IR 05000269/2022011

NRC Inspection Report 05000269/2022011 and 05000270/2022011 and 05000287/2022011

ML22265A219
Person / Time
Site:	Oconee
Issue date:	09/26/2022
From:	James Baptist Division of Reactor Safety II
To:	Snider S Duke Energy Carolinas
References
IR 2022011
Download: ML22265A219 (11)

Text

SUBJECT:

OCONEE NUCLEAR STATION - NRC INSPECTION REPORT 05000269/2022011 AND 05000270/2022011 AND 05000287/2022011

Dear Mr. Snider:

On September 1, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Oconee Nuclear Station. On September 21, 2022, the NRC inspectors discussed the results of this inspection with Mr. Carl Fago 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. 05000269 and 05000270 and 05000287 License Nos. DPR-38 and DPR-47 and DPR-55

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000269, 05000270 and 05000287

License Numbers: DPR-38, DPR-47 and DPR-55

Report Numbers: 05000269/2022011, 05000270/2022011 and 05000287/2022011

Licensee: Duke Energy Carolinas, LLC

Facility: Oconee Nuclear Station

Location: Seneca, SC

Inspection Dates: August 29, 2022 to September 01, 2022

Inspectors: G. Ottenberg, Senior Reactor Inspector A. Ruh, Senior Reactor Inspector T. Su, 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 a NRC inspection at Oconee Nuclear Station, 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 August 29, 2022 to September 1, 2022.

(1) 10 CFR 50.59 Evaluation, AR 02359654, EC 418719, Turbine Component Test Extensions

(2) 10 CFR 50.59 Evaluation, AR 02315683, EC 407399, B Chiller Replacement

(3) 10 CFR 50.59 Evaluation, AR 02312402, EC 416663, Create Molded Case Circuit Breaker Replacement Specification

(4) 10 CFR 50.59 Evaluation, AR 02378611, NSM-13090, Evaluation of Updated Final Safety Analysis Report (UFSAR) Change 09-051 to Resolve 208V/600V Voltage Adequacy Project, AR 01935296

(5) 10 CFR 50.59 Evaluation, ARs 02392480, 02398442, EC 100916, Fabricate New Panels for Unit 3 7kV Switchgear with New Relays

(6) 10 CFR 50.59 Evaluation, AR 02283079, EC 414051, Standby Shutdown Facility (SSF) Thermal Margin Issues Commissioning

(7) 10 CFR 50.59 Evaluation, AR 02229596, Revision to Methodology Report DCP-NE-3005-PA, Rod Ejection Accident Departure from Nucleate Boiling Methodology

(8) 10 CFR 50.59 Evaluation, AR 02153837, EC 409202, Keowee Auxiliary Power Manual Alignment

(9) 10 CFR 50.59 Screening, EC 419878, Revise Seismic Design Basis Document (DBD)and Main Feedwater DBD Due to Seismic Boundary Valve Review

(10) 10 CFR 50.59 Screening, AR 02222496, EC 115216, Replace A&B High Pressure Service Water Pump Impeller/Rotating Assembly

(11) 10 CFR 50.59 Screening, AR 02403026, EC 414403, Unit 1/2/3 HP-5 Alternate Letdown Isolation

(12) 10 CFR 50.59 Screening, AR 02082472, EC 406027, Replace Valves & Actuators on 2HP-3 & 2HP-4

(13) 10 CFR 50.59 Screening, EC 421070, Revise Reactor Building Spray (RBS) System DBD to Include Additional BS-1 Function and RBS System Mission Time

(14) 10 CFR 50.59 Screening, AR 02284577, Update UFSAR to Align the Licensing Basis for AFIS

(15) 10 CFR 50.59 Screening, ARs 02197469, 02267236, 02281077, EC 101839, Replace Keowee Unit 2 Generator Stator

(16) 10 CFR 50.59 Screening, AR 02347950, EC 417305, Trench Cable Tray Infrastructure Modification for SSF Instrumentation

(17) 10 CFR 50.59 Screening, AR 02396126, EC 417310, Unit 1 Borated Water Storage Tank, Cask Decon Tank Room & West Penetration Room Infrastructure Modification for SSF Instrumentation

(18) 10 CFR 50.59 Screening, AR 02413505, EC 417313, Unit 1 Electrical Penetration Replacement, Containment Building Infrastructure, Instrumentation Installation &

Electrical Tie-ins

(19) 10 CFR 50.59 Screening, AR 02424406, EC 420972 - Remove the Trip Function on the Undervoltage Relays for 3TA/3TB Normal/Startup Breakers

(20) 10 CFR 50.59 Screening, AR 02402453, Revise UFSAR 9.1.5.4.2.1 to Reflect OSC-1594, Revision 2, Reactor Vessel Head Drop Analysis

(21) 10 CFR 50.59 Screening, AR 02326613, EC 416971 - SSF Fuel Oil Storage Tank Vent and Fill Line Missile Protection

(22) 10 CFR 50.59 Screening, AR 02406198, EC 419372 - Unit 1 Condensate Heat Exchanger 1A & 1B Upgrades to Support Replacement of 2CCW-41

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On September 21, 2022, the inspectors presented the NRC inspection results to Mr. Carl Fago and other members of the licensee staff.

On September 1, 2022, the inspectors presented the initial inspection results to Mr.

Steven Snider and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.17T Calculations OSC-10899 Analysis of Condensate Coolers A & B Suction and 5

Discharge Piping, Problem No. 1-13-13

OSC-11334 Seismic to Non-Seismic Piping Boundary Valve Review0

OSC-11656 SSF TURBINE BUILDING FLOOD ANALYSIS WITH NEW 8

SSF LETDOWN LINE

OSC-11796 SSF LETDOWN LINE RELEASE TO RX BUILDING - 1

CONTAINMENT RESPONSE

OSC-11922 Owners Review and Acceptance of Vendor Report 7006-1

24-RPT-001, Rev 000 and Associated Documents

OSC-1594 NUREG-0612 - CONTROL OF HEAVY LOADS - LOAD 2

DROP ANALYSIS

OSC-2218 SSF DIESEL ENGINE FUEL OIL SYSTEM - TANK AND 12

VENT SIZING

OSC-6100 INSTRUCTIONS FOR PREPARING THE EVENT 8

MITIGATION DATABASE TYPE III

OSC-6182 MAIN STEAM LINE BREAK: (MSLB) EVENT MITIGATION 21

REQUIREMENTS TYPE III

OSC-6810 STEAM GENERATOR TUBE RUPTURE ACCIDENT DOSE 12

ANALYSIS (DESIGN BASIS RADIOLOGICAL ACCIDENT

DOSE ANALYSIS)

OSC-6885 HIGH TRAJECTORY TURBINE MISSILE STRIKE 7

PROBABILITY ON THE UNIT 1,2,3 LPSW SYSTEM

OSC-7636 SUMMARY OF NUREG-0612 COMMITTMENTS - 1

FRAMATONE ANP

OSC-8028 ROTSG UFSAR SECTION 15.9 - STEAM GENERATOR 7

TUBE RUPTURE ACCIDENT

OSC-9024 SSF Diesel Fuel Tank Vent Pipe Flow Calculation 2

OSC-9276 HELB Letdown Line Break Analysis 0

Corrective Action 01905167,

Documents 02419764,

260463,

01935296,

Inspection Type Designation Description or Title Revision or

Procedure Date

2375135

Corrective Action 02440039 HP-3/4 Flow Loss Decreased with Replacement-OSC-9276

Documents should be updated

Resulting from 02440398 Observation: Event vs Malfunction Discussion in 50.59 Eval

Inspection 02440885 Observation: Lack of Detail in REA methodology assumption

50.59 eval

2440965 Observation: Lack of Clarity in Digital 50.59 Evals

2442122 Lacking Specific Design Guidance for Electrical Separation

via Devices

Drawings OEE-151-03 Elementary Diagram, Letdown Iso. Valve 1HP V0005 15

OEE-151-03 E/D - LETDOWN ISOLATED VALVE FS/1/51/5, 1HP 15C

VA0005

OEE-151-03-01 E/D - LETDOWN ISOLATED VALVE FS/1/51/5, 1HP 4B

VA0005

OFD-101A-02-01 FLOW DIAGRAM OF HIGH PRESSURE INJECTION 51

SYSTEM (LETDOWN SECTION)

Engineering EC 100916 FABRICATE NEW PANELS FOR UNIT 3 7KV 0

Changes SWITCHGEAR WITH NEW RELAYS

EC 101839 REPLACE KEOWEE UNIT #2 GENERATOR STATOR 22

EC 115216 REPLACE A&B HPSW PUMP IMPELLER/ROTATING 1

ASSEMBLY WITH LOW NPSHR VERSION

EC 406027 REPLACE THE VALVES & ACTUATORS ON 2HP-3 & 4 9

ADD EGS CONNECTOR & 50%

EC 414403 UNIT 1/2/3 HP-5 ALTERNATE LETDOWN ISOLATION 8

EC 416663 CREATE ONS MOLDED CASE CIRCUIT BREAKER 0

REPLACEMENT SPECIFICATION

EC 417305 SSF INSTRUMENTATION - TRENCH INFRASTRUCTURE 1

EC 417310 UNIT 1 SSF INSTRUMENTATION 1

EC 418719 VALVE TEST INTERVAL FREQUENCY CHANGES FOR 4

THE MAIN TURBINE OVERSPEED

EC 420972 REMOVE THE TRIP FUNCTION ON THE 4

UNDERVOLTAGE RELAYS FOR 3TA/3TB

Engineering DC-3.13 OCONEE NUCLEAR STATION CABLE AND WIRING 12

Evaluations SEPARATION CRITERIA

Inspection Type Designation Description or Title Revision or

Procedure Date

ONS-490506-QR-Qualification Report for CCW Flow Path Components to 1.1

001 Support LPSW Pump Alternate Suction Source Supply

Miscellaneous AD-EG-ALL-1216 SURVEILLANCE FREQUENCY CONTROL PROGRAM 3

AR/5AD EC406027 - 000 - Replace Valves 2HP-3 & 2HP-4 11/29/2016

2082471

AR/5AD EC115216 - 000 - REPLACE A&B HPSW PUMP 08/02/2018

222494 IMPELLER/ROTATING

AR/5AD 0000407399 - 000 REPLACE B CHILLER 10/30/2019

2300050

AR/5AD SSF INSTRUMENTATION - TRENCH INFRASTRUCTURE 09/09/2020

2347949

AR/5AD Turbine Valve testing frequency changes (EC 418719) 12/03/2020

2360295

AR/5AD UNIT 1 SSF INSTRUMENTATION 08/31/2021

2396125

AR/5EVL 50.59 Evaluation for replacement of B Chiller per 11/05/2019

2300850

AR/5EVL 50.59 Evaluation for replacement of B Chiller per 01/21/2020

2311960

AR/5EVL Evaluation of UFSAR Change 09-051 to resolve AR 04/15/2021

2378611 1935296

AR/5SCR 10 CFR 50.59 Screen for EC 409202, Keowee Auxiliary 03/08/2018

2153836 Power

AR/5SCR Revision to Methodology Report DPC-NE-3005-PA to use 01/01/2019

229594 0.5

AR/5SCR REPLACE KEOWEE UNIT #2 GENERATOR STATOR 04/08/2019

267236

AR/5SCR 0000407399 - 000 REPLACE B CHILLER 10/30/2019

2300063

AR/5SCR 10 CFR 50.59 Screen for EC 414051, SSF Thermal Margin 09/26/2019

283078 Issues

CNS-13-005 License Amendment Request for Methodology Report DPC-11/14/2013

NE-3001-P, Revision 1, Multidimensional Reactor Transients

and Safety Analysis Physics Parameters Methodology

Inspection Type Designation Description or Title Revision or

Procedure Date

DC-1.01 Separation - McGuire 26

DPND-DPC-NE-CATAWBA AND MCGUIRE - MULTIDIMENSIONAL 1

3001-PA REACTOR TRANSIENTS & SAFETY ANALYSIS PHYSICS

PARAMETERS METHODOLOGY

DPND-DPC-NE-OCONEE UFSAR CHAPTER 15 TRANSIENT ANALYSIS 5

3005-PA METHODOLOGY

DUKE-QAPD-001 DUKE ENERGY CORPORATION TOPICAL REPORT 48

Quality Assurance Program Description Operating Fleet

OCONEE RE: REVISION OF LICENSING BASIS FOR HIGH ENERGY 03/15/2021

NUCLEAR LINE BREAKS OUTSIDE OF CONTAINMENT (EPID L-

STATION, UNITS 2019-LLA-0184)

1, 2, AND 3 -

ISSUANCE OF

AMENDMENT

NO

S. 421, 423,

AND 422

ON-SFL SURVEILLANCE FREQUENCY LIST (SFL) 8

OSR-0208.00-00- Technical Requirements For Procurement of Low NPSHR 1

0004 Impeller for HPSW Pumps

OSS-0218.00-00- (ELECT) INSTALLATION SPEC CABLE AND WIRING 19

0019 SEPARATION CRITERIA

OSS-0243.00-00- Piping Installation Specification 35

0001

OSS-0254.00-00- (ELECT) DBD FOR THE 125 VDC VITAL 16

2006 INSTRUMENTATION AND CONTROL POWER SYSTEM

RG 1.115 PROTECTION AGAINST LOW-TRAJECTORY TURBINE 1

MISSILES

UFSAR Change AR Tracking Number 02345023-06 12/03/2020

Number 2020-

ONS-012

Procedures AD-EG-ALL-1107 Quality Classifications 5

AD-EG-ALL-1132 PREPARATION AND CONTROL OF ENGINEERING 21

CHANGES

AD-EG-ALL-1137 ENGINEERING CHANGE PRODUCT SELECTION 12

Inspection Type Designation Description or Title Revision or

Procedure Date

AD-LS-ALL-0005 UFSAR UPDATES 9

AD-LS-ALL-0008 10 CFR 50.59 REVIEW PROCESS 4

AP/0/A/1700/025 Standby Shutdown Facility Emergency Operating Procedure 68

AP/0/A/2000/002 Keowee Hydro Station - Emergency Start 24

AP/0/A/2000/003 Keowee Hydro Station - Auxiliary Power Recovery 2

EP/1/A/1800/001 Unit 1 EOP Turbine Building Flood 2

0H

EP/2/A/1800/001 Unit 2 EOP Enclosures 5.41-5.47 9

0Q

9