Letter Sequence RAI |
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EPID:L-2020-LLA-0114, 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-18-16) (Approved, Closed) |
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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
From: Green, Kimberly Sent: Tuesday, November 17, 2020 12:34 PM To: Wells, Russell Douglas Cc: Shoop, Undine
Subject:
Request for Additional Information Regarding TVA's Request to Revise TS 3.7.11 Related to the MCR Chiller Replacement (EPID L-2020-LLA-0114)
Attachments: Final RAI 11-17-20.pdf
Dear Mr. Wells,
By letter dated May 19, 2020 (Agencywide Documents Access and Management System Accession No. ML20140A342), Tennessee Valley Authority (TVA) submitted a license amendment request for Watts Bar Nuclear Plant, Units 1 and 2. The proposed amendments revise Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (CREATCS), to add a one-time change of a footnote to the Completion Time for Required Action A.1 to allow one CREATCS train to be inoperable for up to 60 days while performing modifications to the CREATCS chillers. The proposed amendments also add a one-time change of a footnote to the Completion Time for Required Action E.1 to allow delayed entry into TS Limiting Condition for Operation (LCO) 3.0.3 for up to four days in the event that both CREATCS trains are inoperable during the modifications to the CREATCS chillers.
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has identified areas where additional information is needed to complete its review.
A draft request for additional information (RAI) was previously transmitted to you by email dated November 5, 2020. At your request, a clarification call was held on November 17th to clarify the NRC staffs requests. Based on the discussion during that call, the NRC has revised SCPB-RAI-1 slightly (changes shown in red) to request that TVA Provide a discussion and justification of the measures, mitigation, or procedures that TVA will implement to assure a safe shutdown of both WBN units after the loss of both trains of CREATCS when the MCR temperature starts at 90 °F. The other two requests remain the same.
As agreed during the call, a response to the attached RAI is requested within 30 days from the date of this email.
The NRC staff considers that timely responses to RAIs help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1627 or via email at Kimberly.Green@nrc.gov.
Sincerely, Kim Green (301) 415-1627 kimberly.green@nrc.gov
Hearing Identifier: NRR_DRMA Email Number: 895 Mail Envelope Properties (MN2PR09MB5388B926CEB77CA5336B1BCF8FE20)
Subject:
Request for Additional Information Regarding TVA's Request to Revise TS 3.7.11 Related to the MCR Chiller Replacement (EPID L-2020-LLA-0114)
Sent Date: 11/17/2020 12:34:00 PM Received Date: 11/17/2020 12:34:00 PM From: Green, Kimberly Created By: Kimberly.Green@nrc.gov Recipients:
"Shoop, Undine" <Undine.Shoop@nrc.gov>
Tracking Status: None "Wells, Russell Douglas" <rdwells0@tva.gov>
Tracking Status: None Post Office: MN2PR09MB5388.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 2288 11/17/2020 12:34:00 PM Final RAI 11-17-20.pdf 80255 Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
REQUEST FOR ADDITIONAL INFORMATION TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-390 AND 50-391 MAIN CONTROL ROOM CHILLER COMPLETION TIME EXTENSION By letter dated May 19, 2020, Tennessee Valley Authority (TVA) submitted a license amendment request (LAR) to revise the technical specifications for the Watts Bar Nuclear Plant (WBN), Units 1 and 2 (Agencywide Documents and Access Management System Accession No. ML20140A342). The requested changes would revise WBN, Units 1 and 2, Technical Specification (TS) 3.7.11 "Control Room Emergency Air Temperature Control System (CREATCS)," to add a one-time change of a footnote to the Completion Time for Required Action A.1 to allow one CREATCS train to be inoperable for up to 60 days while performing modifications to the CREATCS chillers. Additionally, a one-time change of a footnote to the Completion Time for Required Action E.1 to allow delayed entry into TS Limiting Condition for Operation (LCO) 3.0.3 for up to four days in the event that both CREATCS trains are inoperable during the modifications to the CREATCS chillers would be added. The one-time TS changes are limited to the time that the CREATCS modifications are being performed between the timeframe of May 1, 2021, and October 1, 2022.
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing the request and has identified areas for which additional information is needed prior to completing its review. The staffs requests for additional information (RAI) are below.
SCPB-RAI-1 Regulatory Basis Appendix A to Part 50 of Title 10 of the Code of Federal Regulations (10 CFR) contains the principal design criteria for a proposed facility that must be included in an application for a design certification, combined license, design approval, or manufacturing license, respectively.
These General Design Criteria (GDC) establish the minimum requirements for the principal design criteria for water-cooled nuclear power plants similar in design and location to plants for which construction permits have been issued by the Commission.
GDC 19, Control room, states, in part:
A control room shall be provided from which actions can be taken to operate the nuclear power unit safely under normal conditions and to maintain it in a safe condition under accident conditions, including loss-of-coolant accidentsEquipment at appropriate locations outside the control room shall be provided (1) with a design capability for prompt hot shutdown of the reactor, including necessary instrumentation and controls to maintain the unit in a safe condition during hot shutdown, and (2) with a potential capability for subsequent cold shutdown of the reactor through the use of suitable procedures.
Issue TVA has proposed a one-time change to the footnote for the TS 3.7.11, Condition E, completion time to allow a four-day delayed entry into LCO 3.0.3. The proposed change states that main control room (MCR) temperature will be monitored every hour to verify that it is less than or equal to 90 degrees Fahrenheit (°F), and that if the temperature goes above 90 °F, or the duration without a train of CREATCS being operable exceeds four days, immediate entry into LCO 3.0.3 is required.
As stated in LAR Section 3.4.2:
The proposed footnote to WBN Units 1 and 2 TS 3.7.11, Condition E, is also based on verifying that the MCR temperature is less than or equal to 90°F. The temperature limit for MCR equipment operability is 104°F. The 90°F temperature limit provides adequate margin between the normal MCR operating temperature of 75°F and a limit that ensures that the equipment operability limit of 104°F is not exceeded. By maintaining the MCR temperature at or below 90°F, the operability requirements for safety-related functions provided by equipment and instrumentation in the MCR, as well as habitability needs for operating personnel, is satisfied.
The LAR further states:
To support the one-hour frequency for temperature monitoring TVA evaluated the effect of a loss of cooling on the MCR temperature by performing an analysis of the heatup of the MCR and surrounding areas. The analysis assumed normal operating heat loads, normal average initial room temperatures, summertime maximum outdoor temperatures, one [air handling unit] AHU operating, and no chillers in operation. The calculation demonstrates that the temperature increase from 75°F (normal MCR operating temperature) to 104°F takes approximately 5.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. This temperature response does not credit the temporary chiller system cooling.
During the regulatory audit, the staff audited the evaluation referenced above. Calculation MDQ00003120090157, Revision 7, Main Control Room Floor (EL. 755.0) Transient Temperature Analysis, contains Figure H.4, Cases H1 through H3 Main Control Room Temperatures, which shows the calculated MCR transient temperatures. Figure H.4 supports the passage above and indicates that with normal heat loads (i.e., non-LOCA), the time to heat up the MCR to 104 °F from approximately 75 °F for the worst case (i.e., Case H1) is 5.28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br />.
This figure also indicates that the MCR would reach 106°F after 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and 118°F after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, absent a cooling water supply.
The proposed one-time change to the footnote for the TS 3.7.11, Condition E, completion time would allow the MCR temperature to reach 90°F before LCO 3.0.3 is entered. LCO 3.0.3 requires that the reactor shall be placed in MODE 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />; MODE 4 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />; and MODE 5 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
The staff notes that the MCR could reach the 104°F limit for MCR operability and the safety-related equipment operability/integrity could be challenged well before reaching MODE 3 within
7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />; therefore, the staff requires additional information to find that the proposed TS change is acceptable.
Request Provide a discussion and justification of the measures, mitigation, or procedures that TVA will implement to assure a safe shutdown of both WBN units after the loss of both trains of CREATCS when the MCR temperature starts at 90 °F.
EMIB-RAI-1 Regulatory Basis GDC 4, Environmental and dynamic effects design bases, states, in part, that [t]hese structures, systems, and components shall be appropriately protected against dynamic effects, including the effects of missiles, pipe whipping, and discharging fluids, that may result from equipment failures and from events and conditions outside the nuclear power unit.
Issue In Section 3.2, MCR Temporary Chilled Water Equipment Description, of the Enclosure to the LAR, TVA stated that a temporary nonsafety-related chiller system will be installed and used to support MCR cooling during the CREATCS chiller replacements, and that the temporary system is capable of providing adequate cooling to maintain the MCR within its normal temperature band.
In addition, in Section 3.2.1, MCR Temporary Air Conditioning Equipment Description, TVA stated that the temporary chiller equipment is nonsafety-related, but appropriate measures will be taken to minimize the potential for failure of the temporary chiller system and the control room envelope (CRE) boundary. In particular, TVA stated that the temporary hoses, pipe, and fittings are qualified for adequate pressure to protect against rupture and pipe whip, and that the valves at the penetrations are qualified for seismic retention to maintain the integrity of the control room envelope boundary. However, the TVA did not provide sufficient information to substantiate the above two statements.
The NRC staff notes that the temporary chiller equipment installation, though nonsafety-related, supports the safety function of MCR cooling during the CREATCS chiller replacements.
Request
- a. Provide details on the qualification of the temporary hoses, pipe, and fittings for adequate pressure and any other applicable loads to protect against rupture and pipe whip.
- b. Describe the rupture and pipe whip effects that have been considered.
- c. Describe how the valves at the penetrations will be qualified for seismic retention to maintain the integrity of the CRE boundary including a description of the seismic effects that would be considered.
STSB-RAI-1 Regulatory Basis In 10 CFR 50.36, Technical specifications, the NRC established its regulatory requirements related to the content of TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) LCOs; (3) surveillance requirements; (4) design features; and (5) administrative controls. The regulation does not specify the particular requirements to be included in a plants TSs.
The regulation at 10 CFR 50.36(a)(1) states, in part, A summary statement of the bases or reasons for such specifications shall also be included in the application, but shall not become part of the technical specifications.
As required in 10 CFR 50.36(b), the technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto.
As required in 10 CFR 50.36(c)(2), LCOs are the lowest functional capability or performance level of equipment required for safe operation of the facility. When LCOs are not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs until the LCOs can be met.
Issue In Section 3.7 of the Enclosure to the LAR, TVA concluded that a one-time change of the TS 3.7.11 Completion Times is acceptable and stated:
The proposed one-time LAR in support of the modifications to the CREATCS trains is acceptable based on the compensatory measures and the low probability of an event requiring MCR isolation, the consideration that the remaining train can provide the required protection, and that alternate non-safety related cooling means are available.
The proposed footnote for Condition A Completion Time stipulates that the allowance for a 60 day inoperability for one CREATCS train is contingent on implementation of compensatory measures as described in TVA letter CNL-20-012. The proposed footnote for Condition E Completion Time allows monitoring temperatures in lieu of immediate entry into LCO 3.0.3 but does not contain a similar contingency requiring implementation of compensatory measures as described in TVA letter CNL-20-012.
Request Explain why requiring implementation of compensatory measures such as those described in TVA letter CNL-20-012 is not necessary for the footnote for Condition E Completion Time.