IR 05000321/2024004
| ML25030A356 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/05/2025 |
| From: | Alan Blamey NRC/RGN-II/DORS/PB3 |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| IR 2024004 | |
| Download: ML25030A356 (1) | |
Text
SUBJECT:
EDWIN I. HATCH - INTEGRATED INSPECTION REPORT 05000321/2024004 AND 05000366/2024004
Dear Jamie Coleman:
On December 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Edwin I. Hatch. On January 8, 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.
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, 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:
05000321/2024004 and 05000366/2024004
Enterprise Identifier:
I-2024-004-0017
Licensee:
Southern Nuclear Operating Company, Inc.
Facility:
Edwin I. Hatch
Location:
Baxley, GA
Inspection Dates:
October 01, 2024 to December 31, 2024
Inspectors:
J. Bundy, Senior Operations Engineer
R. Easter, Resident Inspector
D. Johnson, Sr Emergency Preparedness Specialist
P. Niebaum, Senior Resident Inspector
A. Nielsen, Senior Health Physicist
K. Schaaf, Operations Engineer
Approved By:
Alan J. Blamey, Chief
Reactor Projects Branch 3
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Edwin I. Hatch, 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
Type Issue Number Title Report Section Status LER 05000321/2024-004-00 LER 2024-004-00 for Edwin I. Hatch Nuclear Plant, Unit 1 Manual Reactor Trip During Hurricane Helene Due to Degrading Condenser Vacuum 71153 Closed NOV 05000321,05000366/20 2409001 Failure to Conduct Radiation Surveys EA-23139 92702 Closed NOV 05000321,05000366/20 2409002 Incomplete and Inaccurate Radiation Surveys EA-23139 92702 Closed
PLANT STATUS
Unit 1 began the inspection period in mode 4 following the September 27, 2024 manual scram due to a degrading main condenser vacuum associated with Hurricane Helene. On October 2, the unit was restarted and began raising power. On October 6, the unit achieved 100% rated thermal power (RTP). On December 14, 2024, power was reduced to approximately 70% RTP to perform a sequence exchange and main turbine valve testing. Operators began raising power and reached full RTP on December 15, 2024. The unit remained at or near RTP for the remainder of the inspection period with limited exceptions for planned evolutions such as rod pattern adjustments on December 17, 2024 and December 18, 2024.
Unit 2 began the inspection period at or near RTP. On December 7, 2024, the unit lowered power to approximately 70% RTP to perform main turbine valve testing. On December 9, 2024, the unit was raised to approximately 90% RTP. The unit remained at or near 90% RTP (due to isolation of two feedwater heaters) for the remainder of the inspection period with limited exceptions for planned evolutions such as rod pattern adjustments on November 16, 2024 and December 4,
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
71111.11 A - Licensed Operator Requalification Program and Licensed Operator Performance Requalification Examination Results (IP Section 03.03)
The licensee completed the annual requalification operating examinations and biennial written examinations required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), "Requalification Requirements," of the NRC's "Operator's Licenses." The inspector performed an in-office review of the overall pass/fail results of the individual operating examinations, the crew simulator operating examinations, and the biennial written examinations in accordance with IP 71111.11, "Licensed Operator Requalification Program and Licensed Operator Performance." These results were compared to the thresholds established in Section 3.03, "Requalification Examination Results," of IP 71111.11.
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered on November 13, 2024.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)
An inspection was performed to assess the effectiveness of the facility licensee in implementing requalification requirements identified in 10 CFR Part 55, Operators Licenses. Each of the following inspection activities was conducted in accordance with IP
===71111.11, Licensed Operator Requalification Program and Licensed Operator Performance.
- (1) The licensee completed the annual requalification operating examinations and biennial written examinations required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2),
"Requalification Requirements," of the NRC's "Operator's Licenses." The inspector performed an in-office review of the overall pass/fail results of the individual operating examinations, the crew simulator operating examinations, and the biennial written examinations in accordance with IP 71111.11, "Licensed Operator Requalification Program and Licensed Operator Performance." These results were compared to the thresholds established in Section 3.03, "Requalification Examination Results," of IP 71111.11.
- (1) Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on October 5, 2023.
Annual Requalification Operating Tests The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.
Administration of an Annual Requalification Operating Test The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.
Requalification Examination Security The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.
Control Room Simulator The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
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 activities:
- Unit 2, '2A' core spray system surveillance on October 1, 2024
- Unit 1, '1A' emergency diesel generator (EDG) monthly surveillance on October 1, 2024
- Unit 1, reactor and plant startup activities on October 2, 2024
- Unit 2, troubleshooting of 'B' 8th stage feedwater heater (FWH) on December 11, 2024 Licensed Operator Requalification Training/Examinations (IP Section 03.02)===
- (1) The inspectors observed and evaluated an annual operating exam in the simulator on October 15, 2024.
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 (SSCs) remain capable of performing their intended function:
- (1) Failure of the 2A residual heat removal service water (RHRSW) pump discharge check valve and its impacts on the 2C RHRSW pump, reviewed on December 19, 2024.
- (2) Failure of unit 1 and unit 2 main turbine valve fast acting solenoids (FAS), reviewed on December 17, 2024.
Aging Management (IP Section 03.03) (1 Sample)
The inspectors evaluated the effectiveness of the aging management program for the following SSCs that did not meet their inspection or test acceptance criteria:
- (1) Unit 1 drywell electrical penetrations 105C and 103A with unsatisfactory leakage test results during the refueling outage, reviewed on December 20, 2024.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 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 2, elevated risk due to 2B residual heat removal system outage on October 22, 2024
- (2) Unit 1, elevated risk due to 1A standby liquid control (SBLC) system outage on October 30, 2024
- (3) Unit 1 and unit 2, elevated risk due to high voltage and low voltage switchyard maintenance, intake structure pump pit cleaning and inspection, and the 1C plant service water (PSW) pump out of service for planned maintenance on November 45, 2024
- (4) Unit 2, risk mitigation measures associated with the return to service of the 'B' 8th stage feedwater heater during the week of December 9, 2024.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (2 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Condition Report (CR) 11116339, Unit 1 received alarm "602222 Pump B Seal Staging Flow High/Low," reviewed on October 8, 2024.
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)1P51C001A, 1A station service air compressor (SSAC) post maintenance functional test after repairs on October 7, 2024 (2)34SV-P41001-2, plant service water pump operability test after replacement of the 2A PSW pump, reviewed on October 21, 2024 (3)34SV-E51002-1, reactor core isolation cooling pump operability test following a turbine control system setpoint adjustment on October 29, 2024 (4)34SV-C41002-1, PMT after gearbox inspection and oil change of the 1A standby liquid control (SBLC) pump, on October 30, 2024
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.0102.04) (1 Sample)
- (1) The inspectors evaluated the maintenance and testing of the alert and notification system during the week of December 2, 2024.
71114.03 - Emergency Response Organization Staffing and Augmentation System
Inspection Review (IP Section 02.0102.02) (1 Sample)
- (1) The inspectors evaluated the readiness of the Emergency Response Organization during the week of December 2, 2024.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.0102.03) (1 Sample)
- (1) The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of December 2, 2024. This evaluation does not constitute NRC approval.
71114.05 - Maintenance of Emergency Preparedness
Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
- (1) The inspectors evaluated the maintenance of the emergency preparedness program during the week of December 2, 2024.
71114.06 - Drill Evaluation
Required Emergency Preparedness Drill (1 Sample)
- (1) Emergency preparedness (EP) drill with a loss of coolant accident, loss of offsite power, loss of containment that results in a radiological release, and fuel clad break(s) that resulted in a general emergency with protective action recommendations on November 12, 2024
Additional Drill and/or Training Evolution (1 Sample)
The inspectors evaluated:
- (1) Training drill involving emergency action level classifications after loss of reactor coolant system barrier due to emergency reactor pressure vessel depressurization on October 8,
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 (October 1, 2023, through September 30, 2024)
- (2) Unit 2 (October 1, 2023, through September 30, 2024)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (October 1, 2023, through September 30, 2024)
- (2) Unit 2 (October 1, 2023, through September 30, 2024)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (October 1, 2023, through September 30, 2024)
- (2) Unit 2 (October 1, 2023, through September 30, 2024)
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) July 1, 2023, through September 30, 2024.
EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) July 1, 2023, through September 30, 2024.
EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)
- (1) July 1, 2023, through September 30, 2024.
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program to identify potential trends associated with the scaffolding procedure implementation that might be indicative of a more significant safety issue. Specifically, the inspectors reviewed the following issues in the CAP:
- CR 11070320, Scaffolding in the intake structure did not have a minimum distance of 2" from a RHRSW strainer isolation valve
- CR 11101696, Scaffolding left in radwaste pump room
- CR 11108703, Scaffold ladder potentially unsafe
- CR 11135732, Scaffold near unit 2 division 1 RHRSW strainer is within 2 inches
- CR 11102407, NRC Resident Concern - scaffold pole left under the stairs to the SW diagonal 130'
- CR 11108054, NRC Resident Concern - scaffolding was installed within 2 inches of standby liquid control squib valve
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensees event reporting determinations to ensure it complied with reporting requirements.
- (1) LER 05000321/2024004-00, "Manual Reactor Trip During Hurricane Helene Due to Degrading Condenser Vacuum," dated November 19, 2024. (ADAMS Accession No. ML24324A187) The inspectors determined that the cause of the condition described in the LER was not reasonably within the licensee's ability to foresee and correct, and therefore was not reasonably preventable. No performance deficiency or violation of NRC requirements was identified. This LER is closed.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
===92702 - Follow-Up on Traditional Enforcement Actions Including Violations, Deviations, Confirmatory Action Letters, and Orders The inspectors conducted a follow-up inspection of the licensee's corrective actions in response to Notice of Violations (NOVs) 05000321, 05000366/202409001 and -02, issued on August 27, 2024 (ADAMS Accession No. ML24214A328).
Follow-Up on Traditional Enforcement Actions Including Violations, Deviations, Confirmatory Action Letters, and Orders===
- (1) The inspectors evaluated corrective actions that were implemented by the licensee to determine whether they were adequate to address the identified deficiencies and to prevent recurrence. The inspection consisted of a review of the licensee's response to the NOVs, dated June 17, 2024 (ML24169A622), all relevant corrective action documents including an Organizational and Programmatic causal analysis evaluation, interviews with six members of the radiation protection (RP) organization regarding expectations for radiological survey performance and documentation, review of 15 surveys of five different plant areas to screen for anomalous results, evaluation of procedural guidance for performance of surveys and RP conduct of operations, and review of corrective action program administrative procedures. The inspectors concluded that the licensee's corrective actions were appropriate. Based on the results of this review, no additional NRC actions are necessary.
For administrative purposes. The original apparent violation (AV) and the circumstances surrounding it were previously described in detail in the NRCs letter to Southern Nuclear Company Hatch on May 15, 2024 (ML24080A415), and was assigned violation tracking number AV 05000321, 05000366/202409001 and -02.
This AV tracking number was re-designated as NOV 05000321, 05000366/202409001 and -02 in NRC inspection report dated August 27, 2024, when the NOV was issued. The NOVs 05000321, 05000366/202409001 and -02, are now closed.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 23, 2024, the inspectors presented the biennial licensed operator requalification program inspection results to Andrew Belcher and other members of the licensee staff.
- On December 4, 2024, the inspectors presented the IP 92702 inspection results to Jason Butler and other members of the licensee staff.
- On December 5, 2024, the inspectors presented the emergency preparedness program inspection results to Matthew Busch, Site Vice President and other members of the licensee staff.
- On January 8, 2025, the inspectors presented the integrated inspection results to Matthew Busch, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
H-LTC-SE-00306
Simulator Guide for Annual Exam Scenario
2.0
Procedures
Plant Startup
10/02/2024
Corrective Action
Documents
Equipment Reliability Checklist for 2E11F005A, Residual
Heat Removal Service Water Pump Discharge Check
Valve Failure.
06/04/2024
Corrective Action
Documents
Cognitive trend on shorted solenoid coils
11/01/2024
Corrective Action
Documents
Main Turbine Valve Fast Dump Failures
10/24/2024
Corrective Action
Documents
CR 10774443
Corrective Action
Documents
CRs: 11067437,
10619830,
11068256,
11050453,
11051050
Corrective Action
Documents
Resulting from
Inspection
CR 11136854
Drawings
H-21039
Hatch Unit 2 RHRSW System P&ID
Engineering
Evaluations
TE 1164315
Create PMCR to increase turbine valve testing frequency
Engineering
Evaluations
TEs: 1043501,
1164173, 1152995
Technical Evaluations - Maintenance Rule Evaluations
Miscellaneous
Type B LLRT data sheets for electrical penetrations during
1R31
Miscellaneous
A-47039
License Renewal Aging Management Review Summary
2.0
Miscellaneous
E1108,
Suppression Pool
Cooling
E1104, RHRSW
Maintenance Rule SSC Function Consolidation and
Performance Criteria Selection Forms
11/12/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Vessel Injection
Miscellaneous
S-75930
PSW Pump and RHRSW Pump Reverse Rotation
Assessment
1.0
Procedures
Primary Containment Type B and Type C Leak Rate
Testing
30.3
Procedures
NMP-ES-027
11.1
Procedures
NMP-GM-002-F02
Cause Determination Report Summary
11/14/2024
Procedures
NMP-GM-002-F08
Organizational and Programmatic Checklist (OPC)
11/14/2024
Procedures
NMP-GM-002-F22
Equipment Reliability Checklist
11/14/2024
Work Orders
SNC1142889
Degraded insulation on SV #4 and CV #4
11/22/2024
Work Orders
SNC2147041
Replace all FAS on U1 from Refurbished to new
11/13/2024
Work Orders
SNC2147045
Remove/reinstall Turbine Building shield plugs
11/19/2024
Procedures
NMP-GM-031
On-Line Configuration Risk Management Program
9.4
Procedures
NMP-GM-031001
Online Maintenance Rule (a)(4) Risk Calculations
8.0
Procedures
NMP-OS-010
Protected train/division and protected equipment program
Procedures
NMP-OS-010002
Hatch Protected Equipment Logs
2.6
Corrective Action
Documents
CR 10710692,
10798439,
11136417
Corrective Action
Documents
CR 11116339,
10951460,
10961511,
11011345,
11061219
Drawings
H16066
Reactor Recirculation System PI&D
04/05/2016
Work Orders
SNC1747169,
2076887
Work Orders
SNC919984
Corrective Action
Documents
CR 11117400
1A SSAC output pressure low at 35 psig
10/09/2024
Procedures
Standby Liquid Control Pump Operability Test
10/30/2024
Procedures
Plant Service Water Pump Operability
10/20/2024
Procedures
Alternate RCIC Turbine Speed Control Test
1.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
SNC1964920,
SNC2082973, SNC
1579390
Procedures
Standard Emergency Plan Annex for Hatch Nuclear Plant,
Units 1 and 2
Rev. 9
Miscellaneous
Drill Scenario for Hatch EP Drill on November 12, 2024.
Miscellaneous
Hatch 24EX03 EP Drill Final Report
Miscellaneous
NMP-EP-142-F01
Emergency Notification Form
2.4
Procedures
H-LTC-SE-00314
Turbine Bldg Fan Flow Low, Gen H2 TCV auto failure,
HPCI inadvertent, MSL Break manually isolate, RCIC fails,
Emergency Depress
2.0
Procedures
NMP-EP-141002
Hatch Emergency Action level and Basis
5.0
Procedures
NMP-EP-142
Emergency Notifications
9.0
Procedures
NMP-EP-144
Protective Actions
11.0
Procedures
NMP-EP-300
SNC Emergency Preparedness Conduct of Operations
31.0
Procedures
NMP-EP-303
Drill and Exercise Standards
24.1
71151
Miscellaneous
Performance Indication Data Hatch Units 1 & 2 for period
10/1/20239/30/2024
Corrective Action
Documents
CR 11101696,
11108703,
11111441,
11135732
Corrective Action
Documents
Resulting from
Inspection
CR 11070320,
11102407,
11108054
Procedures
NMP-MA-010
Erecting, modifying, and disassembling scaffolding
4/17/2024
Procedures
NMP-MA-010-F03
Scaffolding Evaluation
1.1
Miscellaneous
Unit 1 Control Log
09/27/2024
Miscellaneous
Unit 2 Control Log
09/27/2024
Miscellaneous
Reactor Plant Event Notification Worksheet
09/27/2024
Miscellaneous
LER
05000321/2024004-
Manual Reactor Trip During Hurricane Helene Due to
Degrading Condenser Vacuum
11/19/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Scram/Transient Analysis
11/05/2024
Procedures
NMP-GM-020-F02
Event Personnel Statement
09/30/2024
Procedures
NMP-GM-020-F03
Event Recovery Report
2/05/2024
2702
Corrective Action
Documents
CR 11018617
2702
Procedures
NMP-AD-051
Work Verification
Version 9.0
2702
Procedures
NMP-HP-008
Radiological Protection Conduct of Operations
Version 4.14
2702
Procedures
NMP-HP-008001
Radiation Protection Standards and Expectations
Version 8.0
2702
Procedures
NMP-HP-009
Radiological Protection Fundamentals
Version 2.0
2702
Procedures
NMP-HP-300
Radiation and Contamination Surveys
Version 6.1