IR 05000269/2020004
| ML21053A386 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/22/2021 |
| From: | Margaret Tobin NRC/RGN-II/DRP/RPB1 |
| To: | Burchfield J Duke Energy Carolinas |
| References | |
| IR 2020004 | |
| Download: ML21053A386 (21) | |
Text
February 22, 2021
SUBJECT:
REISSUE - OCONEE NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000269/2020004 AND 05000270/2020004 AND 05000287/2020004
Dear Mr. Burchfield:
The U.S. Nuclear Regulatory Commission (NRC) has identified an error in NRC Inspection Report 05000269/2020004 AND 05000270/2020004 AND 05000287/2020004, dated February 4, 2021 (ADAMS Accession No. 21036A001). Specifically, the Plant Status and the Refueling and Other Outage Activities sections (IP 71111.20) had a typo in the dates listed. As a result, the NRC has reissued the report in its entirety to correct this error.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
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
Inspection Report
Docket Numbers:
05000269, 05000270, and 05000287
License Numbers:
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
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: 71111.2
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
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 20, 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:
- (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:
- (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)
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)
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) 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
- (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 18, 2020.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
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,
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.
04.
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 High Radiation Areas:
- (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 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) 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
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)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) 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:
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.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
OP/0/B/1104/050
Weather Related Activities
005
Corrective Action
Documents
2352508
Drawings
OFD-121D-3.1
Flow Diagram of Emergency Feedwater System
Miscellaneous
Clearance: OPS-3-20-FDW-3A MDEFWP MT-1498
Procedures
EP/1/A/1800/001
0Q
Unit 1 EOP Enclosures 5.41-5.46
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
Drawings
O -0310-FZ-013
Auxiliary Building - Units 2 Fire Protection Plan Fire Area &
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
at Mezzanine EL. 796+6
O-0310-L-004
Turbine Building - Unit 1 Fire Protection Plan & Fire Barrier,
Flood, & Pressure Boundaries Plan at Mezzanine EL. 796+6
Fire Plans
CSD-ONS-FS-
20
Standard Operating Guideline 20 Key Equipment List by Fire
Zone
CSD-ONS-PFP-
Pre-Fire Plan for U1 Auxiliary Building Elevation 822
000
CSD-ONS-PFP-
1RB
Pre-Fire Plan for U1 Reactor Building
CSD-ONS-PFP-
Pre-Fire Plan for U3 Turbine Building Elevation 796
CSD-ONS-PFP-
Pre-Fire Plan for U2 Auxiliary Building Elevation 809
Procedures
AD-EG-ALL-1520
Transient Combustible Control
Corrective Action
01893113
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Drawings
OFD-124A-1.1
Flow Diagram of Low-Pressure Service Water System
Turbine Bldg (Low Pressure Service Water Pumps)
OFD-124B-1.1
Flow Diagram of Low-Pressure Service Water System
(Auxiliary Building Services)
Miscellaneous
Clearance: OPS-1-20-LPS-1LPSW-1111-1381
S.D.3.2.16
Control of Passive Design Features
Selected
Licensee
Commitment
(SLC), 15.9.11a
Auxiliary Building Flood Protection Measures
001
Procedures
AP/1-
2/A/1700/030
Auxiliary Building Flood
23
SD 1.3.5
Shutdown Protection Plan
Work Orders
20376855
Drawings
5059431B
BWI Replacement OTSG EDM/ASME/WEAR Array
Calibration Standard As-Built Drawing
5059439B
BWI Replacement OTSG EDM/ASME/WEAR Array
Calibration Standard As-Built Drawing
Engineering
Evaluations
Oconee Unit O1R31 Steam Generator Degradation
Assessment
3013-TECR-
2789
BWXT Technologies, Inc. Steam Generator Condition
Monitoring and Final Operational Assessment for Oconee
O1R30 Outage
000
Miscellaneous
Framatome Steam Generator Team - Oconee Nuclear
Station Analysis Guidelines Training: O1R31
October 21,
20
MoreTech Certificate of Personnel Qualification: ET III-QDA
(Merriam)
08/17/18
MoreTech Certificate of Vision Examination (Merriam)
08/15/20
Procedures
Duke Energy Eddy Current Guidelines for Oconee Nuclear
Stations Replacement Once-Through Steam Generators
(ROTSG)
Duke Energy ROTSG Site Technique Validation for Oconee
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Nuclear Station
Duke Energy Fifth Interval Steam Generator Inservice
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
OOP-OC-15JT-05
Night Shift Shutdown JITT
Procedures
OP/1/A/1102/010
Controlling Procedure for Unit Shutdown
233
OP/1/A/1102/012
Degas of RCS and Pzr
2
OP/1/A/1103/004
Soluble Poison Control
108
OP/1/A/1103/004
A
RCS Boration
25
OP/1/A/1103/005
Pressurizer Operation
065
OP/1/A/1106/002
B
FDWPT Operation
041
OP/1/A/1106/008
Steam Generator Secondary Hot Soak, Fill, Drain and Layup 084
Calculations
OSC-11847
Oconee Low Pressure Turbine Replacement Heavy Lift Risk
Evaluation
Corrective Action
Documents
2352507
Miscellaneous
Quarterly test data of EFM Hale Pump, Serial number EDM-
PU-0004
July 21,
20
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
Instruction 20-04
Low Pressure Turbine Heavy Lift Mitigation Requirements
Procedures
AP/0/A/1700/025
Standby Shutdown Facility Emergency Operating Procedure
EP/1/A/1800/001
Unit 1 EOP Immediate Manual Actions and Subsequent
Actions
EP/1/A/1800/001
0B
Unit 1 EOP Blackout
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
EP/1/A/1800/001
0Q
Unit 1 EOP Enclosures 5.41-5.46
Work Orders
20030028
Calculations
IP/0/A/3011/013
Molded Case Breaker Test and Inspection Using Circuit
Breaker Tester Model PS250A Or PS9116
038
OSC-3144
Pressurizer Heat Losses
Corrective Action
Documents
2353911, 02357910, 02351598, 02351864, 02351624
Drawings
O -0726-A
1/D Pressurizer Heater Fuse Blocks And Pressurizer Heater
Element Panels
O -0985-D-001
Connection Diagram Press HTR CAB (PHC) EOC System
O -2752-A-070
Interconnection Diagram 600V SSF Motor Control Center
3XSF Units F01A Thru F04C
O -2726
Interconnection Diagram Pressurizer Heaters
O EE-149-08
Elementary Diagram SSF Press. HTR Group B Bank 2
O EE-151-39
Elementary Diagram Reactor Coolant Makeup Pump Motor
Controls
O EE-349-01
Pressurizer Heaters Arrangement and Legend
O-0703-K
One Line Diagram - 600V & 208V Essential Motor Control
Aux Pwr Sys SSF
OSS 251.00-00-
0002
4X4X2 YARWAY m-MARC valve
Engineering
Changes
114484
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.
0670.001
I/B - 7100 Series ARC Valve, DMV-1000 Installation,
Operation and Maintenance Guide
003
Procedures
AD-OP-ALL-0102
Operational Decision Making
IP/0/A/0101/001
Low Risk Maintenance Configuration Control
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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,
Panelboards, And Remote Starter Components
IP/O/A/0200/037
A
Pressurizer Heater Group B Surveillance
OP/1/A/1102/010
Controlling Procedure for Unit Shutdown
233
PT/1/A/0230/016
Auxiliary Shutdown Panel Systems Operability Test
PT/1/A/0251/014
Feedwater Check Valve Functional Test
017
Work Orders
20376561, 20376344, 20385098, 20434504, 20188761
Calculations
OSC-4151
Penetration Overcurrent Protection Type III
Corrective Action
Documents
21414
Engineering
Changes
106427
Drawings
0-422M-4
Instrument Details Steam To emergency FDWP Trip Valve
Control
O FD-124B-01-01
Flow Diagram of Low Pressure Service Water System
(Auxiliary Building Services)
OEE-117-47
Elementary Diagram 4160V Switchgear #1TC #9 - HP
Injection Pump Motor No. 1A
OEE-151-04
Elementary Diagram 1A HPI BWST Suction 1HP-24
OEE-151-04-01
Elementary Diagram 1A HPI BWST Suction 1HP-24
OEE-151-04-02
Elementary Diagram 1A HPI BWST Suction 1HP-24
OFD-101A-01.3
Flow Diagram of High Pressure Injection System (Charging
Section)
OM 245. -
25.003
Gate Valve (Compact Design)
OM 251. --
0762.001
Outline Drawing For 6" CCI Drag Valve with Warming Disk,
DMV-1265
OM 251. --
0762.002
Outline Drawing For 6" CCI Drag Valve with Warming Disk,
DMV-1265
Engineering
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Changes
Miscellaneous
Work Order Task Instructions #20319772-43
Work Order Task Instructions #20315362-41
1-LPSW-0149
Valve Packing Datasheet
1-LPSW-0149
8.1
Repair/Replacement Traveler
1-LPSW-0149
8.3
Reconciliation Report
1-MS-0093
Valve Packing Datasheet
AOV Test Datasheet
AD-MN-ALL-
0009, Attachment
Rotor Lift Plan
O1R31
Turbine Deck Heavy Lifts Site Notification Checklist
(Exhaust Hoods, Inner Casings, Rotors)
OSC-5674
1HP-24 Generic Letter 99-10 Test Acceptance Criteria
OSS-0254.00-00-
1001
MECH High Pressure Injection and Purification & Deborating
Demineralizer Systems
REPORT NO.
2000627.401
Duke Energy - Oconee HPI Pump Assessment
Procedures
AD-MN-ALL-0009
Nuclear Rigging, Lifting, and Material Handling
AD/EG/ALL/1907
Cyber Security Sedia Protection Program
IP/0/A/3001/001
Limit Torque Preventive Maintenance
IP/0/A/3012/002
Disconnect and Reconnect of Air Operated Valves
IP/0/A/3012/007 A Diagnostic Testing Air Operated Valves Using
Teledyne/Quiklook System
MP/0/A/1200/001
Valve Packing Replacement and Adjustment
MP/0/A/1200/002
Valve Gate Disassembly, Repair, and Reassembly
MP/0/A/1200/197
Valve and Operator - CCI - Drag Valve - DMV-1265 -
Disassembly, Repair, and Reassembly
MP/0/A/1300/020
Pump - Ingersoll-Rand - High Pressure Injection - Removal
and Replacement of Pump and Motor
MP/0/A/3009/017
Visual Inspection And Electrical Motor Tests Using Baker
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
A
Equipment
MP/0/A/3009/020
B
Motor - QA - Electric - Removal, Replacement, And Post
Maintenance Testing
PT/1/A/0152/011
High Pressure Injection System Valve Stroke Test
PT/1/A/0152/015
Main Steam System Valve Stroke Test
PT/1/A/0202/011
High Pressure Injection Pump Test
105
PT/1/A/0202/012
Component Test of ES Channels 1 & 2
PT/1/A/0230/015
High Pressure Injection Motor Cooler Performance Test
PT/1/A/0251/024
HPI Full Flow Test
PT/1/A/0600/012
Turbine Driven Emergency Feedwater Pump Test
106
TE-MN-ALL-0002
Foreign Material Exclusion Level and Controls Screening
Work Orders
20379772, 20432659, 20376841, 20225916, 20315632
Calculations
OSC-11805
Generic Load Drop Analysis for Turbine Building Operating
Floor Lifts
OSC-11847
Oconee Low Pressure Turbine Replacement Heavy Lift Risk
Evaluation
Corrective Action
Documents
2080235, 2354700, 2354722, 2355166, 2357873,
2353693, 2353503
Drawings
OFD-100A-01-01
Flow Diagram of Reactor Coolant System
Miscellaneous
Oconee 1 Cycle 32 Core Operating Limits Report
O3R30 Shutdown Safety Overview
O1BOC32
Reload Pattern
O1R31
Containment Report WC6487F
October 20,
20
OSS-0254.00-00-
4005
Design Basis Specification for Design Basis Events
Procedures
AD-MN-ALL-0009
Nuclear Rigging, Lifting, And Material Handling
AD-OP-ALL-0106
Conduct of Infrequently Performed Tests or Evolutions
AD-OP-ALL-0203
Reactivity Management
AD-OP-ALL-1000
Conduct of Operations
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AD-OPS-ONS-
0001
ONS Operations Administrative Commitments
001
AD-WC-ALL-0410
Work Activity Integrated Risk Management
AM/0/A/1400/002
B
Equipment Hatch - Reactor Building - Emergency Closing
AP/1/A/1700/026
Loss of Decay Heat Removal
CSD-MN-ALL-
0009
Duke Energy Nuclear Riggers Handbook
March 2016
CSD-MN-ALL-
1000-00
Fleet Technical Fundamentals Handbook
IP/0/B/0200/027 B Ultrasonic Level Instrument Installation and Calibration
IP/0/B/0275/007
OTSG Temporary Level Indication Installation and Removal
MP/0/A/1500/009
Defueling/Refueling Procedure
MP/0/A/1500/032
Documentation of Fuel Assemblies and/or Component
Shuffle Within A Spent Fuel Pool
ONEI-0400-557
Oconee 1 Cycle 32 Final Core Load Map
OP/0/A/1102/026
Operations IPTE Pre-Job Briefings
OP/1/A/1102/001
Controlling Procedure For Unit Startup
2
OP/1/A/1102/010
Controlling Procedure for Unit Shutdown
233
OP/1/A/1102/012
Degas of RCS and Pzr
2
OP/1/A/1103/004
Soluble Poison Control
108
OP/1/A/1103/004
A
RCS Boration
25
OP/1/A/1103/005
Pressurizer Operation
065
OP/1/A/1103/011
Draining and Nitrogen Purging RCS
2
OP/1/A/1105/019
Control Rod Drive System
034
OP/1/A/1106/002
B
FDWPT Operation
041
OP/1/A/1106/008
Steam Generator Secondary Hot Soak, Fill, Drain and Layup 084
OP/1/A/1502/007
Operations Defueling/Refueling Responsibilities
OP/1/A/1502/009
Containment Closure Control
PT/0/A/0711/001
Zero Power Physics Test
075
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PT/0/A/0750/002
Core Inspections Procedure
PT/0/A/0750/012
Development of Fuel Movement Instructions Procedure
PT/0/A/0750/018
Refueling Activities
PT/0/A/0775/015
Core Alignment Verification Procedure
PT/0/A/0811/001
Power Escalation Test
2
PT/1/A/0600/030
NI Overlap
001
SD 1.3.5
Shutdown Protection Plan
Work Orders
20376864, 20315632
Corrective Action
Documents
2357829
Procedures
PT/1/A/0150/034
Leak Rate History Record and Reactor Building Leak Rate
Verification
Corrective Action
Documents
Resulting from
Inspection
2355699
Miscellaneous
AD-RP-ALL-5002
CFR 61 RADIOACTIVE WASTE CLASSIFICATION
10/8/2019 -
9/19/2019
Corrective Action
Documents
2345473, 2297905