IR 05000269/2025004
| ML26030A031 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/04/2026 |
| From: | Robert Williams NRC/RGN-II/DORS/PB1 |
| To: | Snider S Duke Energy Carolinas |
| References | |
| IR 2025004 | |
| Download: ML26030A031 (0) | |
Text
SUBJECT:
OCONEE NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000269/2025004 AND 05000270/2025004 AND 05000287/2025004
Dear Steven Snider:
On December 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Oconee Nuclear Station. On January 14, 2026, 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.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at Oconee Nuclear Station.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; and the NRC Resident Inspector at Oconee Nuclear Station.
February 4, 2026 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, Robert E. Williams, Jr., Chief Projects Branch 1 Division of Operating 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:
05000269/2025004, 05000270/2025004 and 05000287/2025004
Enterprise Identifier:
I-2025-004-0024
Licensee:
Duke Energy Carolinas, LLC
Facility:
Oconee Nuclear Station
Location:
Seneca, South Carolina
Inspection Dates:
October 1, 2025, to December 31, 2025
Inspectors:
N. Smalley, Senior Resident Inspector
D. Dang, Resident Inspector
E. Robinson, Resident Inspector
M. Bradfield, Senior Reactor Technology Instructor
D. Strickland, Senior Reactor Inspector
Approved By:
Robert E. Williams, Jr., Chief
Projects Branch 1
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated 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
Failure to Implement Plant Status Control Procedure Resulted in Momentary Partial Loss of Shutdown Unit's AC Power Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green NCV 05000270/2025004-01 Open/Closed
[H.4] -
Teamwork 71111.20 A self-revealed Green finding and associated non-cited violation (NCV) of Technical Specification (TS) 5.4.1.a, was identified when the licensee failed to implement procedure AD-OP-ALL-0204, Rev. 009, Plant Status Control, in accordance with Regulatory Guide 1.33, Quality Assurance Program Requirements (Operations), Revision 2,
Appendix A, February 1978. Specifically, the licensee failed to control the status of the CT-2 bus potential drawer, resulting in a breaker trip and momentary loss of power to the Unit 2 main feeder bus.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 operated at or near 100 percent rated thermal power (RTP) for the entire inspection period.
Unit 2 began the inspection period at 98.5 percent RTP and continued end of cycle power coastdown in preparation for scheduled refueling outage O2R32, which began October 27, 2025. The unit was returned to 100 percent RTP on November 27, 2025. The unit operated at or near 100 percent RTP for the remainder of the inspection period.
Unit 3 operated at or near 100 percent RTP for the entire 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
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1 low pressure service water (LPSW) system concurrent with Unit 2 component cooling water system dewatering and LPSW valve replacement project during Unit 2 refueling outage on November 6, 2025
- (2) Unit 3 turbine driven emergency feedwater (EFW) pump with the 3A motor driven EFW pump unavailable due to maintenance on December 1, 2025
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 low pressure injection (LPI) system on November 13, 2025.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (2 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) Fire zone 95: Unit 1 electrical equipment room on October 2, 2025
- (2) Fire zone 77: Unit 3 auxiliary building 200 level hallway on October 15, 2025
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protections in the turbine building basement during the condenser circulating water crossover valve replacement project from November 2-4, 2025
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
The licensee completed the annual requalification operating examinations and biennial written examinations required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), "Requalification Requirements," of the NRC's "Operator's Licenses." The inspectors performed an in-office review of the overall pass/fail results of the individual operating examinations, the crew simulator operating examinations, and the biennial written examinations in accordance with IP 71111.11, "Licensed Operator Requalification Program and Licensed Operator Performance." These results were compared to the thresholds established in Section 3.03, "Requalification Examination Results," of IP 71111.11.
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered on March 28, 2025, and the biennial written exam completed on March 28, 2025.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated refueling activities and pre-job brief for the emergency power switching logic functional test on November 18, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed just in time training for activities planned for the Unit 2 refueling outage on October 24, 2025.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Nuclear condition report (NCR) 2494408, 2LPSW-1054 low pressure service water valve failure
- (2) NCR 2573453, Unit 2 purification demineralizer maintenance issues
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)2C LPI pump motor replacement and refurbishment, work order (WO) 20295961
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 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) Unit 1 elevated green risk due to protected service water maintenance concurrent with 1B high pressure injection pump maintenance, on October 13, 2025
- (2) Unit 2 yellow risk due to reduced inventory operations for the refueling outage during the week of October 27, 2025
- (3) Units 1, 2, and 3 plant risk and condenser circulating water crossover valve replacement project risk plan from November 2-14, 2025
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:
- (3) NCR 2572022, battery SY-1 cells 16 and 29 found below the minimum acceptable specific gravity
- (5) NCR 02575718, Unit 2 LPSW piping wall thickness approaching limit during ultrasonic testing
- (6) NCR 2577381, missing mirror insulation on 2B hot leg
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Engineering change (EC) 424583, Unit 2 LPI valve replacements
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated refueling outage O2R32 activities from October 27, 2025, to November 24, 2025.
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) (7 Samples)
- (1) PT/3/A/0261/010, "Essential Siphon Vacuum System Test," following maintenance on valve 3ESV-1, on October 9, 2025
- (2) PT/1/A/0202/11, "High Pressure Injection (HPI) Pump Test," following preventive maintenance on the 1A HPI pump, on October 14, 2025
- (3) IP/0/A/3001/001, "Limitorque Preventive Maintenance," following maintenance on valve 1LP-15, on October 14, 2025
- (4) PT/2/A/0251/069, LPI Cooler Test, following mode change during the Unit 2 refueling outage, on October 28, 2025.
- (5) TT/2/A/EC419099/002, "Post Modification Testing for Unit 1/2 Low Pressure Service Water Pumps," following implementation of EC419099, on November 12, 2025
- (6) PT/2/A/0203/006 A, flow test for valve 2LP-9 following maintenance to resolve rejected weld, on November 20, 2025
- (7) PT/2/A/0230/015, High Pressure Injection Motor Cooler Performance Test, following EC 426266, on November 21, 2025
Surveillance Testing (IP Section 03.01) (3 Samples)
- (1) PT/0/A/0620/018, "Keowee Hydro System (KHS) Out of Tolerance Test," on September 30, 2025
- (2) PT/2/A/0610/001 J, "Emergency Power Switching Logic Functional Test," on November 18, 2025
- (3) PT/0/A/0711/001, Zero Power Physics Test, during Unit 2 startup on November 25, 2025
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
- (1) Low pressure service water valve, 2LPSW-1054 (PEN 63), after valve maintenance complete, on November 10, 2025
OTHER ACTIVITIES - BASELINE
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02) (1 Sample)
- (1) The inspectors reviewed the licensee's corrective action program for potential adverse trends in the area of human performance that might be indicative of a more significant safety issue.
71153 - Follow-Up of Events and Notices of Enforcement Discretion
Personnel Performance (IP Section 03.03) (3 Samples)
- (1) The inspectors evaluated the human performance errors during a demineralizer sluice evolution and subsequent excessive reactor coolant system leakage outside containment on Unit 1 and the licensee's performance on October 23, 2025.
- (2) The inspectors evaluated the excessive reactor coolant system leakage outside containment on Unit 2 and the licensees performance on October 28, 2025.
- (3) The inspectors evaluated the loss of power to Units 1 and 2 loads, subsequent Keowee Hydro Unit emergency start, and the licensees performance on November 15, 2025.
INSPECTION RESULTS
Failure to Implement Plant Status Control Procedure Resulted in Momentary Partial Loss of Shutdown Unit's AC Power Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green NCV 05000270/2025004-01 Open/Closed
[H.4] -
Teamwork 71111.20 A self-revealed Green finding and associated NCV of TS 5.4.1.a, was identified when the licensee failed to implement procedure AD-OP-ALL-0204, Rev. 009, Plant Status Control, in accordance with Regulatory Guide 1.33, Quality Assurance Program Requirements (Operations), Revision 2, Appendix A, February 1978. Specifically, the licensee failed to control the status of the CT-2 bus potential drawer, resulting in a breaker trip and momentary loss of power to the Unit 2 main feeder bus.
Description:
On November 14, 2025, Unit 2 was shut down and defueled for a refueling outage. In preparation for electrical maintenance, licensee operators were tasked to verify a clearance on the potential transformer drawer for the Unit 2 main feeder buses (MFBs) that had been completed on the prior shift. At 22:54, operators proceeded to verify tags were removed from the CT-2 bus potential drawer. However, they were unaware power had been transferred from CT-5 to CT-2 at 22:51. The operators opened the powered CT-2 potential bus drawer. This resulted in two fuses disconnecting, per design, triggering the opening of the E21 and E22 breakers and a subsequent loss of power to the Unit 2 MFBs due to an undervoltage condition. Opening of the drawer was not required to verify the clearance and was not in accordance with procedure AD-OP-ALL-0204, Rev. 009, Plant Status Control.
The Keowee Hydro Units 1 and 2 automatically started as designed due to a main feeder bus undervoltage signal, and Unit 2 load shed channel 'B' initiated. This event resulted in a momentary loss of power to various equipment including the Unit 2 'C' LPSW pump and 'C' spent fuel cooling pump. At 22:55, the E22 breaker was closed, and power was restored to the Unit 2 MFBs before the Keowee Hydro Units completed their emergency startup. The 'C' LPSW Pump was restored when power was restored, and other affected equipment was restored to their proper configuration. The licensee notified the NRC in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted in a valid actuation of the emergency AC power system (event notification 58041).
Corrective Actions: The licensee initiated causal investigation and performance analysis checklists to determine the cause of the event.
Corrective Action References: Action Request (AR) 02576181
Performance Assessment:
Performance Deficiency: The inspectors determined that the licensees failure to control the status of the MFBs in accordance with AD-OP-ALL-0204, Rev. 009, Plant Status Control, was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Configuration Control attribute of the Initiating Events cornerstone and adversely affected the cornerstone objective to limit the likelihood of events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. Specifically, the performance deficiency resulted in a temporary loss of power to several safety-related SSCs.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix G, Shutdown Operations Significance Determination Process. Using IMC 0609, Appendix G, Attachment 1, Exhibit 1, User Guidance for Appendix G Phase 1: Initial Screening and Characterization of Findings, and IMC 0609, Appendix G, Attachment 1, Exhibit 2, Initiating Events Screening Questions, the inspectors determined the finding to be of very low safety significance, Green, because the Unit 2 reactor was defueled at the time, and the event did not result in a loss of margin to spent fuel pool boiling.
Cross-Cutting Aspect: H.4 - Teamwork: Individuals and work groups communicate and coordinate their activities within and across organizational boundaries to ensure nuclear safety is maintained. Specifically, individuals did not effectively communicate and coordinate the tagout verification activity. Supervision failed to communicate the work activity did not require opening the subject drawer. Additionally, operators did not verify plant status to discern the drawer was energized and that opening the drawer constituted an operation of plant equipment.
Enforcement:
Violation: TS 5.4.1.a requires, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978. Section 1.c of Regulatory Guide 1.33, Revision 2, requires procedures associated with Equipment Control (e.g.,
locking and tagging). The licensee established procedure AD-OP-ALL-0204, Rev. 009, Plant Status Control, for the purpose of controlling equipment status. Contrary to the above, the licensee failed to implement procedure AD-OP-ALL-0204, during a tagout verification.
Specifically, operators failed to recognize that the opening of the CT2 drawer constituted an operation of plant equipment prohibited by procedure AD-OP-ALL-0204, which resulted in a loss of power to the Unit 2 MFBs.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 14, 2026, the inspectors presented the integrated inspection results to Steven Snider and other members of the licensee staff.
THIRD PARTY REVIEWS Inspectors reviewed the Nuclear Safety Review Board report that was issued July 2025.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
O FD-102A-02-01
Flow Diagram of Low Pressure Injection System (Borated
Water Supply and LPI Pump Suction)
065
O FD-102A-02-02
Flow Diagram of Low Pressure Injection System (LPI)
Pump Discharge
055
O FD-102A-02-03
Flow Diagram of Low Pressure Injection System (Core
Flood)
25
Drawings
O FD-121D-03-01
Flow Diagram of Emergency Feedwater System
048
Miscellaneous
OSS-0254.00-00-1000
(MECH) Design Basis Specification for the Emergency
Feedwater System
061
CSD-ONS-PFP-1AB-
0796
Pre-Fire Plan for U1 Auxiliary Building Elevation 796
2
Fire Plans
CSD-ONS-PFP-3AB-
0783
Pre-Fire Plan for U3 Auxiliary Building Elevation 783
001
O-0310-FZ-008
Auxiliary Building - Unit 3 Fire Protection Plan Fire Area &
Fire Zone Boundaries Plan at EL 783+9
O-0310-FZ-009
Auxiliary Building - Unit 1 Fire Protection Plan Fire Area &
Fire Zone Boundaries Plan at EL 796+6 & 797+6
O-0310-K-006
Fire Protect Aux BLDG Unit 3 EL 783+9
013
Miscellaneous
O-0310-K-007
Fire Protect Aux BLDG Unit 1 EL 796+6
017
OFD-124A-1.1
Flow Diagram of Low Pressure Service Water System
Turbine Building (Low Pressure Service Water Pumps)
056
OFD-124A-3.1
Flow Diagram of Low Pressure Service Water System
Turbine Building (Low Pressure Service Water Pumps)
040
OFD-133A-1.1
Flow Diagram of Condenser Circulating Water System
(CCW Intake Pumps Discharge)
038
OFD-133A-2.1
Flow Diagram of Condenser Circulating Water System
(CCW Intake Pumps Discharge)
2
Drawings
OFD-133A-3.1
Flow Diagram of Condenser Circulating Water System
(CCW Intake Pumps Discharge)
048
AD-OP-ALL-1000
Conduct of Operations
27
AP/2/A/1700/010
Turbine Building Flood
013
Procedures
PT/1/A/0290/003
Turbine Valve Movement
030
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
TN/2/A/EC419099/002
Alternate Suction Source for A/B LPSW Pumps, Support
EC for 2CCW-41 Valve Replacement
001
TO/0/A/EC104970/001
O2R32 CCW Line Stop Leakage / Failure Actions
000
Corrective Action
Documents
2494408
Drawings
O FD-124B-02-02
Flow Diagram of Low Pressure Service Water System
(Reactor Building Cooling Units)
033
Miscellaneous
OSS-0254.00-00-1039
(MECH) Design Basis Specification for the Low Pressure
Service Water System
069
Procedures
PT/2/A/0151/063
Penetration 63 Leak Rate Test
008
Corrective Action
Documents
2575187
Engineering
Changes
419099
Clearance PRT-0 -25-AB LPSWPSOOS-0235
Clearance PRT-K0-25-AB LPSWPSOOS-0239
Clearance PRT-0 -25-EARLY LPSW -0231
Clearance OPS-0 -25-CCW-ASL INSTALL -0996
Risk Profiles for Units 1, 2 and 3 for the week of October
13, 2025
Risk Profiles and Defense-in-Depth (DID) sheets for Unit 2
for the week of October 27, 2025
Risk Profiles and Defense-in-Depth (DID) sheets for Units
1, 2, and 3 from November 2-14, 2025
Miscellaneous
OSS-0254.00-00-1039
(MECH) Design Basis Specification for the Low Pressure
Service Water System
069
AD-OP-ALL-0106
Conduct of Infrequently Performed Tests or Evolutions
AD-WC-ALL-0420
Shutdown Risk Management
AD-WC-ONS-0420
ONS Shutdown Risk Management
PT/0/A/0600/020
Standby Shutdown Facility Instrument Surveillance
031
Procedures
PT/2/A/0202/011
High Pressure Injection Pump Test
108
Calculations
OSC-8966
Allowable LPSW Leakage for Containment Operability
Corrective Action
Documents
2572022, 2570689, 2573510, 2576182, 2575718, 2577381
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
O FD-107B-01-01
Flow Diagram of Liquid Waste Disposal System (Reactor
Building Normal Sump)
2
O FD-121A-02-08
Flow Diagram of Condensate System (Condensate Make-
up and Emergency FDW Pump Section)
019
O-0480C
Piping Layout Intermediate Floor Sections Reactor Building
046
OFD-124A-1.1
Flow Diagram of Low Pressure Service Water System
Turbine Building LPSW Pumps
55A
Drawings
OFD-124B-1.4
Flow Diagram of Low Pressure Service Water System (RC
Pump Motor Cooling & RB Fire Protection)
037
OSC-1326.06
Low Pressure Service Water Inlet Header Piping Analysis
Problem
OSS-0254.00-00-1000
(MECH) Design Basis Specification for the Emergency
Feedwater System
061
OSS-0254.00-00-1027
(MECH) Design Basis Specification for the Condensate
System, Heater Drain System, and Heater Vent System
055
OSS-0254.00-00-1042
(MECH) Design Basis Specification for the Liquid Waste
Disposal System
033
Miscellaneous
OSS-0254.00-00-2009
(ELECT) DB Spec for Oconee 230KV Switchyard 125VDC
Power System
010
IP/0/A/3000/011 SY1
230 kV Switchyard Battery SY-1 Quarterly Surveillance
005
OP/2/A/1106/002 E
Unit 2 Polishing Demineralizer Operations
015
PT/1/A/0150/034
Leak Rate History Record and Reactor Building Leak Rate
Verification
014
Procedures
PT/1/A/0151/005A
Penetration 5A Leak Rate Test
014
Work Orders
20737381, 20753280
Corrective Action
Documents
2574667, 2512520
Drawings
OFD-102A-2.1
Flow Diagram of Low Pressure Injection System Borated
Water Supply and LPI Pump Suction
Engineering
Changes
24583
Procedures
PT/2/A/0152/012
Low Pressure Injection System Valve Stroke Test
045
Work Orders
20669826, 20669826, 20669819
Corrective Action
2573749, 2573747, 2574498, 2574376, 2576181, 2576320
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Clearance PRT-0 -25-TB HVY LIFT -0228
Clearance PRT-2 -25-CT-2 1ST TIM-0068
Clearance PRT-2 -25-CT-5-U2 MFB -0176
Miscellaneous
AD-WC-ONS-0420
ONS Shutdown Risk Management
AD-MN-ALL-0002
AD-OP-ALL-0200
Clearance And Tagging
28
AD-OP-ALL-0203
Reactivity Management
AD-OP-ALL-0204
Plant Status Control
009
AD-SY-ALL-0460
Managing Fatigue and Work Hour Limits
AD-WC-ALL-0420
Shutdown Risk Management
AP/1-2/A/1700/035
Loss of SFP Cooling and/or Level
26
IP/0/B/3002/002 A
Polar Crane Inspection and Preventive Maintenance
015
MP/0/A/1150/002
Reactor Vessel - Closure Head - Removal
070
MP/0/A/1150/002 G
Reactor Vessel - Closure Head - Movement of Head From
or To Stand
2
MP/0/A/1710/017 B
Crane - Whiting - Polar - Inspection
019
MP/0/A/3005/012
Containment Inspection/Close Out Procedure
23
OP/1-2/A/1104/006
SF Cooling System
114
OP/2/A/1102/001
Controlling Procedure for Unit Startup
291
OP/2/A/1102/010
Controlling Procedure For Unit Shutdown
OP/2/A/1102/028
Reactor Building Tour and Containment Material Controls
23
OP/2/A/1103/005
Pressurizer Operation
OP/2/A/1103/011
Draining and Nitrogen Purging RCS
OP/2/A/1104/004
Low Pressure Injection System
OP/2/A/1107/014
Removal and Restoration of 4160V Switchgear and 600V
Load Centers
041
OP/2/A/1107/021
Removal and Restoration of CT2 Transformer
013
OP/2/A/1502/009
Containment Closure Control
057
PT/2/A/0600/001 B
Instrument Surveillance Prior To Mode Change
X
Procedures
PT/2/A/0630/001
Mode Change Verification
ONTC-1-LP-015
Test Acceptance Criteria for Valve 1LP-15
014
Calculations
OSC-5649
LPSW Test Acceptance Criteria (TAC)
21
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
OSC-5674
Generic Letter 89-10 MOV Calculation for Unit 1 Gate and
Globe Valves at Oconee
044
Corrective Action
Documents
2575485, 2575380, 2533627, 2492238, 2576448,
2576449, 2576450
O FD-124B-01-06
Flow Diagram of Low Pressure Service Water System (Aux
Building Air Handling Units)
2
O FD-124B-02-01
Flow Diagram of Low Pressure Service Water System
(Auxiliary Building Services)
081
OFD-102A-1.2
Flow Diagram of Low Pressure Injection System (LPI Pump
Discharge)
2
Drawings
OFD-124B-02-02
Flow Diagram of Low Pressure Service Water System
(Reactor Building Cooling Units)
033
Engineering
Changes
26266
OSS-0254.00-00-1039
(MECH) Design Basis Specification for the Low Pressure
Service Water System
069
Miscellaneous
OSS-0254.00-00-1049
(MECH) Design Basis Spec for the Essential Siphon
Vacuum System
016
IP/0/A/3001/001
Limitorque Preventive Maintenance
098
IP/0/A/3001/010
Maintenance of Limitorque Valve Operators
2
MP/0/A/1210/011
Operator - Limitorque - SB/SMB-00 - Disassembly,
Repair, and Reassembly
040
PT/0/A/0620/018
KHS Out of Tolerance Test
013
PT/1/A/0251/001
Low Pressure Service Water Pump Test
114
PT/2/A/0151/063
Penetration 63 Leak Rate Test
009
PT/2/A/0202/011
High Pressure Injection Pump Test
108
PT/2/A/0203/006 B
Low Pressure Injection Pump Test - Decay Heat
034
PT/2/A/0230/0015
High Pressure Injection Motor Cooler Performance Test
053
PT/2/A/0251/069
LPI Cooler Test
2
PT/2/A/0610/001 J
Emergency Power Switching Logic Functional Test
058
PT/3/A/0261/010
Essential Siphon Vacuum System Test
038
Procedures
TT/2/A/EC419099/002
Alternate Suction Source for A/B LPSW Pumps
000
Work Orders
20630941, 20745331, 20695118, 20745008, 20738577,
20701608, 20760076
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
2568486, 2570833, 2572069, 2576228, 2560992,
2567951, 2573453, 2576181, 2576766
Corrective Action
Documents
20630941, 20745331, 20695118, 20745008, 20738577,
20701608
AP/1-2/A/1700/035
Loss of SFP Cooling and/or Level
26
AP/1-2/A/1700/036
Degraded Control Room Area Cooling
24
AP/1/A/1700/002
Excessive RCS Leakage
018
AP/1/A/1700/024
Loss of LPSW
030
AP/2/A/1700/002
Excessive RCS Leakage
019
Procedures
AP/2/A/1700/011
Recovery from Loss of Power
067