CONSTRUCTION, SECTION III, DIVISION 1
References:
- 1. 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 (TAC No. MD8314)"
- 2. 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)"
- 3. TVA letter dated July 2, 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 - Response to Request for Additional Information (TAC No. MD8314)
- 4. NRC letter dated October 2, 2008, Watts Bar Nuclear Plant, Unit 2 -
Request for Relief Regarding Alternative Rules for Renewal of Active or Expired N-Type Certificates (TAC No. MD8314)
Pursuant to 10 CFR 50.55a(a)(3)(i), TVA requests approval for the use of the provisions of approved ASME Code Case N-520-3, Alternative Rules for Renewal of Active or Expired
U.S. Nuclear Regulatory Commission Page 2 June 25, 2010 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.
The NRC staff authorized, pursuant to 10 CFR 50.55a{a){3){i), a temporary Certificate of Authorization to TVA for use of the alternatives in Code Case N-520-2 to conduct the transfer of N-type certificates at WBN Unit 2 (References 1 through 4). The use of this Code Case was authorized until such time as*the Code Case is published in a future version of Regulatory Guide (RG) 1.84 and incorporated by reference in 10 CFR 50.55a{b). As a condition, TVA must comply with the duration and terms of the temporary certificates and for renewals as delineated in the Code Case. Code Case N-520-2 authorized a single one-year extension of the temporary Certificate of Authorization. provides TVA's request for relief to use the proposed alternative Code Case.
Approval of the use of this relief is requested to be completed in a time frame to allow TVA to request extension of the temporary N-type Certificat~ for an additional year. The present NA and NPT Certificates expire on May'7, 2011, but Code activities will not be completed by that time. Therefore, a second request for extension will be initiated in November 2010, if the request for relief is approved by the NRC. ASME Section III construction, fabrication, and installation activities on WBN Unit 2 are in progress with contractors who have the appropriate Code Symbol Stamps to complete the construction of WBN Unit 2. Enclosure 2 contains the TVA commitment associated with relief request contained in Enclosure 1.
If you have any questions in this matter, please contact William Crouch, Manager of WBN Unit 2 Nuclear Licensing and Industry Affairs at (423) 365-2004.
Sincerely, l .
Enclosures:
- 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-520-3, "Alternative Rules for Renewal of Active or Expired N-Type Certificates for Plants Not in Active Construction,Section III, Division 1"
- 2. List of Commitments cc: See Page 3
U.S. Nuclear Regulatory Commission Page 3 June 25, 2010 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 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-520-3, 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 to use the provisions of ASME 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. In November 2009, Code Case N-520-3 was issued by Supplement 11 to the 2007 ASME Edition Code Cases. 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-520-3 will allow TVA to renew a temporary Certificate of Authorization from ASME for one additional year to complete and transfer documentation of the partially completed ASME Section III systems and components, to the jurisdiction of a contractor who will be an ASME Section III N Certificate Holder. This will allow the contractor 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 OwnersSection III required responsibilities at the time the unit construction is finished.
Prior to Revision 3 to Code Case N-520, the NRC staff authorized, pursuant to 10 CFR 50.55a(a)(3)(i), the alternatives in Code Case N-520-2 to obtain a temporary Certificate of Authorization to conduct the transfer of N-type certificates at WBN Unit 2 (References 1 through 4 of the transmittal letter). The provisions of Code Case N-520-3 are identical to Code Case N-520-2 with the exception of Reply paragraph(f)(7), which states that the term of the temporary Certificate may be extended twice by the Society upon receipt of a request for an additional period not to exceed one year. Code Case N-520-2, Reply paragraph(f)(7), states that the term of the temporary Certificate may be extended once by the Society upon receipt of a request for an additional period not to exceed one year.
I. Systems and Components Affected This request will be applicable to the WBN Unit 2 safety-related systems and components required to be designed, fabricated, and constructed in compliance with the rules of the ASME Boiler and Pressure Vessel Code,Section III.
E1-1
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. TVAs 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). TVAs program, processes, and procedures to document the partially completed piping systems presently reflect these requirements and Code Case N-520-2.
III. 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 convey jurisdiction for Code activities from the owner of an incomplete unit to a new ASME Certificate Holder. The wording in Section III required these activities to be administered and controlled by N-type certificate holders. Apart from the earlier editions and addenda, it was recognized that circumstances may occur where construction was interrupted prior to the completion of all Code assigned responsibilities, then resumed under a different N-type stamp holder. To address 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. Revision 2 to N-520 was approved and published by Supplement 4 to the 2007 ASME Edition of Section III Code Cases effective November 1, 2007. Revision 3 to Code Case N-520 was approved by Supplement 11 to the 2007 ASME Edition of Section III Code Cases effective November 11, 2009. Revisions 1 and 2 to Code Case N-520 have been superseded.
IV. Reason for Request Subsequent to the suspension of construction activities at WBN Unit 2, TVA allowed the Owners 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 TVAs decision not to complete WBN Unit 2 due to the lack of need for the additional generating capacity. However, TVA maintained the NRC construction permit for Unit 2 in case additional generating capacity would be needed in the future. TVA also maintained 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, TVAs August 3, 2007 letter, Watts Bar Nuclear Plant (WBN)
Unit 2 - Reactivation of Construction Activities (Reference 1), notified the NRC of its intent to resume construction activities on WBN Unit 2. With the resumption of construction activities, TVA needed a means to transfer the partially completed ASME Section III piping systems and components, and the associated documentation, to the N Certificate Holder contracted to complete Unit 2. In this manner, the work previously performed under TVAs N Certificates of E1-2
Authorization could be credited toward the final completion of the units 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-520-3, 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 requirements of ASME Section III.
With the planned restart of construction activities at WBN Unit 2, TVA approached the ASME Section III Committee about the development of a process that would enable the transfer of partially completed documentation and associated Code items from TVA jurisdiction to an N-type Certificate Holder and allow plant systems to be completed in accordance with the requirements of ASME Section III. Revision 2 to Code Case N-520-1 was the result of this request to the ASME Section III Committee.
TVA received one year NA and NPT Certificates of Authorization per Code Case N-520-2 effective May 7, 2009. These certificates were revised December 16, 2009, per TVAs request for a one-year extension per Code Case N-520-2 with expiration on May 7, 2011. TVAs principal contractor for completion of WBN Unit 2 did not receive N Code symbol stamps until January 2010. Remaining Code activity will not be completed to allow TVA to issue the N-3 Data Report prior to expiration of the NA and NPT Certificates of Authorization on May 7, 2011.
Under the current provisions of Code Case N-520-2, TVA must apply to the Society for a renewal survey no later than November 7, 2010.
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.
Code Case N-520-3, like N-520-2, imposes conditions on the Owner to ensure that conveyance of documentation and associated Code items, from the organization with the expired Certificates of Authorization to the new 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 ASME code requirements:
- 1. Temporary Certificates of Authorization, with limited scope of application, are issued to allow TVA to transfer the previously completed code data to the contractor N-type stamp holder.
- 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.
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- 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 completion work that is to be performed by the contractor. The overall process will ensure that the appropriate Codes are applied to the construction activities at WBN Unit 2 to provide an acceptable level of quality and safety.
VI. Duration of Use 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, they will be implemented prior to completion of the N-3 Code Data Report.
VII. Industry 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-520-3.
VIII. References
- 1. TVA letter dated August 3, 2007, Watts Bar Nuclear Plant (WBN) Unit 2 - Reactivation of Construction Activities (ML072190047)
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ENCLOSURE 2 List of Commitments
- 1. 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, they will be implemented prior to completion of the N-3 Code Data Report.
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