Letter Sequence RAI |
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CAC:MF8526, Steam Generator Tube Integrity, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (Approved, Closed) |
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MONTHYEARULNRC-06174, Licensing Document Change Notice (LDCN)14-0014 Application to Revise TS to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process2015-03-0909 March 2015 Licensing Document Change Notice (LDCN)14-0014 Application to Revise TS to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process Project stage: Request ULNRC-06200, Supplement to Licensing Document Change Notice (LDCN)12-0014 Application to Revise Technical Specification to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using Consolidated..2015-04-0808 April 2015 Supplement to Licensing Document Change Notice (LDCN)12-0014 Application to Revise Technical Specification to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using Consolidated.. Project stage: Supplement ULNRC-06236, Additional Supplement to Licensing Document Change Notice 14-0014 TSTF-5102015-08-12012 August 2015 Additional Supplement to Licensing Document Change Notice 14-0014 TSTF-510 Project stage: Supplement ULNRC-06270, Final Supplement to Document Change Notice (LDCN) 14-0014 Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using The..2015-12-10010 December 2015 Final Supplement to Document Change Notice (LDCN) 14-0014 Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using The.. Project stage: Supplement ML15324A1142016-02-0202 February 2016 Issuance of Amendment No. 215, Adopt Technical Specification Task Force (TSTF) Traveler TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection Project stage: Approval CNL-16-141, Application to Modify Technical Specifications Regarding Intermittent Opening of the Auxiliary Building Secondary Containment Closure Technical Specification 3.7.12, Auxiliary Building Gas Treatment System.2016-10-20020 October 2016 Application to Modify Technical Specifications Regarding Intermittent Opening of the Auxiliary Building Secondary Containment Closure Technical Specification 3.7.12, Auxiliary Building Gas Treatment System. Project stage: Request ML16340A0402016-11-30030 November 2016 Acceptance for Review - Request to Modify TS 3.7.12 Auxiliary Building Gas Treatment System Project stage: Acceptance Review ML17076A0232017-03-16016 March 2017 NRR E-mail Capture - Watts Bar, Units 1 and 2 - Final Request for Additional Information Concerning Request to Amend ABGTS TS Project stage: RAI CNL-17-044, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (Abgts), for Watts Bar Nuclear Plant, Units 1 and 22017-05-0505 May 2017 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (Abgts), for Watts Bar Nuclear Plant, Units 1 and 2 Project stage: Response to RAI CNL-17-093, Revised Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (ABGTS)2017-07-21021 July 2017 Revised Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (ABGTS) Project stage: Response to RAI ML17236A0572017-10-17017 October 2017 Issuance of Amendments Regarding Auxiliary Building Gas Treatment System Project stage: Approval 2016-11-30
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Category:E-Mail
MONTHYEARML24022A2592024-01-22022 January 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Unit 1, License Amendment Request to Revise TS LCO 3.8.2 to Remove Note C-S Diesel Generator ML24016A0762024-01-16016 January 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2 - License Amendment Request to Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications ML23347A0642023-12-13013 December 2023 12-13-23 Email from Kimberly Green to Wells, Russell, Subject: Results of NRC SUNSI Review of Watts Bar Nuclear Plant Dual-Unit UFSAR, Amendment 5 ML23334A0932023-11-28028 November 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise TS Surveillance Requirement 3.9.5.1 to Reduce RHR Flow Rate During Mode 6 ML23319A1662023-11-0202 November 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Sequoyah Nuclear Plant, and Watts Bar Nuclear Plant, Exemption Request Related to 10 CFR 37.11(c)(2) ML23254A2872023-09-11011 September 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise TS Table 1.1-1 Re Number of Required Rvh Closure Bolts ML23236A2562023-08-24024 August 2023 NRR E-mail Capture - Acceptance Review Results for the Sequoyah and Watts Bar License Amendment Request to Adopt TSTF-567 (L-2023-LLA-0106) ML23191A8672023-07-10010 July 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML23166A1142023-06-15015 June 2023 Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2023-03 ML23150A2472023-05-25025 May 2023 NRR E-mail Capture - Audit Plan Related to Review of the Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Increase the Number of Tritium Producing Burnable Absorber Rods ML23116A1492023-04-21021 April 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Increase the Number of Tritium Producing Burnable Absorber Rods ML23075A0032023-03-13013 March 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Units 1, 2, and 3, License Amendment Request to Revise TS 3.7.11, Required Actions A.1 and E.1 Footnotes Re Date for the Modification ML23072A0722023-03-10010 March 2023 NRR E-mail Capture - (External_Sender) State Consultation - 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) ML23067A2372023-03-0808 March 2023 WB_2023-02_RP_inspection_doc_request ML23013A0382023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML23013A0362023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML22356A2982022-12-22022 December 2022 Email Response to Letter, Dated November 22, 2022 Regarding Watts Bar Integrated Inspection Report ML22353A0812022-12-15015 December 2022 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Unit 2, Alternative Request WBN-2-ISI-01 Regarding Examination of Upper Head Injection Nozzle Dissimilar Metal Piping Butt Welds ML22348A0972022-12-14014 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML22348A0442022-12-13013 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) 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) ML22227A0712022-08-15015 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 (EPID L-2022-LLA-0103) - Corrected ML22227A0262022-08-12012 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 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 ML22215A2752022-08-0303 August 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-554 ML22194A8762022-07-13013 July 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-529 ML22166A4292022-06-0606 June 2022 NRR E-mail Capture - LAR to Adopt TSTF-577 ML22146A3342022-05-25025 May 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Relief Requests (EPID L-2022-LLR-0045 - 0047) ML22136A0182022-05-16016 May 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah Nuclear Plant, Units 1 and 2, Alternative Request RP-11 and Watts Bar Nuclear Plant, Units 1 and 2, Alternative Request IST-RR-9 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 ML22123A1812022-05-0303 May 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Adopt TSTF-577 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 ML22081A2222022-03-22022 March 2022 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Unit 1, License Amendment Request to Revise Allowable Value for TS Table 3.3.2-1, Function 6.e(1) ML22056A3802022-02-25025 February 2022 Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2022-02 ML22131A1902022-02-23023 February 2022 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Unit 2, Request to Revise the Reactor Vessel Surveillance Capsule Withdrawal Schedule ML22046A0392022-02-15015 February 2022 NRR E-mail Capture - Request for Confirmation of Information Regarding the Watts Bar Nuclear Plant, Unit 2, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Final Report ML22038A1882022-02-0404 February 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Revise the TVA Radiological Emergency Plan ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22011A0382022-01-10010 January 2022 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-205-A, Rev. 3 and TSTF-563-A ML21306A2452021-11-0202 November 2021 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.7.8, Essential Raw Cooling Water (ERCW) System ML21267A1392021-09-23023 September 2021 Document Request for Upcoming RP Inspection at Watts Bar ML21252A0912021-09-0909 September 2021 NRR E-mail Capture - Request for Comments on Proposed Issuance of Amendments to Watts Bar Nuclear Plant, Unit 2 - Revise Steam Generator Secondary Side Water Level ML21223A2592021-08-11011 August 2021 Affidavit - Prop Slides - Partially Closed Meeting with TVA Potential Watts Bar, Unit 2 Tube Locking LAR 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 ML21215A1152021-07-26026 July 2021 NRR E-mail Capture - (External_Sender) Correction to WBN Chiller Replacement LAR ML21215A1142021-07-26026 July 2021 NRR E-mail Capture - (External_Sender) Correction to WBN Chiller Replacement LAR ML21197A0452021-07-15015 July 2021 WBN U1 Isi/Sgisi Request for Information (RFI) Letter ML21193A2422021-07-12012 July 2021 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise the Watts Bar Nuclear Plant, Unit 2 Technical Specifications Related to Steam Generator Inspection/Repair Program Provisions ML21189A0202021-06-29029 June 2021 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specifications 3.3.6 and 3.3.7 Re Radiation Monitor Redundant Unit of Measure 2024-01-22
[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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Text
NRR-PMDAPEm Resource From: Schaaf, Robert Sent: Thursday, March 16, 2017 4:31 PM To: Wells, Russell Douglas; Gordon Arent Cc: Bucholtz, Kristy; Karipineni, Nageswara; Hamm, Matthew; Beasley, Benjamin; Hon, Andrew; Saba, Farideh
Subject:
Watts Bar, Units 1 and 2 - Final Request for Additional Information Concerning Request to Amend ABGTS TS (CAC Nos. MF8526 and MF8527)
Attachments: Watts Bar - Final RAIs Related to ABGTS LAR - MF8526.docx On February 22, 2017, the U.S. Nuclear Regulatory Commission (NRC) staff sent the Tennessee Valley Authority draft Requests for Additional Information (RAIs) via e-mail. These RAIs relate to TVAs license amendment request (LAR) dated October 20, 2016 (ADAMS Accession No. ML16294A551), that would revise the Technical Specifications related to the auxiliary building gas treatment system (ABGTS) to provide an action for when the auxiliary building secondary containment enclosure (ABSCE) boundary is degraded, and to allow the ABSCE boundary to be open intermittently under administrative controls without entering the associated ABGTS limiting condition for operation.
An RAI clarification call was held on March 6, 2017. The final RAIs, modified from the February 22, 2017, draft as discussed below, are attached to this e-mail.
Regarding question ARCB-RAI-2, TVA stated that it did not believe that Part 3 of the question is needed as TVA considered it to not be consistent with Standard Technical Specifications. The staff indicated during the call that it would consider deleting or rewording the question. Upon further consideration, the staff has determined that the requested change remains necessary in order to ensure that the compensatory measures will be implemented to protect plant personnel consistent with the intent of the cited regulatory criteria.
Regarding question SBPB-RAI-1, TVA questioned whether Part 2 of the question was redundant to elements of ARCB-RAI-1. The staff indicated during the call that the information was necessary as supplemental to the information requested in ARCB-RAI-1. The staff has modified the text in the bullet preceding the numbered parts of this question to clarify the staffs concern and modified Part 2 to clarify the requested licensee response.
During the March 6, 2017, clarification call the licensee agreed to provide a response to the final RAIs within 45 days from the date of the call, which is April 20, 2017.
If you have any questions, please contact me at 301-415-6020 or Robert.Schaaf@nrc.gov.
- Regards, Robert G. Schaaf Robert G. Schaaf Senior Project Manager, Watts Bar/Bellefonte Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8G9A Washington, DC 20555 1
301-415-6020 (o)
Robert.Schaaf@nrc.gov 2
Hearing Identifier: NRR_PMDA Email Number: 3407 Mail Envelope Properties (85e53b8f722c4fcabc8af6dcaf210b66)
Subject:
Watts Bar, Units 1 and 2 - Final Request for Additional Information Concerning Request to Amend ABGTS TS (CAC Nos. MF8526 and MF8527)
Sent Date: 3/16/2017 4:30:56 PM Received Date: 3/16/2017 4:30:00 PM From: Schaaf, Robert Created By: Robert.Schaaf@nrc.gov Recipients:
"Bucholtz, Kristy" <Kristy.Bucholtz@nrc.gov>
Tracking Status: None "Karipineni, Nageswara" <Nageswara.Karipineni@nrc.gov>
Tracking Status: None "Hamm, Matthew" <Matthew.Hamm@nrc.gov>
Tracking Status: None "Beasley, Benjamin" <Benjamin.Beasley@nrc.gov>
Tracking Status: None "Hon, Andrew" <Andrew.Hon@nrc.gov>
Tracking Status: None "Saba, Farideh" <Farideh.Saba@nrc.gov>
Tracking Status: None "Wells, Russell Douglas" <rdwells0@tva.gov>
Tracking Status: None "Gordon Arent" <garent@tva.gov>
Tracking Status: None Post Office: HQPWMSMRS08.nrc.gov Files Size Date & Time MESSAGE 2616 3/16/2017 4:30:00 PM Watts Bar - Final RAIs Related to ABGTS LAR - MF8526.docx 36172 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: ZZZ
REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION 3.7.12, AUXILIARY BUILDING GAS TREATMENT SYSTEM (ABGTS).
TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-390 AND 50-391 By letter dated October 20, 2016, (Agencywide Documents Access and Management System Accession Number ML16294A551), Tennessee Valley Authority (TVA), the licensee, proposed changes to the Watts Bar Nuclear Plant (WBN), Units 1 and 2, technical specifications (TSs). The proposed changes would revise WBN TS 3.7.12, Auxiliary Building Gas Treatment System (ABGTS), to provide an action when both trains of the ABGTS are inoperable due to the auxiliary building secondary containment enclosure boundary being inoperable.
During the Nuclear Regulatory Commission (NRC) staffs review of the impact of the proposed changes on all DBAs currently analyzed in the WBN updated final safety analysis report (UFSAR) that could have the potential for significant dose consequences per Regulatory Guide (RG) 1.195 and 1.183, the NRC staff determined that more information was needed to complete the review.
ARCB-RAI-1 In the application a proposed change adds a Note to TS Limiting Condition of Operation (LCO) 3.7.12, Auxiliary Building Gas Treatment System (ABGTS). The proposed Note states, The Auxiliary Building Secondary Containment Enclosure (ABSCE) boundary may be opened intermittently under administrative control.
In addition, the proposed change adds the following sentences to TS 3.7.12 LCO Bases.
The LCO is modified by a Note allowing the ABSCE boundary to be opened intermittently under administrative controls. For entry and exit through doors the administrative control of the opening is performed by the person(s) entering or exiting the area. For other openings, these controls consist of stationing a dedicated individual at the opening who is in continuous communication with the control room. This individual will have a method to rapidly close the opening when a need for auxiliary building isolation is indicated.
Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 50.36 requires the technical specifications be derived from the analyses and evaluation included in the safety analysis report.
Section 15.5.3 of the WBN Updated Final Safety Analysis Report (UFSAR) contains the analysis of the environmental consequences of a postulated Loss of Coolant Accident ENCLOSURE
2 (LOCA). This analysis assumes that activity leaking to the Auxiliary Building is directly released to the environment for the first four minutes, after which it is held up for 0.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and then released through the ABGTS filter system.
The proposed LCO note to TS 3.7.12 described above is not consistent with the environmental consequences of a LOCA licensing basis for WBN, which assumes the ABSCE boundary is established with a negative internal pressure within 4 minutes after occurrence of a LOCA. The proposed note allows the ABSCE boundary to be opened for an indefinite length of time, in addition to its unlimited use. Furthermore, the referenced administrative control is not defined in the operating license or proposed TS for WBN. The administrative control is discussed in the TS Bases. The TS Bases should describe or clarify the TS; the TS bases are not allowed to change the TS. The proposed TS 3.7.12 Bases state requirements for TS 3.7.12 and therefore the TS 3.7.12 Bases are changing the TS.
Therefore, the NRC staff requests TVA to provide the following:
- a proposed change to TS 3.7.12 that is consistent with the NRC-approved design basis as reflected in the UFSAR Section 15.5.3, Environmental Consequences of a LOCA analysis, and
ARCB-RAI-2 WBN current TS 3.7.12 requires the plant to be in hot standby (mode 3) in six hours and in cold shutdown (mode 5) in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> if both ABGTS trains are inoperable for any reason. In this license amendment request (LAR) a new Condition B is proposed which will address both trains of ABGTS being inoperable due to the ABSCE boundary being inoperable and would allow 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore the ABSCE boundary and therefore restore operability to both ABGTS trains. Section 3.2 Technical Analysis, of the LAR states:
During the period that the ABSCE boundary is inoperable, appropriate compensatory measures will be utilized. The preplanned measures will be available to address these concerns for intentional and unintentional entry into proposed new LCO 3.7.12 Condition B. TVA will have approved written procedures in place that describe the compensatory measures to be taken in the event of an intentional or unintentional entry into LCO 3.7.12 Condition B. The procedures will provide appropriate, preplanned compensatory measures consistent with the intent, as applicable, of [Generic Design Criteria] GDCs 19, 60, and 64 and 10 CFR Part 100 to protect plant personnel from potential hazards such as radioactive contamination, toxic chemicals, smoke, temperature and relative humidity, and physical security (see Enclosure 2). The proposed 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> completion time is reasonable based on the low probability of a DBA occurring during this period and the use of preplanned compensatory measures.
Reasonable assurance of adequate protection cannot be based solely on the probability of the accident occurring. With both trains of ABGTS inoperable, the plant is in an
3 unanalyzed condition because the radiological consequence analysis for LOCA does not show that the limits of the 10 CFR 100 and GDC 19 of 10 CFR 50 Appendix A can be met without operation of the ABGTS. This proposal will allow the plant to remain in modes 1, 2, 3, or 4 for an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before requiring the plant to be placed in cold shutdown or mode 5. However, the technical analysis section of the LAR does not provide reasonable assurance that adequate protection will be maintained without the ABGTS and that the limits in GDC 19 of 10 CFR 50 Appendix A and 10 CFR 100 will be met by use of compensatory measures. The conclusion section of the LAR states that the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time limit to restore the inoperable boundary is based on the availability of compensatory measures and the low probability of an accident occurring during the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> periods that the ABGTS trains are inoperable, and TVA concludes that the proposed change is acceptable and complies with applicable regulatory requirements.
However, there is no information presented to support this conclusion. Therefore, please:
- 1. Explain what compensatory measures will be used when the ABSCE boundary is inoperable and in what document they are located; and
- 2. Explain how the requirements of 10 CFR 100 and GDC 19 of 10 CFR 50 Appendix A are met using these compensatory measures.
In addition, if compensatory measures are relied upon as the safety basis for the proposed change then they must be either a condition of the license or be incorporated into the TS, not the TS Bases.
- 3. Please provide a license condition or proposed TS change that requires immediate implementation of the compensatory measures.
ARCB-RAI-3 The licensee states in the amendment request:
In order to support normal operation, short duration events (e.g., venting operations, test evolutions, fire damper testing, annulus entries),
penetration openings, and auxiliary building (AB) isolations may be required. These events have been analyzed and do not exceed Title 10 of the Code of Federal Regulations (10 CFR) Part 100 limits for offsite dose and 10 CFR Part 50, Appendix A, General Design Criterion (GDC) 19 for the control room dose.
It is not clear to the NRC staff which events have been analyzed that support the addition of the new Condition B. Please clarify the statement above, identifying which events have been analyzed, and explain the details of the analysis performed for each event showing that the 10 CFR Part 100 and 10 CFR Part 50, Appendix A, GDC 19 limits are not exceeded.
4 SBPB-RAI-1 The LAR proposes two changes to the TSs. One of the changes proposes to revise LCO 3.7.12 by adding a note stating The Auxiliary Building Secondary Containment Enclosure (ABSCE) boundary may be opened intermittently under administrative control.
The second change adds a new Condition B to specify Required Action with a completion Time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore an inoperable ABSCE boundary to operable status. Based on the discussion provided in the LAR (e.g. Sections 2.2 and 3.2 of ):
- The intent of the new Condition B is to support normal operation, short duration events (e.g. venting operations, test evolutions, fire damper testing, annulus entries). The proposed Condition B would allow the completion time for restoration of the ABSCE boundary to be extended to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, significantly reducing the potential to enter LCO 3.7.12, Condition C (Condition B under the current TS).
Please provide a brief synopsis of how many entries into current LCO 3.7.12, Condition B resulted under the current TS in the last 5 years and if they proceeded into unnecessary shutdowns.
- The intent of the new note under LCO 3.7.12 is to allow normal personnel entry and exit through the doors, and to allow breaches through the ABSCE boundary above those limits applied on a normal basis (i.e. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> as a result of new Condition B) during refueling and maintenance outage activities such as ice blowing activities. All the associated breaches will be handled by administrative procedures. Additionally, the new note will also be used during future replacement of WBN Unit 2 steam generators. Section 2.2 of Enclosure 1 to the LAR states Otherwise with the proposed changes, intermittent opening of the ABSCE boundary under administrative controls will be allowed in Modes 1, 2, 3, and 4 without entering LCO 3.7.12. This note could be interpreted to allow indefinite breaching of the ABSCE boundary (i.e., in excess of the 24-hour limitation imposed as a result of new Condition B).
- 1) Please provide additional information about the frequency and duration of the expected ABSCE boundary breaches to support the work activities as stated in the LAR, and the extent of control the proposed TS may have on the frequency and duration of the breaches.
- 2) Please provide appropriate licensing basis changes to limit the application of the new note to short duration breaches of the ABSCE boundary (i.e., not to exceed the 24-hour period permitted by proposed new Condition B).
- 3) SR 3.7.2.4 requires to Verify one ABGTS train can maintain a pressure between 0.25 and 0.5 inches water gauge with respect to atmospheric pressure during the post-accident mode of operation at a flow rate 9300 and 9900 cfm. Is there any drawdown test applicable to the ABGTS to pull the ABSCE to a minimum vacuum?
5 Please provide available data to verify the capability of ABGTS to establish a negative pressure in the ABSCE (see item 2 above) and discuss the margins embedded in that data.