IR 05000324/2023003
| ML23299A177 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/01/2023 |
| From: | Matthew Fannon Division Reactor Projects II |
| To: | Krakuszeski J Duke Energy Progress |
| References | |
| IR 2023003 | |
| Download: ML23299A177 (11) | |
Text
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT - INTEGRATED INSPECTION REPORT 05000324/2023003 AND 05000325/2023003
Dear John A. Krakuszeski:
On September 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Brunswick Steam Electric Plant. On October 31, 2023, the NRC inspectors discussed the results of this inspection with you 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, Matthew S. Fannon, Chief Reactor Projects Branch 4 Division of Reactor Projects Docket Nos. 05000324 and 05000325 License Nos. DPR-62 and DPR-71
Enclosure:
As stated
Inspection Report
Docket Numbers: 05000324 and 05000325
License Numbers: DPR-62 and DPR-71
Report Numbers: 05000324/2023003 and 05000325/2023003
Enterprise Identifier: I-2023-003-0014
Licensee: Duke Energy Progress, LLC
Facility: Brunswick Steam Electric Plant
Location: Southport, NC
Inspection Dates: July 01, 2023 to September 30, 2023
Inspectors: C. Curran, Resident Inspector P. Gresh, Operations Engineer G. Smith, Senior Resident Inspector J. Walker, Senior Emergency Preparedness Inspector A. Wilson, Senior Project Engineer
Approved By: Matthew S. Fannon, Chief Reactor Projects Branch 4 Division of Reactor Projects
Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Brunswick Steam Electric 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.
PLANT STATUS
Unit 1 began the period at 100 percent rated thermal power (RTP) and operated there until September 23, 2023, when power was reduced to 65 percent RTP to perform a control rod sequence exchange and turbine valve testing. Following the valve testing, sequence exchange, and one control rod improvement, the unit was restored to full RTP on September 27, where it continued to operate for the remainder of the inspection period.
Unit 2 began the period at 100 percent RTP and operated there until September 8, 2023, when power was reduced to 70 percent RTP to perform a control rod sequence exchange, turbine valve testing, and switchyard maintenance. Following the valve testing, sequence exchange, maintenance, and two control rod improvements, the unit was restored to full RTP on September 14, where it continued to operate for the remainder of the inspection period.
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 performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. 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
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) On July 11, 2023, the inspectors completed a readiness evaluation for seasonal extreme weather conditions prior to the onset of hot temperatures for the following systems:
- Nuclear service water (NSW) and conventional service water (CSW)
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors completed an evaluation regarding the adequacy of the overall preparations to protect risk-significant systems from Hurricane Idalia on August 31, 2023.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) EDG-2 while EDG-1 was out-of-service (OOS) for maintenance and testing on August 15-16, 2023
- (2) Unit 1 'A' residual heat removal (RHR) train while the 'B' RHR train was OOS for planned maintenance on July 25 - 26
- (3) Unit 2 'B' standby gas treatment (SBGT) train while the 'B' SBGT train was OOS for planned maintenance on September 5
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Safety-related battery rooms (1A, 1B, 2A, and 2B) on July 8, 2023
- (2) Unit 2 reactor building 20 elevation on July 11
- (3) Unit 2 reactor building 50 elevation on July 12
- (4) Unit 1 and Unit 2 control building 23 elevation on July 13
- (5) Unit 2 reactor building 117 elevation on July 17
- (6) Unit 2 reactor building 80 elevation on July 19
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) On July 1, 2023, the inspectors completed an evaluation of the external flooding mitigation protections associated with the safety-related manhole, 2-MH-2SE.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)
- (1) On July 31, 2023, the inspectors observed and evaluated licensed operator performance in the control room during the Unit 1 mega-volt ampere reactive (MVAR)and voltage regulator testing in accordance with 1PT-40.2.13, "Main Generator MVAR Testing for NERC Reliability Standard MOD-25-2," Rev. 4.
- (2) The inspectors observed and evaluated licensed operator performance in the control room during a Unit 2 down power to 70 percent RTP for a control rod sequence exchange on September 8.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated the 2023 annual operator requalification simulator examinations on September 20 and September 27, 2023.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Reactor core isolation cooling (RCIC) packing steam leak from valve 2-E51-F038 (Nuclear Condition Report [NCR] 2463844)
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
- (1) Commercial grade dedication package associated with Muffin Fan (Engineering Change [EC] 421289)
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Elevated risk due to Unit 2 RCIC outage on July 12, 2023
- (2) Elevated risk due to EDG-1 out of service for troubleshooting and testing during the week of August 14
- (3) Yellow grid status (hands off) due to grid loading on August 22
- (4) Elevated risk due to Unit 2 'B' train RHR outage on September 14
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 1 B recirculation pump seal degradation (NCR 2477285)
- (2) Unit 1 B CSW strainer tube sheet studs loose and cannot be reinstalled (NCR
===2473244)
- (4) 2E control building main control room condenser fan C' magnetic trip (NCR 2483570)
- (5) Inboard main steam isolation valve (1-B21-F022B) 90 percent limit switch failed to actuate during testing (NCR 2487850)
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
=
The inspectors evaluated the following temporary or permanent modifications:
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (8 Samples)
- (1) Post maintenance operational testing of the Unit 2 'A' core spray pump motor following a cable splice repair of a failed 4160-volt power cable in accordance with (IAW) work order (WO) 20483333
- (2) 0PT-12.2C, "No. 3 Diesel Generator Monthly Load Test," following 24-month inspection IAW WO 20583569
- (3) 0PT-06.1, "Standby Liquid Control System Operability Test," following breaker replacement IAW WO 20521886
- (4) 0PT-08.2.2B, "LPCI/RHR System Operability Test - Loop B," Rev. 111 following motor-operated valve maintenance on Unit 1 RHR shutdown cooling suction valve (11-E11-F006B) IAW WO 20495673
- (5) 0PT-01.6.2, "Rod Worth Minimizer System Operability Test," following battery replacement IAW WO 20509658
- (6) 0PT-10.1.8, "RCIC System Valve Operability Test," Rev. 47 following replacement of limit switch rotor on the Unit 2 RCIC vacuum breaker exhaust valve (2-E51-F066) IAW WO 20104641
- (7) 0PT-12.2.2A, "No.1 Diesel Generator Monthly Load Test," Rev. 125 following a loss of excitation trip and subsequent troubleshooting IAW WO 20614759
- (8) 0PT-09.7, "HPCI System Valve Operability Test," Rev. 45, following a spring pack replacement of high pressure coolant injection (HPCI) suppression pool suction valve (1E41-F042) IAW WO 20417951
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.01-02.04) (1 Sample)
- (1) The inspectors evaluated the maintenance and testing of the alert and notification system during the week of September 25, 2023.
71114.03 - Emergency Response Organization Staffing and Augmentation System
Inspection Review (IP Section 02.01-02.02) (1 Sample)
- (1) The inspectors evaluated the readiness of the Emergency Response Organization during the week of September 25, 2023.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated submitted Emergency Action Level and Emergency Plan changes during the week of September 25, 2023. This evaluation does not constitute NRC approval.
71114.05 - Maintenance of Emergency Preparedness
Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
- (1) The inspectors evaluated the maintenance of the emergency preparedness program during the week of September 25, 2023.
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) Operator annual exam simulator scenarios on September 20 and September 27,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===
- (1) Unit 1 (July 1, 2022 through June 30, 2023)
- (2) Unit 2 (July 1, 2022 through June 30, 2023)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 1 (July 1, 2022 through June 30, 2023)
- (2) Unit 2 (July 1, 2022 through June 30, 2023)
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) July 1, 2022 through June 30, 2023 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) July 1, 2022 through June 30, 2023
EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)
- (1) July 1, 2022 through June 30, 2023
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) 2B Recirculation Pump Variable Frequency Drive Trip (NCR 2450785)
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 31, 2023, the inspectors presented the integrated inspection results to John A. Krakuszeski and other members of the licensee staff.
- On September 28, 2023, the inspectors presented the emergency preparedness program inspection results to J. Krakuszeski and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71114.03 Procedures EP-ALL-EPLAN Duke Energy Common Emergency Plan Rev. 4
71114.04 Procedures AD-EP-ALL-0101 Emergency Classification Rev. 5
71114.04 Procedures AD-EP-ALL-0109 Offsite Protective Action Recommendations Rev. 9
71114.04 Procedures AD-EP-ALL-0202 Emergency Response Offsite Dose Assessment Rev. 9
71114.04 Procedures AD-EP-ALL-0304 State and County Notifications Rev. 7
71114.04 Procedures EP-BNP-EPLAN-Duke Energy Brunswick Emergency Plan Annex Rev. 2
ANNEX
71114.05 Corrective Action 2435665 BNP Exercise - Unsatisfactory Objective, Expanded PAR
Documents determination
71114.05 Self-Assessments 2022 BNP Graded Exercise Critique Report 08/20/2022
71114.05 Self-Assessments 2023 Medical Response 02/28/2023
71114.05 Self-Assessments 2022-BNP-EMP-NOS Performance Review Brunswick Emergency 12/06/2022
PR-01 Preparedness
9