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| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 ADril 19, 2010 Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 WATTS BAR NUCLEAR PLANT, UNIT 2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING INDIVIDUAL PLANT EXAMINATION (TAC NO. ME3334) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ADril 19, 2010 Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 |
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| | ==SUBJECT:== |
| | WATTS BAR NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING INDIVIDUAL PLANT EXAMINATION (TAC NO. ME3334) |
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| ==Dear Mr. Bhatnagar:== | | ==Dear Mr. Bhatnagar:== |
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| In its letter dated February 9,2010, Tennessee Valley Authority (TVA) provided the results of the Individual Plant Evaluation (IPE) for Watts Bar Nuclear Plant, Unit 2 (WBN Unit 2). In U.S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 88-20, "Individual Plant Examination | | In its letter dated February 9,2010, Tennessee Valley Authority (TVA) provided the results of the Individual Plant Evaluation (IPE) for Watts Bar Nuclear Plant, Unit 2 (WBN Unit 2). In U.S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 88-20, "Individual Plant Examination [IPEl for Severe Accident Vulnerabilities," dated November 23,1988, as supplemented, the staff requested licensees and construction permit holders to perform a systematic examination to identify any plant-specific vulnerabilities to severe accidents and report the results to the NRC. |
| [IPEl for Severe Accident Vulnerabilities," dated November 23,1988, as supplemented, the staff requested licensees and construction permit holders to perform a systematic examination to identify any plant-specific vulnerabilities to severe accidents and report the results to the NRC. The NRC staff is reviewing the IPE Summary Report in TVA's letter of February 9,2010, in support of the information requested in GL 88-20 for WBN Unit 2. The staff has determined that it needs additional information to complete its review. The specific information is detailed in the enclosed request for additional information (RAI). In this regard, the NRC staff requests a response to this RAI within 30 days of receipt of this letter. If you should have any questions, please contact me at 301-415-1457. | | The NRC staff is reviewing the IPE Summary Report in TVA's letter of February 9,2010, in support of the information requested in GL 88-20 for WBN Unit 2. The staff has determined that it needs additional information to complete its review. The specific information is detailed in the enclosed request for additional information (RAI). In this regard, the NRC staff requests a response to this RAI within 30 days of receipt of this letter. |
| Sincerely, 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 | | If you should have any questions, please contact me at 301-415-1457. |
| | Sincerely, ry~Q)~ |
| | 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:== |
| | RAI cc w/encl: Distribution via Listserv |
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| RAI cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION WADS BAR NUCLEAR PLANT, UNIT 2 INDIVIDUAL PLANT EXAMINATION AND PROBABILISTIC RISK ASSESSMENT TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-391 In a letter dated February 9, 2010, Tennessee Valley Authority (TVA) provided the results of the Individual Plant Evaluation (IPE) for Watts Bar Nuclear Plant, Unit 2 (WBN Unit 2). In U.S. Nuclear Regulatory Commission (NRC) Generic Letter 88-20, "Individual Plant Examination
| | REQUEST FOR ADDITIONAL INFORMATION WADS BAR NUCLEAR PLANT, UNIT 2 INDIVIDUAL PLANT EXAMINATION AND PROBABILISTIC RISK ASSESSMENT TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-391 In a letter dated February 9, 2010, Tennessee Valley Authority (TVA) provided the results of the Individual Plant Evaluation (IPE) for Watts Bar Nuclear Plant, Unit 2 (WBN Unit 2). In U.S. |
| [IPE] for Severe Accident Vulnerabilities," dated November 23, 1988, as supplemented, the staff requested licensees and construction permit holders to perform a systematic examination to identify any plant-specific vulnerabilities to severe accidents and report the results to the NRC. In the February 9 letter, TVA provided an IPE summary report and stated that the IPE was performed in accordance with the applicable portions of American Society of Mechanical Engineers (ASME) Standard RA-Sb-2005, "Standard for Probabilistic Risk Assessment | | Nuclear Regulatory Commission (NRC) Generic Letter 88-20, "Individual Plant Examination |
| [PRA] for Nuclear Power Applications," and NRC Regulatory Guide (RG) 1.200, Revision 1, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk Informed Activities." The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing this report and finds that additional information is needed to complete its review. The specific information is described as follows in this request for additional information: TVA states the IPE was performed using ASME Standard RA-Sb-2005. | | [IPE] for Severe Accident Vulnerabilities," dated November 23, 1988, as supplemented, the staff requested licensees and construction permit holders to perform a systematic examination to identify any plant-specific vulnerabilities to severe accidents and report the results to the NRC. |
| However, it appears that the peer review that was performed used RA-Sa-2009. | | In the February 9 letter, TVA provided an IPE summary report and stated that the IPE was performed in accordance with the applicable portions of American Society of Mechanical Engineers (ASME) Standard RA-Sb-2005, "Standard for Probabilistic Risk Assessment [PRA] |
| Clarify which version of the standard was used to conduct the peer review. If RA-Sa-2009 was used, how were the differences addressed? | | for Nuclear Power Applications," and NRC Regulatory Guide (RG) 1.200, Revision 1, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk Informed Activities." |
| For example, if a requirement changed from 2005 to 2009 version, or a new requirement added, which specific findings and observations (F&Os) address these changes? If not included in the submittal, provide the F&Os. When the peer review was performed, did the peer review members take into account the NRC staff's positions on the requirements in the ASME standard as described in RG 1.200? If not, what was the basis for not considering the NRC position? The standard provides specific requirements for a peer review, and the NRC staff took a few exceptions to these in RG 1.200. How were the NRC exceptions to the peer review requirements addressed? As discussed in RG 1.200, meeting the standard involves both meeting the technical requirements and the peer review requirements as endorsed in RG 1.200. Should this be accomplished. | | The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing this report and finds that additional information is needed to complete its review. The specific information is described as follows in this request for additional information: |
| the NRC staff stated in RG 1.200 that a detailed staff review would be Enclosure | | : 1. TVA states the IPE was performed using ASME Standard RA-Sb-2005. However, it appears that the peer review that was performed used RA-Sa-2009. Clarify which version of the standard was used to conduct the peer review. If RA-Sa-2009 was used, how were the differences addressed? For example, if a requirement changed from 2005 to 2009 version, or a new requirement added, which specific findings and observations (F&Os) address these changes? If not included in the submittal, provide the F&Os. |
| -2 obviated, allowing the staff to focus on, for example, assumptions. | | : 2. When the peer review was performed, did the peer review members take into account the NRC staff's positions on the requirements in the ASME standard as described in RG 1.200? If not, what was the basis for not considering the NRC position? |
| In this regard, the staff finds the information in the submittal on the peer review to be very brief. Thus, address the following: The submittal states there are 112 F&O, but there only appears to be 50 F&Os submitted. | | : 3. The standard provides specific requirements for a peer review, and the NRC staff took a few exceptions to these in RG 1.200. How were the NRC exceptions to the peer review requirements addressed? |
| Even taking into account that some of the F&Os address more than one supporting requirement (SR), the number still does not add up to 112 F&Os. The submittal states that nine SRs were judged not applicable, and no justification or identification of these SRs was provided. | | : 4. As discussed in RG 1.200, meeting the standard involves both meeting the technical requirements and the peer review requirements as endorsed in RG 1.200. Should this be accomplished. the NRC staff stated in RG 1.200 that a detailed staff review would be Enclosure |
| Which SRs from the standard were judged not applicable? | | |
| Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 WATTS BAR NUCLEAR PLANT, UNIT 2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING INDIVIDUAL PLANT EXAMINATION (TAC NO. ME3334) | | -2 obviated, allowing the staff to focus on, for example, assumptions. In this regard, the staff finds the information in the submittal on the peer review to be very brief. Thus, address the following: |
| | : a. The submittal states there are 112 F&O, but there only appears to be 50 F&Os submitted. Even taking into account that some of the F&Os address more than one supporting requirement (SR), the number still does not add up to 112 F&Os. |
| | : b. The submittal states that nine SRs were judged not applicable, and no justification or identification of these SRs was provided. Which SRs from the standard were judged not applicable? |
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| | Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 |
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| | ==SUBJECT:== |
| | WATTS BAR NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING INDIVIDUAL PLANT EXAMINATION (TAC NO. ME3334) |
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| ==Dear Mr. Bhatnagar:== | | ==Dear Mr. Bhatnagar:== |
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| In its letter dated February 9, 2010, Tennessee Valley Authority (TVA) provided the results of the Individual Plant Evaluation (IPE) for Watts Bar Nuclear Plant, Unit 2 (WBN Unit 2). In U.S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 88-20, "Individual Plant Examination | | In its letter dated February 9, 2010, Tennessee Valley Authority (TVA) provided the results of the Individual Plant Evaluation (IPE) for Watts Bar Nuclear Plant, Unit 2 (WBN Unit 2). In U.S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 88-20, "Individual Plant Examination [IPE] for Severe Accident Vulnerabilities," dated November 23, 1988, as supplemented, the staff requested licensees and construction permit holders to perform a systematic examination to identify any plant-specific vulnerabilities to severe accidents and report the results to the NRC. |
| [IPE] for Severe Accident Vulnerabilities," dated November 23, 1988, as supplemented, the staff requested licensees and construction permit holders to perform a systematic examination to identify any plant-specific vulnerabilities to severe accidents and report the results to the NRC. The NRC staff is reviewing the IPE Summary Report in TVA's letter of February 9,2010, in support of the information requested in GL 88-20 for WBN Unit 2. The staff has determined that it needs additional information to complete its review. The specific information is detailed in the enclosed request for additional information (RAI). In this regard, the NRC staff requests a response to this RAI within 30 days of receipt of this letter. If you should have any questions, please contact me at 301-415-1457. | | The NRC staff is reviewing the IPE Summary Report in TVA's letter of February 9,2010, in support of the information requested in GL 88-20 for WBN Unit 2. The staff has determined that it needs additional information to complete its review. The specific information is detailed in the enclosed request for additional information (RAI). In this regard, the NRC staff requests a response to this RAI within 30 days of receipt of this letter. |
| Sincerely, IRA! 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 | | If you should have any questions, please contact me at 301-415-1457. |
| | Sincerely, IRA! |
| | 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:== |
| | | RAI cc w/encl: Distribution via Listserv DISTRIBUTION: RidsOgcRp Resource RidsRgn2MailCenter Resource PUBLIC RidsNrrDorlLpwb Resource RidsResDraPrb Resource LPWB Reading File RidsNrrLABClayton Resource RidsNrrPMWattsBar2 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDoriDpr M. Drouin, RES ADAMS Accession No MI-101060365 OFFICE LPWB/PM LPWB/LA RES/DRAlPRB/BC OGC LPWB/BC NAME PMilano BClayton GDeMoss DRoth LRaQhavan DATE 04/16/10 04/16/10 04/09/10 04/16/10 04/19/10 OFFICIAL AGENCY RECORD}} |
| RAI cc w/encl: Distribution via Listserv DISTRIBUTION: | |
| RidsOgcRp Resource RidsRgn2MailCenter Resource PUBLIC RidsNrrDorlLpwb Resource RidsResDraPrb Resource LPWB Reading File RidsNrrLABClayton Resource RidsNrrPMWattsBar2 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDoriDpr M. Drouin, RES ADAMS Accession No MI-101060365 OFFICE LPWB/PM LPWB/LA RES/DRAlPRB/BC OGC LPWB/BC NAME PMilano BClayton GDeMoss DRoth LRaQhavan DATE 04/16/10 04/16/10 04/09/10 04/16/10 04/19/10 OFFICIAL AGENCY RECORD}} | |
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MONTHYEARML1004915352010-02-0909 February 2010 Probabilistic Risk Assessment Individual Plant Examination Summary Report Project stage: Request ML1004801162010-02-18018 February 2010 User Need Memorandum - Request for Review of Individual Plant Examination and Individual Plant Examination of External Events for Watts Bar Nuclear Plant, Unit 2 Project stage: Approval ML1010603652010-04-19019 April 2010 Request for Additional Information, Regarding Individual Plant Examination Project stage: RAI ML1016005592010-06-0808 June 2010 Request for Additional Information Regarding Individual Plant Examination Project stage: Request ML1016800722010-06-23023 June 2010 Supplemental Request for Additional Information Regarding Individual Plant Examination Project stage: RAI ML1022805852010-08-12012 August 2010 Request for Additional Information Regarding Individual Plant Examination Project stage: Request ML1103400402011-01-31031 January 2011 Request for Additional Information (RAI) Regarding Individual Plant Examination Project stage: Request ML1119602282011-08-12012 August 2011 Plant, Unit 2 - Review of Individual Plant Examination Submittal - Internal Events and Internal Flood Project stage: Approval ML14177A1672014-06-25025 June 2014 Probabilistic Risk Assessment (PRA) Summary Report - Information Previously Committed to Provide (TAC ME3334). Part 4 of 4 Project stage: Other ML14177A7262014-06-25025 June 2014 Probabilistic Risk Assessment (PRA) Summary Report - Information Previously Committed to Provide (TAC ME3334). Part 2 of 4 Project stage: Other ML14177A7252014-06-25025 June 2014 Probabilistic Risk Assessment (PRA) Summary Report - Information Previously Committed to Provide (TAC ME3334). Part 1 of 4 Project stage: Other ML14177A1662014-06-25025 June 2014 Probabilistic Risk Assessment (PRA) Summary Report - Information Previously Committed to Provide (TAC ME3334). Part 3 of 4 Project stage: Other 2010-06-08
[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
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ADril 19, 2010 Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING INDIVIDUAL PLANT EXAMINATION (TAC NO. ME3334)
Dear Mr. Bhatnagar:
In its letter dated February 9,2010, Tennessee Valley Authority (TVA) provided the results of the Individual Plant Evaluation (IPE) for Watts Bar Nuclear Plant, Unit 2 (WBN Unit 2). In U.S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 88-20, "Individual Plant Examination [IPEl for Severe Accident Vulnerabilities," dated November 23,1988, as supplemented, the staff requested licensees and construction permit holders to perform a systematic examination to identify any plant-specific vulnerabilities to severe accidents and report the results to the NRC.
The NRC staff is reviewing the IPE Summary Report in TVA's letter of February 9,2010, in support of the information requested in GL 88-20 for WBN Unit 2. The staff has determined that it needs additional information to complete its review. The specific information is detailed in the enclosed request for additional information (RAI). In this regard, the NRC staff requests a response to this RAI within 30 days of receipt of this letter.
If you should have any questions, please contact me at 301-415-1457.
Sincerely, ry~Q)~
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:
RAI cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION WADS BAR NUCLEAR PLANT, UNIT 2 INDIVIDUAL PLANT EXAMINATION AND PROBABILISTIC RISK ASSESSMENT TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-391 In a letter dated February 9, 2010, Tennessee Valley Authority (TVA) provided the results of the Individual Plant Evaluation (IPE) for Watts Bar Nuclear Plant, Unit 2 (WBN Unit 2). In U.S.
Nuclear Regulatory Commission (NRC) Generic Letter 88-20, "Individual Plant Examination
[IPE] for Severe Accident Vulnerabilities," dated November 23, 1988, as supplemented, the staff requested licensees and construction permit holders to perform a systematic examination to identify any plant-specific vulnerabilities to severe accidents and report the results to the NRC.
In the February 9 letter, TVA provided an IPE summary report and stated that the IPE was performed in accordance with the applicable portions of American Society of Mechanical Engineers (ASME) Standard RA-Sb-2005, "Standard for Probabilistic Risk Assessment [PRA]
for Nuclear Power Applications," and NRC Regulatory Guide (RG) 1.200, Revision 1, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk Informed Activities."
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing this report and finds that additional information is needed to complete its review. The specific information is described as follows in this request for additional information:
- 1. TVA states the IPE was performed using ASME Standard RA-Sb-2005. However, it appears that the peer review that was performed used RA-Sa-2009. Clarify which version of the standard was used to conduct the peer review. If RA-Sa-2009 was used, how were the differences addressed? For example, if a requirement changed from 2005 to 2009 version, or a new requirement added, which specific findings and observations (F&Os) address these changes? If not included in the submittal, provide the F&Os.
- 2. When the peer review was performed, did the peer review members take into account the NRC staff's positions on the requirements in the ASME standard as described in RG 1.200? If not, what was the basis for not considering the NRC position?
- 3. The standard provides specific requirements for a peer review, and the NRC staff took a few exceptions to these in RG 1.200. How were the NRC exceptions to the peer review requirements addressed?
- 4. As discussed in RG 1.200, meeting the standard involves both meeting the technical requirements and the peer review requirements as endorsed in RG 1.200. Should this be accomplished. the NRC staff stated in RG 1.200 that a detailed staff review would be Enclosure
-2 obviated, allowing the staff to focus on, for example, assumptions. In this regard, the staff finds the information in the submittal on the peer review to be very brief. Thus, address the following:
- a. The submittal states there are 112 F&O, but there only appears to be 50 F&Os submitted. Even taking into account that some of the F&Os address more than one supporting requirement (SR), the number still does not add up to 112 F&Os.
- b. The submittal states that nine SRs were judged not applicable, and no justification or identification of these SRs was provided. Which SRs from the standard were judged not applicable?
Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING INDIVIDUAL PLANT EXAMINATION (TAC NO. ME3334)
Dear Mr. Bhatnagar:
In its letter dated February 9, 2010, Tennessee Valley Authority (TVA) provided the results of the Individual Plant Evaluation (IPE) for Watts Bar Nuclear Plant, Unit 2 (WBN Unit 2). In U.S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 88-20, "Individual Plant Examination [IPE] for Severe Accident Vulnerabilities," dated November 23, 1988, as supplemented, the staff requested licensees and construction permit holders to perform a systematic examination to identify any plant-specific vulnerabilities to severe accidents and report the results to the NRC.
The NRC staff is reviewing the IPE Summary Report in TVA's letter of February 9,2010, in support of the information requested in GL 88-20 for WBN Unit 2. The staff has determined that it needs additional information to complete its review. The specific information is detailed in the enclosed request for additional information (RAI). In this regard, the NRC staff requests a response to this RAI within 30 days of receipt of this letter.
If you should have any questions, please contact me at 301-415-1457.
Sincerely, IRA!
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:
RAI cc w/encl: Distribution via Listserv DISTRIBUTION: RidsOgcRp Resource RidsRgn2MailCenter Resource PUBLIC RidsNrrDorlLpwb Resource RidsResDraPrb Resource LPWB Reading File RidsNrrLABClayton Resource RidsNrrPMWattsBar2 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDoriDpr M. Drouin, RES ADAMS Accession No MI-101060365 OFFICE LPWB/PM LPWB/LA RES/DRAlPRB/BC OGC LPWB/BC NAME PMilano BClayton GDeMoss DRoth LRaQhavan DATE 04/16/10 04/16/10 04/09/10 04/16/10 04/19/10 OFFICIAL AGENCY RECORD