IR 05000424/2020001

Integrated Inspection Report 05000424/2020001 and 05000425/2020001

ML20132A016
Person / Time
Site:	Vogtle
Issue date:	05/11/2020
From:	Alan Blamey NRC/RGN-II/DRP/RPB2
To:	Gayheart C Southern Nuclear Operating Co
References
IR 2020001
Download: ML20132A016 (23)

Text

May 11, 2020

SUBJECT:

VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 & 2 - INTEGRATED INSPECTION REPORT 05000424/2020001 AND 05000425/2020001

Dear Ms. Gayheart:

On March 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Vogtle Electric Generating Plant, Units 1 & 2. On May 4, 2020, the NRC inspectors discussed the results of this inspection with Mr. Jesse Thomas, Site Vice President (acting) 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.

If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; and the NRC Resident Inspector at Vogtle Electric Generating Plant, Units 1 & 2. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Alan J. Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket Nos. 05000424 and 05000425 License Nos. NPF-68 and NPF-81

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000424 and 05000425 License Numbers: NPF-68 and NPF-81 Report Numbers: 05000424/2020001 and 05000425/2020001 Enterprise Identifier: I-2020-001-0064 Licensee: Southern Nuclear Operating Co., Inc.

Facility: Vogtle Electric Generating Plant, Units 1 & 2 Location: Waynesboro, GA Inspection Dates: January 01, 2020 to March 31, 2020 Inspectors: S. Downey, Senior Reactor Inspector G. Eatmon, Senior Resident Inspector M. Magyar, Reactor Inspector C. Safouri, 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

Inadequate Corrective Actions Result in Failure of the 1A Engineered Safety Feature Chiller Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.14] - 71152 Systems NCV 05000424/2020001-01 Conservative Open/Closed Bias A self-revealed Green finding and associated Non-cited Violation (NCV) was identified when the licensee failed to meet 10 Code of Federal Regulations (CFR) Part 50, Appendix B,

Criterion XVI, Corrective Action. Specifically, the licensee failed to promptly identify and correct conditions adverse to quality impacting the Unit 1 Train A Engineered Safety Feature (ESF) Chiller.

Additional Tracking Items

Type Issue Number Title Report Status Section LER 05000424/2019-001-00 LER 2019-001-00 for Vogtle, 71153 Closed (License Unit 1, Engineered Safety Event Feature Chiller Inoperability Report) Causes Operation in a Condition Prohibited by Tech Specs.

LER 05000425/2019-001-00 LER 2019-001-00 for Vogtle 71153 Closed Electric Generating Plant, Unit 2, Spurious Closure of Main Steam Isolation Valve results in Manual Reactor Trip.

PLANT STATUS

Unit 1 operated at or near 100 percent rated thermal power (RTP) until is was shutdown for planned refueling outage cycle 22 (1R22) on March 8, 2020. The unit was in Mode 2 at the end of the inspection period.

Unit 2 operated at or near 100 percent RTP for the entire 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/readingrm/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. From January 1 - March 19, 2020, the inspectors performed plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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; and observed risk significant activities when warranted. 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 the cases where it was determined the objectives and requirements could not be performed remotely, management elected to postpone and reschedule the inspection to a later date.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (2 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Unit 1 Train 'A' Safety Injection (SI) system, during Train 'B' SI system quarterly pump and valve in-service test surveillance, on January 2, 2020.

(2) Unit 2 Train 'A' Nuclear Service Cooling Water (NSCW) system while protected for Unit 1 refueling outage Yellow risk profile, on March 18, 2020.

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations during a complete walkdown of Unit 1 Shutdown Cooling during Mid-Loop Operation on March 25, 2020.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (2 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 140A/B/C/E, Unit 1 Containment Building, on March 16, 2020.

(2) Fire Zone 145/146/160A/160B, Unit 2 Train A and B NSCW pump rooms and electrical tunnels, on March 16, 2020.

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 Unit 1 Low Voltage Switchyard on February 7, 2020.

71111.06 - Flood Protection Measures

Cable Degradation (IP Section 03.02) (1 Sample)

The inspectors evaluated cable submergence protection in:

(1) 1NE7ADKEM40 1NE7ADKEM39 1NE9GHKEPB01

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 9 - 20, 2020:

1. Ultrasonic Testing (UT)a. ISI-11201-042, 2" Elbow to Pipe weld, ASME Class 1 (observed)b. ISI-11201-042, 2" Elbow to Pipe weld, ASME Class 1 (observed)c. ISI-11201-051, 2" Elbow to Pipe weld, ASME Class 1 (observed)d. ISI-11204-244, 3" Reducer to Branch Connection weld, ASME Class 1 (observed)2. Penetration Testing (PT)a. 1F05139, 4" Weld Neck Flanges, ASME Class 2 (reviewed)3. Eddy Current Examination (ET)a. Steam Generator 1 - ET for tubes R1C87, R41C44, R41C100 b. Steam Generator 2 - ET for tubes R16C7, R39C103 c. Steam Generator 3 - ET for tube R30C111 The Inspectors evaluated the licensees boric acid corrosion control program performance.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the Control Room during Unit 1 Refueling Outage Shutdown from Mode 1 to Mode 5 on March 8, 2020.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated Just in Time Training on Unit 2 Reactor Coolant Pump (RCP) high vibrations and Unit 1 planned shutdown for the refueling outage, on January 15, 2020 and February 26, 2020, respectively.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (1 Sample)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) Periodic Evaluation (a)(3) Review from August 1, 2018 to December 31, 2019, on February 20, 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 elevated risk due to Reactor Coolant Pump RCP #1 high vibrations on January 13, 2020.

(2) Unit 2 elevated risk due to extended planned and emergent maintenance on Train 'B' Emergency Diesel Generator (EDG) during a Risk Informed Completion Time (RICT)maintenance window on January 18, 2020.

(3) Unit 1 elevated risk due to Train 'A' Motor Driven Auxiliary Feedwater Pump system outage on March 3, 2020.

(4) Unit 1 elevated shutdown risk, Yellow, due to Spent Fuel Pool Cooling and Electrical alignment during Train 'B' Work Window, on March 17, 2020.

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (2 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Unit 2 North Main Steam Valve room steam leak near the steam supply line to the Turbine Driven Auxiliary Feedwater pump, on January 13, 2020.

(2) Units 1 and 2 incorrect boron assumption regarding Variable Shutdown Margin, on March 5, 2020.

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (2 Samples)

The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:

(1) Unit 1 Train 'B' NSCW pump #4 installation after refurbishment, work order SNC121344.

(2) Unit 2 Train 'B' EDG post maintenance functional test, work order SNC915588.

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)

(1) (Partial)

The inspectors evaluated refueling outage 1R22 activities from March 8, 2020 to March 31,2020. The inspectors completed inspection procedure Sections 'a' and 'b'.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) 24991-1, Unit 1 Protection Group II Solid State Protection System Input Relay Test, on February 19, 2020.

(2) 28210-C, Unit 1 Loop 4 Main Steam Line Code Safety Valve Setpoint Verification, on March 4, 2020.

(3) 14668A-2, Unit 2 Train 'A' Diesel Generator Operability Test, on February 12, 2020.

Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) 14378-1, Containment Penetration No. 78 Containment Sump Pumps Discharge Local Leak Rate Test, on March 4, 2020.

71114.06 - Drill Evaluation

Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)

(1) The inspectors observed an emergency preparedness drill that focused on a Cold Leg Loss of Coolant Accident, on February 25,

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, 2019 - December 31, 2019).

(2) Unit 2 (January 1, 2019 - December 31, 2019).

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)

(1) Unit 1 (January 1, 2019 - December 31, 2019).

(2) Unit 2 (January 1, 2019 - December 31, 2019).

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)

(1) Unit 1 (January 1, 2019 - December 31, 2019).

(2) Unit 2 (January 1, 2019 - December 31, 2019).

71152 - Problem Identification and Resolution

Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) Unit 1 Train 'A' Engineered Safety Features Chiller trip on high condenser pressure, Corrective Action Report (CAR) 275705.

71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 05000424/2019-001-00, Engineered Safety Feature Chiller inoperability causes Operation in a Condition Prohibited by TS (ADAMS Accession No.

ML19100A447). The inspection conclusions associated with this LER are documented in this report under Inspection Results Section 71152.

(2) LER 05000425/2019-001-00, Spurious Closure of Main Steam Isolation Valve results in Manual Reactor Trip (ADAMS Accession No. ML19148A469). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements.

INSPECTION RESULTS

Inadequate Corrective Actions Result in Failure of the 1A Engineered Safety Feature Chiller Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.14] - 71152 Systems NCV 05000424/2020001-01 Conservative Open/Closed Bias A self-revealed Green finding and associated Non-cited Violation (NCV) was identified when the licensee failed to meet 10 Code of Federal Regulations (CFR) Part 50, Appendix B, Criterion XVI, Corrective Action. Specifically, the licensee failed to promptly identify and correct conditions adverse to quality impacting the Unit 1 Train A Engineered Safety Feature (ESF) Chiller.

Description:

The primary safety function of the Essential Chilled Water (ECW) system is to support the operation of the safety-related air-conditioning units. The design basis of the ESF room cooler and safety-related chiller system is to maintain air temperatures within required design limits for rooms containing safety-related equipment during and after a design basis accident. The chiller units transfer the head loads from the ECW system to the Nuclear Service Cooling Water (NSCW) system. The ESF chiller purge unit removes condenser air in-leakage to maintain condenser vacuum. The ESF chiller purge units run time provides an indication of degradation that could impact the operability of the safety-related ECW system.

The licensee documented several instances of degraded performance of the Unit 1 Train A ESF Chiller, or 1A ESF Chiller, due to air in-leakage. On September 19, 2018, the purge unit run time for the 1A ESF Chiller increased from minimal leakage trends and reached the alarm limit for run time of 40 minutes per day. On November 14, 2018, the Purge Max Pumpout Rate alarm came in multiple times in a 24-hour period. As permitted by procedure 13744A-1, Train A Essential Chilled Water System, the licensee increased the pumpout rate alarm setpoint from 40 minutes per day to 100 minutes per day, and recommended maintenance support to locate and repair potential in-leakage locations. The purge pump down rates were approximately 30 minutes per hour, however the daily run times were approximately 500 minutes per day. On December 1, 2018, the purge unit run time had increased to near continuous operation with greater than 50 minutes per hour and an average daily run time of 1200 minutes out of 1440 minutes (or 24-hour period). On February 4, 2019, the 1A ESF Chiller was taken out of service for planned maintenance which included: breaker inspections, pressure switch calibration, resolution of purge unit suction temperature sensor issue, and agastat relay calibration. The planned system outage did not scope in resolution of overall air in-leakage to the 1A ESF Chiller. During post maintenance testing, the 1A ESF Chiller unexpectedly tripped on high condenser pressure and the licensee performed emergent repair to potential air in-leakage locations with High Vacuum Sealant. On February 6, 2019, the licensee conducted a 10-hour post maintenance test at maximum loading on the 1A ESF Chiller. The 1A ECW system ran satisfactorily for the duration of the test and was restored to operable on February 7, 2019. However, immediately following the post maintenance test surveillance, the purge unit returned to near continuous operation, with an average daily run time of approximately 1345 minutes of 1440 minutes.

On February 12, 2019, the 1A ESF Chiller was started to support a surveillance and tripped on high condenser pressure approximately 4 minutes following the start. The licensee determined the high condenser pressure trip was due to excessive air in-leakage, which was previously indicated by the near continuous operation of the purge unit after the February 6, 2019 maintenance. The excessive air in-leakage caused the condenser vacuum to degrade to the point where the 1A ESF chiller was not able to perform its required safety function. The 1A ESF chiller was declared inoperable and the licensee identified and sealed several in-leakage locations, which restored operability on February 14, 2019. The total time the 1A ESF Chiller was determined to be inoperable was 169.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, which exceeds the Technical Specification (TS) allowed outage time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> per TS 3.7.14, Condition A.

Corrective Actions: The licensee, with vendor support, identified and corrected two air in-leakage locations on the 1A ESF chiller suction elbow and the Swagelok fitting behind the condenser pressure gauge. In addition, the licensee has made changes to the ECW System Monitoring Plan to improve trending and resolution of conditions adverse to quality.

Corrective Action References: CAR 275705

Performance Assessment:

Performance Deficiency: 10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action, requires that Measures shall be established to assure that conditions adverse to quality are promptly identified and corrected. The licensee did not promptly identify and correct the longstanding and worsening degraded condition associated with air in-leakage, which resulted in the unplanned TS entry and inoperability of the 1A ESF Chiller.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Equipment Performance attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences.

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The affected cornerstone was Mitigating Systems, as determined by Inspection Manual Chapter (IMC) 0609, 4, Initial Characterization of Findings. Utilizing IMC 0609, Appendix A, The Significance Determination Process for Findings At-Power, the performance deficiency did require a Detailed Risk Evaluation because the degraded condition represented a loss of the PRA function of one train of a multi-train TS system for greater than its TS allowed outage time. The total time the 1A ESF Chiller system was determined to be inoperable was 169.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, which is beyond the TS 3.7.14, Condition A, Completion Time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

A detailed risk evaluation was performed by a regional senior reactor analyst in accordance with IMC 0609, Appendix 'A' using SAPHIRE 8 Version 8.2.1 and the Vogtle Units 1 and 2 SPAR model Version 8.60 dated October 17, 2018. The major analysis assumptions included: Exposure time was from the completion of the ten-hour maintenance run on February 7, 2019, until the air in-leakage was repaired and chiller declared operable on February 14, 2019, a period of 7 days, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and 19 minutes. The analyst conservatively assumed the remaining ESF chiller was susceptible to the same failure mechanism and treated the failure as dependent for a failure to continue running common cause event. The analyst set CHW-CHL-FR-001 (ESF CHILLER UNIT 001 FAILS TO RUN) to True. The dominant accident sequence was a Switchyard Related Loss of Offsite Power initiating event with a failure of the Train B Emergency Diesel Generator and failure of the operators to establish alternate room cooling. The analysis determined that the performance deficiency resulted in an increase in core damage frequency of less than 1.0 E-7 events per year which corresponds to a very low safety significance (GREEN) finding.

Cross-Cutting Aspect: H.14 - Conservative Bias: Individuals use decision making-practices that emphasize prudent choices over those that are simply allowable. A proposed action is determined to be safe in order to proceed, rather than unsafe in order to stop.

Enforcement:

Violation: 10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action, requires that Measures shall be established to assure that conditions adverse to quality are promptly identified and corrected.

Vogtle, Units 1 and 2, TS 3.7.14 requires two ESF Room Cooler and Safety-Related Chiller trains to be operable in Modes 1 through 4; if a train is inoperable, it shall be returned to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or the Risk Informed Completion Time, otherwise the unit shall be shut down and in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Contrary to the above, from September 19, 2018 to February 14, 2019, the licensee did not promptly identify and correct the air in-leakage degradation mechanism impacting the 1A ESF Chiller, a condition adverse to quality which rendered the 1A ESF Chiller inoperable for approximately 169.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, which is greater than the TS allowed outage time, and the unit had not been placed in Mode 3 and Mode 5.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• On May 4, 2020, the inspectors presented the integrated inspection results to Mr. Jesse Thomas, Site Vice President (acting) and other members of the licensee staff.

• On April 20, 2020, the inspectors presented the Exit inspection results to Mr. Mathew Norris, Plant Manager (acting) and other members of the licensee staff.

• On March 20, 2020, the inspectors presented the ISI/SGISI Exit Meeting inspection results to Mr. Matthew Norris, Plant Manager (acting) and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.04 Corrective Action 10698400

Documents

Corrective Action 10698568,

Documents 10698570,

Resulting from 10698612,

Inspection 10698619

Drawings 1X4DB111, P&I Diagram - Reactor Coolant System - System No. 24.0

1X4DB112, 1201

1X4DB114,

1X4DB115,

1X4DB116-1,

1X4DB116-2,

1X4DB117,

1X4DB119,

1X4DB120,

1X4DB121,

1X4DB122,

1X4DB136,

1X4DB137,

1X4DB149-1,

1X4DB149-2,

1X4DB149-4

1X4DB112 P&I Diagram - Reactor Coolant System - System No. 43.0

201

1X4DB114 P&I Diagram - Chemical & Volume Control System - 41.0

System No. 1208

1X4DB115 P&I Diagram - Chemical & Volume Control System - 34.0

System No. 1208

1X4DB116-1 P&I Diagram - Chemical & Volume Control System - 53.0

System No. 1208

1X4DB116-2 P&I Diagram - Chemical & Volume Control System - 37.0

System No. 1208

Inspection Type Designation Description or Title Revision or

Procedure Date

1X4DB117 P&I Diagram - Chemical & Volume Control System - 25.0

System No. 1208

1X4DB119 P&I Diagram - Safety Injection System - System No. 1204 31.0

1X4DB120 P&I Diagram - Safety Injection System - System No. 1204 28.0

1X4DB121 P&I Diagram - Safety Injection System - System No. 1204 42.0

1X4DB122 P&I Diagram - Residual Heat Removal - System No. 1205 52.0

1X4DB136 P&I Diagram - Component Cooling Water System - 33.0

System No. 1203

1X4DB137 P&I Diagram - Component Cooling Water System - 19.0

System No. 1203

1X4DB149-1 Flow Diagram - Cooling Water System - Systems 1202, 6.0

203, 1217

1X4DB149-2 Flow Diagram - Cooling Water System - Systems 1202, 6.0

203, 1217

1X4DB149-4 Flow Diagram - Cooling Water System - Systems 1202, 6.0

203, 1217

Miscellaneous Plant Vogtle Unit 1 Mid-Loop Operations Letter 03/23/20

Procedures 11105-1 Safety Injection System Alignment 27.1

2008-C Mid-Loop Operations 33.1

14150A-2 Train A NSCW Fan/Spray Valve Surveillance 6

14552-1 NSCW Flow Path Verification 8.4

71111.05 Corrective Action 10678113,

Documents 10685440,

10685442

Fire Plans 92840A-1 Zone 140A - Containment Building - Levels A, B, 1, and 3 4.0

East Fire Fighting Preplan

2840B-1 Zone 140B - Containment Building - Levels A, B, 1, 2, and 5.0

Fire Fighting Preplan

2840C-1 Zone 140C - Containment Building - Levels A, B, 1 and 3 4

Steam Generator Compartment Fire Fighting Preplan

2840E-1 Zone 140E - Containment Building - Levels A, 1 and 2 Fire 1

Fighting Preplan

2845-2 Zone 145- NSCW Cooling Tower 2A Mechanical and 0.2

Electrical Tunnels 2T23A, and 2T5A Fire Fighting Preplan

Inspection Type Designation Description or Title Revision or

Procedure Date

2860A-2 Zone 160A - NSCW Pumphouse - Train A Fire Fighting 1.2

Preplan

2860B-2 Zone 160B - NSCW Pumphouse - Train B Fire Fighting 1.2

Preplan

2916-1 Zone 516 - Low Voltage Switchyard Fire Fighting Preplan 5

Miscellaneous VPN12 - Course Fire Drill completion record supporting fire team 2/7/2020

completion record qualification

Procedures NMP-ES-035-006- Fire Protection Program Impact Screening; 1

F05 Activity/Document No.: SNC945587

NMP-FLS-003-002 Industrial Extension Cord Instructions 4.0

NMP-TR-425-F01 Fire Drill Scenario Development and Approval Sheet for 2/3/2020

Drill V-009

71111.06 Corrective Action 10678400 Water in cable pull boxes 1/15/2020

Documents

Miscellaneous SNC16683 Implement the Non-EQ Inaccessible Medium-Voltage 5/14/2008

Cables Program as described in License Renewal

Application Section B.3.35

Work Orders SNC1077232 Investigation and repair sump pump in pull boxes 2/21/2020

SNC977859 Pull Box and Manhole water intrusion inspection 1/17/2020

(1NE7ADKEM39)

71111.08P Miscellaneous LTR-CECO-18-049 Evaluation of Foreign Objects in the Secondary Side of Rev. 0

the Vogtle Unit 1 Steam Generators - Fall 2018 1R21

Outage

MRS-TRC-1522 Use of Qualified Techniques for V1R22 Outage Rev. 0

SG-CDMP-20-1 Vogtle 1R22 Steam Generator Degredation Assessment Rev. 0

SG-SGMP-18-18 Vogtle 1R21 Steam Generator Condition Monitoring and Rev. 1

Final Operational Assessment

Procedures MRS-GEN-1217 Rolled Mechanical Plug Installation Using the Advanced Rev. 6

Rolling Tool and the Universal Platform Control Box

NMP-ES-004 Steam Generator Program Rev. 17

71111.11Q Miscellaneous JITT Plan Night/Day Shift 1R22

V-RQ-SG-20200113 RCP High Vibrations 01/13/2020

Procedures 12004-1 Power Operation (MODE 1) 5.0

2006RFO-1 Unit Cooldown to Cold Shutdown for Refueling 1.3

Inspection Type Designation Description or Title Revision or

Procedure Date

13003-1 Reactor Coolant Pump Operation 54

14721-1 ECCS Subsystem Flow Balance and Checkvalve 40.1

Refueling Inservice Test

17008-1 Annunciator Response Procedures for ALB 08 on Panel 20

1A2 on MCB

71111.12 Miscellaneous Vogtle Living (a)(3) Documentation Package - Review

Period: 08/01/18-12/31/2019

Procedures NMP-ES-027 Maintenance Rule Program 10.2

71111.13 Corrective Action 10677298,

Documents 10677454,

10678260,

10678403,

10678431,

10681430,

10685722,

10694868,

10695006,

10695146,

10695242,

10695292,

10695384,

10695964

Miscellaneous 1R22 Unit 1 Spent Fuel Pool Cooling/NSCW DID 03/16/2020

Contingency Plan

eSOMS Unit 1/2 Control Logs on March 17, 2020

2B DG AOT - 2020 1/16/2020

Vibration Trend for RCP #1 vertical and horizontal 7/17/2014

(historical)

1R22 Outage Safety Assessment 3/9/2020

1R22 Unit 1 A Spent Fuel Pool Cooling/NSCW DID 3/16/2020

Contingency Plan, Train B System out of Service for

Maintenance

NMP-OS-003-F01 Operational Ddecision-Making Issues Worksheet for high 1/14/2020

vibration on Unit 2, RCP-1

Inspection Type Designation Description or Title Revision or

Procedure Date

Operability NMP-OS-003-F01 Operational Decision-Making Issue Worksheet for U2 2/28/2020

Evaluations RCP #1 high vibration

Procedures 10032-C Outage Risk Assessment Monitoring 15

10032-C Outage Risk Assessment Monitoring 15

13419-C Diesel Generator RICT Support 7/18/2019

13719-1 Spent Fuel Pool Cooling and Purification System 56.1

230-2 Offsite AC Circuit Verification and Capacity/Capability 26

Evaluation

17008-2 Annunciation Response Procedures for ALB 08 on Panel 1/15/2020

2A2 on MCB

18030-C Loss of Spent Fuel Pool Level or Cooling 24.1

23570-2 RCP Vibration Monitoring System Channel Calibration 14.1

NMP-AD-008-F01 Applicability Determination for Activity/Document No. 1/15/2020

17008-2

NMP-GM-031 On-Line Configuration Risk Management Program 8.0

NMP-GM-031-001 Online Maintenance Rule (a)(4) Risk Calculations 6.0

NMP-GM-031-003 Risk Management Actions for 10 CFR 50.65(a)(4) and the 1/13/2020

Risk Informed Completion Time Program

NMP-OS-007-003 Plant Operating Orders - Unexpected Rise in RCP #1 1/16/2020

Vibration

NMP-OS-010 Protected Train/Division and Protected Equipment 8.0

Program

NMP-OS-010-003 Vogtle Protected Equipment Logs 10.0

NMP-OS-019-311 Vogtle Unit 1 FSG-11, Alternate SFP Makeup and Cooling 1.0

71111.15 Corrective Action 10677506,

Documents 10677691,

10677919,

10678289,

10678731,

10678785,

10681033,

10685243

Engineering 2-VNP-21301012-4- Engineering Evaluation of UT Inspection Component (MS- 9/23/2017

Evaluations EXX1 SG2 to TDAFW PMP)

Inspection Type Designation Description or Title Revision or

Procedure Date

2-VNP-21302013- Engineering Evaluation of UT Inspection Component 9/27/2017

EXX1 AFW-TDAFW PMP to SG 2& 3)

2-VNP-21302018-4- Engineering Evaluation of UT Inspection Component 9/25/2017

EXX1 (AFW-MDAFW pump 2 to SG 2)

Miscellaneous VEGP Unit 1 Cycle 22 Core Operating Limits Report 1

Vogtle Unit 1 Cycle 22 NDR 2

Plant Technical Data Book 4

Westinghouse, Vogtle Units 1 and 2 Variable Shutdown 02/06/2020

Margin, CAP IR-2020-1543 - Initial Response and Safety

Assessment

Work Orders SNC1070425 Steam Leak in U2 North Main Steam Valve Room Piping 1/16/2020

Penetration

71111.19 Corrective Action 10679320,

Documents 10679375,

10680034,

10680066,

10680488,

10680737,

10680829,

10680951,

10680975,

10680991,

10681261,

10681262,

10681293,

10681726,

10681760,

10681779,

10681802,

10684602,

10684757,

10684795,

20682191

Miscellaneous 1B1202NSCWPMP4 System Outage: 1B NSCW PMP 4 2/4/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

AX4AK01-20052-1 Emergency Diesel Generator Operation and Calibration 7/9/1996

701 Digital Speed Control fro Reciprocating Engines

Procedures NMP-GM-031-002- RICT Projection Details 2

F01

Work Orders SNC121344 NSCW Train B PMP-4 refurbishment 1/31/2020

71111.20 Corrective Action 10694240

Documents

Resulting from

Inspection

Procedures 14864-1 Containment General Leak Inspection 3

NMP-HP-302 Restricted Area Classification, Postings, and Access 10.11

Control

71111.22 Calibration Calibration Check Report for Load transducer 067054 3/4/2020

Records 23445-C M&TE Pressure Test Gage Calibration for VP-2596 3/4/2020

SCM-PSC-014 200-1000 LB-FT "Click" Torque Wrench Calibration Data 3/4/2020

Sheet for VP-3-3726

Corrective Action 10625179,

Documents 10686169,

10687515,

10694640

Miscellaneous AX5AC05-00034-1 Installation, Operating and Maintenance for Self-Actuated 3/7/1996

Safety Valves

NMP-DP-001 High Risk Planning Worksheet for SSPS TSLB testing 16.0

Group 2 (QPS2)

Procedures 13219-1 Auxiliary and Containment Buildings and Miscellaneous 36.2

Drain Systems

14300-C Containment Type B & C Leakage Totalization 4.0

14378-1 Containment Penetration No. 78 Containment Sump 12.1

Pumps Discharge Local Leak Rate Test

14668A-1 Train A Diesel Generator Operability Test 9.1

14825-2 Quarterly In service Valve Test 12/12/2019

24904-C Modes 1-4 Containment Leakage Totalization 5.5

24991-1 Protection Group II SSPS Input Relay Test 14

210-C Main Steam Line Code Safety Valve Setpoint Verification 24.1

Inspection Type Designation Description or Title Revision or

Procedure Date

84003-C Pressure Testing of Piping and Components 9.4

Form TCT-05.1 Trevitest Test Sheet for 1PSV-3033 3/4/2020

Form TVT-05.1 Trevitest Test Sheet for 1PSV-3034 3/4/2020

Form TVT-05.1 Trevitest Test Sheet for 1PSV-3035 3/4/2020

Form TVT-05.1 Trevitest Test Sheet for Valve 1PSV-3031 3/4/2020

Form TVT-05.1 Trevitest Test Sheet for 1PSV-3032 3/4/2020

NMP-GM-005-002 Human Performance Tools Instructions 9.0

TEAM Document # Trevitest Procedure Main Steam Safety Valves 8/17/2018

TVT-05

Work Orders SNC713069 1301-1PSV3033-Valve Test- Main Steam SG - Safety 3/4/2020

Relief

SNC713069 Valve Test - Main Steam SG-4 Safety Relief 3/4/2020

SNC992082 A D/G 24HR Run - 18M - I&C Support REQ 2/10/2020

71114.06 Corrective Action 10690418 OSC Gaitronic Speaker Non-Functional 2/25/2020

Documents 10692354 INPO EMPE 2020 - Observation - Protective Actions - 3/3/2020

Gaitronics

10692356 INPO EMPE 2020 - Observation - Protective Actions - 3/3/2020

Performance Gaps

Miscellaneous Vogtle Units 1&2 EMPE February 25,

20

Procedures NMP-EP-303 Drill and Exercise Standards 21.0

71151 Miscellaneous eSOMS Logs on March 10, 2019

eSOMS Logs from March 28, 2019 to April 1, 2019

eSOMS Logs from July 19, 2019 to July 22, 2019

eSOMS Logs from December 1, 2019 to December 11,

2019

Procedures NEI 99-02 Regulatory Assessment Performance Indicator Guideline 7

71152 Corrective Action 275705, 1036634,

Documents 1038278, 1038279,

1038280, 1038281,

10578821,

10579310,

10579341,

10581018,

Inspection Type Designation Description or Title Revision or

Procedure Date

10595165, 1035139,

10673392, 1035219

Procedures 13744A-1 Train A Essential Chilled Water System 17

13744A-1 Train A Essential Chilled Water System 14

71153 Corrective Action 10594804,

Documents 10595528,

10595623,

10596048,

10596120,

10596242,

10596727,

10597166,

10597194,

10604001,

10626898

10596729 On 3/30/2019 @2130, U2 was manually tripped due to 3/30/2019

inability to maintain SG levels and pressures after MSIV

2HV3036A failed shut unexpectedly

Drawings 2X3D-BC-Q02E Elementary Drawing, Main Steam System 10

2X3D-BC-Q02E Main Steam System, Elementary Drawing 10

Miscellaneous 10006-C Reactor Trip Review, Report No 2-19-001 3/30/2019

17014-2 Annunciator Response Procedures for ALM 14 on Panel 12

2B1 on MCB

LER 2019-001-00 Spurious Closure of Main Steam Isolation Valve results in 5/28/2019

Manual Reactor Trip

SOU-73019 Exelon Power Labs - Failure Analysis of an MDR Relay 6/14/2019

and SBM Switch

TE1039694 TE MREVAL - MSIV 2HV3036A failed shut unexpected 4/1/2019

Procedures 26854-C Main Steam Isolation Valve Actuator Maintenance 44

AX4AR17-00189 Document Insertion Sheet - Maintenance Manual Revision 14

concerning Pressure Switch settings on Main STM ISO

Valves

Work Orders SNC666544 Main Steam SG 3 Upstrm MSIV, Clean/Inspect Hydraulic 2/18/2019

System & Air Filter

Inspection Type Designation Description or Title Revision or

Procedure Date

SNC672668 Model A-290 Main Steam Isolation Valve SG3 3/10/2019

Clean/Inspect

SNC672998 Rockwell Model A-290 Main Steam Isolation Valve SG1 2/23/2019

Clean/Inspect

20