IR 05000424/2021011

NRC Inspection Report 05000424/2021011 and 05000425/2021011

ML21250A080
Person / Time
Site:	Vogtle
Issue date:	09/07/2021
From:	James Baptist NRC/RGN-II/DRS/EB1
To:	Gayheart C Southern Nuclear Operating Co
References
IR 2021011
Download: ML21250A080 (10)

Text

September 7, 2021

SUBJECT:

VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 & 2 - NRC INSPECTION REPORT 05000424/2021011 AND 05000425/2021011

Dear Ms. Gayheart:

On August 20, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Vogtle Electric Generating Plant, Units 1 & 2 and discussed the results of this inspection with Jesse Thomas 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/

James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety

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:

05000424/2021011 and 05000425/2021011

Licensee:

Southern Nuclear Operating Co., Inc.

Facility:

Vogtle Electric Generating Plant, Units 1 & 2

Location:

Waynesboro, GA 30830

Inspection Dates:

August 16, 2021 to August 20, 2021

Inspectors:

A. Lerch, Technical Assistant

A. Siwy, Senior Resident Inspector

T. Su, Reactor Inspector

Approved By:

James B. Baptist, Chief

Engineering Branch 1

Division of Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a NRC 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.

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), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.

REACTOR SAFETY

71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)

The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from August 16, 2021, to August 20, 2021.

10 CFR 50.59 Evaluations - 71111.17T

(1) SNC922254, Auxiliary Feedwater Orifice Replacement, Unit 1

(2) SNC922258, Auxiliary Feedwater Orifice Replacement, Unit 2

(3) SNC466754, Essential Chilled Water System High Efficiency Purge Units

(4) SNC1062133, Eliminate Single Point Vulnerabilities (SPV) from Main Steam Isolation Valve (MSIV) Control Circuits for Normally Energized Relays and Micro Switches, Unit 1

(5) SNC1062134, Eliminate SPVs from MSIV Control Circuits for Normally Energized Relays and Micro Switches, Unit 2

(6) SNC121433, Digital Solid State Protection System (SSPS) Card Types & Power Supplies, Unit 1

(7) SNC131026, Digital Solid State Protection System Card Types & Power Supplies, Unit 2

10 CFR 50.59 Screening/Applicability Determinations - 71111.17T

(1) SNC483170, 2B Nuclear Service Cooling Water (NSCW) Seismic Restraints

(2) SNC965540, A-train MSIV Actuator Replacements, Unit 1

(3) SNC847064, 1A Circulating Cooling Water Heat Exchanger NSCW Butterfly Valves Replacement

(4) SNC1052901, Holes in Emergency Diesel Generator (EDG) Crank Case Gear Cover

(5) SNC1083487, 1A Motor Driver AFW Pump Structure Stiffening

(6) SNC965527, Replace Control Rods, Unit 1

(7) SNC965529, Replace Control Rods, Unit 2

(8) SNC959023, SSPS Bridging Strategy, Unit 1

(9) SNC959025, SSPS Bridging Strategy, Unit 2

(10) SNC953976, Emergency Diesel Generator 701 Governor, Unit 1

(11) SNC122166, Replacement of 1E/non-1E Isolation HFB Molded-Case Circuit Breakers (MCCB), Unit1

(12) SNC131605, Replacement of 1E/non-1E Isolation HFB MCCB's, Unit 2

(13) SNC925169, Installation of Voltage Suppression Device on EDG 125VDC Engine Control Power Circuit

(14) SNC120667, HFB Breakers Containment, Unit 1

(15) SNC130200, HFB Breakers Containment, Unit 2

(16) SNC951739, 1B EDG Turbocharger Hold Down Bolts

(17) SNC974243, All EDG Turbocharger Hold Down Bolts

(18) SNC1072083, EDG Overspeed Governor Coupling Configuration Change

(19) SNC854620, Thermocouples

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On August 20, 2021, the inspectors presented the NRC inspection results to Jesse Thomas and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.17T Calculations

CJ-C-19-001

Exclusion Distances for Transceiver Systems

2.0

FMEA-VD-

SNC466754-M001

Failure Mode and Effects Analysis, High Efficiency Purge

Replacement

1.0

MC-V-06-0046

Electrical Penetrations - Short Circuit Currents

1.0

MC-V-06-0047

Fire Event Safe Shutdown Circuit Analysis (DCPs

105176740)

1.0

MC-V-06-0048

Electrical Penetrations - Short Circuit Currents

1.0

MC-V-06-0049

Fire Event Safe shutdown Circuit Analysis (DCPs

2051767701)

1.0

MC-V-19-0009

Evaluate Modifications to Control Room Panel 11605Q5SPA

MC-V-19-0016

Evaluate Modification to Computer Room Panel

21601Q5CBD Per DCP SNC959025

MC-V-19-0017

Evaluate the Replacement of Power Supply and Diode from

Control Room Panel 21605Q5SPA and 21605Q5SPB

MC-V-20-0011

Diesel Generator Building - Normal and Emergency

Operation

2.0

MC-V-20-0012

Diesel Generator Building Minimum Ventilation

Requirements

2.0

NF-V-20-007

Vogtle and Farley Units 1 and 2 - Calculations to Support

Elimination of Rod Worth Measurements from Startup

Physics Testing

1.0

X4C1302V15

AFW Hydraulic Analysis

X4C1531S18

Control Room Cooling with 19000 CFM

Corrective Action

Documents

10503915

10504371

10504866

10693151

10797023

10797024

TE 1063278

Natural Frequency Test on 1A MDAFW Pump

03/13/2020

Corrective Action

Documents

10820964

10821141

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Resulting from

Inspection

Engineering

Changes

1051767401

Electrical Penetration Assembly Circuit Breaker

Replacement

2.0

1081329601

Replacement of 1E/non-1E isolation HFB MCCBs

1.0

2051767701

Electrical Penetration Assembly Circuit Breaker

Replacement

2.0

2081329401

Replacement of 1E/non1E isolation HFB MCCB's

2.0

SNC1052901

DECP to document holes in EDG crank case gear cover

SNC1062133

Eliminate SPVs from MSIV control circuits for Normally

Energized MDR relays and micro switches.

SNC1062134

Eliminate SPVs from MSIV control circuits for Normally

Energized MDR relays and micro switches.

SNC1072083

EDG Overspeed Governor Coupling Configuration Change

SNC1083487

1A MDAFW Pump Structure Stiffening

SNC121433

Unit 1 Solid State Protection System (SSPS) Upgrade

7.0

SNC131026

Unit 2 Solid State Protection System (SSPS) Upgrade

6.0

SNC466754

High Efficiency Purge Units

2.0

SNC483170

2B NSCW Seismic Restraints

2.0

SNC847064

1R21 for 1A CCW Hx NSCW Butterfly Valves Replacement

1.0

SNC854620

1R20 Core Exit Thermocouple Modification

1.0

SNC922254

U1 AFW Orifice Replacement

SNC925169

Installation of Voltage Suppression Device on EDG 125VDC

Engine Control Power Circuit

SNC951739

1B EDG Turbocharger Hold Down Bolts

1.0

SNC953976

U1 Emergency Diesel Generator 701 Governor DCP

SNC959023

U1 SSPS Bridging Strategy: Low Margin, Increase UVTA

Coil Ckt Voltage

SNC959025

U2 SSPS Bridging Strategy

SNC965527

Replace Unit 1 Control Rods (RCCAs)

SNC965529

Replace Unit 2 Control Rods (RCCAs)

SNC965540

U1 A-train MSIV Actuator Replacements

SNC974243

DECP for EDG Turbo Charger Base Bolt

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Engineering

Evaluations

DOEJ-VD-

2071817801

Evaluate Existing Heating and Ventilation System for Control

Room due to the Replacement of Solid State Protection

System Equipment, Vogtle Nuclear Plant Unit 2

2.0

DOEJ-

VD1071817701-

J001

Replacement Westinghouse Solid State Protection System

(SSPS) Printed Circuit Boards (PCBs) EMC Evaluation

1.0

DOEJ-

VD1071817701-

M001

Evaluate Existing Heating and Ventilation System for Control

Room due to the Replacement of Solid State Protection

System Equipment, Vogtle Nuclear Plant Unit 1

1.0

Miscellaneous

AX4AK01-00510

Parts Manual for Model DSRV-16-4 Diesel Engine/Generator

39.0

Design Activity No.

1051767401

Design Verification Summary

Design Activity No.

1051767401

Design Input Record

1.0

Design Activity No.

2051 767701

Design Input Summary

1.0

Design Activity No.

2051767701

Design Verification Summary

2.0

DOEJ-

VDSNC925169-

E001

Evaluation for Proper Sizing of Fly-back Diode and Resistor

for Diesel Generator Power Available Solenoids

FCR No.

2081329401-1-F001

Field Change Request to Add Seismic Qualification Report

5/7/2009

FCR No:

2081329401-1.0-

F003

Field Change Requests

5/11/2011

FS1-0035816

Mechanical Interface and Functional Compatibility of GAIA

Lead Fuel Assemblies for Vogtle (VOG2-21L)

1.0

GP-19655

Transmittal of Vogtle Units 1&2 Auxiliary Feedwater (AFW)

Boundary Conditions Evaluation

2/08/2017

GP-19746

Vogtle AFW Restriction Orifice Modifications - Transmittal of

final letter for additional scope Item 1: Hot Zero Power

Steam Line Break Evaluation

04/17/2019

GP-19756

Vogtle AFW Restriction Orifice Modifications - Transmittal of

05/23/2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

final report for Vogtle Units 1 and 2 Steam Generator Tube

Rupture Input to Dose and Offsite Dose Analyses

SCN466754FCR002 High Efficiency Purge Units

3/18/2013

SCN466754FCR002 High Efficiency Units

3/18/2013

SNC466754

Design Verification Summary

1.0

SNC466754

Design Input Record

1.0

SNC925169

Configuration Change Evaluation - Design

Verification/Engineering Review

1.0

WCAP-14036-P-A

Elimination of Periodic Protection Channel Response Time

Tests

WCAP-17867-P-A

Westinghouse SSPS Board Replacement Licensing

Summary Report

Procedures

DC-1823

Electrical Protection Criteria

IP-ENG-001

Nuclear Industry Standard Design Process

NISP-EN-02

Nuclear Industry Standard Process Engineering

NMP-AD-008

Applicability Determinations

2.1

NMP-AD-009

Licensing Document Change Requests

17.0

NMP-AD-010

CFR 50.59 Screenings and Evaluations

17.1

NMP-ES-007

Conduct of Engineering

NMP-ES-095

Interface Procedure for IP-ENG-001, "Standard Design

Process"

9.0

NMP-ES-095-001

Documentation Change Processes

2.0

NMP-ES-098

Interface Procedure for NISP-EN-02 "Standard Item

Equivalency Process"

1.5

Work Orders

1071817715

Functionally test all circuit boards and power supplies

replace by DCP

2071817819

Functionally Test all Circuit Boards and Power Supplies

replaced by DCP 2071817801

SNC904956

SNC910579

SNC916188

SNC921535

0