IR 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 | |
| Preceding documents: |
|
| Download: ML20038A340 (42) | |
Text
February 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:
Report Number:
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
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: 71111.11
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 Aspect Report Section Mitigating Systems Green NCV 05000341/2019004-01 Open/Closed
[H.13] -
Consistent Process 71111.07T 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 Aspect Report Section Barrier Integrity Green FIN 05000341/2019004-02 Open/Closed None (NPP)71111.12 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,
Unit 2, Division 2 Mechanical Draft Cooling Tower Fan "D" Tripped when Placed in High Speed due to a Blown Fuse 71153 Closed LER 05000341/2019-005-00 LER 2019-005-00 for Fermi,
Unit 2, Secondary Containment Pressure Exceeded Technical Specification due to Reactor Building HVAC Damper Malfunction 71153 Closed LER 05000341/2019-003-00 LER 2019-003-00 for Fermi,
Unit 2, Secondary Containment Declared Inoperable due to Opening Both Airlock Doors 71153 Closed
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.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.02) (1 Sample)
- (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
71111.04Q - 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) 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) (3 Samples)
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.) (1 Sample)
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) (1 Sample)
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 Sample)
- (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 Sample)
- (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 Sample)
- (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) (2 Samples)
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) (6 Samples)
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) (8 Samples)
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
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) (1 Sample)
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) (8 Samples)
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 Sample)
- (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 Sample)
- (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 Sample)
- (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 Sample)
- (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) (2 Samples)
- (1) Observation of emergency action level training evolution on October 18, 2019
- (2) Emergency Preparedness Drill conducted on October 31,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 02.01) (1 Sample)
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)===
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)===
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 Sample)
- (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 Aspect Report Section Mitigating Systems
Green NCV 05000341/2019004-01 Open/Closed
[H.13] -
Consistent Process 71111.07T 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 Aspect Report Section Barrier Integrity
Green FIN 05000341/2019004-02 Open/Closed None (NPP)71111.12 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
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
17-24586
NQA - Seasonal Readiness Program Issues
05/18/2017
19-27989
Notice of First Level Issue Escalation - Repeat
Deficiencies with Non-Compliance to Seasonal
Preparedness Procedures, Ineffective Cross Functional
Team Coordination and Inadequate Oversight of Seasonal
Readiness Activities
10/21/2019
19-28315
Follow-Up Monitoring Plan for Escalation - Repeat
Deficiencies with Non-Compliance to Seasonal
Preparedness Procedures (NAQA-19-0047)
Initiated This AIM to Track Progress
10/31/2019
Procedures
23.104
Condensate Storage and Transfer System Standby Valve
Lineup, Attachment 1, Page 9 of 46
23.208
RHR Complex Service Water Systems
27
MWC16-100
Seasonal Readiness
0A
71111.04Q Drawings
Emergency Equipment Cooling Water System Division II
Reactor Core Isolation Cooling System Sketch
RHR Service Water System Division 2 RHR Complex
AH
Procedures
23.208
RHR Complex Service Water Systems
27
ODE-20
Protected Equipment
71111.05Q Calculations
DC-4921 Vol 1
Appendix R Calculations
E
Corrective Action
Documents
19-27427
NRC Identified Transient Combustible Without Permit
10/01/2019
Drawings
Fire Protection Evaluation Reactor and Auxiliary Buildings
Second Floor Plan El. 613'-6"
Y
Fire Plans
FP-RB-1-7B
Reactor Building South Control Rod Drive (CRD) and
Railroad Bay Area, Zone 7
FP-RB-2-10A
Reactor Building Emergency Equipment Cooling Water
North, Zone 10, El. 613' 6"
FP-RHR-1-14-EDG
RHR Complex EDG 14 Room El 590' 60"
Miscellaneous
EF2-PRA012
Fermi 2 Internal Flood Analysis Notebook
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
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Heat Exchangers
19-27521
Unexpected Increase in Div 1 EECW Heat Exchanger
Differential Pressure After Recent Swap
10/03/2019
Work Orders
49005284
Perform 24.208.03 Division 2 EESW and EECW Makeup
Pump and Valve Operability Test (Section 5.1)
03/27/2019
49538124
Perform 24.208.02 Division 1 EESW and EECW Makeup
Pump and Valve Operability Test (Section 5.1)
06/06/2019
49725438
Perform 24.208.03 Division 2 EESW and EECW Makeup
Pump and Valve Operability Test (Section 5.1)
06/25/2019
50361462
Perform 24.208.02 Division 1 EESW and EECW Makeup
Pump and Valve Operability Test (Section 5.1)
09/05/2019
Calculations
DC-0182 Volume I
RHRSW Mechanical Draft Cooling Towers - Post LOCA
Analysis of UHS
G
DC-0182 Volume VI
RHRSW Mechanical Draft Cooling Towers - Heat Load
After A Design Basis Tornado
C
DC-5474
Waterhammer Analysis for the RHR Service Water
System
DC-5804
DGSW Design Basis Requirements
E
DC-6121
Design Basis for RHR Heat Exchanger Thermal
Performance Test Criteria
B
Calibration
Records
Calibration
Specification Sheet
Emergency Diesel Generator (EDG) 12 Air Temperature
Thermometer
Calibration
Specification Sheet
Emergency Diesel Generator (EDG) No. 13 Service Water
Pump 'B' Water Flow Low
Corrective Action
Documents
14-22832
Acceptance Criteria not met for 47.205.01 during RFO-16
03/26/2014
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
Uncertainty of 47.205.01 from RFO-17 for Case 2
Evaluation
11/06/2015
16-21036
Increase in EDG 13 Heat Exchanger Tubes Blocked
2/04/2016
16-24183
2016 NRC UHS Inspection - Inconsistent Work
05/19/2016
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documentation of RHR Reservoir Inspections
16-26238
2016 Generic Letter (GL) 89-13 Program Health Report
Tracking
08/08/2016
16-27634
NRC Violation - Inadequate Test Procedure Used for
Measuring and Determining Average Silt Levels in the
Service Water Reservoir
09/26/2016
17-00221
EDG 13 DGSW Flow Transmitter Reading High
01/21/2017
17-21233
Operations Shift 4 Crew Learning Opportunity - Identified
EDG 13 DGSW Flow High but Didn't Write a CARD
2/12/2017
18-20572
Excessive Build-up of Grime, and Sludge on Outside of
the Tube Bundle
01/22/2018
Corrective Action
Documents
Resulting from
Inspection
19-28289
2019 NRC Triennial UHS Inspection: Evaluate Effect of
Failed Post-Calibration Check of Ultrasonic Flow Meter on
47.205.01 Performed 11/11/2015
10/30/2019
19-28291
2019 NRC Triennial UHS Inspection: Typographical Error
in DC-0182 Vol I
10/30/2019
19-28324
2019 NRC Triennial UHS Inspection: Average Silt
Accumulation in UHS Reservoir was not Calculated in WO 47534163
10/31/2019
19-28350
2019 NRC Triennial UHS Inspection: RHR Heat
Exchanger Data Sheet Enhancements
11/01/2019
19-28351
2019 NRC Triennial UHS Inspection: Heat Exchanger
Shell Side Cleanliness Impacts
11/01/2019
19-28353
EDG Air Coolant Temperature - DC-5804 Vol I
Discrepancy
11/01/2019
19-28482
2019 NRC Triennial UHS Inspection: Proto-HX Mass Flow
Calculation
11/06/2019
Drawings
Diagram Residual Heat Removal (R.H.R) Division I
BP
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
Walkdown
10/08/2014
NDE Reports
27138
Eddy Current Preliminary Report
10/04/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
23.208
RHR Complex Service Water Systems
26
23.307
Emergency Diesel Generator System
28
24.307.36
DGSW, DFOT and Starting Air Operability Test EDG 13
MES54
Heat Exchanger Component Monitoring Program
7A
Work Orders
18-20990
2/05/2018
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
Operability
04/23/2016
2610300
Perform 24.307.36 DGSW, DFOT & Starting Air
Operability Test EDG 13
07/26/2016
43114139
Perform 24.307.36 DGSW, DFOT & Starting Air
Operability Test EDG 13
10/26/2016
44307098
Perform 24.205.05 Division 1 RHRSW Pump & Valve
Operability
05/09/2017
44348532
Calibrate EDG 13 Service Water Flow Loop
07/26/2017
44813323
Perform 24.307.36 DGSW, DFOT & Starting Air
Operability Test EDG 13
07/26/2017
45376325
Perform 24.307.36 DGSW, DFOT & Starting Air
Operability Test EDG 13
11/06/2017
46513309
Perform 24.205.05 Division 1 RHRSW Pump & Valve
Operability
05/09/2018
47053547
Perform 24.205.05 Division 1 RHRSW Pump & Valve
Operability
07/17/2018
47534163
License Renewal REQ'D Perform Div 2 RHR Reservoir
Zebra Mussel and Ball Valve Inspection Dive
01/15/2019
47788625
Perform 24.307.36 DGSW, DFOT & Starting Air
Operability Test EDG 13
10/31/2018
48505873
Perform 24.307.36 DGSW, DFOT & Starting Air
Operability Test EDG 13
01/27/2019
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
Procedure
Type
Designation
Description or Title
Revision or
Date
Operability Test EDG 13
272520
Perform 24.307.37 DGSW, DFOT & Starting Air
Operability Test-EDG 14
05/01/2019
50014288
Perform 24.307.37 DGSW, DFOT & Starting Air
Operability Test-EDG 14
07/30/2019
50480923
Perform 24.307.32 EDG No. 13 24 Hour Run Followed by
Hot Fast Restart
10/23/2019
Corrective Action
Documents
CARD 17-29439
Significant Arcing in A RRMG Set Exciter Brushes
11/27/2017
CARD 18-26702
NRC Concern - Potential Lack of Timeliness for
Reportability Assessment with Seismic Recorder
09/05/2018
CARD 18-30363
Mispositioned Control Rod while in Mode 4
2/24/2018
CARD 19-22208
Mispositioned Component: Ops Shift 5 CLO - Valve
Found Out of Position During System Fill and Vent
03/22/2019
CARD 19-23136
License Operator Medical-Missed 30-day Notification as
Required by 10 CFR 50.74
04/24/2019
CARD 19-25407
Operator Licenses Not Terminated
07/17/2019
CARD 19-25407
NRC not Notified within 30 Days of Operator License
Termination
08/21/2019
CARD 19-25588
Instructor Presented Modified Training Material in NOR
[Nuclear Operator Requalification]
07/24/2019
CARD 19-26372
NRC Exam Security Compromise for 2019 License
Operator Biennial Exam during Validation
08/23/2019
CARD 19-27233
Missed Emergency Classification During a Simulator
Exam
09/25/2019
Root Cause
Evaluation (RCE) for
CARD 17-29439
RCE for CARD Regarding A RRMG Set Arcing
Engineering
Evaluations
NTWI [Nuclear
Training Work
Instruction] 1.22
Cycle 20 Simulator Core Model Performance Testing
11/20/2018
SM 5
2018 Simulator Operating Limit and Real Time Test
2/15/2018
SM 6
2018 Simulator Steady State Operations Performance
Test
2/17/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SM 7
2018 Simulator Operations Procedures Performance Test
2/17/2018
SM 8
2018 Simulator Malfunction Performance Test
2/17/2018
SM 9
2018 Simulator Initial Conditions Performance Test
2/14/2018
Miscellaneous
CR 6330
Malfunction MFE062 - Loss of 4160 V ESF Bus 65F was
Stopped
01/04/2019
CR 6331
24.404.03 rev. 47 - During Performance of SGTS Oper.
test, valves T4600-F410 and T4600-F407 were Outside
the New Stroke Time Requirements
11/26/2018
CR 6334
24.138.02 Stroke Time for B3100-F014A not Withing IST
Limits
11/28/2018
CR 6336
24.202.01 HPCI Pump and Valve operability Test at 1025
psi. Valve stroke times outside of acceptable limits for
E4100-F029/F054/F053. Stroke time requirements
changes since previous surveillance.
2/07/2018
CR 6458
N6100 Condenser and Auxiliaries - Comparator for MTG
Trip Set at 1425 rpm; included 75 rpm Internal Hysteresis
that was not Appropriate
080/02/2019
JP-OP-315-0105-
181
Manually Initiate Low-Low Set - Alt Path
JP-OP-315-0158-
2
Loss 64C and EDG 12 Fails to Start
JP-OP-802-4101-
2
Obtain and Interpret Electrical Drawings
JP-OP-802-4101-
531
Thermal Limit Verification (MAPRAT) - SRO
NANT-18-0239
Effectiveness Report on Operator Proficiency Training
2/21/2018
Training Program
Description -
Licensed Operator
Requalification
Attachments 3A-D
Licensed Operator Requalification Evaluation Forms for
Simulator Exams Conducted on 10/1/2019
10/01/2019
Procedures
MGA13
Fermi Medical Requirements
MGA25
Inprocessing, Outprocessing, and Change of Vendor
MNT18
Conduct of Operations Training Manual
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NTWI 1.16
Examination Safeguards and Controls
NTWI 1.20
Simulator Fidelity
NTWI 1.23
Licensed Operator Requalification Exams
NTWI 1.25
Licensed Operator Medical Work Processes
Nuclear Licensing
Work Instruction
0053
Requirements for NRC Operator License Letters to the
NRC
ODE [Operations
Department
Expectation]-5
Operations Roles and Responsibilities
ODE-8
Administrative Guidelines and Desk Instructions
Self-
Assessments
NANT-19-0114
Formal Self-Assessment Report (Licensed Operator
Requalification Program)
08/28/2019
71111.11Q Corrective Action
Documents
19-28403
Loss of SJAE #3 Followed by Degrading Condenser
Vacuum
10/23/2019
Miscellaneous
LP-OP-202-1891
Emergency Action Levels for Operations
Procedures
20.125.01
23.125
Condenser Vacuum System
ARP 6D1
SJAE System Trouble
Classification of Emergencies
2C
Corrective Action
Documents
18-26173
Decreasing Trend in Both Div 1 and Div 2 Reference Leg
Backfill Flow
08/15/2018
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
Reference Leg Backfill System and Remove Limit if
Appropriate
2/26/2018
19-20916
B21P408A Nuclear Boiler Div 1 RPV Water Level
Reference Leg Backfill Trending Low
2/07/2019
19-25752
Adjustment of Div 2 Reference Leg Backfill Based on
Current Flow Trend
07/31/2019
19-26302
Div 2 Reference Leg Backfill Current Flow Trend
08/21/2019
19-27379
T4100-F014 Exhaust Damper Failed to Close when
Exhaust Fan was Shutdown
09/29/2019
19-27726
Damper Linkage Bushings Show Indications of Wear
10/10/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
19-27741
Inconsistent Work Order Instruction Results in Incorrect
Torque Values Being Applied
10/10/2019
19-29033
T4100F025 RB Center Supply Fan Shutoff Damper
Failure / Delayed Closure
11/25/2019
19-29081
RBHVAC not Maintaining RB Pressure
11/25/2019
19-29395
Div 1 Reference Leg Backfill is High Out of Specification
for Operator Rounds
2/08/2019
19-29705
RBHVAC Exhaust Fan Modulating Damper Failure
2/18/2019
19-29708
RBHVAC Center Supply Fan Shutoff Damper Failed to
Close
2/18/2019
Drawings
Auto Temp Control System Control Panel H21P527,
P527A, P528, and P529 Control Diagram Ventilation
Flow Diagram Reactor and Auxiliary Building Ventilation
System
P
Flow Diagram Reactor and Auxiliary Building Ventilation
System
D
Diagram Standby Gas Treatment and Primary
Containment Purge System Reactor Building
AI
Miscellaneous
Design Basis
T41-00
Reactor Auxiliary Building Ventilation System
04/23/2019
MES51
Chaper 51 - Preventive Maintenance Program
MMM08
Material Shipping, Handling, and Storage
MMR Appendix E
Maintenance Rule SSC Specific Functions
O & WMI-014
Outage and Work Management Instruction
Procedures
46.000.046
Operation of the Reactor Reference Leg Backfill System
Work Orders
46727448
Replace Filter Cartridges in Div 1 RPV Water Level
Instrumentation Backfill
09/30/2018
Perform Mini Periodic MOV Inspection (E2150-F036B)
2/17/2019
Corrective Action
Documents
19-28364
Generator Stator Lift NRC Question
11/01/2019
19-28371
NRC Question Concerning Presence of 32.RIG.18
Communication Plan
11/01/2019
19-28797
During Electric Fire Pump Run Pump Displayed Excessive
Vibrations
11/15/2019
19-28805
Request Evaluation to Determine if a Proper Risk
11/16/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Assessment was Performed During the Work Planning
Process for WO 50976710
Miscellaneous
50.59 Screen
19-0037
MTG Replacement
A
Black and Veatch
Calculation 193823
1001
Turbine Building Structural Evaluation [Confidential]
Black and Veatch
Evaluation 193823
1000
Fermi 2 Evaluation of Heavy Loads Impacts during Main
Generator Replacement [Proprietary]
Design Information
Transmittal
U21-190813-001
Barnhart Structural and Rigging Design Parameters
Enterprise Risk Plan
80000
Risk Associated with Replacement of the Main Turbine
Generator
Fermi 2
Shift Manager Daily Alignment Meeting
11/26/2019
Infrequently
Performed Test or
Evolution Briefing
Sheet
Main Generator Stator Lift
LCO 2019-0415
Replace Divison 2 NIAS Control Air Dryer Relay
11/22/2019
LCO 2019-0429
Division 2 Switchgear Room Cooler Power Supply
Inspection
11/25/2019
LCO 2019-0483
P5002 Inspect and Adjust D2 CAC Room Cooler Belts
11/25/2019
MES56
Engineering Risk Assessment, Job Briefing, and Product
Quality Review
MMA26
Troubleshooting
7A
MMR Appendix H
On-Line Core Damage Risk Management Guidelines
MMR12
Equipment Out of Service Risk Management
20A
MWC18
Emergent Issues Response
3A
ODE-16
Risk Assessment and Operation of Phoenix
ODE-20
Protected Equipment
Stator Offload Lift
Plan/Communication
Per Procedure 32.RIG.18, Guidelines and Practices for
the use of Hoisting and Rigging Equipment
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Plan
TE-ANL-19-043
PSA Risk Associated with the Lift of Generator Stator per
TE-N30-19-028
Generator Stator Haul Path Evaluation
B
Procedures
20.000.03
Turbine Building Flooding
2.716.01
Turbine Building Crane Operation
2.RIG.18
Guidelines and Practices for the Use of Hoisting and
Rigging Equipment
15A
Work Orders
53495247
Lift Plan per Procedure 32.RIG.18 [Proprietary]
Corrective Action
Documents
19-24737
EDG 14 Surging in Idle During Surveillance Run
06/24/2019
19-25713
E1156-C001D, Div 2 RHRSW MDCT Fan D, Tripped
when Placed in High Speed
07/30/2019
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
Setting Out of Tolerance
09/20/2019
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
24.208.03 Step 5.1.28
09/25/2019
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
Torque Values Being Applied
10/10/2019
19-27743
Failed PMT: As Left Thermography Following Hot Spot
Repair
10/10/2019
19-27748
Revise Tech Spec Bases for LCO 3.7.4
10/11/2019
19-28481
Acrid Odor RCIC Barometric Condenser Vacuum Pump
Motor
11/05/2019
19-28721
Human Performance Error While Performing Surveillance
44.030.263 ECCS ADS L3 and L8 Div 1 Ch A Functional
11/13/2019
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
Diesel Fire Pump Inoperable when Battery Low Level
Identified
2/04/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
19-29325
Temp Diesel Fire Pump
2/05/2019
Drawings
Reactor Core Isolation Cooling (RCIC) System Sketch
Emergency Diesel Generator System
BI
Diesel Generator System Division II RHR Complex
Engineering
Changes
Temporary
Modification
19-0018
Winterization of Temporary Alternate Diesel Fire Pump
A
Engineering
Evaluations
TMSA-06-0067
Evaluation of the No. of MDCT Fans Required for Decay
Heat Removal Success (CARD 06-26273)
2/18/2006
Miscellaneous
Design Basis
R30-00
I
E51-00
Reactor Core Isolation Cooling System Design Basis
Document [proprietary]
Risk Management
Plan (Rev 0)
Electric Fire Pump/Diesel Fire Pump Diving
11/18/2019
Procedures
34.307.001
Emergency Diesel Generators - Inspection and Preventive
Maintenance
44.030.263
ECCS - Reactor Vessel Water Level (ADS Level 3 and
Feedwater / Main Turbine Level 8), Division 1, Channel A
Functional Test
Corrective Action
Documents
18-26318
New Fuel Transfer Crane Cable and Sheave Damaged
08/21/2018
18-27722
New Fuel Transfer Crane Cable and Sheave Damaged
10/10/2019
19-27473
Impact of Padding Installed New Fuel Inspection Stand
may not have been Evaluated
10/02/2019
19-27990
Evaluate New Fuel Inspection Stand Testing and
Inspection Requirements
10/21/2019
19-28020
Safety Concern with Channel Handling Winch Inspection
10/22/2019
Miscellaneous
Design Change
Package 80128
Fuel Uprighting Stand Modification
Work Orders
55442826
Modify Fuel Uprighting Machine 19-27432
11/04/2019
Corrective Action
Documents
19-27229
P44-F400B Did Not Fail in the Full Open Direction During
24.208.03 Step 5.1.28
09/25/2019
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
Procedure
Type
Designation
Description or Title
Revision or
Date
19-27567
Inner Railroad Airlock Door Rail Plugs are Degraded
10/05/2019
19-27588
Suspected Hydraulic Lock on East Outer Railroad Airlock
Door
10/07/2019
Drawings
Control System (DCS-FW) External Connections
H
Feedwater System
BO
Reactor Water Clean-Up Filter Demineralizers
U
Standby Feedwater System Functional Operating Sketch
N
Emergency Equipment Cooling Water (Division II)
BB
Fire Protectin Functional Operating Sketch
BY
I-2331-07
Schematic Diagram Gland Sealing Steam Exhauster (E &
W)
G
Engineering
Changes
EDP 37673
Elimination of Main Steamline Isolation Valve Closure and
Scram Functions of Main Steamline Radiation Monitor
Miscellaneous
MMA11
Valve Testing, Enclosure B
VMC2-105
CCI Drag Valve Vendor Manual
B
Procedures
24.107.03
SBFW Pump and Valve Operability and Lineup
Verification Test
24.207.09
Division 2 EECW Pump and Valve Operability Test
34.307.001
Emergency Diesel Generators - Inspection and Preventive
Maintenance
35.139.006
CCI Drag Valve and Actuator Maintenance
43.000.010
IST Check Valve Inspection Procedure
ARP 2D13
Fuel Pool Cooling Trouble
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
Degradation
10/21/2019
51059456
Perform 28.504.09 Electric Fire Pump Monthly Operability
Test
11/22/2019
51441579
Calibrate RWCU Filter Demin 'B' Effluent Flow Loop
09/30/2019
2071933
EDP 37673 Elimination of Main Steamline Isolation Valve
Closure and Scram Function of Main Steamline Radiation
Monitor Post Maintenance Test for 4D32
10/25/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
208989
44.080.605 East and West Gland Seal Exhauster /
Mechanical Vacuum Pump Logic System Functional Test
10/23/2018
55304662
EECW Div 2 HX B001B/B001D SW Outlet Temp Control
10/05/2019
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 -
Fast Start
10/02/2019
55419277
Blow Down Pneumatic Locking Bar Lines on Exterior RR
Air Lock Doors
10/07/2019
55799429
Troubleshoot/Repair Electric Fire Pump
11/16/2019
Procedures
24.000.02
Shiftly, Daily, and Weekly Required Surveillances
157
24.307.17
Emergency Diesel Generator 14 - Start and Load Test
Work Orders
50698481
Perform 550 kW N Diesel S001A Functional Test 887200
10/12/2019
50943437
Perform 550kW N+1 Diesel S001B Functional Test
887201
11/07/2019
51363396
Perform 24.307.17 Sec-5.1 EDG 14 Start and Load Test -
Slow Start
2/23/2019
Corrective Action
Documents
18-23507
18-23507 Explore Alternate Siren Testing for NRC PI data
05/02/2018
Miscellaneous
FEMA Approval Letter for Fermi 2 ANS Design Report,
Revision 1
11/30/2015
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
Report
255232R
Federal Signal Corporation 2001SRNB Electro-
09/28/2004
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Mechanical Siren
SS2000D -
255318G1
SS2000D Controller/Encoder Installation and Operation
Instructions
10/07/2003
Procedures
Fermi 2 Radiological Emergency Response Preparedness
Plan
Alert and Notification System Operation and Maintenance
Corrective Action
Documents
18-21396
RERP Callout Automated System has Limited
Functionality
2/19/2018
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
Acknowledgement of On-Call ERO Duty
11/30/2018
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
2/20/2012
Fermi 2 ERO Team List
08/31/2019
ERO Team Training and Qualification Records
(Sample - 10)
10/03/2019
Procedures
Fermi 2 Radiological Emergency Response Preparedness
Plan; Section B, Emergency Response Organization
Emergency Notifications
Drills and Exercises
RERP Training Program
Emergency Call Out System - Testing and Maintenance
6A
ECOS Test Reviews (Quarterly)
09/01/2017 -
09/01/2019
QP-ER-670
Radiological Emergency Response Preparedness
Selection, Training and Qualification Program Description
Miscellaneous
CFR 50.54Q Compliance Review Personnel
Qualifications Spreadsheet
06/24/2019
2018-04E
CFR50.54(q) Evaluation - RERP Plan Change, Plant
Radio System Upgrade
08/16/2018
2018-06E
CFR50.54(q) Evaluation - RERP Plan Change,
07/18/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Operations Support Center Relocation
2018-10S
CFR50.54(q) Screen - RERP Plan Change, Central
Alarm Station Relocation
08/11/2018
2018-35S
CFR50.54(q) Screen - RERP Plan Change, Operations
Support Center Relocation
07/18/2018
2018-36S
CFR50.54(q) Screen - RERP Plan Change, Plant
Radio System Upgrade
08/06/2018
Procedures
Fermi 2 Radiological Emergency Response Preparedness
Plan
Fermi 2 Radiological Emergency Response Preparedness
Plan
CFR50.54(q) Screens and Evaluation
0A
Corrective Action
Documents
17-27716
NQA Audit 17-0112 Deficiency - Uncontrolled and
Outdated RERP Documents in the EOF
09/18/2017
17-27788
NQA Audit 17-0112 Recommendation -Training
Enhancements for ERO Positions
09/20/2017
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
2/13/2019
19-21964
Missed and Untimely Classification in the Simulator
03/13/2019
Miscellaneous
Quarterly Operations Support Facility ERF Testing and
Maintenance Records
09/01/2017 -
09/01/2019
Exercise and Drill Evaluation Reports (Sample)
09/01/2017 -
09/01/2019
Quarterly Control Room ERF Testing and Maintenance
Records
09/01/2017 -
09/01/2019
Quarterly Emergency Operations Facility ERF Testing and
Maintenance Records
09/01/2017 -
09/01/2019
Quarterly Technical Support Center ERF Testing and
Maintenance Records
09/01/2017 -
09/01/2019
Emergency Preparedness Letters of Agreements with Off-
Site Response and Support Organizations
09/01/2017 -
09/01/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
KLD-TR-1030
Fermi 2 Nuclear Power Plant 2018 Population Update
Analysis
09/29/2018
Procedures
Classifications
2C
Emergency Notifications
2C
Emergency Call Out - Backup Method
Equipment Important to Emergency Response (EITER)
CFR 50.54(q) Screens and Evaluations
0A
Public Education and Information
Self-
Assessments
Audit Report 17-
0112
Quality Assurance Audit of Emergency Preparedness
Program
09/26/2017
Audit Report 18-
0111
Quality Assurance Audit of the Emergency Preparedness
Program
09/18/2018
Miscellaneous
2019 Fourth Quarter Table Top Drill, DTE Electric
Company, Fermi 2
10/03/2019 -
10/24/2019
Procedures
Classification of Emergencies
2C
Corrective Action
Documents
18-29556
Dose Rate Increase Creating New Locked High Radiation
Area on RB-2
11/28/2018
19-20128
Higher Than Anticipated Dose Rates during RWCU Fill
and Vent Activities
01/06/2019
19-20981
Locked High Radiation Area Conditions Found in the
Torus Room Sub-Basement Reactor Water Clean Up
Return Line
2/09/2019
19-22778
Elevated Dose Rates in the Auxiliary Building T-Room,
Requiring the Posting of a High Radiation Area
04/14/2019
Procedures
68.000.003
Radiological Air Sampling
1A
Radiation
Surveys
00116-A19
Reactor Core Isolation Cooling Run
05/10/2019
252-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
Procedure
Type
Designation
Description or Title
Revision or
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
Permits (RWPs)
191020
Emergent Issues Tasks
191027
E41 and E51 System Maintenance, Inspections,
Surveillance and Test Runs
191050
Reactor Water Clean Up Pump Seal Repair/Replacement
191051
Reactor Water Clean Up Phase Separator Room Entry
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
Performance (DEP)
07/01/2018 -
06/30/2019
Performance Indicator Data Sheets - Alert and Notification
System (ANS)
07/01/2018 -
06/30/2019
Performance Indicator Data Sheets - Emergency
Response Organization (ERO) Drill Participation
07/01/2018 -
06/30/2019
Corrective Action
Documents
19-20353
Mispositioned Component: APRM 3 not Bypassed during
46.604.001
01/16/2019
19-20355
Cognitive Trend - Operations Mispositioning Events
01/16/2019
19-20897
Security CLO - Plant Equipment Bumped during FOF
Drills
2/07/2019
19-21941
Mispositioned Component: Missed Procedure Step when
Placing CFD C in Service
03/13/2019
19-22208
Mispositioned Component: Ops Shift 5 CLO - Valve Fount
out of Position during System Fill and Vent
03/22/2019
19-22351
Evaluation of Operations Plant Status Control
Performance
03/27/2019
19-22376
2019 Plant Status Control Committee (PSCC) Meeting
Actions
03/28/2019
19-22799
DFP Jacket Cooler Inlet Alt Stnr Outlet Isolation Valve was
Found in Closed Position
04/15/2019
19-23602
INPO Evaluation Plant Status Control
09/03/2019
19-23623
Mispositioned Component: Discovered P5000F1013A not
in Correct Positions
05/10/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
19-23859
Potential Mispositioned Component: Unexpected Caps
Left Installed on RB SPING Lines
05/20/2019
19-24681
Document Assessment of IN 2019-03
06/21/2019
19-25901
Mispostioned Component: Rosemount Readout Found
Installed in Rosemount Trip Unit in H21P087 Section Z1
08/05/2019
19-26203
Mispositioned Component: Operations Shift 5 CLO - Step
not Performed in 23.300
08/16/2019
19-26858
Plant Status Control Committee Input to Nuclear Safety
Culture Monitoring Panel
09/12/2019
19-26860
Effectiveness Review Measures will not be Met
09/12/2019
19-27742
Mospositioned Component P6100F020B South Boiler
Steam Relief Valve, While Performing 27.142.01 Auxiliary
Boiler Trip and Safety Valve Test for the South Auxiliary
Boiler
10/10/2019
19-28157
Mispositioned Component - S Aux Boiler Atomizing Air
Isolation Valve Found Open during Reference Leg Filling
10/25/2019
19-28217
Plant Status Control Committee - Maintenance Plant
Status Control Precursors
10/28/2019
19-28218
Plant Status Control Committee - Operations Plant Status
Control Precursors
10/28/2019
19-28721
Human Performance Error while Performing Surveillance
44.030.263 ECCS ADS L3 and L8 Division 1 Channel 'A'
Functional Test
11/13/2019
19-29371
HCU 14-07: Leak Coming from the Manifold Filter Plug for
the C11F120 FCV
2/07/2019
19-29423
Chemistry Performance of SPING Weekly Surveillance
without Signing on with the Tagging Center
2/09/2019
Miscellaneous
MOP05 Operations
Conduct Manual
Control of Equipment
ODE-7 Operations
Department
Expectation
Configuration Control
Corrective Action
Documents
19-25713
E1156-C001D, Div 2 RHRSW MDCT Fan D, Tripped
When Placed in High Speed
07/30/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
19-25722
Blown Fuse on 'D' RHR MDCT Fan High Speed Breaker
07/30/2019
Engineering
Evaluations
TMSA-06-0067
Evaluation of the No. of MDCT Fans Required for Decay
Heat Removal Success (CARD 06-26273)
2/18/2006
Miscellaneous
LER 2019-003
Secondary Containment Declared Inoperable due to
Opening Both Airlock Doors
LER 2019-004
Division 2 Mechanical Draft Cooling Tower Fan "D"
Tripped when Placed in High Speed due to a Blown Fuse
LER 2019-005
Secondary Containment Pressure Exceeded Technical
Specification due to Reactor Building HVAC Damper
Malfunction
00