IR 05000424/2022001
| ML22131A394 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 05/12/2022 |
| From: | Alan Blamey Division Reactor Projects II |
| To: | Gayheart C Southern Nuclear Company |
| References | |
| IR 2022001 | |
| Download: ML22131A394 (22) | |
Text
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1&2 - INTEGRATED INSPECTION REPORT 05000424/2022001 AND 05000425/2022001
Dear Ms. Gayheart:
On March 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Vogtle Electric Generating Plant, Units 1&2. On April 14, 2022, 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.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at Vogtle Electric Generating Plant, Units 1&2.
May 12, 2022
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, 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:
05000424/2022001 and 05000425/2022001
Enterprise Identifier:
I-2022-001-0026
Licensee:
Southern Nuclear Company, Inc.
Facility:
Vogtle Electric Generating Plant, Units 1&2
Location:
Waynesboro, GA
Inspection Dates:
January 01, 2022, to March 31, 2022
Inspectors:
B. Bishop, Sr. Project Engineer
J. Eargle, Senior Resident Inspector
B. Kemker, Senior Resident Inspector
K. Kirchbaum, Operations Engineer
M. Magyar, Reactor Inspector
D. Mas-Penaranda, Project Engineer
C. Safouri, Senior Resident Inspector
R. Smith, Senior Resident Inspector
Approved By:
Alan J. Blamey, Chief
Reactor Projects Branch 2
Division of Reactor Projects
SUMMARY
The 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.
List of Findings and Violations
Safety Injection (SI) Pump Room Unsealed Penetrations During Internal Flooding Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green NCV 05000424,05000425/2022001-01 Open/Closed None (NPP)71111.06 The inspectors identified a Green finding and associated Non-cited Violation (NCV) of Title 10 Code of Federal Regulations (CFR) 50, Appendix B, Criterion III, Design Control, when the licensee failed to analyze possible common mode effects from internal flooding events in the safety injection (SI) pump rooms.
Additional Tracking Items
Type Issue Number Title Report Section Status URI 05000424,05000425/20 21004-01 SI Pump Room Unsealed Penetrations During Internal Flooding 71111.06 Closed
PLANT STATUS
Unit 1 began the inspection period at 100 percent rated thermal power. On March 3, 2022, the unit was down powered to 92 percent rated thermal power to perform a main turbine valve stroke test. The unit was returned to 100 percent rated thermal power on March 4, 2022, and remained at or near 100 percent rated thermal power for the remainder of the inspection period.
Unit 2 began the inspection period at 100 percent rated thermal power. On March 6, 2022, the unit was shutdown for a refueling outage (2R22) and remained shutdown for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
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 1 turbine driven auxiliary feedwater (AFW) pump following a system outage, on February 10, 2022.
- (2) Unit 2 train A component cooling water (CCW) during shutdown cooling (SDC), on March 29, 2022.
- (4) Unit 2 train A residual heat removal (RHR) system during SDC, on March 31, 2022.
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 165/166, Unit 1 train A/B emergency diesel generator (EDG) tanks and pumphouse, on February 8, 2022.
- (2) Fire Zones 165/166, Unit 2 train A/B EDG tanks and pumphouse, on February 8, 2022.
- (3) Fire Zones 155/156/157A/157B, Unit 1 AFW pumphouse, on February 9, 2022.
- (4) Fire Zones 155/156/157A/157B, Unit 2 AFW pumphouse, on February 9, 2022.
- (5) Fire Zones 54/55/148/23/172/147, Unit 1 Level 2 auxiliary building, on March 10, 2022.
- (6) Fire Zones 54/55/148/23/172/147, Unit 2 Level 2 auxiliary building, on March 10, 2022.
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill in the primary chemistry laboratory, on February 2, 2022.
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Unit 2 train A EDG jacket water heat exchanger, on March 17, 2022.
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 March 14 - March 25, 2022:
1. Ultrasonic Testing
a.
===21204-124-3-RB, 10" Elbow to Pipe Weld, Class 1 (reviewed) b.
21201-V6-002-W01, Pressurizer Upper Head to Upper Shell Weld, Class 1 (reviewed)c.
21201-V6-002-W12, Upper Head to 6" Safety Nozzle Weld, Class 1 (reviewed)
2. Magnetic Particle Testing
a.
21201-V6-002-W12, Upper Head to 6" Safety Nozzle Weld, Class 1 (reviewed)
3. Visual Examination (VT)
a.
21201-V6-001-CRDM, Vessel Closure Head Exterior, Code Case N-729 (reviewed)
4. Eddy Current Examination
a.
Steam Generator 4: R37C74, R39C64 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 Unit 2 control room during a letdown isolation transient, on January 10, 2022.
Licensed Operator Requalification Training/Examinations (IP Section 03.02)===
- (1) The inspectors observed and evaluated a simulator scenario of a steam generator tube leak that degraded into a steam generator tube rupture, concurrent with main steam isolation valve failure to close, on February 9, 2022.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 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 train B safety injection (SI) pump system outage with planned risk informed completion time, on January 27, 2022.
- (2) Unit 2 train A reserve auxiliary transformer replacement project near protected equipment, on March 8, 2022.
- (3) Unit 2 Yellow shut down risk for direct current and vital power availability, on March 9,2022.
- (4) Unit 2 train A protected equipment during SDC, on March 29, 2022.
- (5) Unit 2 train B protected equipment during SDC, on March 29, 2022.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (2) Unit 1/2 EDG operability during parallel operations, on February 23, 2022.
- (3) Unit 2 functional failure of safety related snubber for the pressurizer spray line, on March 15, 2022.
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 train B nuclear service cooling water (NSCW) strainer modification to Unit 2 train B SI motor cooler, on January 24, 2022.
- (2) Unit 2 reactor head stand permanent modification, on March 10, 2022.
Severe Accident Management Guidelines (SAMG) Update (IP Section 03.03) (1 Sample)
- (1) The inspectors verified the site Severe Accident Management Guidelines were updated in accordance with the PWR generic severe accident technical guidelines and validated in accordance with NEI 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents, Revision 1.
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
- (1) Unit 1 pressurizer pressure protection channel I (1P-455) channel operational test and channel calibration after replacement of the Westinghouse 7300 NAL signal comparator card (1PB-455A), on January 3, 2022.
- (2) Unit 2 train B NSCW strainer modification to Unit 2 train B SI motor cooler, on January 24, 2022.
- (3) Unit 2 train B centrifugal charging pump (CCP) system outage, on January 26, 2022.
- (4) Unit 2 train B containment spray system outage, on January 27, 2022.
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial)
The inspectors evaluated refueling outage 2R22 from March 5, 2022, to March 31, 2022. The inspectors completed inspection procedure Sections 03.01.a through 03.01.c.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:
Surveillance Tests (other) (IP Section 03.01) (5 Samples)
(1)
===14980B-1, Diesel Generator 1B Operability Test, on January 26, 2022.
(2)24751-2, Steam Generator Level (Narrow Range) Protection Channel I 2L-529 Channel Operational Test and Channel Calibration, on February 9, 2022.
(3)28210-C, Unit 2 loop 1 Main Steam Line Code Safety Valve Setpoint Verification, on March 2, 2022.
(4)14666-2, Section 4.2, Train A Diesel Generator and ESFAS Test - Diesel Generator Start on Loss-of-Offsite Power (LOSP), on March 24, 2022.
(5)14666-2, Section 4.3, Train A Diesel Generator and ESFAS Test - Safety Injection Actuation, on March 24 and 25, 2022.
Containment Isolation Valve Testing (IP Section 03.01)===
(1)
===14372B-2, Containment Penetration No. 72B RCS Loop #3 Accumulator Sample Line Local Leak Rate Test, on March 23, 2022.
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Partial)
(1)
(Partial)
The scenario consisted of fuel clad damage coincident with a faulted steam generator tube rupture accident, on February 22, 2022. The drill did not contribute to drill and exercise performance and emergency response organization performance indicators.
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
- (1) Unit 1 (January 1, 2021, through December 31, 2021)
- (2) Unit 2 (January 1, 2021, through December 31, 2021)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)
- (1) Unit 1 (January 1, 2021, through December 31, 2021)
- (2) Unit 2 (January 1, 2021, through December 31, 2021)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)
- (1) Unit 1 (January 1, 2021, through December 31, 2021)
- (2) Unit 2 (January 1, 2021, through December 31, 2021)
INSPECTION RESULTS
Safety Injection (SI) Pump Room Unsealed Penetrations During Internal Flooding Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green NCV 05000424,05000425/2022001-01 Open/Closed None (NPP)71111.06 The inspectors identified a Green finding and associated Non-cited Violation (NCV) of Title 10 Code of Federal Regulations (CFR) 50, Appendix B, Criterion III, Design Control, when the licensee failed to analyze possible common mode effects from internal flooding events in the safety injection (SI) pump rooms.
Description:
On December 14, 2021, NRC inspectors performed an internal flooding inspection of the Unit 1 train B SI pump room, which is located on Level B of the auxiliary building. The 1B SI pump room is adjacent to the 1A SI pump room, which is separated by a wall enclosure and a fire door that leads to an adjoining hallway. Vogtle Electric Design Manual, Design Control (DC) procedure DC-1003, Flooding - Interdiscipline, specifies that its purpose is to meet Appendix A of Title 10, Code of Federal Regulations, Part 50, (10 CFR Part 50) General Design Criteria (GDC) 4, Environmental and Dynamic Effects Design Bases, which requires in part the assessment of the consequences of flooding from fluids discharging from postulated pipe breaks. Calculation X6CXC-30, Flooding Analysis - Auxiliary Building, Level B" was performed to demonstrate conformance with DC-1003 and thereby conformance with applicable GDCs.
The purpose of Calculations X6CXC-30 (Unit 1) and X6CYC-30 (Unit 2) are to determine the maximum flood volumes and levels, resulting from piping failures, fluid reservoir failures, or fire protection sprinkler activation in the individual rooms in level B of Auxiliary Building. In September 2015, the licensee identified that penetrations in the SI pump rooms needed to be re-evaluated due to an updated maximum flood level in each room. The new flood level was a result of reclassifying the SI discharge piping (per REA 98-VAA075), which raised the flood level from 18" to 135". SI pump room internal flood calculations X6CXC-30 and X6CYC-30 were updated to reflect the new flood level, however, there were unsealed or inadequately rated penetrations that were not evaluated as part of the update. Unsealed or inadequately rated penetrations below the maximum flood level would introduce communication pathways for internal flooding between adjacent rooms.
NRC inspectors identified an open wall penetration approximately 3-4" in diameter near the top of the 1B SI pump rooms (R-B19) watertight door, which was also below the maximum calculated flood height of 135 inches per Calculation X6CXC-30. By means of an extent of condition comparison, NRC inspectors and licensee staff identified additional unsealed or inadequately rated penetrations in the 1A, 2A, and 2B SI pump room walls during subsequent walkdowns performed on December 15-16, 2021. These penetrations varied in both location and number for each pump room and can be summarized by the following:
- 1A SI pump room: 2 unsealed or inadequately rated for flood protection: 1-2108-Z1-0392-B and 1-2108-Z1-1572-B
- 1B SI pump room: 1 unsealed or inadequately rated for flood protection: unscheduled penetration associated with line 1J3-1609-031-3/4
- 2A SI pump room: 2 unsealed or inadequately rated for flood protection: 2-2108-Z1-0090-B and 2-2108-Z1-0488-B
- 2B SI pump room: 5 unsealed or inadequately rated for flood protection: 2-2108-Z1-0080-B, 2-2108-Z1-0081-B, 2-2108-Z1-0082-B, 2-2108-Z1-0480-B, and 2-2108-Z1-0481-B Supporting design documents containing penetration information showed that these penetrations were either unsealed or used inappropriate seal material for internal flooding protection. Additionally, NRC inspectors identified that DC-1003 outlines internal flooding requirements including, in part, the following information:
Penetrations through walls of safety-related rooms or areas should be designed to withstand the design flood levels on either side of the walls to prevent leakage through the penetration.
Penetrations which do not increase flood levels on either side of walls, by means of communication, need not be sealed against water.
NRC inspectors identified that the approved internal flood calculations for the SI pump rooms did not include the unsealed or inadequately rated penetrations, or account for their impact during internal flooding scenarios.
Corrective Actions: Licensee staff completed an initial assessment of the internal flood analyses for the SI pump rooms and determined the SI pumps remained operable with the identified open penetrations. A work order (WO T312172111) was created and implemented to formally seal the penetration at the 17" level for the 2B SI pump room in December 2021. The remainder of the penetrations will be sealed under WO SNC1236398.
Corrective Action References: Condition Report (CR) 10847097, WO T312172111, and WO SNC1236398.
Performance Assessment:
Performance Deficiency: The licensees failure to meet design control procedure DC-1003 was a performance deficiency. Specifically, the licensee failed to evaluate and implement design control measures associated with the affected penetrations for the SI pump rooms as a result of the internal flooding re-evaluation.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Design Control attribute of the Initiating Events cornerstone and adversely affected the cornerstone objective to limit the likelihood of events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. The inspectors screened the performance deficiency utilizing Inspection Manual Chapter (IMC) 0612, Issue Screening, and determined the performance deficiency was More-than-Minor. The performance deficiency was associated with the Initiating Events cornerstone attribute of Design Control and adversely affected the cornerstone objective To limit the likelihood of events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. Specifically, the licensees failure to address the missing internal flood barriers adversely impacted assurance that design basis floods in the SI pump rooms would not result in the loss of function of the safety injection system.
Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The affected cornerstones were Initiating Events and Mitigating Systems, as determined by IMC 0609, Attachment 4, Initial Characterization of Findings. The inspectors screened the performance deficiency using Exhibits 1, 2 and 4 of IMC 0609, Appendix A, The Significance Determination Process for Findings At-Power. The inspectors determined a detailed risk evaluation was required since the finding potentially impacted the likelihood of an internal flooding initiating event involving more than one train of safety injection due to the unsealed internal flood wall penetrations.
A detailed risk evaluation was performed by a regional senior reactor analyst using SAPHIRE Version 8.2.5 and NRC Vogtle SPAR model Version 8.60. A conditional analysis was performed for Unit 1 and 2 to evaluate the risk increase of an internal flood event with unsealed or inadequately rated wall penetrations in the SI pump rooms. A one-year condition exposure time was used for the analysis. No credit was provided in the analysis for recovery of equipment impacted by the internal flood event. The dominant sequences included an internal flood event in the SI MDP room followed by a plant transient with failures of auxiliary feedwater and operator actions to align feed and bleed cooling. The analysis determined that the estimated increase in Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) was less than 1E-06/year for delta-CDF and less than 1E-07/year for delta-LERF, representing a finding of very low safety significance (Green) for both Units 1 and 2.
Cross-Cutting Aspect: Not Present Performance. No cross-cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance.
Enforcement:
Violation: 10 CFR Part 50, Appendix B, Criterion III, Design Control, requires that, in part, design control measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews, by the use of alternate or simplified calculational methods, or by the performance of a suitable testing program.
Safety-related calculations X6CXC-30 and X6CYC-30, along with Design Control procedure DC-1003, "Flooding-Interdiscipline," implemented Appendix B design control requirements and established the adequacy of SI pump room design to withstand internal flooding events.
Contrary to the above, from September 2015, to December 16, 2021, the licensee failed to implement design control measures to verify or check the adequacy of design of the Unit 1 and Unit 2 SI pump rooms when calculating new maximum design flood levels. Specifically, the design control measures used to evaluate higher room flood levels did not consider the presence of unsealed or inadequately rated wall penetrations, which had the potential for an internal flood event to impact safety-related equipment within and adjacent to the SI pump rooms.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
The disposition of this finding and associated violation closes URI:
05000424,05000425/2021004-01.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On April 14, 2022, the inspectors presented the integrated inspection results to Mr.
Drayton Pitts and other members of the licensee staff.
On March 25, 2022, the inspectors presented the Inservice Inspection (ISI) results to Mr. Drayton Pitts and other members of the licensee staff.
THIRD PARTY REVIEWS Inspectors reviewed the following third-party reports during the inspection period:
Nuclear Safety Review Board Chairman's Report, December 14, 2021
Vogtle Station INPO Performance Summary Report, September 2021
Nuclear Safety Review Board Chairman's Report, May 24, 2021
WANO Peer Review Report, February 2021
Nuclear Safety Review Board Chairman's Report, December 10, 2020
Performance Leader Visit Summary, April 10, 2020
National Academy for Nuclear Training - Accreditation Final Report, February 19, 2020
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Condition Report(s)
10843032
Corrective Action
Documents
Resulting from
Inspection
Condition Report(s)
10870081, 10870082, 10870083, 10666535, 10870586,
10870621
1X4DB161-1
P&I Diagram - Auxiliary Feedwater System - Condensate
Storage & Degasifier System - System No. 1302
46.0
1X4DB161-2
P&I Diagram - Auxiliary Feedwater System - System No.
1302
29.0
1X4DB161-3
P&I Diagram - Auxiliary Feedwater Pump System (Aux
Feedwater Pump Turbine Driver) - System 1302
2.0
2X4DB111
P&I Diagram - Reactor Coolant System - System No.
201
30.0
2X4DB115
P&I Diagram - Chemical & Volume Control System -
System No. 1208
35.0
2X4DB121
P&I Diagram - Safety Injection System - System No. 1204
50.0
2X4DB122
P&I Diagram - Residual Heat Removal - System No. 1205
54.0
2X4DB133-1
P&I Diagram - Nuclear Service Cooling Water System -
System No. 1202
56.0
2X4DB133-2
P&I Diagram - Nuclear Service Cooling Water System -
System No. 1202
57.0
2X4DB134
P&I Diagram - Nuclear Service Cooling Water System -
System No. 1202
33.0
2X4DB135-1
P&I Diagram - Nuclear Service Cooling Water System -
System No. 1202
28.0
2X4DB136
P&I Diagram - Component Cooling Water System -
System No. 1203
24.0
Drawings
2X4DB137
P&I Diagram - Component Cooling Water System -
System No. 1203
21.0
Procedures
13610-1
Auxiliary Feedwater System
Corrective Action
Condition Report(s)
10855863, 10855864
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Corrective Action
Documents
Resulting from
Inspection
Condition Report(s)
10855859
2723-1
Zone 23-Auxiliary Building - Electrical Chase Rooms Fire
Fighting Preplan
4.0
2723-2
Zone 23-Auxiliary Building - Electrical Chase Rooms Fire
Fighting Preplan
2.1
2754-1
Zone 54 - Auxiliary Building Level 2 Fire Fighting Preplan
3.1
2754-2
Zone 54 - Auxiliary Building - Level 2, Train "A" CCW HX
Fire Fighting Preplan
0.2
2755-1
Zone 55 - Auxiliary Building Level 2 Fire Fighting Preplan
3.1
2755-2
Zone 55 - Auxiliary Building - Level 2, Train "B" CCW HX
Fire Fighting Preplan
0.2
2812-1
Zone 112 - Control Building - Level 1 Fire Fighting
Preplan
5.0
2847-1
Zone 147-Auxiliary Building - Level 2 Fire Fighting
Preplan
3.1
2847-2
Zone 147-Auxiliary Building - Level 2 Fire Fighting
Preplan
1.3
2848-1
Zone 148 - Auxiliary Building - Level 2 Fire Fighting
Preplan
1.2
2855-1
Zone 155 - Auxiliary Feedwater Pumphouse - Train B Fire
Fighting Preplan
2.2
2855-2
Zone 155 - Auxiliary Feedwater Pumphouse - Train B Fire
Fighting Preplan
0.2
2856-1
Zone 156 - Auxiliary Feedwater Pumphouse Fire Fighting
Preplan
3.1
2856-2
Zone 156 - Auxiliary Feedwater Pumphouse Fire Fighting
Preplan
0.2
2857A-1
Zone 157A - Auxiliary Pumphouse - Train C Fire Fighting
Preplan
2.3
Fire Plans
2857A-2
Zone 157A - Auxiliary Feedwater Pumphouse - Train C
0.2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Fire Fighting Preplan
2857B-1
Zone 157B - Auxiliary Feedwater Pumphouse Fire
Fighting Preplan
1.2
2857B-2
Zone 157B - Auxiliary Feedwater Pumphouse - Train C
Fire Fighting Preplan
0.2
2865-1
Zone 165 - Diesel Generator Tanks and Pumphouse Fire
Fighting Preplan
2.2
2865-2
Zone 165 - Diesel Generator Tanks and Pumphouse Fire
Fighting Preplan
0.2
2866-1
Zone 166 - Diesel Generator Tanks and Pumphouse Fire
Fighting Preplan
1.2
2866-2
Zone 166 - Diesel Generator Tanks and Pumphouse Fire
Fighting Preplan
0.2
2872-1
Zone 172-Auxiliary Building - Level 2 Fire Fighting
Preplan
3.1
2872-2
Zone 172-Auxiliary Building - Auxiliary Building - Level 2
Fire Fighting Preplan
1.2
NMP-TR-425-F01
Fire Drill Scenario Development and Approval Sheet: V-
037
05/12/2021
Miscellaneous
NMP-TR-425-F14
Fire Drill Package: V-037
2.1
Corrective Action
Documents
Condition Report(s)
10119145
Corrective Action
Documents
Condition Report(s)
10867432, 10039178, 10867819
Master-Lee Eddy Current Daily Status Report - Vogtle
2R22
03/17/2022
Miscellaneous
2403G4001E03
Diesel Jacket Water Cooler - 2A, Vogtle V2R22-March
22, Final Repair Map (Tubes to be Plugged)
NMP-ES-012-001
Inspection of Heat Exchangers - 2A EDG Jacket Water
Cooler HX
03/25/2022
Procedures
NMP-ES-024-701
Eddy Current Testing of Heat Exchanger Tubing
5.0
Work Orders
SNC1092262, SNC407903, SNC805929, SNC1142127,
SNC1259623, SNC1261669
Corrective Action
Condition Report(s)
10850039
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Miscellaneous
NMP-TR-209-F02
Lesson Plan Form: Segment 20221 As-Left
1.0
18007-C
Abnormal Operating Procedure - Chemical and Volume
Control System Malfunction
27.1
Procedures
NMP-TR-405
Simulator Exercise Guide and Evaluation
1.2
Corrective Action
Documents
Condition Report(s)
10854083
Corrective Action
Documents
Resulting from
Inspection
Condition Report(s)
10866709, 10869148
eSOMS Logs
01/27/2022
Phoenix A4 Risk
01/27/2022
Phoenix RICT
01/27/2022
Plan of the Day
01/27/2022
Daily Status Report
01/27/2022
Miscellaneous
NMP-GM-031-002-F01
RICT Projection Details - 2B SI pump system outage
01/24/2022
10032-C
Outage Risk Assessment Monitoring
19.1
Procedures
NMP-OS-010
Protected Train/Division and Protected Equipment
Program
8.1
Corrective Action
Documents
Condition Report(s)
10852094, 10852311, 10865004, 10865791
Condition Report(s)
10859532, 10862003
Corrective Action
Documents
Resulting from
Inspection
Technical Evaluation(s)
1101376
1X4AK01-00027
Lube Oil Piping Schematic
Fabrication Isometric - CTMT BLDG Area 4D, LVL, 2, 1,
A, B
10.0
2X4AK01-00361
Engine Control Panel Schematic Sheet 1 of 13
15.0
2X4AK01-00362
Engine Control Panel Schematic
2X4AK01-20021
Diesel Generator Engine Pneumatic Schematic
6.0
Drawings
2X4DB170-1
P&I Diagram - Diesel Generator System Train A - System
No. 2403
43.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Evaluations
SNC1253380
Evaluation of Failed Snubber V2-1201-030-H613
03/26/2022
Miscellaneous
Troubleshooting Support / Refute Matrix: 2A EDG Trip
01/19/2022
Calibration/Examination
- Drawing Number: ISI-
201-030
4-inch Branch Connection to Pipe and three individual 4-
inch Pipes to Elbow.
03/21/2022
Visual Examination of
Pipe Hanger, support
Restraint (VT-3)
Component ID: 21201-030-H610, H611, H612, and H613
03/18/2022
NDE Reports
Visual Examination of
Welds (VT-1)
Unit 2 Line 30 (from Welds 1 to 8)
03/21/2022
Operability
Evaluations
GBE-PP000-TR-PX-
000001
Vogtle Pressurizer Spray Line (BB-02-607) Locked
Snubber H613 Operability Assessment
0.0
13145A-2
Diesel Generator Train A
14.1
Procedures
23922-2
Diesel Generator Train A Calcon Pressure Switch
Calibration
Work Orders
SNC116107, SNC1207913, SNC1253385, SNC1253386,
SNC1253387
Corrective Action
Documents
Condition Report(s)
10865522, 10864280
LDCR 2022005
Licensing Document Change Request for Reactor Head
Stand Modification
1.0
NMP-AD-008-F01
Applicability Determination for DCP SNC 1172256
13.3
NMP-AD-010-F01
CFR 50.59 Screening for SNC1172256
10.4
NMP-AD-010-F03
CFR 50.59 Evaluation for SNC1172256
2.2
SNC102980650.59
CFR 50.59 Screening: NSCW Strainer - 2B SI Pump
2.0
SNC1029806AD
Applicability Determination: NSCW Strainer - 2B SI Pump
2.0
SNC1029806DCP
Design Change Package: NSCW Strainer - 2B SI Pump
SNC1029806FPP5
Fire Protection Program Impact Screen: NSCW Strainer -
2B SI Pump
1.0
SNC1029806FPPP6
Detailed Fire Protection Program Change Evaluation:
1.0
Engineering
Changes
SNC1029806M001
P&I Diagram - Nuclear Service Cooling Water System -
2.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
System No. 1202
SNC1029806M002
Nuclear Service Cooling Water System Fabrication
Isometric - Aux. Bldg. Area 3H, Level B
2.0
SNC1029806M003
Nuclear Service Cooling Water System Fabrication
Isometric - Aux. Bldg. Area 3H, Level B
1.0
SNC1029806M004
Nuclear Service Cooling Water System Fabrication
Isometric - Aux. Bldg. Area 3H, Level B
1.0
SNC1029806M005
Pipe Assembly Support
2.0
SNC1029806M006
Pipe Support Assembly
2.0
SNC1029806M007
P&I Diagram - Nuclear Service Cooling Water System -
System No. 1202
1.0
SNC1029806M008
Pipe Support Assembly
1.0
SNC1029806M009
Pipe Support Assembly
1.0
SNC1029806M010
Engineering Change Worksheet: Piping Class Sheet
1.0
SNC1029806WDR
Walkdown Report Cover Sheet: NSCW Strainer - 2B SI
Pump
1.0
SNC1172256
Head Stand Modification in Support of RPV Peening in
2R22
SNC1172256 FCR02
Modify base plate anchor holes for pedestal #6
03/07/2022
SNC1172256 FCR03
Structural Washer Details
03/08/2022
NMP-ES-095-F05
Design Change/Modification - Risk Mitigation Plan
1.2
PWROG-15015-P
PWROG SAMG Volume 2 Guidelines
0.0
Beyond Design Basis Events Mitigation Guidance
Standard
0.0
PWROG-18031-P
SAMG Training Standard Report and SAMG CBT SAT
Process
0.0
Miscellaneous
VEGP-1 Validation
Playbook
Scenario 1a, 1b, 2 and 3
DPG-C
SAMG Diagnostic Process Guideline
1.0
DPG-C-BD
Diagnostic Process Guideline Background Document
1.0
SAG1-1
Main Control Room Severe Accident Guideline Response
1.0
Procedures
SAG10-1
Technical Support Center Severe Accident Guideline
1.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Control SFP Level
SAG2-1
Main Control Room Severe Accident Guideline TSC
Recommending Strategies
1.0
SAG3-1
Technical Support Center Severe Accident Guideline
Inject Into Steam Generators
1.0
SAG4-1
Depressurize The RCS
1.1
SAG5-1
Inject Into RCS
1.0
SAG6-1
Technical Support Center Severe Accident Guideline
Inject Into Containment
1.0
SAG7-1
Technical Support Center Severe Accident Guideline
Reduce Containment Hydrogen
1.0
SAG8-1
Technical Support Center Severe Accident Guideline
Control Containment Pressure
1.0
SAG9-1
Technical Support Center Severe Accident Guideline
Mitigate Fission Product Release
1.0
TSG1-1
Technical Support Center Guideline Instrumentation
1.0
TSG2-1
Technical Support Center Guideline Ultimate Decision
Maker
1.0
TSG3-C
Technical Support Guideline Capabilities
1.0
TSG4-1
Technical Support Guideline Benefit Consequence
1.0
TSG5-1
Technical Support Guideline Computational Aids
1.0
Work Orders
SNC1088781, SNC1089402, SNC1089896
Corrective Action
Documents
Condition Report(s)
10848256
2408-C
7300 Circuit Board Removal, Inspection, Cleaning and
Reinstallation
24525-1
Pressurizer Pressure Protection Channel I 1P-455
Channel Operational Test and Channel Calibration
33.1
NMP-MA-014
Post Maintenance Testing/Post Modification Testing
2.4
Procedures
NMP-MA-014-001
Post Maintenance Testing Guidance
5.9
Work Orders
SNC1230817, SNC1089896, SNC1088781,
SNC1039714, SNC758755, SNC1032510, SNC1135681,
SNC1123541, SNC935271, SNC986816, SNC1036248,
SNC1114727, SNC1196185
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
Condition Report(s)
10864198, 10869667, 10869812
Corrective Action
Documents
Condition Report(s)
10866009, 10853953, 10854302, 10868840, 10868843
Corrective Action
Documents
Resulting from
Inspection
Condition Report(s)
10863278
14372B-2
Containment Penetration No. 72B RCS Loop #3
Accumulator Sample Line Local Leak Rate Test
14666-2
Train A Diesel Generator and ESFAS Test
39.2
14980B-1
Diesel Generator 1B Operability Test
31.2
24751-2
Steam Generator Level (Narrow Range) Protection
Channel I 2L-529 Channel Operational Test and Channel
Calibration
23.0
Procedures
210-C
Main Steam Line Code Safety Valve Setpoint Verification
24.1
Work Orders
SNC1116951
Corrective Action
Documents
Condition Report(s)
10821283, 10821569, 10847119
Condition Report(s)
10864506
71151
Corrective Action
Documents
Resulting from
Inspection
Corrective Action
Report(s)
300625
Drawings
2X4DB13-1
Purification and Cleanup System, System No. 1505,
1506, & 1508
34.0
Procedures
18035-C
Toxic/Asphyxiant/Flammable Gas Release
14.0