IR 05000424/2021010

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Biennial Problem Identification and Resolution Inspection Report 05000424/2021010 and 05000425/2021010
ML21204A034
Person / Time
Site: Vogtle  Southern Nuclear icon.png
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

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

Procedure

Type

Designation

Description or Title

Revision or

Date

71152B

Corrective Action

Documents

106091117

1B Sequencer Trouble Alarm

05/09/2019

Condition Reports

(CRs)

10574132, 10576714, 10578821, 10581018, 10596729,

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

Various

Corrective Action

Reports (CARs)

275705, 276034, 276123, 276492, 276501, 276561, 276681,

276692, 277356, 277358, 277403, 277442, 277476, 277580,

278172, 278237, 278594, 278688, 278721, 278752, 278754,

278755, 276893, 278614, 279054

Various

Corrective Action

Documents

Resulting from

Inspection

10804385

NRC comment during PI&R inspection; editorial correction

required OS-BP-001

06/09/2021

10807506

Battery Room HVAC Insulation Damage

06/21/2021

10808407

NRC observation on Operator Concerns

06/24/2021

10808417

NRC Identified Improvement: CAR 278784 Emergency

Diesel Generator Governor Actuator

06/24/2021

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

To 3TB 36

9.0

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

1X3D-AA-G01A

Main One Line Class 1E 125V DC and 120V Vital AC

Systems

11.0

1X3D-CE-HO4F

Wiring Diagram SF Sequencer Board Train A 1-1821-U3-001

2X3D-AA-G01A

Main One Line Class 1E 125V DC and 120V Vital AC

Systems

8.0

Engineering

Changes

SNC953976

U1 Emergency Diesel Generator 701 Governor DCP

Engineering

Evaluations

CFR 50.59

Evaluation for

SNC1062133

Eliminate SPVs from MSIV control circuits for Normally

Energized MDR relays and micro switches

1.0

Technical

Evaluations (TEs)

1050312, 1050731, 1055454, 1055609, 1057896, 1062240,

10742502, 1074866

Miscellaneous

Vogtle Living (a)(3) Documentation Package

2/31/2019

Technical Specifications Vogtle Electric Generating Plant

Unit Nos. 1 and 2 Docket Nos. 50-424 and 50-425 Appendix

A to License Nos. NPF-68 and NPF-81

Amendment

No. 204 (Unit

1)

Amendment

No. 187 (Unit

2)

701

Employee Concerns Program

11/20/2019

AX3AA01-00081

On-Line Transformer Monitor Operation & Maintenance

Guide

1.0

CAP Fleet Metrics January 2021, January 2020, October 2019, October 2020,

November 2019, November 2021

Various

CNOS-19-149

FLEET-RGA-2019 AUDIT PACKAGE

06/26/2019

EN#54318

AUTOMATIC START OF EMERGENCY DIESEL

GENERATOR AND AUXILLIARY FEEDWATER SYS

10/9/19

EN#54995

Automatic Reactor Trip

11/12/2020

Fleet OPS-2020

Fleet 2020 Operations Audit Package

08/03/2020

Fleet-ENG-2020

20 Fleet Engineering Complete Audit Package

2/01/2020

Fleet-EP-2020

Fleet Emergency Preparedness 2020 Complete Audit

Package

2/28/2020

Fleet-FP-2020

20 Fleet Fire Protection Complete Audit Package

10/13/2020

INPO 19-002

Industry Reporting and Information System (IRIS)

2/01/2021

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

NMP-GM-024-

F04

Nuclear Safety Culture Leadership Team Report Template,

Vogtle

1/27/2021

NUMARC 93-01

INDUSTRY GUIDELINE FOR MONITORING THE

EFFECTIVENESS OF MAINTENANCE AT NUCLEAR

POWER PLANTS

4A

NUREG-1920

Safety Evaluation Report Related to the License Renewal of

Vogtle Electric Plant, Units 1 and 2

04/01/2009

PRA Measures

Report

Vogtle 1 & 2 Internal Events (w/ internal flooding) PRA Basic

Event Importances

Living

Self

Assessmeents

V-2019-05, V-2019-06a, V-2019-04b, V-2019-07a, TRN-

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-

Various

Site KPI Report

Site KPI Report

05/14/2021

Operability

Evaluations

Operability

Determination

10639744, 10687999, 10786143, PDO 2-20-001, 10772305,

10787293, 10790958, OD-1-2019-001 Rev. 2

Various

Procedures

13540B-1

SAFETY FEATURES SEQUENCER SYSTEM - TRAIN B

3.4

17037-1

ANNUNCIATOR RESPONSE PROCEDURES FOR ALB 37

ON EAB PANEL

NMP-002-GL03

Cause Analysis and Corrective Actions Guideline

30.2

NMP-AD-012

Operability Determinations

14.0

NMP-AD-012-

GL04

Mission Times

1.1

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

Equipment Reliability Improvement

2.2

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-

001

Corrective Action Program Instructions

40.0

NMP-GM-002-

Effectiveness Review Instructions

5.3

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2

NMP-GM-002-

GL03

Cause Analysis and Corrective Actions Guideline

30.2

NMP-GM-003

Self-Assessment and Benchmark Procedure

28.0

NMP-GM-006-

GL11

Work Prioritization Screening

4.0

NMP-GM-008

Operating Experience Program

23.0

NMP-GM-008-

004

Industry Reporting and Information System (IRIS)

7.0

NMP-GM-008-

006

Leverage Internal OE

5.1

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

20 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)

Inoperable-Governor Oil Level Low

2//5/2020

SNC1133619

2403 - 12403G4001GOV - Replace Mech Governor w/New

Model from ESI

2/16/2020