IR 05000315/2021010
| ML21245A413 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/07/2021 |
| From: | Nestor Feliz-Adorno Reactor Projects Region 3 Branch 4 |
| To: | Gebbie J Indiana Michigan Power Co |
| References | |
| IR 2021010 | |
| Download: ML21245A413 (16) | |
Text
SUBJECT:
DONALD C. COOK NUCLEAR PLANT - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000315/2021010 AND 05000316/2021010
Dear Mr. Gebbie:
On August 5, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Donald C. Cook Nuclear Plant. On August 5, 2021 the NRC inspectors discussed the results of this inspection with you 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.
No findings or violations of more than minor significance were identified during this inspection.
September 7, 2021 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, Néstor J. Féliz Adorno, Chief Branch 4 Division of Reactor Projects Docket Nos. 05000315 and 05000316 License Nos. DPR-58 and DPR-74
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000315 and 05000316
License Numbers:
Report Numbers:
05000315/2021010 and 05000316/2021010
Enterprise Identifier:
I-2021-010-0045
Licensee:
Indiana Michigan Power Company
Facility:
Donald C. Cook Nuclear Plant
Location:
Bridgman, MI
Inspection Dates:
July 19, 2021 to August 05, 2021
Inspectors:
E. Fernandez, Reactor Inspector
J. Mancuso, Resident Inspector
R. Ng, Project Engineer
G. O'Dwyer, Reactor Engineer
Approved By:
Néstor J. Féliz Adorno, Chief
Branch 4
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution inspection at Donald C. Cook Nuclear Plant, 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.
OTHER ACTIVITIES - BASELINE
71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 02.04)
- (1) 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. The inspectors also conducted a five-year review of the ice condenser glycol chiller system.
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: Assessment of the Corrective Action Program 71152B Based on the samples reviewed, the team concluded that the licensee's implementation of the Corrective Action Program was generally effective and supported nuclear safety.
Effectiveness of Problem Identification:
Based on the samples reviewed, the team concluded that the licensee continued to identify issues at a low threshold and appropriately entered these issues into the Corrective Action Program. The team determined that the licensee usually entered problems into the Corrective Action Program completely and accurately. The inspectors determined that the station was generally effective at identifying negative trends that could potentially impact nuclear safety.
The team also noted that some deficiencies were identified by external organizations, including the NRC, that had not been previously identified by licensee staff and were subsequently entered into the Corrective Action Program. In addition, the licensee also utilized Corrective Action Program support processes to identify problems, including the self-assessment and audit process and the Operating Experience Program. For example, the licensee performed department self-assessments and quality assurance audits to identify issues in station processes. Similarly, the licensee screened issues from both NRC and industry operating experience and entered them into the Corrective Action Program when they were applicable to the station.
The team determined that the licensee was generally effective at trending low-level issues and taking appropriate corrective actions to prevent more significant problems from developing. In addition, the licensee used the Corrective Action Program to document instances in which previous corrective actions were ineffective or were inappropriately closed.
The team performed a 5-year review of the ice condenser glycol chiller issues. As part of this review, the team interviewed the system engineer, reviewed the plant health report, and reviewed selected corrective actions and condition evaluation documents. The team concluded that the ice condenser glycol chiller concerns were identified and entered into the Corrective Action Program at a low threshold and were resolved in a timely manner commensurate with their safety significance. The team did not identify any additional issues.
Effectiveness of Prioritization and Evaluation of Issues:
Based on the samples reviewed, the team determined that licensee performance was generally effective at prioritizing and evaluating issues commensurate with the safety significance of the identified problem. The Initial Screening Committee and the Management Screening Committee meetings were generally thorough and intrusive in reviewing issues and prioritizing actions. In addition, the team observed a healthy dialogue between the members of these committees and the members challenged each other when dispositioning issues.
In general, once a degraded or non-conforming condition was identified, the Corrective Action Program directed that an equipment operability or functionality review be performed. As a result, most of the samples reviewed were evaluated in a timely manner. However, the team noted examples of condition reports that had less than adequate documentation of evaluation activities. The details of this issue are documented in the observation section below.
Effectiveness of Corrective Actions:
Based on the samples reviewed, the team determined that the licensee was generally effective in corrective action implementation. In general, corrective actions for deficiencies that were safety significant were implemented in a timely manner. Problems identified using a root cause or other cause methodologies were resolved in accordance with Corrective Action Program requirements. The team determined that the licensee generally assigned corrective actions that were effective and timely for NRC identified issues and licensee event reports (LERs).
Assessment: Use of Operating Experience 71152B Based on the samples reviewed, the team determined that licensee's performance in the use of operating experience was generally effective. The licensee screened industry and NRC operating experience information for applicability to the station. The team observed the Operating Experience Screening Committee meeting and determined that the licensee initiated actions in the Corrective Action Program to fully evaluate the impact, if any, to the station. When applicable, actions were developed and implemented to prevent similar issues from occurring. Operating experience lessons learned were communicated and incorporated into plant operations. The team observed the information being used in daily activities, such as pre-job briefs, as well as issue reviews and investigations. The team did not identify any concerns in this area.
Assessment: Self-Assessments and Audits 71152B Based on the samples reviewed, the team determined that the licensee's performance of self-assessments and audits was generally effective. The licensee performed department self-assessments and nuclear oversight audits throughout the organization on a periodic basis. These self-assessments and audits were generally effective at identifying issues and enhancement opportunities at an appropriate threshold. The self-assessments and audits reviewed by the team identified issues that were not previously known, including issues within the Corrective Action Program itself. The licensee's Nuclear Oversight (NOS) identified deficiencies with the licensee's processes and those issues were addressed by the station through the Corrective Action Program. The team did not identify any concern in this area.
Assessment: Safety Conscious Work Environment 71152B The team reviewed the results from the 2019 Employee Concerns Annual Assessment, the 2019 and 2020 departmental safety culture surveys and the 2020 Gallup survey. The team also conducted one-on-one interviews with 23 licensee staff concerning the effectiveness of the Corrective Action Program, the ability to raise issues, and the freedom from potential retaliation for raising issues. The team did not identify any impediment to the establishment of a safety conscious work environment.
In general, the licensee's staff was aware of and familiar with the Corrective Action Program and other processes to raise nuclear safety concerns, such as the Employee Concerns Program. Licensee staff indicated they could raise nuclear safety concerns without a fear of retaliation. The team did not identify examples of retaliation for raising nuclear safety concerns. The licensee staff interviewed believed that operational issues and issues with high safety significance were being appropriately addressed in a timely manner.
Minor Violation: Failure to Follow the Operability Evaluation Procedure 71152B Minor Violation: In 2015, an NRC Component Design Bases Inspection identified a finding for the licensees failure to appropriately establish the in-service inspection boundaries for the safety-related component cooling water system. As part of the corrective actions, the licensee performed Engineering Change (EC) 56391 to upgrade steam generator sample coolers 1-QC-501-6 and 2-QC-501-9 from Seismic Class III to Seismic Class I.
On March 4, 2019, during the walkdown being performed in support of this EC, the licensee noted that support for cooler 1-QC-501-6 was missing the bottom unistrut bolt and support for cooler 2-QC-501-9 was missing a top mounting bolt. The licensee initiated AR 2019-1940 to document the missing bolts. The shift manager stated in the operability review section of the AR that an operability justification was not required because the support was Seismic Class III (not safety related). The licensee also created Work Order Task 55529607-01 to replace the bolts.
In May 2019, the missing top mounting bolt on cooler 2-QC-501-9 was replaced. However, the missing bottom unistrut bolt on cooler 1-QC-501-6 was not accessible and therefore not replaced. The work order was subsequently closed in June 2019.
In January 2020, the licensee discovered that the work order was closed and wrote AR 2020-0255 to ask Engineering to accept the condition as-is. However, engineering stated in the AR that evaluating the acceptance of the missing bolt as-is required significant engineering resources. Therefore, work order 55561980 was initiated to replace the missing bolt, which was in planning status at the time of this inspection.
During this inspection, the team noted the licensee incorrectly treated the affected piping section as Seismic Category III when evaluating the need to perform an operability determination. Procedure PMP-7030-OPR-001, Operability Determination, Revision 37, required an operability evaluation for Seismic Class I components such as this piping section.
The team determined that the failure to follow this procedure was a performance deficiency and a violation of 10 CFR 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings."
Screening: The inspectors determined the performance deficiency was minor. The performance deficiency was minor because it did not adversely affect the mitigating systems cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the deficiency did not result in reasonable doubt about the equipments seismic qualifications as the licensee did not have to revise any calculation or evaluation to resolve the associated operability concerns.
Enforcement:
This failure to comply with 10 CFR50 Appendix B, Criterion V, constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
Observation: Lack of Technical Rigor in Corrective Action Program Evaluation 71152B The team noted examples of lack of technical rigor in corrective action program evaluations, including:
The licensees audit determined a vendors quality assurance program was ineffective as documented in AR 2019-12088. The licensee removed the vendor from the Approved Suppliers List / Quality Suppliers List and concluded items received from that vendor after January 2017 required additional quality evaluation for acceptance or rejection. The licensee also determined that a sight glass provided by this vendor was installed on the oil reservoir for the Unit 1 east charging pump 1-PP-50E. The licensee performed discrepant condition evaluation (DCE) 2020-0390 to evaluate the impact of the non-qualified sight glass to the charging system and initiated work order 55542705 to replace the sight glass with a quality-related part. The DCE concluded that the sight glass had the same form, fit and function as a quality assurance (QA)qualified installation. Therefore, the licensee concluded that the part would maintain the required integrity with no additional justification. However, the team concluded the DCE did not provide sufficient technical justification because it did not consider relevant attributes such as seismic qualifications, material properties and equipment qualification (EQ) as the licensee would have to perform for the unqualified spare parts. The inspectors determined there was no significant safety impact since the sight glass was replaced within a reasonable amount of time.
The licensee generated AR 2020-4967 for degraded essential service water piping due to flow accelerated corrosion. The licensee determined that the minimum allowable wall thickness criteria established in procedures for certain areas were non-conservative due to the presence of welded piping attachments. The licensee created assignments to correct the calculations, revise the affected inspection procedures, and review the extend of condition. However, the team noted the licensee did not establish an interim action until the procedures were revised. The licensee entered this issue into the corrective action program as AR 2021-6742 and planned to revise the affected procedures to add interim guidance. The licensee did not identify examples of unacceptable wall thickness that were deemed acceptable due to the non-conservative acceptance criteria.
The licensee failed to perform an operability evaluation because it incorrectly determined the affected component was Seismic Class III (not safety related). This issue was documented as a minor violation in this inspection report.
The inspectors concluded that the lack of technical rigor in corrective action program evaluation represented a weakness in addressing deficient conditions. The licensee entered this issue into the corrective action program as AR 2021-7077.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On August 5, 2021, the inspectors presented the biennial problem identification and resolution inspection results to you and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Security Survey Results
07/2019
Material Management Survey Results
08/2019
Chemistry/Environmental Survey Results
11/2019
Work Control and Schedule Survey Results
09/2020
2010-11114
Exposed Insulation Found During U2C19 Recirc Sump
Walkdown
10/19/2010
2013-13536
NRC Comment on Methodology of Vortex Calculations
09/13/2013
2013-16557
Cable Tray and Conduit Overfill Issues
10/28/2013
2014-14190
Failure of 2D5 Synch Circuit
11/12/2014
2014-15099
Identified a Pin Hole Leak in 2-HV-AFP-EAC ESW Piping
10/02/2014
2015-4459
ISI-Scope Deferral for U2C22
03/31/2015
2016-12216
U2C23 Baffle-Former Bolt UT Inspection Results
10/23/2016
2016-1537
AR 2016-1537 Plant and Drawing Configuration Discrepancy
for Condensate System
2/08/2016
2016-7752
PRT Seismic Anchor Movement
06/30/2016
2017-11986
1SI-158-L2/L3 Leakage Above Acceptance Criteria
11/22/2017
2017-4740
Loss of CCS Charging Warrants an AOP
05/09/2017
2017-7596
Floor Drain Credited in Fire Modeling Are Not Monitored
08/07/2017
2017-9084
AR 2017-9084, 12-OME-129-9 Glycol Chiller #9 Trouble
Alarm
09/16/2017
20174-5989
N-Train Battery Charger Part Evaluation
06/15/2017
2018-10025
AR 2018-10025 Update Drawing Desktop Guide
10/30/2018
2018-1045
Missed Security Patrol
2/01/2018
2018-10451
NRC Inspection QHSA-71124.05 Rad Monitoring
Instrumentation
11/15/2018
2018-11245
2-DR-GCS2 Missing Required Door Sweep
2/17/2018
2018-6613
Inadequate Evaluation of LOCA Anchor Motions
06/26/2018
2018-7204
Deficiency of Evaluation of Emergency Level Conditions
07/17/2018
2018-9690
1-OME-150-AB Fuel Line Leak Near #6 Rear Fuel Injector
10/16/2018
2019-10855-4
Review Installation of Sight Glass in 1-PP-50E
01/14/2020
Corrective Action
Documents
2019-11077
Drop in Frequency Noted During LOP/LOCA Testing
11/07/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2019-12088
Vendor Quality Program Ineffective
2/11/2019
2019-12191
GT 2019-12191, Cook Review of NRC IN-2012-22, Rev 1:
Counterfeit, Fraudulent, Suspect Item (CRSI) Training
Offerings
11/20/2019
2019-12255
Corrosion in Fire Protection Piping
2/17/2019
2019-1349
Bent Hanger in U2-East RHR Pump Room 2-GRH-V819
2/11/2019
2019-1398
Determine Impact (CDI) for Completion of SD-180820-001
2/12/2019
2019-4190
Air Void Per UT is Unacceptable Location Prior to 1-IMO-261
04/21/2019
2019-5275
Transcript Error of SRD Calibration
05/16/2019
2019-6691
Negative Trend of INPO Radiation Protection Events
Indicator
07/08/2019
2019-6882
AR 2019-6882, Unit 2 Ice Bed Temps above ESOMS
Notification Limits
07/15/2019
2019-6998
AR 2019-6998 Unexpected Alarm in Unit 2 Control Room
07/18/2019
2019-7047
Received a 204 Drop 13 South NESW PP Strainer DP High
07/21/2019
2019-7276
AR 2019-7276 Intermittent Alarm 2-SG-7 PT 162
07/27/2019
2019-8320
AR 2019-8320 Unit 2 ITS 5.5.12.d Specific Requirements
May Not Being Met
08/29/2019
20-0255
WOT 55529607 Was Not Completed as Prescribed
01/09/2020
20-0390
1-PP-50E, Replace Sight Glass Installed Under WO 55455925
01/13/2020
20-0529
Update Specs to Support Section XI Requirements
01/16/2020
20-10105
MTS UPS Condition Identified During PM
2/10/2020
20-10439
GT 2020-10439 Cook Review of IN 2020-004 - Operating
Experience Related to Failure of Buried Fire Protection Main
Yard Piping
2/23/2020
20-10440
GT 2020-10440 Cook Review of IN 2018-11, SUPPLEMENT
1: QA Record Falsification at Kobe Steel and Other
International Vendors 12/23/2020
2/23/2020
20-1047
ACE AR 2020-1047, Gland Seal Effluent RMS High Range
Reading
2/16/2020
20-1877
CCE AR 2020-1877 ERO Qualification Process and Tracking
in PQM
01/13/2021
20-2027
Failed Operations Surveillance
2/28/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
20-2642
ACE AR 2020-2642 Radiation Monitor Communication to
Control Room Lost
06/25/2020
20-3709
RCE CR 2020-3709 RCS Leak - Plug Unit 1 NRV-163/NRV-
164 Bellows Tell-Tale at the Bonnet
08/04/2020
20-3739
ACE AR 2020-3739, 2-NRI-32 is Slowly Failing Low
09/19/2020
20-4285
Actions are Not Always Changing Workflow State as
Required
05/20/2020
20-4891
AR 2020-4891, 1-VTR-185 High Temp Alarm
06/15/2020
20-4946
Wrong Radiation Work Permit used to Enter the U2 Vestibule
06/17/2020
20-4967
Degraded ESW Pipe Downstream of 1-WMO-715
06/17/2020
20-6117
NOS Identified Deficient Execution of Fire Door Surveillance
08/03/2020
20-7242
GT 2020-7242, Cook Review of IN 2020-02 - FLEX Diesel
Generator Operational Challenges
11/23/2020
20-8177
Performance Issues/Common Cause
10/05/2020
21-0169
Cook Review of IN 2007-21, Supplement 1: Pipe Wear Due
to Interaction of Flow-Induced Vibration and Reflective Metal
Insulation
01/06/2021
21-2008
CCE AR 2021-2008, Glycol Chiller Failure Possible Trend
04/28/2021
21-2838
CCE AR 2021-2838 Vulnerabilities introduced During Design
Modifications
04/05/2021
21-2858
AR 2021-2858 U2 Ice Condenser FME Walkdown
04/06/2021
21-3139
AR 2021-3139 Disparity in Unit 2 Source Range Readings
04/17/2021
21-4239
AR 2021-4239, 2-NRV-152 Failed as Found Stroke Time on
Backup Air
05/11/2021
21-4250
GT 2021-4250 Cook Opex Review of NRC IN 21-01,
Lessons Learned from NRC Inspections of Design-Basis
Capability of Power-Operated Valves at Nuclear Power
Plants
05/11/2021
21-4721
Steam/Water Leak on 2FW-115-4
05/21/2021
21-4722
DPM Condensate Leak
05/22/2021
21-4743
2-SV-1A-4 Steam Leak
05/23/2021
21-4750
Leak by on 1-CW-344E
05/23/2021
21-4812
Minor RCS Back Leakage Suspected Through 1-SI-152S
05/25/2021
21-4817
WR Only to Install Missing Clips on CCW Cooling Coils
05/25/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
21-4882
1-OME-34W Packing Leaks on Inlet and Outlet Valves
05/26/2021
21-5016
U2 CD EDG Coalescing Filter Air Leak
06/01/2021
GT 2020-10549
White Finding for Check Valve Not Meeting IST
Requirements
2/30/2020
GT 2021-1076
Perform OE Evaluation for James A Fitzpatrick Finding
2/01/2021
GT 2021-2166
Westinghouse Technical Bulletin TB-19-5 Rev. 1
03/09/2021
21-6378
Drawing Updated Prematurely and EDB Impacts Missed
07/22/2021
21-6638
Operability Review of CR 2019-1940 & Seismic Class
07/29/2021
21-6742
Interim Guidance Not Developed for UT Exam
08/03/2021
21-6785
Attachments Not Attached to AR 2019-1349-2
08/04/2021
21-6809
DIT / Calc Guidance for FAC Tmins Do Not Include WPA
Stresses
08/04/2021
21-7077
Observation of Technical Rigor in ENG Products
08/16/2021
Corrective Action
Documents
Resulting from
Inspection
21-7078
NRC Observation on CR Generation Rates
08/16/2021
Engineering
Evaluations
03554
DIT-B-03554-00-Provided Program Engineering with
Minimum Allowable Pipe Wall Thicknesses
11/22/2013
Operations Survey Results
06/2019
Miscellaneous
5700-11
Interim Acceptance Criteria for Safety Related Piping System
NDE Reports
1-OHP-4030-102-
017
RCS Pressure Isolation Valves Leak Rate Surveillance Test
10/20/2020
2-EHP-5043-
EDC-001
Evaluation of Degraded/Nonconforming Conditions
29
2-MHP-5021-
2-018
Emergency Diesel Engine Fuel Injector Maintenance
ECP-01
Employee Concerns Program Administration Manual
PMI-7030
Corrective Action Program
PMP-7030-CAP-
001
Action Initiation
PMP-7030-CAP-
2
Condition Action and Closure
PMP-7030-MOP-
001
Corrective Action Program Management Oversight Process
Procedures
PMP-7030-OPR-
037
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
001
2019-1575-1
GT 2019-1575-1; CRE Program Full SA; ESYN; System
Engineering NSSS
09/25/2019
2019-8560
AR 2019-8560 DIT Inappropriately Updated BOM for SI
Pumps Caused Configuration Change
09/09/2019
2019-8779
ARM-19-09-01 Mods Not Adequately Prepared with Excess
Emergent Problems After Implementation
10/17/2019
21-6317
AR 2021-6317; 1-WRV-723: AB Emergency Diesel North
Combustion Air Aftercooler HE-47-ABN ESW Inlet/Bypass
Valve
07/20/2021
GT 2019-11203
Improvement Actions
11/10/2019
GT 2020-8602
Biennial PI&R Inspection
2/25/2021
NOS 19-04
Material Control, and Measuring and Test Equipment
07/25/2019
NOS-19-03
Maintenance, Work Control, and Special Processes
06/25/2019
NOS-19-05
Nuclear Oversight Audit - Corrective Action Program
07/29/2019
NOS-19-08
NOS Audit - Engineering, Design Control, & In-Service
Inspection (ISI)/In-Service Testing (IST)
10/17/2019
NOS-20-03
NOS Audit NOS-20-03, Emergency Preparedness
04/04/2020
NOS-21-01
REMP/ODCM
04/08/2021
Self-Assessments
SA-2019-ECP-
001
2019 Employee Concerns Annual Assessment
01/17/2020
Work Orders
55547169
Plug Unit 1 NRV-163 and NRV-164 Bellows Tell-Tale at the
11/05/2020