Text

County Station - Integrated Inspection Report 05000373/2022003 and 05000374/2022003
	ML22304A033
Person / Time
Site:	LaSalle
Issue date:	11/01/2022
From:	Robert Ruiz; NRC/RGN-III/DORS/RPB1
To:	Rhoades D; Constellation Energy Generation, Constellation Nuclear
References
	IR 2022003
	Download: ML22304A033 (1)
	v • d • e

SUBJECT:

LASALLE COUNTY STATION - INTEGRATED INSPECTION REPORT 05000373/2022003 AND 05000374/2022003

Dear Mr. Rhoades:

On September 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at LaSalle County Station. On October 12, 2022, the NRC inspectors discussed the results of this inspection with Mr. P. 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:

NPF-11 and NPF-18

Report Numbers:

05000373/2022003 and 05000374/2022003

Enterprise Identifier:

I-2022-003-0049

Licensee:

Constellation Nuclear

Facility:

LaSalle County Station

Location:

Marseilles, IL

Inspection Dates:

July 01, 2022, to September 30, 2022

Inspectors:

J. Benjamin, Senior Resident Inspector

G. Edwards, Health Physicist

R. Elliott, Resident Inspector

W. Schaup, Senior Project Engineer

R. Zuffa, Illinois Emergency Management Agency

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

None.

PLANT STATUS

Unit 1 began the inspection period at rated thermal power. On July 25, 2022, the unit was down powered to approximately 15 percent and taken offline to support maintenance outage L1M24 in response to a hot spot in the isophase bus duct that was identified during thermography. The unit was returned to rated thermal power on July 27, 2022, 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 September 24, 2022, the unit was down powered to approximately 50 percent to perform power suppression testing. The unit was returned to rated thermal power on September 26, 2022. On September 26, 2022, the unit was manually scrammed, and the turbine was tripped due to a fire in the isophase bus duct, thus entering forced outage L2F46. On September 30, 2022, the unit was at approximately 15 percent power, and proceeding to turbine synchronization and restoration to rated thermal power.

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

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Unit 1 low-pressure core spray system on September 9, 2022

(2) Unit 2 reactor core isolation cooling system with high-pressure core spray unavailable on September 21, and September 26 through 27, 2022

(3) Unit 1 division 1 250V dc power distribution system the week of September 9, 2022

(4) Unit 1 1B diesel generator on September 23, 2022

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 standby liquid control system from September 6 through 9, 2022.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (9 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)fire zone 2F, reactor building, elevation 740'-0", Unit 1 general area and control rod drive repair room (2)fire zone 2G, reactor building, elevation 710'-6", Unit 1 general area and suppression pool entrance (3)fire zone 3H1, reactor building, elevation 694'-0", Unit 2 general area (4)fire zone 8B1, diesel generator building, elevation 710'-0", Unit 2 high-pressure core spray diesel generator room (5)fire zone 7B2, diesel generator building, elevation 710'-0", Unit 1 division 2 standby diesel generator room (6)fire zone 4D3, auxiliary building, elevation 749'-0", Unit 1 electrical equipment room (7)fire zone 4D1, auxiliary building, elevation 740'-0", Unit 1 cable spreading room (8)fire zone 2H4, reactor building elevation 694'-6", Unit 1 reactor core isolation cooling and low-pressure core spray cubicle (9)fire zone 2l4, reactor building elevation 673'-4", Unit 1 low-pressure core spray and reactor core isolation cooling pump cubicle

71111.06 - Flood Protection Measures

Inspection Activities - Internal Flooding (IP Section 03.01) (2 Samples)

The inspectors evaluated internal flooding mitigation protections in the:

(1) Unit 1 main condenser circulating water boot maintenance/inspections and condenser pit level trip testing

(2) Unit 2 main condenser circulating water boot maintenance/inspections and condenser pit level trip testing

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (5 Samples)

(1) The inspectors observed and evaluated licensed operator performance in the control room during a down power for a maintenance outage (L1M24) on July 26, 2022, and returning the unit to full power on July 28, 2022.

(2) The inspectors observed and evaluated licensed operator performance in the control room during Unit 2 power suppression testing on September 24, 2022.

(3) The inspectors observed and evaluated licensed operator performance following the report of a fire in the Unit 2 isophase bus duct on September 26, 2022.

(4) The inspectors observed and evaluated licensed operator performance in the control room during a reactor startup on September 29, 2022.

(5) The inspectors observed and evaluated licensed operator performance in the control room during reactor power changes for rod 10-47 insertion on September 21, 2022.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated out-of-the-box exam OBE 22-4-1 on August 3, 2022.

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) Unit 1 1A reactor protection system motor generator

(2) Unit 2 low-pressure core spray

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (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) Unit 2 elevated risk due to unexpected technical specification limited condition of operation entry for division 3 emergency diesel generator on July 28, 2022

(2) Unit 2 elevated risk with two low-pressure injection sources unavailable on September 6, 2022

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (1 Sample)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Unit 2 division 3 emergency diesel generator and high-pressure core spray following the failure of the Unit 2 2B emergency diesel generator fuel priming pump starter

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (2 Samples)

The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:

(1) Work Order (WO) 5179580, "Division 3 Emergency Diesel Generator Following the Fuel Priming Pump Failure to Start"

(2) WO 5296305, "2A Reactor Protection System"

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (2 Samples)

(1) The inspectors evaluated maintenance outage L1M24 to repair the Unit 1A main power transformer isophase bus from July 25 through 28 2022.

(2) The inspectors evaluated maintenance outage L2M46 due to fire in Unit 2 main power transformer isophase bus duct from September 26 through October 1, 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 2 source range monitor rod block channel B calibration on August 25, 2022

(2) WO 4957429, "Unit 1 Division 3 125V dc Battery Modified Performance Test"

Inservice Testing (IP Section 03.01) (1 Sample)

(1) Unit 2 2B emergency diesel generator operability test on September 21, 2022

FLEX Testing (IP Section 03.02) (1 Sample)

(1) FLEX diesel/hale pump testing LOS-FSG-SR1 on July 14,

RADIATION SAFETY

71124.05 - Radiation Monitoring Instrumentation

Walkdowns and Observations (IP Section 03.01) (8 Samples)

The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:

(1)portable ion chambers stored "ready for use" and/or during use in Unit 1 reactor building (2)portable ion chambers stored "ready for use" and/or during use in Unit 2 reactor building (3)portable ion chambers stored "ready for use" and/or during use on the refueling floor (4)area radiation monitors on the refueling floor (5)area radiation monitors in the reactor building (6)portable friskers used at the exit to the refueling floor (7)telepoles stored "ready for use" in the radiation protection instrument room (8)portable friskers stored "ready for use" in the radiation protection instrument room

Calibration and Testing Program (IP Section 03.02) (12 Samples)

The inspectors evaluated the calibration and testing of the following radiation detection instruments:

(1) Ludlum Model 3, SN #306091

(2) Ludlum Model 3, SN #269215

(3) Eberline RO20, SN #12101

(4) Eberline RO20, SN #12003

(5) Eberline RO20, SN #12566

(6) MGP Telepole, SN #6614-070

(7) MGP Telepole, SN #6612-101

(8) Mirion Accuscan II, SN #13000232

(9) Mirion Fastscan, SN #96-5690

(10) Mirion ARGOS 5, SN #1711-138

(11) Thermo Scientific PM-12, SN #12048

(12) Thermo Scientific SAM-12, SN #12088 Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (2 Samples)

The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:

(1)station standby gas treatment wide range gas monitor (2)station vent stack wide range gas monitor noble gas, iodine, and particulate sampling

71124.06 - Radioactive Gaseous and Liquid Effluent Treatment

Walkdowns and Observations (IP Section 03.01) (3 Samples)

The inspectors evaluated the following radioactive effluent systems during walkdowns:

(1)station ventilation system discharge to main plant vent stack (2)standby gas treatment system discharge to the main plant vent stack (3)main condenser off-gas treatment system effluent monitoring system

71124.07 - Radiological Environmental Monitoring Program

Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

MS06: Emergency AC Power Systems (IP Section 02.05)===

Main article: IP 71151

(1) Unit 1 (July 1, 2021, through June 30, 2022)

(2) Unit 2 (July 1, 2021, through June 30, 2022)

MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)

(1) Unit 1 (July 1, 2021, through June 30, 2022)

(2) Unit 2 (July 1, 2021, through June 30, 2022)

MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)

(1) Unit 1 (July 1, 2021, through June 30, 2022)

(2) Unit 2 (July 1, 2021, through June 30, 2022)

BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)

(1) Unit 1 (August 1, 2021, through August 31, 2022)

(2) Unit 2 (August 1, 2021, through August 31, 2022)

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) August 1, 2021, through August 31, 2022 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) August 1, 2021, through August 31, 2022

71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

Main article: IP 71153

The inspectors evaluated the following licensee event reports (LERs):

(1) Licensee Event Report (LER) 2022-001-00, Unit 1, "Turbine Stop Valve Limit Switch Failure due to Lubricant Degradation," ML22147A131. The circumstances surrounding this LER are documented in NRC integrated inspection report 05000373/2022002; 05000374/2022002 in the Inspection Results Section.

(2) Licensee Event Report (LER) 2022-002-00, Unit 2, "Turbine Stop Valve Limit Switch Failure due to Lubricant Degradation," ML22147A132. The circumstances surrounding this LER are documented in NRC integrated inspection report 05000373/2022002; 05000374/2022002 in the Inspection Results Section.

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 12, 2022, the inspectors presented the integrated inspection results to Mr. P. Hansett, Site Vice President, and other members of the licensee staff.

On August 25, 2022, the inspectors presented the radiation protection inspection results to Mr. P. Hansett, Site Vice President, and other members of the licensee staff.

On September 23, 2022, the inspectors presented the radiation protection inspection results to Mr. P. Hansett, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

AR 4362985

Inventory Loss During SBLC Sparging

08/13/2020

AR 4369371

Unexpected MCR Alarm - 1H13-P603-A105 SBLC Cont.

Loss

09/14/2020

AR 4443678

2B SBLC Pump Oil Leak

08/31/2021

AR 4468818

Inst. Out of Tolerance 2C41-N003 SW#1 Trend Code B4

2/29/2021

Corrective Action

Documents

AR 4480919

1SC01A-4 License Renewal Inspection Results

2/26/2022

Figure 32-1

Figure 32-1: RCIC Piping Diagram

April 2009

Figure 32-1A

Figure 32-1A: RCIC Steam Piping Diagram

April 2009

Figure 32-1B

Figure 32-1B: RCIC Water Piping Diagram

April 2009

Figure 32-2

Figure 32-2: RCIC Control Panel Mimic

April 2009

Figure 32-3

Figure 32-3: RCIC Turbine Trip Throttle Valve

October

1999

Figure 32-4

Figure 32-4: RCIC Turbine Governor System

April 2009

Figure 32-5

Figure 32-5, RCIC Turbine Speed Control

October

1999

Figure 32-6

Figure 32-6, RCIC Turbine Governor Startup

October

1999

Figure 32-7

Figure 32-7: RCIC Turbine Lube Oil System

October

1999

Figure 32-8

Figure 32-8: RCIC Barometric Condenser Assembly

October

1999

Figure 32-9

Figure 32-9: RCIC Rupture Diaphragm

October

1999

M-145

P&ID Standby Liquid Control System

AF

M-2145

Standby Liquid Control System

C

Drawings

RI-1

RI-1: RCIC System

LOP-LP-01E

Unit 1 Low Pressure Core Spray Electrical Checklist

LOP-LP-01M

Unit 1 Low Pressure Core Spray Mechanical Checklist

LOP-RI-02E

Unit 2 Reactor Core Isolation Cooling System Electrical

Checklist

71111.04

Miscellaneous

LOP-RI-02M

Unit 2 Reactor Core Isolation Cooling System Mechanical

Checklist

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

FZ 2F

RX Bldg. 740'-0" Elev. U1 General Area & CRD Repair

Room

FZ 2G

RX Bldg. 710'-6" Elev. U1 General Area & Suppression Pool

Entrance

FZ 2H4

RX Bldg. 694'-6" Elev. U1 RCIC/LPCS Cubicle

FZ 2I4

RX Bldg. 673'-4" Elev. U1 LPCS/RCIC Pump Cubicle

FZ 3H1

RX Bldg. 694'-0" Elev. U2 General Area

FZ 4D1

Aux. Bldg. 749'-0" Elev. U1 Cable Spreading Room

FZ 4D3

Aux. Bldg. 749'-0" Elev. U1 Electrical Equipment Room

FZ 7B2

DG Bldg. 710'-0" Elev. U1 Division 2 Standby

Diesel-Generator Room

71111.05

Fire Plans

FZ 8B1

DG Bldg. 710'-0" Elev. U2 HPCS Diesel-Generator Room

WO 1628734

IM 2LS-CW032 Cond Pit Level Switch Operability Check

2/17/2015

WO 1628735

IM 2LS-CW031 Cond Pit Level Switch Operability Check

2/17/2015

WO 1859159

U2 Condenser Pit Level Switch Trip Logic Upgrade

10/19/2016

WO 1911219

IM EWP - Condenser Pit Level 1LS-CW031 Switch Cal

03/09/2022

WO 1911219-02

IM EWP - Condenser Pit Level 1LS-CW031 Switch Cal

03/09/2022

WO 1911220

IM EWP - Condenser Level 1LS-CW032 Switch Cal

03/09/2022

WO 4681083

TSTR, Watertight Door Inspection, W L02-LMS-ZZ-04

08/26/2019

WO 4807052

EWP U-1 Watertight Door Inspection Per LMS-ZZ-04, Att. A.

2/02/2020

WO 4903022