ML25216A278

The inspectors reviewed a self-revealed Green finding and associated non-cited violation of

10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action, for the licensees failure to

promptly identify and correct a condition adverse to quality. Specifically, the licensee failed to

recognize the applicability of a 10 CFR Part 21 report regarding possible mechanical binding of

full reversing starter mechanical interlocks in 2021. Subsequently, five safety-related

motor-operated valves failed due to this issue.

Additional Tracking Items

None.

3

PLANT STATUS

The plant was shut down for refueling outage 27 for the entire quarter.

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

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (1 Sample)

The inspectors evaluated system configurations during a partial walkdown of the following

system:

(1)

cold overpressure mitigation system during mode 5 operations on May 3, 2025

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1)

The inspectors evaluated system configurations during a complete walkdown of

containment spray train B on May 5, 2025.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a

walkdown and performing a review to verify program compliance, equipment functionality,

material condition, and operational readiness of the following fire areas:

(1)

reactor building fire area RB-1 on April 3, 2025

(2)

control building fire areas C-1, C-5, C-6, C-7, C-8 elevation 1974'-0" on April 3, 2025

(3)

fire area TB-1 on May 19, 2025

4

71111.07A - Heat Exchanger/Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1)

component cooling water train A heat exchanger on April 5, 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 boundary are appropriately

monitored for degradation and that repairs and replacements were appropriately fabricated,

examined and accepted by reviewing the following activities during refueling outage 27 from

March 31 to April 8, 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.

pressurizer, safety 2BB02S001J, pipe to flange

2.

pressurizer, safety 2BB02S006J, pipe to flange

3.

pressurizer, safety 2BB02S007J, pipe to flange

4.

steam generator D, EBB01 D-RSG-SC001, bottom head to tube sheet

5.

steam generator B, EBB01 B-RSG-SC001, bottom head to tube sheet

6.

steam generator B, EBB01 B-RSG-SC003, tube sheet to shell

7.

steam generator B, EBB01 B-RSG-SC008, upper to shell

8.

essential service water train A pump discharge pipe to flange

Visual 1 Examination

1.

containment liner, SUMPLF07DRWIT instrument tunnel sump base metal

repair of liner

Visual 2 Examination

1.

safety injection, penetration 87 to cold leg check valve

2.

safety injection, penetration 48 to cold leg check valve

3.

safety injection, penetration 49 to cold leg check valve

Magnetic particle examination

1.

containment liner, SUMPLF07DRWIT, instrument tunnel sump base metal

repair of liner

2.

essential service water train A pump discharge flange

3.

essential service water train A pump spool piece, welds FW-03, FW-04,

and FW-05

Welding Activities

1.

weld process, shielded metal arc weld

5

a.

essential service water train A pump spool piece, welds FW-03,

FW-04, and FW-05

b.

essential service water train A pump discharge flange, weld FW 07

PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection

Activities (IP Section 03.02)

The inspectors verified that no vessel upper head penetration inspection was required 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 evaluations:

(1)

Boric acid evaluations and screenings:

1.

202306651

2.

202306653

3.

202306659

4.

202306840

5.

202306893

6.

202306945

7.

202307001

8.

202307332

9.

202307476

10. 202307628

11. 202307631

12. 202307736

13. 202307782

14. 202307946

15. 202307950

16. 202308035

17. 202308107

18. 202308167

19. 202308182

20. 202400927

21. 202401126

22. 202401128

23. 202401130

24. 202401250

PWR Inservice Inspection Activities Sample - Steam Generator Tube Inspection Activities

(Section 03.04)

The inspectors verified that no ASME code steam generator tube integrity inspection was

required this outage.

6

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (1 Sample)

The inspectors evaluated the effectiveness of maintenance to ensure the following

structures, systems, and components remain capable of performing their intended function:

(1)

fire water system on June 13, 2025

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated the accuracy and completeness of risk assessments during the

following planned and emergent work activities to ensure configuration changes and

appropriate work controls were addressed:

(1)

engineered safety features train A actuation system testing on April 18, 2025

(2)

risk management actions during yellow risk window for spent fuel pool cooling on

April 9, 2025

(3)

risk assessment regarding mode ascension prior to completion of maintenance on the

incore tunnel sump level indication system on May 3, 2025

(4)

risk management actions while backfeeding power through the main transformers on

April 23, 2025

(5)

risk management actions for reactor vessel lower internals lift on May 16, 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)

erratic indication on gammametrics source range channel N60, on April 1, 2025

(2)

potential reactor coolant system boundary leakage on March 31, 2025

(3)

turbine-driven auxiliary feedwater pump discharge to steam generator B

valve ALHV0009 on April 7, 2025

(4)

control room emergency ventilation system operability during a breach in the control

room envelope on April 8, 2025

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)

(1)

The inspectors evaluated refueling outage 27 activities beginning March 28, 2025,

and continuing beyond the end of the quarter.

7

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) (7 Samples)

(1)

breaker NB01BF03 replacement on April 4, 2025

(2)

post-maintenance testing following flaw repairs on essential service water train A

piping on April 18, 2025

(3)

valve ALHV0031 following rebuild on April 24, 2025

(4)

turbine-driven auxiliary feedwater pump testing following replacement of the trip and

throttle valve on May 5, 2025

(5)

load shed and emergency load sequencer test of breakers NG01BJF5

and NG02BJF5 after replacement on May 2, 2025

(6)

rod drop testing following replacement of control rod drive mechanism thermal

sleeves on May 8, 2025

(7)

turbine-driven auxiliary feedwater pump testing following maintenance on the trip and

throttle valve on May 6, 2025

Surveillance Testing (IP Section 03.01) (3 Samples)

(1)

auxiliary feedwater pump discharge check valve closure test on May 5, 2025

(2)

main feedwater isolation valve inservice test on May 5, 2025

(3)

turbine-driven auxiliary feedwater pump testing on May 5, 2025

Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)

(1)

component cooling water isolation valves EGHV0130 and EGHV0131 on April 15,

2025

71114.06 - Drill Evaluation

Required Emergency Preparedness Drill (1 Sample)

(1)

emergency preparedness exercise on June 12, 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 and the concentrations and quantities of radioactive materials and

how the licensee assesses radiological hazards.

Instructions to Workers (IP Section 03.02) (1 Sample)

(1)

The inspectors evaluated how the licensee instructs workers on plant-related

radiological hazards and the radiation protection requirements intended to protect

workers from those hazards.

8

Contamination and Radioactive Material Control (IP Section 03.03) (3 Samples)

The inspectors observed/evaluated the following licensee processes for monitoring and

controlling contamination and radioactive material:

(1)

observed radiological surveys of potentially contaminated packages/equipment that

were being delivered from offsite locations for incorporation into its radiological

control program

(2)

walked down the storage locations for several nonexempt radioactive sources listed

in the licensee's non-exempt source inventory

(3)

evaluated the licensee's physical and programmatic controls for highly activated and

contaminated non-fuel materials stored within the spent fuel pool

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)

direct observation of locked high radiation area (LHRA) work activities and job

coverage in support of reactor coolant pump removal and movement into a shipping

cask under radiation work permit (RWP) R27DRCPINTLIFT, revision 0

(2)

direct observation of work activities and job coverage in support of fuel assembly

inspection activity and the replacement of a control assembly into an unirradiated fuel

bundle under RWP R27FUEL, revision 0

(3)

walkdown of satellite radiologically controlled areas to assess storage and security of

outage related to posted radioactive materials areas and stored contaminated items

High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)

The inspectors evaluated licensee controls of the following high radiation areas and very

high radiation areas (VHRAs):

(1)

containment instrument in-core tunnel - VHRA

(2)

waste holdup tank room, radwaste room 7122 - LHRA

(3)

entrance to stock system/decant tank room, radwaste room 7213 - LHRA

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 ventilation system (FGK01B)

(2)

technical support center filtered ventilation system (FUB7001)

9

Temporary Ventilation Systems (IP Section 03.02) (2 Samples)

The inspectors evaluated the configuration of the following temporary ventilation systems:

(1)

reactor coolant pump D impeller work, radiation work permit R27DRCPINT,

Revision 0, supported by high efficiency particulate air units VAC-4116-HP, test due

date March 19, 2027, and VAC-4117-HP, test due date May 8, 2025

(2)

reactor head LHRA supported by high efficiency particulate air unit VAC-4111-HP,

test due date March 4, 2027

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 indicator submittals listed below:

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (1 Sample)

(1)

April 2024 to March 2025

MS08: Heat Removal Systems (IP Section 02.07) (1 Sample)

(1)

April 2024 to March 2025

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1)

April 1, 2024, to 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, to December 31, 2024

71152A - Annual Follow-up Problem Identification and Resolution

Annual Follow-up of Selected Issues (Section 03.03) (3 Samples)

The inspectors reviewed the licensees implementation of its corrective action program

related to the following issues:

(1)

non-compliance with ASME Code Section XI during job 20003148.496 on February 5,

2025

10

(2)

corrective actions regarding inadvertent discharge of safety injection on April 5, 2025

(3)

corrective actions regarding a Part 21 notification on faulty full voltage reversing

starters used in motor-operated valve motor control centers on April 23, 2025

71152S - Semiannual Trend Problem Identification and Resolution

Semiannual Trend Review (Section 03.02) (1 Sample)

(1)

The inspectors reviewed the licensees corrective action program to identify instances

of debris found in fuel assemblies on April 8, 2025.

71153 - Follow-Up of Events and Notices of Enforcement Discretion

Event Follow-Up (IP Section 03.01) (1 Sample)

(1)

The inspectors evaluated follow-up on the loss of backfeed during shutdown cooling

operations and the licensees response on April 23, 2025.

INSPECTION RESULTS

Failure to Perform an Adequate Part 21 Review

Cornerstone

Significance

Cross-Cutting

Aspect

Report

Section

Barrier Integrity

Green

NCV 05000483/2025002-01

Open/Closed

[P.5] -

Operating

Experience

The inspectors reviewed a self-revealed Green finding and associated non-cited violation

of 10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action, for the licensees failure to

promptly identify and correct a condition adverse to quality. Specifically, the licensee failed to

recognize the applicability of a 10 CFR Part 21 report regarding possible mechanical binding

of full reversing starter mechanical interlocks in 2021. Subsequently, five safety-related

motor-operated valves failed due to this issue.

Description: On April 29, 2021, Paragon made a report in accordance with 10 CFR Part 21

about mechanical interlocks binding on two different starters and contactors. The licensee

wrote a condition report on May 19, 2021, assessing applicability and incorrectly determined

that the affected starters did not affect the Callaway Plant.

On November 18, 2021, component cooling water from containment outer isolation

valve EGHV0059 providing cooling flow to the reactor coolant pumps failed to open. The

starter was not functioning properly and prevented the valve from opening. The licensee

determined the failure cause was binding of the starter, congruent with the identified failures

of Paragon starters reported in the Part 21. The licensee identified the failed starter, and

21 additional, size 1 starters, as well as 2 size 2 starters that had the same part numbers as

the Part 21 identified faulty starters. Previously the licensee stated in a condition report that

Callaway Energy Center does not use the type of starters (DC Control Coils) discussed in

the Part 21 (Revision 2), because all units at Callaway have AC control power.

On November 7, 2023, the residual heat removal train B minimum flow valve EJFCV0611

failed to open during stroke time testing. The licensee removed the starter and shipped it to

Paragon for analysis, as documented in condition report (CR) 202403500. Paragons

response concluded in part, the date codes and material are within the range under Paragon

11

Part 21 notification P21-03302021 in which similar issues were previously experienced.

ThePart 21 notification indicates the issues in question were from units fabricated between

Sept. 2014 to Sept. 2018. The returned units are from Jan. 2018, and the interlock rockers

are the same material from this revision of interlock. In CR 202403690 the licensees

recommendation was to replace each starter during the next available work window via the

normal work management processes.

Three additional Paragon starters had binding issues resulting in the failure of BNHV0003

containment spray (CS) train B pump suction, EMHV8807A residual heat removal train A

heat exchanger to safety injection pumps suction isolation, and ENHV0006 CS train A pump

discharge valves. These failures prompted the licensee to reassess the applicability of the

Paragon reported Part 21. Failure of CS train A pump discharge valve ENHV0006 to open

degraded the safety function of the system.

In May 2025 the licensee concluded their initial assessment was erroneous and Part 21 did

apply to Callaway.

Corrective Actions: The licensee identified and removed the mechanical interlock on the

Part 21 nonconforming starters, as well as identified and removed the mechanical interlock

on all starters with the part number identified in Part 21, regardless of the affected date range.

Corrective Action References: Condition Reports 202102874, 202308366; 202502573; and

202503012

Performance Assessment:

Performance Deficiency: The inspectors determined that the failure to identify and correct a

condition adverse to quality associated with failing starters identified in a Part 21 report was a

performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor

because it was associated with the Structures, Systems, Components and Barrier

Performance attribute of the Barrier Integrity cornerstone and adversely affected the

cornerstone objective to provide reasonable assurance that physical design barriers protect

the public from radionuclide releases caused by accidents or events. Specifically, the

performance deficiency resulted in the inoperability of containment spray train A subsystems.

Significance: The inspectors assessed the significance of the finding using Inspection Manual

Chapter 0609, Appendix A, The Significance Determination Process for Findings At-Power.

The inspectors used exhibit 3, Barrier Integrity Screening Questions, to determine that the

finding was of very low safety significance (Green) because the finding: (1) did not represent

an actual open pathway in the physical integrity of reactor containment, failure of containment

isolation system, failure of containment pressure control equipment, failure of containment

heat removal components, or failure of the plants severe accident mitigation features; and

(2) did not involve an actual reduction in function of hydrogen igniters in the reactor

containment.

Cross-Cutting Aspect: P.5 - Operating Experience: The organization systematically and

effectively collects, evaluates, and implements relevant internal and external operating

experience in a timely manner.

12

Enforcement:

Violation: Title 10 CFR Part 50, Appendix B, Criterion XVI, requires, in part, that measures

shall be established to assure that conditions adverse to quality, such as failures,

malfunctions, deficiencies, deviations, defective material and equipment, and

nonconformances are promptly identified and corrected.

Contrary to the above, between April 29, 2021, and May 1, 2025, the licensee failed to

establish measures to ensure that conditions adverse to quality, such as failures,

malfunctions, deficiencies, deviations, defective material and equipment, and

nonconformances were promptly identified and corrected. Specifically, the licensee failed to

identify safety-related starters with date codes that were identified in the Part 21 report by

Paragon. As a result, five of the relays experienced mechanical binding and failed to open the

associated valves, rendering the safety functions of the containment spray system degraded.

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 April 8, 2025, the inspectors presented the inservice inspection results to R. Ryterski,

Manager, Nuclear Strategic Initiative, and other members of the licensee staff.

On April 11, 2025, the inspectors presented the occupational radiation safety inspection

results to K. Scott, then Nuclear Site Vice President and other members of the licensee

staff.

On July 15, 2025, the inspectors presented the integrated inspection, inspection results

to K. Scott, Senior Vice President and Chief Nuclear Officer and other members of the

licensee staff.

13

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.04

Procedures

OSP-BB-00003

PORV/RHR COMS Alignment Verification

15

71111.04

Procedures

OTN-EN-00001

Containment Spray System

26

71111.05

Fire Plans

Fire Preplan Manual

43

71111.05

Miscellaneous

Fire Safety Analysis Calculation KC-156, Fire Area TB-1

2

71111.07A

Corrective Action

Documents

Condition Reports

202501956

Corrective Action

Documents

Condition Reports

202202004, 202306096, 202306121, 202306156,

202306300, 202306492, 202306740, 202306747,

202306960, 202306976, 202306995, 202307006,

202307056, 202307085, 202307107, 202307124,

202307134, 202307188, 202307197, 202307212,

202307247, 202307317, 202307374, 202307421,

202307519, 202307524, 202307537, 202307605,

202307608, 202307610, 202307664, 202307688,

202307707, 202307708, 202307749, 202307858,

202307908, 202307945, 202307963, 202308035,

202308042, 202308046, 202308182, 202308192,

202308345, 202308347, 202308370, 202308527,

202308621, 202308766, 202309069, 202309088,

202309089, 202309197, 202309221, 202309248,

202309249, 202400535, 202400690, 202401125,

202401171, 202401172, 202401320, 202401455,

202401559, 202401647, 202401736, 202401794,

202401977, 202401984, 202401988, 202402021,

202402065, 202402276, 202402347, 202402498,

202402501, 202402555, 202402675, 202402715,

202403110, 202403201, 202403225, 202403264,

202403391, 202403614, 202403687, 202403706,

202403708, 202403760, 202403961, 202404134,

202404262, 202404545, 202404947, 202405149,

202405159, 202405178, 202405187, 202405273,

202405377, 202405769, 202405824, 202405951,

14

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

202406120, 202406196, 202406204, 202406233,

202406299, 202406370, 202406412, 202406417,

202406578, 202406609, 202406634, 202406660,

202406681, 202406748, 202406794, 202406822,

202406924, 202407291, 202407318, 202407493,

202407593, 202407635, 202500081, 202500087,

202500095, 202500121, 202500413, 202500465,

202500970, 202501742

Miscellaneous

51 - 9343293

Callaway 1R25 Degradation Assessment - April 2022

0

Miscellaneous

51 - 9350895

Callaway Unit 1 SG Condition Monitoring for Cycles 22, 23,

24 and 25 and Final Operational Assessment for Cycles 26,

27, 28, 29 and 30

0

Miscellaneous

CW0404-05

Callaway Energy Center ISI Program Plan Fifth Inspection

Interval

0

Miscellaneous

CW0404-06

Callaway Energy Center ISI Selection Document Fifth

Inspection Interval

0

Miscellaneous

CW0404-07

Callaway Energy Center Risk-Informed Inservice Inspection

Supplemental Report Fifth Inspection Interval

0

Miscellaneous

EPID L-2024-LLR-

0084

Callaway Plant, Unit 1 - Verbal Authorization of Relief

Requests IWE-01 and IWE-02

03/04/2025

Miscellaneous

RFR 2230232

Steam Generator Integrity Assessment Refuel 26

09/28/2023

Miscellaneous

Technical Report

EP-2014-0001-03-

TR

Ameren Missouri - Callaway Energy Center Erosion

Susceptibility Evaluation (ESE) Update Issued February 13,

2015

0

Miscellaneous

ULNRC-06915

Callaway Plant Unit 1 Union Electric Co. Renewed Facility

Operating License NPF-30 Proposed Change to Technical

Specifications to Allow H-08 Control Rod to be Removed for

Cycle 28 (LDCN 25-0005)

0

Procedures

APA-ZZ-00661

Administration Of Welding

22

Procedures

APA-ZZ-00662

ASME Section XI Repair/Replacement Program

28

Procedures

EDP-ZZ-01004-

R025

BACCP Program Procedure

25

Procedures

LMT-08-PDI-UT-1

Ultrasonic Examination of Ferritic Piping Welds

0

Procedures

LMT-08-PDI-UT-2

Ultrasonic Examination of Austenitic Piping Welds

0

15

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Procedures

LMT-08-PDI-UT-3

Ultrasonic Through Wall Sizing in Piping Welds

0

Procedures

LMT-08-PDI-UT-5

Straight Beam Ultrasonic Examination of Bolts and Studs

07.20.2016-Final

0

Procedures

LMT-08-UT-004

Ultrasonic Examination of Vessel Welds and Adjacent Base

Metal > 2.0 in Thickness

1

Procedures

LMT-08-UT-118

Ultrasonic Examination Technique for Thermal Fatigue

Cracking/Crazing (MRP-146 & MRP-192)

1

Procedures

LMT-08-UT-119

Conventional Ultrasonic Instrument Linearity

1

Procedures

MDP-ZZ-LM001-

R022

Fluid Leak Management Program

22

Procedures

QCP-ZZ-05040

Visual Examination to ASME VT-1

27

Procedures

QCP-ZZ-05041

Visual Examination to ASME VT-2

32

Procedures

QCP-ZZ-05042

Visual Examination to ASME VT-3

24

Procedures

QCP-ZZ-05048-

R015

BA Walkdown for RCS Pressure Boundary QC

15

Procedures

QCP-ZZ-05049-

R007

RPV Head Bare Metal Examination

7

71111.12

Miscellaneous

KC-43, Code

Compliance

Evaluation NFPA-

805

Performance Based Standard for Fire Protection for Light

Water Reactor Electrical Generating Plants

2

71111.12

Procedures

APA-ZZ-00703

Fire Protection Operability Criteria and Surveillance

Requirements

35

71111.12

Procedures

EDP-ZZ-01101

Fire Protection Monitoring Program

4

Corrective Action

Documents

Condition Reports

202503067

Procedures

APA-ZZ-00315

Risk Management Actions

7

Procedures

APA-ZZ-00315,

Appendix E

Configuration Risk Management Program - Shutdown

2

Procedures

OSP-SA-2143A

Train A Diesel Generator and Sequencer Testing

35

Procedures

OTO-NB-00002

Loss of Power to NB02

37

Work Orders

Jobs

22504386

71111.15

Corrective Action

Documents

Condition Reports

202501697, 202501742, 202501920, 202502036,

202502067, 202502095, 202502392

16

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.15

Drawings

M-22AL-1

Piping and Instrumentation Diagram Auxiliary Feedwater

System

51

71111.15

Miscellaneous

Pressure Boundary Breach Evaluation Form

04/07/2025

71111.20

Procedures

OTG-ZZ-00007

Refueling Preparation, Performance, and Recovery

46

Miscellaneous

Modification

Package

25-0008

Procedures

APA-ZZ-00322,

Appendix E

Post-Maintenance Test Program

21

Procedures

ESP-ZZ-00032

Test Procedure for Automated Measurement of Drop Times

of Control and Shutdown Rods in Westinghouse PSRS with

DRPI Power-On

5

Procedures

OSP-AE-V02HS

Main Feedwater Isolation Valve Inservice Test

43

Procedures

OSP-AL-P0002

Turbine Driven Auxiliary Feedwater Pump Inservice Test -

Group B

83

Procedures

OSP-AL-PV005

Turbine Driven Auxiliary Feedwater Pump and Check Valve

Inservice Test

30

Procedures

OSP-AL-V0003

Auxiliary Feedwater Pump Discharge Check Valve Closure

Test

18

Procedures

OSP-AL-V001A

Train A Auxiliary Feedwater Valve Inservice Test

64

Procedures

OSP-ZZ-LL075

Containment Isolation Valve Leak Rate Test

19

Procedures

OTN-ZZ-00004

Operation of the Leak Rate Monitor (LRM)

12

Procedures

QCP-ZZ-05041

Visual Examination to ASME VT-2

32

Work Orders

Jobs

25001164, 22005060, 23512006, 23511787, 23511732,

23511628, 25001164, 23512826, 23512006

71114.06

Procedures

EIP-ZZ-00101

Classification of Emergencies

57

71114.06

Procedures

EIP-ZZ-00101,

Addendum 2

Emergency Action Level Technical Bases

22

Corrective Action

Documents

Condition Reports

202404415, 202404483, 202404709, 202405036,

202405062, 202405388, 202405710, 202405866,

202406202, 202406303, 202406497, 202406990,

202407007, 202500523, 202500524, 202500712,

202500740, 202501136

Foreign Material Exclusion

Procedures

APA-ZZ-00801

62

17

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Procedures

APA-ZZ-01000,

Appendix A

Control of Radioactive Material

25

Procedures

HDP-ZZ-01500

Radiological Postings

54

Procedures

HTP-ZZ-02004

Control of Radioactive Sources

46

Procedures

HTP-ZZ-06028

Radiological Controls for Pools that Contain or Store Spent

Fuel

10

Radiation

Surveys

CA-M-20250406-

20

Characterization Survey of C RCP

Radiation

Surveys

CA-M-20250407-

13

Characterization Survey - Container 30031212

Radiation Work

Permits

23004769

Disassemble, Inspect, Clean, and Reassemble Check Valve

EP8956C

1

Radiation Work

Permits (RWPs)

R27DRCPCOORD

D Reactor Coolant Pump Internals Replacement

Oversite/Coordination Activities

1

Radiation Work

Permits (RWPs)

R27DRCPINT

All Prep Work for the Removal and Installation Associated

with D Reactor Coolant Pump Internals

2

Radiation Work

Permits (RWPs)

R27DRCPINTLIFT

Lift D Reactor Coolant Pump Internals from Housing and

Place in Shipping Container. Install/Remove Temporary

FME Cover. Install FME Shield Plug in Pump Casing. Clean

Flange for Machining.

2

Radiation Work

Permits (RWPs)

R27DRCPINTRP

Radiation Protection Coverage for D Reactor Coolant Pump

Internals Replacement. All Work Associated with D Reactor

Coolant Pump Internals.

0

Radiation Work

Permits (RWPs)

R27FUEL

Offload Reactor, Perform FOSAR, Perform Reactor Reload,

Core Mapping, Insert Shuffle, Pool Mapping, B5B Moves,

and Miscellaneous Support Activities

0

Calibration

Records

Air Quality Analysis Report for Bauer UNIII/25H-E3, SN

102386

03/27/2025

Calibration

Records

Job 24001284

Calibration Certificate of Temporary HEPA Unit

ID# VAC-4111-HP

04/09/2024

Calibration

Records

Job 24002990

Calibration Certificate of Control Room Emergency Air

Supply Tank ID# MAC-0025-HP

09/05/2024

Calibration

Records

Job 25001058

Calibration Certificate of Temporary HEPA Unit

ID# VAC-4116-HP

03/19/2025

18

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Corrective Action

Documents

Condition Reports

202202309, 202202390, 202204037, 202205472,

202205959, 202206137, 202206687, 202206945,

202207201, 202207499, 202207688, 202207869,

202208007, 202208386, 202300634, 202300883,

202302393, 202303626, 202400594, 202401265,

202402782, 202404323, 202405551, 202407056

Drawings

HTP-ZZ-08501-

DTI-AIR TEST

Testing of Breathing Air

5

Miscellaneous

Certification ID

C020875

Scott Technical Support: SCBA Certified Technician II,

Maintenance and Overhaul - Jeff Eldringhoff

01/24/2025

Procedures

ESP-GK-03001

FGK01A Charcoal Test Canister Removal and Lab Testing

20

Procedures

ESP-GK-03002

FGK01B Charcoal Test Canister Removal and Lab Testing

21

Procedures

ESP-UB-03001

FUB7001 Charcoal Test Canister Removal and Lab Testing

18

Procedures

ESP-UB-03012

FUB7001 In-Place Bypass Leakage Test

5

Procedures

ETP-ZZ-03004

In-Place Bypass Leakage Testing of Adsorber Stage

12

Procedures

ETP-ZZ-03005

In-Place Bypass Leakage Testing of HEPA Filters

10

Procedures

HTP-ZZ-08203-

DTI-

REGULATORS

Testing Scott Regulators and Respirators Using the

Biosystems Posichek 3 USB Tester

11

Procedures

HTP-ZZ-08502-

DTI-MAC-CAL

Scott Mobile Air Cart Calibration

4

Procedures

HTP-ZZ-08503-

DTI-

UNIIICompressor

Operation of Bauer Unicus III, 25 CFM Breathing Air

Compressor and Breathing Air Cascade System

7

Work Orders

Job 22509842-500

FGK01B Charcoal Test Canister Removal and Lab Testing

02/13/2024

Work Orders

Job 23506576-500

FGK01A Charcoal Test Canister Removal and Lab Testing

10/15/2024

Work Orders

Job 22507436-500

In-Place Bypass Leakage Testing of Adsorber Stage and In-

Place Bypass Leakage Testing of HEPA Filters for FGK01B

12/07/2023

Work Orders

Job 22510055-500

In-Place Bypass Leakage Testing of Adsorber Stage and In-

Place Bypass Leakage Testing of HEPA Filters for FGK01A

12/18/2023

Work Orders

Job 23500086-500

Radioiodine Penetration / Efficiency Test Report for TSC

Filter Unit FUB7001

05/22/2024

Work Orders

Job 23506199-500

Charcoal Adsorber In-Place Leak Test Report and HEPA

Filter Leak Test Report for TSC Filtering Unit FUB7001

12/16/2024

19

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Work Orders

Job 25000432

Posi3 USB Test Results of Regulator APR-0057-HP

02/07/2025

Work Orders

Job 25000433

Posi3 USB Test Results of Regulator APR-0067-HP

02/07/2025

Work Orders

Respiratory

Protection Monthly

Inspections

22507157, 22508202, 22509545, 22511985, 22512620,

22513609, 23500069, 23502647, 23503603, 23504846,

23506439, 23508039, 23509135, 23509623, 23512047,

23513194, 23514297, 24500708, 24501913, 24502596,

24503986, 24505243, 24506364, 24507852, 24508437,

24509667, 24511131, 24512424, 25500070

71151

Miscellaneous

Heat Removal System Performance Indicator Data for April

2024 through March 2025

71151

Miscellaneous

Safety System Functional Failure Performance Indicator

Data for April 2024 through March 2025

71151

Miscellaneous

PM0911004

Dose Assessment from Liquid Effluents (Quarterly):

January - December 2024 and January - March 2025

71151

Miscellaneous

PM0911009

Dose Assessment from Noble Gases (Quarterly): January -

December 2024 and January - March 2025

71151

Miscellaneous

PM0911010

Dose Assessment from Radioiodines and Particulates

(Quarterly): January - December 2024 and January - March

2025

Corrective Action

Documents

Condition Reports

202005276, 202307958, 202308226, 202308929,

202400480, 202406120, 202406164

Procedures

APA-ZZ-00662

ASME Section XI Repair/Replacement Program

28

Procedures

EDP-ZZ-01007

Mechanical Snubber Program

34