IR 05000269/2022011
| 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:
Report Numbers:
05000269/2022011, 05000270/2022011 and 05000287/2022011
Enterprise Identifier:
I-2022-011-0026
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
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
Procedure
Type
Designation
Description or Title
Revision or
Date
OSC-10899
Analysis of Condensate Coolers A & B Suction and
Discharge Piping, Problem No. 1-13-13
OSC-11334
Seismic to Non-Seismic Piping Boundary Valve Review
OSC-11656
SSF TURBINE BUILDING FLOOD ANALYSIS WITH NEW
SSF LETDOWN LINE
OSC-11796
SSF LETDOWN LINE RELEASE TO RX BUILDING -
CONTAINMENT RESPONSE
OSC-11922
Owners Review and Acceptance of Vendor Report 7006-
24-RPT-001, Rev 000 and Associated Documents
OSC-1594
NUREG-0612 - CONTROL OF HEAVY LOADS - LOAD
DROP ANALYSIS
OSC-2218
SSF DIESEL ENGINE FUEL OIL SYSTEM - TANK AND
VENT SIZING
OSC-6100
INSTRUCTIONS FOR PREPARING THE EVENT
MITIGATION DATABASE TYPE III
OSC-6182
MAIN STEAM LINE BREAK: (MSLB) EVENT MITIGATION
REQUIREMENTS TYPE III
OSC-6810
STEAM GENERATOR TUBE RUPTURE ACCIDENT DOSE
ANALYSIS (DESIGN BASIS RADIOLOGICAL ACCIDENT
DOSE ANALYSIS)
OSC-6885
HIGH TRAJECTORY TURBINE MISSILE STRIKE
PROBABILITY ON THE UNIT 1,2,3 LPSW SYSTEM
OSC-7636
SUMMARY OF NUREG-0612 COMMITTMENTS -
FRAMATONE ANP
OSC-8028
ROTSG UFSAR SECTION 15.9 - STEAM GENERATOR
TUBE RUPTURE ACCIDENT
OSC-9024
SSF Diesel Fuel Tank Vent Pipe Flow Calculation
Calculations
OSC-9276
HELB Letdown Line Break Analysis
Corrective Action
Documents
01905167,
2419764,
260463,
01935296,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2375135
2440039
HP-3/4 Flow Loss Decreased with Replacement-OSC-9276
should be updated
2440398
Observation: Event vs Malfunction Discussion in 50.59 Eval
2440885
Observation: Lack of Detail in REA methodology assumption
50.59 eval
2440965
Observation: Lack of Clarity in Digital 50.59 Evals
Corrective Action
Documents
Resulting from
Inspection
2442122
Lacking Specific Design Guidance for Electrical Separation
via Devices
OEE-151-03
Elementary Diagram, Letdown Iso. Valve 1HP V0005
OEE-151-03
E/D - LETDOWN ISOLATED VALVE FS/1/51/5, 1HP
VA0005
15C
OEE-151-03-01
E/D - LETDOWN ISOLATED VALVE FS/1/51/5, 1HP
VA0005
4B
Drawings
OFD-101A-02-01
FLOW DIAGRAM OF HIGH PRESSURE INJECTION
SYSTEM (LETDOWN SECTION)
FABRICATE NEW PANELS FOR UNIT 3 7KV
SWITCHGEAR WITH NEW RELAYS
REPLACE KEOWEE UNIT #2 GENERATOR STATOR
REPLACE A&B HPSW PUMP IMPELLER/ROTATING
ASSEMBLY WITH LOW NPSHR VERSION
REPLACE THE VALVES & ACTUATORS ON 2HP-3 & 4
ADD EGS CONNECTOR & 50%
UNIT 1/2/3 HP-5 ALTERNATE LETDOWN ISOLATION
CREATE ONS MOLDED CASE CIRCUIT BREAKER
REPLACEMENT SPECIFICATION
SSF INSTRUMENTATION - TRENCH INFRASTRUCTURE
UNIT 1 SSF INSTRUMENTATION
VALVE TEST INTERVAL FREQUENCY CHANGES FOR
Engineering
Changes
REMOVE THE TRIP FUNCTION ON THE
UNDERVOLTAGE RELAYS FOR 3TA/3TB
Engineering
Evaluations
DC-3.13
OCONEE NUCLEAR STATION CABLE AND WIRING
SEPARATION CRITERIA
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
ONS-490506-QR-
001
Qualification Report for CCW Flow Path Components to
Support LPSW Pump Alternate Suction Source Supply
1.1
AD-EG-ALL-1216
SURVEILLANCE FREQUENCY CONTROL PROGRAM
AR/5AD
2082471
EC406027 - 000 - Replace Valves 2HP-3 & 2HP-4
11/29/2016
AR/5AD
222494
EC115216 - 000 - REPLACE A&B HPSW PUMP
IMPELLER/ROTATING
08/02/2018
AR/5AD
2300050
0000407399 - 000 REPLACE B CHILLER
10/30/2019
AR/5AD
2347949
SSF INSTRUMENTATION - TRENCH INFRASTRUCTURE
09/09/2020
AR/5AD
2360295
Turbine Valve testing frequency changes (EC 418719)
2/03/2020
AR/5AD
2396125
UNIT 1 SSF INSTRUMENTATION
08/31/2021
AR/5EVL
2300850
50.59 Evaluation for replacement of B Chiller per
11/05/2019
AR/5EVL
2311960
50.59 Evaluation for replacement of B Chiller per
01/21/2020
AR/5EVL
2378611
Evaluation of UFSAR Change 09-051 to resolve AR
1935296
04/15/2021
AR/5SCR
2153836
CFR 50.59 Screen for EC 409202, Keowee Auxiliary
Power
03/08/2018
AR/5SCR
229594
Revision to Methodology Report DPC-NE-3005-PA to use
0.5
01/01/2019
AR/5SCR
267236
REPLACE KEOWEE UNIT #2 GENERATOR STATOR
04/08/2019
AR/5SCR
2300063
0000407399 - 000 REPLACE B CHILLER
10/30/2019
AR/5SCR
283078
CFR 50.59 Screen for EC 414051, SSF Thermal Margin
Issues
09/26/2019
Miscellaneous
License Amendment Request for Methodology Report DPC-
NE-3001-P, Revision 1, Multidimensional Reactor Transients
and Safety Analysis Physics Parameters Methodology
11/14/2013
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DC-1.01
Separation - McGuire
DPND-DPC-NE-
3001-PA
CATAWBA AND MCGUIRE - MULTIDIMENSIONAL
REACTOR TRANSIENTS & SAFETY ANALYSIS PHYSICS
PARAMETERS METHODOLOGY
DPND-DPC-NE-
3005-PA
OCONEE UFSAR CHAPTER 15 TRANSIENT ANALYSIS
METHODOLOGY
DUKE-QAPD-001
DUKE ENERGY CORPORATION TOPICAL REPORT
Quality Assurance Program Description Operating Fleet
OCONEE
NUCLEAR
STATION, UNITS
1, 2, AND 3 -
ISSUANCE OF
AMENDMENT
NO
- S. 421, 423,
AND 422
RE: REVISION OF LICENSING BASIS FOR HIGH ENERGY
LINE BREAKS OUTSIDE OF CONTAINMENT (EPID L-
2019-LLA-0184)
03/15/2021
ON-SFL
SURVEILLANCE FREQUENCY LIST (SFL)
OSR-0208.00-00-
0004
Technical Requirements For Procurement of Low NPSHR
Impeller for HPSW Pumps
OSS-0218.00-00-
0019
(ELECT) INSTALLATION SPEC CABLE AND WIRING
SEPARATION CRITERIA
OSS-0243.00-00-
0001
Piping Installation Specification
OSS-0254.00-00-
2006
(ELECT) DBD FOR THE 125 VDC VITAL
INSTRUMENTATION AND CONTROL POWER SYSTEM
PROTECTION AGAINST LOW-TRAJECTORY TURBINE
MISSILES
UFSAR Change
Number 2020-
ONS-012
AR Tracking Number 02345023-06
2/03/2020
AD-EG-ALL-1107
Quality Classifications
AD-EG-ALL-1132
PREPARATION AND CONTROL OF ENGINEERING
CHANGES
Procedures
AD-EG-ALL-1137
ENGINEERING CHANGE PRODUCT SELECTION
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AD-LS-ALL-0005
UFSAR UPDATES
AD-LS-ALL-0008
CFR 50.59 REVIEW PROCESS
AP/0/A/1700/025
Standby Shutdown Facility Emergency Operating Procedure
AP/0/A/2000/002
Keowee Hydro Station - Emergency Start
AP/0/A/2000/003
Keowee Hydro Station - Auxiliary Power Recovery
EP/1/A/1800/001
0H
Unit 1 EOP Turbine Building Flood
EP/2/A/1800/001
0Q
Unit 2 EOP Enclosures 5.41-5.47
9