IR 05000382/2025002: Difference between revisions

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| number = ML26030A251
| number = ML26030A251
| issue date = 02/02/2026
| issue date = 02/02/2026
| title = Waterford Steam Electric Station, Unit 3 - Amended Integrated Inspection Report 05000382/2025002
| title = Amended Integrated Inspection Report 05000382/2025002
| author name = Dixon J
| author name = Dixon J
| author affiliation = NRC/RGN-IV/DORS/PBD
| author affiliation = NRC/RGN-IV/DORS/PBD
Line 67: Line 67:
Division of Operating Reactor Safety
Division of Operating Reactor Safety


SUMMARY
=SUMMARY=
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees
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.
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
===List of Findings and Violations===
program for overseeing the safe operation of commercial nuclear power reactors. Refer to
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 NCV 05000382/2025002-01 Open/Closed None (NPP)71111.15 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.
https://www.nrc.gov/reactors/operating/oversight.html for more information.
 
List of Findings and Violations
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 Initiating Events Green NCV 05000382/2025002-02 Open/Closed None (NPP)71153 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.
Preventive Maintenance Planning Failed to Prevent a Safety-Related Valve Failure and
 
Inoperability of an Emergency Diesel Generator
===Additional Tracking Items===
Cornerstone
Type Issue Number Title Report Section Status LER 05000382/2024-003-00 Automatic EFAS Actuation During Surveillance Test 71153 Closed NOV 05000382/2024013-01 Failure to Perform an Adequate Steam Generator (SG) Operational Assessment EA-24-052 71153 Closed
Significance
 
Cross-Cutting
=PLANT STATUS=
Aspect
 
Report
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.
Section
 
Mitigating
==INSPECTION SCOPES==
Systems
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, 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.
Green
 
NCV 05000382/2025002-01
==REACTOR SAFETY==
Open/Closed
==71111.01 - Adverse Weather Protection==
None (NPP)
===Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)===
71111.15
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:
The inspectors reviewed a self-revealed Green finding and associated non-cited violation of
(1)ultimate heat sink, safety-related switchgear, safety injection, and emergency diesel generators on June 27, 2025
10 CFR 50, Appendix B, Criterion V Instructions, Procedures and Drawings. Specifically, the
 
licensee failed to develop and implement preventive maintenance strategies for the
==71111.04 - Equipment Alignment==
condensate makeup solenoids in the emergency diesel generators in accordance with
===Partial Walkdown Sample (IP Section 03.01) (1 Sample)===
procedure EN-DC-324, Preventive Maintenance Program.
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
Failure to Establish Adequate Surveillance Initial Conditions Resulted in Inadvertent
(1)emergency feedwater trains A and B on June 2, 2025
Emergency Feedwater Isolation System Actuation and Reactor Protection Actuation
 
Cornerstone
===Complete Walkdown Sample (IP Section 03.02) (1 Sample)===
Significance
: (1) The inspectors evaluated system configurations during a complete walkdown of the 4160VAC train A safety bus system on May 28, 2025.
Cross-Cutting
 
Aspect
==71111.05 - Fire Protection==
Report
===Fire Area Walkdown and Inspection Sample (IP Section 03.01) (9 Samples)===
Section
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:
Initiating Events
(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)
Green
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.
NCV 05000382/2025002-02
Open/Closed
None (NPP)
71153
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
LER
05000382/2024-003-00
Automatic EFAS Actuation
During Surveillance Test  


71153
PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding
Closed
NOV
05000382/2024013-01
Failure to Perform an
Adequate Steam Generator
(SG) Operational
Assessment EA-24-052
71153
Closed


PLANT STATUS
===Activities (IP Section 03.01) (1 Sample)===
Unit 3 began the inspection period at 94 percent rated thermal power. On April 26, 2025, the
The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:
unit was shut down for refueling outage 26. On June 8, 2025, the unit restarted and reached
: (1) Ultrasonic Examination
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 D, 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
===1. chemical and volume control, MVAAA216A, weld SW-18, pipe to valve===
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (9 Samples)
===2. chemical and volume control, MVAAA216A, weld SW-19, pipe to valve===
The inspectors evaluated the implementation of the fire protection program by conducting a
===3. shutdown cooling, weld 21-004, pipe to pipe===
walkdown and performing a review to verify program compliance, equipment functionality,
===4. shutdown cooling, weld 21-007, elbow to pipe===
material condition, and operational readiness of the following fire areas:
===5. shutdown cooling, weld 21-009, pipe to elbow===
(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
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


===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
Dye Penetrant Examination
1.
 
chemical and volume control, MVAAA216A, weld SW-18, pipe to valve
===1. chemical and volume control, MVAAA216A, weld SW-18, pipe to valve===
2.
===2. chemical and volume control, MVAAA216A, weld SW-19, pipe to valve===
chemical and volume control, MVAAA216A, weld SW-19, pipe to valve
===3. chemical and volume control, FW-1, seal weld on CVCISV0216 A valve===
3.
===4. containment spray, support CSRR035A===
chemical and volume control, FW-1, seal weld on CVCISV0216 A valve
4.
containment spray, support CSRR035A
Visual 2 Examination
Visual 2 Examination
1.
 
chemical and volume control, MVAAA2 16 A, pressurizer auxiliary spray
===1. chemical and volume control, MVAAA2 16 A, pressurizer auxiliary spray===
valve A
valve A Visual 3 Examination
Visual 3 Examination
 
1.
===1. safety injection, pipe hangar SIRR-220===
safety injection, pipe hangar SIRR-220
===2. safety injection, pipe hangar SIRR-498===
2.
===3. containment spray, support CSRR035===
safety injection, pipe hangar SIRR-498
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:
3.
 
containment spray, support CSRR035
===1. CCRR-1184, rigid restraint EC 54082002 evaluated the support as acceptable===
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
to remain in service. Reference W-ISI-EV-23-002
2.
 
CCRR-0322 rigid restraint EC 54071759 evaluated the support as acceptable
===2. CCRR-0322 rigid restraint EC 54071759 evaluated the support as acceptable===
to remain in service. Reference W-ISI-EV-23-00 I
to remain in service. Reference W-ISI-EV-23-00 I
3.
 
CCRR-0393 rigid restraint EC 54088042 evaluated the support as acceptable
===3. CCRR-0393 rigid restraint EC 54088042 evaluated the support as acceptable===
to remain in service. Reference CR-WF3-2023-I 7773
to remain in service. Reference CR-WF3-2023-I 7773 Welding Activities
Welding Activities
 
1.
===1. gas tungsten arc welding===
gas tungsten arc welding
a.
a.
chemical and volume control, MVAAA216A, weld SW-18, pipe to valve
 
b.
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, MVAAA216A, weld SW-18, pipe to valve c.
chemical and volume control, MVAAA2 16A, weld FW-1, pressurizer
 
auxiliary spray valve A
chemical and volume control, MVAAA2 16A, weld FW-1, pressurizer auxiliary spray valve A d.
d.
 
extraction steam, ES-7101A/B, bypass line, FW-9
extraction steam, ES-7101A/B, bypass line, FW-9 e.
e.
 
extraction steam, ES-7101A/B, bypass line, FW-10
extraction steam, ES-7101A/B, bypass line, FW-10 PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection Activities (IP Section 03.02)
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.
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)
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
The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following screenings and evaluations:
through a review of the following screenings and evaluations:
(1)
(1)
1.
22-0020, CVCMVAAA115
2.
22-0037, SI MPMP0002-A
3.
23-0006, SI MVAAA205-A
4.
23-0014, CS MVAAA122-A
5.
23-0012, SI IFT 1307-A
6.
23-0017, CS MVAAA113-A


7.
===1. 22-0020, CVCMVAAA115===
23-0018, SI MVAAA416-B
===2. 22-0037, SI MPMP0002-A===
8.
===3. 23-0006, SI MVAAA205-A===
23-0021, SI MVAAA221-A
===4. 23-0014, CS MVAAA122-A===
9.
===5. 23-0012, SI IFT 1307-A===
24-0006, SI MVAAA115-A
===6. 23-0017, CS MVAAA113-A===
10. 24-0010, CVCMVAAA40631
===7. 23-0018, SI MVAAA416-B===
11. 24-0011, FSMPMP0003
===8. 23-0021, SI MVAAA221-A===
12. 24-0012, SI MVAAA2392
===9. 24-0006, SI MVAAA115-A===
13. 24-0013, RC MRCT0001/1RC42-1RL1
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)
14. 24-0014, RC MPMP0002-B
There was no ASME code required steam generator tube integrity inspection required this outage.
15. 24-0015, SI MVAAA407-A
 
16. 24-0016, SI MVAAA403-A
==71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance==
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)
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)
(1)
: (1) The inspectors observed and evaluated licensed operator performance in the control room during main steam safety valve simmer testing on April 23, 2025.
The inspectors observed and evaluated licensed operator performance in the control
: (2) The inspectors observed and evaluated licensed operator performance in the control room during reactor startup on June 6, 2025.
room during main steam safety valve simmer testing on April 23, 2025.
 
(2)
===Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)===
The inspectors observed and evaluated licensed operator performance in the control
: (1) The inspectors observed and evaluated licensed operator just in time training for reactor startup in the simulator on May 31, 2025.
room during reactor startup on June 6, 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


Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
==71111.15 - Operability Determinations and Functionality Assessments==
(1)
===Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)===
The inspectors observed and evaluated licensed operator just in time training for
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
reactor startup in the simulator on May 31, 2025.
(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
71111.12 - 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
==71111.18 - Plant Modifications==
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
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)
(1)
temporary wiring modification for cold-leg temperature input to core protection
(HRA) spent resin tank room on the -35' elevation of the reactor auxiliary building (2)
calculator A on May 2, 2025
(HRA) boric acid pre-concentration filter cubicles A and B on the -35' elevation of the reactor auxiliary building (3)
(2)
(HRA) purification ion exchanger rooms A and B on the -4' elevation of the reactor auxiliary building (4)
permanent modification of second permissive relay for engineered safety features
(HRA) chemical and volume control filter cubicle on the -4' elevation of the reactor auxiliary building (5)
actuation system train B main steam isolation signal and containment spray actuation
(HRA) process shield No.1 in the radwaste solidification building Radiation Worker Performance and Radiation Protection Technician Proficiency (IP
signal actuation relays to eliminate single point vulnerability on June 28, 2025
 
71111.20 - Refueling and Other Outage Activities
===Section 03.06) (1 Sample)===
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
: (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
(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)
==71124.03 - In-Plant Airborne Radioactivity Control and Mitigation==
safety injection valve SI-120A, safety injection recirculating header A to refueling
===Permanent Ventilation Systems (IP Section 03.01) (2 Samples)===
water storage pool upstream isolation valve, motor operated valve diagnostic test on
The inspectors evaluated the configuration of the following permanently installed ventilation systems:
May 9, 2025
(1)control room emergency filtration, units A and B (2)controlled ventilation areas filter, units A and B
(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)
===Temporary Ventilation Systems (IP Section 03.02) (2 Samples)===
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:
The inspectors evaluated the configuration of the following temporary ventilation systems:
(1)
(1)high-efficiency particulate air (HEPA) filter set up for decontamination work, May 5-6, 2025
high-efficiency particulate air (HEPA) filter set up for decontamination work, May 5-6,
: (2) HEPA filter usage for work associated with RWP 20251454, May 6, 2025
2025
 
(2)
===Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)===
HEPA filter usage for work associated with RWP 20251454, May 6, 2025
: (1) The inspectors evaluated the licensees use of respiratory protection devices.
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
 
(1)
===Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)===
The inspectors evaluated the licensees use of respiratory protection devices.
: (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)===
{{IP sample|IP=IP 71152|count=1}}
: (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.


Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)
===71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02) (2 Samples)===
(1)
{{IP sample|IP=IP 71153|count=2}}
The inspectors evaluated the licensees use and maintenance of self-contained
: (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
breathing apparatuses.
: (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.
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
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.
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
==INSPECTION RESULTS==
unplanned emergency diesel generator inoperabilities. These issues have resulted
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 NCV 05000382/2025002-01 Open/Closed None (NPP)71111.15 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.
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
=====Description:=====
Preventive Maintenance Planning Failed to Prevent a Safety-Related Valve Failure and
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.
Inoperability of an Emergency Diesel Generator
Cornerstone
Significance
Cross-Cutting
Aspect
Report
Section
Mitigating
Systems
Green
NCV 05000382/2025002-01
Open/Closed
None (NPP)
71111.15
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
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.
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
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.
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 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 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.
Corrective Action References: CR-WF3-2025-00951.
Performance Assessment:


Performance Deficiency: The failure to develop and implement a replacement preventive
=====Performance Assessment:=====
maintenance strategy for the condensate makeup solenoid coils was a performance
Performance Deficiency: The failure to develop and implement a replacement preventive maintenance strategy for the condensate makeup solenoid coils was a performance deficiency.
deficiency.
 
Screening: The inspectors determined the performance deficiency was more than minor
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.
because it was associated with the Equipment Performance attribute of the Mitigating
 
Systems cornerstone and adversely affected the cornerstone objective to ensure the
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 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
availability, reliability, and capability of systems that respond to initiating events to prevent
: (1) was not a deficiency affecting design or qualification of a mitigating system,
undesirable consequences. Specifically, the failure to properly implement replacement
: (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,
preventive maintenance strategies resulted in the failure of the condensate makeup valve
: (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,
coil, challenged the ability of the diesel to meet TS requirements, and resulted in inoperability
: (4) does not represent a loss of the PRA function of two separate TS systems for greater than 24 hours,
of EDG A.
: (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 hours, and
Significance: The inspectors assessed the significance of the finding using IMC 0609
: (6) does not result in the loss of a high safety-significant, non-TS train for greater than 3 days.
Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The
 
inspectors determined the finding impacted mitigating systems and used exhibit 2 to evaluate
Cross-Cutting Aspect: No cross-cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance.
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,  
=====Enforcement:=====
(2) does not represent a loss of the probability risk analysis (PRA) function of a single train
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.
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,  
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.
(4) does not represent a loss of the PRA function of two separate TS systems for greater than
 
24 hours, (5) does not represent a loss of PRA system and/or function as defined by the plant
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
risk information e-book or the licensees PRA for greater than 24 hours, and (6) does not
 
result in the loss of a high safety-significant, non-TS train for greater than 3 days.
Minor Violation 71152A 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.
Cross-Cutting Aspect: No cross-cutting aspect was assigned to this finding because the
 
inspectors determined the finding did not reflect present licensee performance.
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.
Enforcement:
 
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.


Violation: Title 10 CFR Part 50, Appendix B, Criterion V Instructions, Procedures and
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.
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
=====Enforcement:=====
establish a preventive maintenance strategy in accordance with their quality procedure for the
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.
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
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 Initiating Events Green NCV 05000382/2025002-02 Open/Closed None (NPP)71153 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.
inoperability of EDG A.
 
Enforcement Action: This violation is being treated as a non-cited violation, consistent with
=====Description:=====
Section 2.3.2 of the Enforcement Policy.
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.
Minor Violation
71152A
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
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.
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
Initiating Events
Green
NCV 05000382/2025002-02
Open/Closed
None (NPP)
71153
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
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.
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 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 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
Corrective Action References: CR-WF3-2024-02523
Performance Assessment:


Performance Deficiency: The failure to implement adequate initial conditions for the
=====Performance Assessment:=====
performance of a surveillance affecting safety-related equipment was a performance
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 of both EFAS and RPS.
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
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.
water level dropping below the EFAS and RPS trip setpoint causing an inadvertent initiation
 
of both EFAS and RPS.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power.


Screening: The inspectors determined the performance deficiency was more than minor
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.
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
Cross-Cutting Aspect: No cross-cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance.
Appendix A, 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
=====Enforcement:=====
written procedures shall be established, implemented, and maintained covering the
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.
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.
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
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.
for the startup, shutdown, and changing modes of operation should be prepared, as
 
appropriate, for the feedwater system.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
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
==EXIT MEETINGS AND DEBRIEFS==
feedwater system. Specifically, the licensee failed to establish adequate initial conditions for
The inspectors verified that no proprietary information was retained or documented in this report.
the performance of a surveillance for the emergency feedwater system which resulted in the
* 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.
steam generator 1 water level dropping below the EFAS and RPS trip setpoints and causing
* 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.
an inadvertent EFAS and RPS actuation.
* On July 21, 2025, the inspectors presented the integrated inspection results to Joseph Sullivan, Site Vice President, and other members of the licensee staff.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with
 
Section 2.3.2 of the Enforcement Policy.
=DOCUMENTS REVIEWED=
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
Inspection
Procedure
Procedure
Line 887: Line 397:
Miscellaneous
Miscellaneous
EN-WM-112,
EN-WM-112,
Attachment 5
Site Certification Letter and Seasonal Reliability Plan
Site Certification Letter and Seasonal Reliability Plan
71111.01
71111.01
Procedures
Procedures
EN-FAP-010
EN-FAP-010
Severe Weather Response
Severe Weather Response
71111.01
71111.01
Work Orders
Work Orders
5255494, 5419260, 54202873
255494, 5419260, 54202873
71111.04
71111.04
Corrective Action
Corrective Action
Line 903: Line 410:
CR-WF3-YYYY-
CR-WF3-YYYY-
NNNNN
NNNNN
2024-00759, 2024-00148, 2024-03504, 2025-01051,
24-00759, 2024-00148, 2024-03504, 2025-01051,
2025-01765, 2025-02626, 2025-02632, 2025-02706,
25-01765, 2025-02626, 2025-02632, 2025-02706,
71111.04
71111.04
Drawings
Drawings
1564-4331
1564-4331
4.16 KV Class 1E SWGR Installation Details
4.16 KV Class 1E SWGR Installation Details
71111.04
71111.04
Drawings
Drawings
1564-6242
1564-6242
4.16 KV Switchgear 3A2 Element Diagram, Sheet 1
4.16 KV Switchgear 3A2 Element Diagram, Sheet 1
71111.04
71111.04
Procedures
Procedures
Line 945: Line 450:
CR-WF3-YYYY-
CR-WF3-YYYY-
NNNNN
NNNNN
2022-03613, 2022-03592, 2024-01190, 2024-01330,
22-03613, 2022-03592, 2024-01190, 2024-01330,
2024-01684
24-01684
71111.05
71111.05
Fire Plans
Fire Plans
RAB 2-001
RAB 2-001
H&V Mechanical Room
H&V Mechanical Room
71111.05
71111.05
Fire Plans
Fire Plans
RAB 36-001
RAB 36-001
Safety Injection Pump Room A
Safety Injection Pump Room A
71111.05
71111.05
Fire Plans
Fire Plans
RAB 5-001
RAB 5-001
Electrical Penetration Room B
Electrical Penetration Room B
71111.05
71111.05
Fire Plans
Fire Plans
RAB 8A-001
RAB 8A-001
Switchgear Room A
Switchgear Room A
71111.05
71111.05
Fire Plans
Fire Plans
RAB 8C-001
RAB 8C-001
Switchgear Room A/B
Switchgear Room A/B
71111.05
71111.05
Fire Plans
Fire Plans
RAB-16-001
RAB-16-001
Emergency Diesel Generator 3A
Emergency Diesel Generator 3A
71111.05
71111.05
Fire Plans
Fire Plans
RAB-37-001
RAB-37-001
Motor Driven Emergency Feed Pump Room A
Motor Driven Emergency Feed Pump Room A
71111.05
71111.05
Procedures
Procedures
EN-EE-S-048-W
EN-EE-S-048-W
Fire Detector Replacement Standard
Fire Detector Replacement Standard
71111.05
71111.05
Procedures
Procedures
Line 997: Line 494:
CR-WF3-YYYY-
CR-WF3-YYYY-
NNNNN
NNNNN
2022-01839, 2022-01891, 2022-01900, 2022-01901,
22-01839, 2022-01891, 2022-01900, 2022-01901,
2022-01929, 2022-01945, 2022-01949, 2022-01960,
22-01929, 2022-01945, 2022-01949, 2022-01960,
2022-01977, 2022-01978, 2022-01979, 2022-01993,
22-01977, 2022-01978, 2022-01979, 2022-01993,
2022-02011, 2022-02012, 2022-02013, 2022-02014,
22-02011, 2022-02012, 2022-02013, 2022-02014,
2022-02015, 2022-02016, 2022-02017, 2022-02018,
22-02015, 2022-02016, 2022-02017, 2022-02018,
2022-02029, 2022-02030, 2022-02031, 2022-02032,
22-02029, 2022-02030, 2022-02031, 2022-02032,
2022-02142, 2022-02156, 2022-02178, 2022-02287,
22-02142, 2022-02156, 2022-02178, 2022-02287,
2022-02289, 2022-02291, 2022-02293, 2022-02295,  
22-02289, 2022-02291, 2022-02293, 2022-02295,
 
Inspection
Inspection
Procedure
Procedure
Line 1,013: Line 509:
Revision or
Revision or
Date
Date
2022-02296, 2022-02301, 2022-02302, 2022-02303,
22-02296, 2022-02301, 2022-02302, 2022-02303,
2022-02304, 2022-02307, 2022-02309, 2022-02310,
22-02304, 2022-02307, 2022-02309, 2022-02310,
2022-02312, 2022-02314, 2022-02385, 2022-02387,
22-02312, 2022-02314, 2022-02385, 2022-02387,
2022-02401, 2022-02449, 2022-02452, 2022-02461,
22-02401, 2022-02449, 2022-02452, 2022-02461,
2022-02462, 2022-02463, 2022-02491, 2022-02555,
22-02462, 2022-02463, 2022-02491, 2022-02555,
2022-02630, 2022-02639, 2022-02703, 2022-02730,
22-02630, 2022-02639, 2022-02703, 2022-02730,
2022-02731, 2022-02732, 2022-02736, 2022-02741,
22-02731, 2022-02732, 2022-02736, 2022-02741,
2022-02742, 2022-02814, 2022-02821, 2022-02937,
22-02742, 2022-02814, 2022-02821, 2022-02937,
2022-03003, 2022-03016, 2022-03017, 2022-03018,
22-03003, 2022-03016, 2022-03017, 2022-03018,
2022-03085, 2022-03086, 2022-03449, 2022-03452,
22-03085, 2022-03086, 2022-03449, 2022-03452,
2022-03501, 2022-03506, 2022-03846, 2022-03959,
22-03501, 2022-03506, 2022-03846, 2022-03959,
2022-03975, 2022-03979, 2022-04023, 2022-04178,
22-03975, 2022-03979, 2022-04023, 2022-04178,
2022-04279, 2022-04280, 2022-04290, 2022-04392,
22-04279, 2022-04280, 2022-04290, 2022-04392,
2022-04649, 2022-04650, 2022-04651, 2022-04656,
22-04649, 2022-04650, 2022-04651, 2022-04656,
2022-04658, 2022-04659, 2022-04661, 2022-04662,
22-04658, 2022-04659, 2022-04661, 2022-04662,
2022-04664, 2022-04665, 2022-04667, 2022-04670,
22-04664, 2022-04665, 2022-04667, 2022-04670,
2022-04672, 2022-04673, 2022-04675, 2022-04987,
22-04672, 2022-04673, 2022-04675, 2022-04987,
2022-04988, 2022-04989, 2022-04990, 2022-04992,
22-04988, 2022-04989, 2022-04990, 2022-04992,
2022-04993, 2022-04994, 2022-04995, 2022-04996,
22-04993, 2022-04994, 2022-04995, 2022-04996,
2022-04998, 2022-05000, 2022-05126, 2022-05132,
22-04998, 2022-05000, 2022-05126, 2022-05132,
2022-05133, 2022-05134, 2022-05135, 2022-05136,
22-05133, 2022-05134, 2022-05135, 2022-05136,
2022-05138, 2022-05139, 2022-05145, 2022-05146,
22-05138, 2022-05139, 2022-05145, 2022-05146,
2022-05147, 2022-05148, 2022-05149, 2022-05150,
22-05147, 2022-05148, 2022-05149, 2022-05150,
2022-05151, 2022-05221, 2022-05270, 2022-05403,
22-05151, 2022-05221, 2022-05270, 2022-05403,
2022-06402, 2022-06403, 2022-06404, 2022-06405,
22-06402, 2022-06403, 2022-06404, 2022-06405,
2022-06406, 2022-06407, 2022-06408, 2022-06409,
22-06406, 2022-06407, 2022-06408, 2022-06409,
2022-06411, 2022-06412, 2022-06413, 2022-06414,
22-06411, 2022-06412, 2022-06413, 2022-06414,
2022-06415, 2022-06609, 2022-06617, 2022-06779,
22-06415, 2022-06609, 2022-06617, 2022-06779,
2022-06895, 2022-06896, 2022-06897, 2022-06898,
22-06895, 2022-06896, 2022-06897, 2022-06898,
2022-06899, 2022-06900, 2022-06901, 2022-06902,
22-06899, 2022-06900, 2022-06901, 2022-06902,
2022-06903, 2022-06904, 2022-06905, 2022-06906,
22-06903, 2022-06904, 2022-06905, 2022-06906,
2022-06907, 2022-06908, 2022-06909, 2022-06910,
22-06907, 2022-06908, 2022-06909, 2022-06910,
2022-06911, 2022-06912, 2022-06915, 2022-07340,
22-06911, 2022-06912, 2022-06915, 2022-07340,
2022-07636, 2022-08022, 2022-08024, 2022-08036,  
22-07636, 2022-08022, 2022-08024, 2022-08036,
 
Inspection
Inspection
Procedure
Procedure
Line 1,055: Line 550:
Revision or
Revision or
Date
Date
2022-08054, 2022-08055, 2022-08056, 2022-08060,
22-08054, 2022-08055, 2022-08056, 2022-08060,
2022-08061, 2022-08062, 2022-08066, 2022-08069,
22-08061, 2022-08062, 2022-08066, 2022-08069,
2022-08071, 2022-08073, 2022-08076, 2022-08078,
22-08071, 2022-08073, 2022-08076, 2022-08078,
2023-00044, 2023-00046, 2023-00049, 2023-00054,
23-00044, 2023-00046, 2023-00049, 2023-00054,
2023-00055, 2023-00056, 2023-00058, 2023-00060,
23-00055, 2023-00056, 2023-00058, 2023-00060,
2023-00061, 2023-00062, 2023-00063, 2023-00064,
23-00061, 2023-00062, 2023-00063, 2023-00064,
2023-00065, 2023-00066, 2023-00083, 2023-00179,
23-00065, 2023-00066, 2023-00083, 2023-00179,
2023-00180, 2023-00399, 2023-00418, 2023-00518,
23-00180, 2023-00399, 2023-00418, 2023-00518,
2023-00623, 2023-00726, 2023-00792, 2023-01008,
23-00623, 2023-00726, 2023-00792, 2023-01008,
2023-01026, 2023-01215, 2023-01298, 2023-01303,
23-01026, 2023-01215, 2023-01298, 2023-01303,
2023-01304, 2023-01305, 2023-01306, 2023-01313,
23-01304, 2023-01305, 2023-01306, 2023-01313,
2023-01315, 2023-01316, 2023-01317, 2023-01343,
23-01315, 2023-01316, 2023-01317, 2023-01343,
2023-01700, 2023-01702, 2023-01703, 2023-01705,
23-01700, 2023-01702, 2023-01703, 2023-01705,
2023-01707, 2023-01709, 2023-01712, 2023-01716,
23-01707, 2023-01709, 2023-01712, 2023-01716,
2023-01717, 2023-01726, 2023-01729, 2023-01731,
23-01717, 2023-01726, 2023-01729, 2023-01731,
2023-01773, 2023-01774, 2023-01972, 2023-01989,
23-01773, 2023-01774, 2023-01972, 2023-01989,
2023-02142, 2023-02169, 2023-02251
23-02142, 2023-02169, 2023-02251
71111.08P
71111.08P
Corrective Action
Corrective Action
Line 1,079: Line 574:
CR-WF3-YYYY-
CR-WF3-YYYY-
NNNNN
NNNNN
2025-01683, 2025-01690, 2025-01787, 2025-01810,
25-01683, 2025-01690, 2025-01787, 2025-01810,
2025-01820, 2025-01823, 2025-01851, 2025-1904
25-01820, 2025-01823, 2025-01851, 2025-1904
71111.08P
71111.08P
Miscellaneous
Miscellaneous
Line 1,092: Line 587:
Weld package
Weld package
CVC MVAAA2 16 A, pressurizer aux spray valve A
CVC MVAAA2 16 A, pressurizer aux spray valve A
71111.08P
71111.08P
Procedures
Procedures
CEP-BAC-001
CEP-BAC-001
Boric Acid Corrosion Control (BACC) Program Plan
Boric Acid Corrosion Control (BACC) Program Plan
71111.08P
71111.08P
Procedures
Procedures
Line 1,103: Line 596:
Manual Ultrasonic Examination of Ferritic Piping Welds  
Manual Ultrasonic Examination of Ferritic Piping Welds  
(ASME XI)
(ASME XI)
71111.08P
71111.08P
Procedures
Procedures
Line 1,109: Line 601:
Straight Beam Ultrasonic Examination of Bolts and Studs  
Straight Beam Ultrasonic Examination of Bolts and Studs  
(ASME XI)
(ASME XI)
71111.08P
71111.08P
Procedures
Procedures
Line 1,115: Line 606:
Manual Ultrasonic Examination of Austenitic Piping Welds  
Manual Ultrasonic Examination of Austenitic Piping Welds  
(ASME XI)
(ASME XI)
71111.08P
71111.08P
Procedures
Procedures
CEP-NDE-0641
CEP-NDE-0641
Liquid Penetrant Examination (PT) for ASME Section XI
Liquid Penetrant Examination (PT) for ASME Section XI
71111.08P
71111.08P
Procedures
Procedures
Line 1,137: Line 626:
CEP-NDE-0901
CEP-NDE-0901
VT-1 Examination
VT-1 Examination
71111.08P
71111.08P
Procedures
Procedures
CEP-NDE-0902
CEP-NDE-0902
VT-2 Examination
VT-2 Examination
71111.08P
71111.08P
Procedures
Procedures
CEP-NDE-0903
CEP-NDE-0903
VT-3 Examination
VT-3 Examination
71111.08P
71111.08P
Procedures
Procedures
CEP-WP-GWS-1
CEP-WP-GWS-1
General Welding Standard ASME/ANSI
General Welding Standard ASME/ANSI
71111.08P
71111.08P
Procedures
Procedures
EN-DC-127
EN-DC-127
Control of Hot Work and Ignition Sources  
Control of Hot Work and Ignition Sources
 
71111.08P
71111.08P
Procedures
Procedures
EN-DC-319
EN-DC-319
Boric Acid Corrosion Control Program (BACCP)
Boric Acid Corrosion Control Program (BACCP)
71111.08P
71111.08P
Procedures
Procedures
EN-DC-328
EN-DC-328
Entergy Nuclear Welding Program
Entergy Nuclear Welding Program
71111.08P
71111.08P
Procedures
Procedures
EN-DC-334
EN-DC-334
Primary Containment Leakage Rate Testing (Appendix J)
Primary Containment Leakage Rate Testing (Appendix J)
71111.08P
71111.08P
Procedures
Procedures
EN-EV-112
EN-EV-112
Chemical Control Program
Chemical Control Program
71111.08P
71111.08P
Procedures
Procedures
EN-IS-109
EN-IS-109
Compressed Gas Cylinder Handling and Storage
Compressed Gas Cylinder Handling and Storage
71111.08P
71111.08P
Procedures
Procedures
EN-IS-114
EN-IS-114
Fall Protection
Fall Protection
71111.08P
71111.08P
Procedures
Procedures
EN-MA-133
EN-MA-133
Control of Scaffolding
Control of Scaffolding
71111.08P
71111.08P
Procedures
Procedures
Line 1,198: Line 675:
Waterford 3 Primary Containment Leakage Rate Testing  
Waterford 3 Primary Containment Leakage Rate Testing  
(Appendix J) Program
(Appendix J) Program
71111.08P
71111.08P
Procedures
Procedures
Line 1,205: Line 681:
Waterford 3 Boric Acid Corrosion Control Program (BACCP)
Waterford 3 Boric Acid Corrosion Control Program (BACCP)
Program Section
Program Section
71111.08P
71111.08P
Procedures
Procedures
Line 1,211: Line 686:
Program Section for ASME Section XI, Division 1 WF3
Program Section for ASME Section XI, Division 1 WF3
Inservice Inspection Program
Inservice Inspection Program
71111.11Q
71111.11Q
Corrective Action
Corrective Action
Line 1,217: Line 691:
CR-WF3-YYYY-
CR-WF3-YYYY-
NNNNN
NNNNN
2024-05669
24-05669
71111.11Q
71111.11Q
Procedures
Procedures
MM-007-015
MM-007-015
Main Steam Safety Valve Test
Main Steam Safety Valve Test
332
2
71111.11Q
71111.11Q
Procedures
Procedures
Line 1,251: Line 725:
CR-WF3-YYYY-
CR-WF3-YYYY-
NNNNN
NNNNN
2025-00889, 2025-01024, 2025-01977, 2025-01980,
25-00889, 2025-01024, 2025-01977, 2025-01980,
2025-02389, 2025-02583
25-02389, 2025-02583
71111.12
71111.12
Procedures
Procedures
EN-QV-102
EN-QV-102
Quality Control Inspection Program
Quality Control Inspection Program
71111.12
71111.12
Work Orders
Work Orders
Line 1,266: Line 739:
CR-WF3-YYYY-
CR-WF3-YYYY-
NNNNN
NNNNN
2025-01400, 2025-02648, 2025-02653, 2025-02671,
25-01400, 2025-02648, 2025-02653, 2025-02671,
2025-02673, 2025-02684, 2025-02706,
25-02673, 2025-02684, 2025-02706,
71111.13
71111.13
Procedures
Procedures
Line 1,284: Line 757:
EN-OP-119
EN-OP-119
Protected Equipment Postings
Protected Equipment Postings
71111.13
71111.13
Procedures
Procedures
Line 1,294: Line 766:
OP-006-009
OP-006-009
Electrical Bus Outages
Electrical Bus Outages
71111.13
71111.13
Procedures
Procedures
PLG-009-014
PLG-009-014
Conduct of Planned Outages
Conduct of Planned Outages
323
23
71111.13
71111.13
Work Orders
Work Orders
Line 1,308: Line 779:
CR-WF3-YYYY-
CR-WF3-YYYY-
NNNNN
NNNNN
2025-00049, 2025-00951, 2025-00966, 2025-01126
25-00049, 2025-00951, 2025-00966, 2025-01126
71111.15
71111.15
Engineering
Engineering
Line 1,319: Line 790:
EN-DC-153
EN-DC-153
Preventive Maintenance Component Classification
Preventive Maintenance Component Classification
71111.15
71111.15
Procedures
Procedures
EN-DC-324
EN-DC-324
Preventive Maintenance Program
Preventive Maintenance Program
71111.18
71111.18
Drawings
Drawings
B425-T122CA
B425-T122CA
Reactor Coolant Cold Leg 2A Temperature Channel A
Reactor Coolant Cold Leg 2A Temperature Channel A
71111.18
71111.18
Engineering
Engineering
Line 1,336: Line 804:
Temporary Modification of 2A Cold Leg Temperature Loop
Temporary Modification of 2A Cold Leg Temperature Loop
RC IT0122-CA
RC IT0122-CA
71111.18
71111.18
Engineering
Engineering
Line 1,342: Line 809:
EC-54172687
EC-54172687
ESFAS Single Point Vulnerability Elimination Train B
ESFAS Single Point Vulnerability Elimination Train B
71111.18
71111.18
Work Orders
Work Orders
Line 1,351: Line 817:
CR-WF3-YYYY-
CR-WF3-YYYY-
NNNNN
NNNNN
2025-01601, 2025-01627, 2025-01837, 2025-02165,
25-01601, 2025-01627, 2025-01837, 2025-02165,
2025-02265, 2025-02422, 2025-02468, 2025-02617,
25-02265, 2025-02422, 2025-02468, 2025-02617,
2025-02837
25-02837
71111.20
71111.20
Procedures
Procedures
EN-OM-123
EN-OM-123
Fatigue Management Program
Fatigue Management Program
71111.20
71111.20
Procedures
Procedures
Line 1,383: Line 848:
OP-903-24
OP-903-24
Reactor Coolant System Water Inventory Balance
Reactor Coolant System Water Inventory Balance
71111.20
71111.20
Procedures
Procedures
PLG-009-014
PLG-009-014
Conduct of Planned Outages
Conduct of Planned Outages
323
23
71111.20
71111.20
Procedures
Procedures
UNT-007-008
UNT-007-008
Control of Heavy and Critical Loads
Control of Heavy and Critical Loads
324
24
71111.24
71111.24
Corrective Action
Corrective Action
Line 1,399: Line 863:
CR-WF3-YYYY-
CR-WF3-YYYY-
NNNNN
NNNNN
2025-01603, 2025-01681, 2025-01815, 2025-02174,
25-01603, 2025-01681, 2025-01815, 2025-02174,
2025-02175, 2025-02543 2025-02563
25-02175, 2025-02543 2025-02563
71111.24
71111.24
Miscellaneous
Miscellaneous
Line 1,428: Line 892:
OP-903-033
OP-903-033
Cold Shutdown IST Valve Tests
Cold Shutdown IST Valve Tests
71111.24
71111.24
Procedures
Procedures
OP-903-046
OP-903-046
Emergency Feed Pump Operability Check
Emergency Feed Pump Operability Check
326
26
71111.24
71111.24
Procedures
Procedures
Line 1,439: Line 902:
Component Cooling Water and Auxiliary Cooling Water Loop
Component Cooling Water and Auxiliary Cooling Water Loop
Operability Check
Operability Check
71111.24
71111.24
Procedures
Procedures
OP-903-050
OP-903-050
Component Cooling Water and Auxiliary Component Cooling
Component Cooling Water and Auxiliary Component Cooling
Water Pump and Valve Operability Test  
Water Pump and Valve Operability Test
 
71111.24
71111.24
Procedures
Procedures
OP-903-094
OP-903-094
ESFAS Subgroup Relay Test - Operating
ESFAS Subgroup Relay Test - Operating
71111.24
71111.24
Procedures
Procedures
Line 1,456: Line 916:
Train A Integrated Emergency Diesel Generator/Engineering
Train A Integrated Emergency Diesel Generator/Engineering
Safety Features Test
Safety Features Test
71111.24
71111.24
Procedures
Procedures
Line 1,462: Line 921:
Train B Integrated Emergency Diesel Generator/Engineering
Train B Integrated Emergency Diesel Generator/Engineering
Safety Features Test
Safety Features Test
71111.24
71111.24
Procedures
Procedures
OP-903-119
OP-903-119
Secondary Auxiliaries Quarterly IST Valve Tests
Secondary Auxiliaries Quarterly IST Valve Tests
71111.24
71111.24
Procedures
Procedures
OP-903-121
OP-903-121
Safety Systems Quarterly IST Valve Tests
Safety Systems Quarterly IST Valve Tests
71111.24
71111.24
Procedures
Procedures
OP-903-121
OP-903-121
Safety Systems Quarterly IST Valve Tests
Safety Systems Quarterly IST Valve Tests
71111.24
71111.24
Procedures
Procedures
Line 1,494: Line 949:
54084263, 54067334, 54067334, 54078411, 54183293,
54084263, 54067334, 54067334, 54078411, 54183293,
54074533, 54082906, 54082875, 54180650, 54085176,
54074533, 54082906, 54082875, 54180650, 54085176,
54282661, 54034262, 54149050, 54115250, 54074824,
282661, 54034262, 54149050, 54115250, 54074824,
54273789, 54127020, 54092060
273789, 54127020, 54092060
71124.01
71124.01
ALARA Plans
ALARA Plans
Line 1,506: Line 961:
CR-WF3-YYYY-
CR-WF3-YYYY-
NNNNN
NNNNN
2024-02475, 2024-02504, 2024-02827, 2024-03049,
24-02475, 2024-02504, 2024-02827, 2024-03049,
2024-03360, 2024-03579, 2024-03580, 2024-04009,
24-03360, 2024-03579, 2024-03580, 2024-04009,
2024-04655, 2024-04757, 2024-05200, 2024-05245,
24-04655, 2024-04757, 2024-05200, 2024-05245,
2024-05671, 2024-05876, 2025-00019, 2025-00370,
24-05671, 2024-05876, 2025-00019, 2025-00370,
2025-00718, 2025-00846, 2025-00929, 2025-01075,
25-00718, 2025-00846, 2025-00929, 2025-01075,
2025-01197, 2025-01245, 2025-01247
25-01197, 2025-01245, 2025-01247
 
Inspection
Inspection
Procedure
Procedure
Line 1,536: Line 990:
EN-RP-101
EN-RP-101
Access Control for Radiologically Controlled Areas
Access Control for Radiologically Controlled Areas
71124.01
71124.01
Procedures
Procedures
EN-RP-108
EN-RP-108
Radiation Protection Posting
Radiation Protection Posting
71124.01
71124.01
Procedures
Procedures
EN-RP-110
EN-RP-110
ALARA Program
ALARA Program
71124.01
71124.01
Procedures
Procedures
EN-RP-121
EN-RP-121
Radioactive Material Control
Radioactive Material Control
71124.01
71124.01
Procedures
Procedures
EN-RP-122
EN-RP-122
Alpha Monitoring
Alpha Monitoring
71124.01
71124.01
Procedures
Procedures
EN-RP-123
EN-RP-123
Radiological Controls for Highly Radioactive Objects
Radiological Controls for Highly Radioactive Objects
71124.01
71124.01
Procedures
Procedures
EN-RP-131
EN-RP-131
Air Sampling
Air Sampling
71124.01
71124.01
Procedures
Procedures
Line 1,576: Line 1,023:
RF-001-012
RF-001-012
Upper Guide Structure
Upper Guide Structure
322
2
71124.01
71124.01
Radiation
Radiation
Line 1,639: Line 1,086:
plate move to upper position
plate move to upper position
05/05/2025
05/05/2025
Inspection
Inspection
Procedure
Procedure
Line 1,665: Line 1,111:
Surveys
Surveys
WF3-AS-031025-
WF3-AS-031025-
0025
25
Particulate Sample Report - charging pump 'A' disassembly
Particulate Sample Report - charging pump 'A' disassembly
03/10/2025
03/10/2025
Line 1,672: Line 1,118:
Surveys
Surveys
WF3-AS-031025-
WF3-AS-031025-
0028
28
Particulate Sample Report - charging pump A disassembly -
Particulate Sample Report - charging pump A disassembly -
35 RAB
RAB
03/10/2025
03/10/2025
71124.01
71124.01
Line 1,701: Line 1,147:
Radiation Work
Radiation Work
Permits (RWPs)
Permits (RWPs)
2025-1405-02
25-1405-02
Tours and Inspections in High Radiation Areas
Tours and Inspections in High Radiation Areas
71124.01
71124.01
Radiation Work
Radiation Work
Permits (RWPs)
Permits (RWPs)
2025-1454-02
25-1454-02
RF26 - Valve Maintenance Activities - Task 2: Valve
RF26 - Valve Maintenance Activities - Task 2: Valve
Maintenance Activities in High Radiation Areas
Maintenance Activities in High Radiation Areas
71124.01
71124.01
Radiation Work
Radiation Work
Permits (RWPs)
Permits (RWPs)
2025-1454-04
25-1454-04
RF26 - Valve Maintenance Activities - Task 4: Valve
RF26 - Valve Maintenance Activities - Task 4: Valve
Maintenance Activities in the Regen Hx Room (HRA)
Maintenance Activities in the Regen Hx Room (HRA)
71124.01
71124.01
Radiation Work
Radiation Work
Permits (RWPs)
Permits (RWPs)
2025-1702-07
25-1702-07
RF26 - Reactor Disassembly (to include all associated work
RF26 - Reactor Disassembly (to include all associated work
activities) - Task 7: ***MEDIUM RISK*** Remove Upper
activities) - Task 7: ***MEDIUM RISK*** Remove Upper
Guide Structure and Store in the Lower Refuel Cavity
Guide Structure and Store in the Lower Refuel Cavity
71124.03
71124.03
Corrective Action
Corrective Action
Line 1,731: Line 1,173:
CR-WF3-YYYY-
CR-WF3-YYYY-
NNNNN
NNNNN
2022-02868, 2022-03587, 2022-05994, 2022-05996,
22-02868, 2022-03587, 2022-05994, 2022-05996,
2022-05998, 2023-00623, 2023-16705, 2023-17095,
22-05998, 2023-00623, 2023-16705, 2023-17095,
2023-17136, 2024-03049, 2024-03266, 2024-03272,
23-17136, 2024-03049, 2024-03266, 2024-03272,
2024-03312, 2024-03579, 2024-03942, 2024-04251,
24-03312, 2024-03579, 2024-03942, 2024-04251,
2024-04308, 2024-04494, 2024-04602, 2025-00080,
24-04308, 2024-04494, 2024-04602, 2025-00080,
2025-00536, 2025-00565, 2025-00572, 2025-00586,
25-00536, 2025-00565, 2025-00572, 2025-00586,
2025-00607, 2025-00870, 2025-00931, 2025-00933,
25-00607, 2025-00870, 2025-00931, 2025-00933,
2025-00935, 2025-01247
25-00935, 2025-01247
71124.03
71124.03
Corrective Action
Corrective Action
Line 1,745: Line 1,187:
CR-WF3-YYYY-
CR-WF3-YYYY-
NNNNN
NNNNN
2025-02029
25-02029
 
Inspection
Inspection
Procedure
Procedure
Line 1,758: Line 1,199:
Engineering
Engineering
Evaluations
Evaluations
2024-0308-02
24-0308-02
TEDE-ALARA Evaluation: Forced Outage - Removal of the
TEDE-ALARA Evaluation: Forced Outage - Removal of the
RCP Seals
RCP Seals
Line 1,765: Line 1,206:
Engineering
Engineering
Evaluations
Evaluations
2024-0312-01
24-0312-01
TEDE-ALARA Evaluation: Forced Outage - Work on Highly
TEDE-ALARA Evaluation: Forced Outage - Work on Highly
Contaminated Valves in the Regen Heat Exchanger Room
Contaminated Valves in the Regen Heat Exchanger Room
Line 1,772: Line 1,213:
Engineering
Engineering
Evaluations
Evaluations
2025-1454-02
25-1454-02
TEDE-ALARA Evaluation: Valve Inspection, Testing, and
TEDE-ALARA Evaluation: Valve Inspection, Testing, and
Repair
Repair
Line 1,779: Line 1,220:
Engineering
Engineering
Evaluations
Evaluations
2025-1708-02/03
25-1708-02/03
TEDE-ALARA Evaluation: Refuel 26 - Reactor Cavity / UGS
TEDE-ALARA Evaluation: Refuel 26 - Reactor Cavity / UGS
Structure ICI Activities and ICI Guide Tube Measurements
Structure ICI Activities and ICI Guide Tube Measurements
Line 1,786: Line 1,227:
Engineering
Engineering
Evaluations
Evaluations
2025-1900-04
25-1900-04
TEDE-ALARA Evaluation: Refuel 26 - Emergent Work -
TEDE-ALARA Evaluation: Refuel 26 - Emergent Work -
Insulation Removal from RCP
Insulation Removal from RCP
Line 1,822: Line 1,263:
71124.03
71124.03
Miscellaneous
Miscellaneous
220615042-01
20615042-01
Laboratory Report - Compressed Air/Gas Quality Testing
Laboratory Report - Compressed Air/Gas Quality Testing
08/08/2024
08/08/2024
Line 1,830: Line 1,271:
MSA FireHawk M7 Air Mask Posi3 USB Test Results -
MSA FireHawk M7 Air Mask Posi3 USB Test Results -
Complete SCBA Test, Unit 2, UEM-6119
Complete SCBA Test, Unit 2, UEM-6119
02/01/2024
2/01/2024
71124.03
71124.03
Miscellaneous
Miscellaneous
Line 1,840: Line 1,281:
Miscellaneous
Miscellaneous
Att. 9.5 to EN-RP-
Att. 9.5 to EN-RP-
502
2
Annual Respiratory Protection Equipment Inventory and
Annual Respiratory Protection Equipment Inventory and
Inspection: Annual In-Service Inspection
Inspection: Annual In-Service Inspection
Line 1,860: Line 1,301:
Fig. 03 Shield Building Ventilation Systems (SBV)
Fig. 03 Shield Building Ventilation Systems (SBV)
05/05/2025
05/05/2025
Inspection
Inspection
Procedure
Procedure
Line 1,872: Line 1,312:
Standard Operating Procedure for Emergency Breathing Air
Standard Operating Procedure for Emergency Breathing Air
Supply
Supply
71124.03
71124.03
Procedures
Procedures
EN-RP-131
EN-RP-131
Air Sampling
Air Sampling
71124.03
71124.03
Procedures
Procedures
Line 1,883: Line 1,321:
Operation and Maintenance of HEPA Vacuum Cleaners and
Operation and Maintenance of HEPA Vacuum Cleaners and
HEPA Ventilation Units
HEPA Ventilation Units
71124.03
71124.03
Procedures
Procedures
EN-RP-501
EN-RP-501
Respiratory Protection Program
Respiratory Protection Program
71124.03
71124.03
Procedures
Procedures
Line 1,894: Line 1,330:
Inspection and Maintenance of Respiratory Protection
Inspection and Maintenance of Respiratory Protection
Equipment
Equipment
71124.03
71124.03
Procedures
Procedures
EN-RP-502-01
EN-RP-502-01
FireHawk M7 SCBA
FireHawk M7 SCBA
71124.03
71124.03
Procedures
Procedures
Line 1,905: Line 1,339:
Selection, Issue and Use of Respiratory Protection
Selection, Issue and Use of Respiratory Protection
Equipment
Equipment
71124.03
71124.03
Procedures
Procedures
EN-RP-504
EN-RP-504
Breathing Air
Breathing Air
71124.03
71124.03
Procedures
Procedures
EN-RP-505
EN-RP-505
PortaCount Respirator Fit Testing
PortaCount Respirator Fit Testing
71124.03
71124.03
Procedures
Procedures
HP-002-603
HP-002-603
Inspection and Use of Control Room EBA filtration Panel
Inspection and Use of Control Room EBA filtration Panel
71124.03
71124.03
Radiation
Radiation
Line 1,937: Line 1,367:
Surveys
Surveys
WF3-AS-031025-
WF3-AS-031025-
0026
26
20250004/4 Maintenance Activities, Unit 1 RAB -35
250004/4 Maintenance Activities, Unit 1 RAB -35
03/10/2025
03/10/2025
71124.03
71124.03
Line 1,944: Line 1,374:
Surveys
Surveys
WF3-AS-031025-
WF3-AS-031025-
0027
27
20250004/4 Maintenance Activities, Unit 1 RAB -35
250004/4 Maintenance Activities, Unit 1 RAB -35
03/10/2025
03/10/2025
71124.03
71124.03
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WF3-AS-050625-
WF3-AS-050625-
0184
0184
20251454/4 - RF26 Valve Maintenance Activities, Unit 1
251454/4 - RF26 Valve Maintenance Activities, Unit 1
RCB +21
RCB +21
05/06/2025
05/06/2025
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Surveys
Surveys
WF3-AS-050725-
WF3-AS-050725-
0209
209
20251900/4 - RF26 Emergent Work - Minor Maintenance
251900/4 - RF26 Emergent Work - Minor Maintenance
Activities, Unit 1 RCB D-Rings
Activities, Unit 1 RCB D-Rings
05/07/2025
05/07/2025
Line 1,967: Line 1,397:
Surveys
Surveys
WF3-AS-050725-
WF3-AS-050725-
0209
209
Lapel Sampling: 20251900/4 RF-26 Emergent Work - Minor
Lapel Sampling: 20251900/4 RF-26 Emergent Work - Minor
Maintenance Activities, Unit 1 RCB D-Rings
Maintenance Activities, Unit 1 RCB D-Rings
Line 1,975: Line 1,405:
Surveys
Surveys
WF3-AS-050725-
WF3-AS-050725-
0210
210
Lapel Sampling: 20251900/4 RF-26 Emergent Work - Minor
Lapel Sampling: 20251900/4 RF-26 Emergent Work - Minor
Maintenance Activities, Unit 1 RCB D-Rings
Maintenance Activities, Unit 1 RCB D-Rings
Line 1,983: Line 1,413:
Surveys
Surveys
WF3-AS-101923-
WF3-AS-101923-
0278
278
20230702/2 Refuel 25 - Disassembly of Reactor Head and
230702/2 Refuel 25 - Disassembly of Reactor Head and
All Associated Work Activities, Unit 1 RCB +46
All Associated Work Activities, Unit 1 RCB +46
10/19/2023
10/19/2023
Line 1,990: Line 1,420:
Radiation Work
Radiation Work
Permits (RWPs)
Permits (RWPs)
20251405
251405
RF26 Tours and Inspections
RF26 Tours and Inspections


Line 2,003: Line 1,433:
Radiation Work
Radiation Work
Permits (RWPs)
Permits (RWPs)
20251454
251454
RF26 - Valve Maintenance Activities
RF26 - Valve Maintenance Activities
71124.03
71124.03
Radiation Work
Radiation Work
Permits (RWPs)
Permits (RWPs)
20251455
251455
RF26 - Remove/Replace the Pressurizer Manway and the
RF26 - Remove/Replace the Pressurizer Manway and the
Pressurizer Safety Relief Valves
Pressurizer Safety Relief Valves
71124.03
71124.03
Radiation Work
Radiation Work
Permits (RWPs)
Permits (RWPs)
20251702
251702
RF26 - Reactor Disassembly (to include all associated work
RF26 - Reactor Disassembly (to include all associated work
activities)
activities)
71124.03
71124.03
Radiation Work
Radiation Work
Permits (RWPs)
Permits (RWPs)
20251900
251900
RF26 - Emergent Work - Minor Maintenance Activities
RF26 - Emergent Work - Minor Maintenance Activities
71124.03
71124.03
Self-Assessments LO-WF3-2024-
Self-Assessments LO-WF3-2024-
Line 2,031: Line 1,457:
In-Plant Airborne Radioactivity Control and Mitigation (IP
In-Plant Airborne Radioactivity Control and Mitigation (IP
71124.03)
71124.03)
02/19/2025
2/19/2025
71124.03
71124.03
Work Orders
Work Orders
Line 2,067: Line 1,493:
SBVMFAN0001 A - Leak Test HEPA Filters and Charcoal
SBVMFAN0001 A - Leak Test HEPA Filters and Charcoal
Absorber
Absorber
12/05/2024
2/05/2024
71151
71151
Miscellaneous
Miscellaneous
Line 2,092: Line 1,518:
EN-FAP-OM-005
EN-FAP-OM-005
Nuclear Performance Indicator Program
Nuclear Performance Indicator Program
71151
71151
Procedures
Procedures
EN-LI-114
EN-LI-114
Regulatory Performance Indicator Process
Regulatory Performance Indicator Process
71152A
71152A
Corrective Action
Corrective Action
Line 2,103: Line 1,527:
CR-WF3-YYYY-
CR-WF3-YYYY-
NNNNN
NNNNN
2023-15311, 2025-00469, 2025-00472
23-15311, 2025-00469, 2025-00472
71152A
71152A
Miscellaneous
Miscellaneous
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EN-DC-115
EN-DC-115
Engineering Change Process
Engineering Change Process
71152A
71152A
Procedures
Procedures
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EN-LI-118
EN-LI-118
Causal Analysis Process
Causal Analysis Process
71152A
71152A
Procedures
Procedures
EN-MA-106
EN-MA-106
71152A
71152A
Procedures
Procedures
OP-002-001
OP-002-001
Auxiliary Component Cooling Water
Auxiliary Component Cooling Water
320
20
71152S
71152S
Corrective Action
Corrective Action
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CR-WF3-YYYY-
CR-WF3-YYYY-
NNNNN
NNNNN
2024, 00655, 2025-00951, 2025-01071, 2025-01090,
24, 00655, 2025-00951, 2025-01071, 2025-01090,
2025-01118, 2025-01137, 2025-01326, 2025-01407,
25-01118, 2025-01137, 2025-01326, 2025-01407,
2025-01434, 2025-01539, 2025-02175, 2025-02272,
25-01434, 2025-01539, 2025-02175, 2025-02272,
2025-02277, 2025-02280, 2025-02293, 2025-02294,
25-02277, 2025-02280, 2025-02293, 2025-02294,
2025-02295, 2025-02300, 2025-02356, 2025-02404,
25-02295, 2025-02300, 2025-02356, 2025-02404,
2025-02543, 2025-02544, 2025-02580, 2025-02997,
25-02543, 2025-02544, 2025-02580, 2025-02997,
2025-03131, 2025-03165
25-03131, 2025-03165
71153
71153
Corrective Action
Corrective Action
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CR-WF3-YYYY-
CR-WF3-YYYY-
NNNNN
NNNNN
2024-02523
24-02523
71153
71153
Procedures
Procedures
EN-FAP-OM-016
EN-FAP-OM-016
Performance Management Processes and Practices
Performance Management Processes and Practices
71153
71153
Procedures
Procedures

Latest revision as of 23:05, 22 February 2026

Amended Integrated Inspection Report 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)
v • d • e


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:

NPF-38

Report Number:

05000382/2025002

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 NCV 05000382/2025002-01 Open/Closed None (NPP)71111.15 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 Initiating Events Green NCV 05000382/2025002-02 Open/Closed None (NPP)71153 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 LER 05000382/2024-003-00 Automatic EFAS Actuation During Surveillance Test 71153 Closed NOV 05000382/2024013-01 Failure to Perform an Adequate Steam Generator (SG) Operational Assessment EA-24-052 71153 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 D, 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. 23-0012, SI IFT 1307-A

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)

Main article: IP 71152
(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)

Main article: IP 71153
(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 NCV 05000382/2025002-01 Open/Closed None (NPP)71111.15 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 A, 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 71152A 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 Initiating Events Green NCV 05000382/2025002-02 Open/Closed None (NPP)71153 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 of both EFAS and RPS.

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 A, 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

71111.01

Miscellaneous

EN-WM-112,

Site Certification Letter and Seasonal Reliability Plan

71111.01

Procedures

EN-FAP-010

Severe Weather Response

71111.01

Work Orders

255494, 5419260, 54202873

71111.04

Corrective Action

Documents

CR-WF3-YYYY-

NNNNN

24-00759, 2024-00148, 2024-03504, 2025-01051,

25-01765, 2025-02626, 2025-02632, 2025-02706,

71111.04

Drawings

1564-4331

4.16 KV Class 1E SWGR Installation Details

71111.04

Drawings

1564-6242

4.16 KV Switchgear 3A2 Element Diagram, Sheet 1

71111.04

Procedures

OP-006-001

Plant Distribution (7KV, 4KV, and SSD) Systems

351

71111.04

Procedures

OP-009-003

System Operating Procedure Emergency Feedwater

313

71111.04

Procedures

OP-010-004

Power Operations

350

71111.04

Procedures

OP-010-005

Plant Shutdown

350

71111.04

Procedures

OP-901-310

Loss of Train A Safety Bus

317

71111.05

Corrective Action

Documents

CR-WF3-YYYY-

NNNNN

22-03613, 2022-03592, 2024-01190, 2024-01330,

24-01684

71111.05

Fire Plans

RAB 2-001

H&V Mechanical Room

71111.05

Fire Plans

RAB 36-001

Safety Injection Pump Room A

71111.05

Fire Plans

RAB 5-001

Electrical Penetration Room B

71111.05

Fire Plans

RAB 8A-001

Switchgear Room A

71111.05

Fire Plans

RAB 8C-001

Switchgear Room A/B

71111.05

Fire Plans

RAB-16-001

Emergency Diesel Generator 3A

71111.05

Fire Plans

RAB-37-001

Motor Driven Emergency Feed Pump Room A

71111.05

Procedures

EN-EE-S-048-W

Fire Detector Replacement Standard

71111.05

Procedures

FP-001-015

Fire Protection System Impairments

335

71111.08P

Corrective Action

Documents

CR-WF3-YYYY-

NNNNN

22-01839, 2022-01891, 2022-01900, 2022-01901,

22-01929, 2022-01945, 2022-01949, 2022-01960,

22-01977, 2022-01978, 2022-01979, 2022-01993,

22-02011, 2022-02012, 2022-02013, 2022-02014,

22-02015, 2022-02016, 2022-02017, 2022-02018,

22-02029, 2022-02030, 2022-02031, 2022-02032,

22-02142, 2022-02156, 2022-02178, 2022-02287,

22-02289, 2022-02291, 2022-02293, 2022-02295,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

22-02296, 2022-02301, 2022-02302, 2022-02303,

22-02304, 2022-02307, 2022-02309, 2022-02310,

22-02312, 2022-02314, 2022-02385, 2022-02387,

22-02401, 2022-02449, 2022-02452, 2022-02461,

22-02462, 2022-02463, 2022-02491, 2022-02555,

22-02630, 2022-02639, 2022-02703, 2022-02730,

22-02731, 2022-02732, 2022-02736, 2022-02741,

22-02742, 2022-02814, 2022-02821, 2022-02937,

22-03003, 2022-03016, 2022-03017, 2022-03018,

22-03085, 2022-03086, 2022-03449, 2022-03452,

22-03501, 2022-03506, 2022-03846, 2022-03959,

22-03975, 2022-03979, 2022-04023, 2022-04178,

22-04279, 2022-04280, 2022-04290, 2022-04392,

22-04649, 2022-04650, 2022-04651, 2022-04656,

22-04658, 2022-04659, 2022-04661, 2022-04662,

22-04664, 2022-04665, 2022-04667, 2022-04670,

22-04672, 2022-04673, 2022-04675, 2022-04987,

22-04988, 2022-04989, 2022-04990, 2022-04992,

22-04993, 2022-04994, 2022-04995, 2022-04996,

22-04998, 2022-05000, 2022-05126, 2022-05132,

22-05133, 2022-05134, 2022-05135, 2022-05136,

22-05138, 2022-05139, 2022-05145, 2022-05146,

22-05147, 2022-05148, 2022-05149, 2022-05150,

22-05151, 2022-05221, 2022-05270, 2022-05403,

22-06402, 2022-06403, 2022-06404, 2022-06405,

22-06406, 2022-06407, 2022-06408, 2022-06409,

22-06411, 2022-06412, 2022-06413, 2022-06414,

22-06415, 2022-06609, 2022-06617, 2022-06779,

22-06895, 2022-06896, 2022-06897, 2022-06898,

22-06899, 2022-06900, 2022-06901, 2022-06902,

22-06903, 2022-06904, 2022-06905, 2022-06906,

22-06907, 2022-06908, 2022-06909, 2022-06910,

22-06911, 2022-06912, 2022-06915, 2022-07340,

22-07636, 2022-08022, 2022-08024, 2022-08036,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

22-08054, 2022-08055, 2022-08056, 2022-08060,

22-08061, 2022-08062, 2022-08066, 2022-08069,

22-08071, 2022-08073, 2022-08076, 2022-08078,

23-00044, 2023-00046, 2023-00049, 2023-00054,

23-00055, 2023-00056, 2023-00058, 2023-00060,

23-00061, 2023-00062, 2023-00063, 2023-00064,

23-00065, 2023-00066, 2023-00083, 2023-00179,

23-00180, 2023-00399, 2023-00418, 2023-00518,

23-00623, 2023-00726, 2023-00792, 2023-01008,

23-01026, 2023-01215, 2023-01298, 2023-01303,

23-01304, 2023-01305, 2023-01306, 2023-01313,

23-01315, 2023-01316, 2023-01317, 2023-01343,

23-01700, 2023-01702, 2023-01703, 2023-01705,

23-01707, 2023-01709, 2023-01712, 2023-01716,

23-01717, 2023-01726, 2023-01729, 2023-01731,

23-01773, 2023-01774, 2023-01972, 2023-01989,

23-02142, 2023-02169, 2023-02251

71111.08P

Corrective Action

Documents

Resulting from

Inspection

CR-WF3-YYYY-

NNNNN

25-01683, 2025-01690, 2025-01787, 2025-01810,

25-01820, 2025-01823, 2025-01851, 2025-1904

71111.08P

Miscellaneous

W3F1-2024-0041

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

71111.08P

Miscellaneous

Weld package

CVC MVAAA2 16 A, pressurizer aux spray valve A

71111.08P

Procedures

CEP-BAC-001

Boric Acid Corrosion Control (BACC) Program Plan

71111.08P

Procedures

CEP-NDE-0404

Manual Ultrasonic Examination of Ferritic Piping Welds

(ASME XI)

71111.08P

Procedures

CEP-NDE-0407

Straight Beam Ultrasonic Examination of Bolts and Studs

(ASME XI)

71111.08P

Procedures

CEP-NDE-0423

Manual Ultrasonic Examination of Austenitic Piping Welds

(ASME XI)

71111.08P

Procedures

CEP-NDE-0641

Liquid Penetrant Examination (PT) for ASME Section XI

71111.08P

Procedures

CEP-NDE-0731

Magnetic Particle Examination (MT) for ASME Section XI

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.08P

Procedures

CEP-NDE-0901

VT-1 Examination

71111.08P

Procedures

CEP-NDE-0902

VT-2 Examination

71111.08P

Procedures

CEP-NDE-0903

VT-3 Examination

71111.08P

Procedures

CEP-WP-GWS-1

General Welding Standard ASME/ANSI

71111.08P

Procedures

EN-DC-127

Control of Hot Work and Ignition Sources

71111.08P

Procedures

EN-DC-319

Boric Acid Corrosion Control Program (BACCP)

71111.08P

Procedures

EN-DC-328

Entergy Nuclear Welding Program

71111.08P

Procedures

EN-DC-334

Primary Containment Leakage Rate Testing (Appendix J)

71111.08P

Procedures

EN-EV-112

Chemical Control Program

71111.08P

Procedures

EN-IS-109

Compressed Gas Cylinder Handling and Storage

71111.08P

Procedures

EN-IS-114

Fall Protection

71111.08P

Procedures

EN-MA-133

Control of Scaffolding

71111.08P

Procedures

SEP-APJ-005

Waterford 3 Primary Containment Leakage Rate Testing

(Appendix J) Program

71111.08P

Procedures

SEP-BAC-WF3-

001

Waterford 3 Boric Acid Corrosion Control Program (BACCP)

Program Section

71111.08P

Procedures

SEP-ISI-104

Program Section for ASME Section XI, Division 1 WF3

Inservice Inspection Program

71111.11Q

Corrective Action

Documents

CR-WF3-YYYY-

NNNNN

24-05669

71111.11Q

Procedures

MM-007-015

Main Steam Safety Valve Test

2

71111.11Q

Procedures

OP-010-003

Plant Startup

371

71111.11Q

Procedures

OP-010-004

Power Operations

350

71111.11Q

Procedures

OP-010-005

Plant Shutdown

350

71111.11Q

Procedures

OP-010-007

Plant Cooldown

347

71111.11Q

Work Orders

54061139

71111.12

Corrective Action

Documents

CR-WF3-YYYY-

NNNNN

25-00889, 2025-01024, 2025-01977, 2025-01980,

25-02389, 2025-02583

71111.12

Procedures

EN-QV-102

Quality Control Inspection Program

71111.12

Work Orders

53026924, 54122524, 54163201, 54163202, 54189378

71111.13

Corrective Action

Documents

CR-WF3-YYYY-

NNNNN

25-01400, 2025-02648, 2025-02653, 2025-02671,

25-02673, 2025-02684, 2025-02706,

71111.13

Procedures

EN-OM-132

Nuclear Risk Management Process

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.13

Procedures

EN-OP-119

Protected Equipment Postings

71111.13

Procedures

OP-001-003

Plant Shutdown

371

71111.13

Procedures

OP-006-009

Electrical Bus Outages

71111.13

Procedures

PLG-009-014

Conduct of Planned Outages

23

71111.13

Work Orders

54122485

71111.15

Corrective Action

Documents

CR-WF3-YYYY-

NNNNN

25-00049, 2025-00951, 2025-00966, 2025-01126

71111.15

Engineering

Changes

0054260118

Operability Input - Emergency Diesel Generator B Outboard

Generator Slinger Ring

71111.15

Procedures

EN-DC-153

Preventive Maintenance Component Classification

71111.15

Procedures

EN-DC-324

Preventive Maintenance Program

71111.18

Drawings

B425-T122CA

Reactor Coolant Cold Leg 2A Temperature Channel A

71111.18

Engineering

Changes

EC-5260652

Temporary Modification of 2A Cold Leg Temperature Loop

RC IT0122-CA

71111.18

Engineering

Changes

EC-54172687

ESFAS Single Point Vulnerability Elimination Train B

71111.18

Work Orders

54163201, 54163202, 54261266

71111.20

Corrective Action

Documents

CR-WF3-YYYY-

NNNNN

25-01601, 2025-01627, 2025-01837, 2025-02165,

25-02265, 2025-02422, 2025-02468, 2025-02617,

25-02837

71111.20

Procedures

EN-OM-123

Fatigue Management Program

71111.20

Procedures

OP-001-003

Reactor Coolant System Drain Down

331

71111.20

Procedures

OP-010-003

Plant Startup

371

71111.20

Procedures

OP-010-005

Plant Shutdown

350

71111.20

Procedures

OP-010-006

Outage Operations

347

71111.20

Procedures

OP-903-24

Reactor Coolant System Water Inventory Balance

71111.20

Procedures

PLG-009-014

Conduct of Planned Outages

23

71111.20

Procedures

UNT-007-008

Control of Heavy and Critical Loads

24

71111.24

Corrective Action

Documents

CR-WF3-YYYY-

NNNNN

25-01603, 2025-01681, 2025-01815, 2025-02174,

25-02175, 2025-02543 2025-02563

71111.24

Miscellaneous

W3-DBD-4

Design Basis Document: Component Cooling Water and

Auxiliary Component Cooling Water

307

71111.24

Procedures

EN-MA-148

Motor Operated Valve Diagnostics

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.24

Procedures

OP-903-014

Emergency Feedwater Flow Verification

319

71111.24

Procedures

OP-903-033

Cold Shutdown IST Valve Tests

71111.24

Procedures

OP-903-046

Emergency Feed Pump Operability Check

26

71111.24

Procedures

OP-903-049

Component Cooling Water and Auxiliary Cooling Water Loop

Operability Check

71111.24

Procedures

OP-903-050

Component Cooling Water and Auxiliary Component Cooling

Water Pump and Valve Operability Test

71111.24

Procedures

OP-903-094

ESFAS Subgroup Relay Test - Operating

71111.24

Procedures

OP-903-115

Train A Integrated Emergency Diesel Generator/Engineering

Safety Features Test

71111.24

Procedures

OP-903-116

Train B Integrated Emergency Diesel Generator/Engineering

Safety Features Test

71111.24

Procedures

OP-903-119

Secondary Auxiliaries Quarterly IST Valve Tests

71111.24

Procedures

OP-903-121

Safety Systems Quarterly IST Valve Tests

71111.24

Procedures

OP-903-121

Safety Systems Quarterly IST Valve Tests

71111.24

Procedures

STA-001-001

Containment Air Lock Door Seal Leakage Test

304

71111.24

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,

282661, 54034262, 54149050, 54115250, 54074824,

273789, 54127020, 54092060

71124.01

ALARA Plans

RWP 2025-1702

ALARA Plan

04/26/2025

71124.01

Corrective Action

Documents

CR-WF3-YYYY-

NNNNN

24-02475, 2024-02504, 2024-02827, 2024-03049,

24-03360, 2024-03579, 2024-03580, 2024-04009,

24-04655, 2024-04757, 2024-05200, 2024-05245,

24-05671, 2024-05876, 2025-00019, 2025-00370,

25-00718, 2025-00846, 2025-00929, 2025-01075,

25-01197, 2025-01245, 2025-01247

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71124.01

Corrective Action

Documents

Resulting from

Inspection

CR-WF3-YYYY-

NNNNN

WF3-2025-01931, HQN-2025-00456

71124.01

Miscellaneous

Waterford-3 RF26 RWP Status Report

05/08/2025

71124.01

Procedures

EN-RP-101

Access Control for Radiologically Controlled Areas

71124.01

Procedures

EN-RP-108

Radiation Protection Posting

71124.01

Procedures

EN-RP-110

ALARA Program

71124.01

Procedures

EN-RP-121

Radioactive Material Control

71124.01

Procedures

EN-RP-122

Alpha Monitoring

71124.01

Procedures

EN-RP-123

Radiological Controls for Highly Radioactive Objects

71124.01

Procedures

EN-RP-131

Air Sampling

71124.01

Procedures

HP-001-213

Control of Reactor Containment Building Power Entries

306

71124.01

Procedures

RF-001-012

Upper Guide Structure

2

71124.01

Radiation

Surveys

WF3-2407-00033

RAB +21 Decontamination Area

07/02/2024

71124.01

Radiation

Surveys

WF3-2504-00098

Resin Sluice - post flushing of sluicing CVC IX C to Spent

Resin Tank

04/09/2025

71124.01

Radiation

Surveys

WF3-2504-00150

PA/Outside RM Storage Area - quarterly survey

04/15/2025

71124.01

Radiation

Surveys

WF3-2504-00244

Rad Waste Compactor Building

04/25/2025

71124.01

Radiation

Surveys

WF3-2504-00254

-4' Reactor Containment Building - RF 26 initial entry

04/26/2025

71124.01

Radiation

Surveys

WF3-2504-00260

+21' Reactor Containment Building - RF 26 initial entry

04/26/2025

71124.01

Radiation

Surveys

WF3-2504-00264

+46' Reactor Containment Building - RF 26 initial entry

04/26/2025

71124.01

Radiation

Surveys

WF3-2504-00275

-11' Reactor Containment Building - RF 26 initial entry

04/26/2025

71124.01

Radiation

Surveys

WF3-2504-00371

Radwaste Solidification Building - quarterly survey

04/28/2025

71124.01

Radiation

Surveys

WF3-2505-00173

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

71124.01

Radiation

Surveys

WF3-2505-00177

Regenerative Heat Exchanger (Upper Level) pre and post

shielding survey

05/05/2025

71124.01

Radiation

Surveys

WF3-AS-011625-

0003

Noble Gas Sample Report - Containment RCB +21

01/16/2025

71124.01

Radiation

Surveys

WF3-AS-031025-

25

Particulate Sample Report - charging pump 'A' disassembly

03/10/2025

71124.01

Radiation

Surveys

WF3-AS-031025-

28

Particulate Sample Report - charging pump A disassembly -

RAB

03/10/2025

71124.01

Radiation

Surveys

WF3-AS-061124-

0171

Noble Gas Sample Report - RDT - 11 RCB

06/11/2024

71124.01

Radiation

Surveys

WF3-AS-073124-

0176

Particulate Sample Report - charging pump 'A' plunger pull

07/31/2024

71124.01

Radiation

Surveys

WF3-AS-080124-

0179

Particulate Sample Report - charging pump A repacking

(seal water box) -35' RAB

08/01/2024

71124.01

Radiation Work

Permits (RWPs)

25-1405-02

Tours and Inspections in High Radiation Areas

71124.01

Radiation Work

Permits (RWPs)

25-1454-02

RF26 - Valve Maintenance Activities - Task 2: Valve

Maintenance Activities in High Radiation Areas

71124.01

Radiation Work

Permits (RWPs)

25-1454-04

RF26 - Valve Maintenance Activities - Task 4: Valve

Maintenance Activities in the Regen Hx Room (HRA)

71124.01

Radiation Work

Permits (RWPs)

25-1702-07

RF26 - Reactor Disassembly (to include all associated work

activities) - Task 7: ***MEDIUM RISK*** Remove Upper

Guide Structure and Store in the Lower Refuel Cavity

71124.03

Corrective Action

Documents

CR-WF3-YYYY-

NNNNN

22-02868, 2022-03587, 2022-05994, 2022-05996,

22-05998, 2023-00623, 2023-16705, 2023-17095,

23-17136, 2024-03049, 2024-03266, 2024-03272,

24-03312, 2024-03579, 2024-03942, 2024-04251,

24-04308, 2024-04494, 2024-04602, 2025-00080,

25-00536, 2025-00565, 2025-00572, 2025-00586,

25-00607, 2025-00870, 2025-00931, 2025-00933,

25-00935, 2025-01247

71124.03

Corrective Action

Documents

Resulting from

CR-WF3-YYYY-

NNNNN

25-02029

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Inspection

71124.03

Engineering

Evaluations

24-0308-02

TEDE-ALARA Evaluation: Forced Outage - Removal of the

RCP Seals

04/09/2024

71124.03

Engineering

Evaluations

24-0312-01

TEDE-ALARA Evaluation: Forced Outage - Work on Highly

Contaminated Valves in the Regen Heat Exchanger Room

04/17/2024

71124.03

Engineering

Evaluations

25-1454-02

TEDE-ALARA Evaluation: Valve Inspection, Testing, and

Repair

10/24/2024

71124.03

Engineering

Evaluations

25-1708-02/03

TEDE-ALARA Evaluation: Refuel 26 - Reactor Cavity / UGS

Structure ICI Activities and ICI Guide Tube Measurements

04/26/2025

71124.03

Engineering

Evaluations

25-1900-04

TEDE-ALARA Evaluation: Refuel 26 - Emergent Work -

Insulation Removal from RCP

05/07/2025

71124.03

Miscellaneous

Employee SCBA Mask Sizes

04/14/2025

71124.03

Miscellaneous

Respiratory Protection Equipment - Monthly Inspection

04/16/2025

71124.03

Miscellaneous

WSES-FSAR-Unit-3, Table 12,5-4, Health Physics

Equipment

305

71124.03

Miscellaneous

WSES-FSAR-Unit-3, Equipment, Instrumentation, and

Facilities

305

71124.03

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

71124.03

Miscellaneous

Training and Qualifications for Entergy Corporation

(AirHawk, FireHawk, SCBAs)

03/27/2025

71124.03

Miscellaneous

20615042-01

Laboratory Report - Compressed Air/Gas Quality Testing

08/08/2024

71124.03

Miscellaneous

71400941

MSA FireHawk M7 Air Mask Posi3 USB Test Results -

Complete SCBA Test, Unit 2, UEM-6119

2/01/2024

71124.03

Miscellaneous

71403719

MSA FireHawk M7 Air Mask Posi3 USB Test Results -

Complete SCBA Test, Unit 66, UEM-6168

01/30/2024

71124.03

Miscellaneous

Att. 9.5 to EN-RP-

2

Annual Respiratory Protection Equipment Inventory and

Inspection: Annual In-Service Inspection

01/15/2025

71124.03

Miscellaneous

Ref. G-853

Fig. 03 Control Room Emergency Filtration Unit (HVC) High

Radiation / SIAS Mode

05/05/2025

71124.03

Miscellaneous

Ref. G-853 SH1

Fig. 06 Controlled Ventilation Areas Filter Unit (CVAS)

05/05/2025

71124.03

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

71124.03

Procedures

Standard Operating Procedure for Emergency Breathing Air

Supply

71124.03

Procedures

EN-RP-131

Air Sampling

71124.03

Procedures

EN-RP-404

Operation and Maintenance of HEPA Vacuum Cleaners and

HEPA Ventilation Units

71124.03

Procedures

EN-RP-501

Respiratory Protection Program

71124.03

Procedures

EN-RP-502

Inspection and Maintenance of Respiratory Protection

Equipment

71124.03

Procedures

EN-RP-502-01

FireHawk M7 SCBA

71124.03

Procedures

EN-RP-503

Selection, Issue and Use of Respiratory Protection

Equipment

71124.03

Procedures

EN-RP-504

Breathing Air

71124.03

Procedures

EN-RP-505

PortaCount Respirator Fit Testing

71124.03

Procedures

HP-002-603

Inspection and Use of Control Room EBA filtration Panel

71124.03

Radiation

Surveys

WF3-2504-00094

-4 Reactor Containment Building

04/09/2025

71124.03

Radiation

Surveys

WF3-2505-00253

Pre-Job Survey for Insulation Removal

05/06/2025

71124.03

Radiation

Surveys

WF3-AS-031025-

26

250004/4 Maintenance Activities, Unit 1 RAB -35

03/10/2025

71124.03

Radiation

Surveys

WF3-AS-031025-

27

250004/4 Maintenance Activities, Unit 1 RAB -35

03/10/2025

71124.03

Radiation

Surveys

WF3-AS-050625-

0184

251454/4 - RF26 Valve Maintenance Activities, Unit 1

RCB +21

05/06/2025

71124.03

Radiation

Surveys

WF3-AS-050725-

209

251900/4 - RF26 Emergent Work - Minor Maintenance

Activities, Unit 1 RCB D-Rings

05/07/2025

71124.03

Radiation

Surveys

WF3-AS-050725-

209

Lapel Sampling: 20251900/4 RF-26 Emergent Work - Minor

Maintenance Activities, Unit 1 RCB D-Rings

05/07/2025

71124.03

Radiation

Surveys

WF3-AS-050725-

210

Lapel Sampling: 20251900/4 RF-26 Emergent Work - Minor

Maintenance Activities, Unit 1 RCB D-Rings

05/07/2025

71124.03

Radiation

Surveys

WF3-AS-101923-

278

230702/2 Refuel 25 - Disassembly of Reactor Head and

All Associated Work Activities, Unit 1 RCB +46

10/19/2023

71124.03

Radiation Work

Permits (RWPs)

251405

RF26 Tours and Inspections

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71124.03

Radiation Work

Permits (RWPs)

251454

RF26 - Valve Maintenance Activities

71124.03

Radiation Work

Permits (RWPs)

251455

RF26 - Remove/Replace the Pressurizer Manway and the

Pressurizer Safety Relief Valves

71124.03

Radiation Work

Permits (RWPs)

251702

RF26 - Reactor Disassembly (to include all associated work

activities)

71124.03

Radiation Work

Permits (RWPs)

251900

RF26 - Emergent Work - Minor Maintenance Activities

71124.03

Self-Assessments LO-WF3-2024-

00063

In-Plant Airborne Radioactivity Control and Mitigation (IP 71124.03)

2/19/2025

71124.03

Work Orders

53015928_1

HVCMFAN0010 A - Obtain Charcoal Test Canister for

Analysis

05/28/2024

71124.03

Work Orders

53017382_1

HVCMFAN0010 A - Leak Test HEPA Filters and Charcoal

Absorber

05/29/2024

71124.03

Work Orders

53023258_1

HVCMFAN0010 B - Leak Test HEPA Filters and Charcoal

Absorber

05/22/2024

71124.03

Work Orders

53023327_1

HVCMFAN0010 B - Obtain Charcoal Test Canister for

Analysis

05/20/2024

71124.03

Work Orders

53025177_1

HVRMFAN0021 B - Leak Test HEPA Filters and Charcoal

Absorber

05/28/2024

71124.03

Work Orders

53034403_1

SBVMFAN0001 A - Leak Test HEPA Filters and Charcoal

Absorber

2/05/2024

71151

Miscellaneous

W3F1-2025-0014

Annual Radioactive Effluent Release Report (ARERR) 2024

04/30/2025

71151

Miscellaneous

W3Fl-2024-0031

NRC Performance Indicator (Pl) Data - 2nd Quarter 2024

07/18/2024

71151

Miscellaneous

W3Fl-2024-0048

NRC Performance Indicator (Pl) Data - 3rd Quarter 2024

10/16/2024

71151

Miscellaneous

W3Fl-2025-0005

NRC Performance Indicator (Pl) Data - 4th Quarter 2024

01/17/2025

71151

Procedures

EN-FAP-OM-005

Nuclear Performance Indicator Program

71151

Procedures

EN-LI-114

Regulatory Performance Indicator Process

71152A

Corrective Action

Documents

CR-WF3-YYYY-

NNNNN

23-15311, 2025-00469, 2025-00472

71152A

Miscellaneous

PSA-WF3-01-SY

WF3 PSA Model Systems Analysis Notebook

71152A

Miscellaneous

SD-EDG

Emergency Diesel Generator System Description

71152A

Procedures

EN-DC-115

Engineering Change Process

71152A

Procedures

EN-LI-102

Corrective Action Program

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71152A

Procedures

EN-LI-118

Causal Analysis Process

71152A

Procedures

EN-MA-106

71152A

Procedures

OP-002-001

Auxiliary Component Cooling Water

20

71152S

Corrective Action

Documents

CR-WF3-YYYY-

NNNNN

24, 00655, 2025-00951, 2025-01071, 2025-01090,

25-01118, 2025-01137, 2025-01326, 2025-01407,

25-01434, 2025-01539, 2025-02175, 2025-02272,

25-02277, 2025-02280, 2025-02293, 2025-02294,

25-02295, 2025-02300, 2025-02356, 2025-02404,

25-02543, 2025-02544, 2025-02580, 2025-02997,

25-03131, 2025-03165

71153

Corrective Action

Documents

CR-WF3-YYYY-

NNNNN

24-02523

71153

Procedures

EN-FAP-OM-016

Performance Management Processes and Practices

71153

Procedures

OP-009-003

Emergency Feedwater

313

71153

Procedures

OP-903-014

Emergency Feedwater Flow Verification

318

71153

Procedures

OP-903-014

Emergency Feedwater Flow Verification

319

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