IR 05000341/2024013

Phase 2 Post Approval License Renewal Report 05000341/2024013

ML24270A207
Person / Time
Site:	Fermi
Issue date:	09/30/2024
From:	Matthew Learn NRC/RGN-III/DORS/RPB2
To:	Peter Dietrich DTE Electric Company
References
IR 2024013
Preceding documents:	ML24100A842 (9 April 2024)
Download: ML24270A207 (1)

Text

SUBJECT:

FERMI POWER PLANT, UNIT 2 - PHASE 2 POST-APPROVAL LICENSE RENEWAL REPORT 05000341/2024013

Dear Peter Dietrich:

On August 29, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Fermi Power Plant, Unit 2, and 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.

One finding of very low safety significance (Green) is documented in this report. This finding 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.

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.September 30, 2024 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, Matthew C. Learn, Acting Branch Chief Engineering and Reactor Projects Branch Division of Operating Reactor Safety Docket No. 05000341 License No. NPF-43

Enclosure:

As stated

Inspection Report

Docket Number: 05000341

License Number: NPF-43

Report Number: 05000341/2024013

Licensee: DTE Electric Company

Facility: Fermi Power Plant, Unit 2

Location: Newport, MI

Inspection Dates: August 12, 2024, to August 29, 2024

Inspectors: M. Domke, Senior Reactor Inspector T. Hartman, Senior Project Engineer B. Jose, Senior Reactor Inspector E. Magnuson, Reactor Inspector M. Siddiqui, Reactor Inspector

Approved By: Matthew C. Learn, Acting Branch Chief Engineering and Reactor Projects Branch Division of Operating Reactor Safety

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Phase 2 Post-Approval License Renewal 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 Control Deviations from Seismic Design Requirements Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green None (NPP) 71003 Systems NCV 05000341/2024013-01 Open/Closed The inspectors identified a finding of very low safety significance (Green) and an associated non-cited violation (NCV) of 10 CFR 50, Appendix B, Criterion III, Design Control, for the licensees failure to identify and control a deviation from the approved design of the south residual heat removal (RHR) heat exchanger platform. Specifically, during periodic structures monitoring walkdowns, the licensee failed to identify a missing bolt in the structural steel supporting the south RHR heat exchanger.

Additional Tracking Items

None.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

===71003 - Post-Approval Site Inspection for License Renewal

The NRC conducted a Phase 2 Post-Approval Site Inspection for License Renewal in accordance with the License Renewal Inspection Program (LRIP). Per Inspection Manual Chapter 2516, the LRIP is the process used by the NRC staff to verify adequacy of aging management programs (AMPs), Time-Limited Aging Analyses (TLAAs), and other activities associated with an applicants request to renew an operating license of a commercial nuclear power plant for an additional 20 years beyond the original operating license period, as stipulated in Title 10 of the Code of Federal Regulations (CFR), Part 54, Requirements for the Renewal of Operating Licenses for Nuclear Power Plants. This Phase 2 inspection was performed before the period of extended operation (PEO), which begins after midnight on March 20, 2025.

The inspectors assessed the licensees implementation and completion of the programs and activities described in regulatory commitments, Updated Final Safety Analysis Report (UFSAR)supplement program descriptions, TLAAs, and license conditions. They reviewed at least 70 percent of the available AMPs and the associated commitments and TLAAs.

Post-Approval Site Inspection for License Renewal===

(1) B.1.1 Aboveground Metallic Tanks Program (XI.M29, XI.M30, XI.M32) and Commitment 3

(2) B.1.2 Bolting Integrity Program (XI.M18) and Commitment 4

(3) B.1.3 Boraflex Monitoring Program and Commitment 5

(4) B.1.5 BWR Control Rod Drive Return Line Nozzle Program (XI.M6) and Commitment 37

(5) B.1.6 BWR Feedwater Nozzle Program (XI.M5)

(6) B.1.7 BWR Penetrations Program (XI.M8)

(7) B.1.8 BWR Stress Corrosion Cracking Program (XI.M7)

(8) B.1.11 Compressed Air Monitoring (XI.M24) and Commitment 8

(9) B.1.12 Containment Inservice Inspection (CII) Program - IWE (XI.S1) and Commitment 9

(10) B.1.13 Containment Leak Rate Program (XI.S4)

(11) B.1.14 Diesel Fuel Monitoring Program (XI.M30) and Commitment 10

(12) B.1.15 Environmental Qualification (EQ) of Electrical Components (X.E1)

(13) B.1.18 Fire Protection Program (XI.M26) and Commitment 13

(14) B.1.19 Fire Water System Program (XI.M27) and Commitment 14

(15) B.1.21 Inservice Inspection (XI.S3)

(16) B.1.22 Inservice Inspection (ISI) - IWF (XI.M1) and Commitment 16

(17) B.1.23 Inspection of Overhead Heavy Load and Light Load (Related to Refueling)

Handling Systems (XI.M23) and Commitment 17

(18) B.1.24 Internal Surfaces in Miscellaneous Piping & Ducting Components (XI.M38)and Commitment 18

(19) B.1.26 Metal Enclosed Bus Inspection (XI.E4) and Commitment 19

(20) B.1.27 Neutron Absorbing Material Monitoring (XI.M40) and Commitment 20

(21) B.1.28 Non-EQ Cable Connections Program (XI.E6) and Commitment 21

(22) B.1.29 Non-EQ Inaccessible Power Cables (400 V to 13.8 kV) Program (XI.E3) and Commitment 22

(23) B.1.30 Non-EQ Instrument Circuits Test Review Program (XI.E2) and Commitment 23

(24) B.1.31 Non-EQ Insulated Cables and Connections Program (XI.E1) and Commitment 24

(25) B.1.32 Oil Analysis Program (XI.M39) and Commitment 25

(26) B.1.33 One Time Inspection Program (XI.M32) and Commitment 26

(27) B.1.34 One Time Inspection - Small Bore Piping Program (XI.M35) and Commitment 27

(28) B.1.35 Periodic Surveillance and Preventive Maintenance and Commitment 28

(29) B.1.36 Protective Coating Monitoring and Maintenance (XI.S8) and Commitment 29

(30) B.1.37 Reactor Head Closure Studs Program (XI.M3) and Commitment 30

(31) B.1.38 Reactor Vessel Surveillance Program (XI.M31)

(32) B.1.39 Inspection of Water-Control Structures Associated w/ Nuclear Power Plants (XI.S7)

(33) B.1.40 Selective Leaching (XI.M33) and Commitment 32

(34) B.1.42 Structures Monitoring (XI.S6) and Commitment 34

(35) B.1.43 Water Chemistry Control - BWR (XI.M2)

(36) B.1.44 Water Chemistry Control - Closed Treated Water Systems (XI.M21A) and Commitment 35

(37) B.1.45 Coating Integrity Program (XI.M42) and Commitment

INSPECTION RESULTS

Failure to Control Deviations from Seismic Design Requirements Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green None (NPP) 71003 Systems NCV 05000341/2024013-01 Open/Closed The inspectors identified a finding of very low safety significance (Green) and an associated non-cited violation (NCV) of 10 CFR 50, Appendix B, Criterion III, Design Control, for the licensees failure to identify and control a deviation from the approved design of the south residual heat removal (RHR) heat exchanger platform. Specifically, during periodic structures monitoring walkdowns, the licensee failed to identify a missing bolt in the structural steel supporting the south RHR heat exchanger.

Description:

On August 14, 2024, inspectors performed a walkdown of the south residual heat removal (RHR) heat exchanger room to verify age-related degradation is being identified and corrected as described in the Structures Monitoring Program. During the walkdown, the inspectors noted a potential missing bolt in the structural steel supports for the RHR heat exchanger. The licensee entered the question in their corrective action program in CR-2024-41559.

The RHR heat exchanger rooms are part of the seismic category 1 reactor building structure, and the seismic qualified design is referenced in drawings C-2510 and C-2672, and supported by calculation SL-R8, Rev A. During review of the design drawings and the associated seismic calculation, the licensee determined that the missing bolt identified in the south RHR heat exchanger platform was required by the design. The seismic calculation of record, SL-R8, analyzed both RHR heat exchanger divisions using a bounding analysis using enveloping seismic loadings for each heat exchanger. Under this calculation, the as-built configuration of the south RHR heat exchanger platform did not have enough design margin to not exceed code allowable stresses in the remaining bolts.

The inspectors reviewed the structures monitoring guidance in procedure MMR14 Structures Monitoring. Step 5.3.5 states Structural steel shall be inspected for the following deficiencies: Structural bolting and anchors/fasteners (nuts and bolts) for loss of material, loose or missing nuts and/or bolts, and cracking of concrete around the anchor bolts.

A of MMR14 identifies the reactor building structure (which includes the RHR heat exchanger rooms) as in scope structures for inspection under both the maintenance rule and license renewal. Enclosure B of MMR14 identifies Structural bolting; Structural steel and miscellaneous steel connections, including high strength bolting (decking, grating, handrails, ladders, platforms, stairs, vents and louvers, framing steel, etc.) as structural components required to be inspected. Inspectors then reviewed structures monitoring inspection records from 2008 and 2021. In both cases, the missing bolt was not noted in inspection reports, or documented in the corrective action program.

The licensee performed an operability determination for the south RHR heat exchanger.

While the calculation of record did not have sufficient design margin to support the as-built condition of the structural steel, the licensee reanalyzed the seismic loading to determine more realistic loading margins. The original calculation used bounding loading values from both RHR heat exchanger rooms to generate a single calculation for both rooms. The new calculation, TSR 100641, used the same method, with specific load values from the south RHR heat exchanger room, to demonstrate that the as-built configuration, with one missing bolt, met the code allowable stresses.

Corrective Actions: The licensee performed an updated seismic calculation, TSR 100641, which demonstrated sufficient margin for the as-built configuration of the structural steel support and entered the issue into their corrective action program.

Corrective Action References: CR-2024-41559

Performance Assessment:

Performance Deficiency: The licensees failure to identify and control a deviation from the seismic design requirements of the south RHR heat exchanger platform during periodic walkdowns was contrary to 10 CFR 50 Appendix B, Criterion III, and was a performance deficiency. Specifically, the licensee failed to identify a missing bolt in the structural steel of the south RHR heat exchanger platform during structures monitoring walkdowns.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Design Control 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 ensure that the as-built configuration of the plant matched the design requirements resulted in reasonable doubt about the equipments seismic qualifications, which reduced assurance in the equipments availability and reliability and required the licensee to revise the calculation to support operability.

Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power.

The inspectors determined that this finding is of very low safety significance (Green) because they answered yes to the question: If the finding is a deficiency affecting the design or qualification of a mitigating SSC, does the SSC maintain its operability or PRA functionality.

The inspectors determined the RHR heat exchanger maintained its operability because with one missing bolt it still met the code allowable stresses.

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:

Violation: 10 CFR Part 50, Appendix B, Criterion III, Design Control, requires, in part, that measures be established to assure that applicable regulatory requirements and the design basis are correctly translated into specifications, drawings, procedures, and instructions.

These measures shall include provisions to assure that appropriate quality standards are specified and included in design documents and that deviations from such standards are controlled.

Contrary to the above, from original construction to September 4, 2024, the licensee failed to assure that deviations from seismic design standards were controlled. Specifically, during period structures monitoring walkdowns, the licensee failed to identify a missing bolt in the structural steel supports of the south RHR heat exchanger platform.

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

Minor Performance Deficiency 71003 Failure to Monitor for Aging

Minor Performance Deficiency: The licensee failed to verify the effectiveness of an aging management program (AMP) that is designed to prevent or minimize aging to the extent that it will not cause the loss of intended function during the period of extended operation as required by AMP B.1.33, One Time Inspections. Specifically, in 2017, while performing one-time inspections, the licensee identified an age-related mechanism (loss of material - corrosion) inside valve G51000F012B, TWM TO CORE SPRAY TEST LINE CHK VLV. They addressed the condition within their corrective action program; however, the recommended actions were not able to evaluate the internal condition of the valve and therefore could not ensure the valves function as a boundary (not leak externally)would be maintained throughout the period of extended operation. Consequently, this was a performance deficiency.

Screening: The inspectors determined the performance deficiency was minor. Although the AMP required follow up actions to monitor the loss of material, the inspectors did not identify any scenarios that could lead to a more significant safety concern nor adversely affect any cornerstone attributes if the valve were to not perform its function.

Observation: Inadequate Preventative Maintenance Grace Frequencies 71003 The inspectors identified a process vulnerability associated with grace frequencies on several license renewal (LR) based preventative maintenance (PM) activities. Specifically, LR aging management program (AMP) B.1.14: Diesel Fuel Monitoring Program was enhanced by revising procedures to monitor and trend water, sediment, particles, and levels of microbial organisms on a quarterly basis. The procedures were credited for monitoring and trending particulates on the emergency diesel generator (EDG) fuel oil storage tanks, EDG fuel oil day tanks, the diesel fire pump fuel oil tank, and the combustion turbine generator (CTG) fuel oil tank.

Licensee procedure MES83, Engineering Support Conduct Manual, Rev. 12, Step 4.2.7.7.c, stated in part, grace for frequencies as described in the Technical Specifications (i.e. +/- 25%) may be used for LR activities occurring with a frequency of 2 years or less, unless there is specific language in the LR commitment that precludes such grace allowance.

The inspectors reviewed PM: C159 Perform Quarterly Chemistry Trend Reviews, and noted the surveillance had a frequency of 91 days, with a grace period of 69 days, and requested the basis for the grace periods on the surveillance. In response to the inspectors questions, the licensee generated Condition Report CR-2024-41540, to document the grace of PM: C159 was greater than the 25 percent procedural allowance. The licensee planned to perform an extent of condition review of all LR PM frequencies, prior to September 20, 2024, to verify the grace frequencies are in accordance with procedure MES83.

Observation: RCIC Licensing Basis and Impacts to ISI Program Requirements 71003 During a periodic self-assessment of the ISI program, the licensee documented that there were inconsistencies in the licensing basis documentation for the reactor core isolation cooling (RCIC) system. Specifically, the licensee questioned that while the ASME Class 1 portions of the RCIC system that connect to the reactor coolant pressure boundary are safety related, the balance of the system components, including the non-reactor coolant system piping and RCIC pump have an unclear safety classification. RCIC is a technical specification required system, and the licensee handles maintenance, procurement, and testing as if it is a safety related system; however, the licensee questioned in their self-assessment whether non ASME Class 1 components were subject to the ISI program. Inspectors questioned the resolution of this concern, and the licensee issued CR-2024-41589, which scoped the balance of the RCIC system into the ISI program for future inspections based on benchmarking of other ISI programs. Notably, this condition report did not resolve the licensing basis question of the safety related status of the RCIC system.

During further discussions with the licensee, several additional inconsistencies in licensing and design basis documents for the RCIC system were discovered. The licensee documented these observations in CR-2024-41881 for resolution of the safety related status of the RCIC system. Because the licensee has taken action to scope the balance of the RCIC system into the ISI program, the inspectors did not identify another programmatic area where the system is not treated as safety related, and the licensee is pursuing resolution of this licensing basis question through their corrective action program, the NRC has decided it is not an efficient use of inspection resources to resolve the licensing basis questions as part of this license renewal inspection.

Observation: Class 2 Welded Attachments 71003 The licensee, during a periodic update of the inservice inspection (ISI) program, identified a potential discrepancy in the examinations required by ASME Section XI. In CARD-23-20366, the licensee identified that while the ISI program has maintained that there are zero ASME Class 2 pump attachment welds in the scope of the program, no basis for this determination could be located. During review of vendor documentation for the residual heat removal (RHR) and core spray (CS) pumps, the licensee discovered a weld that potentially meets the definition of an attachment weld, however, the vendor documents are of insufficient detail to be able to make a definitive determination. In addition, the construction of the pedestal attachments for the HPCI main and booster pumps was unable to be conclusively determined.

The licensee plans to conduct inspections of the RHR, CS, and HPCI pump attachments in upcoming refueling outages to determine if attachment welds in scope of ASME Section XI are present in those components.

Observation: Open Items 71003 As of the completion of the 71003 Phase 2 inspection, the licensee had two aging management programs (AMPs) that had not been completed:

• B.1.3 Boraflex

• B.1.27 Neutron Absorbing Material Monitoring

The licensee has planned for the remaining activities to be completed before the period of extended operation and commitment date (March 20, 2025).

EXIT MEETINGS AND DEBRIEFS

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

• On August 29, 2024, the inspectors presented the Phase 2 Post-Approval License Renewal results to Peter Dietrich, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71003 Calculations SL-R8 Final Load Check of Reactor Building RHR Heat Exchanger B

Platforms

Corrective Action CARD-09-26756 NRC Question - Investigate RHR Complex North Wall 09/01/2009

Documents Condition

CARD-10-30178 Indication Noted in Control Rod Guide Tube 06-35 11/05/2010

(Weld CRGT-2)

CARD-11-30816 Document Applicability of NRC Information Notice 2011-20, 12/08/2011

Concrete Degradation by Alkali-Silica Reaction

CARD-12-23820 Feedwater Nozzle and Sparger Condition Monitoring 04/26/2012

CARD-17-21218 License Renewal - Request Work Orders for 02/10/2017

Cleaning/Inspection of Each EDG Fuel Oil Day Tank (FODT)

CARD-17-22660 Feedwater Nozzle Unclad Area Condition Monitoring 03/27/2017

CARD-17-23000 Abnormal Corrosion Indication on G51000F012B Observed 04/02/2017

During License Renewal One Time Inspection

CARD-17-27112 Evaluate Margin for Acceptance Criteria in Recent 08/24/2017

Performance of 28.504.04

CARD-17-27596 2017 NRC Fire Protection Triennial: DC-5713 Contains an 09/12/2017

Error Used in Acceptance Criteria 28.504.04

CARD-17-28735 Valve Internal Corrosion/Erosion of Interest Erosion 10/26/2017

CARD-17-29197 License Renewal - Obtain PIS Numbers and Labels for 11/14/2017

Valves to be Used to Sample EDG Day Tank Fuel Oil

CARD-18-22133 INPO Identified Missed Feedwater Sparger Visual 03/14/2018

Examination

CARD-18-22726 INPO BWRVIP Review Visit Recommendation: 1. Feedwater 04/03/2018

Sparger Examinations

CARD-18-24187 Boral Campaign 1 and Campaign 2 Coupon Surveillance 05/25/2018

Assemblies Not Placed in Accordance with Requirements of

2.000.16

CARD-18-27590 Indication Noted in Core Differential Pressure / Standby 10/01/2018

Liquid Control Safe End Weld 5-315

CARD-18-28122 Reactor Pressure Vessel Shell Longitudinal Weld 15-308D 10/10/2018

has Reportable Ultrasonic Construction Weld Flaws

Inspection Type Designation Description or Title Revision or

Procedure Date

CARD-19-20432 Diesel Fire Pump Fuel Oil Flash Point Lower than Expected 01/18/2019

Value

CARD-19-23961 2019 DBAI Related (Untimely Corrective Action for Coating 05/23/2019

Restoration on 180 Torus Earthquake Tie)

CARD-20-21684 Pending Version of PTLR has Undesirable Outage Impacts 02/14/2020

CARD-20-23089 Minor Corrosion on RPV Studs 03/23/2020

CARD-20-23858 RF20 IVVI: 30° Surveillance Sample Holder Monitoring 04/04/2020

CARD-20-25259 2020 MMR14 Structures Monitoring Inspection of RBSB 04/27/2020

Southwest Quad (In-Leakage Locations Investigation)

CARD-21-21360 2020 MMR14 Structures Monitoring Inspection of RBSB 02/12/2021

Torus Room Bottom (Bays 9-16) (In-Leakage Investigation)

CARD-21-29328 2020 MMR14 Structures Monitoring Inspection of Reactor 10/21/2021

Building North Exterior Wall (Investigation)

CARD-21-31070 2020 MMR14 Structures Monitoring Inspection of General 12/16/2021

Service Water (GSW) Pump House Exterior Area

(Non Outage WO)

CARD-22-22158 RPV Longitudinal Shell Weld 2-308B Unacceptable 02/20/2022

Indications

CARD-22-22408 RPV Longitudinal Shell Weld 2-308C Unacceptable 02/22/2022

Indications

CARD-22-22850 Ultrasonic Examination Re-Identified Weld Flaw in 02/28/2022

RPV Weld 15-308A

CARD-22-23058 Revision to ISI-NDE Program for Crevice Corrosion Weld 03/04/2022

Classifications

CARD-22-23071 Unapproved Vendor Procedure Used for UT Inspections 03/04/2022

CARD-22-23278 Relevant Indication in SLC Socket Weld 24S25 03/08/2022

CARD-22-24409 Skipped Weld in Div 2 RHR Heat Exchanger Support Ring 03/29/2022

Weld

CARD-22-30378 ISI Snubber Population and Supports Basis Documents Gap 10/14/2022

CARD-22-30548 ISI Self-Assessment Recommendation: Unclear Justification 10/21/2022

for Exclusion of Systems from ISI Scope

CARD-22-30844 Failed Dewpoint for P5002D030A CA IAS East Dryer 11/03/2022

CARD-22-31613 License Renewal - Reactor Head Closure Studs AMP 12/07/2022

Procedure Revisions Required to Meet License Renewal

Inspection Type Designation Description or Title Revision or

Procedure Date

Commitments

CARD-23-20366 Lack of Documentation of Class 2 Pump Attachment Welds 01/12/2023

for ISI Program

CARD-23-21487 Spare Reactor Head Closure Studs Require Evaluation 02/21/2023

CARD-23-22202 EDG13 Fuel Oil Storage Tank Center Bottom Tap Source 03/19/2023

Valve Minor Leak

CARD-23-30861 NQA - Area of Concern - Boraflex Inserts Project 01/31/2023

CARD-98-18949 Shroud Head Bolt Wrench/Rigid Pole Assembly Dropped 10/14/1998

During Separator Latching

CR-2023-30946 License Renewal - Review of Vendor Inspection 06/15/2023

Report - Examination of Condensate Storage Tank

CR-2023-32454 DW Leak Identification - RCS Leakage from B Reactor 08/20/2023

Recirc Sample Line

CR-2023-33196 License Renewal Peer Assessment - AMP B.1.14 Diesel 09/20/2023

Fuel Monitoring - Investigation Required for MIC Parameters

CR-2024-35650 LRI OE Review: OTI Small Bore Piping Program: 01/17/2024

High Vibrations Caused Insulation Fretting Damage on

Make Up Piping

CR-2024-38367 Relevant Indications in Recirc Small Bore Socket Welds 04/14/2024

CR-2024-38529 License Renewal AMP B.1.12 - Sand Accumulation Found 04/18/2024

in 270 Azimuth Drywell Sand Cushion Drain Line

CR-2024-41360 License Renewal AMP B.1.40 Selective Leaching: 08/05/2024

Determination of Program Continuation into the PEO

DER-94-0204 Unusual Surface Conditions Identified on RPV Cladding and 05/18/1994

Nozzles

Corrective Action CR-2024-41394 (TREND CR) License Renewal - Results Books Issued to 08/06/2024

Documents NRC for RFI II.1 for Phase II Inspection Have Open Items to

Resulting from Be Closed Prior to End of Phase II Inspection

Inspection CR-2024-41516 NRC License Renewal Inspection Issue (Self-Identified): 08/12/2024

Issues with Y4100 Sump Pumping Stations for MH03

CR-2024-41529 2024 License Renewal Phase 2 NRC Inspection Typo 08/13/2024

Identified in Procedure 82.000.16

CR-2024-41535 2024 NRC License Renewal Inspection, Self-Identified, 08/13/2024

22 License Renewal Work Orders Have Not Been

Inspection Type Designation Description or Title Revision or

Procedure Date

Scheduled

CR-2024-41540 2024 NRC License Renewal Inspection, NRC Identified, 08/13/2024

PTT C159 Shows a PM Grace of 69 Days. This Grace

Period Should be 23 Days vs 69 Days.

CR-2024-41554 2024 NRC License Renewal Inspection: Scanned Copy of 08/14/2024

WO 53778313 Requested by NRC RFI Not Able to Obtained

After 24 Hours of Request.

CR-2024-41559 2024 NRC License Renewal Inspection: Potential Missing 08/14/2024

Bolt in S RHR Hx Room Support

CR-2024-41563 2024 NRC License Renewal Inspection: NRC Inspector 08/14/2024

Noted Housekeeping Issues in S RHR Hx Room

CR-2024-41570 2024 NRC License Renewal Inspection: Inspectors Badge 08/14/2024

Did Not Have Full Access

CR-2024-41571 2024 NRC License Renewal Inspection: Self Identified Issue 08/14/2024

with Regulatory Frequency for B.1.36 PMs

CR-2024-41577 2024 NRC License Renewal Inspection - LRI Team Identified 08/15/2024

License Renewal PMs with Greater Than 25% Grace

CR-2024-41584 2024 NRC License Renewal Inspection: NRC Identified 08/15/2024

Corrosion on Torus Earthquake Ties

CR-2024-41586 2024 NRC License Renewal Inspection: Efflorescence on 08/15/2024

RBSB Torus Outer Wall at Azimuth 180

CR-2024-41587 2024 NRC License Renewal Inspection: Add LR Crediting 08/15/2024

Statement to RPV Disassembly Procedure

CR-2024-41589 2024 NRC License Renewal Inspection: RCIC Needs to be 08/15/2024

Added to ISI Scope

CR-2024-41598 2024 NRC License Renewal Inspection - R3000F983B Leak 08/15/2024

CR-2024-41599 2024 NRC License Renewal Inspection - R30-R570B Leak 08/15/2024

CR-2024-41600 2024 NRC License Renewal Inspection; Possible CTG Fuel 08/15/2024

Oil Storage Tank Leak

CR-2024-41606 2024 NRC License Renewal Inspection: NRC Inquiry 08/15/2024

Regarding Monitoring of Degraded G5100F012B per

CARD 17-27000

CR-2024-41626 2024 NRC License Renewal Inspection: (Self-Identified) 08/16/2024

Results Book for AMP B.1.04 Contained Procedures and

Inspection Type Designation Description or Title Revision or

Procedure Date

Conduct Manuals with Missing Headers (Adobe Error)

CR-2024-41672 2024 NRC License Renewal Inspection: RFI Response to 08/19/2024

The NRC Not Provided Within the Expected 24 Hours

CR-2024-41693 2024 NRC License Renewal Inspection: Unable to Answer 08/20/2024

NRC Question Within 24 Hours

CR-2024-41720 2024 NRC License Renewal Inspection - NRC-89-0046 In 08/21/2024

Nuclear Documentum Is Missing Pages

CR-2024-41741 2024 NRC License Renewal Inspection - Recommend 08/22/2024

Evaluating XRF24 Frequencies for License Renewal PMs

CR-2024-41783 2024 NRC License Renewal Inspection: Request for 08/26/2024

Performance of an Opportunistic Inspection of Valve

Pressure Boundary Internals of G5100F012B

CR-2024-41797 2024 NRC License Renewal Inspection: NRC Concern on 08/27/2024

RCIC Not Being Included in ISI Program

CR-2024-41805 2024 NRC License Renewal Inspection: Revision to 08/27/2024

Chemistry Conduct Manual MCE03 Required to Remove

Deadline Dates That Are Not Required by License Renewal

Commitments

CR-2024-41881 2024 NRC License Renewal Inspection: Inconsistencies in 08/28/2024

Licensing and Design Bases Documents Concerning RCIC

Functions

CR-2024-41887 2024 NRC License Renewal Inspection: WO Request to 08/28/2024

Clean Out Pipe Sleeve

Drawings 6C721-2510 Reactor Building RHR Heat Exchanger Platforms Unit 2 AB

6C721-2672 Reactor Building RHR Heat Exchanger Platforms Unit 2 E

6M721-2135-1 Diagram Fire Protection System Sheet 2 71

M-5370 Inservice Inspection Detail Drawing RHR Div. 2 Heat A

Exchanger B Reactor Building

Engineering 70210 Fire Protection Header Replacement Phase 2 01/20/2023

Changes TSR-100641 Revise Bolt Evaluation for RHR Hx Platform Beam 09/04/2024

Connections to Separate Per Division

Engineering 005N0158 Enrico Fermi Unit 2 GNF3 and 24-Month Cycle Extension 04/01/2020

Evaluations 38021.004-TR-Standby Liquid Control System - Socket Weld Failure 0

001 Analysis

Inspection Type Designation Description or Title Revision or

Procedure Date

GE-N E-0000- Flaw Indications 127 & 128 RPV Axial Weld 15-308B 1

0076-8499-Rl Indication Evaluation for Enrico Fermi Power Station Unit 2

TE-B11-10-098 Evaluation of Indication on Control Rod Guide Tub 06-35 11/13/2010

Weld CRGT-2

TE-T23-22-063 Degraded Coating Identified on Torus Earthquake Ties 08/05/2022

Miscellaneous 2020 MMR14 Structures Monitoring Program Inspection 03/27/2020

Final Report

211408-R-02-Rev. Final Report on Evaluation of In-Leakage Samples 02/17/2023

51074 2502-2649 Quality Assurance Records Binder RHR Pump 06/06/1974

51085 2127-2216 Quality Assurance Records Binder Core Spray Pump 12/06/1973

C17 Oil Sample Data Sheet 08/22/2023

CTL 262990 Phase 1 - Evaluation of Powder Deposits Turbine, Auxiliary 03/15/2016

and RadWaste Buildings

DET-16-0205 Basis for ISI Classification Boundaries Enrico Fermi Power A

Plant Unit 2

FERMI-RPT-12-Aging Management Program Evaluation Report - Class 1 3

LRD02 Mechanical

FERMI-RPT-12-Aging Management Program Evaluation Report Non-Class 1 3

LRD03 Mechanical

GE-NE-0000- RPV Flaw Evaluation Handbook 0

25-0813-R0

LCR-18-033-UFS Licensing Change Request 0

LCR-18-049-UFS Licensing Change Request 0

LCR-18-052-ISI Licensing Change Request 0

LCR-20-019-UFS Licensing Change Request 0

LCR-23-016-UFS Licensing Change Request 0

LCR-23-023-UFS Licensing Change Request 0

LCR-23-034-UFS Licensing Change Request 0

LCR-24-003-ISI ISI-NDE Program 14

NEDC-33915P DTE Energy/Enrico Fermi Power Plant Unit 2 Pressure and 1

Temperature Limits Report (PTLR) up to 52 Effective

Full-Power Years

OTI.170402.04 One-Time Inspection Report - G5100F012B 04/02/2017

Inspection Type Designation Description or Title Revision or

Procedure Date

SWRI 17-4677 Survey of Class 2 and 3 Systems for Enrico Fermi Atomic 01/01/1977

Power Plant, Unit 2

NDE Reports19-001 As-Found Buried Piping Visual Inspection Report 01/11/2019

VT-S12-037 Visual Examination of E11-5370-G05 04/18/2012

VT-S21-004 Visual Examination of Torus Earthquake Ties 03/02/2022

Procedures 20.000.01 Acts of Nature 57

28.502.04 Low Pressure CO2 System Evaluation Test 5

28.502.06 CO2 Fire Suppression System Functional Test 24

28.504.04 Fire Suppression Water System Flow Test 37.1

28.507.01 Fire Barrier Inspection 11/10/2020

28.507.04 Fire Damper Functional Test 10/26/2004

28.507.05 Inspection of Penetration Fire Stops 24

28.507.07 Fire Barrier Inspections, Balance of Plant 5

35.000.240 Bolting and Torquing 47

35.710.026 Reactor Vessel Reassembly 30

35.CON.001 Excavation and Backfill Replacement Releases 37

35.RIG.012 Miscellaneous Hoist Inspection 50

43.000.001 Shore Barrier Surveillance 25

43.000.005 Visual Examination of Piping and Components (VT-2) 38

43.000.016 Performance of ISI-NDE Inspections 32

43.000.017 Reactor Pressure Vessel - Invessel Internals Inspection 29

43.000.019 Primary Containment Inspection 16

45.000.003 In-Core (SRM and IRM) Removal/Installation/Verification 44

45.604.001 LPRM Testing and Preparation for Removal 49

47.000.20 Testing of Medium Voltage Cables 4

47.000.22 Non-EQ Insulated Cables and Connections Visual 2

Inspections

47.000.88 Infrared Inspection 7

47.0020 Tan Delta Testing of Cables 6

57.000.19 Spent Fuel Storage Rack Management Guidelines 13

2.000.301 Low Flow Ground Water Sampling 9

64.020.105 Fuel Pool Ventilation Exhaust Radiation Monitor, Division 1 17

Channel A Radiological Calibration

Inspection Type Designation Description or Title Revision or

Procedure Date

64.020.106 Fuel Pool Ventilation Exhaust Radiation Monitor, Division 2 15

Channel B Radiological Calibration

64.020.107 Fuel Pool Ventilation Exhaust Radiation Monitor, Division 1 17

Channel C Radiological Calibration

64.020.108 Fuel Pool Ventilation Exhaust Radiation Monitor, Division 2 15

Channel D Radiological Calibration

64.080.029 Main Steam Line Radiation Monitor, Channel A Calibration 1

64.080.030 Main Steam Line Radiation Monitor, Channel B Calibration 1

64.080.031 Main Steam Line Radiation Monitor, Channel C Calibration 1

64.080.032 Main Steam Line Radiation Monitor, Channel D Calibration 1

66.000.409 Control Center Emergency Air (CCEA) South Inlet Division 1 8

Radiation Monitor Radiological Calibration

66.000.410 Control Center Emergency Air (CCEA) South Inlet Division 2 7

Radiation Monitor Radiological Calibration

66.000.411 Control Center Emergency Air (CCEA) North Inlet Division 1 8

Radiation Monitor Radiological Calibration

66.000.412 Control Center Emergency Air (CCEA) North Inlet Division 2 8

Radiation Monitor Radiological Calibration

75.000.115 Operation of Lasernet Fines Instrumentation 2

77.000.103 Determining Microbiological Concentration in Fuel Oil 0.1

77.000.72 IAS and NIAS Sampling and Analysis 12

77.000.81 Sampling EDG Fuel Oil Tanks 6

2.000.16 High Density Spent Fuel Storage Rack Surveillance Activities37

COS 007 Fermi 2 Strategic Water Chemistry Plan 12

EF-ESP-PE-Coating Specialist Job Performance Requirements 0

JPR107-Guide

MCE02 Chemical Controls 21

MCE03 Chemistry Sampling and Analysis 17

MCE04 Chemistry Quality Control and Verification 10

MES23 Inservice Inspection and Testing 23.1

MES24 Engineering Support Conduct Manual Chapter 24-12

Nondestructive Examination

MES27 Verification of System Operability 23

Inspection Type Designation Description or Title Revision or

Procedure Date

MES28 Leakage Reduction and Primary Containment Leakage 24

Rate Programs

MES30 Engineering Support Conduct Manual 14

MES33 Conduct of the Environmental Qualification Program 10

MES35 Fire Protection 17

MES35 Fire Protection 14

MES46 ASME Section XI Containment Inservice Inspection Program 8.2

MES51 Preventative Maintenance Program 24.1

MES60 Electrical Cable Monitoring Program 2

MES83 License Renewal Implementation 12

MES83-014 License Renewal Non-EQ Electrical Cable Connection 1

Thermography

MES83-015 Fermi 2 Non-EQ Electrical Cable Connection Inspection 3

MES83-100 One-Time Inspection Program 5

MES83-101 Engineering Support Conduct Manual Implementing 4

Procedure Coating Integrity Program

MES83-102 Non-EQ Instrumentation Circuits Test Review Program 1

MES83-103 Engineering Support Conduct Manual Implementing 3

Procedure Aboveground Metallic Tanks Aging Management

Program (AMP)

MES83-104 Periodic Surveillance and Preventative Maintenance 3

Program

MES83-106 Selective Leaching Program 2

MES83-107 Metal Enclosed Bus Inspection Program 2

MES83-108 Engineering Support Conduct Manual Implementing 3

Procedure Compressed Air Monitoring Program

MES83-109 Water Chemistry Control - Closed Treated Water System 3

Inspections

MES83-110 One-Time Inspection - Small-Bore Piping Program 1

MES83-111 Non-EQ Cable Connections Program 3

MES83-112 Engineering Support Conduct Manual Implementing 3

Procedure Internal Surfaces in Miscellaneous Piping and

Ducting Components Program

Inspection Type Designation Description or Title Revision or

Procedure Date

MES83-113 Bolting Integrity Program 3

MES83-114 Protective Coating Monitoring and Maintenance Program 3

(MMP) for Service Level I Coating

MES83-115 Overhead Heavy and Light Load Handling Systems Program 1

MGA03 General Administration Conduct Manual Procedure Use 33

and Adherence

MMA02 Maintenance Program 11

MMA07 Lifting, Rigging, and Load Handling 28

MMM08 Materials Shipping, Handling, and Storage 26

MMR14 Structures Monitoring 9

MMR14 Structures Monitoring 8

MMR14 Structures Monitoring 1

MQA11 Corrective Action Program 52

MQA11-100 Operability Determination Process 6

MQA11-300 Screening and Assignment 9

NE-1.16.9-EQE Environmental Qualification Program Manual 7

PEP16 Reactor Vessel Internals Management 16

PEP21 Cable Monitoring Program 7

PEP22 10 CFR 50 Appendix J, Option B Program 1

Self-Assessments DTEFERMI00031-Enrico Fermi Power Plant 2, License Renewal 0

REPT-001 Implementation Program Assessment, Phases I & II

DTEFERMI00031-Enrico Fermi Power Plant 2, License Renewal 0

REPT-002 Implementation Program Assessment, Phase III

MEPF-17-0008 License Renewal Implementation RF18 Quick Hit 06/15/2017

Self-Assessment

MEPF-18-0047 License Renewal Implementation RF19 Quick Hit 11/27/2018

Self-Assessment

NJPR-24-0004 Formal Self-Assessment Readiness for NRC IP-71003 01/22/2024

Post-Approval Site Inspection for License Renewal Report

Supersedes NJPR-23-0020

Work Orders 25971988 Inspect, Test, and Clean-480 Volt Unit Substation 72R. 04/08/2020

29637482 Perform 43.000.017 RPV Invessel Internals Inspection 10/28/2010

34703540 Perform NDE Inspection of RPV Closure Heads, Nuts, 02/12/2014

Inspection Type Designation Description or Title Revision or

Procedure Date

Washers, and Bushings

270229 Inspect Tap Boxes Relating to SST #64 for Signs of Heating 09/30/2018

per Tech Requirements Identified in PM Event L100.

44154168 Inspect SST 65 Powered Tap Boxes for Signs of Heating 04/01/2017

254586 Remove Bonnet to Provide Vent Path for LLRT of 04/18/2017

G5100F607

44478980 Perform NDE Exams for RF18 04/01/2017

47548156 Review Documents Related to Implementation of RPV Surv 04/17/2019

Program

51693480 ECN-70056 Paint/Coat Fuel Oil Storage Tank 09/13/2018

2140857 Perform 43.000.005 Visual Exam (VT-2) During RX Vessel 05/04/2020

System Leakage Test

2189153 Perform 43.000.016 Non-Destructive Exam on Selected 03/21/2020

Components ISI-NDE Program

2309821 LRI REQD -- Replace RCIC Turbine Oil Filter Elements 04/18/2020

284835 Perform 43.000.001 Shore Barrier Surveillance 08/24/2020

53404702 RF21 ISI-NDE Scope-Perform UT Exams of Welds 02/21/2022

4-316A IRS, 4-316A, 4-316A IBR

53404738 RF21 ISI-NDE Scope-Perform UT Exam of Welds 02/17/2022

4-316B IRS, 4-316B, 4-316B IBR

53404781 RF20 ISI-NDE Scope CRDH-X02-Y27-WI1 03/12/2019

53405888 RF20 ISI NDE Scope - Perform UT Exam 01/21/2022

53405942 RF20 ISI NDE Scope Perform UT Exam 03/16/2020

53450893 RF20 ISI NDE Scope - Perform UT Exam 01/22/2022

53665024 License Renewal Peaker Yard Structures Monitoring 03/27/2022

Inspection External Inspection Only

53773325 Perform Electric Hoist Inspection and Lubrication. CRD 02/20/2020

Rebuild Room Hoist.

54338109 Replace Div 1 SGTS Damper Operator Hoses 05/11/2021

(License Renewal)

54892237 License Renewal-Inspect MEB between CTG 11-1 and 02/06/2022

Bus 1-2A

56562441 License Renewal - Perform Periodic Inspections of 08/30/2021

Division 1 64T Manholes for Water Accumulation

Inspection Type Designation Description or Title Revision or

Procedure Date

56662448 Conduct Preparation for Refueling Inspections 03/17/2020

56888901 Perform 82.000.16 Boraflex & Boral Fuel Storage Rack 12/13/2021

Coupon Removal

57010179 Perform 43.000.004 Visual Examination of Component 10/26/2018

Supports (VT-3 and VT-4)

57114560 Perform Inspection on EESW Division 1 Supply/Return 10/23/2021

Piping

57135581 Perform 64.080.032, Main Steam Line Radiation Monitor 02/16/2022

Channel D Calibration

57180516 Perform 43.000.004 Visual Examinations of Component 03/17/2020

Supports (VT-3 & VT-4) Prior to RFO

57180530 License Renewal -47.000.22 Non-EQ Insulated 12/28/2021

Cables/Connections AMP Visual Inspection - Online

57198620 Perform Inspection on EESW Division 2 Supply/Return 10/24/2021

Piping

214622 License Renewal-Inspect MEB between CTG 11 06/30/2022

Transformer and Bus 1 -2B

242639 Perform 43.000.005 Visual Exam (VT-2) During RX Vessel 04/14/2022

System Leakage Test

242816 Perform 45.000.003, Division 1 IRMs Detector/Cable 04/06/2022

243451 Perform 43.000.016 Non-Destructive Exam on Selected 02/07/2022

Components ISI-NDE Program

250233 License Renewal - 47.000.22 Non-EQ Insulated 02/07/2022

Cables/Connections AMP Visual Inspection -Offline

250233 Perform Visual Inspection of B.1.31 Cables 03/17/2022

58551882 License Renewal - Perform Periodic Inspections of Manhole 04/19/2023

16947A/B/C for Water Accumulation

58748627 License Renewal -Check Bolts, Replace Belts, Perform 11/30/2021

Alignment and Lube per CECO

58931970 RF21 ISI-NDE Scope - Perform UT Exam of RPV Long Shell 10/14/2020

Welds 15-308A, 15-308B, 2-308A, 2-308B, 2-308C

58932294 RF21 ISI-NDE Scope-Perform UT Exam of CRD Return 10/14/2020

Nozzle 15-315

58932294 RF21 ISI-NDE Scope-Perform UT Exam of CRD Return 10/14/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

Nozzle 15-315

58932320 RF2 1 ISI-NDE Scope-Perform UT Exam of 02/17/2022

FW Nozzle 4-31 6E (N4E)

58932342 RF2 1 ISI-NDE Scope-Perform UT Exam of 02/21/2022

FW Nozzle 4-31 6F (N4F)

58932418 RF21 ISI-NDE Scope RPV Studs 01/19/2022

58932454 RF21 ISI-NDE Scope-Inspect MSL A Weld 10/14/2020

SW-PS-2-A2-AA1-AA4

58932527 RF21 ISI-NDE Scope-Inspect Div 2 RHR Heat Exchanger 01/19/2022

Welds SW-El 1-D2-HXS-05,06

58938814 RF21 ISI-NDE Scope-Perform UT Exam of CRD Return 10/15/2020

Nozzle-to-Cap Butt Weld

260400 Work Order Request to Perform Borescope Inspection of 01/07/2022

Drywell Sand Cushion Drain Lines

225168 Perform 64.020.106 Fuel Pool Vent Exhaust Radiation 07/18/2023

Monitor Division 2, Channel B Radiological Calibration -

License Renewal Required

61325506 Perform Manhole Dewatering System Checks 10/14/2022

61353786 License Renewal REQD Measure Dewpoint at East IAS 11/01/2022

Dryer Afterfilter

61488926 License Renewal - Obtain HPCI Turbine Oil Reservoir 11/20/2022

Sample for Moisture Check

61760722 Perform 74.000.19 Att. 3 EDG# 13 Fuel Oil Analysis License 12/14/2022

Renewal

2196121 RF21 ISI-NDE Scope Small Bore Butt Welds 08/31/2021

2789643 License Renewal CST Exterior Roof Inspection 06/12/2023

2872252 License Renewal Required - Perform Tan Delta with 06/30/2024

Monitored Withstand per 47.000.20

64460634 FP EDG 12 Fuel Oil Tank Room Sprinkler Drain Valve 01/11/2023

64731092 Relevant Indication in SLC Socket Weld 24S25 03/27/2022

65468990 Fire Protection Diesel Driven Fire Pump C001 09/22/2022

Discharge Outlet Check Valve

65904373 License Renewal - Obtain Sample of Recirc MG Set Fluid 01/01/2024

Drives Oil Reservoirs, NEIL REQ

Inspection Type Designation Description or Title Revision or

Procedure Date

66329036 RF22 ISI-NDE Scope - License Renewal Small Bore Socket 09/16/2022

Weld Inspections

66524860 License Renewal: Perform 43.000.017 RPV Invessel 03/04/2024

Inspections

67329948 Perform Weekly Manhole Water Level Monitoring 07/09/2024

67329950 Perform Weekly Manhole Water Level Monitoring 07/19/2024

67478730 RBHVAC FI-R404B Supply Line Vent Valve 11/14/2023

67631119 SCCW Chiller B001B Oil Cooler Inlet SOV 09/27/2023

262695 Drywell Sand Cushion Drain Line (270 Degree Azimuth) 08/05/2024

73502305 2024 NRC License Renewal Inspection: Missing Bolt in 08/16/2024

S RHR Hx Room Support

F263140100 EDG 14 Main Fuel Oil Tank Cleaning 01/23/2017

TK01080328 Perform Structural Walkdown Inspections as Required by 03/28/2008

MR-14 Maintenance Rule

2