Letter Sequence Approval |
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EPID:L-2022-LLR-0034, Brown Ferry Nuclear Station, Sequoyah Nuclear Station and Watts Bar Station - Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update (Approved, Closed) |
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MONTHYEARCNL-20-033, Brown Ferry Nuclear Station, Sequoyah Nuclear Station and Watts Bar Station - Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update2020-04-24024 April 2020 Brown Ferry Nuclear Station, Sequoyah Nuclear Station and Watts Bar Station - Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update Project stage: Request CNL-20-088, Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update2020-10-29029 October 2020 Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update Project stage: Request CNL-21-048, Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Miilstone Status Update2021-04-29029 April 2021 Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Miilstone Status Update Project stage: Request CNL-21-089, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2021-10-29029 October 2021 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update Project stage: Request ML22167A1672022-03-15015 March 2022, 27 May 2022, 28 June 2022, 9 August 2022, 12 August 2022, 28 September 2022, 29 September 2022, 1 December 2022 1 and 2 Request for Alternative RV-02 - PIV Leakage (EPID L 2022-LLR-0034 Project stage: Request ML22095A0182022-04-0404 April 2022 NRR E-mail Capture - Sequoyah Nuclear Plant - Acceptance of Request for Alternative - Pressure Isolation Valve Leakage ISTC-3630 (L-2022-LLR-0034) Project stage: Acceptance Review CNL-22-052, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status2022-04-27027 April 2022 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Project stage: Request ML22151A0092022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 Project stage: RAI ML22151A0102022-05-27027 May 2022 NRR E-mail Capture - Revised Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 Project stage: RAI CNL-22-062, Response to Request for Additional Information Regarding American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-022022-06-28028 June 2022 Response to Request for Additional Information Regarding American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02 Project stage: Response to RAI ML22220A1072022-08-0909 August 2022 Regulatory Audit in Support of Review of the Request for Alternative to American Society of Mechanical Engineers Operation and Maintenance Code Project stage: Approval ML22263A0082022-09-28028 September 2022 Audit Summary Request for Alternative RV-02 - PIV Leakage Project stage: Other ML22263A3752022-09-29029 September 2022 Authorization of Alternative Request RV-02 for Pressure Isolation Valve Seat Leakage Project stage: Other CNL-22-104, Correction to Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-022022-10-31031 October 2022 Correction to Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02 Project stage: Response to RAI CNL-22-099, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2022-10-31031 October 2022 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update Project stage: Request ML22304A1862022-12-0101 December 2022 Revised Authorization of Alternative Request RV-02 for Pressure Isolation Valve Seat Leakage Project stage: Other 2022-04-27
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Category:Audit Plan
MONTHYEARML22224A0352022-08-12012 August 2022 Regulatory Audit Questions - Request for Alternative to ASME Operation and Maintenance Code Subsection ISTC-3630 ML22220A1072022-08-0909 August 2022 Regulatory Audit in Support of Review of the Request for Alternative to American Society of Mechanical Engineers Operation and Maintenance Code ML21246A0532021-09-15015 September 2021 Regulatory Audit in Support of Review of the Application to Adopt Risk-Informed Extended Completion Times RITSTF Initiative 4B ML16259A1892016-12-0505 December 2016 Nuclear Regulatory Commission Plan for the Audit of Mitigation Strategies Assessment Submittals Related to Order EA-12-049, Order to Modify Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML15106A6322015-04-17017 April 2015 Tennessee Valley Authority FHRR Audit Plan-4-22-2015 ML14356A0032015-02-10010 February 2015 Audit of Licensee Responses to the Expedited Seismic Evaluation Process to Support Implementation of Near-Term Task Force Recommendation 2.1, Seismic ML14302A1972014-11-0606 November 2014 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 ML13067A2442013-03-26026 March 2013 Lr Environmental Site Audit Regarding Sequoyah Nuclear Plant ML13067A2012013-03-11011 March 2013 Plan for the Aging Management Program Regulatory Audit Regarding the Sequoyah Nuclear Plant, Units 1 and 2 License Renewal Application Review (TAC Nos. MF0481 and MF0482) 2022-08-09
[Table view] Category:Letter
MONTHYEARML24304A8492024-10-31031 October 2024 December 2024 Requalification Inspection Notification Letter IR 05000327/20250102024-10-29029 October 2024 Notification of Sequoyah, Units 1 and 2 - Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000327/2025010 and 05000328/2025010 ML24298A1172024-10-24024 October 2024 Cycle 26, 180-Day Steam Generator Tube Inspection Report CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000327/LER-2024-001, Reactor Trip Due to a Turbine Trip2024-10-17017 October 2024 Reactor Trip Due to a Turbine Trip ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 05000328/LER-2024-001, Reactor Trip Due to an Electrical Trouble Turbine Trip2024-09-25025 September 2024 Reactor Trip Due to an Electrical Trouble Turbine Trip CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24267A0402024-09-19019 September 2024 Cycle 27 Core Operating Limits Report Revision 0 CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24185A1742024-09-18018 September 2024 Cover Letter - Issuance of Exemption Related to Non-Destructive Examination Compliance Regarding Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation ML24253A0152024-09-0808 September 2024 Emergency Plan Implementing Procedure Revisions ML24247A2212024-08-29029 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-21-160, NEI 03-08 Needed Guidance: PWR Lower Radial Support Clevis Insert X-750 Bolt Inspection Requirements, September 1, 2021 ML24247A1802024-08-28028 August 2024 Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation for Sequoyah Nuclea IR 05000327/20240052024-08-26026 August 2024 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2024005 and 05000328/2024005 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), IR 05000327/20240022024-07-31031 July 2024 Integrated Inspection Report 05000327/2024002 and 05000328/2024002 ML24211A0572024-07-29029 July 2024 Submittal of Emergency Plan Implementing Procedure Revision ML24211A0542024-07-29029 July 2024 Operator License Examination Report ML24211A0412024-07-26026 July 2024 Unit 1 Cycle 26 Refueling Outage - 90-Day Inservice Inspection Summary Report ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24191A4652024-07-0909 July 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24177A0282024-06-25025 June 2024 Emergency Plan Implementing Procedure Revisions ML24176A0222024-06-24024 June 2024 Retraction of Interim Report of a Deviation or Failure to Comply – Transducer Model 8005N ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24145A0852024-05-30030 May 2024 1B-B Diesel Generator Failure - Final Significance Determination Letter ML24145A1052024-05-29029 May 2024 301 Exam Approval Letter ML24134A1762024-05-13013 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24128A0352024-05-0707 May 2024 Providing Supplemental Information to Apparent Violation ML24120A0582024-04-26026 April 2024 10 CFR 50.46 Annual Report for Sequoyah Nuclear Plant Units 1 and 2 ML24116A2612024-04-25025 April 2024 Interim Report of a Deviation or Failure to Comply - Transducer Model 8005N ML24114A0482024-04-23023 April 2024 Annual Radioactive Effluent Release Report for 2023 Monitoring Period CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24144A2362024-04-20020 April 2024 Discharge Monitoring Report (Dmr), March 2024 ML24144A2322024-04-20020 April 2024 Tennessee Multi-Sector Permit (Tmsp), 2024 Annual Discharge Monitoring Report for Outfalls SW-3, SW-3, and SW-9 ML24089A0882024-04-18018 April 2024 – Exemption from Select Requirements of 10 CFR Part 73; Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24102A1212024-04-18018 April 2024 Summary of Conference Call with Tennessee Valley Authority Regarding Sequoyah Nuclear Plant, Unit 1 Spring 2024 Steam Generator Tube Inspections CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000327/20240012024-04-17017 April 2024 Integrated Inspection Report 05000327/2024001 and 05000328/2024001 ML24109A0272024-04-16016 April 2024 Cycle 27 Core Operating Limits Report Revision 0 CNL-23-006, Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03)2024-04-15015 April 2024 Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03) ML24106A0502024-04-12012 April 2024 Discharge Monitoring Report (Dmr), February 2024 2024-09-08
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Text
August 9, 2022
Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - REGULATORY AUDIT IN SUPPORT OF REVIEW OF THE REQUEST FOR ALTERNATIVE TO AMERICAN SOCIETY OF MECHANICAL ENGINEERS OPERATION AND MAINTENANCE CODE (EPID L-2022-LLR-0034)
Dear Sir or Madam:
By letter dated March 15, 2022, (Agencywide Documents Access an d Management System (ADAMS) Accession No. ML22074A315), as supplemented by a letter dated June 28, 2022 (ML22179A357), Tennessee Valley Authority (the licensee) submitted a request f or an alternative to Inservice Testing (IST) Program requirements for Sequoyah Nuclear Plant, Units 1 and 2, respectively. The alternative would apply to compliance with the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code, Subsection ISTC, paragraphs ISTC-3630, ISTC-3630(f), ISTC-5221(a)(1), and ISTC-5 224, for specific IST Program requirements for certain pressure isolation valves (PIV s).
The U.S. Nuclear Regulatory Commission (NRC) staff has identifi ed the need for a regulatory audit to examine the licensees non-docketed information with t he intent to gain understanding, to verify information, or to identify information that will req uire docketing to support the basis of the licensing or regulatory decision.
The NRC staff will conduct the audit virtually at NRC Headquart ers in Rockville, Maryland, via a licensee-established electronic portal available to NRC staff f rom approximately August 10, 2022, through August 31, 2022, with formal audit meetings to be scheduled during this period as needed. The detailed audit plan is enclosed with this letter.
J.Barstow
If you have any questions, please contact me at (301) 415-1383 or by e-mail at Perry.Buckberg@nrc.gov.
Sincerely,
/RA/
Perry H. Buckberg, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket Nos. 50-327 and 50-328
Enclosure:
Audit Plan
cc: Listserv REGULATORY AUDIT PLAN
BY THE OFFICE OF NUCLEAR REACTOR REGULATION
TO SUPPORT THE REVIEW OF THE REQUEST FOR ALTERNATIVE TO
AMERICAN SOCIETY OF MECHANICAL ENGINEERS OPERATION AND MAINTENANCE
CODE SUBSECTION ISTC-3630
TENNESSEE VALLEY AUTHORITY
SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2
DOCKET NOS. 50-327 AND 50-328
1.0 BACKGROUND
By letter dated March 15, 2022, (Agencywide Documents Access an d Management System (ADAMS) Accession No. ML22074A315), as supplemented by a letter dated June 28, 2022 (ML22179A357), Tennessee Valley Authority (the licensee) submitted a request f or an alternative to the Inservice Testing (IST) Program requirements for Sequoyah Nuclear Plant, Units 1 and 2, respectively. The alternative would apply to com pliance with American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code of Record, Subsection ISTC, paragraphs ISTC-3630, ISTC-3630(f), ISTC-5221(a)(1), and ISTC-5224, for specific IST Program requirements for certain pressure isolation valves (PIV s).
The staff from the U.S. Nuclear Regulatory Commissions (NRC) O ffice of Nuclear Reactor Regulation (NRR) has initiated its review of the request in acc ordance with NRR Office Instruction LIC-102, Revision 3, Review of Relief Requests, Pr oposed Alternatives, and Requests to Use Later Code Editions and Addenda (ML18351A218).
2.0 REGULATORY AUDIT BASIS
A regulatory audit is a planned license-or regulation-related activity that includes the examination and evaluation of primarily non-docketed informatio n associated with the licensees request. An audit is conducted to gain understanding, to verify information, and to identify information that will require docketing to support the basis of a licensing or regulatory decision.
An audit will assist the NRC staff in efficiently conducting it s review and gaining insights to the licensees processes and procedures. Information that the NRC s taff relies upon to make the safety determination must be submitted on the docket. This audi t will be conducted in accordance with NRR Office Instruction LIC-111, Regulatory Aud its, Revision 1, dated October 2019 (ADAMS Accession No. ML19226A274), with exceptions noted within this audit plan.
The NRC staff will perform the audit to support its evaluation of whether the licensees request can be approved per Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a, "Codes and Standards," paragraph (z)(2). The audit will assist the NRC staff with understanding the licensees proposed alternative to ISTC-3630.
Enclosure
3.0 REGULATORY AUDIT SCOPE AND METHODOLOGY
NRCs objectives of the audit are the following:
Gain a better understanding of the specific actions that the l icensee may take to address pressure isolation valve (PIV) leakage and use of mechanical ag itation as an alternative to compliance with ISTC-3630.
The NRC staff will audit the methods that the licensee would us e to mechanically agitate a PIV following failure of a leakage test as part of a repair activit y to achieve acceptable seat leakage.
4.0 INFORMATION AND OTHER MATERIAL NECESSARY FOR THE AUDIT
The NRC staff will request information and an audit meeting(s) throughout the audit period. The NRC staff will use an Audit Items List to identify the inform ation (e.g., methodology, process information, and calculations) to be audited. The NRC staff will provide the final Audit Items List as an enclosure to the audit summary report, which will b e publicly available. The attachment to this audit plan includes the Initial Audit Items List. Throughout the audit period, the NRC staff may provide the licensee with audit questions and audit-related requests so that the licensee can better prepare for audit discussions with NRC staff. Any information accessed through the licensees portal will not be held or retained in a ny way by NRC staff. The NRC staff requests the licensee to have the information listed in the aud it items list to be readily available and accessible for the NRC staffs review via a web-based porta l.
5.0 TEAM ASSIGNMENTS
The audit team will consist of the following NRC staff from NRR and contractors.
Perry Buckberg, Plant Licensing Branch II-2 (LPL2-2)
Gurjendra Bedi, Mechanical Engineering and Inservice Testing B ranch (EMIB)
Thomas Scarbrough, EMIB Ian Tseng, EMIB
6.0 LOGISTICS
To support the review schedule communicated to Tennessee Valley Authority (TVA) when the NRC staff accepted the request for technical review, audit acti vities will be performed remotely and virtually using Microsoft Teams, teleconference, and a web-based portal or other virtual meeting space created by the licensee. NRC information requests and communications with licensee staff will be coordinated through the NRCs licensing project manager.
The virtual audit will begin approximately August 10, 2022 and will continue through August 31, 2022. The NRCs entrance meeting with the licensee w ill take place the first week of the audit. The NRCs licensing project manager will inform the licensee of the entrance and exit meeting dates when they are established. The NRC intends to est ablish an audit meeting(s)
(e.g., a single, multi-day audit meeting; periodic audit meetin gs throughout the audit period) on mutually agreeable dates and times (to be determined) to discus s information needs and questions arising from the NRCs review of the audited items.
The NRC staff requests the licensee to have the information ref erenced in section 4.0 of this audit plan available and accessible for the NRC staffs review via an internet-based portal within 1-week of the date of this audit plan. The NRC staff requests t hat any supplemental information requested be available and accessible for the NRC staffs revie w within 1-week of the date of the NRCs notification to the licensee of the new requests. The NRCs licensing project manager will inform the licensee via routine communications when the NR C staff no longer needs access to the portal. The NRC staff requests the licensee to notify th e review team when an audit item is added to its portal by sending an e-mail to the NRC licensin g project manager.
7.0 SPECIAL REQUESTS
The NRC requests access to requested documents and information through a web-based portal that allows the NRC staff to access documents over the internet. The following conditions associated with the online portal must be maintained while the NRC staff and contractors have access to the online portal:
The online portal will be password-protected. A separate passw ord will be assigned to each member of the NRC staff and NRC contractors participating in the audit.
The online portal will prevent the NRC participants from print ing, saving, downloading, or collecting any information directly from the online portal.
Conditions of use of the online portal will be displayed on th e login screen and will require acknowledgment by each user.
Username and password and/or other web-based portal access info rmation should be provided directly to members of the NRC staff and contractors as needed. The NRC licensing project manager will provide the licensee with names and contact inform ation of the NRC staff and contractors participating in the audit. All other communication s should be coordinated through the NRC project manager.
8.0 DELIVERABLES
The NRC staff will develop any requests for additional informat ion (RAIs), as needed, via NRR Office Instruction LIC-115, Revision 1, Processing Requests fo r Additional Information (ML21141A238) and issue such RAIs s eparately from audit-related correspondence. The NRC staff will issue an audit summary report prior to completing it s review of the request.
Initial Audit Items List
Item # Audit Item 1 The Tennessee Valley Authority (TVA) developed technical eval uation to formally document the guidance for performing mechanical agitation of th e pressure isolation valves. This technical evaluation was referred to in the June 28, 2022, TVA letter (ML22179A357)
2 Technical evaluation supporting documentation as requested by the NRC
Attachment
ML22220A107 OFFICE NRR/DORL/LPLII-2/PM NRR/DORL/LPLII-2/LA NRR/DEX/EMIB/BC NRR/DORL/LPLII-2/PM NAME PBuckberg RButler SBailey PBuckberg DATE 8/8/2022 8/9/2022 8/8/2022 8/9/2022 OFFICE NRR/DORL/LPLII-2/BC NAME DWrona (LHaeg for)
DATE 8/9/2022