IR 05000424/2022010
| ML22334A231 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/02/2022 |
| From: | James Baptist NRC/RGN-II/DRS/EB1 |
| To: | Gayheart C Southern Nuclear Operating Co |
| References | |
| IR 2022010 | |
| Download: ML22334A231 (18) | |
Text
December 2, 2022
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1&2 - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000424/2022010 AND 05000425/2022010
Dear Cheryl A. Gayheart:
On October 21, 2022, 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 Mr. R. Norris 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, James B. Baptist, Chief Engineering Br 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:
Report Numbers:
05000424/2022010 and 05000425/2022010
Enterprise Identifier:
I-2022-010-0047
Licensee:
Southern Nuclear Company, Inc.
Facility:
Vogtle Electric Generating Plant, Units 1&2
Location:
Waynesboro, GA
Inspection Dates:
October 03, 2022 to October 21, 2022
Inspectors:
P. Braxton, Reactor Inspector
T. Fanelli, Senior Reactor Inspector
C. Franklin, Reactor Inspector
J. Lizardi-Barreto, Reactor Inspector
A. Ruh, Resident Inspector
T. Su, Reactor Inspector
Approved By:
James B. Baptist, Chief
Engineering Br 1
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) 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.
REACTOR SAFETY
===71111.21M - Design Bases Assurance (DBA) Inspection The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:
Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (7 Samples)
(1)4160 VAC bus 1AA02, transformer 1BB07X
Material condition and configuration during a walkdown
Operating environment
Corrective and preventive maintenance effectiveness
Protective relay setting and calibration
Overcurrent protection and coordination
Alignment of Plant Wilson after station blackout
- (2) Nuclear service cooling water spray header and cold weather bypass butterfly valves HV-1668A, HV-1669A, HV-1668B and HV-1669B
Thrust, set-point, weak-link, maximum differential pressure calculations
Required capability during normal, abnormal, and emergency operating procedures, including loss of nuclear service cooling water system
Results of recent surveillance tests and procedure adequacy
Material condition of valves and associated equipment during a walkdown
Corrective action effectiveness
Control circuit scheme and periodic verification of electrical interlocks
- (3) Main steam isolation valve 2HV3016B
Thrust, set-point, weak-link, maximum differential pressure calculations
Air supply sizing (time, and pressure)
Required capability during normal, abnormal, and emergency operating procedures, including faulted steam generator, steam generator tube rupture, and station blackout
Results of recent surveillance tests and procedure adequacy
Material condition of valves and associated equipment during a walkdown Corrective action effectiveness
- (4) Containment purge valves 1/2HV-2624A/B, 2626A/B, 2627A/B, 2628A/B, 2629A/B
Material condition and configuration during a walkdown
Effectiveness of corrective and preventative maintenance to ensure containment isolation capability
Maintenance of seismic qualification
- (5) Auxiliary feedwater system pumps and valves 1/2-1302-P4-001, P4-002, P4-003, HV5132
Material condition and configuration during a walkdown
Correlation of flowrate acceptance criteria to accident conditions considering instrument inaccuracies and diesel generator voltage and frequency uncertainties
Surveillance testing results and compliance with inservice testing code requirements (instrumentation selection, reference values, documentation)
System capability and protection during flooding from high energy line breaks
Modifications to safety analysis design basis cases and system assumptions
Control valve closing capability under reverse flow conditions described in failure modes and effects analysis
- (6) Residual heat removal system pumps 1/2-1205-P6-002
Material condition and configuration during a walkdown
Design bases and design assumptions have been appropriately translated into design calculations, drawings, and procedures.
Corrective actions and preventative maintenance effectiveness
Maintenance of seismic qualification
Results of recent surveillance tests in accordance with applicable procedures
Termination of inadvertent safety injection
- (7) Residual heat removal to safety injection discharge motor operated gate valves 1/2-1205-HV-8804B
Material condition and configuration during a walkdown
Design bases and design assumptions have been appropriately translated into design calculations, drawings, and procedures.
Results of recent surveillance tests in accordance with applicable procedures
Corrective actions and preventative maintenance effectiveness
Maintenance of seismic qualification Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02)===
(1)125 VDC panel 1BD11/1BD1 and circuit breaker 1BD105
Corrective and preventive maintenance effectiveness Battery capacity calculation
Effectiveness of corrective actions
Periodic verification of electrical interlocks
Modification Review - Permanent Mods (IP Section 02.03) (4 Samples)
- (1) SNC959023, SNC959025 - Unit 1 and 2 Solid State Protection System Bridging Strategy: Low Margin, Increase Under-Voltage Trip Attachment Coil Circuit Voltage
Post-modification testing and operability
Coil voltage
- (2) SNC922254, SNC922258 - Unit 1 and 2 Auxiliary Feedwater Orifice Replacements
Orifice installation orientation
Post-modification flow tests and hydraulic model assumptions
Pumphouse internal flooding scenario impacts
- (3) SNC1046656 - Unit 2 A-train Main Steam Isolation Valve Actuator Replacements
Design drawings, installation adequacy and post-modification testing
Pipe stress analysis
Updated Technical Requirements Manual curves
Stroke times during high-and low-pressure operations
- (4) SNC1062134, SNC1062133 - Eliminate Single Point Vulnerabilities from Main Steam Isolation Valve Control Circuits for Normally Energized MDR Relays and Micro Switches
Design inputs and elementary drawing logic
Post-modification testing
Review of Operating Experience Issues (IP Section 02.06) (3 Samples)
- (1) Information Notice 2021-01, Lessons Learned from NRC Inspections of Design-Basis Capability of Power-Operated Valves at Nuclear Power Plants
- (2) Information Notice 2020-02, Flex Diesel Generator Operational Challenges
- (3) Information Notice 2019-10, Failures Reported in Eaton/Cutler Hammer A200 and Freedom Series Contactors
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On October 21, 2022, the inspectors presented the design basis assurance inspection (teams) inspection results to Mr. R. Norris and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
GP-17105
Weak Link Analysis for Valves 8804 A & B
05/11/2000
1/2X6AA06-661-4
Valve 4G Seismic Upgrade Evaluation Report
11/09/1988
AX5AC01-00365
HV5132 Weak Link AFW Discharge Valve
09/03/1987
AX5C03-00722-1
Fisher Weak Link Analysis and Calculation Procedure for
280 Series Butterfly Valves
3/17/2000
DC-1000-M
General Design Criteria (Mechanical)
DC-1005
Seismic - Interdiscipline
DC-1007
Environment - Interdiscipline
DC-1009
Plant Single-Failure Criteria
DC-1018
Pipe Break Criteria - Interdiscipline
DC-1204
Safety Injection System
DC-1205
Residual Heat Removal System
SNC143798
NMP-ES-050-F01, RER Response Form to Fleet NMP-MA-
010 Meets the Sites Seismic Criteria
C110878101
VNP-1HV8804B
Thrust and Torque Calculation 1HV8804B (VNPS-1) AC
Motor Operated GL-96-05 Gate Valve
VNP-2HV8804B
Thrust and Torque Calculation 2HV8804B (VNPS-2) AC
Motor Operated GL-96-05 Gate Valve
2.3
X2CQ10.04
Civil/Seismic Requirements of Scaffolding in Safety Related
Area per Procedure NMP-MA-010
X3CA18
Evaluate Station Auxiliary System Loads
X3CF02
Determine Class 1E Battery Sizing per IEEE STD 485-1983
25.0
X3CT08
Fire Event Safe Shutdown Circuit Analysis
X4C1000U01
Differential Pressure Calculations for REA VG-9049
X4C1000U01
Differential Pressure Calculations for REA VG-9049
X4C1202S26
Ultimate Heat Sink Analysis
X4C1202V02
NSCW Cooling Tower Fan Performance - After SBO
Calculations
X4C1202V03
Verification of NSCW Constant Heat Loads and Flows and
Cooldown Heat Loads
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
X4C1204S07
ECCS Reference Summary
X4C1204V23
Generic Decay Heat Power Curve Calculation
X4C1205V01
Residual Heat Removal System Design
11/08/1983
X4C1205V02
Cooldown Transient with One RHR Train
2/1/1993
X4C1205V03
RHR Pump Runout
11/10/1987
X4C1205V04
One and Two Train Cooldown of RCS
07/11/2013
X4C1205V04
One and Two Train Cooldown of RCS
X4C1301S00F1
FMEA - Main Steam System
X4C1301U01
Main Steam Line Pressure Safety Valve Forces
X4C1302S00F1
FMEA - Auxiliary Feedwater and Condensate Storage
System
X4C1302V15
AFW Hydraulic Analysis
X4CPS.0075.411
Qualification of Valves for Generic Letter 89.10 (FQP-11AB-
9)
X5CP1668
NSCW Cooling Tower Spray Header Shutoff and Bypass
Valve Controls Train "A" & Train "B"
X5CP5150
Aux Feedwater Supply to SG Flow Indication
X6CAJ.08
Main Steam Line Break Offsite Doses
1.0
X6CXC36
Flooding Analysis - VNP Auxiliary Feedwater Pumphouse -
Unit 1 & 2
10648087
Adverse trend previously identified in 2B RHR Pump dP
09/20/19
10667477
SI "B" Boric Acid buildup
11/26/19
10667479
SI Accumulator Local Sample valve Boric Acid leak
11/26/19
10698551
U1 CNMT Penetration 84 CNMT PURGE EXH LLRT 1HV-
28A failed
03/25/20
10730669
2R21 Outage Scheduling MOV Delay Starts Lesson
Learned
08/16/20
10740052
14" Flexible connection on the U2 CTB Normal Purge
exhaust line degraded
09/19/20
10748136
SI Accumulator Local Sample valve & Swagelock Fitting
Boric Acid leak
10/22/20
Corrective Action
Documents
10748140
SI Accumulator Local Sample valve & Swagelock Fitting
Boric Acid leak
10/22/20
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
10828191
Unit 1 Containment Mini-Purge Exhaust Tripped
09/18/21
10829955
Unit 1 Train A RHR pump issue observed during start
following maintenance
09/25/21
10861521
2HV0607 - Minor to Moderate Dry Boric Acid on Flange and
bolting
2/23/22
10865776
Valve Needed for 2R22 N2 SI
03/11/22
10866977
2-HIC-607A has no light indication
03/16/22
10881597
Mini Purge Supply Fan trips on low flow causing QHVC
alarm ALB52-F06
05/17/22
276875, 277066,
10698290,
10698575,
10735584,
10651765,
10677066,
10694969,
10695405,
10695498,
10706799,
10731564,
10742075,
1070318,
1074681,
10702730,
10770466,
10777711,
10781950,
10799120,
10787581,
10708502,
10656219,
10719559,
10804425,
10811954,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
10816524,
10819167,
10847364,
10852544,
10736252,
10727859,
10868529,
10774529,
10840714,
10840885,
10899662,
10826914,
10802172,
10797827,
10740785,
10856612,
10789981,
10788415,
10777575,
10746820,
10730606,
10725202,
10723290,
10868818,
10866094,
10834601,
10740784,
10735561,
10878409,
10821009,
10799528,
10768308,
10701339,
10695396,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
10669859,
10656214,
10878379,
10870460,
10859659,
10792727,
10741214,
10690643,
10906295,
10870727,
10833215,
10775867,
10901500,
10902970
10912618
Incorrect dP recorded for TDAFW in surveillance 14748-
103-SNC788814
10912619
Minor oil residue 1B MDAFW pump motor
10912896
Aux building C46 overhead lighting not operating
10912898
Auxiliary building C46 floor degradation
10913164
Inconsistent use of of elbows on solenoid exhaust ports
10913181
Sections of flexible conduit do not have grounding cable
installed
10913183
HVAC damper limit switch missing FME cover
10913184
Scaffold with outdated tag
10913185
Housekeeping around U1 and U2 containment purge valve
actuators
10913186
Minor oil leak on 1HV2629B valve actuator
10913187
Scaffold clamp to be removed
10913188
Review installation of permanent scaffold underneath
1HV2629A/B
10913189
Flex joint tie rod missing nut
10913190
Coating peeling on containment purge valve actuator
Corrective Action
Documents
Resulting from
Inspection
10916850
NMP-MA-010 provides insufficient guidance for particular
cases
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
10916866
Capability of AFW discharge MOV function not
demonstrated
Main One Line Unit 1
One Line Diagram, 4160 Switchgear 1AA02
One Line Diagram-480V Switchgear 1BB07
1X3D-AA-M)8A-56
Unit 1 Relaying Data
034
Unit 1 Relaying Data
035
Unit 1 Relaying Data
Unit 1 Relaying Data
Elementary Diagram for 1HV-1668A
1X3D-BD-K05V
Elementary Diagram for 1HV-1668B
1X3D-BD-K05W
Elementary Diagram for 1HV-1669A
1X3D-BD-K05X
Elementary Diagram for 1HV-1669B
1X4AR17-00208-2
Air and Hydraulic System Schematic & Actuator Control
Wiring Diagram for Gate Valve 1HV-3026B
1.0
1X4DB121
P&I Diagram Safety Injection System No. 1204
1X4DB122
P&I Diagram Safety Injection System No. 1205
1X4DB133-1
P&ID Nuclear Service Cooling Water System No. 1202
1X4DB133-2
P&ID Nuclear Service Cooling Water System No. 1202
1X4DB161-1
P & I Diagram Auxiliary Feedwater System, Condensate
Storage & Degasifier System, System No. 1302
1X4DB161-2
P & I Diagram Auxiliary Feedwater System, System No.
1302
1X4DB161-3
P & I Diagram Auxiliary Feedwater System, (Aux
Feedwater Pump Turbine Driver), System No. 1302
1X4DB168-3
P & I Diagram Condensate & Feedwater System, System
No. 1305
1X6AA06-00411
Motor Op. Gate Valve Mod 08002GM84FEB010
2X4DB159-1
PI&D Main Steam System No. 1301
Drawings
39A2461
Body NT316-SR2-M3-9280 Bettis Actuated Control
C
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Valve CW to Close Valve Shaft Rotation Horiz Pipe, Vert
Shaft
39A2462
Body NT316-SR2-M3-9280 Bettis Actuated Control
Valve CW to Close Valve Shaft Rotation Horiz Pipe, Vert
Shaft
C
AX6AF02-20007-4
Pump Size 8X20WDF Coupled Design
D
AX6AU01-00526
Westinghouse Process I&C Volume 1
AX6D025
Control Building Floor Plan Elevation 2200 Level 1 Seismic
Category Areas
AX6D030
Control Building and Equipment Building Floor Plan EL. 220
FT. -0 IN. Level 1 Seismic Category Areas
3.0
CX3DE001
Grounding - General Notes, Symbols & Details
DC-1018
Design Criteria - Pipe Break Criteria - Interdiscipline
DC-1302
Design Criteria - Auxiliary Feedwater System
SNC1062133E001
Elementary Diagram Main Steam System1HV-3006A
1.0
SNC1062133E002
Elementary Diagram Main Steam System 1HV-3016A
1.0
SNC1046656
U2 A-train MSIV Actuator Replacements
A
SNC1046656
U2 A-Train MSIV Actuator Replacement
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
SNC922254
U1 AFW Orifice Replacement
Engineering
Changes
SNC922258
U2 AFW Orifice Replacement
AX5AG02-00103
Test Report of Flow Determination Testing on Orifices
Performed for Plant Vogtle
DC-1000-E
General Design Criteria ( Electrical)
DC-1804
4160-V AC System
DC-1805
480V AC System
FCP-7
Butterfly Valve Sizing and Internal Component Calculation
Procedures
B
Miscellaneous
GP-19473
Transmittal of LTR-TA-16-148, Vogtle Units 1 and 2:
Auxiliary Feedwater Flow
Assumptions Modeled in the Feedwater System Pipe Break
11/07/2016
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
(Feedline Break) Analysis
NSAL-19-2
NSAL-19-2 Revision 0, "Contactors Failing to
Release/Open When De-energized"
09/24/2019
RAL 5168
Main Steam Isolation Valve Maintenance Manual
RAL-7094
Fatigue Analysis for MSIV Actuator Assembly
TE1051341
Westinghouse NSAL-19-2 Contactors Failing to
Release/Open When Deenergized
9/6/2019
Unit 1 SHR CTMT
CTMT System Health Report # 2101 Vogtle Unit 1
09/30/2022
Unit 1 SHR RHR
RHR System Health Report # 1205 Vogtle Unit 1
09/30/2022
Unit 1 SHR SI
SI System Health Report # 1204 Vogtle Unit 1
09/30/2022
Unit 2 SHR CTMT CTMT System Health Report # 2101 Vogtle Unit 2
09/30/2022
Unit 2 SHR RHR
RHR System Health Report # 1205 Vogtle Unit 2
09/30/2022
Unit 2 SHR SI
SI System Health Report # 1205 Vogtle Unit 2
09/30/2022
A
Treatment of Diesel Generator (DG) Technical Specification
Frequency and Voltage Tolerances
Operability
Evaluations
AX6AA15-00002
Vogtle Electric Generating Plant - Unit 1/2, Pump and Valve
Operability Report
11882-1
Unit 1 Outside Area Rounds
106
14150A-1
Train A NSCW Fan/Spray Valve Surveillance
14150B-1
Train B NSCW Fan/Spray Valve Surveillance
14721C-1
ECCS Subsystem Flow Balance and Checkvalve Refueling
Inservice Test
14721D-1
ECCS Subsystem Flow Balance and Checkvalve Refueling
Inservice Test
14748-1
AFW Pump and Check Valve Cold S/D IST and TDAFWP
Auto Start Test
35.1
14805B-1
Train B Residual Heat Removal Pump IST and Response
Time Test
5.3
14807A-1
Train A Motor Driven Auxiliary Feedwater Pump / Check
Valve Inservice and Response Time Test
10.1
14807B-1
Train B Motor Driven Auxiliary Feedwater Pump / Check
Valve Inservice and Response Time Test
5.2
Procedures
14825-1
Quarterly Inservice Valve Test
106.5
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
14850-1
Cold Shutdown Valve Inservice Test
60.0
14850-2
Cold Shutdown Valve Inservice Test
17061-1
Annunciator Response Procedures for ALB 61 on Process
Control Panel
19.4
18021-C
Loss of Nuclear Service Cooling Water System
19020-1
E-2 Faulted Steam Generator Isolation
1.1
19030-1
E-3 Steam Generator Tube Rupture
26007-C
Bettis Actuator Maintenance (Track Series)
13.3
AX5AC03-10001
Vogtle Electric Generating Plant - Unit No. 1/2 Operating
and Maintenance Instructions Disassemble and Assembly
for Nuclear Series Actuators
2.0
AX6AF02-20030
Vogtle Electric Generating Plant - Unit No. 1/2 Installation
Operation & Maintenance Manual & Supplement RHR
Pumps
18.0
MIS-17-009
Vogtle Electric Generating Plant Fourth 10-Year Interval
Inservice Testing Program
13.0
NMP-AD-028
CFR 21 Evaluations and Reporting Requirements
7.0
NMP-AD-028
CFR 21 Evaluations and Reporting Requirements
7.0
NMP-ES-006
Preventive Maintenance Implementation and
Continuing Equipment Reliability Improvement
13.0
NMP-ES-006-001
PM Template Management and PM Optimization
Guidance
4.1
NMP-ES-006-002
Preventive Maintenance Change Requests
11.0
NMP-ES-006-003
Preventive Maintenance Feedback
6.1
NMP-ES-006-004
Preventive Maintenance Oversight Group
6.0
NMP-GM-002
Corrective Action Program
16.0
NMP-GM-002-001
Corrective Action Program Instructions
43.0
NMP-MA-010-001
Permanent Scaffolding Installation, Modification, and
Removal Process
1.3
SNC1158288
B-RHR IST (Q) - I&C Support Req.
Work Orders
SNC1171119,
SNC1142967,
SNC622778,
SNC970653,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SNC832642,
SNC795416,
SNC979326,
SNC832139,
SNC832138,
SNC1030647,
SNC1030645,
14748-101T-
38119, 14748-
101-1101737801,
SNC351861,
SNC788814,
SNC905686,
SNC1159355,
SNC1174182,
SNC1189035,
SNC1163251,
SNC1178133,
SNC1193831,
SNC1105655,
SNC1233676,
SNC 396689,
SNC494595,
SNC731534,
SNC904311,
SNC909433,
SNC913849,
SNC981075,
SNC377678,
SNC774779,
SNC832143,
SNC856543,
SNC972592,
SNC1089908
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SNC1172960
B-RHR IST (Q) - I&C Support Req.
SNC1187666
B-RHR IST (Q) - I&C Support Req.
SNC1258537
205, 2HIC607A, Investigate and Correct Cause of no light
Indication
SNC809832
ECCS Flow/Bal-14721-C-1
SNC809837
ECCS Flow/Bal-14721-C-1
0