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| | number = ML110820353 | | | number = ML110820353 |
| | issue date = 03/28/2011 | | | issue date = 03/28/2011 |
| | title = Browns Ferry Unit 2 - Request for Additional Information Regarding 2-ISI-1, Updated Risk-Informed Inservice Inspection Program (TAC No. ME3720) | | | title = Request for Additional Information Regarding 2-ISI-1, Updated Risk-Informed Inservice Inspection Program |
| | author name = Gratton C | | | author name = Gratton C |
| | author affiliation = NRC/NRR/DORL/LPLII-2 | | | author affiliation = NRC/NRR/DORL/LPLII-2 |
| | addressee name = Krich R M | | | addressee name = Krich R |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| | docket = 05000260 | | | docket = 05000260 |
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| =Text= | | =Text= |
| {{#Wiki_filter:}} | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 28, 2011 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SUB~IECT: BROWNS FERRY NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING 2-ISI-1, UPDATED RISK-INFORMED INSERVICE INSPECTION PROGRAM (TAC NO. ME3720) |
| | |
| | ==Dear Mr. Krich:== |
| | |
| | In Attachment 10 of letter dated March 31, 2010 (Agencywide Documents Access and Management System Accession No. ML100920542), Tennessee Valley Authority requested authorization to use a risk-informed process as an alternative for the selection of Class 1 and Class 2 piping welds for examination. |
| | Based on our review of your submittal, the U. S. Nuclear Regulatory Commission staff finds that a response to the enclosed request for additional information is needed before we can complete the review. |
| | This request was discussed with Mr. Thomas Mathews of your staff on March 7, 2011, and it was agreed that a response would be provided by May 6,2011 (60 days). |
| | If you have any questions, please contact me at (301) 415-1055. |
| | Christopher Gratton, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-260 |
| | |
| | ==Enclosure:== |
| | Request for Additional Information cc w/encl: Distribution via Listserv |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR RELIEF 2-IS1-1 UPDATED RISK INFORMED INSERVICE INSPECTION PROGRAM TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-260 (TAC NO. ME3720) |
| | : 1. The March 31,2010, submittal (Agencywide Documents Access and Management System Accession No. ML100920542) states that the revised risk-informed inservice inspection (RI-ISI) program represents a reduction in risk with regard to core damage frequency (CDF) and large early release fraction (LERF). There are other risk criteria in Section 4.4.2 of WCAP-14572, Revision 1-NP-A, "Westinghouse Owners Group Application of Risk-Informed Methods to Piping Inservice Inspection Topical Report," February 1999 (WCAP), that must also be met. Please provide the results of your evaluation that will allow you to state that the risk/safety evaluation criteria in 4.4.2 of the WCAP are met. |
| | : 2. Attachment 10, page 6, of the submittal clearly lists 51 previous RI-ISI examinations for R1.16. The value(s) provided for the revised program are unclear. Please clarify how many examinations are listed as R1.16 for the revised RI-ISI program. |
| | : 3. Attachment 10, page 3, of the submittal states: |
| | itA new Delta Risk Evaluation was performed, and the revised RI-ISI program continues to represent a risk reduction when compared to the last deterministic ASME Section XI inspection program. The revised RI-ISI program represents a reduction of 1.869E-05 in regards to CDF and 1.596E-07 in regards to LERF." |
| | A) Per letter dated October 16,2000, the Tennessee Valley Authority reported an increase in CDF and LERF for the previous RI-ISI program when compared to the last deterministic American Society of Mechanical Engineers (ASME), Section XI inspection program. The estimated change in risk was in the third and fourth significant digits for the estimated LERF and CDF; therefore, the RI-ISI program was considered risk neutral. Please clarify the above statement to properly reflect the change in risk of the previous RI-ISI program B) Please provide additional information and clarification for how a decrease in volumetric examinations associated with thermal fatigue and intergranular stress corrosion cracking, when compared to the last RI-ISI program, can produce a very significant risk decrease when compared to the last deterministic ASME, Section XI inspection program. In addition, please provide a table comparing CDF and LERF for "without lSI," "Section XI," and "Risk-Informed" programs. |
| | Enclosure |
| | |
| | March 28, 2011 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 |
| | |
| | ==SUBJECT:== |
| | BROWNS FERRY NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING 2-ISI-1, UPDATED RISK-INFORMED INSERVICE INSPECTION PROGRAM (TAC NO. ME3720) |
| | |
| | ==Dear Mr. Krich:== |
| | |
| | In Attachment 10 of letter dated March 31, 2010 (Agencywide Documents Access and Management System Accession No. ML100920542), Tennessee Valley Authority requested authorization to use a risk-informed process as an alternative for the selection of Class 1 and Class 2 piping welds for examination. |
| | Based on our review of your submittal, the U. S. Nuclear Regulatory Commission staff finds that a response to the enclosed request for additional information is needed before we can complete the review. |
| | This request was discussed with Mr. Thomas Mathews of your staff on March 7, 2011, and it was agreed that a response would be provided by May 6,2011 (60 days). |
| | If you have any questions, please contact me at (301) 415-1055. |
| | Sincerely, IRA! |
| | Christopher Gratton, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-260 |
| | |
| | ==Enclosure:== |
| | Request for Additional Information cc w/encl: Distribution via Listserv Distribution: |
| | PUBLIC LPLlI-2 R/F RidsNrrDorlLpl2-2 RidsNrrDraApla RidsNrrPMBrownsFerry RidsNrrLABClayton RidsOgcRp RidsRgn2MailCenter RidsNrrDorlDpr RidsNrrAcrsAcnwMailCenter ADAMS Accession No'.. ML110820353 OFFICE LPL2-2/PM LPL2-2/LA APLNBC LPL2-2/BC NAME CGratton BClayton DHarrison DBroaddus DATE 03/24/11 03/23/11 03/28/11 03/28/11 OFFICIAL RECORD COpy}} |
Letter Sequence RAI |
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MONTHYEARML1108203532011-03-28028 March 2011 Request for Additional Information Regarding 2-ISI-1, Updated Risk-Informed Inservice Inspection Program Project stage: RAI ML11129A1872011-05-0404 May 2011 Response to NRC Request for Additional Information Regarding Relief Request 2-ISI-1, Updated Risk Informed Inservice Inspection Program Project stage: Response to RAI ML11147A0952011-06-13013 June 2011 Relief from the Requirements to the ASME Code Project stage: Approval 2011-05-04
[Table View] |
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Category:Letter
MONTHYEARML24289A1232024-10-24024 October 2024 Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 ML24270A2162024-09-27027 September 2024 Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075 ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) ML24190A1292024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints ML24185A1512024-07-0303 July 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure ML24184A1142024-07-0202 July 2024 Site Emergency Plan Implementing Procedure Revision ML24183A3842024-07-0101 July 2024 Registration of Use of Cask to Store Spent Fuel (MPC-364, -365) ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) ML24176A1022024-06-24024 June 2024 Reactor Scram Due to Generator Step-Up Transformer Failure ML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 ML24141A2462024-05-20020 May 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24123A2012024-05-0202 May 2024 NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information ML24122A6852024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual CNL-24-036, – 10 CFR 50.46 Annual Report2024-04-25025 April 2024 – 10 CFR 50.46 Annual Report ML24116A2522024-04-25025 April 2024 Site Emergency Plan Implementing Procedure Revision ML24115A1652024-04-24024 April 2024 Breaker Trip Automatically Started an Emergency Diesel Generator 05000296/LER-2024-001, Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup2024-04-22022 April 2024 Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A2302024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 2024-09-03
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24255A5822024-09-10010 September 2024 SLRA - Requests for Additional Information - Set 1 ML24255A5802024-09-10010 September 2024 SLRA - Requests for Additional Information - Set 1 - Email from Jessica Hammock to James Barstow ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24045A0272024-02-14014 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML23332A0042023-11-27027 November 2023 NRR E-mail Capture - Request for Additional Information Related to Proposed Revised Alternative 0-ISI-47 ML23243A9892023-08-29029 August 2023 Inspection Information Request ML23124A0082023-05-0303 May 2023 NRR E-mail Capture - Request for Additional Information Related to Proposed Alternative Requests for the 5th 10-Year Inservice Testing Interval for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML23041A0022023-02-0909 February 2023 NRR E-mail Capture - Request for Additional Information Related to TVA Alternative Request BFN-0-ISI-32 (CNL-22-025) ML22299A0292022-10-26026 October 2022 NRR E-mail Capture - Request for Additional Information for Relief Request BFN-2-ISI-003 Re Weld Examination Coverage ML22292A2722022-10-19019 October 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Adopt TSTF-505 and TSTF-439 for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML22208A2172022-07-15015 July 2022 NRR E-mail Capture - Request for Additional Information Related to TVA Relief Request BFN-21-ISI-02 (CNL-21-081) ML22174A2722022-06-24024 June 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22168A0802022-06-17017 June 2022 NRR E-mail Capture - Request for Confirmation of Information and Additional Information Related to Tva'S Request to Use Control Bay Chiller Cross-Tie ML22160A4742022-06-0303 June 2022 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Re LAR to Use Advanced Framatome Methodologies in Support of Atrium 11 Fuel ML22168A0392022-05-13013 May 2022 NRR E-mail Capture - Draft Request for Confirmation of Information and Additional Information Related to Tva'S Request to Use Control Bay Chiller Cross-Tie 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 ML22047A1612022-02-16016 February 2022 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Expand the SFP Criticality Safety Analysis for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML22025A4132022-01-25025 January 2022 RP Inspection Doc Request ML21343A4232021-12-0909 December 2021 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000259/2022010, 05000260/2022010, and 05000296/2022010) and Request for Information (RFI) ML21173A1042021-06-21021 June 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to TS 3.8.6 ML21041A5422021-02-10010 February 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to Adopt 10 CFR 50.69 ML21041A5432021-02-0505 February 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Draft Request for Additional Information Regarding 10 CFR 50.69 LAR ML21026A1652021-01-26026 January 2021 Document Request for Browns Ferry Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-02 ML20297A3012020-10-22022 October 2020 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to Adopt TSTF-425 ML20296A3782020-10-22022 October 2020 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to Incorporate TMRE ML20294A3762020-09-23023 September 2020 NRR E-mail Capture - Draft Request for Additional Information - Browns Ferry Nuclear Plant, Units 1, 2, and 3, Request to Adopt TSTF-425 ML20266G4472020-09-22022 September 2020 Notification of Inspection and Request for Information ML20224A4732020-08-11011 August 2020 Requalification Program Inspection Browns Ferry Nuclear ML20195B1302020-07-13013 July 2020 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Alternative Request No. 0-ISI-47 ML20149K3212020-05-27027 May 2020 RP Inspection Document Request, Browns Ferry 2020-003 ML20254A3032020-05-13013 May 2020 Request for Supporting Information for the Browns Ferry, Units 1, 2, and 3 Seismic Probabilistic Risk Assessment Audit Review ML20054B8592020-02-20020 February 2020 Emergency Preparedness Program Inspection Request for Information ML20014E6552020-01-14014 January 2020 01 RP Inspection Document Request ML19196A0752019-07-12012 July 2019 NRR E-mail Capture - Final RAIs Browns Ferry Nuclear, Units 1, 2, 3 - Application to Revise Technical Specifications to Adopt TSTF-542 Revision 2, Reactor Pressure Vessel Water Inventory Control ML19116A0712019-06-0303 June 2019 Request for Additional Information Related Resubmittal of Proposed Alternative Request No. 1-ISI-27 for the Period of Extended Operation ML18331A5442018-12-0606 December 2018 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus License Amendment Request (EPID L-2018-LLA-0048) - (Non-Proprietary) ML18317A1642018-11-20020 November 2018 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus License Amendment Request (EPID L-2018-LLA-0048) - Non-Proprietary ML18263A1412018-09-11011 September 2018 NRR E-mail Capture - Browns Ferry Unit 1: RAI Associated with Relief Request 1-ISI-28 ML18138A1102018-05-17017 May 2018 Enclosurequest for Additional Information (Letter to E. D. Schrull Request for Additional Information Regarding Tennessee Valley Authority'S Decommissioning Funding Plan Update for Browns Ferry and Sequoyah Isfsis) ML18108A1872018-04-18018 April 2018 Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000259/2018411, 05000260/2018411, and 05000296/2018411 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) ML17216A0062017-08-18018 August 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to LAR to Revise Modifications and Implementations Related to NFPA 805 for Fire Protection for Light Water Reactor Generating Plants (CAC Nos. MF9814-MF9816) ML17163A0502017-06-0808 June 2017 NRR E-mail Capture - RAI for Browns Ferry RR 3-ISI-28 CAC No. MF9257 ML17150A0792017-05-23023 May 2017 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet LAR for EAL Change to Adopt NEI-99-01 Rev.6 (CAC Nos. MF9054 - MF9060) ML16288A0182016-10-27027 October 2016 Browns Ferry Nuclear Plant, Units 2 and 3 - RAI Related to Relief Request for the Use of Alternatives to Certain American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI Requirements (CAC Nos. MF7795 and MF7796) ML16236A0732016-08-31031 August 2016 Request for Additional Information Related to License Amendment Request to Add New Technical Specification 3.3.8.3 ML16203A0272016-07-25025 July 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (CAC Nos. MF6738, MF6739, and MF6740) ML16194A2292016-07-21021 July 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate ML16187A2932016-07-21021 July 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate (CAC Nos. MF6741, MF6742, and MF6743) ML16154A5442016-06-21021 June 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate 2024-09-10
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 28, 2011 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SUB~IECT: BROWNS FERRY NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING 2-ISI-1, UPDATED RISK-INFORMED INSERVICE INSPECTION PROGRAM (TAC NO. ME3720)
Dear Mr. Krich:
In Attachment 10 of letter dated March 31, 2010 (Agencywide Documents Access and Management System Accession No. ML100920542), Tennessee Valley Authority requested authorization to use a risk-informed process as an alternative for the selection of Class 1 and Class 2 piping welds for examination.
Based on our review of your submittal, the U. S. Nuclear Regulatory Commission staff finds that a response to the enclosed request for additional information is needed before we can complete the review.
This request was discussed with Mr. Thomas Mathews of your staff on March 7, 2011, and it was agreed that a response would be provided by May 6,2011 (60 days).
If you have any questions, please contact me at (301) 415-1055.
Christopher Gratton, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-260
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR RELIEF 2-IS1-1 UPDATED RISK INFORMED INSERVICE INSPECTION PROGRAM TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-260 (TAC NO. ME3720)
- 1. The March 31,2010, submittal (Agencywide Documents Access and Management System Accession No. ML100920542) states that the revised risk-informed inservice inspection (RI-ISI) program represents a reduction in risk with regard to core damage frequency (CDF) and large early release fraction (LERF). There are other risk criteria in Section 4.4.2 of WCAP-14572, Revision 1-NP-A, "Westinghouse Owners Group Application of Risk-Informed Methods to Piping Inservice Inspection Topical Report," February 1999 (WCAP), that must also be met. Please provide the results of your evaluation that will allow you to state that the risk/safety evaluation criteria in 4.4.2 of the WCAP are met.
- 2. Attachment 10, page 6, of the submittal clearly lists 51 previous RI-ISI examinations for R1.16. The value(s) provided for the revised program are unclear. Please clarify how many examinations are listed as R1.16 for the revised RI-ISI program.
- 3. Attachment 10, page 3, of the submittal states:
itA new Delta Risk Evaluation was performed, and the revised RI-ISI program continues to represent a risk reduction when compared to the last deterministic ASME Section XI inspection program. The revised RI-ISI program represents a reduction of 1.869E-05 in regards to CDF and 1.596E-07 in regards to LERF."
A) Per letter dated October 16,2000, the Tennessee Valley Authority reported an increase in CDF and LERF for the previous RI-ISI program when compared to the last deterministic American Society of Mechanical Engineers (ASME),Section XI inspection program. The estimated change in risk was in the third and fourth significant digits for the estimated LERF and CDF; therefore, the RI-ISI program was considered risk neutral. Please clarify the above statement to properly reflect the change in risk of the previous RI-ISI program B) Please provide additional information and clarification for how a decrease in volumetric examinations associated with thermal fatigue and intergranular stress corrosion cracking, when compared to the last RI-ISI program, can produce a very significant risk decrease when compared to the last deterministic ASME,Section XI inspection program. In addition, please provide a table comparing CDF and LERF for "without lSI," "Section XI," and "Risk-Informed" programs.
Enclosure
March 28, 2011 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING 2-ISI-1, UPDATED RISK-INFORMED INSERVICE INSPECTION PROGRAM (TAC NO. ME3720)
Dear Mr. Krich:
In Attachment 10 of letter dated March 31, 2010 (Agencywide Documents Access and Management System Accession No. ML100920542), Tennessee Valley Authority requested authorization to use a risk-informed process as an alternative for the selection of Class 1 and Class 2 piping welds for examination.
Based on our review of your submittal, the U. S. Nuclear Regulatory Commission staff finds that a response to the enclosed request for additional information is needed before we can complete the review.
This request was discussed with Mr. Thomas Mathews of your staff on March 7, 2011, and it was agreed that a response would be provided by May 6,2011 (60 days).
If you have any questions, please contact me at (301) 415-1055.
Sincerely, IRA!
Christopher Gratton, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-260
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv Distribution:
PUBLIC LPLlI-2 R/F RidsNrrDorlLpl2-2 RidsNrrDraApla RidsNrrPMBrownsFerry RidsNrrLABClayton RidsOgcRp RidsRgn2MailCenter RidsNrrDorlDpr RidsNrrAcrsAcnwMailCenter ADAMS Accession No'.. ML110820353 OFFICE LPL2-2/PM LPL2-2/LA APLNBC LPL2-2/BC NAME CGratton BClayton DHarrison DBroaddus DATE 03/24/11 03/23/11 03/28/11 03/28/11 OFFICIAL RECORD COpy