IR 05000269/2019001

Nuclear Regulatory Commission Integrated Inspection Report 05000269/2019001, 05000270/2019001, 05000287/2019001, and 07200004/2019001

ML19129A068
Person / Time
Site:	Oconee
Issue date:	05/09/2019
From:	Frank Ehrhardt NRC/RGN-II
To:	Burchfield J Duke Energy Corp
References
IR 2019001
Download: ML19129A068 (23)

Text

{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION May 8, 2019

SUBJECT:

OCONEE NUCLEAR STATION - NUCLEAR REGULATORY COMMISSION INTEGRATED INSPECTION REPORT 05000269/2019001, 05000270/2019001, 05000287/2019001, AND 07200004/2019001

Dear Mr. Burchfield:

On March 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Oconee Nuclear Station Units 1, 2, and 3. On April 24, 2019, 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.

The NRC inspectors did not identify any finding or violation of more than minor significance.

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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, /RA/ Frank Ehrhardt, Chief Reactor Projects Branch 1 Division of Reactor Projects Docket Nos.: 50-269, 50-270, 50-287, 72-004 License Nos.: DPR-38, DPR-47, DPR-55, SNM-2503

Enclosure:

IR 5000269/2019001, 5000270/2019001, 05000287/2019001, and 07200004/2019001

Inspection Report

Docket Numbers: 50-269, 50-270, 50-287, 72-004 License Numbers: DPR-38, DPR-47, DPR-55, SNM-2503 Report Numbers: 05000269/2019001, 05000270/2019001, 05000287/2019001, 07200004/2019001 Enterprise Identifier: I-2019-001-0020 Licensee: Duke Energy Carolinas, LLC Facility: Oconee Nuclear Station, Units 1, 2, and 3 Location: Seneca, SC Inspection Dates: January 1, 2019 to March 31, 2019 Inspectors: E. Crowe, Senior Resident Inspector J. Parent, Resident Inspector A. Ruh, Resident Inspector J. Bundy, Operations Engineer P. Capehart, Senior Operations Engineer R. Carrion, Senior Reactor Inspector M. Riley, Reactor Inspector Approved By: F. Ehrhardt, Chief Reactor Projects Branch 1 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance by conducting a quarterly baseline inspection at Oconee Units 1, 2, and 3 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. NRC and self-revealed findings, violations, and additional items are summarized in the table below.

List of Findings and Violations No findings were identified.

Additional Tracking Items Type Issue number Title Report Section Status Unresolved 05000269,05000270, Degraded Voltage 71111.21M Closed Item (URI) 05000287/2014007- Relay Scheme

PLANT STATUS

Unit 1 began the inspection period at 100 percent rated thermal power (RTP). On January 24, 2019, the unit performed a planned power reduction to 24 percent RTP to repair to a heater drain system valve (1HD-30). The unit was returned to 100 percent RTP on January 25, 2019.

On March 3, 2019, the 1A2 feedwater heater developed a minor steam leak and the unit performed an unplanned power reduction to 65 percent RTP to make repairs on March 5, 2019.

The unit was returned to 100 percent RTP on March 6, 2019 and remained at this power level for the remainder of the inspection period.

Unit 2 began the inspection period at 100 percent RTP and remained at this power level for the entire inspection period.

Unit 3 began the inspection period at 100 percent RTP and remained at this power level 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 plant status activities described in IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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.

71111.01 - Adverse Weather Protection Impending Severe Weather Sample (IP Section 03.03)

The inspectors evaluated readiness for impending adverse weather conditions for extreme cold weather on January 24, 2019 through January 30, 2019.

Seasonal Extreme Weather Sample (IP Section 03.02) (1 Sample)

The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following systems: standby shutdown facility (SSF); protected service water (PSW) building; auxiliary building heating and cooling; and turbine building heating and cooling on January 9, 2019, January 10, 2019, and January 17, 2019.

71111.04 - Equipment Alignment Partial Walkdown (IP Section 02.01)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) PSW; 4160 volt safety related electrical distribution system; emergency feedwater system (EFW); SSF; and Lee combustion turbines and associated CT-5 transformer during dual Keowee hydro outage on January 15 - 17, 2019 (installation of anti-rotational device during Keowee hydro Unit 1 stator replacement)

(2) SSF on January 19, 2019

(3) Lee combustion turbines and dedicated AC power path to CT-5 on January 31, 2019

(4) PSW; 4160 volt safety related electrical distribution system, EFW; SSF; and Lee combustion turbines and associated CT-5 transformer during dual Keowee hydro outage on February 6 - 7, 2019 (removal of anti-rotational device during Keowee hydro Unit 1 stator replacement)

(5) 'B' chiller and operating temporary chiller during planned maintenance of the 'A' chiller on March 12 - 14, 2019

(6) Unit 2 low pressure injection (LPI) trains 'A' and 'B' during planned maintenance on the 2C LPI pump on March 13 - 14, 2019

71111.04S - Equipment Alignment Complete Walkdown (IP Section 02.02)

The inspectors evaluated system configurations during a complete walkdown of the PSW system on February 6 and 7, 2019.

71111.05A - Fire Protection (Annual) Annual Inspection (IP Section 03.02)

The inspectors evaluated fire brigade performance on January 22, 2019.

71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Unit 2 auxiliary building elevation 771', fire zone 66 on March 13, 2019

(2) Unit 2 auxiliary building elevation 783', fire zone 83 on March 13, 2019

(3) Unit 1 turbine building elevation 775', fire zone 24 on March 14, 2019

(4) Unit 3 auxiliary building elevation 771', fire zone 60 on March 29, 2019

(5) Unit 3 auxiliary building elevation 783', fire zone 79 on March 29, 2019

71111.06 - Flood Protection Measures Inspection Activities - Internal Flooding (IP Section 02.02a.)

The inspectors evaluated internal flooding mitigation protections in the: Unit 1 turbine building basement during preventive maintenance (PM) on the Unit 1 Presray watertight door on February 4, 2019.

Inspection Activities - Underground Cables (IP Section 02.02c.) (1 Sample) The inspectors evaluated cable submergence protection in: CT-5 cable trench in the west laydown yard (elevation 793') on January 15, 2019 and the CT-5 cable trench west of the old radiation protection building (elevation 791') on January 16, 2019.

71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Requalification Program (IP Section 03.04)

The inspectors reviewed the facility operating history and associated documents in preparation for this inspection. During the week of March 11 - 15, 2019, the inspectors reviewed documentation, interviewed licensee personnel, and observed the administration of operating tests associated with the licensees operator requalification program. Each of the activities performed by the inspectors was done to assess the effectiveness of the facility licensee in implementing requalification requirements identified in 10 CFR Part 55, Operators Licenses. The evaluations were also performed to determine if the licensee effectively implemented operator requalification guidelines established in NUREG-1021, Operator Licensing Examination Standards for Power Reactors, and IP 71111.11, Licensed Operator Requalification Program. The inspectors also evaluated the licensees simulation facility for adequacy for use in operator licensing examinations using ANSI/ANS-3.5-2009, American National Standard for Nuclear Power Plant Simulators for use in Operator Training and Examination. The inspectors observed two crews during the performance of the operating tests. Documentation reviewed included written examinations, job performance measures (JPMs), simulator scenarios, licensee procedures, on-shift records, simulator modification request records, simulator performance test records, operator feedback records, licensed operator qualification records, remediation plans, watchstanding records, license reactivation packages, and medical records. The records were inspected using the criteria listed in IP 71111.11.

Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on March 11, 2019.

Annual Requalification Operating Tests The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.

Administration of an Annual Requalification Operating Test The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.

Requalification Examination Security The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.

Remedial Training and Re-examinations The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.

Operator License Conditions The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.

Control Room Simulator The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.

Problem Identification and Resolution The inspectors evaluated the licensees ability to identify and resolve problems associated with licensed operator performance.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)

The inspectors observed and evaluated licensed operator performance in the control room during the start of 'A' chiller due to the unexpected stopping of the 'B' chiller which resulted in degraded control room area cooling on January 24, 2019. Additionally, the inspectors observed and evaluated licensed operator performance in the control room during a reduction in reactor power from 100 percent RTP to 25 percent RTP on January 24, 2019, in preparation for repair to the 1B first stage reheater drain tank dump valve 1HD-30.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample) The inspectors observed and evaluated operator training on SSF operation following a simulated loss of power and loss of all feedwater on January 15, 2019.

71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) Oconee Nuclear Site elevated green risk during Keowee hydro dewater activities for installation of Keowee hydro Unit 1 anti-rotation device to support stator replacement on January 15 - 17, 2019

(2) Unit 1 elevated green risk associated with emergent work activities associated with valve controller failure for 1-HD-30 on January 24, 2019

(3) Oconee Nuclear Site elevated green risk during Keowee hydro dewater activities for removal of Keowee hydro Unit 1 anti-rotation device to support stator replacement on February 6 - 7, 2019

(4) Oconee Nuclear Site elevated yellow risk during PM activities to 3B circulating water system pump discharge valve 3CCW-11 on February 13, 2019

(5) Oconee Nuclear Site elevated yellow risk during PM activities to 1A circulating water system pump discharge valve 1CCW-10 on March 4, 2019

(6) Emergent work activities associated with 1A2 feedwater heater steam leak on March 4 -

6, 2019

(7) Oconee Nuclear Site elevated yellow risk during PM activities to 2C LPI pump on March 13, 2019

==71111.15 - Operability Determinations and Functionality Assessments Operability Determinations and Functionality Assessments Sample (IP Section 02.01) (7 Samples) The inspectors evaluated the following operability determinations and functionality assessments:

(1) Unit 1 essential siphon system tank minimum flow valve 1ESV-29 failed to cycle during stroke testing of February 13, 2019. (Nuclear Condition Report (NCR) 02257474)

(2) Missing flow restrictor cartridge element in valve 3-LPSW-849 (NCR 2253656)

(3) External grid trouble protection system 230kV red bus Y-phase underfrequency relay failure (NCR 2261061)

(4) Vendor identified failure mode for PSW flow control valves (NCR 2259431)

(5) 1-HP-4 failed to operate from SSF power (NCR 2241697)

(6) Incorrectly configured pipe support on Unit 1 B main steam line (NCR 2238294)

(7) 2A high pressure injection pump motor cooler test failed acceptance criteria (NCR

===2265364)

==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 permanent modifications:

(1) Engineering Change (EC)110240, Alternate Chilled Water System And Procedure Changes Associated With Unanalyzed Effects In Unit 3 Cable Room

(2) EC101838, Replacement of Keowee Unit #1 Generator Stator

71111.19 - Post Maintenance Testing Post Maintenance Test Sample (IP Section 03.01)

[[IP sample::=

=IP 71111.15|count=7}}

The inspectors evaluated the following post maintenance tests:

(1) PT/0/A/0400/005, SSF auxiliary service water pump test following planned mechanical and electrical maintenance on January 10, 2019

(2) PT/0/A/0620/009, operability test of Keowee hydro Unit 2 following restoration from dewatering activity on January 16, 2019

(3) OP/3/A/1104/010, Low Pressure Service Water; Enclosure 4.34, Shutdown and Return to Service of 3B LPSW pump following planned mechanical and electrical maintenance on February 4, 2019

(4) PT/1/A/0203/006A, Low Pressure Injection Pump Test - Recirculation following PM to the 1B LPI pump on February 5, 2019

(5) 3B CCW pump discharge valve (3CCW-11) stroke test following planned electrical and mechanical maintenance on February 8, 2019 (Work Order (WO) 20276508)

(6) PT/1/A/0600/027, PAM Instrument Channel Checks following repairs to 1RIA-58 on March 15, 2019 (WO # 20301820)

(7) MP/0/B/3009/020 C, Motor - Non-QA - Electric - Removal, Replacement, and Post Maintenance Testing following the replacement of the B spent fuel pool pump's motor on March 18, 2019 (WO # 20289815)71111.21M - Design Bases Assurance Inspection (Teams)

The inspectors reviewed URI 05000269, 270, 287/2014007-04, Degraded Voltage Relay Scheme, for closure.

Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (1 Partial)

(1) URI 05000269, 270, 287/2014007-04, Degraded Voltage Relay Scheme

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: In Service Testing (IST) (IP Section 03.01)

(1) PT/2/A/0600/013, Test of the 2B Motor Driven Emergency Feedwater Pump, on January 11, 2019

(2) PT/0/A/0500/001, PSW Primary and Booster Pump Test on February 26, 2019 Surveillance Testing (IP Section 03.01) ===

(1) OP/0/A/1600/010, Operation of the SSF Diesel-Generator, on February 19, 2019.

(2) PT/2/A/0152/002, Building Spray System Valve Stroke Test of 2BS-2, on February 26, 2019

71114.06 - Drill Evaluation Drill and/or Simulator-Based Licensed Operator Requalification Training (IP Section 02.01)

Inspectors observed a simulator-based licensed operator requalification training evolution on March 19, 2019, that involved a small RCS leak that developed into a larger leak, fuel damage and a leak through the containment equipment hatch.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below: IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) ===

Unit 1, 2, 3 (March, 2018 - March, 2019) the inspectors verified licensee performance indicator and submittal for unplanned scrams.

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample) Unit 1, 2, 3 (March, 2018 - March, 2019) the inspectors verified licensee performance indicator and submittal for unplanned power changes per 7000 critical hours.

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample) Unit 1, 2, 3 (March, 2018 - March, 2019) the inspectors verified licensee performance indicator and submittal for unplanned scrams with complications.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL Temporary Instruction 2690/011 - Review of Aging Management Programs at Independent Spent Fuel Storage Installations (ISFSIs) This inspection is a Part 72 inspection. The Inspection Number is 07200004/2019001 and this inspection closes Temporary Instruction 2690/011.

Aging Mgmt at ISFSI (1 Sample)

Temporary Instruction 2690/011 is an information-gathering activity whose results will be used to develop an inspection procedure to address the licensees performance of the AMP activities related to ISFSIs. From January 21 to January 22, 2019, the inspectors evaluated the licensees processes or procedures of the aging management program (AMP) for the ISFSI for adequacy. The inspectors conducted an in-office review of additional information following the inspection. Because Oconee is a pre-SRP (Standard Review Plan) plant, it did not specifically follow the ten elements defined in the AMP as identified in NUREG-1927, Standard Review Plan for Renewal of Specific Licenses and Certificates of Compliance for Dry Storage of Spent Nuclear Fuel, Revision 1.

60855.1 - Operation of an Independent Spent Fuel Storage Installation (ISFSI) at Operating Plants Operation of an ISFSI at Operating Plant

The inspectors evaluated the licensee's independent spent fuel storage installation cask loading of DSC 154 and DSC 155 on January 27 - 31, 2019, and February 19 - 21, 2019, respectively.

INSPECTION RESULTS

Unresolved Item Degraded Voltage Relay Scheme 71111.21M (Closed) 05000269,05000270,05000287/2014007-04

Description:

This URI was opened on June 27, 2014, in NRC Design Bases Assurance Inspection Report 05000269/2014007, 05000270/20140007, and 05000287/2014007 (ADAMS Accession Number: ML14178A535) to determine if a performance deficiency existed with respect to the degraded voltage relay (DVR) protection scheme at Oconee Nuclear Station. During the inspection, the team questioned the DVR protection scheme on the 4.16kv safety buses during normal operation, the licensees use of manual actions during mitigation of degraded voltage conditions, and the setpoints of the loss of power relays not being included in the technical specifications. The team determined that consultation with the Office of Nuclear Reactor Regulation was warranted, and task interface agreement (TIA)2014-04, Request for Technical Assistance Regarding the Adequacy of the Oconee Station Design and Licensing Bases for the Degraded Voltage Relay Protection Design, (ADAMS Accession Number: ML18226A215) was issued to determine if these issues were within the plants current licensing basis. TIA 2014-04 concluded that Oconee Nuclear Stations DVR protection scheme, including the issues described above, was consistent with the plants licensing basis. Therefore, based on the conclusions in the TIA, the team determined that no performance deficiency was identified.

Corrective Action Reference(s): PIP O-14-2034

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• On April 24, 2019, the inspector presented the inspection results to Mr. J. Ed Burchfield, and other members of the licensee staff.

DOCUMENTS REVIEWED

71111.01: Adverse Weather Protection Procedures OMP 2-16, Shift Turnover, Rev. 037 OP/0/A/1104/037, Plant Heating, Rev. 005 OP/0/A/1104/041, Auxiliary Building Ventilation, Rev. 042 OP/0/A/1106/041, Turbine Building Ventilation, Rev. 009 OP/0/A/1600/002, Standby Shutdown Facility Heating, Ventilation and Air Conditioning System Operation (HVAC), Rev. 037 OP/0/B/1104/050, Weather Related Activities, Rev. 005 OP/1/A/1104/051, ESV System, Rev. 028 OP/2/A/1102/020 D, SSF and Outside Rounds, Rev. 089 OP/2/A/1104/051, ESV System, Rev. 040 OP/3/A/1104/051, ESV System, Rev. 028 PT/0/A/0110/017, Cold Weather Protection, Rev. 015 RP/0/A/1000/035, Severe Weather Preparations, Rev. 004 Nuclear Condition Report 229621; 02240341; 02242590; 02247787; 02251763; 02251764; 02253556 Other Clearance: OPS-1 -18-AS -EARLY TAGS -2329 Clearance: PSC-0 -18-PH -PH 251 SPINS-0314 Operators Logs on eSOMS Work Orders/Requests 20118741; 20119309; 20122195; 20124638; 20125908; 20130858; 20130863; 20143662; 243947; 20289421 71111.04: Equipment Alignment Documents OMP 5-05, 100 KV Backup/Emergency Power System, Rev. 002 OSS-0254.00-00-1000, Design Basis Document for Emergency Feedwater and Auxiliary Service Water Systems, Rev. 55 OSS-0254.00-00-1021, Design Basis Document for the Control Room Ventilation System, Rev. OSS-0254.00-00-1053, Design Basis Document for Protected Service Water System, Rev. 2 OSS-0254.00-00-2000, Design Basis Document for 4KV Essential Auxiliary Power System, Rev. 22 OSS-0254.00-00-2004, Design Basis Document for 230KV Switchyard System, Rev. 22 OSS-0254.00-00-2011, Design Basis Document for 100KV Alternate Power System. Rev. 17 OSS-0254.00-00-2014, Design Basis Document for 4160/600/120V SSF Essential AC Power System, Rev. 15 Drawings O-702, One Line Diagram 6900V and 4160V Station Auxiliary System, Rev. 36 O-702-A, One Line Diagram 6900V and 4160V Auxiliary System, Rev. 35 O-702-A2, One Line Diagram 6900V and 4160V Station Auxiliary System, Rev. 18 OFD-102A-2.1, Flow Diagram of Low Pressure Injection System (Borated Water Supply and LPI Pump Suction), Rev. 59 OFD-102A-2.2, Flow Diagram of Low Pressure Injection System (LPI Pump Discharge), Rev. 52 OFD-116J-1.2, Flow Diagram of Control Room Air Condition System, Rev. 15 OFD-116J-1.5, Flow Diagram of Chilled Water System Pumps and Chillers, Rev. 26 OFD-116J-1.6, Flow Diagram of Chilled Water System Chilled Water Supply and Return, Rev. 21 OFD-121D-1.1, Flow Diagram of Emergency Feedwater System, Rev. 38 OFD-121D-2.1, Flow Diagram of Emergency Feedwater System, Rev. 40 OFD-121D-3.1, Flow Diagram of Emergency Feedwater System, Rev. 46 OFD-131A-1.1, Flow Diagram of Protected Service Water System, Rev. 2 OFD-131A-1.2, Flow Diagram of Protected Service Water System, Rev. 1 OFD-131A-2.2, Flow Diagram of Protected Service Water System, Rev. 1 OFD-131A-3.2, Flow Diagram of Protected Service Water System, Rev. 2 OFD-133A-1.1, Flow Diagram of Condenser Cooling Water System (CCW Intake Pump Discharge), Rev. 32 OFD-133A-1.2, Flow Diagram of Normal Intake and Discharge (CCW System), Rev. 25 OFD-133A-2.5, Flow Diagram of Condenser Circulating Water System (SSF Aux. Service), Rev. OFD-133A-2.5, Flow Diagram of Condenser Cooling Water System SSF Auxiliary Service Water, Rev. 66 OM 245-2698.001, NPS 6 (DN 150) Bolted Bonnet Globe Valve (Forged) c/w Gear Operator, Rev. D Other Engineering Change 101838 Procedures LECOP/00/TBD/0007, Lee CT, Rev. 004 OMP 5-05, 100 kV Backup/Emergency Power System, Rev. 2 OP/0/A/1107/003, 100 KV Power Supply, Rev. 097 OP/0/A/1107/003, B, Procedure for Furnishing Power to Oconee, Rev. 15 OP/0/A/1650/001, PSW System, Rev. 4 OP/0/A/1650/002, PSW Ventilation, Rev. 4 OP/0/A/1650/005, PSW AC Power. Rev. 18 OP/0/A/1650/006, PSW DC Power, Rev. 9 OSS-0254.00-00-1053, Design Basis Document for Protected Service Water System, Rev. 2 PT/2/A/0203/006 A, Low Pressure Injection Pump Test - Recirculation, Rev. 087 Work Orders/Requests 261363; 20262803 Condition Report 256635; 2195609; 2259431; 2194263; 2108086; 2229649 71111.05: Fire Protection Calculations OSC-9375, Oconee Fire PRA, Fire Scenario Report, Rev. 007 OSC-9588, Oconee Fire Hazard Ignition Source Tabulation, Rev. 006 Documents AD-EG-ALL-1522, Duties of a Fire Watch, Rev. 8 AD-HU-ALL-0003, Conduct of Pre-Job Briefs and Post-Job Critiques, Rev. 7 AD-OP-ALL-0111, Operations, Communications, Rev. 1 AD-OP-ALL-0207, Fire Brigade Administrative Controls, Rev. 1 AD-PI-ALL-0106, Cause Investigation Checklists, Rev. 3 AD-RP-ALL-6002, Inspections of Self-Contained Breathing Apparatus (SCBA) and Associated Equipment, Rev. 1 AD-TQ-ALL-0086, Fire Brigade and Hazmat Training, Rev. 5 AD-TQ-ALL-0660, Use and Administration of the Nuclear Learning Management System

 (NLMS), Rev. 9

O-FS-0-PA-9000-001, PA Unit 2 Transformers T2, 2T and CT2, Rev. 01 O-FS-1-TB-9775-001, Unit 1 - Turbine Building Elevation 775, Rev. 002 O-FS-2-AB-9771-001, Unit 2 - Auxiliary Building Elevation 771, Rev. 002 O-FS-2-AB-9783-001, Unit 2 - Auxiliary Building Elevation 783, Rev. 002 O-FS-2-TB-9775-001, Unit 2 Turbine Building Elevation 775, 796, 822, & 838, Rev. 001 O-FS-3-AB-9771-001, Unit 3 - Auxiliary Building Elevation 771, Rev. 002 O-FS-3-AB-9783-001, Unit 3 - Auxiliary Building Elevation 783, Rev. 002 OSS-0254.00-00-4008, Design Specification for Fire Protection, Rev. 043 Renewed License No. DPR-47, Renewed Facility Operating License, Amendment No. 363 Selected Licensee Commitments, Revised 11/28/2018 Nuclear Condition Report 251618; 02253705; 02254223; 02254847; 02255541; 02259084; 02261330; 02261333 263477 Other Fire Drill Designator: MCC 2 X-C HS0113-N Initial / HS0116-N Requalification, MSA-SCBA, Advanced Basic Respirator Initial, Rev. 01 Impairment Status Sheet IMP-19-2017 IMP-ON-19-2015 IMP-ON-19-2016 IMP-ON-19-2019 IMP-ONS-19-2018 Procedures MP/0/A/1705/032, Fire Hose Stations - Common Areas - SLC Related - Inspections, Rev. 043 MP/0/A/1705/032 F, Fire Extinguisher Carts - Inspection, Rev. 002 PT/0/A/0250/010 A, Fire Protection Systems Monthly Check, Rev. 081 PT/0/B/2000/050, Fire Drill - Performance and Evaluation, Rev. 003 Work Orders/Requests 20300068; 20312030; 20312031 71111.06: Internal Flood Protection Documents AD-HS-ALL-0110, Electrical Safety, Rev. 11 OSS-0274.00-00-0006, Oconee Electric Component Aging Management Review for License Renewal, Rev. 002 OSS-0274.00-00-0008, Time-Limited Aging Analyses of Electrical Components for License Renewal, Rev. 001 Drawings OM 111.-0223.001, PRSD3BHW Watertight Door, Rev. DI OM 111.-0223.002, Sections A-A & C-C, Rev. DI OM 111.-0223.003, Details 1 & 2, Rev. H OM 111.-0223.004, Details 1A-D, 2A-D & 39, Rev. DI OM 111.-0223.005, Details 12, 13, & 35, Rev. DI OM 111.-0223.006, Details: 3, 4, 24 & 27, Rev. H OM 111.-0223.007, Details 32, 50, 53, 56 & View Z, Rev. DI OM 111.-0223 008, Detail 21, Rev. A OM 111.-0223 009, Jamb Stop, Rev. 0 OM 111.-0223 010, Heavy Duty Hinge Blade, Rev. J OM 111.-0223 012, Cam Plate, Rev. DD Nuclear Condition Report 255726 Procedures MP/0/A/1400/031, Door - Presray Watertight - Preventive Maintenance and Repair, Rev. 016 TE-MN-ALL-0002, Foreign Material Exclusion Level and Controls Screening, Rev. 1 Work Orders/Requests 20133147; 20267448 01; 20302072 01; 20302072 03 71111.11: Licensed Operator Requalification Documents AD-HU-ALL-0003, Conduct of Pre-Job Briefs and Post-Job Critiques, Rev. 5 AD-OP-ALL-0203, Reactivity Management, Rev. 11 AD-OP-ALL-1000, Conduct of Operations, Rev. 13 AD-TQ-ALL-0068, Licensed Operator Continuing Training Program, Rev. 9 AD-TQ-ALL-0230, Licensed Operator Requalification Annual and Biennial Exam Development, Rev. 7 AD-TQ-ALL-0320, Development of Simulator Training and Evaluation Guides, Rev. 4 AD-TQ-ALL-0410, Remediation and Reevaluation, Rev. 5 AD-TQ-ALL-0420, Conduct of Simulator Training and Evaluation, Rev. 14 AD-TQ-ALL-0420, Development and Administration of Job Performance Measures, Rev 1 AD-TQ-ALL-0425, Simulator Scenario Based Testing, Rev. 3 AD-TQ-ALL-0450, Conduct of On-The-Job Training and Task Performance Evaluation, Rev. 4 OP-OC-PSF-091, Simulator Exercise Guide (PSF-091), Rev. 05a Procedures AP/0/A/1700/025, Standby Shutdown Facility Emergency Operating Procedure, Rev. 063 AP/1-2/A/1700/036, Degraded Control Room Area Cooling, Rev. 019 AP/3/A/1700/036, Degraded Control Room Area Cooling, Rev. 009 OP/1/A/1102/004, Operation At Power, Rev. 156 OP/1/A/1106/002 B, FDWPT Operation, Rev. 040 OP/1/A/1106/002 D, HDP Operation, Rev. 015 OP/1/A/1106/014, Moisture Separator Reheater, Rev. 067 OP/1/A/6101/006, Alarm Response Guide 1SA-06, Rev. 045 PT/0/A/0120/033, Time Critical Action Verification, Rev. 077 PT/0/A/1103/020, Power Maneuvering Predictions, Rev. 026 Records License Reactivation Packages (1 Record Reviewed) LORP Training Attendance records (4 Records Reviewed) Medical Files (15 Reviewed) Remedial Training Records (4 Records Reviewed) Remedial Training Examinations (4 Records Reviewed) Written Examinations LOR RO Biennial Week 3 3/15/2019 LOR SRO Biennial Week 3 3/15/2019 Simulator Scenario Based Tests ASE-13, 246, 38, 48, 22, 42 Scenario Packages ASE-02A; ASE-13; ASE-18; ASE-22; ASE-38; ASE-41; ASE-42; ASE-44; ASE-48; ASE-246 JPM Packages ADM-CO-003 ADM-SO-023 AO-500 CO-502A CO-P402B AO-S402 CO-S400A CO-S411A Corrective Action Program Documents Action Request 02259786 Action Request 02259986 Action Request 02259032 Action Request 02259027 71111.13: Risk Assessments Documents AD-EG-ALL-1004, Conduct of Probabilistic Risk Analysis Engineering, Rev. 3 AD-NF-ALL-0501, Electronic Risk Assessment Tool (ERAT), Rev. 3 AD-NF-NGO-0502, Probabilistic Assessment (PRA) Model Technical Adequacy, Rev. 3 OSS-0254.00-00-1000, Design Basis Document for Emergency Feedwater and Auxiliary Service Water Systems, Rev. 55 OSS-0254.00-00-1053, Design Basis Document for Protected Service Water System, Rev. 2 OSS-0254.00-00-2000, Design Basis Document for 4KV Essential Auxiliary Power System, Rev. 22 OSS-0254.00-00-2004, Design Basis Document for 230KV Switchyard System, Rev. 22 OSS-0254.00-00-2011, Design Basis Document for 100KV Alternate Power System. Rev. 17 OSS-0254.00-00-2014, Design Basis Document for 4160/600/120V SSF Essential AC Power System, Rev. 15 Drawings O-702, One Line Diagram 6900V and 4160V Station Auxiliary System, Rev. 36 O-702-A, One Line Diagram 6900V and 4160V Auxiliary System, Rev. 35 O-702-A2, One Line Diagram 6900V and 4160V Station Auxiliary System, Rev. 18 OFD-116J-1.5. Flow Diagram of Chilled Water System Pumps and Chillers, Rev. 26 OFD-121D-1.1, Flow Diagram of Emergency Feedwater System, Rev. 38 OFD-121D-2.1, Flow Diagram of Emergency Feedwater System, Rev. 40 OFD-121D-3.1, Flow Diagram of Emergency Feedwater System, Rev. 46 OFD-131A-1.1, Flow Diagram of Protected Service Water System, Rev. 2 OFD-131A-1.2, Flow Diagram of Protected Service Water System, Rev. 1 OFD-131A-2.2, Flow Diagram of Protected Service Water System, Rev. 1 OFD-131A-3.2, Flow Diagram of Protected Service Water System, Rev. 2 OFD-133A-1.1, Flow Diagram of Condenser Cooling Water System (CCW Intake Pump Discharge), Rev. 32 OFD-133A-1.2, Flow Diagram of Normal Intake and Discharge (CCW System), Rev. 25 OFD-133A-2.5, Flow Diagram of Condenser Cooling Water System SSF Auxiliary Service Water, Rev. 66 Nuclear Condition Report 253284; 2260482 Other Projected ERAT Risk Profile Procedures AD-MN-ALL-0006, Fluid Leak Management, Rev. 1 AD-OP-ALL-0102, Operational Decision Making, Rev. 2 AD-WC-ALL-0390, Unit Threat, Forced Outage, and Downpower Management, Rev. 4 AD-WC-ALL-0410, Work Activity Integrated Risk Management, Rev. 7 AD-WC-ALL-0210, Work Request Initiation, Screening, Prioritization and Classification, Rev. 9 OP/1/A/1106/023, High and Low Pressure Extraction, Rev. 20 OP/1/A/1102/004, Operation At Power, Rev. 156 Work Orders/Requests 262803 71111.15: Operability Evaluations Calculations OSC-8671, Auxiliary Building Flood Design Values, Rev. 7 Documents OSS-0254.00-00-1049, Design Basis Document for Essential Siphon Vacuum System, Rev. 13 Reportability Evaluation, AR 02238294 Piping Analysis Problem 1-01-01, dated 11/27/18 Reportability Evaluation, AR 02238294 Piping Analysis Problem 1-01-02, dated 11/21/18 Reportability Evaluation, AR 02238294 Supports affected by Stress analysis OSC-320, OSC- 21 and OSC-2221, dated 11/27/18 Reportability Evaluation, AR 02238294 Piping Analysis Problem 1-01-15, dated 11/26/18 Vendor Letter, Positioner Failure RMA C-18Z027, dated 2/22/19 Vendor Letter, 10 CFR Part 21 Report: Notification of a Defect with Target Rock Modulating Valve Positioner; Model 810000-X, dated 3/6/19 Drawings OFD-130A-1.1, Flow Diagram of Essential Siphon and Vacuum System, Rev. 8 OM 245.2415.001, Griswold, Automatic Flow Control Valves, Rev. 0 OM 253.0116.001, PSW - Modulating SOV System Calibration Procedure for DMV-1463, Rev. DJ OSS-0251.00-00-0007, Modulating Solenoid Operated Throttle Valves (DMV-1463) for the Protected Service Water System, Rev. 4 OFD-124B-3.6, Flow Diagram of Low Pressure Service Water System (LPSW) Auxiliary Building Air Handling Units, Rev. 26 O-2510B, Piping Layout Miscellaneous Piping Turbine Room Mezzanine Plan, Rev. 22 OEE-265-02, Elementary Diagram Protected Service Water Steam Generator 2A Flow Control MOV 2PSW-22, Rev. 2 OLD-2004-04, 230kV Switchyard External Grid Trouble Protection System and Switchyard Isolated Logic Diagram Channel #2, Rev. 2 OEE-76-2, External Grid Trouble Protection Channel No. 2 Logic Diagram, Rev. 1 OEE-76-8, Elementary Diagram External Grid Trouble Protective System Voltage Channel No. 2, Rev. 9 OEE-76-10, External Grid Trouble Protective System Frequency Channel No. 2, Rev. 7 OEE-48F, Elementary Diagram 230kV Switchyard Control PCB No. 18 Control and Degraded Grid, Rev. 4 OEE-151-1, Elementary Diagram Letdown Cooler 1B Outlet Vlv FS/1/15/4 1HP4 1HP VA0004, Rev. 13 OEE-151-01-0A, Elementary Diagram Letdown Cooler 1B Outlet Vlv 1HP4 (FS/1/15/4) 1HP VA0004, Rev. 4 OEE-163-16, Elementary Diagram Standby Shutdown Facility SSF Control Transfer, Rev. 2 OEE-163-16A, Elementary Diagram Standby Shutdown Facility Ctrl. Trans., Rev. 2 OEE-163-16B, Elementary Diagram Standby Shutdown Facility Control Transfer, Rev. 4 Nuclear Condition Report 238294; 02241697; 02253656; 02257474; 02259431; 02261061; 02265364; 2258827; 1893113 Procedures MP/0/A/1200/189 B, Valve - Target Rock - Modulating Solenoid Operated Globe - Model 09L- 001 - Disassembly, Cleaning, Inspection, and Reassembly, Rev. 9 PT/1/A/0600/024, SSF Comprehensive Control Transfer Verification dated 11/9/18, Rev. 20 PT/1/A/0600/024, SSF Valve Control Transfer Verification dated 11/21/16, Rev. 18 PT/2/A/0230/015, High Pressure Injection Motor Cooler Performance Test, Rev. 42 Work Orders/Requests 20134135 71111.18: Plant Modifications Calculations KC-2005, Pipe Supports on Turbine Generator Cooling Water Discharge Piping. Math Model 1- WL-03 (Civil), Rev. 7 KC-2268, Keowee Stator Project - Main and Neutral Lead Support & Barrier, Rev. 002 OSC-9659, Oconee Nuclear Safety Capability Assessment for Units 1, 2, And 3, Rev. 11 OSC-10969, Mechanical Design input Calculation for the Alternate Chilled Water (AWC) System, Rev. 4 OSC-8671, Auxiliary Building Flood Design Values, Rev. 7 OSC-10790, Oconee Nuclear Station Internal Flooding Analysis, Rev. 3 Documents AD-EG-ALL-1501, Fire Protection Change Process, Rev. 2 Drawings K-0708-A, Interconnection Diagram Generator #1 Supervisory Equipment, Rev. 026 KM 300.--0323.001, Main and Neutral Leads Assembly, Rev. 001 OFD-116Q-1.2, Flow Diagram of Alternate Chilled Water System Auxiliary Building Chiller No. 1 Main Headers, Rev. 14 O-2510L, Piping Layout Miscellaneous Piping Elev. 809+3 - Auxiliary Building - Plan, Rev. 23 Engineering Change 101838, Replace Keowee Unit #1 Generator Stator, Rev. 028 110240, Install Chillers, Auxiliary Skid, and Piping for the Alternate Chilled Water System, Rev. Nuclear Condition Report 254365; 02254442; 02254451; 02254469; 02254702; 02254711; 02254734; 02254911; 254985; 02255290; 02255471; 02255506; 02255513; 02262219; 2261444 Procedures AP/1-2/A/1700/036, Degraded Control Room Area Cooling, Rev. 20 OP/0/A/1106/029C, Alternate Chilled Water System, Rev. 16 TT/0/A/EC101838/001, Keowee Stator Unit 1 Functional Testing, Rev. 004 Work Orders/Requests 227339; 2261518; 2261440; 2261234 71111.19: Post-Maintenance Testing Documents NIPM-QAF-18, Nuclear Inspection Program Manual - QAF-18 Mechanical Inspections, Rev. 005 OSS-0254.00-00-1028, Design Basis Document for Low Pressure Injection and Core Flood, Rev. 55 OSS-0254.00-00-1039, Design Basis Document for Low Pressure Service Water System, Rev. Drawings OFD-102A-1.1, Flow Diagram for Lower Pressure Injection System, Rev. 71 OFD-102A-1.2, Flow Diagram of Low Pressure Injection System, Rev. 61 OFD-124A-3.1, Flow Diagram of Low Pressure Service Water Turbine Building (LPSW Pumps), Rev. 39 Nuclear Condition Report 249362; 02254893 Procedures IP/0/A/3001/001, Limitorque Preventive Maintenance, Rev. 96 MP/0/A/1300/019, Pump - Ingersoll Rand - Type 4X13LP - Spent Fuel Pool Coolant Pump - Disassembly and Reassembly, Rev. 029 MP/0/A/1300/040, Generic - Alignment, Rev. 031 MP/0/B/3009/020 C, Motor - Non-QA - Electric - Removal, Replacement, and Post Maintenance Testing, Rev. 009 OP/3/A/1104/010, Low Pressure Service Water, Rev. 114 PT/0/A/0400/004, SSF Auxiliary Service Water Pump Test, Rev. 69 PT/0/A/0620/009, Keowee Hydro Operation, Rev. 054 PT/1/A/0203/006A, Low Pressure Injection Pump Test - Recirculation, Rev. 92 PT/1/A/0600/027, PAM Instrument Channel Checks, Rev. 038 PT/3/A/0152/006, Condenser Circulating Water System Valve Stroke Test, Rev. 19 Work Orders/Requests 20129619; 2025238201; 20276508; 20301820 71111.22: Surveillance Testing Calculations OSC-9595, Protected Service Water System Hydraulic Model, Rev. 8 OSC-9596, Mechanical Design Input Calculation and System Calculation for the Protected Service Water System, Rev. 11 OSC-9847, Protected Service Water (PSW) Primary Pump and Booster Pump Head Curves, Rev. 3 OSC-9901, PSW Primary Pump Discharge Flow Instrument Uncertainty Calculation, Rev. 3 OSC-9536, Electrical Design Input Calculation for EC91878, Rev. 8 Documents CSD-CP-ALL-0003, Fleet Closed Cooling Water Systems Chemistry Strategic Plan, Rev. 0 Drawings OSS-0254.00-00-1053, Protected Service Water System, Rev. 2 ONTC-0-131A-0003-001, Protected Service Water Booster Pump Test Acceptance Criteria, Rev. 0 ONTC-0-131A-0003-002, Protected Service Water Booster Pump Test Acceptance Criteria, Rev. 0 ONTC-0-131A-0004-001, Protected Service Water Primary Pump Test Acceptance Criteria, Rev. 0 ONTC-0-131A-0004-002, Protected Service Water Primary Pump Test Acceptance Criteria, Rev. 0 Nuclear Condition Report 2173686 Other SSF Diesel Jacket Water Chemistry Sample Results & Trends Sheets SSF Engine Vent Exh. & SSF Online Vent Supply Fan Vibration Data Sheets Procedures CP/0/A/4002/032, Sampling the Closed Cooling Systems, Rev. 013 OP/0/A/1600/010, Operation of the SSF Diesel-Generator, Rev. 095 OP/2/A/1106/006, Emergency FDW System, Rev. 116 PT/0/A/0500/001, Protected Service Water Primary and Booster Pump Test dated February 26, 2019, Rev. 3 PT/0/A/0600/020, Standby Shutdown Facility Instrument Surveillance, Rev. 024 PT/0/A/0600/021, Standby Shutdown Facility Diesel-Generator Operation, Rev. 016 PT/0/A/0600/023, Standby Shutdown Facility Fuel Oil Inventory, Rev. 007 PT/2/A/0152/002, Building Spray System Valve Stroke Test, Rev. 036 PT/2/A/0600/013, Motor Driven Emergency Feedwater Pump Test, Rev. 074 Work Orders/Requests 20134795; 20222213 71114.06: Drill Evaluation Documents Critique Report, Oconee 2017-02 Quarterly Drill, dated 2 May 2017 Critique Report, Oconee 2017-03 Quarterly Drill, dated 22 June 2017 Critique Report, Oconee 2017-Augmentation Drill, dated 24 July, 2017 Critique Report, Oconee 4 February 2019 TSC Table Top Drill, WebEOC Critique Report Critique Report, Oconee 21 January 2019 TSC Table Top Drill, WebEOC Critique Report Critique Report, Oconee 11 February 2019 TSC Table Top Drill, WebEOC Critique Report Critique Report, EPDR-ONS 18TT-1 Critique Report for 12 February 2018 Table Top Drill, dated March, 2018 Critique Report, Oconee 18 February 2019 Drill, WebEOC Critique Report ASE6, Simulator Exercise Guide, Rev. 2 71151: Performance Identification Verification Documents Unit 1 Station Operating Logs covering the period of March 1, 2018 through March 20, 2019 Unit 3 Station Operating Logs covering the period of March 1, 2018 through March 20, 2019 TI 2690/011 Procedures AD-EG-ONS-1214, Condition Monitoring of Structures, Rev. 001 AD-LS-ALL-0006, Notification/Reportability Evaluation, Rev. 1 AD-LS-ALL-0007, Applicability Determination Process, Rev. 5 AD-NF-ALL-0602, Spent Fuel Management and ISFSI, Rev. 2 AD-PI-ALL-0100, Corrective Action Program, Rev. 20 AD-PI-ALL-0400, Operating Experience Program, Rev. 7 CSD-CP-ONS-0001, Oconee Primary Chemistry Strategic Plan, Rev. 004 HP/0/B/1000/054, Radiation Protection Routines, Rev. 049 MP/0/A/1700/010 A, Cask - Spent Fuel - Lifting Equipment (NUTECH) - Inspection and Load Test, Rev. 009 MP/0/A/1700/014, Cask - NUTECH 24P Spent Fuel Transfer - Annual Maintenance, Rev. 006 OP/2/A/1102/020 D, SSF and Outside Rounds, Rev. 089 Corrective Action Documents Action Request (AR) 02249489, Move ISFSI Inspection WO Task from Existing MWO Other Documents Reviewed Duke Energy Carolinas, LLC, Oconee, Independent Spent Fuel Storage Installation Technical Specifications for Materials License SNM-2503, Appendix A, Amendment 9 Duke Energy Carolinas, LLC, Oconee, Independent Spent Fuel Storage Installation Technical Specifications for Environmental Protection, Materials License SNM-2503, Appendix C, Amendment 9 Duke Energy Company, Independent Spent Fuel Storage Facility, Oconee Nuclear Site, Updated Final Safety Analysis Report, Rev. 27 OSC -11057, Independent Spent Fuel Storage Installation 5-yr Civil Inspection, Rev. 001 Work Order Package 20194321 01, U0, Mech PM SF NUTECH 24P Transf Cask Work Order Package 20199663 01, U0 PM All Spent Fuel Yokes and Lifting Adapter 60855.1: Operation of an Independent Spent Fuel Storage Installation at Operating Plants Documents AD-RP-ALL-9001, ALARA Planning, Rev. 4 Amendment Number 13 to COC 1004, Technical Specifications for the Standardized NUHOMS Horizontal Modular Storage System, Rev. 1 Docket No. 72-1004, Final Safety Evaluation Report - Transnuclear, Inc. Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel, Amendment No. 13 NUH-003, Updated Final Safety Analysis Report for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel, Rev. 14 Procedures HP/0/B/1000/097, Radiological Protection Requirements for Independent Spent Fuel Storage Installation, Rev. 018 MP/0/A/1500/024, Independent Spent Fuel Storage Installation Phase VIII DSC Loading and Storage, Rev. 001 MP/0/A/1500/028, Spent Fuel Pool Bridge Operation, Rev. 009 MP/0/A/1500/031, Fuel Assembly/Component Tool Operation, Rev. 008 MP/0/A/1810/019, Cask - Nuhoms 24PTH-S-LC Dry Storage Canister - Welding, Rev. 032 NDE-NE-ALL-2101, Helium Mass Spectrometer Leak Test for Dry Fuel Storage ISFSI, Rev. 1 PT/0/A/0750/003, Physical Inventory of Reportable Special Nuclear Materials, Rev. 024 PT/0/A/1500/001, Independent Spent Fuel Storage Installation Horizontal Storage Module Temperature Rise Verification, Rev. 010 Other Completed Learning Activity Report My Quals VSDS Standard Map Survey Report Oconee Nuclear Station Work Orders/Requests 201571 21| ]]