IR 05000324/2020011

U. S. Nuclear Regulatory Commission Evaluation of Changes, Tests, and Experiments Report 05000324/2020011 and 05000325/2020011

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

ML20176A595 Non-Sensitive Publicly Available SUNSI Review Sensitive 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

U.S. NUCLEAR REGULATORY COMMISSION

Inspection Report

Docket Numbers: 05000324 and 05000325 License Numbers: DPR-62 and DPR-71 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 Enclosure

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 Type Designation Description or Title Revision or

Procedure 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 59

Piping Diagram

D-02524, Sheet 1 Reactor Building Core Spray System Piping Diagram 43

D-02524, Sheet 2 Reactor Building Core Spray System Piping Diagram 41

D-02525, Sheet Reactor Building Residual Heat Removal System Piping 52

1A Diagram

D-02525, Sheet Reactor Building Residual Heat Removal System Piping 71

1B Diagram

D-02529, Sheet 1 Reactor Building Reactor Core Isolation Cooling System Piping 63

Diagram

D-25023, Sheet 1 Reactor Building high Pressure Coolant Injection System 61

Piping Diagram

D-25024, Sheet 1 Reactor Building Core Spray System Piping Diagram 43

D-25024, Sheet 2 Reactor Building Core Spray System Piping Diagram 39

D-25025, Sheet Reactor Building Residual Heat Removal System Piping 58

1A Diagram

D-25025, Sheet Reactor Building Residual Heat Removal System Piping 74

1B Diagram

D-25029, Sheet 1 Reactor Building Reactor Core Isolation Cooling System Piping 64

Diagram

D-2506, Sheet 2B Reactor Building Residual Heat Removal System Piping 70

Diagram

D-2526, Sheet 2B Reactor Building Residual Heat Removal System Piping 81

Diagram

Miscellaneous Photos of 1A CW OD Pump Motor

Photo of Motor Nameplate

0BNP-E-002 Specification for Replacement Rotating Rectifier Assembly Rev. 0

Water Ocean Discharge Pump Motors28-003 Specification for Synchronous Motors 100Hp and Larger Rev. 4

Inspection Type Designation Description or Title Revision or

Procedure Date

248-117 Engineering Specification - Installation of Piping Systems 43

Procedures 0BNP-TR-006 Motor Operated Valve (MOV) Design Basis Information 6

Generic Letter 89-10 & Generic Letter 96-05

0PT-08.1.4B Residual Heat Removal Service Water System Operability 78

Test - Loop B

Work Orders 02222589 54 Integrated Testing of Diesel Generator-3 Following Governor 03/12/2016

Replacement

216807 01 Integrated Testing of Diesel Generator-1 Following Governor 03/06/2016

Replacement

222583 37 Integrated Testing of Diesel Generator-2 Following Governor 03/20/2018

Replacement

222597 45 Integrated Testing of Diesel Generator-4 Following Governor 03/28/2017

Replacement

1346472-24,

13464742-27,

13464742-28,

13464742-29,

13464742-33,

13464742-35,

13464742-42

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