ML21036A001
| ML21036A001 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/04/2021 |
| From: | Margaret Tobin NRC/RGN-II |
| To: | Burchfield J Duke Energy Carolinas |
| References | |
| IR 2020004 | |
| Download: ML21036A001 (22) | |
See also: IR 05000269/2020004
Text
February 4, 2021
Mr. J. Ed Burchfield
Site Vice President
Duke Energy Carolinas, LLC
7800 Rochester Highway
Seneca, SC 29672-0752
SUBJECT: OCONEE NUCLEAR STATION - INTEGRATED INSPECTION REPORT
05000269/2020004 AND 05000270/2020004 AND 05000287/2020004
Dear Mr. Burchfield:
On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an
inspection at Oconee Nuclear Station. On January 21, 2021, the NRC inspectors discussed the
results of this inspection with you and other members of your staff. The results of this
inspection are documented in the enclosed report.
No NRC-identified or self-revealing findings were identified during this inspection.
A licensee-identified violation which was determined to be of very low safety significance is
documented in this report. 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.
J. Burchfield 2
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/
Margaret C. Tobin, Acting Chief
Reactor Projects Branch 1
Division of Reactor Projects
Docket Nos. 05000269, 05000270, and 05000287
License Nos. DPR-38, DPR-47, and DPR-55
Enclosure:
As stated
cc w/ encl: Distribution via LISTSERV
X Non-Sensitive X Publicly Available
X SUNSI Review
Sensitive Non-Publicly Available
OFFICE RII: DRP RII: DRP RII: DRP RII: DRP RII: DRP
NAME J. Nadel JHN J. Parent JXP1 A. Ruh AMR4 J. Worosilo JGW1 M. Tobin
DATE 2/3/2021 2/3/2021 2/2/2021 2/3/2021 2/4/2021
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Numbers: 05000269, 05000270, and 05000287
License Numbers: DPR-38, DPR-47, and DPR-55
Report Numbers: 05000269/2020004, 05000270/2020004, and 05000287/2020004
Enterprise Identifier: I-2020-004-0050
Licensee: Duke Energy Carolinas, LLC
Facility: Oconee Nuclear Station
Location: Seneca, South Carolina
Inspection Dates: October 01, 2020 to December 31, 2020
Inspectors: J. Nadel, Senior Resident Inspector
J. Parent, Resident Inspector
A. Ruh, Resident Inspector
S. Bussey, Sr. Reactor Technology Instructor
B. Collins, Senior Reactor Inspector
P. Cooper, Senior Reactor Inspector
C. Dykes, Senior Health Physicist
M. Meeks, Senior Operations Engineer
J. Rivera, Health Physicist
Approved By: Margaret C. Tobin, Acting 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. A licensee-identified
non-cited violation is documented in report section: 71111.20.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
2
PLANT STATUS
Unit 1 began the inspection period at 100 percent rated thermal power (RTP). On October 17,
2020, the unit was shut down for a planned refueling outage. The unit was returned to 100
percent RTP on November 8, 2020 and remained at this power level for the remainder of the
inspection period.
Unit 2 operated at or near 100 percent RTP for the entire inspection period.
Unit 3 operated at or near 100 percent RTP for the entire inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in
effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with
their attached revision histories are located on the public website at http://www.nrc.gov/reading-
rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared
complete when the IP requirements most appropriate to the inspection activity were met
consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection
Program - Operations Phase. The inspectors 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.
Starting on March 20, 2020, in response to the National Emergency declared by the President
of the United States on the public health risks of the Coronavirus Disease 2019 (COVID-
19), resident inspectors were directed to begin telework and to remotely access licensee
information using available technology. During this time, the resident inspectors performed
periodic site visits each week; conducted plant status activities as described in IMC 2515,
Appendix D, Plant Status; observed risk-significant activities; and completed on-site portions of
IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or
portions of the objectives and requirements stated in the IP could be performed remotely. If the
inspections could be performed remotely, they were conducted per the applicable IP. In some
cases, portions of an IP were completed remotely and on-site. The inspections documented
below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
(1) The inspectors evaluated the adequacy of the overall preparations to protect risk-
significant systems from impending severe weather from tropical storm Zeta on
October 29, 2020.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following
systems/trains:
3
(1) Emergency operating procedure Enclosure 5.42 and 5.43 portable pump train during
turbine building heavy lifts on October 8, 2020
(2) Turbine driven emergency feedwater trains on Units 1, 2, and 3 on December 8, 2020
(3) 3B motor driven emergency feedwater (MDEFW) pump train due to planned testing of
the 3A MDEFW pump via PT/3/A/0600/013 on December 17, 2020
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a
walkdown and performing a review to verify program compliance, equipment functionality,
material condition, and operational readiness of the following fire areas:
(1) Fire Zone 34: Unit 1 4160V TC, TD, TE switchgear on October 18, 2020
(2) Fire Zone 29: Unit 3 4160V TC, TD, TE switchgear on October 29, 2020
(3) Fire Zone 103: Unit 2 east penetration room on November 5, 2020
(4) Fire Zone RB01: Unit 1 containment on November 13, 2020
(5) Fire Zone CR12: Unit 1 and 2 control room on November 23, 2020
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
(1) Auxiliary building during 1A low pressure service water (LPSW) system breach for
1LPSW-1111 check valve replacement
71111.08P - Inservice Inspection Activities (PWR)
PWR Inservice Inspection Activities Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated pressurized water reactor nondestructive testing by reviewing the
following examinations from October 19 - 26, 2020:
(1) 03.01.a - Nondestructive Examination and Welding Activities.
1. Ultrasonic Examination (UT)
a. 1-RC-261-266, Drain Safe End to Elbow, ASME Class1, Work Order
(WO) 20337024
b. 1-RC-261-267, Drain Elbow to Pipe, ASME Class 1, WO 20337024
c. 1-RC-261-Elbow, Drain Elbow Base Metal, ASME Class 1, WO 20337024
2. Liquid Penetrant Examination (PT)
a. 1-RC-0337-1, 2.5" Reactor Coolant System elbow weld, ASME Class
2, WO 20346701
03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination
Activities.
1. Visual Examination (VT-2)
4
a. NDE-NE-ALL-7202, PWR Reactor Pressure Vessel Upper Head
Penetrations, Rev. 4, ASME Class 1
03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.
The inspectors reviewed the licensee's boric acid corrosion control program
performance.
03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities.
1. Eddy Current Testing (ECT)
a. SG A, tubes R11C22, R140C49, and R75C116, ASME Class 1
(observed via video)
b. SG B, tubes R78C18 and R70C124, ASME Class 1 (observed via
video)
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
(1) On March 27, 2020, the licensee completed the annual requalification operating
examinations required to be administered to all licensed operators in accordance with
Title 10 of the Code of Federal Regulations 55.59(a)(2), Requalification
Requirements, of the NRCs Operators Licenses. During the week of December
21, 2020, 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 Unit 1 shutdown on October 16, 2020.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1) The inspectors observed and evaluated Just in Time Training (JITT) for a planned
Unit 1 shutdown on October 13, 2020.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the
following planned and emergent work activities to ensure configuration changes and
appropriate work controls were addressed:
(1) Green risk during turbine building heavy lifts and compensatory measures on October
8, 2020
5
(2) Yellow risk during Unit 1 refueling outage high risk plant operating state (HRPOS) on
October 19, 2020
(3) Green risk during planned safe shutdown facility fire penetration breaches and 3A low
pressure injection pump testing on December 23, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the
following operability determinations and functionality assessments:
(1) Engineering evaluations for nuclear condition report (NCR) 2353911, blown fuse
found in cubicle for breaker 1XSF-F3B for standby shutdown facility and auxiliary
shutdown panel bank 'B' pressurizer heaters
(2) Engineering evaluation for NCR 2351598, U3 RC-219 failed fuse during the
performance of PT/3/A/0115/008
(3) Operability determination for NCR 2357910, 1A motor driven emergency feedwater
pump after operation at deadhead conditions for 40 minutes due to a failed minimum
flow valve
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system
operability and functionality:
(1) PT/1/A/0152/011, "High Pressure Injection System Valve Stroke Test," after
preventive maintenance on 1HP-24 motor operated valve, WO 20376841
(2) PT/1/A/0230/015, "High Pressure Injection Motor Cooler Performance Test," after
repair of broken stem of 1LPSW-149, WO 20432659
(3) PT/1/A/0251/024, "HPI Full Flow Test," after replacement of the 1A high pressure
injection pump motor, WO 20319772
(4) PT/1/A/0152/015, "Main Steam System Valve Stroke Test," after preventive
maintenance on 1MS-93 air operated valve, WO 20225916
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
(1) The inspectors evaluated refueling outage U1R31 activities from October 17, 2020 to
November 12, 2020.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
6
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
(1) PT/1/A/0151/012 B, "Penetration 12B and 12C Leak Rate Test" on November 12,
2020
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
(1) The inspectors evaluated how the licensee identifies the magnitude and extent of
radiation levels and the concentrations and quantities of radioactive materials and
how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
(1) The inspectors evaluated radiological protection-related instructions to plant workers.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors evaluated licensee processes for monitoring and controlling contamination
and radioactive material.
(1) Observed licensee perform surveys of potentially contaminated material leaving Unit
1 Containment and the Radiological Control Area (RCA).
(2) Observed workers exiting Unit 1 Containment and the RCA during Unit 1 refueling
outage.
Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and
observation of radiological work activities.
(1) Unit 1 reactor head move, under RWP no. 1158, Rev. 18.
(2) Unit 1 valve work on Low Pressure Injection (LPI) System, under RWP no. 1069, Rev.
04.
(3) Unit 1 preventive maintenance on valves in reactor sump, under RWP no. 1100, Rev.
31.
(4) Unit 1 incore detectors work, under RWP no. 1176, Rev. 19.
High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (5 Samples)
The inspectors evaluated licensee controls of the following High Radiation Areas and Very
(1) Unit 1 Containment
(2) Filter Storage Location in Aux Building
(3) Resin Batch Tank Room in Radwaste Facility
(4) Unit 1 Reactor Coolant Blend Hold Up Tank Room in Aux Building
(5) Back Flush Storage Tank Room in Radwaste Facility
7
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section
03.06) (1 Sample)
(1) The inspectors evaluated radiation worker and radiation protection technician
performance as it pertains to radiation protection requirements.
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &
Transportation
Radioactive Material Storage (IP Section 03.01) (1 Sample)
(1) Inspectors evaluated the licensees performance in controlling, labelling, and securing
radioactive materials.
Radioactive Waste System Walkdown (IP Section 03.02) (1 Sample)
(1) Inspectors walked down accessible portions of the solid radioactive waste systems
and evaluated system configuration and functionality.
Waste Characterization and Classification (IP Section 03.03) (2 Samples)
The inspectors evaluated the licensees characterization and classification of radioactive
waste.
(1) RBT and LW DEMIN Resin Sample Comp
(2) Spent Fuel Pool Filters 2019
Shipment Preparation (IP Section 03.04) (1 Sample)
(1) The inspectors observed the preparation for shipment of radioactive material,
shipment no. 20-2020, LSA-1 DAW, for review against requirements.
Shipping Records (IP Section 03.05) (5 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through
a record review:
(1) RSR 18-2015, UN2908 Radioactive material, excepted package-empty packaging, 7,
Dewatered Mechanical Filters, 06/08/2018
(2) RSR 18-2019 UN332I, Radioactive material, low specific activity (LSA.11), 7, Fissile
Excepted. RD. Radionuclides, Resin, 08/26/2018
(3) RSR 20-2013, UN3321, Radioactive material, low specific activity (LSA-II), 7, Fissile
Excepted, RQ Radionuclides, Dewatered Resin, 05/20/2020
(4) RSR 19-2008, UN3321, Radioactive material, low specific activity (LSA-II), 7, Dry
Active Waste, 05/09/2019
(5) RSR 19-2003, UN3321, Radioactive material, low specific activity (LSA-II), 7, Fissile
Excepted, RQ Radionuclides, Ion Exchanged Resin, 02/20/2019
8
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
(1) 11/01/2019- 09/30/2020
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
(1) NCR 2341117, Human performance events trend from January through April, 2020
71153 - Followup of Events and Notices of Enforcement Discretion
Reporting (IP Section 03.05) (1 Sample)
(1) The inspectors reviewed the circumstances surrounding a potential report issue
involving external leakage from LPI relief valve 2LP-196 following a system pump
start
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71111.20
This violation of very low safety significance was identified by the licensee and has been
entered into the licensee corrective action program and is being treated as a non-cited
violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Oconee Unit 2 Technical Specification 5.4.1, Procedures, states, in part, that
written procedures shall be implemented covering the applicable procedures recommended
in Appendix A of Regulatory Guide (RG) 1.33, February 1978. RG 1.33, Quality Assurance
Program Requirements (Operation), Appendix A, Paragraph 9.a, Procedures for Performing
Maintenance requires that maintenance that can affect the performance of safety-related
equipment should be properly pre-planned and performed in accordance with written
procedures, documented instructions, or drawings appropriate to the circumstances.
Contrary to the above, on October 28, 2020, a heavy load was lifted over safety-related
equipment that exceeded the capacity of the turbine isle auxiliary crane and was
executed without use of a properly pre-planned lift plan. This failure resulted in a 29-
ton load being suspended from a 20 ton crane hook over both 4kV main feeder
buses of Unit 2 while it was operating at 100 percent power.
Significance/Severity: Green. The issue was of very low safety significance (Green)
because post-event inspections of the crane revealed no signs of damage, which implied
that the degraded condition did not increase the likelihood of a complete loss of 4kV
power and plant trip.
Corrective Action References: 2355166
9
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On November 3, 2020, the inspectors presented the RP inspection exit meeting
inspection results to Ed Burchfield, Site Vice President and other members of the
licensee staff.
- On January 21, 2021, the inspectors presented the integrated inspection results to J. Ed
Burchfield and other members of the licensee staff.
10
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.01 Procedures OP/0/B/1104/050 Weather Related Activities 005
71111.04 Corrective Action 2352508
Documents
Drawings OFD-121D-3.1 Flow Diagram of Emergency Feedwater System 46
Miscellaneous Clearance: OPS-3-20-FDW-3A MDEFWP MT-1498
Procedures EP/1/A/1800/001 Unit 1 EOP Enclosures 5.41-5.46 6
0Q
PT/3/A/0600/013 Motor Driven Emergency Feedwater Pump Test 070
TT/0/A/0251/090 EFM Hard Pipe Test November
20, 2015
Work Orders 20429375, 02145807, 20314232, 20421031
71111.05 Drawings O -0310-FZ-013 Auxiliary Building - Units 2 Fire Protection Plan Fire Area & 3
Fire Zone Boundaries Plan At EL 809+3
O -0310-K-011 Fire Protect AUX Bldg Unit 2 EL 809+3 016
O-0310-FZ-028 Fire Protection Plan Fire Area & Fire Zone Boundaries Plan 1
at Mezzanine EL. 796+6
O-0310-L-004 Turbine Building - Unit 1 Fire Protection Plan & Fire Barrier, 13
Flood, & Pressure Boundaries Plan at Mezzanine EL. 796+6
Fire Plans CSD-ONS-FS- Standard Operating Guideline 20 Key Equipment List by Fire 0
020 Zone
CSD-ONS-PFP- Pre-Fire Plan for U1 Auxiliary Building Elevation 822 000
CSD-ONS-PFP- Pre-Fire Plan for U1 Reactor Building 0
1RB
CSD-ONS-PFP- Pre-Fire Plan for U3 Turbine Building Elevation 796 0
CSD-ONS-PFP- Pre-Fire Plan for U2 Auxiliary Building Elevation 809 0
Procedures AD-EG-ALL-1520 Transient Combustible Control 13
71111.06 Corrective Action 01893113
11
Inspection Type Designation Description or Title Revision or
Procedure Date
Documents
Drawings OFD-124A-1.1 Flow Diagram of Low-Pressure Service Water System 54
Turbine Bldg (Low Pressure Service Water Pumps)
OFD-124B-1.1 Flow Diagram of Low-Pressure Service Water System 69
(Auxiliary Building Services)
Miscellaneous Clearance: OPS-1-20-LPS-1LPSW-1111-1381
S.D.3.2.16 Control of Passive Design Features 9
Selected Auxiliary Building Flood Protection Measures 001
Licensee
Commitment
(SLC), 15.9.11a
Procedures AP/1- Auxiliary Building Flood 023
2/A/1700/030
SD 1.3.5 Shutdown Protection Plan 38
Work Orders 20376855
71111.08P Drawings 5059431B BWI Replacement OTSG EDM/ASME/WEAR Array 0
Calibration Standard As-Built Drawing
5059439B BWI Replacement OTSG EDM/ASME/WEAR Array 0
Calibration Standard As-Built Drawing
Engineering Oconee Unit O1R31 Steam Generator Degradation 0
Evaluations Assessment
3013-TECR- BWXT Technologies, Inc. Steam Generator Condition 000
102789 Monitoring and Final Operational Assessment for Oconee
1 O1R30 Outage
Miscellaneous Framatome Steam Generator Team - Oconee Nuclear October 21,
Station Analysis Guidelines Training: O1R31 2020
MoreTech Certificate of Personnel Qualification: ET III-QDA 08/17/18
(Merriam)
MoreTech Certificate of Vision Examination (Merriam) 08/15/20
Procedures Duke Energy Eddy Current Guidelines for Oconee Nuclear 3
Stations Replacement Once-Through Steam Generators
(ROTSG)
Duke Energy ROTSG Site Technique Validation for Oconee 3
12
Inspection Type Designation Description or Title Revision or
Procedure Date
Nuclear Station
Duke Energy Fifth Interval Steam Generator Inservice 0
Inspection Plan Oconee Nuclear Station Unit 1, 2 & 3
Shipping Records S52593 Zetec Certificate of Conformance (Shipment ID 31634) 9/25/20
71111.11Q Miscellaneous Shutdown JITT power point training
AD-TQ-ALL-0420 Conduct of Simulator Training and Evaluation 14
OOP-OC-15JT-05 Night Shift Shutdown JITT 09
Procedures OP/1/A/1102/010 Controlling Procedure for Unit Shutdown 233
OP/1/A/1102/012 Degas of RCS and Pzr 022
OP/1/A/1103/004 Soluble Poison Control 108
OP/1/A/1103/004 RCS Boration 025
A
OP/1/A/1103/005 Pressurizer Operation 065
OP/1/A/1106/002 FDWPT Operation 041
B
OP/1/A/1106/008 Steam Generator Secondary Hot Soak, Fill, Drain and Layup 084
71111.13 Calculations OSC-11847 Oconee Low Pressure Turbine Replacement Heavy Lift Risk 4
Evaluation
Corrective Action 2352507
Documents
Miscellaneous Quarterly test data of EFM Hale Pump, Serial number EDM- July 21,
PU-0004 2020
Pre-Job Brief Form for operations regarding use of portable
pump during turbine building heavy lift
Pre-Job Brief Form for shift maintenance regarding use of
portable pump during turbine building heavy lifts
Standing Low Pressure Turbine Heavy Lift Mitigation Requirements 3
Instruction 20-04
Procedures AP/0/A/1700/025 Standby Shutdown Facility Emergency Operating Procedure 66
EP/1/A/1800/001 Unit 1 EOP Immediate Manual Actions and Subsequent 3
00 Actions
EP/1/A/1800/001 Unit 1 EOP Blackout 6
0B
13
Inspection Type Designation Description or Title Revision or
Procedure Date
EP/1/A/1800/001 Unit 1 EOP Enclosures 5.41-5.46 6
0Q
Work Orders 20030028
71111.15 Calculations IP/0/A/3011/013 Molded Case Breaker Test and Inspection Using Circuit 038
Breaker Tester Model PS250A Or PS9116
OSC-3144 Pressurizer Heat Losses 20
Corrective Action 02353911, 02357910, 02351598, 02351864, 02351624
Documents
Drawings O -0726-A 1/D Pressurizer Heater Fuse Blocks And Pressurizer Heater 2
Element Panels
O -0985-D-001 Connection Diagram Press HTR CAB (PHC) EOC System 10
O -2752-A-070 Interconnection Diagram 600V SSF Motor Control Center 15
3XSF Units F01A Thru F04C
O -2726 Interconnection Diagram Pressurizer Heaters 29
O EE-149-08 Elementary Diagram SSF Press. HTR Group B Bank 2 27
O EE-151-39 Elementary Diagram Reactor Coolant Makeup Pump Motor 8
Controls
O EE-349-01 Pressurizer Heaters Arrangement and Legend 25
O-0703-K One Line Diagram - 600V & 208V Essential Motor Control 82
Aux Pwr Sys SSF
OSS 251.00-00- 4X4X2 YARWAY m-MARC valve 2
0002
Engineering 114484
Changes
Miscellaneous 1A Motor Driven Emergency Feedwater Pump bearing
temperature charts
Sulzer Bingham Pumps Inc minimum flow requirements
Unit 1 Operator Logs for November 15, 2020
Clearance: PRT-1-20-1A MDEFWPOOS-0353
OM 251. I/B - 7100 Series ARC Valve, DMV-1000 Installation, 003
0670.001 Operation and Maintenance Guide
Procedures AD-OP-ALL-0102 Operational Decision Making 3
IP/0/A/0101/001 Low Risk Maintenance Configuration Control 19
14
Inspection Type Designation Description or Title Revision or
Procedure Date
IP/0/A/3011/013 Molded Case Breaker Test and Inspection Using Circuit 038
IP/0/A/3011/015 Removal and Replacement of Motor Control Center, 37
Panelboards, And Remote Starter Components
IP/O/A/0200/037 Pressurizer Heater Group B Surveillance 16
A
OP/1/A/1102/010 Controlling Procedure for Unit Shutdown 233
PT/1/A/0230/016 Auxiliary Shutdown Panel Systems Operability Test 5
PT/1/A/0251/014 Feedwater Check Valve Functional Test 017
Work Orders 20376561, 20376344, 20385098, 20434504, 20188761
71111.18 Calculations OSC-4151 Penetration Overcurrent Protection Type III 17
Corrective Action 1821414
Documents
Engineering 106427
Changes
71111.19 Drawings 0-422M-4 Instrument Details Steam To emergency FDWP Trip Valve 14
Control
O FD-124B-01-01 Flow Diagram of Low Pressure Service Water System 69
(Auxiliary Building Services)
OEE-117-47 Elementary Diagram 4160V Switchgear #1TC #9 - HP 13
Injection Pump Motor No. 1A
OEE-151-04 Elementary Diagram 1A HPI BWST Suction 1HP-24 20
OEE-151-04-01 Elementary Diagram 1A HPI BWST Suction 1HP-24 10
OEE-151-04-02 Elementary Diagram 1A HPI BWST Suction 1HP-24 05
OFD-101A-01.3 Flow Diagram of High Pressure Injection System (Charging 34
Section)
OM 245. - Gate Valve (Compact Design) 14
0925.003
OM 251. -- Outline Drawing For 6" CCI Drag Valve with Warming Disk, 1
0762.001 DMV-1265
OM 251. -- Outline Drawing For 6" CCI Drag Valve with Warming Disk, 1
0762.002 DMV-1265
Engineering EC418213
15
Inspection Type Designation Description or Title Revision or
Procedure Date
Changes
Miscellaneous Work Order Task Instructions #20319772-43
Work Order Task Instructions #20315362-41
1-LPSW-0149 Valve Packing Datasheet 0
1-LPSW-0149 Repair/Replacement Traveler
Enclosure 8.1
1-LPSW-0149 Reconciliation Report
Enclosure 8.3
1-MS-0093 Valve Packing Datasheet 4
AD-MN-ALL- Rotor Lift Plan
0009, Attachment
1
O1R31 Turbine Deck Heavy Lifts Site Notification Checklist 0
(Exhaust Hoods, Inner Casings, Rotors)
OSC-5674 1HP-24 Generic Letter 99-10 Test Acceptance Criteria 31
OSS-0254.00-00- MECH High Pressure Injection and Purification & Deborating 60
1001 Demineralizer Systems
REPORT NO. Duke Energy - Oconee HPI Pump Assessment 0
2000627.401
Procedures AD-MN-ALL-0009 Nuclear Rigging, Lifting, and Material Handling 7
AD/EG/ALL/1907 Cyber Security Sedia Protection Program 7
IP/0/A/3001/001 Limit Torque Preventive Maintenance 96
IP/0/A/3012/002 Disconnect and Reconnect of Air Operated Valves 32
IP/0/A/3012/007 A Diagnostic Testing Air Operated Valves Using 0
Teledyne/Quiklook System
MP/0/A/1200/001 Valve Packing Replacement and Adjustment 77
MP/0/A/1200/002 Valve Gate Disassembly, Repair, and Reassembly 69
MP/0/A/1200/197 Valve and Operator - CCI - Drag Valve - DMV- 1265 - 9
Disassembly, Repair, and Reassembly
MP/0/A/1300/020 Pump - Ingersoll-Rand - High Pressure Injection - Removal 59
and Replacement of Pump and Motor
MP/0/A/3009/017 Visual Inspection And Electrical Motor Tests Using Baker 3
16
Inspection Type Designation Description or Title Revision or
Procedure Date
A Equipment
MP/0/A/3009/020 Motor - QA - Electric - Removal, Replacement, And Post 42
B Maintenance Testing
PT/1/A/0152/011 High Pressure Injection System Valve Stroke Test 40
PT/1/A/0152/015 Main Steam System Valve Stroke Test 17
PT/1/A/0202/011 High Pressure Injection Pump Test 105
PT/1/A/0202/012 Component Test of ES Channels 1 & 2 30
PT/1/A/0230/015 High Pressure Injection Motor Cooler Performance Test 54
PT/1/A/0251/024 HPI Full Flow Test 52
PT/1/A/0600/012 Turbine Driven Emergency Feedwater Pump Test 106
TE-MN-ALL-0002 Foreign Material Exclusion Level and Controls Screening 2
Work Orders 20379772, 20432659, 20376841, 20225916, 20315632
71111.20 Calculations OSC-11805 Generic Load Drop Analysis for Turbine Building Operating 0
Floor Lifts
OSC-11847 Oconee Low Pressure Turbine Replacement Heavy Lift Risk 4
Evaluation
Corrective Action 02080235, 2354700, 2354722, 2355166, 2357873,
Documents 2353693, 2353503
Drawings OFD-100A-01-01 Flow Diagram of Reactor Coolant System 43
Miscellaneous Oconee 1 Cycle 32 Core Operating Limits Report
O3R30 Shutdown Safety Overview
O1BOC32 Reload Pattern
O1R31 Containment Report WC6487F October 20,
2020
OSS-0254.00-00- Design Basis Specification for Design Basis Events 35
4005
Procedures AD-MN-ALL-0009 Nuclear Rigging, Lifting, And Material Handling 7
AD-OP-ALL-0106 Conduct of Infrequently Performed Tests or Evolutions 4
AD-OP-ALL-0203 Reactivity Management 13
AD-OP-ALL-1000 Conduct of Operations 17
17
Inspection Type Designation Description or Title Revision or
Procedure Date
AD-OPS-ONS- ONS Operations Administrative Commitments 001
0001
AD-WC-ALL-0410 Work Activity Integrated Risk Management 9
AM/0/A/1400/002 Equipment Hatch - Reactor Building - Emergency Closing 10
B
AP/1/A/1700/026 Loss of Decay Heat Removal 28
CSD-MN-ALL- Duke Energy Nuclear Riggers Handbook March 2016
0009
CSD-MN-ALL- Fleet Technical Fundamentals Handbook 3
1000-00
IP/0/B/0200/027 B Ultrasonic Level Instrument Installation and Calibration 24
IP/0/B/0275/007 OTSG Temporary Level Indication Installation and Removal 9
MP/0/A/1500/009 Defueling/Refueling Procedure 76
MP/0/A/1500/032 Documentation of Fuel Assemblies and/or Component 5
Shuffle Within A Spent Fuel Pool
ONEI-0400-557 Oconee 1 Cycle 32 Final Core Load Map 0
OP/0/A/1102/026 Operations IPTE Pre-Job Briefings 31
OP/1/A/1102/001 Controlling Procedure For Unit Startup 322
OP/1/A/1102/010 Controlling Procedure for Unit Shutdown 233
OP/1/A/1102/012 Degas of RCS and Pzr 022
OP/1/A/1103/004 Soluble Poison Control 108
OP/1/A/1103/004 RCS Boration 025
A
OP/1/A/1103/005 Pressurizer Operation 065
OP/1/A/1103/011 Draining and Nitrogen Purging RCS 102
OP/1/A/1105/019 Control Rod Drive System 034
OP/1/A/1106/002 FDWPT Operation 041
B
OP/1/A/1106/008 Steam Generator Secondary Hot Soak, Fill, Drain and Layup 084
OP/1/A/1502/007 Operations Defueling/Refueling Responsibilities 93
OP/1/A/1502/009 Containment Closure Control 50
PT/0/A/0711/001 Zero Power Physics Test 075
18
Inspection Type Designation Description or Title Revision or
Procedure Date
PT/0/A/0750/002 Core Inspections Procedure 30
PT/0/A/0750/012 Development of Fuel Movement Instructions Procedure 51
PT/0/A/0750/018 Refueling Activities 24
PT/0/A/0775/015 Core Alignment Verification Procedure 15
PT/0/A/0811/001 Power Escalation Test 052
PT/1/A/0600/030 NI Overlap 001
SD 1.3.5 Shutdown Protection Plan 38
Work Orders 20376864, 20315632
71111.22 Corrective Action 2357829
Documents
Procedures PT/1/A/0150/034 Leak Rate History Record and Reactor Building Leak Rate 14
Verification
71124.08 Corrective Action 02355699
Documents
Resulting from
Inspection
Miscellaneous AD-RP-ALL-5002 10 CFR 61 RADIOACTIVE WASTE CLASSIFICATION 10/8/2019 -
9/19/2019
71153 Corrective Action 2345473, 2297905
Documents
19