IR 05000341/2019004

Integrated Inspection Report 05000341/2019004

ML20038A340
Person / Time
Site:	Fermi
Issue date:	02/07/2020
From:	Richard Skokowski Reactor Projects Region 3 Branch 4
To:	Peter Dietrich DTE Energy
References
IR 2019004
Download: ML20038A340 (42)

Text

ary 7, 2020

SUBJECT:

FERMI POWER PLANT, UNIT 2 - INTEGRATED INSPECTION REPORT 05000341/2019004

Dear Mr. Dietrich:

On December 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Fermi Power Plant, Unit 2. On January 7, 2020, the NRC inspectors discussed the results of this inspection with you and members of your staff. The results of this inspection are documented in the enclosed report.

Two findings of very low safety significance (Green) are documented in this report. One of these findings involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.

A licensee-identified violation which was determined to be Severity Level IV 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.

If you disagree with a cross-cutting aspect assignment or a finding not associated with a regulatory requirement in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; 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 by Michael Kunowski Acting for/

Richard A. Skokowski, 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: 05000341/2019004 Enterprise Identifier: I-2019-004-0057 Licensee: DTE Electric Company Facility: Fermi Power Plant, Unit 2 Location: Newport, MI Inspection Dates: September 30, 2019 to December 31, 2019 Inspectors: R. Baker, Senior Operations Engineer T. Briley, Senior Resident Inspector G. Hansen, Sr. Emergency Preparedness Inspector D. Mills, Senior Resident Inspector V. Myers, Senior Health Physicist V. Petrella, Resident Inspector E. Sanchez Santiago, Senior Reactor Inspector T. Taylor, Resident Inspector C. Zoia, Senior Operations Engineer Approved By: Richard A. Skokowski, 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: 71111.11B.

List of Findings and Violations Failure to Have Appropriate Instructions for Determining the Average Sediment Depth in the Residual Heat Removal Complex Reservoir Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.13] - 71111.07T Systems NCV 05000341/2019004-01 Consistent Open/Closed Process A finding of very low safety significance (Green) and an associated Non-Cited Violation of Title 10 of the Code of Federal Regulation (CFR), Part 50, Appendix B, Criterion V,

Instructions, Procedures, and Drawings, was identified by the inspectors due to the licensees failure to have appropriate instructions for determining the average sediment depth in the Residual Heat Removal Complex Reservoir.

Inadequate Relay Replacement Frequency Causes Momentary Loss of Secondary Containment Vacuum Cornerstone Significance Cross-Cutting Report Aspect Section Barrier Integrity Green None (NPP) 71111.12 FIN 05000341/2019004-02 Open/Closed A self-revealed Green finding was identified when the licensee failed to follow site procedure MES51, "Preventative Maintenance Program." Specifically, the licensee failed to replace a relay within the vendor recommended interval due to an inappropriate application of grace period. As a result, the relay failed and prevented a Reactor Building Heating and Ventilation System (RBHVAC) damper from closing during normal operation of the system, which caused pressure to increase in secondary containment beyond Technical Specification (TS)operability limits.

Additional Tracking Items Type Issue Number Title Report Section Status LER 05000341/2019-004-00 LER 2019-004-00 for Fermi, 71153 Closed Unit 2, Division 2 Mechanical Draft Cooling Tower Fan "D" Tripped when Placed in High Speed due to a Blown Fuse LER 05000341/2019-005-00 LER 2019-005-00 for Fermi, 71153 Closed Unit 2, Secondary Containment Pressure Exceeded Technical Specification due to Reactor Building HVAC Damper Malfunction LER 05000341/2019-003-00 LER 2019-003-00 for Fermi, 71153 Closed Unit 2, Secondary Containment Declared Inoperable due to Opening Both Airlock Doors

PLANT STATUS

Unit 2 operated at or near rated thermal power during the entire inspection period with the exception of power changes to perform planned control rod pattern adjustments and/or required Technical Specification surveillance testing.

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 performed plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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.

71111.01 - Adverse Weather Protection Seasonal Extreme Weather Sample (IP Section 03.02)

(1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold weather preparations for the following systems:

• Condensate Storage and Transfer System

• Ultimate Heat Sink

71111.04Q - Equipment Alignment Partial Walkdown Sample (IP Section 03.01)

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

(1) Reactor Core Isolation Cooling (RCIC) while Division 2 Switchgear Room Cooler was out of service for planned maintenance during the week ending November 30, 2019

(2) Division 2 Emergency Equipment Service Water (EESW) while Division 1 EESW was out of service for planned maintenance during the week ending December 7, 2019

71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Reactor Building Second Floor, North and Division 1 Emergency Equipment Cooling Water (EECW) area during the week ending October 5, 2019

(2) Residual Heat Removal (RHR) Complex First Floor, Emergency Diesel Generator (EDG) 14 room during the week ending October 12, 2019

(3) Reactor Building First Floor, South Control Rod Drive and Railroad Bay area during the week ending December 31, 2019

71111.06 - Flood Protection Measures Inspection Activities - Internal Flooding (IP Section 02.02a.)

The inspectors evaluated internal flooding mitigation protections in the:

(1) Auxiliary Building Third Floor, Direct Current Motor Control Center Area

71111.07A - Heat Sink Performance Annual Review (IP Section 02.01)

The inspectors evaluated readiness and performance of:

(1) Division 1 and 2 EECW Heat Exchangers

71111.07T - Heat Sink Performance Triennial Review (IP Section 02.02)

The inspectors evaluated heat exchanger/sink performance on the following:

(1) RHR North Heat Exchanger Division 1 (E1101B001A)

(2) EDG 13 Jacket Coolant Heat Exchanger (R3001B018)

(3) EDG 13 Air Coolant Heat Exchanger (R3001B026)

(4) Section 02.02d, Specifically Sections 02.02d3 and 02.02d5 were completed

71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance Requalification Examination Results (IP Section 03.03)

(1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered from September 23, 2019 through October 25, 2019.

71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Requalification Program (IP Section 03.04)

(1) Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on October 3, 2019.

Annual Requalification Operating Tests The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.

Administration of an Annual Requalification Operating Test The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.

Requalification Examination Security The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.

Remedial Training and Re-examinations The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.

Operator License Conditions The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.

Control Room Simulator The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.

Problem Identification and Resolution The inspectors evaluated the licensees ability to identify and resolve problems associated with licensed operator performance.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)

(1) The inspectors observed and evaluated licensed operator performance in the Control Room during an abnormal operating procedure entry for an unplanned non-functionality of steam jet air ejector 3 on October 23, 2019, and secondary containment pressure control following a reactor building heating ventilation and air conditioning system damper failure on December 19, 2019 Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated a licensed operator training lesson on emergency action levels (EALs) during the week ending October 19, 2019

71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness Inspection (IP Section 02.01)

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) Reactor Building Heating Ventilation and Air Conditioning (RBHVAC) system dampers during the week ending November 30, 2019

(2) Reference Leg Backfill System during the week ending December 21, 2019

Quality Control (IP Section 02.02) (1 Sample)

The inspectors evaluated maintenance and quality control activities associated with the following equipment performance activities:

(1) Control of grease used for motor operated valve preventative maintenance during the week ending December 28, 2019

71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) Emergent maintenance on EDG 14 starting air system, emergent maintenance on Division 2 EECW temperature control valve, and planned maintenance on Reactor Water Cleanup system during the week ending October 5, 2019

(2) Emergent maintenance on the outer railroad door secondary containment barrier during the week ending October 12, 2019

(3) Planned heavy lift of a Main Generator Stator during the week ending October 19, 2019

(4) Planned Division 1 Battery Charger Room Cooler maintenance during the week ending November 16, 2019

(5) Emergent maintenance on the Electric Fire Pump during the week ending November 23, 2019

(6) Emergent maintenance on the RBHVAC system and planned maintenance on the Non-Interruptible Instrument Air System during the week ending November 30, 2019

71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 02.02)

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Operability and functionality of Division 1 Control Complex Heating Ventilation and Air Conditioning (CCHVAC) system following identification of abnormal 480 volt supply breaker thermography readings, as documented in Condition Assessment Resolution Document (CARD) 19-27694

(2) Technical Specification 3.3.5.1, Emergency Core Cooling System (ECCS)

Instrumentation, and Technical Specification 3.3.2.2, Feedwater and Main Turbine High Water Level Trip Instrumentation, implementation following wrong panel electrical contact checks during ECCS Reactor Vessel Water Level Automatic Depressurization System (ADS) Level 3 and Feedwater / Main Turbine Level 8, Division 1, Channel A Functional Test, as documented in CARD 19-28721

(3) Operability and functionality of EDG 14 following surging at idle speed and identification of a broken starting air system pipe, as documented in CARDs 19-27462 and 19-24737

(4) Operability and functionality of the RCIC system following failure of the RCIC Barometric Condenser Pump, as documented in CARD 19-28481

(5) Operability and functionality of Division 2 EESW and EECW systems following failure of the Division 2 EECW temperature control valve to fully open during a simulated loss of power surveillance test, as documented in CARD 19-27229

(6) Operability and functionality of the Division 2 EESW and EECW systems following identification of a failed fuse in Mechanical Draft Cooling Tower Fan D high speed circuitry, as documented in CARD 19-25713

(7) Operability and functionality of the Division 1 Core Spray system following identification of an out of tolerance pipe support spring can assembly, as documented in CARD 19-27115

(8) Operability and functionality of the fire suppression system following identification of Alternate Diesel Fire Pump battery low electrolyte level while the Electric Fire Pump and permanently installed Diesel Fire Pumps were out of service for corrective maintenance, as documented in CARD 19-28912

71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)

The inspectors evaluated the following temporary or permanent modifications:

(1) Lifting and rigging equipment changes to the new fuel receipt inspection stand and fuel uprighting stand to support a change in reactor fuel design (Permanent Modification)

71111.19 - Post-Maintenance Testing Post-Maintenance Test Sample (IP Section 03.01)

The inspectors evaluated the following post-maintenance tests:

(1) Reactor Water Clean Up (RWCU) flow transmitter calibration during the week ending October 5, 2019

(2) EDG 14 following starting air pipe repair during the week ending October 5, 2019

(3) Secondary Containment following repair of reactor building railroad doors during the week ending October 12, 2019

(4) Standby Feedwater following relief valve and discharge valve breaker preventative maintenance during the week ending October 12, 2019

(5) Division 2 EECW temperature control valve following corrective maintenance during the week ending October 19, 2019

(6) Division 2 EECW equipment sump heat exchanger check valve following planned replacement during the week ending October 26, 2019

(7) Gland Seal Exhaust Trip Logic after Modification Installation in refueling outage 19 during the week ending November 23, 2019

(8) Electric Fire Pump following corrective pump replacement during the week ending November 23, 2019

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Surveillance Tests (other) (IP Section 03.01)

(1) EDG 14 slow start surveillance test on December 23, 2019

(2) Control Room technical specification shiftly channel checks on December 30, 2019

FLEX Testing (IP Section 03.02) (1 Sample)

(1) N and N+1 Flex Diesel Generator load testing on October 12, 2019 and November 7, 2019

71114.02 - Alert and Notification System Testing Inspection Review (IP Section 02.01-02.04)

(1) The inspectors evaluated the following maintenance and testing of the alert and notification system:

• Annual siren inspection and maintenance records for the period from September 2017 to September 2019

• Monthly alert notification system (siren) tests for the period from September 2017 to September 2019

71114.03 - Emergency Response Organization Staffing and Augmentation System Inspection Review (IP Section 02.01-02.02)

(1) The inspectors evaluated the readiness of the Emergency Preparedness Organization.

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 November 21, 2019. This evaluation does not constitute NRC approval.

71114.05 - Maintenance of Emergency Preparedness Inspection Review (IP Section 02.01 - 02.11)

(1) The inspectors evaluated the maintenance of the emergency preparedness program.

71114.06 - Drill Evaluation Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01)

(1) Observation of emergency action level training evolution on October 18, 2019

(2) Emergency Preparedness Drill conducted on October 31,

71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment (IP Section 02.01)

The inspectors evaluated radiological hazards assessments and controls.

(1) The inspectors reviewed the following:

Radiological Surveys

• RWCU pump room

• Steam tunnel

• RWCU phase separator room

• RCIC room Risk Significant Radiological Work Activities

• Investigation and isolation of steam leak under high pressure turbine

• RWCU pump seal repair/replacement

• Limit switch work on reactor water clean up phase separator tank

• RCIC surveillance Air Sample Survey Records

• 00252-A19, Turbine deck to steam tunnel

• 00305-A19, RWCU pump room

• 00116-A19, RCIC pump room

Instructions to Workers (IP Section 02.02) (1 Sample)

The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas.

(1) The inspectors reviewed the following:

Radiation Work Packages

• 191020, Emergent Issues Tasks

• 191050, RWCU Pump Seal Repair/Replacement

• 191051, RWCU Phase Separator Room Entry and Component Repair

• 191027, E41 and E51 System Maintenance, Inspections, Surveillance and Test Runs Electronic Alarming Dosimeter Alarms

• CARD 19-21358

• CARD 19-21994

• CARD 19-24234 Labeling of Containers

• Tri Nuclear filter in spent fuel pool

• Low power range monitor quiver

• Tool cabinet on refuel floor Contamination and Radioactive Material Control (IP Section 02.03) (1 Sample)

The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.

(1) The inspectors verified the following sealed sources are accounted for and are intact:

• L07-0063

• L92-0016 Radiological Hazards Control and Work Coverage (IP Section 02.04) (1 Sample)

The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.

(1) The inspectors also reviewed the following radiological work package for areas with airborne radioactivity:

• No work packages were available for review during this inspection High Radiation Area and Very High Radiation Area Controls (IP Section 02.05) (1 Sample)

(1) The inspectors evaluated risk-significant high radiation area and very high radiation area controls.

Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 02.06) (1 Sample)

(1) The inspectors evaluated radiation worker performance and radiation protection technician proficiency.

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) 07/01/2018 - 06/30/2019

EP02: ERO Drill Participation (IP Section 02.13) (1 Sample)

(1) 07/01/2018 - 06/30/2019 EP03: Alert & Notification System Reliability (IP Section 02.14) (1 Sample)

(1) 07/01/2018 - 06/30/2019

71152 - Problem Identification and Resolution Semiannual Trend Review (IP Section 02.02)

(1) Adverse trend in plant configuration control events

71153 - Follow-up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 05000341/2019-003-00, Secondary Containment Declared Inoperable due to Opening Both Airlock Doors, ADAMS accession: ML19210B833. The circumstances surrounding this LER are documented in report Section 71153.

(2) LER 05000341/2019-004-00, Division 2 Mechanical Draft Cooling Tower Fan "D" Tripped when Placed in High Speed due to a Blown Fuse, ADAMS accession:

ML19273A053. The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors also concluded that no violation of NRC requirements occurred.

(3) LER 05000341/2019-005-00, Secondary Containment Pressure Exceeded Technical Specification due to Reactor Building HVAC Damper Malfunction, ADAMS accession:

ML19329C825. The circumstances surrounding this LER are documented in report Section

INSPECTION RESULTS

Failure to have Appropriate Instructions for Determining the Average Sediment Depth in the Residual Heat Removal Complex Reservoir Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.13] - 71111.07T Systems NCV 05000341/2019004-01 Consistent Open/Closed Process A finding of very low safety significance (Green) and an associated Non-Cited Violation of Title 10 of the Code of Federal Regulation (CFR), Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, was identified by the inspectors due to the licensees failure to have appropriate instructions for determining the average sediment depth in the Residual Heat Removal Complex Reservoir.

Description:

The Residual Heat Removal Complex Reservoir performs the ultimate heat sink function at Fermi. Periodically, the licensee performs a preventive maintenance activity to remove debris and sediment from the reservoir to ensure a sufficient volume of water remained available within the ultimate heat sink.

During this inspection, the inspectors reviewed completed Work Order 47534163. This work order (WO) was performed to remove debris and sediment from the Division 2 side of the Residual Heat Removal Complex Reservoir. Step 150.1.a.1 of the work order stated, DETERMINE AND DOCUMENT the average depth of sediment. The inspectors noted the licensee had recorded an average sediment depth of approximately 1/4 inches. The inspectors used the sediment depths recorded within the WO to calculate an average sediment depth but were unable to replicate the licensees results. However, the inspectors results were less than the acceptance criteria contained in the WO. The inspectors discussed their calculation with the licensee, and the licensee was also unable to replicate the average sediment depth result recorded in the WO. As a result, the inspectors determined the WO instructions were not appropriate to the circumstance because they allowed the WO performer to determine the method used when determining the average sediment depth. This led to documenting an average sediment depth which could not be replicated using actual plant data and a consistent, repeatable process.

Corrective Actions: The licensee planned to revise preventive maintenance activities PM244 and PM245 to require the average sediment depth be determined by adding all of the individual sediment depth data points contained in the associated WO and dividing by the total number of data points. The final average calculation will be checked by the Strategic Engineer or Component Engineer.

Corrective Action References: CARD 19-28324, "2019 NRC Triennial UHS Inspection:

Average Silt Accumulation in UHS Reservoir was not Calculated in WO 47534163"

Performance Assessment:

Performance Deficiency: The inspectors determined the failure to have appropriate instructions for activities affecting quality was a violation of 10 CFR Part 50, Appendix B, Criterion V and was a performance deficiency. Specifically, the licensee failed to have instructions appropriate to the circumstance for determining the average sediment depth in the Residual Heat Removal Complex Reservoir.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Procedure Quality attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the failure to have appropriate instructions for determining the average sediment depth in the Residual Heat Removal Complex Reservoir adversely affected the cornerstone objective because it resulted in an incorrect and non-conservative sediment depth level being recorded as part of a preventive maintenance activity.

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Specifically, the inspectors determined the finding was of very low safety significance (Green) because all of the mitigating systems screening questions were answered no.

Cross-Cutting Aspect: H.13 - Consistent Process: Individuals use a consistent, systematic approach to make decisions. Risk insights are incorporated as appropriate. The finding had a cross-cutting aspect in the Consistent Process (H.13) component of the Human Performance cross-cutting area, because individuals did not use a consistent, systematic approach to make decisions. Specifically, the licensee did not have a consistent and systematic approach to determine the average sediment depth in the Residual Heat Removal Complex Reservoir.

Enforcement:

Violation: Title 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, requires in part, that activities affecting quality be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and be accomplished in accordance with these instructions, procedures, or drawings.

Contrary to the above, on September 25, 2018, an activity affecting quality was not prescribed by documented instructions appropriate to the circumstances. Specifically, the licensee did not prescribe instructions appropriate to the circumstance for determining the average sediment depth in the Residual Heat Removal Complex Reservoir. This led to an incorrect and non-conservative sediment depth level being recorded within Work Order 47534163.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Licensee-Identified Non-Cited Violation 71111.11B 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: Title 10 of the Code of Federal Regulations (CFR) § 50.74(c) requires, in part, that each licensee notify the appropriate Regional Administrator as listed in appendix D to part 20 of this chapter within 30 days of the following in regard to licensed operator or senior operator of a permanent disability or illness as described in § 55.25. Section 55.25 requires that if, during the term of the license, the licensee develops a permanent physical or mental condition that causes the licensee to fail to meet the requirements of § 55.21, the facility licensee shall notify the Commission, within 30 days of learning of the diagnosis, in accordance with § 50.74(c). For conditions for which a conditional license (as described 10 CFR 55.33(b)) is requested, the facility licensee shall provide medical certification on Form NRC 396 to the Commission (as described in 10 CFR 55.23).

Contrary to the above, as of April 24, 2019, the facility licensee did not notify the NRC within 30 days of learning of a permanent condition for a licensed operator which caused the licensed operator to fail to meet the requirements § 55.21. Specifically, the Medical Review Officer and site nurse became aware on approximately March 12, 2018, of a medical condition that changed the operator's ability to meet the requirements of § 55.21 and for which a license condition was required. However, the facility did not notify the NRC of this medical change until May 22, 2019, a period greater than 30 days.

Significance/Severity: Severity Level IV. This issue is similar to the violation example 6.9.d.1 in the NRC Enforcement Policy, dated May 28, 2019, for a Severity Level IV violation because it involved a facility licensee's failure to make a required report that, had it been submitted, would have resulted in a licensing decision to amend a condition to the operator's license prescribing required action to maintain medical qualification while performing functions authorized by the license.

Corrective Action References: CARD 19-23136; License Operator Medical - Missed 30-day Notification as Required by 10 CFR 50.74 Inadequate Relay Replacement Frequency Causes Momentary Loss of Secondary Containment Vacuum Cornerstone Significance Cross-Cutting Report Aspect Section Barrier Integrity Green None (NPP) 71111.12 FIN 05000341/2019004-02 Open/Closed A self-revealed Green finding was identified when the licensee failed to follow site procedure MES51, "Preventative Maintenance Program." Specifically, the licensee failed to replace a relay within the vendor recommended interval due to an inappropriate application of grace period. As a result, the relay failed and prevented a Reactor Building Heating and Ventilation System (RBHVAC) damper from closing during normal operation of the system, which caused pressure to increase in secondary containment beyond Technical Specification (TS)operability limits.

Description:

On September 29, 2019, operators performed a routine swap of running RBHVAC trains.

RBHVAC is a system that provides normal ventilation to the reactor and auxiliary buildings, and is designed to maintain secondary containment at a lower pressure than the surrounding environs. With secondary containment at a lower pressure, any unplanned radioactive releases to secondary containment would be contained within the reactor building, limiting release of radioactivity outside the building. A safety-related standby gas treatment (SBGT)system is also available and is credited for use during emergencies. During the shutdown of the west RBHVAC train, the west exhaust fan discharge shutoff damper failed to close. With the damper still open and the east train in operation, some exhaust flow returned back into the reactor building, which caused secondary containment pressure to increase. The pressure increase continued until operators responded to the resultant reactor building pressure alarms in the plant's main control room by restoring the west RBHVAC train to service. The maximum positive pressure observed was 0.1" water column. The TS 3.6.4.1 pressure limit for secondary containment operability is negative 0.125" water column, and was restored approximately eight minutes later. Therefore, no TS Allowable Outage Time Requirements were exceeded.

The damper is controlled by a time delay relay, which delays opening the damper for approximately 20 seconds when starting the fan. This allows the fan to reach full speed before providing air flow for that train, so as to maintain secondary containment at the required pressure. The shutoff damper failed to close because electrical contacts on the Agastat time delay relay associated with the west RBHVAC train exhaust fan stuck closed when the fan was secured, which allowed a solenoid associated with the damper positioner to remain energized, which kept the damper open. Once operators restored the west RBHVAC train to service in accordance with the alarm response procedures, the relay reset, causing the damper to shut and then open again after the time delay expired.

Investigation by the licensee revealed that the vendor recommended replacement interval for the relay was 10 years. While the licensee had established a replacement frequency of 10 years for the relay, the relay in question had been installed for over 11 years. Per the licensee's preventative maintenance and work management procedures, there is a 25 percent grace period that is typically allowed for most components. So, for a 10-year interval, the replacement would have to be made within 12.5 years, utilizing grace. However, MES51, "Preventative Maintenance Program," section 5.1.6.8, specifically states that grace does not apply to Agastat relays unless there is an evaluation that approves of the use of grace. In this case there was no evaluation supporting an extended replacement interval, therefore, the relay was past due for replacement. Following their investigation, the licensee changed the replacement interval in the preventative maintenance program for this and other affected relays in the RBHVAC system, such that the relays would be replaced before 10 years following installation.

As a result of the secondary containment pressure increase beyond the TS 3.6.4.1 allowed limit, the licensee declared secondary containment inoperable. The licensee also submitted an eight-hour event notification (EN 54299) and LER (05000341/2019-005) for a loss of safety function based on this inoperability. The LER was evaluated under Section 71153 of this report.

Corrective Actions: To restore operability of secondary containment, the licensee restored the west train of RBHVAC to operation. As a result of their investigation, the licensee changed the replacement interval of the affected relays from 10 years to 8 years.

Corrective Action References: CARD 19-27379

Performance Assessment:

Performance Deficiency: Licensee procedure MES51, "Preventative Maintenance Program,"

section 5.1.6.8 precludes use of a grace period for PM Records that have a desired completion period established via an engineering evaluation (i.e., Agastat relays). Contrary to this requirement, the licensee utilized a grace period for an Agastat relay. As a result, the relay was not replaced within the vendor recommended interval, and no evaluation had been performed to use the grace period.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the SSC and Barrier Performance attribute of the Barrier Integrity cornerstone and adversely affected the cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events. Specifically, failure of the relay caused secondary containment to be inoperable.

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Specifically, the inspectors answered 'yes' to exhibit 3, question D.1., since the finding only affected secondary containment.

Cross-Cutting Aspect: Not Present Performance. No cross cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance.

Enforcement:

Inspectors did not identify a violation of regulatory requirements associated with this finding, because the Preventative Maintenance Program procedure was not subject to the requirements of 10 CFR 50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, or TS 5.4, Procedures.

Observation: Adverse Trend in Configuration Control Events 71152 Controlling plant configuration of structures, systems, and components (SSCs) is an important aspect to maintaining plant design functions and defense-in-depth (e.g., multiple trains or divisions of SSCs or multiple SSCs to perform the same design function). A mispositioned structure, system, or component has the potential to adversely impact plant systems and equipment resulting in problems that could cause initiating events or impact the availability and functional capability of mitigating systems or barriers. During the course of calendar year 2019, the licensee identified an adverse trend of configuration control issues, often referred to as plant status control or component mispositionings. The licensee entered the trend on multiple occasions into the corrective action program along with the various individual configuration control issues (approximately ten). Some notable configuration control event examples included, but were not limited to:

• On January 16, 2019, Average Power Range Monitor (APRM) 3 was not bypassed as required by procedure prior to planned data collection on three local power range monitors that were replaced during the previous refueling outage. Although the specified procedure step directing APRM 3 to be placed in bypass mode was marked as complete, the instrumentation and control technician performing the procedure misinterpreted the step and did not ensure the APRM switch was placed in bypass.

The condition was recognized by a control room licensed senior reactor operator during the maintenance evolution. There were no impacts to the plant as the three local power range monitors had each been individually bypassed per procedure and APRM 3 had already been declared inoperable the same day at the start of the planned maintenance evolution. [CARD 19-20353]

• On March 13, 2019, a non-licensed equipment operator did not perform a procedure step to open a closed discharge valve on nonsafety-related condensate filter demineralizer (CFD) C during system restoration following planned maintenance.

As a result, when the system was attempted to be returned to service no condensate flow was observed through CFD C. The equipment operator had manipulated the same component earlier in the procedure and thought it was already open without re-verifying the valve position. There were no adverse effects on the condensate system as multiple other CFDs were in service at the time. [CARD 19-21941]

• On March 22, 2019, a high-pressure coolant injection (HPCI) pump discharge isolation valve was found closed while attempting to return the system to service following planned maintenance. A licensed operator did not verify the HPCI pump discharge valve was open as required by procedure, in part due to six other valves listed in the same procedure verification step. The condition was identified during a fill and vent of the system to ensure it was appropriately water solid. Specifically, no water flow was noted when an attempt was made to vent the discharge piping. There were no adverse system effects on the HPCI system as it was already out of service for planned maintenance. [CARD 19-22208]

• On August 2, 2019, a piece of test equipment was not removed from a Division 2 reactor protection system (RPS) trip unit prior to returning the system to service following planned maintenance on a RPS reactor steam dome pressure instrument channel. The procedure step to remove the test equipment (calibration unit readout assembly) was not performed and inadvertently marked as completed. On August 5, 2019, instrumentation and control technicians identified the installed test equipment in the field while preparing for an unrelated surveillance test. The test equipment was determined to have no adverse impact on system operation while connected and was subsequently removed. [CARD 19-25901]

• On October 10, 2019, a non-licensed equipment operator installed a gagging device (restraint) on an incorrect relief valve while performing planned relief valve testing on the nonsafety-related Auxiliary Boiler system. The physical procedure indicating which relief valve should have been secured and which relief valve should have been tested was not in hand during the gagging evolution. The condition was recognized when the tested relief valve lift set point was lower than expected. There were no adverse impacts on the Auxiliary Boiler system. [CARD 19-27742]

The majority of configuration control issues were associated with not performing a procedure or work order step as written due to a less-than-thorough pre-job briefing prior to starting the activity, poor place-keeping of in-progress and/or completed procedural steps, or inadequate verification practices. In multiple instances, another individual was present as a peer checker during the evolution to validate the correct actions were taken and also did not identify the error.

The licensee performed several configuration control causal evaluations over the course of calendar year 2019 in an effort to address the adverse trend. In general, those causal evaluations determined that 1) high standards were not well established, internalized, and followed; 2) station leadership did not align the workforce to station priorities and goals; and 3) inadequate oversight to enforce standards. In addition, there was a perceived lack of urgency in quickly addressing the adverse trend due to the perception that the various events were low-level and/or non-consequential.

In general, individual coaching, human performance briefings, and training were not effective in mitigating the adverse trend based on a continuation of configuration control events throughout calendar year 2019 in multiple departments. Corrective actions taken or planned to address the adverse trend include, but are not limited to: 1) routine communications to all departments of configuration control standards and current status of configuration control performance; 2) increased oversight through focused configuration control observations; and 3) as part of pre-job briefings prior to performing work in the plant a series of configuration control questions must be answered by individual workers focused on appropriate recognition and mitigation of mispositioning vulnerabilities.

The inspectors did not identify any violations of regulatory requirements or performance deficiencies of more than minor significance based on the circumstances stated above.

Minor Violation 71153 Minor Violation: Licensee event report 2019-003 described that during security drills on May 29, 2019, both doors in the secondary containment airlock on the reactor building first floor were opened at the same time for approximately two seconds due to a failure to adequately control the drill. Technical Specification (TS) surveillance requirement 3.6.4.1.3 required at least one door in each secondary containment access opening to be closed during the Mode 1 (power operation) conditions at the time. With both doors open, secondary containment was rendered inoperable. Title 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, requires, in part, that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances and shall be accomplished in accordance with those instructions, procedures, or drawings. Fermi Procedure 23.428, Secondary Containment Airlocks and Penetrations, was a procedure affecting quality and required the first door opened of a secondary containment access to be closed and latched prior to opening the second door.

Screening: The inspectors determined the performance deficiency was minor. The issue was minor because it did not adversely affect the barrier integrity cornerstone. At least one door was able to be closed within two seconds upon discovery of both doors being open, secondary containment pressure was not affected, and there were no other known deficiencies with the secondary containment access doors.

Enforcement:

This failure to comply with Title 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy. The licensee closed at least one door in the secondary containment access and entered the issue in their CAP as CARD 19-24107.

EXIT MEETINGS AND DEBRIEFS

The inspectors confirmed that proprietary information was controlled to protect from public disclosure.

• On January 7, 2020, the inspectors presented the integrated inspection results to Mr. P. Dietrich, Senior Vice President and Chief Nuclear Officer, and other members of the licensee staff.

• On October 3, 2019, the inspectors presented the Emergency Preparedness Baseline Inspection inspection results to Mr. A. Mann, Radiological Emergency Preparedness Manager, and other members of the licensee staff.

• On October 4, 2019, the inspectors presented the licensed operator requalification program inspection results inspection results to Mr. P. Fessler, Senior Vice President and Chief Nuclear Officer, and other members of the licensee staff.

• On November 1, 2019, the inspectors presented the heat sink inspection results to Mr.

M. Caragher, Plant Manager and Executive Director, and other members of the licensee staff.

• On November 8, 2019, the inspectors presented the radiation protection program inspection results to Mr. R. LaBurn, Radiation Protection Manager, and other members of the licensee staff.

• On November 21, 2019, the inspectors presented the Emergency Action Level and Emergency Plan Changes Inspection inspection results to Mr. A. Mann, Emergency Preparedness Manager, and other members of the licensee staff.

THIRD PARTY REVIEWS Inspectors reviewed Institute of Nuclear Power Operations reports that were issued during the inspection period.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action 17-24586 NQA - Seasonal Readiness Program Issues 05/18/2017

Documents 19-27989 Notice of First Level Issue Escalation - Repeat 10/21/2019

Deficiencies with Non-Compliance to Seasonal

Preparedness Procedures, Ineffective Cross Functional

Team Coordination and Inadequate Oversight of Seasonal

Readiness Activities

19-28315 Follow-Up Monitoring Plan for Escalation - Repeat 10/31/2019

Deficiencies with Non-Compliance to Seasonal

Preparedness Procedures (NAQA-19-0047)

Initiated This AIM to Track Progress

Procedures 23.104 Condensate Storage and Transfer System Standby Valve

Lineup, Attachment 1, Page 9 of 46

23.208 RHR Complex Service Water Systems 127

MWC16-100 Seasonal Readiness 0A

71111.04Q Drawings 6M721-5357 Emergency Equipment Cooling Water System Division II BU

6M721-5709 Reactor Core Isolation Cooling System Sketch AO

6M721N-2053 RHR Service Water System Division 2 RHR Complex AH

Procedures 23.208 RHR Complex Service Water Systems 127

ODE-20 Protected Equipment 25

71111.05Q Calculations DC-4921 Vol 1 Appendix R Calculations E

Corrective Action 19-27427 NRC Identified Transient Combustible Without Permit 10/01/2019

Documents

Drawings 6A721-2405 Fire Protection Evaluation Reactor and Auxiliary Buildings Y

Second Floor Plan El. 613'-6"

Fire Plans FP-RB-1-7B Reactor Building South Control Rod Drive (CRD) and 5

Railroad Bay Area, Zone 7

FP-RB-2-10A Reactor Building Emergency Equipment Cooling Water 4

North, Zone 10, El. 613' 6"

FP-RHR-1-14-EDG RHR Complex EDG 14 Room El 590' 60" 6

71111.06 Miscellaneous EF2-PRA012 Fermi 2 Internal Flood Analysis Notebook 3

71111.07A Calculations DC-6286 Volume 1 EECW HX Performance Requirements with Plugging A

Corrective Action 19-24051 Recommend Scheduling Swap of the Division 1 EECW 05/28/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents Heat Exchangers

19-27521 Unexpected Increase in Div 1 EECW Heat Exchanger 10/03/2019

Differential Pressure After Recent Swap

Work Orders 49005284 Perform 24.208.03 Division 2 EESW and EECW Makeup 03/27/2019

Pump and Valve Operability Test (Section 5.1)

49538124 Perform 24.208.02 Division 1 EESW and EECW Makeup 06/06/2019

Pump and Valve Operability Test (Section 5.1)

49725438 Perform 24.208.03 Division 2 EESW and EECW Makeup 06/25/2019

Pump and Valve Operability Test (Section 5.1)

50361462 Perform 24.208.02 Division 1 EESW and EECW Makeup 09/05/2019

Pump and Valve Operability Test (Section 5.1)

71111.07T Calculations DC-0182 Volume I RHRSW Mechanical Draft Cooling Towers - Post LOCA G

Analysis of UHS

DC-0182 Volume VI RHRSW Mechanical Draft Cooling Towers - Heat Load C

After A Design Basis Tornado

DC-5474 Waterhammer Analysis for the RHR Service Water 0

System

DC-5804 DGSW Design Basis Requirements E

DC-6121 Design Basis for RHR Heat Exchanger Thermal B

Performance Test Criteria

Calibration Calibration Emergency Diesel Generator (EDG) 12 Air Temperature 0

Records Specification Sheet Thermometer

R30A23C-S

Calibration Emergency Diesel Generator (EDG) No. 13 Service Water 0

Specification Sheet Pump 'B' Water Flow Low

R30N569B-S

Corrective Action 14-22832 Acceptance Criteria not met for 47.205.01 during RFO-16 03/26/2014

Documents 15-28706 Ultrasonic Flow Meter Calibration Required for 47.205.01 11/06/2015

15-28710 Low Decay Heat Load for 47.205.01 in RFO-17 11/06/2015

15-28719 Actual Test Uncertainty Exceeds the Acceptable Test 11/06/2015

Uncertainty of 47.205.01 from RFO-17 for Case 2

Evaluation

16-21036 Increase in EDG 13 Heat Exchanger Tubes Blocked 02/04/2016

16-24183 2016 NRC UHS Inspection - Inconsistent Work 05/19/2016

Inspection Type Designation Description or Title Revision or

Procedure Date

Documentation of RHR Reservoir Inspections

16-26238 2016 Generic Letter (GL) 89-13 Program Health Report 08/08/2016

Tracking

16-27634 NRC Violation - Inadequate Test Procedure Used for 09/26/2016

Measuring and Determining Average Silt Levels in the

Service Water Reservoir

17-00221 EDG 13 DGSW Flow Transmitter Reading High 01/21/2017

17-21233 Operations Shift 4 Crew Learning Opportunity - Identified 02/12/2017

EDG 13 DGSW Flow High but Didn't Write a CARD

18-20572 Excessive Build-up of Grime, and Sludge on Outside of 01/22/2018

the Tube Bundle

Corrective Action 19-28289 2019 NRC Triennial UHS Inspection: Evaluate Effect of 10/30/2019

Documents Failed Post-Calibration Check of Ultrasonic Flow Meter on

Resulting from 47.205.01 Performed 11/11/2015

Inspection 19-28291 2019 NRC Triennial UHS Inspection: Typographical Error 10/30/2019

in DC-0182 Vol I

19-28324 2019 NRC Triennial UHS Inspection: Average Silt 10/31/2019

Accumulation in UHS Reservoir was not Calculated in WO 47534163

19-28350 2019 NRC Triennial UHS Inspection: RHR Heat 11/01/2019

Exchanger Data Sheet Enhancements

19-28351 2019 NRC Triennial UHS Inspection: Heat Exchanger 11/01/2019

Shell Side Cleanliness Impacts

19-28353 EDG Air Coolant Temperature - DC-5804 Vol I 11/01/2019

Discrepancy

19-28482 2019 NRC Triennial UHS Inspection: Proto-HX Mass Flow 11/06/2019

Calculation

Drawings 6M721-2084 Diagram Residual Heat Removal (R.H.R) Division I BP

6M721N-2053 RHR Service Water System Division 2 RHR Complex AH

Miscellaneous IST Components

Heat Exchanger Specification Sheet 01/17/1995

Results of the 2014 MMR14 Structures Monitoring 10/08/2014

Walkdown

NDE Reports 27138 Eddy Current Preliminary Report 10/04/2018

Inspection Type Designation Description or Title Revision or

Procedure Date

Procedures 23.208 RHR Complex Service Water Systems 126

23.307 Emergency Diesel Generator System 128

24.307.36 DGSW, DFOT and Starting Air Operability Test EDG 13 56

MES54 Heat Exchanger Component Monitoring Program 7A

Work Orders 18-20990 Replace EDG 13 SW Pump 02/05/2018

25976827 Eddy Current Testing of Heat Exchanger 10/19/2018

2416088 Calibrate EDG 13 DGSW Pump 'B' Low Flow Switch 08/03/2015

34438905 Perform 47.205.01 RHR Division 1 HX Performance Test 04/25/2014

203843 Perform 47.205.01 RHR Division 1 HX Performance Test 11/11/2015

286065 Perform 24.205.05 Division 1 RHRSW Pump & Valve 04/23/2016

Operability

2610300 Perform 24.307.36 DGSW, DFOT & Starting Air 07/26/2016

Operability Test EDG 13

43114139 Perform 24.307.36 DGSW, DFOT & Starting Air 10/26/2016

Operability Test EDG 13

44307098 Perform 24.205.05 Division 1 RHRSW Pump & Valve 05/09/2017

Operability

44348532 Calibrate EDG 13 Service Water Flow Loop 07/26/2017

44813323 Perform 24.307.36 DGSW, DFOT & Starting Air 07/26/2017

Operability Test EDG 13

45376325 Perform 24.307.36 DGSW, DFOT & Starting Air 11/06/2017

Operability Test EDG 13

46513309 Perform 24.205.05 Division 1 RHRSW Pump & Valve 05/09/2018

Operability

47053547 Perform 24.205.05 Division 1 RHRSW Pump & Valve 07/17/2018

Operability

47534163 License Renewal REQ'D Perform Div 2 RHR Reservoir 01/15/2019

Zebra Mussel and Ball Valve Inspection Dive

47788625 Perform 24.307.36 DGSW, DFOT & Starting Air 10/31/2018

Operability Test EDG 13

48505873 Perform 24.307.36 DGSW, DFOT & Starting Air 01/27/2019

Operability Test EDG 13

48913263 Inspect and Replace EDG 13 Exchanger Tube Bundles 01/22/2018

242378 Perform 24.307.36 DGSW, DFOT, & Starting Air 04/24/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

Operability Test EDG 13

272520 Perform 24.307.37 DGSW, DFOT & Starting Air 05/01/2019

Operability Test-EDG 14

50014288 Perform 24.307.37 DGSW, DFOT & Starting Air 07/30/2019

Operability Test-EDG 14

50480923 Perform 24.307.32 EDG No. 13 24 Hour Run Followed by 10/23/2019

Hot Fast Restart

71111.11B Corrective Action CARD 17-29439 Significant Arcing in A RRMG Set Exciter Brushes 11/27/2017

Documents CARD 18-26702 NRC Concern - Potential Lack of Timeliness for 09/05/2018

Reportability Assessment with Seismic Recorder

Inoperable

CARD 18-30363 Mispositioned Control Rod while in Mode 4 12/24/2018

CARD 19-22208 Mispositioned Component: Ops Shift 5 CLO - Valve 03/22/2019

Found Out of Position During System Fill and Vent

CARD 19-23136 License Operator Medical-Missed 30-day Notification as 04/24/2019

Required by 10 CFR 50.74

CARD 19-25407 Operator Licenses Not Terminated 07/17/2019

CARD 19-25407 NRC not Notified within 30 Days of Operator License 08/21/2019

Termination

CARD 19-25588 Instructor Presented Modified Training Material in NOR 07/24/2019

[Nuclear Operator Requalification]

CARD 19-26372 NRC Exam Security Compromise for 2019 License 08/23/2019

Operator Biennial Exam during Validation

CARD 19-27233 Missed Emergency Classification During a Simulator 09/25/2019

Exam

Root Cause RCE for CARD Regarding A RRMG Set Arcing 0

Evaluation (RCE) for

CARD 17-29439

Engineering NTWI [Nuclear Cycle 20 Simulator Core Model Performance Testing 11/20/2018

Evaluations Training Work

Instruction] 1.22

SM 5 2018 Simulator Operating Limit and Real Time Test 12/15/2018

SM 6 2018 Simulator Steady State Operations Performance 12/17/2018

Test

Inspection Type Designation Description or Title Revision or

Procedure Date

SM 7 2018 Simulator Operations Procedures Performance Test 12/17/2018

SM 8 2018 Simulator Malfunction Performance Test 12/17/2018

SM 9 2018 Simulator Initial Conditions Performance Test 12/14/2018

Miscellaneous CR 6330 Malfunction MFE062 - Loss of 4160 V ESF Bus 65F was 01/04/2019

Stopped

CR 6331 24.404.03 rev. 47 - During Performance of SGTS Oper. 11/26/2018

test, valves T4600-F410 and T4600-F407 were Outside

the New Stroke Time Requirements

CR 6334 24.138.02 Stroke Time for B3100-F014A not Withing IST 11/28/2018

Limits

CR 6336 24.202.01 HPCI Pump and Valve operability Test at 1025 12/07/2018

psi. Valve stroke times outside of acceptable limits for

E4100-F029/F054/F053. Stroke time requirements

changes since previous surveillance.

CR 6458 N6100 Condenser and Auxiliaries - Comparator for MTG 080/02/2019

Trip Set at 1425 rpm; included 75 rpm Internal Hysteresis

that was not Appropriate

JP-OP-315-0105- Manually Initiate Low-Low Set - Alt Path 0

181

JP-OP-315-0158- Loss 64C and EDG 12 Fails to Start 6

2

JP-OP-802-4101- Obtain and Interpret Electrical Drawings 0

2

JP-OP-802-4101- Thermal Limit Verification (MAPRAT) - SRO 1

531

NANT-18-0239 Effectiveness Report on Operator Proficiency Training 12/21/2018

Training Program Licensed Operator Requalification Evaluation Forms for 10/01/2019

Description - Simulator Exams Conducted on 10/1/2019

Licensed Operator

Requalification

Attachments 3A-D

Procedures MGA13 Fermi Medical Requirements 18

MGA25 Inprocessing, Outprocessing, and Change of Vendor 13

MNT18 Conduct of Operations Training Manual 1

Inspection Type Designation Description or Title Revision or

Procedure Date

NTWI 1.16 Examination Safeguards and Controls 45

NTWI 1.20 Simulator Fidelity 4

NTWI 1.23 Licensed Operator Requalification Exams 14

NTWI 1.25 Licensed Operator Medical Work Processes 5

Nuclear Licensing Requirements for NRC Operator License Letters to the 3

Work Instruction NRC

0053

ODE [Operations Operations Roles and Responsibilities 26

Department

Expectation]-5

ODE-8 Administrative Guidelines and Desk Instructions 17

Self- NANT-19-0114 Formal Self-Assessment Report (Licensed Operator 08/28/2019

Assessments Requalification Program)

71111.11Q Corrective Action 19-28403 Loss of SJAE #3 Followed by Degrading Condenser 10/23/2019

Documents Vacuum

Miscellaneous LP-OP-202-1891 Emergency Action Levels for Operations 1

Procedures 20.125.01 Loss of Condenser Vacuum 26

23.125 Condenser Vacuum System 65

ARP 6D1 SJAE System Trouble 16

EP-101 Classification of Emergencies 42C

71111.12 Corrective Action 18-26173 Decreasing Trend in Both Div 1 and Div 2 Reference Leg 08/15/2018

Documents Backfill Flow

18-26786 Operator Red Reading for Div 1 Reference Leg Backfill 09/09/2018

18-30374 Request Engineering to Evaluate the Upper Limit of the 12/26/2018

Reference Leg Backfill System and Remove Limit if

Appropriate

19-20916 B21P408A Nuclear Boiler Div 1 RPV Water Level 02/07/2019

Reference Leg Backfill Trending Low

19-25752 Adjustment of Div 2 Reference Leg Backfill Based on 07/31/2019

Current Flow Trend

19-26302 Div 2 Reference Leg Backfill Current Flow Trend 08/21/2019

19-27379 T4100-F014 Exhaust Damper Failed to Close when 09/29/2019

Exhaust Fan was Shutdown

19-27726 Damper Linkage Bushings Show Indications of Wear 10/10/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

19-27741 Inconsistent Work Order Instruction Results in Incorrect 10/10/2019

Torque Values Being Applied

19-29033 T4100F025 RB Center Supply Fan Shutoff Damper 11/25/2019

Failure / Delayed Closure

19-29081 RBHVAC not Maintaining RB Pressure 11/25/2019

19-29395 Div 1 Reference Leg Backfill is High Out of Specification 12/08/2019

for Operator Rounds

19-29705 RBHVAC Exhaust Fan Modulating Damper Failure 12/18/2019

19-29708 RBHVAC Center Supply Fan Shutoff Damper Failed to 12/18/2019

Close

Drawings 5I721-2615-04 Auto Temp Control System Control Panel H21P527, 0

P527A, P528, and P529 Control Diagram Ventilation

6M721-2707 Flow Diagram Reactor and Auxiliary Building Ventilation P

System

6M721-2707-1 Flow Diagram Reactor and Auxiliary Building Ventilation D

System

6M721-2709 Diagram Standby Gas Treatment and Primary AI

Containment Purge System Reactor Building

Miscellaneous Design Basis Reactor Auxiliary Building Ventilation System 04/23/2019

T41-00

MES51 Chaper 51 - Preventive Maintenance Program 19

MMM08 Material Shipping, Handling, and Storage 21

MMR Appendix E Maintenance Rule SSC Specific Functions 25

O & WMI-014 Outage and Work Management Instruction 9

Procedures 46.000.046 Operation of the Reactor Reference Leg Backfill System 41

Work Orders 46727448 Replace Filter Cartridges in Div 1 RPV Water Level 09/30/2018

Instrumentation Backfill

WO 51297761 Perform Mini Periodic MOV Inspection (E2150-F036B) 12/17/2019

71111.13 Corrective Action 19-28364 Generator Stator Lift NRC Question 11/01/2019

Documents 19-28371 NRC Question Concerning Presence of 32.RIG.18 11/01/2019

Communication Plan

19-28797 During Electric Fire Pump Run Pump Displayed Excessive 11/15/2019

Vibrations

19-28805 Request Evaluation to Determine if a Proper Risk 11/16/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

Assessment was Performed During the Work Planning

Process for WO 50976710

Miscellaneous 50.59 Screen MTG Replacement A

19-0037

Black and Veatch Turbine Building Structural Evaluation [Confidential] 1

Calculation 193823

1001

Black and Veatch Fermi 2 Evaluation of Heavy Loads Impacts during Main 0

Evaluation 193823 Generator Replacement [Proprietary]

1000

Design Information Barnhart Structural and Rigging Design Parameters 0

Transmittal

U21-190813-001

Enterprise Risk Plan Risk Associated with Replacement of the Main Turbine 2

80000 Generator

Fermi 2 Shift Manager Daily Alignment Meeting 11/26/2019

Infrequently Main Generator Stator Lift

Performed Test or

Evolution Briefing

Sheet

LCO 2019-0415 Replace Divison 2 NIAS Control Air Dryer Relay 11/22/2019

LCO 2019-0429 Division 2 Switchgear Room Cooler Power Supply 11/25/2019

Inspection

LCO 2019-0483 P5002 Inspect and Adjust D2 CAC Room Cooler Belts 11/25/2019

MES56 Engineering Risk Assessment, Job Briefing, and Product 7

Quality Review

MMA26 Troubleshooting 7A

MMR Appendix H On-Line Core Damage Risk Management Guidelines 15

MMR12 Equipment Out of Service Risk Management 20A

MWC18 Emergent Issues Response 3A

ODE-16 Risk Assessment and Operation of Phoenix 3

ODE-20 Protected Equipment 25

Stator Offload Lift Per Procedure 32.RIG.18, Guidelines and Practices for 3

Plan/Communication the use of Hoisting and Rigging Equipment

Inspection Type Designation Description or Title Revision or

Procedure Date

Plan

TE-ANL-19-043 PSA Risk Associated with the Lift of Generator Stator per 0

WO 54150509

TE-N30-19-028 Generator Stator Haul Path Evaluation B

Procedures 20.000.03 Turbine Building Flooding 12

2.716.01 Turbine Building Crane Operation 6

2.RIG.18 Guidelines and Practices for the Use of Hoisting and 15A

Rigging Equipment

Work Orders 53495247 Lift Plan per Procedure 32.RIG.18 [Proprietary]

71111.15 Corrective Action 19-24737 EDG 14 Surging in Idle During Surveillance Run 06/24/2019

Documents 19-25713 E1156-C001D, Div 2 RHRSW MDCT Fan D, Tripped 07/30/2019

when Placed in High Speed

19-25722 Blown Fuse on 'D' RHR MDCT Fan High Speed Breaker 07/30/2019

19-27115 NRC Identified - Support E21-3144-G04 Spring Can 09/20/2019

Setting Out of Tolerance

19-27144 Adverse Trend with EDG 14 Fast Start Time 09/23/2019

19-27229 P44-F400B Did Not Fail in the Full Open Direction During 09/25/2019

24.208.03 Step 5.1.28

19-27462 Severed Tubing on EDG 14 10/02/2019

19-27694 Hot Spot on 'A' Phase of 72C-2A Pos. 2AR 10/09/2019

19-27741 Inconsistent Work Order Instruction Results in Incorrect 10/10/2019

Torque Values Being Applied

19-27743 Failed PMT: As Left Thermography Following Hot Spot 10/10/2019

Repair

19-27748 Revise Tech Spec Bases for LCO 3.7.4 10/11/2019

19-28481 Acrid Odor RCIC Barometric Condenser Vacuum Pump 11/05/2019

Motor

19-28721 Human Performance Error While Performing Surveillance 11/13/2019

44.030.263 ECCS ADS L3 and L8 Div 1 Ch A Functional

19-28910 SPF Inaccuracies 11/20/2019

19-28912 Temp Diesel Fire Pump Low Battery Water 11/20/2019

19-29282 NRC Identified - Operations did not Declare Alternate 12/04/2019

Diesel Fire Pump Inoperable when Battery Low Level

Identified

Inspection Type Designation Description or Title Revision or

Procedure Date

19-29325 Temp Diesel Fire Pump 12/05/2019

Drawings 6M721-5709-1 Reactor Core Isolation Cooling (RCIC) System Sketch AO

6M721-5734 Emergency Diesel Generator System BI

6M721N-2047 Diesel Generator System Division II RHR Complex AL

Engineering Temporary Winterization of Temporary Alternate Diesel Fire Pump A

Changes Modification

19-0018

Engineering TMSA-06-0067 Evaluation of the No. of MDCT Fans Required for Decay 12/18/2006

Evaluations Heat Removal Success (CARD 06-26273)

Miscellaneous Design Basis Emergency Diesel Generator I

R30-00

E51-00 Reactor Core Isolation Cooling System Design Basis

Document [proprietary]

Risk Management Electric Fire Pump/Diesel Fire Pump Diving 11/18/2019

Plan (Rev 0)

Procedures 34.307.001 Emergency Diesel Generators - Inspection and Preventive 81

Maintenance

44.030.263 ECCS - Reactor Vessel Water Level (ADS Level 3 and 37

Feedwater / Main Turbine Level 8), Division 1, Channel A

Functional Test

71111.18 Corrective Action 18-26318 New Fuel Transfer Crane Cable and Sheave Damaged 08/21/2018

Documents 18-27722 New Fuel Transfer Crane Cable and Sheave Damaged 10/10/2019

19-27473 Impact of Padding Installed New Fuel Inspection Stand 10/02/2019

may not have been Evaluated

19-27990 Evaluate New Fuel Inspection Stand Testing and 10/21/2019

Inspection Requirements

19-28020 Safety Concern with Channel Handling Winch Inspection 10/22/2019

Miscellaneous Design Change Fuel Uprighting Stand Modification 0

Package 80128

Work Orders 55442826 Modify Fuel Uprighting Machine 19-27432 11/04/2019

71111.19 Corrective Action 19-27229 P44-F400B Did Not Fail in the Full Open Direction During 09/25/2019

Documents 24.208.03 Step 5.1.28

19-27403 AFCC4 for RWCU B Flow Control Loop 09/30/2019

19-27498 Wrong Fuse Found in Bag for Restoration of EDG 14 10/03/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

19-27567 Inner Railroad Airlock Door Rail Plugs are Degraded 10/05/2019

19-27588 Suspected Hydraulic Lock on East Outer Railroad Airlock 10/07/2019

Door

Drawings 6I721-2125-06 Control System (DCS-FW) External Connections H

6M721-2023 Feedwater System BO

6M721-5711-2 Reactor Water Clean-Up Filter Demineralizers U

6M721-5715-3 Standby Feedwater System Functional Operating Sketch N

6M721-5729-2 Emergency Equipment Cooling Water (Division II) BB

6M721-5733-1 Fire Protectin Functional Operating Sketch BY

I-2331-07 Schematic Diagram Gland Sealing Steam Exhauster (E & G

W)

Engineering EDP 37673 Elimination of Main Steamline Isolation Valve Closure and 0

Changes Scram Functions of Main Steamline Radiation Monitor

Miscellaneous MMA11 Valve Testing, Enclosure B 25

VMC2-105 CCI Drag Valve Vendor Manual B

Procedures 24.107.03 SBFW Pump and Valve Operability and Lineup 46

Verification Test

24.207.09 Division 2 EECW Pump and Valve Operability Test 44

34.307.001 Emergency Diesel Generators - Inspection and Preventive 81

Maintenance

35.139.006 CCI Drag Valve and Actuator Maintenance 3

43.000.010 IST Check Valve Inspection Procedure 40

ARP 2D13 Fuel Pool Cooling Trouble 23

Work Orders 48449374 Perform Non-ASME As-Found and As-Left Relief 10/10/2019

49062676 Inspect/Test 260 VDC MCC 2PC-1 Pos 5A 10/10/2019

49705777 Disassemble/Inspect Check Valve Internals for 10/21/2019

Degradation

51059456 Perform 28.504.09 Electric Fire Pump Monthly Operability 11/22/2019

Test

51441579 Calibrate RWCU Filter Demin 'B' Effluent Flow Loop 09/30/2019

2071933 EDP 37673 Elimination of Main Steamline Isolation Valve 10/25/2018

Closure and Scram Function of Main Steamline Radiation

Monitor Post Maintenance Test for 4D32

Inspection Type Designation Description or Title Revision or

Procedure Date

208989 44.080.605 East and West Gland Seal Exhauster / 10/23/2018

Mechanical Vacuum Pump Logic System Functional Test

55304662 EECW Div 2 HX B001B/B001D SW Outlet Temp Control 10/05/2019

AOV

55304788 Adverse Trend with EDG 14 Fast Start Time 09/30/2019

55372321 Perform 24.307.17 Sec-5.2 EDG 14 Start and Load Test - 10/02/2019

Fast Start

55419277 Blow Down Pneumatic Locking Bar Lines on Exterior RR 10/07/2019

Air Lock Doors

55799429 Troubleshoot/Repair Electric Fire Pump 11/16/2019

71111.22 Procedures 24.000.02 Shiftly, Daily, and Weekly Required Surveillances 157

24.307.17 Emergency Diesel Generator 14 - Start and Load Test 59

Work Orders 50698481 Perform 550 kW N Diesel S001A Functional Test 887200 10/12/2019

50943437 Perform 550kW N+1 Diesel S001B Functional Test 11/07/2019

887201

51363396 Perform 24.307.17 Sec-5.1 EDG 14 Start and Load Test - 12/23/2019

Slow Start

71114.02 Corrective Action 18-23507 18-23507 Explore Alternate Siren Testing for NRC PI data 05/02/2018

Documents

Miscellaneous FEMA Approval Letter for Fermi 2 ANS Design Report, 11/30/2015

Revision 1

Alert Notification System Siren Test Results 09/01/2017 -

09/01/2019

ANS Sirens Corrective Maintenance Records 09/01/2017 -

09/01/2019

ANS Siren Annual Preventative Maintenance Records 09/01/2017 -

09/01/2019

2019 Monthly Siren Test Schedule

DTE Energy Emergency Preparedness for Monroe and

Wayne Counties 2019 (Handbook)

Fermi 2 Alert and Notification System (ANS) Design 6

Report

255232R Federal Signal Corporation 2001SRNB Electro- 09/28/2004

Inspection Type Designation Description or Title Revision or

Procedure Date

Mechanical Siren

SS2000D - SS2000D Controller/Encoder Installation and Operation 10/07/2003

255318G1 Instructions

Procedures Fermi 2 Radiological Emergency Response Preparedness 48

Plan

EP-560 Alert and Notification System Operation and Maintenance 6

71114.03 Corrective Action 18-21396 RERP Callout Automated System has Limited 02/19/2018

Documents Functionality

18-24950 ECOS Test Results TSC/EOF Personnel 06/26/2018

18-26311 Red Team ECOS Response was not 100% 08/21/2018

18-29646 Potential Trend in ECOS Non-Response for 11/30/2018

Acknowledgement of On-Call ERO Duty

19-24138 Failure to Respond to ECOS Callout 05/30/2019

Miscellaneous ERO Quarterly Augmentation Drill Records 09/01/2017 -

09/01/2019

Fermi 2 On-shift Staffing Analysis 12/20/2012

Fermi 2 ERO Team List 08/31/2019

ERO Team Training and Qualification Records 10/03/2019

(Sample - 10)

Procedures Fermi 2 Radiological Emergency Response Preparedness 48

Plan; Section B, Emergency Response Organization

EP-290 Emergency Notifications 61

EP-540 Drills and Exercises 39

EP-550 RERP Training Program 58

EP-570 Emergency Call Out System - Testing and Maintenance 6A

EP-570, ECOS Test Reviews (Quarterly) 09/01/2017 -

09/01/2019

QP-ER-670 Radiological Emergency Response Preparedness 8

Selection, Training and Qualification Program Description

71114.04 Miscellaneous 10 CFR 50.54Q Compliance Review Personnel 06/24/2019

Qualifications Spreadsheet

2018-04E 10 CFR50.54(q) Evaluation - RERP Plan Change, Plant 08/16/2018

Radio System Upgrade

2018-06E 10 CFR50.54(q) Evaluation - RERP Plan Change, 07/18/2018

Inspection Type Designation Description or Title Revision or

Procedure Date

Operations Support Center Relocation

2018-10S 10 CFR50.54(q) Screen - RERP Plan Change, Central 08/11/2018

Alarm Station Relocation

2018-35S 10 CFR50.54(q) Screen - RERP Plan Change, Operations 07/18/2018

Support Center Relocation

2018-36S 10 CFR50.54(q) Screen - RERP Plan Change, Plant 08/06/2018

Radio System Upgrade

Procedures Fermi 2 Radiological Emergency Response Preparedness 47

Plan

Fermi 2 Radiological Emergency Response Preparedness 48

Plan

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

71114.05 Corrective Action 17-27716 NQA Audit 17-0112 Deficiency - Uncontrolled and 09/18/2017

Documents Outdated RERP Documents in the EOF

17-27788 NQA Audit 17-0112 Recommendation -Training 09/20/2017

Enhancements for ERO Positions

17-29094 RadDose Program 11/09/2017

17-29260 Incorrect Calibration Constant in RadDose V 11/16/2017

19-21090 RERP Excellence Initiatives Tracking EI2 02/13/2019

19-21964 Missed and Untimely Classification in the Simulator 03/13/2019

Miscellaneous Quarterly Operations Support Facility ERF Testing and 09/01/2017 -

Maintenance Records 09/01/2019

Exercise and Drill Evaluation Reports (Sample) 09/01/2017 -

09/01/2019

Quarterly Control Room ERF Testing and Maintenance 09/01/2017 -

Records 09/01/2019

Quarterly Emergency Operations Facility ERF Testing and 09/01/2017 -

Maintenance Records 09/01/2019

Quarterly Technical Support Center ERF Testing and 09/01/2017 -

Maintenance Records 09/01/2019

Emergency Preparedness Letters of Agreements with Off- 09/01/2017 -

Site Response and Support Organizations 09/01/2018

Inspection Type Designation Description or Title Revision or

Procedure Date

KLD-TR-1030 Fermi 2 Nuclear Power Plant 2018 Population Update 09/29/2018

Analysis

Procedures EP-101 Classifications 42C

EP-290 Emergency Notifications 42C

EP-292 Emergency Call Out - Backup Method 32

EP-580 Equipment Important to Emergency Response (EITER) 7

EP-590 10 CFR 50.54(q) Screens and Evaluations 0A

EP-601 Public Education and Information 11

Self- Audit Report 17- Quality Assurance Audit of Emergency Preparedness 09/26/2017

Assessments 0112 Program

Audit Report 18- Quality Assurance Audit of the Emergency Preparedness 09/18/2018

0111 Program

71114.06 Miscellaneous 2019 Fourth Quarter Table Top Drill, DTE Electric 10/03/2019 -

Company, Fermi 2 10/24/2019

Procedures EP-101 Classification of Emergencies 42C

71124.01 Corrective Action 18-29556 Dose Rate Increase Creating New Locked High Radiation 11/28/2018

Documents Area on RB-2

19-20128 Higher Than Anticipated Dose Rates during RWCU Fill 01/06/2019

and Vent Activities

19-20981 Locked High Radiation Area Conditions Found in the 02/09/2019

Torus Room Sub-Basement Reactor Water Clean Up

Return Line

19-22778 Elevated Dose Rates in the Auxiliary Building T-Room, 04/14/2019

Requiring the Posting of a High Radiation Area

Procedures 68.000.003 Radiological Air Sampling 1A

Radiation 00116-A19 Reactor Core Isolation Cooling Run 05/10/2019

Surveys 00252-A19 Turbine Deck To Steam Tunnel 09/16/2019

00305-A19 Reactor Water Clean Up Pump Room 10/02/2019

01312-R19 Reactor Core Isolation Cooling Run 05/10/2019

2412-R19 Reactor Core Isolation Cooling Run 08/14/2019

2766-R19 Steam Tunnel 09/15/2019

2787-R19 Steam Tunnel 09/17/2019

2930-R19 Reactor Water Clean Up Pump Room 10/01/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

2958-R19 Reactor Water Clean Up Pump Room 10/01/2019

254-R19 Reactor Water Clean Up Phase Separator Room 11/06/2019

03450-R18 Reactor Water Clean Up Phase Separator Room 09/25/2018

Radiation Work 191020 Emergent Issues Tasks 01

Permits (RWPs) 191027 E41 and E51 System Maintenance, Inspections, 02

Surveillance and Test Runs

191050 Reactor Water Clean Up Pump Seal Repair/Replacement 01

191051 Reactor Water Clean Up Phase Separator Room Entry 00

and Component Repair

Work Orders 54082896 Perform 64.713.050 Source Leak Testing 06/19/2019

71151 Miscellaneous Performance Indicator Data Sheets - Drill and Exercise 07/01/2018 -

Performance (DEP) 06/30/2019

Performance Indicator Data Sheets - Alert and Notification 07/01/2018 -

System (ANS) 06/30/2019

Performance Indicator Data Sheets - Emergency 07/01/2018 -

Response Organization (ERO) Drill Participation 06/30/2019

71152 Corrective Action 19-20353 Mispositioned Component: APRM 3 not Bypassed during 01/16/2019

Documents 46.604.001

19-20355 Cognitive Trend - Operations Mispositioning Events 01/16/2019

19-20897 Security CLO - Plant Equipment Bumped during FOF 02/07/2019

Drills

19-21941 Mispositioned Component: Missed Procedure Step when 03/13/2019

Placing CFD C in Service

19-22208 Mispositioned Component: Ops Shift 5 CLO - Valve Fount 03/22/2019

out of Position during System Fill and Vent

19-22351 Evaluation of Operations Plant Status Control 03/27/2019

Performance

19-22376 2019 Plant Status Control Committee (PSCC) Meeting 03/28/2019

Actions

19-22799 DFP Jacket Cooler Inlet Alt Stnr Outlet Isolation Valve was 04/15/2019

Found in Closed Position

19-23602 INPO Evaluation Plant Status Control 09/03/2019

19-23623 Mispositioned Component: Discovered P5000F1013A not 05/10/2019

in Correct Positions

Inspection Type Designation Description or Title Revision or

Procedure Date

19-23859 Potential Mispositioned Component: Unexpected Caps 05/20/2019

Left Installed on RB SPING Lines

19-24681 Document Assessment of IN 2019-03 06/21/2019

19-25901 Mispostioned Component: Rosemount Readout Found 08/05/2019

Installed in Rosemount Trip Unit in H21P087 Section Z1

19-26203 Mispositioned Component: Operations Shift 5 CLO - Step 08/16/2019

not Performed in 23.300

19-26858 Plant Status Control Committee Input to Nuclear Safety 09/12/2019

Culture Monitoring Panel

19-26860 Effectiveness Review Measures will not be Met 09/12/2019

19-27742 Mospositioned Component P6100F020B South Boiler 10/10/2019

Steam Relief Valve, While Performing 27.142.01 Auxiliary

Boiler Trip and Safety Valve Test for the South Auxiliary

Boiler

19-28157 Mispositioned Component - S Aux Boiler Atomizing Air 10/25/2019

Isolation Valve Found Open during Reference Leg Filling

19-28217 Plant Status Control Committee - Maintenance Plant 10/28/2019

Status Control Precursors

19-28218 Plant Status Control Committee - Operations Plant Status 10/28/2019

Control Precursors

19-28721 Human Performance Error while Performing Surveillance 11/13/2019

44.030.263 ECCS ADS L3 and L8 Division 1 Channel 'A'

Functional Test

19-29371 HCU 14-07: Leak Coming from the Manifold Filter Plug for 12/07/2019

the C11F120 FCV

19-29423 Chemistry Performance of SPING Weekly Surveillance 12/09/2019

without Signing on with the Tagging Center

Miscellaneous MOP05 Operations Control of Equipment 57

Conduct Manual

ODE-7 Operations Configuration Control 10

Department

Expectation

71153 Corrective Action 19-25713 E1156-C001D, Div 2 RHRSW MDCT Fan D, Tripped 07/30/2019

Documents When Placed in High Speed

Inspection Type Designation Description or Title Revision or

Procedure Date

19-25722 Blown Fuse on 'D' RHR MDCT Fan High Speed Breaker 07/30/2019

Engineering TMSA-06-0067 Evaluation of the No. of MDCT Fans Required for Decay 12/18/2006

Evaluations Heat Removal Success (CARD 06-26273)

Miscellaneous LER 2019-003 Secondary Containment Declared Inoperable due to 0

Opening Both Airlock Doors

LER 2019-004 Division 2 Mechanical Draft Cooling Tower Fan "D" 00

Tripped when Placed in High Speed due to a Blown Fuse

LER 2019-005 Secondary Containment Pressure Exceeded Technical 00

Specification due to Reactor Building HVAC Damper

Malfunction

39