IR 05000373/2022004
| ML23031A188 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 01/31/2023 |
| From: | Robert Ruiz NRC/RGN-III/DORS/RPB1 |
| To: | Rhoades D Constellation Energy Generation, Constellation Nuclear |
| References | |
| IR 2022004 | |
| Download: ML23031A188 (1) | |
Text
SUBJECT:
LASALLE COUNTY STATION - INTEGRATED INSPECTION REPORT 05000373/2022004 AND 05000374/2022004
Dear David Rhoades:
On December 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at LaSalle County Station and discussed the results of this inspection with Phil Hansett, 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, Robert Ruiz, Chief Reactor Projects Branch 1 Division of Operating Reactor Safety Docket Nos. 05000373 and 05000374 License Nos. NPF-11 and NPF-18
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000373 and 05000374
License Numbers:
Report Numbers:
05000373/2022004 and 05000374/2022004
Enterprise Identifier:
I-2022-004-0049
Licensee:
Constellation Nuclear
Facility:
LaSalle County Station
Location:
Marseilles, IL
Inspection Dates:
October 01, 2022, to December 31, 2022
Inspectors:
J. Benjamin, Senior Resident Inspector
R. Elliott, Resident Inspector
G. Hansen, Senior Emergency Preparedness Inspector
A. Tran, Resident Inspector
Approved By:
Robert Ruiz, Chief
Reactor 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 LaSalle County Station, 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 05000374/2021-002-00 LER 2021-002-00 for LaSalle County Station, Unit 2,
Reactor Protection System Half Scram due to Motor Generator Set Output Breaker Trip 71153 Closed LER 05000374/2022-002-00 LER 2022-002-00 for LaSalle County Station, Unit 2, Turbine Stop Valve Limit Switch Failure due to Lubricant Degradation 71153 Closed LER 05000373/2022-001-00 LER 2022-001-00 for LaSalle County Station, Unit 1, Turbine Stop Valve Limit Switch Failure due to Lubricant Degradation 71153 Closed LER 05000374/2021-002-01 LER 2021-002-01 for LaSalle County Station, Unit 2,
Reactor Protection System Half Scram due to Motor Generator Set Output Breaker Trip 71153 Closed
PLANT STATUS
Unit 1 began the inspection period at rated thermal power. On October 8, 2022, the unit was down powered to 80 percent for a rod pattern adjustment. The unit was returned to rated thermal power the same day. On November 4, 2022, the unit was down powered to 82 percent for a rod pattern adjustment. The unit was returned to rated thermal power on November 5, 2022. On December 4, 2022, the unit was down powered to 70 percent for turbine control valve testing, scram time testing, channel distortion testing, and a rod sequence exchange. The unit was returned to rated thermal power on December 5, 2022. On December 17, 2022, the unit was down powered to 77 percent for the final rod pattern adjustment for the cycle. The unit was returned to rated thermal power the same day and remained at or near rated thermal power for the remainder of the inspection period.
Unit 2 began the inspection period at rated thermal power. On December 18, 2022, the unit was down powered to 82 percent for a rod sequence exchange and channel distortion testing. The unit was returned to rated thermal power on December 16, 2022, and remained at or near rated thermal power 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
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following systems:
1. intake structure
2. FLEX storage building
3. intake warming lines
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 in preparation of the season's first winter storm on December 21, 2022.
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with a design basis maximum precipitation event.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 reactor core isolation cooling on October 17, 2022, during elevated risk plant conditions
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 high pressure core spray system.
71111.05 - Fire Protection
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill on October 25, 2022, Unit 2 710' turbine building.
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered between September 2, 2022, and October 6, 2022.
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 Unit 1 control room operations during a rod sequence exchange on December 3, 2022.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operators training on November 10, 2022.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 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) Unit 2 high pressure core spray (2)review of the LaSalle County Station periodic assessment of the maintenance rule program July 2020 through June 2022
- (3) Unit 1 and Unit 2 main generator isophase bus duct temperature adverse condition monitoring
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) Unit 1 elevated risk 2B emergency diesel generator planned work window on October 11, 2022
- (2) Unit 2 elevated risk during 2A emergency diesel generator planned work window on October 19, 2022
- (3) Unit 1 elevated risk during Unit 1 reactor vessel high water level trip calibration on November 18, 2022
- (4) Unit 1 use of risk-informed completion time following the discovery of the 'A' and 'C' average power range monitors inoperable due to reactor recirculation flow input on November 22, 2022 (5)scheduled readiness certification meeting and risk management for work week 2252 (12/26/22-01/01/23) on December 16, 2022
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (9 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) AR 4525029, "Unit 2 Control Rod 38-55 Scram Time Slow"
- (2) AR 4526443, "Control Rod 38-31 Hydraulic Temperature High Alarm"
- (3) AR 4528929, "RM-Unexpected Alarm for HCU [hydraulic control unit] 18-19 High Water Level"
- (4) AR 4530276, "2B DG [diesel generator] Cooling Water Strainer Root Valve Fitting Leak"
- (5) AR 4530501, "2B DC Lube Oil Soak Back Pump Noise"
- (6) AR 4530673, "2B Emergency Diesel Generator Failed First 2 Overspeed Test"
- (7) AR 4531445, "2A DG Compression Fitting Fuel Oil Leak"
- (8) AR 4533417, "Entered LOA-WL-001 Due to Low Lake Level"
- (9) Part 21 Rosemount 3153N series pressure transmitter with Rosemount 3159 remote seals with the LG1 option
71111.18 - Plant Modifications
Severe Accident Management Guidelines (SAMG) Update (IP Section 03.03) (1 Sample)
- (1) The inspectors verified the site Severe Accident Management Guidelines were updated in accordance with the BWR generic severe accident technical guidelines and validated in accordance with NEI 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents, Revision 1.
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
(1)post-maintenance test following average power range monitor 'A' and 'C' card replacement on November 23, 2022 (2)2B DG fast start following 2B DG work week on October 19, 2022 (3)residual heat removal operability and inservice testing following residual heat removal valves cubicle and breaker inspection on October 5, 2022
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:
Surveillance Tests (other) (IP Section 03.01) (2 Samples)
- (1) Unit Common emergency diesel generator 24-hour endurance run
- (2) Unit 1 125 Vdc battery capacity test
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) Unit 1 residual heat removal service water inservice test on November 15, 2022
RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)
- (1) Unit 1 and Unit 2 reactor coolant system unidentified leakage detection surveillances
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes:
Evaluation No. 22-06, Emergency Action Levels for LaSalle Station This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) LaSalle Station fourth quarter 2022 PI drill, Operations crew in simulator on November 1, 2022
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) LaSalle Station fourth quarter 2022 drill, Operations crew in simulator on November 9,
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 (November 1, 2021, through September 30, 2022)
- (2) Unit 2 (November 1, 2021, through September 30, 2022)
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
- (1) Unit 1 (November 1, 2021, through September 30, 2022)
- (2) Unit 2 (November 1, 2021, through September 30, 2022)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (November 1, 2021, through September 30, 2022)
- (2) Unit 2 (November 1, 2021, through September 30, 2022)
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) The inspectors reviewed the licensee's identification of aging management program related issues tagged as potential aging management issues identified within the corrective action program, based upon external operating experience, and station completed work activities.
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 associated with emergency diesel generators issues that might be indicative of a more significant safety issue.
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 05000374/2021-002-00 for LaSalle County Station, Unit 2, "Reactor Protection System Half Scram due to Motor Generator Set Output Breaker Trip," (ADAMS Accession No. ML21210A168). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER, therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements.
- (2) LER 05000374/2022-002-00 for LaSalle County Station, Unit 2, "Turbine Stop Valve Limit Switch Failure due to Lubricant Degradation," (ML22147A132). This LER is included in this report for the purpose of rectifying an administrative item-closure issue whereby it was intended to have been closed in the NRC's internal item tracking system (RRPS) under section 71153 of NRC Inspection Report 05000373/2022003 AND 05000374/2022003.
- (3) LER 05000373/2022-001-00 for LaSalle County Station, Unit 1, "Turbine Stop Valve Limit Switch Failure due to Lubricant Degradation," (ML22147A131). This LER is included in this report for the purpose of rectifying an administrative item-closure issue whereby it was intended to have been closed in the NRC's internal item tracking system (RRPS) under section 71153 of NRC Inspection Report 05000373/2022003 AND 05000374/2022003.
- (4) LER 05000374/2021-002-01 for LaSalle County Station, Unit 2, Reactor Protection System Half Scram due to Motor Generator Set Output Breaker Trip (ML21266A150). The inspectors reviewed the updated LER submittal. The previous LER submittal was reviewed in NRC Inspection Report 05000373/2022004 AND 05000374/2022004.
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 11, 2023, the inspectors presented the integrated inspection results to Phil Hansett, Site Vice President, and other members of the licensee staff.
On November 28, 2022, the inspectors presented the emergency action level and emergency plan changes inspection results to Ron Vanderhyden, Emergency Preparedness Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Evaluations
Mitigating Strategies Flood Hazard Assessment (MSFHA) and
Support Documents
HPCS Instrument Panel 2H22-P024 Leak
03/17/2021
2HP08D-14" License Renewal Inspection Results
06/24/2021
U2 HPCS Water Leg Pump License Renewal Inspection
06/24/2021
Corrective Action
Documents
Unexpected MCR Alarm 2H13-A104
06/24/2021
Drawings
M-141
P&ID High Pressure Core Spray System
Miscellaneous
LS-PSA-005.06
LaSalle PRA High Pressure Core Spray (HPCS) System
Notebook
LOP-HP-03
Preparation for Standby Operation of High-Pressure Core
Spray System (HPCS)
LOP-RI-02E
Unit 2 Reactor Core Isolation Cooling Electrical Checklist
LOP-RI-02M
Unit 2 Reactor Core Isolation Cooling System Mechanical
Checklist
LOP-RI-03
Reactor Core Isolation Cooling System Isolation and System
Shutdown
Procedures
LOP-RI-05
Preparation for Standby Operation of the Reactor Core
Isolation Cooling System
Corrective Action
Documents
HPCS Min Flow Iso. Valve Has Un-Landed Ground Strap
08/20/2021
Miscellaneous
TQ-AA-150-F25
LaSalle County Station 2022 LORT Annual Exam Status
Report
10/06/2022
Miscellaneous
N-01ORQM6
Radiation Surveys ER-AA-700-1003
Use of Operating Experience for License Renewal
Implementation/Aging Management
Perform Stem Lube 2E22-F015
11/24/2022
Work Orders
LOS-HP-Q4 ATT B, HPCS System
09/20/2022
LIS-RI-112
Unit 1 Reactor Vessel High Water Level 8 RCIC Turbine Trip
and Main Turbine/Feedwater Pump Trip Calibration
Procedures
Risk Informed Completion Time
Work Orders
IM LIS-RI-112 U1 RX LVL 8 RCIC Turb Trip Cal
11/17/2022
Engineering
Revision to LGAs and SAMGs Resulting for Revision 4 of
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Changes
LPGP-PSTG-01B
Derivation of the LGA and LSAMG Flowcharts
LPGP-REV-01
EOP & SAMG Revision Instructions
LSAMG-001
RPV and Primary Containment Injection
LSAMG-002
RPV, Containment, and Radioactivity Release Control
LSAMG-003
RPV and Primary Containment Injection (5)
Procedures
LSAMG-004
Containment and Radioactivity Release Control (5)
Corrective Action
Documents
Resulting from
Inspection
NRC ID: Paperwork Error Found in Work Order 05056600-01
2/13/2022
Replace 2B DG Air Start Solenoid
10/19/2022
'A' RHR Pump Full Flow Test Isol Valve Cubicle and Breaker
Inspection
10/03/2022
10/03/2022
Perform LES-DG-202 ATT 1, B, & C If Applicable on the
U-2 B DG
10/17/2022
LOS-DG-M3 2B DG Fast Start ATT 2B-FAST
10/19/2022
Unit 1 'A' RHR System Operability and Inservice Test
10/05/2022
Work Orders
U1 Flow Unit 'C' APRM 'A' and APRM 'C' OOT
11/22/2022
Corrective Action
Documents
Resulting from
Inspection
NRC ID: PCRA for LOS-RH-Q1
11/15/2022
Procedures
LOS-RH-Q1
RHR (LPCI) and RHR Service Water Pump and Valve
Inservice Test for Modes 1,2,3,4, and 5
EM *LOE* Perform LES-DC-103A on 1DC23E, Inspection
Capacity Test
10/04/2022
OP LOS-DG-R0 0 Diesel Generator 24 Hour Testing
10/03/2022
Work Orders
LRA_OP LOS-RH-Q1 ATT:2E 2B RHRWS Inservice Test
(Week 2)
11/16/2022
Miscellaneous
Q 22-06
Emergency Action Levels for LaSalle Station
03/23/2022
Procedures
Addendum 3
Emergency Action Levels for LaSalle Station
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Addendum 3
Emergency Action Levels for LaSalle Station
Corrective Action
Documents
Resulting from
Inspection
NRC ID: 2022 Q3 ROP Submittal Missing Required Comment
2/06/2022
CSCS URI/UAI
Derivation Report
CSCS URI/UAI Derivation Report
Q1 2022 MSPI
Data
Q1 2022 MSPI Data
Q2 2022 MSPI
Data
Q2 2022 MSPI Data
Q3 2022 MSPI
Data
Q3 2022 MSPI Data
Q4 2021 MSPI
Data
Q4 2021 MSPI Data
71151
Miscellaneous
RHR URI/UAI
Derivation Report
RHR URI/UAI Derivation Report
11/09/2022