IR 05000269/2019004

Integrated Inspection Report 05000269/2019004 and 05000270/2019004 and 05000287/2019004

ML20044D438
Person / Time
Site:	Oconee
Issue date:	02/13/2020
From:	Frank Ehrhardt NRC/RGN-II/DRP/RPB1
To:	Burchfield J Duke Energy Carolinas
References
IR 2019004
Download: ML20044D438 (35)

Text

{{#Wiki_filter:ary 12, 2020

SUBJECT:

OCONEE NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000269/2019004 AND 05000270/2019004 AND 05000287/2019004

Dear Mr. Burchfield:

On December 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Oconee Nuclear Station. On January 27, 2020, 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. 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, /RA/ Frank J. Ehrhardt, Chief Reactor Projects Branch 1 Division of Reactor Projects 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: 05000269/2019004, 05000270/2019004 and 05000287/2019004 Enterprise Identifier: I-2019-004-0022 Licensee: Duke Energy Carolinas, LLC Facility: Oconee Nuclear Station Location: Seneca, SC Inspection Dates: October 01, 2019 to December 31, 2019 Inspectors: J. Nadel, Senior Resident Inspector J. Parent, Resident Inspector A. Ruh, Resident Inspector A. Butcavage, Reactor Inspector P. Cooper, Reactor Inspector C. Dykes, Health Physicist M. Meeks, Senior Operations Engineer A. Nielsen, Senior Health Physicist M. Riley, Reactor Inspector J. Rivera, Health Physicist Approved By: Frank J. Ehrhardt, Chief Reactor Projects Branch 1 Division of Reactor Projects Enclosure

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 Verify Adequacy of Reactor Building Cooling Units Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.6] - Design 71111.18 Systems NCV Margins 05000269,05000270,05000287/2019004-01 Open/Closed Inspectors identified a Green, non-cited violation of 10 CFR Part 50, Appendix B, Criterion III, Design Control, when the licensee failed to verify the adequacy of design of the reactor building cooling units (RBCUs). Specifically, safety analysis engineers failed to verify the minimum test acceptance criteria for RBCU capacity remained adequate after modifying the safety analysis.

Additional Tracking Items Type Issue Number Title Report Section Status LER 05000269/2019-002-00 LER 2019-002-00 for 71153 Closed Oconee Nuclear Station, Unit 1, Core Flooding System Loss of Safety Function

PLANT STATUS

Unit 1 operated at or near 100 percent rated thermal power (RTP) for the entire inspection period.

Unit 2 began the inspection period at 100 percent RTP. On November 9, 2019 the unit was shut down for a planned refueling outage. The unit was returned to 100 percent RTP on December 11, 2019 and remained at this power level for the remainder of the inspection period.

Unit 3 operated at or near 100 percent RTP for the entire inspection period.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed 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.

71111.04Q - Equipment Alignment Partial Walkdown Sample (IP Section 03.01)

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

(1) Alternate chilled water system during turbine building heavy lifts over main feeder buses on November 5-7, 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 1 Turbine Building Elevation 796', Fire Zones 34, 34A, 35, 36, and 44 on October 21, 2019

(2) Unit 2 Turbine Building Elevation 822', Fire Zones 40 and 41 on October 24, 2019

(3) Unit 3 Turbine Building Elevation 822', Fire Zones 38, 39, and 39A on October 24, 2019

(4) U2 Reactor Building All Elevations, Fire Zone 123 on December 8, 2019

71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)

(1) The inspectors evaluated pressurized water reactor non-destructive testing by reviewing the following examinations from October 7 - 11, 2019:

1. Ultrasonic Examination (UT)a. UT Examination of Component ID: 2-GRID-001, Containment Liner Plate, (Observed)2. Penetrant Testing (PT)a. Review of Pre-Fab Final PT, Weld ID 171162, Engineering Change No. 402444, Unit-2 Alloy 600 Phase III RCS Hot Leg Pressure Tap Safe End, Final PT Documentation, ASME Class 1, Fillet Weld, Work Order 20083860-03 3. Visual Examination (VT-2)a. VT-2 Leakage Examination, 2-RPV-HEAD-PEN, Reactor Vessel Closure Head, Outer Surface , ASME Class 1 (Reviewed)4. Eddy Current Testing (ET)a. SG 2A- ET for tubes R12C23, R26C3, ASME Class 1 (Observed)b. SG 2B- ET for tubes R131C53, R138C33 & R151C1, ASME Class 1 (Observed) The inspectors evaluated the licensees boric acid corrosion control program performance, through field walk-down inside containment and review of the boric acid program corrective actions and evaluations of reported leakage.

71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance Requalification Examination Results (IP Section 03.03)

(1) Annual Review of Licensee Requalification Examination Results: On July 1, 2019, the licensee completed the comprehensive biennial requalification written examinations and 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 NRCs Operators Licenses. During the week of December 16, 2019, the inspectors 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. These results were compared to the thresholds established in Section 3.02, Requalification Examination Results, of IP 71111.11.

==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 Unit 2 Control Room during reactor coolant system draining to 145" on November 10, 2019.

Licensed Operator Requalification Training/Examinations (IP Section 03.02)==

(1) The inspectors observed and evaluated licensed operators perform table top training on new emergency preparedness procedure AD-EP-ALL-0111, "Control Room Activation of the ERO," Revision 0, on November 20, 2019.

71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness Inspection (IP Section 02.01)

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) Nuclear Condition Report (NCR) 2249515, Standby shutdown facility (SSF) diesel generator (DG) tripped on overcurrent

(2) NCR 2294220, Repetitive processor failures in Unit 3 automatic feedwater isolation system digital channel 1B trip confirm module

(3) NCR 02303769, Blown fuse caused a partial loss of control power to ACB-6, which provides normal auxiliary power to the 2X switchgear for KHU-2

(4) NCR 02295613, B main control room chiller compressor tripped after seizing

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) Risk assessment and work controls for SSF auxiliary service water (ASW) pump oil drain/sample and analysis on October 24, 2019

(2) Risk assessment and work controls for the Unit 2 reactor coolant system (RCS) drain down to 145 inches on November 10, 2019

(3) Risk assessment and work controls for low pressure service water (LPSW) system breach during 2LPSW-1116 replacement on November 16, 2019

71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 02.02)

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Immediate determination of operability (IDO) for NCR 2294192, acceptance criteria for reactor building cooling unit capacities may be non-conservative

(2) IDO for NCR 2286307, discovery of metal chunk foreign material in 3B LPSW min-flow line

(3) IDO for NCR 2300141, main control room envelope door found blocked open

(4) IDO for NCR 02301011, evaluation of a Part 21 for Rotork Valves - failure of the beryllium copper clutch ring in their NA1 actuators manufactured between January 1, 1979 and December 31, 1982

(5) Wall thickness acceptance evaluation for NCR 2302194, ultrasonic readings below recommended minimum thickness on Unit 2 main feed piping in east penetration room

(6) NRC operability review of NCR 02304315, U1/U2 LPSW A & B pumps auto start due to low U1/U2 LPSW header pressure during Unit 2 engineered safeguards (ES) Ch 3 testing

==71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample) The inspectors evaluated the following temporary or permanent modifications:

(1) Change to calculation OSC-8064, Appendix K to credit increased reactor building cooling unit capacities in accident containment analyses for 24 month operating cycles

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

[[IP sample::=

=IP 71111.18|count=5}}

The inspectors evaluated the following post maintenance tests:

(1) Post-modification test of motor operated valve 2RC-219 per PT/2/A/0152/017, "Reactor Coolant System Valve Stroke Test," following implementation of engineering change (EC) 403752 to replace the SSF letdown line on December 2, 2019

(2) Post-modification test of solenoid valve 2RC-223 per PT/2/A/0152/017, "Reactor Coolant System Valve Stroke Test," following implementation of EC 403752 to replace the SSF letdown line on December 2, 2019

(3) Post-modification test of motor operated valve 2RC-218 per PT/2/A/0152/017, "Reactor Coolant System Valve Stroke Test," following implementation of EC 403752 to replace the SSF letdown line on December 6, 2019

(4) Post-modification test PT/2/A/0400/020, "SSF RC Letdown Line Discharge Test,"

following implementation of EC 403752 to replace the SSF letdown line on December 6, 2019

(5) PT/3/A/0203/006 A, "Low Pressure Injection Pump Test - Recirculation," following the removal and reinstallation of the 3A Low Pressure Injection Pump Motor on December 12, 2019

71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01)

(1) The inspectors evaluated U2R29 activities from November 9, 2019 to December 12, 2019.

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Surveillance Tests (other) (IP Section 03.01)

(1) PT/2/A/0203/008, "Component Test of ES Channels 3 & 4," on November 23, 2019

(2) PT/2/A/0610/001 J, "Emergency Power Switching Logic Functional Test," on November 25, 2019

Inservice Testing (IP Section 03.01) (1 Sample)

(1) PT/1/A/0152/013, "Low Pressure Service Water System Valve Stroke Test," on October 23, 2019 Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) PT/2/A/0151/019, "Penetration 19 Leak Rate Test," on December 1,

71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment (IP Section 02.01)

The inspectors evaluated radiological hazards assessments and controls.

(1) The inspectors reviewed the following:

Radiological Surveys

• ONS-M-20190808-8, Independent Spent Fuel Storage Installation, August 8, 2019
• ONS-M-20190913-12, Independent Spent Fuel Storage Installation, September 13, 2019
• ONS-M-20191112-63, Unit 2 Reactor Building 3rd floor, November 12, 2019
• ONS-M-20019116-14, Unit 2 Reactor Building Basement, November 16, 2019
• ONS-M-20191118-4, Unit 2 1st Floor Containment, November 18, 2019
• ONS-M-20191118-3, Unit 2 2nd Floor Containment, November 18, 2019
• ONS-M-20191119-44, Unit 2 Reactor Building Basement, November 19, 2019
• ONS-M-20191119-11, Unit 2 Reactor Building 3rd floor, November 19, 2019 Air Sample Survey Records
• ON19111200063 U2RX HDMOVE #7393...RWP 2158, November 12, 2019
• ON19111900048 U2RB Valve breach 2LP-177 #01201 RWP 2100, November 19, 2019
• ON19111900038 U2RB 2LP-176 Valve Inspection RWP 2100, November 19, 2019
• ON19111900003 U2RX Reactor Head "O" Ring Cut and Removal, November 19, 2019

Instructions to Workers (IP Section 02.02) (1 Sample)

The inspectors evaluated instructions to workers including, labels, radiation work permits and electronic dosimeter alarm setpoints used to access high radiation areas.

(1) The inspectors reviewed the following:

Radiation Work Permits, including RWPs for airborne areas if available

              * # 2216, U2 RXB A/B ROTSG- Set up/Remove/Replace Primary Manway/Handhole Covers, Revision 29
              * # 2221, U2 RXB- A/B ROTSG Tube Plugging/ Stabilization/ Plug Removal, Revision 24
              * # 2069, SSF Let Down Line Replacement, Revision 0 Electronic Alarming Dosimeter Alarms

• RWP #3999, Dose rate setpoint/Dose rate alarm: 25 mrem/hr/57 mrem/hr, April 23, 2018
• RWP #1270, 50 mrem/hr /51 mrem/hr, November 2, 2018 Labeling of Containers
• Auxiliary Building 304
• Refueling Floor by equipment hatch Contamination and Radioactive Material Control (IP Section 02.03) (1 Sample)

The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material. The inspectors verified transactions of nationally tracked sources had been reported.

(1) The inspectors verified the following sealed sources are accounted for and are intact:

• ONS 732, March 1988, 4.0 E+5
• ONS 733, March 1988, 1.3 E+2
• ONS 65, February 1971, 5.00 E+5
• ONS 534, October 1985, 1.00 e+3 Radiological Hazards Control and Work Coverage (IP Section 02.04) (1 Sample)

The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.

(1) The inspectors also reviewed and observed the following risk significant radiological work activities:

• Steam Generator A & B tube plugging/manway removal
• SSF let down line replacement activities
• U2RB 2LP-176 & 177 valve inspection work
• U2 2B1 "J" leg decontamination High Radiation Area and Very High Radiation Area Controls (IP Section 02.05) (1 Sample)

(1) The inspectors evaluated risk-significant high radiation area and very high radiation area controls, including postings and physical controls.

Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 02.06) (1 Sample)

(1) The inspectors evaluated radiation worker awareness and performance and radiation protection technician proficiency.

71124.02 - Occupational ALARA Planning and Controls Radiological Work Planning (IP Section 02.01)

The inspectors evaluated the licensees radiological work planning.

(1) The inspectors reviewed the following activities:

• ALARA Plan 2019-ONS-2-O-006, Safe Shutdown Facility Letdown Line Replacement, Revision 0, Revision 1, Revision 2
• ALARA Plan 2018-ONS-1-O-017, Incore Instrumentation, Revision 0
• ALARA Plan 2019-ONS-2-O-001, Incore Instrumentation, Revision 0 Verification of Dose Estimates and Exposure Tracking Systems (IP Section 02.02) (1 Sample)

The inspectors evaluated dose estimates, exposure tracking and source term reduction effectiveness

(1) The inspectors reviewed the following as low as reasonably achievable planning documents:

• ALARA Critique (Equivalent), 2018-ONS-1-O-017, November 13, 2018
• In-Progress Review (Equivalent), 2019-ONS-2-O-006, 50%, November 15, 2019
• RWP 2069 Special ALARA Committee Meeting Agenda, November 20, 2019
• In-Progress Review (Equivalent), 2019-ONS-2-O-006, 75%, November 24, 2019
• ALARA Critique RWP 2069, December 8, 2019 Implementation of ALARA and Radiological Work Controls (IP Section 02.03) (1 Sample)

The inspectors reviewed as low as reasonably achievable practices and radiological work controls.

(1) The inspectors reviewed the following activities:

• RWP 2069, SSF Letdown Line Replacement Unit 2
• RWP 2221, Steam Generator Tube Plugging

Radiation Worker Performance (IP Section 02.04) (1 Sample)

The inspectors evaluated radiation worker and radiation protection technician performance and implementation of ALARA techniques and controls for work activities during job tasks associated with Unit 2 Refueling Outage 29.

(1) The inspectors reviewed the following:

• Steam generator manway removal/ replacement & tube plugging
• U2RB 2LP-176 & 177 valve work
• SSF letdown line replacement
• 2B "J" leg decontamination

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation Engineering Controls (IP Section 02.01)

The inspectors evaluated equipment used to mitigate and monitor airborne radioactivity and verified licensee has established trigger points for evaluating airborne alpha and beta emitting radionuclides.

(1) The inspectors reviewed the following:

Installed Ventilation Systems

• Unit 1 and Unit 2 Main Control Room Emergency Filtration System Temporary Ventilation System Setups
• Unit 2 Refueling Outage 29 S/G A HEPA Vacuum Portable or Installed Monitoring Systems
• AMS-4 Continuous Air Monitor, Unit 1 and Unit 2 Spent Fuel Pool Use of Respiratory Protection Devices (IP Section 02.02) (1 Sample)

The inspectors evaluated the licensees use and maintenance of respiratory protection equipment. This included review of respirator qualification records and grade D quality supplied air.

(1) The inspectors reviewed the following:

TEDE-ALARA evaluations for the use of respiratory protection equipment

• Unit 2, B Cavity, "J leg decontamination
• Reactor vessel O-ring cut and removal Respiratory protection used during work activities
• Unit 2, B Cavity, "J leg decontamination Periodic Inspection records for staged respirators (ready-for-use)
• October 2019
• November 2019 Self-Contained Breathing Apparatus for Emergency Use (IP Section 02.03) (1 Sample)

The inspectors evaluated the licensees storage and maintenance of SCBA for emergency use. This included a review of SCBA qualification records.

(1) The inspectors reviewed the following:

Periodic Inspection records for staged SCBAs (ready-for-use)

• August 2019
• September 2019 SCBA maintenance records (past 2 years)
• SCBA Enrad # 4214
• SCBA Enrad # 4145

==71124.04 - Occupational Dose Assessment Inspectors evaluated licensee performance with respect to the methods for instrumentation use, monitoring, assessment and assignment for occupational dose.

Source Term Categorization (IP Section 02.01)==

(1) The inspectors evaluated the licensees characterization of the source term and use of scaling factors for the use of hard-to-detect radionuclide activity.

External Dosimetry (IP Section 02.02) (1 Sample)

(1) The inspectors evaluated the external dosimetry program implementation.

Internal Dosimetry (IP Section 02.03) (1 Sample)

The inspectors evaluated the internal dosimetry program implementation.

(1) The inspectors reviewed the following:

Whole Body Counts

• Internally Deposited Beta/Gamma, 1B2 RCP Machining of Flange (Individual 1), October 29, 2018
• Internally Deposited Beta/Gamma, 1B2 RCP Machining of Flange (Individual 2), October 29, 2018
• Facial Particle, U2 Reactor Building Deep End Canal Work, November 27, 2019 In-vitro internal monitoring
• Sample No. 4, Diving Activities, April 30, 2019 Dose assessments performed using air sampling and DAC-hr monitoring
• Sample ON19111900004, U2 Reactor Building Cutting of O-Ring, November 18, 2019

Special Dosimetric Situations (IP Section 02.04) (1 Sample)

The inspectors evaluated licensee methods for assessment of special dosimetric situations such as declared pregnant worker, exposure in nonuniform fields, shallow dose equivalent and neutron exposure.

(1) In addition to DPW records inspectors also reviewed the following:

EDEX exposures

• None were available during this inspection period.

Shallow Dose Equivalent

• None were available during this inspection period.

Neutron Dose Assessment

• Temporary Neutron Exposure Log, DSC159 ISFSI Campaign, July 7, 2019

71124.05 - Radiation Monitoring Instrumentation Walk Downs and Observations (IP Section 02.01)

During plant walkdowns the inspectors evaluated and observed material condition, calibration stickers, and source check status of many portable survey instruments and personnel contamination monitors. Inspectors also observed source check demonstrations on portable instrumentation. Inspectors also evaluated the use of area radiation monitors and continuous air monitors.

(1) Some instruments and records inspectors reviewed included but were not limited to the following:

Personnel contamination monitors, portal monitors and small article monitors

• ARGOS personnel contamination monitors at Turbine Building satellite RCA exit point
• CHRONOS small article monitors at Turbine Building satellite RCA exit point
• GEM-5 portal monitors at Protected Area exit Portable Survey Instruments, ARMS, and Air Samplers/CAMS
• Portable ion chambers
• Portable telescoping GM detectors
• Area Radiation Monitors in Auxiliary Building
• AMS-4 continuous air monitor in U1/U2 spent fuel pool

Calibration and Testing Program (IP Section 02.02) (1 Sample)

The inspectors reviewed the calibration/testing frequency, methods and records for various types of monitoring, survey and analysis instrumentation. Inspectors reviewed results of the Inter-laboratory comparison program.

(1) The inspectors reviewed the following calibration records:

Laboratory Instruments

• Liquid Scintillation Detector # 106756 TR-4, July 1, 2019
• High Purity Germanium Detector # 5, August 26, 2019 Whole Body Counter
• Whole Body Counter # ONSFS1, October 18, 2019 Post-Accident Monitoring Instrumentation
• 1-RIA 57, Containment High Range Radiation Monitor, March 26, 2019
• 1-RIA 58, Containment High Range Radiation Monitor, March 26, 2019 Portal Monitors, Personnel contamination Monitors, and Small Article Monitors
• ARGOS-5ABZ, Enrad ID # 07808, September 16, 2019
• GEM-5, Enrad ID # 03351, September 26, 2019
• Chronos-4, Enrad ID # 12395, September 17, 2019 Portable Survey Instruments, Area Radiation Monitors, and Continuous Airborne Monitors
• Ludlum Model 12-4 (remball), Enrad ID # 02844, January 15, 2019
• Telepole Enrad ID # 02707, March 21, 2019
• 1-RIA 1, Unit 1 and Unit 2 Main Control Room Area Radiation Monitor, September 1, 2019
• Ion chamber, Enrad ID # 11433, September 6, 2019
• AMS-4 Continuous Airborne Monitor Enrad # 10728, October 15, 2019 Electronic Dosimeters
• Dosimeter # A11CAA, August 21,

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 (October 1, 2018 - September 30, 2019)

(2) Unit 2 (October 1, 2018 - September 30, 2019)

(3) Unit 3 (October 1, 2018 - September 30, 2019)

MS09: Residual Heat Removal Systems (IP Section 02.08) (3 Samples)

(1) Unit 1 (October 1, 2018 - September 30, 2019)

(2) Unit 2 (October 1, 2018 - September 30, 2019)

(3) Unit 3 (October 1, 2018 - September 30, 2019)

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) November 2018 - October 2019 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) April 2018 - October 2019

71152 - Problem Identification and Resolution Semiannual Trend Review (IP Section 02.02)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends that might be indicative of a more significant safety issue from July 1, 2019 through December 31, 2019.

Annual Follow-up of Selected Issues (IP Section 02.03) (3 Samples) The inspectors reviewed the licensees implementation of its corrective action program related to the plant modifications in Trench 3 and the protected service water ductbank, the rotork motor operated valve actuators, and the Keowee CX transformer:

(1) NCRs 2203327 and 2282671, corrective actions for NRC violations from report 2018-013 associated with separation of buried cables

(2) NCR 2235278, resolution of NRC identified violation regarding incorrect use of combined qualification for Rotork motor operated valve actuators

(3) NCR 2257729, deferral of planned CX PM and Doble Test following 2018 deferral of CX Doble test. Resulted in a corrective action to replace the CX Transformer ahead of the 2024 planned replacement schedule.

71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 05000269/2019-002-00, Unit 1 Core Flooding System Loss of Safety Function (ML19262H511). The circumstances surrounding this LER are documented in Inspection Report 05000269/2019003 Section

INSPECTION RESULTS

Failure to Verify Adequacy of Reactor Building Cooling Units Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.6] - Design 71111.18 Systems NCV Margins 05000269,05000270,05000287/2019004-01 Open/Closed Inspectors identified a Green, non-cited violation of 10 CFR Part 50, Appendix B, Criterion III, Design Control, when the licensee failed to verify the adequacy of design of the reactor building cooling units (RBCUs). Specifically, safety analysis engineers failed to verify the minimum test acceptance criteria for RBCU capacity remained adequate after modifying the safety analysis.

Description:

On December 15, 2015, safety analysis engineers revised the large break loss of coolant accident long-term containment response calculation, OSC-8064. The purpose of the revision was to show with new, improved reactor building cooling unit (RBCU)performance data, that the existing post-LOCA containment temperature and pressure profiles would remain bounding even after considering the increased decay heat produced by operating the reactor on a 24-month vs. an 18-month cycle. Maintaining the existing profiles was important because the acceptable environmental qualification of post-accident monitoring instrumentation and other electrical components in the reactor building were based on those profiles. In Appendix K of the calculation, safety analysis engineers began using a new, vendor-supplied, performance capability curve for modeling the cooling capacity of the RBCUs.

Although the improved capacity was being used in the safety analysis, the acceptance criteria for routine RBCU performance tests continued to be based on the old curve. Monitoring performance against the old curve was considered appropriate because engineers assumed that a cooling unit performing at the old curve would, under the new external conditions, also perform at the new, improved curve. Engineers made this assumption because they considered the two curves to be representative of the capacity of the same physical cooling unit with just the external conditions being changed. Inspectors identified that this assumption was incorrect because the two curves made different assumptions about the cooling units internal fouling.

On September 26, 2019, inspectors identified that when engineers began using the new, improved capacity curve, they failed to recognize that most of the improvement was due to a difference in the assumed fouling factor between the new and old curves. The old curve was based on a 0.0005 (hr-ft2-°F/BTU) fouling factor, but the new curve was based on zero fouling. Removing the fouling factor accounted for approximately 75 percent of the improvement gain in the new capacity curve. The remaining 25 percent improvement was due to the curve being generated from reactor building environmental conditions that more closely resembled the safety analysis initial conditions. As a result, a cooling unit operating at the old curve would only be operating at approximately 83 percent of what was assumed in the safety analysis.

Once the performance test acceptance criteria were recognized to be non-conservative, operators reviewed the most recent actual performance data for the three RBCUs on each unit to verify that the safety analysis could still be satisfied. For Unit 1 the available operating margin was reduced from 77 percent to 47 percent. For Unit 2 the available operating margin was reduced from 19 percent to -0.8 percent. For Unit 3 the available operating margin was reduced from 39 percent to 16 percent. The available margin is routinely monitored during plant operation because it declines over time due to tube-side fouling from the low pressure service water system. To support continued operability on Unit 2 until the planned refueling outage in November 2019, engineers demonstrated in an immediate determination of operability that the existing post-loss-of-coolant accident (LOCA) containment temperature and pressure profiles would be maintained if the assumed low pressure service water temperature was reduced from 90 degrees Fahrenheit to 85 degrees. This was reasonable because the lake temperature had already peaked for the season at 83 degrees. About two weeks later, a prompt determination of operability demonstrated an alternate approach by re-performing the safety analyses with a 20 percent reduction in assumed RBCU capacity, and showing that the post-LOCA containment temperature profile would generally be elevated by 10°F, but the limiting reactor building electrical equipment would remain environmentally qualified and operable.

Corrective Actions: The licensee revised the safety analysis to reflect the expected minimum RBCU capacity, issued a human performance crew learning communication to the safety analysis group, and initiated action to procure additional RBCU data from the vendor to validate assumptions.

Corrective Action References: NCR 2294192

Performance Assessment:

Performance Deficiency: The failure to verify the adequacy of design of the RBCUs per 10 CFR Part 50, Appendix B, Criterion III, was a performance deficiency. Specifically, safety analysis engineers failed to verify the minimum test acceptance criteria for RBCU capacity remained adequate after modifying the safety analysis.

Screening: The inspectors determined the performance deficiency was more than minor because if left uncorrected, it would have the potential to lead to a more significant safety concern. Specifically, the non-conservative acceptance criteria could have reasonably resulted in unintended operation outside of the safety analyses because expected higher fouling over time could have reduced margin to the point where the safety analyses were no longer bounding.

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Using Exhibit 2, Mitigating Systems Screening Questions, inspectors determined the finding was of very low safety significance (Green) because it was a deficiency affecting the design of the RBCUs, and qualification of reactor building electrical equipment, but they maintained their operability.

Cross-Cutting Aspect: H.6 - Design Margins: The organization operates and maintains equipment within design margins. Margins are carefully guarded and changed only through a systematic and rigorous process. Special attention is placed on maintaining fission product barriers, defense-in-depth, and safety related equipment. In this case, a change was made to a design calculation that involved items outside the expertise of the originator (i.e.

fouling). Applying special attention and rigor such as obtaining additional reviews from subject matter experts or the vendor may have prevented the error. Although the original deficiency was introduced more than the nominal three-year period typically associated with present performance, the cross-cutting aspect was assigned because, in April 2019, safety analysis engineers re-validated the existing methodology after it was questioned by site engineering.

Enforcement:

Violation: 10 CFR Part 50, Appendix B, Criterion III required, in part, that design control measures shall provide for checking the adequacy of design, such as by the performance of design reviews. Contrary to the above, since December 15, 2015, the design review performed for large break loss of coolant accident long-term containment response did not verify the adequacy of design of the RBCUs. Specifically, safety analysis engineers failed to verify the minimum test acceptance criteria for RBCU capacity remained adequate after modifying the safety analysis.

Enforcement Action: This violation is being treated as an 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 December 12, 2019, the inspectors presented the Radiation Protection Baseline Inspection inspection results to Ed Burchfield, Site Vice President and other members of the licensee staff.
• On January 27, 2020, the inspectors presented the integrated inspection results to J. Ed Burchfield and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or Procedure Date 71111.04Q Calculations OSC-10963 Electrical Design Input Calculation for Engineering Change 0 110408 OSC-10969 Mechanical Design input Calculation for the Alternate 4 Chilled Water (AWC) System OSC-7934 Auxiliary Building GOTHIC Heat Up Analysis - PSW Event 11 Cases OSC-9659-ICC- NFPA 805 Impacts due to AWC Manual Valve Position 0 0004 Changes Corrective Action 2286301, 20153797, 2276864, 1854557, 1857675, Documents 2277519, 2278566, 2296376, 2298512, 2167815 Drawings O-6708 One Line Diagram Alternate Chill Water (AWC) 4160/600V 3 System O-6708-A One Line Diagram Alternate Chill Water (AWC) 600/208V 5 System O-6708-B One Line Diagram Alternate Chill Water (AWC) 600/208V 1 System OFD-116Q-1.1 Flow Diagram of AWC System Yard Chillers and Auxiliary 7 Skids OFD-116Q-1.2 Flow Diagram of AWC System Auxiliary Building Chiller 14 No.1 Main Headers OFD-116Q-1.3 Flow Diagram of AWC System Auxiliary Building Chiller 6 No.2 Main Headers OFD-116Q-1.4 Flow Diagram of AWC System Auxiliary Building Cable 2 Rooms OFD-126C-1.1 Flow Diagram of Drinking Water System (Drinking Wtr. 20 Make-up Service Building) OFD-126C-1.2 Flow Diagram of Plant Drinking Water System (Turbine 25 Bldg., Admin. Bldg., IRW Facility, & QA Radiographic Facility Supply) Procedures AM/0/A/3007/066 Abnormal Procedure for Installation and Removal of RBCU 4 Inspection Type Designation Description or Title Revision or Procedure Date Hale Pumps and Hoses AM/0/A/3007/085 Abnormal Procedure for Installation and Removal of Unit 1 1 and 2 Cable Room AWC Coolers AM/0/A/3007/086 Abnormal Procedure for Installation and Removal of 2 Nitrogen System for Auxiliary Building Air Handling Units and Exhaust Fan Damper Control During AWC Operation AM/0/A/3007/087 Abnormal Procedure for Installation and Removal of AWC - 1 Trane 500-Ton Model RTAC Chiller Make-up Water AP/1- Degraded Control Room Area Cooling 20 2/A/1700/036 OP/0/A/1106/029 Alternate Chilled Water System 18 C 71111.05Q Calculations OSC-10731 Fire PRA Input to the ONS NRPA 805 Monitoring Program 003 OSC-9314 NFPA 805 Transition Risk-Informed, Performance-Based 006 Fire Risk Evaluation OSC-9378 ONS Fire PRA (FPRA) Summary Report 004 OSC-9659 Oconee Nuclear Safety Capability Assessment for Units 1, 011 2, and 3 Drawings O-0756-M Fire Detection System Detector Tabulation 021 Fire Plans CSD-ONS-FS-020 Standard Operating Guide Key Equipment List by Fire Zone 0 CSD-ONS-PFP- Pre-Fire Plan for U1 Turbine Building Elevation 796 0 1TB-0796 CSD-ONS-PFP- Pre-Fire Plan for U2 Reactor Building All Elevations 0 2RB CSD-ONS-PFP- Pre-Fire Plan for U2 Turbine Building Elevation 822 0 2TB-0822 CSD-ONS-PFP- Pre-Fire Plan for U3 Turbine Building Elevation 822 0 3TB-0822 71111.08P Calculations NS-TECR-102658 Oconee Mathematically Calculated Calibration Curve Rev. 001 Calibration MIZ-80 166, 526480, 540464, 542183, 542555, 544984, 648200, Records 648202, 649080, 649081, 654402, 654403, 654404 Probes 11342, 12024, 14379, 23627, 24010, 24058, 24654, 25921 S000001-07- Mechanical Rolled Tube Plug & Stabilizer Installation Field Rev. 13 Inspection Type Designation Description or Title Revision or Procedure Date 000015 Procedure for Replacement Once Through Steam Generators Corrective Action A/R # 02294252 2HP-123 Boron Leak Containment Isolation Valve 9/27/19 Documents ACTION NCR - ISI Visual Examination of 2-RPV-HEAD-PEN 11/17/19 REQUEST - 2302962 AR-02171026 Active Boric Acid Leak from Valve 2HP-110 12/10/17 AR-02173332 2C-HPI Pump Shaft has Active Boron Leak 12/20/17 AR-02302078 ISI Visual Examination of Component 2-SCV-011, 11/16/19 Containment Liner NCR 02294245 Boric Acid Corrosion Evaluation 10/24/19 Corrective Action NCR-02302449 BORON OBSERVED IN PRESSURIZER HEATER PLUGS 11/14/19 Documents NCR-02302598 Safety Concern - Fall Protection 11/14/19 Resulting from WO 20158328 Clean (Boric Acid ) Stains on Underside of Grating Below 2B 11/9/19 Inspection Hot Leg Elbow, Considerable deposits on the underside of grating, below the pressurizer surge line where the hot leg comes out. WO 20158790 Boron Observed on Pressurizer Heater Sleeves 11/13/19 Drawings 0-ISIC2-1062- Oconee Unit-2, Containment Liner Plate, In-service Rev. 2 0010 Inspection Areas, Developed Elevation, Sht. 2 0-ISIC2-1962-009 Oconne Unit-2, Containment line Plate, In-service Inspection Rev. 2 Areas, Developed Elevation, Sht. 1 28719E B&W Reactor Vessel Radio-graphic Outline and Weld Rev. 3 Identifiers 149766E Pressurizer Heater Bundle Assembly and Details Rev. 8 151991 E Arrangement Reactor Vessel Longitudinal Section Rev. 14 5059428B BWI Replacement OTSG EDM/ASME/WEAR Array Rev. 0 Calibration Standard O-1479 A Oconee U-2, Piping Layout, Ground Floor Plan, Reactor Rev. 55 Building OM 1201.- Arrangement Reactor Vessel Long Section Rev.14 1538.001

                            (151991-E)

Engineering 0300-TECR- Condition Monitoring and Preliminary Operational Rev. 0 Inspection Type Designation Description or Title Revision or Procedure Date Evaluations 104094 Assessment for Oconee-2 O2R29 Outage 3011-AST-101520 Steam Generator Condition Monitoring and Final Rev. 0 Operational Assessment for Oconee-2 O2R28 Outage AD-EG-PWR- Steam Generator Degradation Assessment Rev. 0 1813 AR-02294252 Valve 2HP-123 9/27/19 Boric Acid Evaluation NCR-02171026, Evaluation of Active Boric Acid Leak at Valve 2HP-VA-110 1/10/18 Boric Acid Corrosion Evaluation Oconee Unit-2, Collective Significance Review for Leakage 2/27/19 Cycle 29 Miscellaneous Badge # 285307 Duke Energy, NDE Examiner Certification Review 9/5/19 Badge # 463070 Duke Energy, NDE Examiner Certification Review 9/10/19 Badge #224415 Duke Energy, NDE Examiner Certification Review 9/9/19 Badge #472208 Duke Energy, NDE Examiner Certification Review 9/5/19 C-Q-02.04-F02 Training Attendance Roster O2R29 GTOO0808-04 ASME Section XI, Welding Procedure Specification Rev. 4 Technical Sheet NIS 2-A (Work Owners Certificate of Conformance for Repair Replacement 1/17/18 Order 20083860 Plan 20083860-03 Oconee UFSAR Design of Structures 12/31/17 Section 3.8 Oconee Unit-2 Integrated Leakage Rate Test Report 12/7/2015 Doc. ID 2015-85 Personnel

J. Baumann,

S. Merriam,

T. Thulien,

Qualifications ST3118 Oconee WO 20218685 Completion Information 11/19/19 Completion Information Visual Acuity

S. Merriam,

T. Thulien,

NDE Reports UT-19-010 System ID: CONT (Containment Liner Plate), Component 11/16/19 Inspection Type Designation Description or Title Revision or Procedure Date ID: 2-GRID-001, Ultrasonic Examination Report IAW, Procedure NDE-NE-ALL-6401 gRID-001 VT-17-107 Visual Examination for Boric Acid Detection, RPV Bottom 1/25/18 Head BMI Nozzles VT-19-076 System ID: CONT (Containment), Component ID: 2-SCV- 11/14/19 011, Report of Visual Examination of IWE Surfaces (VT-1) VT-19-110 Component ID, 2-RPV-HEAD-PEN, Reactor Pressure 11/22/19 Vessel Outer Head Surface -Visual Examination Procedures 0300-PLAN- ROTSG ECT Inspection Plan Rev. 1 103523 8-QPP-761 Multifrequency Eddy Current Examination of Steam Rev. 8 Generator Tubing ETSS 13091.2, 27091.2, 96042.1, 96043.4 NDE-NE-ALL- Utilization of PDI-UT-2 Generic Procedure for the Ultrasonic, Rev. 002 6102 Examination of Austenitic Pipe Welds NDE-NE-ALL- Straight Beam Ultrasonic Examination Rev. 000 6403 NDE-NE-ALL- Visual Examination of IWE Components Rev. 1 7402 NDE-NE-ONS- Eddy Current Guidelines for Oconee Nuclear Station's Rev. 2 0131 Replacement Once-Through Steam Generators NDE-NE-ONS- ROTSG Site Technique Validation for Oconee Nuclear Rev. 2 0132 Station O-ISISG- Fifth Interval Steam Generator Inservice Inspection Plan Rev. 1 0169.030.0050 S000001-07- Mechanical Rolled Tube Plug & Stabilizer Installation Field Rev. 13 000015 Procedure for Replacement Once Through Steam Generators Work Orders 20154083 2HP-123 Boron Leak- Containment Isolation 9/27/19 WO 20083860 Oconee Unit-2 Alloy 600 Phase III, RCS Hot Leg Pressure 1/17/18 Inspection Type Designation Description or Title Revision or Procedure Date Tap Safe End, Weld Pre-Fab of Instrument Valves, for Outage 02R28 WO 20158781 2HP-348 has 1/4 TSP. DRY BORON on PIPE CAP 11/13/19 WO 20303980 Oconee Unit-2, Engineer (Mode 3) Reactor Bldg. Boric Acid 11/9/19 Leak Inspection WO-20218685 Active Boron Leak From Valve 2HP-110 11/26/19 WR 20092675 Active Boron Leak from Valve 2HP-110 12/10/17 WR-20158781 2HP-348 Has 1/4 TSP Dry Boron on Cap 11/13/19 71111.11Q Procedures OP/0/A/1102/026 Operations IPTE Pre-Job Briefings 031 OP/2/A/1103/011 Draining and Nitrogen Purging RCS 101 71111.12 Corrective Action 2200104, 2249753, 1845371, 1773940, 1761628, 2290674, Documents 2291819, 2294220, 2291906, 2292616, 2298746, 2298508, 295613, 02296687, 02303769, 02299588 Drawings K-0700 One Line Diagram Relays & Meters 13.8-230kV 44 OEE-345-105 Elementary Diagram AFIS Analog Inputs to Digital Channel 1 Trip Confirm (Blue) OM 2311.D- Oconee Unit 3 AFIS - STAR Trip Confirm Dig. CH 1 & 2 D1 21.001 15V DC Distribution OM 351-0272.001 Circuit Board Assembly A OM 351-0274.001 Final Assembly - Regulator A OM 351-0275.001 Schematic - Remote S.V.S Regulator 3-phase with A Paralleling Miscellaneous Maintenance Rule (a)(1) evaluation for NCR 2292616 Maintenance Rule Expert Panel Meeting Minutes dated November 7, 2019 Equipment Reliability Suite, MRule - Function Scoping software Oconee OAC eSOMS - Operator Logs Regulatory Guide 1.160 - Monitoring the Effectiveness of 4 Maintenance at Nuclear Power Plants Inspection Type Designation Description or Title Revision or Procedure Date 8003189-AFIR-1 As-Found Inspection Report for Automatic Voltage 0 Regulator, Repair and Return OM 2201.C- STAR System Instruction Manual D07 28.001 OM 351-0164.002 SSF Diesel Generator Instructions and Parts Manual 31 OSS-0254.00-00- (ELEC) Automatic Feedwater Isolation System 7 26 Procedures AD-EG-ALL-1210 Maintenance Rule Program 1 AD-EG-ALL-1311 Failure Investigation Process (FIP) 1 IP/0/A/2005/004 NEI, PP-EP SVS Static Voltage Regulator Exciter System 16 IP/0/A/2005/004 A SSF Diesel Generator Automatic Voltage Regulator Bench 0 Test Work Orders 20208499, 2083722, 20201615, 20208939, 20357208, 20154895, 20157106 71111.13 Drawings OFD-124B-2.1 Flow Diagram of Low Pressure Service Water System 77

                                          (Auxiliary Building Services)

OFD-133A-2.5 Flow Diagram of Condenser Circulating Water System (SSF 61 AUX. Service) OM 245.- Velan Bolted Cover Swing Check Valve (Cast) 1 28.001 Miscellaneous Complex Activity Plan for 2LPSW-1116 during O2R29 0 and 1 O2R29 Shutdown Safety Overview - Outage Defense in Effect Oconee U2, O2R29 Summary Schedule, IRT September 9, 2019 Procedures MP/0/A/1200/108 Valve-Removal and Installation of Flanged Valves or Wafer 66 Valves to Piping MP/0/A/1840/040 Pumps - Motors - Miscellaneous Components - Lubrication 039

                                          - Oil Sampling - Oil Change

OP/0/A/1102/026 Operations IPTE Pre-Job Briefings 031 Inspection Type Designation Description or Title Revision or Procedure Date OP/2/A/1103/011 Draining and Nitrogen Purging RCS 101 Site Directive Shutdown Protection Plan 39 1.3.5 Work Orders 20137409, 20352487 71111.15 Calculations OSC-5649 LPSW Test Acceptance Criteria (TAC) 19 Corrective Action 2292821, 2286307, 02304315, 02293695, 02301011 Documents Drawings 18ALV500X11 ALV Pump B OFD-124A-3.1 Flow Diagram of Low Pressure Service Water System 39 Turbine Building OM 1240-002 Instruction Manual Operation-Maintenance Instructions and 1 Parts Catalog for Automatic Pipeline Strainer Model No. 590

                                            & 592

OM 208-0064.001 Service Water Pump Installation Manual 0 OM 240-002 Zurn Strain-O-Matic Model 67 Automatic Self-Cleaning 0 Strainer with Exclusive Lin-A-Flo Design OM 245-617 Chart of List 1233 F.E. Tilting Disc Check Valves with 0 Flexitallic Gasket ONTC-3-124A- Unit 3 LPSW Pump Discharge Check Valve Leakage Test 0 0006-001 Acceptance Criteria OSC-10448 Environmental Qualification Evaluation for Oconee Reactor 1 Building Water Level Transmitters and Supporting Equipment OSC-2784 Oconee Fouled Coolers / High Lake Temperature 6 Equipment Qualification Evaluation Miscellaneous Results / Erosion / Corrosion Wall Thickness Acceptance Evaluation for locations 2-FDW60-A & 2-03-18-25 UT Erosion/Corrosion Examination Summary No. O2-05927, O2-05930 Licensees Logs via eSOMS Oconee OAC SDS ASME OM Code- Code for Operation and Maintenance of Nuclear Power Inspection Type Designation Description or Title Revision or Procedure Date 2004 Plants OSS-0254.00-00- (Mech) Design Basis Specification for Standby Shutdown 056 1004 Facility Reactor Coolant Makeup System OSS-0254.00-00- (Mech) Design Basis Spec for the Low Pressure Injection 059 28 and Core Flood System (LPI) Procedures AP/1/A/1700/024 Loss of LPSW 028 MP/0/A/1600/031 Strainer - Zurn - LPSW Pump Maintenance 5 PT/0/0160/006 Reactor Building Cooling Units Performance Test performed 42 March 11, 2019 PT/2/A/0160/002 Reactor Building Cooling Unit Air Flow Test performed 12 November 16, 2017 PT/2/A/0203/008 Component Test of ES Channels 3 & 4 025 Work Orders 20346861, 2142983, 20304470 71111.18 Calculations OSC-10511 LPSW Flow to RBCUs for Environmental Qualification 0 Purposes OSC-5666 Reactor Building Cooling Unit Performance Test - Unit 2 67, 68 OSC-5667 Reactor Building Cooling Unit Performance Test - Unit 3 72 OSC-6146 Post-LOCA Reactor Bldg Cooling Unit Capacity 2 OSC-8064 ROTSG Long-Term Containment Response Following a 16 Large Break LOCA Corrective Action 2294192, 1905036 Documents Engineering 110165 Revise TAC Sheets for setpoints of LPSW pressure 0 Changes switches and LPSW pump TAC sheets ONTC-1-12 Miscellaneous ONEI-0400-400 Oconee Nuclear Station Revised RBCU Requirements in 0 Support of 1-Year Mission Times 71111.19 Calculations OSC-10826 SSF Letdown Flow Instrumentation Loop Uncertainty, 1/2/3 RC FE0016 OSC-11212 SSF RC Letdown Line Valve Data Sheet Calculation (RC- 3 218, RC-219, RC-223) OSC-5675 Generic Letter 89-10 Calculation for Unit 2 Gate and Globe 39 Inspection Type Designation Description or Title Revision or Procedure Date Valves OSC-7184 Generic Letter 89-10 MOV Calculation for Units 1,2, 3 Gate 5 and Globe Valves at Oconee Corrective Action 2304894 Documents Drawings O-1721-C RC Makeup & Letdown and High Pressure Injection & 12D Purification System OFD-101A-2.5 Flow Diagram of High Pressure Injection System (SSF 23 Portion) OFD-102A-2.1 Flow Diagram of Low Pressure Injection System (Borated 60 Water Supply And LPI Pump Suction) OFD-104A-1.1 Flow Diagram of Spent Fuel Cooling System 64 OFD-107A-2.1 Flow Diagram of Coolant Storage System Quench Tank 15 Portion OM 245.- DMV-2184, 2.5 Class 2500 SD Valve, BW Ends, with 2 2830.001 Rotork 25NET1 Electric Actuator OM 253.- Solenoid Operated Valve Energize to Open (FC) On/Off 2.5- 2 23.001 inch BW ONTC-2-101A- Unit 2 SSF RC Letdown Line Performance Test 2 25 Engineering EC403752 Modify U2 SSF RCS Letdown Line to Support SSF 15 Changes Operability in All Modes of Operation Miscellaneous EC403752 Post-Modification Test Exceptions Management November Review 14, 2018 OM 245.- NIB - Flow Test Two SPX Flow Copes-Vulcan 2.5-inch 0 2830.003 Class 2500# Severe Duty Control Valves (DMV-2184 & DMV-2198) OM 245.- NIIB - (DMV-2184 & DMV-2198) Weak Link Report with 0 2830.005 Seismic Acceleration & Fatigue Life 2.5 Class 2500 OM 245.- I/B - DMV-2184 & DMV-2198 25NET Hand/Auto Lever 1 2830.020 Upgrade Instructions Procedures IP/0/A/3001/011 L Diagnostic Testing Motor Operated Valves Using 5 Teledyne/Quicklook System Inspection Type Designation Description or Title Revision or Procedure Date OP/2/A/1600/008 SSF RC Makeup and Letdown Systems 035 PT/2/A/0152/017 Reactor Coolant System Valve Stroke Test 032 PT/2/A/0400/020 SSF RC Letdown Line Discharge Test 011 PT/3/A/0203/006 Low Pressure Injection Pump Test - Recirculation 094 A TN/2/A/403752/E1 Procedure for Implementation of EC403752 - Unit 2 SSF 001 RC Letdown Line Control Circuit Replacement Installation Work Orders 20307071-99, 20307071-42, 20307071-43, 20367709-11, 20307071-66, 20307071-50 71111.20 Corrective Action 2307084, 2167511, 2306246, 2306288, 2307084, 2934250 Documents Drawings OFD-124B-2.1 Flow Diagram of Low Pressure Service Water System 77

                                             (Auxiliary Building Services)

OM 245.- Bolted Cover Swing Check Valve (Cast) 1 28.001 Miscellaneous Complex Activity Plan for 2LPSW-1116 during O2R29 0, 1 Oconee Nuclear Station Technical Specifications, Revised August 8, 2019 Oconee Nuclear Station Selected Licensee Commitments November 7, 2019 Oconee U2, O2R29 Summary Schedule, IRT September 9, 2019 Generic Letter No. 88-17, Loss of Decay Heat Removal October 17, 1988 Unit Shutdown/Cooldown & Depressurization JITT NIGHT 5m Shift Clearance OPS-2 -19-LPS-2LPSW-1116 -0455 O2R29 Shutdown Safety Overview - Outage Defense in Effect Procedures AD-MN-ALL-0002 Foreign Material Exclusion 10 AD-OP-ALL-0203 Reactivity Management 12 AP/1- Loss of SFP Cooling and/or Level 024 2/A/1700/035 EP/2/A/1800/001 Restoration of Power 001 Inspection Type Designation Description or Title Revision or Procedure Date 0P - Enclosure 5.38 FG/0/A/1900/005 Initial Assessment and FLEX Equipment Staging 005 MP/0/A/1150/002 Reactor Vessel - Closure Head - Removal 63 MP/0/A/1200/108 Valve-Removal and Installation of Flanged Valves or Wafer 66 Valves to Piping ONEI-0400-491 Oconee 2 Cycle 29 Core Operating Limits Report 002 OP/0/A/1102/026 Operations IPTE Pre-Job Briefings 031 OP/0/A/1108/001 Curves and General Information 115 OP/0/A/1108/001 Reactor Core and SFP Loss of Cooling Heatup Tables 007 A OP/1- SF Cooling System 109 2/A/1104/006 OP/2/A/1102/001 Controlling Procedure for Unit Startup 279 OP/2/A/1102/004 Operation At Power 126 OP/2/A/1102/004 ICS Operation 014 A OP/2/A/1102/010 Controlling Procedure for Unit Shutdown 222 OP/2/A/1103/004 RCS Boration 025 A OP/2/A/1103/011 Draining and Nitrogen Purging RCS 101 OP/2/A/1105/019 Control Rod Drive System 027 PT/0/A/0711/001 Zero Power Physics Test 73 PT/2/A/0115/012 Unborated Water Source Isolation Verification 005 PT/2/A/0600/001 Instrument Surveillance Prior to Mode Change 044 B PT/2/A/0600/030 NI Overlap 001 PT/2/A/1103/015 Reactivity Balance Procedure (Unit 2) 73 Site Directive Shutdown Protection Plan 39 Manual 1.3.5 TE-MN-ALL-0002 Foreign Material Exclusion Level and Controls Screening 2 Inspection Type Designation Description or Title Revision or Procedure Date Work Orders 20304120, 20137409 71111.22 Calculations OSC-4672 Unit 1 & 2 LPSW System LOCA/LOOP Response 11 Corrective Action 2298193, 02304315 Documents Drawings O-422H-22-02 Instrument Detail LPSW Flow Control to Decay Heat Cooler 8 1B OFD-116A-2.1 Flow Diagram of Reactor Building Purge System 12 OFD-124B-1.1 Flow Diagram of Low Pressure Service Water System 68 Engineering 412012 Equivalent Change, Use of VALCOR V70900-65-24 0 Changes Miscellaneous Licensees Logs via eSOMS Oconee OAC SDS Procedures AP/1/A/1700/024 Loss of LPSW 028 PT/2/A/0150/006 Mechanical Penetration Leak Rate Data 067 PT/2/A/0150/034 Leak Rate History Record and Reactor Building Leak Rate 012 Verification PT/2/A/0151/019 Penetration 19 Leak Rate Test 016 PT/2/A/0203/008 Component Test of ES Channels 3 & 4 025 Work Orders 20304541, 20304470 71124.01 Corrective Action 02222444; Documents 02200884; 207944; 211886 Miscellaneous AD-RP-ALL-2017 Access Controls to Very High Radiation Areas and December Supplemental Access Controls for HRA and LHRA: Unit 2 11, 2019 RB Annulus 71124.02 Corrective Action 02203837; Documents 02296924; 2166562; 241719 Miscellaneous HP/0/B/1000/016 OTSG Platform Worker Dose Tracking; Steam Generator November Tube Plugging RWP 2221/ Task 11 19, 2019, 08:18 Inspection Type Designation Description or Title Revision or Procedure Date Self-Assessments AD-PI-ALL-0300 Self Assessment and Benchmark Programs: Quick Hitter May 05, Self-Assessment Report 02114260-05 2017 71124.03 Miscellaneous SCBA Qualification List for the RP Group October 31, 2019 71124.04 Corrective Action NCRs 02163071, Documents 02201294, and 221063 Procedures AD-RP-ALL-4015 Dosimetry in Gradient Radiation Fields Rev. 0 71124.05 Corrective Action AR 02242797 Documents Procedures AD-EG-ALL-1202 Preventive Maintenance and Surveillance Testing Rev. 8 Administration Radiation ONS-M- Rad Waste Room 123 Resin Batch Tk. Transfer Pump November 9, Surveys 20181109-13 2018 71151 Corrective Action 02200447; Documents 02241002 Miscellaneous Unit 1, 2, and 3 MSPI Derivation Report for period ending September 2019 MSPI Basis Document 26 Unit 1, 2, and 3 MSPI Margin Report for period ending September 2019 NEI 99-02 Regulatory Assessment Performance Indicator Guideline 7 71152 Calculations OSC-11832 Evaluation of Switchyard Trenches S105 and S117 1 Corrective Action 1702592, 01907384, 02257729 Documents AR 02295447, 282671, 203327, 293642 Drawings K-0700 One Line Diagram Relays & Meters 13.8-230kV 44 K-0702 One Line Diagram 600 Volt Station Auxiliary Circuits 62 K-0708 Three Line Diagram Generator No. 1 12 K-0709 Three Line Diagram Transformers No. 1, 1X, 2X, CX, 1E & 21 Inspection Type Designation Description or Title Revision or Procedure Date 2E Engineering 415620 Update OM-245-1931.001 vendor manual based on vendor 0 Changes supplied information 415794 Keowee CX Transformer Replacement 003 Miscellaneous CNM 1392.00- Doble Evaluation Criteria 0 0013.001 DPM-1393.01- Rotork NQR Series Reports 2 0038.001 EQMM-1393-01- Environmental Qualification Maintenance Manual - 17 A01-00 Equipment Type: Electric Motor Actuator Manufacturer: Rotork Model/Series: NA1 MCM 1354.00- Overload and Short Circuit Tests of Cables 9/29/14 29.001 OM 245-0980.001 Rotork Valve Operator Nuclear Qualification (Post 1978) 4 OM 245-1931.001 Technical Repair Guide for Rotork Valve Actuators NA 6 Range Models Procedures AD-HS-ALL-0110 Electrical Safety 14 AD-MN-ALL-0002 Foreign Material Exclusion 10 AD-OP-ALL-0200 Clearance and Tagging 20 AD-PI-ALL-0100 Corrective Action Program 21 IP/0/A/2000/004 Doble Testing 023 OSS-0218.00-00- (ELECT) Installation Spec Cable and Wiring Separation 18 0019 Criteria OSS-0254.00-00- (MECH) Design Basis Specification for the Oconee Single 8 4013 Failure TE-MN-ALL-0202 Transformer and Apparatus Testing 000 Work Orders 20147967, 02208634, 20086331, 02164537, 02208634, 20179664, 20245600, 20008002, 20008003, 20023531 2| ]]