IR 05000341/2022001
| ML22126A044 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 05/09/2022 |
| From: | Nestor Feliz-Adorno Reactor Projects Region 3 Branch 4 |
| To: | Peter Dietrich DTE Electric Company |
| References | |
| IR 2022001 | |
| Download: ML22126A044 (28) | |
Text
SUBJECT:
FERMI POWER PLANT, UNIT 2 - INTEGRATED INSPECTION REPORT 05000341/2022001
Dear Mr. Dietrich:
On March 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Fermi Power Plant, Unit 2. On April 19, 2022, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
Two findings of very low safety significance (Green) are documented in this report. Two of these findings involved violations of NRC requirements. We are treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violations or the significance or severity of the violations 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 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.
May 9, 2022 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, Néstor J. Féliz Adorno, Chief Branch 4 Division of Reactor Projects Docket No. 05000341 License No. NPF-43
Enclosure:
As stated
Inspection Report
Docket Number:
05000341
License Number:
Report Number:
Enterprise Identifier:
I-2022-001-0056
Licensee:
DTE Electric Company
Facility:
Fermi Power Plant, Unit 2
Location:
Newport, MI
Inspection Dates:
January 01, 2022 to March 31, 2022
Inspectors:
T. Ospino, Acting Senior Resident Inspector
T. Taylor, Resident Inspector
J. Bozga, Senior Reactor Inspector
T. Briley, Project Engineer
J. Cassidy, Senior Health Physicist
A. Dahbur, Senior Reactor Inspector
E. Fernandez, Reactor Inspector
M. Holmberg, Senior Reactor Inspector
M. Jones, Reactor Inspector
L. Kozak, Senior Reactor Analyst
R. Ng, Project Engineer
A. Shaikh, Senior Reactor Inspector
D. Turpin, Reactor Engineer
Approved By:
Néstor J. Féliz Adorno, Chief
Branch 4
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Fermi Power Plant, Unit 2, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
Failure to Establish Periodic Inspection and Maintenance of the Alternate Diesel Fire Pump Engine Fuel-Water Separator Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000341/2022001-01 Open/Closed
[H.4] -
Teamwork 71111.12 A self-revealed Green finding and associated NCV was identified when the licensee failed to establish periodic inspection, maintenance, and testing procedures for the alternate diesel fire pump (ADFP) in accordance with MES35, Fire Protection. Specifically, the licensee did not establish a procedure to routinely check the water level of the ADFP engine fuel water separator and drain water when needed to ensure continued functionality of the ADFP.
Failure to Identify an Adverse Containment Isolation Valve Stroke Time Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000341/2022001-02 Open/Closed
[H.12] - Avoid Complacency 71111.15 A Green finding and an associated violation of 10 CFR 50, Appendix B, Criterion XVI,
"Corrective Actions," was self-revealed when the drywell equipment drain sump outboard containment isolation valve G1100F019 failed its Inservice Testing (IST) stoke time test on January 2, 2022. Specifically, the licensee discovered the valve had a slow close stroke time.
Consequently, they increased the valve testing frequency with the intent of promptly identifying and correcting an adverse closed stroke time. However, the licensee failed to stroke time test the valve in accordance with the increased frequency in November and December 2021.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000341/2021-003-00 LER 2021-003-00 for Fermi 2, High Pressure Coolant Injection Inoperable due to Contact Oxidation 71153 Closed
PLANT STATUS
The plant began the inspection period at or near 58 percent rated thermal power in preparation for a planned refueling outage. On February 4, 2022, during a planned power reduction to start the refueling outage, the plant experienced a perturbation in the feedwater system which resulted in a reactor scram. Following stabilization after the scram, the plant commenced a cooldown to commence outage activities. Fermi remained shut down for the remainder of the inspection period due to the RF21 outage.
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 activities described in IMC 2515, Appendix D, Plant Status, conducted routine reviews using IP 71152, Problem Identification and Resolution, observed risk significant activities, and completed on-site portions of IPs. 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
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from extreme cold temperatures and high winds on January 11, 2022.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Hydraulic control units (HCUs) 10-39 and 30-43 following replacement and testing during the week ending January 8, 2022
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) High pressure coolant injection (HPCI) room during the week ending March 19, 2022
- (2) Reactor building 1 - north, during the week ending March 19, 2022
- (3) Reactor building 1 - south, during the week ending March 19, 2022 Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Partial)
(1)
(Partial)
The inspectors evaluated the on-site response to small incipient fires that required discharge of portable extinguishers. One occurred due to an electrical fault in a breaker, the other in the drywell. Since other elements of the inspection procedure were not observed (namely, actual observation of fire brigade performance) the sample will remain open.
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Disturbed flood penetrations in the reactor building during elevator modification during the week ending January 22, 2022
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Partial)
The inspectors evaluated readiness and performance of:
(1)
(Partial)
The inspectors evaluated the condition of the Division 1 residual heat removal service water (RHRSW) heat exchanger during planned licensee inspections. The sample continued into the second quarter so as to compare with the results of the Division 2 RHRSW heat exchanger inspections.
71111.08G - Inservice Inspection Activities (BWR)
BWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding
Activities (IP Section 03.01)
- (1) The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from February 7th, 2022 to March 7th, 2022:
03.01.a - Nondestructive Examination and Welding Activities.
1. Ultrasonic examination (UT) of reactor pressure vessel (RPV) long shell
weld 15-308A
2. Liquid penetrant examination (PT) of fillet weld on FW-P44-3057-68$C1,
and 63$C3
3. Welding of socket weld for EDP 80124 drywell cooler 13 (WO # 58368468)
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 turnover following a reactor scram on February 5, 2022. Additionally, the inspectors observed operator response to an unplanned trip of several breakers on safety-related 480V bus 72B, concluding the week ending February 12, 2022.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples 1 Partial)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) HFA relays following failure of a circuit described in CARD 21-24863 during the week ending March 12, 2022
- (2) Alternate diesel fire pump (3)
(Partial)
Division 1 and Division 2, 120 volt alternating current NOVA inverters
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
- (1) Quality control questions regarding a safety-related valve stem procurement; and warehouse temperature issues during the week ending March 31, 2022
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Unplanned inoperability of emergency diesel generator 12 due to failed standby lube oil pump on January 12, 2022
- (2) Main condenser tube leak identified on January 31, 2022
- (3) Feedwater heater to condenser pipe leak during the planned power reduction/post-scram the week ending February 12, 2022
- (4) Unexpected loss of 480V bus 72B-4C temporary power on February 14, 2022
- (5) Investigation and restoration of 480V bus 72EB breaker position 'D' following a small incipient fire on March 7, 2021
- (6) Loss of the reactor protection system (RPS) motor generator (MG) set 'A' on March 12, 2022
- (7) Trip of 480V bus 72B breakers unexpectedly during a surveillance during the week ending March 31, 2022
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples 1 Partial)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Potential issue with underground duct banks during the week ending January 29, 2022
- (2) Spurious reactor building heating ventilation and air conditioning (RBHVAC) isolation caused by the fuel pool exhaust radiation monitor failing downscale, with associated group isolation during the week ending March 12, 2022
- (3) Investigation of indications found when inspecting reactor vessel during the week ending March 19, 2022
- (4) Hydraulic control units found with wrong sized component in check valves during the week ending March 31, 2022
- (5) Missed inservice testing (IST) of the drywell equipment sump containment isolation valve, which had been placed on increased monitoring, during the week ending March 31, 2022 (6)
(Partial)
Vital power distribution 120 volt alternating current NOVA inverters R31K001 and B21K801B voltage and frequency out of tolerance as documented in CARD 22-22886 during the week ending March 9, 2022
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
(2 Samples 1 Partial)
- (1) Review of permanent modification RID 89937, Replace ABB undervoltage relay part number 211R1175 with part number 411R1175, on February 22, 2022
- (2) Interim alarm system during installation of new control room alarm system during the week ending March 19, 2022 (3)
(Partial)
Review of piping supports for new RHRSW and emergency equipment service water (EESW) piping during the week ending March 31, 2022
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (9 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
- (1) Scram time testing of two control rods following HCU work during the week ending January 8, 2022
- (2) Emergency Diesel Generator (EDG) 11 lube oil heater/control circuit repairs during the week ending January 22, 2022
- (3) West fuel pool cooling and cleanup pump during the week ending February 5, 2022
- (4) SRM 'B' during the week ending February 12, 2022
- (5) Failed relay associated with 480V safety-related bus 72EA on February 26, 2022
- (6) Main steam isolation valve (MSIV) actuator replacements during the week ending March 12, 2022
- (7) E1150F024A overthrusting repair during the week ending March 26, 2022 (8)480V safety-related bus 72EB-2D following repairs after fire during the week ending March 26, 2022
- (9) RHRSW/EESW replacement pipe during the week ending March 31, 2022
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial)
The inspectors evaluated Refueling Outage 21 activities from February 4, 2022, until the end of the inspection period. Major activities evaluated included review of the outage risk plan, shutdown/cooldown, drywell and torus entries, and movement of fuel. Since the outage was still in-progress at the end of the inspection period, the inspectors will continue the sample into the second quarter.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:
Surveillance Tests (other) (IP Section 03.01) (2 Samples)
- (1) Division 1 ECCS and loss of offsite power testing on February 7, 2022
- (2) Local leak rate test (LLRT) performed for penetration X-22 on February 28, 2022
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) As-found MSIV local leak rate test during the week ending February 5,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
- (1) Licensee surveys of potentially contaminated material leaving the radiologically controlled area (RCA), and workers exiting the RCA at drywell control point during a refueling outage
- (2) Licensee surveys of potentially contaminated material leaving the RCA, and workers exiting the RCA at turbine building control point during a refueling outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
- (1) Torus vent header repairs
- (2) Removal of local power range monitor (LPRM) bending tool from the reactor cavity
- (3) Removal of shoot-out steel from under vessel High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)
The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:
- (1) Division 1 residual heat exchanger room
- (2) Reactor water cleanup heat exchanger room
- (3) Under vessel access point Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Temporary Ventilation Systems (IP Section 03.02) (1 Sample)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) Temporary high-efficiency particulate air (HEPA) ventilation established under the reactor building head on the refuel floor
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees use of respiratory protection devices
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
- (1) January 1, 2021 - December 31, 2021 IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)
- (1) January 1, 2021 - December 31, 2021
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)
- (1) January 1, 2021 - December 31, 2021
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (1 Sample)
- (1) January 1, 2021 - December 31, 2021
===71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03) (1 Partial)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)
(Partial)
Inspection of the torus and vent header following recoating last refueling outage (sample continued into the second quarter)71153 - Follow Up of Events and Notices of Enforcement Discretion Event Followup (IP Section 03.01)===
- (1) The inspectors evaluated the immediate response to a reactor low water level scram during the power reduction leading into the refueling outage the week ending March 5, 2022
Event Report (IP Section 03.02) (1 Sample)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 2021-003 High Pressure Coolant Injection Inoperable due to Contact Oxidation (ADAMS Accession No. ML21363A084). 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 did not identify a violation of NRC requirements.
INSPECTION RESULTS
Failure to Establish Periodic Inspection and Maintenance of the Alternate Diesel Fire Pump Engine Fuel-Water Separator Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000341/2022001-01 Open/Closed
[H.4] -
Teamwork 71111.12 A self-revealed Green finding and associated NCV was identified when the licensee failed to establish periodic inspection, maintenance, and testing procedures for the alternate diesel fire pump (ADFP) in accordance with MES35, Fire Protection. Specifically, the licensee did not establish a procedure to routinely check the water level of the ADFP engine fuel water separator and drain water when needed to ensure continued functionality of the ADFP.
Description:
On February 7, 2021, an ADFP was installed via temporary modification (TM)21-0001 due to an equipment problem with the permanently installed diesel fire pump. The ADFP was in an outdoor environment with the normally water filled portions of the system (i.e., pump and associated piping) inside a temporary enclosure that was heated in the winter.
The ADFP engine and associated fuel supply were not enclosed by design and were subject to outdoor environmental conditions.
On January 7, 2022, the ADFP was removed from service for planned seasonal (cold weather) maintenance. Planned maintenance activities included replacement of the engine fuel system primary filter (i.e., fuel water separator). Upon removal of the ADFP engine fuel water separator, the filter element itself was found half-dry with a large piece of ice present at the bottom of the fuel water separator bowl. The licensee replaced the fuel water separator, primed the fuel system, and attempted to start the ADFP to inspect the fuel system for leaks.
The ADFP subsequently failed to start on January 7, 2022. Troubleshooting identified ice buildup in the fuel lines as the most likely cause. The ADFP was returned to service on January 14, 2022, which was within the allowable 14-day Technical Requirements Manual 3.12.2 required action completion time. The ADFP had started, and ran successfully during the previous weekly operability test on January 3, 2022.
Licensee procedure MES35, Fire Protection, required the fire protection program to consist of periodic inspection, maintenance, and testing of fire detection and protection systems.
TM 21-0001 included the manufacturer operation and maintenance manual (TM 21-0001.016), which included instructions for maintaining the fuel water separator. Too much water in the fuel water separator can lead to engine performance problems regardless of environmental conditions (e.g., summer or winter). However, the licensee periodic inspection, maintenance, and testing procedures did not contain provisions to routinely monitor for, or drain water if present from the ADFP engine fuel water separator as recommended by the manufacturer operation and maintenance manual.
Corrective Actions: The licensee revised procedure 28.504.02, Diesel Fire Pump Engine Weekly Operability Test, to include an inspection of the ADFP fuel water separator water level. The revised procedure specified to write a CARD if the ADFP fuel water separator water level was greater than 25 percent to allow draining of the water, and to declare the ADFP non-functional if the water level was greater than 50 percent water (regardless of environmental conditions).
Corrective Action References: CARD 22-20233
Performance Assessment:
Performance Deficiency: The licensee's failure to establish periodic inspection, maintenance, and testing procedures for the ADFP was not in accordance with procedure MES35, Fire Protection, and was a performance deficiency. Specifically, the licensee did not establish a procedure to routinely check the water level of the ADFP engine fuel water separator and drain water when needed to ensure continued functionality of the ADFP.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Equipment Performance 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 establish periodic inspection, maintenance, and testing procedures for the ADFP resulted in enough water accumulation in the ADFP engine fuel water separator to render the ADFP non-functional.
Significance: The inspectors assessed the significance of the finding using Appendix F, Fire Protection and Post - Fire Safe Shutdown SDP. In accordance with Step 1.4.3, Fire Water Supply, the inspectors determined that the finding was of very low safety significance (Green). Specifically, the electric fire pump was available to provide adequate fire water capacity for protection of equipment important to safe shutdown in the most limiting location onsite for the duration that the ADFP was non-functional.
Cross-Cutting Aspect: H.4 - Teamwork: Individuals and work groups communicate and coordinate their activities within and across organizational boundaries to ensure nuclear safety is maintained. Specifically, work groups did not communicate and coordinate during the ADFP modification review to ensure it was informed about the maintenance provisions included in the ADFP manufacturer operation and maintenance manual.
Enforcement:
Violation: Technical Specification 5.4.1.d requires written procedures to be established, implemented, and maintained covering fire protection program implementation. The licensee established MES35, Fire Protection, Revisions 12 and 13, as a fire protection program implementation procedure.
Contrary to the above, from February 7, 2021, to January 13, 2022, the licensee failed to implement a written procedure covering fire protection program implementation.
Specifically, the licensee did not implement procedure MES35, step 3.3.7. This step required, in part, periodic inspection and maintenance of fire protection systems. However, the licensee did not establish periodic inspection and maintenance to check the water level of the ADFP engine fuel water separator and drain water when necessary. As a result, on January 7, 2022, the ADFP was declared non-functional due to water in the ADFP engine fuel system.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Failure to Identify an Adverse Containment Isolation Valve Stroke Time Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000341/2022001-02 Open/Closed
[H.12] - Avoid Complacency 71111.15 A Green finding and an associated violation of 10 CFR 50, Appendix B, Criterion XVI, "Corrective Actions," was self-revealed when the drywell equipment drain sump outboard containment isolation valve G1100F019 failed its Inservice Testing (IST) stoke time test on January 2, 2022. Specifically, the licensee discovered the valve had a slow close stroke time.
Consequently, they increased the valve testing frequency with the intent of promptly identifying and correcting an adverse closed stroke time. However, the licensee failed to stroke time test the valve in accordance with the increased frequency in November and December 2021.
Description:
On April 2, 2021, during performance of Inservice Testing (IST) Surveillance 24.702.01, Miscellaneous Systems Valve Operability Test, the licensee discovered that the drywell equipment drain sump outboard containment isolation valve G1100F019 and drywell floor drain sump outboard containment isolation valve G1100F003 closing stroke time fell outside the IST limit of 34.0 seconds, and owner specified limit of 36.8 seconds. Specifically, the stroke times of G1100F019 and G1100F003 were 42.5 and 52.7 seconds, respectively.
Both valves were air-operated containment isolation valves (AOVs). Per Fermi Technical Requirement Manual Section 3.6, the maximum isolation times for these two automatic containment isolation valves were 60 seconds.
The licensee entered this issue into their corrective action program as CARD 21-22976. Per the 2012 Edition of the American Society of Mechanical Engineer (ASME) Operation and Maintenance (OM) Code, the licensee immediately declared the valves as inoperable, retested them, and performed an analysis to show that the valves were working correctly per subsequent stroke time measurements. The licensee determined that both valves were degraded but functional and the potential causes for the long stroke time likely were debris-related binding at the seat, or a sticking solenoid. The licensee placed both valves on an increase testing frequency (monthly) to ensure potential adverse closed stroke time trend was promptly identified and corrected.
On May 9, 2021, during performance of the increased frequency stroke time test for valve G1100F003, the licensee identified that the close stroke time was 1,020 seconds. The licensee immediately declared the valve inoperable and determined that the AOV solenoid was sticking. The licensee replaced the solenoid and established a new periodic replacement frequency for the solenoid. Since the replacement of the solenoid in May 2021, stroke time testing of valve G1100F003 has shown no degradation in the closing stroke time.
The licensee determined valve G1100F019 needed to remain on increased testing frequency until the refueling outage scheduled to start in February 2022 based on their review of stroke times. Specifically, the close stroke time of valve G1100F019 were 30.8, 29.7, 28.8, 30.3, 28.5 and 33.6 seconds in May, June, July, August, September, and October of 2021, respectively. The licensee added a work order to replace the solenoid associated with valve G1100F019 in the 2022 refueling outage. However, the licensee did not monitor the valve condition by failing to perform the increased frequency stroke time test in November and December 2021. On January 2, 2022, the licensee performed the normal quarterly IST surveillance (i.e., procedure 24.702.01) and observed the stroke time of the valve to be 61.4seconds. The licensee immediately declared the valve to be inoperable, retested the valve, and performed an analysis to show that the valve was working correctly per subsequent stroke time measurements. Subsequently, the licensee concluded that valve G1100F019 was unable to perform its design function to close between the time the surveillance performed on October 1, 2021, and the surveillance performed on January 2, 2022.
Corrective Actions: At the time of this inspection period, the licensee planned to replace the solenoid during the 2022 refueling outage. The licensee also initiated an action to create a process change for scheduling and performing partial surveillance.
Corrective Action References: CARD 22-20008
Performance Assessment:
Performance Deficiency: The inspectors determined that the failure to promptly identify the G1100F019 stroke time exceeded IST and TRM limits was contrary to 10 CFR 50, Appendix B, Criterion XVI, Corrective Action, and was a performance deficiency.
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, the valve with a degraded stroke time was not monitored and eventually the stroke time exceeded the containment isolation timing assumed in the safety analysis.
Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Since this finding does not represent an actual open pathway in the physical integrity of the containment and it does not involve the function of the hydrogen igniters, this finding was of very low safety significance (Green).
Cross-Cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Individuals implement appropriate error reduction tools. Specifically, the licensee did not verify that all the required surveillances needed for the increased test frequency were scheduled.
Enforcement:
Violation: Title 10 CFR 50, Appendix B, Criterion XVI, Corrective Action, requires, in part, that measures shall be established to assure that conditions adverse to quality, such as non-conformances, are promptly identified and corrected.
Contrary to the above, from November 1, 2021, to January 2, 2022, the licensee failed to promptly identify a condition adverse to quality. Specifically, the licensee discovered the drywell equipment drain sump outboard containment isolation valve G1100F019 had a degrading close stroke time. Consequently, they increased the valve testing frequency from quarterly to monthly, with the intent of promptly identifying and correcting an adverse closed stroke time. However, the licensee failed to stroke time test the valve in accordance with the increased frequency in November and December 2021. On January 2, 2022, a normal quarterly IST surveillance revealed the stroke time exceeded the IST and TRM stroke time limits.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On April 19, 2022, the inspectors presented the integrated inspection results to Mr. P. Dietrich, Chief Nuclear Officer, and other members of the licensee staff.
On February 18, 2022, the inspectors presented the radiation protection inspection results to Mr. P. Dietrich, Chief Nuclear Officer, and other members of the licensee staff.
On March 7, 2022, the inspectors presented the Exit Meeting for ISI Inspection for Refueling Outage 21 inspection results to Mr. P. Dietrich, Chief Nuclear Officer, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
13-28648-03
Heat Balance for EDG Fuel Oil Storage Tank Room
10/11/2017
Corrective Action
Documents
Resulting from
Inspection
16-20500
NRC Identified Question Regarding EDG Fuel Oil Storage
Room Temperature Below UFSAR Cited Minimum
Temperature
01/20/2016
Procedures
23.106
Individual HCU Valve Lineup Verification
Corrective Action
Documents
2-23470
Potential Near Miss
03/11/2022
Corrective Action
Documents
Resulting from
Inspection
2-23741
NRC Identified Concern: Electrical Opening Penetration
Seal at Column C-17, Reactor Building First Floor, Shows
Signs of Degradation, Potential Damage. See Attached
Pictures. Recommend Assign to Design Engineering and or
Fire Protection Engineer to Evaluate
03/16/2022
FP-RB-1-7a
Reactor Building North Control Rod Drive (CRD) Area,
Zone 7, Elevation 583'6"
FP-RB-1-7b
Reactor Building South Control Rod Drive (CRD) and
Railroad Bay Area, Zone 7
Fire Plans
FP-RB-SB-4a
High Pressure Coolant Injection Pump and Turbine Room,
Zone 4
Corrective Action
Documents
2-20245
Penetration Material Not Cured as Expected
01/09/2022
CARD-20-23723
RF20 IVVI: Linear Indications in Steam Dryer Lifting Lug D
Tack Welds
04/02/2022
CARD-20-23725
RF20 IVVI: Steam Dryer Drain Channel Weld DC-D-3
Monitoring
04/20/2020
Corrective Action
Documents
CARD-20-23973
RF20 IVVI: Steam Separator Shroud Head Bolt Monitoring
04/29/2020
CARD - 22-22408
RPV Longitudinal Shell Weld 2-308C Unacceptable
Indications
2/22/2022
Corrective Action
Documents
Resulting from
Inspection
CARD-22-22158
RPV Longitudinal Shell Weld 2-208B Unacceptable
Indications
2/20/2022
NDE Reports
2-QCR-0153
PT Report for Final Welds for Drywell Cooler 12
2/08/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
VE-S21-004
Examination Summary Sheet
03/01/2022
39.NDE.001
Liquid Penetrant Procedure
GEH-UT-716
Procedure for The Examination of Reactor Pressure Vessel
Welds from The Outside Surface with Microtomo in
Accordance with Appendix VIII
WPS A11-2.1
Welding Procedure Specification P1 to P1
Procedures
WPS A18-2.1
Welding Procedure Specification P1 to P8
Miscellaneous
Fermi 2 Control Room Log
2/04/2022-
2/05/2022
Procedures
29.100.01 SH1
RPV Control
2-28921
Periodic Testing Required for Devices Analyzed in
DC 6480 Vol I
11/01/2012
17-22671
R31K004 AC/DC Inverter Found Out of Spec
03/27/2017
17-27786
Resolution Required Regarding Performance of Inverter
PMs Without Contingency Replacements
03/29/2017
18-27246
Spec Sheet for B21K801 (Output Voltage) Left Out of Spec
09/24/2018
19-26433
Cold Weather Preps for Alternate Diesel Fire Pump
08/26/2019
21-27428
Bench Calibration Found OOT for New Inverter
08/24/2021
21-29478
ADFP Missed in Winter Readiness Preparations
10/25/2021
21-30514
Alternate Diesel Fire Pump (ADFP) Hard to Start
11/29/2021
21-30960
Gauges Not Matching
2/13/2021
21-31105
Condition of the Alternate Diesel Fire Pump
2/21/2021
21-31177
No Mechanism for Tracking 28.504.03 Fire Suppression
Water System Simulated Auto Actuation Test for ADFP
2/19/2021
2-20216
ADFP Fuel/Water Separator Leaking
01/07/2022
2-20233
Alternate Diesel Fire Pump Failed to Start
01/07/2022
2-20297
Alternate Diesel Fire Pump Cold Weather Maintenance Not
Performed in Timely Manner
01/11/2022
2-20370
Bench Work Failed for 2KV Nova Inverters Q-1 Parts
01/13/2022
2-20371
Galaxy Nova Inverter Failed Bench Test
01/13/2022
2-20986
Relay Contact Checks UNSAT during Surveillance Testing
2/01/2022
Corrective Action
Documents
2-21554
Request Engineering Clarification on Checking Open
Contacts on Relays in Reference to CARD 21-24863
2/11/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-21793
HFA Relay C71A-K19C Found with Damage
2/15/2022
2-22189
E11A-K7A Was Out of Tolerance for Pick Up
2/20/2022
2-22406
Engineering Evaluation for Condition of Material
2/22/2022
2-22438
WO I507160100 Inspection of HFA Relay C71A-K5G per
35.318.024, Contacts on Relay Showed Signs of Pitting and
Coil Warn
2/23/2022
2-22611
As-Found Pick-Up Voltage Above Acceptance Criteria
2/24/2022
2-22665
NQA RF21 - TCN Inappropriately Used to Revise
Acceptance Criteria
2/25/2022
2-22830
ADFP Did Not Start at 105 PSIG
2/28/2022
2-23050
Lack of Familiarity with Nova Inverter Testing
03/04/2022
2-23191
Relays C71A-K10C and C71A-K10G Showing Signs of
Deterioration
03/07/2022
2-23217
RF21 HFA Relay Roll-Up
03/07/2022
2-23266
Frequency and Voltage Adjustments to Nova Inverters
03/08/2022
2-23286
Relay Room H11P614
03/08/2022
2-23291
Stop Gap Was Not Put in Place for CARD 22-22406
03/08/2022
2-23293
Relay Room H11P614
03/08/2022
2-23544
Incorrect Vendor Manual Listed in CECO
03/12/2022
2-24725
Snubber Group
04/05/2022
2-24926
NQA RF21 - Safety-Related Parts Not Properly Controlled
04/08/2022
08-0011
Provide an Alternate Diesel Fire Pump (ADFP) Backup for
the EF2 Diesel Fire Pump
A
19-0014
Alternate Diesel Fire Pump (ADFP)
F
21-0001
Alternate Diesel Fire Pump
A
Engineering
Changes
ERE-45451
NOVA Electric Inverter Replacement
C
100329166
Technical Evaluation Material Master
07/12/2018
EED 20160
The Stem Machined Under Shop WO 64517197, for Use on
E1150F024A Needs to be Receipt Inspected, Accepted, and
Placed into Inventory to be Issued Under a Material WO
2/28/2022
FPEE 08-0029
Review Temp Mod 08-0011 Rev. 0 - Temporary Fire Pumps
Engineering
Evaluations
FPEE-21-0002
Evaluation of TM-21-0001 Rev A - Temporary Diesel Fire
Pump
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
ERE 37328
Material Change, Replacement of Stem for WM.
Powell 3051 WE 18" - 300 Globe Valve
NISP-EN-02
Replacement Stem for MOV E1150F024A
Miscellaneous
VMC1-545
[CONFIDENTIAL] Nova Electric Galaxy Inverter Installation
and Operations Manual
28.504.02
Diesel Fire Pump Engine Weekly Operability Test
2-46
35.318.024
Inspection and Testing of HFA Relays
MES08
Control of Vendor Technical Manuals
14A
MES35
Fire Protection
2-13
MES51
Preventative Maintenance Program
MES91
Standard Item Equivalency Process Interface
MMM03
Technical Evaluation of Procurement Documents
33B
Procedures
MWC16-100
Seasonal Readiness
60088154
Installation WO for TM 21-0001 "Alternate Diesel Fire Pump"
2/06/2021
60131918
Weather Protection Structure TM 21-0001 Installation
2/07/2021
2879276
Perform Alternate Diesel Fire Pump Cold Weather
Maintenance
01/14/2022
Work Orders
64092763
Troubleshoot the ADFP Not Starting
01/14/2022
2-23206
Bus 72EB Pos 'D' Failed to Open
03/07/2022
2-23548
Lost RPS MG Set 'A' and Lost Power RPS 'A'
03/12/2022
2-23969
AB2 Division 1 Switchgear Room
03/20/2022
2-23988
Request Specification for Safety-Related String Monitor
Lights
03/21/2022
Corrective Action
Documents
2-24065
Division 1 Switchgear Room
03/22/2022
Schematic Diagram 480V Ess. Bus 72B Pos. 4C and 3B
P
Schematic Diagram 480V Ess Bus 72B and 72C Load
Shedding Strings
P
Drawings
One Line Diagram 480V Ess. Bus 72B, 72C, 72E, and 72F
Miscellaneous
Shift Manager Daily Alignment Meeting
01/12/2022
23.101
105
Procedures
23.321
Engineered Safety Features Auxiliary Electrical Distribution
System
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2.305.01
Logic System Functional Test of Division 1 480 Volt Bus 72B
and 72C Undervoltage Circuits
MMR Appendix H
On-Line Core Damage Risk Management Guidelines
MMR12
Equipment Out of Service Risk Management
20A
Work Orders
291466
Condenser Tube Leak in SW Quad
01/31/2022
Calculations
DC-6480 Vol I
[CONFIDENTIAL] 130/260V DC System Analysis
C
21-22976
G1100F003 DW Floor Drain Sump Otbd Containment
Isolation Valve and G1100F019 'DW Equip Drain Sump
OTBD Containment Isolation Valve Stroke Time Values Fall
Outside IST Limits and Owner Specified Limits
04/02/2021
21-28012
PMG142 and H859 Frequency Requested
09/10/2021
21-30086
APS: As-Found Obstructed Conduit
11/11/2021
21-31012
Need Investigation into Impacts of Newly Identified
Broken/Busted Conduits
2/14/2021
2-20003
G1100F019 'DW Equipment Drain Sump Otbd Containment
Isolation Valve Stroke Time Values Fall Outside IST Limits
and Owner Specified Limits
01/02/2022
2-20008
Investigate not Performing Increased Frequency Testing
for G1100F019
01/02/2022
2-20509
Deteriorated Duct Bank Conduits Identified in MH16553,
MH16554, and MH16555
01/18/2022
2-20928
Trip of RBHVAC, AutoStart of SGTS-2, Shift of CCHVAC-1
to Recirculation Mode
01/31/2022
2-20932
IPCS GRPISO did Not Display Groups 14 and 16 Isolated
During Actuation
2/01/2022
2-22158
RPV Longitudinal Shell Weld 2-208B Unacceptable
Indications
2/21/2022
2-22199
Frequency Oscillations Occurring for Installed Power
Supplies and Contingency Power Supplies Need Evaluated
2/21/2022
2-22408
RPV Longitudinal Shell Weld 2-308C Unacceptable
Indications
2/22/2022
2-22886
Nova Inverters Found OOT for B21K801B and R31K001
03/01/2022
Corrective Action
Documents
2-23091
As-found 115 Check Valve with Incorrect Sized Check Ball
(HCU 18-31)
03/04/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-23266
Frequency and Voltage Adjustments to Nova Inverters
03/08/2022
Process Radiation Monitoring Instrumentation Rack
H11P604
P
Schematic Diagram - Distribution of 120 VAC Division I and
Division II
AW
Process Radiation Monitoring Power Distribution Notes,
Reference Drawings, and Tables
AE
Process Rad Monitor System Fuel Pool Ventilation
Rad Monitor Sub System Part 1
L
Process Radiation Monitor System Fuel Pool Ventilation
Radiation Monitor Sub System Part 2
M
Reactor Building Secondary Containment Isolation Signals
Division II
Q
Sum Pumps System Functional Operating Sketch
Drawings
48/24V DC Instrumentation Batteries Distribution
Engineering
Changes
ECR-37261-1
Inverter Replacement to Improve Safety Related Battery
Systems Margins - Removal of EOC's
IST 21-006
Analysis of G1100F003 and G1100F019 Stroke Time
Recorded on 4/2/2021
TE-G11-21-028
Past Operability Evaluation for G1100F003, DW FLR DRN
B
Engineering
Evaluations
TE-G11-22-002
Past Operability Evaluation for G1100F019, DW EQUIP
Weschler Instruments Owners Manual for BG Series
2.8
DBD T41-00
Reactor Auxiliary Building Ventilation System
E
Miscellaneous
VMC1-545
[CONFIDENTIAL] Nova Electric Galaxy Inverter Installation
and Operations Manual
Operability
Evaluations
TE-E21-22-003
2KV Nova Inverters Failed Bench Tests
23.601
Fuel Pool Ventilation Exhaust Radiation - High
Procedures
PEP 07
Pump and Valve Inservice Testing (IST) Program
Description
36769029
Inspect and Test Div 2 AC/DC Inverter 1
04/05/2017
Work Orders
43908024
Inspect and Test Div 1 AC/DC Inverter 2
10/09/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
61165209
Troubleshoot the Slow Stroke of G1100F003 and to Replace
G11F408 If Necessary
08/03/2021
2-22520
IAS (Interm Annunciator System) System Crashed Multiple
Times Before It Crashed Hard. IAS Application had to be
Restarted
2/24/2022
2-23019
Unexpected Voltage Found While Performing Contact
Burnishing on E21A-K12B
03/03/2022
2-23090
Unexpected Voltage Found During Live Dead Live Checks
on N2200F448 Limit Switches
03/04/2022
2-23134
Loss of the Interim VAS
03/05/2022
2-23226
Stray DC Voltages Found in Two Locations Impacting
Tagging and IAS
03/07/2022
Corrective Action
Documents
2-23831
IAS Shows Alarm in for 64B Possible B8 Tripped with the
Breaker Actually Closed
03/18/2022
Core Spray System Relay Logic System 1 and 2 and Relay
Schedules
AE
Drawings
Core Spray System Annunciator Circuits
R
20-0005
Installation of an Interim Annunciator System to Support the
Replacement of the Annunciator with the New Visual
Annunciator System per EDP 80024
2/22/2021
TCTEDP 20-0005
Revise Sketch-01
06/28/2021
TCTEDP 20-
0005.025
Revise I-2080-27
2/11/2020
TCTEDP 20-
0005.184
Revise I-N-2711-20
2/11/2020
Engineering
Changes
TCTEDP
20.0005.114
Revise I-2572-53
2/11/2020
Engineering
Evaluations
RID-89937
Replace ABB Undervoltage Relay Part Number 211R1175
with Part Number 411R1175
2/02/2022
Calculations
31129 ESW 15
002
[Confidential] RHRSW and EESW Piping Replacement
2-20231
EDG 11 Lube Oil Temp Outside of APT
01/07/2022
Corrective Action
Documents
2-20234
EDG 13 Lube Temperature Low Alarm
01/08/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-20343
EDG 12 was Declared Inoperable due to the Standby Lube
Oil Pump Degrading
01/12/2022
2-20583
Seal was Found Leaking While Clearing Tags
01/21/2022
2-20715
As-Found Measurement of Seal Placement
01/25/2022
2-22698
Results of Internal Valve Inspection
2/26/2022
2-22702
NQA RF21 - Results of PT Exam for RHR Division 1
Cooling/Test Isolation MOV E1150F024A Valve Seat
2/26/2022
2-22729
E1150F024A SMB-4 Actuator Damage Following
Over Thrust
2/26/2022
2-23079
E1150F024A New Motor Leads to Large for Term Strip
03/04/2022
2-23133
Weidmuller Term Strip Replacement
03/05/2022
2-23180
Broken Terminal Strip E1150F024A
03/06/2022
2-23438
WO 64696217 Requires Scheduling
03/10/2022
2-23614
Evaluation Needed for Running RHRSW with no Water on
the RHR Side of the System Heat Exchanger
03/14/2022
2-23802
SOE 21-02 Lacking Test Point
03/17/2022
2-24037
RF21 LL: SOE Acceptance Criteria Observation
03/22/2022
2-24059
SOE 21-02 Testing Indicated EESW Lower Flow Margin
03/22/2022
2-27000
Failed PMT
2/26/2022
Corrective Action
Documents
Resulting from
Inspection
2-00396
Abnormal Noise EDG 12 Standby Lube Oil Pump - NRC
Identified
01/11/2022
480V Ess. Bus 72EB Pos. 1B and 2D
Q
Residual Heat Removal Division 1
BS
Emergency Equipment Cooling Water Division 1
CD
Drawings
RHR Service Water System Division 1 RHR Complex
Plan of the Day
01/03/2022
Scram Time Test 54.000.03
01/04/2022
Request to Perform SOE 21-02
2/14/2022
DBD B21-00
[Confidential] MS and Nuclear Boiler Instrumentation System
D
Miscellaneous
DBD E11-XX
Residual Heat Removal Service Water System
E
Procedures
23.208
RHR Complex Service Water Systems29-130
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
23.708
Fuel Pool Cooling and Cleanup System
35.304.009
Refurbishing 600 Volt K-Line Air Circuit Breakers
IST Program
Pump Basis
Inservice Testing Program for Pumps and Valves
MMA11
Pump/Fan Testing
MWC02
Work Management Process
37B
MWC10
Work Package Preparation
000Z050691
West Fuel Pool Cooling Circulation Pump
07/20/2006
000Z052927
Seal Leak/Oil Use East Pump
09/30/2005
46483107
Replace All Actuator Springs on Outboard MSIV Line 'C'
2/19/2022
46483116
Replace All Actuator Springs on Inboard MSIV Line 'C'
2/18/2022
2496756
ECN - 80026 / 28 - Div 1 - Phase 4 - RF21 - RHRSW -
Buried Pipe - PMT Hydro (Final Whole System)
2/09/2022
55778752
Replace the MSIV Hydraulic Actuator
2/16/2022
55789696
Replace the MSIV Hydraulic Actuator
2/16/2022
61786363
Water Alarm Trend - CRD 30-43
2/22/2021
202238
Replace Mechanical Seal/Replace Components
01/19/2022
64436091
RF21 - Actuator Inspection on E1150F024A After Over
Thrust
2/11/2022
64436532
RF21 - Valve Inspection on E1150F024A After Over Thrust
2/11/2022
64495448
Replace LOR Relay 27X-72EA, Wiring at K-1 Coil Burned up
on Re-Energizing
2/26/2022
64707085
Breaker 72EB Pos. 2D Failed to Open
03/10/2022
64717660
Grounded Cable
03/10/2022
Work Orders
64803407
Perform 24.205.05 Division 1 RHRSW Pump and Valve
Operability
03/22/2022
2-20997
Cognitive Trend Challenges with Welding Qualifications and
Performance
2/02/2022
2-21200
RB1 Steam Tunnel
2/05/2022
2-21242
Unable to Complete Calibration of Floodup Level Indicator
2/06/2022
2-21251
RF21 Outage Lesson Learned
2/06/2022
2-21363
Loss of Bus 72P
2/08/2022
Corrective Action
Documents
2-21743
Poor Communication Practices/Time Pressure
2/14/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-21789
Failure to Identify High Risk Activity
2/14/2022
Nuclear Boiler System
BP
Drawings
Nuclear Boiler System
Clearance
R1200-000132(1)
System Service Transformer 64 13.2/4.16KV
2/14/2022
Miscellaneous
Shutdown Safety
risk Management
Planning Form
RF-21 Reactor Cavity Flood-up Evolution
2.000.03
Power Operation 25% to 100% to 25%
107
2.000.04
SDC and RWCU Outboard Isolations Defeat
35.710.025
Reactor Vessel Disassembly
46.137.001
Installation and Removal of Air Supplied Reference Leg for
B21-N027 and Filling Reactor Instrumentation Sensing Line
to Level Tap B21L012
2.000.04
Refueling and Core Post - Alteration Verification
MMA07-200
NUREG 0612 Lifts
MMA17-200
Refuel Floor FME Plan
MOP05-200
Procedures
MWC13
Outage Nuclear Safety
Corrective Action
Documents
2-22883
LLRT Measured Leakage per 43.401.318 Above Maximum
Allowable Leakage
03/01/2022
43.401.318
Local Leak Rate Testing for Penetration X-22
03/08/2022
Procedures
43.401.500
Local Leakage Rate Testing for Penetration X-7A, X-7B,
X-7C, and X-7D
68.000.006
Personnel Contamination Monitoring
Procedures
68.000.007
Control of Radioactive Material
Radiation
Surveys
P-M-20220213-
Torus Proper
2/13/2022
23015
RF20 Under Vessel Support
24002
RB5 - Reactor Core Alterations, Bridge Maintenance,
LPRM Replacement and Support Activities
25002
E1150F068AB Replacement Tasks
Radiation Work
Permits (RWPs)
25006
Torus Vent Header Repairs
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
51430912
Evaluate Status of Fermi 2 Alpha Source Term
2/23/2020
Work Orders
55449365
E1150Y000-001 Remove and Reinstall Interfering Piping
and Associated Supports
2/13/2022
65.000.704
Issuance of Respiratory Protection Equipment
Procedures
MRP09
Respiratory Protection
Corrective Action
Documents
21-23411
Step Change in RB Steam Tunnel Temperature Due to
Possible HPCI Steam Leak
04/16/2021
Monthly Operating Report (January 2021 - December 2021)
Various
71151
Miscellaneous
Monthly Safety System Functional Failure (SSFF) IRIS
Data Entry, Verification, and Approval
(January 2021 - December 2021)
Various
2-21157
Reactor Scram on Loss of Feed
2/04/2022
2-21159
Following Reactor Scram on 2/4/2022 the MTG did Not Trip
as Expected on Reverse Power
2/05/2022
2-21160
South Reactor Feedpump had to be Manually Tripped due to
High Vibratons
2/05/2022
2-21172
Unable to Close N1100F059B West MS Bypass Valve from
the MCR
2/05/2022
Corrective Action
Documents
2-21203
Investigation for NRFPT Trip EIT for Low Suction Trip
Instruments/Relays
2/05/2022
Fermi 2 Control Room Log
2/04/2022 -
2/05/2022
Miscellaneous
LER 2021-003
High Pressure Coolant Injection Inoperable due to Contact
Oxidation
20.107.01
Loss of Feedwater or Feedwater Control
Procedures
2.000.04
Plant Shutdown from 25 Percent Power
90