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| | issue date = 05/22/2008 | | | issue date = 05/22/2008 |
| | title = Request for Additional Information, Renewal of Active or Expired N-Type Certificates for Plants | | | title = Request for Additional Information, Renewal of Active or Expired N-Type Certificates for Plants |
| | author name = Milano P D | | | author name = Milano P |
| | author affiliation = NRC/NRR/ADRO/DORL/WBSPB | | | author affiliation = NRC/NRR/ADRO/DORL/WBSPB |
| | addressee name = Bhatnagar A S | | | addressee name = Bhatnagar A |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| | docket = 05000391 | | | docket = 05000391 |
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Line 68: |
| OFFICE LWPB/PM LWPB/LA EQVA/BC LWPB/BC NAME PMilano BClayton DThatcher LRaghavan DATE 5/12/08 5/12/08 5/19/08 5/22/08 OFFICIAL RECORD COPY ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION WATTS BAR NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-391 | | OFFICE LWPB/PM LWPB/LA EQVA/BC LWPB/BC NAME PMilano BClayton DThatcher LRaghavan DATE 5/12/08 5/12/08 5/19/08 5/22/08 OFFICIAL RECORD COPY ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION WATTS BAR NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-391 |
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| By letter dated February 1, 2008 (Agencywide Documents Access and Management System Accession No. ML080370185), Tennessee Valley Authority submitted a request for authorization to use of the provisions of American Society of Mechanical Engineers (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 I," for Watts Bar Nuclear Plant, Unit 2 (WBN-2). In reviewing the application, the Nuclear Regulatory Commission staff has determined that the following information is needed in order to complete its review: | | By letter dated February 1, 2008 (Agencywide Documents Access and Management System Accession No. ML080370185), Tennessee Valley Authority submitted a request for authorization to use of the provisions of American Society of Mechanical Engineers (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 I," for Watts Bar Nuclear Plant, Unit 2 (WBN-2). In reviewing the application, the Nuclear Regulatory Commission staff has determined that the following information is needed in order to complete its review: |
| : 1. In paragraph (c) of the ASM E Code Case N-520-2 it is stated that: "[t]he 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." However, in the second paragraph of page 1 of to the application, it notes that the ASME Section III Quality Assurance (QA) | | : 1. In paragraph (c) of the ASM E Code Case N-520-2 it is stated that: "[t]he 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." However, in the second paragraph of page 1 of 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 appears that the code | | Manual was applied to WBN-2 only through October 25, 1996. It appears that the code |
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| case requires that 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. | | case requires that 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. |
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| Clarify whether the QA manual was applied after October 25, 1996, for such items as layup, maintenance, and removal of components. | | Clarify whether the QA manual was applied after October 25, 1996, for such items as layup, maintenance, and removal of components. |
| : 2. In Enclosure 1, the section entitled "Proposed Alternative and Basis for Use" states in Item No. 2 that: "[t]he 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." | | : 2. In Enclosure 1, the section entitled "Proposed Alternative and Basis for Use" states in Item No. 2 that: "[t]he 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." |
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| Since NRC staff has not yet reviewed this revised code case, nor has it approved its generic use by the industry through the usual processes of incorporation (i.e., Regulatory Guides, Title 10 of the Code of Federal Regulations, Section 50.55a), the staff's position is that a FULL ASME survey, and not a limited survey, should be performed. | | Since NRC staff has not yet reviewed this revised code case, nor has it approved its generic use by the industry through the usual processes of incorporation (i.e., Regulatory Guides, Title 10 of the Code of Federal Regulations, Section 50.55a), the staff's position is that a FULL ASME survey, and not a limited survey, should be performed. |
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| Clarify your definition of a "limited scope survey" to provide, in more detail, the scope of the survey of the QA program to be performed. | | Clarify your definition of a "limited scope survey" to provide, in more detail, the scope of the survey of the QA program to be performed. |
| : 3. In Enclosure 1, Item No. 6 of the section entitled "Proposed Alternative 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 requirements for the term of the temporary certificates and for renewals. | | : 3. In Enclosure 1, Item No. 6 of the section entitled "Proposed Alternative 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 requirements for the term of the temporary certificates and for renewals. |
| Clarify your definition of "limited duration" to a more detailed timeframe, and describe how this will comply with requirements of the code case. | | Clarify your definition of "limited duration" to a more detailed timeframe, and describe how this will comply with requirements of the code case. |
Letter Sequence RAI |
|---|
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
|
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
[Table View] |
|
|---|
Category:Letter
MONTHYEARCNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
IR 05000390/20243012024-10-17017 October 2024
Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301
ML24282B0412024-10-15015 October 2024
Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2
ML24261C0062024-10-0404 October 2024
Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96
ML24260A1682024-10-0404 October 2024
Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5
ML24284A1072024-09-26026 September 2024
Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2
CNL-24-047, 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)
ML24172A1342024-07-15015 July 2024
Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter
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
IR 05000390/20244402024-07-12012 July 2024
95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter
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
IR 05000391/20240072024-04-30030 April 2024
Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007
ML24120A1182024-04-29029 April 2024
– Notification of NRC Supplemental Inspection (95001) and Request for Information
CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024
Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42
ML24087A1912024-04-18018 April 2024
Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting
CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024
Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
CNL-24-024, 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)
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-24-007, Annual Insurance Status Report2024-03-27027 March 2024
Annual Insurance Status Report
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
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)
CNL-24-031, Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-03-18018 March 2024
Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance
CNL-24-028, Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024
Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024
Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37
IR 05000390/20240102024-03-0808 March 2024
Age-Related Degradation Inspection Report 05000390/2024010 and 05000391/2024010
2024-09-05
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24260A0322024-09-10010 September 2024
NRR E-mail Capture - Request for Additional Information Regarding the Watts Bar Unit 2 Steam Generator Tube Inspection Report for U2R5
ML24155A1372024-05-29029 May 2024
Email from K. Green to S. Hughes Request for Additional Information Related to License Amendment Request to Revise Residual Heat Removal Flow Rate
ML24120A1182024-04-29029 April 2024
– Notification of NRC Supplemental Inspection (95001) and Request for Information
ML24116A2012024-04-17017 April 2024
Nrctva ISFSI CBS (RFI)
ML24045A0312024-02-14014 February 2024
NRR E-mail Capture - Request for Additional Information Related to the Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule
ML23166A1142023-06-15015 June 2023
Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2023-03
ML23067A2372023-03-0808 March 2023
WB_2023-02_RP_inspection_doc_request
ML23030A3512023-01-25025 January 2023
Notification of Watts Bar Nuclear Plant - Design Bases Assurance Inspection (Programs) and Initial Information Request
ML22343A0692022-12-0808 December 2022
NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103)
ML22227A0272022-08-11011 August 2022
NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2
ML22144A1002022-05-12012 May 2022
NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans
ML22115A1402022-04-25025 April 2022
NRR E-mail Capture - Requests for Confirmation of Information and Additional Information Regarding Watts Bar Nuclear Plant, Unit 2 Exemption Request Re 10 CFR Part 26 (L-2022-LLE-0017)
ML22083A2372022-03-24024 March 2022
NRR E-mail Capture - Request for Additional Information and Confirmation of Information Related to Tva'S Request for Changes to Watts Bar Nuclear Plant, Units 1 and 2, Technical Specification 3.7.8
ML22056A3802022-02-25025 February 2022
Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2022-02
ML21267A1392021-09-23023 September 2021
Document Request for Upcoming RP Inspection at Watts Bar
ML21221A2602021-08-0909 August 2021
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ML21102A1312021-04-19019 April 2021
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ML21095A0402021-04-0202 April 2021
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ML21095A0422021-04-0202 April 2021
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ML21091A0772021-04-0101 April 2021
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ML21095A0442021-04-0101 April 2021
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ML21095A0412021-04-0101 April 2021
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ML21095A0462021-03-22022 March 2021
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ML21012A2032021-01-11011 January 2021
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ML19218A0302019-08-0505 August 2019
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ML19218A0282019-07-25025 July 2019
NRR E-mail Capture - Watts Bar Nuclear Plant - Draft Second-Round Request for Additional Information Related to Application to Revise Technical Specifications Regarding DC Electrical Systems, TSTF-500, Revision 2
ML19186A4352019-07-0505 July 2019
NRR E-mail Capture - Watts Bar Nuclear Plant - Correction to Final Request for Additional Information Related to Application to Adopt 10 CFR 50.69
ML19169A3592019-06-18018 June 2019
NRR E-mail Capture - Watts Bar Nuclear Plant - Final Request for Additional Information Related to Application to Adopt 10 CFR 50.69
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NRR E-mail Capture - Sequoyah Nuclear Plant and Watts Bar Nuclear Plant - Final Request for Additional Information Related to Request for Alternative to OM Code Requirements
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NRR E-mail Capture - Watts BAR, Units 1 and 2 Request for Additional Informatin (RAI) Regarding Changes to Technical Specifications Sections 3.8.1, 3.8.7, 3.8.8, and 3.8.9
ML19071A3542019-03-0808 March 2019
NRR E-mail Capture - Watts Bar Nuclear Plant - Final Request for Additional Information Related to Request to Adopt TSTF-425 to Relocate Specific Surveillance Frequency Requirements to Licensee-Controlled Program
ML18313A2202018-11-0707 November 2018
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ML18282A6372018-10-0909 October 2018
NRR E-mail Capture - RAIs (Final) - LAR to Revise the Steam Generator Technical Specifications for Watts Bar Nuclear Plant, Unit 2
ML18270A2362018-09-26026 September 2018
NRR E-mail Capture - Watts Bar Units 1 and 2 RAIs - Modify TS 3.8.9 Completion Time for Inoperable 120V AC Vital Buses (L-2018-LLA-0050)
ML18240A0702018-08-27027 August 2018
NRR E-mail Capture - RAI for Watts Bar Unit 2 Tpbars LAR and Watts Bar Units 1 and 2 LAR Related to Fuel Storage
ML18199A1822018-07-17017 July 2018
NRR E-mail Capture - Request for Additional Information Regarding Watts Bar Unit 1 Extension of Surveillance Requirement Intervals
2024-09-10
[Table view] |
Text
May 22, 2008
Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
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)
Dear Mr. Bhatnagar:
By letter to the Nuclear Regulatory Commission (NRC) dated February 1, 2008, Tennessee Valley Authority (TVA) submitted a request for authorization to use an alternative to the requirements in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section III. Specifically, T VA requested to use 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 C onstruction,Section III, Division I." 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 system s and components to the jurisdiction of a subcontractor, who will be an ASME Section III N-Certificate holder.
The NRC staff is reviewing your submittal and has determined that additional information is needed to complete its review. The specific information requested is addressed in the enclosure to this letter.
This request for additional information was discussed with members of your staff, and it was agreed that a response would be provided within 45 days of the date of this letter. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1457.
Sincerely,
/RA/
Patrick D. Milano, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket No. 50-391
Enclosure:
Request for Additional Information
cc w/encl: See next page
This request for additional information was discussed with members of your staff, and it was agreed that a response would be provided within 45 days of the date of this letter. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1457.
Sincerely,
/RA/
Patrick D. Milano, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket No. 50-391
Enclosure:
Request for Additional Information
cc w/encl: See next page
DISTRIBUTION:
PUBLIC RidsOgcRp RidsNrrDorlLwpb RidsNrrPMPMilano RidsNroDcipCqvb RidsNrrDorlDpr RidsNrrPMJUribe RidsNrrDciCpnb R. McIntyre, NRO RidsNrrDeEqva RidsAcrsAcnw&mMailCenter RidRgn2MailCenter (R. Haag) RidsNrrLABClayton (Hard Copy)
ADAMS Accession Number: ML081300809
OFFICE LWPB/PM LWPB/LA EQVA/BC LWPB/BC NAME PMilano BClayton DThatcher LRaghavan DATE 5/12/08 5/12/08 5/19/08 5/22/08 OFFICIAL RECORD COPY ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION WATTS BAR NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-391
By letter dated February 1, 2008 (Agencywide Documents Access and Management System Accession No. ML080370185), Tennessee Valley Authority submitted a request for authorization to use of the provisions of American Society of Mechanical Engineers (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 I," for Watts Bar Nuclear Plant, Unit 2 (WBN-2). In reviewing the application, the Nuclear Regulatory Commission staff has determined that the following information is needed in order to complete its review:
- 1. In paragraph (c) of the ASM E Code Case N-520-2 it is stated that: "[t]he 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." However, in the second paragraph of page 1 of 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 appears that the code
case requires that 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 layup, maintenance, and removal of components.
- 2. In Enclosure 1, the section entitled "Proposed Alternative and Basis for Use" states in Item No. 2 that: "[t]he 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."
Since NRC staff has not yet reviewed this revised code case, nor has it approved its generic use by the industry through the usual processes of incorporation (i.e., Regulatory Guides, Title 10 of the Code of Federal Regulations, 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 "limited scope survey" to provide, in more detail, the scope of the survey of the QA program to be performed.
- 3. In Enclosure 1, Item No. 6 of the section entitled "Proposed Alternative 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 requirements for the term of the temporary certificates and for renewals.
Clarify your definition of "limited duration" to a more detailed timeframe, and describe how this will comply with requirements of the code case.
Ashok S. Bhatnagar Tennessee Valley Authority WATTS BAR NUCLEAR PLANT UNIT 2 cc:
Mr. Gordon P. Arent New Generation Licensing Manager Tennessee Valley Authority 5A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
Senior Resident Inspector, Unit 2 Watts Bar Nuclear Plant U.S. Nuclear Regulatory Commission 1260 Nuclear Plant Road Spring City, TN 37381
Mr. Michael K. Brandon, Manager Licensing and Industry Affairs Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381
Mr. William R. Campbell, Jr.
Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
County Executive 375 Church Street Suite 215 Dayton, TN 37321
County Mayor P. O. Box 156 Decatur, TN 37322
Mr. John C. Fornicola, General Manager Nuclear Assurance Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 General Counsel Tennessee Valley Authority 6A West Tower 400 West Summit Hill Drive Knoxville, TN 37902
Mr. Michael J. Lorek, Plant Manager Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381
Mr. Lawrence E. Nanney, Director Tennessee Dept. of Environmental Health &
Conservation Division of Radiological Health 3rd Floor, L&C Annex 401 Church Street Nashville, TN 37243-1532
Mr. Larry E. Nicholson, General Manager Performance Improvement Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
Mr. Masoud Bajestani, Vice President Watts Bar Unit 2 Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381
Mr. Michael D. Skaggs Site Vice President Watts Bar Nuclear Plant Tennessee Valley Authority P. O. Box 2000 Spring City, TN 37381
Ms. Ann P. Harris 341 Swing Loop Road Rockwood, TN 37854
