IR 05000244/2024001
| ML24115A027 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/24/2024 |
| From: | Erin Carfang Division of Operating Reactors |
| To: | Rhoades D Constellation Energy Generation, Constellation Nuclear |
| References | |
| IR 2024001 | |
| Download: ML24115A027 (1) | |
Text
April 24, 2024
SUBJECT:
R.E. GINNA NUCLEAR POWER PLANT, LLC - INTEGRATED INSPECTION REPORT 05000244/2024001
Dear David Rhoades:
On March 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at R.E. Ginna Nuclear Power Plant, LLC. On April 18, 2024, the NRC inspectors discussed the results of this inspection with Richard Everett, 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 (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Erin E. Carfang, Chief Projects Branch 1 Division of Operating Reactor Safety
Docket No. 05000244 License No. DPR-18
Enclosure:
As stated
Inspection Report
Docket Number:
05000244
License Number:
Report Number:
Enterprise Identifier: I-2024-001-0041
Licensee:
Constellation Energy Generation, LLC
Facility:
R.E. Ginna Nuclear Power Plant, LLC
Location:
Ontario, New York
Inspection Dates:
January 1, 2024 to March 31, 2024
Inspectors:
J. Schussler, Senior Resident Inspector
C. Swisher, Resident Inspector
B. Dyke, Operations Engineer
S. Veunephachan, Health Physicist
Approved By:
Erin E. Carfang, Chief
Projects Branch 1
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at R.E. Ginna Nuclear Power Plant, LLC, 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 05000244/2023-003-00 LER 2023-003-00 for R.E.
Ginna Nuclear Power Plant,
Manual Reactor Trip due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation due to Low Steam Generator Level 71153 Closed LER 05000244/2023-003-01 LER 2023-003-01 for R.E.
Ginna Nuclear Power Plant,
Manual Reactor Trip due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation due to Low Steam Generator Level 71153 Closed
PLANT STATUS
Ginna began the inspection period operating at rated thermal power and remained at, or near, rated thermal power 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
71111.01 - Adverse Weather Protection
Impending Severe Weather (IP Section 03.02) (2 Samples)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather, high winds, on January 9, 2024
- (2) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending extreme cold weather on January 17, 2024
71111.04 - Equipment Alignment
Partial Walkdown (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)
'B' safety injection on January 12, 2024 (2)
'D' standby auxiliary feedwater on March 7, 2024 (3)
'A' emergency diesel generator on March 19, 2024
71111.05 - Fire Protection
Fire Area Walkdown and Inspection (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)
'A' battery room on January 25, 2024
- (2) Uninterrupted power supply and central alarm station diesel generator area on February 14, 2024
- (3) Screen house basement on February 20, 2024
- (4) Intermediate building clean side middle level on March 6, 2024
Fire Brigade Drill Performance (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the on-site fire brigade training and performance during an unannounced fire drill on February 8, 2024
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 main control room during:
- Shift turnover on February 8, 2024
- A emergency diesel generator testing on March 13, 2024
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the simulator during licensed operator requalification training the week of January 30, 2024. The requalification involved a scenario that contained, but was not limited to, a steam generator tube leak and steam generator tube rupture.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management (IP Section 03.01) (2 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) Evaluation of plant risk (Green) during planned 'A' emergency diesel generator maintenance on January 18, 2024
- (2) Evaluation of plant risk (Action Green) during planned 'B' residual heat removal pump and breaker maintenance on February 27, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Operability assessment of the 'A' emergency diesel generator lube oil temperature following immersion heater failures on January 17, 2024
- (2) Operability assessment of seismic qualification for hanger supporting electric supply power conduit to motor-operated valves 896A and 896B, refueling water storage tank to safety injection and containment spray pump suctions on February 1, 2024
- (3) Operability assessment of the 'B' emergency diesel generator tornado missile and flood door camlock found disengaged on February 12, 2024
- (4) Operability assessment of the 'A' service water header coincident with the 'B' service water discharge check valve V-4602 leaking on February 14, 2024
- (5) Operability assessment of the 'D' service water motor outboard horizontal vibration point rising trend on March 18, 2024
- (6) Operability assessment of degraded liquid crystal display for control rod bank 'B',
group 2, on March 26, 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 (IP Section 03.01) (3 Samples)
- (1) Operational testing of the 'B' safety injection pump following discharge check valve 898B maintenance on January 10, 2024
- (2) Functional testing of the diesel driven fire pump following planned maintenance on the pump angle drive and engine turbo on January 24, 2024
- (3) Functional testing of the central alarm station diesel generator following planned maintenance on the engine on February 15, 2024
Surveillance Testing (IP Section 03.01) (4 Samples)
- (1) STP-O-2.7.1D, "D Service Water Pump Test" on January 9, 2024
- (2) STP-E-12.5, "Technical Support Center Diesel Test" on January 10, 2024
- (3) STP-O-12.2, "B Emergency Diesel Generator" on January 31, 2024
- (4) STP-O-17.4, "Control Room Radiation Monitor R-45 and R-46 Operability Test" on March 15, 2024
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) STP-O-16QT-RECIRC, "Auxiliary Feedwater Turbine Pump - Quarterly (Recirculation Alignment)" on January 2, 2024
71114.06 - Drill Evaluation
Required Emergency Preparedness Drill (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated an emergency drill in the simulator control room and technical support center involving an Alert and Site Area Emergency declaration due to a scenario which contained, but was not limited to, a simulated steam generator tube leak, rupture, and a faulted steam generator on February 13,
RADIATION SAFETY
71124.08 - Radioactive Solid Waste Processing and Radioactive Material Handling, Storage,
and Transportation
Radioactive Material Storage (IP Section 03.01)
The inspectors evaluated the licensees performance in controlling, labeling and securing the following radioactive materials:
- (1) Radioactive materials containers in storage outside in a temporary yard area and within the upper radwaste storage building
- (2) Part 37 radioactive material and select sealed sources
Radioactive Waste System Walkdown (IP Section 03.02) (2 Samples)
The inspectors walked down the following accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality:
- (1) Radioactive liquid processing systems
- (2) Solid radioactive waste system
Waste Characterization and Classification (IP Section 03.03) (2 Samples)
The inspectors evaluated the following characterization and classification of radioactive waste:
(1)2023 Part 61 dry active waste stream analysis and characterization
- (2) Waste stream analysis of Chem-Nuclear Systems, Inc. resin bed shipment and waste characterization
Shipping Records (IP Section 03.05) (4 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
- (4) Shipment number 2023-088, UN2915, Type A Package, Yellow II
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours (IP Section 02.01)===
- (1) For the period January 1, 2023 through December 31, 2023
IE03: Unplanned Power Changes per 7000 Critical Hours (IP Section 02.02) (1 Sample)
- (1) For the period January 1, 2023 through December 31, 2023
IE04: Unplanned Scrams with Complications (IP Section 02.03) (1 Sample)
- (1) For the period January 1, 2023 through December 31, 2023
===71153 - Follow Up of Events and Notices of Enforcement Discretion
Event Report (IP Section 03.02)===
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 2023-003-00 for R.E. Ginna Nuclear Power Plant, Manual Reactor Trip due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation due to Low Steam Generator Level (ADAMS Accession No. ML23345A157). 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 nor violation of NRC requirements was identified. This LER is closed.
- (2) LER 2023-003-01 for R.E. Ginna Nuclear Power Plant, Manual Reactor Trip due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation due to Low Steam Generator Level (ADAMS Accession No. ML24067A253). The inspectors reviewed the supplement to LER 2023-003-00. The initial LER was reviewed and dispositioned in this inspection report. This LER supplement is 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 March 14, 2024, the inspectors presented the radiation safety inspection results to Caroline Holshouser, Radiation Protection Manager, and other members of the licensee staff.
- On April 18, 2024, the inspectors presented the integrated inspection results to Richard Everett, Plant Manager, 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
04727767
V-4602 B SWP discharge check valve leaking by
01/09/2024
04731282
Hanger contacting containment spray recirculation full flow
test piping
01/16/2024
04759178
Detectable air leak on 5905A - A EDG starting air PCV
03/19/2024
Corrective Action
Documents
Resulting from
Inspection
04733048
Space heater inside electrical panel floor exclusion zone
01/18/2025
04733080
Work in progress signage not at all entrances to work area
01/18/2024
Corrective Action
Documents
04752557
LCD for control bank B, group 2, is degraded
2/23/2024
Corrective Action
Documents
Resulting from
Inspection
04738586
SD/18 (B EDG door) camlock found disengaged
01/29/2024
Miscellaneous
VTD-C1493-4001
CJ Enterprises digital rod step counter model DRSC-100/B
service manual
Revision 000
Procedures
Post-maintenance testing
Revision 28
Work Orders
C93965814
Minor maintenance worksheet, ZI-BG2, AR04752557
2/23/2024
Corrective Action
Documents
Resulting from
Inspection
04727510
Procedural enhancements to STP-O-16QT-RECIRC
01/08/2024