ML24191A379
| ML24191A379 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/10/2024 |
| From: | Bradley Davis NRC/RGN-II/DCI/CIB2 |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| IR 2024011 | |
| Download: ML24191A379 (13) | |
Text
Jamie Coleman Regulatory Affairs Director Southern Nuclear Operating Company, Inc.
3535 Colonnade Parkway, N 274 EC Birmingham, AL 35243
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNIT 4 - INITIAL TEST PROGRAM AND OPERATIONAL PROGRAMS INSPECTION REPORT 05200026/2024011
Dear Jamie Coleman:
On June 10, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Vogtle Electric Generating Plant, Unit 4. The enclosed inspection report documents the inspection results, which the inspectors discussed on June 10, 2024, with William Garrett, Vogtle Units 3 & 4 Licensing Manager.
The inspection examined a sample of construction activities conducted under your Combined License (COL) as it relates to safety and compliance with the Commissions rules and regulations and with the conditions of these documents. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Based on the results of this inspection, no findings of significance were identified.
This inspection report marks the completion of all inspections associated with operational programs and startup testing described in Inspection Manual Chapter (IMC) 2504, Construction Inspection Program: Inspection of Construction and Operational Programs, and IMC 2514, AP1000 Reactor Inspection Program - Startup Testing Phase.
July 10, 2024 J. Coleman 2 The NRC will continue to monitor your performance in accordance with the Reactor Oversight Process, 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.
Sincerely, Bradley J. Davis, Chief Division of Construction Oversight Construction Inspection Branch 2 Docket Nos.: 5200026 License Nos: NPF-92
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV Signed by Davis, Bradley on 07/10/24
J. Coleman 3
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNIT 4 - INITIAL TEST PROGRAM AND OPERATIONAL PROGRAMS INSPECTION REPORT 05200026/2024011 DATED JULY 10, 2024
DISTRIBUTION:
R2EICS RidsNrrPMVogtle Resource RidsNrrDro Resource RidsNrrVpo Resource
ADAMS ACCESSION NO ML24191A379 SUNSI Review Non-Sensitive Publicly Available Sensitive Non-Publicly Available OFFICE RII/DCO RII/DCO RII/DCO NAME J. Quiones J. Parent B.Davis DATE 7/8/2024 7/9/2024 7/10/2024 OFFICIAL RECORD COPY U.S. NUCLEAR REGULATORY COMMISSION Region II
Docket Numbers: 5200026
License Numbers: NPF-92
Report Numbers: 05200026/2024011
Enterprise Identifier: I-2024-011-0035
Licensee: Southern Nuclear Operating Company, Inc
Facility: Vogtle Unit 4 Combined License
Location: Waynesboro, GA
Inspection Dates: April 1, 2024, through June 10, 2024
Inspectors: J. Eargle, Senior Resident Inspector, Division of Construction Oversight (DCO)
J. Parent, Resident Inspector, DCO B. Griman, Resident Inspector, DCO S. Egli, Senior Construction Inspector, DCO M. Magyar, Operations Inspector, Division of Reactor Safety (DRS)
B. Bowker, Operations Inspector, DRS
Approved by: Bradley J. Davis, Chief Division of Construction Oversight Construction Inspection Branch 2
Enclosure
SUMMARY
OF FINDINGS
Inspection Report (IR) 05200026/2024011; April 1 - June 10, 2024; Vogtle Unit 4 Combined License, initial test program and operational programs integrated inspection report.
This report covers an almost three-month period of announced inspections of startup testing and operational programs by resident and regional inspectors. The significance of most findings is indicated by their color (Green, White, Yellow, or Red), using Inspection Manual Chapter (IMC) 0609, Significance Determination Process. Cross-cutting aspects are determined using IMC 0310, Aspects Within the Cross-Cutting Areas. All violations of NRC requirements are dispositioned in accordance with the NRCs Enforcement Policy. The NRCs program for oversight of AP1000 startup activities is described in IMC 2514, AP1000 Reactor Inspection Program - Startup Testing Phase.
A. NRC-Identified and Self Revealed Findings
None
B. Licensee-Identified Violations
None
2 REPORT DETAILS
Summary of Plant Construction Status
During this report period for Unit 4, the licensee completed all remaining startup tests as part of the initial test program. These tests were part of the power ascension testing at 100% power.
These tests included main generator trip from 100%, a loss of offsite power, and a 100% load rejection.
This concluded the initial test program and operational programs as the licensee transitioned to commercial operations on April 29, 2024.
- 3. OPERATIONAL READINESS
Cornerstones: Operational Programs
IMC 2504, Construction Inspection Program - Inspection of Construction and Operational Programs
3P01 Preservice Inspection
The inspectors used the following NRC inspection procedure (IP)/section to perform this inspection:
- IP 73757-02.02 - General Records Review
- IP 73757-02.02 - American Society of Mechanical Engineers (ASME) Class 1 Records Review
- a. Inspection Scope
The inspectors reviewed the licensees preservice and inservice inspection programs to verify if the programs where in conformance with the regulatory requirements of 10CFR 50.55a and the licensees commitments. The inspectors further evaluated the programs to verify the programs contained the proper scope of components, applicable quality assurance, contained repair/replacement programs, records management, and training for staff. In addition, the inspectors evaluated the licensees application of non-destructive testing for the reactor vessel and attachments by reviewing the following examinations to verify if they satisfied the ASME Code,Section III, 1998 Edition with Addenda 1999 through 2000:
3 Exam Category B-A:
- B1.11, Weld SV4-RPV-101-51
- B1.21, Weld SV4-RPV-201-40 Exam Category B-B:
- B2.11, Welds SV4-PRZ-CW-001, SV4-CMTA-CW-001/1
- B2.21, Weld SV4-CMTA-CW-002/2
- B2.22, Weld SV4-CMTA-LW-014-1/-1
- B2.40, Weld SV4-SG-A-5101-71
- B2.60, Weld SV4-PRHRHX-CW-029/1 Exam Category B-D:
- B3.90, Weld SV4-RPV-24A-101
- B3.100, Weld SV4-RPV-24A-101-IRS
- B3.120, Weld SV4-PRZ-CW-031-IRS
- B3.140, Weld SV4-SG-1 A-8301-52A-IRS
- B3.160, Weld SV4-PRHRHX-NZ-001/1-IRS Exam Category B-F:
- B5.10, Weld SV4-RPV-24A-103-SE
- B5.40, Welds SV4-PRZ-CW-031-SE, SV4-PRZ-CW-035-SE, SV4-PRZ-N05-SE Exam Category B-G-1:
- B6.20, Studs SV4-RPVH-S01, SV4-RPVH-S02, SV4-RPVH-S03 Exam Category B-G-2:
- B7.40, Cap Screws SV4-RCP-1A-CS01 thru CS04, SV4-RCP-1 B-CS01 thru CS04, SV4-RCP-2B-CS01 thru CS04 Exam Category B-J:
- B9.11, Weld SV4-PXS-PLW-011-FW1
- B9.21, Welds SV4-RCP-1A-04, SV4-RCP-1A-05, SV4-RCP-1A-06 Exam Category B-K:
- B10.10, Welds SV4-PRHRHX-CW-006/1, SV4-PRZ-ULS-B01, SV4-PRZ-ULS-B02 Exam Category B-N-1:
- B13.10, Vessel Interior SV4-RVI-VIS-001 Exam Category B-N-2:
- B13.60, Interior Attachments beyond beltline region SV4-RVI-FSS-01 to 08, SV4-RVI-RS-01 to 04 Exam Category B-N-3:
- B13.70, Core support structures SV4-RVI-CB-08, SV4-RVI-CS-03, SV4-RVI-LCSP-02, SV4-RVI-NP-07, SV4-RVI-SC-01 to 06, SV4-RVI-UCB-05, SV4-RVI-USP-11, SV4-RVI-VSP-01, SV4-RVI-LGT-04 Exam Category B-O:
- B14.20, Welds SV4-CRDM-1506-Joint 1, SV4-CRDM-1507-Joint 1, SV4-CRDM-1508-Joint 1 Exam Category B-Q:
- B16.20, SG2 Tubes R139C67, R146C84 Exam Category C-A:
- C1.10, Welds SV4-SG-A-101-35, SV4-SG-A-7101-71 Exam Category C-B:
4
- C2.21, Welds SV4-SG-A-202-21, SV4-SG-A-203-21
- C2.22, Weld SV4-SG-A-202-21-IRS Exam Category C-F-1:
- C5.21, Welds SV4-CVS-PLW-531-FW1, SV4-CVS-PLW-531-FW8, SV4-CVS-PLW-531-SW5 Exam Category C-F-2:
- C5.51, SV4-SGS-PLW-010-FW1, SV4-SGS-PLW-010-FW11, SV4-SGS-PLW-010-FW15 Exam Category D-A:
- D1.20, Welds SV4-12167-ML-P38, SV4-PCS-PH-12A0340, SV4-PCS-PH-12A0341
- b. Findings
No findings were identified.
IMC 2514, AP1000 Reactor Inspection Program - Startup Testing Phase
3T01 Initial Test Program (Startup)
The inspectors used the following NRC IP/section to perform this inspection:
- IP 72304, Attachment 14 - Plant Trip from 100% Power
- a. Inspection Scope
The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedure to verify if Unit 4s automatic control systems had the ability to sustain a manual generator trip from 100% rated thermal power and bring the plant to stable conditions following the transient, in addition to assessing the dynamic response of the plant when the turbine was subjected to its maximum overspeed condition. The inspectors observed the conduct of this procedure to verify if they satisfied the applicable quality and technical requirements of the updated final safety analysis report (UFSAR) and Technical Specifications.
- 4-GEN-ITPS-636, Plant Trip from 100% Power Startup test Procedure, Ver. 1.0 (TPC 1.0 & 2.0)
The inspectors used appropriate portions of the IP to review the licensees completed work package to verify if Unit 4s automatic control systems had the ability to sustain a manual main generator trip from 100% rated thermal power and to bring the plant to stable conditions following the transient, in addition to assessing the dynamic response of the plant when the turbine was subjected to its maximum overspeed condition. The inspectors reviewed the test results to verify if they satisfied the applicable quality and technical requirements of the UFSAR and Technical Specifications.
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- WO SNC1465839, ITP perform 4-GEN-ITPS-636 Plant Trip from 100% Power Startup Test, Rev. 0, Completed 04/23/2024.
- b. Findings
No findings were identified.
3T02 Initial Test Program (Startup)
The inspectors used the following NRC IP/section to perform this inspection:
- IP 72304, Attachment 11 - Loss of Offsite Power
- a. Inspection Scope
The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedure to verify if Unit 4s automatic control systems had the ability to sustain a manual generator trip with no offsite power available, and to bring the plant to stable conditions following the transient. The inspectors observed the conduct of this procedure to verify if they satisfied the applicable quality and technical requirements of the UFSAR and Technical Specifications.
- 4-GEN-ITPS-638, Loss of Offsite Power Startup Test Procedure, Ver. 1.0
The inspectors used appropriate portions of the IP to review the licensees completed work package to verify if Unit 4s automatic control systems had the ability to sustain a manual main generator trip with no offsite power available, and to bring the plant to stable conditions following the transient. The inspectors reviewed the test results to verify if they satisfied the applicable quality and technical requirements of the UFSAR and Technical Specifications.
- WO SNC1465841, 4-GEN-ITPS-638 Perform Loss of Offsite Power Startup Test, Rev. 0, Completed 04/19/2024.
- b. Findings
No findings were identified.
3T03 Initial Test Program (Startup)
The inspectors used the following NRC IP/section to perform this inspection:
- IP 72304, Attachment 23 - 100% Load Rejection
6
- a. Inspection Scope
The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedure to verify if Unit 4s automatic control systems had the ability to sustain the plant in island mode following a full load rejection. The inspectors observed the conduct of this procedure to verify if they satisfied the applicable quality and technical requirements of the UFSAR and Technical Specifications.
- 4-GEN-ITPS-633, 100% Load Rejection Startup Test Procedure, Ver. 3.0 (TPC 1)
The inspectors used appropriate portions of the IP to review the licensees completed work package to verify if Unit 4s automatic control systems had the ability to sustain the plant in island mode following a full load rejection. The inspectors reviewed the test results to verify if they satisfied the applicable quality and technical requirements of the UFSAR and Technical Specifications.
- b. Findings
No findings were identified.
- 4. OTHER INSPECTION RESULTS
4OA6 Meetings, Including Exit
.1 Exit Meeting.
On June 10, 2024, the inspectors presented the inspection results to William Garrett, Vogtle Units 3 & 4 Licensing Manager. Proprietary information was reviewed during the inspection period but was not included in the inspection report.
7 SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensees and Contractor Personnel
A. Nix, ITP Director E. Loehlein, Operations Director J. Coleman, Regulatory Affairs Director J. Hartman, Shift Operations Manager D. Trafford, Operations Support Manager C. Parkes, Operations Services Manager S. Leighty, Regulatory Affairs Manager W. Garrett, Licensing Manager C. Houseal, Startup Manager J. Dixon, Radiation Protection Manager S. Trickett, Radiation Protection Support Superintendent
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Item Number Type Status Description
None
LIST OF DOCUMENTS REVIEWED
IMC 2514, AP1000 Reactor Inspection Program - Startup Testing Phase
Section 3T01 Procedures:
4-GEN-ITPS-636, Plant Trip from 100% Power Startup test Procedure, Ver. 1.0 (TPC 1 & 2) 4-AOP-207, Loss of Turbine Load, Ver. 3.0
Miscellaneous:
WO SNC1465839, ITP perform 4-GEN-ITPS-636 Plant Trip from 100% Power Startup Test, Rev. 0, Completed 04/23/2024.
SV4-PMS-T2R-6361, Vogtle Unit 4 Plant Trip from 100% Power (GEN-636) Reactor Trip Post Test Analysis to Validate the Overall Hot Leg RTD Response Time, Rev. 0 SNC1756447, OAR SV4-ZAS-GEF-033: Unit 4 Generator Relay Stator Earth Fault Setting &
SV4-ZAS-GEF-034 GE G60 Relay Over Frequency GCB Open Supervision, Rev. 0 CR 11066747 CR 11066644 CR 11065353 CR 11065274
Section 3T02 Procedures:
8 4-GEN-ITPS-638, Loss of Offsite Power Startup Test Procedure, Ver. 1.0 4-AOP-302, Loss of AC Power, Ver. 1.0 4-AOP-207, Loss of Turbine Load, Ver. 2.0 4-EOP-E-0, Reactor Trip or Safeguards Actuation, Ver. 1.0 4-EOP-ES-0.1, Reactor Trip response, Ver. 1.0
Miscellaneous:
WO SNC1465841, 4-GEN-ITPS-638 Perform Loss of Offsite Power Startup Test, Rev. 0, Completed 04/19/2024.
SV4-GW-GNR-028, Disposition of Deviation Identified During Loss of Offsite Power Test, Rev. 0 CR 11062915 CR 11067200 CR 11065567
Section 3T03 Procedures:
4-GEN-ITPS-633, 100% Load Rejection Startup Test Procedure, Ver. 2.0 (TPC 1) 4-AOP-207, Loss of Turbine Load, Ver. 3.0
Miscellaneous:
WO SNC1465837, ITP Perform 4-GEN-ITPS-633 100% Load Rejection Test, Rev. 0, Completed 04/25/2024.
TE 1152938 CR 11003392 CR 11066094 CR 11066100
9 LIST OF ACRONYMS
COL Combine License DCO Division of Construction Oversight DRS Division of Reactor Safety IMC inspection manual chapter IP inspection procedure IR inspection report NRC Nuclear Regulatory Commission UFSAR Updated Final Safety Analysis Report
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