IR 05000482/2021003
| ML21302A194 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom, Wolf Creek  |
| Issue date: | 11/05/2021 |
| From: | Greg Werner NRC/RGN-IV/DRP |
| To: | Reasoner C Wolf Creek |
| References | |
| IR 2021001 | |
| Download: ML21302A194 (25) | |
Text
SUBJECT:
WOLF CREEK GENERATING STATION - INTEGRATED INSPECTION REPORT 05000482/2021003 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION INSPECTION REPORT 07200079/2021001
Dear Mr. Reasoner:
On September 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Wolf Creek Generating Station. On October 7, 2021, the NRC inspectors discussed the results of this inspection with Mr. Jaime McCoy, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
NRC inspectors documented one finding of very low safety significance (Green) in the report that did not involve a violation of NRC requirements.
If you disagree with a cross-cutting aspect assignment or a finding not associated with a regulatory requirement in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; and the NRC Resident Inspector at Wolf Creek Generating Station.
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 November 5, 2021 Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Gregory E. Werner, Chief Reactor Projects Branch B Division of Reactor Projects Docket Nos. 05000482 and 07200079 License No. NPF-42
Enclosure:
As stated
Inspection Report
Docket Number:
05000482 and 07200079
License Number:
Report Number:
05000482/2021003 and 07200079/2021001
Enterprise Identifier:
I-2021-003-0031 and I-2021-001-0007
Licensee:
Wolf Creek Nuclear Operating Corporation
Facility:
Wolf Creek Generating Station and Independent Spent Fuel Storage
Installation
Location:
Burlington, KS
Inspection Dates:
July 1, 2021 to September 30, 2021
Inspectors:
L. Brookhart, Senior Spent Fuel Storage Inspector
M. Davis, Trans And Storage Safety Inspector
M. Doyle, Operations Engineer
C. Henderson, Senior Resident Inspector
J. Melfi, Project Engineer
P. Patel, Structural Engineer
G. Pick, Senior Reactor Inspector
R. Rodriguez, Structural Engineer
E. Simpson, Health Physicist
C. Smith, Health Physicist
J. Vera, Resident Inspector
Approved By:
Gregory E. Werner, Chief
Reactor Projects Branch B
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection and an independent spent fuel storage installation 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
Failure to Implement Critical Design Parameters for the Main Feedwater System During Digital Control System Modifications Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green FIN 05000482/2021003-01 Open/Closed
[H.12] - Avoid Complacency 71153 The inspectors reviewed a self-revealed, Green finding associated with the licensees failure to ensure balance of plant control system vendor used critical design parameters for the nonsafety-related main feedwater system bypass regulating valves in accordance with Procedure AI 05-005, Modifications to Non-Controlled [structures, systems, and components], Revision 5. Procedure AI 05-005 implemented the licensee self--imposed standard to control the main feedwater system as controlled plant equipment which required configuration-control to conform with Title 10 Code of Federal Regulations Part 50,
Appendix B rules and regulations. As a result, operators observed oscillating and divergent water levels in all four steam generators that caused an automatic reactor trip.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000482/2021-003-00 Automatic Reactor Trip Due to Low Steam Generator Level 71153 Closed
PLANT STATUS
Wolf Creek Generating Station began the inspection period at full power. On August 18, 2021, an automatic reactor trip from 100 percent reactor occurred due to a loss of main feedwater flow to the B steam generator caused by a stem separation of the B main feedwater regulating valve.
The licensee commenced Forced Outage 25-02 to repair the B main feedwater regulating valve and performed extent of condition reviews of the remaining three main feedwater regulating valves. On August 21, 2021, the unit commenced reactor startup, and the reactor was made critical. The unit was returned to full power on August 22,
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week, increasing the amount of time onsite as local COVID-19 conditions permitted.
As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; conducted routine reviews using IP 71152, Problem Identification and Resolution, observed risk significant activities; and completed onsite portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and onsite. The inspections documented below met the objectives and requirements for completion of the IP.
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) Train B essential service water to emergency diesel generator jacket water and lube oil heat exchangers on July 9, 2021
- (2) Train A electrical penetration cooling unit SGL15A on July 21, 2021
- (3) Train A safety injection on September 23, 2021
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the component cooling water system on September 28, 2021.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 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) Electrical penetration room A, fire area A-18, on July 21, 2021
- (2) Electrical penetration room B, fire area A-17, on July 21, 2021
- (3) Essential service water pump house pump room B, fire area essential service water B, on August 4, 2021
- (4) Safety injection pump room B, fire area A-4, on September 8, 2021
- (5) Safety injection pump room A, fire Area A-2, on September 23, 2021
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill on July 20, 2021.
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Train B engineering safety feature 4160volt switchgear (NB02) room on August 5, 2021
Cable Degradation (IP Section 03.02) (1 Sample)
The inspectors evaluated cable submergence protection in:
- (1) Train B essential service water electrical cable manhole MHE5B inspection on August 31, 2021
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (2 Samples)
The inspectors evaluated readiness and performance of:
- (1) Train B emergency diesel generator jacket water heat exchanger on July 16, 2021
- (2) Train A component cooling water heat exchanger on September 10, 2021
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered on September 14, 2021.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during control rod movement and parking on August 12, 2021.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated the annual licensed operator requalification exam on September 8, 2021.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Containment fan cooler supply breaker starter relay failures on August 5, 2021
- (2) Adverse trend in valve program issues on September 7, 2021
- (3) Safety injection system maintenance effectiveness review on September 23, 2021
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 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) Train A essential service water manhole MHE3A and safety injection planned maintenance window on July 14, 2021
- (2) Turbine driven auxiliary feedwater pump planned maintenance window on August 24, 2021
- (3) Emergent work activities for a partial loss of power to train B balance of plant engineered safety feature actuation system cabinet SA036E during control room radiation monitor testing on September 3, 2021
- (4) Emergency diesel generator A, 7-day planned maintenance window on September 14, 2021
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) Train B turbine drive auxiliary feedwater essential feedwater suction check valve operability determination on July 7, 2021
- (2) Trains A and B containment coolers with support system inoperable during maintenance operability determination on August 4, 2021
- (3) Train B battery charger momentary voltage drop when starting emergency diesel generator B supply fan operability determination on September 10, 2021
- (4) Emergency exhaust system damper failure to reclutch following maintenance past operability determination on September 16, 2021
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Ovation balance of plant digital control upgrade - main feedwater pump trip and turbine runback on September 10, 2021
- (2) Manual operator actions with the emergency diesel generator paralleled with offsite power on September 16, 2021
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Train A safety injection pump and breaker maintenance post-maintenance testing on July 16, 2021
- (2) Train A safety injection discharge header motor operated valve EMHV8812A post-maintenance testing on July 16, 2021
- (3) Train B Emergency exhaust system non-radioactive tunnel supply downstream isolation damper, GLD0037, failure to reclutch following maintenance post-maintenance testing on July 23, 2021.
- (4) Train A charging pump discharge header to boron injection tank isolation motor operated valve, EMHV8803A, packing adjustment post-maintenance testing on July 28, 2021.
- (5) Main feedwater regulating valve B stem replacement post-maintenance testing on August 20, 2020
- (6) Train A auxiliary feedwater pump and valve maintenance post-maintenance testing on September 22, 2021
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Train B component cooling water pumps B and D comprehensive inservice surveillance testing on July 8, 2021
- (2) Trains A and B electrical penetration room cooler surveillance testing requirements on August 5, 2021
- (3) Train A safety injection solid station protection system logic test on August 12, 2021
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) FLEX 500 kW diesel generator and reactor coolant system make up pump testing on September 7, 2021
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) Emergency preparedness drill involving a complete loss of core exit thermocouple indication, loss of control room indications, and loss-of-coolant accident on August 18,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
- (1) July 1, 2020 through June 30, 2021
MS06: Emergency AC Power Systems (IP Section 02.05) (1 Sample)
- (1) July 1, 2020 through June 30, 2021
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) FLEX diesel generator testing operating experience on August 24, 2021
- (2) Effectiveness of corrective actions related to the full implementation cyber security program inspection findings as described in NRC Cyber Security Inspection Report 05000482/2019410 (ML19268A037)
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Followup (IP Section 03.01)
- (1) The inspectors evaluated the reactor trip from 100 percent reactor power due to a loss of feedwater to steam generator B and licensees response on August 18, 2021.
Event Report (IP Section 03.02) (1 Sample)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000482/2021-003-00, "Automatic Reactor Trip Due to Low Steam Generator Level" (ADAMS Accession No. ML21193A078). The inspection conclusions associated with this LER are documented in this report under Inspection Results Section
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
===60856 - Review of 10 CFR 72.212(b) Evaluations The inspection was conducted to determine if Wolf Creek Generating Station met the general license requirements of 10 CFR Part 72 before conducting operations to load their Independent Spent Fuel Storage Installation (ISFSI).
Review of 10 CFR 72.212(b) Evaluations===
- (1) On August 16-19, 2021, the NRC conducted a team inspection of Wolf Creek Generating Station's 10 CFR Part 72 program implementation and 10 CFR 72.212 report prior to the licensee's first loading campaign, which is scheduled for the fall of 2021. Wolf Creek Generating Station has elected to become a 10 CFR Part 72 general licensee in accordance with 10 CFR 72.210. The licensee has selected the Transnuclear Americas LLC Nutech Horizontal Modular Storage Extended Optimized Storage (EOS) system. The licensee constructed the ISFSI storage pad in the spring of 2020 and built the EOS NUMHOMS in the fall of 2020, in accordance with the Transnuclear NUHOMS EOS Certificate of Compliance 72-1042, Amendment 1 and Final Safety Analysis Report, Revision 3.
The following programs, procedures, and calculations were inspected:
Site specific analysis that confirmed the licensee met the license conditions for flooding, lightning, blockage of inlet openings, off-normal temperature requirements, and snow and ice
Evaluation to confirm annual dose equivalent would meet 10 CFR 72.104 and 72.106 requirements
Evaluation under 10 CFR 50.59 of ISFSI's impact on the reactor facility and compliance to site's heavy load program Evaluation of the fuel building's crane to meet the criteria of NUREG 0554 Single-Failure-Proof Cranes for Nuclear Power Plants,"
Review of calculations for structural and seismic stability for the transfer cask on the fuel building crane and placement locations within the fuel building
Work orders and procedures that the fuel building's crane meets ASME B30.2 for load testing and annual maintenance requirements
Reviewed site's new Emergency Plan for inclusion of ISFSI specific emergencies
Evaluation of ISFSI impact on the reactor Quality Assurance Plan
Evaluation of the ISFSI's impact on the reactor facility's radiation protection plan
Training program for qualification of Part 72 operations within the fuel building
Training program and procedures for performing 10 CFR 72.48 evaluations
Training program qualification for the updated Emergency Plan with ISFSI specific requirements
Load testing and non-destructive testing records of special lifting devices used during loading operations
Fuel selection procedures to ensure fuel contents meet license conditions
Record retention program implementation for ISFSI records Remaining items that have yet to be fully reviewed include:
Site specific analysis confirming license conditions for tornados, earthquake, fire and explosions, normal environmental temperatures, and soil liquefaction
Matrix loading crane and roller trays structural and seismic analysis
Training documentation for qualification of Part 72 operations outside at the ISFSI pad
Review of site specific 10 CFR 72.48 changes, tests, and experiments
Finalized 10 CFR 72.212 report
INSPECTION RESULTS
Failure to Implement Critical Design Parameters for the Main Feedwater System During Digital Control System Modifications Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green FIN 05000482/2021003-01 Open/Closed
[H.12] - Avoid Complacency 71153 The inspectors reviewed a self-revealed, Green finding associated with the licensees failure to ensure balance of plant control system vendor used critical design parameters for the nonsafety-related main feedwater system bypass regulating valves in accordance with Procedure AI 05-005, Modifications to Non-Controlled SSCs, Revision 5.
Procedure AI 05-005 implemented the licensee self--imposed standard to control the main feedwater system as controlled plant equipment which required configuration-control toconform with Title 10 Code of Federal Regulations Part 50, Appendix B rules and regulations. As a result, operators observed oscillating and divergent water levels in all four steam generators that caused an automatic reactor trip.
Description:
During Refueling Outage (RF) 24, the licensee upgraded multiple nonsafety-related nuclear supply system control systems to the Ovation based distribution control system. These changes included new digital controls for the main feedwater system regulating valves and the associated bypass valves. The main feedwater system was a nonsafety-related SSC that was controlled in accordance with Procedure AI 05-005.
Procedure AI 05-005, Attachment A, classified the main feedwater system as controlled plant equipment. This designation implemented the self-imposed standard that configuration control for the main feedwater system conforms with 10 CFR Part 50, Appendix B rules and regulations. Therefore, the inspectors concluded the licensees self-imposed standard was to ensure modifications of the nonsafety-related main feedwater system to the Ovation based distribution control system was controlled in accordance with 10 CFR Part 50, Appendix B, Criterion III, which states, in part, that measures shall also be established for the selection and review suitability of application of material, parts, equipment, and processes that are essential to the safety-related functions of the structures, systems, and components.
On May 12, 2021, the licensee was performing a reactor startup following the completion of RF 24 when steam generator water levels began oscillating and diverging at approximately 8 percent reactor power while in automatic control. Operators took manual control of the main feedwater regulating bypass valves but were unable to restore levels prior to a steam generator low level automatic reactor trip. The cause of the automatic reactor trip was the low-power controller gains for the main feedwater bypass regulating valves were set too high. This led to a higher feedwater flow to the steam generators than needed for the feedwater system demand. This condition resulted in steam generator water level control instability causing oscillating and diverging water levels. The licensee entered this issue into their corrective action program as Condition Report 10005736, classified this a significant condition adverse to quality and performed a root cause evaluation. The root cause evaluation identified one root cause and one contributing cause associated with the automatic reactor trip that occurred on May 12, 2021. The root cause and contributing cause are as follows:
Root
Cause:
The licensees specific main feedwater bypass regulating valve characteristics and the impact of the feedwater control system designed were not fully recognized. This resulted in the incorrect control system tuning parameters and inadequate risk mitigation strategies for the initial power ascension following the implementation of the Ovation main feedwater digital control system. Specifically, the licensees vendor did not incorporate the stations main feedwater bypass regulating valve critical design parameters of a 4-inch bypass valve with a maximum flow coefficient of 150 for determining the initial tuning parameters for the valves during the Ovation upgrade. Instead, the vendor used a 6-inch bypass valve with a flow coefficient near double the value of the stations bypass valve flow coefficient. This resulted in the low-power controller gain values for the main feedwater bypass regulating valves being set too high. These parameters resulted in the steam generator water level control instability causing oscillating and diverging water levels, resulting in the May 12, 2021, automatic reactor trip.
Contributing cause: Throughout the Ovation modification design and implementation process, there was inadequate risk recognition and advocacy which resulted in missed opportunities for leaders to engage cross-functionally and make key decisions. For example, the licensees initial just-in-time training for the Ovation system modification was based on an analysis of training needs and focused on performing the reactor startup activities with the Ovation system. However, the licensee concluded the possible failures of all main feedwater bypass regulating valves, with oscillating and diverging steam generator water levels at low power, was not determined to be a likely failure even though it occurred on the plant training simulator. This similar event occurring on the plant training simulator provided the licensee with an opportunity to validate the vendor used the correct main feedwater system critical design parameters and their conclusion the plant training simulator was not comparable to the anticipated plant response when implementing the new main feedwater digital control system.
The inspectors reviewed the above information and concluded the licensee failed to implement the self-imposed standard to control the main feedwater system as a controlled plant equipment in accordance with Procedure AI 05-005. Specifically, the licensee failed to ensure the balance of plant control system vendor used critical design parameters for the main feedwater system bypass regulating valves.
Corrective Actions: The licensee implemented the following immediate corrective actions: 1. The initial controller gain values were updated for the main feedwater bypass regulating valves using the stations critical design parameters prior to commencing reactor startup on May 14, 2021; 2. The licensee performed additional just-in-time training to ensure licensed operators were familiar with manual digital control system for the main feedwater bypass regulating valves prior to the May 14, 2021 reactor startup. The corrective action to prevent recurrence was to update design drawings with a caution that a change to the valve critical design parameters could impact the Ovation feedwater control logic.
Corrective Action References: Condition Report 10005736
Performance Assessment:
Performance Deficiency: The licensees failure to ensure balance of plant control system vendor used critical design parameters for the main feedwater system bypass regulating valves was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Design Control 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 licensees failure to use the main feedwater system bypass regulation valve critical design parameters during balance of plant control system modification resulted in oscillating and divergent water levels in all four steam generators resulting in an automatic reactor trip.
Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Using Exhibit 1, Section B.
The inspectors determined the finding was of very low safety significance (Green) because the finding did cause a reactor trip, but not the loss of mitigation equipment relied upon to transition the plant from the onset of the trip to a stable shutdown condition (e.g., loss of condenser, loss of feedwater).
Cross-Cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Individuals implement appropriate error reduction tools. Specifically, the licensee failed to validate the vendor design control parameters for the main feedwater system bypass regulating valves and reevaluate the risk associated with oscillating and diverging water levels in all four steam generators, even when plant training simulator indicated the potential of this event to occur.
Enforcement:
Inspectors did not identify a violation of regulatory requirements associated with this finding.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On July 28, 2021, the inspectors presented the cyber security problem identification and resolution inspection results to Mr. L. Lane, Director Strategic Engineering and other members of the licensee staff.
On September 14, 2021, the inspectors presented the Wolf Creek 2021 annual requalification inspection results to Mr. A. Servaes, Regulatory Exam Writer and other members of the licensee staff.
On October 7, 2021, the inspectors presented the integrated inspection results to Mr. J. McCoy, Site Vice President and other members of the licensee staff.
On October 7, 2021, the inspectors presented the Independent Spent Fuel Installation 72.212 Inspection results to Mr. C. Reasoner, Chief Executive Officer and Chief Nuclear Officer, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
60856
Engineering
Evaluations
50.59 Document
Number 15044
Cask Handling Crane NUREG 0554/0612 Compliance
Safety Analysis Report
60856
Engineering
Evaluations
BED WO 21-
468230-001
Characterization of Fuel Assemblies and Control
Components Discharged through RF22
07/27/2021
60856
Engineering
Evaluations
Calc 30501-0506
NUHOMS HSM-MX Dose Rates and ISFSI Site Dose
Analysis
60856
Engineering
Evaluations
HG-C-003
Stability of Loaded Transfer Cask in all Planned
Configurations in the Fuel Building
60856
Engineering
Evaluations
HG-C-006
Heavy Loads Summary for Pool-to-Pad Operational
Evolutions
60856
Engineering
Evaluations
KE-C-019
Crane Structural Analysis and Trolley Evaluation
60856
Procedures
AI 19C-001
Dry Cask Storage Loading Plan
60856
Procedures
AP 06-002
Radiological Emergency Response Plan
60856
Procedures
APF 06-002-02
Emergency Action Levels Technical Bases
Calculations
GL-M-002
Calculate Tube Plugging Allowance for Aerofin (Cu-Ni) Coils
for Electrical Penetration Room Coolers (SGL15A and
SGL15B)
Calculations
KJ-M-015
EKJ06A/B Thermal Performance Calculation
Calculations
KJ-M-017
Emergency Diesel Standby Generator (KKJ01 BB) Runtime
without ESW Flow
Calculations
XX-M-005
Evaluation of the UHS Maximum Temperature to Exceed
95F Design Basis Temperature Short Periods during the 30
Day Following a DBA
Calculations
XX-M-068
Tube Plugging Criteria for Safety-Related Room Cooler
(Aerofin AL6XN) Cooling Coils
Corrective Action
Documents
Condition Reports
10006569, 10007097, 10007129, 10007128
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10007353
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
E-13KJ03B
Schematic Diagram Diesel Generator KKJ01B Engine
Control (D/G Trips)
Drawings
M-12EF01
Piping Instrumentation Diagram Essential SVC Water
System
Drawings
M-12EF02
Piping and Instrumentation Essential SVC Water System
Drawings
M-12EG01
Piping & Instrumentation Diagram Component Cooling
Water System
Drawings
M-12EG02
Piping & Instrumentation Diagram Component Cooling
Water System
Drawings
M-12EG03
Piping & Instrumentation Diagram Component Cooling
Water System
Drawings
M-12GL01
Piping and Instrumentation Diagram Auxiliary Building HVAC
Drawings
M-12KJ04
Piping and Instrumentation Diagram Standby Diesel
Generator B Cooling Water System
Drawings
M-12KJ06
Piping and Instrumentation Diagram Standby Diesel
Generator B Lube Oil System
Engineering
Changes
CCP 012774
EKJ06A/B Replacement Jacket Water Heat Exchangers
Miscellaneous
E-1F9915
Design Basis Document for OFN PR-017, Control Room
Evacuation
Procedures
Control of Locked Components Status
78A
Procedures
CKL EF-120
Essential Service Water Valve, Breaker and Switch Lineup
56B
Procedures
CKL EG-120
Component Cooling Water System Valve Switch and
Breaker Lineup
Procedures
OFN RP-017
Control Room Evacuation
Procedures
STN EF-022B
ESW Train B Post-LOCA Flow Balance
2A
Procedures
STN PE-037B
ESW Train B Heat Exchanger Low and DP Trending
Work Orders
17-432437-006
Corrective Action
Documents
Condition Report
10007600
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10009053
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
M-12LF02
Piping and Instrumentation Diagram Auxiliary Building Floor
and Equipment Drain System
Drawings
M-12LF04
Piping and Instrumentation Diagram Auxiliary Building Floor
and Equipment Drain System
Miscellaneous
E-1F9905
Fire Hazard Analysis
Miscellaneous
E-1F9910
Post Fire Safe Shutdown Area Analysis
Procedures
AP 10-106
Fire Preplans
Calculations
FL-08
Control Building Flooding
Corrective Action
Documents
Condition Reports
10004542, 10005554
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10008129
Drawings
E-11NG20
Sheet 11
MCC-NG02A
238
Drawings
M-12EF01
Piping Instrumentation Diagram Essential SVC Water
System
Drawings
M-12KC02
Piping and Instrumentation Diagram Fire Protection System
Drawings
M-12LE02
Piping and Instrumentation Diagram Control and Diesel Gen.
Bldg. Oily Waste System
Drawings
M-1G051
Equipment Locations Control and Diesel Gens BLDFS and
Comm. Corridor Plan EL. 2000-00 and EL. 2016-00
Miscellaneous
BAP-21-0353
Barrier Authorization Permit
Miscellaneous
WCRE-035
Boundary Matrix
Procedures
AI 21-016
Operator Time Critical Actions Validation
Procedures
ALR 00-008B
Serv WTR Press HI LO
Procedures
ALR 00-049E
CTRL BLD OW Sump Level Hi
Procedures
ALR 00-055A
11A
Procedures
AP 21-004
Operator Response Time Program
4C
Procedures
OFN SG-003
Natural Events
Work Orders
17-427039-000
Calculations
KJ-M-011
EKJ03A/B Thermal Performance Calculation
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
KJ-M-015
EKJ06A/B Thermal Performance Calculation
Corrective Action
Documents
Condition Reports
107702, 107706, 137997, 138950, 145929, 145940,
10002803, 10003532, 10003541, 10003543, 10003585,
10003642, 10003654, 10003697, 10003826, 10004111,
10004152, 10004284, 10004325, 10004276, 10004495
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10004457
Drawings
M-1HX001
Heat Exchanger Tube Sheet Maps
Miscellaneous
M-018E
Design Specification for Replacement Jacket Water Heat
Exchangers ASME Code Section III Class 3
Procedures
Heat Exchanger Program
Procedures
STN PE-037B
ESW Train B Heat Exchanger Flow and DP Trending
Work Orders
16-418115-000, 17-433842-000, 18-447320-000,
19-440206-000, 19-451425-000, 19-456598-000,
20-457635-000, 20-458813-000, 20-458813-002,
20-461902-000, 20-464226-000
Miscellaneous
Wolf Creek ARQ
exam results
Wolf Creek ARQ exam results
09/14/2021
Procedures
STN SF-001
Control Rod Parking
21A
Work Orders
21-468846-000
Calculations
SA-88-015
Determination of the SI Flowrate under HL Injection Mode
Corrective Action
Documents
Condition Reports
109647, 110725, 123103, 125945, 127042, 134338, 134339,
141615, 10001654, 10005727, 10006141, 10006569,
10007097, 10007128, 10007387, 10007433, 10007439,
10008024, 10008863
Corrective Action
Documents
Resulting from
Inspection
Condition Reports
10007665, 10008147, 10009043
Drawings
M-12BB01
Piping and Instrumentation Diagram Reactor Coolant
System
Drawings
M-12EM01
Piping and Instrumentation Diagram High Pressure Coolant
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Injection System
Drawings
M-12EP01
Piping and Instrumentation Diagram Accumulator Safety
Injection
Engineering
Changes
DCP 020393
EDG Supply Fan Motor Starters Replacement
Miscellaneous
E-018-00189
Qualification and Test Summary Report
11W
Miscellaneous
EDSD-I
Equipment Qualification Design Basis Document
Miscellaneous
M-000
Mechanical/Nuclear Design Criteria for Wolf Creek
Generating Station
Miscellaneous
WCOP-02
Inservice Testing Program for Pumps, Valves, and Snubbers
Procedures
AI 29B-002
Check Valve Condition Monitoring Program
8A
Procedures
ELE-007
NG001T - NG004T Motor Control Center Inspection,
Cleaning and Testing
Procedures
EM-M-036
Establishment of the Safety Injection Pump Comprehensive
Test Error Allowance and Minimum Operability Limit Curve
Procedures
STS CV-103
Inservice Testing Check Valve Condition Monitoring for
BB8949A/B/C/D
Procedures
STS CV-210A
ECCS SI Comprehensive Pump and Inservice Check Valve
Test
Procedures
STS EJ-209A
Train A RHR System Inservice Valve Test
Procedures
STS EJ-209B
Train B RHR System Inservice Valve Test
Procedures
STS PE-019E
RCS Isolation Check Valve Leak Test
Procedures
SYS GN-120
Containment Cooling System Operation
Work Orders
13-374331-000, 18-440567-009, 20-462172-000
Calculations
NAI-1878-001
Wolf Creek HELB Analysis
Corrective Action
Documents
Condition Reports
84848, 10008360, 10008523, 10008827, 10008829,
10009004, 10009065, 10009124
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10008652
Drawings
Logic Block Diagram ESFAS
W08
Drawings
KD-7496 Sheet 1
One Line Diagram
Drawings
M-12AL01
Piping and Instrumentation Diagram Auxiliary Feedwater
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
System
Miscellaneous
BAP-21-0349
Breach Authorization Permit TDAFW TESO Work
Miscellaneous
EQSD-I
Equipment Qualification Design Basis Document
Miscellaneous
WCRE-35
Boundary Matrix
Procedures
AI 22C-013
Protected Equipment Program
23A
Procedures
AP 10-104
Breach Authorization
Procedures
On-Line Nuclear Safety and Generation Risk Assessment
Procedures
Risk Management and Contingency Planning
Procedures
Qualitative Risk Management
Procedures
EMG C-0
Loss of All AC Power
Procedures
EMG E-0
Reactor Trip or Safety Injection
Procedures
EMG ES-02
Reactor Trip Response
Procedures
EMG FR-H1
Response to Loss of Secondary Heat Sink
Procedures
OFN NB-030
Loss of AC Emergency Bus NB01 (NB02)
39A
Procedures
STS IC-455B
Channel Calibration Control Room Air Intake Radiation
Monitor GK RE-0004
18A
Procedures
SYS AP-122
Non-Safety Aux Feed Pump Operation
Procedures
SYS SY-120
Sharpe Diesel Operation and Alignment to Site
14A
Work Orders
20-466623-001, 20-458883-018, 21-474284-000
Calculations
EF-M-80
UHS Inventory Losses form ESW through the AFW System
Calculations
GL-M-005
Electrical Penetration Room Temperature with Inoperable
Room Cooler
Calculations
HV-288
Loss of Ventilation
Corrective Action
Documents
Condition Reports
10007131, 10007263, 10007622
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10009180
Drawings
M-12AL01
Piping and Instrumentation Diagram Auxiliary Feedwater
System
Engineering
Changes
CCP 09816
Inoperable Electrical Penetration Room Cooler (SGL15A/B)
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
E-018-00189
Qualification and Test Summary Report
11W
Miscellaneous
EQSD-I
Equipment Qualification Design Basis Document
Miscellaneous
EQSD-II
Equipment Qualification Design Basis Document
Miscellaneous
WCRE-34
Fourth 10-Year Interval Inservice Testing Basis Document
Procedures
Operability Determination and Functionality Assessment
Procedures
MPE RC-001
Room Cooler Maintenance
Procedures
MPE VD-001
27A Ventilation Damper Maintenance
Procedures
SYS GL-200
Inoperable Penetration Room Cooler
13A
Procedures
SYS OQT-001B
Operations B Train Quarterly Tasks
Work Orders
20-466019-000, 20-466019-001
Calculations
GM-M-002
Diesel Generator Building Minimum Room Temperature
Calculations
KJ-M-017
Emergency Diesel Standby Generator (KKJ01 BB) Runtime
without ESW Flow
Corrective Action
Documents
Condition Reports
10003002, 10003106, 10003334, 10003523, 10003525,
10003731, 10004244, 10004269, 10007567
Corrective Action
Documents
Resulting from
Inspection
Condition Reports
10007846, 10008687
Miscellaneous
M-018-00155
Operation of Engine without Cooling Water
Procedures
ALR 00-120A
MFP A Trip
Procedures
ALR 00-123A
MFP B Trip
Procedures
ALR 00-123A
MFP B Trip
Procedures
BD-EMG E-0
Reactor Trip or Safety Injection
29A
Procedures
EMG E-0
Reactor Trip or Safety Injection
Procedures
MFP A Trip
MFP A Trip
Procedures
OFN EF-033
Loss of Essential Service Water
Procedures
OFN NB-042
Loss of Offsite Power to NB01 (NB02) with EDG Paralleled
Corrective Action
Documents
Condition Reports
10005026, 10007439, 10008456, 10008543
Miscellaneous
WCOP-02
Inservice Testing Program for Pumps, Valves, and Snubbers
Miscellaneous
WCRE-34
Fourth 10-Year Interval Inservice Testing Program
Procedures
AI 23D-002
Motor Operated Valve Calculation Program
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Post Maintenance Testing Development
20A
Procedures
Motor Operated Valve Program
Procedures
MPM LT-001
Limitorque Operator Minor Maintenance, Lubrication, and
Inspection
Procedures
STN EM-201
Safety Injection Valve Test
Procedures
STS AE-211
Main Feed Reg Valve Inservice Test
Procedures
STS AL-101
MDAFW Pump A Inservice Pump Test
Procedures
STS EM-100A
Safety Injection Pump A Inservice Pump Test
Procedures
STS VT-001
Verification of OMN-1, MOV Exercise Requirements
Work Orders
15-399593-001, 15-399593-018, 15-399593-021,
20-466803-000, 20-467625-000, 20-467625-001,
21-470469-000, 21-470469-001, 21-473455-007,
21-473455-008, 21-473455-013
Calculations
FD-13-008
Corrective Action
Documents
Condition Reports
139748, 142288, 142515, 145234, 10000718, 10006728
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10007983
Miscellaneous
WCNOC-183
Operations and Maintenance Manual RCS Pump Cat Triplex
353 HS.AIP Plunger Pump rated 20 GPM @ 1650 psig
W01
Procedures
Post Maintenance Testing Equipment
20A
Procedures
Diverse and Flexible Coping Mitigating Strategies (FLEX)
Program
Procedures
Heat Exchanger Program
Procedures
STN PE-036
Safety Related Room Cooler Heat Transfer Verification and
Performance Trending
Procedures
STN PE-037A
ESW Train A Heat Exchanger Flow and DP Trending
Procedures
STN PE-037B
ESW Train A Heat Exchanger Flow and DP Trending
Procedures
STS EG-101B
Component Cooling Water Pumps B/D Comprehensive
Pump Test
7B
Procedures
STS IC-211
Actuation Logic Test Train A Solid State Protection System
37A
Procedures
SYS FD-001
Operations Monthly FLEX Tasks
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
SYS FD-002
Operations Annual FLEX Tasks
Work Orders
10-323422-000, 11-338649-000, 12-357297-000,
18-446961-000, 18-446961-001, 19-457078-005,
19-457425-000, 20-457635-000, 20-463186-002,
20-463186-010, 20-464266-000, 20-465658-000,
20-465658-002, 20-467211-000, 20-467211-001,
20-467213-000, 20-467458-000, 21-468259-000,
21-472930-000
Corrective Action
Documents
Condition Reports
10008457, 10008465, 10008468
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10008633
Procedures
ALR 00-130C
ESF N2 ACC Press LoLo
Procedures
ALR 00-130D
ESF N2 ACC Press Lo
71151
Corrective Action
Documents
Condition Report
10001662
71151
Miscellaneous
WCNOC-163
Mitigating System Performance Index Basis Document
71151
Procedures
FSG-05
Initial Assessment and FLEX Equipment Staging
Calculations
DAR-PEUS-12-6
FLEX Electrical Conceptual Design for the Wolf Creek
Nuclear Operating Corporation
Calculations
FD-E-001
FD System Electrical Calculations
Corrective Action
Documents
Condition Reports
139748, 142288, 142515, 145234, 128958, 133406, 133814,
134405, 134406, 134409, 141390, 10003270, 10004822,
10000718
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10007628
Drawings
CYBER-C-0001
Cyber Security Network Block Diagram
E
Miscellaneous
AC-VULN-
10003270
Windows Server 2003 and Windows XP Vulnerabilities
identified through CVEs
05/26/2021
Miscellaneous
Critical System Administrative Guide
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
LCM-20210405
SCS-LCM-202993.00, Security Computer System
Miscellaneous
RC-VULN-
10003270
Windows Server 2003 and Windows XP Vulnerabilities
identified through CVEs
05/26/2021
Miscellaneous
WCNOC-185
Beyond Design Basis Flex Equipment Operations and
Maintenance Manual 500 kW Generator C15 Model
W02
Miscellaneous
Cyber Security Plan
Procedures
AI 15D-020
Defense-in-Depth Cyber Security Protective Strategy
Procedures
AI 15D-027
Ongoing Monitoring & Vulnerability Analysis (OM&VA)
Procedures
Wolf Creek Cyber Security Program
Procedures
FSG-08
Alternate RCS Boration
Work Orders
18-443033-001, 20-457258-000, 20-458235-000,
20-460439-000, 20-461349-000, 20-463623-000,
20-464828-000, 20-464837-000, 20-464838-000,
20-464839-000, 20-464840-000, 20-464840-000,
20-464842-000, 20-464843-000, 20-464844-000,
20-469726-000
Corrective Action
Documents
Condition Report
10008456
Procedures
EMG E-0
Reactor Trip or Safety Injection
Procedures
EMG ES-02
Reactor Trip Response
Work Orders
21-473455-015, 21-473455-016, 21-473455-017,
21-473455-018