IR 05000324/2020011
| ML20176A595 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/24/2020 |
| From: | James Baptist NRC/RGN-II |
| To: | Krakuszeski J Duke Energy Progress |
| References | |
| IR 2020011 | |
| Download: ML20176A595 (8) | |
Text
June 24, 2020
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT - U. S. NUCLEAR REGULATORY COMMISSION EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS REPORT 05000324/2020011 AND 05000325/2020011
Dear Mr. Krakuszeski:
On May 22, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Brunswick Steam Electric Plant and 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, James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety
Docket Nos. 05000324 and 05000325 License Nos. DPR-62 and DPR-71
cc w/ encl: Distribution via LISTSERV
SUNSI Review
Non-Sensitive Sensitive
Publicly Available Non-Publicly Available
OFFICE RII/DCO RII/DRS RII/DCO RII/DRS
NAME C. Even P. Braxton W. Sifre J. Baptist
DATE 06/24/2020 06/24/2020 06/24/2020 06/24/2020
Enclosure
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Numbers:
05000324 and 05000325
License Numbers:
Report Numbers:
05000324/2020011 and 05000325/2020011
Enterprise Identifier: I-2020-011-0018
Licensee:
Duke Energy Progress, LLC
Facility:
Brunswick Steam Electric Plant
Location:
Southport, NC
Inspection Dates:
May 18, 2020 to May 22, 2020
Inspectors:
P. Braxton, Reactor Inspector
C. Even, Senior Construction Inspector
W. Sifre, Senior Reactor Inspector
Approved By:
James B. Baptist, Chief
Engineering Branch 1
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an U. S. NUCLEAR REGULATORY COMMISSION EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS 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.
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
71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)
The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from May 18-22, 2020.
(1)50.59 Evaluation: AR 2044953 - Replacement of the Unit 1 Fuel Zone Level Digital Recorder (EC 300782)
(2)50.50 Evaluation: AR 2144947 - Replacement of the Emergency Diesel Generator Exciter/Voltage Regulator (EC 270989)
(3)50.59 Evaluation: AR 02207965 - CPLD AB 700RTC Installed in 2-DG3-STR/2-DG4-STR (EC 411346)
(4)50.59 Screening: AR 01953074 - GE Recorder Replacements 2-D12-RR-R604 (EC 400731)
(5)50.59 Screening: AR 02274896 - Remove Electrical Loads (EC 415332)
(6)50.59 Screening: AR 00688026 - Alternate Motor FOR 1-CW-1D-OD-PMP-M (EC 296520)
(7)50.59 Screening: AR 02264787 - Implementing Malicious Code Protection (Anti-Virus) on Data Diodes (EC 413054)
- (8) Applicability Determination: AR 02304553 - 0CM-FHE506 Deletion
- (9) Applicability Determination: AR 02177954 - DG-2 Generator Voltage Regulator (Basler) Calibration
- (10) Applicability Determination: AR 02145239 - RHR And CS Time Delay Relays Chan Cal And Functional Test (11)50.59 Evaluation: AR 1966822 - FSAR Tornado Basis Update (12)50.59 Screening: AR 02118693 - Hardened Containment Vent System (EC 294259)
(13)50.59 Screening: AR 02106399 - Make Diesel Cell Exhaust Fans Safety-Related (EC 280258)
(14)50.59 Screening: 00498893 - RPS EPA Undervoltage Setting for U1 EPA Breakers 5
& 6 (EC 81018)
(15)50.59 Screening: 02312909 - Replace Obsolete Temperature Switch for 1-B21-TS-N010A/B/C/D Main Steam Line Tunnel Area Leak Detection (EC 416915)
(16)50.59 Screening: 02077298 - VFD Runback to Limiter #1 on RPS Trip (EC 300810)
(17)50.59 Screening: 02216350 - Castle Hayne East Line Relay Panel Replacement (EC 406780)
(18)50.59 Screening: 02318535 - MOV Actuator for Valve 1-E11-PDV-F068B Pinion Gear Replacement to a Higher Gear Ratio (EC 417148)
(19)50.59 Screening: 02206166 - Piping Designation to Align with Atomic Energy Commission Group D Specifications (EC 412341)
(20)50.59 Screening: 00731094-Diesel Generator Margin Improvements Jet Air Assist Upgrades (EC 86411)
(21)50.59 Screening: 00736790 - Diesel Generator Excitation System Upgrade (EC 70989)
(22)50.59 Screening: 02055746 - Replace a Rubber Lined Spool Piece of Service Water line 2-SW-103-24-157 with AL-6XN Piping Material (EC 404628)
(23)50.59 Screening: 2191411 - Apply a Full Structural Weld Overlay to Dissimilar Metal Reactor Pressure Vessel (RPV) Nozzle Weld N4D (EC 411749)
(24)50.59 Screening: 2191409 - Apply a Full Structural Weld Overlay to Dissimilar Metal Reactor Pressure Vessel (RPV) Nozzle Weld N4A (EC 411737)
(25)50.59 Evaluation: 02237606 - Incorporation of Findings from the Final Test Results from BWR Refueling Platform EMI/RFI Test Report, F.503100 (EC 300707)
(26)50.59 Evaluation: 2194691 - Install Mod to Eliminate intermittent Failure of Index Mechanism 1-C51-J002C Limit Switch S2 (EC 411912)
(27)50.59 Evaluation: 02099588 - Prompt Determination of Operability to Justify Restoration of the Control Room Envelope (CRE) to Operable Status Based on a Temporary Assumption of 115 scfh MSIV Combined Leakage
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On May 22, 2020, the inspectors presented the U. S. NUCLEAR REGULATORY COMMISSION EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS results to John Krakuszeski and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.17T Calculations
BNP-E-8.010
AC Coordination Study
Rev.25
BNP-E-8.010
AC Coordination Study
Rev.16
Drawings
D-02523, Sheet 1
Reactor Building High Pressure Coolant Injection System
Piping Diagram
D-02524, Sheet 1
Reactor Building Core Spray System Piping Diagram
D-02524, Sheet 2
Reactor Building Core Spray System Piping Diagram
D-02525, Sheet
1A
Reactor Building Residual Heat Removal System Piping
Diagram
D-02525, Sheet
1B
Reactor Building Residual Heat Removal System Piping
Diagram
D-02529, Sheet 1
Reactor Building Reactor Core Isolation Cooling System Piping
Diagram
D-25023, Sheet 1
Reactor Building high Pressure Coolant Injection System
Piping Diagram
D-25024, Sheet 1
Reactor Building Core Spray System Piping Diagram
D-25024, Sheet 2
Reactor Building Core Spray System Piping Diagram
D-25025, Sheet
1A
Reactor Building Residual Heat Removal System Piping
Diagram
D-25025, Sheet
1B
Reactor Building Residual Heat Removal System Piping
Diagram
D-25029, Sheet 1
Reactor Building Reactor Core Isolation Cooling System Piping
Diagram
D-2506, Sheet 2B
Reactor Building Residual Heat Removal System Piping
Diagram
D-2526, Sheet 2B
Reactor Building Residual Heat Removal System Piping
Diagram
Miscellaneous
Photo of Motor Nameplate
Specification for Replacement Rotating Rectifier Assembly
Water Ocean Discharge Pump Motors
Rev. 0
28-003
Specification for Synchronous Motors 100Hp and Larger
Rev. 4
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
248-117
Engineering Specification - Installation of Piping Systems
Procedures
Motor Operated Valve (MOV) Design Basis Information
Generic Letter 89-10 & Generic Letter 96-05
0PT-08.1.4B
Residual Heat Removal Service Water System Operability
Test - Loop B
Work Orders
222589 54
Integrated Testing of Diesel Generator-3 Following Governor
Replacement
03/12/2016
216807 01
Integrated Testing of Diesel Generator-1 Following Governor
Replacement
03/06/2016
222583 37
Integrated Testing of Diesel Generator-2 Following Governor
Replacement
03/20/2018
222597 45
Integrated Testing of Diesel Generator-4 Following Governor
Replacement
03/28/2017
1346472-24,
13464742-27,
13464742-28,
13464742-29,
13464742-33,
13464742-35,
13464742-42