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

February 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

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

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 Aspect Report Section Mitigating Systems Green NCV 05000269,05000270,05000287/2019004-01 Open/Closed

[H.6] - Design Margins 71111.18 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 Oconee Nuclear Station,

Unit 1, Core Flooding System Loss of Safety Function 71153 Closed

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) (1 Sample)

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) (4 Samples)

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 Sample)

(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 Sample)

(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) (4 Samples)

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) (3 Samples)

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) (6 Samples)

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) (5 Samples)

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 Sample)

(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) (1 Sample)

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

1. 2216, U2 RXB A/B ROTSG-Set up/Remove/Replace Primary Manway/Handhole Covers, Revision 29

1. 2221, U2 RXB-A/B ROTSG Tube Plugging/ Stabilization/ Plug Removal, Revision 24

1. 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) (1 Sample)

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) (1 Sample)

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 Sample)

(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) (1 Sample)

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 Sample)

(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 Aspect Report Section Mitigating Systems

Green NCV 05000269,05000270,05000287/2019004-01 Open/Closed

[H.6] - Design Margins 71111.18 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

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.04Q Calculations

OSC-10963

Electrical Design Input Calculation for Engineering Change 110408

OSC-10969

Mechanical Design input Calculation for the Alternate

Chilled Water (AWC) System

OSC-7934

Auxiliary Building GOTHIC Heat Up Analysis - PSW Event

Cases

OSC-9659-ICC-

0004

NFPA 805 Impacts due to AWC Manual Valve Position

Changes

Corrective Action

Documents

286301, 20153797, 2276864, 1854557, 1857675,

277519, 2278566, 2296376, 2298512, 2167815

Drawings

O-6708

One Line Diagram Alternate Chill Water (AWC) 4160/600V

System

O-6708-A

One Line Diagram Alternate Chill Water (AWC) 600/208V

System

O-6708-B

One Line Diagram Alternate Chill Water (AWC) 600/208V

System

OFD-116Q-1.1

Flow Diagram of AWC System Yard Chillers and Auxiliary

Skids

OFD-116Q-1.2

Flow Diagram of AWC System Auxiliary Building Chiller

No.1 Main Headers

OFD-116Q-1.3

Flow Diagram of AWC System Auxiliary Building Chiller

No.2 Main Headers

OFD-116Q-1.4

Flow Diagram of AWC System Auxiliary Building Cable

Rooms

OFD-126C-1.1

Flow Diagram of Drinking Water System (Drinking Wtr.

Make-up Service Building)

OFD-126C-1.2

Flow Diagram of Plant Drinking Water System (Turbine

Bldg., Admin. Bldg., IRW Facility, & QA Radiographic

Facility Supply)

Procedures

AM/0/A/3007/066

Abnormal Procedure for Installation and Removal of RBCU

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Hale Pumps and Hoses

AM/0/A/3007/085

Abnormal Procedure for Installation and Removal of Unit 1

and 2 Cable Room AWC Coolers

AM/0/A/3007/086

Abnormal Procedure for Installation and Removal of

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 -

Trane 500-Ton Model RTAC Chiller Make-up Water

AP/1-

2/A/1700/036

Degraded Control Room Area Cooling

OP/0/A/1106/029

C

Alternate Chilled Water System

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

Fire Risk Evaluation

006

OSC-9378

ONS Fire PRA (FPRA) Summary Report

004

OSC-9659

Oconee Nuclear Safety Capability Assessment for Units 1,

2, and 3

011

Drawings

O-0756-M

Fire Detection System Detector Tabulation

21

Fire Plans

CSD-ONS-FS-020 Standard Operating Guide Key Equipment List by Fire Zone

CSD-ONS-PFP-

1TB-0796

Pre-Fire Plan for U1 Turbine Building Elevation 796

CSD-ONS-PFP-

2RB

Pre-Fire Plan for U2 Reactor Building All Elevations

CSD-ONS-PFP-

2TB-0822

Pre-Fire Plan for U2 Turbine Building Elevation 822

CSD-ONS-PFP-

3TB-0822

Pre-Fire Plan for U3 Turbine Building Elevation 822

71111.08P

Calculations

NS-TECR-102658

Oconee Mathematically Calculated Calibration Curve

Rev. 001

Calibration

Records

MIZ-80

166, 526480, 540464, 542183, 542555, 544984, 648200,

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

Procedure

Type

Designation

Description or Title

Revision or

Date

000015

Procedure for Replacement Once Through Steam

Generators

Corrective Action

Documents

A/R # 02294252

2HP-123 Boron Leak Containment Isolation Valve

9/27/19

ACTION

REQUEST -

2302962

NCR - ISI Visual Examination of 2-RPV-HEAD-PEN

11/17/19

AR-02171026

Active Boric Acid Leak from Valve 2HP-110

2/10/17

AR-02173332

2C-HPI Pump Shaft has Active Boron Leak

2/20/17

AR-02302078

ISI Visual Examination of Component 2-SCV-011,

Containment Liner

11/16/19

NCR 02294245

Boric Acid Corrosion Evaluation

10/24/19

Corrective Action

Documents

Resulting from

Inspection

NCR-02302449

BORON OBSERVED IN PRESSURIZER HEATER PLUGS

11/14/19

NCR-02302598

Safety Concern - Fall Protection

11/14/19

WO 20158328

Clean (Boric Acid ) Stains on Underside of Grating Below 2B

Hot Leg Elbow, Considerable deposits on the underside of

grating, below the pressurizer surge line where the hot leg

comes out.

11/9/19

WO 20158790

Boron Observed on Pressurizer Heater Sleeves

11/13/19

Drawings

0-ISIC2-1062-

0010

Oconee Unit-2, Containment Liner Plate, In-service

Inspection Areas, Developed Elevation, Sht. 2

Rev. 2

0-ISIC2-1962-009

Oconne Unit-2, Containment line Plate, In-service Inspection

Areas, Developed Elevation, Sht. 1

Rev. 2

28719E

B&W Reactor Vessel Radio-graphic Outline and Weld

Identifiers

Rev. 3

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

Calibration Standard

Rev. 0

O-1479 A

Oconee U-2, Piping Layout, Ground Floor Plan, Reactor

Building

Rev. 55

OM 1201.-

1538.001

(151991-E)

Arrangement Reactor Vessel Long Section

Rev.14

Engineering

0300-TECR-

Condition Monitoring and Preliminary Operational

Rev. 0

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Evaluations

104094

Assessment for Oconee-2 O2R29 Outage

3011-AST-101520 Steam Generator Condition Monitoring and Final

Operational Assessment for Oconee-2 O2R28 Outage

Rev. 0

AD-EG-PWR-

1813

Steam Generator Degradation Assessment

Rev. 0

AR-02294252

Boric Acid

Evaluation

Valve 2HP-123

9/27/19

NCR-02171026,

Boric Acid

Corrosion

Evaluation

Evaluation of Active Boric Acid Leak at Valve 2HP-VA-110

1/10/18

Oconee Unit-2,

Cycle 29

Collective Significance Review for Leakage

2/27/19

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

Technical Sheet

Rev. 4

NIS 2-A (Work Order 20083860

Owners Certificate of Conformance for Repair Replacement

Plan 20083860-03

1/17/18

Oconee UFSAR

Section 3.8

Design of Structures

2/31/17

Oconee Unit-2

Doc. ID 2015-85

Integrated Leakage Rate Test Report

2/7/2015

Personnel

Qualifications

J. Baumann,

S. Merriam,

T. Thulien,

ST3118

Completion

Information

Oconee WO 20218685 Completion Information

11/19/19

Visual Acuity

S. Merriam,

T. Thulien,

NDE Reports

UT-19-010

System ID: CONT (Containment Liner Plate), Component

11/16/19

Inspection

Procedure

Type

Designation

Description or Title

Revision or

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

Head BMI Nozzles

1/25/18

VT-19-076

System ID: CONT (Containment), Component ID: 2-SCV-

011, Report of Visual Examination of IWE Surfaces (VT-1)

11/14/19

VT-19-110

Component ID, 2-RPV-HEAD-PEN, Reactor Pressure

Vessel Outer Head Surface -Visual Examination

11/22/19

Procedures

0300-PLAN-

103523

ROTSG ECT Inspection Plan

Rev. 1

8-QPP-761

Multifrequency Eddy Current Examination of Steam

Generator Tubing

Rev. 8

ETSS

13091.2, 27091.2, 96042.1, 96043.4

NDE-NE-ALL-

6102

Utilization of PDI-UT-2 Generic Procedure for the Ultrasonic,

Examination of Austenitic Pipe Welds

Rev. 002

NDE-NE-ALL-

6403

Straight Beam Ultrasonic Examination

Rev. 000

NDE-NE-ALL-

7402

Visual Examination of IWE Components

Rev. 1

NDE-NE-ONS-

0131

Eddy Current Guidelines for Oconee Nuclear Station's

Replacement Once-Through Steam Generators

Rev. 2

NDE-NE-ONS-

0132

ROTSG Site Technique Validation for Oconee Nuclear

Station

Rev. 2

O-ISISG-

0169.030.0050

Fifth Interval Steam Generator Inservice Inspection Plan

Rev. 1

S000001-07-

000015

Mechanical Rolled Tube Plug & Stabilizer Installation Field

Procedure for Replacement Once Through Steam

Generators

Rev. 13

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

Procedure

Type

Designation

Description or Title

Revision or

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

Leak Inspection

11/9/19

WO-20218685

Active Boron Leak From Valve 2HP-110

11/26/19

WR 20092675

Active Boron Leak from Valve 2HP-110

2/10/17

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

Documents

200104, 2249753, 1845371, 1773940, 1761628, 2290674,

291819, 2294220, 2291906, 2292616, 2298746, 2298508,

295613, 02296687, 02303769, 02299588

Drawings

K-0700

One Line Diagram Relays & Meters 13.8-230kV

OEE-345-105

Elementary Diagram AFIS Analog Inputs to Digital Channel

Trip Confirm (Blue)

OM 2311.D-

21.001

Oconee Unit 3 AFIS - STAR Trip Confirm Dig. CH 1 & 2

15V DC Distribution

D1

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

Paralleling

A

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

Maintenance at Nuclear Power Plants

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

8003189-AFIR-1

As-Found Inspection Report for Automatic Voltage

Regulator, Repair and Return

OM 2201.C-

28.001

STAR System Instruction Manual

D07

OM 351-0164.002

SSF Diesel Generator Instructions and Parts Manual

OSS-0254.00-00-

26

(ELEC) Automatic Feedwater Isolation System

Procedures

AD-EG-ALL-1210

Maintenance Rule Program

AD-EG-ALL-1311

Failure Investigation Process (FIP)

IP/0/A/2005/004

NEI, PP-EP SVS Static Voltage Regulator Exciter System

IP/0/A/2005/004 A

SSF Diesel Generator Automatic Voltage Regulator Bench

Test

Work Orders

208499, 2083722, 20201615, 20208939, 20357208,

20154895, 20157106

71111.13

Drawings

OFD-124B-2.1

Flow Diagram of Low Pressure Service Water System

(Auxiliary Building Services)

OFD-133A-2.5

Flow Diagram of Condenser Circulating Water System (SSF

AUX. Service)

OM 245.-

28.001

Velan Bolted Cover Swing Check Valve (Cast)

Miscellaneous

Complex Activity Plan for 2LPSW-1116 during O2R29

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

Valves to Piping

MP/0/A/1840/040

Pumps - Motors - Miscellaneous Components - Lubrication

- Oil Sampling - Oil Change

039

OP/0/A/1102/026

Operations IPTE Pre-Job Briefings

031

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

OP/2/A/1103/011

Draining and Nitrogen Purging RCS

101

Site Directive

1.3.5

Shutdown Protection Plan

Work Orders

20137409, 20352487

71111.15

Calculations

OSC-5649

LPSW Test Acceptance Criteria (TAC)

Corrective Action

Documents

292821, 2286307, 02304315, 02293695, 02301011

Drawings

18ALV500X11

ALV Pump

B

OFD-124A-3.1

Flow Diagram of Low Pressure Service Water System

Turbine Building

OM 1240-002

Instruction Manual Operation-Maintenance Instructions and

Parts Catalog for Automatic Pipeline Strainer Model No. 590

& 592

OM 208-0064.001

Service Water Pump Installation Manual

OM 240-002

Zurn Strain-O-Matic Model 67 Automatic Self-Cleaning

Strainer with Exclusive Lin-A-Flo Design

OM 245-617

Chart of List 1233 F.E. Tilting Disc Check Valves with

Flexitallic Gasket

ONTC-3-124A-

0006-001

Unit 3 LPSW Pump Discharge Check Valve Leakage Test

Acceptance Criteria

OSC-10448

Environmental Qualification Evaluation for Oconee Reactor

Building Water Level Transmitters and Supporting

Equipment

OSC-2784

Oconee Fouled Coolers / High Lake Temperature

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

Procedure

Type

Designation

Description or Title

Revision or

Date

2004

Plants

OSS-0254.00-00-

1004

(Mech) Design Basis Specification for Standby Shutdown

Facility Reactor Coolant Makeup System

056

OSS-0254.00-00-

28

(Mech) Design Basis Spec for the Low Pressure Injection

and Core Flood System (LPI)

059

Procedures

AP/1/A/1700/024

Loss of LPSW

28

MP/0/A/1600/031

Strainer - Zurn - LPSW Pump Maintenance

PT/0/0160/006

Reactor Building Cooling Units Performance Test performed

March 11, 2019

PT/2/A/0160/002

Reactor Building Cooling Unit Air Flow Test performed

November 16, 2017

PT/2/A/0203/008

Component Test of ES Channels 3 & 4

25

Work Orders

20346861, 2142983, 20304470

71111.18

Calculations

OSC-10511

LPSW Flow to RBCUs for Environmental Qualification

Purposes

OSC-5666

Reactor Building Cooling Unit Performance Test - Unit 2

67, 68

OSC-5667

Reactor Building Cooling Unit Performance Test - Unit 3

OSC-6146

Post-LOCA Reactor Bldg Cooling Unit Capacity

OSC-8064

ROTSG Long-Term Containment Response Following a

Large Break LOCA

Corrective Action

Documents

294192, 1905036

Engineering

Changes

110165

Revise TAC Sheets for setpoints of LPSW pressure

switches and LPSW pump TAC sheets ONTC-1-12

Miscellaneous

ONEI-0400-400

Oconee Nuclear Station Revised RBCU Requirements in

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-

218, RC-219, RC-223)

OSC-5675

Generic Letter 89-10 Calculation for Unit 2 Gate and Globe

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Valves

OSC-7184

Generic Letter 89-10 MOV Calculation for Units 1,2, 3 Gate

and Globe Valves at Oconee

Corrective Action

Documents

2304894

Drawings

O-1721-C

RC Makeup & Letdown and High Pressure Injection &

Purification System

2D

OFD-101A-2.5

Flow Diagram of High Pressure Injection System (SSF

Portion)

OFD-102A-2.1

Flow Diagram of Low Pressure Injection System (Borated

Water Supply And LPI Pump Suction)

OFD-104A-1.1

Flow Diagram of Spent Fuel Cooling System

OFD-107A-2.1

Flow Diagram of Coolant Storage System Quench Tank

Portion

OM 245.-

2830.001

DMV-2184, 2.5 Class 2500 SD Valve, BW Ends, with

Rotork 25NET1 Electric Actuator

OM 253.-

23.001

Solenoid Operated Valve Energize to Open (FC) On/Off 2.5-

inch BW

ONTC-2-101A-

25

Unit 2 SSF RC Letdown Line Performance Test

Engineering

Changes

EC403752

Modify U2 SSF RCS Letdown Line to Support SSF

Operability in All Modes of Operation

Miscellaneous

EC403752 Post-Modification Test Exceptions Management

Review

November

14, 2018

OM 245.-

2830.003

NIB - Flow Test Two SPX Flow Copes-Vulcan 2.5-inch

Class 2500# Severe Duty Control Valves (DMV-2184 &

DMV-2198)

OM 245.-

2830.005

NIIB - (DMV-2184 & DMV-2198) Weak Link Report with

Seismic Acceleration & Fatigue Life 2.5 Class 2500

OM 245.-

2830.020

I/B - DMV-2184 & DMV-2198 25NET Hand/Auto Lever

Upgrade Instructions

Procedures

IP/0/A/3001/011 L

Diagnostic Testing Motor Operated Valves Using

Teledyne/Quicklook System

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

OP/2/A/1600/008

SSF RC Makeup and Letdown Systems

035

PT/2/A/0152/017

Reactor Coolant System Valve Stroke Test

2

PT/2/A/0400/020

SSF RC Letdown Line Discharge Test

011

PT/3/A/0203/006

A

Low Pressure Injection Pump Test - Recirculation

094

TN/2/A/403752/E1 Procedure for Implementation of EC403752 - Unit 2 SSF

RC Letdown Line Control Circuit Replacement Installation

001

Work Orders

20307071-99, 20307071-42, 20307071-43, 20367709-11,

20307071-66, 20307071-50

71111.20

Corrective Action

Documents

2307084, 2167511, 2306246, 2306288, 2307084, 2934250

Drawings

OFD-124B-2.1

Flow Diagram of Low Pressure Service Water System

(Auxiliary Building Services)

OM 245.-

28.001

Bolted Cover Swing Check Valve (Cast)

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

Shift

5m

Clearance OPS-2 -19-LPS-2LPSW-1116 -0455

O2R29

Shutdown Safety Overview - Outage Defense in Effect

Procedures

AD-MN-ALL-0002

Foreign Material Exclusion

AD-OP-ALL-0203

Reactivity Management

AP/1-

2/A/1700/035

Loss of SFP Cooling and/or Level

24

EP/2/A/1800/001

Restoration of Power

001

Inspection

Procedure

Type

Designation

Description or Title

Revision or

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

MP/0/A/1200/108

Valve-Removal and Installation of Flanged Valves or Wafer

Valves to Piping

ONEI-0400-491

Oconee 2 Cycle 29 Core Operating Limits Report

2

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

A

Reactor Core and SFP Loss of Cooling Heatup Tables

007

OP/1-

2/A/1104/006

SF Cooling System

109

OP/2/A/1102/001

Controlling Procedure for Unit Startup

279

OP/2/A/1102/004

Operation At Power

26

OP/2/A/1102/004

A

ICS Operation

014

OP/2/A/1102/010

Controlling Procedure for Unit Shutdown

2

OP/2/A/1103/004

A

RCS Boration

25

OP/2/A/1103/011

Draining and Nitrogen Purging RCS

101

OP/2/A/1105/019

Control Rod Drive System

27

PT/0/A/0711/001

Zero Power Physics Test

PT/2/A/0115/012

Unborated Water Source Isolation Verification

005

PT/2/A/0600/001

B

Instrument Surveillance Prior to Mode Change

044

PT/2/A/0600/030

NI Overlap

001

PT/2/A/1103/015

Reactivity Balance Procedure (Unit 2)

Site Directive

Manual 1.3.5

Shutdown Protection Plan

TE-MN-ALL-0002

Foreign Material Exclusion Level and Controls Screening

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Work Orders

20304120, 20137409

71111.22

Calculations

OSC-4672

Unit 1 & 2 LPSW System LOCA/LOOP Response

Corrective Action

Documents

298193, 02304315

Drawings

O-422H-22-02

Instrument Detail LPSW Flow Control to Decay Heat Cooler

1B

OFD-116A-2.1

Flow Diagram of Reactor Building Purge System

OFD-124B-1.1

Flow Diagram of Low Pressure Service Water System

Engineering

Changes

2012

Equivalent Change, Use of VALCOR V70900-65-24

Miscellaneous

Licensees Logs via eSOMS

Oconee OAC SDS

Procedures

AP/1/A/1700/024

Loss of LPSW

28

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

Verification

2

PT/2/A/0151/019

Penetration 19 Leak Rate Test

016

PT/2/A/0203/008

Component Test of ES Channels 3 & 4

25

Work Orders

20304541, 20304470

71124.01

Corrective Action

Documents

222444;

200884;

207944;

211886

Miscellaneous

AD-RP-ALL-2017

Access Controls to Very High Radiation Areas and

Supplemental Access Controls for HRA and LHRA: Unit 2

RB Annulus

December

11, 2019

71124.02

Corrective Action

Documents

203837;

296924;

2166562;

241719

Miscellaneous

HP/0/B/1000/016

OTSG Platform Worker Dose Tracking; Steam Generator

Tube Plugging RWP 2221/ Task 11

November

19, 2019,

08:18

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Self-Assessments AD-PI-ALL-0300

Self Assessment and Benchmark Programs: Quick Hitter

Self-Assessment Report 02114260-05

May 05,

2017

71124.03

Miscellaneous

SCBA Qualification List for the RP Group

October 31,

2019

71124.04

Corrective Action

Documents

NCRs 02163071,

201294, and

221063

Procedures

AD-RP-ALL-4015

Dosimetry in Gradient Radiation Fields

Rev. 0

71124.05

Corrective Action

Documents

AR 02242797

Procedures

AD-EG-ALL-1202

Preventive Maintenance and Surveillance Testing

Administration

Rev. 8

Radiation

Surveys

ONS-M-

20181109-13

Rad Waste Room 123 Resin Batch Tk. Transfer Pump

November 9,

2018

71151

Corrective Action

Documents

200447;

241002

Miscellaneous

Unit 1, 2, and 3 MSPI Derivation Report for period ending

September 2019

MSPI Basis Document

Unit 1, 2, and 3 MSPI Margin Report for period ending

September 2019

NEI 99-02

Regulatory Assessment Performance Indicator Guideline

71152

Calculations

OSC-11832

Evaluation of Switchyard Trenches S105 and S117

Corrective Action

Documents

1702592, 01907384, 02257729

AR 02295447,

282671,

203327,

293642

Drawings

K-0700

One Line Diagram Relays & Meters 13.8-230kV

K-0702

One Line Diagram 600 Volt Station Auxiliary Circuits

K-0708

Three Line Diagram Generator No. 1

K-0709

Three Line Diagram Transformers No. 1, 1X, 2X, CX, 1E &

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2E

Engineering

Changes

415620

Update OM-245-1931.001 vendor manual based on vendor

supplied information

415794

Keowee CX Transformer Replacement

003

Miscellaneous

CNM 1392.00-

0013.001

Doble Evaluation Criteria

DPM-1393.01-

0038.001

Rotork NQR Series Reports

EQMM-1393-01-

A01-00

Environmental Qualification Maintenance Manual -

Equipment Type: Electric Motor Actuator Manufacturer:

Rotork Model/Series: NA1

MCM 1354.00-

29.001

Overload and Short Circuit Tests of Cables

9/29/14

OM 245-0980.001

Rotork Valve Operator Nuclear Qualification (Post 1978)

OM 245-1931.001

Technical Repair Guide for Rotork Valve Actuators NA

Range Models

Procedures

AD-HS-ALL-0110

Electrical Safety

AD-MN-ALL-0002

Foreign Material Exclusion

AD-OP-ALL-0200

Clearance and Tagging

AD-PI-ALL-0100

Corrective Action Program

IP/0/A/2000/004

Doble Testing

23

OSS-0218.00-00-

0019

(ELECT) Installation Spec Cable and Wiring Separation

Criteria

OSS-0254.00-00-

4013

(MECH) Design Basis Specification for the Oconee Single

Failure

TE-MN-ALL-0202

Transformer and Apparatus Testing

000

Work Orders

20147967, 02208634, 20086331, 02164537, 02208634,

20179664, 20245600, 20008002, 20008003, 20023531