IR 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 | |
| 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:
Report Number:
Enterprise Identifier:
I-2024-013-0008
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
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 Aspect Report Section Mitigating Systems Green NCV 05000341/2024013-01 Open/Closed None (NPP)71003 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
- (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
- (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 Aspect Report Section Mitigating Systems Green NCV 05000341/2024013-01 Open/Closed None (NPP)71003 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
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
SL-R8
Final Load Check of Reactor Building RHR Heat Exchanger
Platforms
B
CARD-09-26756
NRC Question - Investigate RHR Complex North Wall
Condition
09/01/2009
CARD-10-30178
Indication Noted in Control Rod Guide Tube 06-35
(Weld CRGT-2)
11/05/2010
CARD-11-30816
Document Applicability of NRC Information Notice 2011-20,
Concrete Degradation by Alkali-Silica Reaction
2/08/2011
CARD-12-23820
Feedwater Nozzle and Sparger Condition Monitoring
04/26/2012
CARD-17-21218
License Renewal - Request Work Orders for
Cleaning/Inspection of Each EDG Fuel Oil Day Tank (FODT)
2/10/2017
CARD-17-22660
Feedwater Nozzle Unclad Area Condition Monitoring
03/27/2017
CARD-17-23000
Abnormal Corrosion Indication on G51000F012B Observed
During License Renewal One Time Inspection
04/02/2017
CARD-17-27112
Evaluate Margin for Acceptance Criteria in Recent
Performance of 28.504.04
08/24/2017
CARD-17-27596
2017 NRC Fire Protection Triennial: DC-5713 Contains an
Error Used in Acceptance Criteria 28.504.04
09/12/2017
CARD-17-28735
Valve Internal Corrosion/Erosion of Interest Erosion
10/26/2017
CARD-17-29197
License Renewal - Obtain PIS Numbers and Labels for
Valves to be Used to Sample EDG Day Tank Fuel Oil
11/14/2017
CARD-18-22133
INPO Identified Missed Feedwater Sparger Visual
Examination
03/14/2018
CARD-18-22726
INPO BWRVIP Review Visit Recommendation: 1. Feedwater
Sparger Examinations
04/03/2018
CARD-18-24187
Boral Campaign 1 and Campaign 2 Coupon Surveillance
Assemblies Not Placed in Accordance with Requirements of
2.000.16
05/25/2018
CARD-18-27590
Indication Noted in Core Differential Pressure / Standby
Liquid Control Safe End Weld 5-315
10/01/2018
71003
Corrective Action
Documents
CARD-18-28122
Reactor Pressure Vessel Shell Longitudinal Weld 15-308D
has Reportable Ultrasonic Construction Weld Flaws
10/10/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CARD-19-20432
Diesel Fire Pump Fuel Oil Flash Point Lower than Expected
Value
01/18/2019
CARD-19-23961
2019 DBAI Related (Untimely Corrective Action for Coating
Restoration on 180 Torus Earthquake Tie)
05/23/2019
CARD-20-21684
Pending Version of PTLR has Undesirable Outage Impacts
2/14/2020
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
20 MMR14 Structures Monitoring Inspection of RBSB
Southwest Quad (In-Leakage Locations Investigation)
04/27/2020
CARD-21-21360
20 MMR14 Structures Monitoring Inspection of RBSB
Torus Room Bottom (Bays 9-16) (In-Leakage Investigation)
2/12/2021
CARD-21-29328
20 MMR14 Structures Monitoring Inspection of Reactor
Building North Exterior Wall (Investigation)
10/21/2021
CARD-21-31070
20 MMR14 Structures Monitoring Inspection of General
Service Water (GSW) Pump House Exterior Area
(Non Outage WO)
2/16/2021
CARD-22-22158
RPV Longitudinal Shell Weld 2-308B Unacceptable
Indications
2/20/2022
CARD-22-22408
RPV Longitudinal Shell Weld 2-308C Unacceptable
Indications
2/22/2022
CARD-22-22850
Ultrasonic Examination Re-Identified Weld Flaw in
2/28/2022
CARD-22-23058
Revision to ISI-NDE Program for Crevice Corrosion Weld
Classifications
03/04/2022
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
CARD-22-30378
ISI Snubber Population and Supports Basis Documents Gap
10/14/2022
CARD-22-30548
ISI Self-Assessment Recommendation: Unclear Justification
for Exclusion of Systems from ISI Scope
10/21/2022
CARD-22-30844
Failed Dewpoint for P5002D030A CA IAS East Dryer
11/03/2022
CARD-22-31613
License Renewal - Reactor Head Closure Studs AMP
Procedure Revisions Required to Meet License Renewal
2/07/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Commitments
CARD-23-20366
Lack of Documentation of Class 2 Pump Attachment Welds
for ISI Program
01/12/2023
CARD-23-21487
Spare Reactor Head Closure Studs Require Evaluation
2/21/2023
CARD-23-22202
EDG13 Fuel Oil Storage Tank Center Bottom Tap Source
Valve Minor Leak
03/19/2023
CARD-23-30861
NQA - Area of Concern - Boraflex Inserts Project
01/31/2023
CARD-98-18949
Shroud Head Bolt Wrench/Rigid Pole Assembly Dropped
During Separator Latching
10/14/1998
CR-2023-30946
License Renewal - Review of Vendor Inspection
Report - Examination of Condensate Storage Tank
06/15/2023
CR-2023-32454
DW Leak Identification - RCS Leakage from B Reactor
Recirc Sample Line
08/20/2023
CR-2023-33196
License Renewal Peer Assessment - AMP B.1.14 Diesel
Fuel Monitoring - Investigation Required for MIC Parameters
09/20/2023
CR-2024-35650
LRI OE Review: OTI Small Bore Piping Program:
High Vibrations Caused Insulation Fretting Damage on
Make Up Piping
01/17/2024
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
in 270 Azimuth Drywell Sand Cushion Drain Line
04/18/2024
CR-2024-41360
License Renewal AMP B.1.40 Selective Leaching:
Determination of Program Continuation into the PEO
08/05/2024
Unusual Surface Conditions Identified on RPV Cladding and
Nozzles
05/18/1994
CR-2024-41394
(TREND CR) License Renewal - Results Books Issued to
NRC for RFI II.1 for Phase II Inspection Have Open Items to
Be Closed Prior to End of Phase II Inspection
08/06/2024
CR-2024-41516
NRC License Renewal Inspection Issue (Self-Identified):
Issues with Y4100 Sump Pumping Stations for MH03
08/12/2024
CR-2024-41529
24 License Renewal Phase 2 NRC Inspection Typo
Identified in Procedure 82.000.16
08/13/2024
Corrective Action
Documents
Resulting from
Inspection
CR-2024-41535
24 NRC License Renewal Inspection, Self-Identified,
22 License Renewal Work Orders Have Not Been
08/13/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Scheduled
CR-2024-41540
24 NRC License Renewal Inspection, NRC Identified,
PTT C159 Shows a PM Grace of 69 Days. This Grace
Period Should be 23 Days vs 69 Days.
08/13/2024
CR-2024-41554
24 NRC License Renewal Inspection: Scanned Copy of
WO 53778313 Requested by NRC RFI Not Able to Obtained
After 24 Hours of Request.
08/14/2024
CR-2024-41559
24 NRC License Renewal Inspection: Potential Missing
Bolt in S RHR Hx Room Support
08/14/2024
CR-2024-41563
24 NRC License Renewal Inspection: NRC Inspector
Noted Housekeeping Issues in S RHR Hx Room
08/14/2024
CR-2024-41570
24 NRC License Renewal Inspection: Inspectors Badge
Did Not Have Full Access
08/14/2024
CR-2024-41571
24 NRC License Renewal Inspection: Self Identified Issue
with Regulatory Frequency for B.1.36 PMs
08/14/2024
CR-2024-41577
24 NRC License Renewal Inspection - LRI Team Identified
License Renewal PMs with Greater Than 25% Grace
08/15/2024
CR-2024-41584
24 NRC License Renewal Inspection: NRC Identified
Corrosion on Torus Earthquake Ties
08/15/2024
CR-2024-41586
24 NRC License Renewal Inspection: Efflorescence on
RBSB Torus Outer Wall at Azimuth 180
08/15/2024
CR-2024-41587
24 NRC License Renewal Inspection: Add LR Crediting
Statement to RPV Disassembly Procedure
08/15/2024
CR-2024-41589
24 NRC License Renewal Inspection: RCIC Needs to be
Added to ISI Scope
08/15/2024
CR-2024-41598
24 NRC License Renewal Inspection - R3000F983B Leak
08/15/2024
CR-2024-41599
24 NRC License Renewal Inspection - R30-R570B Leak
08/15/2024
CR-2024-41600
24 NRC License Renewal Inspection; Possible CTG Fuel
Oil Storage Tank Leak
08/15/2024
CR-2024-41606
24 NRC License Renewal Inspection: NRC Inquiry
Regarding Monitoring of Degraded G5100F012B per
CARD 17-27000
08/15/2024
CR-2024-41626
24 NRC License Renewal Inspection: (Self-Identified)
Results Book for AMP B.1.04 Contained Procedures and
08/16/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Conduct Manuals with Missing Headers (Adobe Error)
CR-2024-41672
24 NRC License Renewal Inspection: RFI Response to
The NRC Not Provided Within the Expected 24 Hours
08/19/2024
CR-2024-41693
24 NRC License Renewal Inspection: Unable to Answer
NRC Question Within 24 Hours
08/20/2024
CR-2024-41720
24 NRC License Renewal Inspection - NRC-89-0046 In
Nuclear Documentum Is Missing Pages
08/21/2024
CR-2024-41741
24 NRC License Renewal Inspection - Recommend
Evaluating XRF24 Frequencies for License Renewal PMs
08/22/2024
CR-2024-41783
24 NRC License Renewal Inspection: Request for
Performance of an Opportunistic Inspection of Valve
Pressure Boundary Internals of G5100F012B
08/26/2024
CR-2024-41797
24 NRC License Renewal Inspection: NRC Concern on
RCIC Not Being Included in ISI Program
08/27/2024
CR-2024-41805
24 NRC License Renewal Inspection: Revision to
Chemistry Conduct Manual MCE03 Required to Remove
Deadline Dates That Are Not Required by License Renewal
Commitments
08/27/2024
CR-2024-41881
24 NRC License Renewal Inspection: Inconsistencies in
Licensing and Design Bases Documents Concerning RCIC
Functions
08/28/2024
CR-2024-41887
24 NRC License Renewal Inspection: WO Request to
Clean Out Pipe Sleeve
08/28/2024
Reactor Building RHR Heat Exchanger Platforms Unit 2
Reactor Building RHR Heat Exchanger Platforms Unit 2
E
Diagram Fire Protection System Sheet 2
Drawings
M-5370
Inservice Inspection Detail Drawing RHR Div. 2 Heat
Exchanger B Reactor Building
A
210
Fire Protection Header Replacement Phase 2
01/20/2023
Engineering
Changes
TSR-100641
Revise Bolt Evaluation for RHR Hx Platform Beam
Connections to Separate Per Division
09/04/2024
005N0158
Enrico Fermi Unit 2 GNF3 and 24-Month Cycle Extension
04/01/2020
Engineering
Evaluations
38021.004-TR-
001
Standby Liquid Control System - Socket Weld Failure
Analysis
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
GE-N E-0000-
0076-8499-Rl
Flaw Indications 127 & 128 RPV Axial Weld 15-308B
Indication Evaluation for Enrico Fermi Power Station Unit 2
TE-B11-10-098
Evaluation of Indication on Control Rod Guide Tub 06-35
Weld CRGT-2
11/13/2010
TE-T23-22-063
Degraded Coating Identified on Torus Earthquake Ties
08/05/2022
20 MMR14 Structures Monitoring Program Inspection
Final Report
03/27/2020
211408-R-02-Rev.
Final Report on Evaluation of In-Leakage Samples
2/17/2023
51074 2502-2649
Quality Assurance Records Binder RHR Pump
06/06/1974
51085 2127-2216
Quality Assurance Records Binder Core Spray Pump
2/06/1973
C17
Oil Sample Data Sheet
08/22/2023
CTL 262990
Phase 1 - Evaluation of Powder Deposits Turbine, Auxiliary
and RadWaste Buildings
03/15/2016
DET-16-0205
Basis for ISI Classification Boundaries Enrico Fermi Power
Plant Unit 2
A
FERMI-RPT-12-
LRD02
Aging Management Program Evaluation Report - Class 1
Mechanical
FERMI-RPT-12-
LRD03
Aging Management Program Evaluation Report Non-Class 1
Mechanical
GE-NE-0000-
25-0813-R0
RPV Flaw Evaluation Handbook
LCR-18-033-UFS
Licensing Change Request
LCR-18-049-UFS
Licensing Change Request
LCR-18-052-ISI
Licensing Change Request
LCR-20-019-UFS
Licensing Change Request
LCR-23-016-UFS
Licensing Change Request
LCR-23-023-UFS
Licensing Change Request
LCR-23-034-UFS
Licensing Change Request
LCR-24-003-ISI
ISI-NDE Program
DTE Energy/Enrico Fermi Power Plant Unit 2 Pressure and
Temperature Limits Report (PTLR) up to 52 Effective
Full-Power Years
Miscellaneous
OTI.170402.04
One-Time Inspection Report - G5100F012B
04/02/2017
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SWRI 17-4677
Survey of Class 2 and 3 Systems for Enrico Fermi Atomic
Power Plant, Unit 2
01/01/1977
19-001
As-Found Buried Piping Visual Inspection Report
01/11/2019
VT-S12-037
Visual Examination of E11-5370-G05
04/18/2012
NDE Reports
VT-S21-004
Visual Examination of Torus Earthquake Ties
03/02/2022
20.000.01
Acts of Nature
28.502.04
Low Pressure CO2 System Evaluation Test
28.502.06
CO2 Fire Suppression System Functional Test
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
28.507.07
Fire Barrier Inspections, Balance of Plant
35.000.240
Bolting and Torquing
35.710.026
Reactor Vessel Reassembly
35.CON.001
Excavation and Backfill Replacement Releases
35.RIG.012
Miscellaneous Hoist Inspection
43.000.001
Shore Barrier Surveillance
43.000.005
Visual Examination of Piping and Components (VT-2)
43.000.016
Performance of ISI-NDE Inspections
43.000.017
Reactor Pressure Vessel - Invessel Internals Inspection
43.000.019
Primary Containment Inspection
45.000.003
In-Core (SRM and IRM) Removal/Installation/Verification
45.604.001
LPRM Testing and Preparation for Removal
47.000.20
Testing of Medium Voltage Cables
47.000.22
Non-EQ Insulated Cables and Connections Visual
Inspections
47.000.88
Infrared Inspection
47.0020
Tan Delta Testing of Cables
57.000.19
Spent Fuel Storage Rack Management Guidelines
2.000.301
Low Flow Ground Water Sampling
Procedures
64.020.105
Fuel Pool Ventilation Exhaust Radiation Monitor, Division 1
Channel A Radiological Calibration
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
64.020.106
Fuel Pool Ventilation Exhaust Radiation Monitor, Division 2
Channel B Radiological Calibration
64.020.107
Fuel Pool Ventilation Exhaust Radiation Monitor, Division 1
Channel C Radiological Calibration
64.020.108
Fuel Pool Ventilation Exhaust Radiation Monitor, Division 2
Channel D Radiological Calibration
64.080.029
Main Steam Line Radiation Monitor, Channel A Calibration
64.080.030
Main Steam Line Radiation Monitor, Channel B Calibration
64.080.031
Main Steam Line Radiation Monitor, Channel C Calibration
64.080.032
Main Steam Line Radiation Monitor, Channel D Calibration
66.000.409
Control Center Emergency Air (CCEA) South Inlet Division 1
Radiation Monitor Radiological Calibration
66.000.410
Control Center Emergency Air (CCEA) South Inlet Division 2
Radiation Monitor Radiological Calibration
66.000.411
Control Center Emergency Air (CCEA) North Inlet Division 1
Radiation Monitor Radiological Calibration
66.000.412
Control Center Emergency Air (CCEA) North Inlet Division 2
Radiation Monitor Radiological Calibration
75.000.115
Operation of Lasernet Fines Instrumentation
77.000.103
Determining Microbiological Concentration in Fuel Oil
0.1
77.000.72
IAS and NIAS Sampling and Analysis
77.000.81
Sampling EDG Fuel Oil Tanks
2.000.16
High Density Spent Fuel Storage Rack Surveillance Activities
COS 007
Fermi 2 Strategic Water Chemistry Plan
EF-ESP-PE-
JPR107-Guide
Coating Specialist Job Performance Requirements
MCE02
Chemical Controls
MCE03
Chemistry Sampling and Analysis
MCE04
Chemistry Quality Control and Verification
MES23
Inservice Inspection and Testing
23.1
MES24
Engineering Support Conduct Manual Chapter 24-
MES27
Verification of System Operability
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
MES28
Leakage Reduction and Primary Containment Leakage
Rate Programs
MES30
Engineering Support Conduct Manual
MES33
Conduct of the Environmental Qualification Program
MES35
Fire Protection
MES35
Fire Protection
MES46
ASME Section XI Containment Inservice Inspection Program
8.2
MES51
Preventative Maintenance Program
24.1
MES60
Electrical Cable Monitoring Program
MES83
License Renewal Implementation
MES83-014
License Renewal Non-EQ Electrical Cable Connection
MES83-015
Fermi 2 Non-EQ Electrical Cable Connection Inspection
MES83-100
One-Time Inspection Program
MES83-101
Engineering Support Conduct Manual Implementing
Procedure Coating Integrity Program
MES83-102
Non-EQ Instrumentation Circuits Test Review Program
MES83-103
Engineering Support Conduct Manual Implementing
Procedure Aboveground Metallic Tanks Aging Management
Program (AMP)
MES83-104
Periodic Surveillance and Preventative Maintenance
Program
MES83-106
Selective Leaching Program
MES83-107
Metal Enclosed Bus Inspection Program
MES83-108
Engineering Support Conduct Manual Implementing
Procedure Compressed Air Monitoring Program
MES83-109
Water Chemistry Control - Closed Treated Water System
Inspections
MES83-110
One-Time Inspection - Small-Bore Piping Program
MES83-111
Non-EQ Cable Connections Program
MES83-112
Engineering Support Conduct Manual Implementing
Procedure Internal Surfaces in Miscellaneous Piping and
Ducting Components Program
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
MES83-113
Bolting Integrity Program
MES83-114
Protective Coating Monitoring and Maintenance Program
(MMP) for Service Level I Coating
MES83-115
Overhead Heavy and Light Load Handling Systems Program
MGA03
General Administration Conduct Manual Procedure Use
and Adherence
MMA02
Maintenance Program
MMA07
Lifting, Rigging, and Load Handling
MMM08
Materials Shipping, Handling, and Storage
MMR14
Structures Monitoring
MMR14
Structures Monitoring
MMR14
Structures Monitoring
MQA11
Corrective Action Program
MQA11-100
Operability Determination Process
MQA11-300
Screening and Assignment
NE-1.16.9-EQE
Environmental Qualification Program Manual
PEP16
Reactor Vessel Internals Management
PEP21
Cable Monitoring Program
PEP22
CFR 50 Appendix J, Option B Program
DTEFERMI00031-
REPT-001
Enrico Fermi Power Plant 2, License Renewal
Implementation Program Assessment, Phases I & II
DTEFERMI00031-
REPT-002
Enrico Fermi Power Plant 2, License Renewal
Implementation Program Assessment, Phase III
MEPF-17-0008
License Renewal Implementation RF18 Quick Hit
Self-Assessment
06/15/2017
MEPF-18-0047
License Renewal Implementation RF19 Quick Hit
Self-Assessment
11/27/2018
Self-Assessments
NJPR-24-0004
Formal Self-Assessment Readiness for NRC IP-71003
Post-Approval Site Inspection for License Renewal Report
Supersedes NJPR-23-0020
01/22/2024
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
Work Orders
34703540
Perform NDE Inspection of RPV Closure Heads, Nuts,
2/12/2014
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Washers, and Bushings
270229
Inspect Tap Boxes Relating to SST #64 for Signs of Heating
per Tech Requirements Identified in PM Event L100.
09/30/2018
44154168
Inspect SST 65 Powered Tap Boxes for Signs of Heating
04/01/2017
254586
Remove Bonnet to Provide Vent Path for LLRT of
G5100F607
04/18/2017
44478980
Perform NDE Exams for RF18
04/01/2017
47548156
Review Documents Related to Implementation of RPV Surv
Program
04/17/2019
51693480
ECN-70056 Paint/Coat Fuel Oil Storage Tank
09/13/2018
2140857
Perform 43.000.005 Visual Exam (VT-2) During RX Vessel
System Leakage Test
05/04/2020
2189153
Perform 43.000.016 Non-Destructive Exam on Selected
Components ISI-NDE Program
03/21/2020
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
4-316A IRS, 4-316A, 4-316A IBR
2/21/2022
53404738
RF21 ISI-NDE Scope-Perform UT Exam of Welds
4-316B IRS, 4-316B, 4-316B IBR
2/17/2022
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
Inspection External Inspection Only
03/27/2022
53773325
Perform Electric Hoist Inspection and Lubrication. CRD
Rebuild Room Hoist.
2/20/2020
54338109
Replace Div 1 SGTS Damper Operator Hoses
05/11/2021
54892237
License Renewal-Inspect MEB between CTG 11-1 and
Bus 1-2A
2/06/2022
56562441
License Renewal - Perform Periodic Inspections of
Division 1 64T Manholes for Water Accumulation
08/30/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
56662448
Conduct Preparation for Refueling Inspections
03/17/2020
56888901
Perform 82.000.16 Boraflex & Boral Fuel Storage Rack
Coupon Removal
2/13/2021
57010179
Perform 43.000.004 Visual Examination of Component
Supports (VT-3 and VT-4)
10/26/2018
57114560
Perform Inspection on EESW Division 1 Supply/Return
Piping
10/23/2021
57135581
Perform 64.080.032, Main Steam Line Radiation Monitor
Channel D Calibration
2/16/2022
57180516
Perform 43.000.004 Visual Examinations of Component
Supports (VT-3 & VT-4) Prior to RFO
03/17/2020
57180530
License Renewal -47.000.22 Non-EQ Insulated
Cables/Connections AMP Visual Inspection - Online
2/28/2021
57198620
Perform Inspection on EESW Division 2 Supply/Return
Piping
10/24/2021
214622
License Renewal-Inspect MEB between CTG 11
Transformer and Bus 1 -2B
06/30/2022
242639
Perform 43.000.005 Visual Exam (VT-2) During RX Vessel
System Leakage Test
04/14/2022
242816
Perform 45.000.003, Division 1 IRMs Detector/Cable
04/06/2022
243451
Perform 43.000.016 Non-Destructive Exam on Selected
Components ISI-NDE Program
2/07/2022
250233
License Renewal - 47.000.22 Non-EQ Insulated
Cables/Connections AMP Visual Inspection -Offline
2/07/2022
250233
Perform Visual Inspection of B.1.31 Cables
03/17/2022
58551882
License Renewal - Perform Periodic Inspections of Manhole
16947A/B/C for Water Accumulation
04/19/2023
58748627
License Renewal -Check Bolts, Replace Belts, Perform
Alignment and Lube per CECO
11/30/2021
58931970
RF21 ISI-NDE Scope - Perform UT Exam of RPV Long Shell
Welds 15-308A, 15-308B, 2-308A, 2-308B, 2-308C
10/14/2020
58932294
RF21 ISI-NDE Scope-Perform UT Exam of CRD Return
Nozzle 15-315
10/14/2020
58932294
RF21 ISI-NDE Scope-Perform UT Exam of CRD Return
10/14/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Nozzle 15-315
58932320
RF2 1 ISI-NDE Scope-Perform UT Exam of
FW Nozzle 4-31 6E (N4E)
2/17/2022
58932342
RF2 1 ISI-NDE Scope-Perform UT Exam of
FW Nozzle 4-31 6F (N4F)
2/21/2022
58932418
RF21 ISI-NDE Scope RPV Studs
01/19/2022
58932454
RF21 ISI-NDE Scope-Inspect MSL A Weld
SW-PS-2-A2-AA1-AA4
10/14/2020
58932527
RF21 ISI-NDE Scope-Inspect Div 2 RHR Heat Exchanger
Welds SW-El 1-D2-HXS-05,06
01/19/2022
58938814
RF21 ISI-NDE Scope-Perform UT Exam of CRD Return
Nozzle-to-Cap Butt Weld
10/15/2020
260400
Work Order Request to Perform Borescope Inspection of
Drywell Sand Cushion Drain Lines
01/07/2022
225168
Perform 64.020.106 Fuel Pool Vent Exhaust Radiation
Monitor Division 2, Channel B Radiological Calibration -
License Renewal Required
07/18/2023
61325506
Perform Manhole Dewatering System Checks
10/14/2022
61353786
License Renewal REQD Measure Dewpoint at East IAS
Dryer Afterfilter
11/01/2022
61488926
License Renewal - Obtain HPCI Turbine Oil Reservoir
Sample for Moisture Check
11/20/2022
61760722
Perform 74.000.19 Att. 3 EDG# 13 Fuel Oil Analysis License
Renewal
2/14/2022
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
Monitored Withstand per 47.000.20
06/30/2024
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
Discharge Outlet Check Valve
09/22/2022
65904373
License Renewal - Obtain Sample of Recirc MG Set Fluid
Drives Oil Reservoirs, NEIL REQ
01/01/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
66329036
RF22 ISI-NDE Scope - License Renewal Small Bore Socket
Weld Inspections
09/16/2022
66524860
License Renewal: Perform 43.000.017 RPV Invessel
Inspections
03/04/2024
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
24 NRC License Renewal Inspection: Missing Bolt in
S RHR Hx Room Support
08/16/2024
F263140100
EDG 14 Main Fuel Oil Tank Cleaning
01/23/2017
TK01080328
Perform Structural Walkdown Inspections as Required by
MR-14 Maintenance Rule
03/28/2008