IR 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:
Report Number:
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
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.
REACTOR SAFETY
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.
- 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,
RADIATION SAFETY
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
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
10-25389
Overall Condition of Construction Sub #2 Evaluation/Repair
06/28/2010
18-29193
Received Annunciator 11D44, Transformer 1 Trouble
11/09/2018
20-23111
Lake Erie Water Levels Approaching Starting Point of
Design Basis Flood Event
03/23/2020
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
Elevation
03/30/2020
Corrective Action
Documents
03-11894
06/05/2003
Drawings
Core Spray System Functional Operating Sketch
AG
Emergency Diesel Generator System Functional Operating
Sketch
BK
Engineering
Evaluations
TE-E11-07-032
RBCCW Cooling Instead of EECW for RHR-SDC
Miscellaneous
VMR1-69.2
Triclad Vertical Induction Motor Vendor Manual
F
Procedures
ODE-20
Protected Equipment
Fire Plans
Turbine Building
Miscellaneous
MOP 11
Fire Protection
MOP11-100
Fire Protection Implementation
71111.08G Corrective Action
Documents
18-28122
Reactor Pressure Vessel Longitudinal Shell Weld 15-308D
has Reportable Ultrasonic Examination Construction Flaws
10/10/2018
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
Examination
10/31/2007
UT-F19-002
Standby Liquid Control Nozzle-to-Safe End Butt Weld
Ultrasonic Examination
10/02/2018
UT-F20-005
B31-Reactor Recirculation-Loop A Circumferential Weld
03/31/2020
VE-F19-006
RPV Longitudinal Shell Weld 15-308D Ultrasonic
Examination
10/11/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
VT-F20-017
RHR Integral Attachment Weld G.20 Visual Examination
04/02/2020
Work Orders
2189217
Repair/Replace Pipe Downstream of E1150F605A
10/25/2018
Corrective Action
Documents
15-28948
Div 2 LPCI Testable Check Valve Remained in Open
Position Following Full Stroke Test
11/13/2015
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
Packing and Follower as Found was Unsatisfactory
04/22/2020
20-27145
E1100F050A Indicates Dual in the MCR when it Should
Indicate Closed
06/22/2020
Corrective Action
Documents
18-24343
Procedure and Required M&TE Inconsistency
05/31/2018
20-23741
Low Margin Specific Gravity Values Found on Division 1
Battery
04/02/2020
20-24159
Corrected Specific Gravity Passes at Low End of
Acceptance Range
04/09/2020
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
at Minimum Value for Corrected Specific Gravity
05/07/2020
20-25786
The M&TE Used to Measure the Specific Gravity of the
Divisional Batteries is Not Appropriate
05/15/2020
20-25795
Inappropriate Procedure Revision
05/15/2020
20-26283
Leak in South Reactor Feedwater Pump Drip and Drains
Piping
05/29/2020
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
Unacceptable Indication
05/30/2020
20-26350
RF20 ASME Section XI Torus Visual Examination
Unacceptable Indication
05/30/2020
20-26415
RF20 ASME Section XI Torus Visual Examination
Indications
06/01/2020
20-26717
Roll up CARD for Torus Structural Repairs Past Operability
06/09/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
Piping Isometric Drips and Drains From Main and Reheat
Steam to Reactor Feedwater Pump Turbine
H
Piping Isometric Drips and Drains From Main and Reheat
Steam to Reactor Feedwater Pump Turbine South Turbine
Building
L
M-2985-1
Diagram Drips and Drains From Steam Lines and Main
Turbine
Q
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
23.129
Station and Control Air System
20
23.621
Main Control Room Annunciator and Sequence Recorder
3D19
Annunciator System Trouble
2.309.01
Division 1/2 Weekly 130/260VDC Battery Check
2.309.02
Division 1/2 Quarterly 130/260 VDC Battery Check
QCP-9.1.6-
NUC2019138
Torus Class MC Metal Containment Examination-RF20 Prior
to Recoat
01/29/2020
Work Orders
57509039
Leak in SRFP Drip and Drains Piping Downstream of
P9500F621
06/01/2020
57524622
Extent of Condition UT Inspection on North Train
06/11/2020
Corrective Action
Documents
19-23374
DC-4550-A-01
05/01/2019
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
Revision J Issued 9/18/17
10/31/2019
19-29099
Procedure 44.110.001 has Required Test Gauge Tolerance
Specified as +/- 4.8 PSIG. DC-4556 Volume 1 Revision H
Issued 11/3/2011 Requires an Accuracy of +/- 0.75 PSIG
11/26/2019
19-29754
DC-4573 Volume 1 Revision B Issued 8/13/2019 has
Multiple Changes with no Revision Bars, Some of Which
may Affect Current Configuration
2/19/2019
20-24104
E1100F050B Failed Pressure Isolation Valve Leakage Test
04/09/2020
20-24715
Pole Actuator for EDG 14 Breaker Aux Switches in ED2,
ED3, ED4 and ED5 Damaged
04/17/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
20-24896
Score Identified on B3105F031B Stem
04/21/2020
20-25056
2S/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
Compensator Housing
06/05/2020
Corrective Action
Documents
Resulting from
Inspection
20-26620
NRC Identified - Arc Strike Outboard Ring Girder 14/15
06/06/2020
20-26629
NRC Identified - Indication on Torus Shell Bay #6
06/07/2020
20-26997
Past Operability Reviews Need a Process Developed to
Drive Consistency and Accuracy
06/18/2020
Procedures
24.204.05
Div 1 and Div 2 RHR Valve Position Indication Verification
Test
44.030.156
ECCS - HPCI Torus Level Calibration
Corrective Action
Documents
20-24055
Torus Water Activity in Bladder Bags is Higher than
Expected
04/08/2020
Engineering
Changes
19-0019
Confidential: Torus Dewatering and Water Storage
Temporary Modification to the Support the Torus Recoating
Project
Corrective Action
Documents
19-00081
RPS East MG Set 'A' Noise Coming from Outboard Flywheel
Bearing
06/29/2019
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
Functional, MG Set Gen Output Breaker Tripped
04/05/2020
20-23963
Walkdown Photos Appear to Show Tapecoat Stopping Just
Short of Penetration Seal at MK151
04/06/2020
Drawings
I-2151-01
Reactor Protection System Motor-Generator Set A
AI
I-2155-01
Reactor Protection System Power Distribution Notes and
References
T
Engineering
Evaluations
ACMP 19-014
07/03/2019
Miscellaneous
Cycle 21 Master Core Loading Pattern
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Design Equivalent
Change Package
266
Contingency Pipe Replacement for RHRSW Penetration
Inspection for MK 1-4
Procedures
24.106.02
Control Rod Drive Coupling Integrity Verification
27.106.03
Control Rod Drive Insert and Withdrawal Stall Flow
Measurement
27.106.05
Control Rod Drive Timing and Adjustment
35.307.008
Emergency Diesel Generator - Engine General Maintenance
35.316.001
20 VAC Reactor Protection MG Set
35.317.003
RPS MG Set General Maintenance
Work Orders
2177931
Perform Electrical-Mechanical Checks and Lubrication of
03/30/2020
2180058
Replace RPS MG Set Voltage Reg Module and Voltage
Control Rheostat
03/30/2020
2180190
Perform 42.610.02 Div 1, Normal Feed, EPAs A and C,
Cal/Functional
04/06/2020
235174
RHR Return Piping Seals not Designed as Water Barriers
10/26/2018
55667627
Contingency - DECP 70266 - Replace Div 1 RHRSW Piping
at Penetration MK-104
09/06/2019
57410471
05/18/2020
Corrective Action
Documents
20-24463
Recirc Loop B Jet Pump Plugs not Holding
04/14/2020
Corrective Action
Documents
Resulting from
Inspection
20-23940
NRC Resident Observation and Feedback; Lifting and
Rigging at RHR Complex
04/06/2020
20-25570
NRC Identified : Technical Specification 5.1.2 Uses
Outdated Title for Shift Manager
05/06/2020
20-25651
NRC Identified - Lack of No Mode (Defueled) Requirements
Specified in Fermi Tech Specs and MOP01
05/11/2020
Drawings
M-2083
Residual Heat Removal Division 2
CB
M-2084
Residual Heat Removal Division 1
BP
Engineering
Evaluations
TE-E-11-20-007
RF20 Decay Heat Evaluation
Miscellaneous
RF 20 Core Verification Video
06/23/2020
MOP05-200
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
MOP13
Conduct of Refueling and Core Alterations
MWC13
Outage Nuclear Safety
Procedures
20.205.01
Loss of Shutdown Cooling
35.710.016
Installation and Removal of the Jet Pump Nozzle Plugs
MWC13
Outage Nuclear Safety
ODE-20
Protected Equipment
Drawings
64721-2205-O6
RHR Relay Logic B Circuit - Part 2
M
One Line Diagram Plant 416V & 480V System Service
CD
Procedures
24.137.01
Main Steam Line Isolation Channel Functional Test
24.137.03
Main Steam Line Valve Operability Test
43.401.500
Local Leakage Rate Testing for Penetration X-7A, X-7B, X-
7C, and X-7D
38C
Work Orders
47453964
Perform 24.307.13 EDG No. 14 ECCS Start and Load
Rejection Test and LF of Bus 65F
05/16/2020
29304
Final 43.401.500 LLRT for X-7D B2103F022D & F028D
05/27/2020
Corrective Action
Documents
20-24300
LHRA Conditions Identified in the Torus Proper
04/11/2020
Miscellaneous
WI-RPO-057
Work Instruction for RP Playbook for Torus Recoat Project
(RFO-20)
Radiation
Surveys
286-R20
Torus Radiological Survey
04/11/2020
Radiation Work
Permits (RWPs)
2040
Torus Recoat Project - Overall Diving, Decontamination,
Wash Down, Water Management and Associated Work
and 02
2042
Torus Recoat Project - Grit Blasting, Painting, Demob,
Shipping and Associated Work
71151
Engineering
Evaluations
19-24737
EDG 14 Surging in Idle During Surveillance Run
Miscellaneous
RCS Leakage Data
2019
RCS Leakage Data
20
EDG MSPI and WANO Performance Indicators Table
Various
MSPI Derivation Report - Emergency AC Power System
Unavailability Index
03/2020
MSPI Derivation Report - Emergency AC Power System
03/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Unreliability Index
MSPI Derivation Report - High Pressure Injection System
Unavailability Index
03/2020
MSPI Derivation Report - High Pressure Injection System
Unreliability Index
03/2020
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
at 1025 PSIG
11/21/2019