IR 05000498/2023001
| ML23121A105 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 05/03/2023 |
| From: | Patricia Vossmar NRC/RGN-IV/DORS/PBA |
| To: | Gerry Powell South Texas |
| References | |
| IR 2023001 | |
| Download: ML23121A105 (21) | |
Text
May 03, 2023
SUBJECT:
SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000498/2023001 AND 05000499/2023001
Dear G. T. Powell:
On March 31, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at South Texas Project Electric Generating Station, Units 1 and 2. On April 20, 2023, the NRC inspectors discussed the results of this inspection with you and other members of your staff.
The results of this inspection are documented in the enclosed report.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC Resident Inspector at South Texas Project Electric Generating Station, Units 1 and 2.
G. 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, Patricia J. Vossmar, Chief Projects Branch A Division of Operating Reactor Safety Docket Nos. 05000498, 05000499 License Nos. NPF-76, NPF-80
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000498 and 05000499
License Numbers:
Report Numbers:
05000498/2023001 and 05000499/2023001
Enterprise Identifier:
I-2023-001-0003
Licensee:
STP Nuclear Operating Company
Facility:
South Texas Project Electric Generating Station, Units 1 and 2
Location:
Wadsworth, TX 77483
Inspection Dates:
January 1, 2023, to March 31, 2023
Inspectors:
D. Antonangeli, Health Physicist
B. Baca, Health Physicist
J. Drake, Senior Reactor Inspector
G. Kolcum, Senior Resident Inspector
C. Stott, Resident Inspector
Approved By:
Patricia J. Vossmar, Chief
Projects Branch A
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at South Texas Project Electric Generating Station, 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
Failure to Maintain Design Control of Essential Cooling Water Valves Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000498/2023001-01 Open/Closed None 71152A The inspectors identified a Green finding and associated non-cited violation (NCV) of 10 CFR Part 50 Appendix B, Criterion III, Design Control, for the licensees failure to adequately maintain the design of essential cooling water butterfly isolation valves associated with the essential cooling water return piping from the emergency diesel generators. Specifically, the licensee failed to evaluate the material of the valve packing follower studs used in replacement essential cooling water valves and ensure they were compatible with the rest of the valve.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period at rated thermal power and commenced a reactor shutdown on March 17, 2023, to begin refueling outage 1RE24.
Unit 2 began the inspection period at rated thermal power. Unit 2 lowered power to 90 percent power on February 18, 2023, for main turbine steam inlet valve testing and returned to full power on February 19, 2023, and remained there for 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
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1, essential cooling water the week of January 9, 2023
- (2) Unit 1, train A essential cooling water while train B was inoperable for maintenance during the week of February 6, 2023
- (3) Unit 1, train A emergency diesel generator essential cooling water valves the week of February 21, 2023
- (4) Unit 1, train C emergency diesel generator essential cooling water valves the week of February 21, 2023
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 1, train B 125VDC on March 16, 2023.
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) Unit 2, train A electrical auxiliary building cable spreading room on January 18, 2023
- (2) Unit 2, mechanical auxiliary building heating, ventilation, and air conditioning intake and hot machine shop on February 14, 2023
- (3) Unit 2, mechanical auxiliary building heating, ventilation, and air conditioning outside exhaust equipment on February 14, 2023
- (4) Unit 1, main control room, fire area 01 and fire zone 34 on March 14, 2023
- (5) Unit 2, main control room, fire area 01 and fire zone 34 on March 14, 2023
- (6) Unit 1, containment on March 24, 2023
Fire Brigade Drill Performance Sample (IP Section 03.02) (2 Samples)
- (1) The inspectors evaluated the onsite fire brigade performance during a simulated fire at the Unit 2 channel II battery room on January 11, 2023.
- (2) The inspectors evaluated the onsite fire brigade performance during a simulated fire at the Unit 2 emergency switchgear area on January 18, 2023.
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated external flooding mitigation protections in the: Unit 1, essential cooling water pumphouse the week of January 9, 2023
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Ultimate heat sink the week of March 20, 2023
71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01)
The inspectors observed or reviewed records and reports to verify that the following nondestructive examination and welding activities were performed appropriately:
- (1) Ultrasonic Examination
Reactor coolant, 1-RC-0015, 8-RC-1324-BB1, pipe to elbow
Main steam, 1-WD-551-791, 30-MS-1001-GA2, pipe to pipe Main steam, 1-WD-551-841, 30-MS-1001-GA2, valve to pipe
Residual heat removal, 1P-RH-1106-KB2-1-A, FW-6, pipe to elbow Radiographic Examination
Residual heat removal, 1P-RH-1106-KB2-1-A, FW-6, pipe to elbow Dye Penetrant Examination
Pressurizer spray, RC-51, FW-001, valve to pipe
Pressurizer spray, RC-52, FW-001, valve to pipe Visual 3 Examination
Residual coolant, RC-0015, vessel support 12-RC-1125-BB1-A SH-V
Pressurizer spray, RC-51, FW-001, valve to pipe
Pressurizer spray, RC-52, FW-001, valve to pipe
Pressurizer, Base plate, 1-CS-117000 Welding Activities
Weld Process, o
Pressurizer spray, RC-51, FW-001, valve to pipe o
Pressurizer spray, RC-52, FW-001, valve to pipe PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection
Activities (IP Section 03.02) (1 Sample)
The inspectors verified that the license conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:
- (1) The inspector observed portions of the reactor vessel head inspection, penetration nozzles 1-9, 14-23, 25-27, 29-61,66,68,70,72, 75-78, including vent pipe, and general head area.
PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)
The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following evaluations:
- (1) 21-12971, Spent fuel pool purification loop 1a normal return header vent valve 1-FC-0087
22-00701, Spent fuel pool heat exchanger 1A outlet valve 1-FC-0087
22-02443 High head safety injection pump 1C shaft seal
22-02444 Containment spray pump 1B shaft seal
22-02446 High head safety injection pump 1B shaft seal
22-02447 Low head safety injection pump 1B shaft seal
22-02449 containment spray pump 1A shaft seal
22-02458 Low head safety injection pump 1A shaft seal
22-02612 Spent fuel pool heat exchanger 1A flange connection bolts
22-02936 Spent fuel pool demineralizer 1B inlet sample panel isolation valve 1-XPS-0162 stem packing 22-05120 Chemical and volume control system volume control tank outlet check valve 2R171XCV0212, body-bonnet joint
22-05122 Boric acid to Chemical and volume control system blender tee flow control valve 1-CV-FCV-0110A
22-09545 Low Head Safety injection pump 1A shaft seal PWR Inservice Inspection Activities Sample - Steam Generator Tube Inspection Activities (Section 03.04) (1 Partial)
The inspectors verified that the licensee is monitoring the steam generator tube integrity appropriately through a review of the following examinations:
(1)
(Partial)
No steam generator tube inspection activities performed during the outage.
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 a Unit 2 grid disturbance on February 15, 2023.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during operator training on plant cooldown to residual heat removal conditions on March 14, 2023.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (4 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) Unit 1, train A essential cooling water pump seal leakage maintenance on January 2, 2023
- (2) Unit 2, train B essential cooling water pump seal leakage maintenance on January13, 2023
- (3) Unit 1, train C emergency diesel generator on January 19, 2023
- (4) Unit 2, train A essential chiller the week of January 30, 2023
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) Unit 1, reactor vessel head inner O-ring inspection on March 20, 2023
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) Unit 1, planned entry into configuration risk management for train B 125VDC battery bank and inverter maintenance on January 11, 2023
- (2) Unit 1, planned entry into configuration risk management for train C 125VDC battery bank and inverter maintenance on January 17, 2023
- (3) Unit 1, planned entry into configuration risk management for train D 125VDC battery bank and inverter maintenance on January 24, 2023
- (4) Unit 1, yellow risk due to planned maintenance during the week of February 6, 2023
- (5) Unit 2, yellow risk due to planned maintenance during the week of February 21, 2023
- (6) Unit 1, white risk due to planned maintenance during the week of March 6, 2023
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (7 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 1, train B essential chiller 12 lube oil pump leaking on January 2, 2023
- (2) Unit 1, train A essential cooling water pump seal leakage inoperable on January 2, 2023
- (3) Unit 2, train B essential cooling water pump seal leakage on January 10, 2023
- (4) Unit 1, train C emergency diesel generator packing studs on January 19, 2023 (5)fire pump No. 1 temperature alarm on January 24, 2023
- (6) Unit 2, Tave channel inoperable after calibration on January 25, 2023
- (7) Unit 1, train A emergency diesel generator failed to secure after cooldown on February 1, 2023
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated 1RE24 on March 17, 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) (4 Samples)
- (1) Unit 1, train C essential chiller 12 lube oil pump maintenance on December 31, 2022
- (2) Unit 2, condensate polishing total dissolved solids radiation monitor maintenance on January 2, 2023
- (3) Unit 2, supplemental purge exhaust fan 21 train A maintenance January 2, 2023
- (4) Unit 1, turbine generator building drains radiation monitor maintenance on January 2, 2023
Surveillance Testing (IP Section 03.01) (3 Samples)
- (1) Unit 1, train A emergency diesel generator on January 5, 2023
- (2) Unit 1, train C emergency diesel generator on January 17, 2023
- (3) Unit 1, train A emergency diesel generator on February 1, 2023
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
(1)essential cooling water pump 1B inservice test on March 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 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) (3 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
(1)radiation technicians surveying potentially contaminated material leaving and workers exiting the radiologically controlled area for Units 1 and 2.
(2)radiological contamination controls regarding the safety injection valve replacement activities in Unit 1: glove bag, high efficiency particulate air (HEPA) unit, wetting supplies, and radiological vacuum.
(3)surveying, labeling, staging, and removal of radioactive trash bags from the reactor containment.
Radiological Hazards Control and Work Coverage (IP Section 03.04) (5 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
(1)radiation work permit (RWP) 2023-1510, "1RE24 - Maintenance and support in rooms 001, 003, and 307," task 3, covering scaffolding construction in residual heat removal room 307.
- (2) RWP 2023-1524, "1RE24 - Reactor head lift, upper internals movement in airborne areas <5 DAC, high radiological risk," revision 0, task1, covering activities associated with the reactor head lift.
- (3) RWP 23-1530, "1RE24 - Radiography," revision 0, task 2 with regard to locked high radiation area (LHRA) controls of radiography inside the bioshield and reactor containment.
- (4) RWP 2023-01531, "1RE24 - Cutout and replace of SI-0010B, medium radiological risk," task 22, covering safety injection valve (SI-0010B) machine cutting of the pipe ends, preparations for valve fit-up, and valve weld defect repair.
- (5) RWP 2023-01532, "1RE24 - Cutout and replace of SI-0010B, high radiological risk,"
task 22, covering the safety injection valve (SI-0010B) mechanical preparation of pipe ends (fluff and buff) for the new valve installation.
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) Unit 1 high radiation area bioshield entrances
- (2) Unit 1 LHRA incore instrument room 3
- (3) Unit1 LHRA residual heat removal room 307
- (4) Unit 1 LHRA room 2 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) (2 Samples)
The inspectors evaluated the following internal dose assessments:
(1)whole body count data for a group of maintenance workers (CR 2022-10593)
(2)positive whole body count data for a maintenance worker (CR 2022-11412)
Special Dosimetric Situations (IP Section 03.04) (2 Samples)
The inspectors evaluated the following special dosimetric situations:
- (1) four declared pregnant worker packages (2)one work group multi-pack badging package
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
- (1) Unit 1 (January 1, 2022, through December 31, 2022)
- (2) Unit 2 (January 1, 2022, through December 31, 2022)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)
- (1) Unit 1 (January 1, 2022, through December 31, 2022)
- (2) Unit 2 (January 1, 2022, through December 31, 2022)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)
- (1) Unit 1 (January 1, 2022, through December 31, 2022)
- (2) Unit 2 (January 1, 2022, through December 31, 2022)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) October 1, 2022, through December 31, 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) October 1, 2022, through December 31,
INSPECTION RESULTS
Failure to Maintain Design Control of Essential Cooling Water Valves Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000498/2023001-01 Open/Closed None 71152A The inspectors identified a Green finding and associated non-cited violation (NCV) of 10 CFR Part 50 Appendix B, Criterion III, Design Control, for the licensees failure to adequately maintain the design of essential cooling water butterfly isolation valves associated with the essential cooling water return piping from the emergency diesel generators. Specifically, the licensee failed to evaluate the material of the valve packing follower studs used in replacement essential cooling water valves and ensure they were compatible with the rest of the valve.
Description:
On January 17, 2023, the inspectors identified broken packing studs on essential cooling water valve EW-0092. This valve was installed in the essential cooling water return piping from diesel generator 13. The essential cooling water system supplies each emergency diesel generator with required cooling water from the ultimate heat sink.
Valve EW-0092 is a normally locked open valve and does not have a safety function to shut but does have a safety function to maintain a pressure boundary to ensure there is minimal leakage. The valve is normally only shut for convenience during maintenance work on the emergency diesel generator.
Emergency diesel generator 13 was already inoperable for maintenance. However, the licensee determined that the repair of the valve was required to maintain operability. The packing could have failed at any time prior to discovery rendering the emergency diesel generator inoperable and therefore unable to perform its safety function. The affected essential cooling water train was also declared inoperable in order to replace the valve.
The licensee performed a cause analysis and noted that valve EW-0092 was replaced with a stainless-steel valve on January 23, 2013. Design change package (DCP) 00-18220-3, November 3, 2005, Supplement 0, which the licensee used to approve the new stainless steel valve design, failed to discuss if there would be any other materials used on the valve.
Specifically, the valve packing studs were low alloy steel.
The installation work package noted there was a packing leak for EW-0092 found during the post maintenance testing. The valve packing studs were then tightened further to correct the packing leakage. The cause analysis states that this packing leakage likely accelerated galvanic corrosion between the stainless-steel valve body and low alloy steel packing studs.
The installation package failed to list any torque values, so it is indeterminate if the packing studs were also over torqued.
Corrective Actions: The licensee had previously declared emergency diesel generator 13 inoperable due to maintenance and replaced valve EW-0092. The licensee performed an extent of condition to ensure this condition was not present on the same style valves for emergency diesel generators 11, 22, and the supply essential cooling water valve to 13. The licensee scheduled replacement of the packing studs and packing glands for the remaining five valves with a material more suitable for contact with stainless steel.
Corrective Action References: condition report 2023-611
Performance Assessment:
Performance Deficiency: The licensees failure to adequately maintain the design of essential cooling water butterfly isolation valves associated with the essential cooling water return piping from the emergency diesel generators was a performance deficiency. Specifically, the licensee failed to evaluate the material of the valve packing follower studs used in replacement essential cooling water valves and ensure they were compatible with the rest of the valve.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Design Control attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the licensee failed to evaluate the modification for incompatibility of low alloy steel with the raw water of the essential cooling water system which could lead to corrosion, stress, and fatigue failure. The corrosion, stress, and fatigue failure of the packing gland bolts on the essential cooling water return valve resulted in the licensees determination that the valve needed to be replaced to maintain diesel generator operability.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors determined that the finding had very low safety significance (Green) because the finding describes a deficiency affecting the design of a mitigating SSC in which it maintained its operability or probabilistic risk assessment (PRA) functionality. Therefore, this finding did not represent a condition that affected the PRA functionality of the emergency diesel generator system per the significance determination process.
Cross-Cutting Aspect: None. No cross-cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance.
Enforcement:
Violation: Title 10 CFR Part 50, Appendix B, Criterion III, Design Control, requires, in part, that measures shall be established for the selection and review for suitability of application of materials, parts, equipment, and processes that are essential to the safety-related functions of the structures, systems and components.
Contrary to the above, from January 23, 2013, measures were not established for the selection and review for suitability of application of materials, parts, equipment, and processes that are essential to the safety-related functions of the structures, systems, and components. Specifically, the licensee failed to establish measures for the selection and review for suitability of application of essential cooling water valve packing studs that are essential to ensure adequate essential cooling water system inventory for completing the system's safety related functions.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On March 27, 2023, the inspectors presented the Unit 1 inservice inspection results to G. T. Powell, President and Chief Executive Officer and other members of the licensee staff.
On March 30, 2023, the inspectors presented the occupational radiation safety inspection results to G. T. Powell, President and Chief Executive Officer and other members of the licensee staff.
On April 20, 2023, the inspectors presented the integrated inspection results to G. T. Powell, President and Chief Executive Officer and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
CR-YYYY-NNNN
23-1680
Procedures
Fire Preplan Electric Auxiliary Building Channel II Battery
Room
Procedures
Fire Preplan Electrical Auxiliary Building Emergency
Switchgear Area
Procedures
Fire Preplan Electrical Auxiliary Building Cable Spreading
Room Train A
Procedures
Fire Preplan Mechanical Auxiliary Building HVAC Intake and
Hot Machine Shop
Procedures
Fire Preplan Mechanical Auxiliary Building HVAC Outside
Exhaust Equipment
Procedures
Procedures
STPEGS Fire Brigade
Corrective Action
Documents
CR-YYYY-NNNN
2007-1655, 2017,16376, 2017-22540, 2018-3751,
2018-6504, 2020-369, 2020-6488, 2021-12084,
21-12446, 2021-12584, 2021-12862, 2021-12935,
21-12971, 2022-437, 2022-471, 2022-564, 2022-621,22-700, 2022-701, 2022-1213, 2022-1626, 2022-1692,
22-1737, 2022-2223, 2022-2443, 2022-24444, 2022-2446,
22-2447, 2022-2449, 2022-2458, 2022-2612, 2022-2667,
22-2847, 2022-2936, 2022-5091, 2022-5120, 2022-5122
Corrective Action
Documents
Resulting from
Inspection
CR-YYYY-NNNN
23-2975, 2023-3052, 2023-3086, 2023-3140, 2023-3141,
23-3142, 2023-3143, 2023-3246
Drawings
0105-0100251
WNA
Replacement Reactor Vessel Head Project Closure Head
And Nozzle Assembly
Drawings
Top Head Insulation
Engineering
Engineering evaluation of ECW 2C traveling screen seismic
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Changes
CREE 18-6504
guides
Engineering
Changes
CREE 22-10201-
Boric Acid Leakage U2 Rx Vessel Head O-Ring
Engineering
Changes
CREE 23-3109
Stress evaluation for the Unit 1 Thermal fatigue 8" RH-1106,
RHR mixing Tee location
03/26/2023
Miscellaneous
LTR-CECO-20-
047
Evaluation of South Texas Unit 1 SG 1RE22 Scale Profiling
Miscellaneous
OPGP03-ZX-
0003
Station Self-Assessment Program Snapshot Self-
Assessment Plan
Miscellaneous
Plant Investment
Plan 13670C
ECW (Essential Cooling Water) Traveling Screen
Replacement
Miscellaneous
SG-CDMP-19-21
South Texas 1RE22 Steam Generator Degradation
Assessment
Miscellaneous
SG-CECO-20-002
South Texas Project Nuclear Operating Company 1RE22
Secondary Side Integrity Plan
Miscellaneous
ST-WN-NOC-20-
Transmittal of SG-CDMP-20-10, Revision 1, South Texas
Project Unit 1 Steam Generator
Cycle 22 Condition Monitoring and Cycles 23, 24, and 25
Final Operational Assessment
07/14/2020
Miscellaneous
Plan
Inservice Inspection Program Plan for The South Texas
Project Electric Generating Station Units 1 And 2
Miscellaneous
TR 1025145
Boric Acid Corrosion Guidebook
Procedures
ASME Section XI VE Visual Examinations
Procedures
0PEP10ZA0010
Procedures
0PEP10ZA0017
Magnetic Particle
Procedures
0PEP10ZA0023
Visual Component Supports
Procedures
0PEP10ZA0024
Visual Test 1 and Visual Test 3
Procedures
0001
General Welding Requirements
Procedures
0001A
ASME Repair-Replacement Welding Requirements
Procedures
0001A
ASME Repair-Replacement Welding Requirements
Procedures
ASME - ANSI B31.1 Welding Requirements
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0001B
Procedures
0001C
AWS/HVAC Welding Requirements
Procedures
0001D
Welding Documentation Requirements
Procedures
0002
Welding Procedure Specification Preparation and
Qualification
Procedures
0003
Welder Qualification and Certification
Procedures
0004
Control of Filler Materials
Procedures
0005
Control of Post Weld Heat Treatment
Procedures
0006
Arc Wire Thermal Spray Coatings
Corrective Action
Documents
CR-YYYY-NNNN
22-13087. 2023-323, 2023-2829, 2023-1130, 2022-13085
Corrective Action
Documents
CR-YYYY-NNNN
22-13085, 2022-13087, 2023-323, 2022-12066, 2023-611,23-934, 2023-786, 2023-1113
Engineering
Changes
CREE-07-15363-3
Corrective Action
Documents
CR-YYYY-NNNN
2006-12433, 2006-14117, 2013-11375, 2013-13380,
2016-12254, 2019-9961-9, 2020-3657-2, 2020-3657-4
Procedures
Development Phase
Procedures
Operations Training Guidelines
Procedures
Makeup to the Reactor Coolant System
Procedures
Residual Heat Removal System Operations
Procedures
Plant Cooldown
Procedures
Refueling LOCA
Procedures
Shutdown LOCA
Procedures
Loss of Residual Heat Removal
Procedures
COMS Actuation or Failure
Corrective Action
Documents
CR-YYYY-NNNN
23-1113, 2022-13085, 2023-15, 2022-12618, 2023-77,
22-13085
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
CR-YYYY-NNNN
23-611
Drawings
5Q159F22544,
sheet 1
Standby Diesel Shutdown Systems & Alarms
Drawings
5Q159F22545,
sheet 1
Standby Diesel Shutdown System
Drawings
5Q159F22546,
sheet 1
Standby Diesel Starting Air
Engineering
Changes
CREE 07-15363-3
Procedures
Standby Diesel 11(21) Operability Test
Procedures
Standby Diesel 13(23) Operability Test
Procedures
0018
Essential Cooling Water System Train B Testing
Work Orders
Work
Authorization
Number
655418, 655346, 657428, 657462, 627202, 627205, 655340
Corrective Action
Documents
CR-YYYY-NNNN
22-10348, 2022-10593, 2022-10613, 2022-10626,
22-10644, 2022-10679, 2022-10727, 2022-10735,
22-10786, 2022-10791, 2022-10805, 2022-10823,
22-11009, 2022-11010, 2022-11011, 2022-11012,
22-11105, 2022-11109, 2022-11142, 2022-11143,
22-11151, 2022-11193, 2022-11204, 2022-11235,
22-11236, 2022-11237, 2022-11238, 2022-11293,
22-11313, 2022-11396, 2022-11547, 2022-11553,
22-11554, 2022-11724, 2022-11830, 2022-12003,
22-12004, 2022-12005, 2022-12075, 2022-12298,
22-12362, 2023-00717, 2023-01371, 2023-02550,
23-02931, 2023-02957, 2023-03002, 2023-03284
Corrective Action
Documents
Resulting from
CR-YYYY-NNNN
23-03386
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Inspection
Miscellaneous
Air Sample Log - Reactor Containment Building: 03/16/2023
through 03/29/2023
03/29/2023
Procedures
Spent Fuel Pool Storage and Work
Procedures
Radiological Access Controls Standards
Procedures
ALARA Program
Procedures
Radiological Survey Program
Procedures
Radiological Postings and Warning Devices
Procedures
High Radiation Area Access Controls
Procedures
Radiation Work Permits/Radiological Work ALARA Reviews
Radiation
Surveys
117087
Refueling Pool
10/27/2021
Radiation
Surveys
117087
Reactor Cavity
10/27/2021
Radiation
Surveys
117141
Reactor Cavity
10/28/2021
Radiation
Surveys
23880
Refueling Pool
03/22/2023
Radiation
Surveys
24144
Inside Secondary Shield Wall
03/27/2023
Radiation
Surveys
24249
Inside Secondary Shield Wall
03/30/2023
Corrective Action
Documents
CR-YYYY-NNNN
21-09086, 2021-10477, 2022-00849, 2022-03755,
22-03756, 2022-03929, 2022-04223, 2022-04271,
22-04345, 2022-07492, 2022-07494, 2022-07993,
22-08430, 2022-0994, 2022-10626, 2022-10646,
22-10823
Corrective Action
Documents
Resulting from
Inspection
CR-YYYY-NNNN
23-03345
Miscellaneous
Dry active waste stream distribution report - common to both
units
2/01/2022
Miscellaneous
23 Neutron correction factor development memo
2/27/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Whole body count data for individuals with possible intakes
Miscellaneous
Declared pregnant workers assigned dose since last
inspection
Procedures
DLR Issue and Collection
Procedures
Evaluation of Intakes
Procedures
Personnel Exposure Investigation
Procedures
Determination of Skin Dose
Procedures
Biological Sample Collection
Procedures
Non-Routine Dosimetry Issue and Control
Procedures
DLR Dose Estimating and Dose Reporting
Procedures
Storage and Handling of Personnel TLDs
Self-Assessments Audit Report #22-
Radiological Controls Quality Audit Report
03/10/2022
71151
Corrective Action
Documents
CR-YYYY-NNNN
22-00087, 2022-04649, 2022-09238, 2022-10543,
22-10918, 2022-11105, 2022-11057, 2022-11142,
23-01064, 2023-01348
Corrective Action
Documents
CR-YYYY-NNNN
22-11764, 2022-11716, 2023-782, 2023-819, 2023-1497,
23-1498, 2023-1499, 2023-328, 2023-1496