IR 05000424/2020002

Integrated Inspection Report 05000424/2020002 and 05000425/2020002 and Independent Spent Fuel Storage Installation Report 07201039/2020001

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: NPF-68 and NPF-81 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 Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Vogtle Electric Generating Plant, Units 1

& 2, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

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.

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.

(2) Unit 1 Train 'A' Motor Driven AFW Pump following AFW Orifice Replacement, on April 29, 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)

(1) Unit 1 Train 'A' EDG fast start and hot restart, on April 28, 2020.

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 Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action 10718800

Documents

Corrective Action 10704755,

Documents 10704790,

Resulting from 10704737

Inspection

Engineering SNC1042051 U1 & U2 Low Vacuum Alarm and C-9 Interlock Setpoint 0

Changes Changes

Engineering SNC1042259 C-9 Setpoint Change U1 & U2 08/27/2019

Evaluations

Miscellaneous NMP-GM-025 Site Certification for Summer Readiness 05/07/2020

Procedures 11889-C Severe Weather Checklist 27

17019-1 Annunciator Response Procedures for ALB 19 on Panel 1B2 29

on MCB

17019-2 Annunciator Response Procedures for ALB 19 on Panel 2B2 27.1

on MCB

71111.04 Drawings 1X4DB133-1 P&I Diagram, Nuclear Service Cooling Water System, 56

System No. 1202

1X4DB133-2 P&I Diagram, Nuclear Service Cooling Water System, 52

System No. 1202

1X4DB161-1 P&I Diagram, Auxiliary Feedwater System, Condensate 46

Storage & Degasifier System, System No 1302

1X4DB161-2 P&I Diagram, Auxiliary Feedwater System, System No 1302 29

2X4DB116-1 P&I Diagram - Chemical & Volume Control System - System 49.0

No. 1208

2X4DB116-2 P&I Diagram - Chemical & Volume Control System - System 32.0

No. 1208

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. 43

2403

Inspection Type Designation Description or Title Revision or

Procedure 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 18

13006-2 Chemical and Volume Control System 99

13011-2 Residual Heat Removal System 70

13610-1 Auxiliary Feedwater System 53

14802B-1 Train B NSCW Pump/Check Valve IST and Response Time 12.5

Test

14808B-2 Train B Centrifugal Charging Pump and Check Valve IST 6.0

and Response Time Test

14825-2 Quarterly Inservice Valve Test 102

14980A-2 Diesel Generator 2A Operability Test 31.1

Work Orders SNC10556911 5/3/2020

71111.05 Calculations X4C2301S310 VEGP SSEL and Safe Shutdown Fault Tree 5

X4C2301S311 VEGP Multiple Spurious Operations Analysis 4.0

X4C2301S312 Evaluation of Emergency Diesel Generator Capacity for 1.0

Abnormal Loading Conditions Due to a Fire

X4C2301S315 Circuit Analysis Calculation for Post Fire Safe Shutdown 2

X4C2301S316 Post Fire Safe Shutdown Compliance Analysis 3

X4C2301S317 Post Fire Safe Shutdown Manual Action Feasibility Study 2

Corrective Action 10698568

Documents

Resulting from

Inspection

Fire Plans 92749-2 Zone 49 - Auxiliary Building - Level 1, Train "A" ACCW Hx 1

Room Fire Fighting Preplan

2752-2 Zone 52 - Auxiliary Building - Level 1, Train "B" ACCW HX 1

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 Type Designation Description or Title Revision or

Procedure 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- 3

Level B Fire Fighting Preplan

2852-1 Zone 152 - Control Building - Level B Fire Fighting Preplan 3

2861-2 Zone 161 - Diesel Generator Building Fire Fighting Preplan 1.1

2863-2 Zone 163 - Diesel Generator Building - Train A DFO Day 0.2

Tank Fire Fighting Preplan

Procedures 92000-C Fire Protection Program 27

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 3.2

Room Fire Fighting Preplan

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 1.3

Preplan

2846-1 Zone 146 - Tunnels 1T2B and 1T5B Fire Fighting Preplan 2.0

2860A-1 Zone 160A - NSCW Pumphouse - Train A Fire Fighting 1

Preplan

2860B-1 Zone 160B - NSCW Pumphouse - Train B Fire Fighting 0.2

Preplan

71111.06 Calculations X6CXC-28 Flooding Analysis - Auxiliary Building, Level A 11

Drawings 1X4DB147-2 P&I Diagram - Aux Bldg Flood Retaining Rooms Alarms & 9.0

Drains - System No. 1218

Inspection Type Designation Description or Title Revision or

Procedure Date

2X4DB126 P&I Diagram - Waste Processing System - Liquid System 27.0

No. 1901

2X4DB145-3 P&I Diagram - Auxiliary Building & Misc. Drains - System 14.0

No. 1215

2X4DB145-5 P&I Diagram - Auxiliary Building & Misc. Drains - System 12.0

No. 1215

2X4DB145-6 P&I Diagram - Auxiliary Building & Misc. Drains - System 14.0

No. 1215

2X4DB147-2 P&I Diagram - Aux Bldg Flood Retaining Rooms Alarms & 8.0

Drains - System No. 1218

Procedures 11219-2 Auxiliary and Containment Buildings and Miscellaneous 27

Drain Systems Alignment

219-2 Auxiliary and Containment Buildings and Miscellaneous 31.3

Drain System

71111.07A Corrective Action 10711871,

Documents 10712138

Miscellaneous NMP-ES-012-001 Visual Inspection Report of 1A CCW Heat Exchanger 05/29/2020

RBD-V12-5069- 10CFR50.69 Categorization of the Component Cooling 1

203 Water System

NDE Reports SNC814761 Eddy Current Inspection Results - Component Cooling 05/28/2020

Water Heat Exchanger 1A

Procedures NMP-ES-012 Heat Exchanger Program 12.02

NMP-ES-012-001 Inspection of Heat Exchangers 2.0

71111.11Q Miscellaneous V-RQ-SE-20204 2020 Segment 2 SM Choice 2.0

Procedures 12004-2 Power Operation (Mode 1) 4.0

13003-2 Reactor Coolant Pump Operation 52.1

17008-2 Annunciator Response Procedures for ALB 08 on Panel 2A2 15.3

on MCB

71111.12 Calculations V-RIE-MR-U00 Vogtle 1&2 Maintenance Rule Risk Ranking and 2

Performance Criteria Assessment

Corrective Action 10693151,

Documents 10692582,

1069360, 277408,

1063278

Inspection Type Designation Description or Title Revision or

Procedure Date

Corrective Action 10703555

Documents

Resulting from

Inspection

Engineering SNC1083487 1A MDAFW Pump Structure Stiffening 3/14/2020

Changes

Miscellaneous 11302P4003 1A MDAFW Oil Sample Analysis Report for Outboard Pump 3/27/2020

Bearing

11302P4003 1A MDAFW Oil Sample Analysis Report for Inboard Pump 3/27/2020

Bearing

11302P4003M01 1A MDAFW Oil Sample Analysis Report for Outboard Motor 3/27/2020

Bearing

11302P4003M01 1A MDAFW Oil Sample Analysis Report for Inboard Motor 3/27/2020

Bearing

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 4

71111.13 Corrective Action 10716920,

Documents 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 05/08/2020

Work

NMP-OS-003-F01 ODMI VNP2-20-001 U2 RCP1 Vibrations 3

PWROG-16069 Reactor Coolant Pump Seal and Motor Operating 0

Parameters - Phase III

Procedures NMP-DP-001 Operational Risk Awareness 16.0

Inspection Type Designation Description or Title Revision or

Procedure Date

NMP-GM-031- RICT Projection Details 2.0

2-F01

71111.15 Calculations SNC1096341-01 Evaluation of Flooding Levels in the CCW Pump Rooms 05/15/2020

from Breaks in Opposite Train Rooms

Corrective Action 10677033,

Documents 277188, 1063131,

10704907,

10712447,

10715645,

277804

Corrective Action 1067495,

Documents 10708494

Resulting from

Inspection

Drawings 1X6AB02-00109 Coordinates & Elevation of Closure Head Penetrations 2.0

1X6AB02-00110 Record Data Sheet 2.0

2X3D-AA-K01A One Line Diagram - Diesel Generators 2A & 2B Relays & 12.0

Meters

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 8

ANSI/ANS-56.11- Design Criteria for Protection Against the Effects of

1988 Compartment Flooding in Light Water Reactor Plants

LTR-RIDA-18-277 Evaluation of Thermal Sleeve Flange Wear Condition and 09/27/2018

Recommendation

LTR-RIDA-19-60 Evaluation of Vogtle Unit 2 Thermal Sleeve Flange Wear 03/21/2019

Conditions and Recommendations

MWO Class 1E Motor Repair Job Package, Repair Shop Job 07/20/2015

SNG10097724 Number 513718

MWO SNG27007- Class 1E Motor Repair Job Package, Repair Shop Job 03/06/2014

0035 Number 49680

NSAL-20-1 Reactor Vessel Head Control Rod Drive Mechanism 02/14/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

Penetration Thermal Sleeve Corss-Sectional Failure

PWROG-16003-P Evaluation of Potential Thermal Sleeve Flange Wear 2

Procedures 14980B-2 Diesel Generator 2B Operability Test 30.1

SCL00160 Maintenance Requirements and Special Instructions for 8.2

General Electric Frame 6338 Motor

Work Orders SNC131625 NSCW 10 YR Major Motor Refurbishment 01/18/2012

Disassemble/Clean

71111.18 Calculations X4C1302V15 AFW Hydraulic Analysis 3

Corrective Action 10710726 Unit 1 TDAFW Room Delay Door difficult to Operate 5/22/2020

Documents

Resulting from

Inspection

Engineering SNC922254 U1 AFW Orifice Replacement 2

Changes

Work Orders SNC922254 Advanced Work Authorization Form for Engineering Change 1

Number: DCP SNC922254

71111.19 Corrective Action 10582508,

Documents 10702730,

10715307

Corrective Action 10706804, 1B MDAFW Fragnet 4/14/20

Documents 277823,

Resulting from 10711382

Inspection

Engineering SNC922254 U1 AFW Orifice Replacement 03/27/2020

Changes

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 5.1

Valve Inservice and Response Time Test

14951-C Fire Suppression System Operability Tests (FSAR Fire 34

Protection Surveillance)

Inspection Type Designation Description or Title Revision or

Procedure 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, 03/23/2020

Data Sheet 5

93141-C Control Rod Drive Shaft Latch Verification, Data Sheet 6 03/23/2020

931410-C Electrically Operated CRDS Latching/Unlatching Tool 1

NMP-MA-010 Erecting, Modifying, and Disassembling Scaffolding 12.0

Work Orders SNC1029743,

SNC922254,

SNC777146,

SNC898661,

SNC855658,

SNC895749,

SNC930133,

SNC9666642,

SNC995732,

SNC1068985,

SNC908146,

SNC999393,

SNC942721,

SNC974855,

SNC1011038,

SNC1012572,

SNC1039587,

SNC1068381

71111.20 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 52.2

NMP-AD-016- Security - Quarterly Review of Work Hours 1.2

004-F01

Inspection Type Designation Description or Title Revision or

Procedure Date

NMP-AD-016- Operations - Quarterly Review of Work Hours 1.2

004-F01

71111.22 Corrective Action 10686257,

Documents 10690899,

10687515,

10705430,

10705826,

10719246

Miscellaneous AX4AK01-20052- Emergency Diesel Generator Operation & Calibration 701 07/09/1996

Digital Speed Control for Reciprocating Engines

Procedures 14825-2 Quarterly Inservice Valve Test 102

14825-2 Quarterly Inservice Valve Test 99

84003-C System Operating Pressure Test, Unit 1, TDAFW Pump 3/19/2020

84003-C System Operating Pressure Test, Unit 1, AFW system, Train 3/20/2020

A

84003-C System Operating Pressure Test, Unit 1, AFW system, Train 3/20/2020

B

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

NEI 99-02 Regulatory Assessment Performance Indicator Guideline 7

71152 Corrective Action 10616930,

Documents 10621114,

10632946,

10636146,

10653676,

1065037,

10670569,

10671610,

10690609,

10693041,

Inspection Type Designation Description or Title Revision or

Procedure Date

10709801,

10717090,

10704211,

10619056,

10634755,

10630238,

10630231,

10630409,

10630260,

10638064,

10630323,

1048496,

1050235, 276561,

1052813

Corrective Action 10717276,

Documents 10719714

Resulting from

Inspection

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 Type Designation Description or Title Revision or

Procedure Date

T+1 Meeting Notes for Work Week 2006: 2/3/2020-2/9/2020

Agenda for T-2 (Execution Readiness Challenge Board) for 5/19/2020

Work Week (Code) 2023

Gaps for Work Week 2007 (2/10/2020 - 2/16/2020)

AX4AR17-00189 Main Steam Isolation Valve Maintenance Manual 14.0

NMP-GM-006- System Outage Guidance, Attachment 3, System Outage 6

GL06 Critique for 2B2403DGAOT

Procedures 26854-C Main Steam Isolation Valve Actuator Maintenance 45.0

NMP-ES-006 Preventive Maintenance Implementation and Continuing 12.0

Equipment Reliability Improvement

NMP-GM-005- Human Performance Clock Reset Criteria 5.1

005

Work Orders SNC1035937,

SNC385403

71153 Corrective Action 10630238,

Documents 276561

Drawings 2X3D-BC-Q01X Elementary Diagram Main Steam System 2Hv-3016B 12.0

2X4AR17-00217 Generator Assembly Actuator 6.0

2X4AR17-00219- Generator Assembly Actuator Sheet 001 5

2X4AR17-00219- Generator Assembly Actuator Sheet 002 5

2X4AR17-00224 Air & Hydraulic System Schematic K

Miscellaneous 10006-C-DS1- Reactor Trip Review 07/19/2019

2019

10006-C-DS2- Reactor Trip Review 07/19/2019

2019

AX4AR17-00189 Main Steam Isolation Valve Maintenance Manual 14.0

21