IR 05000341/2020002

Integrated Inspection Report 05000341/2020002

ML20220A568
Person / Time
Site:	Fermi
Issue date:	08/07/2020
From:	Nestor Feliz-Adorno Reactor Projects Region 3 Branch 4
To:	Peter Dietrich DTE Electric Company
References
IR 2020002
Download: ML20220A568 (18)

Text

August 7, 2020

SUBJECT:

FERMI POWER PLANT, UNIT 2 - INTEGRATED INSPECTION REPORT 05000341/2020002

Dear Mr. Dietrich:

On June 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Fermi Power Plant, Unit 2. On July 21, 2020, 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.

No NRC-identified or self-revealing findings were identified during this inspection.

A licensee-identified violation which was determined to be of very low safety significance is documented in this report. We are treating this violation as a non-cited violation (NCV)

consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector at Fermi Power Plant, Unit 2. 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. Feliz 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: 05000341/2020002 Enterprise Identifier: I-2020-002-0030 Licensee: DTE Electric Company Facility: Fermi Power Plant, Unit 2 Location: Newport, MI Inspection Dates: April 1, 2020 to June 30, 2020 Inspectors: T. Briley, Senior Resident Inspector V. Myers, Senior Health Physicist R. Ng, Project Engineer A. Shaikh, Senior Reactor Inspector T. Taylor, Resident Inspector Approved By: Néstor J. Feliz 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. A licensee-identified non-cited violation is documented in report section: 71124.0

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

PLANT STATUS

Unit 2 remained shut down for a planned refueling outage during 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 (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 and during that time conducted plant status activities as described in IMC 2515, Appendix D; 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 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.

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated summer readiness for extreme weather conditions during the week ending June 20, 2020

External Flooding Sample (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensee's readiness to cope with external flooding under the following conditions:

• Elevated Lake Erie water levels during the week ending May 30, 2020

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (2 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Division 1 core spray as protected inventory control equipment during the week ending April 11, 2020

(2) Division 1 emergency diesel generators (EDGs) 11 and 12 during Division 2 EDGs 13 and 14 planned maintenance during the week ending April 18, 2020

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (2 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) Turbine building basement condenser pump bay during the week ending May 30, 2020

(2) Turbine building first floor pipe chase during the week ending May 30, 2020

71111.08G - Inservice Inspection Activities (BWR)

BWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding

Activities (IP Section 03.01)

(1) The inspectors verified the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary were appropriately monitored for degradation and repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from March 23 to April 10, 2020:

03.01.a - Nondestructive Examination and Welding Activities.

Nondestructive Examinations:

• Residual Heat Removal Integral Attachment Weld (G.20) Visual Examination (VT)

• B31-Reactor Recirculation Loop A Circumferential Weld (FW-RD-2-A9)

Ultrasonic Examination (UT)

• Control Rod Drive Housing Tube-to-Tube Weld (CRD#-X02-Y27-WZ) Liquid Penetrant Examination (PT)

Nondestructive Examinations with Indications from Previous Outage:

• Standby Liquid Control Nozzle-to-Safe End Butt Weld (5-315) Ultrasonic Examination

• Reactor Pressure Vessel Longitudinal Shell Weld (15-308D) Ultrasonic Examination Welding Activity:

• Residual Heat Removal Service Water Pump Pipe Replacement Downstream of E1150F605A

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (1 Sample)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) Division 1 and Division 2 low pressure coolant injection (LPCI) testable check valves (E1100F050A and E1100F050B) during the week ending June 20, 2020

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (6 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) Emergent work on west station air compressor following loss of station air during the week ending April 18, 2020

(2) Emergent work on visual annunciator system (VAS) following a loss of VAS during the week ending April 18, 2020

(3) Emergent work on Division 1 and Division 2 130/260 volt batteries following low specific gravity measurements during the weeks ending May 9, 2020 and May 16, 2020

(4) Emergent work on torus structural indications identified during structures monitoring and ASME [American Society of Mechanical Engineers] section XI visual examinations during the week ending June 6, 2020

(5) Emergent work on drips and drains piping from steam lines and main turbine piping following identification of a through wall leak during the week ending June 6, 2020

(6) Planned shutdown cooling system valve maintenance with shutdown cooling out of service during the week ending June 27, 2020

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Legacy issues in calculations for surveillances affected by license amendment request for 24-month fuel cycle

(2) Operability and functionality of Division 2 LPCI testable check valve (E1100F050B)stuck open, as documented in CARD 20-24104

(3) Operability and functionality of EDG 14 following identification of pole actuator cracking during planned maintenance, as documented in CARD 20-24715

(4) Operability and functionality of the reactor recirculation pump B discharge motor operated valve (B2105F031B) following identification of stem and stem nut damage, as documented in CARD 20-24896

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)

(1 Sample)

The inspectors evaluated the following temporary or permanent modifications:

(1) Draining of torus, using temporary water transfer system and storage

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 protection system motor generator set 'A' output breaker troubleshooting and component replacements following abnormal operation during the week ending April 18, 2020

(2) Division 1 residual heat removal service water (RHRSW) piping replacement following identification of piping degradation during the week ending May 9, 2020

(3) EDG 13 cylinder liner adapter gasket replacement following unsatisfactory borescope inspections during the week ending June 13, 2020

(4) Core reload alignment verification during the week ending June 27, 2020

(5) Control rod exercising following planned maintenance during the week ending June 27, 2020

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)

(1) (Partial)

The inspectors evaluated refueling outage 20 activities throughout the inspection period. The inspectors completed inspection procedure section 03.01.c.11.

Refueling outage and associated inspection activities continued during the next inspection period.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) EDG 14 emergency core cooling system start test and logic functional tests of bus 65F breakers during the week ending July 4, 2020

Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) Main steam isolation valves local leak rate testing during the week ending May 30,

71124.01 - Radiological Hazard Assessment and Exposure Controls

High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (1 Sample)

The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:

(1) Torus

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

MS06: Emergency AC Power Systems (IP Section 02.05) ===

(1) Unit 2 (April 1, 2019 - March 31, 2020)

MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)

(1) Unit 2 (April 1, 2019 - March 31, 2020)

BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)

(1) Unit 2 (April 1, 2019 - March 31, 2020)

INSPECTION RESULTS

Licensee-Identified Non-Cited Violation 71124.01 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: Technical Specification (TS) 5.7.2 states, in part, that areas accessible to individuals with radiation levels such that an individual could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, a dose equivalent > 1000 mrems but < 500 rads at one meter from sources of radioactivity shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Nuclear Shift Supervisor on duty and/or the radiation protection supervision.

Technical Specification 5.7.3 states, in part, that for individual areas accessible to individuals with radiation levels such that a major portion of the individual's body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, a dose > 1000 mrems with measurement made at 30 centimeters from the source of radioactivity, but < 500 rads at one meter from the source of radioactivity that that are located within large areas such as reactor containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be roped off and conspicuously posted, and a flashing light shall be activated as a warning device.

Contrary to the above, on April 11, 2020, the licensee failed either to provide locked doors to prevent unauthorized entry or to activate a flashing light as a warning device for an area accessible to individuals with radiation levels such that a major portion of the individuals body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose > 1000 mrems with measurement made at 30 centimeters from the source of radioactivity. Specifically, individual areas of the torus (with accumulated coating chips) had measured radiation levels up to about 2500 mrem in any one hour; however, the torus was roped off and conspicuously posted as a High Radiation Area but was not locked nor was there a flashing light as a warning device.

Significance/Severity: Green. Specifically, the inspectors determined that this finding is of very low safety significance (Green) because the performance deficiency did not involve ALARA planning or work controls, there was no overexposure or substantial potential for an overexposure, and the ability to assess dose was not compromised.

Corrective Action References: CARD 20-24300, LHRA Conditions Identified in the Torus Proper

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• On July 21, 2020, the inspectors presented the integrated inspection results to Mr. P. Dietrich, Senior VP and Chief Nuclear Officer and other members of the licensee staff.

• On April 29, 2020, the inspectors presented the radiation protection inspection results to Mr. R. LaBurn, Radiation Protection Manager and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action 10-25389 Overall Condition of Construction Sub #2 Evaluation/Repair 06/28/2010

Documents 18-29193 Received Annunciator 11D44, Transformer 1 Trouble 11/09/2018

20-23111 Lake Erie Water Levels Approaching Starting Point of 03/23/2020

Design Basis Flood Event

20-23667 Lake Level Elevation 04/01/2020

20-24215 Lake Level Above PMME Starting Elevation 04/10/2020

20-24689 CB Disconnect Rollers Showing Signs of Degradation 04/17/2020

20-26217 M-WARM20 Work will not be Completed Before 6/1/20 05/28/2020

Miscellaneous ACMP 20-0004 Adverse Condition Monitoring Plan - Lake Erie Water Level 03/30/2020

Elevation

71111.04 Corrective Action 03-11894 RFI #111 NRC SSDI EECW 06/05/2003

Documents

Drawings 6M721-5707 Core Spray System Functional Operating Sketch AG

6M721-5734 Emergency Diesel Generator System Functional Operating BK

Sketch

Engineering TE-E11-07-032 RBCCW Cooling Instead of EECW for RHR-SDC 0

Evaluations

Miscellaneous VMR1-69.2 Triclad Vertical Induction Motor Vendor Manual F

Procedures ODE-20 Protected Equipment 25

71111.05 Fire Plans FP-TB Turbine Building 10

Miscellaneous MOP 11 Fire Protection 23

MOP11-100 Fire Protection Implementation 7

71111.08G Corrective Action 18-28122 Reactor Pressure Vessel Longitudinal Shell Weld 15-308D 10/10/2018

Documents has Reportable Ultrasonic Examination Construction Flaws

NDE Reports PT-F20-004 CRDH Tube-to-Tube Weld Liquid Penetrant Examination 04/04/2020

RFO-12-10 Reactor Pressure Vessel Shell Weld 15-308D Ultrasonic 10/31/2007

Examination

UT-F19-002 Standby Liquid Control Nozzle-to-Safe End Butt Weld 10/02/2018

Ultrasonic Examination

UT-F20-005 B31-Reactor Recirculation-Loop A Circumferential Weld 03/31/2020

VE-F19-006 RPV Longitudinal Shell Weld 15-308D Ultrasonic 10/11/2018

Examination

Inspection Type Designation Description or Title Revision or

Procedure Date

VT-F20-017 RHR Integral Attachment Weld G.20 Visual Examination 04/02/2020

Work Orders 52189217 Repair/Replace Pipe Downstream of E1150F605A 10/25/2018

71111.12 Corrective Action 15-28948 Div 2 LPCI Testable Check Valve Remained in Open 11/13/2015

Documents Position Following Full Stroke Test

17-22684 E1100F050B Failed Pressure Isolation Valve Leakage Test 03/28/2017

20-24104 E1100F050B Failed Pressure Isolation Valve Leakage Test 04/09/2020

20-24790 E1100F050B Internal Damage 04/19/2020

20-25005 E1100F050B Indicator Shaft Bushing and Stuffing Box 04/22/2020

Packing and Follower as Found was Unsatisfactory

20-27145 E1100F050A Indicates Dual in the MCR when it Should 06/22/2020

Indicate Closed

71111.13 Corrective Action 18-24343 Procedure and Required M&TE Inconsistency 05/31/2018

Documents 20-23741 Low Margin Specific Gravity Values Found on Division 1 04/02/2020

Battery

20-24159 Corrected Specific Gravity Passes at Low End of 04/09/2020

Acceptance Range

20-24502 Visual Annunciator System Total System Failure 04/14/2020

20-24698 West Station Air Compressor Tripped 04/17/2020

20-25590 Division 1 Batteries Meet Acceptance Criteria One Pilot Cell 05/07/2020

at Minimum Value for Corrected Specific Gravity

20-25786 The M&TE Used to Measure the Specific Gravity of the 05/15/2020

Divisional Batteries is Not Appropriate

20-25795 Inappropriate Procedure Revision 05/15/2020

20-26283 Leak in South Reactor Feedwater Pump Drip and Drains 05/29/2020

Piping

20-26297 RF20 ASME Section XI Torus Visual Examination Indication 05/29/2020

20-26312 VAS Clock Signal Distortion Cause and Remediation 05/30/2020

20-26349 RF20 ASME Section XI Torus Visual Examination 05/30/2020

Unacceptable Indication

20-26350 RF20 ASME Section XI Torus Visual Examination 05/30/2020

Unacceptable Indication

20-26415 RF20 ASME Section XI Torus Visual Examination 06/01/2020

Indications

20-26717 Roll up CARD for Torus Structural Repairs Past Operability 06/09/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

Drawings 6WM-N30-5021-1 Piping Isometric Drips and Drains From Main and Reheat H

Steam to Reactor Feedwater Pump Turbine

6WM-N30-5022-1 Piping Isometric Drips and Drains From Main and Reheat L

Steam to Reactor Feedwater Pump Turbine South Turbine

Building

M-2985-1 Diagram Drips and Drains From Steam Lines and Main Q

Turbine

Miscellaneous Fermi 2, Plan of the Day 06/22/2020

Fermi 2, RF20 Outage Nuclear Safety Review 03/16/2020

MOP05-100 Protected Equipment 2C

Procedures 20.129.01 Loss of Station and/or Control Air 35

23.129 Station and Control Air System 120

23.621 Main Control Room Annunciator and Sequence Recorder 87

3D19 Annunciator System Trouble 20

2.309.01 Division 1/2 Weekly 130/260VDC Battery Check 39

2.309.02 Division 1/2 Quarterly 130/260 VDC Battery Check 42

QCP-9.1.6- Torus Class MC Metal Containment Examination-RF20 Prior 01/29/2020

NUC2019138 to Recoat

Work Orders 57509039 Leak in SRFP Drip and Drains Piping Downstream of 06/01/2020

P9500F621

57524622 Extent of Condition UT Inspection on North Train 06/11/2020

71111.15 Corrective Action 19-23374 DC-4550-A-01 05/01/2019

Documents 19-23497 DC-4535 Calibrating Instrument Errors 05/06/2019

19-28317 44.030.156 Tables 7 and 14 do not Match DC-4534 Volume 10/31/2019

Revision J Issued 9/18/17

19-29099 Procedure 44.110.001 has Required Test Gauge Tolerance 11/26/2019

Specified as +/- 4.8 PSIG. DC-4556 Volume 1 Revision H

Issued 11/3/2011 Requires an Accuracy of +/- 0.75 PSIG

19-29754 DC-4573 Volume 1 Revision B Issued 8/13/2019 has 12/19/2019

Multiple Changes with no Revision Bars, Some of Which

may Affect Current Configuration

20-24104 E1100F050B Failed Pressure Isolation Valve Leakage Test 04/09/2020

20-24715 Pole Actuator for EDG 14 Breaker Aux Switches in ED2, 04/17/2020

ED3, ED4 and ED5 Damaged

Inspection Type Designation Description or Title Revision or

Procedure Date

20-24896 Score Identified on B3105F031B Stem 04/21/2020

20-25056 52S/H Aux Switch Rod Head Cracks 04/23/2020

20-25071 Request WO to Schedule Inspections 04/23/2020

20-26588 B3105F031B Foreign Material Found in Actuator 06/05/2020

Compensator Housing

Corrective Action 20-26620 NRC Identified - Arc Strike Outboard Ring Girder 14/15 06/06/2020

Documents 20-26629 NRC Identified - Indication on Torus Shell Bay #6 06/07/2020

Resulting from 20-26997 Past Operability Reviews Need a Process Developed to 06/18/2020

Inspection Drive Consistency and Accuracy

Procedures 24.204.05 Div 1 and Div 2 RHR Valve Position Indication Verification 53

Test

44.030.156 ECCS - HPCI Torus Level Calibration 49

71111.18 Corrective Action 20-24055 Torus Water Activity in Bladder Bags is Higher than 04/08/2020

Documents Expected

Engineering 19-0019 Confidential: Torus Dewatering and Water Storage 0

Changes Temporary Modification to the Support the Torus Recoating

Project

71111.19 Corrective Action 19-00081 RPS East MG Set 'A' Noise Coming from Outboard Flywheel 06/29/2019

Documents Bearing

20-23266 Corrosion of RHRSW Pipe at MDCT Penetration MK-151 03/26/2020

20-23410 Document Trend for RHRSW Internal Pipe Condition 03/28/2020

20-23625 RPS Output Breaker Failed Acceptance Criteria 04/01/2020

20-23627 RPS MG Set 'A' Motor Internals Dirty 04/01/2020

20-23906 While Performing 42.610.02 EPA Channel acl and 04/05/2020

Functional, MG Set Gen Output Breaker Tripped

20-23963 Walkdown Photos Appear to Show Tapecoat Stopping Just 04/06/2020

Short of Penetration Seal at MK151

Drawings I-2151-01 Reactor Protection System Motor-Generator Set A AI

I-2155-01 Reactor Protection System Power Distribution Notes and T

References

Engineering ACMP 19-014 RPS A MG Set 07/03/2019

Evaluations

Miscellaneous Cycle 21 Master Core Loading Pattern 1

Inspection Type Designation Description or Title Revision or

Procedure Date

Miscellaneous Design Equivalent Contingency Pipe Replacement for RHRSW Penetration 0

Change Package Inspection for MK 1-4

266

Procedures 24.106.02 Control Rod Drive Coupling Integrity Verification 34

27.106.03 Control Rod Drive Insert and Withdrawal Stall Flow 18

Measurement

27.106.05 Control Rod Drive Timing and Adjustment 23

35.307.008 Emergency Diesel Generator - Engine General Maintenance 46

35.316.001 120 VAC Reactor Protection MG Set 34

35.317.003 RPS MG Set General Maintenance 29

Work Orders 52177931 Perform Electrical-Mechanical Checks and Lubrication of 03/30/2020

RPS MG Set A

2180058 Replace RPS MG Set Voltage Reg Module and Voltage 03/30/2020

Control Rheostat

2180190 Perform 42.610.02 Div 1, Normal Feed, EPAs A and C, 04/06/2020

Cal/Functional

235174 RHR Return Piping Seals not Designed as Water Barriers 10/26/2018

55667627 Contingency - DECP 70266 - Replace Div 1 RHRSW Piping 09/06/2019

at Penetration MK-104

57410471 Replace EDG Adapter Gaskets 05/18/2020

71111.20 Corrective Action 20-24463 Recirc Loop B Jet Pump Plugs not Holding 04/14/2020

Documents

Corrective Action 20-23940 NRC Resident Observation and Feedback; Lifting and 04/06/2020

Documents Rigging at RHR Complex

Resulting from 20-25570 NRC Identified : Technical Specification 5.1.2 Uses 05/06/2020

Inspection Outdated Title for Shift Manager

20-25651 NRC Identified - Lack of No Mode (Defueled) Requirements 05/11/2020

Specified in Fermi Tech Specs and MOP01

Drawings M-2083 Residual Heat Removal Division 2 CB

M-2084 Residual Heat Removal Division 1 BP

Engineering TE-E-11-20-007 RF20 Decay Heat Evaluation 0

Evaluations

Miscellaneous RF 20 Core Verification Video 06/23/2020

MOP05-200 RPV Water Inventory Control 1

Inspection Type Designation Description or Title Revision or

Procedure Date

MOP13 Conduct of Refueling and Core Alterations 19

MWC13 Outage Nuclear Safety 20

Procedures 20.205.01 Loss of Shutdown Cooling 22

35.710.016 Installation and Removal of the Jet Pump Nozzle Plugs 24

MWC13 Outage Nuclear Safety 20

ODE-20 Protected Equipment 25

71111.22 Drawings 64721-2205-O6 RHR Relay Logic B Circuit - Part 2 M

6SD721-2500-01 One Line Diagram Plant 416V & 480V System Service CD

Procedures 24.137.01 Main Steam Line Isolation Channel Functional Test 47

24.137.03 Main Steam Line Valve Operability Test 45

43.401.500 Local Leakage Rate Testing for Penetration X-7A, X-7B, X- 38C

7C, and X-7D

Work Orders 47453964 Perform 24.307.13 EDG No. 14 ECCS Start and Load 05/16/2020

Rejection Test and LF of Bus 65F

29304 Final 43.401.500 LLRT for X-7D B2103F022D & F028D 05/27/2020

71124.01 Corrective Action 20-24300 LHRA Conditions Identified in the Torus Proper 04/11/2020

Documents

Miscellaneous WI-RPO-057 Work Instruction for RP Playbook for Torus Recoat Project 00

(RFO-20)

Radiation 02286-R20 Torus Radiological Survey 04/11/2020

Surveys

Radiation Work 202040 Torus Recoat Project - Overall Diving, Decontamination, 00 and 02

Permits (RWPs) Wash Down, Water Management and Associated Work

2042 Torus Recoat Project - Grit Blasting, Painting, Demob, 00

Shipping and Associated Work

71151 Engineering 19-24737 EDG 14 Surging in Idle During Surveillance Run 1

Evaluations

Miscellaneous RCS Leakage Data 2019

RCS Leakage Data 2020

EDG MSPI and WANO Performance Indicators Table Various

MSPI Derivation Report - Emergency AC Power System 03/2020

Unavailability Index

MSPI Derivation Report - Emergency AC Power System 03/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

Unreliability Index

MSPI Derivation Report - High Pressure Injection System 03/2020

Unavailability Index

MSPI Derivation Report - High Pressure Injection System 03/2020

Unreliability Index

HPCI Performance Indicators Table Various

Operators' Narrative Log Various

Procedures 24.000.02 Eight Hour - Mode 1, 2, 3 -- Control Room Various

Work Orders 51059475 Perform 24.202.01 HPCI Pump / Flow Test & Valve Stroke 11/21/2019

at 1025 PSIG

15