Letter Sequence RAI |
---|
|
|
MONTHYEARCNL-18-118, Application to Revise Technical Specifications Regarding DC Electrical Systems TStf-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 (WBN-TS-18-09)2018-11-29029 November 2018 Application to Revise Technical Specifications Regarding DC Electrical Systems TStf-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 (WBN-TS-18-09) Project stage: Request 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 Project stage: RAI CNL-19-054, Correction to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14)2019-06-0606 June 2019 Correction to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14) Project stage: Request 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 Project stage: Draft Approval 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 Project stage: RAI CNL-19-060, Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14)2019-08-29029 August 2019 Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14) Project stage: Supplement CNL-19-062, Response to Second-Round NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2 (WBN-TS-18-09)2019-09-0404 September 2019 Response to Second-Round NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2 (WBN-TS-18-09) Project stage: Request ML19249C6672019-10-0808 October 2019 Revision of Schedule and Level-of-Effort Estimates for Review of License Amendment Requests Project stage: Approval CNL-19-084, Second Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program...2020-01-17017 January 2020 Second Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program... Project stage: Supplement ML20028F7332020-02-28028 February 2020 Issuance of Amendment Nos. 132 and 36 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-425, Revision 3 Project stage: Approval 2019-07-25
[Table View] |
|
---|
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
[Table view] |
Text
NRR-DMPSPEm Resource From: Schaaf, Robert Sent: Friday, March 8, 2019 3:00 PM To: Wells, Russell Douglas Cc: Hulvey, Kimberly Dawn; Edmondson, Carla; Brown, Michael Anthony; Shoop, Undine; Saba, Farideh
Subject:
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 (EPID L-2018-LLA-0279)
Attachments: Watts Bar TSTF-425 Final RAI Attachment for Transmittal L-2018-LLA-0279.pdf
- Russ, By letter dated October 12, 2018 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML18288A352), the Tennessee Valley Authority (TVA) submitted a license amendment request for the Watts Bar Nuclear Plant (WBN), Units 1 and 2. The requested amendments would modify the WBN, Unit 1 and 2, Technical Specifications to adopt Technical Specification Task Force (TSTF) traveler TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b, (ADAMS Accession No. ML090850642).
The U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information, as described in the attached request for additional information (RAI), is required for the staff to complete its review of the subject request.
These RAIs were transmitted to TVA as draft on February 19, 2019. TVA requested a clarification teleconference regarding the draft RAIs, which was held on March 6, 2019. During the call, the staff agreed to a minor wording change to question RAI APLA-04. The staff has also decided to delete question RAI APLA-06, regarding modelling of test-caused transients and wear of equipment.
During the call, TVA requested a 60-day period from the date of issuance of the final RAIs to respond to this request, due to TVA resource considerations. The staff has subsequently determined that the requested response time period is acceptable. Therefore, please provide TVAs responses to the attached RAIs within 60-days of the date of this transmittal in order to enable the staff to complete its review in accordance with TVAs requested schedule. Please call me at 301-415-6020 if you have any additional questions regarding this request for information.
- Regards, Robert G. Schaaf Senior Project Manager
====================
U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Operating Reactor Licensing Mail Stop O-8B1A
====================
301-415-6020 Robert.Schaaf@nrc.gov 1
Hearing Identifier: NRR_DMPS Email Number: 855 Mail Envelope Properties (BN7PR09MB2690B75A9D5141FE727B6CCDF97C0)
Subject:
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 (EPID L-2018-LLA-0279)
Sent Date: 3/8/2019 2:59:53 PM Received Date: 3/8/2019 2:59:00 PM From: Schaaf, Robert Created By: Robert.Schaaf@nrc.gov Recipients:
"Hulvey, Kimberly Dawn" <kdhulvey@tva.gov>
Tracking Status: None "Edmondson, Carla" <cedmondson@tva.gov>
Tracking Status: None "Brown, Michael Anthony" <mabrown6@tva.gov>
Tracking Status: None "Shoop, Undine" <Undine.Shoop@nrc.gov>
Tracking Status: None "Saba, Farideh" <Farideh.Saba@nrc.gov>
Tracking Status: None "Wells, Russell Douglas" <rdwells0@tva.gov>
Tracking Status: None Post Office: BN7PR09MB2690.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 2082 3/8/2019 2:59:00 PM Watts Bar TSTF-425 Final RAI Attachment for Transmittal L-2018-LLA-0279.pdf 157582 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: ZZZ
REQUESTS FOR ADDITIONAL INFORMATION REGARDING RISK-INFORMED JUSTIFICATION FOR THE RELOCATION OF SPECIFIC SURVEILLANCE FREQUENCY REQUIREMENTS TO A LICENSEE CONTROLLED PROGRAM TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT - UNITS 1 & 2 FACILITY OPERATING LICENSE NO. NPF-90 AND NPF-96 By letter dated October 12, 2018 (ADAMS Accession No. ML18288A352), Tennessee Valley Authority (TVA), submitted a license amendment request (LAR) regarding Watts Bar Nuclear Plant, Units 1 and 2. The proposed amendment would modify the Watts Bar TS by relocating specific surveillance frequencies to a licensee-controlled program with the implementation of NEI 04-10. The licensee states that the proposed changes are consistent with Nuclear Regulatory Commission (NRC) approved industry/Technical Specification Task Force (TSTF)
Standard Technical Specifications (STS) change TSTF-425, Revision 3 (ADAMS Accession No. ML090850642).
REGULATORY BASES AND GUIDANCE Title 10 of the Code of Federal Regulations (10 CFR) Part 50.36(c)(3), requires, in part, that Technical Specifications (TSs) include surveillance requirements. Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
Nuclear Energy Institute (NEI) guidance document NEI 04-10, Revision 1, Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies" (ADAMS Accession No. ML071360456), provides guidance for relocating the surveillance frequencies from the TSs to a licensee-controlled program by providing an NRC-approved methodology for control of the surveillance frequencies. The guidance in NEI 04-10, Revision 1, is acceptable for referencing in licensing actions to the extent specified and under the limitations delineated in NEI 04-10, and the NRC safety evaluation providing the basis for NRC acceptance of NEI 04-10 (ADAMS Accession No. ML072570267).
NEI 04-10 Step 5, RG 1.200 PRA Technical Adequacy, requires the probabilistic risk assessment (PRA) to be of sufficient technical capability and be subjected to a peer review process assessed against a standard or set of acceptance criteria that is endorsed by NRC Regulatory Guide (RG) 1.200, Revision 2, An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities (ADAMS Accession No. ML090410014).
NEI 04-10 Step 5 also states that plants implementing TSTF-425 shall evaluate their PRAs in accordance with RG 1.200. Further, it is stated that the RG specifically addresses the need to evaluate important assumptions that relate to key modeling uncertainties and the identified key sources of uncertainty serve as inputs to identifying appropriate sensitivity cases in [NEI 04-10]
Step 14.
NEI 04-10 Step 5 ALSO discusses how RG 1.200 provides attributes of importance for risk determinations relative to external events, seismic, internal fires, and shutdown. The RG specifically addresses the need to evaluate important assumptions that relate to key modeling uncertainties and the need to evaluate parameter uncertainties and demonstrate that calculated risk metrics (e.g., CDF and LERF) represent mean values.
NEI 04-10 Step 8, Associated STI [Surveillance Test Interval] SSC [structures, systems, and components] Modeled in PRA, discusses considerations for SSCs that are not evaluated in the seismic PRA.
NEI 04-10 Step 14, Perform Sensitivity Studies states that, Additional sensitivity cases should also be explored for particular areas of uncertainty associated with any of the significant contributors to the CDF and LERF results or if there are open Gap Analysis items when compared to the ASME Standard Capability Category II that would impact the results of the assessment. Step 14 also calls for ensuring that there is not an undue reliance on key assumptions and causes of uncertainty.
RG 1.177 outlines the staff position in performing sensitivity and uncertainty analyses in support of surveillance frequency changes to technical specifications.
RG 1.200, Revision 2, Section 2.2, provides regulatory guidance regarding peer reviews and the staff regulatory position on NEI 00-02, Probabilistic Risk Assessment (PRA) Peer Review Process Guidance (ADAMS Accession No. ML061510619), NEI 05-04 Process for Performing Follow-On [Internal Events] PRA Peer Reviews Using the American Society of Mechanical Engineers (ASME)/American Nuclear Society (ANS) PRA Standard (ADAMS Accession No. ML083430462), and NEI 07-12 Fire Probabilistic Risk Assessment (FPRA)
Peer Review Process Guidelines (ADAMS Accession No. ML102230070).
RG 1.200, Revision 2, Section 4, states that a risk informed submittal should contain discussions concerning peer review. If the peer review is not performed against the established standards, then information needs to be included in the submittal demonstrating that the different criteria used are consistent with the established standards, as endorsed by NRC.
REQUESTS FOR ADDITIONAL INFORMATION Section 2 of the LAR states that the PRA models have been developed in accordance with the requirements of RG 1.200, Revision 2, subjected to peer review and the Facts and Observations (F&O) independent assessment process.
The following requests for additional information (RAIs) are needed to enable the staff to complete its review of the licensees application:
RAI APLA-01 The finding (F&O 1-6) pertaining to supporting requirement DA-D3, located in Table 6, Open IE With IF PRA Open F&Os of Attachment 2 of the LAR, observes that TVA did not enter uncertainty interval data into the CAFTA databases with proper distribution parameters. TVA stated that point estimates were used, and that missing uncertainty information would not impact the results. However, NEI-04-10 Step 14, Perform Sensitivity Studies, requires that sensitivity analyses need to be performed as gap analyses for Common Cause Failure (CCF) to account for uncertainty. It is expected that other areas of uncertainty outside of the SSC in question can impact the result of its Surveillance Test Interval (STI) calculations. Therefore, the staff requests TVA to:
- 1. Discuss the methodology used to propagate uncertainty through the model and how the results of gap analyses will be integrated into the STI calculation.
- 2. The adoption of alpha factors for CCF was part of the changes made in Rev 2 of the model.
Discuss the impact of the omission of uncertainty in STI calculations.
RAI APLA-02 The finding (F&O 2-18) pertaining to supporting requirements HR-D5, HR-G7, QU-C1, and QU-C2, located in Table 6, Open IE With IF PRA Open F&Os of Attachment 2 of the LAR, observed that the lower combined Human Error Probability (HEP) limit was not applied in the QRecover file. It is not clear if dependent multiple Human Failure Events (HFEs) exist which fall below the established threshold. It is noted in RG 1.177, An Approach For Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications, Section A-2.3.4, Parameters for Component Unavailability, that human errors following test or maintenance, if modeled, can contribute to the estimated component unavailability for technical specification changes. The staff therefore requests TVA to identify if there are any such dependent HFEs and to discuss their impact to the model and to the STI calculations.
RAI APLA-03 The finding (F&O 3-6) pertaining to supporting requirements QU-A3 and QU-E3, located in Table 6, Open IE With IF PRA Open F&Os of Attachment 2 of the LAR, require a State of Knowledge Correlation (SOKC) between event probabilities shall be applied. It appears that TVA discussed modeling uncertainty in the Uncertainty and Sensitivity notebook but, did not include parametric uncertainty as required. The staff requests TVA to provide a discussion on how parametric uncertainty through the SOKC will be applied for STI determinations impacting remaining in-service components.
RAI APLA-04 The finding (F&O 7-10) pertaining to supporting requirement IFQU-A6, located in Table 6, Open IE With IF PRA Open F&Os of Attachment 2 of the LAR, require that internal flood scenario-specific Performance Shaping Factors (PSFs) for Main Control Room (MCR) actions be revised in the assessment to account for potential changes to HEPs such as timing, stress, etc. The Electric Power Research Institute (EPRI) guidance states that PSFs do not have to be
revised for those events which require more than one hour available for operator action. There may be HFEs which would require less than an hour to either diagnose or perform. Therefore, the staff requests TVA to provide a tabulation and corresponding evaluation for those internal flood-related HFEs taking less than an hour for diagnosis and action, and their corresponding impact separately and, as a whole, to the STI evaluations.
RAI APLA-05 The finding (F&O 7-21) pertaining to supporting requirement IFEV-B3, located in Table 6, Open IE With IF PRA Open F&Os of Attachment 2 of the LAR, require that range factors related to parametric uncertainty data for flooding initiators be entered and propagated through the model for various pipe and break sizes. It had appeared that uncertainty data was lumped together for all pipe breaks and sizes and was not clear whether this was conservative. To ensure that there is no underestimate of risk, the staff requests TVA provide additional information on individual internal flood initiators and their associated error factors with their potential impact to the STI evaluations.
RAI APLB Seismic PRA Peer Review Criteria Section 2 of the licensees June 30, 2017, response (ADAMS Accession No. ML17181A485) to the 10 CFR 50.54(f) information request arising from Near Term Task Force (NTTF) recommendation 2.1 states that the seismic PRA peer review was performed in accordance with the guidance in NEI 12-13. NRC letter dated March 7, 2018, U.S. Nuclear Regulatory Commission Acceptance of Nuclear Energy Institute (NEI) Guidance NEI 12-13, External Hazards PRA Peer Review Process Guidelines (August 2012), (ADAMS Accession No. ML18025C025), provides the staff comments on this guidance for seismic and external hazard PRA peer reviews. Further, the staff provided its expectations on the F&O independent assessment process in its letter dated May 1, 2017, U.S. Nuclear Regulatory Commission Staff Expectations for an Industry Facts and Observations Independent Assessment Process, (ADAMS Accession No. ML17121A271).
The LAR does not discuss the consideration of the staffs comments on NEI 12-13 during the performance of the peer review for the licensees seismic PRA or the consideration of the staffs expectations on the F&O independent assessment process used for closure of the seismic PRA finding level F&Os.
Discuss how the seismic PRA peer review and the F&O independent assessment considered the staffs comments in the letters dated March 7, 2018, and May 1, 2017, respectively. Provide justification for not considering specific comments in those letters in the context of this application.
RAI APLB Use of Addendum B of the PRA Standard (2013)
Section 2.5.1 of Attachment 2 to the LAR states that the seismic PRA was peer reviewed against the requirements in Part 5 of Addendum B of the ASME/ANS PRA Standard (ASME/ANS RA-Sb-2013). RG 1.200, Revision 2, endorses ASME/ANS PRA Standard Addendum A (ASME/ANS RA-Sa-2009). As noted in letter dated July 6, 2011, U.S. Nuclear Regulatory Commission (NRC) Comments on Addenda to a Current ANS: ASME RA-SB -
20XX, Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications (ADAMS Accession No. ML111720067), NRC did not endorse Addendum B of the PRA Standard. The licensees seismic PRA peer review was performed using a PRA Standard different from that endorsed by the NRC staff in RG 1.200, Revision 2.
Discuss how the supporting requirements (SRs) in Addendum B, which is not endorsed by the NRC for licensing applications, and the NRC staffs comments in the above cited letter dated July 6, 2011, are consistent with the SRs in Part 5 of Addendum A, for this application. If the different criteria are not consistent with the endorsed Standard, describe how the analogous Addendum A supporting requirements have been met.
RAI APLB Key Assumptions and Uncertainties that could Impact the Application Section 2.5.5 of Attachment 2 to the LAR states that [t]he TVA Technical Instruction governing the process requires key assumptions and key modeling uncertainties to be addressed to ascertain sensitivity of these on the proposed STI extensions and included in the documented evaluation for [Integrated Decision-making Panel] IDP consideration. LAR Attachment 2 Section 2.5.5 states that there is a negligible to small impact of key assumptions and sources of uncertainty in the seismic PRA. It is unclear how the key assumptions and sources of uncertainty from the seismic PRA were identified, and were determined to have negligible to small impact on this application.
- a. Describe the approach used to identify and characterize the key assumptions and key sources of uncertainty in the licensees seismic PRA. The description should contain sufficient detail to identify: (1) whether all assumptions and sources of uncertainty related to all aspects of the hazard, fragility, and plant response analysis were evaluated to determine whether they were key, and (2) the criteria used to determine whether the modeling assumptions and sources of uncertainty were considered key.
- b. Discuss how each identified key assumption and key source of uncertainty was dispositioned for this application justifying the negligible to small impact on this application. Identify appropriate sensitivity cases that will be used to support the disposition for this application or use a qualitative discussion to justify why different reasonable alternative assumptions would not affect this application.
RAI APLB Consideration of Structures, Systems, and Components (SSCs) Not Evaluated in the Seismic PRA Section 4.3.6 of the licensees June 30, 2017, response (ADAMS Accession No. ML17181A485) to the 10 CFR 50.54(f) information request arising from NTTF recommendation 2.1 discusses the screening approach for SSCs during the development of the licensees seismic PRA. The supplement to that submittal (ADAMS Accession No. ML18100A966) also discusses the screening performed during the development of the seismic PRA and states that rugged SSCs were screened out. It is not clear in the LAR how SSCs not modeled explicitly or implicitly such as inherently rugged are considered in the surveillance frequency control program (SFCP).
Discuss how SSCs that are not evaluated in the seismic PRA, either explicitly or implicitly, will be considered in the SFCP. Examples of such SSCs include inherently rugged components and SSCs that were not included in the seismic PRA based on a screening criteria (e.g.,
capacity based screening), especially if the excluded components have surveillances associated with them (e.g., relief valves).
RAI APLB Incorporation of Diverse and Flexible Coping Strategies (FLEX)
Equipment in Seismic PRA and Internal Events PRA The information presented in the licensees response to the 10 CFR 50.54(f) information request arising from NTTF recommendation 2.1 (ADAMS Accession No. ML17181A485) indicates that
Diverse and Flexible Coping Strategies (FLEX) diesel generators and other FLEX equipment, with associated operator actions, were credited in the licensees seismic PRA.
The NRC memorandum dated May 30, 2017, "Assessment of the Nuclear Energy Institute 16-06, 'Crediting Mitigating Strategies in Risk-Informed Decision Making,' Guidance for Risk-Informed Changes to Plants Licensing Basis (ADAMS Accession No. ML17031A269), provides the NRCs staff assessment of challenges to incorporating FLEX equipment and strategies into a PRA model in support of risk-informed decision making in accordance with the guidance of RG 1.200, Revision 2. The methodology used to assess the failure probabilities of FLEX equipment and how the human reliability analysis (HRA) was performed to model the corresponding human actions is unclear. Further, it is not clear how the FLEX equipment will be credited and treated in the licensees proposed SFCP.
- a. Discuss the methodology used to assess the failure probabilities of FLEX equipment credited in both the licensees internal events and seismic PRAs. The discussion should include a justification explaining the rationale for parameter values, whether the uncertainties associated with the parameter values are considered in accordance with the ASME/ANS PRA Standard as endorsed by RG 1.200, Revision 2, and how the staffs comments on NEI 16-06, Crediting Mitigating Strategies in Risk-Informed Decision Making, in letter dated May 30, 2017 (ADAMS Accession No. ML17031A269) were appropriately considered.
- b. Discuss the HRA approach used to model FLEX actions including the consistency of the approach with the corresponding technical elements in the NRC endorsed ASME/ANS PRA Standard.
- c. Step 19, Periodic Re-assessment of NEI 04-10 states that part of the periodic re-assessment also includes interfacing the SFCP with updates to the PRA model.
Discuss the approach, including any existing or planned programmatic elements, which will be taken to ensure that the data assumptions for the FLEX equipment credited in the seismic PRA will continue to remain valid during the implementation of the licensees SFCP.