IR 05000341/2020004
| ML21041A276 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 02/10/2021 |
| From: | Nestor Feliz-Adorno NRC/RGN-III |
| To: | Peter Dietrich DTE Electric Company |
| References | |
| IR 2020004 | |
| Download: ML21041A276 (25) | |
Text
February 10, 2021
SUBJECT:
FERMI POWER PLANT, UNIT 2 - INTEGRATED INSPECTION REPORT 05000341/2020004
Dear Mr. Dietrich:
On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Fermi Power Plant, Unit 2. On January 19, 2021, the NRC inspectors discussed the results of this inspection with Mr. E. Olson, 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,
/RA/
Néstor J. Féliz Adorno, Chief Branch 4 Division of Reactor Projects
Docket No. 05000341 License No. NPF-43
Enclosure:
As stated
Inspection Report
Docket Number:
05000341
License Number:
Report Number:
Enterprise Identifier: I-2020-004-0062
Licensee:
DTE Electric Company
Facility:
Fermi Power Plant, Unit 2
Location:
Newport, MI
Inspection Dates:
October 01, 2020 to December 31, 2020
Inspectors:
T. Briley, Senior Resident Inspector
T. McGowan, Resident Inspector
V. Myers, Senior Health Physicist
R. Ng, Project Engineer
T. Taylor, Resident Inspector
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 an integrated inspection at Fermi Power Plant, Unit 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.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
Unit 2 began the inspection period at rated thermal power. On November 18, 2020, the unit was down powered to 94 percent rated thermal power for planned hydraulic control unit maintenance. The unit was returned to rated thermal power the following day. On November 20, 2020, the unit was down powered to 74 percent rated thermal power for a planned control rod pattern adjustment. The unit was returned to rated thermal power the following day. The unit 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 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 Disease 2019 (COVID-19),resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week; conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; observed risk-significant activities; and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or portions 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
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of the cold weather winter months for the following systems:
- Plant heating steam, including secondary containment isolations
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 due to a high wind advisory on November 19, 2020
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) Division 2 emergency diesel generators (EDG) 13 and 14 while EDG 11 was out of service for maintenance during the week ending October 10, 2020
- (2) Division 2 emergency equipment cooling water while the reactor core isolation cooling (RCIC) system was out of service for maintenance during the week ending November 7, 2020
- (3) Division 1 non-interruptible air system (NIAS) while Division 2 NIAS was out of service for maintenance during the week ending November 21, 2020
- (4) Division 2 emergency equipment service water (EESW) while Division 1 EESW was out of service for maintenance during the week ending December 5, 2020
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Division 1 residual heat removal (RHR) system during the week ending October 31, 2020
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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) Auxiliary building first floor, Division 1 switchgear room during the week ending October 17, 2020
- (2) Auxiliary building basement, control rod drive pump room during the week ending October 17, 2020
- (3) Reactor building basement and sub-basement, north east quad during the week ending December 12, 2020
- (4) Circulating water pump house during the week ending December 12, 2020
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) Relay room
- (2) Division 1 switchgear room
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) EDG 13 lubricating oil, jacket water, and air coolant heat exchangers
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 program annual operating test administered between October 19 and November 20, 2020
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a licensed operator requalification graded scenario in the control room simulator on October 8, 2020
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (6 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) Reactor recirculation system during the week ending October 31, 2020
- (2) Reactor feedwater system during the week ending November 28, 2020
- (3) Safety relief valves during the week ending December 12, 2020
- (4) NIAS during the week ending December 5, 2020
- (6) Visual annunciator system during the week ending December 19, 2020
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 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) Division 1 switchyard breaker GK and EDG 11 out of service for planned maintenance during the week ending October 10, 2020
- (2) RCIC system and offsite power Shoal line planned maintenance, and emergent work on combustion turbine generator (CTG) 11-1 with CTG 11-2 and 11-4 out of service during the week ending November 7, 2020
- (3) Emergent work on main turbine control system during the week ending December 31, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (2 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Operability and functionality of RCIC following Division 1 high steam line flow master trip unit failure, as documented in condition assessment resolution document (CARD) 20-39104
- (2) Operability and functionality of EDG 11 following identification of a change in crankcase oil chemistry parameters, as documented in CARD 20-33238
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Condensate storage tank vortex suppressor installation (permanent)
- (2) Uninterruptible power supply 'B' logic and fuse sizing change (permanent)
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Reactor building outer railroad door testing following identification of a degraded seal during the week ending October 3, 2020
- (2) RCIC system testing following a planned maintenance outage during the week ending November 7, 2020
- (3) Reactor building ventilation radiation monitor testing following identification of spurious operation and trips during the week ending November 14, 2020
- (4) Division 2 NIAS system testing following planned maintenance during the week ending November 28, 2020
- (5) Recirculation pump 'B' differential pressure channel 'B' master trip unit (MTU) testing following planned MTU replacement during the week ending December 4, 2020
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) EDG 13 slow start surveillance testing during the week ending October 24, 2020
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) Division 2 core spray auto actuation testing during the week ending December 12, 2020
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) N+1 Neptune pump testing during the week ending November 28, 2020
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors completed an evaluation of submitted emergency action level and emergency plan changes on December 8, 2020. This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) Emergency preparedness tabletop drill on October 8,
RADIATION SAFETY
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
Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program
GPI Implementation (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees implementation of the Groundwater Protection Initiative program to identify incomplete or discontinued program elements
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage,
& Transportation
Radioactive Material Storage (IP Section 03.01)
- (1) Inspectors evaluated the licensees performance in controlling, labelling and securing radioactive materials
Radioactive Waste System Walkdown (IP Section 03.02) (1 Sample)
- (1) Inspectors walked down accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality
Waste Characterization and Classification (IP Section 03.03) (3 Samples)
The inspectors evaluated the licensees characterization and classification of the following radioactive waste shipments:
- (1) EF2-19-050, resin
- (2) EF2-20-040, torus paint chips
- (3) EF2-20-117, resin
Shipment Preparation (IP Section 03.04) (1 Sample)
The inspectors observed the preparation of the following radioactive material shipment:
- (1) EF2-20-120, resin shipped as Type B
Shipping Records (IP Section 03.05) (3 Samples)
- (1) EF2-19-050, resin shipped as LSA-II
- (2) EF2-20-040, torus paint chips shipped as LSA-II
- (3) EF2-20-117, resin shipped as Type B
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
EP01: Drill/Exercise Performance (IP Section 02.12)===
- (1) July 1, 2019 through September 30, 2020
EP02: ERO Drill Participation (IP Section 02.13) (1 Sample)
- (1) July 1, 2019 through September 30, 2020
EP03: Alert & Notification System Reliability (IP Section 02.14) (1 Sample)
- (1) July 1, 2019 through September 30, 2020 BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (1 Sample)
- (1) July 1, 2019 through September 30, 2020
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) July 1, 2019 through September 30, 2020
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) July 1, 2019 through September 30, 2020
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends that might be indicative of a more significant safety issue
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) A sample of issues open in the corrective action program with operability being maintained via compensatory measure or pending some final action to update or change the design basis. The inspectors reviewed a partial modification to the condensate storage tank to address the potential for vortexing, a degraded valve in the lube oil system for EDG 14, and licensee follow up to an error in methodology regarding motor operated valve calculations that had been discovered during a prior NRC inspection.
71153 - Follow-up of Events and Notices of Enforcement Discretion Personnel Performance (IP Section 03.03)
- (1) The inspectors evaluated a control rod drive hydraulic system transient and licensees performance on November 14,
INSPECTION RESULTS
Observation: Semi-Annual Corrective Action Program Trend Review 71152 The inspectors noted a trend in organizational and programmatic issues entered into the corrective action program that did not have sustainable corrective actions. Several examples included, but were not limited to, the following:
- In May 2019, following a planned safety system maintenance outage for EDG 14, Nuclear Quality Assurance (NQA) identified several tube clamps taped to the wall in the EDG 14 room that had not been reinstalled as intended. The primary cause listed in the organizational effectiveness analysis that followed was inadequate field oversight. Specifically, it concluded that one field supervisor was not sufficient to oversee multiple major-scope jobs occurring in parallel. However, none of the corrective actions taken addressed the primary cause or the organizational issues which led to the breakdown during the EDG outage. The missing clamps ultimately did not impact EDG 14 operability.
- In February 2020, the licensee initiated CARD 20-21195 for some organizational effectiveness issues associated with execution and implementation of a planned safety system maintenance outage for EDG 13. The licensee determined the work delays were caused by issues with how the schedule was prepared, communication challenges between day and night shift and between departments, and the operations department not being formally part of the outage control center (OCC) staff. The corrective action was to revise a post-outage critique form which added some organizational effectiveness questions. However, the inspectors noted this corrective action did not address issues associated with the execution and implementation of system outages because the post-outage critique form was used following the completion of safety system outages.
- During the most recent refueling outage (i.e., from March to August 2020), the inspectors identified foreign material issues (mainly small cleanliness issues) during their primary containment closeout inspection. Most of the material was fairly easy to find or was discovered in a location that was easily accessible. During the prior refueling outage, inspectors also noted a large amount of material during their closeout inspections. Given the prior issues, the inspectors questioned the process the licensee employed to validate primary containment cleanliness prior to final closeout. In response, the licensee added a list of drywell areas and a reference to operations department cleanliness standards to a work order used by decontamination personnel. However, these actions were similar to those documented for a similar issue captured in May 2018 as CARD 18-23959. The inspectors questioned the effectiveness of implementing corrective actions that were similar to actions that were already in place and demonstrated to not address the issue during the most recent refueling outage.
The inspectors discussed their observations with licensee staff, who subsequently generated CARD 21-20263 to capture the issues. Through the discussions with licensee personnel, the inspectors learned that licensee staff had recently noted similar (but separate) issues regarding sustainability of corrective actions as part of a self-assessment. The inspectors will continue to routinely monitor CAP performance via the baseline inspection program.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 19, 2021, the inspectors presented the integrated inspection results to Mr. E. Olson, Site Vice President, and other members of the licensee staff.
- On October 22, 2020, the inspectors presented the radiation protection inspection results to Mr. R. LaBurn, Radiation Protection Manager, and other members of the licensee staff.
- On December 8, 2020, the inspectors presented the emergency action level and emergency plan changes inspection results to Mr. E. Olson, Site Vice President, and other members of the licensee staff.
- On December 15, 2020, the inspectors presented the licensed operator requalification program annual operating test results inspection results to Mr. A. Spencer, Licensed Operator Requalification Program Lead, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
20-29557
NQA-First Level Escalation-Repeat Deficiencies with
Seasonal Readiness Activities
08/24/2020
20-32239
Pri 4 Cold Weather Prep Work Order Not Scheduled
11/16/2020
Engineering
Changes
TM-16-0025
Install One Temp Boiler and Provide Spare Connections for
a Second Temp Boiler
11/08/2016
Miscellaneous
MOP01-200
Severe Weather Guidelines
Procedures
MWC16-100
Seasonal Readiness
Work Orders
51732374
Perform MWC16-100 Cold Weather System Readiness
Review Checklists
03/20/2020
Calculations
DC-6356
Stress and Seismic Analysis of the Reactor/Auxiliary
Building CTI Nuclear Fan Coil Units
A
Corrective Action
Documents
20-31283
Damaged Labels - RBSB NW
10/15/2020
20-31377
Torus Room AZ 250
10/19/2020
20-31440
NRC Identified Condition, Insulation Repairs
10/20/2020
20-32269
NRC Identified Issue: The E1100F619A and E1100F619B
have Local Manual Positioners but are Not Tracked by
Valve Lineups
11/17/2020
20-32273
NRC Concern: Missing Label on P50R413A
11/17/2020
Drawings
Diagram Residual Heat Removal (RHR) Division I
BQ
Diagram Residual Heat Removal (RHR) Division I
BQ
EECW Division II Functional Operating Sketch
BD
Emergency Diesel Generator System Functional Operating
Sketch
BL
M-2015
Station and Control Air
M-4615
Interruptible and Non-Interruptible Control Air
AH
M-5706-3
RHR Service Water Make-Up Decant and Overflow
Systems
AH
M-5729-2
Emergency Equipment Cooling Water Division II
BD
Miscellaneous
Operator Logs
Operations AUTOTOUR Logs - Reactor Building
Procedures
23.129
Station and Control Air
21
23.205
Division 1 RHR LPCI Standby Lineup Verification,
8A
147
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
23.208
RHR Complex Service Water Systems
29
Fire Plans
FP-AB-2-9b
Auxiliary Building, Division 1 Switchgear Room, Zone 9, El.
613'6"
FP-AB-B-4b
Control Rod Drive Pump Room, Zone 4, El. 562'0"
FP-CWPH-1-32
Circulating Water Pumphouse Zone 32 Elevation 58'6"
FP-RB-B-5b
Reactor Building Basement Northeast Corner Room
Zone 5, Elevation 562'0"
Engineering
Evaluations
EF2-PRA-011
Internal Flood Walkdown Summary Notebook
EF2-PRA-012
Fermi 2 Nuclear Power Station PRA Internal Flood Analysis
Notebook
Calculations
DC-5804
Diesel Generator Service Water Design Basis
Requirements Calculation
F
Miscellaneous
MES540001
EDG 11 Air Coolant Heat Exchanger Inspection Report
10/05/2020
MES54001
EDG 11 Jacket Cooling Heat Exchanger Inspection Report
10/05/2020
MES54001
EDG 11 Lube Oil Heat Exchanger Inspection Report
10/05/2020
Miscellaneous
Fermi 2020 LORT Annual Operating Test Summary Results
2/15/2020
71111.11Q Miscellaneous
SS-OP-904-2001
Evaluation Scenario
Corrective Action
Documents
17-25639
Management Review Committee (MRC) Cognitive Trend -
06/27/2017
18-20350
North Reactor Feed Pump Turbine Lube Oil Level High
01/16/2018
18-20351
N RFPT Turning Gear Engage Solenoid Valve (N21F111A)
is Blowing By
04/30/2018
18-23923
Received 5D28 South RFP/RFPT Shaft Trouble While
Taking the N RFP Out of Service
05/17/2018
19-20000
Unexpected Alarm During Startup of NRFPT
01/01/2019
19-20309
SRV 'A' (B2104F013A) Tail Pipe Temperature Elevated to
~205F
01/14/2019
19-20660
SRV 'J' Tail Pipe Temperature Elevated to ~212F
01/30/2019
19-21751
Need RF20 WO to Perform a Body Off Inspection of
SRV 'A' due to Elevated Tailpipe Temperatures per CARD
19-20309
03/06/2019
19-23939
2019 DBAI: MRFF Action Needed for Previously Closed
CARD 17-23452
05/22/2019
19-24545
Oil Surrounding Mechanical Seal on RRMG LO
06/17/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
B3103C001D
19-28069
Excessive Carbon on Brushes and Intake
10/23/2019
20-00023
Bushing Broken on N2100-F006B SRFPT OTBD Seal
Water TCV Outlet Isolation Valve
03/23/2020
20-20091
Division 1 RHR Pump Room Dampers
01/06/2020
20-20099
Abnormal Noise/Indications from P50-F516A Solenoid
01/06/2020
20-21585
Time Delay Relay P50M832 Failed as Found Testing
2/12/2020
20-21602
Division 2 Control Air Compressor Failed PMT
2/13/2020
20-21659
Control Air Compressor PMT
2/14/2020
20-21688
Online Work Orders for Vendor Inspection of Recirc MG Set
Brushes and Potential Stoning
2/14/2020
20-21708
As-Found Condition of Division II NIAS Dryer
2/16/2020
20-21840
Division 2 Control Air Compressor Will Not Load
2/11/2020
20-21936
X4103F128 Excessive Scoring on Hydra Motor Shaft
2/20/2020
20-23975
Received 3D19 Annunciator System Trouble
2/16/2020
20-24502
VAS Total System Failure
04/14/2020
20-24779
VAS Multiplexor C Time Errors
04/19/2020
20-25054
Potential Common Cause Failure of VAS
04/23/2020
20-25856
Discharge Pressure is High Out of Spec for N RRMG Set
Lube Oil Pump (B103C001A)
05/17/2020
20-25881
B3103C001D PMT Unsatisfactory due to Vibration Level
05/18/2020
20-26161
Stopped and Backed Out of 27.129.04
05/27/2020
20-26271
Findings from Division 1 NIAS Air Dryer Troubleshooting
05/29/2020
20-26312
VAS Clock Signal Distortion Cause and Remediation
05/30/2020
20-26672
RRMG Set Lube Oil Level Challenges in Refuel Requires
Add and Removal of Oil
06/08/2020
20-26692
P603 VAS Alarm Check Malfunction and System Battery
Low Voltage Warning
06/08/2020
20-26723
Dual Indication for Open Damper X4103F115
06/10/2020
20-26772
Dual Indication for Open Damper X4103F103
06/10/2020
20-27423
Two of Four North and South RFPT Speed Indications in
IPCS Erroneous
06/29/2020
20-28723
UNSAT SRV Inspection
07/28/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
20-29013
SRV 'A' Tailpipe Temperature Elevated Following RF-20
Startup
08/06/2020
20-29165
SRV 'M' Tailpipe Temperature Elevated Following RF-20
Startup
08/10/2020
20-30180
Abnormal Speed Changes on South RFPT
09/13/2020
20-30351
Learnings from Industry Responses for 20-30180, SRFPT
Speed Anomaly
09/17/2020
20-30443
Abnormal Speed Differential Between North and South
09/21/2020
20-30554
Three SRVs Removed in RF-20 Found Outside of
As-Found Set-Point Tolerance
09/24/2020
20-30779
Oil Leak
09/30/2020
20-32479
Trend CARD - B2104F013A Tailpipe Temperature Increase
11/25/2020
20-32730
Broken Insulation in Hydra Motor Electrical Housing
2/08/2020
Engineering
Evaluations
Monthly Maintenance Rule Evaluation Report - Safety Relief
Valve - September 2020
10/09/2020
Miscellaneous
RHR Complex Ventilation (X4103) System Performance
Monitoring Plan
09/20/2020
P5002 (NIAS) System Monitoring Plan
03/15/2019
ACMP 20-007
SRV 'A' & 'M' Weeping
MMR 02
Maintenance Rule Program Description
6A
MMR 10
Maintenance Rule, Monitoring
18A
MMR APP E
Maintenance Rule Conduct Manual, Appendix E,
Maintenance Rule SSC Specific Functions
MMR Appendix B
Maintenance Rule Conduct Manual, Terms and Definitions
MMR Appendix D
Maintenance Rule Conduct Manual, Guidelines for
Determining Functional Failures and Maintenance
Preventable Function Failures
MMR Appendix E
Maintenance Rule Conduct Manual, Maintenance Rule SSC
Specific Functions
MMR Appendix F
Maintenance Rule Conduct Manual, Maintenance Rule
Performance Criteria
Monthly M-Rule
Evaluation Report
Tracking Group: N2100
July -
September,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
20
Plant Health
Report
Reactor Feedwater (System N2100)
2019, Quarter
and 2
Plant Health
Report
Condensate and Heater Feed Pumps (System N2000 and
N2003)
2019, Quarter
Plant Health
Report
Reactor Feedwater (System N2100)
2019, Quarter
Plant Health
Report
Reactor Feedwater (System N2100)
20, Quarter
1, 2, and 3
VMR1-46
Target Rock Model 7567F Safety Relief Valves Vendor
Manual
J
Procedures
23.420
RHR Complex Heating and Ventilation
23.621
Main Control Room Annunciator and Sequence Recorder
24.129.04
Control Air Valve Operability/Position Verification/Isolation
Integrity Test
49.419.002
VAS USER
Visual Annunciator System (VAS) User Manual
Work Orders
54506175
North Recirc MG Set Slip Ring Measurement
04/09/2020
54506203
South Recirc MG Set Slip Ring Measurement
04/08/2020
Corrective Action
Documents
15-21424
Number 2 HPSV went Closed and Then Open to 22 Percent
Multiple Times
2/21/2015
20-30925
Radka Air Compressor Air Leak
10/05/2020
20-31945
CTG 11-1 Not Ratcheting
11/04/2020
20-32152
Shoal Line Maintenance Risk Evaluation
11/11/2020
20-32176
Operations Performance Gap in Risk Management and
Identification of Risk
2/02/2020
20-33180
4D91 Electric Governor Trouble Number 1 HP Stop Valve
CC2 HW
2/23/2020
Corrective Action
Documents
Resulting from
Inspection
20-33113
Update ARP Action for Ratchet Trouble
2/21/2020
Miscellaneous
EF2-PRA-005.33
Combustion Turbine Generators (CTGs)
MMR APP H
Maintenance Rule Conduct Manual, Appendix H - On-Line
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Core Damage Risk Management Guidelines
Procedures
11D50
CTG 11 Unit 1 Trouble Alarm Response Procedure
ARP 4D91
Electric Governor Trouble
MMR12
Equipment Out of Service Risk Management
20A
MOP05-100
Protected Equipment
2C
MWC15
Elevated Risk Management
Corrective Action
Documents
20-31904
MTU Failed During 44.020.234
11/03/2020
20-33238
EDG 11 Crankcase Oil Exhibits Increased Fuel Oil in the
Crankcase Oil
11/29/2020
Procedures
44.020.234
NSSSS-RCIC Steam Line Flow, Trip System B
Calibration/Functional
Work Orders
54136747
Perform 44.020.234 NS4 RCIC Steam Line Flow, Trip
System B, Calibration/Functional
11/03/2020
Corrective Action
Documents
19-23227
Recommend Review of Site Response to Open
CARD 07-23630
04/26/2019
20-23661
UPS Battery Feed to UPS-B Fuse Found Blown
04/21/2020
20-26704
3071-128-EJ Spec R3100S027 Fuse Discrepancy
07/03/2020
20-27546
UPS B Appears to Have Repeat Failure of Battery Fuse
07/02/2020
20-27855
UPS A and B Fuse Ratings
07/09/2020
20-31438
Material Found at Bottom of Condensate Storage Tank
10/20/2020
20-31468
18-inch Pipe Clamp Bolt Length Issue
10/21/2020
20-31488
Threaded Rod Set Screw Too Short
10/21/2020
Drawings
M-5715-3
EDP-80127-018
M-5721-1
EDP-80127-006
M-Y-2000
EDP-80127
A
Engineering
Changes
80127
ECCS Pump CST Vortex Suppression Device
B
DEC 70303
UPS A/B DC Circuit Fuses and Cables
A
DEC 70304
UPS B Parallel Operation Software Change
EDP 70042
UPS A and B Replacement
C
Miscellaneous
Risk Management
Plan
CST Vortex Suppression
10/19/2020
Corrective Action
Documents
20-30561
Received 3D6, Division 1/2 Reactor Building Vent Exhaust
Rad Monitor Upscale Trip, RBHVAC Trip, and D1 SGTS
09/24/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
20-30756
While Replacing Seals on RR Car Interlock Door, 4 Bolts
Failed While Removing Bolts
09/30/2020
20-30824
East and West Airlock Door Seal Long Term
Recommendations
10/01/2020
20-32018
RCIC Turbine Exhaust Rupture Disc Leak
11/06/2020
20-32205
NRC Identified: IST Program Testing Methodology for
E5100F011
11/13/2020
Drawings
Reactor Building Main Control Room A/C Mode Selection
Division 1
Reactor Building Secondary Containment Isolation Signals
Division 1
T
Core Spray System CSS Reactor Building
High Pressure Coolant Injection System Reactor Building
BP
Reactor Core Isolation Cooling System
BE
Reactor Core Isolation Cooling System Barometric
Condenser
AT
Miscellaneous
2A1354AR
Reactor Core Isolation Cooling System
Clearance:
D1100-000138
Jumper Out High High Trip of Division 1 Rad Monitor
11/13/2020
ERE 54575
Evaluate Suitability of Replacement Garlock 3400 Sheet
VMR4-15
Continental Disc Corp
A
Procedures
23.206
Reactor Core Isolation Cooling System
104
24.206.01
RCIC System Pump and Valve Operability Test
44.030.073
ECCS - Reactor Recirculation Pump B DP, Division 1,
Channel B Calibration/Functional
46.206.001
RCIC Turbine Governor Control System Calibration
45A
Work Orders
231076
Replace MTU B31N614A - Tin Whisker Susceptible
Rosemont 710DY MTU
11/30/2020
2386240
Replace and Calibrate RCIC Speed Controller (EG-M)
11/02/2020
2386240
Replace and Calibrate RCIC Speed Controller (EG-M)
01/14/2015
43954320
Replace NIAS Isolation Valve P5000F403 Solenoid Valve
11/17/2020
43954342
Replace Time Delay Relays in P50P402B, D2 NIAS Dryer
Control Cabinet
11/17/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
53421010
Calibrate Pressure Switch RCIC Pump Suction Low
Pressure Trip
11/03/2020
54136663
Perform 24.206.01 RCIC System Pump Operability and
Valve Test at 1000 PSIG
11/05/2020
268801
Replace Division 2 S Control Air Compressor Unloading
Cylinder Solenoid Valve
11/17/2020
58734795
Troubleshoot/Replace Relay T41M80 in H21P296C
Causing 3D36 and RBHVAC Trip
11/02/2020
E967190100
Replace Secondary Containment Railroad SE Airlock Door
Inflatable Seal NE-6.6-EQMS.122
09/28/2020
E967190100
Replace Secondary Containment Railroad SE Airlock Door
Inflatable Seal
09/28/2020
T363180100
License Renewal Required Replace Secondary
Containment Railroad South Airlock Door Inflatable Seal
09/29/2020
Corrective Action
Documents
20-32994
Procedure Enhancement to 24.203.02 and 24.203.03
Division 1 / 2 Core Spray Operability Test
2/16/2020
Drawings
Diagram Core Spray System CSS Reactor Building
Work Orders
53934688
Perform 24.307.16 Sec 5.1 EDG 13 Start and Load
Test-Slow Start
10/19/2020
54370155
Perform Quarterly Testing of N+1 Train Neptune Diesel
11/28/2020
54514769
Perform 24.203.03 Sec-5.2 Division 2 CSS Simulated
Automatic Actuation Test
2/16/2020
Corrective Action
Documents
CARD 19-25318
Review EP-101 Revisions Using ACR Process to Determine
10CFR50.54(q) Applicability
07/15/2019
CARD 19-27058
Changes Needed to Improve EP-101
09/19/2019
CARD 19-28389
Error Made While Revising EP-101
11/04/2019
Miscellaneous
10CFR50.54(q) Screen Number 2019-69S
10/18/2019
10CFR50.54(q) Screen Number 2019-71S
10/17/2019
10CFR50.54(q) Screen Number 2019-72S
10/18/2019
10CFR50.54(q) Screen Number 2019-73S
10/18/2019
10CFR50.54(q) Screen Number 2019-74S
10/18/2019
10CFR50.54(q) Screen Number 2019-75S
10/18/2019
10CFR50.54(q) Screen Number 2019-76S
10/18/2019
10CFR50.54(q) Screen Number 2019-82S
10/18/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
10CFR50.54(q) Screen Number 2019-87S
10/23/2019
10CFR50.54(q) Evaluation Number 2019-11E
10/18/2019
10CFR50.54(q) Screen Number 2019-88S
10/23/2019
10CFR50.54(q) Screen Number 2019-89S
10/23/2019
10CFR50.54(q) Screen Number 2019-90S
10/23/2019
10CFR50.54(q) Screen Number 2019-91S
11/01/2019
10CFR50.54(q) Evaluation Number 2019-15E
10/23/2019
Procedures
Classification of Emergencies
2C
Classification of Emergencies
Classification of Emergencies
43A
10CFR50.54(q) Screens and Evaluation
LP-ER-874-0001
CFR 50.54Q Compliance Reviews Training Lesson Plan
Fermi 2 Radiological Emergency Response Preparedness
Plan
Fermi 2
Radiological
Emergency
Response
Preparedness
Plan;
Revision 48
Fermi 2 Radiological Emergency Response Preparedness
Plan
Procedures
Classification of Emergencies
43A
Calibration
Records
Radeco Model AVS-28A Calibration Form for Serial Number
6980
01/03/2020
Radeco Model AVS-28A Calibration Form for Serial Number
7570
01/03/2020
Radeco Model AVS-28A Calibration Form for Serial Number
7571
01/03/2020
Corrective Action
Documents
Resulting from
Inspection
20-31431
NRC Identified - Vegetation Sampling in ODCM Not
Consistent with Annual Report and Surveillances
10/20/2020
Miscellaneous
Offsite Dose Calculation Manual
Offsite Dose Calculation Manual
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Annual Radioactive Effluent Release Report and
Radiological Environmental Operating Report
04/29/2020
Miscellaneous
NPRP-20-0044
Scaling Factor Report for Torus Debris
05/27/2020
Procedures
67.000.505
Survey and Movement of Waste Liners in the OSSF
1C
MRP15
Controlling Radioactive Material Outside the Plant
Radiologically Controlled Area
Shipping Records EF2-19-050
Resin Characterization and Shipping Package
08/28/2019
EF2-20-040
Torus Paint Chips Characterization and Shipment
04/21/2020
EF2-20-117
Resin Characterization and Shipping Package
09/30/2020
71151
Miscellaneous
Alert and Notification System Reliability Performance
Indicator Records
07/01/2019 -
09/30/2020
Emergency Response Organization Drill Participation
Performance Indicator Records
07/01/2019 -
09/30/2020
Drill and Exercise Performance - Performance Indicator
Records
07/01/2019 -
09/30/2020
Corrective Action
Documents
07-23630
CDBI: UFSAR Anti-Vortex Methodology Non-Conservative
06/28/2007
18-28666
NRC Concern: Foreign Material Left in Drywell
10/23/2018
19-21822
NQA - EDG 14 Tubing Not Secured Per Design
03/08/2019
19-23328
NQA - Failure of Multiple Groups to Adequately Evaluate
the EDG 14 Clamp Issue and Associated Contributors
05/01/2019
19-23915
2019 DBAI: Methodology Error Found in MOV Torque
Calculation
05/21/2019
19-23915
2019 DBAI: Methodology Error Found in MV Torque
Calculation
05/21/2019
20-20867
Received 10D21 Division II EDG 14 Lube Oil Tank D Level
High/Low in MCR
01/24/2020
20-20876
Clarification of Design Basis Document R40-00 Needed
Regarding EDG Lube Oil Requirements
01/25/2020
20-21195
OCC Effectiveness Challenged During EDG 13 SSO
2/03/2020
20-21597
2/12/2020
20-27717
07/07/2020
20-28726
Emerging Trend in CAP Performance Gaps
07/28/2020
20-28753
Results of Drywell Closeout Walkdown
07/28/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
20-29742
Request a Revision to Planners Template: FO18
08/28/2020
20-29776
Revision to the RFO Plant Restoration Checklist
08/31/2020
20-31928
EDG Lube Oil Tank Low Level Alarm Less than Required
for 7-Day Run Time
11/03/2020
20-32446
NQA Audit 02-0112 Finding - Identified Gap Between Fermi
Corrective Action Program Performance and Standards
11/24/2020
20-32817
ODMI 20-007 has Incorrect LCO Completion Time
2/10/2020
Corrective Action
Documents
Resulting from
Inspection
20-31385
NRC Identified: CARD 20-28850 Closed Without Issue
Resolution
10/19/2020
20-32182
NRC Identified-Meeting Effectiveness
11/12/2020
20-32858
NRC Identified - NRC Question on CARD 20-28753
2/11/2020
21-20263
NRC Identified - NRC Semiannual PI&R Trend Review
Observations
01/08/2021
Miscellaneous
Fermi 2 Refuel
Outage 20
Plan of the Day
07/06/2020
MOP05
Operations Conduct Manual, Chapter 5 - Control of
Equipment
MQA11-200
Quality Assurance Conduct Manual Implementing
Procedure, Condition Initiation
1B
MWC13
Outage Nuclear Safety
Operations
Department
Expectation ODE-
Operator Challenges
Procedures
24.000.02
Shiftly, Daily, and Weekly Required Surveillances
159
Corrective Action
Documents
20-31731
CRD Pump Suction Press Control Valve Issues
10/29/2020
20-31732
Received CRD Accumulator Trouble for HCU 22-15 due to
High Water Level
10/29/2020
Fire Plans
Troubleshooting
Plan
CARD 20-31731, WO 59092486, Component C1106C001B
Miscellaneous
Day Recharge
Report
CRD Accumulator Recharge Report
November
20
ARP 3D1
CRD Pump A/B Suction Pressure Low
ARP 3D13
CRD Hydraulic Temperature High
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Operator Log
10/29/2020
SOER Log Report
11/06/2020
Procedures
20.106.01
CRD Hydraulic System Failure
21