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

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

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 Aspect Report Section Mitigating Systems Green NCV 05000424/2020001-01 Open/Closed

[H.14] -

Conservative Bias 71152 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 Section Status LER (License Event Report)05000424/2019-001-00 LER 2019-001-00 for Vogtle,

Unit 1, Engineered Safety Feature Chiller Inoperability Causes Operation in a Condition Prohibited by Tech Specs.

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

71153 Closed

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)

===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 Aspect Report Section Mitigating Systems

Green NCV 05000424/2020001-01 Open/Closed

[H.14] -

Conservative Bias 71152 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

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.04

Corrective Action

Documents

10698400

Corrective Action

Documents

Resulting from

Inspection

10698568,

10698570,

10698612,

10698619

Drawings

1X4DB111,

1X4DB112,

1X4DB114,

1X4DB115,

1X4DB116-1,

1X4DB116-2,

1X4DB117,

1X4DB119,

1X4DB120,

1X4DB121,

1X4DB122,

1X4DB136,

1X4DB137,

1X4DB149-1,

1X4DB149-2,

1X4DB149-4

P&I Diagram - Reactor Coolant System - System No.

201

24.0

1X4DB112

P&I Diagram - Reactor Coolant System - System No.

201

43.0

1X4DB114

P&I Diagram - Chemical & Volume Control System -

System No. 1208

41.0

1X4DB115

P&I Diagram - Chemical & Volume Control System -

System No. 1208

34.0

1X4DB116-1

P&I Diagram - Chemical & Volume Control System -

System No. 1208

53.0

1X4DB116-2

P&I Diagram - Chemical & Volume Control System -

System No. 1208

37.0

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

1X4DB117

P&I Diagram - Chemical & Volume Control System -

System No. 1208

25.0

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

2.0

1X4DB122

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

2.0

1X4DB136

P&I Diagram - Component Cooling Water System -

System No. 1203

33.0

1X4DB137

P&I Diagram - Component Cooling Water System -

System No. 1203

19.0

1X4DB149-1

Flow Diagram - Cooling Water System - Systems 1202,

203, 1217

6.0

1X4DB149-2

Flow Diagram - Cooling Water System - Systems 1202,

203, 1217

6.0

1X4DB149-4

Flow Diagram - Cooling Water System - Systems 1202,

203, 1217

6.0

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

14552-1

NSCW Flow Path Verification

8.4

71111.05

Corrective Action

Documents

10678113,

10685440,

10685442

Fire Plans

2840A-1

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

East Fire Fighting Preplan

4.0

2840B-1

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

Fire Fighting Preplan

5.0

2840C-1

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

Steam Generator Compartment Fire Fighting Preplan

2840E-1

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

Fighting Preplan

2845-2

Zone 145-NSCW Cooling Tower 2A Mechanical and

Electrical Tunnels 2T23A, and 2T5A Fire Fighting Preplan

0.2

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2860A-2

Zone 160A - NSCW Pumphouse - Train A Fire Fighting

Preplan

1.2

2860B-2

Zone 160B - NSCW Pumphouse - Train B Fire Fighting

Preplan

1.2

2916-1

Zone 516 - Low Voltage Switchyard Fire Fighting Preplan

Miscellaneous

VPN12 - Course

completion record

Fire Drill completion record supporting fire team

qualification

2/7/2020

Procedures

NMP-ES-035-006-

F05

Fire Protection Program Impact Screening;

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

Drill V-009

2/3/2020

71111.06

Corrective Action

Documents

10678400

Water in cable pull boxes

1/15/2020

Miscellaneous

SNC16683

Implement the Non-EQ Inaccessible Medium-Voltage

Cables Program as described in License Renewal

Application Section B.3.35

5/14/2008

Work Orders

SNC1077232

Investigation and repair sump pump in pull boxes

2/21/2020

SNC977859

Pull Box and Manhole water intrusion inspection

(1NE7ADKEM39)

1/17/2020

71111.08P

Miscellaneous

LTR-CECO-18-049

Evaluation of Foreign Objects in the Secondary Side of

the Vogtle Unit 1 Steam Generators - Fall 2018 1R21

Outage

Rev. 0

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

Final Operational Assessment

Rev. 1

Procedures

MRS-GEN-1217

Rolled Mechanical Plug Installation Using the Advanced

Rolling Tool and the Universal Platform Control Box

Rev. 6

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

2004-1

Power Operation (MODE 1)

5.0

2006RFO-1

Unit Cooldown to Cold Shutdown for Refueling

1.3

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

13003-1

Reactor Coolant Pump Operation

14721-1

ECCS Subsystem Flow Balance and Checkvalve

Refueling Inservice Test

40.1

17008-1

Annunciator Response Procedures for ALB 08 on Panel

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

Documents

10677298,

10677454,

10678260,

10678403,

10678431,

10681430,

10685722,

10694868,

10695006,

10695146,

10695242,

10695292,

10695384,

10695964

Miscellaneous

1R22 Unit 1 Spent Fuel Pool Cooling/NSCW DID

Contingency Plan

03/16/2020

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

(historical)

7/17/2014

1R22 Outage Safety Assessment

3/9/2020

1R22 Unit 1 A Spent Fuel Pool Cooling/NSCW DID

Contingency Plan, Train B System out of Service for

Maintenance

3/16/2020

NMP-OS-003-F01

Operational Ddecision-Making Issues Worksheet for high

vibration on Unit 2, RCP-1

1/14/2020

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Operability

Evaluations

NMP-OS-003-F01

Operational Decision-Making Issue Worksheet for U2

RCP #1 high vibration

2/28/2020

Procedures

10032-C

Outage Risk Assessment Monitoring

10032-C

Outage Risk Assessment Monitoring

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

Evaluation

17008-2

Annunciation Response Procedures for ALB 08 on Panel

2A2 on MCB

1/15/2020

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.

17008-2

1/15/2020

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

Risk Informed Completion Time Program

1/13/2020

NMP-OS-007-003

Plant Operating Orders - Unexpected Rise in RCP #1

Vibration

1/16/2020

NMP-OS-010

Protected Train/Division and Protected Equipment

Program

8.0

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

Documents

10677506,

10677691,

10677919,

10678289,

10678731,

10678785,

10681033,

10685243

Engineering

Evaluations

2-VNP-21301012-4-

EXX1

Engineering Evaluation of UT Inspection Component (MS-

SG2 to TDAFW PMP)

9/23/2017

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2-VNP-21302013-

EXX1

Engineering Evaluation of UT Inspection Component

AFW-TDAFW PMP to SG 2& 3)

9/27/2017

2-VNP-21302018-4-

EXX1

Engineering Evaluation of UT Inspection Component

(AFW-MDAFW pump 2 to SG 2)

9/25/2017

Miscellaneous

VEGP Unit 1 Cycle 22 Core Operating Limits Report

Vogtle Unit 1 Cycle 22 NDR

Plant Technical Data Book

Westinghouse, Vogtle Units 1 and 2 Variable Shutdown

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

Assessment

2/06/2020

Work Orders

SNC1070425

Steam Leak in U2 North Main Steam Valve Room Piping

Penetration

1/16/2020

71111.19

Corrective Action

Documents

10679320,

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

Procedure

Type

Designation

Description or Title

Revision or

Date

AX4AK01-20052-1

Emergency Diesel Generator Operation and Calibration

701 Digital Speed Control fro Reciprocating Engines

7/9/1996

Procedures

NMP-GM-031-002-

F01

RICT Projection Details

Work Orders

SNC121344

NSCW Train B PMP-4 refurbishment

1/31/2020

71111.20

Corrective Action

Documents

Resulting from

Inspection

10694240

Procedures

14864-1

Containment General Leak Inspection

NMP-HP-302

Restricted Area Classification, Postings, and Access

Control

10.11

71111.22

Calibration

Records

Calibration Check Report for Load transducer 067054

3/4/2020

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

Sheet for VP-3-3726

3/4/2020

Corrective Action

Documents

10625179,

10686169,

10687515,

10694640

Miscellaneous

AX5AC05-00034-1

Installation, Operating and Maintenance for Self-Actuated

Safety Valves

3/7/1996

NMP-DP-001

High Risk Planning Worksheet for SSPS TSLB testing

Group 2 (QPS2)

16.0

Procedures

219-1

Auxiliary and Containment Buildings and Miscellaneous

Drain Systems

36.2

14300-C

Containment Type B & C Leakage Totalization

4.0

14378-1

Containment Penetration No. 78 Containment Sump

Pumps Discharge Local Leak Rate Test

2.1

14668A-1

Train A Diesel Generator Operability Test

9.1

14825-2

Quarterly In service Valve Test

2/12/2019

24904-C

Modes 1-4 Containment Leakage Totalization

5.5

24991-1

Protection Group II SSPS Input Relay Test

210-C

Main Steam Line Code Safety Valve Setpoint Verification

24.1

Inspection

Procedure

Type

Designation

Description or Title

Revision or

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 #

TVT-05

Trevitest Procedure Main Steam Safety Valves

8/17/2018

Work Orders

SNC713069

1301-1PSV3033-Valve Test-Main Steam SG - Safety

Relief

3/4/2020

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

Documents

10690418

OSC Gaitronic Speaker Non-Functional

2/25/2020

10692354

INPO EMPE 2020 - Observation - Protective Actions -

Gaitronics

3/3/2020

10692356

INPO EMPE 2020 - Observation - Protective Actions -

Performance Gaps

3/3/2020

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

71152

Corrective Action

Documents

275705, 1036634,

1038278, 1038279,

1038280, 1038281,

10578821,

10579310,

10579341,

10581018,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

10595165, 1035139,

10673392, 1035219

Procedures

13744A-1

Train A Essential Chilled Water System

13744A-1

Train A Essential Chilled Water System

71153

Corrective Action

Documents

10594804,

10595528,

10595623,

10596048,

10596120,

10596242,

10596727,

10597166,

10597194,

10604001,

10626898

10596729

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

inability to maintain SG levels and pressures after MSIV

2HV3036A failed shut unexpectedly

3/30/2019

Drawings

2X3D-BC-Q02E

Elementary Drawing, Main Steam System

2X3D-BC-Q02E

Main Steam System, Elementary Drawing

Miscellaneous

10006-C

Reactor Trip Review, Report No 2-19-001

3/30/2019

17014-2

Annunciator Response Procedures for ALM 14 on Panel

2B1 on MCB

LER 2019-001-00

Spurious Closure of Main Steam Isolation Valve results in

Manual Reactor Trip

5/28/2019

SOU-73019

Exelon Power Labs - Failure Analysis of an MDR Relay

and SBM Switch

6/14/2019

TE1039694

TE MREVAL - MSIV 2HV3036A failed shut unexpected

4/1/2019

Procedures

26854-C

Main Steam Isolation Valve Actuator Maintenance

AX4AR17-00189

Document Insertion Sheet - Maintenance Manual Revision

concerning Pressure Switch settings on Main STM ISO

Valves

Work Orders

SNC666544

Main Steam SG 3 Upstrm MSIV, Clean/Inspect Hydraulic

System & Air Filter

2/18/2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

SNC672668

Model A-290 Main Steam Isolation Valve SG3

Clean/Inspect

3/10/2019

SNC672998

Rockwell Model A-290 Main Steam Isolation Valve SG1

Clean/Inspect

2/23/2019