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MONTHYEARML0832602022008-11-25025 November 2008 Request for Additional Information Regarding Cable Issues Corrective Action Program Project stage: RAI ML0835401392008-12-17017 December 2008 Response to Request for Additional Information Regarding Cable Issues Corrective Action Program Project stage: Response to RAI ML0902104732009-01-14014 January 2009 Response to Request for Additional Information Regarding Cable Issue Corrective Action Program Project stage: Response to RAI ML0905604272009-03-0606 March 2009 Notice of Meeting with Tennessee Valley Authority to Discuss Corrective Action Program (CAP) for Cable Issues for Watts Bar Nuclear Plant Unit 2 Project stage: Request ML0909101502009-04-0202 April 2009 Summary of Meeting with Tennessee Valley Authority (Tva), Regarding Corrective Action Program (CAP) for Cable Issues at Watts Bar Unit 2 Project stage: Meeting ML0911201832009-04-0606 April 2009 Unit 2 - Additional Information Regarding WBN Unit 2 Corrective Action Programs Project stage: Other ML0914102842009-05-18018 May 2009 Additional Information Regarding Corrective Action Programs Project stage: Other ML0921511552009-08-31031 August 2009 Safety Evaluation - Corrective Action Program Plans for Cable and Electrical Issues Project stage: Approval ML0921511532009-08-31031 August 2009 Letter - Corrective Action Program Plans for Cable and Electrical Issues Project stage: Other 2009-03-06
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Category:Letter
MONTHYEARCNL-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 CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation IR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 ML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule ML24081A0262024-03-21021 March 2024 Emergency Plan Implementing Procedure Revisions ML24079A0312024-03-19019 March 2024 Wb 2024-301, Corporate Notification Letter (210-day Ltr) CNL-24-031, Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-03-18018 March 2024 Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance CNL-24-028, Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 IR 05000390/20240102024-03-0808 March 2024 Age-Related Degradation Inspection Report 05000390/2024010 and 05000391/2024010 CNL-24-012, Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-02-28028 February 2024 Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance IR 05000390/20230062024-02-28028 February 2024 Annual Assessment Letter for Watts Bar Nuclear Plant Units 1 and 2 - Report 05000390/2023006 and 05000391/2023006 CNL-24-023, Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 ML24009A1712024-02-16016 February 2024 Environmental Assessment and Finding of No Significant Impact Related to an Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods (EPID L-2023-LLA-0039) - Letter ML24019A0722024-02-14014 February 2024 Request for Withholding Information from Public Disclosure IR 05000390/20230042024-02-13013 February 2024 Integrated Inspection Report 05000390/2023004 and 05000391/2023004 and Apparent Violation 2024-09-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24260A0322024-09-10010 September 2024 NRR E-mail Capture - Request for Additional Information Regarding the Watts Bar Unit 2 Steam Generator Tube Inspection Report for U2R5 ML24155A1372024-05-29029 May 2024 Email from K. Green to S. Hughes Request for Additional Information Related to License Amendment Request to Revise Residual Heat Removal Flow Rate ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24045A0312024-02-14014 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML23166A1142023-06-15015 June 2023 Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2023-03 ML23067A2372023-03-0808 March 2023 WB_2023-02_RP_inspection_doc_request ML23030A3512023-01-25025 January 2023 Notification of Watts Bar Nuclear Plant - Design Bases Assurance Inspection (Programs) and Initial Information Request ML22343A0692022-12-0808 December 2022 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML22227A0272022-08-11011 August 2022 NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2 ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans ML22115A1402022-04-25025 April 2022 NRR E-mail Capture - Requests for Confirmation of Information and Additional Information Regarding Watts Bar Nuclear Plant, Unit 2 Exemption Request Re 10 CFR Part 26 (L-2022-LLE-0017) ML22083A2372022-03-24024 March 2022 NRR E-mail Capture - Request for Additional Information and Confirmation of Information Related to Tva'S Request for Changes to Watts Bar Nuclear Plant, Units 1 and 2, Technical Specification 3.7.8 ML22056A3802022-02-25025 February 2022 Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2022-02 ML21267A1392021-09-23023 September 2021 Document Request for Upcoming RP Inspection at Watts Bar ML21221A2602021-08-0909 August 2021 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 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) ML21095A0422021-04-0202 April 2021 NRR E-mail Capture - Added Clarification to RAI 2 for Thot LAR 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 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) 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) 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 2024-09-10
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 25, 2008 Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction 6A Lookout Place 110'1 Market Street Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING CABLE ISSUES CORRECTIVE ACTION PROGRAM (TAC NO. MD9182)
Dear Mr. Bhatnagar:
By letter dated May 29, 2008, the Tennessee Valley Authority (TVA) submitted the program methods that it proposes to use to resolve those sub-issues of the Cable Issues Corrective Action Program (CAP) at Watts Bar Nuclear Plant (WBN) Unit 2 that are different from those used for WBN Unit 1. TVA also provided the differences, along with their justification, to demonstrate that the alternate resolutions to these cable issues would be equally effective.
The staff has reviewed the information provided by TVA and has determined that additional information is required to complete its evaluation of the proposed cable issues CAP for WBN Unit 2. The specific questions are detailed for each of the issues in the enclosed request for additional information (RAI). Based on discussions with your staff, we understand that you plan to respond to the enclosed RAI within 30 days of the date of this letter.
If you should have any questions, please contact me at 301-415-1457.
Sincerel ,
~7~X~~
trick D. Milano, Senior Project Manager lant Licensing Branch 111-1 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 Related to Cable Issues Corrective Action Program Tennessee Valley Authority Watts Bar Nuclear Plant Unit 2 Docket No. 50-391 By letter dated May 29, 2008 (Agencywide Documents Access and Management System Accession No. ML081560183), the Tennessee Valley Authority (TVA) submitted its proposed program methods to resolve those sub-issues of the Cable Issues Corrective Action Program (CAP) at Watts Bar l\Iuclear Plant (WBN) Unit 2 that are different from those used for WBN Unit 1. TVA provided the differences in the program for WBN Unit 2, along with the justification for the differences, to demonstrate that the alternate resolutions would be equally effective.
After reviewing the information provided by TVA, the NRC staff requests the following be addressed:
- 1. Cable Jamming Issue
- a. Justify the acceptance criteria regarding the assumed relationship between sidewall bearing pressure (SWBP) and jamming. If applicable, provide industry references.
- b. Identify the manufacturer and types of cable used at WBN Unit 2. Also, identify the manufacturer and types of the six cables that formed the basis for the conclusions.
- c. Provide a detailed justification on how TVA was able to extrapolate the results of the six cables to a total of 39 cables. Also, provide a detailed discussion on the condition of the additional 37 conduits found with unacceptable jamming ratios during walkdowns.
Furthermore, explain why the additional 37 conduits were not identified during the original investigation that discovered 39 cables with unacceptable jamming ratios.
- d. Describe the circumstances that would lead TVA to accepting a jamming ratio outside the requirements of General Construction Specification G-38.
- e. Regarding TVA Calculation WBPEVAR8905050, which establishes the criteria for selecting cables in the jamming population (2.8 - 3.1) based on SWBP:
- 1. The calculation appears to define jam ratio as the ratio of the conduit inside diameter (D) to the average cable outside diameter (d). This is contrary to other industry guidance on cable pulling, which defines the jam ratio as 1.05 Old (e.g., Okonite Cable Installation Manual; Polywater Technical Paper; Electric Power Research Institute (EPRI) EL-5036, "Power Plant Electrical Reference Series, Vol. 4, Wire and Cable;" Thue, et aI., Electrical Power Cable Engineering, 2nd Edition; and Southwire Power Cable Installation Guide). In addition, many of these industry sources extend the jam ratio upper limit to 3.2, and at least two sources use a jam ratio lower limit of 2.6.
-2 Discuss the discrepancy between TVA's criteria and the recommended industry criteria, and explain how TVA's criteria bounds the recommended industry criteria.
- 2. Describe whether pulling tensions and SWBP were calculated in both directions and whether the samples were categorized by the worst-case results.
- 3. The basic assumption used in the calculation is that damage from jamming is worse with higher SWBP. However, SWBP is calculated without regard to jamming. Therefore, a cable with a lower value of SWBP could jam and result in higher SWBP than calculated.
Provide the technical basis for the above mentioned assumption.
- 4. Confirm that SWBP was not calculated with tension assumed at the breaking point of the pull rope or conductor.
- f. Regarding TVA calculation WBPEVAR9008003, which provided the results of inspections and evaluation of the sample of six cables in 34 conduits:
- 1. Provide a detailed discussion on the follow-up actions that were performed after cable '1 PL4985B was found in different conduits.
- 2. The TVA analysis addressed only single conductor power cables (e.g., 3-1/c, 400 and 500 MCM, 600 V with jam ratios in the range 2.8-3.0 and a single 3-1/c, 2/0, 8 kV cable with a jam ratio of 2.9). Provide a detailed technical justification for routing the one medium voltage cable in a three inch conduit. Describe any corrective actions that may be associated with this cable routing.
- 3. Provide a detailed technical justification as to why the three-multi-conductor cables (either multi-conductor control cable (2/c #14 and 7/c #14), low voltage power cables (3/c #10,1 /c#12 and 2/c #12), or instrumentation cables (2/c#16 SHLD, 3/c#16 TW)) with the same outside diameter were not addressed in the acceptance criteria even though their jam ratios were within the target range.
- 2. Cable Pull-By Issue
- a. Identify the physical mechanisms that could result in cable damage from pull-bys. This should include damage that may result from the pulling rope on existing cables and the residual dried cable pulling lubricant in the conduit on the new cable.
- b. Clarify the relationship of SWBP on cable pull-by damage. If applicable, provide industry references.
- c. The assumption that pull-bys have always occurred does not appear to be conservative.
This could imply that any cable could be subject to pull-by damage, and the lack of evidence on any cable selected could be used for justification of not having a problem with cable damage due to pull-bys. Given this scenario, describe how the assumption that pull-bys have always occurred is conservative.
-3
- d. Describe how SWBP is calculated with existing cables in the conduit. If applicable, provide industry references. Explain the basis for crediting a coefficient of friction less than 1.0. In the response, discuss how the presence of foreign material in the conduit (e.g., other cables and dried lubricant) would impact the coefficient of friction?
- e. Provide the total number of cables that were high-pot tested. Provide the total number of cables that only received a visual inspection.
- f. Define "short length" of conduit.
- g. TVA's proposed corrective action for WBN Unit 2 states that "[ilf any segment remains in a high risk category, the cables in that conduit will be replaced." Confirm that the entire length of cable will be replaced, not just the cable in the high-risk segment.
- h. The TVA Cable Issues CAP noted that industry guidance did not exist for cable pull-bys.
The Institute of Electrical and Electronics Engineers (IEEE) Standard 1185-1994, "IEEE Guide for Installation Methods for Generating Station Cables," provides guidance for cable pull-bys. Address the recommended precautions contained in IEEE 1185, Section 9, "Cable Pull-bys," and identify how concerns similar to those identified in the industry guidance as noted below were addressed.
- 1. What, if any, limits were in place at WBN UNIT 2 for conduit fill before and following the installation of additional cables using the cable pull-by method?
- 2. Did any of the cable pull-bys result in adding a third cable to two eXisting cables of the same cable outside diameter (OD) such that cable jamming could be a factor?
- 3. Was the compatibility of the existing cable installation and the additional cable installation evaluated for (1) their abrasive effect on one another, (2) cut-through resistance, and (3) thermal endurance?
- 4. IEEE 1185 states that the coefficient of friction between unlubricated, soft, rubber-like jackets could easily exceed 1.0. Clarify how the coefficients of friction used in the cable pulling calculation were adjusted for the unlubricated cable sections, solidified lubricants, and leftover pulling ropes existing in the conduits.
- 5. IEEE 1185 states that the damage that can occur during cable pull-bys could affect both the existing cables and the cables being installed. Describe how the impact of sidewall pressures on the existing cables during the pulling of new cables was evaluated.
- 6. IEEE 1185 states that the severity of the potential damage encountered in cable pull-bys is a function of exerted forces and the duration of those forces between the existing (stationary) cable(s) and of the pull-by (moving) cables. Describe what limits, if any, were imposed on the length of the pUll-by cable so as to limit the contact duration time between the existing (stationary) cable(s) and of the pull-by (moving) cable(s).
- 4
- 7. IEEE 1185 states that the existing raceway should be evaluated to assess the difficulty of the pull-by. Expected pull tension and sidewall pressure should be calculated to ensure that damaging forces will not be encountered. Describe how the pulling tension and sidewall calculations were performed to ensure that damage would not occur to either the existing cables or the new pull-by cables.
- i. The following question relates to TVA calculation WBPEVAR8906036, which is the cable pull-by analysis.
Criterion 3 requires three polyvinyl chloride (PVC) jacketed cables in the conduit prior to the final pull-by. Criterion 4 requires the initial pull and at least two pull-bys be made prior to August 1984 (the time when the use of Polywater J began to be used for a cable lubricant). Criterion 7b requires a minimum of two cables with either Hypalon or CPE jackets installed prior to August 1984. Explain the technical bases for these criteria.
- j. The following question relates to TVA calculation QIR EEB WBN 890003, which discusses the basis for the pull charts.
The coefficient of friction assumptions of 0.75 for fills of <40%, 0.85 for fills of 50%, and 1.0 for fills of 60% appear to be non-conservative when compared to the latest industry standards. Provide a detailed technical discussion on the apparent non-conservative coefficient of friction assumptions.
- 3. Cable SWBP Issue
- a. Define "severe case conduit configurations."
- b. Provide the cable manufacturers' allowable pulling tensions and SWBP for each Class 1E cable installed in WBN UNIT 2.
- c. If applicable, identify all construction specifications (other than G-38) that were revised as a result of the SWBP issue.
- d. Confirm that a minimum of 10 WBN UNIT 2 cables of each type (Le., V2, V3, V4, and V5) were included in the WBN Unit 1 analysis. Identify the cable manufacturer and cable type and construction for each of these cables.
- e. Did the manufacturers of cables for WBN UNIT 2 concur with the higher allowable SWBP values used by TVA? Provide the cable manufacturers' concurrence correspondence or a detailed technical justification that supports these higher allowable SWBP values. .
- f. Reference 7 appears to be a TVA report on cable ampacity, not SWBP. Please clarify.
- g. Identify the contents of the one WBN UNIT 1 conduit that did not meet the new higher SWBP criteria. Describe the corrective action that was performed to assure that this condition does not exist in WBN UNIT 2.
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- h. The following question refers to TVA calculation WBPEVAR9010001, which relates to cable SWBP in harsh environments.
Describe how a random sampling of 40 cables out of a population of 1914 cables in harsh environments with the potential for damage from excessive SWBP is a conservative sample size without regard to the amount of excessive SWBP.
- 4. Pulling Cables Through gO-Degree Condulets and Mid-Route Flexible Conduits Issue
- a. In an earlier submittal, TVA stated that there were no cases of cables actually being pulled through gO-degree conduits. Describe how TVA determined that no cables were pulled through gO-degree conduits. Also, clarify whether this statement is also applicable to gO-degree condulets.
- b. Define "Critical case condulets."
- c. The TVA evaluation was limited to silicone rubber (SR) cables pulled through two gO-degree condulets. Describe how TVA has determined that this was the worst-case scenario for SR cables and not, for instance, longer pulls through one gO-degree condulet.
- d. Provide the construction details for all of the SR cables installed in WBN Unit 2, including the construction details of all SR cables used in the loss-of-coolant accident (LOCA) testing.
- e. The TVA LOCA evaluation was limited to SR cables pulled through gO-degree condulets.
Describe how this envelopes other cable constructions that may have had longer pulls.
- 5. Computer Cable Routing System (CCRS) Software and Database Verification And Validation Issue
- a. TVA identified two contributing factors that resulted in this issue: (1) lack of verification procedures and (2) failure to follow installation procedures. TVA's resolution statement for this issue did not address failure to follow the installation procedures. Describe the corrective actions that were performed to assure that all cables were correctly installed or how the incorrectly installed cables were removed and then correctly routed.
- b. TVA's verification of cable routing appears to have only addressed WBN Unit 1 cables.
Describe how the cable routing of WBN Unit 2 cables that were previously installed using the original CCRS software was verified.
- c. TVA's verification of cable routing appears to have only addressed Class 'I E cables.
The NRC staff is concerned that this could affect raceway fill and raceway permissible loading weights. Describe how non-Class 1E cables routed with Class 1E cables have been considered in determining the adequacy of raceway fill (e.g., permissible loading weights and ampacity).
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- d. Provide the total number of overfilled cable raceways that are identified in the CCRS/lntegrated Cable and Raceway Design System (ICRDS) database. Provide a detailed technical justification for concluding that it is acceptable to allow overfilled raceways.
- e. Provide documentation for the cable ampacity derating analyses that resulted from the overfilled raceways.
- f. Provide a detailed technical justification for determining that the raceway supports for the overfilled raceways is adequate.
- g. Describe how cables designated as "abandoned-in-place" were handled in the CCSRlICRDS database.
- h. Describe the independent verification steps in the procedure (for controlling data entry, data revision, and data utilization) that verify data entry into the CCSRlICRDS database reflects the "as-built configuration."
L The CCSRlICRDS cable data sheets in Sampling Report Number WBNLEE-SR-2004 0001, provided as part of our supplemental information request, reflect design lengths.
However, the installed length field is blank. Describe how the "as-built" lengths were verified and documented. In addition, describe how the electrical calculations/analyses involving cable length considered "as-built" cable lengths.
- j. With regards to page 30 of Sampling Report Number WBNLEE-SR-2004-0001, it appears that the one cable splits into two cables starting from route 3643. Describe how cable 2PP 675 A was routed. Also, describe the ampere value that is reflected in AMP field (Le., cable ampere, load ampere, derated ampere, etc.).
- k. The Note at the bottom of hand-written sheet 30 of Sampling Report Number WBNLEE SR-2004-0001 states that the exact insulation type of cable 2PP 675 A is unknown and requires further research. How many such cases exist, and when will this issue be verified and resolved?
I. With regard to hand written sheet 27 of Sampling Report Number WBNLEE-SR-2004 0001, describe why cable 2PL 3960 A is routed as #4/0 American wire gauge (AWG)
(49.8 amps) for 75 feet and then changes cable size to #1/0 AWG (24.9 amps) for 2013 feet in a cable tray and then changes back to cable size #4/0 AWG (49.8 amps) for 334 feet. Provide the amperage value that was used to size the protection for this cable.
- 6. TVA Cable Issue CAP
- a. The WBN Unit 2 Cable Issue CAP did not address how TVA will comply with General Design Criterion (GDC) 18, "Inspection and testing of electric power systems," of Appendix A to Part 50 of Title 10 of the Code of Federal Regulations. Describe the plant programs or procedures that address periodic inspection and testing of underground cables (including cable insulation) important to safety.
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- b. TVA's description of the various inspections and tests performed to justify acceptability of the as.,.installed cables stated that a sample of cables was selected for WBN Unit 1, WBN Unit 2, and common areas. Describe the sampling criteria. For the cables selected for WBN Unit 2, indicate how many of those cables are required to support WBN Unit 1 operations. Furthermore, describe how many WBN Unit 2 cables are required exclusively for WBN Unit 2 operation.
November 25, 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 CABLE ISSUES CORRECTIVE ACTION PROGRAM (TAC NO. MD9182)
Dear Mr. Bhatnagar:
By letter dated May 29,2008, the Tennessee Valley Authority (TVA) submitted the program methods that it proposes to use to resolve those sUb-issues of the Cable Issues Corrective Action Program (CAP) at Watts Bar Nuclear Plant (WBN) Unit 2 that are different from those used for WBN Unit 1. TVA also provided the differences, along with their justification, to demonstrate that the alternate resolutions to these cable issues would be equally effective.
The staff has reviewed the information provided by TVA and has determined that additional information is required to complete its evaluation of the proposed cable issues CAP for WBN Unit 2. The specific questions are detailed for each of the issues in the enclosed request for additional information (RAI). Based on discussions with your staff, we understand that you plan to respond to the enclosed RAI within 30 days of the date of this letter.
If you should have any questions, please contact me at 301-415-1457.
Sincerely, lRAI Patrick D. Milano, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391
Enclosure:
RAI cc w/encl: Distribution via Listserv DISTRIBUTION:
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