IR 05000341/2020004

Integrated Inspection Report 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: NPF-43 Report Number: 05000341/2020004 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 Enclosure

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.

71111.01 - Adverse Weather Protection Seasonal Extreme Weather Sample (IP Section 03.01)

(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

• Circulating water system

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)

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)

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)

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)

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)

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

(5) RHR complex dampers during the week ending December 11, 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)

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 Sample)

(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) 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)

The inspectors evaluated:

(1) Emergency preparedness tabletop drill on October 8,

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 Sample)

(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) 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 Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action 20-29557 NQA-First Level Escalation-Repeat Deficiencies with 08/24/2020

Documents Seasonal Readiness Activities

20-32239 Pri 4 Cold Weather Prep Work Order Not Scheduled 11/16/2020

Engineering TM-16-0025 Install One Temp Boiler and Provide Spare Connections for 11/08/2016

Changes a Second Temp Boiler

Miscellaneous MOP01-200 Severe Weather Guidelines 3

Procedures MWC16-100 Seasonal Readiness 1

Work Orders 51732374 Perform MWC16-100 Cold Weather System Readiness 03/20/2020

Review Checklists

71111.04 Calculations DC-6356 Stress and Seismic Analysis of the Reactor/Auxiliary A

Building CTI Nuclear Fan Coil Units

Corrective Action 20-31283 Damaged Labels - RBSB NW 10/15/2020

Documents 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 11/17/2020

have Local Manual Positioners but are Not Tracked by

Valve Lineups

20-32273 NRC Concern: Missing Label on P50R413A 11/17/2020

Drawings 6M721-2084 Diagram Residual Heat Removal (RHR) Division I BQ

6M721-2084 Diagram Residual Heat Removal (RHR) Division I BQ

6M721-5729-2 EECW Division II Functional Operating Sketch BD

6M721-5734 Emergency Diesel Generator System Functional Operating BL

Sketch

M-2015 Station and Control Air CS

M-4615 Interruptible and Non-Interruptible Control Air AH

M-5706-3 RHR Service Water Make-Up Decant and Overflow AH

Systems

M-5729-2 Emergency Equipment Cooling Water Division II BD

Miscellaneous Operator Logs Operations AUTOTOUR Logs - Reactor Building 0

Procedures 23.129 Station and Control Air 121

23.205 Division 1 RHR LPCI Standby Lineup Verification, 147

8A

Inspection Type Designation Description or Title Revision or

Procedure Date

23.208 RHR Complex Service Water Systems 129

71111.05 Fire Plans FP-AB-2-9b Auxiliary Building, Division 1 Switchgear Room, Zone 9, El. 3

613'6"

FP-AB-B-4b Control Rod Drive Pump Room, Zone 4, El. 562'0" 4

FP-CWPH-1-32 Circulating Water Pumphouse Zone 32 Elevation 58'6" 6

FP-RB-B-5b Reactor Building Basement Northeast Corner Room 4

Zone 5, Elevation 562'0"

71111.06 Engineering EF2-PRA-011 Internal Flood Walkdown Summary Notebook 0

Evaluations EF2-PRA-012 Fermi 2 Nuclear Power Station PRA Internal Flood Analysis 3

Notebook

71111.07A Calculations DC-5804 Diesel Generator Service Water Design Basis F

Requirements Calculation

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

71111.11A Miscellaneous Fermi 2020 LORT Annual Operating Test Summary Results 12/15/2020

71111.11Q Miscellaneous SS-OP-904-2001 Evaluation Scenario 2

71111.12 Corrective Action 17-25639 Management Review Committee (MRC) Cognitive Trend - 06/27/2017

Documents SRVs

18-20350 North Reactor Feed Pump Turbine Lube Oil Level High 01/16/2018

18-20351 N RFPT Turning Gear Engage Solenoid Valve (N21F111A) 04/30/2018

is Blowing By

18-23923 Received 5D28 South RFP/RFPT Shaft Trouble While 05/17/2018

Taking the N RFP Out of Service

19-20000 Unexpected Alarm During Startup of NRFPT 01/01/2019

19-20309 SRV 'A' (B2104F013A) Tail Pipe Temperature Elevated to 01/14/2019

~205F

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 03/06/2019

SRV 'A' due to Elevated Tailpipe Temperatures per CARD

19-20309

19-23939 2019 DBAI: MRFF Action Needed for Previously Closed 05/22/2019

CARD 17-23452

19-24545 Oil Surrounding Mechanical Seal on RRMG LO 06/17/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

B3103C001D

19-28069 Excessive Carbon on Brushes and Intake 10/23/2019

20-00023 Bushing Broken on N2100-F006B SRFPT OTBD Seal 03/23/2020

Water TCV Outlet Isolation Valve

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 02/12/2020

20-21602 Division 2 Control Air Compressor Failed PMT 02/13/2020

20-21659 Control Air Compressor PMT 02/14/2020

20-21688 Online Work Orders for Vendor Inspection of Recirc MG Set 02/14/2020

Brushes and Potential Stoning

20-21708 As-Found Condition of Division II NIAS Dryer 02/16/2020

20-21840 Division 2 Control Air Compressor Will Not Load 02/11/2020

20-21936 X4103F128 Excessive Scoring on Hydra Motor Shaft 02/20/2020

20-23975 Received 3D19 Annunciator System Trouble 12/16/2020

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 05/17/2020

Lube Oil Pump (B103C001A)

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 06/08/2020

Add and Removal of Oil

20-26692 P603 VAS Alarm Check Malfunction and System Battery 06/08/2020

Low Voltage Warning

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 06/29/2020

IPCS Erroneous

20-28723 UNSAT SRV Inspection 07/28/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

20-29013 SRV 'A' Tailpipe Temperature Elevated Following RF-20 08/06/2020

Startup

20-29165 SRV 'M' Tailpipe Temperature Elevated Following RF-20 08/10/2020

Startup

20-30180 Abnormal Speed Changes on South RFPT 09/13/2020

20-30351 Learnings from Industry Responses for 20-30180, SRFPT 09/17/2020

Speed Anomaly

20-30443 Abnormal Speed Differential Between North and South 09/21/2020

RFPTs

20-30554 Three SRVs Removed in RF-20 Found Outside of 09/24/2020

As-Found Set-Point Tolerance

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 12/08/2020

Engineering Monthly Maintenance Rule Evaluation Report - Safety Relief 10/09/2020

Evaluations Valve - September 2020

Miscellaneous RHR Complex Ventilation (X4103) System Performance 09/20/2020

Monitoring Plan

P5002 (NIAS) System Monitoring Plan 03/15/2019

ACMP 20-007 SRV 'A' & 'M' Weeping 1

MMR 02 Maintenance Rule Program Description 6A

MMR 10 Maintenance Rule, Monitoring 18A

MMR APP E Maintenance Rule Conduct Manual, Appendix E, 27

Maintenance Rule SSC Specific Functions

MMR Appendix B Maintenance Rule Conduct Manual, Terms and Definitions 7

MMR Appendix D Maintenance Rule Conduct Manual, Guidelines for 20

Determining Functional Failures and Maintenance

Preventable Function Failures

MMR Appendix E Maintenance Rule Conduct Manual, Maintenance Rule SSC 27

Specific Functions

MMR Appendix F Maintenance Rule Conduct Manual, Maintenance Rule 26

Performance Criteria

Monthly M-Rule Tracking Group: N2100 July -

Evaluation Report September,

Inspection Type Designation Description or Title Revision or

Procedure Date

20

Plant Health Reactor Feedwater (System N2100) 2019, Quarter

Report 1 and 2

Plant Health Condensate and Heater Feed Pumps (System N2000 and 2019, Quarter

Report N2003) 3

Plant Health Reactor Feedwater (System N2100) 2019, Quarter

Report 4

Plant Health Reactor Feedwater (System N2100) 2020, Quarter

Report 1, 2, and 3

VMR1-46 Target Rock Model 7567F Safety Relief Valves Vendor J

Manual

Procedures 23.420 RHR Complex Heating and Ventilation 41

23.621 Main Control Room Annunciator and Sequence Recorder 89

24.129.04 Control Air Valve Operability/Position Verification/Isolation 52

Integrity Test

49.419.002 RHR Damper Blocking 7

VAS USER Visual Annunciator System (VAS) User Manual 0

Work Orders 54506175 North Recirc MG Set Slip Ring Measurement 04/09/2020

54506203 South Recirc MG Set Slip Ring Measurement 04/08/2020

71111.13 Corrective Action 15-21424 Number 2 HPSV went Closed and Then Open to 22 Percent 02/21/2015

Documents Multiple Times

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 12/02/2020

Identification of Risk

20-33180 4D91 Electric Governor Trouble Number 1 HP Stop Valve 12/23/2020

CC2 HW

Corrective Action 20-33113 Update ARP Action for Ratchet Trouble 12/21/2020

Documents

Resulting from

Inspection

Miscellaneous EF2-PRA-005.33 Combustion Turbine Generators (CTGs) 1

MMR APP H Maintenance Rule Conduct Manual, Appendix H - On-Line 15

Inspection Type Designation Description or Title Revision or

Procedure Date

Core Damage Risk Management Guidelines

Procedures 11D50 CTG 11 Unit 1 Trouble Alarm Response Procedure 15

ARP 4D91 Electric Governor Trouble 19

MMR12 Equipment Out of Service Risk Management 20A

MOP05-100 Protected Equipment 2C

MWC15 Elevated Risk Management 20

71111.15 Corrective Action 20-31904 MTU Failed During 44.020.234 11/03/2020

Documents 20-33238 EDG 11 Crankcase Oil Exhibits Increased Fuel Oil in the 11/29/2020

Crankcase Oil

Procedures 44.020.234 NSSSS-RCIC Steam Line Flow, Trip System B 41

Calibration/Functional

Work Orders 54136747 Perform 44.020.234 NS4 RCIC Steam Line Flow, Trip 11/03/2020

System B, Calibration/Functional

71111.18 Corrective Action 19-23227 Recommend Review of Site Response to Open 04/26/2019

Documents CARD 07-23630

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 0

M-5721-1 EDP-80127-006 0

M-Y-2000 EDP-80127 A

Engineering 80127 ECCS Pump CST Vortex Suppression Device B

Changes DEC 70303 UPS A/B DC Circuit Fuses and Cables A

DEC 70304 UPS B Parallel Operation Software Change 0

EDP 70042 UPS A and B Replacement C

Miscellaneous Risk Management CST Vortex Suppression 10/19/2020

Plan

71111.19 Corrective Action 20-30561 Received 3D6, Division 1/2 Reactor Building Vent Exhaust 09/24/2020

Documents Rad Monitor Upscale Trip, RBHVAC Trip, and D1 SGTS

Inspection Type Designation Description or Title Revision or

Procedure Date

20-30756 While Replacing Seals on RR Car Interlock Door, 4 Bolts 09/30/2020

Failed While Removing Bolts

20-30824 East and West Airlock Door Seal Long Term 10/01/2020

Recommendations

20-32018 RCIC Turbine Exhaust Rupture Disc Leak 11/06/2020

20-32205 NRC Identified: IST Program Testing Methodology for 11/13/2020

E5100F011

Drawings 6I721-2611 Reactor Building Main Control Room A/C Mode Selection AA

Division 1

6I721-2611-10 Reactor Building Secondary Containment Isolation Signals T

Division 1

6M721-2034 Core Spray System CSS Reactor Building AS

6M721-2035 High Pressure Coolant Injection System Reactor Building BP

6M721-2044 Reactor Core Isolation Cooling System BE

6M721-2045 Reactor Core Isolation Cooling System Barometric AT

Condenser

Miscellaneous 22A1354AR Reactor Core Isolation Cooling System 13

Clearance: Jumper Out High High Trip of Division 1 Rad Monitor 11/13/2020

D1100-000138

ERE 54575 Evaluate Suitability of Replacement Garlock 3400 Sheet 0

Gasket

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 87

44.030.073 ECCS - Reactor Recirculation Pump B DP, Division 1, 36

Channel B Calibration/Functional

46.206.001 RCIC Turbine Governor Control System Calibration 45A

Work Orders 24231076 Replace MTU B31N614A - Tin Whisker Susceptible 11/30/2020

Rosemont 710DY MTU

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 11/17/2020

Control Cabinet

Inspection Type Designation Description or Title Revision or

Procedure Date

53421010 Calibrate Pressure Switch RCIC Pump Suction Low 11/03/2020

Pressure Trip

54136663 Perform 24.206.01 RCIC System Pump Operability and 11/05/2020

Valve Test at 1000 PSIG

268801 Replace Division 2 S Control Air Compressor Unloading 11/17/2020

Cylinder Solenoid Valve

58734795 Troubleshoot/Replace Relay T41M80 in H21P296C 11/02/2020

Causing 3D36 and RBHVAC Trip

E967190100 Replace Secondary Containment Railroad SE Airlock Door 09/28/2020

Inflatable Seal NE-6.6-EQMS.122

E967190100 Replace Secondary Containment Railroad SE Airlock Door 09/28/2020

Inflatable Seal

T363180100 License Renewal Required Replace Secondary 09/29/2020

Containment Railroad South Airlock Door Inflatable Seal

71111.22 Corrective Action 20-32994 Procedure Enhancement to 24.203.02 and 24.203.03 12/16/2020

Documents Division 1 / 2 Core Spray Operability Test

Drawings 6M721-2034 Diagram Core Spray System CSS Reactor Building AS

Work Orders 53934688 Perform 24.307.16 Sec 5.1 EDG 13 Start and Load 10/19/2020

Test-Slow Start

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 12/16/2020

Automatic Actuation Test

71114.04 Corrective Action CARD 19-25318 Review EP-101 Revisions Using ACR Process to Determine 07/15/2019

Documents 10CFR50.54(q) Applicability

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 Type Designation Description or Title Revision or

Procedure 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 EP-101 Classification of Emergencies 42C

EP-101 Classification of Emergencies 43

EP-101 Classification of Emergencies 43A

EP-590 10CFR50.54(q) Screens and Evaluation 0

LP-ER-874-0001 10 CFR 50.54Q Compliance Reviews Training Lesson Plan 0

RERP Fermi 2 Radiological Emergency Response Preparedness Fermi 2

Plan Radiological

Emergency

Response

Preparedness

Plan;

Revision 48

RERP Fermi 2 Radiological Emergency Response Preparedness 49

Plan

71114.06 Procedures EP-101 Classification of Emergencies 43A

71124.07 Calibration Radeco Model AVS-28A Calibration Form for Serial Number 01/03/2020

Records 6980

Radeco Model AVS-28A Calibration Form for Serial Number 01/03/2020

7570

Radeco Model AVS-28A Calibration Form for Serial Number 01/03/2020

7571

Corrective Action 20-31431 NRC Identified - Vegetation Sampling in ODCM Not 10/20/2020

Documents Consistent with Annual Report and Surveillances

Resulting from

Inspection

Miscellaneous Offsite Dose Calculation Manual 22

Offsite Dose Calculation Manual 23

Inspection Type Designation Description or Title Revision or

Procedure Date

NRC-20-0027 Annual Radioactive Effluent Release Report and 04/29/2020

Radiological Environmental Operating Report

71124.08 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 14

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 07/01/2019 -

Indicator Records 09/30/2020

Emergency Response Organization Drill Participation 07/01/2019 -

Performance Indicator Records 09/30/2020

Drill and Exercise Performance - Performance Indicator 07/01/2019 -

Records 09/30/2020

71152 Corrective Action 07-23630 CDBI: UFSAR Anti-Vortex Methodology Non-Conservative 06/28/2007

Documents 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 05/01/2019

the EDG 14 Clamp Issue and Associated Contributors

19-23915 2019 DBAI: Methodology Error Found in MOV Torque 05/21/2019

Calculation

19-23915 2019 DBAI: Methodology Error Found in MV Torque 05/21/2019

Calculation

20-20867 Received 10D21 Division II EDG 14 Lube Oil Tank D Level 01/24/2020

High/Low in MCR

20-20876 Clarification of Design Basis Document R40-00 Needed 01/25/2020

Regarding EDG Lube Oil Requirements

20-21195 OCC Effectiveness Challenged During EDG 13 SSO 02/03/2020

20-21597 EDG 14 LO Sump Level High 02/12/2020

20-27717 EDG 14 Oil Sump Level HOOS 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 Type Designation Description or Title Revision or

Procedure 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 11/03/2020

for 7-Day Run Time

20-32446 NQA Audit 02-0112 Finding - Identified Gap Between Fermi 11/24/2020

Corrective Action Program Performance and Standards

20-32817 ODMI 20-007 has Incorrect LCO Completion Time 12/10/2020

Corrective Action 20-31385 NRC Identified: CARD 20-28850 Closed Without Issue 10/19/2020

Documents Resolution

Resulting from 20-32182 NRC Identified- Meeting Effectiveness 11/12/2020

Inspection 20-32858 NRC Identified - NRC Question on CARD 20-28753 12/11/2020

21-20263 NRC Identified - NRC Semiannual PI&R Trend Review 01/08/2021

Observations

Miscellaneous Fermi 2 Refuel Plan of the Day 07/06/2020

Outage 20

MOP05 Operations Conduct Manual, Chapter 5 - Control of 57

Equipment

MQA11-200 Quality Assurance Conduct Manual Implementing 1B

Procedure, Condition Initiation

MWC13 Outage Nuclear Safety 22

Operations Operator Challenges 18

Department

Expectation ODE-

Procedures 24.000.02 Shiftly, Daily, and Weekly Required Surveillances 159

71153 Corrective Action 20-31731 CRD Pump Suction Press Control Valve Issues 10/29/2020

Documents 20-31732 Received CRD Accumulator Trouble for HCU 22-15 due to 10/29/2020

High Water Level

Fire Plans Troubleshooting CARD 20-31731, WO 59092486, Component C1106C001B 0

Plan

Miscellaneous 30 Day Recharge CRD Accumulator Recharge Report November

Report 2020

ARP 3D1 CRD Pump A/B Suction Pressure Low 10

ARP 3D13 CRD Hydraulic Temperature High 20

Inspection Type Designation Description or Title Revision or

Procedure Date

Operator Log 10/29/2020

SOER Log Report 11/06/2020

Procedures 20.106.01 CRD Hydraulic System Failure 21

23