IR 05000269/2024004
| ML25037A263 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/10/2025 |
| From: | Robert Williams Division of Operating Reactors |
| To: | Snider S Duke Energy Carolinas |
| References | |
| IR 2024004 | |
| Download: ML25037A263 (1) | |
Text
SUBJECT:
OCONEE NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000269/2024004 AND 05000270/2024004 AND 05000287/2024004
Dear Steven Snider:
On December 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Oconee Nuclear Station. On February 3, 2025, 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.
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, 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:
05000269/2024004, 05000270/2024004 and 05000287/2024004
Enterprise Identifier:
I-2024-004-0021
Licensee:
Duke Energy Carolinas, LLC
Facility:
Oconee Nuclear Station
Location:
Seneca, South Carolina
Inspection Dates:
October 01, 2024, to December 31, 2024
Inspectors:
N. Smalley, Senior Resident Inspector
D. Dang, Resident Inspector
E. Robinson, Resident Inspector
S. Downey, Senior Reactor Inspector
D. Neal, Health Physicist
A. Nielsen, Senior Health Physicist
J. Viera, Senior Operations Engineer
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
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000269/2022-001-00 LER 2022-001-00 for Oconee Nuclear Station,
Unit 1, Ultrasonic Examination Indications Identifies Degraded Reactor Coolant System Pressure Boundary 71153 Closed LER 05000269/2022-001-01 LER 2022-001-01 for Oconee Nuclear Station,
Unit 1, Ultrasonic Examination Indication Identifies Degraded Reactor Coolant System Pressure Boundary 71153 Closed
PLANT STATUS
Unit 1 began the inspection period at or near 100 percent rated thermal power (RTP). On October 21, 2024, the unit was shut down for a scheduled refueling outage (O1R33). Unit 1 returned to 100 percent RTP on November 14, 2024, and operated at or near 100 percent RTP for the remainder of the inspection period.
Unit 2 operated at or near 100 percent RTP for the entire 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
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following systems: low pressure injection (LPI), essential siphon vacuum (ESV), and auxiliary building ventilation on December 6, 2024.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Protected service water system with standby shutdown facility out of service (OOS)for instrumentation modification on October 29, 2024
- (2) Transformer CT-5 power path during O1R33 refueling outage on November 5, 2024
- (3) Unit 3 A train reactor building spray concurrent with testing on the B train on December 11, 2024
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete system walkdown of Unit 1 low pressure injection during the O1R33 refueling outage between October 22 and November 12, 2024.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 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 33: Unit 2 4160V switchgear on October 3, 2024
- (2) Fire zone 95: Unit 1 equipment room on October 7, 2024
- (3) Fire zone 103: Unit 2 east penetration room on October 7, 2024
- (4) Fire zone 77: Unit 3 auxiliary building 200 level hallway on November 5, 2024
- (5) Fire zone 122: Unit 1 containment on November 7, 2024
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protections for the coolant storage system, low pressure injection system, and the spent fuel cooling system in the Unit 1, 2, and 3 auxiliary building.
===71111.08P - Inservice Inspection Activities (PWR) The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities in Unit 1 during refueling outage O1R33 from October 28 to November 6, 2024.
PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01)===
The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:
- (1) Ultrasonic Examination
1. 1-03-3-3X4, pipe to pipe weld, ASME Class 2
2. 1-FDW-250-30B, elbow to reducer weld, ASME Class 2
3. 1-FDW-250-31B, pipe to reducer weld, ASME Class 2
4. 1-PDB2-11, safe end to pipe dissimilar metal weld, ASME Class 1
5. 1-RC-0201-126V, high pressure injection 1B2 weld overlay, ASME Class 1
PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection
Activities (IP Section 03.02) (1 Sample)
The inspectors verified that the licensee conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:
- (1) Bare metal visual examination of 1-RPV-HEAD-PEN, reactor pressure vessel upper head, ASME Class 1 PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)
The inspectors evaluated the licensees boric acid control program performance, which included the following activities:
(1)
1. Boric acid walkdown - October 29, 2024
2. Review of the following boric acid evaluations (by condition report number):
a.
Nuclear condition report (NCR) 02484541 b.
NCR 02486699 c.
NCR 02494772 d.
NCR 02503578 e.
3. Review of the following corrective actions performed for evidence of boric acid
leaks that were identified (by work request number):
a.
Work request (WR) 20238022 b.
WR 20238153 c.
WR 20254024 d.
WR 20254232 e.
WR 20261484 PWR Inservice Inspection Activities Sample - Steam Generator Tube Inspection Activities (Section 03.04) (1 Sample)
The inspectors verified that the licensee is monitoring the steam generator tube integrity appropriately through a review of the following examinations:
(1)
1. Steam generator 1A - eddy current testing (ECT) for tubes R1C10, R60C3,
R127C2
2. Steam generator 1B - ECT for tubes R54C21, R70C2, R74C3, R75C20
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 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 inspector performed an in-office review of the overall pass/fail results of the individual operating examinations, and the crew simulator operating examinations in accordance with inspection procedure (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, 2024.
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 licensed operator performance in the main control room of Unit 1 during outage and unit startup activities on November 12, 2024.
Licensed Operator Requalification Training/Examinations (IP Section 03.02)===
- (1) The inspectors observed and evaluated a simulator exam for an operating crew in accordance with annual simulator exam (ASE)-30 in the simulator on November 19, 2024.
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) NCR 2533422, loss of the 1XR motor control center during preventive maintenance on October 28, 2024
- (2) NCR 2535065, transformer CX feeder breaker tripped during troubleshooting on November 9, 2024
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 and 2 elevated green risk prior to unit shutdown due to minor leak repair on B train of high pressure service water (HPSW), on October 17-20, 2024
- (2) Unit 1 yellow risk due to reactor coolant system draining and lowered inventory operations, on October 23 and 24, 2024
- (3) Unit 1 yellow risk due to reduced inventory following refueling, on November 4 and 5, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (2) NCR 2533422, main control room and technical support center (TSC) following loss of power to motor control center 1XR on October 28, 2024
- (4) NCR 2533976, 1MS-164 (1B main steam atmospheric dump valve control valve)valve disc stem unconnected from actuator stem
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated refueling outage O1R33 activities from October 21, 2024, to November 16, 2024.
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) (4 Samples)
- (1) Periodic test (PT)/1/A/0150/055, borated water storage tank return valve 1LP42 retest, on October 22, 2024
- (2) Instrument procedure (IP)/2/A/0315/014 A, post maintenance testing on Unit 2 control rod drive (CRD) breaker, on October 30, 2024
- (3) IP/0/A/3000/003 KB2, "Keowee Hydro Station Battery 2 Service Test and Annual Surveillance," following complete battery bank replacement, on November 21, 2024
- (4) PT/0/A/0610/017, operability test of 4160V breakers following refurbishment of breaker B2T-09 on December 16, 2024
Surveillance Testing (IP Section 03.01) (3 Samples)
- (1) PT/3/A/0202/011, "High Pressure Injection Pump Test," on October 16, 2024
- (2) PT/0/A/0711/001, "Zero Power Physics Test," on November 12, 2024
- (3) PT/3/A/0600/012, "Turbine Driven Emergency Feedwater Pump Test," on Unit 3, on December 9, 2024
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
- (1) PT/1/A/0151/019, "Penetration 19 Leak Rate Test," on November 8, 2024
Reactor Coolant System Leakage Detection Testing (IP Section 03.01) (1 Sample)
- (1) Increased unidentified reactor coolant leakage on Unit 1 using PT/1/A/0600/010 during the week of December 9,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
- (1) Licensee surveys of potentially contaminated material leaving the Warehouse 10 outside storage area radiologically controlled area (RCA)
- (2) Workers exiting the RCA during the Unit 1 refueling outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
- (1) Removal of transfer tube covers
- (2) Low pressure service water piping replacement
- (3) Preparation for reactor vessel head removal High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (4 Samples)
The inspectors evaluated licensee controls of the following high radiation areas (HRAs) and very high radiation areas (VHRAs):
- (1) Unit 1-2 spent resin storage tank room locked high radiation area (LHRA)
- (2) Unit 1-3 reactor coolant bleed evaporator room LHRA
- (3) Miscellaneous waste LHRA
- (4) In-core wire casks 1 and 2 VHRA Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &
Transportation
Radioactive Material Storage (IP Section 03.01)
The inspectors evaluated the licensees performance in controlling, labeling and securing the following radioactive materials:
- (1) Outside radioactive material storage areas adjacent to Warehouse 10
Radioactive Waste System Walkdown (IP Section 03.02) (3 Samples)
The inspectors walked down the following accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality:
- (1) Radwaste facility liquid and solid radioactive waste processing systems
- (2) Abandoned concentrate batch tanks
- (3) Interim radwaste building filter handling area
Waste Characterization and Classification (IP Section 03.03) (2 Samples)
The inspectors evaluated the following characterization and classification of radioactive waste:
- (1) Dry active waste, 2022-2023 waste stream report
- (2) Resin batch tank resin, waste stream report, dated April 17, 2024
Shipping Records (IP Section 03.05) (4 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
- (1) Shipping record 22-2029, low specific activity (LSA), resin
- (2) Shipping record 23-2008, LSA, resin
- (3) Shipping record 23-2028, LSA, filters
- (4) Shipping record 24-2010, LSA, resin
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15)===
- (1) November 19, 2023, through October 25, 2024 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) June 17, 2023, through October 23, 2024
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in CRD breaker trip time failure that might be indicative of a more significant safety issue.
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensees event reporting determinations to ensure it complied with reporting requirements.
- (1) Licensee Event Report (LER) 05000269/2022-001-00, Ultrasonic Examination Indications Identifies Degraded Reactor Coolant System Pressure Boundary (ADAMS Accession No. ML22355A448) The inspectors determined that a cause could not be determined at this time and therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements. This LER is closed.
- (2) LER 05000269/2022-001-01, Ultrasonic Examination Indications Identifies Degraded Reactor Coolant System Pressure Boundary (ADAMS Accession No. ML24312A416)
The inspectors determined that a cause could not be determined at this time and therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements. This LER is closed.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 24, 2024, the inspectors presented the radiation protection inspection results to Steven Snider and other members of the licensee staff.
- On November 6, 2024, the inspectors presented the baseline inservice inspection results to Steven Snider and other members of the licensee staff.
- On February 3, 2025, the inspectors presented the integrated inspection results to Steven Snider and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AD-OP-ONS-
20
Severe Weather Preparations
AD-WC-ALL-0230
Seasonal Readiness
IP/0/B/1606/009
Preventive Maintenance and Operational Check of Freeze
Protection
035
Procedures
OP/0/B/1140/050
Weather Related Activities
008
Work Orders
20632079, 20627923
OFD-102A-1.1
Flow Diagram of Low Pressure Injection System (Borated
Water Supply & LPI Pump Suction)
OFD-102A-1.2
Flow Diagram of Low Pressure Injection System LPI Pump
Discharge
OFD-103A-3.1
Flow Diagram Of Reactor Building Spray System (BS)
Drawings
OFD-121A-1.1
Flow Diagram of Protected Service Water (PSW) System
Clearance PRT-0-24-SSF OOS-0268
Clearance PRT-1-24-CT-5-U1 MFB-0258(2)
Clearance PRT-3-24-3A RBS TRAIN-0261
Miscellaneous
OSS-0254.00-00-
28
(Mech) Design Basis Spec For The Low Pressure Injection
And Core Flood System (LPI)
Work Orders
20575684
OSC-10816
ONS TCCA A and B Area Basis for AD-EG-ALL-1520
005
OSC-9294
NFPA-805 Transition Existing Engineering Equivalency
Evaluations
OSC-9314
NFPA 805 Transition Risk-Informed Performance-Based
Fire Risk Evaluation
006
Calculations
OSC-9659
Oconee Nuclear Safety Capability Assessment for Units 1,
2, and 3
011
Corrective Action
Documents
23868, 2444366
CSD-ONS-PFP-
Pre-Fire Plan for U1 Auxiliary Building Elevation 796
Fire Plans
CSD-ONS-PFP-
Pre-Fire Plan for U1 Reactor Building
000
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1RB
CSD-ONS-PFP-
Pre-Fire Plan for U2 Auxiliary Building Elevation 809
CSD-ONS-PFP-
Pre-Fire Plan for U2 Turbine Building Elevation 796
CSD-ONS-PFP-
Pre-Fire Plan for U3 Auxiliary Building Elevation 783
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 - Units 1 Fire Protection Plan Fire Area &
Fire Zone Boundaries Plan at EL 796+6 & EL 797+6
O-0310-FZ-021
Reactor Building - Unit 1 Fire Protection Plan Fire Area &
Fire Zone Boundaries Plan at EL 861+6
O-0310-K-006
Auxiliary Building - Unit 3 Fire protection Plan & Fire Barrier,
Flood & Pressure Boundaries Plan at EL 783+9
O-0310-K-007
Fire Protect Aux Bldg Unit 1 EL 796+6
O-0310-K-019
Reactor Building - Unit 1 Fire Protection Plan & Fire Barrier,
Flood, & Pressure Boundaries Plan at EL 861+6
Miscellaneous
O-0310-K-11
Auxiliary Building - Unit 2 Fire Protection Plan & Fire
Barrier, Flood & Pressure Boundaries Plan at EL 809+3
Corrective Action
Documents
2412854, 2533950, 2424871
Miscellaneous
OSS-0254.00-00-
4005
Design Basis Specification for Design Basis Events
040
AD-OP-ALL-0205
Time Critical Actions/Sensitive Actions
AP/1-
2/A/1700/030
Auxiliary Building Flood
24
PT/0/A/0120/033
Time Critical Action Verification
010
Procedures
PT/0/B/0120/034
Time Critical Component Surveillance
2
Work Orders
20545338
Miscellaneous
Oconee Unit 1 O1R22 Outage Steam Generator
Degradation Assessment
1-PDB2-11
Phased Array Ultrasonic Examination of 1-PDB2-11
11/02/2024
NDE Reports
Phased Array Ultrasonic Examination of 1-RC-0201-126V
11/02/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
R1
UT-24-012
Ultrasonic Examination of 1FDW-250-30B
11/02/2024
UT-24-039
Ultrasonic Examination of 1-03-3-3X4
10/28/2024
UT-24-043
Ultrasonic Examination of 1FDW-250-31B
11/02/2024
VT-24-037
Visual Examination of 1-RPV-HEAD-PEN
11/01/2024
Miscellaneous
Simulator Exam Guide SEG 2405
Procedures
AD-EP-ALL-0002
NRC Regulatory Assessment Performance Indicator
Guideline Emergency Preparedness Cornerstone
Corrective Action
Documents
2533422, 2534759, 2535065, 2534607
AD-EG-ALL-1210
IP/0/A/2001/003
O
Inspection and Maintenance of 600 VAC Loadcenters
008
IP/0/A/3000/018 A
Ground Location for Instrument and Control DC Systems
IP/0/A/3009/017
Wire Terminal Installation, Labeling And Termination (600
Volts Or Less)
044
OP/0/A/1106/019
Keowee Hydro at Oconee
114
Procedures
OP/1/A/1107/018
Removal and Restoration of Motor Control Centers
038
Work Orders
277904, 20278973
Corrective Action
Documents
2532272
Risk Profile and Defense in Depth Status Sheets for Unit 1
October 23rd and 24th
Risk Profile and Defense in Depth Status Sheets for Unit 1
November 4th and 5th
Risk Profiles for Units 1 and 2 on the week of October 14,
24
Miscellaneous
OSS-0254.00-00-
1002
(MECH) Design Basis Specification For High Pressure
Service Water System
AD-FP-ALL-1522
Duties of a Compensatory Fire Watch
AD-WC-ONS-
20
ONS Shutdown Risk Management
Procedures
OP/1/A/1103/011
Draining and Nitrogen Purging RCS
104
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
20691508
2533422
Corrective Action
Documents
2532897
O-0703-F
One Line Diagram Station Auxiliary Circuits 600V
Drawings
OFD-102A-1.3
Flow Diagram of Low Pressure Injection System Core Flood
OSS-0254.00-00-
21
(MECH) Design Basis Specification for the Control Room
Ventilation System
Miscellaneous
OSS-0254.00-00-
28
(MECH) Design Basis Spec for the Low Pressure Injection
and Core Flood System (LPI)
OP/1/A/1104/001
Core Flooding System
OP/1/A/1107/018
Removal and Restoration of Motor Control Centers, Encl.
4.19, Removal and Restoration of MCC 1XR
Procedures
PT/1/A/0152/007
Core Flood System Valve Stroke Test
277904, 20692435
Work Orders
20641698, 20277443
2531092, 2531281, 2532429, 2532695, 2532784, 2353718
Corrective Action
Documents
2532821, 2514360, 2533734. 2533950
Drawings
OFD-104A-01-01
Flow Diagram of Spent Fuel Cooling System
O1R33 Schedules, risk profiles and OCC packages
ONEI-0400-606
Oconee 1 Cycle 34 Physics Tests Manual
000
ONEI-0400-607
Oconee 1 Cycle 34 Core Operating Limits Report
000
OSC-1594
NUREG-0612 - Control of Heavy Loads - Load Drop
Analysis
2
Miscellaneous
OSS-0254.00-00-
1006
(MECH) Design Basis Specification for the Spent Fuel
Cooling System
AD-MN-ALL-0002
AP/1-
2/A/1700/035
Loss of SFP Cooling and/or Level
26
IP/0/B/3002/002 A
Polar Crane Inspection and Preventative Maintenance
015
MP/0/A/1710/017
B
Crane - Whiting - Polar - Inspection
019
MP/0/A/3005/012
Containment Inspection/Close Out Procedure
Procedures
MP/0/B/1710/022
Operation of Reactor Building Polar Crane and Auxiliary
039
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Hoist (CRD Crane)
OP/0/A/1108/001
Curves and General Information
20
OP/0/A/1108/001
A
Reactor Core and SFP Loss of Cooling Heatup Tables
009
OP/0/A/1108/001
B
Spent Fuel Pool Level vs. Temperature Curves
019
OP/1-
2/A/1104/006
SF Cooling System
113
OP/1/A/1102/001
Controlling Procedure For Unit Startup
331
OP/1/A/1102/004
Operation at Power
165
OP/1/A/1102/010
Controlling Procedure for Unit Shutdown
238
OP/1/A/1102/028
Reactor Building Tour and Containment Materiel Controls
019
OP/1/A/1103/006
RCP Operation
090
OP/1/A/1103/011
Draining and Nitrogen Purging RCS
104
OP/1/A/1105/019
Control Rod Drive System
037
OP/1/A/1106/001
Turbine Generator
141
OP/1/A/1502/009
Containment Closure Control
053
PT/1/A/0251/069
LPI Cooler Test
013
PT/1/A/0600/001
B
Instrument Surveillance Prior to Mode Change
050
PT/1/A/0630/001
Mode Change Verification
PT/1/A/1103/015
Reactivity Balance Procedure
084
Corrective Action
Documents
217854, 2218178, 2537631
K-0704
One Line Diagram - 125VDC Station Auxiliary Circuits
043
Drawings
OFD-101A-1.1
Flow Diagram of High Pressure Injection System (Letdown
Section)
KM 320.0028.001
Installation and Operating Instructions for Keowee Batteries
004
Miscellaneous
OSS-0254.00-00-
2018
(ELECT) Keowee 125VDC Power System
010
AD-EG-ALL-1311
Failure Investigation Process (FIP)
Procedures
IP/0/A/3000/001
C
Removal, Installation, and Jumpering of Battery Cells
047
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
IP/0/A/3000/003
KB2
Keowee Hydro Station Battery 2 Service Test and Annual
Surveillance
009
IP/0/A/3000/026
Battery Cell Connection Resistance Test
048
IP/2/A/0315/014 A
TXS RPS Interposing Relay Test and Control Rod Drive
Breaker Trip Timing Test
006
OP/0/B/1106/033
Primary System Leak Identification
23
PT/0/A/0610/017
Operability Test of 4160V Breakers
031
PT/0/A/0620/009
Keowee Hydro Operation
056
PT/0/A/0711/001
Zero Power Physics Test
081
PT/1/A/0150/006
Mechanical Penetration Leak Rate Data
119
PT/1/A/0150/055
1LP-42 Leak Test
PT/1/A/0151/019
Penetration 19 Leak Rate Test
018
PT/1/A/0600/010
Reactor Coolant Leakage
2
PT/3/A/0202/011
High Pressure Injection Pump Test
095
PT/3/A/0600/012
Turbine Driven Emergency Feedwater Pump Test
096
Work Orders
20522956, 20629929, 20683468, 20443780
ALARA Plans
ALARA Plan
RWP 1022 - Alloy
600
Procedures
AD-RP-ALL-0007
Control of Radioactive Material
Radiation Work
Permits (RWPs)
RWP # 1150
U1 RX BLDG CANAL SUPPORT ACTIVITIES
71151
Corrective Action
Documents
Corrective Action
Documents
2532763, 2303601, 2465306
Engineering
Changes
Environmental Qualification Maintenance Manual,
Equipment Type: Resistance Temperature Detectors
(RTDs), Manufacturer: Weed Instrument Company
000
OM 267.1336.001
Installation Instruction Operation Manual for N9031-1A RTD
and Associated Equipment
003
Miscellaneous
OSS-0218.00-00-
0013
(ELECT) Installation Spec Sealing Cable Entrances on
Class 1E Devices
Procedures
IP/0/A/0200/029 A
Sealing Cable Entrance Fittings on Class 1E Devices
035
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
IP/0/A/0200/032
RTD Replacement
066
Work Orders
20568069
Corrective Action
Documents
2517798, 2518187, 2517794, 2524972, 2304822, 2415976
EVAL-2018-ON-
CRD-00001084
CRD-Unit 1-LSS; CRD-Unit 1-LSS (Plant Level)
EVAL-2022-ON-
CRD-00002210
CRD-Unit 2 -HSS 100% Required
LTAM ON-22-
0019
Remove APSR CRDMs
LTAM ON-22-
23
CRD System Replacement
ON-19-0001
Unit 1 Dropped Rod Event
04/12/2018
Miscellaneous
OSS-0254.00-00-
2013
(ELEC) Design Basis Specification for the Control Rod Drive
System
018
Procedures
IP/1/A/0315/014 A
TXS RPS Interposing Relay Test and Control Rod Drive
Breaker Trip Timing Test
018
Corrective Action
Documents
2447967, 1905753
OFD-100A-1.1
Flow Diagram of Reactor Coolant System
Drawings
OFD-101A-1.4
Flow Diagram of High Pressure Injection System (Charging
Section)
Engineering
Changes
21842
Procedures
AD-PI-ALL-0106
Cause Investigation Checklists
Work Orders
20513217