IR 05000373/2021012
| ML21301A047 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/28/2021 |
| From: | Karla Stoedter NRC/RGN-III/DRS/EB2 |
| To: | Rhoades D Exelon Generation Co, Exelon Nuclear |
| References | |
| IR 2021012 | |
| Download: ML21301A047 (10) | |
Text
SUBJECT:
LASALLE COUNTY STATION - 50.59 TEAM INSPECTION REPORT 05000373/2021012 AND 05000374/2021012
Dear Mr. Rhoades:
On September 17, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at LaSalle County Station and 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, Karla K. Stoedter, Chief Engineering Branch 2 Division of 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:
05000373/2021012 and 05000374/2021012
Enterprise Identifier:
I-2021-012-0034
Licensee:
Exelon Generation Company, LLC
Facility:
LaSalle County Station
Location:
Marseilles, IL
Inspection Dates:
September 13, 2021 to September 17, 2021
Inspectors:
J. Benjamin, Senior Reactor Inspector
E. Fernandez, Reactor Inspector
G. Hausman, Senior Reactor Inspector
Approved By:
Karla K. Stoedter, Chief
Engineering Branch 2
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a 50.59 Team 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.
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 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.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)
The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from September 13, 2021, to September 17, 2021.
- (1) Evaluation: L18-015 LaSalle Control Rod Drop Accident (CRDA) Revision to Alternative Source Term
- (2) Evaluation: L18-115 Re-Route of Line 2DG05A-4"
- (3) Evaluation: L19-101 Operation of Both "C" VP [Primary Containment Cooling System]
Chillers with One Primary Containment Chilled Water Loop
- (4) Evaluation: L19-150 Upgraded LaSalle Unit 2 Main Generator Auto Voltage Regulator
- (5) Evaluation: L20-067 Unit 2 Main Steam Isolation Valve Weir Internals Retrofit Modification
- (6) Evaluation: L20-135 Unit 1 Main Steam Isolation Valve Weir Internals Retrofit Modification
- (7) Evaluation: L21-004 Alternate Reactor Recirculation Seal Staging Path for 1BRR
- (8) Evaluation: L21-024 Upgraded LaSalle Unit1 Main Generator Auto Voltage Regulator
- (9) Evaluation: L21-037 Reactor Recirculation Pump Motor Tertiary Oil Reserve
- (10) Screening: L18-014 Unit 1 Drywell Equipment Drain System Gravity Drain Install Bypass Flow Transmitter
- (11) Screening: L18-017 Increase High Pressure Core Spray Room Accident Temperature to 155 F
- (12) Screening: L18-024 Unit 1 Reactor Vessel Hydro Preparation Mechanical Checklist Change the Position for the Inboard MSIV [main steam isolation valve] to Close
- (13) Screening: L18-031 Filling the Reactor, Reactor Well and Dryer/Separator Pit Through Feedwater with Suppression Pool Cleanup. Changed the Procedure to Make the +2.5 Feet of Suppression Pool Level Conditional.
- (14) Screening: L18-062 Separated Steps to Provide Different Actions Based Upon Whether and Intersystem LOCA is Expected or Not
- (15) Screening: L18-066 Changes Position of 1DG011 in LOS-DG-Q2 and LOP-DG-04 Based Upon Last Performance of LOS-DG-SR6
- (16) Screening: L18-070 Upgraded Unit 2 Main Steam Line High Flow Switches with Rosemount Differential Pressure Transmitters (BL 86-02)
- (17) Screening: L18-074 Unit 2 Hardened Containment Vent System (HCVS) Phase 2 Modification
- (18) Screening: L18-076 Temporary Modification to Defeat High Level Alarm on the Upper and Lower Motor Bearing Oil Reservoir of the 1B Reactor Recirculation Pump Motor
- (19) Screening: L18-107 Unit 2 Drywell Equipment Drain System Gravity Drain - Install Bypass Flow Transmitter
- (20) Screening: L18-123 Revise Calculation NED-I-EIC-0260 for Maximum Suppression Pool Temperature of 212F
- (21) Screening: L18-161 Upgraded Unit 1 Main Steam Line High Flow Switches with Rosemount Differential Pressure Transmitters (BL 86-02)
- (22) Screening: L20-015 Lake Level and Slowdown Flow Control/River Screen House and Lake Abnormal. Changed in All Places the Low Lake Level Limit to 699.000 for Support of Condenser Work for Unit 1.
- (23) Screening: L20-046 Evaluation of Water Hammer in Reactor Core Isolation Cooling Exhaust Steam Piping
- (25) Applicability: LUCR-0423 Revised IFSAR Sections and Table for Replacement of Switches with Rosemont Model 3153N Transmitters
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On September 17, 2021, the inspectors presented the 50.59 Team 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
HPCS Pump Cubicle Cooler Ventilation System
Cross Index for Environmental Qualification Parameters &
Their Respective Source Documents
Main Steam Line High Flow MSIV Isolation Error Analysis
(Rosemount Model 3153N)
LaSalle Unit 2 PRC-019 Coordination Study
NED-I-ECI-0260
Suppression Chamber Wide Range Water Level Indication
Error, Maj Rev: 000, Min Rev: B
08/29/2016
Calculations
NED-I-ECI-0260
Suppression Chamber Wide Range Water Level Indication
Error, Maj Rev: 000, Min Rev: C
08/31/2018
50.59 SA: Discrepancy with Calc NED-I-EIC-0260
01/17/2018
AR 04269679-17
Add Passwords in Cyber Ark for AVR
07/14/2021
Corrective Action
Documents
50.59 to Be Performed
03/11/2021
Drawings
S-1252
La Salle County Station Unit 1 & 2
Floor Loading Diagram
Reactor BLDG. EL. 673-4 & EL. 694-6
01/06/1975
Upgrade Unit 2 MSL High Flow SOR Switches with
Rosemount DP Transmitters
06/01/2018
U1 DWEDS [Drywell Equipment Drain System] Gravity Drain
- Install Bypass Flow Transmitter Dated 2018-03-05
Upgrade Unit 1 MSL SOR Flow Switches with Rosemount
DP Transmitters Dated 2019-07-31
U2 DWEDS [Drywell Equipment Drain System] Gravity Drain
- Install Bypass Flow Transmitter
Increase HPCS Room Accident Temperature to 155°F
Revise Calc NED-I-EIC-0260 for Max Suppression Pool
Temperature of 212 Degrees F
Upgrade LaSalle Unit 2 Main Generator Auto Voltage
Regulator (AVR)
Upgrade LaSalle Unit 1 Main Generator Auto Voltage
Regulator (AVR)
Engineering
Changes
RX Recirculation Pump Motor Tertiary Oil Reservoir
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
U2 Hardened Containment Vent System (HCVS) Phase 2
000
Diesel Generator Special Operations/1A(2A) Diesel
Generator Auxiliaries Inservice Test
L18-24
Unit 1 Reactor Vessel Hydro Preparation Mechanical
Checklist
L18-76
Tmod to Defeat High Level Alarm on Upper and Lower Motor
Bearing Oil Reservoir of the "1B" Reactor Recirculation
Pump Motor
000
L20-15
Lake Level Blowdown Flow Control/River Screen House and
Lake Abnormal
L18-115
Reroute of Line 2DG05A-4"
000
L19-150
Upgrade LaSalle Unit 2 Main Generator Auto Voltage
Regulator (AVR); Existing GE Alterex AVR is Replaced with
ABB Digital AVR, Model UNITROL 6000 Medium Digital AVR
with Dual Channels
L20-046
Evaluation of Water Hammer in RICI Exhaust System Piping
L20-67
U2 MSIV Weir Internals Retrofit Modifications
L21-024
Upgrade LaSalle Unit 1 Main Generator Auto Voltage
Regulator (AVR); Existing GE Alterex AVR is Replaced with
ABB Digital AVR, Model UNITROL 6000 Medium Digital AVR
with Dual Channels
Engineering
Evaluations
L21-37
RX Recirculation Pump Motor Tertiary Oil Reservoir
Commonwealth Edison Response to Bulletin 86-02, Re:
Static-O-Ring Differential Pressure Switches
07/25/1986
Commonwealth Edison Response to Bulletin 86-02, Re:
Supplemental Response to Bulletin 86-002, "Static O-Ring
Differential Pressure Switches
08/29/1986
Commonwealth Edison Response to Bulletin 86-02, Re:
Supplemental Response to Bulletin 86-002, "Static O-Ring
Differential Pressure Switches
09/10/1986
Miscellaneous
Commonwealth Edison Response to Bulletin 86-02, Re:
Supplemental Response to Bulletin 86-002, "Static O-Ring
Differential Pressure Switches
09/08/1986
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AT 04142160-02
Action Tracking Item to Incorporate Changes to EQ Binders
EQ-LS075 and EQ-LS108 Will Be Revised to Delete SOR
Switches as Required
09/25/2018
BL 86-02
Static "O" Ring Differential Pressure Switches
07/18/1986
Design Analysis97-200
VY Cooler Thermal Performance Model 1(2)VY01A and
(2)VY02A
04/23/2018
Emerson
00807-0100-6182
Rosemount 3150 Series Nuclear Pressure Transmitters,
June 2018
BA
EQ-01
Temp & Humidity Profile for the ECCS Pump Cubicles
EQ-GEN067
Environmental Qualification of Rosemount Pressure
Transmitters Models 3153N and 3154N
L18-014
Unit 1 DWEDS [Drywell Equipment Drain System] Gravity
Drain - Install Bypass Flow Transmitter
L18-017
Increase HPCS Room Accident Temperature to 155°F
L18-070
Upgrade Unit 2 MSL High Flow SOR Switches with
Rosemount DP Transmitters
L18-107
Unit 2 DWEDS [Drywell Equipment Drain System] Gravity
Drain - Install Bypass Flow Transmitter
L18-123
Revise Calculation NED-I-EIC-0260 for Maximum
Suppression Pool Temperature of 212°F
L18-161
Upgrade Unit 1 MSL High Flow SOR Switches with
Rosemount DP Transmitters Model 3153N
LUCR-421
U2 DWEDS [Drywell Equipment Drain System] Gravity Drain
- Install Bypass Flow Transmitter; Revise Operation of the
Drywell Sump (LUCR 403 Not Implemented as of Submitting
This Change Request)
05/09/2019
LUCR-423
Upgrade Unit 1 MSL High Flow SOR Switches with
Rosemount DP Transmitters; Revise UFSAR Sections
7.3.2.2.3.4 & 7.6.2.2.3, and Table 7.3.2
06/27/2019
Guideline on Licensing Digital Upgrades: EPRI TR-102348,
Revision 1, NEI 01-01: A Revision of EPRI TR-102348 to
Reflect Changes to the 10 CFR 50.59 Rule, March 2002
Appendix A
Supplemental Questions for Addressing 10 CFR 50.59
Evaluation Criteria
03/15/2002
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NES-EIC-20.04
Analysis of Instrument Channel Setpoint Error and
Instrument Loop Accuracy
Supplement 1
Clarification on Endorsement of Nuclear Energy Institute
Guidance in Designing Digital Upgrades in Instrumentation
and Control Systems
05/31/2018
Process for Managing Plant Modifications Involving Digital
Instrumentation & Control Equipment and System Systems
Software Quality Assurance Process for Plant Digital
Instrumentation and Control Systems and Components
Maintenance Specification: Installation and Control of
Temporary Shielding
LOP-DG-04
Diesel Generator Special Operations
Procedures
Scaffold Installation, Modification, And Removal Request
Process
Work Orders
Scaffold Needed for Shadow Shield for 2RH26AA
03/26/2021