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EPID:L-2022-LLA-0190, License Amendment Request to Revise Technical Specification 1.1 and Add 5.5.23 to Use Online Monitoring Methodology (Approved, Closed) |
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Category:Audit Report
MONTHYEARML23166A0332023-07-0505 July 2023 LAR-23-005 Timing of TS Effectiveness Prior to Initial Criticality Audit Report ML23080A2812023-03-27027 March 2023 Regulatory Audit in Support of Review of the License Amendment Request to Revise Technical Specification 1.1, Use and Application Definitions, and to Add Technical Specification 5.5.23, Online Monitoring Program ML23059A4562023-03-10010 March 2023 Audit Summary for License Amendment Request to Allow Use of Accident-Tolerant Fuel Lead Test Assemblies ML22279B0532022-11-0808 November 2022 Audit Agenda and Topics in Support of Review of the Application to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel ML20258A0022020-12-10010 December 2020 Letter, Audit Report for the Promise Version 1.0 Probabilistic Fracture Mechanics Software Used in Relief Request VEGP-ISI-ALT-04-04 ML20141L6982020-05-26026 May 2020 Audit Report for Vogtle Electric Generating Plant Unit 3 LAR 20-001: Auxiliary Building Wall 11 Seismic Gap Requirements ML20084L5972020-04-22022 April 2020 Audit Summary for LAR-19-019 ML20085G6992020-04-0808 April 2020 Audit Report for LAR-19-010 Auxiliary Building Room Heat-up ML20080L9272020-03-20020 March 2020 Audit Summary for LAR 19-017, Removal of the Preoperational Passive Residual Heat Removal Heat Exchanger Natural Circulation Test (Public) ML20063H2062020-03-20020 March 2020 Audit Plan for LAR 20-001 Auxiliary Building Wall 11 Seismic Gap Requirements ML20065M8032020-03-11011 March 2020 Audit Report for Vogtle Electric Generating Plant Units 3 and 4 (LAR 19-009) Request for License Amendment and Exemption: Automatic Depressurization System (ADS) and Core Makeup Tank Cmt Design Parameters ML19338C1512019-12-18018 December 2019 Regulatory Audit Report (LAR-19-014) ML19336A3762019-12-16016 December 2019 Audit Report for Vogtle Electric Generating Plant Unit 4, Request for License Amendment: Reinforcement Changes for Wall L and Wall 7.3 (LAR-19-016R1) ML19326A9372019-11-22022 November 2019 Audit Report for Vogtle Electric Generating Plant Units 3 and 4, Request for License Amendment: Crediting Previously Completed First Plant Only Startup Tests (LAR-19-011) - Publicly Available Version ML19290H1142019-10-21021 October 2019 Audit Report for Vogtle Units 3 and 4 LAR 19-006 (Public) ML19280D8722019-10-11011 October 2019 Audit Report for Vogtle Electric Generating Plant Unit 4 - Request for License Amendment LAR-19-016 ML19283C5112019-10-10010 October 2019 LAR-19-001 Audit Summary Public Version ML18338A0902018-12-0303 December 2018 Audit Report (LAR-18-019) Public (Non-Proprietary) ML18267A3702018-10-26026 October 2018 Us NRC Audit Report Related to Vogtle Electric Generating Plant, Units 3 and 4 License Amendment Request (LAR 17-043) Containment Pressure Analysis ML18290A5942018-10-19019 October 2018 Audit Summary for ESF Safeguard Actuation TS Applicability Changes, LAR 18-011 ML18262A0982018-09-20020 September 2018 LAR-17-031 Final Audit Report - Public ML18138A4192018-06-18018 June 2018 Regulatory Audit Report - Phase 1 Audit Conducted 4/4 to 4/6/18; Phase 2 Audit Conducted 5/15/18 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis ML18142B4822018-05-31031 May 2018 Us NRC Audit Report Related to License Amendment Request (LAR) 17-039 Unqualified Service Level 1 Coatings Program ML18113A1052018-04-24024 April 2018 Audit Summary - Vogtle Electric Generating Plant, Units 3 and 4 (LAR 18-002) ML18072A3182018-04-0303 April 2018 Audit Report for Vogtle Electric Generating Plant, Units 3 and 4 LAR-17-023 ML18058A3312018-03-27027 March 2018 Audit Summary for VEGP Units 3 and 4 Request for License Amendment and Exemption LAR-17-018 ML18066A9132018-03-13013 March 2018 Staff Review of Spent Fuel Pool Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1: Seismic ML18059A7552018-03-12012 March 2018 Audit Report for Vogtle Electric Generating Plant, Units 3 and 4, Request for License Amendment and Exemption: Prhr Heat Transfer and IRWST Heat Up Test Acceptance Criteria Change (LAR 17-033) ML18054A0662018-03-0808 March 2018 Summary Report for NRC Audit for Vogtle Electric Generating Plant, Units 1 and 2, Amendment Request to Incorporate Seismic Probabilistic Risk Assessment Into 10 CFR 50.69 Categorization Process (CAC Nos. MF9861 and MF9862; EPID L-2017-LLA-0 ML18045A7392018-03-0101 March 2018 Audit Report Prha and Flooding (LAR-17-010) ML18045A8622018-02-26026 February 2018 Units and 4 - Audit Report for LAR-17-025 ML16172A0952016-06-30030 June 2016 Summary of NRC Audit of Vogtle Electric Generating Plant, Units 1 and 2, for License Amendment Request to Revise Technical Specifications to Implement Nuclear Energy Institute (NEI) 06-09, Revision 0 ML15210A5102015-08-25025 August 2015 Report for the Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML15118A7532015-07-10010 July 2015 Audit of Southern Nuclear Operating Company, Inc. Management of Regulatory Commitments ML12061A2452012-03-0505 March 2012 Audit for the Process Being Developed to Support a License Amendment Request to Risk Informed Categorization of Systems, Structures and Components ML11304A2612011-11-0707 November 2011 Audit of the Southern Nuclear Operating Company Categorization Process Being Developed to Support a Request for a License Amendment to Implement 10 CFR 50.69 ML1107303502011-03-28028 March 2011 Audit of Southern Nuclear Operating Company, Inc.'S (Snc), Management of Regulatory Commitments ML1019002272010-07-0909 July 2010 Audit of Steam Generator H* Amendment Reference Documents (TAC Numbers ME3003 and ME3004) ML0826802952008-10-0101 October 2008 License Renewal Audit Summary Report 2023-07-05
[Table view] Category:Letter
MONTHYEARNL-24-0385, Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator2024-10-31031 October 2024 Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator IR 05000424/20240032024-10-30030 October 2024 – Integrated Inspection Report 05000424/2024003 and 05000425/2024003 NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0386, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information2024-10-28028 October 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information NL-24-0366, Core Operating Limits Report, Cycle 26, Version 12024-10-25025 October 2024 Core Operating Limits Report, Cycle 26, Version 1 ML24297A6482024-10-23023 October 2024 5 to the Updated Final Safety Analysis Report, Technical Specification Bases Changes, Technical Requirements Manual Changes, Summary Report and Revised NRC Commitments Report ML24269A2502024-09-26026 September 2024 Acknowledgement of the Withdrawal of the Requested Exemption and License Amendment Request to Remove Tier 1 and Tier 2* Requirements NL-24-0369, Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements2024-09-25025 September 2024 Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements NL-24-0350, Core Operating Limits Report, Cycle 24, Version 22024-09-25025 September 2024 Core Operating Limits Report, Cycle 24, Version 2 ML24243A0072024-09-10010 September 2024 – Correction of Amendment Nos. 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 ML24102A2642024-09-0909 September 2024 – Exemption Request Regarding Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0013) - Letter NL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024 Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program ML24249A2942024-09-0606 September 2024 Correction of Amendment Nos. 218 and 201 Regarding Revision to Technical Specifications to Use Online Monitoring Methodology 05200025/LER-2024-002, Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve2024-09-0505 September 2024 Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve IR 05000424/20240052024-08-26026 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 - Report 05000424/2024005 and 05000425/2024005 ML24235A1952024-08-22022 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 3 and 4 - Report 05200025/2024005 and 05200026/2024005 IR 05000424/20244012024-08-15015 August 2024 4 - Security Baseline Inspection Report 05000424-2024401, 05000425-2024401, 05200025-2024402, and 05200026-2024403 - Cover Letter NL-24-0299, Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information2024-08-14014 August 2024 Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information 05000425/LER-2024-001, Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod2024-08-0909 August 2024 Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod ML24218A1842024-08-0707 August 2024 Examination Report and Cover Letter 05200026/LER-2024-001, Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal2024-08-0606 August 2024 Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal ML24212A1442024-08-0101 August 2024 Integrated Inspection Report 05200025/2024002 and 05200026/2024002 IR 05000424/20240022024-07-29029 July 2024 Integrated Inspection Report 05000424/2024002 and 05000425/2024002 IR 05000424/20244042024-07-26026 July 2024 Material Control and Accounting Program Inspection Report 05000424/2024404 and 05000425/2024404 (Cover Letter) NL-24-0282, License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements2024-07-25025 July 2024 License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements NL-24-0126, – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.62024-07-25025 July 2024 – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.6 ML24204A0722024-07-23023 July 2024 Issuance of Amendment No. 225, Regarding LAR to Revise TS 3.7.9 for a one-time Change to Support Nuclear Service Cooling Water Transfer Pump Repairs - Emergency Circumstances NL-24-0286, Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair2024-07-20020 July 2024 Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 ML24191A4562024-07-19019 July 2024 Request for Relief and Alternative Requirements for Squib (Explosively Actuated) Valves First Test Interval ML24194A0342024-07-12012 July 2024 Review of the Refueling Outage 1R24 Steam Generator Tube Inspection Report ML24191A3792024-07-10010 July 2024 – Initial Test Program and Operational Programs Inspection Report 05200026/2024011 NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0087, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks2024-06-21021 June 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0243, Registration of Spent Fuel Cask Use2024-06-18018 June 2024 Registration of Spent Fuel Cask Use ML24163A0632024-06-12012 June 2024 2024 Licensed Operator Re-qualification Inspection Notification Letter Vogtle, Units 3 & 4 ML24155A1772024-06-0505 June 2024 Regulatory Audit in Support of Review of the LAR to Revise Emergency Diesel Generator Frequency and Voltage Ranges for Technical Specification 3.8.1, Surveillance Requirements NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24094A1402024-05-16016 May 2024 Staff Response to Request for Revision to NRC Staff Assessment of Updated Seismic Hazard Information and Latest Understanding of Seismic Hazards at the Vogtle Plant Site Following the NRC Process for the Ongoing Assessment of Natural Hazard ML24130A2412024-05-13013 May 2024 Integrated Inspection Report 05200025/2024001 and 05200026/2024001 ML24120A1812024-05-13013 May 2024 Request for Withholding Information from Public Disclosure Responses to NRC Request for Additional Information for Refueling Outage IR24 Steam Generator Tube Inspection Report – Enclosure 2 ML24101A2112024-05-11011 May 2024 Expedited Issuance of Amendment No. 198 Change to Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 ML24127A2372024-05-0909 May 2024 Initial Test Program and Operational Programs Inspection Report 05200026/2024010 NL-24-0194, Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1)2024-05-0707 May 2024 Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1) ML24120A2832024-04-30030 April 2024 Project Manager Reassignment 2024-09-09
[Table view] |
Text
March 27, 2023
Mr. R. Keith Brown Regulatory Affairs Director Southern Nuclear Operating Co., Inc.
3535 Colonnade Parkway Birmingham, AL 35243
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 -
REGULATORY AUDIT IN SUPPORT OF REVIEW OF THE LICENSE AMENDMENT REQUEST TO REVISE TE CHNICAL SPECIFICATION 1.1, USE AND APPLICATION DEFINITIONS, AND TO ADD TECHNICAL SPECIFICATION 5.5.23, ONLINE MONITORING PROGRAM (EPID L-2022-LLA-0190)
Dear Mr. Brown:
By letter dated December 21, 2022 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML22355A588), Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request (LAR) for Vogtle Electric Generating Plant (Vogtle), Units 1 and 2. The proposed LAR would revise Technical Specification (TS) 1.1, Use and Application Definitions, and add TS 5.5.23, Online Monitoring Program.
SNC proposes to use online monitoring (OLM) methodology as the technical basis to switch from time-based surveillance frequency for channel calibrations to a condition-based calibration frequency based on OLM results. The proposed LAR is based on the U.S. Nuclear Regulatory Commission (NRC)-approved Analysis and Measur ement Services Corporation (AMS) topical report (TR) AMS-TR-0720R2-A, Online Monitoring Technology to Extend Calibration Intervals of Nuclear Plant Pressure Transmitters (ML21235A493).
The NRC staff conducted a virtual regulatory audit between February 1 and March 21, 2023, to examine the SNCs non-docketed information on the proposed Vogtle OLM program. This audit was conducted in accordance with the audit plan dated January 20, 2023 (ML23011A274). The purpose of this audit was to gain understanding, to verify information, or to identify information that will require docketing to support the basis of the licensing or regulatory decision.
The purpose of this letter is to provide the results of the regulatory audit. Documented in the enclosed report are the observations the NRC staff identified during the audit.
Sincerely,
/RA/
John G. Lamb, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Enclosure:
Audit Report
cc: Listserv
REGULATORY AUDIT REPORT
BY THE OFFICE OF NUCLEAR REACTOR REGULATION
TO SUPPORT THE REVIEW OF THE LICENSE AMENDMENT REQUEST
TO REVISE TS 1.1 and ADD TS 5.5.23
SOUTHERN NUCLEAR OPERATING COMPANY
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2
DOCKET NOS. 50-424 AND 50-425
DATE: February 1 to March 21, 2023
LOCATION: Remote
AUDIT TEAM MEMBERS:
Richard Stattel, Audit Team Member, NRR/DEX/EICB Joseph Ashcraft, Audit Team Member, NRR/DEX/EICB Tarico Sweat, Audit Team Member, NRR/DSS/STSB
BACKGROUND:
By letter dated December 21, 2022 (Agencywi de Documents and Access Management System (ADAMS) Accession No. ML22355A588), Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request (L AR) for Vogtle Electric Generating Plant (Vogtle), Units 1 and 2. The proposed LAR would revise Technical Specification (TS) 1.1, Use and Application Definitions, and add TS 5.5.23, Online Monitoring Program.
The licensee proposes to use online monitoring (OLM) methodology as the technical basis to switch from time-based surveillance frequency for channel calibrations to a condition-based calibration frequency based on OLM results. The proposed LAR is based on the U.S. Nuclear Regulatory Commission (NRC)-approved Analys is and Measurement Services Corporation (AMS) topical report (TR) AMS-TR-0720R2-A, Online Monitoring Technology to Extend Calibration Intervals of Nuclear Plant Pressure Transmitters (ML21235A493).
REGULATORY AUDIT BASES:
A regulatory audit is a planned license or regulation related activity that includes the examination and evaluation of primarily non-docketed information associated with the LAR. The purpose of this audit was to gain understanding, to verify information, or to identify information that will require docketing to support the basis of the licensing or regulatory decision. This audit was conducted in accordance with NRR Office Instruction LIC-111, Regulatory Audits, Revision 1, dated October 2019 (ML19226A274), with exceptions noted within the audit plan.
The NRC staff performed this audit to support its evaluation of whether the SNC LAR can be approved per Title 10 of the Code of Federal Regulations (10 CFR), Section 50.90, Application for amendment of license, construction permit, or early site permit. The NRC staffs review will be informed by NUREG-0800, Standard Review Plan. The results of this audit are being used to enhance the NRC staffs understanding the licensees proposed OLM LAR.
AUDIT SCOPE:
This audit focused on reviewing the OLM procedures and Vogtle specific OLM reports to confirm that the Vogtle OLM program is being implemented in a manner that is consistent with the NRC approved AMS OLM topical report. A secondary purpose of this audit was to enable the NRC staff to develop a better understanding of the information being used to support the implementation of the Vogtle OLM program.
The licensee and AMS supported the audit by providing remote access to requested reports and by making appropriate staff with detailed knowledge of AMS-TR-0720R1 available for discussions with the NRC staff.
REGULATORY AUDIT ACTIVITIES:
The licensee supported the audit by making appropriate staff available for discussions who have detailed knowledge of AMS-TR-0720 R1, and the principles and bases for the OLM processes discussed in the TR. The following documents were made available for the NRC staffs review on a web-based portal throughout the duration of the audit period.
- 1. AMS Report SNO2201R2, OLM Amenable Tr ansmitters Report for Vogtle Units 1 and 2, December 2022.
- 2. AMS Report SNO2202R1, OLM Analysis Methods and Limits Report for Vogtle Units 1 and 2, December 2022.
- 3. AMS Report SNO2203R1, OLM Drift Monitoring Implementation Report for Vogtle Units 1 and 2, December 2022.
- 4. AMS Procedure OLM2201, Procedure for Online Monitoring Data Retrieval, AMS Corporation, December 2022.
- 5. AMS Procedure OLM2202, Procedure for Performing Online Monitoring Data Qualification and Analysis, AMS Corporation, December 2022.
- 6. AMS Report SNO2204R1, Noise Analysi s Technique Implementation for Vogtle Units 1 and 2, AMS Corporation, December 2022.
- 7. AMS Procedure NPS1501, Procedure for Noise Data Collection from Plant Sensors, AMS Corporation, March 2015.
- 8. AMS Procedure NAR2201, Procedure for Performing Dynamic Failure Mode Assessment Using Noise Analysis, AMS Corporation, December 2022.
Review notes for each of the audited AMS reports are provided below.
SNO2201: OLM AMENABLE TRANSMITTERS REPORT FOR VOGTLE UNITS 1 AND 2
This report addresses Steps 1 through 6 of Section 11.1.1 of the TR for the transmitters in Vogtle Units 1 and 2 that are included in the OLM program.
The report identifies groups of Pressure, Level and Flow Transmitters for each unit that qualify to be entered into the Vogtle OLM program.
The NRC staff notes that for Steam Generator Level Wide Range Loop transmitters, the OLM program will compare these transmitter signals to the narrow range level transmitters associated with each steam generator in order to accomplish OLM.
The NRC staff also noted that Table 3.35 identifies a transmitter that was not included in the AMS-TR-0720 topical report as being amenable to OLM. This transmitter model was different from all other transmitters measuring in the group. The licensee responded to this comment by explaining that this transmitter had been replaced with a newer model than the other Auxiliary Feedwater flow transmitters.
The NRC held an audit meeting with SNC on February 29 to discuss transmitter model amenability to OLM. During this meeting, the licensee and AMS explained that the transmitter model number was correct and that a justification for including this transmitter into the OLM program would be added to the SN2201 report.
The NRC staff reviewed the revised report and c onfirmed that the process for including instruments into OLM was consistent with the AMS-TR-0720 topical report.
SN02202: OLM Analysis Methods and Limits Report
This report documents OLM implementation steps 7 and 8 of Section 11.1.1 of the TR.
Step 7 - Identify Data Analysis Methods Step 8 - Establish OLM Limits
The NRC staff observed that transmitter groups with greater numbers of sensors have higher OLM limits. More transmitters in a group result in smaller Process Estimate Uncertainty (PEU).
The NRC staff also noted that the formula for calculating ECEU on page 7 of this report, Equation 2.6 seems to have an error in one of the terms of the equation. This was later confirmed to be a typographical error and was corrected in a revision to the report.
SG WR Level note: Each Steam Generator Level Wide Range transmitter is compared with the other four Steam Generator Level Narrow Range transmitters which are more accurate than the wide range level transmitter, so this service is considered as having five redundant sensors. The four Steam Generator Level Narrow Range are scaled into the wide range percent (%) scaling for the uncertainty calculations.
A table was provided in the report which provides summary data for all of the transmitter groups.
The NRC staff noted a calculation discrepancy in one of the transmitter groups. The results of the uncertainty calculations seemed to be different than the results documented in the report.
This discrepancy was discussed with the licensee and AMS during the audit call on February 23, 2023. The licensee subsequently responded by providing an update to the report SNO2202R0 which will include an explanation that one of the terms used in the calculation was intentionally excluded. A justification for modifying the calculations will also be added to the report.
The NRC staff reviewed the revised report and confir med that corrections and justifications for deviations from the AMS-TR-0720 topical report described above were provided.
SN02203: OLM Drift Monitoring Implementation Report
Purpose:
This document provides the steps that must be followed to implement OLM for transmitter drift monitoring in accordance with the U.S Nuclear Regulatory Commission (NRC)-
approved methodology developed by Analysis and Measurement Services Corporation (AMS) in Topical Report (TR) AMS-TR-0720R2-A, Online Monitoring Technology to Extend Calibration Intervals of Nuclear Plant Pressure Transmitters.
The steps described in this document are intended to be repeated during each operating cycle in order to identify transmitters to be calibrated. A total of eleven (11) steps must be performed each operating cycle to perform transmitter drift monitoring with OLM and report the results.
A description is provided of AMS software that is used to retrieve data from the plants historian.
This software ensures that the OLM data for each sensor is synchronized before OLM analysis is performed.
Another software tool is described which perform s calibration reduction. This software performs OLM analysis of data from pressure, level, and flow transmitters in nuclear facilities.
The report also describes a software tool which allows users to enter manual transmitter calibration information and calculate backstop intervals for each group of redundant sensors.
This document is primarily a plan for conducting these activities on a continuing bases for Vogtle once the OLM program is in place. It is not a report of current transmitter drift monitoring or drift data analysis activities having been perform ed. Vogtle, Units 1 or 2, data is provided in the report and the report does not include results of assessment or report of transmitters to be calibrated, though it established the processes for these activities to be performed when the OLM program is in place.
SN02204: NOISE ANALYSIS TECHNIQUE IMPLEMENTATION FOR VOGTLE UNITS 1 AND 2
This document provides the steps that must be followed to implement noise analysis for assessment of transmitter dynamic failure modes. The steps described in this document are intended to be repeated during each operating cycle for a minimum of one transmitter on a staggered basis in each redundant group which has a response time requirement to identify its dynamic failure modes.
The process involves Six (6) steps that are taken at each operating cycle at Vogtle, Units 1 and 2, to perform dynamic failure mode assessment of transmitters.
- 1. Select qualified noise data acquisition equipment,
- 2. Connect noise data acquisition equipment to plant signals,
- 3. Collect and store data for noise analysis,
- 4. Screen data for artifacts and anomalies,
- 5. Perform Data analysis, and
- 6. Review and document results.
The appendices of this document provide a listing of the transmitters to be included for OLM.
The document does not provide time response requirements of the Vogtle transmitters that are to be included in the OLM program.
OLM2201: PROCEDURE FOR ONLINE MONITORING DATA RETRIEVAL (9p)
This is a test procedure for retrieving OLM data from the plant historian using the AMS Bridge software. It is not a Vogtle specific document, so it does not describe any of the Vogtle data archival systems. It provides general steps that are followed when retrieving OLM data.
OLM2202: PROCEDURE FOR PERFORMING ONLINE MONITORING DATA QUALIFICATION AND ANALYSIS
This document outlines the general steps that are followed when performing OLM data analysis.
It is not a Vogtle specific document, so it does not describe any of the Vogtle data archival systems or provide any actual analysis of Vogtle specific data.
NPS1501: PROCEDURE FOR NOISE DATA COLLECTION FROM PLANT SENSORS
This procedure provides guidelines for the collection of noise data to determine the dynamic performance characteristics of sensors and systems in nuclear power plants and other processes. It is not a Vogtle-specific document, so it does not provide any actual noise data from Vogtle.
This procedure is used for online data acquisition from a wide variety of sensors and systems including the Vogtle pressure transmitters in the OLM program while the plant is operating at any mode that provides adequate signal amplitudes for analysis. Because the noise tests are passive and do not create any disturbance to plant operation, the data acquisition can be performed with the plant at steady state, gradual coast down, or during start-up conditions.
Under some circumstances sensors connected to inactive processes may also be tested by disconnecting them from the process and subjecting them to simulated process signals which contain electronically produced noise.
NAR2201: PROCEDURE FOR PERFORMING DYNAMIC FAILURE MODE ASSESSMENT USING NOISE ANALYSIS
This procedure provides general guidelines fo r performing dynamic failure mode assessment using the noise analysis method. It is not a Vogtle -specific document, so it does not provide any actual Vogtle noise data or analyses results.
Package: ML23081A059 Audit Summary: ML23080A281 Audit Plan: ML23011A274 OFFICE NRR/DORL/LPLII-1/PM NRR/DORL/LPLII-1 /LA NRR/DSS/STSB/BC NAME JLamb KGoldstein VCusumano DATE 03/21/2023 03/22/2023 03/25/2023 OFFICE NRR/DEX/EICB/BC NRR/DORL/LPII-1/BC NRR/DORL/LPII-1/PM NAME MWaters MMarkley JLamb DATE 03/26/2023 03/27/2023 03/27/2023