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MONTHYEARCNL-21-020, Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518)2021-11-0505 November 2021 Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518) Project stage: Other ML21343A4212021-12-0909 December 2021 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1, 2, and 3, License Amendment Request to Revise TS 3.8.7 for Installation of the Control Bay Chiller Cross-Tie Project stage: Acceptance Review ML21349A2262021-12-15015 December 2021 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, License Amendment Request to Revise TS 3.8.7 for Installation of the Control Bay Chiller Cross-Tie Project stage: Acceptance Review CNL-22-007, Supplement to Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518)2022-04-0606 April 2022 Supplement to Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518) Project stage: Supplement ML22168A0392022-05-13013 May 2022 NRR E-mail Capture - Draft Request for Confirmation of Information and Additional Information Related to Tva'S Request to Use Control Bay Chiller Cross-Tie Project stage: Draft Other ML22168A0802022-06-17017 June 2022 NRR E-mail Capture - Request for Confirmation of Information and Additional Information Related to Tva'S Request to Use Control Bay Chiller Cross-Tie Project stage: Other CNL-22-065, Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie.2022-08-0101 August 2022 Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie. Project stage: Supplement ML22273A1032022-11-22022 November 2022 Issuance of Amendment Nos. 323, 346, and 306 Regarding Chilled Water Cross-Tie Modification Project stage: Approval 2022-11-22
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Category:E-Mail
MONTHYEARML23355A2202023-12-21021 December 2023 Radiation Protection Inspection - Inspection Report 2024-01 ML23332A0042023-11-27027 November 2023 NRR E-mail Capture - Request for Additional Information Related to Proposed Revised Alternative 0-ISI-47 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) ML23243A9892023-08-29029 August 2023 Inspection Information Request ML23208A0872023-07-26026 July 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry 1, 2, and 3, Alternative Request 0-ISI-47 to Use an Alternative to ASME Code, Section XI, Examination Requirements for Examination Categories B-N-1 and B-N-2 ML23124A0082023-05-0303 May 2023 NRR E-mail Capture - Request for Additional Information Related to Proposed Alternative Requests for the 5th 10-Year Inservice Testing Interval for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML23117A0702023-04-26026 April 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry, 1, 2, and 3, License Amendment Request to Revise Tech Specs Surveillance Requirements 3.4.3.2 and 3.5.1.11 Safety Relief Valves (BFN TS-540) ML23097A0172023-04-0606 April 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry, Units 1, 2, and 3, License Amendment Request to Adopt TSTF-566-A and TSTF-580-A, Revision 1 ML23073A2082023-03-10010 March 2023 TVA Intentions on EA-22-122 - Choice Letter Response Email Message ML23073A2072023-03-10010 March 2023 TVA Intentions on EA-22-122 - Choice Letter Response Email Message - NRC Acknowledgement ML23075A0502023-03-10010 March 2023 TVA Intentions on EA-22-122 - Choice Letter Response Email Message and TVA Intentions on EA-22-122 - Choice Letter Response Email Message -- NRC Acknowledgement ML23052A0792023-02-21021 February 2023 NRR E-mail Capture - Acceptance Review for Browns Ferry and Sequoyah License Amendment Request to Adopt TSTF-541 ML23041A0022023-02-0909 February 2023 NRR E-mail Capture - Request for Additional Information Related to TVA Alternative Request BFN-0-ISI-32 (CNL-22-025) ML23013A1512023-01-13013 January 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Request to Use Later ASME OM Code Edition and Alternative Requests BFN-IST-01 Through BFN-IST-05 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) ML23017A0062023-01-12012 January 2023 Initial Information Request Inspection Report: 2023001 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) ML23004A0352023-01-0404 January 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry, Units 1, 2, and 3, License Amendment Request to Delete TS 3.6.3.1 by Adopting TSTF-478 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) ML22304A1852022-10-31031 October 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry, Units 1, 2, and 3, License Amendment Request to Remove Site Acreage Description from TS 4.1 ML22299A0292022-10-26026 October 2022 NRR E-mail Capture - Request for Additional Information for Relief Request BFN-2-ISI-003 Re Weld Examination Coverage ML22292A2722022-10-19019 October 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Adopt TSTF-505 and TSTF-439 for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML22265A1492022-09-21021 September 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Alternative Request BFN-0-ISI-32 ML22259A0392022-09-14014 September 2022 NRR E-mail Capture - Browns Ferry TSTF-505 Audit Questions - Part 5 ML22259A0382022-09-14014 September 2022 NRR E-mail Capture - Browns Ferry TSTF-505 Audit Questions - Part 4 ML22259A0372022-09-13013 September 2022 NRR E-mail Capture - Browns Ferry TSTF-505 Audit Questions - Part 3 ML22238A0672022-08-24024 August 2022 NRR E-mail Capture - Browns Ferry TSTF-505 Audit Questions - Part 2 ML22238A0652022-08-19019 August 2022 NRR E-mail Capture - Browns Ferry TSTF-505 Audit Questions ML22215A2752022-08-0303 August 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-554 ML22208A2172022-07-15015 July 2022 NRR E-mail Capture - Request for Additional Information Related to TVA Relief Request BFN-21-ISI-02 (CNL-21-081) ML22194A8762022-07-13013 July 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-529 ML22173A1682022-06-21021 June 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Unit 2, Relief Request BFN-2-ISI-003 ML22168A0802022-06-17017 June 2022 NRR E-mail Capture - Request for Confirmation of Information and Additional Information Related to Tva'S Request to Use Control Bay Chiller Cross-Tie ML22160A4742022-06-0303 June 2022 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Re LAR to Use Advanced Framatome Methodologies in Support of Atrium 11 Fuel 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) ML22168A0392022-05-13013 May 2022 NRR E-mail Capture - Draft Request for Confirmation of Information and Additional Information Related to Tva'S Request to Use Control Bay Chiller Cross-Tie ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans ML22131A1692022-05-0303 May 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, License Amendment Request to Adopt TSTF-505 and TSTF-439 ML22091A1942022-03-0808 March 2022 2022 BFN POV Inspection Information Request ML22055A0772022-02-22022 February 2022 NRR E-mail Capture - Results of NRC SUNSI Review of Browns Ferry Nuclear Plant, Units 1, 2, and 3, Updated Final Safety Analysis Report, Amendment 29 ML22047A1612022-02-16016 February 2022 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Expand the SFP Criticality Safety Analysis for Browns Ferry Nuclear Plant, Units 1, 2, and 3 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 ML22032A0322022-01-27027 January 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Unit 2, Alternative Request BFN-21-ISI-02 ML22025A4132022-01-25025 January 2022 RP Inspection Doc Request ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22010A0282022-01-0606 January 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry, Units 1, 2, and 3, License Amendment Request to Adopt TSTF-205-A, Rev. 3 and TSTF-563-A, and Rescind the Consolidation of Several Surveillance Requirements ML21349A2262021-12-15015 December 2021 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, License Amendment Request to Revise TS 3.8.7 for Installation of the Control Bay Chiller Cross-Tie ML21343A4212021-12-0909 December 2021 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1, 2, and 3, License Amendment Request to Revise TS 3.8.7 for Installation of the Control Bay Chiller Cross-Tie ML21334A3012021-11-30030 November 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Acceptance of License Amendment Request Regarding Adoption of TSTF-568-A 2023-08-29
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23332A0042023-11-27027 November 2023 NRR E-mail Capture - Request for Additional Information Related to Proposed Revised Alternative 0-ISI-47 ML23243A9892023-08-29029 August 2023 Inspection Information Request ML23124A0082023-05-0303 May 2023 NRR E-mail Capture - Request for Additional Information Related to Proposed Alternative Requests for the 5th 10-Year Inservice Testing Interval for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML23041A0022023-02-0909 February 2023 NRR E-mail Capture - Request for Additional Information Related to TVA Alternative Request BFN-0-ISI-32 (CNL-22-025) ML22299A0292022-10-26026 October 2022 NRR E-mail Capture - Request for Additional Information for Relief Request BFN-2-ISI-003 Re Weld Examination Coverage ML22292A2722022-10-19019 October 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Adopt TSTF-505 and TSTF-439 for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML22208A2172022-07-15015 July 2022 NRR E-mail Capture - Request for Additional Information Related to TVA Relief Request BFN-21-ISI-02 (CNL-21-081) ML22174A2722022-06-24024 June 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22168A0802022-06-17017 June 2022 NRR E-mail Capture - Request for Confirmation of Information and Additional Information Related to Tva'S Request to Use Control Bay Chiller Cross-Tie ML22160A4742022-06-0303 June 2022 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Re LAR to Use Advanced Framatome Methodologies in Support of Atrium 11 Fuel ML22168A0392022-05-13013 May 2022 NRR E-mail Capture - Draft Request for Confirmation of Information and Additional Information Related to Tva'S Request to Use Control Bay Chiller Cross-Tie ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans ML22047A1612022-02-16016 February 2022 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Expand the SFP Criticality Safety Analysis for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML22025A4132022-01-25025 January 2022 RP Inspection Doc Request ML21343A4232021-12-0909 December 2021 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000259/2022010, 05000260/2022010, and 05000296/2022010) and Request for Information (RFI) ML21173A1042021-06-21021 June 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to TS 3.8.6 ML21041A5422021-02-10010 February 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to Adopt 10 CFR 50.69 ML21041A5432021-02-0505 February 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Draft Request for Additional Information Regarding 10 CFR 50.69 LAR ML21026A1652021-01-26026 January 2021 Document Request for Browns Ferry Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-02 ML20296A3782020-10-22022 October 2020 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to Incorporate TMRE ML20297A3012020-10-22022 October 2020 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to Adopt TSTF-425 ML20294A3762020-09-23023 September 2020 NRR E-mail Capture - Draft Request for Additional Information - Browns Ferry Nuclear Plant, Units 1, 2, and 3, Request to Adopt TSTF-425 ML20266G4472020-09-22022 September 2020 Notification of Inspection and Request for Information ML20224A4732020-08-11011 August 2020 Requalification Program Inspection Browns Ferry Nuclear ML20195B1302020-07-13013 July 2020 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Alternative Request No. 0-ISI-47 ML20149K3212020-05-27027 May 2020 RP Inspection Document Request, Browns Ferry 2020-003 ML20254A3032020-05-13013 May 2020 Request for Supporting Information for the Browns Ferry, Units 1, 2, and 3 Seismic Probabilistic Risk Assessment Audit Review ML20054B8592020-02-20020 February 2020 Emergency Preparedness Program Inspection Request for Information ML20014E6552020-01-14014 January 2020 01 RP Inspection Document Request ML19196A0752019-07-12012 July 2019 NRR E-mail Capture - Final RAIs Browns Ferry Nuclear, Units 1, 2, 3 - Application to Revise Technical Specifications to Adopt TSTF-542 Revision 2, Reactor Pressure Vessel Water Inventory Control ML19116A0712019-06-0303 June 2019 Request for Additional Information Related Resubmittal of Proposed Alternative Request No. 1-ISI-27 for the Period of Extended Operation ML18331A5442018-12-0606 December 2018 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus License Amendment Request (EPID L-2018-LLA-0048) - (Non-Proprietary) ML18317A1642018-11-20020 November 2018 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus License Amendment Request (EPID L-2018-LLA-0048) - Non-Proprietary ML18263A1412018-09-11011 September 2018 NRR E-mail Capture - Browns Ferry Unit 1: RAI Associated with Relief Request 1-ISI-28 ML18138A1102018-05-17017 May 2018 Enclosurequest for Additional Information (Letter to E. D. Schrull Request for Additional Information Regarding Tennessee Valley Authority'S Decommissioning Funding Plan Update for Browns Ferry and Sequoyah Isfsis) ML18108A1872018-04-18018 April 2018 Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000259/2018411, 05000260/2018411, and 05000296/2018411 ML18057A6372018-02-23023 February 2018 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet Topical Report TVA-NPG-AWA16 - EPIC: L-2016-TOP-0011) ML17216A0062017-08-18018 August 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to LAR to Revise Modifications and Implementations Related to NFPA 805 for Fire Protection for Light Water Reactor Generating Plants (CAC Nos. MF9814-MF9816) ML17163A0502017-06-0808 June 2017 NRR E-mail Capture - RAI for Browns Ferry RR 3-ISI-28 CAC No. MF9257 ML17150A0792017-05-23023 May 2017 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet LAR for EAL Change to Adopt NEI-99-01 Rev.6 (CAC Nos. MF9054 - MF9060) ML16288A0182016-10-27027 October 2016 Browns Ferry Nuclear Plant, Units 2 and 3 - RAI Related to Relief Request for the Use of Alternatives to Certain American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI Requirements (CAC Nos. MF7795 and MF7796) ML16236A0732016-08-31031 August 2016 Request for Additional Information Related to License Amendment Request to Add New Technical Specification 3.3.8.3 ML16203A0272016-07-25025 July 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (CAC Nos. MF6738, MF6739, and MF6740) ML16187A2932016-07-21021 July 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate (CAC Nos. MF6741, MF6742, and MF6743) ML16194A2292016-07-21021 July 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate ML16154A5442016-06-21021 June 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate ML16146A6352016-06-13013 June 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate ML16145A1582016-06-0303 June 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate (SBPB-RAI 4) (CAC Nos. MF6741, MF6742, and MF6743) ML16144A6452016-06-0303 June 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Non-proprietary Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate (EMCB-RAI) ML16119A1332016-05-0606 May 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate (SNPB-RAI) (CAC Nos. MF6741, MF6742, and MF6743) 2023-08-29
[Table view] |
Text
From: Green, Kim Sent: Friday, June 17, 2022 10:31 AM To: Eckermann, J Beau
Subject:
Request for Confirmation of Information and Additional Information Related to TVA's Request to Use Control Bay Chiller Cross-Tie (EPID L-2021-LLA-0203)
Attachments: Final RAI.pdf
Dear Mr. Eckermann,
By letter dated November 5, 2021 (ADAMS Accession No. ML21309A038), the Tennessee Valley Authority (TVA) requested one-time changes to the Browns Ferry Nuclear Plant Technical Specifications (TS) 3.8.7, Distribution Systems - Operating, to allow for the use of a cross-tie modification between Unit 3 control bay (CB) chilled water system and the Units 1/2 CB chilled water system supplying the electric board room (EBR) air handling units (AHUs).
Specifically, TVA requested the addition of Conditions I (Unit 1) and J (Units 2 and 3) with Completion Times of 9 days, and conforming changes all other Conditions for Units 1 and 2, except C (Unit 1) and D (Unit 2), and conforming changes to Unit 3 Conditions G and H so that cross-tie can be installed and tested. Additionally, TVA proposed to revise Browns Ferry Updated Final Safety Analysis Report, section 10.12, HVAC Systems, and Appendix F, Unit Sharing and Interactions, to reflect the design modification and to incorporate licensing basis changes describing the Unit 3 CB chilled water system as both a shared system and as an alternate chilled-water source for Unit 1 and Unit 2 EBR AHUs.
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 confirmation of information and additional information (RCI and RAI) was previously transmitted to you on May 13, 2022 (ML22168A039). At TVAs request, an initial clarification call was held on June 8, 2022, to clarify the NRC staffs draft RCI and RAI. During the call, the NRC staff stated that it would review the LAR to determine if EEEB RAI 1 was needed. The staff subsequently convened to further discuss EEEB RAI 3. A subsequent clarification call was held on June 15, 2022. As a result of the clarification calls and further NRC deliberation, the staff determined that EEEB RAI 1 was unnecessary because sufficient information exists in the license amendment request. The staff also edited STSB RAIs 1 and 2.a, SCPB RAI 1, and EEEB RAI 3 to clarify the staffs requests. The attached RCI and RAI reflect the discussed changes.
A response to the attached RAI is requested no later than 45 days, as requested, 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 me at (301) 415-1627 or via email at Kimberly.Green@nrc.gov.
Sincerely, Kimberly Green, Sr. Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Hearing Identifier: NRR_DRMA Email Number: 1680 Mail Envelope Properties (DM6PR09MB5462A35FCAF84E4F1A5270B78FAF9)
Subject:
Request for Confirmation of Information and Additional Information Related to TVA's Request to Use Control Bay Chiller Cross-Tie (EPID L-2021-LLA-0203)
Sent Date: 6/17/2022 10:30:37 AM Received Date: 6/17/2022 10:30:00 AM From: Green, Kim Created By: Kimberly.Green@nrc.gov Recipients:
"Eckermann, J Beau" <jbeckermann@tva.gov>
Tracking Status: None Post Office: DM6PR09MB5462.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 2865 6/17/2022 10:30:00 AM Final RAI.pdf 96426 Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
REQUEST FOR ADDITIONAL INFORMATION TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE AMENDMENT REQUEST FOR CONTROL BAY CHILLED WATER CROSS-TIE USE AND ONE-TIME EXCEPTION TO TECHNICAL SPECIFICATION 3.8.7
==
Introduction:==
By letter dated November 5, 2021 (ADAMS Accession No. ML21309A038), as supplemented by letter dated April 6, 2022 (ADAMS Accession No. ML22096A328), the Tennessee Valley Authority (TVA) submitted a license amendment request (LAR) to the U.S. Nuclear Regulatory Commission (NRC) requesting one-time changes to the Browns Ferry Nuclear Plant Technical Specifications (TS) 3.8.7, Distribution Systems - Operating, to allow for the use of cross-tie modification between Unit 3 control bay (CB) chilled water system and the Units 1/2 CB chilled water system supplying the electric board room (EBR) air handling units (AHUs). Specifically, TVA requested the addition of Conditions I (Unit 1) and J (Units 2 and 3) with Completion Times of 9 days, and conforming changes all other Conditions for Units 1 and 2, except C (Unit 1) and D (Unit 2), and conforming changes to Unit 3 Conditions G and H so that cross-tie can be installed and tested. Additionally, TVA proposed to revise Browns Ferry Updated Final Safety Analysis Report, section 10.12, HVAC Systems, and Appendix F, Unit Sharing and Interactions, to reflect the design modification and to incorporate licensing basis changes describing the Unit 3 CB chilled water system as both a shared system and as an alternate chilled-water source for Unit 1 and Unit 2 EBR AHUs.
Regulatory Basis:
Section 50.36(b) of Title 10 of the Code of Federal Regulations (10 CFR) states, in part, The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to 50.34.
Section 50.36(c)(2)(i) of 10 CFR states, in part, Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met.
As stated in the LAR, during the construction permit licensing process, each of the three Browns Ferry units was evaluated against the then-current draft of the Atomic Energy Commission (AEC) Proposed General Design Criteria. Units 1 and 2 were evaluated against the AEC-27 Criteria, while Unit 3 was evaluated against the AEC-70 Criteria.
TVA stated that based on its understanding of the intent of the proposed criteria current at the time of operating license application, TVA concluded that each Browns Ferry unit conforms to the intent of the AEC General Design Criteria for Nuclear Power Plant Construction Permits.
Criterion 5Sharing of structures, systems, and components. Structures, systems, and components important to safety shall not be shared among nuclear power units unless it can be shown that such sharing will not significantly impair their ability to perform their safety functions, including, in the event of an accident in one unit, an orderly shutdown and cooldown of the remaining units.
Requests:
The following information is needed so the NRC staff can make a conclusion as to whether the NRC staffs understanding of the proposed changes is correct and that the proposed changes are supported by the justifications provided by TVA in the LAR.
STSB RCI 1 In Attachment 2 to the supplement, TVA proposes to add conditional phrase , for reasons other than Condition I (Unit 1) and , for reasons other than Condition J (Units 2 and 3) to Conditions A, B, C (Units 2 and 3), D (Unit 1), E, F, G, H (Unit 1), and I (Units 2 and 3).
Confirm that the proposed language being added to the NOTE for Conditions I (Unit 1) and J (Units 2 and 3) means that if the compensatory actions of TVA letter CNL-21-020 are not taken (or found to be not taken) during installation of the Unit 3 control bay chiller cross-tie, then the associated Conditions, Required Actions and Completion Times for the applicable Conditions would apply.
STSB RAI 1 Proposed Condition I (Unit 1) and Condition J (Units 2 and 3) contain one Required Action that is applicable when the compensatory actions of TVA letter CNL-21-020 are taken. Explain how these compensatory actions will be implemented and how they will be maintained in place during the installation and testing of the cross-tie.
STSB RAI 2 Page E-7 of the LAR contains a description of the cross-tie installation. Condition H (Unit 1 ) and Condition I (Units 2 and 3) are stated as Two or more electrical power distribution subsystems inoperable that result in a loss of function. In the supplement, TVA proposed to add the phrase
, for reasons other than Condition I to Condition H (Unit 1) and , for reasons other than Condition J to Condition I (Unit 2). However, the phrase is not proposed to be added to Condition I for Unit 3.
The current Bases for the Condition description states:
Condition H [I for Units 2 and 3] corresponds to a level of degradation in the electrical distribution system that causes a required safety function to be lost
[emphasis added]. When more than one AC or DC electrical power distribution subsystem is lost, and this results in the loss of a required function [emphasis added], the plant is in a condition outside the accident analysis. Therefore, no additional time is justified for continued operation. LCO 3.0.3 must be entered immediately to commence a controlled shutdown.
- a. Discuss whether a loss of safety function could occur during cross-tie installation and/or testing, including which safety functions on which units could be lost and the potential duration of each loss. Alternatively, revise the TS markups to reflect when Condition H (Unit 1) and Condition I (Unit 2) would apply during the installation and/or testing.
- b. Explain why the proposed addition to Condition H (Unit 1) and Condition I (Unit 2) was not proposed for Unit 3 Condition I.
SCPB RAI 1 The following information is needed to ensure that the sharing of chiller systems will not significantly impair their ability to perform their safety functions during installation.
The LAR indicates that Browns Ferry will take compensatory actions during installation of the Unit 3 CB chilled water cross-tie to reduce risk.
One of the compensatory actions indicates:
Monitor the ambient air temperature in the 1A, 1B, 2A, and 2B EBRs and their associated 480V shutdown board rooms twice per shift and document the temperatures in the narrative logs. If the temperatures in these board rooms exceed 100°F [degrees Fahrenheit], open the associated board room doors and install fans to assist in maintaining the associated temperatures below 100°F. Do not block open the electric board room doors unless their ambient air temperature exceeds 100°F.
The ventilation capability and efficiency of using open doors and fans is unclear, including the effect of the reactor building at 127 °F and/or elevated outdoor ambient air temperature conditions. Provide a discussion on the open doors and fans ability to keep the room below the 104 °F design operating limit during cross-tie installation. In event that ventilation using open doors becomes inadequate, describe any additional mitigating or recovery actions that may be taken prior to and if the temperature exceeds104 °F limit.
EEEB RAI 1 In Section 2.2 of the LAR, TVA explained that the installation is expected to last 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br /> based on the estimated work steps required to install and leak check the prepared piping spool sections at the Units 1 and 2 chilled water piping. TVA further stated:
An additional 7 days is also requested for flow-balancing the system with the Unit 3 chiller cross-tie aligned to the Unit 1 and Unit 2 EBR AHUs. During this time, the Unit 1 and Unit 2 EBR AHUs and the aligned Unit 3 CB chilled water system train will be available but will not be OPERABLE. The standby Unit 3 CB chilled water system train and both Unit 1/2 CB chilled water system trains remain OPERABLE. Because the limiting EBR takes approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to reach 104°F, there is ample time to realign the systems to their normal configurations before cooling is needed. Therefore, the requested time to complete the installation and testing and to restore the affected electrical power
distribution subsystems to OPERABLE status is 9 days, 2 days for installation and 7 days for testing.
No explanation or justification was provided for the 7-day testing/flow-balancing period.
Provide a justification for the 7-day completion time for testing/flow-balancing the cross-tie.
EEEB RAI 2 In the supplement, for the TS Bases for Required Action I.1 associated with new Condition I, the following is stated:
In this Condition the equipment in the Unit 1 and Unit 2 electrical board rooms are considered not OPERABLE because chilled water will be isolated from the air handling units in those rooms. Without chilled water to those air handling units during a design basis accident, the temperature in the Unit 1 and Unit 2 electrical board rooms would eventually increase above design limits.
While not OPERABLE, the electrical power distribution subsystems are able to perform their safety function until the temperature in the Unit 1 and Unit 2 electrical board rooms exceed the design limits. At that point, the expected service life of equipment in those rooms are shortened by the increased temperatures. Given the most limiting boardroom reaches the design-limit temperature in approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with no mitigating actions taken, there is sufficient time during installation to restore the chilled water to the Unit 1 and Unit 2 electrical board room air handling units to prevent the temperature in the Unit 1 and Unit 2 electrical board rooms from reaching the design limits.
- a. Although the Bases are not part of the TSs, 10 CFR 10 CFR 50.36(b), states that the TSs are derived from the analyses and evaluation included in safety analysis report. The NRC staff could not locate the basis for 104 °F design temperature limit for the EBRs in the Browns Ferry Updated Final Safety Analysis Report (UFSAR).
Provide the basis for the design limit temperature of 104°F for the EBRs.
- b. In the LAR on Page E7, the following is stated: Current analysis indicates that the Unit 1 and Unit 2 EBRs will not reach the design operating limit of 104 °F for approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during a design-basis accident when no cooling is provided to the EBRs, the doors are closed, and the reactor building is already at 127°F.
Provide the temperature at which the EBR electrical equipment is declared inoperable.
Also, briefly describe the assumptions and conservatisms used in the GOTHIC analysis.