IR 05000321/2023004
| ML24026A264 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/31/2024 |
| From: | Alan Blamey NRC/RGN-II/DRP/RPB2 |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| IR 2023004 | |
| Download: ML24026A264 (11) | |
Text
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000321/2023004 AND 05000366/2023004
Dear Jamie Coleman:
On December 31, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Edwin I. Hatch Nuclear Plant, Units 1 and 2. On January 18, 2024, the NRC inspectors discussed the results of this inspection with Jason Butler, Plant Manager, 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 2 Division of Reactor Projects Docket Nos. 05000321 and 05000366 License Nos. DPR-57 and NPF-5
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000321 and 05000366 License Numbers:
DPR-57 and NPF-5 Report Numbers:
05000321/2023004 and 05000366/2023004 Enterprise Identifier:
I-2023-004-0018 Licensee:
Southern Nuclear Operating Company, Inc.
Facility:
Edwin I. Hatch Nuclear Plant, Units 1 and 2 Location:
Baxley, GA Inspection Dates:
October 01, 2023, to December 31, 2023 Inspectors:
B. Caballero, Senior Operations Engineer R. Easter, Resident Inspector P. Gresh, Operations Engineer B. Kellner, Senior Health Physicist P. Niebaum, Senior Resident Inspector J. Walker, Sr Emergency Preparedness Inspector Approved By:
Alan J. Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Edwin I. Hatch Nuclear Plant, Units 1 and 2, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period at 100 percent rated thermal power (RTP). On October 7, 2023, power was reduced to approximately 91 percent RTP for a control rod pattern adjustment and returned to 100 percent on October 8. On October 21, power was reduced to approximately 84 percent RTP for a control rod pattern adjustment and returned to 100 percent on October 22.
Around November 2, unit operators responded to a reduced steam quality condition and made a series of core flow changes via reactivity management plans through the remainder of the inspection period. On November 3, power was reduced to approximately 73 percent RTP for a control rod pattern adjustment and returned to 100 percent on November 4. On November 18, power was reduced to approximately 75 percent RTP for a control rod pattern adjustment and returned to 100 percent on November 19. On December 2, power was reduced to approximately 78 percent for a control rod pattern adjustment and returned to 100 percent on December 3. On December 26, while at approximately 94 percent RTP, the unit began coasting down while maintaining reduced core flow for reduced steam quality. On December 30, unit power was reduced to approximately 80 percent RTP due to an electro-hydraulic control fluid leak that impacted the operation of the number 2 main turbine control valve. The unit remained at that power level through the end of the inspection period.
Unit 2 began the inspection period at 100 percent RTP. On November 1, 2023, power was reduced to approximately 58 percent to remove the A reactor feed pump (RFP) and turbine from service due to a feedwater pipe break on a small-bore drainpipe. Following the removal of the A RFP from service, the B RFP tripped and unit operators inserted a manual scram due to the loss of feedwater. Later, on November 1, the unit was cooled down to Mode 4 for equipment repairs. Following repairs, unit startup began on November 5. The main generator was tied to the electrical grid on November 7, and the unit was returned to 100 percent RPT on November 10. On November 12, power was reduced to approximately 90 percent RTP for a control rod adjustment and returned to 100 percent on November 13. On November 25, power was reduced to approximately 87 percent RTP for a control rod pattern adjustment and returned to 100 percent on November 26. On December 9, power was reduced to approximately 75 percent RTP for a control rod pattern adjustment and to isolate a feedwater heater for repairs.
Later, on December 9, power was raised to approximately 91 percent RTP and raised again to 95 percent on December 10. On December 11, the feedwater heater was placed back in service and power was reduced to approximately 74 percent for a control rod pattern adjustment and returned to 100 RTP on December 12. The unit remained at or near 100 percent RTP for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
The licensee completed the annual requalification operating tests 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 tests, the crew simulator operating tests, 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 tests completed on October 25, 2023, and the biennial written examinations completed on October 26, 2023.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during unit 1 and unit 2 manual scram functional testing on October 30, 2023; during unit 2 power ascension activities on November 7, 2023; and during unit 1 high pressure coolant injection (HPCI) surveillance test on November 29, 2023.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated two different crews in the simulator performing scenario H-LTC-SE-00212, "TB Supply Fan Fail/HPCI Inadvertent Start, Governor Sticks/Loss FWH/Cond. Demin Loss HP FW/Steam Leak, Manually Isolate/Manually Start RCIC, Trips/ED Reactor Water Level," on October 17, 2023.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
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:
Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)
- (1) Unit 2 elevated risk due to scheduled unit 2 reactor core isolation cooling (RCIC) outage, on October 3, 2023.
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) 11009250. Inconsistencies identified between the existing turbine high-speed trip setpoints for HPCI and RCIC and the most limiting General Electric (i.e., reactor vendor) analysis for the HPCI and RCIC systems.
- (2) CR 11017663. Breaker for diesel engine fuel oil transfer pump 1C1, 1Y52-C001C, tripped.
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated unit 2 forced-outage activities from November 1, 2023, to November 7, 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) (1 Sample)
- (1) Procedure 34SV-R43-001-2, Diesel Generator 2A Monthly Test, following a 2A diesel generator work window for preventive maintenance per work order (WO)
SNC1412965.
Surveillance Testing (IP Section 03.01) (1 Sample)
(1)34SV-E41-002-2, Unit 2 HPCI Pump Operability, for a comprehensive pump test on November 30, 2023.
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
(1)34SV-E41-002-1, Unit 1 HPCI pump IST, on November 29, 2023.
71114.01 - Exercise Evaluation
Inspection Review (IP Section 02.01-02.11) (1 Sample)
- (1) The inspectors evaluated the biennial emergency plan exercise during the week of October 30, 2023. The simulated scenario began when a fuel bundle is bent while moving it from the unit 2 fuel rack, releasing a stream of air bubbles from the bundle. Refueling floor area radiation monitors alarm and the conditions for an Alert declaration are met. A short time later, torus water level begins to lower from a pipe rupture. When a loss of coolant accident occurs, the conditions for a Site Area Emergency declaration are met. Primary containment radiation levels increased to threshold levels from low reactor water level and the conditions for a General Emergency declaration were met, allowing the offsite response organizations to demonstrate their ability to implement emergency actions.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated the submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of October 30, 2023. This evaluation does not constitute NRC approval.
71114.08 - Exercise Evaluation - Scenario Review
Inspection Review (IP Section 02.01 - 02.04) (1 Sample)
- (1) The inspectors reviewed and evaluated the proposed scenario for biennial emergency plan exercise prior to the week of the inspection.
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, 2022, through September 30, 2023)
- (2) Unit 2 (October 1, 2022, through September 30, 2023)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (October 1, 2022, through September 30, 2023)
- (2) Unit 2 (October 1, 2022, through September 30, 2023)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (October 1, 2022, through September 30, 2023)
- (2) Unit 2 (October 1, 2022, through September 30, 2023)
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) October 1, 2022, through June 30, 2023.
EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) October 1, 2022, through June 30, 2023.
EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)
- (1) October 1, 2022, through June 30, 2023.
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends with safety related equipment degradation that might be indicative of a more significant safety issue. Specifically, the inspectors reviewed the following CRs and their associated corrective actions.
- CR 11013549 associated with the residual heat removal service water pump seismic restraints.
- CR 11015070 associated with diesel generator air compressors.
- CR 11015070 associated with diesel generator room ventilation louvers.
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Follow up (IP Section 03.01)
- (1) The inspectors evaluated the unit 2 manual scram due to the loss of the B RFP and the licensees response on November 1, 2023. (NRC Event Notification 56826)
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 18, 2024, the inspectors presented the integrated inspection results to Jason Butler, Plant Manager, and other members of the licensee staff.
- On November 16, 2023, the inspectors presented the emergency preparedness inspection results to Johnny Weissinger, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
H-LTC-SE-00212
Operations Training Simulator Evaluation Guide
09/14/2023
Miscellaneous
NMP-TR-424-F05
Annual Simulator Exam Development and Validation
2.7
Reactor Manual Scram Functional Test
5.2
Reactor Manual Scram Functional Test
3.6
Procedures
NMP-OS-007-001
Conduct of Operations Standards and Expectations
20.0
NMP-OS-010
Protected Train/Division and Protected Equipment Program
10.0
Procedures
NMP-OS-010-002
Hatch Protected Equipment Logs
2.4
Corrective Action
Documents
Condition reports
(CR)
11017663, 11019855, 10747548, 10749675, 11025173,
11026029, 11009250
Engineering
Evaluations
Technical
Evaluations (TE)
1140463, 1140718
Operability
Evaluations
NMP-AD-012-F01
Operability Determination Support Basis
4.1
Work Orders
SNC 16131712
Miscellaneous
H22023B RFPT
Hatch Unit 2 Outage Safety Assessment
Loss of Shutdown Colling
6.24
Plant Startup
51.12
Shutdown/Refueling Mode Preparation Strategy for Flex
1.2
Maintaining Cold Shutdown or Refueling Condition
16.2
Procedures
Drywell Closeout
7.22
Procedures
HPCI Pump Operability
33.2
Nuclear Power Plant Emergency Notification Form - Hatch
Drill Messages #1 through 8
10/31/2023
Miscellaneous
SNC Dose Assessment Data Form - Two (2) completed by
Site Dose Assessment staff and fifteen (15) completed by
EOF Dose Assessment staff during the course of the Hatch
exercise (drill)
10/31/2023
NMP-EP -141 -
2 -F01
HNP Units 1 & 2 EAL Classification Matrix - HOT
CONDITIONS
4.0
NMP-EP-141
Event Classification
3.0
Procedures
NMP-EP-141
Event Classification
4.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NMP-EP-141-002
Hatch Emergency Action Levels and Basis (NEI 99-01
Revision 6)
5.0
NMP-EP-142
Emergency Notification
6.0
NMP-EP-142
Emergency Notification
7.0
NMP-EP-143
Facility Activation
10.0
NMP-EP-143
Facility Activation
9.0
NMP-EP-147
Offsite Dose Assessment Automated Midas
7.0
NMP-EP-147
Offsite Dose Assessment Automated Midas
6.0
NMP-EP-147-001
SNC Field Monitoring Teams Radiological Surveys and
Sampling
7.0
NMP-EP-147-003
Hatch Units 1 and 2 MIDAS-NU Dose Projections
6.0
FLT-023-002-01
CFR 50.54(q) Screening for NMP-EP-144
9.0
Miscellaneous
FLT-023-002-01
CFR 50.54(q) Evaluation for NMP-EP-144
9.0
Miscellaneous
23EX03 Graded Exercise, Southern Nuclear Plant Hatch,
10/31/2023
10/17/2023
71151
Miscellaneous
PI Information
Report
PI Information Report 10/1/2022 - 9/30/2023
1.0
Corrective Action
Documents
Corrective Action
Report (CAR)
363146
Miscellaneous
PMCR 104999
Preventive Maintenance Change Request
04/05/2023
NMP-GM-002-
001
CAP Instructions
47.0
71152S
Procedures
NMP-GM-051
Trending, Gap Identification, Analysis and Closure
1.0
Corrective Action
Documents
Condition Reports
(CRs)
11020416, 11020611
Event Notification (non-emergency) for Unit 2 Scram on Nov.
1, 2023
11/01/2023
Miscellaneous
SRO Event
Report 2-23-02
per 31GO-OPS-
010-0
Unit 2 Manual Scram due to Loss of Reactor Feed Pump
High Pressure Injection
11/03/2023
Scram Procedure
14.4
Procedures
Normal Plant Shutdown
33.7