IR 05000244/2024002
ML24215A181 | |
Person / Time | |
---|---|
Site: | Berkeley Research Reactor, Ginna |
Issue date: | 08/05/2024 |
From: | Erin Carfang NRC/RGN-I/DORS |
To: | Rhoades D Constellation Energy Generation, Constellation Nuclear |
References | |
IR 2024002, IR 2024001 | |
Download: ML24215A181 (1) | |
Text
August 5, 2024
David Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer (CNO)
Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT: R.E. GINNA NUCLEAR POWER PLANT, LLC - INTEGRATED INSPECTION REPORT 05000244/2024002 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION REPORT 07200067/2024001
Dear David Rhoades:
On June 30, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at R.E. Ginna Nuclear Power Plant, LLC. On August 1, 2024, the NRC inspectors discussed the results of this inspection with Daren Blakenship, Site Vice President, a nd 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 Nos. 05000244 and 07200067 License No. DPR-18
Enclosure:
As stated
Inspection Report
Docket Numbers: 05000244 and 07200067
License Number: DPR-18
Report Numbers: 05000244/2024002 and 07200067/2024001
Enterprise Identifier: I-2024-002- 0034 and I-2024- 001- 059
Licensee: Constellation Energy Generation, LLC
Facility: R.E. Ginna Nuclear Power Plant, LLC
Location: Ontario, New York
Inspection Dates: April 1, 2024 to June 30, 2024
Inspectors: C. Swisher, Senior Resident Inspector B. Dyke, Acting Senior Resident Inspector C. Hargest, Health Physicist M. Henrion, Senior Health Physicist A. Kostick, Health Physicist N. Mentzer, Reactor Inspector J. Schussler, Senior Project Engineer K. Smetana, Reactor Engineer T. Winkel, Health Physicist
Approved By: Erin E. Carfang, Chief Projects Branch 1 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 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
None.
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
Seasonal Extreme Weather (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of high temperatures and heat advisories for the following systems on June 17, 2024:
- On-site switchyard 13
- Screenhouse
- Relay room
- Standbyiliy fat
- Equitlignment
Ptikdow(IPecti) (4 Sple
The ipectors evted systonfirions duritikdow ofling emtrains:
( 'A' mot driven au*iliy f pum May 2024
( 'A' charng pum May 2024
( contt s on, 2024
( 'B' contt s on, 2024
71111.05 - Fire Protection
Fire Area Walkdown and Inspection (IP Section 03.01) (6 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Canister preparation building on April 19, 2024
- (2) Auxiliary building spent fuel pool Area on April 19, 2024
- (3) Auxiliary building intermediate level on April 25, 2024
- (4) Main control room on April 30, 2024
- (5) Charging pump room on May 10, 2024
- (6) All volatile treatment room on June 12, 2024
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) 'B' spent fuel pool heat exchanger EAC13 on June 17, 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 control room during shift briefing and 'A' emergency diesel generator monthly testing on May 17, 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 April 23, 2024. The requalification involved a scenario that contained a simulated loss of coolant accident, fuel failure, and loss of containment boundary.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:
- (1) Service water pump discharge check valve preventative maintenance on May 1, 2024
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management (IP Section 03.01) (7 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 'D' service water pump and motor maintenance on April 9, 2024
- (2) Evaluation of plant risk (Green) during planned circuit breaker replacement and post-maintenance inspection on motor control center 'N' and unplanned maintenance on control room ventilation dampers on April 18, 2024
- (3) Evaluation of plant risk (Action Green) during planned 'A' auxiliary feedwater pump and valve maintenance on April 25, 2024
- (4) Evaluation of plant risk (Action Green) during planned 'D' standby auxiliary feedwater pump and valve maintenance on May 2, 2024
- (5) Evaluation of plant risk (Action Green) during planned offsite power circuit '7T' breaker and relay maintenance on May 7, 2024
- (6) Evaluation of plant risk (Action Green) during planned 'B' auxiliary feedwater pump and valve maintenance on May 20, 2024
- (7) Evaluation of plant risk (Green) during planned 'A' residual heat removal pump system outage window on June 12, 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) Functional assessment of the 'B' battery room door following the identification of cracks in the welds associated with the door hinges on April 18, 2024
- (2) Operability assessment of the helium mass flow totalizer after failing calibration check on April 20, 2024
- (3) Operability assessment of the 'D' service water pump discharge check 4604 internal degradation on April 29, 2024
- (4) Functional assessment of the R10B/13/14 plant vent radiation monitor sample pump after flow was determined to be high out of specification on May 11, 2024
- (5) Functional assessment of the 'A' spent fuel pool recirculation pump after identifying a packing leak on May 14, 2024
- (6) Operability assessment of control rod L06 after a change in indication in the plant processing computer on May 16, 2024
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) ECP-23-000041, Design equivalent change package to replace service water pump motors from random to form wound to improve motor reliability with new units on May 6, 2024
- (2) ECP-24-000007, Re-route hose for PAC03 spent fuel pool 'C' pump on June 27, 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) (11 Samples)
- (1) Operational testing of the 'A' auxiliary feedwater pump following lubrication oil pump replacement on April 25, 2024
- (2) Functional testing of the 'A' charging pump following pump repack on April 30, 2024
- (3) Operational testing of the 'D' standby auxiliary feedwater pump following valve maintenance on May 2, 2024
- (4) Functional testing of the 'B' diesel driven flexible coping strategies air compressor following maintenance on May 14, 2024
- (5) Operational testing of core exit temperature thermocouple TCG07 after failed channel check on June 7, 2024
- (6) Operational testing of the 'A' residual heat removal pump following valve maintenance on June 12, 2024
- (7) Operational testing of motor operated valve 896A after light was found extinguished on June 19, 2024
- (8) Operational testing of the 'D' standby auxiliary feedwater pump following valve repair and replacement on June 21, 2024
- (9) Functional testing of the 'B' charging pump following valve replacement, variable frequency drive maintenance, and preventative maintenance on June 24, 2024
- (10) Functional testing of the diesel driven fire pump following preventative maintenance and replacement of the turbocharger on June 24, 2024
- (11) Operational testing of the 'C' safety injection pump following motor operated valve maintenance and pump preventative maintenance on June 25, 2024
Surveillance Testing (IP Section 03.01) (4 Samples)
- (1) STP-O-R-2.5, "Service Water Pump Discharge Check Valves Closure Verification" on April 11, 2024
- (2) STP-O-2.7.1-COMP-D, "'D' Service Water Comprehensive Pump Test" on April 11, 2024
- (3) STP-O-36QC, "Standby Auxiliary Feedwater Pump 'C' - Quarterly" on April 16, 2024
- (4) STP-O-3QA, "Containment Spray Pump 'A' Quarterly Test" on May 16, 2024
Inservice Testing (IP Section 03.01) (2 Samples)
- (1) STP-O-2.2QB, "Residual Heat Removal Pump 'B' Inservice Test" on May 23, 2024
- (2) STP-O-16QT-RECIRC, "Auxiliary Feedwater Turbine Pump - Quarterly (Recirculation Alignment)" on May 29, 2024
71114.06 - Drill Evaluation
Required Emergency Preparedness Drill (1 Sample)
- (1) The inspectors evaluated an emergency drill in the simulator control room and the technical support center involving an Alert, Site Area Emergency, and a General Emergency due to a scenario that contained a simulated steam generator tube leak which escalated to a rupture, a faulted steam generator, and fuel failure on June 11, 2024
Additional Drill and/or Training Evolution (1 Sample)
- (1) The inspectors evaluated an emergency drill in the simulator control room and technical support center involving an Alert, Site Area Emergency and General Emergency declaration due to a scenario which contained a simulated loss of coolant accident which later combined a loss of containment and fuel failure on April, 23,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (IP Section 02.04)===
- (1) For the period April 1, 2023 through March 31, 2024
BI01: Reactor Coolant System Specific Activity (IP Section 02.10) (1 Sample)
- (1) For the period April 1, 2023 through March 31, 2024
BI02: RCS Leak Rate (IP Section 02.11) (1 Sample)
- (1) For the period April 1, 2023 through March 31, 2024
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Work group evaluation regarding service water valves stem and disc corrosion (AR
===04725893) on May 13, 2024
- (2) Intermittent failures of loop A over temperature delta temperature (TI-405A) on June 3, 2024 71152S - Semiannual Trend Problem Identification and Resolution
Semiannual Trend Review (Section 03.02)===
- (1) The inspectors reviewed the licensees corrective action program for potential emerging or adverse trends that might be indicative of a more significant safety issue on June 10,
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
===60855 - Operation of an Independent Spent Fuel Storage Installation (ISFSI)
Operation of an ISFSI===
- (1) The inspectors evaluated the licensee's ISFSI cask loadings April 22-26, 2024, and April 29-30, 2024. Specifically, the inspectors observed the following activities:
- Transfer of cask #1 from canister processing building to ISFSI pad
- Multipurpose canister and transfer cask (HI-TRAC) processing of cask #2
- Foreign Material Exclusion inspection of empty cask #2
- Insertion of fuel spacers for cask #2
- Welding activities for cask #1 and cask #2
- Blowdown, vacuum drying, and forced helium dehydration of cask #2
- Independent fuel verification for cask #2
- Inspection of material conditions of ISFSI pad and previously loaded spent fuel canisters
- Itliem modifiiftitands
INSPECTION RESULTS
Observation: Service Water Valves Stem and Disc Corrosion 71152A The inspectors performed a review of Constellations evaluation and corrective actions associated with an ineffective preventative maintenance strategy for service water valves with dissimilar metal stem-to-disc connections that are susceptible to galvanic corrosion and stem-to-disc separation. During the age related degradation inspection in November 2023, the inspection team identified a Green finding and associated non-cited violation of 10 CFR 50, Appendix B, Criterion XVI, Corrective Action, because Constellation did not correct a condition adverse to quality associated with service water manual valve stem-to-disc separation failures discovered in March 1993. This finding was documented in inspection report 05000244/2023010.
Constellation staff entered this issue into their corrective action program as A R 04725893.
The inspectors reviewed the work group evaluation, corrective actions, and extent of condition of the issue. In addition, the inspectors reviewed the Service Water System Reliability Optimization Program and the License Renewal Aging Management Program Basis Document for the Service Water System Program which detailed the basis of managing age related degradation in the service water system to provide for reliability and operability.
The inspectors found that Constellation scheduled corrective actions to implement new preventative maintenance tasks to examine each susceptible service water valve internals for corrosion with periodicities that considered valve disc design margin and past inspection or replacement history.
The inspectors reviewed the corrective action program products and did not identify any violations or performance deficiencies.
Observation: Intermittent Failures of Loop A Over Temperature Delta 71152A Temperature (TI-405A)
On June 3, 2024, Constellation received multiple alarms for temperature indicator TI-405A for channel 1 of loop A over temperature delta temperature failing low and returning to a normal reading. Due to the intermittent failures, Ginna declared channel 1 over temperature delta temperature inoperable.
Constellation entered this condition into their corrective action program as IR 04685644.
Constellation performed a work group evaluation to investigate the cause of the intermittent failures. It was determined that the probable cause of the failures originated from one of six instrumentation and control modules. Because the specific module that caused the deficiency could not be identified, Constellation replaced all six modules and monitored the modules for 90 days following the replacement and observed no abnormalities.
The inspectors reviewed the corrective action program products and did not identify any violations or performance deficiencies.
Assessment 71152S Corrective Action Program Semiannual Trend Review
The inspectors reviewed Constellations corrective action program and evaluated a sample of issues and events that occurred from January 2024 through June 2024 at Ginna. The inspectors then verified whether the issues were appropriately evaluated by Constellation for emerging or adverse trends and addressed within the scope of the corrective action program or through department review.
The inspection did not reveal any new trends that could indicate a more significant safety issue. The inspectors determined that Constellation personnel were identifying trend issues at a low threshold and entered them into the corrective action program for resolution. The inspectors noted low level or precursor trends identified by Constellation relating to equipment performance trends and material condition precursors.
Based on the overall results of the semiannual trend review, the inspectors determined that Constellation had properly identified adverse trends at Ginna before they became more significant safety problems. The inspectors independently evaluated the deficiencies noted above for significance in accordance with the guidance in IMC 0612, Appendix B, "Issue Screening," and Appendix E, "Examples of Minor Issues.
" The inspectors determined that none of the conditions were deficiencies of greater than minor significance and, therefore, are not subject to enforcement action in accordance with the NRC's Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On May 15, 2024, the inspectors presented the ISFSI Loading Campaign inspection results to Daren Blankenship, Site Vice President, and other members of the licensee staff.
- On May 16, 2024, the inspectors presented the service water valves stem and disc corrosion annual problem identification and resolution sample inspection results to Chris Birke, Senior Manager Strategic Engineering, and other members of the licensee staff.
- On August 1, 2024, the inspectors presented the integrated inspection results to Daren Blakenship, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71152A Corrective Action 04493977
Documents 04672224
04720652
04725893
Miscellaneous Service Water System Reliability Optimization Program Revision 16
Procedures LR-SWS-License Renewal Aging Management Program Basis Revision 5
PROGPLAN Document - Service Water System Program
11