IR 05000373/2019010
| ML19143A272 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/22/2019 |
| From: | Kenneth Riemer NRC/RGN-III/DRP/B1 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| References | |
| IR 2019010 | |
| Download: ML19143A272 (16) | |
Text
SUBJECT:
LASALLE COUNTY STATION, UNITS 1 AND 2NRC BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000373/2019010 AND 05000374/2019010
Dear Mr. Hanson:
On April 26, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your LaSalle County Station, Units 1 and 2 and discussed the results of this inspection with Mr. W. Trafton and other members of your staff.
The results of this inspection are documented in the enclosed report.
The NRC inspection team reviewed the stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.
Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
Finally the team reviewed the stations programs to establish and maintain a safety-conscious work environment, and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews the team found no evidence of challenges to your organizations safety-conscious work environment. Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available. The NRC inspectors did not identify any finding or violation of more than minor significance.
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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Kenneth Riemer, Chief Branch 1 Division of Reactor Projects Docket Nos.: 05000373; 05000374 License Nos.: NPF-11; NPF-18
Enclosure:
IR 05000373/2019010; 05000374/2019010
Inspection Report
Docket Numbers: 05000373 and 05000374 License Numbers: NPF-11 and NPF-18 Report Numbers: 05000373/2019010 and 05000374/2019010 Enterprise Identifier: I-2019-010-0043 Licensee: Exelon Generation Company, LLC Facility: LaSalle County Station, Units 1 and 2 Location: Marseilles, IL Inspection Dates: April 08, 2019 to April 26, 2019 Inspectors: J. Havertape, Resident Inspector M. Learn, Reactor Engineer V. Meghani, Reactor Inspector N. Shah, Project Engineer Approved By: Kenneth Riemer, Chief Branch 1 Division of Reactor Projects Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a problem identification and resolution inspection at LaSalle County Station, Units 1 and 2 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. Findings and violations being considered in the NRCs assessment are summarized in the table below.
List of Findings and Violations No findings 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.
OTHER ACTIVITIES - BASELINE
71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 02.04)
The inspectors performed a biennial assessment of the licensees corrective action program, use of operating experience, self-assessments and audits, and safety conscious work environment.
- Corrective Action Program Effectiveness: The inspectors assessed the corrective action programs effectiveness in identifying, prioritizing, evaluating, and correcting problems.
- Operating Experience, Self-Assessments and Audits: The inspectors assessed the effectiveness of the stations processes for use of operating experience, audits and self-assessments.
- Safety Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.
INSPECTION RESULTS
Assessment 71152B Corrective Action Program: Based on the samples reviewed, the inspectors determined that staffs performance in each of these areas adequately supported nuclear safety.
Effectiveness of Problem Identification: Overall, the licensee was effective at identifying issues at a low threshold and was properly entering them into the Corrective Action Program (CAP) as required by procedures. The inspectors determined that the station was generally effective at identifying negative trends that could potentially impact nuclear safety. The inspectors did several plant walkdowns; for the areas reviewed, the inspectors did not identify any concerns in the area of problem identification.
Effectiveness of Prioritization and Evaluation of Issues: In depth reviews of a risk-informed sampling of Action Requests (ARs), work orders (WOs), and cause evaluations were completed, including a 5 year review of issues associated with the Switchgear Heat Removal (VX) system. The inspectors identified that the licensee generally, appropriately prioritized and evaluated issues for resolution.
The inspectors identified several examples where the issue documentation was insufficient to clearly understand the actions taken to evaluate and resolve the issues. One of the expectations in the licensees CAP program procedure was that each CAP item be sufficiently documented to function as a stand alone product. Specifically, that an independent reader could clearly understand the issue and how it was evaluated and corrected. This expectation was supposed to be reinforced by the Station Oversight (SOC) and Management Review (MRC) Committees, who were responsible for screening each CAP issue. A similar observation had also been identified in the most recent and previous Nuclear Oversight (NOS)audits of the program. Although the inspectors were able to verify that the associated issues were properly addressed, this appeared to be an ongoing issue warranting further licensee attention. The licensee documented this observation in the CAP.
Effectiveness of Corrective Actions: The inspectors concluded that the licensee was generally effective in developing Corrective Actions that were appropriately focused to correct the identified problem and correct conditions adverse to quality. For issues considered significant conditions adverse to quality, the licensee took action to address the root and contributing causes and to preclude repetition. Corrective actions were generally completed in a timely manner and in accordance with procedural requirements commensurate with the safety significance of the issue.
The inspectors reviewed a root cause to address fuel channel distortion issues documented in AR 4169154. This issue was considered a Condition Adverse to Quality. The corrective action for this concern was to transition to advanced channel materials, that were less susceptible to this distortion, by 2023. As interim actions, the licensee had initiated rechanneling of fuel bundles, equipment inspections, revising the channel friction model and updating the channel distortion monitoring plan. As stated in the root cause, these interim actions were designed to mitigate the risk of fuel channel distortion until the final actions were completed. However, the inspectors noted that these items were coded as action tracking items (ACITs), instead of corrective actions in the CAP. The ACITs were considered a lower classification than a corrective action, meaning that they could be cancelled, rescheduled or modified without station management review. Another example was AR 1136071, documenting a potential non-conservative Technical Specification applicable to LaSalle station, which was also considered a Condition Adverse to Quality. One of the interim actions, was to track the NRC review of an industry document which recommended actions to address this concern. Upon competition of the NRC review, the licensee planned to implement these recommendations as the final corrective action. However, this interim action was tracked as an ACIT rather than as a corrective action. As a result, even though the NRC review was completed in 2017, the ACIT did not show up as overdue, given its lower priority status, until the inspectors brought it to the attention of the licensee. Based on interviews, the inspectors determined that the practice of using ACITs was in part due to a misconception among licensee staff, that since the interim actions were not the final corrective actions, they did not warrant such coding. However, since these interim actions were designed to mitigate the risk until the final actions were implemented, the inspectors determined that they should be treated as corrective actions. By coding them as ACITS, the inspectors concluded that this may result in some Conditions Adverse to Quality not being adequately addressed. The licensee documented this observation in the CAP.
The inspectors also identified examples where risk assessments were not being performed in accordance with the CAP procedures. Each of these examples were classified as Conditions Adverse to Quality. This was in part due to unclear guidance regarding what constituted an appropriate risk assessment and the lack of reinforcement of this expectation during CAP product screenings. For example, the root cause evaluation for AR 4193000, concluded that inadequate oversight by mid-level management was a primary contributor in several equipment failures occurring at the site. Under the CAP procedure, each root cause was required to have either a Corrective Action to Prevent Recurrence (CAPR) or a risk assessment, if a CAPR was not assigned. For this issue, there was no documented CAPR or risk assessment. Similarly, the licensee CAP procedures required that for Corrective Action Program Evaluations (CAPEs; formally referred to as Apparent Cause Evaluations), if a cause was not identified, then the most probable cause should be documented and a risk assessment performed. The inspectors identified two CAPEs (ARs 4110933; 4117722) for which no cause was identified, but there was no stated probable cause or risk assessment documented. Based on interviews with those licensee staff involved in the above evaluations, the inspectors determined that the risk had been considered, even though the licensee procedural requirements were not strictly followed. Also, in all of the examples, the licensee had implemented interim actions which the inspectors reviewed and concluded were sufficient to address the concern and mitigate the risk; however, these actions were documented as ACITs and not corrective actions. Since the intent of the procedure, if not necessarily the strict requirements were met, this was not considered a violation, however, the inspectors concluded that this was a failure to reinforce CAP expectations and requirements. This licensee documented this issue in the CAP.
No corrective action program issues were identified during the review of the VX system.
As stated, the observations identified by the inspectors were documented in the licensee CAP.
The specific ARs are listed in the attached List of Documents Reviewed for this inspection.
Assessment 71152B Operating Experience and Self-Assessment and Audits: Based on the samples reviewed, team determined that the licensees performance in each of these areas adequately supported nuclear safety.
The team noted that Operating Experience identified by external organizations, such as industry groups and the NRC, were appropriately addressed by station procedures.
Specifically, there was prescriptive guidance regarding how these items were to be tracked, documented and processed in the CAP. However, the inspectors noted that similar guidance was not prescribed for Operating Experience identified through internal corporate oversight.
For example, the licensees corporate organization had identified a potential fleet trend involving configuration control events. This trend was captured as a corporate CAP and several actions were identified to be taken by each of the individual plants in the fleet.
However, there was no documentation or evidence of any tracking items ensuring that the actions were taken at each site (including LaSalle) nor was there any assessment of their effectiveness in addressing the trend. As a result, these types of issues were not processed similarly to those originating from the industry. The licensee documented this observation in the CAP. The specific CAP item is documented in the List of Documents Reviewed that is attached to this report.
Assessment 71152B Safety Conscious Work Environment (SCWE): The inspectors found no significant challenges to the licensees organizations safety conscious work environment. Through interviews and field observations, the inspectors determined that workers were willing to identify issues through any of the available means and had generally positive feedback on the program effectiveness. The overall health of the Employee Concerns Program was good and no adverse, discernible trend was noted during the review of issues.
One area of focus was the stations use of the OR7 code to classify issues having potential safety culture concerns. Individuals whose issues were assigned this code, were to be contacted by supervision to discuss the issue and assess the impact. During interviews, most individuals had only a general awareness of this code with some expressing concerns that it was potentially detrimental--i.e., the code could be used to identify complainers; however, none of the individuals expressed any reluctance to raise issues. The inspectors noted that the station had identified a similar concern and had initiated a CAP item (AR 4237390) to address this issue.
Overall the licensee was maintaining an appropriate safety conscious and work environment.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 26, 2019, the inspector presented the problem identification and resolution inspection results to Mr. W. Trafton and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71152B Corrective Action AR 4144044 CCP Drawing Discrepancies Identified - 22078 and VPF-3411- 6/4/2018
Documents 10
AR 02453200 Outage Delay due H4 Shroud Weld 2/16/2015
AR 02478819 Perform Root Cause on the 2B33-F067A/B from L2R15 4/2/2015
AR 02704946 Generate EACE Actions for 1VX05C Breaker Trip Alarm 8/16/2016
AR 02705960 Electrical Overheating Indications on Failed Contactors 8/18/2016
AR 02714273 Division 2 Battery Room Fan Tripped 9/10/2016
AR 02718493 1VX03C Contactor has Elevated Coil Temperature 9/21/2016
AR 03972830 Compensatory Measures for Plant Barrier Impairments not Met 2/6/2017
AR 03984867 High Pressure Core Spray Maintenance Rule Reliability 3/14/2017
Criteria
AR 04004367 NRC Scaffold Built Close to Safety Related Equipment 4/29/2017
AR 04004367 NRC Scaffold Built Close to Safety Related Equipment 4/29/2017
AR 04022566 NOS ID: Scaffold Not Erected IAW Procedure Requirements 6/16/2017
AR 04028406 Maintenance Trend: Lapses Documented in Scaffolding 7/3/2017
AR 04028406 Maintenance Trend: Lapses Documented in Scaffolding 7/3/2017
AR 04037236 2VX01C Division 1 Switchgear Room Supply Fan Breaker Trip 7/31/2017
AR 04051196 NRC Identified Violation for Hardened Containment Vent 9/12/2017
System Top Hat
AR 04056931 NRC Question on Division 3 Protected Pathways 9/27/2017
AR 04062821 2017 Mid Cycle Gap to Excellence (GTE) in Work 10/13/2017
Management (WM.1-1)
AR 04069173 Lapses in Maintenance Fundamentals Deliberate and 10/31/2017
Conservative
AR 04069173 Lapses in Maintenance Fundamental Deliberate and 10/31/2017
Conservative
AR 04074546 Maintenance Trend: Line of Fire 11/14/2017
AR 04077095 Daughtering of Parent Nuclides Not Included in LOCA Dose 11/15/2017
Calculation
AR 04091820 Non-Technical Specification Flow Switch Broke, Causing 1/9/2018
Reactor Core Isolation Cooling Isolation
Inspection Type Designation Description or Title Revision or
Procedure Date
AR 04105645 Low Flow During LOS-RH-R1 2/19/2018
AR 04110933 1B21-F013U Fails Set-Pressure Test 3/3/2018
AR 04115533 Generate CAP Product for Unit 1 Division 1 Battery 3/16/2018
AR 04121071 Maintenance Trend IR - Valve Team Performance 3/30/2018
AR 04127238 FME Prevention Enhancements 4/16/2018
AR 04127878 NRC Identified Potential Finding on 1E12-F050A Post 4/17/2018
Maintenance Test
AR 04134599 Potential Green Non-Cited Violation for not Meeting OM Code 5/4/2018
Requirements
AR 04136375 New Eaton Contactor Found Bound in the Energized State 5/10/2018
AR 04148965 Trend in Maintenance Safety Behaviors 6/30/2018
AR 04174611 NRC Identified Scaffold Question Division 2 CSCS Room 9/18/2018
AR 04182624 Hi Pressure Steam Leak Off B TDRFP Drain Valve 2TE126B 10/11/2018
AR 04185035 NRC Identified Potential Scaffold Issue in U2 CSCS Pump 10/18/2018
Room
AR 04185256 NRC Identified: Potential Scaffold Issue in U2 B/C RHR Room 10/19/2018
AR 04189380 Additional Data Points to be Added to CAPE 04185035 10/30/2018
AR 04192778 2018 WANO AFI ER.2 11/7/2018
AR 04200198 1A Emergency Diesel Generator Soak Back Pump Did Not 12/4/2018
Stop When Control Switch Taken to Off
AR 04202638 CCP - 1VX19YA Not Responding to IMD Testing 12/13/2018
AR 04202744 2VX02C Failed to Stop when C/S Taken to Stop 12/13/2018
AR 04204165 ER 2A Diesel Generator Day Tank Level Indicator Gauge, 12/18/2018
Poor 1998 Work Order Issues With Parts Too
AR 04221825 APS as Found: FME within 2A RR Pump Air Cooler Inspection 2/20/2019
Panel
AR 04228310 L2R17 OPA Lessons Learned 3/10/2019
AR 2389133 U2 Leak Detection System LD-14 Function MR Criteria 10/1/2014
Exceeded
AR 2639566 LOS-RD-SR7 Friction Settle Test Times 3/13/2016
AR 2641420 1B RR PumpTripped During Upshift 3/16/2016
AR 2642954 1B Pump Seal Cavity #2 Increased to 1000 PSIG 3/21/2016
AR 2742254 U1 RCIC Trip on Low Suction Pressure 11/17/2016
Inspection Type Designation Description or Title Revision or
Procedure Date
AR 3965622 Check-In NRC Pre-Dry Cask Campaign Readiness 1/19/2017
Assessment
AR 3975576 1FW005 Feed Reg Valve Positioner Arm Broken 2/18/2017
AR 3982397 RM-U2 Rod 06-35 Position 8 Settles at XX 3/7/2017
AR 3984936 2017 Biennial Operating Experience Program Assessment 7/19/2017
AR 3999427 2017 Mid Cycle Organizational Effectiveness Self-Assessment 12/20/2017
AR 4001039 Performance Monitoring of OOT HCU Pressure Switches 4/21/2017
AR 4002295 10 CFR Part 21 Interim--Control Rod Drive Mechanism 4/25/2017
Contaminated With Chlorides
AR 4005230 Level 3 OPEX Review Requested #408052 Comanche Peak 5/1/2017
AR 4013979 Level Three OPEX Review Prairie Island Unit 2 408134 5/23/2017
AR 4019235 Trending IR on 2A RWCU Regen HX Tube 6/7/2017
Outlet Temperature
AR 4021408 10 CFR Part 21 Interim--Potential Defect in Greyboot Socket 6/13/2017
AR 4022270 Level 3 OPEX Review Requested #414434 Monticello Unit 1 6/15/2017
AR 4024815 0DG01P Tripped After Attempting to Shut Down Pump 6/27/2017
AR 4038696 1TE111 Vacuum Breaker Requires Fill More Often 8/3/2017
AR 4048867 1A IN Compressor Loss of Power 9/4/2017
AR 4049063 OPEX Eval: IN 2017-05 Square-D CKT BKR Binding 9/5/2017
AR 4050373 2A IN Compressor not Loading 9/9/2017
AR 4051128 RM-U2 CR 30-31 Slow Trace and High Stall Flow 9/12/2017
AR 4091551 RCIC Isolation Alarm Received 1/8/2018
AR 4094528 CAPE Requested for ER Critical Component Failures 1/17/2018
AR 4103166 10 CFR Part 21 Interim--Deviation in SOR Qualification Testing 2/12/2018
AR 4105375 RM- Multiple Rods Slow to Settle L1R17 SD 2/19/2018
AR 4105400 Additional Slow to Settle Rod L1R17 2/19/2018
AR 4108860 OPEX: IN 2018-02 Target Rock SRV Degradation 2/27/2018
AR 4110933 1B21-F013U Fails Set-Pressure Test 2/27/2018
AR 4111658 OPEX Review for Industry Event 431025 3/6/2018
AR 4111767 Refuel Bridge Trend 3/6/2018
AR 4117722 RM-1A Reactor Recirculation Pump Failed to Downshift and 3/22/2018
Tripped to 0 Speed
AR 4117757 RM - 1B33-F067B Vent Line Leak 3/22/2018
Inspection Type Designation Description or Title Revision or
Procedure Date
AR 4121081 Main. Trend IR - Valve Team Performance 3/30/2018
AR 4136655 2018 Employee Concerns Program Performance and 1/23/2019
Effectiveness Review
AR 4149479 NRC ID: Potential NCV for Non-Conformance With OM Code 6/22/2018
AR 4149537 NRC ID: UHS Inspection - ER-AA-340-1002 HX Inspection 6/22/2018
Procedure
AR 4162014 Unprofessional ERO Qualification Coercion 8/3/2018
AR 4162942 NRC ID: Potential Finding IST Valve Position Verification 8/9/2018
AR 4163020 Numerous Equipment Deficiency Tags Not Addressed for 8/9/2018
Years
AR 4169321 RM-U2 Rod 54-15 Failed to Settle and Friction Tested 9/1/2018
AR 4174521 EC 617710 Cancelled U2 Main Steam Differential Pressure 9/17/2018
Switch to Rosemounts/ALARA and Manpower
AR 4174521 EC 617710 Cancelled U2 Main Steam Differential Pressure 9/17/2018
Switch to Rosemounts/ALARA and Manpower
AR 4180633 Incorrect Station Vent Stack Wide Range Gas Monitor Base 10/1/2018
Provided
AR 4180633 Incorrect Station Vent Stack Wide Range Gas Monitor Data 10/1/2018
Base Provided
AR 4191219 RM-U2 Rod 26-31 Friction Tested and Failed to Settle 11/3/2018
AR 4192776 2018 WANO MA.1 Supplemental Valve Team Performance 11-6-2019
AR 4193000 2018 World Institute of Nuclear Operators AFI.ER.1 11/8/2018
AR 4193001 2018 World Institute of Nuclear Operators AFI.EN.1 11/8/2018
AR 4199673 10 CFR Part 21--Emergency Diesel Generator EMD Soakback 12/03/2018
Pump
AR 4204165 ER 2A DG Day Tank Level Instrumentation Gauge, Poor 1998 12/18/2018
Work Order Issues With Parts Too
AR 4219430 Unprepared to Perform RP-LA-706 to Complete LIS-PC-106B 2/6/2019
AR 4219430 Unprepared to Perform RP-LA-706 to Complete LIS-PC-106B 2/6/2019
AR 4223111 Scope Delete Removal of Bonnet Vent Valves on 2B33- 2/24/2019
F067A/B
AR 4223314 Unit 2 Cable Spreading Room Sprinkler Trouble Alarm 2/25/2019
AR 4223737 NRC IDD: WO not Coded as a CA 2/26/2019
Inspection Type Designation Description or Title Revision or
Procedure Date
AR 4228310 L2R17 OPA Lessons Learned 3/10/2019
AR 4228557 TRM 3.3P / 3.7K 14 Day Time Clock Expiration (U2 CSR) 3/11/2019
AR 4228653 Untimely Completion of Corrective Action Report 3/11/2019
AR 4236826 Fuel Pool Cooling 1A Pump Trip 4/5/2019
AR 4236934 LOS-AA-S101 A Channel Narrow Range Level Channel Check 4/6/2019
Unsat
AR 4236985 LOS-AP-W1 Complete W/ Portions Unsat 4/6/2019
AR 4237302 1WR001A - A WR PMP DSCH CK VLV Making Loud 4/8/2019
Knocking Noise
AR 4237375 RM-U2 HCU 26-27 Accumulator Trouble Alarm 4/8/19
AR 4237390 Trend IR: Lack of OR7 Communication to Originators 4/8/2019
AR 4237390 Trend IR: Lack of OR7 Communication to Originators 4/8/2019
AR 4237434 Trend: Little to No Notice for Non-Emergent Activities- Eng 4/8/2019
AR 4237528 2A RHR Seal Cooler <15 GPM During LOS-RH-SR1 4/8/19
AR 4237723 1VY01A Area Cooler Flow/DP Results 4/8/2019
AR 4242432 PI&R NRC ID: Corrective Actions Not Generated in Timely 4/22/2019
Manner
kAR 04090775 NRC Identified Potential Finding on 0 Diesel Generator Braze 1/5/2018
Repair
Corrective Action AR 4223737 NRC IDD: Work Order Not Coded As a Corrective Action 3/22/2018
Documents AR 4238596 NRC Identified: WANO ER.1 Area for Improvement 4/11/2019
Resulting from Effectiveness
Inspection AR 4238622 NRC PI&R Review of Root Cause Report 4193001 4/11/2019
AR 4242432 PI&R NRC ID: CAS Not Generated In Timely Matter 4/22/2019
AR 4243078 NRC Identified: WO#1840264 Not Completed for PS 4/24/2019
Calibration
AR 4243128 2019 PI&R--Risk Assessment Procedure Clarity 4/24/2019
AR 4243135 PI&R NRC ID: ER-AA-340-1002 Procedure Writers Guide 4/24/2019
Deviation
AR 4243141 2019 LaSalle PI&R--Observation on Corporate Documentation 4/24/2019
AR 4243257 PI&R NRC ID: WO Referenced in IR Not 4/25/2019
Completed/Cancelled
AR 4243301 NRC PI&R Review of Root Cause 4169154 4/24/2019
Inspection Type Designation Description or Title Revision or
Procedure Date
AR 4243354 2019 PI&R Classification of IR 4136375 Not Changed to SL3 4/25/2019
AR 4243473 2019 PI&R SA 4037526 SYSMON - Benchmarking Not 4/25/2019
Completed
AR 4243649 Enhancement Needed for Extent of Condition for CAPE 4/26/2019
4185035
Engineering 397773 Unit 1 2015 Online Replacement of Klockner-Moeller Cubicles Revision 1
Changes EC 622475 Bypass 1VP01CA Chiller Bearing Module 0
EC 623895 TMOD to Defeat High Level Alarm on the Upper and Lower 0
Motor Bearing Oil Reservoir of the 1B Reactor Recirculation
Pump Motor
Engineering 1480441 Unit 2 18-31 High Friction Found During Shutdown Not Part of 2/11/2013
Evaluations Test Population (Only Test 10% of Population)
2640121 Investigation of L1C16 EOC No-Settle Control Rods 2/14/2016
4169154 Control Rod 30-12 Did Not Fully Insert During the U2 Manual 8/31/2018
Scram on 8/31/2018
455968 Unit 1 SAE, Channel Friction Not Detected by Testing Criteria 3/20/2006
667185 Repeat Reactor Core Channel Distortion Issues on LaSalle 9/2/2007
Units 1 and 2
27361 Unit 1 Channel Distortion Root Cause Report 1/26/2008
Miscellaneous DIERS Daily Industry Events Reports 4/9-13/2018
OP-AA-102-103- Key Function Review Justification 1/4/2019
1001, Att 3
OP-AA-102-103- Quarterly Operator Burden Degraded Equipment Aggregate 1/4/2019
1001, Att. 1 Assessments - Unit Common, Unit 1 and Unit 2
PIIM 2017-0401 Lapses in Documented Scaffolding 7/12/2017
PIIM 2017-0593 Opportunities for Improvements in Maintenance Fundamentals 10/31/2017
Operability 18-001 Eaton Contactor binding 12/13/2018
Evaluations
Procedures EI-AA-101 Employee Concerns Program 11
EI-AA-101-1001 Employee Concerns Program Process 15
ER-AA-340-1002 Service Water Heat Exchanger Inspection Guide 7, 8
NF-AB-1102210 Core Loading Pattern Development Revision 18
NF-AB-135-1420 Establishing Rechanneling and Channel Distortion Monitoring Revision 15
Populations
Inspection Type Designation Description or Title Revision or
Procedure Date
OP-AA-102-103- Operator Burden and Plant Significant Decisions Impact Revision 8
1001 Assessment Program
PA-AA-125 Corrective Action Program Procedure Revision 6
PI-AA-1012 Safety Culture Monitoring Revision 2
PI-AA-1012 Safety Culture Monitoring 2
PI-AA-115 Operating Experience Program 4
PI-AA-115-1001 Processing of Level 1 OPEX Evaluations 2
PI-AA-115-1002 Processing of Level 2 OPEX Evaluations 3
PI-AA-115-1003 Processing of Level 3 OPEX Evaluations 5
PI-AA-120 Issue Identification and Screening Process Revision 8
PI-AA-125-1003 Corrective Action Program Evaluation Manual Revision 4
Self-Assessments AR 4037526 Self-Assessment SYSMON Plans 9/28/17
AR 3964622 LaSalle Pre-NRC Inspection / 2017 Spent Fuel Loading 3/22/2017
Campaign Readiness Assessment
AR 3983403 Self Assessment - Triennial 50.59 (NRC-IP 71111.17T) 3/9/2017
NOSA-LAS-17-05 Engineering Design Control Audit Report 6/28/2017
NOSA-LAS-17-09 Fire Protection Audit Report 9/20/2017
NOSA-LAS-18-01 Maintenance Functional Area Audit Report 2/7/2018
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