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| {{#Wiki_filter:May 22, 2008 | | {{#Wiki_filter: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 |
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| Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 | |
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| ==SUBJECT:== | | ==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) | | 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) |
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| ==Dear Mr. Bhatnagar:== | | ==Dear Mr. Bhatnagar:== |
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| 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. | | 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, TVA 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 Construction, 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 systems 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. |
| 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. | |
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| 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.
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| Sincerely,
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| /RA/
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| Patrick D. Milano, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
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| Docket No. 50-391 | | A. Bhatnagar 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 |
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| ==Enclosure:== | | ==Enclosure:== |
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| Request for Additional Information | | Request for Additional Information cc w/encl: See next page |
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| cc w/encl: See next page | |
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| 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.
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| Sincerely, | | A. Bhatnagar 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/
| | /RA/ |
| Patrick D. Milano, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | | 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 |
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| Docket No. 50-391 | |
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| ==Enclosure:== | | ==Enclosure:== |
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| Request for Additional Information | | 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) |
| cc w/encl: See next page | | 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 |
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| DISTRIBUTION: | |
| PUBLIC RidsOgcRp RidsNrrDorlLwpb RidsNrrPMPMilano RidsNroDcipCqvb RidsNrrDorlDpr RidsNrrPMJUribe RidsNrrDciCpnb R. McIntyre, NRO RidsNrrDeEqva RidsAcrsAcnw&mMailCenter RidRgn2MailCenter (R. Haag) RidsNrrLABClayton (Hard Copy) | |
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| ADAMS Accession Number: ML081300809 | |
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| 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:
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| : 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)
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| 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.
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| | 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 ASME 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 Enclosure 1 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. | | 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. |
| | | 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 staffs 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. | | 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. |
| 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. | | 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. | | ENCLOSURE |
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| Ashok S. Bhatnagar Tennessee Valley Authority WATTS BAR NUCLEAR PLANT UNIT 2 cc:
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| Mr. Gordon P. Arent New Generation Licensing Manager Tennessee Valley Authority 5A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
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| Senior Resident Inspector, Unit 2 Watts Bar Nuclear Plant U.S. Nuclear Regulatory Commission 1260 Nuclear Plant Road Spring City, TN 37381
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| Mr. Michael K. Brandon, Manager Licensing and Industry Affairs Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381
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| Mr. William R. Campbell, Jr.
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| Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
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| County Executive 375 Church Street Suite 215 Dayton, TN 37321
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| County Mayor P. O. Box 156 Decatur, TN 37322
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| 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
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| Mr. Michael J. Lorek, Plant Manager Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381
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| Mr. Lawrence E. Nanney, Director Tennessee Dept. of Environmental Health &
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| Conservation Division of Radiological Health 3rd Floor, L&C Annex 401 Church Street Nashville, TN 37243-1532
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| Mr. Larry E. Nicholson, General Manager Performance Improvement Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
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| Mr. Masoud Bajestani, Vice President Watts Bar Unit 2 Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381
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| Mr. Michael D. Skaggs Site Vice President Watts Bar Nuclear Plant Tennessee Valley Authority P. O. Box 2000 Spring City, TN 37381
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| Ms. Ann P. Harris 341 Swing Loop Road Rockwood, TN 37854}} | | Ashok S. Bhatnagar WATTS BAR NUCLEAR PLANT Tennessee Valley Authority UNIT 2 cc: |
| | Mr. Gordon P. Arent General Counsel New Generation Licensing Manager Tennessee Valley Authority Tennessee Valley Authority 6A West Tower 5A Lookout Place 400 West Summit Hill Drive 1101 Market Street Knoxville, TN 37902 Chattanooga, TN 37402-2801 Mr. Michael J. Lorek, Plant Manager Senior Resident Inspector, Unit 2 Watts Bar Nuclear Plant Watts Bar Nuclear Plant Tennessee Valley Authority U.S. Nuclear Regulatory Commission P.O. Box 2000 1260 Nuclear Plant Road Spring City, TN 37381 Spring City, TN 37381 Mr. Lawrence E. Nanney, Director Mr. Michael K. Brandon, Manager Tennessee Dept. of Environmental Health & |
| | Licensing and Industry Affairs Conservation Watts Bar Nuclear Plant Division of Radiological Health Tennessee Valley Authority 3rd Floor, L&C Annex P.O. Box 2000 401 Church Street Spring City, TN 37381 Nashville, TN 37243-1532 Mr. William R. Campbell, Jr. Mr. Larry E. Nicholson, General Manager Chief Nuclear Officer and Performance Improvement Executive Vice President Tennessee Valley Authority Tennessee Valley Authority 3R Lookout Place 3R Lookout Place 1101 Market Street 1101 Market Street Chattanooga, TN 37402-2801 Chattanooga, TN 37402-2801 Mr. Masoud Bajestani, Vice President County Executive Watts Bar Unit 2 375 Church Street Watts Bar Nuclear Plant Suite 215 Tennessee Valley Authority Dayton, TN 37321 P.O. Box 2000 Spring City, TN 37381 County Mayor P. O. Box 156 Mr. Michael D. Skaggs Decatur, TN 37322 Site Vice President Watts Bar Nuclear Plant Mr. John C. Fornicola, General Manager Tennessee Valley Authority Nuclear Assurance P. O. Box 2000 Tennessee Valley Authority Spring City, TN 37381 3R Lookout Place 1101 Market Street Ms. Ann P. Harris Chattanooga, TN 37402-2801 341 Swing Loop Road Rockwood, TN 37854}} |
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] |
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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
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML23166A1142023-06-15015 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
NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise Watts Bar, Unit 1 Tech Specs Related to Continuous Opening of the Auxiliary Building Secondary Containment Enclosure Boundary
ML21102A1312021-04-19019 April 2021
Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Unit 1
ML21095A0422021-04-0202 April 2021
NRR E-mail Capture - Added Clarification to RAI 2 for Thot LAR
ML21095A0402021-04-0202 April 2021
NRR E-mail Capture - Request for Additional Information Re Generic Letter 95-05 90-Day Report and LAR to Adjust Growth Rate for Thot (EPIDs L-2021-LRO-0003 and L-2021-LLA-0026)
ML21095A0412021-04-0101 April 2021
NRR E-mail Capture - Revised Draft RAI - Combined RAI Set for Watts Bar Unit 2 90-Day Report and Thot LAR (EPIDs L-2021-LRO-0003 and L-2021-LLA-0026)
ML21095A0442021-04-0101 April 2021
NRR E-mail Capture - Revised Draft RAI - Combined RAI Set for Watts Bar Unit 2 90-Day Report and Thot LAR (EPIDs L-2021-LRO-0003 and L-2021-LLA-0026)
ML21091A0772021-04-0101 April 2021
NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise Technical Specification 5.7.2.19, Containment Leakage Rate Testing Program
ML21095A0462021-03-22022 March 2021
NRR E-mail Capture - Draft Request for Additional Information Regarding Tva'S Generic Letter 95-05 90-Day Report for Watts Bar Unit 2
ML21039A6402021-02-0808 February 2021
NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise the Watts Bar Nuclear Plant, Unit 1 Technical Specifications Related to Steam Generator Tube Inspection Frequency
ML21012A2032021-01-11011 January 2021
NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise the Watts Bar UFSAR to Use Alternate Probability of Detection
ML20350B5592020-12-15015 December 2020
NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Adopt Traveler TSTF-490 Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec
ML20338A3202020-12-0303 December 2020
Notification of an NRC Fire Protection Team Inspection (NRC Inspection Report 05000390/2021011 and 05000391/2021011) and Request for Information
ML20322A4412020-11-17017 November 2020
NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise TS 3.7.11 Related to the MCR Chiller Replacement
ML20322A4392020-11-0505 November 2020
NRR E-mail Capture - Draft Request for Additional Information Regarding Tva'S Request to Revise TS 3.7.11 Related to the MCR Chiller Replacement
ML20308A3512020-11-0202 November 2020
Request for Additional Information on WBN Request for Exemption from 10 CFR Part 73, Appendix B, Section VI for the Conduct of an Annual Force-on-Force Exercise (EPID L-2020-LLE-0165 (COVID-19))
ML20253A1782020-09-0909 September 2020
Emergency Preparedness Program Inspection Request for Information
ML20266G4592020-08-14014 August 2020
Notification of Inspection and Request for Information
ML20196L8622020-07-14014 July 2020
NRR E-mail Capture - Watts Bar Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Request to Implement the Full Spectrum LOCA Methodology
ML20086G4802020-03-26026 March 2020
NRR E-mail Capture - Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000) - Part 2
ML20085G3572020-03-25025 March 2020
NRR E-mail Capture - Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000)
ML20084M1942020-03-24024 March 2020
NRR E-mail Capture - Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000)
ML20083J3952020-03-12012 March 2020
NRR E-mail Capture - Draft Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000)
ML19340A6842019-12-0505 December 2019
NRR E-mail Capture - Request for Additional Information for WBN2 Request for One-Time Extension of Completion Time for TS 3.7.8 (L-2019-LLA-0020)
ML19218A0302019-08-0505 August 2019
NRR E-mail Capture - Watts Bar Nuclear Plant - Second-Round Request for Additional Information Related to Application to Revise Technical Specifications Regarding DC Electrical Systems, TSTF-500, Revision 2
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
ML19148A7912019-05-28028 May 2019
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
ML19106A0462019-04-15015 April 2019
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
Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection
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
ML18123A3942018-05-0303 May 2018
NRR E-mail Capture - Request for Additional Information Unit 2 Cycle 1 Steam Generator Tube Inspection Report
ML18057A6372018-02-23023 February 2018
NRR E-mail Capture - Request for Additional Information Related to TVA Fleet Topical Report TVA-NPG-AWA16 - EPIC: L-2016-TOP-0011)
ML18031A6592018-02-0606 February 2018
Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Revise Technical Specification 4.2.1 and Technical Specifications Related to Fuel Storage
ML18016A0112018-01-12012 January 2018
Draft Request for Additional Information Exigent Amendment Request for Inoperable Reactor Coolant Temperature Indication
ML17226A0032017-08-11011 August 2017
NRR E-mail Capture - Watts Bar, Unit 1 - Final Request for Additional Information Concerning Request to Amend Turbine Trip Low Fluid Oil Pressure Reactor Protection System Trip Setpoint
2023-06-15
[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, TVA 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 Construction,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 systems 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.
A. Bhatnagar 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
A. Bhatnagar 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
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 ASME 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 Enclosure 1 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 staffs 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.
ENCLOSURE
Ashok S. Bhatnagar WATTS BAR NUCLEAR PLANT Tennessee Valley Authority UNIT 2 cc:
Mr. Gordon P. Arent General Counsel New Generation Licensing Manager Tennessee Valley Authority Tennessee Valley Authority 6A West Tower 5A Lookout Place 400 West Summit Hill Drive 1101 Market Street Knoxville, TN 37902 Chattanooga, TN 37402-2801 Mr. Michael J. Lorek, Plant Manager Senior Resident Inspector, Unit 2 Watts Bar Nuclear Plant Watts Bar Nuclear Plant Tennessee Valley Authority U.S. Nuclear Regulatory Commission P.O. Box 2000 1260 Nuclear Plant Road Spring City, TN 37381 Spring City, TN 37381 Mr. Lawrence E. Nanney, Director Mr. Michael K. Brandon, Manager Tennessee Dept. of Environmental Health &
Licensing and Industry Affairs Conservation Watts Bar Nuclear Plant Division of Radiological Health Tennessee Valley Authority 3rd Floor, L&C Annex P.O. Box 2000 401 Church Street Spring City, TN 37381 Nashville, TN 37243-1532 Mr. William R. Campbell, Jr. Mr. Larry E. Nicholson, General Manager Chief Nuclear Officer and Performance Improvement Executive Vice President Tennessee Valley Authority Tennessee Valley Authority 3R Lookout Place 3R Lookout Place 1101 Market Street 1101 Market Street Chattanooga, TN 37402-2801 Chattanooga, TN 37402-2801 Mr. Masoud Bajestani, Vice President County Executive Watts Bar Unit 2 375 Church Street Watts Bar Nuclear Plant Suite 215 Tennessee Valley Authority Dayton, TN 37321 P.O. Box 2000 Spring City, TN 37381 County Mayor P. O. Box 156 Mr. Michael D. Skaggs Decatur, TN 37322 Site Vice President Watts Bar Nuclear Plant Mr. John C. Fornicola, General Manager Tennessee Valley Authority Nuclear Assurance P. O. Box 2000 Tennessee Valley Authority Spring City, TN 37381 3R Lookout Place 1101 Market Street Ms. Ann P. Harris Chattanooga, TN 37402-2801 341 Swing Loop Road Rockwood, TN 37854
