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Category:Letter
MONTHYEARCNL-25-009, And Watts Bar Nuclear Plant, Units 1 and 2 - Organization Topical Report, TVA-NPOD89-A, Revision 262025-01-29029 January 2025 And Watts Bar Nuclear Plant, Units 1 and 2 - Organization Topical Report, TVA-NPOD89-A, Revision 26 IR 05000327/20240042025-01-28028 January 2025 Integrated Inspection Report 05000327/2024004 and 05000328/2024004 ML25023A0572025-01-23023 January 2025 Cycle 27 Core Operating Limits Report Revision 2 CNL-25-016, Comments on Preliminary Accident Sequence Precursor Program Analysis2025-01-16016 January 2025 Comments on Preliminary Accident Sequence Precursor Program Analysis CNL-24-084, Response to Request for Confirmatory Information Regarding Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.32025-01-13013 January 2025 Response to Request for Confirmatory Information Regarding Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.3 ML25006A1892025-01-0606 January 2025 ISFSI Inspection (Request for Information) ML24341A2102024-12-23023 December 2024 Exemption from the Requirements of 10 CFR Part 26, Section 205(D)(4) (EPID L-2024-LLE-0029) (Letter) ML24312A3222024-12-23023 December 2024 Issuance of Amendment Nos. 334, 357, & 317; 368 & 362; 172 & 77 Regarding Revision to TS 5.4 & 5.7.1 IR 05000327/20240102024-12-19019 December 2024 Design Basis Assurance Inspection (Programs) Inspection Report 05000327/2024010 and 05000328/2024010 CNL-24-009, Brown Ferry Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2 and Watts Bar Plant, Units 1 & 2 - Triennial Decommission Funding Plans for Independent Spent Fuel Storage Installations2024-12-17017 December 2024 Brown Ferry Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2 and Watts Bar Plant, Units 1 & 2 - Triennial Decommission Funding Plans for Independent Spent Fuel Storage Installations CNL-24-082, Central Emergency Control Center Emergency Plan Implementing Procedure Revision2024-12-17017 December 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML24347A0592024-12-12012 December 2024 Annual Non-Radiological Environmental Operating Report - 2024 ML24339B8242024-12-11011 December 2024 Summary of November 20, 2024, Public Pre-Submittal Meeting with TVA Regarding a One-Time Exemption Request from the Requirements of Title 10 of the Code of Federal Regulations Part 26, Section 26.205, Work Hours ML24337A1912024-12-0202 December 2024 Discharge Monitoring Report (Dmr), April 2024 ML24337A1932024-12-0202 December 2024 Discharge Monitoring Report (Dmr), June 2024 ML24337A1922024-12-0202 December 2024 Discharge Monitoring Report (Dmr), May 2024 ML24337A1942024-12-0202 December 2024 Discharge Monitoring Report (Dmr), July 2024 ML24337A1972024-12-0202 December 2024 Discharge Monitoring Report (Dmr), October 2024 ML24337A1952024-12-0202 December 2024 Discharge Monitoring Report (Dmr), August 2024 ML24337A1962024-12-0202 December 2024 Discharge Monitoring Report (Dmr), September 2024 CNL-24-073, Request for Exemption from Requirements of 10 CFR 26.205, Fitness for Duty Programs - Work Hours2024-11-27027 November 2024 Request for Exemption from Requirements of 10 CFR 26.205, Fitness for Duty Programs - Work Hours CNL-24-075, Response to Request for Additional Information for 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-TSTS-23-02 and W2024-11-27027 November 2024 Response to Request for Additional Information for 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-TSTS-23-02 and WBN CNL-24-071, Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the (SQN-TS-24-04)2024-11-26026 November 2024 Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the (SQN-TS-24-04) 05000327/LER-2024-002, Reactor Trip Due to a Turbine Trip2024-11-20020 November 2024 Reactor Trip Due to a Turbine Trip ML24319A2672024-11-14014 November 2024 Discharge Monitoring Report (DMR) Quality Assurance Study 44 Final Report 2024 CNL-24-021, Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020)2024-11-12012 November 2024 Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020) ML24312A1552024-11-0606 November 2024 Cycle 27 Core Operating Limits Report, Revision 1 IR 05000327/20240032024-11-0606 November 2024 Integrated Inspection Report 05000327/2024003 and 05000328/2024003 CNL-24-014, License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22)2024-11-0404 November 2024 License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22) ML24304A8492024-10-31031 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-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems 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 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 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 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 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), 2025-01-06
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SUBJECT:
NOTIFICATION OF SEQUOYAH, UNITS 1 AND 2 - COMPREHENSIVE ENGINEERING TEAM INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION INSPECTION REPORT 05000327, 328/2025010
Dear Jim Barstow:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a Comprehensive Engineering Team Inspection (CETI) at your Sequoyah, Units 1 and 2 during the weeks of January 27 and February 10, 2025. Mr. Adam Ruh, a Senior Reactor Inspector from the NRCs Region II office, will lead the inspection team.
The inspection will be conducted in accordance with Inspection Procedure 71111.21M, Comprehensive Engineering Team Inspection (CETI), issued October 7, 2022.
The inspection will evaluate the capability of components that have been modified and risk-significant/low-margin components to function as designed and to support proper system operation. The inspection will also include a review of selected operator actions, and operating experience, and modifications.
During a phone conversation on October 24th, 2024, with Mr. Scott Bowman, we confirmed arrangements for an information-gathering site visit and the two-week onsite inspection. The schedule is as follows:
Information-gathering visit: Week of November 11, 2024
Onsite weeks: Weeks of January 27 and February 10, 2025 The purpose of the information-gathering visit is to meet with members of your staff to identify components that have been modified, risk-significant components, and operator actions.
Information and documentation needed to support the inspection will also be identified.
Mr. Shane Sandal, a Region II Senior Reactor Analyst, will support Mr. Ruh during the information-gathering visit to review probabilistic risk assessment data and identify components to be examined during the inspection. Additionally, during the onsite weeks, time may be needed on the plant-referenced simulator to facilitate the development of operator action-based scenarios.
The enclosure lists documents that are requested to support sample selection following the information-gathering visit. Please provide the referenced information by Wednesday, November 20, 2024. Additional documents will be requested following the information-gathering October 29, 2024 visit. The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for inspection preparation. The additional information will be needed in the Region II office by Wednesday, January 15, 2025, to support the inspection teams preparation week. During the information-gathering trip, Mr. Ruh will also discuss the following inspection support administrative details: (1) availability of knowledgeable plant engineering and licensing personnel to serve as points of contact during the inspection; (2)
method of tracking inspector requests during the inspection; (3) licensee computer access; (4)
working space; (5) arrangements for site access; and (6) other applicable information.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Thank you for your cooperation in this matter. If you have any questions, regarding the information requested or the inspection, please contact Mr. Ruh at 404-997-4669 or contact me at 404-997-4710.
Sincerely, Anthony Masters, Chief Engineering Branch 1 Division of Operating Reactor Safety Docket Nos. 05000327 and 05000328 License Nos. DPR-77 and DPR-79 Enclosure:
Information Request for Sequoyah, Units 1 and 2 Comprehensive Engineering Team Inspection cc w/ encl: Distribution via LISTSERV Signed by Masters, Anthony on 10/29/24
ML24303A150 X
SUNSI Review X
Non-Sensitive
Sensitive X
Publicly Available
Non-Publicly Available OFFICE R2/DRS/EB1 R2/DORS/EB1 NAME A. Masters A. Ruh DATE 10/29/2024 10/29/2024
Enclosure INFORMATION REQUEST FOR SEQUOYAH, UNITS 1 AND 2 COMPREHENSIVE ENGINEERING TEAM INSPECTION Please provide the information electronically in.pdf files, Excel, or other searchable format on CDROM (or FTP site, SharePoint, etc.). The CDROM (or website) should be indexed and hyperlinked to facilitate ease of use. The requested items below, identified with an asterisk (*),
should have a date range from December 15, 2021, until present.
Information requested to support information gathering visit:
1.
- List of modifications to systems, structures or components (SSCs) that are permanent and field work completed. (For the purpose of this inspection, modifications include permanent: plant changes, design changes, calculation changes, procedure changes, and set point changes.)
The list should contain the number of the modification, a short description, affected system and unit. If multiple categories/stages of modifications exist, provide a description of the types relative to the coding scheme in your transmittal. Additionally, the list should be categorized by quality level (i.e., safety or non-safety) as well as whether accompanied by a screening or 10 CFR 50.59 evaluation. A query report return-field-set might look like:
e.g. If systems are provided with some type of number or acronym designation, define the systems designation on a separate list or document
e.g. Engineering Design/Document Change, Design Change Notice, Test, Experiment, etc.
e.g. Closed, Returned to Operation, Void, Partially Completed, Released for Installation, Phase 1 Completed, etc.
e.g. Safety Related or Non-Safety Related
e.g. Screened Out or Full 10 CFR 50.59 Evaluation 2.
From your most recent probabilistic safety analysis (PSA) excluding external events and fires:
a.
Two risk rankings of components from your site-specific PSA: one sorted by Risk Achievement Worth (RAW), and the other sorted by Birnbaum Importance b.
A list of the top 500 cut-sets c.
A list of the top 500 LERF contributors 3.
From your most recent PSA including external events and fires:
a.
Two risk rankings of components from your site-specific PSA: one sorted by RAW, and the other sorted by Birnbaum Importance b.
A list of the top 500 cut-sets 4.
Risk ranking of operator actions from your site-specific PSA sorted by RAW and human reliability worksheets for these items 5.
List of time-critical operator actions with a brief description of each action with applicable administrative procedures used to maintain them 6.
- List and brief description of Root Cause Evaluations performed Identifier Unit System1 Description Type2 Status3 QA Condition4 50.595
7.
8.
- List and reason for equipment that has been classified in maintenance rule (a)(1) status and most recent (a)(3) review.
9.
- List of equipment on the sites Station Equipment Reliability Issues or Heat Map lists, including a description of the reason(s) why each component is on that list, and summaries (if available) of your plans to address the issue(s) along with dates added or removed from the issues list 10. List of current operator work arounds/burdens and control room deficiencies 11. List of heat exchangers covered by license renewal or service water programs 12. List of motor operated valves and air operated valves in IST/valve programs and their associated design margin (i.e. High/Medium/Low), risk ranking (i.e. High/Medium/Low), and IST Program document.
13. List (procedure number, title, and current revision) of station Emergency Operating Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures 14. Copies of corrective action documents generated from previous design bases assurance inspections 15. Copy of any self-assessments performed, and corrective action documents generated, in preparation for current comprehensive engineering team inspection 16. Contact information for a person to discuss PSA information prior to and during the information-gathering trip (Name, title, phone number, and e-mail address)
17. List of system acronyms 18. One-line diagram of electrical plant (Electronic only)
19. *List of components with low-design margins (i.e., pumps closest to the design limit for flow or pressure, diesel generator close to design-required output, heat exchangers close to rated design heat removal, and motor-operated valve risk-margin rankings, etc.) and associated evaluations or calculations 20. Copy of procedures addressing the following: loss of service water system or ultimate heat sink (UHS); controls to prevent clogging due to macrofouling; and performance, testing, and inspection requirements for service water system and UHS 21. Primary AC and DC calculations for safety-related buses