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:
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
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)
===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)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
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
NMP-GM-025
Seasonal Readiness Process
7.0
Procedures
NMP-OS-017
Severe Weather
3.0
Corrective Action
Documents
Condition Reports
10828286, 10829033
Drawings
1X4DB116-1
P & I Diagram - Chemical & Volume Control System -
System No. 1208
53.0
Drawings
1X4DB116-2
P&I Diagram - Chemical & Volume Control System - System
No. 1208
37.0
Drawings
1X4DB116-2
P&I Diagram - Chemical & Volume Control System - System
No. 1208
37.0
Drawings
1X4DB130
P & I Diagram Spent Fuel Pool Cooling and Purification
System
50.0
Procedures
2006RFO-1
Unit Cooldown to Cold Shutdown for Refueling
3.0
Procedures
2007-C
Refueling Operations (Mode 5 to Mode 6)
85.0
Procedures
13719-1
Spent Fuel Cooling and Purification System
58.0
Corrective Action
Documents
Resulting from
Inspection
Condition Reports
10824371, 10824367, 10824089
Fire Plans
2736-2
Zone 36 - Auxiliary Building - Level A, CCW Pumps, Train A
Firefighting Preplan
5.0
Fire Plans
2737-2
Zone 37 - Auxiliary Building - Level A, CCW Pumps, Train B
Firefighting Preplan
3.12
Fire Plans
2760-2
Zone 60 - Control Building - Level B Fire Fighting Preplan
1.0
Fire Plans
2761-2
Zone 61 - Control Building - Level B Fire Fighting Preplan
1.1
Fire Plans
2762-2
Zone 62 - Control Building - Level B Fire Fighting Preplan
2.0
Fire Plans
2763-2
Zone 63 - Control Building - Level B Fire Fighting Preplan
0.2
Fire Plans
2764-2
Zone 64 - Control Building - Level B Fire Fighting Preplan
1.1
Fire Plans
2782-2
Zone 82 - Control Building - Level B Fire Fighting Preplan
1.2
Fire Plans
2787-2
Zone 87 - Control Building - Level A Fire Fighting Preplan
2.2
Fire Plans
2788-2
Zone 88 - Control Building - Level A Fire Fighting Preplan
2.2
Fire Plans
2789-2
Zone 89 - Control Building - Level A Fire Fighting Preplan
3.1
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Fire Plans
2790-2
Zone 90 - Control Building - Level A Fire Fighting Preplan
2.2
Fire Plans
2793-2
Zone 93 - Control Building Level A Fire Fighting Preplan
3.2
Fire Plans
2802-2
Zone 102 - Control Building - Level A Fire Fighting Preplan
2.2
Fire Plans
2807-1
Zone 107 - Control Building - Levels 1 and 2 Fire Fighting
Preplan
5.1
Fire Plans
2808-1
Zone 108 - Control Building - Levels 1 and 2 Fire Fighting
Preplan
5.1
Fire Plans
2820-1
Zone 120 - Control Building - Level 2 Fire Fighting Preplan
Fire Plans
2843-1
Zone 143 - Diesel Generator Building Electrical Tunnel A -
Level B Fire Fighting Preplan
3.1
Fire Plans
2858-2
Zone 158 - Control Building - Level A Fire Fighting Preplan
1.2
Fire Plans
2859-2
Zone 159 - Control Building - Level A Fire Fighting Preplan
1.2
Fire Plans
2861-1
Zone 161 - Diesel Generator Building Fire Fighting Preplan
Fire Plans
2863-1
Zone 163 - Diesel Generator Building - Train A DFO Day
Tank Fire Fighting Preplan
3.2
Procedures
NMP-ES-035-014
Fleet Transient Combustible Controls
5.0
71111.11Q Drawings
1X4DB168-3
P&I Diagram - Condensate & Feedwater System - System
No. 1305
36.0
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
Corrective Action
Documents
Condition Reports
10817516, 10827191, 10827787, 10827797
Corrective Action
Documents
Corrective Action
Reports
279589
Corrective Action
Documents
Technical
Evaluations
1063056, 1063653
Corrective Action
Documents
Resulting from
Inspection
Condition Reports
10830116
Miscellaneous
21-0907
Maintenance Rule Expert Panel Meeting
09/07/2021
Miscellaneous
21-20210209
Maintenance Rule Expert Panel Meeting #2021-20210209
2/09/2021
Miscellaneous
RBD-V12-5069-
CFR 50.69 System Categorization - Chemical & Volume
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
208
Control
Miscellaneous
SPX
WU1/235.003948
Vogtle Unit 1 Y-Y Axis Wind Wall Design Changes
08/11/2021
Procedures
NMP-ES-027
10.4
Corrective Action
Documents
Condition Reports
10827508
Corrective Action
Documents
Resulting from
Inspection
Condition Reports
10817902, 10827146
Miscellaneous
Crew Fleet Learning CR# 10827146 - Gap in Equipment
Hatch Closure Crew Performance
09/14/2021
Miscellaneous
Vogtle 1&2 Sitewide Stand Down
09/15/2021
Miscellaneous
Daily Status Report
07/12/2021
Miscellaneous
Daily Status Report
07/13/2021
Miscellaneous
eSOMS Logs 07/12-13/2021
Miscellaneous
Phoenix Unit 1 RICT
07/13/2021
Miscellaneous
Daily Plan Status
07/14/2021
Miscellaneous
Phoenix Unit 1 RICT
07/14/2021
Miscellaneous
Plan of the Day
07/14/2021
Miscellaneous
10032-C
Outage Risk Assessment Monitoring - Mode 6 Midloop &
SIP B Tagout
09/30/2021
Miscellaneous
1093810
ODMI U2 Main Generator Stator Cooling Hydrogen Leak
09/30/2021
Procedures
10032-C
Outage Risk Assessment Monitoring
18.1
Procedures
13506-C
Digital Feedwater Control System
10.1
Procedures
27504-C
Equipment Hatch Emergency Closure
23.1
Procedures
NMP-GM-031-
001
Online Maintenance Rule (a)(4) Risk Calculations
6.0
Procedures
NMP-OS-010
Protected Train/Division and Protected Equipment Program
8.1
Work Orders
SNC1166760, SNC929820
Corrective Action
Documents
Condition Reports
10817682, 10817917, 10818748, 10818906, 10824580,
10811118, 10830224, 10831207, 10818342, 10810094,
10800430, 10800442, 10812379, 10816162, 10632909,
10828263
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Technical
Evaluations
1091790
Corrective Action
Documents
Resulting from
Inspection
Condition Reports
10828667, 10829369, 10812916
Drawings
Main One Line - Class 1E 125V DC and 120V Vital AC
Systems
11.0
Drawings
One Line Diagram - 120V AC Class 1E Vital Instrument Dist
Pnls 1AY1A, 1BY1B, 1CY1A & 1DY1B
30.0
Drawings
20V AC Class 1E Vital Instr Distr Pnls 1-1807-03-V15 &
V16
17.0
Drawings
041
Unit 1 Relaying Data
1.0
Drawings
040
Unit 1 Relaying Data
2.0
Drawings
1X4DB168-3
P&I Diagram - Condensate & Feedwater System - System
No. 1305
36.0
Drawings
2X4DB134
P & I Diagram - Nuclear Service Cooling Water System -
System No. 1202
31.0
Miscellaneous
1B NSCW Fan #3 Vibration Review
08/10/2021
Miscellaneous
Deficiency Card
190-193
RVLIS exceeds static pressure shift
04/07/1990
Miscellaneous
Technical Bulletin
11-6
Reactor Vessel Level Instrumentation System Calibration
Anomalies Due to Air In-leakage
03/14/2011
Procedures
13506-C
Digital Feedwater Control System
10.1
Procedures
18016-1
Condensate and F/W Malfunction
3.0
Procedures
200-CD1
Unit 1 Data Sheets for Westinghouse Type CO Overcurrent
Relay Calibration
7.4
Procedures
24676-1
Reactor Vessel Level Transmitter Calibration
18.0
Procedures
83308-C
Testing of Safety - Related NSCW System Coolers
33.3
Procedures
NMP-ES-074-005
Fleet Vibration Instruction
3.0
Work Orders
SNC1171219, SNC1180726, SNC1180760, SNC1180768,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SNC1180788, SNC1137391, SNC1165949, SNC1166760,
SNC781853
Corrective Action
Documents
Resulting from
Inspection
Condition Reports
10826061
Engineering
Changes
SNC953976
Unit 1 Emergency Diesel Generator Governor DCP
Miscellaneous
X4AK01A
Specifications for EDG speed control upgrade
Work Orders
SNC957852
Corrective Action
Documents
Resulting from
Inspection
Condition Reports
10812285
Procedures
13506-C
Digital Feedwater Control System
10.1
Work Orders
SNC1165582, SNC1166760, SNC589229, SNC884948,
SNC916714, SNC972822, SNC981336, SNC690133,
SNC986323
Corrective Action
Documents
Condition Reports
10828893, 10829090, 10827822, 10828664, 10828688,
10827473, 10827232, 10827820, 10828197, 10827823
Corrective Action
Documents
Resulting from
Inspection
Condition Reports
10829871
Corrective Action
Documents
Condition Reports
10825778
Corrective Action
Documents
Resulting from
Inspection
Condition Reports
10825453, 10826051
Procedures
14378-1
Containment Penetration No. 78 Containment Sump Pumps
Discharge Local Leak Rate Test
2.1
Procedures
14670A-1
Diesel Generator 1A Hot Restart Test
1.6
Procedures
14980A-1
Diesel Generator 1A Operability Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
28912B-2
2-Day Unit 2 "B" Train Safety Related Battery and Charger
Inspection and Maintenance
4.0
Procedures
28912D-2
2-Day Unit 2 "D" Train Safety Related Battery and Charger
Inspection and Maintenance
4.0
Work Orders
SNC1119986, SNC1135974, SNC1136137
Corrective Action
Documents
Resulting from
Inspection
10828031
Corrective Action
Documents
Resulting from
Inspection
10828073
Corrective Action
Documents
Resulting from
Inspection
10828077
Corrective Action
Documents
Resulting from
Inspection
10828078
Procedures
NMP-HP-108
Issuance, Use, and Collection of Personnel Dosimetry
Version 2.11
Procedures
NMP-HP-108-002
Use of EDE (Effective Dose Equivalent) Methodologies
Revision 3.2
ALARA Plans
21-1004
Micro ALARA Plan, Installation and Removal of Scaffolding
Corrective Action
Documents
CR 10809912
Corrective Action
Documents
Resulting from
Inspection
10828079
Corrective Action
Documents
Resulting from
Inspection
10828081
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
10828082
Corrective Action
Documents
Resulting from
Inspection
10828083
Procedures
NMP-AD-041
Cobalt Reduction Program
Version 2.0
Procedures
NMP-HP-204
ALARA Planning and Job Review
Version 9.2
Corrective Action
Documents
CRs: 10799784,
10777270,
10769896,
10766114,
10736963,
10736160,
10731997, and
10730328
Corrective Action Reports
Various
Procedures
33040-C
Compositing Samples Weekly, Monthly, Quarterly
Rev. 22
Procedures
36015-OEMS
RADIOACTIVE LIQUID EFFLUENT RELEASE PERMIT
GENERATION AND DATA CONTROL COMPUTER
(OpenEMS) METHOD
Rev. 10.1
Procedures
37420-1
Sampling of the Unit One Radioactive Liquid Waste
Management System
Rev. 5.2
Procedures
37420-2
Sampling of the Unit Two Radioactive Liquid Waste
Management System
Rev. 4.3
Procedures
37420-C
Sampling of the Common Radioactive Liquid Waste
Management System
Rev. 5.2
Corrective Action
Documents
Resulting from
Inspection
CR 10821631
Corrective Action
Documents
CR 10821633
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Resulting from
Inspection
Corrective Action
Documents
Resulting from
Inspection
CR 10821634
Corrective Action
Documents
Resulting from
Inspection
CR 10821637
Corrective Action
Documents
Resulting from
Inspection
CR 10822624
Miscellaneous
20 VEGP
20 Plant Vogtle Annual Radiological Environmental
Operating Report
Procedures
A19N5001
Radwaste Transfer Tunnel Visual Inspection
Revision 2
Procedures
NMP-EN-002
Radiological Groundwater Protection Program
Version 9.3
Radiation
Surveys
RIS #221251
Radwaste Transfer Tunnel
2/14/2018
Work Orders
SNC 102645
Waste Water Transfer Tunnel Visual Inspection
05/19/2021
Corrective Action
Documents
Resulting from
Inspection
CR 10821331
Corrective Action
Documents
Resulting from
Inspection
CR 10821339
Procedures
NMP-HP-408
Solid Radioactive Waste Scaling Factor Determination and
Implementation and Waste Classification
Version 2.0
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
Procedure
Type
Designation
Description or Title
Revision or
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
Calculations
RBA-21-003-V
IN 92-18 FPRA Impacts
Rev. 1
Corrective Action
Documents
Condition Reports
10818441