IR 05000424/2024002

Integrated Inspection Report 05000424/2024002 and 05000425/2024002

ML24205A003
Person / Time
Site:	Vogtle
Issue date:	07/29/2024
From:	Alan Blamey Division Reactor Projects II
To:	Coleman J Southern Nuclear Operating Co
References
IR 2024002
Download: ML24205A003 (1)

Text

SUBJECT:

VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000424/2024002 AND 05000425/2024002

Dear Jamie Coleman:

On June 30, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Vogtle Electric Generating Plant, Units 1 and 2. On July 11, 2024, the NRC inspectors discussed the results of this inspection with J. Weissinger, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at Vogtle Electric Generating Plant, Units 1 and 2.

If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; and the NRC Resident Inspector at Vogtle Electric Generating Plant, Units 1 and 2.

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 Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.July 29, 2024

Sincerely, Alan J. Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket Nos. 05000424 and 05000425 License Nos. NPF-68 and NPF-81

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000424 and 05000425

License Numbers: NPF-68 and NPF-81

Report Numbers: 05000424/2024002 and 05000425/2024002

Licensee: Southern Nuclear Operating Company, Inc.

Facility: Vogtle Electric Generating Plant, Units 1 and 2

Location: Waynesboro, GA

Inspection Dates: April 01, 2024, to June 30, 2024

Inspectors: S. Battenfield, Operations Engineer J. Bell, Senior Health Physicist B. Griman, Resident Inspector M. Kennard, Sr. Operations Engineer T. Morrissey, Senior Resident Inspector D. Neal, Health Physicist J. Parent, Resident Inspector J. Tornow, Physical Security Inspector B. Truss, Resident Inspector J. Walker, Sr Emergency Preparedness Inspector

Approved By: Alan J. Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Vogtle Electric Generating Plant, Units 1 and 2, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

Failure to perform adequate surveys to assess doses to members of the public from environmental direct radiation.

Cornerstone Significance Cross-Cutting Report Aspect Section Public Radiation Green [P.6] - Self-71124.07 Safety NCV 05000424,05000425/2024002-01 Assessment Open/Closed The NRC identified a Green non-cited violation (NCV) of Title 10 of the Code of Federal Regulations (10 CFR) 20.1302, Compliance with dose limits for individual members of the public, for the licensee's failure to adequately control and account for transit dose on environmental dosimeters.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 began the inspection period at rated thermal power (RTP). On May 24, 2024, power was reduced to approximately 92 percent RTP for several hours to support main turbine valve testing. The unit remained at or near RTP for the remainder of the inspection period.

Unit 2 began the inspection period at RTP. On May 20, 2024, power was reduced to approximately 93 percent RTP for several hours to support main turbine valve testing. On June 21, 2024, the unit was shut down to Mode 3 to implement repairs on a main feedwater isolation valve. The unit was restarted on June 22, 2024, and returned to RTP on June 23, 2024. The unit remained at or near RTP for the remainder of the inspection period.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

71111.01 - Adverse Weather Protection

Impending Severe Weather Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated licensee readiness for impending adverse weather conditions due to a strong weather front approaching the site on May 9, 2024. The site was under a tornado watch; however, severe winds were not experienced on site.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (3 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Unit 1, train "A" emergency diesel generator (EDG), engineered safeguard 4.16kV (kilovolts) busses (1BA03 and 1AA02), and reserve auxiliary transformers (1A and 1B) while train "B" EDG was out of service (OOS) for a planned outage on April 21-29, 2024

(2) Unit 1, train "B" EDG and turbine-driven auxiliary feedwater (TDAFW) pump while train "A" EDG was OOS for a planned outage on May 5-13, 2024

(3) Unit 1, train "B" residual heat removal (RHR) while train "A" RHR was OOS for a planned outage on June 17, 2024

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Fire zones 49 and 52. Unit 1 trains "A" and "B" auxiliary component cooling water (ACCW) heat exchanger rooms, on April 7, 2024.

(2) Fire zones 94, 95, 107, 108, 120, 121, 173, 174. Unit 2 cable spreading rooms, on May 14, 2024.

(3) Fire zones 94, 95, 173, 174. Unit 1 cable spreading rooms, on June 10, 2024.

(4) Fire zones 36 and 37. Unit 2 trains A and B component cooling water pump rooms, on May 31, 2024.

(5) Fire zones 59, 68, 69, and 75. Unit 1 rod control switchgear rooms, on June 26, 2024.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the main control room while lowering unit 2 power from 32 percent RTP until the unit was placed in Mode 3 by tripping the unit at 18 percent RTP on June 21, 2024; and when the unit was restarted and entered Mode 2 on June 22, 2024. The unit was shut down to repair a hydraulic leak on the loop 3 main feedwater isolation valve actuator.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)

(1) The inspectors observed and evaluated a simulator scenario consisting of a main feedwater pump with high vibrations, a required rapid down power, a steam line break in containment, and a failure of a reactor trip switch to trip the reactor, on May 6, 2024.

(2) The inspectors observed and evaluated a simulator annual exam scenario consisting of a loss of the normal charging pump, a failed open steam generator atmospheric relief valve, and a reactor coolant pump seal failure, on June 11, 2024.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (3 Samples)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) Revision of the ACCW system maintenance rule scope, on April 12, 2024

(2) Unit 2 RHR system, on April 29, 2024

(3) Maintenance rule periodic evaluation (i.e., 10 CFR 50.65(a)(3)) for the period of December 1, 2022, through May 1, 2024

Quality Control (IP Section 03.02) (1 Sample)

The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSCs remain capable of performing its intended function:

(1) Quality control work orders (WOs) completed between April 15 and 26, 2024, and on May 24, 2024; WOs SNC1160196, SNC1170020, SNC1756322, SNC1105679, SNC1017731, SNC1181191, SNC1350907-13, SNC1750971, SNC1298729, SNC956439, SNC1170016, and SNC960479. The WOs were associated with the main control room ventilation, unit 1 train "B" EDG, units 1 and 2 nuclear service cooling water (NSCW) system, and a spent fuel cask.

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:

(1) Unit 1, elevated risk with train "B" EDG OOS for a planned maintenance outage on April 21-29, 2024

(2) Unit 1, elevated risk with train "A" EDG OOS for a planned maintenance outage on May 6-13, 2024

(3) Unit 1, elevated risk with train "A" NSCW system OOS for planned maintenance on June 3, 2024

(4) Unit 2, elevated risk with the "A" EDG OOS due to planned work of the EDG sequencer direct current (DC) power supply, on June 21, 2024

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Condition report (CR) 11066640. Unit 1 accumulator #4 level rising, on April 18, 2024.

(2) CR 11070115. Unit 2 TDAFW driver output, 2VI15133, inconsistent rounds reading, on May 8, 2024.

(3) CR 11074690. Unit 1 "A" EDG loose heat shield bolt, on May 21, 2024.

(4) CR 11080030. Unit 1 main steam isolation valve, 1HV-3016A, dual position indication, on May 29, 2024.

(5) CR 11088209. Unit 1 RHR motor operated valve, 1HV8812A, test trace anomaly in both open and closed stroke directions, on June 27, 2024.

71111.24 - Testing and Maintenance of Equipment Important to Risk

The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:

Post-Maintenance Testing (PMT) (IP Section 03.01) (5 Samples)

(1) Procedure 14430-1, "NSCW Cooling Tower Fans Monthly Test," after planned replacement of unit 1 NSCW fan #3 gearbox, on April 19, 2024; WO SNC1017731

(2) 14804B-2 "Safety Injection Pump Inservice and Response Time Test," after planned maintenance, on April 25, 2024; WO SNC994368

(3) 14980B-1, "Diesel Generator 1B Operability Test," after planned maintenance, on April 29, 2024; WOs SNC1186506, SNC1154315, SNC1170031, SNC11652651

(4) 14980A-1, "Diesel Generator 1A Operability Test," after planned maintenance, on May 13, 2024; WOs SNC1186516, SNC1394018, SNC1159679

(5) 14825-1, "Quarterly Inservice Valve Test," (valves 1HV8812A, 1HV8811A, and 1FV-0610A), and 13011-1, "Residual Heat Removal System," after performing planned maintenance on the unit 1 train A RHR system, on June 18, 2024; WO's SNC1125435, SNC1222420, and SNC1222381

Surveillance Testing (IP Section 03.01) (4 Samples)

(1) Procedure 24710-1, "Nuclear Instrumentation System Power Range Channel 1N43 Channel Calibration," and 24714-1 "Nuclear Instrumentation System Power Range Channel 1N44 Channel Calibration," on May 7, 2024

(2) 14980A-2, "Diesel Generator 2A Operability Test," (fast start), on May 15, 2024

(3) 24395-1, "Auxiliary Feedwater Pump Turbine Speed Control 1P-5180 Channel Calibration," on June 12, 2024

(4) 14925-2, "Power Range Reactor Trip Interlocks 18M ACOT," on June 21, 2024

Inservice Testing (IST) (IP Section 03.01) (1 Sample)

(1) Procedure 14804A-2, "Safety Injection Pump A Inservice and Response Time Tests," (IST portion only), on April 19, 2024

Reactor Coolant System (RCS) Leakage Detection Testing (IP Section 03.01) (1 Sample)

(1) Procedure 14905-1, "RCS Leakage Calculation (Inventory Balance)," on May 1, 2024

71114.01 - Exercise Evaluation

Inspection Review (IP Section 02.01-02.11) (1 Sample)

(1) The inspectors evaluated the biennial emergency plan exercise during the week of May 20, 2024. The simulated scenario began with a design basis loss of coolant accident (LOCA) that met the conditions for declaring an Alert (i.e., emergency classification). As a result of the LOCA, radiation levels in containment continued to rise and when they reached a predetermined value a Site Area Emergency is declared due to loss of the RCS barrier and potential loss of fuel clad barrier.

Sometime later, a safety injection pump experiences a line break causing the plant vent radiation monitor to alarm. This met the conditions for declaring a General Emergency and allowed the offsite response organizations to demonstrate their ability to implement emergency actions.

71114.04 - Emergency Action Level and Emergency Plan Changes

Inspection Review (IP Section 02.01-02.03) (1 Sample)

(1) The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of May 20, 2024. This evaluation does not constitute NRC approval.

71114.06 - Drill Evaluation

Additional Drill and/or Training Evolution (1 Sample)

The inspectors evaluated:

(1) The inspectors observed and evaluated a simulator annual exam scenario consisting of a loss of the normal charging pump, a failed open steam generator atmospheric relief valve, and a reactor coolant pump seal failure, resulting in an Alert emergency declaration and notification to the State of Georgia and surrounding counties, on June 11, 2024.

71114.08 - Exercise Evaluation - Scenario Review

Inspection Review (IP Section 02.01 - 02.04) (1 Sample)

(1) The inspectors reviewed and evaluated (in-office), the proposed scenario for the biennial emergency plan exercise at least 30 days prior to the day of the exercise.

71124.06 - Radioactive Gaseous and Liquid Effluent Treatment

Walkdowns and Observations (IP Section 03.01) (5 Samples)

The inspectors evaluated the following radioactive effluent systems during walkdowns:

(1) Units 1 and 2 plant vent stack particulate, iodine and gas sampling skids 1/2RE-

===12442 and 1/2RE-12444

(2) Units 1 and 2 waste monitor tanks and release flow paths including 1/2RE-0018

(3) Units 1 and 2 turbine building sump flow paths including 1/2RE-0848

(4) Units 1 and 2 containment building purge filter trains and 1/2RE-2565

(5) Fuel handling building effluent rad monitor ARX-2532

Sampling and Analysis (IP Section 03.02)===

Inspectors evaluated the following effluent samples, sampling processes and compensatory samples:

(1) Unit 2 weekly plant vent stack particulate and iodine sampling

(2) Unit 2 monthly plant vent stack gas and tritium sampling

(3) Compensatory flow estimation for inoperable plant vent flow instruments 1FT-12442 and 1FT-12835, December 2022

(4) Air sampler staged at railroad bay entrance

Dose Calculations (IP Section 03.03) (2 Samples)

The inspectors evaluated the following dose calculations:

(1) Liquid waste release permit L-20240501-016-B

(2) Gaseous waste release permit G-20240525-191-B

71124.07 - Radiological Environmental Monitoring Program

Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.

Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the implementation of the licensees Radiological Environmental Monitoring Program.

Groundwater Protection Initiative (GPI) Implementation (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensees implementation of the GPI program to identify incomplete or discontinued program elements.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

BI01: RCS Specific Activity Sample (IP Section 02.10)===

(1) Unit 1 (April 1, 2023, through March 31, 2024)

(2) Unit 2 (April 1, 2023, through March 31, 2024)

BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)

(1) Unit 1 (April 1, 2023, through March 31, 2024)

(2) Unit 2 (April 1, 2023, through March 31, 2024)

PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) September 1, 2023, through June 1, 2024

EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)

(1) April 1, 2023, through March 31, 2024 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)

(1) April 1, 2023, through March 31, 2024

EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)

(1) April 1, 2023, through March 31, 2024

71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends that might be indicative of a more significant safety issue on April 26, 2024.

71153 - Follow Up of Events and Notices of Enforcement Discretion Personnel Performance (IP Section 03.03)

(1) The inspectors evaluated operator and equipment performance when shutting down unit 2 to Mode 3 to repair a main feedwater isolation valve and the subsequent reactor startup, on June 21 - June 22,

INSPECTION RESULTS

Failure to perform adequate surveys to assess doses to members of the public from environmental direct radiation.

Cornerstone Significance Cross-Cutting Report Aspect Section Public Radiation Green [P.6] - Self-71124.07 Safety NCV 05000424,05000425/2024002-01 Assessment Open/Closed The NRC identified a Green non-cited violation (NCV) of 10 CFR 20.1302, Compliance with dose limits for individual members of the public, for the licensee's failure to adequately control and account for transit dose on environmental dosimeters.

Description:

The inspectors performed reviews of the 2023 Annual Radiological Environmental Operating Report (AREOR) report (ADAMS Accession No. ML24131A140)during the week of June 10, 2024. During this review, inspectors observed lower than expected results of direct radiation environmental measurements for dosimeters meant to provide estimates of direct radiation in the environment surrounding the plant.

The inspectors identified that inadequate control of transit correction dosimeters resulted in lower than expected environmental dose measurements reported in the AREOR. Specifically, the licensees process included shipping the transit correction dosimeters to the site and back twice, whereas the field dosimeters were in transit once, thus, effectively doubling transit dose. In addition, the transit correction dosimeters spent several weeks outside of lead shielding on either end of the quarter, waiting to be shipped, while the field dosimeters were in the field. In total, it was determined that the transit correction dosimeters spent up to 60 days per quarter improperly accumulating extraneous background and transit dose, which was then incorrectly subtracted from field dosimeter readings. This results in reported doses in the AREOR that did not adequately represent direct radiation in the environment surrounding the plant. At most locations, the reported environmental radiation levels are substantially lower (10 - 15 mrem) than normal background radiation levels. At some locations, the reported quarterly level is zero (e.g., the background radiation levels at locations V06A, V35B, V08B, etc., whereas normal background radiation levels in the USA ranges from approximately 12 - 25 mrem/quarter). These discrepancies in Attachment 4 of the AREOR indicate that the process for measuring environmental radiation is not being adequately controlled.

Corrective Actions: The licensee captured this issue in their corrective action program and plans to evaluate the process for handling environmental dosimetry and implement necessary changes to produce representative direct radiation measurements in the environment due to plant operations.

Corrective Action References: Condition reports (CRs) 11084945 and 11095542

Performance Assessment:

Performance Deficiency: The inspectors determined that the licensee's failure to adequately control and account for transit dose on environmental dosimeters was a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Program and Process attribute of the Public Radiation Safety cornerstone and adversely affected the cornerstone objective to ensure adequate protection of public health and safety from exposure to radioactive materials released into the public domain as a result of routine civilian nuclear reactor operation. Specifically, not adequately analyzing environmental dosimetry per the Radiological Environmental Monitoring Program (REMP) program degrades the ability to confirm that plant releases are not having an unexpected impact on the environment.

Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix D, Public Radiation Safety SDP. The finding was of very low safety significance (Green) because it was associated with the REMP and no unexpected radiological conditions in the environment were identified.

Cross-Cutting Aspect: P.6 - Self-Assessment: The organization routinely conducts self-critical and objective assessments of its programs and practices. Specifically, during a recent self-assessment, the licensee did not identify that it was not adequately controlling the dose to environmental control radiation dosimeters during transit and storage to ensure the field dose measurements are adequately analyzed and reported.

Enforcement:

Violation: Title 10 CFR 20.1302(a) requires the licensee make or cause to be made, as appropriate, surveys of radiation levels in unrestricted and controlled areas and radioactive materials in effluents released to unrestricted and controlled areas to demonstrate compliance with the dose limits for individual members of the public in 10 CFR 20.1301, "Dose limits for individual members of the public."

Contrary to these requirements, the Vogtle Units 1 and 2 did not adequately analyze data from environmental dosimeters. Specifically, the licensee subtracted incorrectly estimated transit dose from the dose received by environmental field dosimeters resulting in inadequate estimates of environmental radiation doses surrounding the plant to ensure compliance with the dose limits for individual members of the public in 10 CFR 20.1301.

Enforcement Action: This violation is being treated as an NCV, consistent with Section 2.3.2 of the Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• On May 23, 2024, the inspectors presented the emergency preparedness and exercise inspection results to J. Weissinger, Site Vice President (SVP), and other members of the licensee staff.

• On June 14, 2024, the inspectors presented the radiation safety inspection results to J. Weissinger, SVP, and other members of the licensee staff.

• On July 11, 2024, the inspectors presented the integrated inspection results to J. Weissinger, SVP, and other members of the licensee staff.

• On July 24, 2024, the inspectors re-exited the radiation safety inspection results to R. Norris, Plant Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71114.01 Procedures Standard Emergency Plan Annex for Vogtle Electric Rev. 7

Generating Plant Units 3 and 4

NMP-EP-141 Event Classification Rev. 4

NMP-EP-141-003 Vogtle 1 & 2 Emergency Action Levels and Basis (NEI 99-01 Rev. 6

Revision 6)

NMP-EP-141-VEGP Units 1 & 2, EAL Classification Matrix HOT Rev. 4

003-F01 CONDITIONS

NMP-EP-141-VEGP Units 1 & 2, EAL Classification Matrix COLD Rev. 4

003-F02 CONDITIONS

NMP-EP-141-004 Vogtle 3 & 4 Emergency Action Levels and Basis Rev. 4

(Amendments 77 and 76 (Vogtle Electric Generating Plant

Units 3 and 4 LAR 16-002))

NMP-EP-141-VEGP Units 3 & 4, EAL Classification Matrix HOT Rev. 3

004-F01 CONDITIONS

NMP-EP-141-VEGP Units 3 & 4, EAL Classification Matrix COLD Rev. 2

004-F02 CONDITIONS

NMP-EP-142 Emergency Notification Rev. 8

NMP-EP-144 Protective Actions Rev. 11

NMP-EP-147 Offsite Dose Assessment Automated MIDAS Rev. 7

NMP-TR-480 Emergency Response Organization (ERO) Training and Ver. 5.0

Qualifications

71114.04 Miscellaneous FLT-23-008-01 10 CFR 50.54(q) Screening for Emergency Response 12/11/2023

Organization Call Out and Emergency Notification Platform

Changes

FLT-23-008-01 10 CFR 50.54(q) Evaluation for Emergency Response 12/12/2023

Organization Call Out and Emergency Notification Platform

Changes

71114.08 Procedures Standard Emergency Plan Rev. 7

Standard Emergency Plan Annex for Vogtle Electric Rev. 6

Generating Plant Units 1 and 2

71124.06 Corrective Action Condition report Auxiliary building continuous exhaust fan 1 07/27/2022

Documents (CR) 10896886

Inspection Type Designation Description or Title Revision or

Procedure Date

CRs 11083791, CRs for missed effluent instrument reports

11079946,

11079951

Corrective Action CR 11084987 Reporting errors in 2021 and 2023 Annual Radiological 06/14/2024

Documents Effluent Release Reports

Resulting from

Inspection

Miscellaneous Vogtle Units 1&2 Annual Radiological Effluent Reports 2021-2023

Procedures Vogtle 1&2 Offsite Dose Calculation Manual Ver. 36

NMP-GM-002-Corrective Action Program Instructions Ver. 51.0

001

71124.07 Self-Assessments CISA Public Radiological Safety Check-In Self-Assessment pre- 03/06/2024

TE#1134064 NRC Baseline Inspection

71151 Miscellaneous Drill and Exercise Corporate Key ERO Quarterly Participation PI Records 2023-4/9/2024

Participation 2024

Performance

Indicators

Procedures NMP-AD-029 Preparation and Reporting of Regulatory Assessment Ver. 3.2

PI Data and the Monthly Operating Report

NMP-EP-311 SNC Emergency Preparedness Tier 4 PI Ver. 6.0

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