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MONTHYEARCNL-20-002, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (TS-BFN-529)2020-07-17017 July 2020 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (TS-BFN-529) Project stage: Request CNL-20-047, Brown Ferry Nuclear Plant, Sequoyah Nuclear Plant & Watts Bar Nuclear Plant - Tennessee Valley Authority License Amendment Request to Revise Radiological Emergency Plan Regarding On-shift Emergency Medical Technician and Onsite Ambulance2020-07-31031 July 2020 Brown Ferry Nuclear Plant, Sequoyah Nuclear Plant & Watts Bar Nuclear Plant - Tennessee Valley Authority License Amendment Request to Revise Radiological Emergency Plan Regarding On-shift Emergency Medical Technician and Onsite Ambulance Re Project stage: Request ML20337A4392020-12-0202 December 2020 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Audit Plan and Setup of Online Reference Portal Project stage: Other ML21007A1642021-01-0707 January 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Revision 1 of Audit Plan and Setup of Online Reference Portal Project stage: Other 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 Project stage: Draft RAI 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 Project stage: RAI ML21036A2872021-02-23023 February 2021 Regulatory Audit Summary Related to Request to Implement 10 CFR 50.69 Risk-Informed Categorization and Treatment for Structures, Systems, and Components Project stage: Other CNL-21-033, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components2021-04-28028 April 2021 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components Project stage: Response to RAI ML21173A1772021-07-27027 July 2021 Issuance of Amendment Nos. 317, 340, and 300 Regarding Adoption of Title 10 of the Code of Federal Register Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components Project stage: Approval 2021-02-10
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Category:E-Mail
MONTHYEARML24255A5802024-09-10010 September 2024 SLRA - Requests for Additional Information - Set 1 - Email from Jessica Hammock to James Barstow ML24170A6392024-06-17017 June 2024 Notification of Inspection and Request for Information ML24123A0882024-05-0202 May 2024 NRR E-mail Capture - Correction Acceptance Review Results for the Browns Ferry, Sequoyah, and Watts Bar License Amendment Request to Revise TS 5.4.1 or 5.7.1 (L-2024-LLA-0039) ML24122B4872024-04-30030 April 2024 NRR E-mail Capture - Acceptance Review Results for the Browns Ferry, Sequoyah, and Watts Bar License Amendment Request to Revise TS 5.4.1 or 5.7.1 (L-2024-LLA-0039) ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24047A2792024-02-15015 February 2024 RAI Related to the Exemption Request for 10 CFR 37.11 ML24045A0272024-02-14014 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML23355A2202023-12-21021 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) ML24074A4172023-10-12012 October 2023 2024 EP Inspections RFI Email Confirmations: Redacted 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 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) 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) 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 TVAs 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 ML22259A0382022-09-14014 September 2022 NRR E-mail Capture - Browns Ferry TSTF-505 Audit Questions - Part 4 ML22259A0392022-09-14014 September 2022 NRR E-mail Capture - Browns Ferry TSTF-505 Audit Questions - Part 5 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 TVAs 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 TVAs Request to Use Control Bay Chiller Cross-Tie ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to TVAs 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 TVAs Request to Expand the SFP Criticality Safety Analysis for Browns Ferry Nuclear Plant, Units 1, 2, and 3 2024-09-10
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From: Wentzel, Michael Sent: Wednesday, December 2, 2020 11:33 AM To: Orf, Tracy J
Subject:
Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Audit Plan and Setup of Online Reference Portal (EPID L-2020-LLA-0162)
Attachments: Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Plan for Audit of Information in Support of LAR to Adopt 10 CFR 50.69 (L-2020-LLA-0162).pdf
Dear Mr. Orf:
By application dated July 17, 2020 (Agencywide Documents Access and Management System Accession No. ML20199M373); the Tennessee Valley Authority (TVA), submitted a license amendment request to allow for the voluntary adoption of the requirements of Title 10 of the Code of Federal Regulations, Section 50.69, Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors, at Browns Ferry Nuclear Plant, Units 1, 2, and 3.
To improve the efficiency of the U.S. Nuclear Regulatory Commission (NRC) staffs review, TVAs representatives and the NRC staff have discussed the use of an audit using an online reference portal that would allow the NRC staff limited, read-only access to the information identified in Section 4.0 of the attached audit plan. The NRC staff plans to conduct a desk audit to review the documentation provided on the portal. The online reference portal would allow the NRC staff to audit internal licensee information to confirm that the information support statements made in the license amendment request and to determine whether the information included in the documents is necessary to reach a safety conclusion on the application. The audit information the NRC staff determines to be necessary to support the development of the NRC staffs safety evaluation will be requested to be formally submitted on the docket. The audit may also include interactions (e.g. teleconferences or webinars) on a mutually agreeable schedule sufficient to understand or resolve issues associated with the information made available on the online reference portal.
Use of the online reference portal is acceptable, as long as the following conditions are met:
- The online reference portal will be password-protected and passwords will be assigned to those directly involved in the review on a need-to-know basis;
- The online reference portal will be sufficiently secure to prevent NRC staff from printing, saving, or downloading any documents; and
- Conditions of use of the online reference portal will be displayed on the login screen and will require concurrence by each user.
These conditions associated with the online reference portal must be maintained throughout the duration of the audit process.
The NRC staff would like to request that the portal be populated with the information identified in Section 4.0 of the attached audit plan. The NRC staff may request additional documents during the review, which will be transmitted to you via email.
If you have any questions, please contact me at (301) 415 6459 or michael.wentzel@nrc.gov.
Sincerely, Michael J. Wentzel, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Hearing Identifier: NRR_DRMA Email Number: 912 Mail Envelope Properties (MN2PR09MB586761578A9142A8EA5F641BE7F30)
Subject:
Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Audit Plan and Setup of Online Reference Portal (EPID L-2020-LLA-0162)
Sent Date: 12/2/2020 11:33:17 AM Received Date: 12/2/2020 11:33:17 AM From: Wentzel, Michael Created By: Michael.Wentzel@nrc.gov Recipients:
"Orf, Tracy J" <tjorf@tva.gov>
Tracking Status: None Post Office: MN2PR09MB5867.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 2847 12/2/2020 11:33:17 AM Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Plan for Audit of Information in Support of LAR to Adopt 10 CFR 50.69 (L-2020-LLA-0162).pdf 92535 Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
AUDIT PLAN REGARDING LICENSE AMENDMENT REQUEST TO ADOPT THE REQUIREMENTS OF 10 CFR 50.69 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 DOCKET NOS. 50-259, 50-260, AND 50-296 EPID L-2020-LLA-0162
1.0 BACKGROUND
By application dated July 17, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20199M373), the Tennessee Valley Authority (TVA; the licensee) submitted a license amendment request (LAR) for Browns Ferry Nuclear Plant, Units 1, 2, and 3 (Browns Ferry). The proposed amendments would allow for the voluntary adoption of the requirements of Title 10 of the Code of Federal Regulations, Section 50.69, Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors.
The U.S. Nuclear Regulatory commission (NRC) staff has reviewed the licensees submittal and determined that a regulatory audit of the information identified in the Information Request section below would assist in the timely completion of the subject LAR review process. The NRC staff is continuing to review other aspects of the licensees submittal and may identify the need for additional audit subjects by separate correspondence.
2.0. REGULATORY AUDIT BASES An audit was determined to be the most efficient approach toward a timely resolution of questions associated with this LAR review, because the NRC staff will have an opportunity to minimize the potential for RAIs and ensure no unnecessary burden will be imposed by requiring the licensee to address issues that are no longer necessary to make a safety determination.
The NRC staff is requesting an initial set of internal licensee information to be audited by the staff using an online reference portal. Upon completion of this audit, the NRC staff is expected to achieve the following.
- 1. Confirm internal licensee information that supports statements made in the LAR.
- 2. Determine whether the information included in the documents is necessary to be submitted to support a safety conclusion.
The audit information the NRC staff determines to be necessary to support the development of the NRC staffs safety evaluation will be requested to be submitted on the docket.
3.0 REGULATORY AUDIT SCOPE AND METHODOLOGY The purpose of the remote audit is to gain a more detailed understanding of the licensees process to implement risk-informed categorization and treatment of structures, systems and components as proposed in the LAR. The NRC staff will audit internal events and fire probabilistic risk assessment (PRA) and the risk informed approach implementing 10 CFR 50.69.
The areas of focus for the regulatory audit are the information contained in the licensees submittal, the enclosed audit information needs, and all associated and relevant supporting documentation (e.g., methodology, process information, calculations, etc.) identified below. The audit will be performed consistent with NRC Office of Nuclear Reactor Regulation Office Instruction LIC-111, Revision 1, Regulatory Audits, dated October 31, 2019 (ADAMS Accession No. ML19226A274).
4.0 INFORMATION REQUESTS Please provide the following information for the NRC staff to audit:
- 1. Applicable peer review reports and closure reports for internal events, internal flooding, fire and seismic PRAs.
- 2. Available 10 CFR 50.69 structures, systems, and components categorization program procedures (i.e., Categorization review and adjustment process, decision criteria for Independent Decision-Making Panel (IDP), etc.).
- 3. Uncertainty notebooks for internal events, internal flooding, and fire PRAs related to PRA model assumptions and sources of uncertainty.
- 4. Documentation of review of PRA model assumptions and sources of uncertainty and identification of key assumptions and sources of uncertainty for the application identified in the LAR.
- 5. PRA notebooks for the modeling of FLEX equipment and FLEX human error probabilities, if credited in the PRA 5.0 AUDIT TEAM Key licensee personnel involved in the development of the LAR should be made available for interactions on a mutually agreeable schedule to respond to any questions from the NRC staff.
Team Member Division Area of Responsibility Michael Wentzel NRR/DORL/LPLII-2 Project Management Mihaela Biro NRR/DRA/APLA Technical Review Jigar Patel NRR/DRA/APLA Technical Review Shilp Vasavada NRR/DRA/APLC Technical Review De Wu NRR/DRA/APLC Technical Review Garill Coles Pacific Northwest Technical Review National Laboratory
6.0 LOGISTICS The audit will be conducted from December 7, 2020 to January 20, 2021 through an online portal established by the licensee. The NRC staff and contractors access to the online portal should be terminated on February 19, 2021.
7.0 SPECIAL REQUESTS The NRC staff would like access to the documents listed above in Section 4.0 through an online portal that allows the NRC staff and contractors to access documents via the internet. The following conditions associated with the online portal must be maintained throughout the duration that the NRC staff and contractors have access to the online portal:
x The online portal will be password-protected, and separate passwords will be assigned to the NRC staff and contractors who are participating in the audit.
x The online portal will be sufficiently secure to prevent the NRC staff and contractors from printing, saving, downloading, or collecting any information on the online portal.
x Conditions of use of the online portal will be displayed on the login screen and will require acknowledgement by each user.
Username and password information should be provided directly to the NRC staff and contractors. The NRC project manager will provide TVA the names and contact information of the NRC staff and contractors who will be participating in the audit. All other communications should be coordinated through the NRC project manager.
7.0 DELIVERABLES The NRC team will develop an audit summary report to convey the results. The report will be placed in ADAMS within 90 days of the completion of the final audit session. The audit information the NRC staff determines to be necessary to support the development of the NRC staffs safety evaluation will be requested to be submitted on the docket.