IR 05000424/2020003
| ML20318A004 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/13/2020 |
| From: | Alan Blamey NRC/RGN-II/DRP/RPB2 |
| To: | Gayheart C Southern Nuclear Operating Co |
| References | |
| IR 2020003 | |
| Download: ML20318A004 (27) | |
Text
November 13, 2020
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 & 2 - INTEGRATED INSPECTION REPORT 05000424/2020003 AND 05000425/2020003
Dear Ms. Gayheart:
On September 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Vogtle Electric Generating Plant, Units 1 & 2. On October 22, 2020, the NRC inspectors discussed the results of this inspection with Mr. Drayton Pitts 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:
05000424/2020003 and 05000425/2020003
Enterprise Identifier: I-2020-003-0050
Licensee:
Southern Nuclear Operating Co., Inc.
Facility:
Vogtle Electric Generating Plant, Units 1 & 2
Location:
Waynesboro, GA
Inspection Dates:
July 1, 2020 to September 30, 2020
Inspectors:
A. Beasten, PhD, Acting Senior Resident Inspector
P. Cooper, Reactor Inspector
S. Downey, Senior Reactor Inspector
W. Pursley, Health Physicist
C. Safouri, Resident Inspector
S. Temple, Resident 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: 71124.0
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000425/2019-003-00 LER 2019-003-00 for Vogtle Electric Generating Plant,
Unit 2, Transformer Deenergization Results in Emergency Diesel Generator and Auxiliary Feedwater Systems Starting 71153 Closed
PLANT STATUS
Unit 1 operated at or near Rated Thermal Power (RTP) for the entire inspection period.
Unit 2 operated at or near RTP until the unit was shutdown for planned refueling outage cycle 21 (2R21) on August 16, 2020. The unit was returned to RTP on September 14, 2020 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 teleworking 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 onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; 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 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
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 Train 'B' Emergency Diesel Generator (EDG) and associated equipment during 2A EDG maintenance outage, on July 21, 2020.
- (2) Unit 2 Train 'B' Residual Heat Removal (RHR) system during Train 'A' RHR system outage, on July 29, 2020.
- (3) Unit 2 Train 'A' and 'B' RHR for Shutdown Cooling alignment during lowered inventory, on August 19, 2020.
- (4) Unit 1/2 Spent Fuel Pool Cooling while Unit 2 was defueled, on August 24, 2020.
- (5) Restoration of Unit 2 Train 'B' of Engineered Safety Features Actuation System (ESFAS) following ESFAS testing, on September 2, 2020.
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 Train 'B' EDG system on July 27, 2020.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 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 36/37, Unit 1 Trains 'A' and 'B' Component Cooling Water Pump Rooms, on July 14, 2020.
- (2) Fire Zones 144/162/164, Unit 2 Train 'B' EDG and Cable Tunnel 2T4B, on July 22, 2020.
- (3) Fire Zones 140A/B/C/E, Unit 2 Containment Building, on August 20, 2020.
- (4) Fire Zones 57A/81A/125B/126B/153/178/180, Unit 2 Control Building and Engineered Safety Features (ESF) Chiller Rooms, on September 2, 2020.
- (5) Fire Zones 155/156/157A/157B, Unit 2 Auxiliary Feedwater (AFW) pump houses, on September 15, 2020.
- (6) Fire Zones 91/92/97/98/103, Unit 1 Control Building Level A and 4.16 kV switchgear and remote shutdown rooms, on September 16, 2020.
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Unit 2 Train 'B' EDG Jacket Water Heat Exchanger, on August 25, 2020.
===71111.07T - Heat Sink Performance
Triennial Review (IP Section 03.02)===
- (1) Unit 2: Piping Penetration Cooler (21561E7002000), Cooled by Service Water - Section 02.02b
- (2) Unit 1: Component Cooling Water 'B' Heat Exchanger (11203E4002), Cooled by Service Water - Section 02.02b
- (3) Unit 2: Nuclear Service Cooling Water Pump Motor Cooler (21202P4006M01),
Cooled by Service Water - Section 02.02b
- (4) Unit 1: Residual Heat Removal B Heat Exchanger (11205E6002), Closed Loop Intermediate System - Section 02.02c
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 14 to September 18, 2020:
1. Liquid Penetrant Examination
a. Weld 683246-W2, Containment Spray Pump A valve replacement weld, ASME Class 2. This included a review of associated welding activities.
b. Weld 683246-W3, Containment Spray Pump A valve replacement weld, ASME Class 2. This included a review of associated welding activities.
2. Magnetic Particle Examination
a. Weld 21201-B6-002-W26, 6 Auxiliary Feedwater nozzle to shell weld, ASME Class 2
3. Ultrasonic Examination
a. Weld 21201-B6-002-W26, 6 Auxiliary Feedwater nozzle to shell weld, ASME Class 2.
b. Weld 21201-V6-002-W01, Pressurizer upper head to shell weld, ASME Class 1. This included the review of relevant indications that the licensee analytically evaluated and accepted for continued service.
c. Weld 21204-246-32-RB, 1.5 valve to pipe weld in Safety Injection Cold Leg Loop 4, ASME Class 1.
d. Weld 21204-245-34-RB, 3 reducer to branch connection weld in Safety Injection Cold Leg Loop 3, ASME Class 1
4. Visual Examination
a. Bare Metal Visual of Reactor Vessel Head (per Code Case N-729-6)b. VT-2 (System Leakage) of Reactor Coolant Pump 1 Seal Injection from Penetration 54 to Valve 006
The inspectors also evaluated the licensee's 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 the reactor shutdown from Mode 1 to Mode 4 to commence the Unit 2 Refueling Outage on August 16, 2020.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a licensed operator annual requalification exam scenario involving a faulted and ruptured Steam Generator and various transients, on September 22, 2020.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 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) Effectiveness of lubrication program to ensure reliability and operability of safety-related equipment for Units 1 and 2, on September 23, 2020.
- (2) Unit 1 Seismic Gap and Hazard Barrier Seals for Cable Tunnel Rooms 1T4A and 1T4B, on September 30, 2020.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (6 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 2 elevated risk due to Train 'B' Nuclear Service Cooling Water (NSCW) being inoperable during seismic restraint modifications, on July 15, 2020.
- (2) Unit 2 elevated risk due to Train 'A' EDG major outage with use of Risk Informed Completion Time, on July 20, 2020.
- (3) Unit 2 high risk activity for new fuel storage in the Spent Fuel Pool, on August 6, 2020.
- (4) Unit 2 elevated shutdown risk, Yellow, for core cooling and Reactor Coolant System (RCS) inventory due to lowered inventory in the RCS, and for Electrical DC Power due to 2D batteries being out of service during lowered inventory, on August 19, 2020.
- (5) Unit 2 high risk activity for fuel offloading during 2R21 Refueling Outage, on August 21, 2020.
- (6) Unit 1 elevated risk due to swapping from Train 'A' Stator Cooling Water (SCW) Pump to Train 'B' SCW pump for troubleshooting, on September 24, 2020.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (9 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (2) Unit 2 Main Feedwater Regulating Valve solenoid valves exceeding Environmental Qualification qualified life, on August 4, 2020.
- (3) Unit 1 Train 'A' RHR Pump Motor Cooler Pressure Relief Valve, 1PSV11748, exceeding testing requirements, on August 11, 2020.
- (4) Unit 1 Train 'B' NSCW pump motor cooling outlet spool flange surface outside of procedure limits, on September 14, 2020.
- (5) Unit 1 Train 'A' ESF Chiller compressor oil temperature found high, on September 15, 2020.
- (6) Part 21 Evaluation for Framatome Letter LTR19061 (D26 Relays Only), on September 16, 2020.
- (7) Unit 2 Electrical Containment Penetration #64 leaking by, on September 17, 2020.
- (8) Unit 1 Plant Ventilation Radiation Monitor, 1-RE-12442, functionality challenges while 1-RE-12444 was out of service, on September 17, 2020.
- (9) Unit 1 Train 'A' EDG broken fuel rail hold-down bolt, on September 21, 2020.
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Unit 2 Solid State Protection System (SSPS) Bridging Strategy, on August 27, 2020.
- (2) Unit 2 Single Point Vulnerabilities (SPVs) reduction from Main Steam Isolation Valve (MSIV) control circuits, on September 17, 2020.
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (8 Samples)
The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:
(1)
===14980A-2, Unit 2 Train 'A' EDG operability run, following extended maintenance outage, on July 27, 2020.
- (2) Functional Test following Unit 2 Train 'A' RHR system outage, on July 29, 2020.
- (3) Unit 2 Train 'A' and 'B' SSPS General Warning Monitor Circuit and Power Supplies functional testing after Modifications, on August 26, 2020.
- (4) Leak checks following Unit 2 Train 'B' EDG Jacket Water Heat Exchanger inspection, on August 28, 2020.
- (5) Work Order (WO) SNC1115784, for replacement activities on Unit 1 Loop 4 Delta T instrument card, on September 2, 2020.
- (6) Unit 2 Main Generator Protective Relay Replacement Functional Test, on September 24, 2020.
- (7) Operation of Unit 1 Train 'B' NSCW Pump 2 following planned maintenance, on September 29, 2020.
- (8) Functional Test for Train 'A' MSIV following reduction of SPVs from control circuits, on September 30, 2020.
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01)===
- (1) The inspectors evaluated Unit 2 refueling outage (2R21) activities from August 16, 2020 to September 11, 2020.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
(1)
===28914-C, Unit 1 Group 'A' Pressurizer Heater Capacity Test, on July 31, 2020.
(2)14721C-2, Unit 2 Emergency Core Cooling System Subsystem Flow Balance and Check valve Refueling Inservice Test, on August 19, 2020.
(3)14667-2, Unit 2 Train 'B' Diesel Generator and ESFAS Test, on September 1, 2020.
(4)14244-2, Unit 2 Main Turbine Safety Injection / P-14 or P-4 Final Trip Device Actuation Test, on September 11, 2020.
Inservice Testing (IP Section 03.01)===
- (1) Unit 2 Train 'B' Motor Driven AFW Pump Inservice Test and Response Time Test, on July 21, 2020.
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) Containment Penetration No. 80 Containment Service Air Supply Line Local Leak Rate Test, on August 12, 2020.
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) Licensed Operator Requalification Training exam scenario involving a Reactor Coolant Pump seal failure and various system malfunctions, on September 21,
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.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated radiological protection-related instructions to plant workers.
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 workers exiting the RCA at Unit 2 during a refueling outage.
- (2) Observed licensee surveys of potentially contaminated material leaving the RCA during the Unit 2 refueling outage.
- (3) Evaluated reasons for differences in personnel contamination monitoring equipment count times between plant RCA exit and the Unit 2 personnel hatch.
Radiological Hazards Control and Work Coverage (IP Section 03.04) (5 Samples)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.
- (1) Unit 2 Reactor Coolant Pump Motor Removal under RWP #20-2200. involved work in area with potential for airborne radioactivity.
- (2) Unit 2 Reactor Coolant Pump Seal Removals under RWP #20-2203 involving a breach of the RCS system and potential for high contamination levels and potential alpha level II controls.
- (3) Unit 2 Reactor Coolant Pump Impeller Removal under RWP #20-2203 involving high potential airborne risks, expected dose rates up to 7 Rem per hour and large dose rate gradients.
- (4) U2 RP entry into Unit 2 Regenerative Heat Exchanger Room for Pre-Job Survey under RWP #20-2108 involving RP surveys in Locked High Radiation Areas with unknown dose rates prior to entry.
- (5) Decon of Unit 2 Reactor Coolant Pump Housing Flange under RWP #20-2109 involving highly contaminated surfaces.
High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)
The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:
- (1) High Radiation Area controls during the Unit 2 Reactor Coolant Pump Impeller Removal
- (2) Very High Radiation Area controls for the Unit 2 Spent Fuel Pool Transfer Canal
- (3) Unit 2 Chemical Volume Control System Letdown Heat Exchanger Room.
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.
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, 2019 - June 30, 2020)
- (2) Unit 2 (July 1, 2019 - June 30, 2020)
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
- (1) Unit 1 (July 1, 2019 - June 30, 2020)
- (2) Unit 2 (July 1, 2019 - June 30, 2020)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (July 1, 2019 - June 30, 2020)
- (2) Unit 2 (July 1, 2019 - June 30, 2020)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) 09/30/2019 to 06/01/2020
===71153 - Followup of Events and Notices of Enforcement Discretion
Event Report (IP Section 03.02)===
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000425/2019-003-00, Transformer deenergization results in Emergency Diesel Generator and Auxiliary Feedwater Systems Starting (ADAMS Accession No.
ML19338C617). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements.
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71124.01 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: Licensee Identified Violation of 10CFR 20.1501(a)(1) which requires in part, surveys necessary to evaluate the magnitude and extent of radiation levels. In addition, 10CFR20.1902 requires posting of areas as a High Radiation Area (HRA) where dose rates exceed 100 mrem in one hour at 30 centimeters. Contrary to these requirements, on September 1, 2020, following a primary resin sluice on Unit 2, a down-posting survey was performed that failed to fully evaluate the magnitude and extent of radiation levels and failed to identify that HRA conditions still existed. Specifically, room 2-AB-86-Mezzanine which contained a portion of the resin line was not surveyed. On September 18, during a routine RP survey, dose rates as high as 8000 mrem per hour contact and 400 mrem per hour at 30 centimeters were discovered on this portion of the resin line, however the room was no longer posted in accordance with 10CFR1902.
Significance/Severity: Green.
Corrective Action References: CR10739998
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 22, 2020, the inspectors presented the integrated inspection results to Mr.
Drayton Pitts and other members of the licensee staff.
- On July 17, 2020, the inspectors presented the Triennial Heat Sink Inspection results to Drayton Pitts, Site Vice President and other members of the licensee staff.
- On September 1, 2020, the inspectors presented the RP Routine Baseline Inspection 2020003 Exit inspection results to Drayton Pitts, Site Vice President and other members of the licensee staff.
- On September 18, 2020, the inspectors presented the Baseline ISI Exit Meeting inspection results to Drayton Pitts, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
1X4DB130
P&I Diagram - Spent Fuel Cooling & Purification
System - System No. 1213
50.0
Drawings
2X4DB121
P&I Diagram - Safety Injection System - System No.
204
50.0
Drawings
2X4DB122
P&I Diagram - Residual Heat Removal - System No.
205
54.0
Drawings
2X4DB130
P&I Diagram - Spent Fuel Cooling & Purification
System - System No. 1213
2.0
Drawings
2X4DB170-2
P&I Diagram Diesel Generator System Train B
System No. 2403
45.0
Miscellaneous
10032-C
Shutdown Defense-In-Depth Assessment
08/24/2020
Procedures
11145-2
Diesel Generator Alignment
14.1
Procedures
NMP-OS-010
Protected Train/Division and Protected Equipment
Program
8.1
Procedures
NMP-OS-010-003
Vogtle Protected Equipment Logs
11.0
Corrective Action
Documents
10574691, 10732376
Fire Plans
2736-1
Zone 36 - Auxiliary Building Level A Fire Fighting
Preplan
5.0
Fire Plans
2737-1
Zone 37 - Auxiliary Building Level A Fire Fighting
Preplan
5.0
Fire Plans
2757A-1
Zone 57A - Control Building - Levels B, A, 1, 2, and 3
Fire Fighting Preplan
4.2
Fire Plans
2781A-1
Zone 81A - Control Building - Levels B, A, 1, 2, and 3
Fire Fighting Preplan
5.0
Fire Plans
2791-1
Zone 91 - Control Building Level A Fire Fighting
Preplan
4.1
Fire Plans
2792-1
Zone 92 - Control Building Level A Fire Fighting
Preplan
3.1
Fire Plans
2797-1
Zone 97 - Control Building - Level A Fire Fighting
Preplan
Fire Plans
2798-1
Zone 98 - Control Building - Level A Fire Fighting
4.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Preplan
Fire Plans
2803-1
Zone 103 - Control Building - Level A Fire Fighting
PrePlan
3.0
Fire Plans
2825B-1
Zone 125 B Control Building Level 3 Fire Fighting
Preplan
5.3
Fire Plans
2826B-1
Zone 126B - Control Building - Level 3 Fire Fighting
Preplan
3.2
Fire Plans
2840A-2
Zone 140A - Containment Building - Levels A, B, 1, 2
and 3 Fire Fighting Preplan
3.1
Fire Plans
2840B-2
Zone 140B - Containment Building - Levels A, B, 1, 2
and 3 Fire Fighting Preplan
4.1
Fire Plans
2840C-2
Zone 140C - Containment Building - Levels A, B, 1, 2
and 3 Fire Fighting Preplan
2.1
Fire Plans
2840E-2
Zone 140E - Containment Building - Levels A, B, 1, 2
and 3 Fire Fighting Preplan
1.1
Fire Plans
2844-2
Zone 144 - Diesel Generator Building - Electrical
Tunnel - Train B - Fire Fighting Preplan
2.2
Fire Plans
2853-2
Zone 153 - Control Building - Level B Fire Fighting
Preplan
0.2
Fire Plans
2855-2
Zone 155 - Auxiliary Feedwater Pumphouse - Train B
Fire Fighting Preplan
0.2
Fire Plans
2856-2
Zone 156 - Auxiliary Feedwater Pumphouse Fire
Fighting Preplan
0.2
Fire Plans
2857A-2
Zone 157A - Auxiliary Feedwater Pumphouse - Train
C Fire Fighting Preplan
0.2
Fire Plans
2857B-2
Zone 157B - Auxiliary Feedwater Pumphouse - Train
C Fire Fighting Preplan
0.2
Fire Plans
2862-2
Zone 162 - Diesel Generator Building Fire Fighting
Preplan
1.1
Fire Plans
2864-2
Zone 164 - Diesel Generator Building - Train B DFO
Day Tank Fire Fighting Plan
0.2
Fire Plans
2878-2
Zone 178 Control Building Level 3 Fire Fighting
Preplan
1.1
Fire Plans
2880-2
Zone 180 Control Building Level 3 Fire Fighting
0.2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Preplan
Fire Plans
NMP-ES-035-007
Fleet Fire Watch Instruction
5.0
Procedures
2040-C
Fire Protection Functionality and LCO Requirements
46.3
Work Orders
SNC1114249,
SNC782278,
SNC902691, SNC993922
Procedures
83395-C
Heat Exchanger Testing/Maintenance Program
7.10
Procedures
NMP-ES-012
Heat Exchanger Program
2.0
Work Orders
SNC1013636,
SNC820593
Corrective Action
Documents
Condition Reports (by CR
- )
CR10613570, CR10631016, CR10636903,
CR10729805, CR10729936, CR10730672,
CR10730754, CR10733292
Engineering
Evaluations
Corrosion Assessment
Number 1213-2011-009
Boric Acid Corrosion Assessment for Train A Spent
Fuel Pool Heat Exchanger
08/14/2020
Engineering
Evaluations
LTR-SDA-19-018-P
Vogtle Unit 2 Pressurizer top Head to Upper Shell
Weld ASME Section XI Evaluation of As-Found
Indications
Revision 0
Engineering
Evaluations
SNC1115524
Evaluation of V2R21 Reactor Head Inspection
Results
09/03/2020
Miscellaneous
SG-CDMP-20-18
Steam Generator Degradation Review for Vogtle Unit
Cycle 21
Revision 0
NDE Reports
S20V2V045
Visual Examination Report for Vessel Closure Head
Exterior
08/30/2020
Procedures
NMP-ES-019-001
Boric Acid Corrosion Control Program
Implementation
Version 11.1
Procedures
NMP-ES-019-004
Boric Acid Corrosion Control Program - Corrosion
Assessment
Version 5.1
Procedures
NMP-ES-024-202
Visual Examination (VT-2)
Version 7.0
Procedures
NMP-ES-024-208
Visual Examination of Reactor Vessel Head
Penetrations and Base Material
Version 6.3
Procedures
NMP-ES-024-401
Magnetic Particle Examination
Version 12.0
Procedures
NMP-ES-024-501
PDI Generic Procedure for Ultrasonic Examinatiokn
of Austenitic Pipe Welds (Appendix VIII)
Version 7.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
NMP-ES-024-516
Manual Ultrasonic Examination of Pressure Vessel
Welds (Non-Appendix VIII)
Version 6.0
71111.11Q Procedures
2004-2
Power Operation (Mode 1)
4.1
71111.11Q Procedures
2005-C
Reactor Shutdown to Hot Standby (Mode 2 to Mode
3)
71111.11Q Procedures
2006RFO-2
Unit Cooldown to Cold Shutdown for Refueling
1.7
Corrective Action
Documents
23064, 162028, 162032,
395948, 503291, 802581,
841494, 10313228,
10313317, 10315786,
10315787, 10407211,
10407213, 10645149,
10658620, 10659181,
10686716
Corrective Action
Documents
Resulting from
Inspection
10658261
Drawings
AX2D94V030
Waterstops & Waterproofing General Arrangement
Plan
Drawings
AX2D94V031
Waterstops & Waterproofing Sections and Details
Sheet 1
Drawings
AX2D94V033
Waterstops & Waterproofing Sections and Details
Sheet 3
Procedures
20411-C
Control of Lubricants
16.3, 17,
18.1
Procedures
NMP-ES-021
Structural Monitoring Program for the Maintenance
Rule
11.0
Procedures
NMP-ES-027
10.2
Procedures
NMP-ES-074-006
Fleet Lubrication Instruction
4.0
Work Orders
SNC1033792,
SNC1057746
Corrective Action
Documents
10725636
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
10722710
Miscellaneous
Phoenix Risk Profile
07/15/2020
Miscellaneous
Protecting Equipment Logs
07/15/2020
Miscellaneous
Phoenix Risk Model
07/21/2020
Miscellaneous
Plan of the Day
07/20/2020
Miscellaneous
V2R21 Defense in Depth Assessment Final Report
Miscellaneous
Phoenix Risk Model
07/20/2020
Miscellaneous
Plan of the Day
08/06/2020
Miscellaneous
10032-C
Shutdown Defense-In-Depth Assessment (Mode 4, 5,
6, 0)
08/21/2020
Miscellaneous
VNP-1-20-003
Procedures
10032-C
Outage Risk Assessment Monitoring
Procedures
13419-C
Diesel Generator RICT Support
10.3
Procedures
NMP-AD-002
Conduct of Problem Solving and Troubleshooting
13.5
Procedures
NMP-AD-002-F04
Troubleshooting Log
1.1
Procedures
NMP-DP-001-F01
Operational Risk Awareness Form 1 Risk Activity
Evaluation Worksheet
1.0
Procedures
NMP-GM-031-003
Risk Management Actions for 10 CFR 50.65(a)(4)
and the Risk Informed Completion Time Program
8.0
Procedures
NMP-MA-009
Foreign Material Exclusion Program
15.0
Procedures
NMP-MA-009-001
Foreign Material Exclusion Program Requirements
10.0
Procedures
NMP-OM-002
Shutdown Risk Management
6.0
Procedures
NMP-OS-003
Operational Decision Making Issue Evaluation
Process
10.0
Procedures
NMP-OS-010
Protected Train/Division and Protected Equipment
Program
8.1
Procedures
NMP-RE-011
Special Nuclear Material Movement
1.0
Work Orders
SNC963072
Calculations
X4CPS.0075.183
Qualified Life (QL) Extension for ASCO Solenoid
Valves
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
10714605, 10727375,
10739502, 277403,
10691621, 10693484,
10727332, 10727518,
277066, 277582,
265306, 10646853,
10728167, 10708633,
10704418, 10731746,
10720064, 10732422
Engineering
Evaluations
2B RHR leak rate calculation
Engineering
Evaluations
2B RHR Motor - Oil Level Trend
Miscellaneous
1-2020-3
Standing Order: Actions Required if overpressure
condition (pipe rupture) occurs on NSCW A to RHR A
pump motor cooler due to a failure of the relief valve
1PSV11748 to lift
1.0
Miscellaneous
AX4AJ04-20000
Installation, Operation, & Maintenance Manual ESF
Chillers
9.0
Miscellaneous
MIS-17-009
Vogtle Electric Generating Plant Fourth 10-Year
Interval Inservice Testing Program
11.0
Miscellaneous
MIS-17-027
Vogtle Electric Generating Plant Unit 1 Fourth 10-
Year Interval Valve Inservice Testing Basis
Document
2.0
Miscellaneous
SO 2-2020-4
Standing Order - 2B RHR Oil Leak Monitoring Plan
08/01/2020
Procedures
11881-2
Unit 2 Auxiliary Building Rounds
64.0
Procedures
24965-C
Containment Electrical Penetration Local Leak Rate
Test and Charging Instructions
Procedures
34316-C
Operation of DRMS Plant Vent Effluent Monitor (RE-
2442)
Procedures
GEN-87
Operator Lubricant Addition List
6.0
Procedures
NMP-AD-012
Operability Determinations and Functionality
Assessments
13.3
Procedures
NMP-AD-012-GL04
1.1
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
NMP-EP-305-GL03
VEGP Equipment Important to the EP Function
6.2
Procedures
NMP-ES-013
Inservice Testing Program
8.1
Procedures
NMP-ES-013-006
IST Ten Year Interval Update
2.1
Procedures
NMP-ES-013-010
IST Relief Valve Program Development and
Maintenance
1.0
Procedures
NMP-ES-016
Environmental Qualification Program
11.1
Work Orders
SNC1096401,
SNC1096402,
SNC1096403,
SNC1096404
Engineering
Changes
SNC106213450.59
50.59 Evaluation of Eliminate SPVs from MSIV
control circuits for Normally Energized MDR relays
and micro switches
Engineering
Changes
SNC1062134COMPACTS Risk Mitigation plan for elimination of SPVs from
MSIV control circuits for Normally Energized MDR
relays and micro switches
Engineering
Changes
SNC1062134DCP
Eliminate SPVs from MSIV control circuits for
Normally Energized MDR relays and micro switches
Engineering
Changes
SNC1062134WKCOMP
Implementing Work Order for elimination of SPVs
from MSIV control circuits for Normally Energized
MDR relays and micro switches
Engineering
Changes
SNC95902550.59
CFR 50.59 Screening: U2 SSPS Bridging
Strategy: Low Margin, Increase UVTA Coil Ckt
Voltage
0.0
Engineering
Changes
SNC959025AD
Applicability Determination: U2 SSPS Bridging
Strategy: Low Margin, Increase UVTA Ckt Voltage
1.0
Engineering
Changes
SNC959025DCP
U2 SSPS Bridging Strategy
Engineering
Changes
SNC959025FFP6
Detailed Fire Protection Program Change Evaluation:
U2 SSPS Bridging Strategy
0.0
Engineering
Changes
SNC959025FPP5
Fire Protection Program Impact Screening: U2 SSPS
Bridging Strategy
0.0
Engineering
Evaluations
SNC1062134RISK
Risk Assessment Form for elimination of SPVs from
MSIV control circuits for Normally Energized MDR
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
relays and micro switches
Miscellaneous
EQ3663
Seismic Qualification Data Summary / Seismic and
Dynamic Qualification Summary
1.0
Miscellaneous
EQ3666
Seismic Qualification Data Summary / Seismic and
Dynamic Qualification Summary
1.0
Miscellaneous
PWROG-14063-P
SSPS Conceptual General Warning Monitor Circuit
Summary Report
Miscellaneous
SNC959025RISK
Design Change/Modification - Risk Assessment
Form: SNC959025
0.0
Corrective Action
Documents
10726268, 10730390,
10735813, 10736030,
10736032, 10735143
Miscellaneous
DCP SNC959025
Unit 2 SSPS General Warning Monitor Circuit
(GWMC) Site Acceptance Test
1.0
Procedures
11885A-2
Diesel Generator 2A Operating Log
5.3
Procedures
13150B-1
Train B Nuclear Service Cooling Water System
Procedures
14420-2
Solid State Protection System Train A Operability
Test
2.1
Procedures
14980A-2
Diesel Generator 2A Operability Test
31.1
Procedures
2408-C
7300 Circuit Board Removal, Inspection, Cleaning,
and Reinstallation
44.2
Procedures
24813-1
Delta T/T Avg Loop 4 Protection Channel IV 1T-441
Channel Operational Test and Channel Calibration
Work Orders
SNC1056311,
SNC1056316,
SNC1060825,
SNC872956DCP,
SNC1070289,
SNC1085621,
SNC1091321,
SNC1091322,
SNC1115784,
SNC928745, SNC931262
Corrective Action
10637850, 10722762,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
10729784, 10731967
Drawings
One Line Diagram - 480V Switchgear 1NB01 - 1-
1805-S3-B01
15.0
Drawings
One Line Diagram - 480V Pressurizer Heater Panels
- 1NBPC, 1NBPB1, 1NBPB2, 1NBPB3
7.0
Miscellaneous
Clarification of TMI Action Plan Requirements
11/1990
Procedures
13430-1
480V AC Non 1E Electrical Distribution System
16.2
Procedures
244-2
Main Turbine SI/P-14 or P-4 Final Trip Device
Actuation Test
Procedures
14380-2
Containment Penetration No. 80 Containment
Service Air Supply Line Local Leak Rate Test
Procedures
14545B-2
Motor Driven Auxiliary Feedwater Pump B Operability
Test
1.2
Procedures
14721C-2
ECCS Subsystem Flow Balance and Checkvalve
Refueling Inservice Test
Procedures
14807B-2
Train B Motor Driven Auxiliary Feedwater Pump /
Check Valve Inservice and Response Time Test
5.1
Procedures
18031-1
Loss of Class 1E Elect Systems
1.2
Procedures
19011-1
1.1
Procedures
28914-C
Pressurizer Heater Capacity Test
ALARA Plans
RWP 20-2203
20-2203 Remove and Replace RCP#1 Pump
08/03/2020
Corrective Action
Documents
10733187
Key to LHRA lock 02 was lost in containment
08/25/2020
Corrective Action
Documents
Resulting from
Inspection
10734162
Relocation of dosimetry due to potential gradient
dose rates not evaluated in accordance with RP
procedural requirements.
08/31/2020
Corrective Action
Documents
Resulting from
Inspection
10734865
ALARA plan for the RCP pump replacement did not
discuss contingencies for the pump binding as it did
in 1998
08/31/20
Corrective Action
Documents
Resulting from
10734866
Permanent High Radiation Area postings in U2
containment have not been Updated
08/31/20
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Inspection
Corrective Action
Documents
Resulting from
Inspection
10734869
RP supervisory oversight required for high risk work
may be more effective in central monitoring than at
the job when telemetry and video capabilities are
available.
08/31/20
Corrective Action
Documents
Resulting from
Inspection
10734871
Organizational knowledge gap in the appropriate
criteria for relocation of dosimetry since the NISPs
were issued.
08/31/20
Procedures
NM-HP-306
Radiological Job Coverage
Version 1.0
Procedures
NMP-HP-108
Issuance, Use, and Collection of Personnel
Dosimetry
Version 2.7
Procedures
NMP-HP-108-002
Use of EDE (Effective Dose Equivalent)
Methodologies
Version 3.1
Procedures
NMP-HP-204
ALARA Planning and Job Review
Version 5.5
Procedures
NMP-HP-300
Radiation and Contamination Surveys
Version 5.4
Radiation
Surveys
28197
HI_STORM SURFACE DOSE RATES (C) MPC #489
08/17/2019
Radiation
Surveys
28198
HI_STORM SURFACE DOSE RATES (C) MPC #489
08/17/2019
Radiation
Surveys
28388
HI_STORM SURFACE DOSE RATES (C) MPC #490
08/26/2019
Radiation
Surveys
28389
HI_STORM SURFACE DOSE RATES (C) MPC #490
08/26/2019
Radiation
Surveys
28946
HI_STORM SURFACE DOSE RATES (C) MPC #544
09/14/2019
Radiation
Surveys
28947
HI_STORM SURFACE DOSE RATES (C) MPC #539
09/21/2019
Radiation
Surveys
237531
Plant Vogtle Quadrant 4 Elevation 197
08/16/2020
Radiation
Surveys
237538
Plant Vogtle Level A Lower Overview (2RXAL)
08/16/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation
Surveys
237856
Plant Vogtle Level A Lower Overview
08/16/2020
Radiation
Surveys
238058
Plant Vogtle RCP Motor (2RXAI15)
08/23/2020
Radiation
Surveys
238069
RCP #1 Shroud (rev#2) (2RXB5)
08/23/2020
Radiation
Surveys
238070
RCP #1 Seal Plate (2RXB9)
08/23/2020
Radiation
Surveys
238113
Plant Vogtle Regenerative Heat Exchanger Room
08/24/2020
Radiation
Surveys
238263
Reactor Coolant Pump Impeller (1RXA-19)
08/27/2020
Radiation
Surveys
2H19
Vogtle Boundary Report from Environmental
Laboratory
07/12/2019 -
2/31/2019
Radiation Work
Permits (RWPs)
20-0148
Unit 1 Remove and Replace Pump on RCP#1 and All
Associated Work in Unit 2 Containment
Revision 0
Radiation Work
Permits (RWPs)
20-2003
2R21 Refueling Outage Work Activities to Include
CMs/PMs, Surveillance, Calibration and Misc/Support
Work Activities in High Radiation Areas not Covered
Under Other RWPs.
Revision 0
Radiation Work
Permits (RWPs)
20-2109
Decon Activities in Locked High Radiation Areas in
U2 CNMT
Revision 0
Radiation Work
Permits (RWPs)
20-2202
Remove and Replace RCP #1 Pump to Include All
Associated Work for Assemby and Reassembly in
Unit 2 Containment
Revision 0
Radiation Work
Permits (RWPs)
20-2202
Remove and Replace RCP #1 Pump to Include All
Associated Work for Assemby and Reassembly in
Unit 2 Containment
Radiation Work
Permits (RWPs)
20-2203
RP Surveys and Job Coverage In Locked High
Radiation Areas in U2 Containment
Revision 0
Radiation Work
Permits (RWPs)
20-2505
Under Rx Vessel Work Including DMIMS, Cavity
Sump CM/PM, Liner Plate Inspection,/Repair and All
Associated Work
Revision 0
Self-
NMP-HP-305
Vogtle Alpha Plant Charactgerization Study
04/24/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Assessments
71151
Corrective Action
Documents
10730772
Individual Received Unanticipated Dose Rate Alarm
08/16/2020
71151
Corrective Action
Documents
Resulting from
Inspection
10741335, 278373
71151
Miscellaneous
Access Control Alarms
Report
Access Control Alarms Report
01/16/2019
to
08/21/2020
71151
Procedures
MSPI-VOGTLE
NRC Mitigating System Performance Index (MSPI)
Basis Document
71151
Procedures
MSPI-VOGTLE
NRC Mitigating System Performance Index (MSPI)
Basis Document
71151
Procedures
NMP-ES-076
Mitigating System Performance Index Program
(MSPI)
3.1
71151
Procedures
NMP-ES-076-001
Mitigating System Performance Index Implementation
Instruction
4.1
Corrective Action
Documents
10724196, 10650853,
10653959, 10653949,
276893, 256995,
1057750, 1054522
Drawings
AX3D-AA-A03A
Vogtle - Wilson - Master One Line Diagram
20.0
Miscellaneous
Plant Wilson Services Agreement Between Georgia
Power Company and Southern Nuclear Operating
Company, Inc.
Miscellaneous
Nuclear Energy Institute - Industry Guideline for
Monitoring the Effectiveness of Maintenance at
Nuclear Power Plants
4A
Miscellaneous
Monitoring the Effectiveness of Maintenance at
Nuclear Power Plant
Procedures
13418A-2
Standby Auxiliary Transformer Unit Two Train A
Operations
6.2
Procedures
13418A-2
Standby Auxiliary Transformer Unit Two Train A
7.1
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Operations
Procedures
230-2
Offsite AC Circuit Verification and Capacity/Capability
Evaluation
Procedures
NMP-GM-021-003
Plant Vogtle 1-2 Switchyard Access and Maintenance
Controls
2.0
Procedures
NMP-GM-021-003
Plant Vogtle 1-2 Switchyard Access and Maintenance
Controls
1.1
Procedures
NMP-OS-010-003
Vogtle Protected Equipment Logs
11.0
Procedures
NMP-OS-010-003
Vogtle Protected Equipment Logs
10.0