IR 05000424/2021010
| ML21204A034 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/23/2021 |
| From: | Alan Blamey NRC/RGN-II/DRP/RPB2 |
| To: | Gayheart C Southern Nuclear Operating Co |
| References | |
| IR 2021010 | |
| Download: ML21204A034 (12) | |
Text
July 23, 2021
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000424/2021010 AND 05000425/2021010
Dear Ms. Gayheart:
On June 25, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Vogtle Electric Generating Plant and discussed the results of this inspection with Mr. Drayton Pitts and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspection team reviewed the stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.
Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews the team found no evidence of challenges to your organizations safety-conscious work environment. Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
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/
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: 05000424/2021010 and 05000425/2021010 Enterprise Identifier: I-2021-010-0020 Licensee: Southern Nuclear Operating Co., Inc.
Facility: Vogtle Electric Generating Plant Location: Waynesboro, GA Inspection Dates: June 07, 2021 to June 25, 2021 Inspectors: J. Hickman, Senior Resident Inspector D. Mas-Penaranda, Resident Inspector N. Peterka, Fuel Facility Inspector M. Singletary, Reactor Inspector T. Su, Reactor 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 a biennial problem identification and resolution inspection at Vogtle Electric Generating Plant, 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.
OTHER ACTIVITIES - BASELINE
71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 02.04)
- (1) The inspectors performed a biennial assessment of the licensees corrective action program, use of operating experience, self-assessments and audits, and safety conscious work environment (SCWE).
- Corrective Action Program Effectiveness: The inspectors assessed the corrective action programs effectiveness in identifying, prioritizing, evaluating, and correcting problems. The inspectors also conducted an in-depth CAP review of the 125 VDC System, Reactor Protection System and Alternating Current (AC) Power System including 480 V and 4160 V Safety Related AC Power.
- Operating Experience: The inspectors assessed the effectiveness of the stations processes for use of operating experience, audits and self-assessments.
- Self-Assessments and Audits: The inspectors assessed the effectiveness of the licensee's self-assessments and audits.
- Safety Conscious Work Environment (SCWE): The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.
INSPECTION RESULTS
Assessment 71152B 1. Corrective Action Program Effectiveness Problem Identification: The team determined that the licensee was effective in identifying problems and entering them into the corrective action program and that there was a low threshold for entering issues into the corrective action program. This conclusion was based on a review of the requirements for initiating condition reports as described in licensee procedure NMP-GM-002, "Corrective Action Program," and managements expectation that employees were encouraged to initiate condition reports. Additionally, site management was actively involved in the corrective action program and focused appropriate attention on significant plant issues.
Problem Prioritization and Evaluation: Based on the review of condition reports, the team concluded that problems were prioritized and evaluated in accordance with the condition report significance determination guidance in procedure NMP-GM-002. The team determined that adequate consideration was given to system or component operability and associated plant risk. The team determined that plant personnel had conducted cause evaluations in compliance with the licensees corrective action program procedures and that cause determinations were appropriate, and considered the significance of the issues being evaluated.
Corrective Actions: Based on a review of corrective action documents, interviews with licensee staff, and verification of completed corrective actions, the team determined that corrective actions were mostly timely, commensurate with the safety significance of the issues, and effective, in that conditions adverse to quality were corrected. For significant conditions adverse to quality, the corrective actions directly addressed the cause and effectively prevented recurrence. The team reviewed condition reports and effectiveness reviews to verify that the significant conditions adverse to quality had not recurred.
Effectiveness reviews for corrective actions to prevent recurrence were sufficient to ensure corrective actions were properly implemented and were effective.
Based on the samples reviewed, the team determined that the licensees corrective action program complied with regulatory requirements and self-imposed standards. The licensees implementation of the corrective action program adequately supported nuclear safety.
2. Operating Experience The team determined that the station's processes for the use of industry and NRC operating experience information and for the performance of audits and self-assessments were effective and complied with all regulatory requirements and licensee standards. The implementation of these programs adequately supported nuclear safety. The team concluded that operating experience was adequately evaluated for applicability and that appropriate actions were implemented to address lessons learned as needed.
3. Self-Assessments and Audits The team determined that the licensee effectively perform self-assessments and audits to identify issues at a low level, properly evaluated those issues, and resolved them commensurate with their safety significance.
Self-assessments were generally detailed and critical. The team verified that condition reports (CRs) were created to document areas for improvement and findings resulting from self-assessments and verified that actions had been completed consistent with those recommendations. Audits of the quality assurance program appropriately assessed performance and identified areas for improvement. Generally, the licensee performed evaluations that were technically accurate.
4. Safety Conscious Work Environment Based on interviews with plant staff and reviews of the latest safety culture survey results to assess the safety conscious work environment on site, the team found no evidence of challenges to the safety conscious work environment. Employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On June 25, 2021, the inspectors presented the biennial problem identification and resolution inspection results to Mr. Drayton Pitts and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71152B Corrective Action 106091117 1B Sequencer Trouble Alarm 05/09/2019
Documents Condition Reports 10574132, 10576714, 10578821, 10581018, 10596729, Various
(CRs) 10605455, 10606308, 10609273, 10610150, 10610565,
10610582, 10610586, 10611294, 10611826, 10611966,
10614567, 10616757, 10621148, 10621884, 10623946,
10624291, 10624913, 10624928, 10628474, 10630409,
1063736, 10639744, 10650332, 10661586, 106631175,
10665156, 10665477, 10668922, 10670982, 10674888,
10676556, 10676870, 10677350, 10684511, 10687999,
10689059, 10691131, 10692583, 10695648, 10696902,
10698949, 10699985, 10702019, 10706950, 10708715,
10718138, 10722011, 10723078, 10725277, 10726201,
10734519, 10735075, 10738957, 10739998, 10742315,
10742502, 10742675, 10745502, 10746171, 10748044,
10748916, 10749689, 10751488, 10752698, 10752936,
10753578, 10753852, 10753974, 10755315, 10758197,
10762502, 10764608, 10766557, 10773708, 10774361,
10778217, 10789823, 10786197, 10792118, 10877264,
10789823, 10795987, 10796431
Corrective Action 275705, 276034, 276123, 276492, 276501, 276561, 276681, Various
Reports (CARs) 276692, 277356, 277358, 277403, 277442, 277476, 277580,
278172, 278237, 278594, 278688, 278721, 278752, 278754,
278755, 276893, 278614, 279054
Corrective Action 10804385 NRC comment during PI&R inspection; editorial correction 06/09/2021
Documents required OS-BP-001
Resulting from 10807506 Battery Room HVAC Insulation Damage 06/21/2021
Inspection 10808407 NRC observation on Operator Concerns 06/24/2021
10808417 NRC Identified Improvement: CAR 278784 Emergency 06/24/2021
Diesel Generator Governor Actuator
Drawings 1X-3D-AA-H01A One Line Diagram 125V DC Class 1E Distribution Train A 18.00
1X3AE03-00082 Field Connected Terminal Arrangement 9N57-5 Rear 3TB25 9.0
To 3TB 36
Inspection Type Designation Description or Title Revision or
Procedure Date
1X3D-AA-G01A Main One Line Class 1E 125V DC and 120V Vital AC 11.0
Systems
1X3D-CE-HO4F Wiring Diagram SF Sequencer Board Train A 1-1821-U3-001 6
2X3D-AA-G01A Main One Line Class 1E 125V DC and 120V Vital AC 8.0
Systems
Engineering SNC953976 U1 Emergency Diesel Generator 701 Governor DCP 2
Changes
Engineering 10 CFR 50.59 Eliminate SPVs from MSIV control circuits for Normally 1.0
Evaluations Evaluation for Energized MDR relays and micro switches
SNC1062133
Technical 1050312, 1050731, 1055454, 1055609, 1057896, 1062240,
Evaluations (TEs) 10742502, 1074866
Miscellaneous Vogtle Living (a)(3) Documentation Package 12/31/2019
Technical Specifications Vogtle Electric Generating Plant Amendment
Unit Nos. 1 and 2 Docket Nos. 50-424 and 50-425 Appendix No. 204 (Unit
A to License Nos. NPF-68 and NPF-81 1)
Amendment
No. 187 (Unit
2)
701 Employee Concerns Program 11/20/2019
AX3AA01-00081 On-Line Transformer Monitor Operation & Maintenance 1.0
Guide
CAP Fleet Metrics January 2021, January 2020, October 2019, October 2020, Various
November 2019, November 2021
CNOS-19-149 FLEET-RGA-2019 AUDIT PACKAGE 06/26/2019
EN #54318 AUTOMATIC START OF EMERGENCY DIESEL 10/9/19
GENERATOR AND AUXILLIARY FEEDWATER SYS
EN #54995 Automatic Reactor Trip 11/12/2020
Fleet OPS-2020 Fleet 2020 Operations Audit Package 08/03/2020
Fleet-ENG-2020 2020 Fleet Engineering Complete Audit Package 12/01/2020
Fleet-EP-2020 Fleet Emergency Preparedness 2020 Complete Audit 2/28/2020
Package
Fleet-FP-2020 2020 Fleet Fire Protection Complete Audit Package 10/13/2020
INPO 19-002 Industry Reporting and Information System (IRIS) 02/01/2021
Inspection Type Designation Description or Title Revision or
Procedure Date
NMP-GM-024- Nuclear Safety Culture Leadership Team Report Template, 1/27/2021
F04 Vogtle
NUMARC 93-01 INDUSTRY GUIDELINE FOR MONITORING THE 4A
EFFECTIVENESS OF MAINTENANCE AT NUCLEAR
POWER PLANTS
NUREG-1920 Safety Evaluation Report Related to the License Renewal of 04/01/2009
Vogtle Electric Plant, Units 1 and 2
PRA Measures Vogtle 1 & 2 Internal Events (w/ internal flooding) PRA Basic Living
Report Event Importances
Self V-2019-05, V-2019-06a, V-2019-04b, V-2019-07a, TRN- Various
Assessmeents 2019-03V1-2, V-2019-07b, V-2019-06b, V-2019-23, V-2019-
24, V-2019-75, V-2019-76, V-2019-09, V-2019-10, V-2019-
Site KPI Report Site KPI Report 05/14/2021
Operability Operability 10639744, 10687999, 10786143, PDO 2-20-001, 10772305, Various
Evaluations Determination 10787293, 10790958, OD-1-2019-001 Rev. 2
Procedures 13540B-1 SAFETY FEATURES SEQUENCER SYSTEM - TRAIN B 3.4
17037-1 ANNUNCIATOR RESPONSE PROCEDURES FOR ALB 37 21
ON EAB PANEL
NMP-002-GL03 Cause Analysis and Corrective Actions Guideline 30.2
NMP-AD-012 Operability Determinations 14.0
NMP-AD-012- Mission Times 1.1
GL04
NMP-AD-034 Key Performance Indicators 11.0
NMP-ES-002 System Monitoring and Health Reporting 25.4
NMP-ES-002-006 System Vulnerability Review Process 3.4
NMP-ES-006 Preventive Maintenance Implementation and Continuing 12.2
Equipment Reliability Improvement
NMP-ES-006-002 Preventive Maintenance Change Requests 9.0
NMP-ES-027 Maintenance Rule Program 10.4
NMP-GM-002 Corrective Action Program 16.0
NMP-GM-002- Corrective Action Program Instructions 40.0
001
NMP-GM-002- Effectiveness Review Instructions 5.3
Inspection Type Designation Description or Title Revision or
Procedure Date
2
NMP-GM-002- Cause Analysis and Corrective Actions Guideline 30.2
GL03
NMP-GM-003 Self-Assessment and Benchmark Procedure 28.0
NMP-GM-006- Work Prioritization Screening 4.0
GL11
NMP-GM-008 Operating Experience Program 23.0
NMP-GM-008- Industry Reporting and Information System (IRIS) 7.0
004
NMP-GM-008- Leverage Internal OE 5.1
006
NMP-GM-027 Plant Health Process 15.3
NMP-MA-055 Conduct of FIN 2.1
NMP-OS-006-002 Aggregate Operator Impact Review Instruction 3.0
NMP-OS-007 Conduct of Operations 17.0
NMP-OS-007-003 Plant Operating Orders 3.1
NMP-OS-007-007 Rounds 5.2
OS-BP-001 Operations Performance Indicators 5.1
Self-Assessments Fleet-SEC-2020 2020 Fleet Security Audit 06/26/2020
TE 1076818 CISA 6/12/2020
TE 1076818 CISA1R22 End of Cycle Review 10/29/2020
Work Orders SNC1031381, SNC1050000, SNC1059443, SNC1070325,
SNC1072688, SNC1085973, SNC1087365, SNC1087882,
SNC1089987, SNC1094916, SNC543069, SNC691794,
SNC802998, SNC840546, SNC876925, SNC1124508,
SNC1115409, SNC1127963, SNC1116738
SNC1131860 2403, 22403G4002, 2B Emergency Diesel Generator (EDG) 12//5/2020
Inoperable- Governor Oil Level Low
SNC1133619 2403 - 12403G4001GOV - Replace Mech Governor w/New 12/16/2020
Model from ESI
9