IR 05000269/2024003
| ML24310A040 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/31/2024 |
| From: | Robert Williams NRC/RGN-II/DORS |
| To: | Snider S Duke Energy Carolinas |
| References | |
| IR 2024003 | |
| Download: ML24310A040 (1) | |
Text
SUBJECT:
OCONEE NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000269/2024003 AND 05000270/2024003 AND 05000287/2024003
Dear Steven Snider:
On September 30, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Oconee Nuclear Station. On October 29, 2024, 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.
October 31, 2024 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:
DPR-38, DPR-47 and DPR-55 Report Numbers:
05000269/2024003, 05000270/2024003 and 05000287/2024003 Enterprise Identifier:
I-2024-003-0025 Licensee:
Duke Energy Carolinas, LLC Facility:
Oconee Nuclear Station Location:
Seneca, South Carolina Inspection Dates:
July 1, 2024, to September 30, 2024 Inspectors:
N. Smalley, Senior Resident Inspector D. Dang, Resident Inspector E. Robinson, Resident Inspector S. Battenfield, Operations Engineer M. Bradfield, Senior Reactor Technology Instructor K. Schaaf, Operations Engineer J. Tornow, Physical Security Inspector J. Walker, Senior Emergency Preparedness 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 Follow Shutdown Procedure Resulted in Inadvertent Automatic Feedwater Isolation System Actuation Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green NCV 05000287/2024003-01 Open/Closed
[H.12] - Avoid Complacency 71153 A self-revealed Green finding and associated non-cited violation (NCV) of Technical Specification 5.4, Procedures, was identified when the licensee failed to properly implement procedure OP/3/A/1102/010, Controlling Procedure for Unit Shutdown, during a planned shutdown on Unit 3 which resulted in the inadvertent actuation of the automatic feedwater isolation system (AFIS). The subsequent level transient in the once-through steam generators (SG) caused an emergency feedwater (EFW) system actuation.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000287/2024-001-00 LER 2024-001-00 for Oconee Nuclear Station,
Unit 3, Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation 71153 Closed
PLANT STATUS
Unit 1 operated at or near 100 percent rated thermal power (RTP) for the entire inspection period, with the exception of a temporary power reduction to 98.2 percent on August 3, 2024, as required to implement a measurement uncertainty recapture power uprate from 2568 megawatts to 2608 megawatts core thermal power.
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, with the exception of a temporary power reduction to 98.2 percent on September 16, 2024, as required to implement a measurement uncertainty recapture power uprate from 2568 megawatts to 2608 megawatts core thermal power.
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
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending Hurricane Helene expected on September 26, 2024, to include heavy rain, wind gusts up to 69 mph, and widespread power outages.
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) Unit 3 A train of the essential siphon vacuum system concurrent with maintenance on the B train on July 16, 2024
- (2) Unit 3 turbine driven emergency feedwater on August 14, 2024
- (3) Underground emergency power path while 230kV red bus out of service on September 18, 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 106: Unit 1 cable room on July 10, 2024
- (2) Fire zone 81: Unit 2 auxiliary building 200 level hallway on July 29, 2024
- (3) Fire zone 110: Units 1/2 control room on July 29, 2024
- (4) Fire zone 6: Unit 3 main feed pump area on August 27, 2024
- (5) Fire zone 29: Unit 3 4160V switchgear on August 28, 2024
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated external flooding mitigation protection provided in the:
- Unit 3 auxiliary building work area, Vaqua room roof drains, and exterior subsurface walls and penetrations
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 power ascension and measurement uncertainty recapture activities on August 5, 2024
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated the training staff while performing training in the simulator (ASE3) on July 23, 2024
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:
- (1) Nuclear condition report (NCR) 2523154, leakage in Unit 3 core flood tank sample line relief valve, and associated sample line blockage maintenance on July 23, 2024
- (2) NCR 2526449, 1C low pressure injection (LPI) pump difficult to rotate by hand on August 22, 2024
- (3) NCR 2494408, Unit 2 low pressure service water supply valve 2LPSW-1054 failed leak rate test on September 18, 2024
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (6 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, 2, and 3 green risk due to transformer CT5 maintenance, on July 8, 2024
- (2) Unit 1, 2, and 3 yellow risk due to planned maintenance on the standby shutdown facility, on July 29, 2024
- (3) Unit 1, 2, and 3 elevated green risk due to maintenance on the backup instrument air compressor, on August 4, 2024
- (4) Unit 2 green risk due to 2C LPI pump motor replacement, on August 8, 2024
- (5) Unit 1 high green and yellow risk due to C LPI pump testing, nuclear instrumentation calibration, and concentrated boric acid storage tank water movements, on August 22-23, 2024
- (6) Unit 2 green risk due to emergent nuclear instrument calibration, on September 11, 2024
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:
- (1) NCR 2521743, reactor building emergency sump detectors past environmental qualification end of life
- (3) NCR 2450961, 1B motor driven emergency feedwater pump following postponed replacement of leaking motor air cooler gaskets
- (4) NCR 2522001, response to notification of deviation in welding of incore detector assemblies by Framatome
- (5) NCR 2494408, Unit 2 reactor building auxiliary cooling system supply control valve 2LPSW-1054 failed leak rate test
- (6) NCR 2525104, 2B motor driven emergency feedwater pump test block valve degradation and missing parts
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) NCR 2524513, replacement of test flow throttling valve 2FDW-354 due to issues achieving required flow
- (2) NCR 2512808, compensatory action for isolation of Unit 2 low pressure injection cross-train suction relief valves 2LP-195/196
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) (6 Samples)
- (1) PT/0/A/0750/025, "Fuel Assembly Inspection by Canned Sipping," following indications of fuel leakage during Unit 3 maintenance outage, on July 24, 2024
- (2) PT/0/A/0400/005, "[Standby Shutdown Facility (SSF)] Auxiliary Service Water Pump Test," following preventative maintenance on electrical relays and service water components, on July 31, 2024
- (3) OP/0/A/1600/010, "Operation of the SSF Diesel-Generator," following annual maintenance on the diesel engines, on August 1, 2024
- (4) IP/1/A/0315/014 A, "Unit 1 CRD Breaker Test," following breaker replacement due to initial timing test failure, on August 8, 2024
- (5) PT/2/A/0202/011, "Unit 2 B High Pressure Injection Pump Test," following preventative maintenance and lubrication, on September 17, 2024
- (6) PT/1/A/0600/012, "Retest of Turbine Driven Emergency Feedwater Pump," following leakage repair of Unit 1 turbine driven emergency feedwater pump seal pressure regulator valve, on September 18, 2024
Surveillance Testing (IP Section 03.01) (2 Samples)
- (1) PT/1/A/0251/001, "1-2 C Low Pressure Service Water Comprehensive Test," on July 12, 2024
- (2) PT/2/A/2200/003, KHU-2 operability checks following outage for semi-annual inspection and electrical preventative maintenance, on August 6, 2024
Inservice Testing (IST) (IP Section 03.01) (2 Samples)
- (1) PT/0/A/0400/004, SSF Diesel Engine Service Water Pump Test, on July 31, 2024
- (2) PT/0/A/0400/005, SSF Auxiliary Service Water Pump Test, on September 12, 2024
71114.01 - Exercise Evaluation
Inspection Review (IP Section 02.01-02.11) (1 Sample)
- (1) The inspectors evaluated the biennial emergency preparedness exercise during the week of August 19, 2024. The simulated scenario began with a reactor coolant pump shaft shear and subsequent trip. Shortly after, lightning strikes in the switchyard resulted in the inability to power essential transformers with a combination of lockouts and failed open breakers, which also impacted the alternate underground power source. This resulted in the loss of all offsite and all emergency AC power capability and a Site Area Emergency was declared. As the scenario progressed, the 1B steam generator experienced a tube leak. When a chemistry sample indicating dose equivalent iodine sample results were greater than threshold values, a General Emergency was declared which allowed the offsite response organizations to demonstrate the ability to implement emergency actions.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated submitted emergency action level, emergency plan, and emergency plan implementing procedure changes during the week of August 19, 2024. This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (1 Sample)
The inspectors evaluated:
- (1) Simulator drill exercise and performance (DEP) training session using lesson plan ASE-3 on July 23, 2024
71114.08 - Exercise Evaluation - Scenario Review
Inspection Review (IP Section 02.01 - 02.04) (1 Sample)
- (1) The inspectors reviewed and evaluated in-office, the proposed scenario for the biennial emergency plan exercise at least 30 days prior to the day of the exercise.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS06: Emergency AC Power Systems (IP Section 02.05)===
- (1) Unit 1 (July 1, 2023, through June 30, 2024)
- (2) Unit 2 (July 1, 2023, through June 30, 2024)
- (3) Unit 3 (July 1, 2023, through June 30, 2024)
MS09: Residual Heat Removal Systems (IP Section 02.08) (3 Samples)
- (1) Unit 1 (July 1, 2023, through June 30, 2024)
- (2) Unit 2 (July 1, 2023, through June 30, 2024)
- (3) Unit 3 (July 1, 2023, through June 30, 2024)
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (3 Samples)
- (1) Unit 1 (July 1, 2023, through June 30, 2024)
- (2) Unit 2 (July 1, 2023, through June 30, 2024)
- (3) Unit 3 (July 1, 2023, through June 30, 2024)
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) January 1, 2023, through June 30, 2024 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) January 1, 2023, through June 30, 2024 EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)
- (1) January 1, 2023, through June 30, 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:
- (2) NCR 2495187, magnesium Limitorque motor replacement with motor operated valves 2MS-79 and 2MS-76
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) 05000287/2024-001-00, Procedural Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation (ADAMs Accession No. ML24215A408). The inspection conclusions associated with this LER are documented in this report under Inspection Results Section
INSPECTION RESULTS
Failure to Follow Shutdown Procedure Resulted in Inadvertent Automatic Feedwater Isolation System Actuation Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green NCV 05000287/2024003-01 Open/Closed
[H.12] - Avoid Complacency 71153 A self-revealed Green finding and associated non-cited violation (NCV) of Technical Specification 5.4, Procedures, was identified when the licensee failed to properly implement procedure OP/3/A/1102/010, Controlling Procedure for Unit Shutdown, during a planned shutdown on Unit 3 which resulted in the inadvertent actuation of the automatic feedwater isolation system (AFIS). The subsequent level transient in the once-through steam generators (SG) caused an emergency feedwater (EFW) system actuation.
Description:
AFIS is an accident mitigating system designed to provide protection to the plant by monitoring main steam (MS) pressure and sending a signal to automatically secure feedwater flow following a drop in MS pressure below the setpoint of 550 psig. Securing feedwater prevents containment over pressurization following a main steam line break (MSLB) inside containment, and limits SG tube-to-shell differential temperature increase in a faulted SG. AFIS is required to be in operation in Modes 1 and 2 to provide this accident mitigating function. However, during the performance of a unit shutdown, it is necessary to cooldown and depressurize the reactor coolant system (RCS), which necessitates that MS pressure is decreased in a controlled manner. Since this decrease in MS pressure is due to a planned operator action and not a MSLB, disabling AFIS is required to prevent unnecessary loss of main feedwater.
On June 3, 2024, Oconee Nuclear Station Unit 3 was in Mode 3 conducting a shutdown and cooldown for a maintenance outage (O3F32A). At approximately 0047, an AFIS actuation occurred which resulted in a trip of the operating main feedwater (MFW) pump. The resulting SG water level transient caused an EFW actuation due to low SG water level at 0051. Prior to the AFIS actuation, the licensee acknowledged but did not perform procedure OP/3/A/1102/010, step 2.7.4, for disabling AFIS at MS pressure of 625-675 psig. Instead, the licensee prioritized subsequent steps to continue the depressurization of the RCS, and MS pressure decreased, unmonitored, until it passed below the AFIS actuation pressure setpoint of 550 psig. Following the EFW actuation, motor driven EFW pumps 3A and 3B started and supplied feedwater which controlled SG level in band as designed until operators could properly exit emergency response procedures. Operators restored MFW flow at 0411, and continued the shutdown as planned.
Corrective Actions: OP/3/A/1102/010, Controlling Procedure for Unit Shutdown, was revised (07/03/2024, revision 257) to restructure steps and add an additional note for emphasis to ensure AFIS is bypassed in a timely manner.
Corrective Action References: PRR 02520442, NCR 02518069
Performance Assessment:
Performance Deficiency: The inspectors determined that the licensees failure to perform step 2.7.4 of procedure OP/3/A/1102/010 to disable AFIS was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Human Performance 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 caused a SG level transient substantial enough to initiate EFW actuation. This is similar to example 4.b in IMC 0612, Appendix E, Examples of Minor Issues.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Using Exhibit 1, Initiating Events Screening Questions, inspectors determined this finding was of very low safety significance (Green). Specifically, this event did not cause a reactor trip, did not prevent safety systems such as emergency feedwater from operating as designed, and did not prevent main feedwater from being returned to service by the operators.
Cross-Cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Individuals implement appropriate error reduction tools. Specifically, operators and supervisors present in the control room failed to recognize the risk presented by delaying the deactivation of AFIS and failed to adequately prioritize actions to avoid the AFIS actuation or establish a critical parameter to monitor the lowering MS pressure.
Enforcement:
Violation: Oconee Unit 3 Technical Specification 5.4, Procedures, states, in part, that written procedures shall be implemented covering the applicable procedures recommended in Appendix A of Regulatory Guide (RG) 1.33, Quality Assurance Program Requirements (Operation), February 1978. RG 1.33, Appendix A, Paragraph 2, General Plant Operating Procedures, Section i, includes procedures for Plant Shutdown to Hot Standby. The licensee established procedure OP/3/A/1102/010, Controlling Procedure for Unit Shutdown,"
to implement the requirements for commencing plant shutdown to hot standby. Contrary to the above, on June 3, 2024, the licensee failed to implement procedure OP/3/A/1102/010, step 2.7.4, to disable the AFIS system prior to its actuation.
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 October 29, 2024, the inspectors presented the integrated inspection results to Steven Snider and other members of the licensee staff.
- On August 22, 2024, the inspectors presented the emergency preparedness exercise inspection results to Steven Snider and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Risk profile for the week of September 23rd for Units 1, 2
and 3
AD-OP-ONS-0120
Severe Weather Preparations
AP/0/A/1700/006
Natural Disaster
035
Procedures
AP/0/A/2000/001
Keowee Hydro Station - Natural Disaster
009
Drawings
OFD-121D-3.1
Flow Diagram of Emergency Feedwater System
Miscellaneous
OSS_0254.00-00-
1049
(Mech) Design Basis Spec for the Essential Siphon
Vacuum System
015
Work Orders
20563290
Corrective Action
Documents
2517405
CSD-ONS-PFP-
Pre-Fire Plan for U1 Auxiliary Building Elevation 809
000
CSD-ONS-PFP-
Pre-Fire Plan for U1 Auxiliary Building Elevation 822
000
CSD-ONS-PFP-
Pre-Fire Plan for U2 Auxiliary Building Elevation 783
2
CSD-ONS-PFP-
Pre-Fire Plan for U3 Turbine Building Elevation 775
001
Fire Plans
CSD-ONS-PFP-
Pre-Fire Plan for U3 Turbine Building Elevation 796
000
O-0310-FZ-012
Auxiliary Building - Unit 1 Fire Protection Plan Fire Area
and Fire Zone Boundaries Plan at EL 809+3
003
O-0310-K-005
Auxiliary Building Unit 2 Fire Protection Plan & Fire Barrier,
Flood & Pressure Boundaries Plan at EL 783+9
O-0310-K-010
Auxiliary Building Unit 1 Fire Protection Plan & Fire Barrier,
Flood & Pressure Boundaries Plan at EL 809+3
O-0310-K-013
Auxiliary Building Unit 1 Fire Protection Plan & Fire Barrier,
Flood & Pressure Boundaries Plan at EL 822+0 & EL
25+0
Miscellaneous
O-0310-K-014
Auxiliary Building Unit 2 Fire Protection Plan & Fire Barrier,
Flood & Pressure Boundaries Plan at EL 822+0 & EL
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
25+0
O-0310-L-003
Turbine Building Unit 3 Fire Protection Plan & Fire Barrier,
Flood, & Pressure Boundaries Plan at EL 775+0
OFD-124C-1.2
Flow Diagram of High Pressure Service Water System
Turbine Building
AD-FP-ALL-1520
Transient Combustible Control
Procedures
OP/0/A/1106/029 C
Alternate Chilled Water System
23
Work Orders
20668484
OSC -0070
Auxiliary Building Design of Slabs/Beams @elevations
771'+0, 783'+9, 809'+3, 858'+0
Calculations
OSC -10856
PMP Hydraulic Analysis - Local Drainage Basin Surface,
Yard and Roof Drainage
Corrective Action
Documents
24 ARD Return U3 AB roof drains to their as-designed
condition
06/17/2024
O-1030-07-07
Auxiliary Building Architectural Wall Section & Details
O-2412-C
Piping Layout Auxiliary Building Roof Drains Plan
Drawings
O-2412B
Piping Layout Roof Drains Details & Sections
Engineering
Changes
408447
OSS-0254.00-00-
3007
(Civil) Auxiliary Building DBD
OSS-0254.00-00-
4005
Design Basis Specification for Design Basis Events
Miscellaneous
OSS-0254.00-00-
4016
(Civil) Design Basis Specification for Flooding from
External Sources
Procedures
S.D. 3.2.16
Control of Passive Design Features
Miscellaneous
Simulator Exam Guide 2404 (ASE3)
AD-OP-ALL-0106
Conduct of Infrequently Performed Tests or Evolutions
004
AD-OP-ALL-0203
Reactivity Management
016
Procedures
AD-OP-ALL-1000
Conduct of Operations
23
Corrective Action
Documents
21028, 2523154, 2523306, 2526449, 2494408
Drawings
OFD-102A-3.3
Flow Diagram of Low Pressure Injection System (Core
Flood)
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
OSS-0254.00-00-
28
(MECH) Design Basis Spec for the Low Pressure Injection
and Core Flood System (LPI)
070
Miscellaneous
Oss-0254.00-00-
4001
(MECH) Design Basis Spec for Reactor Building
Containment Isolation
046
OM-251.0797.004
I/B - DMV - 1367 & DMV-1385 - 6-inch Seated Butterfly
Valve
D03
PT/1/A/0203/006 B
Low Pressure Injection Pump Test-Decay Heat
031
Procedures
PT/3/A/0151/058
Rev. 011-Penetration 59 Leak Rate Test
011
Work Orders
20678136, 20668054, 20448182, 20678136, 20675159,
20513458, 20568516, 20592909, 20663523, 1866458
Corrective Action
Documents
26323, 2526449
OFD-102A-2.1
Flow Diagram of Low Pressure Injection System Borated
Water Supply and LPI Pump Suction
Drawings
OFD-102A-2.2
Flow Diagram of Low Pressure Injection System LPI Pump
Discharge
Operator Logs for ONS Units 1, 2, and 3 on July 8, 2024
Risk assessments for the week of July 29, 2024, for ONS
Units 1, 2, and 3
Elevated Risk Activity Plan 2024 SSF Annual Outage
Risk assessments for the week of August 5, 2024, for ONS
Unit 2
Risk assessment for the week of August 19, 2024, for ONS
Unit 1
Risk assessment for the week of September 2, 2024, for
ONS Units 1, 2, and 3
Risk assessment for the week of September 9, 2024, for
ONS Unit 2
Risk assessments for the week of July 8th for ONS Units 1,
2, and 3
OSS-0254.00-00-
25
Design Basis Specifications for the Instrument Air System
Miscellaneous
OSS-0254.00-00-
1053
Protected Service Water System
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
OSS-0254.00-00-
2005
(Elect) Keowee Emergency Power Design Basis Document
AD-EC-ALL-0240
Online Risk Management Process
AD-NF-ALL-0501
Electronic Risk Assessment Tool (ERAT)
AD-OP-ALL-0201
Protected Equipment
AD-OP-ALL-0210
Operational Risk Management
AD-WC-ALL-0200
Online Work Management
AD-WC-ALL-0410
Work Activity Integrated Risk Management
IP/2/A/0315/012
TXS RPS Power Range Calibration at Power
OP/0/A/1106/041
Turbine Building Ventilation
OP/0/A/1107/011 D
Removal and restoration of 100KV components
OP/0/A/1600/010
Operation of the SSF Diesel-Generator
101
OP/2/A/1102/004A
ICS Operation
017
Procedures
SD 3.2.16
Control of Passive Design Features
011
Work Orders
20557591, 20598649, 20295961, 20676362, 20685925
OSC-6928
Containment Isolation Single Failure Analysis
004
OSC-7592 02
BS-1&2 Stroke Time and Header Fill Time Calculation
OSC-8592
LPS-1054/1055/1061/1062 Capability Evaluation
OSC-8787
Containment Isolation System Notebook
OSC-9592
Gas-Water Waterhammer Loads in Building Spray Header
(PIP O-08-5705, PDO)
Calculations
OSC-9610
Evaluation of LPI, CF, RBS, & HPI Systems for Generic Letter 2008-01
2
Corrective Action
Documents
20135, 2521546, 1906532, 2521011, 2413191,
2450961, 2521743, 2522001, 2469194, 2521743,
2494408, 2355644, 2327394, 2327551, 2401085,
2514567, 2346040, 1785659, 2520135, 2525104, 2518879
O-1422-H-132
Instrument Details Reactor Building Auxiliary Coolers
LPSW Supply Control Valve 2LPSW-1054
OFD-103A-3.1
Flow Diagram of Reactor Building Spray System (BS)
Drawings
OFD-121D-2.1
Flow Diagram of Emergency Feedwater System
Engineering
Changes
24596
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
OSS-0254.00-00-
1000
(Mech) Design Basis Specification for the Emergency
Feedwater System
059
OSS-0254.00-00-
1034
(MECH) Design Basis Specification for the Reactor Bldg
Spray System
29
OSS-0254.00-00-
1039
(Mech) Design Basis Specification for the Low Pressure
Service Water System
064
Miscellaneous
OSS-0254.00-00-
4001
Design Basis Document for Reactor Building Containment
Isolation
046
AD-EG-ALL-1612
Environmental Qualification (EQ) Program
009
AD-OP-All-0105
AD-PI-ALL-0100
Corrective Action Program
IP/0/A/3012/002
Disconnect and Reconnect of Air Operated Valves
036
IP/0/A/3012/007A
Diagnostic Testing of Air Operated Valves Using
Teledyne/Quiklook System
005
MP/0/A/1100.026
Heat Exchanger - Motor Driven Emergency Feedwater
Pump Cooler Maintenance
009
MP/0/A/1200/032
Valves - Butterfly - Disassembly and Reassembly
039
MP/0/A/1200/032
Valves - Butterfly - Disassembly and Reassembly
040
OP/3/A/1104/005
Reactor Building Spray System
044
PT/2/A/0151/063
Penetration 63 Leak Rate Test
008
PT/3/A/0150/024
Reactor Building Spray System Leakage
015
PT/3/A/0152/002
Building Spray System Valve Stroke Test
034
Procedures
PT/3/A/0203/012
HPI/LPI/RBS Piping Ventilation
018
Work Orders
271110, 20271109, 20271533, 20580165, 20258991,
258852, 20214911, 20521928, 20266999, 20661273,
20583830, 20420226, 20271533
OSC-2754
RCS Wide Range Pressure Instrument loop current
leakage calc
OSC-2820
Emergency Procedure Setpoints
043
OSC-4542
RBS System GL 89-10 Applicability
008
OSC-6210
Rosemount Transmitters QLE
OSC-7480
LPI/HPI Hydraulic Analysis (EOP Bases)
Calculations
OSC-8125
Diverse HPI/LPI actuation system loop uncertainty and
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
setpoint determination
OSC-8829
Digital RPS/ES Wide range RCS pressure instrument loop
uncertainty
Corrective Action
Documents
2520680, 2524513, 2512808, 2517564, 2491967
OEE-259-03
E/D - Reactor Bldg Spray System - RB Spray Pump A
013
OEE-259-04
E/D - Reactor Bldg Spray System - RB Spray Pump B
2
Drawings
OFD-100A-3.1
Flow Diagram of Reactor Coolant System
Engineering
Changes
408734, 414836, 424546
Development of Emergency Action Levels for Non-Passive
Reactors
OSS-0254.00-00-
1000
(MECH) Design Basis Specification for the Emergency
Feedwater System
OSS-0254.00-00-
28
(MECH) Design Basis Spec for the Low Pressure Injection
and Core Flood System (LPI)
070
OSS-0254.00-00-
1034
(MECH) Design Basis Specification for the Reactor Bldg
Spray System
29
Miscellaneous
OSS-0254.00-00-
4001
(MECH) Design Basis Spec for Reactor Building
Containment Isolation
046
AD-EG-All-1132
Preparation and Control of Engineering Changes
AD-OP-ALL-0110
General Equipment Operating Standards
006
EP/2/A/1800/001
0M
Unit 2 EOP Enclosures 5.1-5.10
004
EP/2/A/1800/001
0Q
Unit 2 EOP Enclosures 5.41-5.47
010
IP/0/A/0075/008
Rosemount Pressure Transmitter Assembly, Initial
Calibration, And Mounting Instructions
PT/2/A/0150/067
010
Procedures
PT/2/A/0600/013
Motor Driven Emergency Feedwater Pump Test
077
Work Orders
20173121, 20518868
Calculations
ONTC-1-124A-
U1 and 2 LPSW pump test acceptance criteria
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0001-001
ONTC-1-124A-
0005-001
U1 and 2 LPSW Minimum flow line requirements
ONTC-1-124A-
0006-001
U1 and 2 LPSW pump discharge check valve leakage
OSC-11214
SSF Licensing Summary Documents
005
OSC-5093
SSF Electrical Distribution System Voltage Adequacy and
Fault Study
OSC-8721
Functionality Evaluation of the Areva Vacuum Can Sipping
System for Oconee
Corrective Action
Documents
2518355, 2518557, 1937198, 2049786, 2186961,
2490672, 2523872, 2524055, 2524972
Drawings
OFD-133A-2.5
Flow Diagram of Condenser Circulating Water System SSF
Aux Service
OM-351.0164.001
SSF Diesel Generator Instructions & Parts Manual
054
OSS-0254.00-00-
1005
(MECH) Design Basis Specification for the Standby
Shutdown Facility Auxiliary Service Water System
046
OSS-0254.00-00-
1008
(MECH) Design Basis Specification for the Standby
Shutdown Facility Diesel Support System
053
OSS-0254.00-00-
1043
(Mech) Design Basis Spec for the Keowee Turbine Guide
Bearing Oil (GBO) System
014
OSS-0254.00-00-
1043
(Mech) Design Basis Spec for the Keowee Turbine Guide
Bearing Oil (GBO) System
014
OSS-0254.00-00-
2014
(ELECT) Design Basis Document for the 4160/600/120V
SSF Essential AC Power System
019
Miscellaneous
OSS-0347.00-00-
0001
Safe Shutdown Diesel Electric Generating Unit
005
IP/0/A/2005/004
NEI, PP-EP SVS Static Voltage Regulator Exciter System
018
IP/0/A/4980/051C
ABB/ITE Type 51 Relay Test
045
IP/1/A/0315/014 A
TXS RPS Interposing Relay Test and Control Rod Drive
Breaker Trip Timing Test
018
IP/2/A/4980/050A
Brown Boveri Gr-5 Ground Shield Relay Test
011
MP/0/A/1600/004
Strainer - Zurn - SSF Service Water Maintenance
010
Procedures
MP/0/A/1800/003
Flange - to - Flange Connections
055
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
MP/0/A/5050/032
Diesels - SSF - 12 and 16 Cylinder - Preventive
Maintenance - 2, 4, and 6 Year
047
OP/0/A/1106/019
Keowee Hydro At Oconee
114
OP/0/A/1600/009
SSF Auxiliary Service Water System
039
OP/0/A/1600/010
Operation of the SSF Diesel-Generator
101
OP/0/A/2000/014
KHU-2 Generator
PT/0/A/0400/004
SSF Diesel Engine Service Water Pump Test
041
PT/0/A/0400/005
SSF Auxiliary Service Water Pump Test
070
PT/0/A/0750/023
Fuel Assembly Inspection by In-Mast Sipping
009
PT/0/A/0750/025
Fuel Assembly Inspection by Canned Sipping
001
PT/1/A/0251/001
LPSW Pump Test
114
PT/1/A/0600/012
Turbine Driven Emergency Feedwater Pump Test
108
PT/2/A/0202/011
High Pressure Injection Pump Test
PT/2/A/2200/003
KHU-2 Semi-Annual Surveillance
Work Orders
258991, 20250551, 20579847, 20580352, 20546018,
20573540, 20575868, 20648454, 20583389, 148508701,
20657258, 20685602, 20590405, 20634905
AD-EP-ALL-0104
ERO Common Guidelines and Forms
AD-EP-ALL-0107
Emergency Operations Facility (EOF) Services
AD-EP-ALL-0109
Offsite Protective Action Recommendations
AD-EP-ALL-0111
Control Room Activation of the ERO
AD-EP-ALL-0112
Onsite Protective Measures
AD-EP-ALL-0203
Field Monitoring During Declared Emergency
AD-EP-ALL-0301
Activation of the Emergency Response Organization
Notification System (ERONS)
AD-EP-ALL-0404
Administration of the Emergency Response Data System
(ERDS)
AD-EP-ALL-0406
Duke Emergency Management Network (DEMNET)
AD-EP-ALL-0407
Emergency Operations Facility Surveillance
AD-EP-ALL-0407
Emergency Operations Facility Surveillance
AD-EP-ALL-0500
Emergency Response Training
AD-EP-ALL-0500
Emergency Response Training
Procedures
AD-EP-ALL-0501
Emergency Preparedness Staff Training and Job
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Familiarization
AD-EP-ALL-0902
Offsite Interface
AD-PI-ALL-0100
Corrective Action Program
CSD-EP-ONS-
0101-01
EAL Technical Basis Document
CSD-EP-ONS-
0101-02
AD-EP-ALL-0101
Emergency Classification
Duke Energy Common Emergency Plan
EP-ONS-EPLAN-
ANNEX
Duke Energy Oconee Emergency Plan Annex
HP/0/B/1009/001
Emergency Equipment Inventory And Instrument Check
CSD-EP-ONS-
0101-01
EAL Technical Basis Document
Procedures
CSD-EP-ONS-
0101-02
EAL Wall Chart
Miscellaneous
Simulator Exam Guide 2404 (ASE3)
Procedures
AD-EP-ALL-0801
Design and Development of Drills and Exercises
MSPI Margin and Derivation reports for Emergency AC
Power for October, November and December 2023 for
Units 1, 2 and 3
MSPI Margin and Derivation reports for Residual Heat
Removal for Quarter 3 2023 for Unit 1
MSPI Margin and Derivation reports for Residual Heat
Removal for Quarter 1 2024 for Unit 2
MSPI Margin and Derivation reports for Residual Heat
Removal for Quarter 2 2024 for Unit 3
Duke Energy Oconee Nuclear Station Units 1, 2, and 3
Mitigating Systems Performance Index (MSPI) Basis
Document
Miscellaneous
CP/0/A/2005/022
Determination of Reported Tech Spec Dose Equivalent
71151
Procedures
AD-EP-ALL-0305
Fleet Emergency Preparedness (EP) Alert and Notification
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
21025, 2372374, 2505803, 2508058, 2495187, 2495288
OFD-102A-1.1
Flow Diagram of Low Pressure Injection System (Borated
Water Supply & LPI Pump Suction)
Drawings
OFD-102A-2.1
Flow Diagram of Low Pressure Injection System (Borated
Water Supply & LPI Pump Suction)
Crosby Information Notice 2024-01, May 6, 2024
Duke Metallurgy Report #6429, March 6, 2024
Miscellaneous
OSS-0254.00-00-
28
(Mech) Design Basis Spec for the Low Pressure Injection
and Core Flood System (LPI)
AD-LS-ALL-0018
Evaluating and Reporting Defects and Noncompliance in
Accordance with 10 CFR 21
Procedures
AD-PI-ALL-0106
Cause Investigation Checklists
71152A
Work Orders
20448182, 20668054, 20634548
Corrective Action
Documents
21856
Procedures
OP/3/A/1102/010
Controlling Procedure For Unit Shutdown
257