ML22304A181
| ML22304A181 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/08/2022 |
| From: | Bradley Davis NRC/RGN-II/DCI/CIB2 |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| IR 2022011 | |
| Download: ML22304A181 (17) | |
Text
Ms. Jamie Coleman Regulatory Affairs Director Southern Nuclear Operating Company 7825 River Road, BIN 63031 Waynesboro, GA 30830
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNIT 3 - NRC INITIAL TEST PROGRAM AND OPERATIONAL PROGRAMS INTEGRATED INSPECTION REPORT 05200025/2022011
Dear Ms. Coleman:
On September 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Vogtle Electric Generating Plant, Unit 3. The enclosed inspection report documents the inspection results, which the inspectors discussed on October 18, 2022, with Mr.
Glen Chick, Vogtle 3 & 4 Executive Vice President, and other members of your staff.
The inspection examined a sample of construction activities conducted under your Combined License (COL) as it relates to safety and compliance with the Commissions rules and regulations and with the conditions of these documents. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Based on the results of this inspection, no findings of significance were identified.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system ADAMS.November 8, 2022 J. Coleman 2 ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Should you have any questions concerning this letter, please contact us.
Sincerely, Bradley J. Davis, Chief Construction Inspection Branch 2 Division of Construction Oversight Docket No. 5200025 License No. NPF-91
Enclosure:
As stated w/attachment: Supplemental Information cc w/ encl: Distribution via LISTSERV Signed by Davis, Bradley on 11/08/22
ML22304A181 X Non-Sensitive X Publicly Available X SUNSI Review Sensitive Non-Publicly Available
OFFICE RII/DCO RII/DCO RII/DCO RII/DCO NAME J. Eargle J. Parent C. Even B. Davis DATE 11/3/2022 11/8/2022 10/31/2022 11/8/2022
U.S. NUCLEAR REGULATORY COMMISSION Region II
Docket Number: 5200025
License Number: NPF-91
Report Number: 05200025/2022011
Licensee: Southern Nuclear Company, Inc.
Facility: Vogtle Unit 3 Combined License
Location: Waynesboro, GA
Inspection Dates: August 4, 2022 through September 30, 2022
Inspectors: J. Eargle, Sr. Resident Inspector-Testing, Division of Construction Oversight J. Parent, Resident Inspector, Division of Construction Oversight S. Downey, Sr. Reactor Inspector, Division of Reactor Safety M. Magyar, Reactor Inspector, Division of Reactor Safety T. Scarbrough, Sr. Mechanical Engineer, Nuclear Reactor Regulation B. Kellner, Sr. Health Physicist, Division of Reactor Safety A. Nielsen, Sr. Health Physicist, Division of Reactor Safety J. Diaz-Velez, Sr. Health Physicist, Division of Reactor Safety
Approved by: Bradley J. Davis, Chief Construction Inspection Branch 2 Division of Construction Oversight
Enclosure
SUMMARY
OF FINDINGS
Inspection Report (IR) 05200025/2022011; August 4, 2022, through September 30, 2022; Vogtle Unit 3 Combined License, initial test program and operational programs integrated inspection report.
This report covers an eight-week period of announced inspections of preoperational test program, and operational program inspections by resident and regional inspectors. The significance of most findings are indicated by their color (Green, White, Yellow, or Red), using Inspection Manual Chapter (IMC) 0609, Significance Determination Process. Cross-cutting aspects are determined using IMC 0310, Aspects Withing the Cross-Cutting Areas. All violations of NRC requirements are dispositioned in accordance with the NRCs Enforcement Policy. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in IMC 2515, Light Water Reactor Inspection Program Operations Phase.
A. NRC-Identified and Self Revealed Findings
None
B. Licensee-Identified Violations
None
2 REPORT DETAILS
Summary of Plant Construction Status
During this report period for Unit 3, the licensee continued to perform the remaining testing needed to transition Mode 6 required systems to operations. The licensee also performed surveillance testing to ensure system and component operability/functionality to support fuel load and plant transition to Mode 6.
- 3. OPERATIONAL READINESS
Cornerstones: Operational Programs
IMC 2504, Construction Inspection Program - Inspection of Construction and Operational Programs
3P01 Motor-Operated Valves
Inspection Procedure (IP) 73758 - Attachment 1. Motor Operated Valves
- a. Inspection Scope
The inspectors performed the following activities related to the development of the in-service test programs for pumps, valves, and dynamic restraints that will perform safety-related functions at Vogtle Units 3 & 4:
The inspectors reviewed the motor-operated valve (MOV) program and supporting documents for Vogtle Units 3 & 4. In addition to the main MOV program document, the inspectors reviewed MOV documents describing the regulatory scoping process, design-basis setpoint determination, performance trending and margin management, database control and design data datasheet activities, diagnostic testing procedure, and program implementation checklist.
The inspectors also reviewed documents describing the self-assessment process, equipment reliability process, scoping and importance determination for equipment reliability, preventive maintenance implementation and continuing equipment reliability improvement, engineering program health reports, development and control of procedures, general engineering guidance, and regulatory scope and program plan. In addition, the inspectors reviewed Technical Evaluation Quality Record 600002643, COMTA 1709, for determination of the test frequency for verification of MOV capability to meet its design-basis functional requirements.
- b. Findings
No findings were identified.
3P02 Preservice Inspection
3 IP 73757-02.01 - General Records Review IP 73757-02.02 - ASME Class 1 Records Review
- a. Inspection Scope
The inspectors evaluated the AP1000 pressurized water reactor non-destructive testing by reviewing the following examinations to verify if they satisfied the American Society of Mechanical Engineers Code,Section III, 1998 Edition with Addenda 1999 through 2000:
Category B-F o SV3-SGA-Nozzle A-201-96A, SG1A Outlet Nozzle to RCP1A Weld, Class 1 o SV3-RPV-26A-103-SE, DVI Safe-End DM Weld, Class 1 o SV3-PRHRHX-5/1-05, Inlet Nozzle-to-Safe End Weld, Class 1 Category B-J o SV3-PXS-PLW-012-FW1, Pipe to Pipe, Class 1 o SV3-PXS-PLW-025-SW3, Pipe to Pipe, Class 1
- b. Findings
No findings were identified.
3P03 Preservice Testing
IP 73758 - Appendix A. Review of Functional Design, Qualification, and PST/IST Programs for Pumps, Valves, and Dynamic Restraints
- a. Inspection Scope
4 The inspectors performed the following activities related to the development of the in-service test programs for pumps, valves, and dynamic restraints that will perform safety-related functions at Vogtle Units 3 & 4:
The inspectors reviewed the MOV program and supporting documents for Vogtle Units 3 & 4. In addition to the main MOV program document, the inspectors reviewed MOV documents describing the regulatory scoping process, design-basis setpoint determination, performance trending and margin management, database control and design data datasheet activities, diagnostic testing procedure, and program implementation checklist. The inspectors also reviewed documents describing the self-assessment process, equipment reliability process, scoping and importance determination for equipment reliability, preventive maintenance implementation and continuing equipment reliability improvement, engineering program health reports, development and control of procedures, general engineering guidance, and regulatory scope and program plan. In addition, the inspectors reviewed Technical Evaluation Quality Record 600002643, COMTA 1709, for determination of the test frequency for verification of MOV capability to meet its design-basis functional requirements.
- b. Findings
No findings were identified.
3P04 Radiation Protection
83535 - Part 52, Control of Radioactive Materials and Contamination, Surveys, and Monitoring
- a. Inspection Scope
Minimum Inspection Requirement B: Area Monitor and Airborne Monitor Readiness
The inspectors evaluated the operational readiness of area radiation and airborne radioactivity monitors including containment high range radiation monitors, main control room ventilation, and area radiation monitors to verify if the licensee was prepared to monitor changing radiological conditions. The inspectors observed instruments installed in various locations, reviewed calibration procedures, surveillance testing schedules, surveillance test procedures, and testing records to determine whether the licensee was in compliance with Title 10 of the Code of Federal Regulations (10 CFR), Part 20, the Offsite Dose Calculation Manual (ODCM), and Chapters 11 and 12 of the Updated Final Safety Analysis Report (UFSAR).
- b. Findings
No findings were identified.
3P05 Process and Effluent Monitoring
83746 - Part 52, Offsite Dose Calculation Manual
5
- a. Inspection Scope
Minimum Inspection Requirement B: Effluent Monitor Readiness
The effluent monitors described in the ODCM were evaluated for readiness, on a sampling basis, under IP 84528, Part 52, Liquid Waste Management Program and IP 84529, Part 52, Gaseous Waste Management System.
Minimum Inspection Requirement C: Laboratory Instruments
The inspectors evaluated the operational readiness of laboratory instruments, including a liquid scintillation detector and a high-purity germanium gamma spectroscopy system, to verify that the licensee is prepared to analyze samples of liquid and gaseous effluents.
The inspectors observed the instruments installed in the count room and reviewed procedures and testing records to determine whether the licensee was in compliance with 10 CFR 20, the ODCM, and Chapters 11 and 12 of the UFSAR.
- b. Findings
No findings were identified.
3P06 Process and Effluent Monitoring
84527 - Part 52, Solid Waste Management Program
- a. Inspection Scope
Minimum Inspection Requirement A: Operational Procedures
The inspectors evaluated a solid radioactive waste system (WSS) procedure to verify adequate protocols for safe system operation had been established. The inspectors also reviewed a preventative maintenance (PM) surveillance frequency spreadsheet to verify establishment of a PM program. The following procedure was reviewed against system design documents and the requirements of UFSAR chapter 11.
3-WSS-SOP-001, Solid Radwaste System, Version (Ver.) E=0.4
Minimum Inspection Requirement C: Pre-Operational Testing
The inspectors evaluated the following initial test procedure against WSS system design documents and the requirements of UFSAR, Chapters 11 and 14, to verify if adequate testing protocols had been established.
3-WSS-ITPP-501, TPC for Solid Radwaste System Pre-Op Test, Ver. 2.0
Minimum Inspection Requirement D: Waste Solidification
The inspectors observed the following vendor-provided mobile resin processing equipment to verify receipt of equipment necessary to package wet radioactive waste.
6 The following equipment was evaluated for physical condition and compared against the requirements of the licensees process control program for solidification of wet waste and Chapter 11 of the UFSAR.
Resin fill head Resin dewatering apparatus Multiple steel storage/shipping liners
The inspectors also reviewed vendor testing of the solidification/dewatering process and a vendor-supplied liner inspection checklist to determine if they satisfied the requirements of the process control program and Chapter 11 of the UFSAR.
- b. Findings
No findings were identified.
3P07 Process and Effluent Monitoring
84528 - Part 52, Liquid Waste Management Program
- a. Inspection Scope
Minimum Inspection Requirement A: Operational Procedures
The inspectors evaluated liquid radioactive waste system (WLS) procedures to verify if adequate protocols for safe system operation had been established. The inspectors also reviewed a PM surveillance frequency spreadsheet to verify if a PM program had been established. The following procedures were reviewed to determine if they satisfied the system design documents, the ODCM, and the UFSAR, Chapter 11.
3-WLS-SOP-001, Liquid Radwaste System, Ver. 4.0 B-WLS-CEF-001, Monitoring of the Radioactive Liquid Waste Management System, Ver. 1.0 B-WLS-CEF-002, Chemistry Control of the Liquid Radwaste System (WLS), Ver.
2.0 B-WLS-MIS-005, Liquid Radwaste Discharge Liquid Process Rad Monitor WLS-JS-229 Channel Functional Test and Channel Calibration, Unreleased Revision (Rev.) 1.0 [Quarterly Channel Functional Check]
Minimum Inspection Requirement D: Pre-operational Testing
The inspectors reviewed the following document showing completion of system testing and transition of the WLS to Operations control. The document was evaluated to verify if the system satisfied the requirements of UFSAR, Chapters 11 and 14.
SV3-WLS, Liquid Radwaste System, Transition to Operations 10/9/2022
- b. Findings
No findings were identified.
7 3P08 Process and Effluent Monitoring
84529 - Part 52, Gaseous Waste Management System
Minimum Inspection Requirement A: Operational Procedures
The inspectors evaluated gaseous radioactive waste system (WGS) procedures to verify if adequate protocols for safe system operation had been established. The inspectors also reviewed a PM surveillance frequency spreadsheet to verify if the licensee had established a PM program. The following procedures were reviewed to determine whether they were in accordance with the system design documents, the ODCM, and Chapter 11 of the UFSAR.
3-WGS-SOP-001, Gaseous Radwaste System, Ver. 2.0 B-WGS-CEF-001, Monitoring of the Gaseous Radwaste System, Ver. 1.0
Minimum Inspection Requirement D: Pre-operational Testing
Selected pre-operational testing records were reviewed to verify operational readiness of selected components in the WGS and VFS systems. This included high efficiency particulate air/charcoal filter bank testing, WGS automatic isolation valve interlock testing, a procedure for air duct flow testing of the plant vent, and documentation showing completion of system testing and transition of WGS to operations control. The documents were evaluated against the requirements of the UFSAR, Chapters 11 and 14.
VFS Train A HEPA/charcoal testing, 11/8/21 VFS Train B HEPA/charcoal testing, 11/10/21 ITAAC Technical Report SV3-WGS-ITR-800454, Unit 3 WGS provides non safety-related function of controlling the releases of radioactive materials in gaseous effluents, ITAAC 2.3.11.03b, NRC Index Number 454 SV3-WLS, Liquid Radwaste System, Transition to Operations, 10/9/2022 3-RMS-ITPP-501, Radiation Monitoring System, Ver. 2.0
Minimum Inspection Requirement E: Effluent Monitors
The inspectors evaluated primary/transfer calibration documents, calibration source certificates, site acceptance testing records, and a procedure for the establishment of alarm setpoints for gaseous effluent monitors to verify if accurate detector alignment, calibration source traceability, and compliance with 10 CFR Part 20, the ODCM, and Chapter 11 of the UFSAR. The inspectors noted that plant operators in the main control room were able to obtain indications from the radiation monitoring system for installed plant radiation monitors that were operational. The following effluent monitors were selected for review:
WGS-JE-RE017, Gaseous Radwaste Discharge VFS-JE-RE101, Plant Vent (Particulate)
VFS-JE-RE102, Plant Vent (Iodine)
VFS-JE-RE103, Plant Vent (Gaseous - Normal range)
8 VFS-JE-RE104A, Plant Vent (Gaseous - Mid range)
VFS-JE-RE104B, Plant Vent (Gaseous - High range)
- b. Findings
No findings were identified.
- 4. OTHER INSPECTION RESULTS
4OA6 Meetings, Including Exit
.1 Exit Meeting.
On October 18, 2022, the inspectors presented the inspection results to Mr. Glen Chick, Vogtle 3 & 4 Executive Vice President, and other licensee and contractor staff members.
Proprietary information was reviewed during the inspection period but was not included in the inspection report.
9 SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensees and Contractor Personnel
A. Nix, NI Manager M. Hickox, Test Support Manager C. Alexander, Milestone Manager S. Boyle, Milestone Manager D. Pagan-Diaz, ITP Turnover. Manager J. Olsen, NI Supervisor W. Garrett, SNC Licensing Supervisor C. Castell, SNC Licensing Engineer N. Chapman, SNC Licensing Engineer R. McKay, ITP Test Engineer S. Turner, ITP Test Engineer G. Weaver, ITP Test Engineer R. Nicoletto, ITP Test Engineer W. Pipkins, ITP Test Engineer D. Melton, ITP Test Engineer R. Espara, ITP Test Engineer J. Clark, ITP Test Engineer K. Morgan, ITP Test Engineer J. Dixon, SNC RP C. Hartfield, SNC RP K. Stacy, SNC Licensing
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Item Number Type Status Description
None
LIST OF DOCUMENTS REVIEWED
- 3. OPERATIONAL READINESS
Section 3P01 Corrective Action Documents Condition Report 10902228 for revision to NMP-ES-038-GL01, 8/19/2022 Technical Evaluations Quality Record 600002643, COMTA 1709, 3/21/2019
Procedures NMP-AP-001, Development and Control of Southern Nuclear Procedures, Rev. 21.2 NMP-ES-001, Equipment Reliability Process Description, Rev. 11 NMP-ES-005, Scoping and Importance Determination for Equipment Reliability, Rev. 18.2
10 NMP-ES-006, Preventive Maintenance Implementation and Continuing Equipment Reliability Improvement, Rev. 13 NMP-ES-009-002, Engineering Programs - Heath Reports and Notebooks, Rev. 24.3 NMP-ES-017, Motor-Operated Valve Program, Rev. 11 NMP-ES-017-001, Motor-Operated Valve (MOV) Regulatory Scoping Process, Rev. 7 NMP-ES-017-001-V34, MOV Regulatory Scope and Program Plan, Rev. 1 NMP-ES-017-002, Motor-Operated Valve Design Basis Setpoint Determination, Rev. 7 NMP-ES-017-003, Motor-Operated Valve Performance Trending and Margin Management, Rev.
6 NMP-ES-017-006, Motor-Operated Valve Design Database Control and Design Data Sheet Activities, Rev. 2 NMP-ES-017-021, MOV Diagnostic Procedure for VOTES Infinity, Rev. 2.4 NMP-ES-038-GL01, General Engineering Guidance, Rev. 17.1 NMP-GM-003, Self-Assessment and Benchmark Procedure, Rev. 33 NMP-GM-003-F19, Focused Area Self-Assessment (FASA) Plan and Report, Rev. 5 Program Implementation Checklist B-GEN-ADM-001-F06, Motor Operated Valve Program, Rev.
1
Section 3P02 PT Summary Report 19-002863 PT Summary Report 045400 PT Summary Report 054750 UT Summary Report 054750 UT Summary Report 045400 UT Summary Report 19-002892 (0)
UT Summary Report 19-002893 (45)
UT Summary Report 19-002894 (45)
UT Summary Report 19-002895 (45)
UT Summary Report 19-002896 (60)
WDI-PJF-1324121-FSR-001, Rev 0 WDI-STD-1060 (PDI-ISI-254-DVI-SE), "Remote Inservice Examination of Direct Vessel Injection (DVI) Nozzle to Safe End and Safe End to Pipe Welds", Rev 2 WDI-PJF-1322201-FSR-001, "Steam Generator to Reactor Coolant Pump Casing Suction Welds, Rev 0 WDI-STD-1075, "Automated Ultrasonic Examination of the AP1000 Steam Generator Outlet Nozzle to Reactor Coolant Pump Suction Nozzle Weld, Rev 2 WDI-STD-1077, Remote Eddy Current Examination of the AP1000 SG Outlet Nozzles to Cast Stainless Steel RCP Casing Suction Nozzle Weld, Rev 0 WDI-STD-1086, "Liquid Penetrant Examination for Pre-Service Inspections", Rev 4 WDI-STD-1091, "Ultrasonic Examination of Dissimilar Metal Welds in Accordance with PDI-UT-10 for the AP1000 Pre-Service Inspections", Rev 2 WDI-STD-1091-S6, "Site Specific Configuration Ultrasonic Examination of the AP1000 PRHR Heat Exchanger Inlet and Outlet Nozzle to Safe End Welds", Rev 0 WDI-SSP-1308, Preservice Material Thickness and Contour Acquisition - AP1000, Rev 2
11 WDI-STD-1099, Generic AP1000 Pre-Service Inspection Procedure for Ultrasonic Examination of Austenitic Pipe Welds in Accordance with PDI-UT-2, Rev 4
Section 3P03 Corrective Action Documents Condition Report 10902228 for revision to NMP-ES-038-GL01, 8/19/2022 Technical Evaluations Quality Record 600002643, COMTA 1709, 3/21/2019
Procedures NMP-AP-001, Development and Control of Southern Nuclear Procedures, Rev. 21.2 NMP-ES-001, Equipment Reliability Process Description, Rev. 11 NMP-ES-005, Scoping and Importance Determination for Equipment Reliability, Rev. 18.2 NMP-ES-006, Preventive Maintenance Implementation and Continuing Equipment Reliability Improvement, Rev. 13 NMP-ES-009-002, Engineering Programs - Heath Reports and Notebooks, Rev. 24.3 NMP-ES-017, Motor-Operated Valve Program, Rev. 11 NMP-ES-017-001, Motor-Operated Valve (MOV) Regulatory Scoping Process, Rev. 7 NMP-ES-017-001-V34, MOV Regulatory Scope and Program Plan, Rev. 1 NMP-ES-017-002, Motor-Operated Valve Design Basis Setpoint Determination, Rev. 7 NMP-ES-017-003, Motor-Operated Valve Performance Trending and Margin Management, Rev.
6 NMP-ES-017-006, Motor-Operated Valve Design Database Control and Design Data Sheet Activities, Rev. 2 NMP-ES-017-021, MOV Diagnostic Procedure for VOTES Infinity, Rev. 2.4 NMP-ES-038-GL01, General Engineering Guidance, Rev. 17.1 NMP-GM-003, Self-Assessment and Benchmark Procedure, Rev. 33 NMP-GM-003-F19, Focused Area Self-Assessment (FASA) Plan and Report, Rev. 5 Program Implementation Checklist B-GEN-ADM-001-F06, Motor Operated Valve Program, Rev.
1
Section 3P04 B-GEN-CHM-011, Post Accident Sampling Contingency Plan, Version 2.1 B-GEN-PLMC-041, Operation of The Main Control Room Supply Air Duct Monitors, Version B=0.1 [Operational Draft]
B-GEN-PLMC-118, Chemistry Technical Specification Surveillance Performance Coordination, Version A=0.0 [Operational Draft]
B-PSS-CHM-001, Operation of Containment Atmosphere Radiation Monitor, Version 1.0 B-PSS-CHM-002, Operation of The Primary Sampling System Gaseous Sample Radiation Monitor, Version 1.0 B-PXS-CHM-001, Operation of the Containment High Range Radiation Monitors, Version 1.0 B-RMS-CHM-001, Operation of Non-Safety Related Area Radiation Monitors, Version 1.0 B-RMS-ADM-001, Surveillance of the Radiation Monitoring System, Version 1.0 B-103-RPP-001, Radiation Protection Department - Mode Change Requirements, Version 1.1 NMP-GM-006-002, Surveillance Program, Version 4.4 ODCM Related Radiation Monitor Surveillance Schedule Cross-Reference Spreadsheet, undated Vogtle 3 RMS Completion Status Spreadsheet, 9/13/2022 Work Order (WO) WO 1053693, Site Acceptance Test (SAT) for RMS-JS-11, Chemistry Laboratory, 03/09/2022
12 WO 1053695, Site Acceptance Test (SAT) for RMS-JS-13, Rail Car Bay/Filter Storage Area (Auxiliary Building Loading Bay), 02/21/2022 WO 1053700, Site Acceptance Test (SAT) for RMS-JS-20, Fuel Handling Area Radiation Monitor 2, 06/08/2022 3-GOP-301, Mode Change Checklists, Version J=0.9 [Operational Draft]
3-PXS-OTS-16-001, Division A - Containment High Range Radiation Monitor Calibration, Revision 1.0 [3-PXS-JS-160]
3-PXS-OTS-16-002, Division B - Containment High Range Radiation Monitor Calibration, Revision 1.0 [3-PXS-JS-161]
3-PXS-OTS-16-003, Division C - Containment High Range Radiation Monitor Calibration, Revision 1.0 [3-PXS-JS-162]
3-PXS-OTS-16-004, Division D - Containment High Range Radiation Monitor Calibration, Revision 1.0 [3-PXS-JS-163]
3-RMS-ARP-001, Radiation Monitoring System, Version D=0.3 [Operational Draft]
3-RMS-SOP-001, Radiation Monitoring System, Version D=0.3 [Operational Draft]
3-VBS-OTS-16-002, Division C MCR Duct Radiation Detector Calibration and Response Time Test, Revision 1.0 [3-VBS-RE002B]
Section 3P05 NMP-CH-021, Chemistry Counting Room Program, Ver. 1.0 NMP-CH-021-001, Gamma Spectroscopy using Apex, Ver. 1.0 NMP-CH-021-003, Calibration of the Gamma Spectroscopy System using Apex, Ver. 3.1 NMP-CH-021-005, Operation of Liquid Scintillation Systems, Ver. 4.0 NMP-CH-716, Performing Tritium Analysis, Ver. 1.0 Quality Control Check Results, Liquid Scintillation Detector Serial # 2200880, 4/14/22 - 9/1/22 Calibration Record, Liquid Scintillation Detector Serial # 2200880, 2/24/2022 Calibration Certificate for Unquenched Liquid Scintillation Source Set, Serial Number(s):
114317, 114337, and 111564, 11/12/2019 Calibration Certificate for Unquenched Liquid Scintillation Source Set, Serial Number(s):
120432, 121786, and 121772, 04/05/2022 Efficiency Calibration and Minimum Detectable Activity Reports, Multiple Geometries, Gamma Detector #15, 12/22/21 - 2/15/22 Calibration Certificate for Gamma Source Set, Serial Numbers: 1516, 1517, 1520, 1523, 10/1/2020
Section 3P08 Primary Calibration Report 03608961, Radiation Monitoring System, Plant Vent Normal Range Primary Calibration Report E-255-1167, Radiation Monitoring System, Plant Vent Mid and High Range SV3-RMS-VQQ-043, Plant Vent Monitoring System - Normal Range, Transfer Calibration SV3-VFS-TOW-1049623, Component Test, Plant Vent JS-01 Normal Range SV3-VFS-TOW-1049629, Component Test, Plant Vent JS-02 Accident Range SV3-WGS-TOW-1075671, Component Test, WGS JS-17 SV3-WGS-TOW-1273152, Perform Vendor Specified Alignment of WGS JS-17 B-ADM-CEF-001, Gaseous Effluent Monitor Setup for Releases, Ver. 1.0
LIST OF ACRONYMS
10 CFR Title 10 of the Code of Federal Regulations COL Combined License
13 IMC Inspection Manual Chapter IP inspection procedure IR inspection report MOV motor operated valve NRC Nuclear Regulatory Commission ODCM offsite dose calculation manual PARS Publicly Available Records PM preventative maintenance Rev. revision UFSAR Updated Final Safety Analysis Report Ver. Version WGS gaseous radioactive waste system WLS liquid radioactive waste system WSS solid radioactive waste system
14