IR 05000445/2023002
| ML23192A835 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 07/14/2023 |
| From: | Greg Werner NRC/RGN-IV/DORS/PBB |
| To: | Peters K Vistra Operations Company |
| Werner G | |
| References | |
| IR 2023002 | |
| Download: ML23192A835 (16) | |
Text
July 14, 2023
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 -
INTEGRATED INSPECTION REPORT 05000445/2023002 AND 05000446/2023002
Dear Ken Peters:
On June 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Comanche Peak Nuclear Power Plant, Units 1 and 2. On July 13, 2023, the NRC inspectors discussed the results of this inspection with J. Lloyd, Senior Director, Engineering and Regulatory Affairs, 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, Gregory E. Werner, Chief Reactor Projects Branch B Division of Operating Reactor Safety Docket Nos. 05000445, 05000446 License Nos. NPF-87, NPF-89
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000445 and 05000446
License Numbers:
Report Numbers:
05000445/2023002 and 05000446/2023002
Enterprise Identifier:
I-2023-002-0004
Licensee:
Vistra Operations Company, LLC
Facility:
Comanche Peak Nuclear Power Plant, Units 1 and 2
Location:
Glen Rose, TX 76043
Inspection Dates:
April 1, 2023, to June 30, 2023
Inspectors:
B. Baca, Health Physicist
N. Day, Senior Resident Inspector
J. Ellegood, Senior Resident Inspector
D. Nani, Resident Inspector
D. Proulx, Branch Chief
E. Simpson, Nuclear Systems Scientist
R. Smith, Senior Resident Inspector
H. Strittmatter, Emergency Preparedness Inspector
Approved By:
Gregory E. Werner, Chief
Reactor Projects Branch B
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Comanche Peak Nuclear Power Plant,
Units 1 and 2, 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 began the inspection period at 100 percent reactor power. On June 16, 2023, Unit 1 tripped due to the loss of the 1-02 main feed pump. The site repaired the pump and restarted the unit on June 18, 2023. The licensee raised power to 78 percent with power limited due to a failure of a heater drain pump. Unit 1 remained at or near 78 percent power for the remainder of the inspection period.
Unit 2 began the inspection period at or near 100 percent power. On April 23, 2023, the licensee shutdown the unit for a planned refueling outage. On May 26, 2023, the licensee started Unit 2.
On May 30, 2023, Unit 2 reached 100 percent power and remained there for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed 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
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal hot weather for control room ventilation, station service water, and safety chill water systems on June 26, 2023.
71111.04 - Equipment Alignment
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
- (1) Unit 2, diesel generator starting air system for DG 2-02 on April 12, 2023 (2)circulating water intake structure dewatering pumps on April 17, 2023
- (3) Unit 2, temporary mid-loop level indication system on May 18, 2023
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 area AE, Unit 2, component cooling water pump 2-01 room and hallway on May 6, 2023 (2)fire area AB, Unit 2, centrifugal charging pump 2-01 room and hallway on May 6, 2023 (3)fire area EM, Unit 2, cable spreading room on June 14, 2022 (4)fire area EN, Unit 1, cable spreading room on June 14, 2022 (5)electrical and control building elevation 840'-6", technical support center on June 28, 2023
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill on June 13, 2023.
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) diesel generator jacket water heat exchanger 2-02
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during Unit 2 shutdown for refueling outage 20 on April 23, 2023.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated reactor startup just in time training on April 18, 2023.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Unit 1, safety chillers.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (6 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)equipment hatches demonstration of ability to close in required amount of time on April 24, 2023 (2)recovery of the dropped catwalk platform over the reactor cavity on April 25, 2023
- (3) Unit 2, unplanned orange risk due to planned yellow outage risk with a thunderstorm warning on April 26, 2023 (4)risk associated with vacuum fill on May 18, 2023
- (5) Unit 1, risk following trip of safety chiller 1-06 on May 4, 2023
- (6) Unit 2, reactor trip breakers not closing during planned maintenance on May 21, 2023
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 1, train B component cooling water to containment spray pump 1-03 cooler
- (2) Unit 2, reactor cavity due to dropped catwalk
- (3) Unit 2, reactor vessel head O-ring groves had indications of pitting corrosion around the inner O-ring seating surface and single indication on the outer O-ring on May 15, 2023
- (4) Unit 2, mode 6 readiness on May 17, 2023
- (5) Unit 2, fuel anomaly
- (6) Unit 2, cold leg 3 resistance temperature detector 2-TE-0430F for mode change on May 24, 2023
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) Units 1 and 2, replacement of safety injection pump lube oil coolers' service water flow transmitters (2)install switchyard digital fault recorder
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated 2RF20 from April 23 to May 26, 2023.
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (9 Samples)
- (1) Unit 2, post construction verification of pre outage scaffold in auxiliary feedwater pump rooms, component cooling water heat exchanger rooms, auxiliary building 810' elevation, and safeguards building 790' elevations install on April 11, 2023 (2)diesel generator 2-02 run, load, and load reject testing following mechanical governor replacement on May 2, 2023 (3)safety chiller 2-06 maintenance, clearance release, fill, and operational test on May 4, 2023 (4)turbine driven auxiliary feedwater pump 2-01, overspeed trip test following maintenance during refueling outage 20, on May 16, 2023 (5)safety chiller 1-06 maintenance following a trip on hi motor temperature, investigation, and repair, on May 5, 2023 (6)diesel generator 2-01 maintenance outage window on May 19, 2023
- (7) Unit 2, turbine driven auxiliary feedwater pump 2-01 following governor maintenance on May 25, 2023 (8)coolant charging pump 2-01 filter change and mounting ring repair and post
-maintenance testing on May 14, 2023 (9)motor driven auxiliary feedwater pump 2-01 performance run and pump curve verification following repairs on May 20, 2023
Surveillance Testing (IP Section 03.01) (5 Samples)
(1)installation of the hatch to confirm closure time within defense in depth contingency plan 2RF20-02, revision 0, on April 24, 2023
- (2) Unit 1, alignment neutron flux power range channels ion current gain and summing level amplifier for power range nuclear instruments N-41, N-42, N-43, and N-44 loop, on May 17, 2023 (3)polar crane PM review and verification of readiness prior to major lift operations for outage 2RF20 on April 28, 2023
- (4) Unit 2, residual heat removal flow and temperature indication systems 2-TI-0609, 2-TI-0613, and 2-FIS-0611 per work orders 4515269 and 21-347057 on May 12, 2023
- (5) Unit 1, reactor trip breaker test on June 17, 2023
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
- (1) Unit 2, local leakage rate test for pressurizer steam sample line outside reactor containment isolation valve 2-HS-4176 on May 2, 2023
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
(1)gold team drill on June 21, 2023.
71114.08 - Exercise Evaluation - Scenario Review
Inspection Review (IP Section 02.01 - 02.04) (1 Sample)
- (1) The inspectors reviewed the licensee's preliminary exercise scenario that was submitted to the NRC on May 18, 2023, (ADAMS Accession No. ML23138A407) for the exercise scheduled to occur on July 26, 2023. The inspectors discussed the preliminary scenario with K. Faver, Emergency Planning, and other members of the emergency preparedness staff on June 13, 2023. The inspectors' review does not constitute NRC approval of the scenario.
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) Observed the licensee conduct surveys of potentially contaminated packages/equipment from the radiologically controlled area for release offsite and workers exiting potential contaminated areas.
- (2) Evaluated the licensee's physical and programmatic controls for highly activated and contaminated non-fuel materials stored within the spent fuel pool.
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
(1)high risk radiological work and job coverage of steam generator nozzle dam installation and removal activities under radiation work permit (RWP) 20232400, task 50 (2)medium risk radiological work and job coverage of steam generator manway/diaphragm removal and installation activities under RWP 20232400, task 31 (3)medium risk radiological work and job coverage for eddy current inspection of steam generator tubes under RWP 20232400, task 30 High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (4 Samples)
The inspectors evaluated licensee controls of the following high radiation areas and very high radiation areas:
(1)fuel building Unit-1 fuel transfer tube, 860-foot elevation (2)fuel building Unit-2 fuel transfer tube, 860-foot elevation (3)fuel building train bay ladder, 810-foot elevation (4)fuel building filter carousel access port, 810-foot elevation 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.
71124.04 - 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) (3 Samples)
The inspectors evaluated the following internal dose assessments:
(1)six workers' internal dose assessment during 2021 (2)four workers' internal dose assessment during 2022 (3)two workers' internal dose assessment for 2023
Special Dosimetric Situations (IP Section 03.04) (2 Samples)
The inspectors evaluated the following special dosimetric situations:
- (1) One declared pregnant worker package
- (2) Six effective dose equivalents for external radiation exposure work packages involving the following radiation work permits:
2021-2400, "2RF20 Westinghouse Primary Side Steam Generator," revision 1 2021-2600, "2RF20 Westinghouse Refueling Activities," revision 1
2021-2604, "2RF19 Mechanical Stress Improvement Process - Westinghouse NuVision," revision 3
2021-2605, "2RF19 Interference Removal," revision 2
2022-1400, "1RF22 Westinghouse Primary Side Steam Generator," revision 1
2022-1603, "1RF22 Refuel In-Service Inspection, Alloy 600, Underwater Inspection, Reactor Head," revision
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
- (1) Unit 1 (April 1, 2022, through March 31, 2023)
- (2) Unit 2 (April 1, 2022, through March 31, 2023)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) October 1, 2022, through March 31, 2023 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) October 1, 2022, through March 31, 2023
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)circulating water system following through wall pipe leaks.
- (2) Unit 2, train B component cooling water through wall leak
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Follow-up (IP section 03.01)
- (1) The inspectors evaluated a Unit 1 trip due to low steam generator level and licensees response from June 16-18,
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On May 4, 2023, the inspectors presented the occupational radiation safety inspection results to A. Marzloff, Plant Manager, and other members of the licensee staff.
On June 13, 2023, the inspectors presented the emergency preparedness exercise scenario review inspection results to K. Faver, Scenario Writer, Emergency Planning, and other members of the licensee staff.
On July 13, 2023, the inspectors presented the integrated inspection results to J. Lloyd, Senior Director, Engineering and Regulatory Affairs, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
TR-YYYY-NNNN
23-001181-1, 2023-001181-17
Work Orders
2-113519, 22-241898
Corrective Action
Documents
EV-TR-2021-
007593-9
ODMI for CWIS CIRC WTR ACCESS AREA
Procedures
SOP-609B-DG-
V02
Train B DG Air System Valve Lineup
2/24/2021
Work Orders
21-613544
Fire Plans
FPI-403
AUXILIARY BUILDING ELEVATION 810'-6"
Fire Plans
FPI-502
Electrical and Control Building Unit 1 and 2 Battery Rooms,
2'-0" Elevation
Fire Plans
FPI-504
Electrical and Control Building Elevation 807'-0" Unit 2 cable
Spreading Room
Fire Plans
FPI-505
Electrical and Control Building Elevation 807'-0" Unit 1 cable
Spreading Room
Procedures
ABN-806A
Response to Fire in the Electrical and Control Building
Procedures
CPNPP/FPR
CPNPP Fire Protection Report Unit 1 and Unit 2
Procedures
FPI-507
Electrical & Control Building Elevation 840'-6"
Procedures
MSM-P0-3357
Emergency Diesel Engine Jacket Water Cooler Cleaning
Work Orders
21-813260
Corrective Action
Documents
CR-YYYY-NNNN
20-005256, 2023-003153
Corrective Action
Documents
TR-YYYY-NNNN
20-003081
Miscellaneous
CPNPP System Status: Safety Chilled Water
2/31/2022
Procedures
STI-744.01
Maintenance Rule Event Review Guide
07/28/2016
Corrective Action
Documents
IR 2023-003796
Unable to close reactor trip breakers from the control room.
Previous day Ops stated that breakers were able to be closed
locally but were not attempted to be closed remotely from
control room. Issue was found while trying to perform Pulser
check on Roc Control Cabinets IAW WO 21-846683.
05/25/2023
Procedures
STA-694
Station Verification Activities
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
STI-606.05
Station Troubleshooting Activities
Work Orders
21-846683
Corrective Action
Documents
CR-YYYY-NNNN
23-003454, 2023-002559, 2023-002777, 2023-003855
Drawings
M1-229
Flow Diagram Component Cooling Water
CP23
Procedures
MSM-C2-9901
Reactor Vessel Head Removal and Installation (Head)
10.0
Engineering
Changes
FDA-2020-
000022
Replace Units 1 and 2 safety injection pumps lube oil cooler
service water flow transmitters
Engineering
Changes
FDA-2020-
000059
Install switchyard digital fault recorder
Procedures
IPO-010B
Reactor Coolant System Reduced Inventory Operations
18.0
Procedures
MDA-402
Control of Load Handling Equipment
Procedures
SOP-101B
10.0
Work Orders
21-877905
Corrective Action
Documents
CR-YYYY-NNNN
23-003454, 2023-003153, 2023-003195, 2023-003748
Procedures
ETP-211B
Auxiliary Feedwater Pump Test
Procedures
ETP-304B
Turbine Driven Auxiliary Feedwater Pump Overspeed Test
4.0
Procedures
IPO-002A
Plant start-up from hot standby
Procedures
OPT-206B
AFW System
Procedures
SOP-609B
Diesel Generator System
Work Orders
21-796712, 23-185821, 23-95210, 23-95233, 23-95315,
23-95322, 6037488, 4515269, 21-347057, 22-376312,
2-376298, 21-846920, 23-195740, 21-842875, 23-162078,
23-185710, 23-185615, 23-117702, 21-945738, 21-945672
Miscellaneous
Onsite exercise guide
06/21/2023.
Miscellaneous
Comanche Peak Nuclear Power Plant 2023 Biennial
Emergency Preparedness Exercise Scenario
05/18/2023
Corrective Action
Documents
Issue Reports (IR-
) / Tracking
Reports (TR-)
22-000493, 2022-002998, 2022-005442, 2022-005860,
22-006261, 2022-006865, 2023-001201, 2023-001622,
23-003039, 2023-003111
Procedures
RPI-115
Alarm Response
Procedures
RPI-302
Radiation and Contamination Surveys
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
RPI-304
Radiological Posting and Labeling
Procedures
RPI-306
Personnel Contamination Monitoring
Procedures
RPI-315
Off-Normal RP Postings and Surveys
Procedures
RPI-602
Radiological Surveillance
Procedures
STA-650
General Health Physics Plan
Procedures
STA-656
Radiation Work Control
Radiation Surveys M-20230430-41
Auxiliary Building 842-foot Valve and Pipe Gallery
04/30/2023
Radiation Surveys M-20230501-31
Auxiliary Building 842-foot Valve and Pipe Gallery
05/01/2023
Radiation Surveys M-20230501-58
Auxiliary Building 842-foot Valve and Pipe Gallery
05/01/2023
Radiation Surveys M-20230503-19
Channel Head Survey for Steam Generator #3
05/04/2023
Radiation Surveys M-20230503-29
Channel Head Survey for Steam Generator #1
05/04/2023
Radiation Surveys M-20230503-30
Channel Head Survey for Steam Generator #2
05/04/2023
Radiation Surveys M-20230503-32
Channel Head Survey for Steam Generator #4
05/04/2023
Radiation Surveys M-20230503-67
Steam Generator #3 Platform Survey
05/02/2023
Radiation Work
Permits (RWPs)
23-2101
Spent Fuel Pool Cooling and Clean-up
Radiation Work
Permits (RWPs)
23-2101
2RF20 Operations Activities
Radiation Work
Permits (RWPs)
23-2400
2RF20 Westinghouse Primary Side Steam Generator
Radiation Work
Permits (RWPs)
23-2404
ISI, FAC, and associated activities
Radiation Work
Permits (RWPs)
23-2600
Westinghouse Refueling Activities
Work Orders
21-846953
ISI Examination
Work Orders
21-945672
Eddy Current Inspection of Steam Generator Tubes
Work Orders
21-945738
Eddy Current Inspection of Steam Generator Tubes
Work Orders
21-945985
Eddy Current Inspection of Steam Generator Tubes
Work Orders
21-946816
Eddy Current Inspection of Steam Generator Tubes
Corrective Action
Documents
Issue Reports (IR-
) / Tacking
Reports (TR-)
21-006545, 2022-000243, 2022-005506, 2022-005860,
22-006261, 2022-006388, 2022-006865, 2023-002953
Corrective Action
TR-YYYY-NNNN
23-003054
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Resulting from
Inspection
Miscellaneous
Comanche Peak Nuclear Power Plant, Radiation Protection
Department: Five Year Dose Reduction Plan - 2022-2026
April 2023
Miscellaneous
EV-TR-2022-
008755-1
Annual Energy Calculation of 2022
Procedures
RPI-105
Exposure Records
Procedures
RPI-115
Alarm Response
Procedures
RPI-302
Radiation and Contamination Surveys
Procedures
RPI-306
Personnel Contamination Monitoring
Procedures
RPI-402
Personnel Contamination Event Documentation
Procedures
RPI-501
In Vitro Sampling
Procedures
RPI-503
Operation of the Stand-Up Whole Body Counter
Procedures
RPI-507
Internal Dose Calculation
Procedures
RPI-508
Calibration of the Stand-Up Whole Body Counter
Procedures
RPI-509
Personnel Dosimetry Program
Procedures
RPI-515
Neutron Dose Measurement and Recording
Procedures
RPI-516
Dose Determination
Procedures
RPI-527
Quality Control of the Dosimetry Processing Program
Procedures
RPI-528
Multiple Dosimetry Badging
71151
Miscellaneous
22 Annual Radiological Effluents Release Report: January
1, 2022 - December 31, 2022
03/30/2023
71151
Miscellaneous
23 First Quarter Gaseous Status Summary Report
05/03/2023
71151
Miscellaneous
23 First Quarter Liquid Status Summary Report
05/03/2023
71152A
Corrective Action
Documents
CR-YYYY-NNNN
23-002559