IR 05000424/2020002
| ML20227A002 | |
| Person / Time | |
|---|---|
| Site: | Vogtle, 07201039  |
| Issue date: | 08/14/2020 |
| From: | Alan Blamey NRC/RGN-II/DRP/RPB2 |
| To: | Gayheart C Southern Nuclear Operating Co |
| References | |
| IR 2020001, IR 2020002 | |
| Download: ML20227A002 (23) | |
Text
August 14, 2020
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 & 2 - INTEGRATED INSPECTION REPORT 05000424/2020002 AND 05000425/2020002 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION REPORT 07201039/2020001
Dear Ms. Gayheart:
On June 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Vogtle Electric Generating Plant, Units 1 & 2. On August 12, 2020, the NRC inspectors discussed the results of this inspection with Mr. Matt Horn and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
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 and 07201039 License Nos. NPF-68 and NPF-81
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000424 and 05000425 and 07201039
License Numbers:
Report Numbers:
05000424/2020002 and 05000425/2020002 and 07201039/2020001
Enterprise Identifier: I-2020-002-0056 and I-2020-001-0139
Licensee:
Southern Nuclear Operating Co., Inc.
Facility:
Vogtle Electric Generating Plant, Units 1 & 2
Location:
Waynesboro, GA
Inspection Dates:
April 01, 2020 to June 30, 2020
Inspectors:
G. Eatmon, Sr. Resident Inspector
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.
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 in Mode 2 as part of refueling outage cycle 22 (1R22) and returned to Rated Thermal Power (RTP) on April 5, 2020. Unit 1 operated at or near RTP for the remainder of the inspection period.
Unit 2 began the inspection period at RTP. On June 21, 2020, the unit was taken to Mode 3 for a maintenance outage in order to resolve Unit 2 Reactor Coolant Pump (RCP) #1 elevated vibrations. The unit was returned to RTP on June 25, 2020. Unit 2 operated 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 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 and during that time 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
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal hot temperatures for the following systems:
Ultimate Heat Sink Main Condenser
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather heavy thunderstorms and rain on April 23, 2020.
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 Train 'A' and 'B' Motor Driven Auxiliary Feedwater (AFW) Pump, on April 1, 2020.
- (2) Unit 2 Train 'A' Emergency Diesel Generator (EDG), on April 13, 2020.
- (3) Unit 2 Train 'B' Centrifugal Charging Pump following Solid State Protection System testing, Response Time Testing (RTT), and Inservice Testing (IST), on April 14, 2020.
- (4) Unit 1 Train 'B' Nuclear Service Cooling Water (NSCW) after RTT, on May 17, 2020.
- (5) Unit 2 Train 'A' and 'B' Residual Heat Removal (RHR) following valve IST, on June 5, 2020.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (7 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 Zone 16/18/24, Unit 1 Train A and B RHR Heat Exchanger rooms and Auxiliary Building Level C area, on April 1, 2020.
- (2) Fire Zone 4/5/9/10, Unit 1 Train A and B Containment Spray and RHR pump rooms, on April 2, 2020.
- (3) Fire Zone 145/146/160A/160B, Unit 1 Train A and B NSCW pump rooms and electrical tunnels, on April 6, 2020.
- (4) Fire Zone 71/76/77A/77B/78A/78B, Unit 1 Train A and B Battery and Emergency Switchgear rooms, on April 9, 2020.
- (5) Fire Zone 56A/56B/79A/79B/83/152, Unit 1 Train 'C' and 'D' Battery and Emergency Switchgear rooms, on April 9, 2020.
- (6) Fire Zone 143/161/163, Unit 2 Train 'A' EDG rooms and electrical tunnels, on April 13, 2020.
- (7) Fire Zone 49/52, Unit 2 Train A and 'B Auxiliary Component Cooling Water Heat Exchanger rooms, on April 27, 2020.
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Unit 2 Train 'A' and 'B' Component Cooling Water (CCW) pump rooms, on April 16, 2020.
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Unit 1 Train 'A' CCW Heat Exchanger.
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 2 power descension (Mode 1) and ascension (Mode 3, 2, 1), on June 21, 2020, and June 24, 2020, respectively.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a simulator scenario consisting of loss of Spent Fuel Pool inventory, various transients, and a small to large break Loss of Coolant Accident on May 14, 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) Unit 1/2, NSCW unavailability performance criteria, on April 7, 2020.
- (2) Unit 1 Train 'A' Motor Driven AFW pump natural frequency vibration and oil sampling, on April 8, 2020.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed;
- (1) Unit 2 NSCW Fan Phoenix risk modeling, on April 29, 2020.
- (2) Unit 1 Train 'A' CCW system outage with utilization of Risk Informed Completion Time (RICT), on May 26, 2020.
- (3) Unit 1 NSCW Motor #5 replacement, on June 2, 2020.
- (4) Unit 2 Emergent Issue on RCP #1 vibrations, on June 15, 2020.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Report of Defects and Noncompliance - Westinghouse Part 21 Notification for Control Rod Drive Mechanism thermal sleeve degradation, on April 1, 2020.
- (2) Report of Defects and Noncompliance - Schultz Electric Part 21 Notification for NSCW Pump Motors, on May 4, 2020.
- (3) Unit 2 Intermediate Stop Valve #3 failure to stroke, on June 1, 2020.
- (4) Unit 2 CCW system Operable but Degraded Nonconforming due to NRC-identified flood calculation issues, on June 3, 2020.
- (5) Unit 2 Train 'B' EDG Control Room Voltage Indication Failing Low, on June 15, 2020.
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) SNC922254, Unit 1 AFW orifice replacement for the Turbine Driven AFW Pump and Motor Driven AFW Pumps, on April 2, 2020.
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 Train 'B' Motor Driven AFW planned system outage, on April 14, 2020.
- (3) Unit 1 Electronically Operated Control Rod Drive Shaft Latching/Unlatching Tool after reinstallation from 1R22, on April 30, 2020.
- (4) Diesel Fire Pump (DFP) #1 planned system outage, on April 30, 2020.
- (5) Unit 1 Train 'A' Room Cooler Group 1 Fragnet, on May 7, 2020.
- (6) DFP #2 corrective action work, on June 8, 2020.
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (2 Samples)
- (1) The inspectors evaluated refueling outage 1R22 activities from April 1, 2020 to April 5, 2020. The inspectors completed inspection procedure Section C during this inspection period.
- (2) The inspectors evaluated Unit 2 maintenance outage activities related to RCP #1 elevated vibrations from June 21, 2020 to June 25, 2020.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
Inservice Testing (IP Section 03.01) (2 Samples)
- (1) Unit 1 Train 'A', 'B', and 'C' AFW Pressure Test, on April 22, 2020.
- (2) Unit 2 Train 'A' Safety Injection System valve IST, on June 30,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===
- (1) Unit 1 (April 1, 2019 - March 31, 2020)
- (2) Unit 2 (April 1, 2019 - March 31, 2020)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 1 (April 1, 2019 - March 31, 2020)
- (2) Unit 2 (April 1, 2019 - March 31, 2020)
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in Quality Assurance (QA) Records that might be indicative of a more significant safety issue. The inspectors determined there is an adverse trend of QA Records not being complete, accurate, and/or available as required by 10 CFR 50, Appendix B, Criterion XVII, "Quality Assurance Records," and licensee programmatic requirements. The inspection report documents in total three minor violations associated with the regulatory requirements for QA records. Two minor violations are documented under Section 71152 and one minor violation is documented under Section 71153, all three reflecting the potential adverse trend related to QA records.
The licensee captured this adverse trend in their Corrective Action Program under Condition Report (CR) 10719715.
Annual Follow-up of Selected Issues (IP Section 02.03) (3 Samples)
- (1) Review of work planning, management and control during routine operation, system outages and RICT application, specifically scoping work cycle meetings and evaluation, system outage for 2B EDG, Unit 1 Refueling Outage 22, and emergent COVID-19 impacts.
- (2) Unit 2 Loop 2 Train 'B' Main Steam Isolation Valve closure resulting in a Reactor Trip, Corrective Action Report 276561.
- (3) The inspectors reviewed the licensees inspection and evaluation of qualified coatings using Licensee procedure NMP-MA-011-006, Procedure for Coating Condition Assessments, for the Unit 1 Containment Liner during Refueling Outage 22.
The inspectors performed a material condition inspection of the containment liner coating, noting deficiencies for accessible areas followed by review of the licensees results. The results of the coating inspection for the Containment Liner are quality assurance records and are retained for plant life. The inspectors determined that the licensee, in general, identified coating deficiencies accurately and in accordance with procedure, including the requirements to specifically document relevant information such as the inspector, observation type, and results. The inspectors identified that the licensee failed to create or retain records regarding the acceptability of the inspection results, and actions taken in connection with the deficiencies noted for Unit 1 during Refueling Outage 22.
Additionally, the licensee identified in CR 10704211 an irretrievable quality assurance record for the previous containment liner coating inspection for both Unit 1 in Refueling Outage 21 and Unit 2 in Refueling Outage 20.
71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
- (1) LER 05000425/2019-002-00, Microswitch failure causes closure of Main Steam Isolation Valve and subsequent Automatic Reactor Trip (ADAMS Accession No.
ML19247C285). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
60855.1 - Operation of an Independent Spent Fuel Storage Installation at Operating Plants Operation of an Independent Spent Fuel Storage Installation at Operating Plants
- (1) The inspectors evaluated the licensees activities related to long-term operation and monitoring of their independent spent fuel storage installation on April 30,
INSPECTION RESULTS
Minor Violation 71152 Minor Violation: The inspectors identified a performance deficiency of 10 CFR Part 50, Appendix B, Criterion XVII, Quality Assurance Records, for the failure to maintain records to furnish evidence of activities affecting quality. Specifically, the licensee failed to maintain the containment liner coating inspection results regarding the acceptability, and the action taken in connection with any deficiencies noted for Unit 1 Refueling Outage 22. The licensees inspection of the containment liner coating is described in procedure, NMP-MA-011-006, Procedure for Coating Condition Assessments, which designates inspection of the containment coating liner as a quality assurance record. Section 6.0, Records, of the procedure states that the results of the inspection and assessment of the containment liner coating is a quality assurance record required to be maintained for the lifetime of the plant.
Screening: The inspectors determined the performance deficiency was minor.
This performance deficiency was screened as minor using Manual Chapter 0612, Issue Screening, Appendix B, Additional Issue Screening Guidance, and Appendix E, Examples of Minor Issues, after all screening questions were answered NO.
The performance deficiency has been entered the Corrective Action Program as CR 10719714.
Enforcement:
This failure to comply with 10 CFR Part 50, Appendix B, Criterion XVII, "Quality Assurance Records," constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
Minor Violation 71152 Minor Violation: The licensee identified a performance deficiency of 10 CFR Part 50, Appendix B, Criterion XVII, Quality Assurance Records, for the failure to maintain retrievable records to furnish evidence of activities affecting quality. Specifically, the licensee failed to retain any inspection records of the coating condition inspection and assessment for Unit 1 Refueling Outage 21 and Unit 2 Refueling Outage 20. Licensees procedure NMP-MA-011-006, Procedure for Coating Condition Assessments, section 6.0, Records, identifies the coating assessment as a quality assurance record, required to be maintained for the lifetime of the plant. Specifically, the procedure states that (Coating)
Condition Assessment Recordsshall be submitted to the applicable site Document Control Department and maintained as an official QA record. Licensee procedure NMP-AD-025, Quality Assurance and Non-Quality Assurance Records Administration, documented the missing quality assurance record in a condition report.
Screening: The inspectors determined the performance deficiency was minor.
This performance deficiency was screened as minor using Manual Chapter 0612, Issue Screening, Appendix B, Additional Issue Screening Guidance and Appendix E, Examples of Minor Issues, after all screening questions were answered NO.
The performance deficiency has been entered the Corrective Action Program as CR 10704211.
Enforcement:
This failure to comply with 10 CFR Part 50, Appendix B, Criterion XVII, "Quality Assurance Records," constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
Minor Violation 71153 Minor Violation: The inspectors identified a performance deficiency of 10 CFR Part 50, Appendix B, Criterion XVII, Quality Assurance Records, for the failure to maintain records to furnish evidence of activities affecting quality for the results of the Unit 2 Reactor Trip on July 19, 2019. Specifically, 1006-C-D52-2019, "Reactor Trip Review," which was captured as a Quality Record in Documentum, the official record repository database, contained approximately 19 pages of unreadable data associated with plant and system response. The unreadable portions of the record were able to be reproduced and corrected.
Screening: The inspectors determined the performance deficiency was minor. This violation was screened as minor using Manual Chapter 0612, Appendix B, Additional Issue Screening Guidance, when all more-than-minor screening questions were answered NO.
The performance deficiency has been entered into the Corrective Action Program as Condition Report 10717276 and corrected.
Enforcement:
This failure to comply with 10 CFR Part 50, Appendix B, Criterion XVII, "Quality Assurance Records," constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 20, 2020, the inspectors presented the integrated inspection results to Mr.
Drayton Pitts and other members of the licensee staff.
- On August 12, 2020, the inspectors discussed the corrective actions for single failure vulnerabilities identified in CR 10606308 with Mr. Matt Horn and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
10718800
Corrective Action
Documents
Resulting from
Inspection
10704755,
10704790,
10704737
Engineering
Changes
SNC1042051
U1 & U2 Low Vacuum Alarm and C-9 Interlock Setpoint
Changes
Engineering
Evaluations
SNC1042259
C-9 Setpoint Change U1 & U2
08/27/2019
Miscellaneous
NMP-GM-025
Site Certification for Summer Readiness
05/07/2020
Procedures
11889-C
Severe Weather Checklist
17019-1
Annunciator Response Procedures for ALB 19 on Panel 1B2
on MCB
17019-2
Annunciator Response Procedures for ALB 19 on Panel 2B2
on MCB
27.1
Drawings
1X4DB133-1
P&I Diagram, Nuclear Service Cooling Water System,
System No. 1202
1X4DB133-2
P&I Diagram, Nuclear Service Cooling Water System,
System No. 1202
1X4DB161-1
P&I Diagram, Auxiliary Feedwater System, Condensate
Storage & Degasifier System, System No 1302
1X4DB161-2
P&I Diagram, Auxiliary Feedwater System, System No 1302
2X4DB116-1
P&I Diagram - Chemical & Volume Control System - System
No. 1208
49.0
2X4DB116-2
P&I Diagram - Chemical & Volume Control System - System
No. 1208
2.0
2X4DB119
P&I Diagram - Safety Injection System - System No. 1204
28.0
2X4DB121
P&I Diagram - Safety Injection System - System No. 1204
50.0
2X4DB122
P&ID Diagram Residual Heat Removal System No. 1205
54.0
2X4DB170-1
PI&Diagram, Diesel Generator System, Train A, System No.
2403
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Daily Safety & Alignment Meeting
05/14/2020
Plan of the Day
05/14/2020
Procedures
11145-2
Diesel Generator Alignment
14.1
11150-1
Nuclear Service Cooling Water System Alignment
13006-2
Chemical and Volume Control System
13011-2
Residual Heat Removal System
13610-1
Auxiliary Feedwater System
14802B-1
Train B NSCW Pump/Check Valve IST and Response Time
Test
2.5
14808B-2
Train B Centrifugal Charging Pump and Check Valve IST
and Response Time Test
6.0
14825-2
Quarterly Inservice Valve Test
2
14980A-2
Diesel Generator 2A Operability Test
31.1
Work Orders
SNC10556911
5/3/2020
Calculations
X4C2301S310
VEGP SSEL and Safe Shutdown Fault Tree
X4C2301S311
VEGP Multiple Spurious Operations Analysis
4.0
X4C2301S312
Evaluation of Emergency Diesel Generator Capacity for
Abnormal Loading Conditions Due to a Fire
1.0
X4C2301S315
Circuit Analysis Calculation for Post Fire Safe Shutdown
X4C2301S316
Post Fire Safe Shutdown Compliance Analysis
X4C2301S317
Post Fire Safe Shutdown Manual Action Feasibility Study
Corrective Action
Documents
Resulting from
Inspection
10698568
Fire Plans
2749-2
Zone 49 - Auxiliary Building - Level 1, Train "A" ACCW Hx
Room Fire Fighting Preplan
2752-2
Zone 52 - Auxiliary Building - Level 1, Train "B" ACCW HX
Fire Fighting Preplan
2756A-1
Zone 56A - Control Building Level B Fire Fighting Preplan
0.2
2756B-1
Zone 56B - Control Building Level B Fire Fighting Preplan
1.2
2771-1
Zone 71 - Control Building Level B Fire Fighting Preplan
4.1
2776-1
Zone 76 - Control Building - Level B Fire Fighting Preplan
2.1
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2777A-1
Zone 77A - Control Building - Level B Fire Fighting Preplan
1.1
2777B-1
Zone 77B - Control Building Level B Fire Fighting Preplan
1.2
2778A-1
Zone 78A - Control Building Level B Fire Fighting Preplan
2.1
2778B-1
Zone 78B - Control Building Level B Fire Fighting Preplan
1.2
2779A-1
Zone 79A - Control Building Level B Fire Fighting Preplan
0.2
2779B-1
Zone 79B - Control Building Level B Fire Fighting Preplan
1.2
2783-1
Zone 83 - Control Building - Level B Fire Fighting Preplan
2.2
2843-2
Zone 143 - Diesel Generator Building Electrical Tunnel A-
Level B Fire Fighting Preplan
2852-1
Zone 152 - Control Building - Level B Fire Fighting Preplan
2861-2
Zone 161 - Diesel Generator Building Fire Fighting Preplan
1.1
2863-2
Zone 163 - Diesel Generator Building - Train A DFO Day
Tank Fire Fighting Preplan
0.2
Procedures
2000-C
2040-C
Fire Protection Functionality and LCO Requirements
46.3
2704-1
Zone 4 - Auxiliary Building Wing Area Fire Fighting Preplan
2.2
2705-1
Zone 5 - Auxiliary Building - Level D Fire Fighting Preplan
4.2
2709-1
Zone 9 - Auxiliary Building - Level D Fire Fighting Preplan
3.2
2710-1
Zone 10 - Auxiliary Building Level D Fire Fighting Preplan
4.2
2716-1
Zone 16 - Auxiliary Building RHR Heat Exchanger Train B
Room Fire Fighting Preplan
3.2
2718-1
Zone 18 - Auxiliary Building - Level C Fire Fighting Preplan
3.2
2724-1
Zone 24 - Auxiliary Building - Level C Fire Fighting Preplan
5.0
2845-1
Zone 145 - Tunnels 1T2A, 1T3A, and 1T5A Fire Fighting
Preplan
1.3
2846-1
Zone 146 - Tunnels 1T2B and 1T5B Fire Fighting Preplan
2.0
2860A-1
Zone 160A - NSCW Pumphouse - Train A Fire Fighting
Preplan
2860B-1
Zone 160B - NSCW Pumphouse - Train B Fire Fighting
Preplan
0.2
Calculations
Flooding Analysis - Auxiliary Building, Level A
Drawings
1X4DB147-2
P&I Diagram - Aux Bldg Flood Retaining Rooms Alarms &
Drains - System No. 1218
9.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2X4DB126
P&I Diagram - Waste Processing System - Liquid System
No. 1901
27.0
2X4DB145-3
P&I Diagram - Auxiliary Building & Misc. Drains - System
No. 1215
14.0
2X4DB145-5
P&I Diagram - Auxiliary Building & Misc. Drains - System
No. 1215
2.0
2X4DB145-6
P&I Diagram - Auxiliary Building & Misc. Drains - System
No. 1215
14.0
2X4DB147-2
P&I Diagram - Aux Bldg Flood Retaining Rooms Alarms &
Drains - System No. 1218
8.0
Procedures
219-2
Auxiliary and Containment Buildings and Miscellaneous
Drain Systems Alignment
219-2
Auxiliary and Containment Buildings and Miscellaneous
Drain System
31.3
Corrective Action
Documents
10711871,
10712138
Miscellaneous
NMP-ES-012-001
Visual Inspection Report of 1A CCW Heat Exchanger
05/29/2020
RBD-V12-5069-
203
10CFR50.69 Categorization of the Component Cooling
Water System
NDE Reports
SNC814761
Eddy Current Inspection Results - Component Cooling
Water Heat Exchanger 1A
05/28/2020
Procedures
NMP-ES-012
Heat Exchanger Program
2.02
NMP-ES-012-001
Inspection of Heat Exchangers
2.0
71111.11Q Miscellaneous
V-RQ-SE-20204
20 Segment 2 SM Choice
2.0
Procedures
2004-2
Power Operation (Mode 1)
4.0
13003-2
Reactor Coolant Pump Operation
2.1
17008-2
Annunciator Response Procedures for ALB 08 on Panel 2A2
on MCB
15.3
Calculations
V-RIE-MR-U00
Vogtle 1&2 Maintenance Rule Risk Ranking and
Performance Criteria Assessment
Corrective Action
Documents
10693151,
10692582,
1069360, 277408,
1063278
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
10703555
Engineering
Changes
SNC1083487
1A MDAFW Pump Structure Stiffening
3/14/2020
Miscellaneous
11302P4003
1A MDAFW Oil Sample Analysis Report for Outboard Pump
Bearing
3/27/2020
11302P4003
1A MDAFW Oil Sample Analysis Report for Inboard Pump
Bearing
3/27/2020
11302P4003M01
1A MDAFW Oil Sample Analysis Report for Outboard Motor
Bearing
3/27/2020
11302P4003M01
1A MDAFW Oil Sample Analysis Report for Inboard Motor
Bearing
3/27/2020
MREP2019-12
Maintenance Rule Expert Panel Meeting #2019-12
07/10/2019
RBA-20-003-V
Risk-Based Analysis: RBA-20-003-V
04/24/2020
Procedures
NMP-ES-074-006
Fleet Lubrication Instruction
Corrective Action
Documents
10716920,
10716998,
10716999
Miscellaneous
Plan of the Day
05/29/2020
Phoenix A4 Risk
05/26/2020
Phoenix A4 Risk
05/29/2020
Unit 1 Control Room Logs
06/02/2020
Phoenix A4 Risk
06/02/2020
Plan of the Day
06/02/2020
Plan of the Day
05/26/2020
NMP-DP-001
High Risk Planning Worksheet
16.0
NMP-GM-042
Technical Decision Making Form - U2 RCP #1 2R21 Outage
Work
05/08/2020
NMP-OS-003-F01 ODMI VNP2-20-001 U2 RCP1 Vibrations
Reactor Coolant Pump Seal and Motor Operating
Parameters - Phase III
Procedures
NMP-DP-001
Operational Risk Awareness
16.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NMP-GM-031-
2-F01
RICT Projection Details
2.0
Calculations
SNC1096341-01
Evaluation of Flooding Levels in the CCW Pump Rooms
from Breaks in Opposite Train Rooms
05/15/2020
Corrective Action
Documents
10677033,
277188, 1063131,
10704907,
10712447,
10715645,
277804
Corrective Action
Documents
Resulting from
Inspection
1067495,
10708494
Drawings
1X6AB02-00109
Coordinates & Elevation of Closure Head Penetrations
2.0
1X6AB02-00110
Record Data Sheet
2.0
One Line Diagram - Diesel Generators 2A & 2B Relays &
Meters
2.0
2X6AB02-00140
Unit 2 Closure Head As-Builts
3.0
Miscellaneous
Unit 2 Outage 20 Thermal Sleeve Data
Unit 1 Outage 21 Thermal Sleeve Data
1X4AF02-00093-
Instruction Manual Nuclear Service Cooling Water Pump
ANSI/ANS-56.11-
1988Property "ANSI code" (as page type) with input value "ANSI/ANS-56.11-</br></br>1988" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process.
Design Criteria for Protection Against the Effects of
Compartment Flooding in Light Water Reactor Plants
LTR-RIDA-18-277 Evaluation of Thermal Sleeve Flange Wear Condition and
Recommendation
09/27/2018
LTR-RIDA-19-60
Evaluation of Vogtle Unit 2 Thermal Sleeve Flange Wear
Conditions and Recommendations
03/21/2019
MWO
SNG10097724
Class 1E Motor Repair Job Package, Repair Shop Job
Number 513718
07/20/2015
MWO SNG27007-
0035
Class 1E Motor Repair Job Package, Repair Shop Job
Number 49680
03/06/2014
NSAL-20-1
Reactor Vessel Head Control Rod Drive Mechanism
2/14/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Penetration Thermal Sleeve Corss-Sectional Failure
PWROG-16003-P
Evaluation of Potential Thermal Sleeve Flange Wear
Procedures
14980B-2
Diesel Generator 2B Operability Test
30.1
SCL00160
Maintenance Requirements and Special Instructions for
General Electric Frame 6338 Motor
8.2
Work Orders
SNC131625
NSCW 10 YR Major Motor Refurbishment
Disassemble/Clean
01/18/2012
Calculations
X4C1302V15
AFW Hydraulic Analysis
Corrective Action
Documents
Resulting from
Inspection
10710726
Unit 1 TDAFW Room Delay Door difficult to Operate
5/22/2020
Engineering
Changes
SNC922254
U1 AFW Orifice Replacement
Work Orders
SNC922254
Advanced Work Authorization Form for Engineering Change
Number: DCP SNC922254
Corrective Action
Documents
10582508,
10702730,
10715307
Corrective Action
Documents
Resulting from
Inspection
10706804,
277823,
10711382
1B MDAFW Fragnet 4/14/20
Engineering
Changes
SNC922254
U1 AFW Orifice Replacement
03/27/2020
Miscellaneous
Daily Safety & Alignment Meeting
04/30/2020
Plan of the Day
04/14/2020
Plan of the Day
05/07/2020
Plan of the Day
04/30/2020
Procedures
13903-C
Fire Protection System Opeation
46.4
14807B-1
Train B Motor Driven Auxiliary Feedwater Pump / Check
Valve Inservice and Response Time Test
5.1
14951-C
Fire Suppression System Operability Tests (FSAR Fire
Protection Surveillance)
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
27585-C
Diesel Engine Driven Fire Pump CFP11E Series Inspection
5.1
2040-C
Fire Protection Functionality and LCO Requirements
46.3
93141-C
Control Rod Drive Shaft Latching and Drag Test Data Sheet,
Data Sheet 5
03/23/2020
93141-C
Control Rod Drive Shaft Latch Verification, Data Sheet 6
03/23/2020
931410-C
Electrically Operated CRDS Latching/Unlatching Tool
NMP-MA-010
Erecting, Modifying, and Disassembling Scaffolding
2.0
Work Orders
SNC1029743,
SNC922254,
SNC777146,
SNC898661,
SNC855658,
SNC895749,
SNC930133,
SNC9666642,
SNC995732,
SNC1068985,
SNC908146,
SNC999393,
SNC942721,
SNC974855,
SNC1011038,
SNC1012572,
SNC1039587,
SNC1068381
Miscellaneous
Entrant's Daily Tool Log
03/12/2020
Shift Operations work schedule
04/27/2020
Procedures
10032-C
Outage Risk Assessment Monitoring
03/08/2020
10032-C
Outage Risk Assessment Monitoring
03/09/2020
2003-2
Reactor Startup (Mode 3 to Mode 2)
3.1
2004-2
Power Operation (Mode 1)
4.0
13003-2
Reactor Coolant Pump Operation
2.2
NMP-AD-016-
004-F01
Security - Quarterly Review of Work Hours
1.2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NMP-AD-016-
004-F01
Operations - Quarterly Review of Work Hours
1.2
Corrective Action
Documents
10686257,
10690899,
10687515,
10705430,
10705826,
10719246
Miscellaneous
AX4AK01-20052-
Emergency Diesel Generator Operation & Calibration 701
Digital Speed Control for Reciprocating Engines
07/09/1996
Procedures
14825-2
Quarterly Inservice Valve Test
2
14825-2
Quarterly Inservice Valve Test
84003-C
System Operating Pressure Test, Unit 1, TDAFW Pump
3/19/2020
84003-C
System Operating Pressure Test, Unit 1, AFW system, Train
A
3/20/2020
84003-C
System Operating Pressure Test, Unit 1, AFW system, Train
B
3/20/2020
84003-C
Pressure Testing of Piping and Components
9.4
Work Orders
SNC1056609,
SNC1067043
71151
Miscellaneous
U1 Cycle 22 UID Assessment April 2019 - March 2020
U2 Cycle 21 UID Assessment April 2019 - March 2020
RCS DEI Data April 2019 - March 2020
Regulatory Assessment Performance Indicator Guideline
Corrective Action
Documents
10616930,
10621114,
10632946,
10636146,
10653676,
1065037,
10670569,
10671610,
10690609,
10693041,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
10709801,
10717090,
10704211,
10619056,
10634755,
10630238,
10630231,
10630409,
10630260,
10638064,
10630323,
1048496,
1050235, 276561,
1052813
Corrective Action
Documents
Resulting from
Inspection
10717276,
10719714
Miscellaneous
T+1 Meeting Notes for Work Week 2007: 2/10/2020-
2/16/2020
Gaps for Work Week 2006 (2/3/2020-2/9/2020)
Agenda for T+1 (Critique) for Work Week (Code) 2019
5/18/2020
Agenda for T+1 (Critique) for Work Week (Code) 2017
5/4/2020
Gaps for Work 2B EDG AOT (1/27/20-1/29/20)
T+1 Meeting Notes for Work Week 2004: 1/20/2020-
1/26/2020
Gaps for Work Week 2004 (1/20/2020-1/26/2020)
T+1 Meeting Notes for Work Week 2005: 1/27/2020-
2/2/2020
Agenda for T-5 (Readiness Review - Schedule Freeze)
Agenda for T-9 (Scope Freeze)
T-16 (Select Scope)
T-24 (Base Scope) for Work Week
Gaps for Work Week 2005 (1/27/2020 - 2/2/2020)
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
T+1 Meeting Notes for Work Week 2006: 2/3/2020-2/9/2020
Agenda for T-2 (Execution Readiness Challenge Board) for
Work Week (Code) 2023
5/19/2020
Gaps for Work Week 2007 (2/10/2020 - 2/16/2020)
AX4AR17-00189
Main Steam Isolation Valve Maintenance Manual
14.0
NMP-GM-006-
GL06
System Outage Guidance, Attachment 3, System Outage
Critique for 2B2403DGAOT
Procedures
26854-C
Main Steam Isolation Valve Actuator Maintenance
45.0
NMP-ES-006
Preventive Maintenance Implementation and Continuing
Equipment Reliability Improvement
2.0
NMP-GM-005-
005
Human Performance Clock Reset Criteria
5.1
Work Orders
SNC1035937,
SNC385403
Corrective Action
Documents
10630238,
276561
Drawings
Elementary Diagram Main Steam System 2Hv-3016B
2.0
2X4AR17-00217
Generator Assembly Actuator
6.0
2X4AR17-00219-
Generator Assembly Actuator Sheet 001
2X4AR17-00219-
Generator Assembly Actuator Sheet 002
2X4AR17-00224
Air & Hydraulic System Schematic
K
Miscellaneous
10006-C-DS1-
2019
Reactor Trip Review
07/19/2019
10006-C-DS2-
2019
Reactor Trip Review
07/19/2019
AX4AR17-00189
Main Steam Isolation Valve Maintenance Manual
14.0