IR 05000482/2025004
| ML26016A522 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 01/23/2026 |
| From: | Ami Agrawal NRC/RGN-IV/DORS/PBB |
| To: | Reasoner C Wolf Creek |
| References | |
| IR 2025004 | |
| Download: ML26016A522 (0) | |
Text
January 23, 2026
SUBJECT:
WOLF CREEK GENERATING STATION - INTEGRATED INSPECTION REPORT 05000482/2025004
Dear Cleve Reasoner:
On December 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Wolf Creek Generating Station. On January 8, 2026, the NRC inspectors discussed the results of this inspection with Robert Bayer, Vice President of Engineering, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
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, Ami N. Agrawal, Chief Reactor Projects Branch B Division of Operating Reactor Safety Docket No. 05000482 License No. NPF-42
Enclosure:
As stated
Inspection Report
Docket Number:
05000482
License Number:
Report Number:
Enterprise Identifier:
I-2025-004-0006
Licensee:
Wolf Creek Nuclear Operating Corp.
Facility:
Wolf Creek Generating Station
Location:
Burlington, KS
Inspection Dates:
October 1, 2025 to December 31, 2025
Inspectors:
J. Drake, Senior Reactor Inspector
D. Grau, Health Physicist
C. Henderson, Senior Resident Inspector
J. O'Donnell, Senior Health Physicist
C. Sigel, Resident Inspector
Approved By:
Ami N. Agrawal, Chief
Reactor Projects Branch B
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Wolf Creek Generating Station, 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
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000482/2025-001-00 Improperly Breached Control Building Doors Cause a Condition Prohibited by Technical Specifications 71153 Closed LER 05000482/2025-003-00 Loss of Voltage on ESF
[Engineered Safety Feature]
Bus Results in Automatic Actuation of Emergency Diesel Generator 71153 Closed
PLANT STATUS
Wolf Creek Generating Station began the inspection period with a power coast down to refueling outage 27. On October 2, 2025, the unit was shut down to begin refueling outage 27.
On November 14, 2025, the unit commenced reactor startup, and the reactor was made critical.
The unit returned to full power on November 19, 2025, where it remained for the rest 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 onsite 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) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)trains A and B residual heat removal shutdown cooling alignment during refueling outage on October 19, 2025 (2)reactor coolant system pressure control system and pressurizer spray line on November 3, 2025 (3)trains A and B containment spray system following containment integrated leak rate testing on December 15, 2025
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (2 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)main transformer deluge testing, fire area yard, on November 3, 2025 (2)condensate pump C, fire area "Turb", on November 21, 2025 71111.08P - Inservice Inspection Activities (PWR)
Due to the government shutdown, this inspection was completed remotely via in office document review. 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 documents associated with the following activities in Unit 1 during refueling outage 1R27.
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
- steam generator, EBB01A-SEAM-3-W, stub barrel to shell section weld
- steam generator, EBB01A-SEAM-6-W, stub barrel to shell section weld
- steam generator, EBB01A-SEAM-2-W, tubesheet to stub barrel weld
- steam generator, EBB01A-11-W, feedwater nozzle to shell weld Dye Penetrant Examination
- residual heat removal, EEJ01A-SKIRT, skirt support weld Magnetic Particle Examination
- steam generator, EBB01A-11-W, feedwater nozzle to shell weld Visual 3 Examination
- accumulator safety injection, EP-01-R008, piping support
- accumulator safety injection, EP-01-H006, piping support Welding Activities
- gas tungsten arc welding process
- safety injection, valve BGHV8153B, socket welds, SW-1A, SW-2, SW-3a PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection Activities (IP Section 03.02)
There was no ASME Code reactor vessel head inspection 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)
- 10033393 / 20047316 BBV0311
- 10044591 / 20053937 BBPT0150
- 10044585 / 20053950 EMV0223
- 10044582 BGV0340
- 10044585 EMV0223
- 10044588 BBV0259
- 10044591 BBPT0150
- 10044602 BB8378A
- 10044609 BBV0007
- 10044612 BGV0437
- 10044616 BB8016B
- 10044642 Canopy Seal Weld
- 10044645 BBPCV0455C
- 10044826 EP8956A
- 10044867 BBV0224
- 10045692 ENV0109
- 10045916 EMV0179
- 10046153 BBV0311
- 10046278 BGPIS0140
- 10046430 ENV0027 PWR Inservice Inspection Activities Sample - Steam Generator Tube Inspection Activities (Section 03.04)
There were no ASME Code required steam generator tube inspections required for 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 reactor plant shutdown for refueling outage 27 on October 1, 2025.
- (2) The inspectors observed and evaluated licensed operator performance in the control room during reactor startup from refueling outage 27 on November 14, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated reactor startup from refueling outage 27 just-in-time training on October 28, 2025.
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 (SSCs) remain capable of performing their intended function:
(1)emergency diesel generators A and B maintenance effectiveness and operating experience review on October 24, 2025
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (2 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)emergent work and troubleshooting of the turbine-driven auxiliary feedwater pump tripping on overspeed during surveillance testing on November 19, 2025 (2)auxiliary building and control room pressurization test with multiple doors breached to verify emergency exhaust and control room emergency ventilation past operability on November 28, 2025
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (1 Sample)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)emergency diesel generator B intercooler heat exchanger power pill and air start relay failure past operability review on December 16, 2025
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
(1)main transformer and main generator automatic voltage regulator replacement on October 15, 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 from October 1 to November 16, 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) (7 Samples)
(1)train A and B residual heat removal maintenance outage post-maintenance testing on October 15, 2025 (2)emergency diesel generator B major overhaul post-maintenance testing on October 23, 2025 (3)train B essential service water maintenance outage post-maintenance testing on October 23, 2025 (4)train B component cooling water system maintenance outage post-maintenance testing on October 24, 2025 (5)reactor coolant system loop 2 pressurizer spray valve, BBPCV0455B, replacement post-maintenance testing on November 14, 2025 (6)main generator automatic voltage regulator and main transformer replacement post-maintenance testing on November 18, 2025 (7)train A motor-driven auxiliary feedwater discharge header to steam generator C motor-operated isolation valve actuator, ALHV0011, replacement post-maintenance testing on December 15, 2025
Surveillance Testing (IP Section 03.01) (4 Samples)
(1)borated refueling water storage tank system inservice valve leakage surveillance testing on October 15, 2025 (2)containment integrated leak rate testing on November 1, 2025 (3)train B load shedder and emergency sequencer card replacement post-maintenance testing and engineering safety feature actuation instrumentation surveillance testing on November 7, 2025 (4)excess letdown solenoid operated valves inservice testing following replacement on December 4, 2025
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
(1)local leak rate testing of reactor coolant pump loop B seal water supply valve, containment penetration 22, on October 24, 2025
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS08: Heat Removal Systems (IP Section 02.07) (1 Sample)
- (1) November 1, 2024, through June 30, 2025
MS09: Residual Heat Removal Systems (IP Section 02.08) (1 Sample)
- (1) November 1, 2024, through June 30, 2025
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) April 1, 2024, through September 30, 2025 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 September 30, 2025 71152A - Annual Follow-up Problem Identification and Resolution
Annual Follow-up of Selected Issues (Section 03.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)pressurizer spray valve leakage and bypass valve flow setting on November 3, 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 potential trends in opened items in the operations deficiency log and corrective actions closed to work orders backlog that might be indicative of a more significant safety issue.
71153 - Follow-Up of Events and Notices of Enforcement Discretion Event Follow-up (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated the loss of construction loop electrical circuit due to breaker 13-4 tripping open and actuation of control room ventilation isolation signal, containment purge isolation signal, fuel building isolation signal, and train A control room air condition and pressurizer fan trip due to blown fuse and licensees response on November 20, 2025.
Event Report (IP Section 03.02) (2 Samples)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000482/2025-001-00, "Improperly Breached Control Building Doors Cause a Condition Prohibited by Technical Specifications" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML25351A282). The inspection conclusions associated with this LER are documented in this report under Inspection Results Section 71153. This LER is Closed.
- (2) LER 05000482/2025-003-00, "Loss of Voltage on ESF Bus Results in Automatic Actuation of Emergency Diesel Generator" (ML25351A150). The inspectors determined that the cause of the condition described in the LER was not reasonably within the licensee's ability to foresee and correct, and therefore was not reasonably preventable. No performance deficiency nor violation of NRC requirements was identified. This LER is Closed.
INSPECTION RESULTS
Minor Violation 71153 Minor Violation: The licensee identified a failure to implement administrative controls for an opening in the control room envelope and control building envelope boundaries, ensuring they are closed consistently with the safety analysis during core alterations. This was a performance deficiency.
Screening: The inspectors determined the performance deficiency was minor. The performance deficiency is minor because it did not adversely impact the Barrier Integrity cornerstone for maintaining the radiological barrier functionality of the control room. Specifically, the licensee performed Procedure STS PE-004, Auxiliary Building and Control Room Pressure Test, Revision 20, Doors 33012 and 31011 open under administrative controls to demonstrate the control room envelope would maintain the required technical specification pressurization of greater than or equal to 0.25 inches water gauge.
Enforcement:
Technical Specification 3.7.10, Control Room Emergency Ventilation System (CREVS), requires that while the plant is in MODES 1, 2, 3, and 4, during core alterations, during movement of irradiated fuel assemblies, two CREVS trains shall be operable and the control room envelope and control building envelope boundaries may be opened intermittently under administrative controls that ensure the building boundary can be closed with the safety analysis. Condition E requires when one or more CREVS trains are inoperable due to an inoperable control room envelope boundary during core alterations, it immediately suspends core alterations.
Contrary to the above, on October 10, 2025, from 9:06 a.m. to 9:19 a.m., during core alterations the licensee failed to implement administrative controls for when Doors 33012 and 31011 were opened to ensure they are closed consistently with the safety analysis during core alterations. The licensee immediately closed Doors 333012 and 31011 upon discovery to restore compliance with Technical Specification 3.7.10, Condition E. This failure to comply with Technical Specification 3.7.10 constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 8, 2026, the inspectors presented the integrated inspection results to Robert Bayer, Vice President of Engineering, and other members of the licensee staff.
- On December 4, 2025, the inspectors presented the Exit meeting for inservice inspection results to Josh Turner, Regulatory Affairs Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Condition Report
(CR)
67683, 10034501, 10043396, 10045196, 10046236,
10046237, 10046246, 10017814, 10025638, 10021234
Corrective Action
Documents
Resulting from
Inspection
Condition Report
(CR)
10045290, 10045591, 10045601, 10045603, 10046136,
10047948
M-12BB01
Piping and Instrumentation Diagram Reactor Coolant
System
M-12BB02
Piping and Instrumentation Diagram Reactor Coolant
System
Drawings
M-12EJ01
Piping and Instrumentation Diagram Residual Heat Removal
System
Engineering
Changes
CP 020865
BBPCV0455B Valve Replacement
M-10EJ
System Description Residual Heat Removal
M-724-00448
Instruction Manual for Pressurizer Spray Valve
W10
Wolf Creek Generating Station Transition of Core Design
and Safety Analyses to Westinghouse Methods and
Alternate Source Term Engineering Report
Miscellaneous
WCRE-34
Fourth 10-Year Interval Inservice Testing Basis Document
ALR 00-033C
PZR Press LO HTRS On
ALR 00-035B
PORV Open
BD-OFN MA-038
Rapid Plant Shutdown
GEN 00-004
Power Operation
2
GEN 00-006
Hot Standby to Cold Shutdown
106
OFN BB-031
Shutdown LOCA
OFN EJ-015
Loss of RHR Cooling
OFN EJ-040
CL Recirc during Mode 3with Accumulators Isolated Mode 4,
5, o 6
OFN MA-001
Load Rejection or Turbine Trip
OFN MA-038
Rapid Plant Shutdown
2A
Procedures
SYS BB-203
Pressurizer Backup Heater Operations
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SYS EF-121
Startup of A RHR Train in Cooldown Mode
SYS EJ-120
Startup of A Residual Heat Removal Train
Work Orders
WO 23, 128490, 147853, 147862, 20036382, 20039620,
2-483478-000
Corrective Action
Documents
Condition Report
(CR)
10044951, 10045435, 10045485
Miscellaneous
WCRE-35
Boundary Matrix
Procedures
STN KC-216E
Main Transformers Deluge Spray Testing
008
Corrective Action
Documents
10031846, 10031864, 00136243, 10034009, 10035593,
10035594, 10038448, 10042664, 10031862, 10031957,
10031999, 10032067, 10032127, 10035080, 10035591,
10035592, 10036043, 10038960, 10039174, 10041804,
10042596, 10043072, 10043394, 10043579, 10044110,
10044886, 10044876
INR-WC-1R26-
24-04
Radial Support Keys at 120°, 240° and 300°
04/14/2024
PWROG letter
OG-21-160R1
Justification for Continued Operation for Clevis Block Insert
and Bolts Inspection
04/27/2024
Miscellaneous
SA-2025-0204
ISI self assessment 2025
07/03/2025
54-IS1-604-017
Automated Ultrasonic Examination of Open Tube RPV
Closure Head Penetrations
54-ISI-460-009
Multi-Frequency Eddy Current Orthogonal Coil Array Probe
Examination of Nozzle Welds and Regions
54-ISI-494-005
Multi-Frequency Eddy Current Array ID Probe Examination
of Vent Line and RVLIS Nozzle Bores
54-ISI-603-013
Automated Ultrasonic Examination of RPV Closure Head
Penetrations Containing Thermal Sleeves
54-UT-901-004
Automated Ultrasonic Examination of Wear in RPV Closure
Head Thermal Sleeves
AI 16F-001
Evaluation Of Boric Acid Leakage
AI 16F-002
Boric Acid Leakage Management
Boric Acid Corrosion Control Program
Fluid Leakage Management
1A
Procedures
Self-Assessment Process
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Docket No. 50-
2
Notification of Extension to the Fourth Ten-Year Interval of
the Inservice Testing Program
09/03/2025
GWS-ASME
ASME General Welding Standard
LMT-08-MT-01
Magnetic Particle Examination
LMT-08-PDI-UT-1 Ultrasonic Examination of Ferritic Piping Welds
LMT-08-PDI-UT-
Ultrasonic Examination of Nozzle Inner Radius Areas at Wolf
Creek Nuclear Operating Corporation
LMT-08-PDI-UT-2 Ultrasonic Examination of Austenitic Piping Welds
LMT-08-PDI-UT-3 Ultrasonic Through Wall Sizing in Piping Welds
LMT-08-UT-004
Ultrasonic Examination of Vessel Welds and Adjacent Base
Metal > 2.0 in Thickness
LMT-08-UT-119
Conventional Ultrasonic Instrument Linearity
WCRE-30
Inservice Inspection Program Plan Wolf Creek Generating
Station Interval 4
WCRE-36
Containment Inservice Inspection (CISI) Program Plan Wolf
Creek Generating Station Interval 3
WCRE-40
Inservice Inspection Program Plan Wolf Creek Generating
Station Interval 5
Work Orders
WO 60740, 77098, 92648, 109004, 113426, 113460
EMG E-0
Reactor Trip or Safety Injection
EMG ES-02
Reactor Trip Response
GEN 00-003
Hot Standby to Minimum Load
111, 112
GEN 00-004
Power Operations
2
GEN 00-005
Minimum Load to Hot Standby
Procedures
GEN 00-006
Hot Standby to Cold Shutdown
106
Corrective Action
Documents
Condition Report
(CR)
10045385, 10042393, 10041165, 10041372, 10041703,
10041825, 10041890, 10042663, 10042690, 10043234,
10043335, 10043351, 10043395, 10043492, 10043719,
10043714, 10044201, 10044345, 10044497, 10044552,
10012536, 10012550, 10029593
Work Orders
WO 114936, 75563, 58731, 70762, 104553, 17194, 17201,
212, 81637, 81641, 106888, 114106, 140169, 58995,
59001, 59009, 67436, 67672, 67708, 59001, 59009, 67436,
67672,96036, 104553, 17205, 70762, 39977
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Condition Report
(CR)
10046923, 10046945, 10046948, 10046985
Breach authorization permits: PT118168, 118170, 118174,
118176, 118258
M-021-00086
Instruction Manual for Terry Turbine Corp.
W53
M-021A-00011
Instruction Manual for Terry Turbine Digital Controls
Replacement/Retrofit
W07
Miscellaneous
WCRE-35
Boundary Matrix
AI 16C-006
Troubleshooting
13A
AP 10-103
Fire Protection Impairment Control
AP 10-104
Breach Authorization
STS AL-211
TD AFP Comprehensive Pump Testing, Flow Path
Verification and CV Testing
Procedures
STS PE-004
Aux Building and Control Room Pressure Test
Work Orders
Corrective Action
Documents
Condition Report
(CR)
10045385
Corrective Action
Documents
Condition Report
(CR)
10043534, 10044228, 10044289, 10044405, 10044534,
10044544, 10045241
Drawings
KD-7496
One Line Diagram
DCP 020384
Main Generator Step-Up Power Transformer (GSU)-
XMA01A, B, C Replacement
Engineering
Changes
DCP 13071
AVR Replacement Project
AI 26A-003
Regulatory Evaluations (Other Than 10 CFR 50.59)
CFR 50.59 Reviews
Procedures
OFN KC-016
Fire Response
Corrective Action
Documents
Condition Report
(CR)
10003133, 10002793, 135907, 10044649, 10045142,
10045143, 10044894, 10044935, 10045173, 10045176,
10045160, 10045627, 10044797, 10045738, 10045072,
10045253, 10045701, 10045393, 10045742, 10045600,
10045484, 10045261, 10045016, 10045124
Corrective Action
Documents
Resulting from
Condition Report
(CR)
10044645, 10044646, 10044647, 10044648, 10044864,
10044849, 10044954, 10044955, 10044959, 10046432,
10046463, 10046498, 10047953, 10047955
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Inspection
K-12KJ04
Piping and Instrumentation Diagram Standby Diesel
Generator B Cooling Water System
M-12EF01
Piping Instrumentation Diagram Essential Service Water
M-12FC03
Piping and Instrumentation Diagram Auxiliary Turbines
SGFP Turbine A
Drawings
M-12KA02
Piping and Instrumentation Diagram Compressed Air System
(Service AR)
C27-R-KJ-B-
001A
EDG B Clearance Order
Miscellaneous
WCRE-34
Fourth 10-Year Interval Inservice Testing Basis Document
AP 12-004
Containment Entry and Material Control
Control of Locked Component Status
78E
On-Line Nuclear Safety and Generation Risk Assessment
FHP 02-001
Refueling Operations
47A
FHP 02-007B
Reactor Vessel Closure Head Installation
20A
FHP 05-001
Equipment Hatch Operations
GEN 00-002
Cold Shutdown to Hot Standby
110B
GEN 00-003
Hot Standby to Minimum Load
111, 112
GEN 00-005
Minimum Load to Hot Standby
GEN 00-008
RCS Level Less Than Reactor Vessel Flange Operations
OFN EJ-015
Loss of RHR Cooling
OFN NB-030
Loss of All AC Power - Shutdown Conditions
35A
STN EJ-002
Containment Inspection
STS BB-011
Reactor Coolant System and Pressurizer Heatup/Cooldown
Surveillance
STS EJ-002
Containment Sump Inspection
17A
SYS EJ-111
Initial RCS Fill
Procedures
SYS SL-139
Energizing #10 or #11 Transformer
Work Orders
WO 26058, 26813, 70712, 147953, 148576, 149045
Calculations
BN-M-013
RWST Volume Requirements for Injection, ECCS, and
Containment Spray Pumps Transfer and Time Available for
Operator Actions
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Condition Report
(CR)
33323, 38960, 39037, 39056, 39193, 39285, 39331, 46927,
10041112, 10045750, 10044967, 10044972, 10045149,
10045150, 10045074, 10045087, 10045058, 10045252,
10045287, 10045298, 10045341, 10045926, 10046056,
10046452, 10046454, 10044764, 10045125, 10045053,
10045196, 10045002, 10045192, 10045862, 10045925,
10045979, 10046231, 10046767, 10045688, 10045706,
10045707, 10045727, 10044240, 10044497, 10044775,
10044857, 10045496, 10045426, 10046474, 10044982,
10045068, 10045492, 10045613, 10045686, 10045764,
10046572, 10046575, 10045621, 10046631, 10046633,
10046686, 10046733, 10043694, 10046237, 10046246,
10046000, 10044860, 10044862, 10044863, 10043310,
10045059, 10045060, 10045481, 10045665, 10045795,
10046003, 10047248, 10046779
Corrective Action
Documents
Resulting from
Inspection
Condition Report
(CR)
10046236
E-025-00007,
Sheet 236
RHR A to SIS Hot Leg Recirc Loops 2 and 3 ISO
W14
E-025-00007,
Sheet 237
RHR B to SIS Hot Leg Recirc Loops 2 and 3 ISO
W16
E-13BG48
Schematic Diagram Excess Letdown Line Isolation Valves
M-12BG01
Piping and Instrumentation Diagram Chemical and Volume
Control System
M-12BG01
Piping and Instrumentation Diagram Chemical and Volume
Control System
M-12BN01
Piping and Instrumentation Diagram Borated Refueling
Water Storage System
M-12EG01
Piping and Instrumentation Diagram Component Cooling
Water System
Drawings
M-12EG02
Piping and Instrumentation Diagram Component Cooling
Water System
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
M-12EG03
Piping and Instrumentation Diagram Component Cooling
Water System
M-12EJ01
Piping and Instrumentation Diagram Residual Heat Removal
System
M-12EM01
Piping and Instrumentation Diagram High Pressure Coolant
Injection System
M-12GP01
Piping and Instrumentation Diagram Containment Integrated
Leak Rate Test
M-1HX001, Sheet
Heat Exchanger Tube Sheet Map Component Cooling Water
Heat Exchanger B (South End)
STS BN-206
Borated Refueling Water Storage System Inservice Testing
Valve Test
Engineering
Changes
DCP 013071
Main Generator Automatic Voltage Regulator Replacement
C27-R-KJ-B-
001A
EDG B Clearance Order
WCLR-22
CFR 50, Appendix J B2.1.30 NUREG-1801 Program
XI.S4 Aging Management Program
Miscellaneous
WCRE-34
Fourth 10-Year Interval Inservice Testing Basis Document
Post Maintenance Testing Development Guide
2A
Control of Locked Component Status
78E
Motor Operated Valve Program
4A
ASME Code Testing of Pumps and Valves
2A
Program Plan for Containment Leakage Measurement
17A
CKL EG-120
Component Cooling Water System Valve, Switch and
Breaker Lineup
EMG ES-12
Transfer to Cold Leg Recirculation
25A
EMG ES-13
Transfer to Hot Leg Recirculation
14A
MEC-009
Disassembly/Assembly of Westinghouse Style A Check
Valves
STN EF-022B
ESW Train B Post-Loca Flow Balance
2A
STN EJ-202
System Valve Test
Procedures
STN IC-902
Cross Trip Check: Main Transformers, Main
Generator/Switchyard
13A
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
STS CV-211
RHR Full Flow Test and Accumulator Safety Injection Check
Valve Test
STS EJ-100A
RHR System Inservice Pump A Test
STS KJ-001B
Integrated D/G and Safeguards Actuation Test - Train B
STS MT-027
Snubber Functional Test
STS PE-007
Periodic Verification of Motor Operated Valves
5A
STS PE-018
Containment Integrated Leakage Rate Test
STS PE-122
LLRT Valve Lineup for Penetration 22
STS VT-001
Verification of ASME OM Code Mandatory Appendix III,
MOV Exercise Requirements
SYS GP-510B
CILRT - BB System (RCPS & SEAL INJ)
SYS GP-516
CILRT - EG System
SYS GP-517
CILRT - EJ System
SYS KJ-124
Post Maintenance Run of Emergency Diesel Generator B
Work Orders
WO 23830, 32141, 71730, 71732, 71737, 80932, 104728,
2409, 112410, 118065, 120018, 21-473687-003, 23-
485897-001, 92819, 23-485897-001, 23-485897-000, 20-
2318-000, 146043, 23912, 23916, 23918, 104697,
104696, 104694, 71689, 146043, 120311, 152336, 149775,
104157, 151489, 75563, 114936, 75563, 58731, 70762,
104553, 17194, 17201, 17212, 81637, 81641, 106888,
114106, 140169, 58995, 59001, 59009, 67436, 67672,
67708, 59001, 59009, 67436, 67672,96036, 104553, 17205,
70762, 39977, 10045739, 10045740, 114936, 75563, 58731,
70762, 104553, 17194, 17201, 17212, 81637, 81641,
106888, 114106, 140169, 58995, 59001, 59009, 67436,
67672, 67708, 59001, 59009, 67436, 67672,96036, 104553,
205, 70762, 39977, 70712, 107997, 144373, 81350,
96766, 137093, 7164, 81328, 81332, 82966, 135735,
104803, 21-473172, 9719, 81328, 81332, 71658, 71666,
71662, 19-450030-005, 153024, 153066, 152956, 152957,
2961, 152908, 152845, 152846, 152931, 10326827-000,
08-306055-002, 80979, 23-485785-000, 21-473687-000, 23-
485786-000, 23-485787-000, 23-485785-005, 72894
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Condition Report
(CR)
88519, 103802, 126718, 23157, 40756, 146699, 10002001,
10003500, 10012402, 10023022, 10025491,10027136,
10033678, 10034501, 10034549, 10041825, 10041992,
10043396, 10044344, 10045192
M-12BB01
Piping and Instrumentation Diagram Reactor Coolant
System
Drawings
M-12BB02
Piping and Instrumentation Diagram Reactor Coolant
System
Miscellaneous
M-724-00448
Instruction Manual for Pressurizer Spray Valve
W10
ALR 00-033C
Press LO HTRS On
BD-OFN MA-038
Rapid Plant Shutdown
GEN 00-004
Power Operation
2
OFN MA-001
Load Rejection or Turbine Trip
OFN MA-038
Rapid Plant Shutdown
2A
SU7-BB05
Pressurizer Continuous Spray Flow Setting
Procedures
SYS BB-220
Pressurizer Continuous Spray Flow Setting
Work Orders
WO 76485, 11-343606-001, 12-350340-000, 13-375254-006
Calculations
XX-M-080
Wolf Creek Generating Station Pump Room Heat-up
Analysis
Corrective Action
Documents
Condition Report
(CR)
10023022, 10041992, 10027136, 10025491, 10012402,
26718, 88519, 103802, 146699, 10002001, 10003500,
10041825, 10037556, 10036376, 10036649, 10040645,
10036368
M-13EF02
Piping Isometric Essential Service Water Sys Aux BLDG A
Train Supply
Drawings
M-1HX001
Heat Exchanger Tube Sheet Maps
Engineering
Changes
CP 014266
ESW Aboveground Pipe Replacement
Operability Determinations and Functionality Assessments
Procedures
STN FP-452
Fire Barrier Penetration Seals Inspection
Work Orders
WO 68145, 85293, 85303, 87055, 87228, 91842, 100855,
20072, 14-383646-000, 14-387207-002, 15-404306-000,
16-412985-000, 18-436050-000, 19-456291-001, 21-
474963-003
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
XX-E-006
AC System Analysis
Corrective Action
Documents
Condition Report
(CR)
10045627, 138017,138036, 138042, 10045630, 10045632,
100456652, 10045661, 10045689, 10045691, 10045713,
10037832, 10031456, 10037823, 10046428, 10045821,
10045853, 10045730, 10045586, 10045588, 10045592,
10045829, 10043577, 10043578, 10046405, 10046409
Corrective Action
Documents
Resulting from
Inspection
Condition Report
(CR)
10045950, 10043580, 10047946
KD-7496
One Line Diagram
Drawings
M-622.1A-00007
SGK04A and SGK04B Air Conditioning Electric Schematic
Engineering
Changes
DECP 020350
SGK05A/B Fuse Replacement
WCNOC-76
Medium Low Voltage AC and Low Voltage DC Overcurrent
Protection Coordination for Wolf Creek Generating Station
WCRE-08
WCGS Fuse List
Miscellaneous
WCRE-35
Boundary Matrix
ALR 00-018D
NB01 UV Relay 1/4
7A
AP 10-104
AP 10-104
Breach Authorization
STS IC-208A
4kV Loss of Voltage and Degraded Voltage TADOT NB01
Bus - Sep GRP 1
9A
STS PE-004
Aux Building and Control Room Pressure Test
SYS GK-201
Mitigating Actions for Inoperable SGK05 Train
5A
SYS SL-138
Energizing 13.8 kV Buses SL-7 and SL-8
Procedures
TMP 25-003
Energizing Main Transformers from Backfeed for Post
Installation Soak
0A
Work Orders
WO 14042, 95363, 102802, 149045, 18-437840-000,
18-437840-001, 423-488488-000