IR 05000414/2022003
| ML22304A141 | |
| Person / Time | |
|---|---|
| Site: | Catawba  (NPF-035, NPF-052) |
| Issue date: | 10/31/2022 |
| From: | Eric Stamm NRC/RGN-II/DRP/RPB1 |
| To: | Simril T Duke Energy Carolinas |
| References | |
| IR 2022003 | |
| Download: ML22304A141 (18) | |
Text
October 31, 2022
SUBJECT:
CATAWBA NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000413/2022003 AND 05000414/2022003
Dear Tom Simril:
On September 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Catawba Nuclear Station. On October 25, 2022, 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 findings or violations of more than minor significance were identified during this inspection.
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, Eric J. Stamm, Chief Reactor Projects Branch 1 Division of Reactor Projects Docket Nos. 05000413 and 05000414 License Nos. NPF-35 and NPF-52
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000413 and 05000414
License Numbers:
Report Numbers:
05000413/2022003 and 05000414/2022003
Enterprise Identifier:
I-2022-003-0015
Licensee:
Duke Energy Carolinas, LLC
Facility:
Catawba Nuclear Station
Location:
York, South Carolina
Inspection Dates:
July 1, 2022, to September 30, 2022
Inspectors:
D. Rivard, Senior Resident Inspector
J. Austin, Senior Project Engineer
J. Bell, Health Physicist
P. Cooper, Senior Reactor Inspector
J. Diaz-Velez, Senior Health Physicist
S. Downey, Senior Reactor Inspector
C. Fontana, Emergency Preparedness Inspector
P. Gresh, Emergency Preparedness Inspector
B. Kellner, Senior Health Physicist
M. Kennard, Senior Operations Engineer
K. Kirchbaum, Operations Engineer
A. Nielsen, Senior Health Physicist
S. Sanchez, Senior Emergency Preparedness Inspector
N. Smalley, Resident Inspector
J. Walker, Emergency Response Inspector
Approved By:
Eric J. Stamm, 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 Catawba 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
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
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 or near 100 percent RTP. On September 10, 2022, the unit was shut down for the remainder of the inspection period for a scheduled refueling outage.
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 activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. 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.
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 Hurricane Ian on September 28, 2022, through September 30, 2022.
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding on September 30, 2022.
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)120VAC power inverter (1KSI) on July 28, 2022
- (2) Steam generator steam line pressure control (nitrogen bottle backup for steam generator power operated relief valves) on August 24, 2022
- (3) Emergency diesel generator 1B on August 31, 2022
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 train A, fuel handling ventilation exhaust system, on September 30, 2022.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 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 Area 02: Unit 2, auxiliary building, elevation 543, auxiliary feedwater (CA) pump room (rooms 260, 265, and 266) on August 24, 2022
- (2) Fire Areas 31 and 32: Unit 2, auxiliary building, elevation 543, train A shutdown panel, and train B shutdown panel (rooms 262 and 263) on August 24, 2022
- (3) Fire Area 36: Unit 2, auxiliary building, elevation 543, turbine driven CA pump control panel (room 261) on August 24, 2022
- (4) Fire Area 03: Unit 1, auxiliary building, elevation 543, CA pump room (rooms 250, 255, and 256) on August 25, 2022
- (5) Fire Areas 32 and 34: Unit 1, auxiliary building, elevation 543, train A shutdown panel and train B shutdown panel (rooms 252 and 253) on August 25, 2022
- (6) Fire Area 37: Unit 2, auxiliary building, elevation 543, turbine driven CA pump control panel (room 251) on August 25, 2022
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) Diesel generator room sump system
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Component cooling heat exchangers resistance factor degradation and the sites action item response
71111.07T - Heat Exchanger/Sink Performance Heat Exchanger (Service Water Cooled) (IP Section 03.02)
The inspectors evaluated heat exchanger performance on the following:
- (1) Unit 1 containment spray heat exchangers (1NSHXA, 1NSHXB)
- (2) Unit 2 diesel generator jacket water coolers (2KDHXA, 2KDHXB)
Heat Exchanger (Closed Loop) (IP Section 03.03) (2 Samples)
The inspectors evaluated heat exchanger performance on the following:
- (1) Unit 2 centrifugal charging pump motor coolers (2KCHX44, 2KCHX54)
- (2) Unit 1 residual heat removal (RHR) heat exchangers (1NDHXA, 1NDHXB)
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 September 19 - 22, 2022
1. Visual Examination (VT-2): bare metal visual examination of the reactor
pressure vessel upper head, ASME Class 1 (reviewed)
2. Eddy Current: pressurized-water reactor vessel upper head penetrations
nozzle 74 and nozzle 7 (observed)
3. Liquid Penetrant (PT): pressurized-water reactor vessel upper head
penetration nozzle 74 (reviewed)
4. Ultrasonic Examination: pressurized-water reactor vessel upper head
penetrations nozzle 74 and nozzle 7 (observed) The Inspectors evaluated the licensees boric acid control program performance.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)
- (1) Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on July 25-29, 2022.
Annual Requalification Operating Tests The inspectors evaluated the adequacy of the facility licensees annual requalification operating test administered on July 29, 2022.
Administration of an Annual Requalification Operating Test The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.
Requalification Examination Security The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.
Control Room Simulator The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
Problem Identification and Resolution The inspectors evaluated the licensees ability to identify and resolve problems associated with licensed operator performance.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (3 Samples)
- (1) The inspectors observed and evaluated operator performance in the main control room during the Unit 2 performance of licensee procedure OP/1/A/6350/005, Alternate AC Power Sources, enclosure 4.16, Shifting Train A 4.16 KV Essential Switchgear to Standby Transformer, on September 6, 2022.
- (2) The inspectors observed and evaluated licensed operator performance in the main control room during Unit 2 shutdown operation and preparing for refueling evolutions, on September 10, 2022.
- (3) The inspectors observed and evaluated licensed operator performance in the main control room during the Unit 2 performance of licensee procedure OP/2/A/6150 006, Draining the Reactor Coolant System, on September 14, 2022.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a recorded simulator requalification scenario and critique that contained power range nuclear instrument failure, loss of a component cooling water train, loss of letdown flow and restoration, reactor coolant system to RHR system leak outside containment, manual reactor trip, and emergency core cooling system actuation on August 10, 2022.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Work order (WO) 20546050, FACP9 (Fire Alarm Control Panel) needs parts replaced due to water intrusion
minimum flow isolation) did not open in the required flow range on September 26, 2022
- (3) NCR 20231492, 2A steam generator power operated relief valve sheared piping connection
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
- (1) NCR 2437486, independent nuclear oversight (NOS) audit - operator control room panel walkdowns on August 10, 2022
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 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) NCR 02435679, Emergency Conditional Vulnerability (CV) Prep Plan - Unit 1 Isophase Bus (IPB) Equipment Failure ([Fan] Damper Disconnected),on July 26, 2022
- (2) Unit 2 control rod movement test, on August 4, 2022
- (3) Safe shutdown facility out of service (OOS) for scheduled maintenance, on August 18, 2022
- (4) Nuclear service water train B strainer OOS for scheduled maintenance, on August 23, 2022
- (5) NCR 02439135, Units 1 and 2, "E" station air compressor motor failure, on August 24, 2022
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) NCR 2433814, 2A nuclear service water strainer fastener found missing upon inspection on July 11, 2022
- (2) NCR 2436542, 2A emergency diesel generator (EDG) engine cooling water (KD) leak on August 4, 2022
- (3) NCR 2436695, Motor control center 2EMXE breaker F02D tab broken on August 4, 2022
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Engineering change (EC) 419169, Evaluation of 2A Nuclear Service Water Strainer with Removed Tube Sheet Studs/Nuts, for WO 20514945
- (2) EC 420675, Reactor Coolant (NC) Hot Leg and Cold Leg Narrow Range Resistance Temperature Detectors, and EC 421569, Ultra RTD Shield Float at Device, on September 26, 2022
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
(1)1B nuclear service water strainer, WO 20475243
- (2) Fire alarm control panel 9, WO 20546050
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial)
The inspectors evaluated refueling outage C2R25 activities from September 10, 2022, to September 30, 2022.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:
Surveillance Tests (other) (IP Section 03.01) (5 Samples)
- (1) PT/1/A/4400/003 E, Component Cooling Miniflow Verification, on July 13 and 14, 2022
- (2) PT/1/A/4200/007 B, Centrifugal Charging Pump 1B Test, WO 20535019, on July 27, 2022
- (3) PT/2/A/4600/003 B, Quarterly Surveillance Items (Pressurizer Heaters), on July 28, 2022
- (4) PT/2/A/4600/002 A, Mode 1 Periodic Surveillance Items, on September 10, 2022
- (5) PT/2/A/4600/002 C, Mode 3 Periodic Surveillance Items, on September 10, 2022
RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)
- (1) PT/2/A/4150/001 D, NC (Reactor Coolant) System Leakage Calculations, on July 26, 2022
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) PT/2/A/4200/001 I, As Found Containment Isolation Valve Leak Rate Test, on September 19, 2022
71114.01 - Exercise Evaluation
Inspection Review (IP Section 02.01-02.11) (1 Sample)
- (1) The inspectors evaluated the biennial emergency plan exercise during the week of August 15, 2022. The simulated scenario began with a reactor coolant pump (RCP)experiencing increased vibrations and coincidental loose parts alarm received in the simulator control room. This was followed shortly by the same RCP failing and causing an automatic reactor trip. However, the reactor failed to automatically (and manually) trip from the simulator control room, thus meeting the criteria for declaration of an Alert. In addition, a main steam safety valve (MSSV) failed open, which resulted in a safety injection signal. Sometime later, a steam generator tube rupture occurred on the same line as the failed open MSSV, thus meeting the conditions for declaration of a Site Area Emergency. Once specific dose equivalent iodine values were reached, conditions for a General Emergency were met, and the offsite response organizations were able to demonstrate their ability to implement emergency actions.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated submitted emergency action level, emergency plan, and emergency plan implementing procedure changes during the week of August 15, 2022. This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) Simulator-based licensed operator requalification training evolutions involving shift operating crew was evaluated on August 19, 2022. The requalification scenario consisted of power range nuclear instrument failure, loss of component cooling train, reactor trip, safety injection actuation, and a loss of coolant accident.
71114.08 - Exercise Evaluation - Scenario Review
Inspection Review (IP Section 02.01 - 02.04) (1 Sample)
- (1) The inspectors reviewed and evaluated in-office, the proposed scenario for the biennial emergency plan exercise at least 30 days prior to the day of the exercise.
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 how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
- (1) Material stored in the Unit 2 spent fuel pool
- (2) Licensee surveys of material and personnel released from the radiologically controlled area (RCA)
Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
- (1) Unit 2 reactor vessel head lift
- (2) As Low As Reasonably Achievable (ALARA) Plan C2R25-22-12, Reactor vessel head cavitation peening
- (3) ALARA Plan C2R25-22-9, Reactor vessel head insulation replacement
- (4) Maintenance work in Unit 2 transfer canal High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)
The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas (VHRAs):
- (1) VHRA in Unit 2 lower containment allowing access to under vessel area
- (2) Locked High Radiation Area (LHRA) in Unit 2 spent fuel pool demineralizer room
- (3) LHRA in Unit 1 spent resin valve body room 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.
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Permanent Ventilation Systems (IP Section 03.01) (1 Sample)
The inspectors evaluated the configuration of the following permanently installed ventilation systems:
- (1) Main control room area ventilation
Temporary Ventilation Systems (IP Section 03.02) (1 Sample)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) Two high efficiency particulate air vacuum units used as engineering controls for reactor vessel head work
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees use of respiratory protection devices.
Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.
71124.04 - Occupational Dose Assessment
Source Term Characterization (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.
External Dosimetry (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee processes, stores, and uses external dosimetry.
Internal Dosimetry (IP Section 03.03) (2 Samples)
The inspectors evaluated the following internal dose assessments:
- (1) Internal dose evaluation for an intake on 4/17/21
- (2) Internal dose evaluation for an intake on 4/28/21
Special Dosimetric Situations (IP Section 03.04) (2 Samples)
The inspectors evaluated the following special dosimetric situations:
- (1) Records associated with monitoring of three current declared pregnant workers
- (2) Records associated with three cases where effective dose equivalent due to external exposure was used to assign external dose for reactor vessel head work in April 2021
71124.05 - Radiation Monitoring Instrumentation
Walkdowns and Observations (IP Section 03.01) (9 Samples)
The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:
- (1) Cronos-1, Enrad #12698, in use at dosimetry
- (2) Gem-5, Enrad #13351, in use at dosimetry
- (3) Argos-5AB, Enrad #12888, in use at RCA exit
- (4) Argos-5AB, Enrad #12887, in use at RCA exit
- (5) Ludlum 3030, Enrad #7949, in use at RCA exit
- (6) Ludlum 177, Enrad #13021, in use at RCA exit
- (7) Canberra iCam, Enrad #13256, in use in the auxiliary building (8)1EMF4, area radiation monitor of charging pump hallway (9)1EMF9, area radiation monitor for auxiliary building corridor
Calibration and Testing Program (IP Section 03.02) (14 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Cronos-1, Enrad #12698, in use at dosimetry, calibrated on 3/1/2022 and 3/2/2021
- (2) Gem-5, Enrad #13351, in use at dosimetry, calibrated on 7/21/2022 and 7/28/2021
- (3) Argos-5AB, Enrad #12888, in use at RCA exit, calibrated on 7/20/2022 and 7/27/2021
- (4) Argos-5AB, Enrad #12887, in use at RCA exit, calibrated on 7/20/2022 and 7/27/2021
- (5) Cronos-4, Enrad #12684, calibrated on 3/1/2022 and 3/2/2021
- (6) Counting Room Gamma Spectroscopy System (MCA001), calibrated on 12/6/2021
- (7) Unit 1 Containment High Range Monitor 1EMF53B, calibrated on 5/21/2020 and 10/27/2021 (WOs 20339353 and 20426800)
- (8) Canberra iCam, Enrad #13069, calibrated on 3/1/2021 and 2/28/2022
- (9) Ludlum 3030P scaler, Enrad #3734, calibrated on 6/30/2021 and 8/5/2022
- (10) Gooseneck air sampler, Enrad #1868, calibrated on 4/14/2020 and 3/3/2022
- (11) Ludlum 177 pancake frisker, Enrad #13021, calibrated on 10/6/2020 and 10/28/2021
- (12) Sirius hand and foot monitor, Enrad #12572, calibrated on 7/26/2021 and 7/20/2022
- (13) Telepole, Enrad #12176, calibrated on 3/9/2020 and 1/11/2022
- (14) Ludlum 9-3 ion chamber, Enrad #11929, calibrated on 9/28/2020 and 6/23/2022 Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (3 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) Waste Liquid Discharge Monitor 0EMF049, calibrated on 9/16/2020 and 4/21/2022 (WOs 20386001 and 20492179)
- (2) Unit Vent Gas Monitor (Normal Range) 1EMF36, calibrated on 5/24/2020 and 3/23/2022 (WOs 20329873 and 20469322)
- (3) Unit Vent Gas Monitor (High Range) 1EMF54, calibrated on 2/29/2016 and 6/16/2020 (WOs 2182582 and 20375784)
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)
- (1) Unit 1 (July 1, 2021, through June 30, 2022)
- (2) Unit 2 (July 1, 2021, through June 30, 2022)
MS09: Residual Heat Removal Systems (IP Section 02.08)===
- (1) Unit 1 (July 1, 2021, through June 30, 2022)
- (2) Unit 2 (July 1, 2021, through June 30, 2022)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) October 23, 2021, through August 2, 2022 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) May 29, 2021, through July 31, 2022
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) July 1, 2021, through June 30, 2022 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) July 1, 2021, through June 30, 2022 EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)
- (1) July 1, 2021, through June 30, 2022
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) NCR 02428722, boron poison rod assembly (BPRA) inadvertently lifted with spent fuel pool handling tool
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On July 28, 2022, the inspectors presented the licensed operator requalification program inspection results to John Hecker and other members of the licensee staff.
On August 18, 2022, the inspectors presented the emergency preparedness exercise inspection results to Tom Simril and other members of the licensee staff.
On August 30, 2022, the inspectors presented the triennial heat sink inspection results to Tom Simril and other members of the licensee staff.
On September 22, 2022, the inspectors presented the Unit 2 inservice inspection results to Tom Simril and other members of the licensee staff.
On September 30, 2022, the inspectors presented the radiation protection baseline inspection results to Tom Simril and other members of the licensee staff.
On October 25, 2022, the inspectors presented the integrated inspection results to Tom Simril and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CNC-1223.13-00-
0002
Acceptable RN Flow and Fouling in the NS Heat Exchangers
for One RN Pump Operation
Revision 10
CNC-1223.23-00-
0011
Component Cooling System Test Acceptance Criteria
Revision 17
CNC-1223.23-00-
22
Component Cooling System Heat Load and Flow
Requirements
Revision 11
Calculations
CNC-1223.59-01-
0005
RN Flow and Fouling Acceptance Criteria on KD Heat
Exchangers
Revision 16
Corrective Action
Documents
CRs (by Number)
28876
Corrective Action
Documents
Resulting from
Inspection
AD-RP-ALL-0004
Radiological Posting and Labeling
Revision 6
Procedures
AD-RP-ALL-002
Radiation and Contamination Surveys
Revision 2
CN22092100011
Air sample - Rx head inspection under south door
09/21/22
Radiation
Surveys
CN22092800023
Air sample - U2 Rx Head Peening South Door
09/28/22
AD-RP-ALL-2019
TEDE-ALARA Evaluations and DAC-Hour Tracking
Revision 4
Procedures
AD-RP-ALL-6002
Inspections of Self-contained Breathing Apparatus (SCBA)
and Associated Equipment
Revision 4
Corrective Action
Documents
AR #s:
2380765, 02386256, 02390738, 02427726, 02430505,
2431028, and 02442917
Various
09/09/2022
Corrective Action
Documents
Resulting from
Inspection
Engineering
Changes
0000419486
Qualification of Alternate Radioactive Chlorine Source for
EMF Calibrations [Serial Number Cl-36-09-1601 (CNS ID #
X-0688)
05/19/2021
Miscellaneous
001/06 / CHP-S-
D527 (Vendor
RT-11 Calibration Source Documentation including expected
detector dose rate response. [source used to calibrate post
2/23/2007
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
source number /
Licensee source
number)
accident high range detectors
D5-432 / X-0488
(Vendor Source
Number/Licensee
Source Number)
Certificate of calibration for electrodeposited Technetium 99
calibration source, 100 X 100 mm
07/10/2006
CSD-EP-CNS-
0101-01
EAL TECHNICAL BASIS DOCUMENT
Revision 3
CSD-EP-CNS-
0101-02
EAL Wall Charts (Hot and Cold)
Revision 1
ENRAD-PROC-
26
Calibration and QA of Canberra Argos Personnel Monitors
Revision 9
ENRAD-PROC-
857
Calibration and QA of Canberra Cronos Tool and Equipment
Monitor
Revision 3
Procedures
IP/0/B/3314/049
R
0EMF49 (Low Range) Liquid Monitor Channel Calibration
Revision 27