IR 05000424/2021003
| ML21314A588 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/10/2021 |
| From: | Alan Blamey Division Reactor Projects II |
| To: | Gayheart C Southern Nuclear Company |
| References | |
| IR 2021003 | |
| Download: ML21314A588 (25) | |
Text
November 10, 2021
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1&2 - INTEGRATED INSPECTION REPORT 05000424/2021003 AND 05000425/2021003
Dear Ms. Gayheart:
On September 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Vogtle Electric Generating Plant, Units 1&2. On October 22, 2021, the NRC inspectors discussed the results of this inspection with Mr. Jesse Thomas and other members of your staff. The results of this inspection are documented in the enclosed report.
No NRC-identified or self-revealing findings were identified during this inspection.
A licensee-identified violation which was determined to be of very low safety significance is documented in this report. 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&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.
Sincerely
/RA/
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: 05000424/2021003 and 05000425/2021003 Enterprise Identifier: I-2021-003-0011 Licensee: Southern Nuclear Company, Inc.
Facility: Vogtle Electric Generating Plant, Units 1&2 Location: Waynesboro, GA Inspection Dates: July 01, 2021 to September 30, 2021 Inspectors: J. Diaz-Velez, Senior Health Physicist C. Fontana, Emergency Preparedness Inspector J. Hickman, Resident Inspector N. Karlovich, Resident Inspector M. Magyar, Reactor Inspector D. Mas-Penaranda, Resident Inspector T. Morrissey, Senior Construction Inspector A. Nielsen, Senior Health Physicist W. Pursley, Health Physicist C. Safouri, Senior Resident Inspector S. Sanchez, Senior Emergency Preparedness Inspector R. Smith, Senior Resident Inspector J. Walker, Emergency Response 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&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. A licensee-identified non-cited violation is documented in report section: 7115
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period at rated thermal power (RTP). On September 12, 2021, the unit was shutdown for a refueling outage (1R23) and remained shutdown for the remainder of the inspection period.
Unit 2 began the inspection period at RTP. On August 18, 2021, the unit was down powered to 78 percent due to a sodium excursion. The unit was returned to RTP on August 23, 2021 and 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 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.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week, increasing the amount of time on-site as local COVID-19 conditions permitted.
As part of their on-site activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP
===71152, Problem Identification and Resolution, observed risk significant activities; and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on-site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) ===
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of tropical storm Elsa and seasonal hot weather, on July 6, 2021, for the following systems:
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 B centrifugal charging pump (CCP) due to Unit 1 train A CCP out of service for maintenance, on July 14, 2021.
- (2) Unit 1 train B CCP during reduced inventory activities during the Unit 1 refueling outage, on September 14, 2021.
- (3) Unit 1 train B spent fuel pool cooling and purification system following unexpected lowering level in the spent fuel pool, on September 21, 2021.
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 143/161/163, Unit 1 train A EDG and electrical tunnel to control building, on August 31, 2021.
- (2) Fire Zones 107/108/120/121, Unit 1 upper cable spreading room, on September 1, 2021.
- (3) Fire Zones 89/90/159/87/88/93/102/158, Unit 2 level A east and west penetration areas, on September 1, 2021.
- (4) Fire Zones 60/61/64/62/63/82, Unit 2 level B east and west penetration areas, on September 1, 2021.
- (5) Fire Zones 36/37, Unit 2 level A, train A and B component cooling water (CCW)rooms, on September 24, 2021.
71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)
- (1) The inspectors evaluated pressurized water reactor non-destructive testing by reviewing the following examinations from September 12 - 30, 2021:
1. Ultrasonic Testing a. V1 11201-V6-002-W12, Upper Head to 6" Safety Nozzle Weld, ASME Class 1 (reviewed)b. V1 11201-053-4-RB, 16" Pipe to Reducer, ASME Class 1 (reviewed)2. Magnetic Particle Testing a. V1 11201-V6-002-W12, Upper Head to 6" Safety Nozzle Weld, ASME Class 1 (reviewed)3. Visual Examination (VT)a. Reactor vessel closure head outer surface, Bare metal visual exam (reviewed)4. Eddy Current Examination a. Steam Generator 2: ET for tube R42C76 and R50C84 b. Steam Generator 3: ET for tube R41C102 c. Steam Generator 4: ET for tube R14C82 and R16C56 The Inspectors evaluated the licensees boric acid corrosion control program performance.
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 control room during Unit 1 main feedwater regulation valve (MFRV) malfunction, on July 7, 2021.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a simulator scenario consisting of loss of coolant accident with loss of barriers on July 20, 2021.
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) Unit 1 Class 1E 480 VAC, system 1805, (a)(1) evaluation, on August 2, 2021.
- (2) Unit 1 condenser impacts due to cooling tower fill material and wind deflectors degrading vacuum, on August 3, 2021.
- (3) Unit 1 and 2 chemical volume and control system re-scoping, on August 17, 2021.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (8 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 high risk nuclear troubleshooting plan for loop 1 MFRV malfunction, on July 8, 2021.
- (2) Unit 1 elevated risk due to train A nuclear service cooling water (NSCW) fan #2 being declared inoperable, on July 12, 2021.
- (3) Unit 1 train A CCP system outage with planned risk informed completion time, on July 14, 2021.
- (4) Unit 1 and 2 high risk nuclear troubleshooting plan for digital feedwater control ovation feed and steam flow indication adjustment, on July 19, 2021.
- (5) Unit 2 elevated risk due to train B EDG inoperable for planned maintenance, on August 4, 2021.
- (6) Unit 1 yellow shutdown risk for containment due to reactor coolant system not intact and containment equipment hatch being open, on September 14, 2021.
- (7) Unit 2 generator hydrogen leak into stator water cooling system, on September 16, 2021.
- (8) Unit 1 yellow shutdown risk due to cold mid-loop operations, on September 30, 2021.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (10 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 1 train B CCW pump #4 breaker incorrect ground relay setting, on July 5, 2021.
- (2) Unit 1 Loop 1 MFRV malfunction, on July 7, 2021.
- (3) Unit 2 train B NSCW basin level lowering, on July 8, 2021.
- (4) Unit 2 train A safety injection (SI) pump lube oil flow outside of expected limits, on July 14, 2021.
- (5) Unit 1 train B EDG KVAR swinging during surveillance, on July 28, 2021.
- (6) Unit 1 train B CCW pump #2 pump-side inboard bubbler found low after an oil fill, on August 9, 2021.
- (7) Unit 1 train B NSCW fan #3 elevated vibrations, on August 10, 2021.
- (8) Unit 1 train D low voltage bus alarm on 1DD1 during residual heat removal (RHR)isolation valve inverter load test, on September 3, 2021.
- (9) Unit 1 reactor vessel level instrumentation system transmitters failed calibration, on September 18, 2021.
- (10) Unit 1 train A motor driven AFW pump motor stator temperatures rising while feeding steam generators, on September 27, 2021.
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Unit 1 train A EDG mechanical governor modification, on August 26, 2021.
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Unit 1 loop 1 digital feedwater ovation relay electronics module replacement, on July 8, 2021.
- (2) Unit 1 train A spent fuel pool cooling system outage, on July 12, 2021.
- (3) Unit 1 train B SI pump relief valve replacement (1PSV8853B), on July 27, 2021.
- (4) Unit 1 train A CCP system outage, on July 14, 2021.
- (5) Unit 1 train A emergency safety feature chiller system outage, on July 19, 2021.
- (6) Unit 1 train A RHR system outage, on July 21, 2021.
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1) (Partial) The inspectors evaluated refueling outage 1R23 from September 12, 2021, to September 30, 2021. The inspectors completed inspection procedure Sections 03.01.a through 03.01.c.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) 28912B-2 and 28912D-2, 92-Day Unit 2 "B" and "D" Train Safety Related Battery and Charger Inspection and Maintenance, on August 4, 2021.
- (2) 14980A-1 and 14670A-1, Diesel Generator 1A Operability Test and Diesel Generator 1A Hot Restart Test, on August 11, 2021.
- (3) 14722-1, Emergency Core Cooling System to Reactor Water Storage Tank Backleakage In-service Test, on September 18, 2021.
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) 14378-1, Containment Penetration No. 78 Containment Sump Pumps Discharge Local Leak Rate Test, on September 8, 2021.
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) 480V FLEX diesel generator full load test, July 21, 2021.
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.01-02.04) (1 Sample)
- (1) The inspectors evaluated the maintenance and testing of the alert and notification system during the week of August 9, 2021.
71114.03 - Emergency Response Organization Staffing and Augmentation System
Inspection Review (IP Section 02.01-02.02) (1 Sample)
- (1) The inspectors evaluated the readiness of the Emergency Response Organization during the week of August 9, 2021.
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 August 9, 2021. This evaluation does not constitute NRC approval.
71114.05 - Maintenance of Emergency Preparedness
Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
- (1) The inspectors evaluated the maintenance of the emergency preparedness program during the week of August 9,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards during the Unit 1 refueling outage (1R23).
Instructions to Workers (IP Section 03.02) (1 Sample)
The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas.
- (1) The inspectors reviewed the following:
Radiation Work Packages
- Radiation Work Permit (RWP) 21-1303 - Secondary S/Gs - Sludge Lance, FOSAR, Hand Holes on Steam Generators 1, 2, 3, 4
- RWP 21-1400 - Reactor head assembly/assembly
- RWP 21-1612 - Core Exit Thermocouple Connector Upgrade Electronic Alarming Dosimeter Alarms
- RWP 20-2203, 08/31/2020
- RWP 20-2100, 08/24/2020
- RWP 20-2010, 02/18/2021 Labeling of Containers
- Sea Lands in Satellite Radiation Control Area (RCA) outside Unit 1 Equipment Hatch
- Equipment/Tool Boxes inside Unit 1 Containment
- Equipment/Tool Boxes in Satellite RCA outside the Radwaste Processing
Facility Contamination and Radioactive Material Control (IP Section 03.03) (3 Samples)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.
- (1) Observed radiation protection technician (RPT) surveys of potentially contaminated material at Unit 1 equipment hatch during refueling outage 1R23
- (2) Observed RPT surveys of potentially contaminated material at Unit 1 personnel hatch during refueling outage 1R23
- (3) Observed RPT surveys of potentially contaminated material at the RCA exit during refueling outage 1R23
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.
- (1) RWP 21-1400, Reactor head disassembly/assembly
- (3) RWP 21-1303, Secondary steam generator hand holes on steam generator 2 High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (5 Samples)
The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:
- (1) Unit 1 RHR Heat Exchanger room in Unit 1 containment
- (2) Unit 2 reactor building personnel hatch entry
- (3) Unit 1 Recycle Evaporator Feed Demin Valve Gallery
- (4) Unit 1 Spent Resin Sluice Pump
- (5) Unit 1 Waste Evaporator Condensate Demin Valve Gallery Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements during 1R23.
71124.02 - Occupational ALARA Planning and Controls
Radiological Work Planning (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensees radiological work planning.
- (1) ALARA Plan 21-1301, Nozzle dam install/remove
- (2) ALARA Plan 21-1302, Eddy current testing
- (3) ALARA Plan 21-1400, Reactor head disassembly/reassembly
- (4) ALARA Plan 21-1612, Core exit thermocouple upgrade Verification of Dose Estimates and Exposure Tracking Systems (IP Section 03.02) (3 Samples)
The inspectors evaluated dose estimates and exposure tracking.
- (1) Micro ALARA Plan 20-2004, Scaffolding, Post-job ALARA review, 9/23/20
- (3) Daily dose tracking burndown curves, 1R23 refueling outage, 9/13/21 - 9/17/21
Implementation of ALARA and Radiological Work Controls (IP Section 03.03) (2 Samples)
The inspectors reviewed as low as reasonably achievable practices and radiological work controls.
- (1) 1R23 refueling outage, Reactor head disassembly
- (2) 1R23 refueling outage, Reactor head lift
Radiation Worker Performance (IP Section 03.04) (1 Sample)
The inspectors evaluated radiation worker and radiation protection technician performance during:
- (1) 1R23 refueling outage, Reactor head disassembly.
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) Unit 1 and Unit 2, RE-12442A/B/C - Plant Vent Effluent (Particulate, Iodine, and Radiogas) Monitors (Low Range)
- (2) Unit 1 and Unit 2, RE-0018 - Waste Liquid Effluent Monitor
- (3) Unit 1 and Unit 2, RE-0021 - Seam Generator Blowdown Liquid Process Monitor
- (4) Unit 1 RE-12444A/B/C/D/E - Plant Vent Effluent Monitors (Unit 2 RE-124444 observed but was not commissioned for operation yet)
- (5) Unit 1 Auxiliary Building Ventilation System Filter Surveillance (HEPA/Charcoal test)
Sampling and Analysis (IP Section 03.02) (3 Samples)
Inspectors evaluated effluent samples, sampling processes and compensatory samples, as available.
- (1) Permit G-20210617-210B, Unit 1- Containment Release, 06/17/2021
- (2) Permit G-20210619-213-B, Unit 2- Containment Release, 06/19/2021
- (3) Permit L-20200928-079-B, Unit 1- Waste Monitor Tank #12 (sample for OOS Monitor
RE-0018), 09/28/2020 Dose Calculations (IP Section 03.03) (2 Samples)
The inspectors evaluated the following dose calculations:
- (1) Gaseous Permit Release No.: G-20210619-213-B, dated 06/19/2021
- (2) Liquid Permit Release No.: L-20200928-079-B, dated 09/28/2020
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.
GPI Implementation (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees implementation of the Groundwater Protection Initiative program to identify incomplete or discontinued program elements.
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &
Transportation
Radioactive Material Storage (IP Section 03.01)
- (1) Inspectors evaluated the licensees performance in controlling, labeling and securing radioactive materials.
Radioactive Waste System Walkdown (IP Section 03.02) (1 Sample)
- (1) Inspectors walked down accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality.
Waste Characterization and Classification (IP Section 03.03) (2 Samples)
The inspectors evaluated the licensees characterization and classification of radioactive waste.
- (1) 2020 Unit 1 Reactor Coolant System Filters
- (2) 2020 Dry Active Waste (DAW)
Shipping Records (IP Section 03.05) (4 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
- (3) RVRS20-006, Type B, Filters
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS07: High Pressure Injection Systems (IP Section 02.06) ===
- (1) Unit 1 (July 1, 2020 - June 30, 2021)
- (2) Unit 2 (July 1, 2020 - June 30, 2021)
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
- (1) Unit 1 (July 1, 2020 - June 30, 2021)
- (2) Unit 2 (July 1, 2020 - June 30, 2021)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (July 1, 2020 - June 30, 2021)
- (2) Unit 2 (July 1, 2020 - June 30, 2021)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) September 01, 2020 through August 31, 2021 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (2 Samples)
- (1) Unit 1 (June 1, 2019 through August 14, 2021)
- (2) Unit 2 (June 1, 2019 through August 14, 2021)
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) Unit 1 (October 1, 2020, through June 30, 2021)
Unit 2 (October 1, 2020, through June 30, 2021)
EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) Unit 1 (October 1, 2020, through June 30, 2021)
Unit 2 (October 1, 2020, through June 30, 2021)
EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)
- (1) Unit 1 (October 1, 2020, through June 30, 2021)
Unit 2 (October 1, 2020, through June 30, 2021)
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Fire protection program and the licensee's evaluation of multiple spurious operations as it relates to Information Notice 92-18, Condition Report
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71152 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Vogtle Unit 1 & 2 Operating License Condition 2.G requires the licensee to "maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report." The Final Safety Analysis Report, section 9.5.1.3.E.7, requires that one train of equipment and cables be free from fire damage.
Contrary to the above, since March 16, 1987, the licensee has failed to ensure one train of equipment and cables was free from fire damage. Specifically, the licensee identified multiple fire areas and valves that may be impacted by a fire event such that the torque and limit switch is bypassed which results in a stalled motor and potential valve damage.
Significance/Severity: Green. The inspectors assessed the significance of the finding using Appendix F, Fire Protection and Post - Fire Safe Shutdown SDP. Utilizing IMC 0609, Appendix F, the inspectors determined the finding was of very low safety significance (Green)because the performance deficiency constituted a low degradation of safe shutdown systems. The inspectors utilized risk insights and evaluations from the licensee to determine that the licensee is not crediting the repositioning of these valves in their internal events probabilistic risk assessment.
Corrective Action References: Condition Report
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On August 12, 2021, the inspectors presented the Emergency Preparedness Program inspection results to Mr. Drayton Pitts, Site Vice President, and other members of the licensee staff.
- On August 19, 2021, the inspectors presented the RP Public Radiation Safety and Transportation inspection results to Mr. Jesse Thomas, Plant Manager, and other members of the licensee staff.
- On September 17, 2021, the inspectors presented the RP Occupational Baseline inspection results to Mr. Drayton Pitts and other members of the licensee staff.
- On October 22, 2021, the inspectors presented the integrated inspection results to Mr.
Jesse Thomas and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.01 Miscellaneous NMP-GM-025 Seasonal Readiness Process 7.0
71111.01 Procedures NMP-OS-017 Severe Weather 3.0
71111.04 Corrective Action Condition Reports 10828286, 10829033
Documents
71111.04 Drawings 1X4DB116-1 P & I Diagram - Chemical & Volume Control System - 53.0
System No. 1208
71111.04 Drawings 1X4DB116-2 P&I Diagram - Chemical & Volume Control System - System 37.0
No. 1208
71111.04 Drawings 1X4DB116-2 P&I Diagram - Chemical & Volume Control System - System 37.0
No. 1208
71111.04 Drawings 1X4DB130 P & I Diagram Spent Fuel Pool Cooling and Purification 50.0
System
71111.04 Procedures 12006RFO-1 Unit Cooldown to Cold Shutdown for Refueling 3.0
71111.04 Procedures 12007-C Refueling Operations (Mode 5 to Mode 6) 85.0
71111.04 Procedures 13719-1 Spent Fuel Cooling and Purification System 58.0
71111.05 Corrective Action Condition Reports 10824371, 10824367, 10824089
Documents
Resulting from
Inspection
71111.05 Fire Plans 92736-2 Zone 36 - Auxiliary Building - Level A, CCW Pumps, Train A 5.0
Firefighting Preplan
71111.05 Fire Plans 92737-2 Zone 37 - Auxiliary Building - Level A, CCW Pumps, Train B 3.12
Firefighting Preplan
71111.05 Fire Plans 92760-2 Zone 60 - Control Building - Level B Fire Fighting Preplan 1.0
71111.05 Fire Plans 92761-2 Zone 61 - Control Building - Level B Fire Fighting Preplan 1.1
71111.05 Fire Plans 92762-2 Zone 62 - Control Building - Level B Fire Fighting Preplan 2.0
71111.05 Fire Plans 92763-2 Zone 63 - Control Building - Level B Fire Fighting Preplan 0.2
71111.05 Fire Plans 92764-2 Zone 64 - Control Building - Level B Fire Fighting Preplan 1.1
71111.05 Fire Plans 92782-2 Zone 82 - Control Building - Level B Fire Fighting Preplan 1.2
71111.05 Fire Plans 92787-2 Zone 87 - Control Building - Level A Fire Fighting Preplan 2.2
71111.05 Fire Plans 92788-2 Zone 88 - Control Building - Level A Fire Fighting Preplan 2.2
71111.05 Fire Plans 92789-2 Zone 89 - Control Building - Level A Fire Fighting Preplan 3.1
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.05 Fire Plans 92790-2 Zone 90 - Control Building - Level A Fire Fighting Preplan 2.2
71111.05 Fire Plans 92793-2 Zone 93 - Control Building Level A Fire Fighting Preplan 3.2
71111.05 Fire Plans 92802-2 Zone 102 - Control Building - Level A Fire Fighting Preplan 2.2
71111.05 Fire Plans 92807-1 Zone 107 - Control Building - Levels 1 and 2 Fire Fighting 5.1
Preplan
71111.05 Fire Plans 92808-1 Zone 108 - Control Building - Levels 1 and 2 Fire Fighting 5.1
Preplan
71111.05 Fire Plans 92820-1 Zone 120 - Control Building - Level 2 Fire Fighting Preplan 7
71111.05 Fire Plans 92843-1 Zone 143 - Diesel Generator Building Electrical Tunnel A - 3.1
Level B Fire Fighting Preplan
71111.05 Fire Plans 92858-2 Zone 158 - Control Building - Level A Fire Fighting Preplan 1.2
71111.05 Fire Plans 92859-2 Zone 159 - Control Building - Level A Fire Fighting Preplan 1.2
71111.05 Fire Plans 92861-1 Zone 161 - Diesel Generator Building Fire Fighting Preplan 4
71111.05 Fire Plans 92863-1 Zone 163 - Diesel Generator Building - Train A DFO Day 3.2
Tank Fire Fighting Preplan
71111.05 Procedures NMP-ES-035-014 Fleet Transient Combustible Controls 5.0
71111.11Q Drawings 1X4DB168-3 P&I Diagram - Condensate & Feedwater System - System 36.0
No. 1305
71111.11Q Miscellaneous Vogtle 1-2 Off Year Exercise Scenario Book 07/20/2021
71111.11Q Procedures 13506-C Digital Feedwater Control System 10.1
71111.11Q Procedures 18016-1 Condensate and F/W Malfunction 3.0
71111.12 Corrective Action Condition Reports 10817516, 10827191, 10827787, 10827797
Documents
71111.12 Corrective Action Corrective Action 279589
Documents Reports
71111.12 Corrective Action Technical 1063056, 1063653
Documents Evaluations
71111.12 Corrective Action Condition Reports 10830116
Documents
Resulting from
Inspection
71111.12 Miscellaneous 2021-0907 Maintenance Rule Expert Panel Meeting 09/07/2021
71111.12 Miscellaneous 2021-20210209 Maintenance Rule Expert Panel Meeting #2021-20210209 02/09/2021
71111.12 Miscellaneous RBD-V12-5069- 10 CFR 50.69 System Categorization - Chemical & Volume 3
Inspection Type Designation Description or Title Revision or
Procedure Date
208 Control
71111.12 Miscellaneous SPX Vogtle Unit 1 Y-Y Axis Wind Wall Design Changes 08/11/2021
WU1/235.003948
71111.12 Procedures NMP-ES-027 Maintenance Rule Program 10.4
71111.13 Corrective Action Condition Reports 10827508
Documents
71111.13 Corrective Action Condition Reports 10817902, 10827146
Documents
Resulting from
Inspection
71111.13 Miscellaneous Crew Fleet Learning CR# 10827146 - Gap in Equipment 09/14/2021
Hatch Closure Crew Performance
71111.13 Miscellaneous Vogtle 1&2 Sitewide Stand Down 09/15/2021
71111.13 Miscellaneous Daily Status Report 07/12/2021
71111.13 Miscellaneous Daily Status Report 07/13/2021
71111.13 Miscellaneous eSOMS Logs 07/12-13/2021
71111.13 Miscellaneous Phoenix Unit 1 RICT 07/13/2021
71111.13 Miscellaneous Daily Plan Status 07/14/2021
71111.13 Miscellaneous Phoenix Unit 1 RICT 07/14/2021
71111.13 Miscellaneous Plan of the Day 07/14/2021
71111.13 Miscellaneous 10032-C Outage Risk Assessment Monitoring - Mode 6 Midloop & 09/30/2021
SIP B Tagout
71111.13 Miscellaneous 1093810 ODMI U2 Main Generator Stator Cooling Hydrogen Leak 09/30/2021
71111.13 Procedures 10032-C Outage Risk Assessment Monitoring 18.1
71111.13 Procedures 13506-C Digital Feedwater Control System 10.1
71111.13 Procedures 27504-C Equipment Hatch Emergency Closure 23.1
71111.13 Procedures NMP-GM-031- Online Maintenance Rule (a)(4) Risk Calculations 6.0
001
71111.13 Procedures NMP-OS-010 Protected Train/Division and Protected Equipment Program 8.1
71111.13 Work Orders SNC1166760, SNC929820
71111.15 Corrective Action Condition Reports 10817682, 10817917, 10818748, 10818906, 10824580,
Documents 10811118, 10830224, 10831207, 10818342, 10810094,
10800430, 10800442, 10812379, 10816162, 10632909,
10828263
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.15 Corrective Action Technical 1091790
Documents Evaluations
71111.15 Corrective Action Condition Reports 10828667, 10829369, 10812916
Documents
Resulting from
Inspection
71111.15 Drawings 1X3D-AA-G01A Main One Line - Class 1E 125V DC and 120V Vital AC 11.0
Systems
71111.15 Drawings 1X3D-AA-G02A One Line Diagram - 120V AC Class 1E Vital Instrument Dist 30.0
Pnls 1AY1A, 1BY1B, 1CY1A & 1DY1B
71111.15 Drawings 1X3D-AA-G02C 120V AC Class 1E Vital Instr Distr Pnls 1-1807-03-V15 & 17.0
V16
71111.15 Drawings 1X3D-AA-M08A- Unit 1 Relaying Data 1.0
041
71111.15 Drawings 1X3D-AA-MO8A- Unit 1 Relaying Data 2.0
040
71111.15 Drawings 1X4DB168-3 P&I Diagram - Condensate & Feedwater System - System 36.0
No. 1305
71111.15 Drawings 2X4DB134 P & I Diagram - Nuclear Service Cooling Water System - 31.0
System No. 1202
71111.15 Miscellaneous 1B NSCW Fan #3 Vibration Review 08/10/2021
71111.15 Miscellaneous Deficiency Card RVLIS exceeds static pressure shift 04/07/1990
190-193
71111.15 Miscellaneous Westinghouse Reactor Vessel Level Instrumentation System Calibration 03/14/2011
Technical Bulletin Anomalies Due to Air In-leakage
11-6
71111.15 Procedures 13506-C Digital Feedwater Control System 10.1
71111.15 Procedures 18016-1 Condensate and F/W Malfunction 3.0
71111.15 Procedures 23200-CD1 Unit 1 Data Sheets for Westinghouse Type CO Overcurrent 7.4
Relay Calibration
71111.15 Procedures 24676-1 Reactor Vessel Level Transmitter Calibration 18.0
71111.15 Procedures 83308-C Testing of Safety - Related NSCW System Coolers 33.3
71111.15 Procedures NMP-ES-074-005 Fleet Vibration Instruction 3.0
71111.15 Work Orders SNC1171219, SNC1180726, SNC1180760, SNC1180768,
Inspection Type Designation Description or Title Revision or
Procedure Date
SNC1180788, SNC1137391, SNC1165949, SNC1166760,
SNC781853
71111.18 Corrective Action Condition Reports 10826061
Documents
Resulting from
Inspection
71111.18 Engineering SNC953976 Unit 1 Emergency Diesel Generator Governor DCP 2
Changes
71111.18 Miscellaneous X4AK01A Specifications for EDG speed control upgrade 4
71111.18 Work Orders SNC957852
71111.19 Corrective Action Condition Reports 10812285
Documents
Resulting from
Inspection
71111.19 Procedures 13506-C Digital Feedwater Control System 10.1
71111.19 Work Orders SNC1165582, SNC1166760, SNC589229, SNC884948,
SNC916714, SNC972822, SNC981336, SNC690133,
SNC986323
71111.20 Corrective Action Condition Reports 10828893, 10829090, 10827822, 10828664, 10828688,
Documents 10827473, 10827232, 10827820, 10828197, 10827823
71111.20 Corrective Action Condition Reports 10829871
Documents
Resulting from
Inspection
71111.22 Corrective Action Condition Reports 10825778
Documents
71111.22 Corrective Action Condition Reports 10825453, 10826051
Documents
Resulting from
Inspection
71111.22 Procedures 14378-1 Containment Penetration No. 78 Containment Sump Pumps 12.1
Discharge Local Leak Rate Test
71111.22 Procedures 14670A-1 Diesel Generator 1A Hot Restart Test 1.6
71111.22 Procedures 14980A-1 Diesel Generator 1A Operability Test 32
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.22 Procedures 28912B-2 92-Day Unit 2 "B" Train Safety Related Battery and Charger 4.0
Inspection and Maintenance
71111.22 Procedures 28912D-2 92-Day Unit 2 "D" Train Safety Related Battery and Charger 4.0
Inspection and Maintenance
71111.22 Work Orders SNC1119986, SNC1135974, SNC1136137
71124.01 Corrective Action 10828031
Documents
Resulting from
Inspection
71124.01 Corrective Action 10828073
Documents
Resulting from
Inspection
71124.01 Corrective Action 10828077
Documents
Resulting from
Inspection
71124.01 Corrective Action 10828078
Documents
Resulting from
Inspection
71124.01 Procedures NMP-HP-108 Issuance, Use, and Collection of Personnel Dosimetry Version 2.11
71124.01 Procedures NMP-HP-108-002 Use of EDE (Effective Dose Equivalent) Methodologies Revision 3.2
71124.02 ALARA Plans 21-1004 Micro ALARA Plan, Installation and Removal of Scaffolding
71124.02 Corrective Action CR 10809912
Documents
71124.02 Corrective Action 10828079
Documents
Resulting from
Inspection
71124.02 Corrective Action 10828081
Documents
Resulting from
Inspection
Inspection Type Designation Description or Title Revision or
Procedure Date
71124.02 Corrective Action 10828082
Documents
Resulting from
Inspection
71124.02 Corrective Action 10828083
Documents
Resulting from
Inspection
71124.02 Procedures NMP-AD-041 Cobalt Reduction Program Version 2.0
71124.02 Procedures NMP-HP-204 ALARA Planning and Job Review Version 9.2
71124.06 Corrective Action CRs: 10799784, Corrective Action Reports Various
Documents 10777270,
10769896,
10766114,
10736963,
10736160,
10731997, and
10730328
71124.06 Procedures 33040-C Compositing Samples Weekly, Monthly, Quarterly Rev. 22
71124.06 Procedures 36015-OEMS RADIOACTIVE LIQUID EFFLUENT RELEASE PERMIT Rev. 10.1
GENERATION AND DATA CONTROL COMPUTER
(OpenEMS) METHOD
71124.06 Procedures 37420-1 Sampling of the Unit One Radioactive Liquid Waste Rev. 5.2
Management System
71124.06 Procedures 37420-2 Sampling of the Unit Two Radioactive Liquid Waste Rev. 4.3
Management System
71124.06 Procedures 37420-C Sampling of the Common Radioactive Liquid Waste Rev. 5.2
Management System
71124.07 Corrective Action CR 10821631
Documents
Resulting from
Inspection
71124.07 Corrective Action CR 10821633
Documents
Inspection Type Designation Description or Title Revision or
Procedure Date
Resulting from
Inspection
71124.07 Corrective Action CR 10821634
Documents
Resulting from
Inspection
71124.07 Corrective Action CR 10821637
Documents
Resulting from
Inspection
71124.07 Corrective Action CR 10822624
Documents
Resulting from
Inspection
71124.07 Miscellaneous 2020 VEGP 2020 Plant Vogtle Annual Radiological Environmental
AREOR Operating Report
71124.07 Procedures A19N5001 Radwaste Transfer Tunnel Visual Inspection Revision 2
71124.07 Procedures NMP-EN-002 Radiological Groundwater Protection Program Version 9.3
71124.07 Radiation RIS #221251 Radwaste Transfer Tunnel 12/14/2018
Surveys
71124.07 Work Orders SNC 102645 Waste Water Transfer Tunnel Visual Inspection 05/19/2021
71124.08 Corrective Action CR 10821331
Documents
Resulting from
Inspection
71124.08 Corrective Action CR 10821339
Documents
Resulting from
Inspection
71124.08 Procedures NMP-HP-408 Solid Radioactive Waste Scaling Factor Determination and Version 2.0
Implementation and Waste Classification
71151 Miscellaneous Unit 1 and Unit 2 MSPI Heat Removal System Derivation
Report - Unavailability Index from July 2020 - June 2021
71151 Miscellaneous Unit 1 and Unit 2 MSPI Heat Removal System Derivation
Inspection Type Designation Description or Title Revision or
Procedure Date
Report - Unreliability Index from July 2020 - June 2021
71151 Miscellaneous Unit 1 and Unit 2 MSPI for High Pressure Injection Systems
from July 2020 - June 2021
71151 Miscellaneous Unit 1 and Unit 2 MSPI High Pressure Injection System
Derivation Report - Unavailability Index from July 2020 -
June 2021
71151 Miscellaneous Unit 1 and Unit 2 MSPI High Pressure Injection System
Derivation Report - Unreliability Index from July 2020 - June
21
71151 Miscellaneous Unit 1 and Unit 2 MSPI for RHR from July 2020 - June 2021
71151 Miscellaneous Unit 1 and Unit 2 MSPI RHR Derivation Report -
Unavailability Index from July 2020 - June 2021
71151 Miscellaneous Unit 1 and Unit 2 MSPI RHR Derivation Report - Unreliability
Index from July 2020 - June 2021
71151 Miscellaneous MSPI Indicator Margin Remaining in Green from July 2020 -
June 2021
71151 Miscellaneous Unit 1 and Unit 2 MSPI for AFW from July 2020 - June 2021
71152 Calculations RBA-21-003-V IN 92-18 FPRA Impacts Rev. 1
71152 Corrective Action Condition Reports 10818441
Documents
2