IR 05000382/2025002
| ML26030A251 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 02/02/2026 |
| From: | John Dixon NRC/RGN-IV/DORS/PBD |
| To: | Sullivan J Entergy Operations |
| References | |
| EA-24-052 IR 2025002 | |
| Download: ML26030A251 (0) | |
Text
February 02, 2026
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - AMENDED INTEGRATED INSPECTION REPORT 05000382/2025002
Dear Joseph Sullivan:
On June 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Waterford Steam Electric Station, Unit 3. On July 21, 2025, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC identified the need to reissue NRC Inspection Report 05000382/2025002, dated August 6, 2025 (ADAMS Accession Number ML25216A248). Specifically, the inspection report should not have included a steam generator inservice inspection sample in Section 71111.08P -
Inservice Inspection Activities (PWR) and needed to correct the number of samples completed in Section 71153 - Follow-Up of Events and Notices of Enforcement Discretion, to two samples completed instead of one. Two findings of very low safety significance (Green) are documented in this report and were not affected by the two changes listed above.
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, John L. Dixon, Jr., Chief Reactor Projects Branch D Division of Operating Reactor Safety Docket No. 05000382 License No. NPF-38
Enclosure:
As stated
Inspection Report
Docket Number:
05000382
License Number:
Report Number:
Enterprise Identifier:
I-2025-002-0003
Licensee:
Entergy Operations Inc.
Facility:
Waterford Steam Electric Station, Unit 3
Location:
Killona, LA 70057
Inspection Dates:
April 1, 2025, to June 30, 2025
Inspectors:
K. Chambliss, Senior Resident Inspector
K. Cook-Smith, Resident Inspector
J. Drake, Senior Reactor Inspector
N. Greene, Senior Health Physicist
S. Hamilton, Project Engineer
J. O'Donnell, Senior Health Physicist
A. Smallwood, Senior Resident Inspector
Approved By:
John L. Dixon, Jr., Chief
Reactor Projects Branch D
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees
performance by conducting an integrated inspection at Waterford Steam Electric Station, Unit 3,
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
Preventive Maintenance Planning Failed to Prevent a Safety-Related Valve Failure and
Inoperability of an Emergency Diesel Generator
Cornerstone
Significance
Cross-Cutting
Aspect
Report
Section
Mitigating
Systems
Green
Open/Closed
None (NPP)
The inspectors reviewed a self-revealed Green finding and associated non-cited violation of
10 CFR 50, Appendix B, Criterion V Instructions, Procedures and Drawings. Specifically, the
licensee failed to develop and implement preventive maintenance strategies for the
condensate makeup solenoids in the emergency diesel generators in accordance with
procedure EN-DC-324, Preventive Maintenance Program.
Failure to Establish Adequate Surveillance Initial Conditions Resulted in Inadvertent
Emergency Feedwater Isolation System Actuation and Reactor Protection Actuation
Cornerstone
Significance
Cross-Cutting
Aspect
Report
Section
Green
Open/Closed
None (NPP)
The inspectors reviewed a self-revealed Green finding and associated non-cited violation of
Technical Specification 6.8.1a, Procedures and Programs. Specifically, the licensee failed to
properly implement procedure OP-903-014, Emergency Feedwater Flow Verification, during
a planned startup which resulted in the inadvertent emergency feedwater actuation signal and
an inadvertent reactor protection signal. The initial conditions for the procedure did not provide
adequate margin to account for shrink caused by the initiation of emergency feedwater into
the steam generator resulting in steam generator water level dropping below the emergency
feedwater actuation signal and reactor protection signal actuation setpoint.
Additional Tracking Items
Type
Issue Number
Title
Report Section
Status
Automatic EFAS Actuation
During Surveillance Test
Closed
Failure to Perform an
Adequate Steam Generator
(SG) Operational
Assessment EA-24-052
Closed
PLANT STATUS
Unit 3 began the inspection period at 94 percent rated thermal power. On April 26, 2025, the
unit was shut down for refueling outage 26. On June 8, 2025, the unit restarted and reached
91 percent rated thermal power on June 13, 2025, and remained at 91 percent rated thermal
power for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in
effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with
their attached revision histories are located on the public website at http://www.nrc.gov/reading-
rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared
complete when the IP requirements most appropriate to the inspection activity were met
consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection
Program - Operations Phase. The inspectors performed activities described in IMC 2515,
Appendix DProperty "Inspection Manual Chapter" (as page type) with input value "NRC Inspection Manual 2515,</br></br>Appendix D" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process., Plant Status, observed risk significant activities, and completed on-site portions of
IPs. The inspectors reviewed selected procedures and records, observed activities, and
interviewed personnel to assess licensee performance and compliance with Commission rules
and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness for seasonal extreme weather conditions prior to the
onset of seasonal hot temperatures and hurricane and tropical storm season for the
following systems:
(1)
ultimate heat sink, safety-related switchgear, safety injection, and emergency diesel
generators on June 27, 2025
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated system configurations during partial walkdowns of the following
systems/trains:
(1)
emergency feedwater trains A and B on June 2, 2025
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated system configurations during a complete walkdown of the
4160VAC train A safety bus system on May 28, 2025.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (9 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a
walkdown and performing a review to verify program compliance, equipment functionality,
material condition, and operational readiness of the following fire areas:
(1)
fire area reactor auxiliary building 8C-001, elevation +21 switchgear room A/B on
April 3, 2025
(2)
fire area reactor auxiliary building 5-001, elevation +35 electrical penetration room B
on April 3, 2025
(3)
fire area reactor control building-001, elevations -4, +21, +46 containment on May 1,
2025
(4)
fire area reactor auxiliary building 8A-001, elevation +21 switchgear room A on
May 5, 2025
(5)
fire area reactor auxiliary building 16-001, elevation +21 emergency diesel
generator 3A on May 5, 2025
(6)
fire area turbine building, elevation +15 turbine generator building switchgear/east on
May 7, 2025
(7)
fire area reactor auxiliary building 37-001, elevation -35 motor driven emergency feed
pump room A on May 8, 2025
(8)
fire area reactor auxiliary building 36-001, elevation -35 safety injection pump room A
on May 8, 2025
(9)
fire area reactor auxiliary building 2-001, elevation +46 H&V mechanical room on
June 11, 2025
71111.08P - Inservice Inspection Activities (PWR)
The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk-
significant piping system boundaries, and containment boundaries were appropriately monitored
for degradation and that repairs and replacements were appropriately fabricated, examined and
accepted by reviewing the following activities in Waterford Unit 3 during refueling outage 26
from April 28 to May 5, 2025.
PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding
Activities (IP Section 03.01) (1 Sample)
The inspectors verified that the following nondestructive examination and welding activities
were performed appropriately:
(1)
Ultrasonic Examination
1.
chemical and volume control, MVAAA216A, weld SW-18, pipe to valve
2.
chemical and volume control, MVAAA216A, weld SW-19, pipe to valve
3.
shutdown cooling, weld 21-004, pipe to pipe
4.
shutdown cooling, weld 21-007, elbow to pipe
5.
shutdown cooling, weld 21-009, pipe to elbow
Digital Radiographic Examination
1.
chemical and volume control, MVAAA216A, weld SW-18, pipe to valve
2.
chemical and volume control, MVAAA216A, weld SW-19, pipe to valve
Dye Penetrant Examination
1.
chemical and volume control, MVAAA216A, weld SW-18, pipe to valve
2.
chemical and volume control, MVAAA216A, weld SW-19, pipe to valve
3.
chemical and volume control, FW-1, seal weld on CVCISV0216 A valve
4.
containment spray, support CSRR035A
Visual 2 Examination
1.
chemical and volume control, MVAAA2 16 A, pressurizer auxiliary spray
valve A
Visual 3 Examination
1.
safety injection, pipe hangar SIRR-220
2.
safety injection, pipe hangar SIRR-498
3.
containment spray, support CSRR035
The inspectors reviewed the following volumetric and surface examination records for
relevant indications from the previous outage that the licensee analytically evaluated
and accepted for continued service:
1.
CCRR-1184, rigid restraint EC 54082002 evaluated the support as acceptable
to remain in service. Reference W-ISI-EV-23-002
2.
CCRR-0322 rigid restraint EC 54071759 evaluated the support as acceptable
to remain in service. Reference W-ISI-EV-23-00 I
3.
CCRR-0393 rigid restraint EC 54088042 evaluated the support as acceptable
to remain in service. Reference CR-WF3-2023-I 7773
Welding Activities
1.
gas tungsten arc welding
a.
chemical and volume control, MVAAA216A, weld SW-18, pipe to valve
b.
chemical and volume control, MVAAA216A, weld SW-18, pipe to valve
c.
chemical and volume control, MVAAA2 16A, weld FW-1, pressurizer
auxiliary spray valve A
d.
extraction steam, ES-7101A/B, bypass line, FW-9
e.
extraction steam, ES-7101A/B, bypass line, FW-10
PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection
Activities (IP Section 03.02)
There was no ASME code required vessel upper head penetration inspection of this outage.
PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities
(IP Section 03.03) (1 Sample)
The inspectors verified the licensee is managing the boric acid corrosion control program
through a review of the following screenings and evaluations:
(1)
1.
22-0020, CVCMVAAA115
2.
22-0037, SI MPMP0002-A
3.
23-0006, SI MVAAA205-A
4.
23-0014, CS MVAAA122-A
5.
6.
23-0017, CS MVAAA113-A
7.
23-0018, SI MVAAA416-B
8.
23-0021, SI MVAAA221-A
9.
24-0006, SI MVAAA115-A
10. 24-0010, CVCMVAAA40631
11. 24-0011, FSMPMP0003
12. 24-0012, SI MVAAA2392
13. 24-0013, RC MRCT0001/1RC42-1RL1
14. 24-0014, RC MPMP0002-B
15. 24-0015, SI MVAAA407-A
16. 24-0016, SI MVAAA403-A
17. 24-0017, SI MVAAA335-A
18. 24-0018, SI MVAAA2401
19. 24-0019, SI MVAAA126-A
20. 24-0020, SI MVAAA112-A
21. 24-0021, SI MVAAA6061-B
22. 24-0022, SI MVAAA413-B
23. 24-0023, SI MVAAA2032-B
24. 24-0024, SI MVAAA2031-A
25. 24-0025, CVCMVAAA1922-A
26. 24-0026, SI MVAAA605-A
27. 24-0027, BM MVAAA121
28. 24-0028, BAMMVAAA131-B
29. 24-0029, SI MVAAA1142-B
30. 24-0030, SI MVAAA126-B
31. 24-0031, CS MVAAA113-B
32. 24-0032, CS MVAAA116-B
33. 25-0001, FS MVAAA404
34. 25-0002, CS MPMP0001-A
35. 25-0003, CS MVAAA116-B
36. 25-0004, CS MVAAA113-B
37. 25-0006, SI MVAAA115-A
PWR Inservice Inspection Activities Sample - Steam Generator Tube Inspection Activities
(Section 03.04)
There was no ASME code required steam generator tube integrity inspection required this
outage.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)
(1)
The inspectors observed and evaluated licensed operator performance in the control
room during main steam safety valve simmer testing on April 23, 2025.
(2)
The inspectors observed and evaluated licensed operator performance in the control
room during reactor startup on June 6, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1)
The inspectors observed and evaluated licensed operator just in time training for
reactor startup in the simulator on May 31, 2025.
71111.12 - Maintenance Effectiveness
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to
ensure the following SSC remains capable of performing its intended function:
(1)
various quality control activities of safety-related maintenance during spring refueling
outage including radiation monitor relay replacements, 125V battery maintenance,
emergency safety features actuation signal relay maintenance, and essential chill
water train B isolation valve maintenance on June 1, 2025
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the
following planned and emergent work activities to ensure configuration changes and
appropriate work controls were addressed:
(1)
yellow outage risk due to startup nuclear instrument channel 1 replacement on
April 28, 2025
(2)
yellow outage risk due to lowered inventory conditions on April 30, 2025
(3)
yellow risk due to extensive oil leak on auxiliary component cooling water pump A on
May 5, 2025
(4)
yellow risk due to extensive safety bus train B work window on May 15, 2025
(5)
yellow risk due to 125VDC train A battery being disconnected for maintenance on
May 24, 2025
(6)
orange risk due to unplanned emergency feedwater pump AB inoperability on
June 3, 2025
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the
following operability determinations and functionality assessments:
(1)
emergency diesel generator A failure due to a failed condensate makeup solenoid
valve on April 16, 2025
(2)
emergency diesel generator B failure to pass post-maintenance testing following
governor replacement and tuning on June 18, 2025
(3)
containment purge isolation radiation monitor converter board missing a resistor and
a capacitor on June 18, 2025
(4)
emergency diesel generator B due to elevated copper in outboard bearing oil on
June 30, 2025
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
(1)
temporary wiring modification for cold-leg temperature input to core protection
calculator A on May 2, 2025
(2)
permanent modification of second permissive relay for engineered safety features
actuation system train B main steam isolation signal and containment spray actuation
signal actuation relays to eliminate single point vulnerability on June 28, 2025
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated refueling outage 26 activities from April 25 to June 8, 2025.
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system
operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (11 Samples)
(1)
post-maintenance testing on nitrogen accumulator No. 3 pressure switches following
replacement on April 9, 2025
(2)
post-maintenance testing on emergency diesel generator B following governor
replacement on June 23, 2025
(3)
post-maintenance testing of train B 125VDC battery following outage maintenance
window on June 24, 2025
(4)
post-maintenance testing of pressurizer vents to quench tank header isolation valve
testing following maintenance on June 24, 2025
(5)
post-maintenance testing of containment spray train B header isolation valve
following outage maintenance activities on June 24, 2025
(6)
post-maintenance testing of emergency feed water pump AB following seal
replacement due to excessive water leakage on June 26, 2025
(7)
post-maintenance testing following repairs of pressurizer auxiliary spray valve train A
on June 26, 2025
(8)
post-maintenance testing following maintenance activities on component cooling
water train B on June 27, 2025
(9)
post-maintenance testing and system verification for emergency diesel generator
train A following maintenance window during refueling outage on June 27, 2025
(10)
post-maintenance testing of plant protection system following emergency feedwater
actuation system component replacements on June 27, 2025
(11)
post-maintenance testing of engineered safety features subgroup relay following
component replacements on June 30, 2025
Surveillance Testing (IP Section 03.01) (5 Samples)
(1)
safety injection valve SI-207B, high pressure safety injection pump B discharge check
valve, quarterly surveillance valve test on April 25, 2025
(2)
safety injection valve SI-120A, safety injection recirculating header A to refueling
water storage pool upstream isolation valve, motor operated valve diagnostic test on
May 9, 2025
(3)
N+1 FLEX water transfer pump 3-year surveillance test on June 11, 2025
(4)
emergency diesel generator B integrated testing on June 25, 2025
(5)
emergency feedwater flow verification test on June 26, 2025
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
(1)
train A auxiliary component cooling water operability test on April 21, 2025
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
(1)
containment isolation valve testing during refueling outage 26 on June 30, 2025
Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)
(1)
N+1 FLEX diesel 3-year 100 percent load test on May 13, 2025
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated how the licensee identifies the magnitude and extent of
radiation levels, identifies the concentrations and quantities of radioactive materials,
and assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated how the licensee instructs workers on plant-related
radiological hazards and the radiation protection requirements intended to protect
workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and
controlling contamination and radioactive material:
(1)
surveys of potentially contaminated material leaving the radiologically controlled area
(2)
workers exiting the containment building during a refueling outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following
radiological work:
(1)
preparation for the removal of the upper guide structure using radiation work
permit 2025-1702, Revision 0, task 7
(2)
removal and replacement of manual valve CVCMVAAA105 in the regenerative heat
exchanger room using radiation work permit 2025-1454, Revision 0, task 4
(3)
removal and inspection of check valve SI MVAAA604 B in the overhead of the reactor
auxiliary building -35' elevation using radiation work permit 2025-1454, Revision 0,
task 2
High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (5 Samples)
The inspectors evaluated licensee controls of the following high radiation areas (HRAs) and
very high radiation areas (VHRAs):
(1)
(HRA) spent resin tank room on the -35' elevation of the reactor auxiliary building
(2)
(HRA) boric acid pre-concentration filter cubicles A and B on the -35' elevation of the
reactor auxiliary building
(3)
(HRA) purification ion exchanger rooms A and B on the -4' elevation of the reactor
auxiliary building
(4)
(HRA) chemical and volume control filter cubicle on the -4' elevation of the reactor
auxiliary building
(5)
(HRA) process shield No.1 in the radwaste solidification building
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP
Section 03.06) (1 Sample)
(1)
The inspectors evaluated radiation worker and radiation protection technician
performance as it pertains to radiation protection requirements.
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Permanent Ventilation Systems (IP Section 03.01) (2 Samples)
The inspectors evaluated the configuration of the following permanently installed ventilation
systems:
(1)
control room emergency filtration, units A and B
(2)
controlled ventilation areas filter, units A and B
Temporary Ventilation Systems (IP Section 03.02) (2 Samples)
The inspectors evaluated the configuration of the following temporary ventilation systems:
(1)
high-efficiency particulate air (HEPA) filter set up for decontamination work, May 5-6,
2025
(2)
HEPA filter usage for work associated with RWP 20251454, May 6, 2025
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
(1)
The inspectors evaluated the licensees use of respiratory protection devices.
Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)
(1)
The inspectors evaluated the licensees use and maintenance of self-contained
breathing apparatuses.
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)
(1)
April 1, 2024, through March 31, 2025
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
(1)
April 1, 2024, through December 31, 2024
PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual
Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample
(IP Section 02.16) (1 Sample)
(1)
April 1, 2024, through December 31, 2024
71152A - Annual Follow-up Problem Identification and Resolution
Annual Follow-up of Selected Issues (Section 03.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program
related to the following issues:
(1)
Failure of the emergency diesel generator A to reach 4600-4800 KW loading. The
inspection conclusions associated with this issue are documented as a minor
violation in this report under Inspection Results Section.
(2)
The inspectors reviewed as a selected issue for follow-up a Green non-cited violation
of 10 CFR 50 Appendix B Criterion V (as issued in Waterford Steam Electric Station,
Unit 3 Inspection Report 05000383/20240002, ADAMS Accession
No. ML24215A277) for failure to provide adequate guidance and instructions when
taking an oil sample from an operating auxiliary component cooling water pump motor
which caused a bearing failure and the pump to become inoperable. The inspectors
reviewed the causal product, the corrective actions, and reviewed recent oil sampling
briefings. The inspectors determined the licensees actions and responses for the
Green non-cited violation to be adequate.
71152S - Semiannual Trend Problem Identification and Resolution
Semiannual Trend Review (Section 03.02) (1 Sample)
(1)
The inspectors reviewed the licensees corrective action program to identify potential
trends in the emergency diesel generator that might be indicative of a more significant
safety issue.
The inspectors performed a semi-annual trend review of the sites recent issues with
unplanned emergency diesel generator inoperabilities. These issues have resulted
from maintenance practices, work planning practices, and engineering practices.
Each individual issue has resulted in regulatory action. During the course of the
semi-annual trend review, the licensee developed an internal comprehensive review
of the recent emergency diesel generator trends to assess any common cause
amongst the issues. Additionally, the licensee elevated two emergency diesel
generator issues to full root cause evaluations. These root cause evaluations will be
inspected using a separate inspection procedure. The inspectors determined the
sites approach to determining the cause of the issue trend, the corrective actions,
and planned actions are adequate.
71153 - Follow Up of Events and Notices of Enforcement Discretion
Event Report (IP Section 03.02) (2 Samples)
(1)
LER 05000382/2024-003-00, Automatic EFAS Actuation During Surveillance Testing
(ADAMS Accession No. ML24192A173). The inspection conclusions associated with
this LER are documented in this report under Inspection Results Section. This LER
is closed
(2)
Enforcement Action Number: EA-24-052, Inspection Report 05000382/2024013
(ADAMS Accession No. ML24228A261). The inspectors evaluated the response to
cited violation 05000382/2024013-01 as well as the independent third-party
operational assessment for the steam generators for operating cycles 21 through 25.
The inspectors reviewed the licensee's response to NOV 05000382/2024013-01 and
determined the reason, the corrective actions taken and planned to address
recurrence, and the date when full compliance was achieved for this violation were
adequately addressed. Full compliance was achieved on November 11, 2023, once
the steam generator tubes that exceeded the structural integrity criteria were
plugged and stabilized. This issue has been adequately addressed and captured on
the docket. This NOV is closed.
INSPECTION RESULTS
Preventive Maintenance Planning Failed to Prevent a Safety-Related Valve Failure and
Inoperability of an Emergency Diesel Generator
Cornerstone
Significance
Cross-Cutting
Aspect
Report
Section
Mitigating
Systems
Green
Open/Closed
None (NPP)
The inspectors reviewed a self-revealed Green finding and associated non-cited violation of
10 CFR 50, Appendix B, Criterion V Instructions, Procedures and Drawings. Specifically, the
licensee failed to develop and implement preventive maintenance strategies for the
condensate makeup solenoids in the emergency diesel generators in accordance with
procedure EN-DC-324, Preventive Maintenance Program.
Description: On March 16, 2025, emergency diesel generator A (EDG A) was declared
inoperable due to jacket water temperature falling below its alarm setpoint of 100°F, to
approximately 95°F. According to a 2005 evaluation by the licensee, a 10 second start of the
diesel cannot be guaranteed with jacket water temperatures below 100°F; the 10-second
diesel start time is a technical specification (TS) requirement. The lowered jacket water
temperature was due to condensate makeup solenoid valve, CMU-524A, failing open, which
provided constant flow through the system from the condensate storage pool, through the
jacket water heat exchanger, to the jacket water standpipe overflow line. Troubleshooting of
the valve found that the solenoids coil had failed.
During investigation of the failure, it was found that the valve was incorrectly classified as
non-critical, high duty cycle, mild environment. This classification resulted in no preventive
maintenance strategy for this valve. In accordance with procedure EN-DC-153, Preventive
Maintenance Component Classification, revision 24, the solenoid valve should have been
classified as high critical, high duty cycle, mild environment due to the valves failure resulting
in the inoperability of EDG A.
It was also found that the current testing of the valve only included quarterly testing of open
and close stroke times. The licensee reviewed this data for both CMU-524A and CMU-524B
and found very little variance in results. This data shows that these valves remain operable
during testing, but they do not adequately predict a failure of the solenoid operated valve. In
accordance with procedure EN-DC-324, Preventive Maintenance Program, revision 31,
successful implementation of a [Preventive Maintenance] Program should ultimately result in
the identification of optimum level of [preventive maintenance] tasks necessary to achieve
balance between plant equipment performance and effective use of resources. The licensee
failed to adequately identify the optimum level of tasks to predict or prevent failure of
CMU-524A. In order to identify the correct preventive maintenance strategy, the licensee
used their own operating experience for the service life of these valves (22 years for
CMU-524A and 30 years for CMU-524B), and industry guidance (20 year recommended coil
replacement) to determine the correct maintenance periodicity.
Corrective Actions: The licensee initiated a condition report to enter this issue into the
corrective action program. The condition report initiated an equipment failure evaluation with
the following corrective actions: 1) issue a preventive maintenance change to revise the
coding of the valve and create a 15-year replacement preventive maintenance for CMU-524A
and CMU-524B, and 2) perform an extent of condition for EDG components that may be
currently classified incorrectly or not have a preventive maintenance strategy that could
potentially effect EDG operability.
Corrective Action References: CR-WF3-2025-00951.
Performance Assessment:
Performance Deficiency: The failure to develop and implement a replacement preventive
maintenance strategy for the condensate makeup solenoid coils was a performance
deficiency.
Screening: The inspectors determined the performance deficiency was more than minor
because it was associated with the Equipment Performance attribute of the Mitigating
Systems cornerstone and adversely affected the cornerstone objective to ensure the
availability, reliability, and capability of systems that respond to initiating events to prevent
undesirable consequences. Specifically, the failure to properly implement replacement
preventive maintenance strategies resulted in the failure of the condensate makeup valve
coil, challenged the ability of the diesel to meet TS requirements, and resulted in inoperability
of EDG A.
Significance: The inspectors assessed the significance of the finding using IMC 0609
Appendix AProperty "Inspection Manual Chapter" (as page type) with input value "NRC Inspection Manual 0609</br></br>Appendix A" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process., The Significance Determination Process (SDP) for Findings At-Power. The
inspectors determined the finding impacted mitigating systems and used exhibit 2 to evaluate
the condition. The finding was determined to be of very low safety significance (Green)
because it (1) was not a deficiency affecting design or qualification of a mitigating system,
(2) does not represent a loss of the probability risk analysis (PRA) function of a single train
TS system for greater than allowed outage time, (3) does not represent a loss of PRA
function of one train of a multi-train TS system for greater than its allowed outage time,
(4) does not represent a loss of the PRA function of two separate TS systems for greater than
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, (5) does not represent a loss of PRA system and/or function as defined by the plant
risk information e-book or the licensees PRA for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and (6) does not
result in the loss of a high safety-significant, non-TS train for greater than 3 days.
Cross-Cutting Aspect: No cross-cutting aspect was assigned to this finding because the
inspectors determined the finding did not reflect present licensee performance.
Enforcement:
Violation: Title 10 CFR Part 50, Appendix B, Criterion V Instructions, Procedures and
Drawings, states in part, that activities affecting quality shall be prescribed by documented
instructions, procedures, or drawings, of a type appropriate to the circumstances. The
licensee established procedure EN-DC-324, Preventive Maintenance Program, Revision 31,
in part to meet this requirement.
Contrary to the above, from 1989 to March 16, 2025, the licensee failed to adequately
establish a preventive maintenance strategy in accordance with their quality procedure for the
replacement of the condensate makeup solenoid valve coil, which resulted in the inoperability
of emergency diesel generator A. Specifically, the licensee failed to properly classify the
solenoid valves as high critical components due to their failure effecting the operability of the
emergency diesel generators, and subsequently failed to develop a preventive maintenance
strategy adequate to predict and prevent failures of the valve which resulted in the
inoperability of EDG A.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with
Section 2.3.2 of the Enforcement Policy.
Minor Violation
Minor Violation: Title 10 CFR 50, Appendix B, Criterion III Design Control, states in part, that
measures shall be established to assure that applicable regulatory requirements and the
design basis for systems, structures and components are correctly translated into
specifications, drawings, procedures and instructions and that measures also be established
for the selection and review for suitability of application of materials, parts, equipment, and
processes that are essential to the safety-related functions of the SSCs. The licensee
established procedure EN-DC-115, Engineering Change Process, revision 15, in part to
meet this requirement.
Contrary to the above, from 2013 to February 8, 2025, the licensee failed to adequately
assure that the design basis was correctly translated into specifications, procedures, and
instructions for emergency diesel generator A. Specifically, the licensee did not adequately
evaluate the digital reference unit (DRU) high limit droop setpoint during the engineering
change process, nor did the licensee adequately evaluate vendor recommendations for the
DRU high limit droop setpoint during the causal analysis process. The emergency diesel
generator only operates in the droop mode of operation when paralleling to the grid, therefore
this setpoint does not affect the isochronous mode of the diesel used in an emergency;
however, the inadequate evaluation of the setpoint resulted in emergency diesel generator A
not being able to achieve 4700-4900 KW during the 24-hour diesel surveillance as required
by technical specifications and resulted in the inoperability of the diesel.
Screening: The inspectors determined the performance deficiency was minor. Based on
review of more-than-minor questions in IMC 0612, appendix B, informed by minor issue
examples for performance deficiencies (IMC 0612, appendix E), this issue screens to minor.
Specifically, due to the fact the emergency diesel generator only operates in isochronous
mode during an emergency run, this performance deficiency did not adversely affect a
cornerstone objective, would not lead to a more significant safety concern if left uncorrected,
and could not reasonably by viewed as a precursor to a significant event.
Enforcement: This failure to comply with 10 CFR 50, Appendix B, Criterion III Design
Control constitutes a minor violation that is not subject to enforcement action in accordance
with the NRCs Enforcement Policy.
Failure to Establish Adequate Surveillance Initial Conditions Resulted in Inadvertent
Emergency Feedwater Isolation System Actuation and Reactor Protection Actuation
Cornerstone
Significance
Cross-Cutting
Aspect
Report
Section
Green
Open/Closed
None (NPP)
The inspector reviewed a self-revealed Green finding and associated non-cited violation of
Technical Specification 6.8.1a, Procedures and Programs. Specifically, the licensee failed to
properly implement procedure OP-903-014, Emergency Feedwater Flow Verification, during
a planned startup which resulted in the inadvertent emergency feedwater actuation signal and
an inadvertent reactor protection signal. The initial conditions for the procedure did not
provide adequate margin to account for shrink caused by the initiation of emergency
feedwater into the steam generator resulting in steam generator water level dropping below
the emergency feedwater actuation signal and reactor protection signal actuation setpoint.
Description: On July 17, 2024, during a reactor startup, while in Mode 3, the site performed a
surveillance of the emergency feed water pump AB in accordance with procedure OP-903-
014, Emergency Feedwater Flow Verification. As allowed per the procedure at the time, the
site lowered steam generator 1 water level to 30 percent upon initiating emergency feed flow
per procedure OP-903-014, the initial shrink caused by the introduction of emergency
feedwater due to the difference in enthalpies between the condensate storage pool and the
steam generator resulted in steam generator 1 water level dropping below 27.4 percent which
corresponds to the reactor trip signal and the emergency feed actuation signal setpoints.
Since all control element assemblies were fully inserted and all control element assembly
disconnects were open, no reactor trip occurred; however, the reactor trip circuit breakers did
open on the valid reactor trip actuation signal. Additionally, the entire emergency feed system
did fully actuate as designed on a valid loss of steam generator water level signal. The
operators took manual control of the emergency feed system and restored steam generator
water level above emergency feed actuation signal reset setpoint.
In a previous revision of procedure OP-903-014 from at least before 1999, the licensee
procedures initial conditions stated the steam generator level should be above at least
27.4 percent, which corresponds to the reactor trip signal and the emergency feed actuation
signal setpoints. The site recognized the need for additional margin to prevent an inadvertent
trip condition and established the initial conditions to be at least 30 percent steam generator
water level. In the most recent performances of the surveillance, the site established a steam
generator water level of at least 39.78 percent or higher. In each of these previous
surveillances, the steam generator water level did experience an initial shrink when
emergency feedwater was initiated. When revising the initial conditions of the minimum steam
generator water level for the emergency feedwater flow surveillance from 27.4 to 30 percent,
the site did not adequately assess for the effects of shrink and established adequate initial
conditions to prevent an unplanned initiation of the emergency feedwater actuation signal nor
a reactor trip.
Corrective Actions: The licensee initiated a condition report to enter this issue into the
corrective action program. The condition report initiated an adverse condition analysis with
the following corrective action: revise procedure OP-903-014 to provide a more restrictive
steam generator level control band to provide adequate margin to the emergency feedwater
actuation signal (EFAS) and reactor protection signal (RPS) trip setpoint.
Corrective Action References: CR-WF3-2024-02523
Performance Assessment:
Performance Deficiency: The failure to implement adequate initial conditions for the
performance of a surveillance affecting safety-related equipment was a performance
deficiency. Specifically, the failure to implement a restrictive steam generator level control
band prior to manually initiating emergency feedwater flow resulted in steam generator 1
water level dropping below the EFAS and RPS trip setpoint causing an inadvertent initiation
Screening: The inspectors determined the performance deficiency was more than minor
because it was associated with the Procedure Quality attribute of the Initiating Events
cornerstone and adversely affected the cornerstone objective to limit the likelihood of events
that upset plant stability and challenge critical safety functions during shutdown as well as
power operations. Specifically, the failure to implement adequate initial conditions prior to the
manual initiation of emergency feedwater pump AB resulted in an unplanned actuation of
EFAS system components and an unplanned actuation of RPS components due to steam
generator 1 water level dropping below the trip setpoint.
Significance: The inspectors assessed the significance of the finding using IMC 0609
Appendix AProperty "Inspection Manual Chapter" (as page type) with input value "NRC Inspection Manual 0609</br></br>Appendix A" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process., The Significance Determination Process (SDP) for Findings At-Power.
Specifically, this event did not cause a reactor trip, did not prevent safety systems such as
emergency feedwater from operating as designed, and did not prevent main feedwater from
being returned to service by the operators.
Cross-Cutting Aspect: No cross-cutting aspect was assigned to this finding because the
inspectors determined the finding did not reflect present licensee performance.
Enforcement:
Violation: Technical Specification 6.8.1.a, Procedures and Programs, states in part, that
written procedures shall be established, implemented, and maintained covering the
applicable procedures listed in Regulatory Guide 1.33, Quality Assurance Program
Requirements, Revision 2, Appendix A, February 1978.
Regulatory Guide 1.33, Revision 2, Appendix A, Section 3.k Procedures for Startup,
Operation, and Shutdown of Safety-Related PWR Systems, states, in part, that instructions
for the startup, shutdown, and changing modes of operation should be prepared, as
appropriate, for the feedwater system.
Contrary to the above, from 1999 to July 17, 2024, the licensee failed to prepare, as
appropriate, instructions for the startup, shutdown, and changing modes of operation for the
feedwater system. Specifically, the licensee failed to establish adequate initial conditions for
the performance of a surveillance for the emergency feedwater system which resulted in the
steam generator 1 water level dropping below the EFAS and RPS trip setpoints and causing
an inadvertent EFAS and RPS actuation.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with
Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified that no proprietary information was retained or documented in this
report.
On May 5, 2025, the inspectors presented the exit meeting for inservice inspection
results to David Oertling, General Manager Plant Operations, and other members of the
licensee staff.
- On May 10, 2025, the inspectors presented the occupational radiation safety inspection
results to Joeseph Sullivan, Site Vice President, and other members of the licensee
staff.
On July 21, 2025, the inspectors presented the integrated inspection results to
Joseph Sullivan, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Attachment 5
Site Certification Letter and Seasonal Reliability Plan
Procedures
EN-FAP-010
Severe Weather Response
Work Orders
5255494, 5419260, 54202873
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2024-00759, 2024-00148, 2024-03504, 2025-01051,
2025-01765, 2025-02626, 2025-02632, 2025-02706,
Drawings
1564-4331
4.16 KV Class 1E SWGR Installation Details
Drawings
1564-6242
4.16 KV Switchgear 3A2 Element Diagram, Sheet 1
Procedures
OP-006-001
Plant Distribution (7KV, 4KV, and SSD) Systems
351
Procedures
OP-009-003
System Operating Procedure Emergency Feedwater
313
Procedures
OP-010-004
Power Operations
350
Procedures
OP-010-005
Plant Shutdown
350
Procedures
OP-901-310
Loss of Train A Safety Bus
317
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2022-03613, 2022-03592, 2024-01190, 2024-01330,
2024-01684
Fire Plans
RAB 2-001
H&V Mechanical Room
Fire Plans
RAB 36-001
Safety Injection Pump Room A
Fire Plans
RAB 5-001
Electrical Penetration Room B
Fire Plans
Switchgear Room A
Fire Plans
Switchgear Room A/B
Fire Plans
RAB-16-001
Fire Plans
RAB-37-001
Motor Driven Emergency Feed Pump Room A
Procedures
EN-EE-S-048-W
Fire Detector Replacement Standard
Procedures
Fire Protection System Impairments
335
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2022-01839, 2022-01891, 2022-01900, 2022-01901,
2022-01929, 2022-01945, 2022-01949, 2022-01960,
2022-01977, 2022-01978, 2022-01979, 2022-01993,
2022-02011, 2022-02012, 2022-02013, 2022-02014,
2022-02015, 2022-02016, 2022-02017, 2022-02018,
2022-02029, 2022-02030, 2022-02031, 2022-02032,
2022-02142, 2022-02156, 2022-02178, 2022-02287,
2022-02289, 2022-02291, 2022-02293, 2022-02295,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2022-02296, 2022-02301, 2022-02302, 2022-02303,
2022-02304, 2022-02307, 2022-02309, 2022-02310,
2022-02312, 2022-02314, 2022-02385, 2022-02387,
2022-02401, 2022-02449, 2022-02452, 2022-02461,
2022-02462, 2022-02463, 2022-02491, 2022-02555,
2022-02630, 2022-02639, 2022-02703, 2022-02730,
2022-02731, 2022-02732, 2022-02736, 2022-02741,
2022-02742, 2022-02814, 2022-02821, 2022-02937,
2022-03003, 2022-03016, 2022-03017, 2022-03018,
2022-03085, 2022-03086, 2022-03449, 2022-03452,
2022-03501, 2022-03506, 2022-03846, 2022-03959,
2022-03975, 2022-03979, 2022-04023, 2022-04178,
2022-04279, 2022-04280, 2022-04290, 2022-04392,
2022-04649, 2022-04650, 2022-04651, 2022-04656,
2022-04658, 2022-04659, 2022-04661, 2022-04662,
2022-04664, 2022-04665, 2022-04667, 2022-04670,
2022-04672, 2022-04673, 2022-04675, 2022-04987,
2022-04988, 2022-04989, 2022-04990, 2022-04992,
2022-04993, 2022-04994, 2022-04995, 2022-04996,
2022-04998, 2022-05000, 2022-05126, 2022-05132,
2022-05133, 2022-05134, 2022-05135, 2022-05136,
2022-05138, 2022-05139, 2022-05145, 2022-05146,
2022-05147, 2022-05148, 2022-05149, 2022-05150,
2022-05151, 2022-05221, 2022-05270, 2022-05403,
2022-06402, 2022-06403, 2022-06404, 2022-06405,
2022-06406, 2022-06407, 2022-06408, 2022-06409,
2022-06411, 2022-06412, 2022-06413, 2022-06414,
2022-06415, 2022-06609, 2022-06617, 2022-06779,
2022-06895, 2022-06896, 2022-06897, 2022-06898,
2022-06899, 2022-06900, 2022-06901, 2022-06902,
2022-06903, 2022-06904, 2022-06905, 2022-06906,
2022-06907, 2022-06908, 2022-06909, 2022-06910,
2022-06911, 2022-06912, 2022-06915, 2022-07340,
2022-07636, 2022-08022, 2022-08024, 2022-08036,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2022-08054, 2022-08055, 2022-08056, 2022-08060,
2022-08061, 2022-08062, 2022-08066, 2022-08069,
2022-08071, 2022-08073, 2022-08076, 2022-08078,
2023-00044, 2023-00046, 2023-00049, 2023-00054,
2023-00055, 2023-00056, 2023-00058, 2023-00060,
2023-00061, 2023-00062, 2023-00063, 2023-00064,
2023-00065, 2023-00066, 2023-00083, 2023-00179,
2023-00180, 2023-00399, 2023-00418, 2023-00518,
2023-00623, 2023-00726, 2023-00792, 2023-01008,
2023-01026, 2023-01215, 2023-01298, 2023-01303,
2023-01304, 2023-01305, 2023-01306, 2023-01313,
2023-01315, 2023-01316, 2023-01317, 2023-01343,
2023-01700, 2023-01702, 2023-01703, 2023-01705,
2023-01707, 2023-01709, 2023-01712, 2023-01716,
2023-01717, 2023-01726, 2023-01729, 2023-01731,
2023-01773, 2023-01774, 2023-01972, 2023-01989,
2023-02142, 2023-02169, 2023-02251
Corrective Action
Documents
Resulting from
Inspection
CR-WF3-YYYY-
NNNNN
2025-01683, 2025-01690, 2025-01787, 2025-01810,
2025-01820, 2025-01823, 2025-01851, 2025-1904
Miscellaneous
Reply to a Notice of Violation, EA-24-052 Waterford Steam
Electric Station, Unit 3 Docket No. 50-382 Renewed Facility
Operating License No. NPF-38
11/19/2024
Miscellaneous
Weld package
CVC MVAAA2 16 A, pressurizer aux spray valve A
Procedures
CEP-BAC-001
Boric Acid Corrosion Control (BACC) Program Plan
Procedures
CEP-NDE-0404
Manual Ultrasonic Examination of Ferritic Piping Welds
(ASME XI)
Procedures
CEP-NDE-0407
Straight Beam Ultrasonic Examination of Bolts and Studs
(ASME XI)
Procedures
CEP-NDE-0423
Manual Ultrasonic Examination of Austenitic Piping Welds
(ASME XI)
Procedures
CEP-NDE-0641
Liquid Penetrant Examination (PT) for ASME Section XI
Procedures
CEP-NDE-0731
Magnetic Particle Examination (MT) for ASME Section XI
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
CEP-NDE-0901
VT-1 Examination
Procedures
CEP-NDE-0902
VT-2 Examination
Procedures
CEP-NDE-0903
VT-3 Examination
Procedures
CEP-WP-GWS-1
General Welding Standard ASME/ANSI
Procedures
Control of Hot Work and Ignition Sources
Procedures
Boric Acid Corrosion Control Program (BACCP)
Procedures
Entergy Nuclear Welding Program
Procedures
Primary Containment Leakage Rate Testing (Appendix J)
Procedures
Chemical Control Program
Procedures
Compressed Gas Cylinder Handling and Storage
Procedures
Fall Protection
Procedures
Control of Scaffolding
Procedures
SEP-APJ-005
Waterford 3 Primary Containment Leakage Rate Testing
(Appendix J) Program
Procedures
SEP-BAC-WF3-
001
Waterford 3 Boric Acid Corrosion Control Program (BACCP)
Program Section
Procedures
SEP-ISI-104
Program Section for ASME Section XI, Division 1 WF3
Inservice Inspection Program
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2024-05669
Procedures
MM-007-015
332
Procedures
OP-010-003
Plant Startup
371
Procedures
OP-010-004
Power Operations
350
Procedures
OP-010-005
Plant Shutdown
350
Procedures
OP-010-007
Plant Cooldown
347
Work Orders
54061139
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2025-00889, 2025-01024, 2025-01977, 2025-01980,
2025-02389, 2025-02583
Procedures
Quality Control Inspection Program
Work Orders
53026924, 54122524, 54163201, 54163202, 54189378
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2025-01400, 2025-02648, 2025-02653, 2025-02671,
2025-02673, 2025-02684, 2025-02706,
Procedures
Nuclear Risk Management Process
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Protected Equipment Postings
Procedures
OP-001-003
Plant Shutdown
371
Procedures
OP-006-009
Electrical Bus Outages
Procedures
PLG-009-014
Conduct of Planned Outages
323
Work Orders
54122485
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2025-00049, 2025-00951, 2025-00966, 2025-01126
Engineering
Changes
0054260118
Operability Input - Emergency Diesel Generator B Outboard
Generator Slinger Ring
Procedures
Preventive Maintenance Component Classification
Procedures
Preventive Maintenance Program
Drawings
B425-T122CA
Reactor Coolant Cold Leg 2A Temperature Channel A
Engineering
Changes
Temporary Modification of 2A Cold Leg Temperature Loop
RC IT0122-CA
Engineering
Changes
ESFAS Single Point Vulnerability Elimination Train B
Work Orders
54163201, 54163202, 54261266
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2025-01601, 2025-01627, 2025-01837, 2025-02165,
2025-02265, 2025-02422, 2025-02468, 2025-02617,
2025-02837
Procedures
Fatigue Management Program
Procedures
OP-001-003
Reactor Coolant System Drain Down
331
Procedures
OP-010-003
Plant Startup
371
Procedures
OP-010-005
Plant Shutdown
350
Procedures
OP-010-006
Outage Operations
347
Procedures
OP-903-24
Reactor Coolant System Water Inventory Balance
Procedures
PLG-009-014
Conduct of Planned Outages
323
Procedures
UNT-007-008
Control of Heavy and Critical Loads
324
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2025-01603, 2025-01681, 2025-01815, 2025-02174,
2025-02175, 2025-02543 2025-02563
Miscellaneous
W3-DBD-4
Design Basis Document: Component Cooling Water and
Auxiliary Component Cooling Water
307
Procedures
Motor Operated Valve Diagnostics
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
OP-903-014
Emergency Feedwater Flow Verification
319
Procedures
OP-903-033
Cold Shutdown IST Valve Tests
Procedures
OP-903-046
Emergency Feed Pump Operability Check
326
Procedures
OP-903-049
Component Cooling Water and Auxiliary Cooling Water Loop
Operability Check
Procedures
OP-903-050
Component Cooling Water and Auxiliary Component Cooling
Water Pump and Valve Operability Test
Procedures
OP-903-094
ESFAS Subgroup Relay Test - Operating
Procedures
OP-903-115
Train A Integrated Emergency Diesel Generator/Engineering
Safety Features Test
Procedures
OP-903-116
Train B Integrated Emergency Diesel Generator/Engineering
Safety Features Test
Procedures
OP-903-119
Secondary Auxiliaries Quarterly IST Valve Tests
Procedures
OP-903-121
Safety Systems Quarterly IST Valve Tests
Procedures
OP-903-121
Safety Systems Quarterly IST Valve Tests
Procedures
STA-001-001
Containment Air Lock Door Seal Leakage Test
304
Work Orders
00558906, 00582638, 54073316, 54082875, 54082906,
54140427, 54141427, 54180650, 54183293, 54244318,
54065513, 54065510, 54127031, 00579184, 00579185,
00579197, 54140427, 54209905, 54078303, 54078293,
54139211, 54135480, 54132130, 54131774, 54119240,
54141427, 54125344, 54085283, 54131751, 54078403,
54093506, 53020780, 54094363, 54135260, 00559200,
54084263, 54067334, 54067334, 54078411, 54183293,
54074533, 54082906, 54082875, 54180650, 54085176,
54282661, 54034262, 54149050, 54115250, 54074824,
54273789, 54127020, 54092060
ALARA Plans
RWP 2025-1702
ALARA Plan
04/26/2025
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2024-02475, 2024-02504, 2024-02827, 2024-03049,
2024-03360, 2024-03579, 2024-03580, 2024-04009,
2024-04655, 2024-04757, 2024-05200, 2024-05245,
2024-05671, 2024-05876, 2025-00019, 2025-00370,
2025-00718, 2025-00846, 2025-00929, 2025-01075,
2025-01197, 2025-01245, 2025-01247
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
CR-WF3-YYYY-
NNNNN
WF3-2025-01931, HQN-2025-00456
Miscellaneous
Waterford-3 RF26 RWP Status Report
05/08/2025
Procedures
Access Control for Radiologically Controlled Areas
Procedures
Radiation Protection Posting
Procedures
ALARA Program
Procedures
Radioactive Material Control
Procedures
Alpha Monitoring
Procedures
Radiological Controls for Highly Radioactive Objects
Procedures
Air Sampling
Procedures
HP-001-213
Control of Reactor Containment Building Power Entries
306
Procedures
RF-001-012
Upper Guide Structure
322
Radiation
Surveys
RAB +21 Decontamination Area
07/02/2024
Radiation
Surveys
Resin Sluice - post flushing of sluicing CVC IX C to Spent
Resin Tank
04/09/2025
Radiation
Surveys
PA/Outside RM Storage Area - quarterly survey
04/15/2025
Radiation
Surveys
Rad Waste Compactor Building
04/25/2025
Radiation
Surveys
-4' Reactor Containment Building - RF 26 initial entry
04/26/2025
Radiation
Surveys
+21' Reactor Containment Building - RF 26 initial entry
04/26/2025
Radiation
Surveys
+46' Reactor Containment Building - RF 26 initial entry
04/26/2025
Radiation
Surveys
-11' Reactor Containment Building - RF 26 initial entry
04/26/2025
Radiation
Surveys
Radwaste Solidification Building - quarterly survey
04/28/2025
Radiation
Surveys
Upper Guide Structure Work Platform - post thimble support
plate move to upper position
05/05/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation
Surveys
Regenerative Heat Exchanger (Upper Level) pre and post
shielding survey
05/05/2025
Radiation
Surveys
WF3-AS-011625-
0003
Noble Gas Sample Report - Containment RCB +21
01/16/2025
Radiation
Surveys
WF3-AS-031025-
0025
Particulate Sample Report - charging pump 'A' disassembly
03/10/2025
Radiation
Surveys
WF3-AS-031025-
0028
Particulate Sample Report - charging pump A disassembly -
35 RAB
03/10/2025
Radiation
Surveys
WF3-AS-061124-
0171
Noble Gas Sample Report - RDT - 11 RCB
06/11/2024
Radiation
Surveys
WF3-AS-073124-
0176
Particulate Sample Report - charging pump 'A' plunger pull
07/31/2024
Radiation
Surveys
WF3-AS-080124-
0179
Particulate Sample Report - charging pump A repacking
(seal water box) -35' RAB
08/01/2024
Radiation Work
Permits (RWPs)
2025-1405-02
Tours and Inspections in High Radiation Areas
Radiation Work
Permits (RWPs)
2025-1454-02
RF26 - Valve Maintenance Activities - Task 2: Valve
Maintenance Activities in High Radiation Areas
Radiation Work
Permits (RWPs)
2025-1454-04
RF26 - Valve Maintenance Activities - Task 4: Valve
Maintenance Activities in the Regen Hx Room (HRA)
Radiation Work
Permits (RWPs)
2025-1702-07
RF26 - Reactor Disassembly (to include all associated work
activities) - Task 7: ***MEDIUM RISK*** Remove Upper
Guide Structure and Store in the Lower Refuel Cavity
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2022-02868, 2022-03587, 2022-05994, 2022-05996,
2022-05998, 2023-00623, 2023-16705, 2023-17095,
2023-17136, 2024-03049, 2024-03266, 2024-03272,
2024-03312, 2024-03579, 2024-03942, 2024-04251,
2024-04308, 2024-04494, 2024-04602, 2025-00080,
2025-00536, 2025-00565, 2025-00572, 2025-00586,
2025-00607, 2025-00870, 2025-00931, 2025-00933,
2025-00935, 2025-01247
Corrective Action
Documents
Resulting from
CR-WF3-YYYY-
NNNNN
2025-02029
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Inspection
Engineering
Evaluations
2024-0308-02
TEDE-ALARA Evaluation: Forced Outage - Removal of the
RCP Seals
04/09/2024
Engineering
Evaluations
2024-0312-01
TEDE-ALARA Evaluation: Forced Outage - Work on Highly
Contaminated Valves in the Regen Heat Exchanger Room
04/17/2024
Engineering
Evaluations
2025-1454-02
TEDE-ALARA Evaluation: Valve Inspection, Testing, and
Repair
10/24/2024
Engineering
Evaluations
2025-1708-02/03
TEDE-ALARA Evaluation: Refuel 26 - Reactor Cavity / UGS
Structure ICI Activities and ICI Guide Tube Measurements
04/26/2025
Engineering
Evaluations
2025-1900-04
TEDE-ALARA Evaluation: Refuel 26 - Emergent Work -
Insulation Removal from RCP
05/07/2025
Miscellaneous
Employee SCBA Mask Sizes
04/14/2025
Miscellaneous
Respiratory Protection Equipment - Monthly Inspection
04/16/2025
Miscellaneous
WSES-FSAR-Unit-3, Table 12,5-4, Health Physics
Equipment
305
Miscellaneous
WSES-FSAR-Unit-3, Equipment, Instrumentation, and
Facilities
305
Miscellaneous
Inventory Checklist for OSC Storage Rooms, Field Kit Back-
up for OSC, EOF Storage Locker, Ambulance Kit, Hospital
Locker, Security, Dosimetry Office, and RAB -4 Access
Control Point
03/26/2025
Miscellaneous
Training and Qualifications for Entergy Corporation
(AirHawk, FireHawk, SCBAs)
03/27/2025
Miscellaneous
220615042-01
Laboratory Report - Compressed Air/Gas Quality Testing
08/08/2024
Miscellaneous
71400941
MSA FireHawk M7 Air Mask Posi3 USB Test Results -
Complete SCBA Test, Unit 2, UEM-6119
02/01/2024
Miscellaneous
71403719
MSA FireHawk M7 Air Mask Posi3 USB Test Results -
Complete SCBA Test, Unit 66, UEM-6168
01/30/2024
Miscellaneous
Att. 9.5 to EN-RP-
502
Annual Respiratory Protection Equipment Inventory and
Inspection: Annual In-Service Inspection
01/15/2025
Miscellaneous
Ref. G-853
Fig. 03 Control Room Emergency Filtration Unit (HVC) High
Radiation / SIAS Mode
05/05/2025
Miscellaneous
Ref. G-853 SH1
Fig. 06 Controlled Ventilation Areas Filter Unit (CVAS)
05/05/2025
Miscellaneous
Ref. G-853 SH2
Fig. 03 Shield Building Ventilation Systems (SBV)
05/05/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Standard Operating Procedure for Emergency Breathing Air
Supply
Procedures
Air Sampling
Procedures
Operation and Maintenance of HEPA Vacuum Cleaners and
HEPA Ventilation Units
Procedures
Respiratory Protection Program
Procedures
Inspection and Maintenance of Respiratory Protection
Equipment
Procedures
EN-RP-502-01
FireHawk M7 SCBA
Procedures
Selection, Issue and Use of Respiratory Protection
Equipment
Procedures
Breathing Air
Procedures
PortaCount Respirator Fit Testing
Procedures
HP-002-603
Inspection and Use of Control Room EBA filtration Panel
Radiation
Surveys
-4 Reactor Containment Building
04/09/2025
Radiation
Surveys
Pre-Job Survey for Insulation Removal
05/06/2025
Radiation
Surveys
WF3-AS-031025-
0026
20250004/4 Maintenance Activities, Unit 1 RAB -35
03/10/2025
Radiation
Surveys
WF3-AS-031025-
0027
20250004/4 Maintenance Activities, Unit 1 RAB -35
03/10/2025
Radiation
Surveys
WF3-AS-050625-
0184
20251454/4 - RF26 Valve Maintenance Activities, Unit 1
RCB +21
05/06/2025
Radiation
Surveys
WF3-AS-050725-
0209
20251900/4 - RF26 Emergent Work - Minor Maintenance
Activities, Unit 1 RCB D-Rings
05/07/2025
Radiation
Surveys
WF3-AS-050725-
0209
Lapel Sampling: 20251900/4 RF-26 Emergent Work - Minor
Maintenance Activities, Unit 1 RCB D-Rings
05/07/2025
Radiation
Surveys
WF3-AS-050725-
0210
Lapel Sampling: 20251900/4 RF-26 Emergent Work - Minor
Maintenance Activities, Unit 1 RCB D-Rings
05/07/2025
Radiation
Surveys
WF3-AS-101923-
0278
20230702/2 Refuel 25 - Disassembly of Reactor Head and
All Associated Work Activities, Unit 1 RCB +46
10/19/2023
Radiation Work
Permits (RWPs)
20251405
RF26 Tours and Inspections
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation Work
Permits (RWPs)
20251454
RF26 - Valve Maintenance Activities
Radiation Work
Permits (RWPs)
20251455
RF26 - Remove/Replace the Pressurizer Manway and the
Pressurizer Safety Relief Valves
Radiation Work
Permits (RWPs)
20251702
RF26 - Reactor Disassembly (to include all associated work
activities)
Radiation Work
Permits (RWPs)
20251900
RF26 - Emergent Work - Minor Maintenance Activities
Self-Assessments LO-WF3-2024-
00063
In-Plant Airborne Radioactivity Control and Mitigation (IP 71124.03)
02/19/2025
Work Orders
53015928_1
HVCMFAN0010 A - Obtain Charcoal Test Canister for
Analysis
05/28/2024
Work Orders
53017382_1
HVCMFAN0010 A - Leak Test HEPA Filters and Charcoal
Absorber
05/29/2024
Work Orders
53023258_1
HVCMFAN0010 B - Leak Test HEPA Filters and Charcoal
Absorber
05/22/2024
Work Orders
53023327_1
HVCMFAN0010 B - Obtain Charcoal Test Canister for
Analysis
05/20/2024
Work Orders
53025177_1
HVRMFAN0021 B - Leak Test HEPA Filters and Charcoal
Absorber
05/28/2024
Work Orders
53034403_1
SBVMFAN0001 A - Leak Test HEPA Filters and Charcoal
Absorber
12/05/2024
71151
Miscellaneous
Annual Radioactive Effluent Release Report (ARERR) 2024
04/30/2025
71151
Miscellaneous
NRC Performance Indicator (Pl) Data - 2nd Quarter 2024
07/18/2024
71151
Miscellaneous
NRC Performance Indicator (Pl) Data - 3rd Quarter 2024
10/16/2024
71151
Miscellaneous
NRC Performance Indicator (Pl) Data - 4th Quarter 2024
01/17/2025
71151
Procedures
EN-FAP-OM-005
Nuclear Performance Indicator Program
71151
Procedures
Regulatory Performance Indicator Process
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2023-15311, 2025-00469, 2025-00472
Miscellaneous
PSA-WF3-01-SY
WF3 PSA Model Systems Analysis Notebook
Miscellaneous
SD-EDG
Emergency Diesel Generator System Description
Procedures
Engineering Change Process
Procedures
Corrective Action Program
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Causal Analysis Process
Procedures
Procedures
OP-002-001
Auxiliary Component Cooling Water
320
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2024, 00655, 2025-00951, 2025-01071, 2025-01090,
2025-01118, 2025-01137, 2025-01326, 2025-01407,
2025-01434, 2025-01539, 2025-02175, 2025-02272,
2025-02277, 2025-02280, 2025-02293, 2025-02294,
2025-02295, 2025-02300, 2025-02356, 2025-02404,
2025-02543, 2025-02544, 2025-02580, 2025-02997,
2025-03131, 2025-03165
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2024-02523
Procedures
EN-FAP-OM-016
Performance Management Processes and Practices
Procedures
OP-009-003
Emergency Feedwater
313
Procedures
OP-903-014
Emergency Feedwater Flow Verification
318
Procedures
OP-903-014
Emergency Feedwater Flow Verification
319