IR 05000321/2025001
| ML25128A298 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/13/2025 |
| From: | Alan Blamey Division of Operating Reactors |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| IR 2025001 | |
| Download: ML25128A298 (25) | |
Text
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANTS UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000321/2025001 AND 05000366/2025001
Dear Jamie Coleman:
On March 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Edwin I. Hatch Nuclear Plants, units 1 and 2. On April 17, 2025, the NRC inspectors discussed the results of this inspection with Matthew Busch, Site Vice President and other members of your staff. The results of this inspection are documented in the enclosed report.
Two findings of very low safety significance (Green) are documented in this report. Two of these findings involved violations of NRC requirements. We are treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violations or the significance or severity of the violations documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at Edwin I. Hatch Nuclear Power Plants, units 1 and 2.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; and the NRC Resident Inspector at Edwin I. Hatch Nuclear Plants, unit 1 and 2.
May 13, 2025 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, Alan J. Blamey, Chief Reactor Projects Branch 3 Division of Operating Reactor Safety Docket Nos. 05000321 and 05000366 License Nos. DPR-57 and NPF-5
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000321 and 05000366
License Numbers:
Report Numbers:
05000321/2025001 and 05000366/2025001
Enterprise Identifier: I-2025-001-0025
Licensee:
Southern Nuclear Operating Company, Inc.
Facility:
Edwin I. Hatch Nuclear Plants, Unit 1 and 2
Location:
Baxley, GA
Inspection Dates:
January 01, 2025 to March 31, 2025
Inspectors:
J. Bell, Senior Health Physicist
J. Diaz-Velez, Senior Health Physicist
R. Easter, Resident Inspector
P. Niebaum, Senior Resident Inspector
A. Nielsen, Senior Health Physicist
D. Restrepo, Health Physicist
D. Strickland, Senior Reactor Inspector
Approved By:
Alan J. Blamey, Chief
Reactor Projects Branch 3
Division of Operating Reactor Safety
Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Edwin I. Hatch Nuclear Plants, 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
Unit 1 Reactor Core Isolation Cooling (RCIC) Rendered Inoperable Due to Human Error Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000321,05000366/2025001-01 Open/Closed
[H.12] - Avoid Complacency 71111.20 A Green self-revealed non-cited violation (NCV) of 10 CFR 50, Appendix B, Criterion XI, Test Control was identified when licensee personnel failed to follow test procedure 34SV-E51-010-2, RCIC Logic System Functional Test for unit 2. Specifically, licensee personnel installed electrical jumpers in a unit 1 panel instead of the unit 2 panel required by the procedure. As a result, on February 10, 2025, the unit 1 reactor core isolation cooling system was inadvertently isolated and rendered inoperable and unavailable for approximately 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
Failure to properly calibrate effluent radiation monitors Cornerstone Significance Cross-Cutting Aspect Report Section Public Radiation Safety Green NCV 05000321,05000366/2025001-02 Open/Closed
[H.6] - Design Margins 71124.05 The NRC inspectors identified a Green finding and associated NCV of Technical Specification 5.5.1, for the failure to properly calibrate effluent radiation monitors 2D11K601 and 2D11K602, in accordance with the Offsite Dose Calculation Manual requirements.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period at or near rated thermal power (RTP) and remained at or near RTP for the entire inspection reporting period.
Unit 2 began the inspection period at approximately 90 percent RTP due to the 10th and 12th stage 'A' feedwater heaters being out of service and the isolation of extraction steam to the 8th stage 'B' feedwater heater. Around January 10, the unit began a controlled coastdown in preparation for refueling outage 2R28. On February 8, a reactor shutdown was initiated from approximately 80 percent RTP, and the unit entered the refueling outage on February 9.
Following completion of the outage, a reactor startup commenced on March 14, and power ascension began. The main generator output breaker was closed on March 17, marking the end of the refueling outage. On March 19, the unit reached approximately 90 percent RTP.
Subsequently, on March 21, power was reduced to approximately 80 percent RTP due to removal of the 'B' condensate pump from service. The unit was shut down on March 26 for a maintenance outage to repair the pump. The unit was restarted on March 30, and power was raised in preparation for synchronizing to the grid, which occurred on April 1,
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 and during the onset of seasonal cold temperatures for the following systems during the week of January 6, 2025:
- Plant service water (PSW)
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 (i.e., tornado watch and warning)on March 16, 2025.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 'B' standby gas treatment (SBGT) system on January 7, 2025
- (2) Common '1A' and '1B' main control room air conditioning subsystems on January 14, 2025
- (3) Unit 2 high pressure coolant injection (HPCI) system on January 28, 2025
- (4) Unit 1 'A' SBGT system on January 29, 2025
- (5) Unit 2 'C' emergency diesel generator (EDG) on February 4, 2025
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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 1 reactor building 228-foot elevation (refuel floor) on January 3, 2025
- (2) Unit 2 reactor building 228-foot elevation (refuel floor) on January 3, 2025
- (3) Unit 1 northeast diagonal and HPCI room on January 8, 2025
- (4) Unit 2 low voltage switch yard on January 8, 2025
71111.08G - Inservice Inspection Activities (BWR)
BWR Inservice Inspection Activities Sample - Non-destructive Examination and Welding
Activities (IP Section 03.01)
The inspectors evaluated boiling water reactor non-destructive testing by reviewing the following examinations from February 17 - February 20, 2025:
(1)
1. Non-Destructive Examinations
Ultrasonic (UT) Exams
1. 2E11-1RHR-20-RS-5, valve-to-elbow, ASME Class 1
2. 2B31-1RCM-28AD-4, elbow to pipe, ASME Class 1
3. 2E51-1RCIC-4-D-16A, valve-to-penetration, ASME Class 1
Liquid Penetrant Exam
1. 2B11\2-26-03-1, pipe-to-pipe, ASME Class 1
Visual Exams
1. 2B11 I\H-121ID, perform EVT-1 of H5/V5 Weld in Cell Lane 46-43 from ID,
2. 2B11 I\M-8AB, VT-1 exam of middle core spray (CS) sparger bracket to
shroud (SB) at 60 deg, Weld 8, ASME Class 1 Welding Activities
1. SNC850244, replace residual heat removal (RHR) and CS Pump room cooler
cover bolts/cut and reweld piping to facilitate eddy current testing (ECT), ASME Class 3
2. SNC1804568, replace reactor building component cooling water piping to
accommodate new recirculation motor, ASME Class 2 Examinations with Relevant Indications Accepted for Continued Service
1. 2B11\2C-2-B, longitudinal weld on upper MID shell, UT exam, ASME
Class 1
2. 2B31-S32-H2, spring can, VT-3, ASME Class 1 Piping Support
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 the following:
1. Unit 2 train A CS pump in-service test (IST) on January 3, 2025
2. Unit 1 A cooling tower restoration on January 29, 2025
3. Unit 2 turbine building chiller swap on January 29, 2025
4. Unit 2 division 1 main steam line relay logic response time testing
on January 29, 2025
5. Unit 2 down power for refueling outage on February 8, 2025
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated just-in-time training prior to unit 2 down power for refueling outage on February 5 and February 6, 2025.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSC) remain capable of performing their intended function:
- (1) Unit 1 analog transmitter trip system (ATTS) maintenance rule (10 CFR 50.65)(a)(1))
evaluation.
- (2) SNC1797850, unit 2 B recirculation motor replacement and functional test reviewed on March 6, 2025.
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) Condition report (CR) 11130062, acceptance of the conditional release of nonconforming material for use on unit 1 'B' RHR pump.
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)
- (2) Unit 2, elevated risk due to A SBGT system outage on January 7, 2025 Unit 2, elevated risk due to reactor core isolation cooling (RCIC) system outage on
- (3) January 28, 2025 Unit 1 and unit 2, elevated risk due to the 2A EDG system outage on February 4, 2025
- (4) Unit 2, elevated risk (i.e., Yellow) for decay heat removal due to reactor pressure vessel head and piping not intact with cavity drained on March 3, 2025
- (5) Unit 1, elevated risk due to PSW conditionally critical during 1A PSW breaker preventive maintenance and cubicle inspection on March 25, 2025
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) CR 11062086, unit 1 C safety relief valve (SRV), 1B21-F013C, 2nd stage temperature is erratic.
- (3) CRs 11121610 and 11125821, evaluate high energy line break (HELB) impacts from partially obstructed HELB grating in unit 1 reactor building.
- (4) CR 11151026, PSW piping below minimal wall thickness.
- (5) CR11158186, unit 2 reactor pressure vessel head closure bolt no. 33 not installed.
- (6) CR 11152297, unit 2 snubber in torus bay identified to have a loose base bolt.
- (7) CR 11158154, indication on reactor pressure vessel (RPV) flange stud hole 33.
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (2 Samples)
- (1) The inspectors evaluated unit 2 refueling outage 2R28 activities from February 9 to March 17, 2025.
- (2) The inspectors evaluated unit 2 maintenance outage activities to repair the B condensate pump from March 26 to March 31, 2025.
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 (IP Section 03.01) (6 Samples)
- (1) SNC2270673, main control room air conditioner 1C run after relay replacement reviewed on January 21, 2025 (2)34SV-E51-002-2, unit 2 RCIC pump operability after high speed setpoint increase reviewed on January 29, 2025 (3)34SV-T46-003-2, unit 2 SBGT ventilation and operability after 'B' SBGT system outage on January 30, 2025 (4)34SV-C41-002-1, unit 1 standby liquid control (SBLC) pump operability test after A SBLC system outage on January 30, 2025 (5)34SV-R43-001-2, unit 2 A EDG monthly test after system outage on February 4, 2025 (6)52SV-B21-001-2, main steam isolation valve limit switch response and component inspection/repair on February 28, 2025
Surveillance Testing (IP Section 03.01) (4 Samples)
(1)34SV-E11-001-1, RHR pump operability for the unit 1 'B' and 'D' RHR pumps on January 13, 2025 (2)34SV-SUV-008-2, primary containment isolation valve operability for unit 2 reviewed on January 15, 2025 (3)34SV-E11-002-2, RHR valve operability for the unit 2 RHR loop B valves on January 21, 2025 (4)34SV-R43-020-2, Diesel Generator 2A loss of coolant accident LOCA/ loss of offsite power (LOSP) logic system functional test (LSFT) on February 13, 2025
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
(1)42SV-TET-001-2, primary containment periodic Type B and Type C leakage tests for penetration 26 on February 11 and 19,
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) Health physics personnel controlling material entering and exiting the radiologically controlled area (RCA) through an open vault door to the outside.
- (2) Personnel exiting the drywell contaminated area during the unit 2 outage (2R28).
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) Unit 2 'B' recirculation motor removal and replacement.
- (2) Unit 2 reactor vessel disassembly.
- (3) Feed water and CS system nozzles 15-year inservice inspections.
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 (VHRAs):
- (1) Reactor building east-west hallway posted VHRA.
- (2) Reactor water cleanup heat exchanger, 'A' pump room, and 'B' pump room posted locked high radiation areas (LHRA).
- (3) Unit 1 operating turbine enclosure LHRA.
- (4) Unit 2 traversing in-core probe room LHRA.
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 environmental control system filter testing in accordance with the ventilation filter testing program in 'A' and 'B' trains.
Temporary Ventilation Systems (IP Section 03.02) (1 Sample)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) Portable high-efficiency particulate air (HEPA) unit, Serial #13, used Refuel Floor 2/10/2025.
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) (1 Sample)
The inspectors evaluated the following internal dose assessments:
- (1) Tritium in-vitro bioassay results, torus diving, February 2024
Special Dosimetric Situations (IP Section 03.04) (1 Sample)
The inspectors evaluated the following special dosimetric situations:
- (1) Declared pregnant worker dosimetry records, January 1, 2023 through February 12, 2025.
71124.05 - Radiation Monitoring Instrumentation
Walkdowns and Observations (IP Section 03.01) (8 Samples)
The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:
- (1) Thermo Scientific, Small Article Monitor 12 at the main RCA exit (devices #289, and
- 286), and at the T-16 RCA exit (devices D21-N1929, and D21-N1927)
- (2) Gem 5 portal monitors at the main RCA exit (devices D21-N1903, and D21-N1904),and at the T-16 RCA exit (device D21-N1842)
- (3) Argos 5AB, personnel contamination monitors at the main RCA exit (devices D21-N1844, D21-N1900, D21-1901, and D21-N1902), and at the T-16 RCA exit (devices D21-N1853, and D21-N1848)
- (4) Ludlum, Model 3, survey meters at the radiation protection (RP) office (devices D21-N1861, and D21-N1875)
- (5) Telepole, survey meter at the RP office (device D21-1950)
- (6) Alpha contamination friskers in use at various radiological protection checkpoints in the field, including Ludlum Model 3000 #25023061
- (7) Ludlum Model 9-3, ion chamber survey meter at the unit 2 RP control point (drywell),
Serial Number (SN): 273437
- (8) Eberline Model RM-25, at unit 2 refuel floor exit, SN: 690
Calibration and Testing Program (IP Section 03.02) (13 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Unit 0, 1Z41N015A, Control Room Area Radiation Monitor, calibrated on August 3, 2023, and August 8, 2024
- (2) Unit 0, 1Z41N015B, Control Room Area Radiation Monitor, calibrated on January 28, 2023, and January 24, 2024
- (3) Mirion HNP-DO People Mover Whole-Body Counter, calibrated on July 30, 2024
- (4) HIDEX Liquid Scintillator Counter, SN: 300SL 425-201, calibrated March 5, 22024
- (5) Unit 2, 2D11-K621A, and 2D11-K621B, Drywell Wide-Range (Post LOCA) Radiation Monitors, calibrated on February 24, 2021 and February 17, 2023
- (6) Unit 2, 64CI-OCB-006-2, Off-Gas Pre-Treatment Radiation Monitor, calibrated on February 13, 2023
- (7) Unit 2, 64CI-OCB-007-0 Main Steam Line Radiation Monitor Channels A, B, C, and D, calibrated February 14, 2023
- (8) Counting Room High Purity Germanium Detector 2, LVCC0 geometry, calibrated on April 30, 2019
- (9) Counting Room High Purity Germanium Detector 3, LTBS geometry, calibrated on March 18, 2019
- (10) Unit 2, 2D11-K622A, Drywell Post LOCA Radiation Monitor, calibrated January 26, 2021, and January 10, 2023
- (11) Ludlum Model 3000 (Sn:25023080) with Alpha probe (Sn:PR403791), calibrated October 8, 2024
- (12) Mirion, Telepole II, SN:232921-054, calibrated February 10, 2025
- (13) Ludlum Model 9-3, Ion Chamber Survey Meter (SN: 358500), calibrated July 22, 2024 Effluent Monitoring Calibration and Testing Program Sample (IP Section 03.03) (3 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) Unit 2, 2D11K604, Liquid Radwaste Radiation Monitor, calibrated on August 10, 2021, and July 21, 2023
- (2) Unit 1, 1D11K600A, Plant Main Stack Radiation Monitoring, calibrated on May 30, 2024
- (3) Unit 1, 1D11K600B, Plant Main Stack Radiation Monitoring, calibrated on May 30,
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 through December 31, 2024)
- (2) Unit 2 (January 1 through December 31, 2024)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)
- (1) Unit 1 (January 1 through December 31, 2024)
- (2) Unit 2 (January 1 through December 31, 2024)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)
- (1) Unit 1 (January 1 through December 31, 2024)
- (2) Unit 2 (January 1 through December 31, 2024)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) February 10, 2024 through February 14, 2025 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) February 10, 2024 through February 14,
INSPECTION RESULTS
Unit 1 Reactor Core Isolation Cooling (RCIC) Rendered Inoperable Due to Human Error Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000321,05000366/2025001-01 Open/Closed
[H.12] - Avoid Complacency 71111.20 A Green self-revealed non-cited violation (NCV) of 10 CFR 50, Appendix B, Criterion XI, Test Control was identified when licensee personnel failed to follow test procedure 34SV-E51-010-2, RCIC Logic System Functional Test for unit 2. Specifically, licensee personnel installed electrical jumpers in a unit 1 panel instead of the unit 2 panel required by the procedure. As a result, on February 10, 2025, the unit 1 reactor core isolation cooling (RCIC)system was inadvertently isolated and rendered inoperable and unavailable for approximately 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
Description:
On February 10, 2025, with unit 1 in Mode 1 at rated thermal power and unit 2 shutdown for a refueling outage, the licensee was performing a logic system functional test for the unit 2 RCIC system in accordance with test procedure 34SV-E51-010-2, RCIC Logic System Functional Test. Step 13 in Section 4.4, RCIC Auto-Isolation Logic B Test, requires installation of electrical jumpers in panel 2H11-P926 which is a unit 2 panel in the common main control room (MCR). This step simulates a steam line high differential pressure. During the test, electrical jumpers were incorrectly placed inside a unit 1 MCR panel instead of a unit 2 MCR panel as directed by the procedure. As a result, the unit 1 RCIC steam supply isolation valve (2E51-F007) went closed which isolated RCIC and rendered the system inoperable and unavailable. This was immediately recognized by the unit 1 operations staff through several MCR alarms. The licensee restored the unit 1 RCIC system after approximately 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The licensee classified test procedure 34SV-E51-010-2 as a safety related procedure.
Corrective Actions: The licensee removed the electrical jumpers in the unit 1 panel and completed the unit 1 RCIC system standby alignment procedure which restored RCIC operability and availability.
Corrective Action References: Condition report (CR) 11150079 and corrective action report (CAR) 819309.
Performance Assessment:
Performance Deficiency: The failure to follow test procedure 34SV-E51-010-2 which required installation of electrical jumpers in a unit 2 MCR panel during testing of the unit 2 RCIC system was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Human Performance 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, a unit 1 RCIC steam supply isolation valve went closed because of the performance deficiency which rendered the unit 1 RCIC system inoperable and unavailable for approximately 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
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 screened this finding using Exhibit 2, Mitigating Systems Screening Questions of IMC 0609, Appendix A. The finding screened to Green, very low safety significance, because all the screening questions were answered as No.
Cross-Cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. This includes the effective use of appropriate error-reduction tools. In this case, licensee personnel involved in the installation of electrical jumpers did not adequately apply such tools. Specifically, both the performer and the peer checker failed to identify that the jumpers were being installed in a unit 1 panel, rather than the unit 2 panel specified in the procedure.
Enforcement:
Violation: 10 CFR 50, Appendix B, Criterion XI, Test Control requires in part, a test program shall be established to assure that all testing required to demonstrate that structures, systems, and components will perform satisfactorily in service is identified and performed in accordance with written test procedures. Contrary to this requirement, on February 10, 2025, licensee personnel failed to perform a logic system functional test for the unit 2 RCIC system in accordance with test procedure 34SV-E51-010-2, RCIC Logic System Functional Test.
Specifically, licensee personnel installed electrical jumpers in a unit 1 panel instead of the unit 2 panel as required by the procedure which isolated unit 1 RCIC and rendered the system inoperable and unavailable for approximately 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The licensee classified test procedure 34SV-E51-010-2 as a safety related procedure.
Enforcement Action: This violation is being treated as an NCVs, consistent with Section 2.3.2 of the Enforcement Policy.
Failure to properly calibrate effluent radiation monitors Cornerstone Significance Cross-Cutting Aspect Report Section Public Radiation Safety Green NCV 05000321,05000366/2025001-02 Open/Closed
[H.6] - Design Margins 71124.05 The NRC inspectors identified a Green finding and associated non-cited violation (NCV) of Technical Specification (TS) 5.5.1, Offsite Dose Calculation Manual (ODCM), for the failure to properly calibrate effluent radiation monitors 2D11K601 and 2D11K602, in accordance with the ODCM requirements.
Description:
The ODCM identifies unit 2 pre-treatment radiation monitors 2D11K601 and 2D11K602 as effluent radiation monitors in Table 3-1. The ODCM defines channel calibration as the adjustment, as necessary, of the channel output, such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors.
NRC inspectors reviewed calibration records of radiation monitors 2D11K601, and 2D11K602 using procedure 64CI-OCB-006-2 Pre-treatment Radiation Monitoring, and determined 1) the wrong calibration source output data was used; 2) the calibration source-detector setup lacked an alignment jig or tool to ensure adequate exposure of the active volume of the detector; 3) a fixed source-detector distance setup methodology was not appropriately used to ensure exposure distance repeatability; and 4) instrument calibration acceptance criteria, required by Updated Final Safety Analysis Report (UFSAR) Section 11.4.4.2, was not kept within +/- 15 percent. Additionally, the main steam line radiation monitors, and the post-LOCA (loss of coolant accident) monitors, as well as the unit 1 pre-treatment radiation monitors, were found to have the same issues.
Corrective Actions: The licensee entered the issue in their corrective action program. The licensee conducted industry benchmarking, obtained vendor support, and pulled historical records for additional review. The licensee indicated that after the applicable procedures are revised, the monitors in question will have the calibrations re-performed (as soon as reasonably achievable) with any adjustments to electronics needed to bring their response within the revised calibration acceptance criterion.
The licensee attempted to re-calibrate unit 2 pre-treatment radiation monitors, 2D11K601 and 2D11K602, using a proposed new methodology, but the radiation monitors were found to be outside the +/- 15 percent acceptance criteria required.
Corrective Action References: Condition Report (CR) 11162134
Performance Assessment:
Performance Deficiency: The failure to properly calibrate effluent radiation monitors, 2D11K601 and 2D11K602, per the UFSAR Section 11.4.4.2 and in accordance with the ODCM as required by TS 5.5.1, was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Plant Facilities/Equipment and Instrumentation attribute of the Public Radiation Safety cornerstone and adversely affected the cornerstone objective to ensure adequate protection of public health and safety from exposure to radioactive materials released into the public domain as a result of routine civilian nuclear reactor operation.
Specifically, the as-found condition of the effluent radiation monitors was out of the UFSAR-described acceptance criteria tolerance.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix D, Public Radiation Safety SDP. Specifically, the finding is associated with the radioactive effluent release program but with no dose impact to a member of the public and did not exceed the dose values in Appendix I to 10 CFR Part 50 and/or 10 CFR 20.1301(e),resulting in a very low radiological significance, which the Significance Determination Process (SDP) classifies as Green.
Cross-Cutting Aspect: H.6 - Design Margins: The organization operates and maintains equipment within design margins. Margins are carefully guarded and changed only through a systematic and rigorous process. Special attention is placed on maintaining fission product barriers, defense-in-depth, and safety related equipment. Specifically, the procedures in use were inadequate to ensure that the radiation monitors responded within the necessary range and accuracy to a known radiation source.
Enforcement:
Violation: Technical Specification 5.5.1 Offsite Dose Calculation Manual (ODCM), requires in part that the ODCM be established, implemented, and maintained. The ODCM requires, in part, that each gaseous effluent monitoring instrumentation channel be demonstrated operable by performance of a channel calibration. The ODCM defines channel calibration as the adjustment, as necessary, of the channel output, such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors.
The ODCM identifies radiation monitors 2D11K601 and 2D11K602 as effluent radiation monitors in Table 3-1.
Contrary to the above, as of March 7, 2025, the licensee failed to perform calibrations on the pre-treatment gaseous effluent monitors such that they responded within the necessary range and accuracy to a known radiation source.
Enforcement Action: This violation is being treated as an NCV, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified that no proprietary information was retained or documented in this report.
- On April 17, 2025, the inspectors presented the integrated inspection results to Matthew Busch, Site Vice President (SVP), and other members of the licensee staff.
- On February 20, 2025, the inspectors presented the in-service inspection results to Matthew Busch, SVP, and other members of the licensee staff.
- On February 14, 2025, the inspectors presented the RP inspection results to Matthew Busch, SVP, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Condition Report
(CRs)
11090278, 11090700, 11090736
Corrective Action
Documents
Resulting from
Inspection
CRs
11140676, 11140693, 11140695, 11141146
Miscellaneous
1-DT-21-X41-
00100(2)
Danger Tagout for 1X41B005A, Intake Structure Room
Heater 1A
Naturally Occurring Phenomena
20.6
Intake Structure Ventilation System
4.7
Cold Weather Checks
18.7
DI-OPS-36-0989
Cold Weather Checks
23.8
NMP-OS-017
Severe Weather
5.0
Procedures
NMP-OS-020
Hatch Station Response To Southern Company System
Alert Conditions
1.0
Work Orders
SNC1235494
07/08/2024
CR 11146329
NRC resident concern
01/28/2025
Corrective Action
Documents
Resulting from
Inspection
CR 11146740
Valve restraint required tightening based on NRC resident
question
01/29/2025
HPCI System
31.5
Diesel Generator Standby AC System
30.11
21.7
15.3
Procedures
Control Room Ventilation System
25.3
CR 11040584
Trouble Alarm on panel in PCR
01/18/2024
CR 11104855
08/24/2024
Corrective Action
Documents
CR 11108507
Fire Alarm Panel alarming in PCR Room
09/07/2024
Fire Plans
NMP-ES-035-
019-GL02-F12
U1 Reactor Building El. Below 130
1.0
Fire Plans
NMP-ES-035-
019-GL02-F17
U1 Reactor Building El. 228
1.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NMP-ES-035-
019-GL02-F34
U2 Reactor Building El. 228
1.0
NMP-ES-035-
019-GL02-F57
Unit 2 Main Power Transformer Yard El. 129
1.0
CR 10945502
FAC Component Alternate Calculation
2/03/2023
CR 10949041
SBLC ISI Pressure Test Equipment Issue
2/17/2023
Corrective Action
Documents
11020740
Eng Recommendation - Pipe Support Inspection
11/01/2023
Work Orders
SNC1857323
Repair Leak on 2E11-D002B
06/19/2024
Corrective Action
Documents
CR 11146794
Relay Logic Time Response Failures
01/29/2025
Normal Plant Shutdown
33.9
Core Spray Pump Operability
24.11
Relay Logic Response Time Testing Channel A
5.0
Procedures
Relay Logic Response Time testing In Mode 1 Channel A
2.1
Work Orders
SNC1011189
Relay Logic Response Time Testing
01/29/2025
CR 11129891
Unit 1 ATTS channel check UNSAT for 1E11-N655B/N656B
11/21/2024
CR 11130062
VP Approval is REQUIRED to accept/reject the conditional
release of nonconforming material
11/21/2024
CR 11136901
MRule CME criteria exceeded for A70-01
2/19/2024
Corrective Action
Documents
CR 11157186
H23355
Single Line Diagram 4160V Bus 2A & 2B
H26003
Recirculating System P & ID
Drawings
H27481
Reactor Recirc. Pump & ASD "A" System
EVAL-H-A70-
06730
ATTS (a)(1) review
01/14/2025
Engineering
Evaluations
TE 1167023
RR-1-2
2B31-C001B Reactor Recirc Pump Motor Uncoupled Run
FT
Reactor Recirculation System Recirculation Pump
Mechanical Seal Replacement
Reactor Recirculation Pump Maintenance
Procedures
NMP-ES-027
11.1
Work Orders
SNC 1797850
2B Recirc Pump motor replacement
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SNC1455927
Repair/Replace ATTS card 1E11N694D
03/18/2023
SNC1564256
Replace ATTS card and calibrate per applicable
09/11/2023
SNC2162038
Unit 1 ATTS channel check UNSAT for 1E11-N655B/N656B
11/22/2024
Calculations
U2 Phoenix
model
U2 Phoenix model
2/04/2025
Outage Safety Assessment
03/03/2025
NMP-OS-010
Protected train/division and protected equipment program
Procedures
NMP-OS-010-002
Hatch Protected Equipment Logs
2.6
Calculations
BH1-M-V005-0003
Reactor Building HELB Flow Model
11/11/2003
CRs
11070121, 11079222, 11090655, 11089513, 11081767,
11082238
CR 11151026
PSW piping below min wall thickness
2/13/2025
Corrective Action
Documents
CR 11152297
Snubber base bolt thread engagement
2/17/2025
009N7112
Hatch unit 2 RPV Closure Region Stress and Fatigue
Reconciliation to Address Bushing Modification
2/21/2025
FDDR 009N7732
Field Deviation Disposition Request Evaluation for
indications on RPV flange stud hole 33
03/06/2025
Engineering
Evaluations
Technical
Evaluations (TEs)
1153550, 1165673, 1170355
Reactor Vessel Reassembly (RPV Stud Elongation
Readings)
25.0
Adverse Condition Monitoring Plan - 1C SRV Leakage
04/18/2024
Miscellaneous
ODMI: 1-24-004
1C safety relief valve (SRV) 2nd stage leak
1.0
NDE Reports
S17H2U001
2/23/2017
Procedures
Failure of Safety/Relief Valves
10.5
SNC 1764525
2R28 - 2E11 - Snubber visual examination
2/13/2025
SNC 2327951
Replace snubber at location 2E11RHRR226A
2/24/2025
Work Orders
SNC1811373
Repair steam leak at 1E51-D003 cover
07/10/2024
RCIC Pump Operability
27.3
Procedures
RC-1-2
Alternate RCIC Turbine Speed Control Test
1.0
CR 11150238
PQ&S not validated/approved by end of shift
2/11/2025
Corrective Action
Documents
CR 11152551
PQ&S not validated/approved by end of shift
2/18/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR 11153378
PQ&S not validated/approved by end of shift
2/19/2025
CR 11155830
Training Impact Review - Throttling for 2E11F048B
2/27/2025
CR 11155830
Training Impact Review - Throttling for 2E11F048B
2/27/2025
CR 11155997
Missing Pipe Cap on unit 2 Vent Valve in Drywell
2/27/2025
CR 11155998
Crack on transformer drawer on 2R22-S006 FR 6
2/27/2025
CR 11158511
Multiple T48 valve model 9200 thrust washers found missing
03/07/2025
CR 11158873
Damaged Insulation in the Drywell
03/09/2025
CR 11152406
Inaccurate Time To Boil in Outage Safety Assessment
CR 11153274
Questioned tag placement position of RHR valve
2E11F017A
CR 11157616
2R28 Torus proper walkdown with NRC
03/05/2026
CR 11158760
Items identified during drywell closeout.
03/09/2025
Corrective Action
Documents
Resulting from
Inspection
CR 11160314
Seismic and housekeeping concerns inside U2 Reactor
Building
03/13/2025
Drawings
H10167
Refueling Floor Heavy Load Paths
13.0
H2R28 Shutdown Safety Assessment
01/09/2025
Hatch unit 2 Core, Cycle 29 Final Core Map
2/27/2025
2-CA-25-2P41-
04000
Tagout
2/15/2025
2-DT-25-2E11-
00091
Tagout
2/16/2025
Hatch Nuclear Plant Spring 2025 unit 2 Refueling Outage
Summarized LLRT Test Results Report
03/13/2025
Main Control Room Schedule Report
Feb. 2025
Maintenance Department Schedule Report
Feb. 2025
Miscellaneous
Fatigue
Management
Program
Documents
Operations A Team Schedule Report
Feb. 2025
Loss of Shutdown Cooling
6.26
Plant Startup
51.16
Startup System Status Checklist
15.11
Normal Plant Shutdown
33.9
Maintaining Cold Shutdown or Refuel Condition
16.4
Procedures
Drywell Closeout
7.23
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Torus and Torus Area Closeout
4.0
Decay Heat Removal System
19.3
LLRT Testing Methodology
13.1
Reactor Wide Range Level Indication
4.4
NMP-AD-003
Equipment Clearance and Tagging
33.1
NMP-AD-016
Fatigue Management Program
11.2
NMP-OM-002
Shutdown Risk Management
6.11
NMP-OS-010-002
Hatch Protected Equipment Logs
2.7
NMP-RE-007
Core Verification
6.0
Work Orders
SNC1155459
Perform Channel Calibration of 2B21N027 and 2B21R605
2/09/2025
Partially Completed Surveillance
01/14/2025
2A EDG Trip
CR 11142216
Partially Completed Surveillance
01/14/2025
CR 11143415
C MCR air conditioner tripped after starting
01/17/2025
CR 11143417
main power relay is faulty
01/17/2025
CR 11146518
Unit 2 RCIC oil level is low following special purpose run
01/29/2025
CR 11146552
RCIC pump/turbine new reference data
01/29/2025
CR 11147164
2B SBGT Flow High
01/30/2025
CR 11147167
2B SBGT Heater Not Energized
01/30/2025
CR 11148513
2/05/2024
CR 11151270
2A EDG Trip
2/13/2025
CR 11151726
EDG Industry Best Maintenance Practices
2/14/2025
Corrective Action
Documents
TE 1168944
IRT for Partially Completed Surveillance
01/14/2025
Drawings
H-26084
Hatch Unit 2 Primary Containment Purge & Inerting System
Form ENG-0135
Volumetric Leak Rate Monitor Local Leak Rate Test Data
Sheets for Valves 2T48-F319 and F320, Drywell Vent
Isolation Valves
2/11/2025
MIS-16-005
Unit 1 Fifth 10-Year Interval Pump Inservice Testing Basis
Document
3.0
Unit 2 Control Log
Unit 2 Control Log
01/08/2025
Miscellaneous
Unit 2 Control Log
Unit 2 Control Log
11/26/2024
Procedures
Standby Liquid Control Pump Operability Test
01/30/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Residual Heat Removal Pump Operability
01/08/2025
RHR Valve Operability
01/21/2025
RCIC Pump Operability
01/29/2025
Diesel Generator 2A Monthly Test
2/04/2025
Diesel Generator 2A LOCA/LOSP LSFT
2/14/2025
Primary Containment Isolation Valve Operability
08/27/2024
Primary Containment Isolation Valve OOperability
01/14/2025
Standby Gas Treatment Ventilation & Operability
01/30/2025
RC-1-2
Alternate RCIC Turbine Speed Control Test
01/29/2025
SNC1129763
01/30/2025
SNC1150432
Unit 2 MCR Level Indicator for 2A Fuel Oil Tank
2/20/2021
SNC1155232,
1155253,
1155292,
1155293
Outboard Main Steam Isolation Valve 24-Month Preventive
Maintenance
SNC1579391
RCIC Turbine Control System Setpoint
01/29/2025
SNC1637229
Primary Containment Isolation Valve Operability
11/26/2024
SNC1681030
01/08/2025
SNC1681045
01/08/2025
SNC1695773
1A SBLC IST
01/30/2025
SNC1710586
2A EDG Monthly Test
2/04/2025
SNC2262873
Perform 34SV-SUV-008-2 Section 4.3
01/14/2025
SNC2270673
Replace relays on 1C main control room air conditioner
01/17/2025
SNC2319920
Replace Overspeed Trip Switch for 2R43S001A
2/14/2025
Work Orders
SNC456365
evaluate replacement relays for MCREC condenser unit
09/26/2013
Corrective Action
Documents
Resulting from
Inspection
CRs
11151237, 11151643, 11151875, 11151877, 11151881
NMP-HP-501
Radiological Respiratory Protection Program
2.0
Procedures
NMP-HP-501-003
Inspection, Repair, and Storage of Non-SCBA Respiratory
Protection Equipment
1.2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NMP-HP-501-005
Inspection, Repair and Storage of the MSA G1 SCBA
3.0
NMP-HP-504
Quantitative Fit Testing of Individuals for Respiratory Use
5.0
SNC1137783
Testing of Control Room Habitability Filter Trains
2/11/2024
SNC805890
Testing of Control Room Habitability Filter Trains
05/26/2021
SNC839149
Testing of Control Room Habitability Filter Trains
01/21/2021
SNC988760
Testing of Control Room Habitability Filter Trains
04/14/2023
Work Orders
SNC992454
Testing of Control Room Habitability Filter Trains
01/16/2023
NMP-HP-107
Individual Radiation Exposure Records and Reports
Version 4.0
NMP-HP-107-F02
Declaration of Pregnancy
Version 1.0
Procedures
NMP-HP-108-001
Instruction for Issuing and Activating Dosimetry and
Updating Dose Records in HIS-20
Version 2.3
Unit 2, Pre-treatment Radiation Monitoring
2/13/2023
Main Steam Line Channel A
2/14/2023
Main Steam Line Channel B
2/14/2023
Main Steam Line Channel C
2/14/2023
Main Steam Line Channel D
2/14/2023
Calibration of Post-LOCA Monitors 2D11K622A
01/26/2021
Calibration of Post-LOCA Monitors 2D11K622A
01/10/2023
Calibration of Post-LOCA Monitors 2D11K622B
2/27/2021
Calibration of Post-LOLA Monitors 2D11K622B
2/27/2021
Calibration of Post-LOCA Monitors 2D11K622B
2/15/2023
Calibration of Post-LOCA Monitors 2D11K622C
2/27/2021
Calibration of Post-LOCA Monitors 2D11K622C
01/10/2023
Calibration of Post-LOCA Monitors 2D11K622D
01/26/2021
Calibration
Records
Calibration of Post-LOCA Monitors 2D11K622D
01/17/2023
Corrective Action
Documents
CRs
10992832, 11033362, 10963536, 10964305, 10980185,
11002375, 11011800, 11020950, 11064846, 11093894
Miscellaneous
IRIS Report
585807
PI Report
03/11/2024
IRIS Report
588449
PI Report
03/19/2024
71151
IRIS Report
588450
PI Report
03/26/2024