ML25037A263
| ML25037A263 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/10/2025 |
| From: | Robert Williams NRC/RGN-II/DORS |
| To: | Snider S Duke Energy Carolinas |
| References | |
| IR 2024004 | |
| Download: ML25037A263 (1) | |
Text
Steven Snider Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672-0752
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 cc w/ encl: Distribution via LISTSERV February 10, 2025 Signed by Williams, Robert on 02/10/25
SUNSI Review X
Non-Sensitive
Sensitive X
Publicly Available
Non-Publicly Available OFFICE RII/DORS RII/DORS RII/DORS NAME N. Smalley J. Seat R. Williams DATE 02/10/2025 02/06/2025 02/10/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:
05000269, 05000270 and 05000287 License Numbers:
DPR-38, DPR-47 and DPR-55 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
2
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
3 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)
4 (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) (1 Sample)
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)
5 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.
NCR 02540684 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.
6 (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 Sample)
(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)
7 The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)
NCR 2533234, safety valve 1CF-1 failed to operate from the control room (2)
NCR 2533422, main control room and technical support center (TSC) following loss of power to motor control center 1XR on October 28, 2024 (3)
NCR 2532897, 1LP-37 LPI cooler B thermal relief valve lifted during LPI alignment (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, 2024 RADIATION SAFETY
8 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
9 Radioactive Material Storage (IP Section 03.01) (1 Sample)
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 Sample)
(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
10 Annual Follow-up of Selected Issues (Section 03.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)
NCR 2532763, unqualified sealant used to repair resistance temperature detector (RTD) cable 71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02) (1 Sample)
(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) (2 Samples)
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.
11 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date AD-OP-ONS-0120 Severe Weather Preparations 1
AD-WC-ALL-0230 Seasonal Readiness 2
IP/0/B/1606/009 Preventive Maintenance and Operational Check of Freeze Protection 035 Procedures OP/0/B/1140/050 Weather Related Activities 008 71111.01 Work Orders 20632079, 20627923 OFD-102A-1.1 Flow Diagram of Low Pressure Injection System (Borated Water Supply & LPI Pump Suction) 72 OFD-102A-1.2 Flow Diagram of Low Pressure Injection System LPI Pump Discharge 62 OFD-103A-3.1 Flow Diagram Of Reactor Building Spray System (BS) 32 Drawings OFD-121A-1.1 Flow Diagram of Protected Service Water (PSW) System 3
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 1028 (Mech) Design Basis Spec For The Low Pressure Injection And Core Flood System (LPI) 70 71111.04 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 0
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 2423868, 2444366 CSD-ONS-PFP-1AB-0796 Pre-Fire Plan for U1 Auxiliary Building Elevation 796 1
71111.05 Fire Plans CSD-ONS-PFP-Pre-Fire Plan for U1 Reactor Building 000
12 Inspection Procedure Type Designation Description or Title Revision or Date 1RB CSD-ONS-PFP-2AB-0809 Pre-Fire Plan for U2 Auxiliary Building Elevation 809 0
CSD-ONS-PFP-2TB-0796 Pre-Fire Plan for U2 Turbine Building Elevation 796 1
CSD-ONS-PFP-3AB-0783 Pre-Fire Plan for U3 Auxiliary Building Elevation 783 1
O-0310-FZ-008 Auxiliary Building - Unit 3 Fire Protection Plan Fire Area &
Fire Zone Boundaries Plan at EL 783+9 3
O-0310-FZ-009 Auxiliary Building - Units 1 Fire Protection Plan Fire Area &
Fire Zone Boundaries Plan at EL 796+6 & EL 797+6 3
O-0310-FZ-021 Reactor Building - Unit 1 Fire Protection Plan Fire Area &
Fire Zone Boundaries Plan at EL 861+6 1
O-0310-K-006 Auxiliary Building - Unit 3 Fire protection Plan & Fire Barrier, Flood & Pressure Boundaries Plan at EL 783+9 13 O-0310-K-007 Fire Protect Aux Bldg Unit 1 EL 796+6 17 O-0310-K-019 Reactor Building - Unit 1 Fire Protection Plan & Fire Barrier, Flood, & Pressure Boundaries Plan at EL 861+6 2
Miscellaneous O-0310-K-11 Auxiliary Building - Unit 2 Fire Protection Plan & Fire Barrier, Flood & Pressure Boundaries Plan at EL 809+3 17 Corrective Action Documents 2412854, 2533950, 2424871 Miscellaneous OSS-0254.00 4005 Design Basis Specification for Design Basis Events 040 AD-OP-ALL-0205 Time Critical Actions/Sensitive Actions 3
AP/1-2/A/1700/030 Auxiliary Building Flood 024 PT/0/A/0120/033 Time Critical Action Verification 010 Procedures PT/0/B/0120/034 Time Critical Component Surveillance 012 71111.06 Work Orders 20545338 Miscellaneous Oconee Unit 1 O1R22 Outage Steam Generator Degradation Assessment 0
1-PDB2-11 Phased Array Ultrasonic Examination of 1-PDB2-11 11/02/2024 71111.08P NDE Reports 1B2-HPI-UT Phased Array Ultrasonic Examination of 1-RC-0201-126V 11/02/2024
13 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 71111.11Q Procedures AD-EP-ALL-0002 NRC Regulatory Assessment Performance Indicator Guideline Emergency Preparedness Cornerstone 7
Corrective Action Documents 2533422, 2534759, 2535065, 2534607 AD-EG-ALL-1210 Maintenance Rule Program 5
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 17 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 71111.12 Work Orders 20277904, 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, 2024 Miscellaneous OSS-0254.00 1002 (MECH) Design Basis Specification For High Pressure Service Water System AD-FP-ALL-1522 Duties of a Compensatory Fire Watch 3
AD-WC-ONS-0420 ONS Shutdown Risk Management 6
71111.13 Procedures OP/1/A/1103/011 Draining and Nitrogen Purging RCS 104
14 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 89 Drawings OFD-102A-1.3 Flow Diagram of Low Pressure Injection System Core Flood 32 OSS-0254.00 1021 (MECH) Design Basis Specification for the Control Room Ventilation System 45 Miscellaneous OSS-0254.00 1028 (MECH) Design Basis Spec for the Low Pressure Injection and Core Flood System (LPI) 70 OP/1/A/1104/001 Core Flooding System 83 OP/1/A/1107/018 Removal and Restoration of Motor Control Centers, Encl.
4.19, Removal and Restoration of MCC 1XR 37 Procedures PT/1/A/0152/007 Core Flood System Valve Stroke Test 22 20277904, 20692435 71111.15 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 69 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 002 Miscellaneous OSS-0254.00 1006 (MECH) Design Basis Specification for the Spent Fuel Cooling System 34 AD-MN-ALL-0002 Foreign Material Exclusion 16 AP/1-2/A/1700/035 Loss of SFP Cooling and/or Level 026 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 22 71111.20 Procedures MP/0/B/1710/022 Operation of Reactor Building Polar Crane and Auxiliary 039
15 Inspection Procedure Type Designation Description or Title Revision or Date Hoist (CRD Crane)
OP/0/A/1108/001 Curves and General Information 120 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 39 PT/1/A/1103/015 Reactivity Balance Procedure 084 Corrective Action Documents 2217854, 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) 55 KM 320.0028.001 Installation and Operating Instructions for Keowee Batteries 004 Miscellaneous OSS-0254.00 2018 (ELECT) Keowee 125VDC Power System 010 AD-EG-ALL-1311 Failure Investigation Process (FIP) 3 71111.24 Procedures IP/0/A/3000/001 C
Removal, Installation, and Jumpering of Battery Cells 047
16 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 023 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 16 PT/1/A/0151/019 Penetration 19 Leak Rate Test 018 PT/1/A/0600/010 Reactor Coolant Leakage 102 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 71124.01 Radiation Work Permits (RWPs)
RWP # 1150 U1 RX BLDG CANAL SUPPORT ACTIVITIES 71151 Corrective Action Documents NCR 02526306 Corrective Action Documents 2532763, 2303601, 2465306 Engineering Changes EC 424824 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 0013 (ELECT) Installation Spec Sealing Cable Entrances on Class 1E Devices 9
71152A Procedures IP/0/A/0200/029 A Sealing Cable Entrance Fittings on Class 1E Devices 035
17 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 0019 Remove APSR CRDMs LTAM ON 0023 CRD System Replacement ON-19-0001 Unit 1 Dropped Rod Event 04/12/2018 Miscellaneous OSS-0254.00 2013 (ELEC) Design Basis Specification for the Control Rod Drive System 018 71152S 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 44 Drawings OFD-101A-1.4 Flow Diagram of High Pressure Injection System (Charging Section) 52 Engineering Changes 421842 Procedures AD-PI-ALL-0106 Cause Investigation Checklists 8
71153 Work Orders 20513217