IR 05000482/2018003
| ML18311A384 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 11/07/2018 |
| From: | Nick Taylor NRC/RGN-IV/DRP/RPB-B |
| To: | Heflin A Wolf Creek |
| References | |
| IR 2018003 | |
| Download: ML18311A384 (62) | |
Text
ber 7, 2018
SUBJECT:
WOLF CREEK GENERATING STATION - NRC INTEGRATED INSPECTION REPORT 05000482/2018003
Dear Mr. Heflin:
On September 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Wolf Creek Generating Station. On October 31, 2018, the NRC inspectors discussed the results of this inspection with Mr. S. Smith, Vice President Engineering, 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 this report.
This finding involved a violation of NRC requirements. Additionally, NRC inspectors documented one Severity Level IV violation with no associated finding. The NRC is treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violations or significance of these NCVs, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC resident inspector at the Wolf Creek Generating Station.
If you disagree with a cross-cutting aspect assignment 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 the 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 Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Nicholas H. Taylor, Chief Project Branch B Division of Reactor Projects Docket No. 50-482 License No. NPF-42 Enclosure:
Inspection Report 05000482/2018003 w/Attachments:
1. Documents Reviewed 2. Request for Information Public Radiation Safety Inspection
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number: 05000482 License Number: NPF-42 Report Number: 05000482/2018003 Enterprise Identifier: I-2018-003-0012 Licensee: Wolf Creek Nuclear Operating Corporation Facility: Wolf Creek Generating Station Location: Burlington, Kansas Inspection Dates: July 1 to September 30, 2018 Inspectors: D. Dodson, Senior Resident Inspector F. Thomas, Resident Inspector S. Alferink, Reactor Inspector H. Anagnostopoulos, NRC Region I, CHP, Senior Health Physicist L. Carson II, Senior Health Physicist P. Elkmann, Senior Emergency Preparedness Inspector N. Greene, PhD, Senior Health Physicist J. Kirkland, Senior Operations Engineer J. Melfi, Project Engineer J. ODonnell, CHP, Health Physicist D. Proulx, Senior Project Engineer Approved By: Nicholas H. Taylor Chief, Project Branch B Division of Reactor Projects Enclosure
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. NRC-identified and self-revealed findings, violations, and additional items are summarized in the table below.
Licensee-identified non-cited violations are documented in the Inspection Results at the end of this report.
List of Findings and Violations Failure to Correct Degraded Performance of a Safety-Related Tornado Damper Cornerstone Significance Cross-cutting Aspect Inspection Procedure Mitigating Green H.14 - Human 71152 -
Systems NCV 05000482/2018003-01 Performance, Problem Closed Conservative Bias Identification and Resolution The inspectors identified a Green non-cited violation of 10 CFR Part 50, Criterion XVI,
Corrective Action, for the licensees failure to promptly correct a condition adverse to quality associated with a safety-related tornado damper. Specifically, damper GTD0002 failed tests in 2012 and 2015, and following maintenance on the damper in 2017, again failed its next as-found test on February 8, 2018. As a result, this safety-related tornado dampers ability to close during a design basis tornado event was adversely impacted.
Failure to Submit a Licensee Event Report for a Condition Prohibited by Technical Specifications Cornerstone Significance Cross-cutting Aspect Inspection Procedure Not Severity Level IV Not Applicable 71152 -
Applicable NCV 05000482/2018003-02 Problem Closed Identification and Resolution The inspectors identified a Severity Level IV non-cited violation of 10 CFR 50.73(a)(2)(i)(B),
because the licensee did not provide a written licensee event report (LER) to the NRC within 60 days. Specifically, the licensee did not provide a written LER to the NRC within 60 days of identifying a condition prohibited by the plants Technical Specifications associated with inoperability of control room emergency ventilation system train B for longer than its Technical Specification allowed outage time. As a result, the NRCs ability to regulate was impacted.
PLANT STATUS
Wolf Creek Generating Station began the inspection period operating at full power. On August 16, 2018, operators reduced power to approximately 59 percent following the loss of the Wolf Creek-Rosehill offsite 345 kV line as a result of heavy offsite storms and the 345-40 switchyard circuit breaker failing to reclose. The plant was restored to approximately full power on August 18, 2018, and the plant operated at or near full power for the rest of the 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 plant status activities described in IMC 2515 Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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
71111.01Adverse Weather Protection External Flooding
The inspectors evaluated readiness to cope with external flooding on July 12, August 8, and September 11, 2018.
71111.04Equipment Alignment Partial Walkdown
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Safety injection train B on July 17, 2018
- (2) Charging pump train B on July 24, 2018
- (3) Class 1E offsite electrical circuit alignment in preparation for realigning to an alternate supply line-up to Class 1E 4160 volt alternating current bus NB01 on August 21, 2018
- (4) Motor driven auxiliary feedwater train A on August 29, 2018
- (5) Emergency diesel generator train B on September 19, 2018
71111.05AQFire Protection Annual/Quarterly Quarterly Inspection
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Control building, elevation 2,016 feet, fire areas C-13, C-14, C-15, C-16, C-18, C-19, and C-35 (Class 1E air conditioning unit rooms, safety-related battery rooms, and switchgear rooms) on July 12, 2018
- (2) Control building, elevation 2,032 feet, fire areas C-21, C-23, and C-24 (lower cable spreading room and cable chases) on July 12, 2018
- (3) Auxiliary building, elevation 1,974 feet, fire areas A-1 and A-4 (emergency core cooling system train B) on July 26, 2018
- (4) Control building, elevation 1,984 feet, fire area C-5 (access control) on September 11, 2018
Annual Inspection (1 Sample)
The inspectors evaluated fire brigade performance on August 10 and September 7, 2018.
71111.06Flood Protection Measures Cables
The inspectors evaluated cable submergence protection in essential service water electrical manhole MHE2B on July 30, 2018.
71111.11Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification
The inspectors observed and evaluated licensed operator requalification activities in the simulator that included multiple instrument and component malfunctions and a steam generator tube rupture scenario on August 27, 2018.
Operator Performance (1 Sample)
The inspectors observed and evaluated power ascension activities after a reduction in power associated with the loss of the Rosehill 345 kV line on August 17, 2018.
Operator Requalification Program (1 Sample)
The inspectors evaluated the operator requalification program from June 4 to June 7, 2018.
71111.12Maintenance Effectiveness Routine Maintenance Effectiveness
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Class 1E instrument alternating current power inverter NN11 unexpectedly transferring to its bypass transformer on May 21, 2018
- (2) Chemical and volume control system reactor coolant system letdown to regenerative heat exchanger valve diaphragm leak and failure to open on April 29, 2018
- (3) Containment cooler train A breaker tripped while shifting to fast speed on May 9, 2018
71111.13Maintenance Risk Assessments and Emergent Work Control
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Planned safety-related NK24 battery charger maintenance on July 9 and July 10, 2018
- (2) Unplanned component cooling water train A essential service water weld leak on July 22 and July 23, 2018
- (3) Risk assessment and mitigation associated with protection of containment spray train B on July 24, 2018
- (4) Risk assessment associated with unplanned station blackout diesel generator switchgear PB005 non-functionality and planned emergency diesel generator train B maintenance on August 1, 2018
- (5) Risk assessment associated with extended service water pump A maintenance, abnormal switchyard alignment, and numerous lifts in the spent fuel pool building during the week of August 20, 2018
- (6) Risk assessment associated with protection of fuel building equipment during lift of cask handling crane trolley assembly from elevation 2,047 feet to crane trolley rail structure on August 27, 2018
- (7) Risk assessment associated with planned switchyard manipulations and extended instrument air compressor train A out-of-service time due to an unexpected breaker trip while restoring from maintenance
71111.15Operability Determinations and Functionality Assessments
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Essential service water system piping U-bolt support configuration on June 13, 2018
- (2) Essential service water train A to component cooling water train A heat exchanger isolation valve EFHV0051 leakby on July 23, 2018
- (3) Class 1E 125 Volt direct-current busses NK01, NK02, NK03, and NK04, and switchboards and components downstream of the NK buses on July 31, 2018
- (4) Boric acid storage tank train B seismic support configuration on August 6, 2018
- (5) Essential service water train B pin hole leakage on the return line of control room chiller unit SGK04B on August 8, 2018
71111.18Plant Modifications
The inspectors evaluated the Class 1E heating, ventilation, and air conditioning system recirculation system permanent modification.
71111.19Post Maintenance Testing
The inspectors evaluated the following post maintenance tests:
- (1) Component cooling water heat exchanger train A essential service water leak repair on July 24, 2018
- (2) Component cooling water pumps A and C following planned breaker and pump maintenance on August 13, 2018
- (3) Charging pump train A following planned maintenance on September 18, 2018
71111.22Surveillance Testing The inspectors evaluated the following surveillance tests: Routine
- (1) STS EN-005, Containment Spray Additive Tank Volume Verification, on July 18, 2018
In-service (2 Samples)
- (1) STS EJ-100B, [Residual Heat Removal] System Inservice Pump B Test, on July 11, 2018
- (2) STS BG-210, [Chemical and Volume Control System] Inservice Check Valve Test, on September 20, 2018
71114.02Alert and Notification System Testing
The inspector evaluated the maintenance and testing of the licensees alert and notification system on September 20, 2018.
71114.03Emergency Response Organization Staffing and Augmentation System
The inspector evaluated the readiness of the licensees Emergency Preparedness Organization on September 20, 2018.
71114.05Maintenance of Emergency Preparedness
The inspector evaluated the maintenance of the emergency preparedness program on September 18, 2018. The inspector observed emergency response organization training conducted on September 18 and September 19, 2018.
71114.06Drill Evaluation Emergency Planning Drill
The inspectors evaluated the emergency planning drill on August 28, 2018.
Drill/Training Evolution (1 Sample)
The inspectors evaluated simulator-based licensed operator qualification training on September 17,
RADIATION SAFETY
71124.05Radiation Monitoring Instrumentation Walk Downs and Observations
The inspectors evaluated radiation monitoring instrumentation during plant walkdowns.
Calibration and Testing Program (1 Sample)
The inspectors evaluated the licensees calibration and testing program.
71124.06Radioactive Gaseous and Liquid Effluent Treatment Walk Downs and Observations
The inspectors evaluated the licensees radioactive gaseous and liquid effluent treatment systems during plant walkdowns.
Calibration and Testing Program (Process and Effluent Monitors) (1 Sample)
The inspectors evaluated the licensees gaseous and liquid effluent monitor instrument calibration and testing.
Sampling and Analyses (1 Sample)
The inspectors evaluated radioactive effluent sampling and analysis activities.
Instrumentation and Equipment (1 Sample)
The inspectors evaluated radioactive effluent instrumentation and equipment.
Dose Calculations (1 Sample)
The inspectors evaluated dose calculations.
71124.07Radiological Environmental Monitoring Program Site Inspection
The inspectors evaluated the licensees radiological environmental monitoring program.
Groundwater Protection Initiative Implementation (1 Sample)
The inspectors evaluated the licensees groundwater monitoring program.
The inspectors identified an incomplete element of Wolf Creek Nuclear Operating Corporations implementation of the Ground Water Protection Initiative as described in NEI 07-07, Industry Ground Water Protection Initiative - Final Guidance Document, dated August 2007.
Specifically, the inspectors could not find evidence that Objective 1.2.2, Evaluate work practices that involve licensed material and for which there is a credible mechanism for the licensed material to reach ground water, had been performed as described in the initiatives acceptance criteria for that objective.
The inspectors found that:
- The licensee hired a contractor to perform a site risk assessment in 2008. That risk assessment focused specifically on site systems, structures and components as described in objective 1.2.1. The assessment did not specifically look at work practices as required in the second objective 1.2.2.
- Quick Hit Assessment QH-2013-0660 reviewed the sites compliance with NEI 07-07 using a comprehensive checklist of the documents requirements. The checklist combined objectives 1.2.1 and 1.2.2 together as one item. As a result, the previous failure to evaluate work practices (per objective 1.2.2) was not identified.
- Quick Hit Assessment QH-2016-1249 again reviewed the sites compliance with NEI 07-07, but using team members from other utilities. This assessment identified that there was no documentation that lists the identified work practices that meet this criteria
[objective 1.2.2]. Condition Report 101560 was written.
- The description provided in Condition Report 101560 adequately reflects the condition as identified in QH-2016-1249. The inspectors found, however, that the actions taken in response to the condition report focused only on updating the existing evaluation of systems, structures, and components (objective 1.2.1) and again did not address the missing evaluation of work practices as required in objective 1.2.2.
The incomplete implementation of NEI 07-07 was reviewed with licensee management on August 23, 2018. This was entered into the corrective action program by documenting the observations in Condition Reports 118440 and 126115.
71124.08Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation Radioactive Material Storage
The inspectors evaluated the licensees radioactive material storage.
Radioactive Waste System Walk-down (1 Sample)
The inspectors evaluated the licensees radioactive waste processing facility during plant walkdowns.
Waste Characterization and Classification (1 Sample)
The inspectors evaluated the licensees radioactive waste characterization and classification.
Shipment Preparations (1 Sample)
The inspectors evaluated the licensees radioactive material shipment preparation processes.
Shipment Records (1 Sample)
The inspectors evaluated the licensees non-excepted package shipment records.
OTHER ACTIVITIES - BASELINE
71151Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
- (1) MS06: Emergency AC Power Systems (07/01/2017 - 06/30/2018)
- (2) MS07: High Pressure Injection Systems (07/01/2017 - 06/30/2018)
- (3) MS10: Cooling Water Support Systems (07/01/2017 - 06/30/2018)
- (4) EP01: Drill/Exercise Performance Sample (10/1/2017 - 06/30/2018)
- (5) EP02: Emergency Response Organization Drill Participation Sample (10/1/2017 -
06/30/2018)
- (6) EP03: Alert And Notification System Reliability Sample (10/1/2017 - 06/30/2018)
71152Problem Identification and Resolution Annual Follow-up of Selected Issues
The inspectors reviewed the licensees implementation of its corrective action program related to an unplanned auxiliary feedwater train actuation on May 12,
INSPECTION RESULTS
Failure to Correct Degraded Performance of a Safety-Related Tornado Damper Cornerstone Severity Cross-cutting Aspect Inspection Procedure Mitigating Systems Green H.14 - Human
71152 - Problem NCV Performance,
Identification and 05000482/2018003-01 Conservative Bias Resolution Closed The inspectors identified a Green non-cited violation of 10 CFR Part 50, Criterion XVI, Corrective Action, for the licensees failure to promptly correct a condition adverse to quality associated with a safety-related tornado damper. Specifically, damper GTD0002 failed tests in 2012 and 2015, and following maintenance on the damper in 2017, again failed its next as-found test on February 8, 2018. As a result, this safety-related tornado dampers ability to close during a design basis tornado event was adversely impacted.
Description:
In December 2012 the licensee identified in Condition Report 61246 that during preventive maintenance and testing, the GTD0002 tornado damper exceeded its acceptance criteria for breakaway torque. Specifically, the as-found torque was 320 ft-lbs, which exceeded the acceptance criteria of 299 ft-lbs or less. The licensee implemented Work Order 12-355727-011, cycled the damper six times, and each time the damper break away torque was noted as between or equal to 280 to 290 ft-lbs. This failure was determined to be a result of lack of cycling leading to a non-uniform lubrication profile. No additional action was taken.
In January 2015, the licensee identified in Condition Report 90975 that during preventive maintenance and testing the GTD0002 damper was rubbing and exceeded its acceptance criteria for breakaway torque (as found break away torque was 380 ft-lbs as compared to the acceptance criteria of 299 ft-lbs or less). A contingency work order was implemented and actions were taken to reduce the rubbing that was identified. Rubbing was still noted following the corrective maintenance, but the as-left break away torque was found to be within acceptable ranges and the damper was described as cycling relatively smooth. The licensee performed a basic cause evaluation and determined that the probable cause was inadequate clearances between the damper blades and the associated ductwork during initial installation resulting in a rubbing or binding condition of the damper. A planned action included performing Work Order 15-397077-000.
On January 11, 2017, the licensee performed Work Order 15-397077-000 to adjust the ductwork at the GTD0002 damper. Bolting between the damper framework and the ductwork was loosened and the vertical duct face was mechanically adjusted. Work Order 15-397077-000 noted the as found condition of the two middle blades stating that they rub hard. Condition Report 110377 also noted that five of nine damper blades still exhibited rubbing as the ductwork relaxed. Work Order 15-397077-000 also noted that the damper passed its as-left break away torque test at 291 ft-lbs. Though, the work order pointed out, Damper blade still rubbing after adjustment. An email from maintenance personnel (attached to the work order) described the condition of the damper following maintenance.
The email stated, I was able to cycle the damper much easier than before but when we put the to[r]que wrench on it we were getting it to move at [approximately] 330 [ft-lbs].
We tried several times and we were all eyeballing it but each time it seemed it would just barely start to creep at around 290 [ft-lbs] but nothing very noticeable until 320-330 [ft-lbs].
Engineering personnel were contacted and the condition was accepted based on Slight movement at 290 [ft-lbs] during three subsequent attempts.
On February 8, 2018, while performing planned testing and maintenance on normally open safety-related tornado damper GTD0002 in accordance with Work Order 17-428518-000, the first stroke breakaway torque failed to meet the acceptance criteria of less than or equal to 299 foot-lbs. Condition Report 119330 noted the damper did not break away until applied torque had reached 325 foot-lbs and the damper seemed to be binding up the first quarter of the rotation.
Section 9.4.3.2.2, Component Description, of the Updated Final Safety Analysis Report describes the function of the normally open GTD0002 damper. It states, Tornado dampers are employed where isolation from the effects of extreme wind or tornado conditions is required. These dampers close with the flow produced by the differential pressure associated with tornadoes or high winds. Otherwise, the safety-related damper must be open to allow flow for the emergency exhaust system to vent through the unit stack.
Section 9.4.3.1.1, Safety Design Bases, of Section 9.4.3, Auxiliary Building, of the Updated Final Safety Analysis Report describes the design basis for this damper:
The emergency exhaust system, and those portions of the auxiliary buildingand the auxiliary/fuel building normal exhaustwhich are required to provide isolation of the auxiliary building are safety-related and are required to function following a [design basis accident] and to achieve and maintain the plant in a postaccident safe shutdown conditionThe emergency exhaust system, and the auxiliary building isolation provisions are protected from the effects of natural phenomena, such as earthquakes, tornadoes, hurricanes, floods, and external missiles (GDC-2).
The inspectors noted that both trains of the safety-related emergency exhaust system could be prevented from performing their safety-related functions if the damper did not close as designed during a design basis tornado. Specifically, the negative pressure created by a tornado could result in the collapse of the unit vent exhaust plenum, which is the exhaust flowpath for the emergency exhaust system.
Corrective Actions: On February 8, 2018, Work Order 17-421482-000 was performed to remove a small amount of the GTD0002 damper blade material at the edge of the damper blades to eliminate rubbing. The licensee also created long-term action 18-0008 to provide a permanent resolution for the rubbing issues that have contributed to the numerous failures of the breakaway torque testing.
Corrective Action References: Condition Reports 119330 and 127690.
Performance Assessment:
Performance Deficiency: The failure to promptly correct a condition adverse to quality associated with safety-related tornado damper GTD0002 was a performance deficiency.
Screening: The performance deficiency is more than minor, and therefore a finding, because it is associated with the structure, system and component, and barrier performance attribute of the Barrier Integrity Cornerstone objective to provide reasonable assurance that physical design barriers (fuel cladding, reactor coolant system, and containment) protect the public from radionuclide releases caused by accidents or events. Specifically, the auxiliary building boundary and the emergency exhaust systems ability to exhaust potentially contaminated air from the emergency core cooling system could be adversely impacted by the GTD0002 dampers inability to meet breakaway torque requirements.
Significance: The inspectors assessed the significance of the finding using Exhibit 3, Barrier Integrity Screening Questions, of Inspection Manual Chapter 0609, Appendix A, Significance Determination Process (SDP) for Findings At-Power, issued June 19, 2012, and determined this finding does not only represent a degradation of the radiological barrier function provided for the control room, or auxiliary building, or spent fuel pool, and the finding does not represent a degradation of the barrier function of the control room against smoke or a toxic atmosphere. Therefore, the inspectors determined the finding was of very low safety significance (Green).
Cross-cutting Aspect: The inspectors determined that the finding has a human performance cross-cutting aspect in the area of conservative bias in that individuals did not use decision making-practices that emphasize prudent choices over those that are simply allowable.
Specifically, individuals rationalized assumptions for the sake of completing a task when the rubbing condition was accepted with slight movement of the damper at the acceptance criteria, rather than pursuing resolution of the known degraded condition of the damper blades. As a result, when the damper was next tested, it failed at the same unsatisfactory torque value as that observed in January 2017.
Enforcement:
Violation: Title 10 CFR 50, Appendix B, Criterion XVI, Corrective Action, requires, in part, that measures shall be established to assure that conditions adverse to quality, such as failures, are promptly corrected.
Contrary to the above, until February 8, 2018, measures were not established to assure that conditions adverse to quality, such as failures, were promptly corrected. Specifically, actions taken to correct the degraded condition of safety-related tornado damper GTD0002 were inadequate to ensure it could perform its safety function from January 2017 through February 2018. As a result, the damper failed testing again in 2018.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Failure to Submit a Licensee Event Report for a Condition Prohibited by Technical Specifications Cornerstone Severity Cross-cutting Aspect Inspection Procedure Not Applicable Severity Level IV Not Applicable
71152 - Problem NCV
Identification and 05000482/2018003-02 Resolution Closed The inspectors identified a Severity Level IV non-cited violation of 10 CFR 50.73(a)(2)(i)(B),because the licensee did not provide a written licensee event report (LER) to the NRC within 60 days. Specifically, the licensee did not provide a written LER to the NRC within 60 days of identifying a condition prohibited by the plants Technical Specifications associated with inoperability of control room emergency ventilation system train B for longer than its Technical Specification allowed outage time. As a result, the NRCs ability to regulate was impacted.
Description:
On March 5, 2018, the licensee performed Procedure STS PE-004, Aux Building and Control Room Pressure Test, Revision 16, and the B train control room emergency ventilation systems ability to pressurize the control room envelope and maintain pressure greater than or equal to 0.25 inches water gauge failed. Later tests on March 5, 2018, which maintained control of control building doors, had results that varied between 0.18 and 0.26 inches water gauge, with an average of 0.2258 inches water gauge.
Troubleshooting was performed and, on March 6, 2018, an interim configuration associated with Design Change Package 14269, SGK05 Tech Spec Addition and Compensatory Modifications, was found to be impacting readings. Specifically, between September 17, 2017, and January 17, 2018, four openings, approximately 2 foot by 2 foot, were cut in the floor/ceiling between the 2,032 foot and 2,016 foot elevations of the control building to support ongoing ductwork installation. On January 17, 2018, after penetrations for the modification were completed, compensatory measures consisting of steel plates covering the four floor openings were in place until ductwork installation began on February 19, 2018. Beginning on February 19, 2018, the penetrations remained open during ductwork and damper installation until March 6, 2018, when the ductwork and damper installation was completed.
Following numerous actions to restore margin to the ability to pressurize the control room envelope, surveillance testing was performed for the B and A trains of the control room emergency ventilation system on March 15, 2018, and the control room envelope was pressurized to 0.3448 and 0.3695 inches water gauge, respectively. Additional information on this issue is described in NCV 05000482/2018002-02, Failure to Maintain Adequate Pressurization of the Control Room Envelope, (ADAMS ML18226A175).
The licensees cause evaluation determined that the probable causes of the issue were inadequate identification of control building ventilation isolation boundaries in WCRE-35, Boundary Matrix, and control of conditions during STS PE-004. Relative to the interim configuration in which the ducting was found on March 6, 2018, the licensees cause evaluation stated, When the ducting was fully installed and the control room pressure tested in the same configuration, an increase of 0.04 to 0.07 [inches water gauge] was noted initially. Enough to pass acceptance criteria and close to the pressures last noted during performance of STS PE-004 in 2016. The readings were taken immediately following the closure of the main control room door and while the total average over that period was 0.2641 [inches water gauge], the last 5 minutes of readings averaged 0.2935 [inches water gauge]. This would seem to indicate that the control room pressure was still stabilizing and that the pressure was similar to those found during past differential pressure tests.
When the surveillance was ran the following week it did not pass but conditions under which the surveillance were ran differed in both timing and alignment which may have contributed to the lower than expected pressure.
In addition to the licensees conclusions regarding the interim configurations impact on the control room emergency ventilation system, the licensees evaluation noted, A number of factors were found to be consequential to control room pressure during the event under evaluation. Direct comparison between all the pressures found is complicated by the numerous varying factors between each of the tests. However, based on the test results the probable cause of the initial failure is related to the penetration between the 2032 and 2016 elevations of the Control Building.
Considering successful informational testing on March 6, 2018, after ductwork and dampers were installed, considering additional information provided in the licensees cause evaluation, and considering reportability subject matter expert input the inspectors determined that train B of the control room emergency ventilation system was inoperable between February 19, 2018, and March 16, 2018, when the system was returned to operable.
Corrective Actions: In response to the inspectors questions the licensee initiated Condition Report 127691.
Corrective Action References: Condition Report 127691.
Performance Assessment:
The inspectors determined this violation was associated with a minor performance deficiency.
Enforcement:
The Reactor Oversight Processs significance determination process does not specifically consider the regulatory process impact in its assessment of licensee performance.
Therefore, it is necessary to address this violation which impedes the NRCs ability to regulate using traditional enforcement to adequately deter non-compliance.
Severity: The inspectors determined that the failure to provide a written LER within 60 days was a performance deficiency that was reasonably within the licensees ability to foresee and correct, and should have been prevented. This violation involved not making a required report to the NRC and is considered to impact the regulatory process. Such violations are dispositioned using the traditional enforcement process instead of the Significance Determination Process. Using the Enforcement Policy, Section 6.9, Inaccurate and Incomplete Information or Failure to Make a Required Report, example (d)(9), which states, A licensee fails to make a report required by 10 CFR 50.72 or 10 CFR 50.73, the NRC determined this violation is more than minor and is categorized as a Severity Level IV violation (very low safety significance).
Violation: Title 10 CFR 50.73(a) requires, in part, that licensees submit an LER for any event of the type described in the paragraph within 60 days after the discovery of the event.
Title 10 CFR 50.73(a)(2)(i)(B) requires, in part, that any operation or condition which was prohibited by the plants Technical Specifications be reported in an LER.
Contrary to the above, on May 4, 2018, an operation or condition which was prohibited by the plants Technical Specifications was not reported in an LER. Specifically, Technical Specification 3.7.10, Control Room Emergency Ventilation System (CREVS), requires, in part, immediate initiation of action to implement mitigating actions when one or more control room emergency ventilation system trains is inoperable due to an inoperable control room envelope boundary or control building envelope boundary in MODES 1, 2, 3, or 4, or the unit must be in MODE 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Neither immediate initiation of action to implement mitigating actions was implemented, nor the unit placed in MODE 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 5 in 36, and the condition prohibited by the plants Technical Specifications was not later reported in an LER.
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
On August 16, 2018, the inspector presented the licensed operator requalification inspection results to Ms. J. Yunk, Training Manager, and other members of the licensee staff. The inspector verified no proprietary information was retained or documented for this inspection period.
On August 23, 2018, the inspectors presented the baseline radiation protection inspection results to Mr. T. Fugate, Director, Plant Support, and other members of the licensee staff. The inspectors verified no proprietary information was retained or documented in this report.
On September 21, 2018, the inspector presented the results of the onsite inspection of the emergency preparedness program to Mr. M. Boyce, Director, Engineering Projects, and other members of the licensee staff. The inspector verified no proprietary information was retained or documented in this report.
On October 31, 2018, the inspector presented the quarterly resident inspector inspection results to Mr. S. Smith, Vice President, Engineering, and other members of the licensee staff. The inspectors verified no proprietary information was retained or documented in this report.
DOCUMENTS REVIEWED
71111.01Adverse Weather Protection
Procedures
Number Title Revision
OFN SG-048 Flash Flood Warning 6
STS PE-049E Train A Essential Service Water System in Vaults Pressure 1
Test
Drawings
Number Title Revision
10466-A-1330 Access Control Floor Plan, El. 1984-0 5
C-1C3902 Control Building Area 1 Concrete Neat Lines and 7
Reinforcing Wall Elevations Sheet 2
C-K201 E.S.
Sections and Schedules Sht. 1
C-K201 E.S.
Sections and Schedules Sht. 1
C-K202 E.S.
Sections and Schedules Sht. 2
C-K202 E.S.
Sections and Schedules Sht. 2
C-K208 E.S.
- W.S. Yard Pipeline Valve House Plans, Sections, and 5
Details Sht. 1
C-K208 E.S.
- W.S. Yard Pipeline Valve House Plans, Sections, and 8
Details Sht. 1
Condition Reports
21699 124381 124382 124383 124397
24409 124988 125177 125196 125197
26267 126345
Miscellaneous Documents
Number Title Revision
014592 Field Change Notice - Change Package Title: ESW Below 2
Ground Plant Tie-In Approval and Component Abandonment
Miscellaneous Documents
Number Title Revision
014592 Field Change Notice - Change Package Title: ESW Below 3
Ground Plant Tie-In Approval and Component Abandonment
10466-C107-1 Bechtel: Technical Specification for Purchase of Waterstops 1
and Expansion Joint Filler for the Standardized Nuclear Unit
Power Plant System (Snupps); Job No. 10466
APF 05-002-05 Engineering Disposition: ESW Below Ground Plant Tie-In 0
Approval and Component Abandonment - Package
- 014592
APF 05-002-05 Engineering Disposition: ESW Below Ground Plant Tie-In 1
Approval and Component Abandonment - Package
- 014592
APF 05-007-01 Safety Classification Analysis - Change Package #013503 1
71111.04Equipment Alignment
Procedures
Number Title Revision
AI 15C-006 Management Oversight Requirements for Infrequently 22
Performed and Potentially Degrading Evolutions
AP 21G-001 Control of Locked Component Status 73
AP 26C-004 Operability Determination and Functionality Assessment 32
CKL AL-120 Auxiliary Feedwater Normal Lineup 42
CKL BG-120 Chemical and Volume Control System Normal Valve Lineup 41
CKL BG-130 Chemical and Volume Control System Switch and Breaker 31A
Lineup
CKL EM-120 Safety Injection System Lineup Checklists 32
CKL KJ-121 Diesel Generator NE01 and NE02 Valve Checklist 40B
MGM MOOP-01 Relief Valve Bench Testing 25
STS IC 645A Slave Relay Test K645 Train A Containment Spray 17
SYS NB-200 Transferring XNB01 Supply Between SL7 and #7 19
Transformer
SYS NP-201 Transferring NB01 Power Sources 61
Drawings
Number Title Revision
E-1001 Single Line Diagram Site Area Loads 37
E-11001 Main Single Line Diagram 11
E-11005 List of Loads Supplied by Emergency Diesel Generator 52
E-11010 DC Main Single Line Diagram 11
E-11010A DC Main Single Line Diagram (PK03 and PK04 BUS) 5
E-12KJ01 Standby Generation Engine and Governor Control Logic 6
Diagram
E-12NE01 Standby Generation Excitation Control Logic Diagram 3
E-12NE02 Logic Diagram Standby Gen. System Protection 6
E-K1001 Single Line Diagram Essential Service Water System 3
KD-7496 One Line Diagram 63
KD-7496 One Line Diagram 67
KD-7750 Wolf Creek Substation General Plan 13
M-12AL01 Piping & Instrumentation Diagram Auxiliary Feedwater 28
System
M-12AP01 Piping & Instrumentation Diagram Condensate Storage and 21
Transfer System
M-12BG03 Piping and Instrumentation Diagram Chemical & Volume 48
Control System
M-12EJ01 Piping and Instrumentation Diagram Residual Heat 52
Removal System
M-12EM01 Piping & Instrumentation Diagram High Pressure Coolant 42
Injection System
M-12EM01 Piping & Instrumentation Diagram High Pressure Coolant 45
Injection System
M-12EM02 Piping & Instrumentation Diagram High Pressure Coolant 23
Injection System
M-12EM03 Piping & Instrumentation Diagram High Pressure Coolant 4
Injection System Test Line
M-12KJ04 Piping & Instrumentation Diagram, Standby Diesel 18
Generator B, Cooling Water System
M-12KJ05 Piping & Instrumentation Diagram, Standby Diesel 17
Generator B, Intake Exhaust, F.O. & Start Air Sys.
Drawings
Number Title Revision
M-12KJ06 Piping & Instrumentation Diagram, Standby Diesel 22
Generator B, Lube Oil System
M-724-00323 Crosby Valve & Gage Co. Drawing DS-C-60705, Titled - W05
Nozzle Type Relief Valve
Condition Reports
25096 125097 125253
Miscellaneous Documents
Number Title Revision/Date
0303 Westar Energy, Inc. - Transmission Operating Directive August 17,
2018
APF 21C-001-01 Wolf Creek Substation Work Authorization: 2018-026, August 20,
SY124 Cable PMT 2018
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment: August 20 to
Schedule Week 2018-308 26, 2018
M-724-00811 Installation, Operation and Maintenance Instructions for W01
Anderson Greenwood Crosby Style Pressure Relief Valves
71111.05AQFire Protection Annual/Quarterly
Procedures
Number Title Revision
AP 10-105 Fire Protection Training and Drills 22
AP 10-105 Fire Protection Training and Drills 23
AP 10-106 Fire Preplans 18A
AP 10-107 Fire Event Investigation and Reporting 5
OFN KC-016 Fire Response 47
Condition Reports
25027 125028 125752 126417 126418
26419 126517 126518 126527 126528
26529 126530
Work Orders
17-428938-000
Miscellaneous Documents
Number Title Revision/Date
APF 06-002-01 Emergency Action Levels 17B
APF 10-105-02 Fire Drill Scenario and Critique Report: Time - 0800 August 10,
2018
APF 10-105-02 Fire Drill Scenario and Critique Report: Time - 0800 September 7,
2018
APF 10-105-02 Fire Drill Scenario and Critique Report: Time - 1300 September 7,
2018
APF 10-105-04 Fire Brigade Meeting Agenda September 7,
2018
APF 21-001-02 Control Room Turnover Checklist - On-Coming CRS/WC September 7,
SRO/RO/BOP Review: Day Shift 2018
APF 21-001-02 Control Room Turnover Checklist - On-Coming CRS/WC September 7,
SRO/RO/BOP Review: Night Shift 2018
APF 21-001-02 Control Room Turnover Checklist - On-Coming CRS/WC September 8,
SRO/RO/BOP Review: Night Shift 2018
APF 30E-003-02 Training Attendance September 10,
2018
E1F9905 Fire Hazard Analysis 8
EPF 06-007-01 Wolf Creek Generating Station Emergency Notification 14
FL1224000 Fire Brigade Leader/Incident Commander 8
No. 18 Coffey County Emergency Management Office Contingency 14
Plan Implementing Procedure
OBSR 2018- Observation Card: Fire Protection - Fire Brigade Drill August 10,
27 2018
XX-X-004 Combustible Fire Loading For Each Room in the Various 4
Fire Areas at WCNOC
71111.06Flood Protection Measures
Drawings
Number Title Revision
C-K202 E.S.
Sections and Schedules Sht.-2
Drawings
Number Title Revision
C-K209 E.S.W.S. Electrical Manholes Plans Sections and Details 9
C-K210 ESWS Yard Pipelines and Elect. Duct Banks Sections and 9
Details
C-K212 E.S.W.S. Yard Pipelines and Elec. Duct Banks Plan and 3
Sections
C-K212 E.S.W.S. Yard Pipelines and Elec. Duct Banks Plan and 4
Sections
E-KR0231 Raceway Plot Plan Essential Service Water System Plan 9
and Sections
E-KR0231 Raceway Plot Plan Essential Service Water System Plan 10
and Sections
71111.11Licensed Operator Requalification Program and Licensed Operator Performance
Procedures
Number Title Revision
AI 21-016 Operator Time Critical Actions Validation 7
AI 30B-005 Conduct of Simulator Activities for Licensed Operator 30
Training
AI 30B-15 Licensed Operator Requalification Exam Guidelines 12
AI 30C-001 Continued Assurance of Simulator Fidelity 17
AI 30C-004 Simulator Real Time Capacity Testing 5B
AI 30C-005 Simulator Steady State Testing 9A
AI 30C-006 Simulator Transient Testing 11
AI 30C-007 Simulator Core Testing 3
AI 30C-008 Scenario Based Testing 2A
AI 30E-13 Written and Oral Examinations 26A
AI 30E-15 Just in Time Training 13
AI 30E-23 Remediation 3
AP 30B-001 Licensed Operator Requalification Training Program 29
GEN 00-004 Power Operation 91
STS SE-001 Power Range Adjustment to Calorimetric 36
SYS MA-200 Placing the Switchyard in a Ring Bus Configuration 14
Drawings
Number Title Revision
KD-7496 One Line Diagram 67
Condition Reports
105145 105841 112616 114281 115643
116660 117338 117340 117341 117414
117619 120012 120582 123951
Miscellaneous Documents
Number Title Revision/Date
Rose Hill Line Return to 100% August 17,
2018
AIF 30B-15-07 Ops Requal Walk-through Exam Prep Checklist 1
AIF 30B-15-08 Simulator Examination Preparation Checklist 1
AIF 30B-15-09 Simulator Security Checklist 8
AIF 30B-15-15 Sequestering Checklist 1
AIF 30B-15-18 Simulator Setup Checklist 1
AIF 30B-15-19 JPM Exam Simulator Setup Checklist 1
APF 21-001-02 Control Room Turnover Checklist - On-Coming CRS/WC August 16,
SRO/RO/BOP Review: Day Shift 2018
APF 21-001-02 Control Room Turnover Checklist - On-Coming CRS/WC August 16,
SRO/RO/BOP Review: Night Shift 2018
APF 21-001-02 Control Room Turnover Checklist - On-Coming CRS/WC August 17,
SRO/RO/BOP Review: Night Shift 2018
APF 29B-003-01 Surveillance Test Routing Sheet: STS SE-001 Completed
August 17,
2018
JPMs 2018 Exam -Week 2 June 2018
Remediation February 2017 February 2017
Plan
Remediation February 2018 February 2018
Plan
Remediation January 2017 January 2017
Plan
Miscellaneous Documents
Number Title Revision/Date
Remediation March 2018 March 2018
Plan
Remediation September 2016 September
Plan 2016
Scenario 16-06 Requalification Exam 2
Scenarios 2018 Exam - Week 2 June 2018
Simulator Test ATWS with a Faulted Steam Generator May 10, 2017
Simulator Test Steam Generator Fault Inside Containment May 24, 2017
Simulator Test Steam Generator Fault Outside Containment May 18, 2017
SMP A11-095 Alarm Sounds are Different than in the Plant May 31, 2011
SMP A16-041 Accumulator Reliefs Will Not Open or Leak By August 24,
2016
SMP A16-047 Turbine Trip on Loss of Condensate Pump B July 27, 2016
SMP A16-068 A Change in CCW Temp Does not Change RCP Bearing November 15,
Temps 2016
SMP A17-102 Ventilation Fans Wont Stop/Start July 20, 2017
SMP A17-114 MFP Speed Impacted by Change in RCS Pressure April 10, 2018
SMP A17-160 Taking DRPI Switch to Half Accuracy Cleared DRPI Short December 4,
2017
71111.12Maintenance Effectiveness
Procedures
Number Title Revision
AI 22C-010 Operations Work Controls 1
AI 22C-013 Protected Equipment Program 21
AP 22C-003 On-Line nuclear Safety and Generation Risk Assessment 22
AP 22C-007 Risk Management Contingency Planning 11
AP 22C-008 Qualitative Risk Management 4B
SYS NN-200A Transferring NN01 and NN03 Buses Between Power 1
Sources
Drawings
Number Title Revision
M-12BG01 Piping & Instrumentation Diagram, Chemical and Volume 19
Control System
Condition Reports
21823 122610 122858 123047 123103
25743
Work Orders
17-426767-000
Miscellaneous Documents
Number Title Revision/Date
Evidence and Action Matrix: CR 122858/SWO 18-439146- May 3, 2018
000/001
Functional Failure Evaluation - CR 94075 Review Date
April 24, 2015
Functional Failure Evaluation for GN - CR 89850 Review Date
December 8,
2014
Functional Failure Evaluation for GN - CR 91851 Review Date
March 21,
2015
Functional Failure Evaluation for GN - CR 94058 Review Date
April 21, 2015
Functional Failure Evaluation for GN - CR 95765 Review Date
May 3, 2015
Functional Failure Evaluation for GN - CR 95845 Review Date
May 4, 2015
Functional Failure Evaluation for GN - CR 110725 Review Date
August 22,
2017
Functional Failure Evaluation for GN - CR 11072508 Review Date
July 20, 2017
Functional Failure Evaluation for GN - CR 117126 Review Date
November 22,
2017
Miscellaneous Documents
Number Title Revision/Date
Functional Failure Evaluation for GN - CR 123103 Review Date
June 7, 2018
Functional Failure Evaluation for GN - CR 123272 Review Date
May 23, 2018
System Health Report - Containment Cooling - System January 1 -
GN June 30, 2017
System Health Report - Containment Cooling - System July 1 -
GN December 31,
2017
System Health Report - Containment Cooling - System January 1 -
GN June 30, 2018
System Health Report - Instrument AC Power - System January 1 -
NN June 30, 2017
System Health Report - Instrument AC Power - System July 1 -
NN December 31,
2017
System Health Report - Instrument AC Power - System January 1 -
NN June 30, 2018
APF 15C-002-01 Procedure Cover Sheet: Transferring NN01 and NN03 1
Buses Between Power Sources
EDI 23M-050 Engineering Desktop Instruction Monitoring Performance May 21, 2018
to Criteria and Goals: System NN
GN Maintenance Rule Final Scope Evaluation: Containment Printed
Cooling System - GN-01 September 18,
2018
GN Maintenance Rule Final Scope Evaluation: Containment Printed
Cooling System - GN-02 September 18,
2018
GN Maintenance Rule Final Scope Evaluation: Containment Printed
Cooling System - GN-03 September 18,
2018
GN Maintenance Rule Final Scope Evaluation: Containment Printed
Cooling System - GN-04 September 18,
2018
GN Maintenance Rule Final Scope Evaluation: Containment Printed
Cooling System - GN-05 September 18,
2018
Miscellaneous Documents
Number Title Revision/Date
GN Maintenance Rule Final Scope Evaluation: Containment Printed
Cooling System - GN-06 September 18,
2018
GN Maintenance Rule Final Scope Evaluation: Containment Printed
Cooling System - GN-07 September 18,
2018
GN Maintenance Rule Final Scope Evaluation: Containment Printed
Cooling System - GN-08 September 18,
2018
NN Maintenance Rule Final Scope Evaluation: Instrument AC Printed
Power System - 120V (Class IE Power System) - NN01 August 15,
2018
NN Maintenance Rule Final Scope Evaluation: Instrument AC Printed
Power System - 120V (Class IE Power System) - NN02 August 15,
2018
71111.13Maintenance Risk Assessments and Emergent Work Control
Procedures
Number Title Revision
AI 15C-006 Management Oversight Requirements for Infrequently 22
Performed and Potentially Degrading Evolutions
CWD-1 Welding Program Manual 14
SYS NB-200 Transferring XNB01 Supply Between SL7 and #7 19
Transformer
SYS NB-200 Transferring XNB01 Supply Between SL7 and #7 20
Transformer
Drawings
Number Title Revision
C-1C6311 Fuel Building Conc. Neat Line & Reinforcing Plan Floor 2
El. 2,047-6
KD-7496 One Line Diagram 67
M-618.4-00010
M-12EF01 Piping & Instrumentation Diagram Essential SVC Water 29
System
Drawings
Number Title Revision
M-12EF02 Piping & Instrumentation Diagram Essential SVC Water 42
System
M-12EG01 Piping & Instrumentation Diagram Component Cooling 24
Water System
M-12EG02 Piping & Instrumentation Diagram Component Cooling 27
Water System
M12EG03 Piping & Instrumentation Diagram Component Cooling 19
Water System
M-12EM02 Piping & Instrumentation Diagram High Pressure Coolant 23
Injection System
M-K2EF01 Piping & Instrumentation Diagram Essential Service Water 70
System
M-K2EF03 Piping & Instrumentation Diagram Essential Service Water 19
System
Condition Reports
25201 125205 125224 125239 125245
25249 125250 125251 125252 125280
25372 125563 125637 125638 125716
Work Orders
16-414781-223 16-414781-304 18-441467-000 18-441467-003 18-441467-005
18-441467-008
Miscellaneous Documents
Number Title Date
303 Westar Energy, Inc. - Transmission Operating Directive August 17, 2018
2987 Performance Improvement Request October 2, 1998
APF 05C-004-01 WCNOC - Basic Engineering Disposition - SWO June 25, 2018
16-4162460926 - Evaluation of Fuel Building for Loads
From Installation of the Cask Handling Crane (HKE14 -
Change Package 15044)
APF 05C-004-01 WCNOC - Basic Engineering Disposition - Cask August 28, 2018
Handling Crane Modification: SARENs Heavy Lift Unit
(HLU)
APF 10-104-06 Boundary Watch Duties: Door #11274 July 22, 2018
Miscellaneous Documents
Number Title Date
APF 21-001-02 Control Room Turnover Checklist - On-Coming CRS/WC August 24, 2018
SRO/RO/BOP Review - Day Shift
APF 21-001-02 Control Room Turnover Checklist - On-Coming CRS/WC August 25, 2018
SRO/RO/BOP Review - Night Shift
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk July 30 to
Assessment: 2018-0305 August 5, 2018
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk August 20 to
Assessment: 2018-0308 August 26, 2018
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment August 27 to
2018-0309 September 2,
2018
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk September 24 to
Assessment: 2018-0313 September 30,
2018
APF 28A-001-01 Performance Improvement Request PIR 982987
71111.15Operability Determinations and Functionality Assessments
Procedures
Number Title Revision
AP 21I-001 Temporary Configuration Changes 15
AP 26C-004 Operability Determination and Functionality Assessment 35
CNT-MM-303 Temporary Support Guidelines 3
CWD-1 Welding Program Manual 14
Drawings
Number Title Revision
M-12BG05 Piping & Instrumentation Diagram Chemical and Volume 24
Control System
M-12EF01 Piping & Instrumentation Diagram Essential SVC Water 29
System
M-12EF02 Piping & Instrumentation Diagram Essential SVC Water 42
System
M-12EF06 Piping Isometric Essential Service Water Sys. [System] Aux. 23
[Auxiliary] Bldg. [Building] A & B Train Supply & Return
Drawings
Number Title Revision
M-12EG01 Piping & Instrumentation Diagram Component Cooling 24
Water System
M-12EG02 Piping & Instrumentation Diagram Component Cooling 27
Water System
M-12EG03 Piping & Instrumentation Diagram Component Cooling 19
Water System
M18BG35A(Q) Hanger Details Small Pipes Misc. and Boric Acid Storage 2
Tanks Vents - Auxiliary Building
M-19BG35(Q) Hanger Location Drawing Small Pipe Misc. and Boric Acid 5
Storage Tanks Vents-Auxiliary Building
M-K2EF01 Piping & Instrumentation Diagram Essential Service Water 70
System
M-K2EF03 Piping & Instrumentation Diagram Essential Service Water 19
System
Condition Reports
23902 123903 123905 123906 123907
23908 124948 125201 125205 125224
25243 125361 125374 125468 125487
25552 125560 125561 125638 125641
25716
Work Orders
18-439119-000 18-440015-000 18-441039-002 18-441039-003 18-441467-000
18-441467-003 18-441467-005 18-441467-008
Miscellaneous Documents
Number Title Revision/Date
AIF 28A-100-12 Wolf Creek Generating Station - Basic Cause Evaluation: September 8,
BGLT0106 Temporary Support Usage 2018
APF 05C-004-01 Basic Engineering Disposition - Evaluation of the Use of a 0
Temporary Pipe Support for Replacement of BGLT0106,
Boric Acid Tank B Level Transmitter
APF 10-104-06 Boundary Watch Duties: Door #11274 July 22, 2018
Miscellaneous Documents
Number Title Revision/Date
CNTF-MM-300-01 Quality Inspection Checklist - Pipe Support: BG35- 3
C527/112 (Q)
CNTF-MM-300-02 Section I Generic Inspection Item Instructions 3
CNTF-MM-300-07 Section VI - Small Bore/MS 25W Supports - Pipe 2
Support: BG35-C257/112 (Q)
CNTF-MM-303-01 Temporary Supports - Pipe Support: BG35-C527/112 (Q) 1
DG-C-002 Wolf Creek Nuclear Operating Corporation - Design 1
Guide: Evaluation Criteria for Temporary Acceptance of
Flaws in Moderate Energy Class 2 or 3 Piping
NK-E-001 125 VDC [Volt Direct Current] Class 1E Battery System 4
Sizing, Voltage Drop and Short Circuit Studies
OE EF-18-003 Operability Evaluation 0
OE NK-18-005 Operability Evaluation 0
WCRE-34 Fourth 10-Year Interval Inservice Testing Basis Document 9
71111.18Plant Modifications
Work Orders
16-414781-160 16-414781-223 16-414781-351
Miscellaneous Documents
Number Title Revision
DCP 14269 50.59 Evaluation TMP 18-001 0
DCP 14269 Configuration Summary 1
DCP 14269 Design Input Data Sheet 0
DCP 14269 Design Verification Report, SGK05 Permanent 0
Compensatory Modifications
DCP 14269 Engineering Screening, SGK05 Permanent Compensatory 0
Modifications
DCP 14269 Post Modification Testing Plan 0
71111.19Post Maintenance Testing
Procedures
Number Title Revision
QCP-20-540 VT-1 Visual Examination 1
STS BG-100A Centrifugal Charging System A Train Inservice Pump Test 48
STS EG-100A Component Cooling Water Pumps A/C Inservice Pump Test 33A
SYS EG-120 Component Cooling Water System 41
Drawings
Number Title Revision
M-12EG01 Piping & Instrumentation Diagram Component Cooling 24
Water System
Condition Reports
26021 126025 126036 126037 126038
26039 126040 126041 126734
Work Orders
18-441467-000 18-441467-003
Miscellaneous Documents
Number Title Revision/Date
18-025 Section XI Program Final Work Order Completion Review July 31, 2018
Signature Sheet: Work Order Number 18-441467-003
APF 15C-002-01 Procedure Cover Sheet - Component Cooling Water 41
System
APF 16A-003-01 ASME Section XI Repair/Replacement Plan Wolf Creek July 22, 2018
Generating Station - Plan No. 2018-025
APF 22C-008-01 Qualitative Risk Screening July 22, 2018
APF 29B-003-01 Surveillance Test Routing Sheet - Component Cooling August 13,
Water Pumps A/C Inservice Pump Test 2018
APF 29B-003-01 Surveillance Test Routing Sheet - STS BG-100A Completed
September 18,
2018
Miscellaneous Documents
Number Title Revision/Date
ET 18-0026 Docket No. 50-482: Supplement to Letter Dated July 23, August 28,
2018, Inservice Inspection Program Relief Request From 2018
the Requirements of American Society of Mechanical
Engineers (ASME) Code Case N-666-1, Weld Overlay of
Class 1, 2, and 3 Socket Welded Connections,Section XI,
Division 1
71111.22Surveillance Testing
Procedures
Number Title Revision
STS BG-210 CVCS Inservice Check Valve Test 35
STS CH-019 Containment Spray Additive Tank NAOH Concentration 7A
STS EJ-100B RHR System Inservice Pump A Test 55
STS EN-005 Containment Spray Additive Tank Volume Verification 3
STS IC-459 Channel Calibration Spray Additive Tank Level Loop 6C
ENLP0015
Drawings
Number Title Revision
10466-J-110- Instrument Loop Diagram - Containment Spray System 0
149-W08 Spray Additive Tank Full Range Level (Train A)
M-105B-0005 A6 ODX13Y-8 LG Contain Spray Additive Tank 11
M-105B-00018 Details-Containment Spray Additive Tank 4
Condition Reports
24979 125017 126396
Miscellaneous Documents
Number Title Revision/Date
APF 05-002-05 Engineering Disposition: Use of EN-LG-22 for Tech Spec 0
Surveillance
APF 28A-001-01 Performance Improvement Request: PIR 2006-0425 Initiated
February 19,
2006
Miscellaneous Documents
Number Title Revision/Date
APF 29B-003-01 Surveillance Test Routing Sheet - STS BG-210 Completed
September 20,
2018
APF 29B-003-01 Surveillance Test Routing Sheet - STS CH-019 Completed
July 18, 2018
APF 29B-003-01 Surveillance Test Routing Sheet - STS EN-005 Completed
July 18, 2018
APF 05-002-05 Engineering Disposition: PIR 2000-0394 - Use of EN-LG-22 0
for Tech Spec Surveillance
APF 05-004-01 Design Specification for Shop Fabricated Tanks (ASME III): 15
M-105B
LER 2000-001-00 Surveillance Method Results in Low NaOH Level in the March 13,
Spray Additive Tank 2000
STS CH-019 Containment Spray Additive Tank NAOH Concentration Completed
July 18, 2018
STS EN-005 Containment Spray Additive Tank Volume Verification Completed
July 18, 2018
71114.02 - Alert and Notification System Testing
Procedures
Number Title Revision
EPP 06-019 Alert and Notification System Sirens, March 26, 2003 3
EPP 06-019 Alert and Notification System Sirens, October 2, 2016 9A
EPP 06-022 Tone Alert Radio Maintenance/Compensating Measures, 5A
April 4, 2014
Work Orders
16-411700 16-416603 17-422188 17-430259
Miscellaneous Documents
Number Title Date
Letter, Mr. Ronald
Region VII to Mr. Richard Flannigan, Manager, Regulatory
Affairs, Wolf Creek Nuclear Operating Corporation;
Response to the Final Siren Test Report Review, from
American Signal Corporation for WCNOC
Miscellaneous Documents
Number Title Date
Memorandum, American Signal Corporation; Validation of
Outdoor Siren Propagation Model through Acoustic Testing
and Measurement of the Wolf Creek ANS Sy
REP-10 Design Review Report, Wolf Creek Nuclear May 7, 2008
Operating Company
Tone Alert Radio Audit Plan December 5,
2017
Tone Alert Radio Audit Plan December 8,
2016
71114.03 - Emergency Response Organization Staffing and Augmentation System
Procedures
Number Title Revision
EPP 06-015 Emergency Response Organization Callout, September 30, 14
2015
Condition Reports
115983 124451
Miscellaneous Documents
Number Title Date
16-Q3 Quarterly Callout Test Conducted September 12, September 13,
2016 2016
16-Q4 Quarterly Callout Test Conducted December 8, December 8,
2016 2016
17-Q1 Quarterly Callout Test Conducted March 28, 2017 March 30,
2017
17-Q2 Quarterly Callout Test Conducted June 27, 2017 June 29, 2017
17-Q3 Quarterly Callout Test Conducted September 6, September 20,
2017 2017
17-Q4 Quarterly Callout Test Conducted November 27, November 29,
2017 2017
18-Q1 Quarterly Callout Test Conducted March 14, 2018 March 14,
2018
18- Q2 Quarterly Callout Test Conducted June 18, 2018 June 21, 2018
71114.05 - Maintenance of Emergency Preparedness
Procedures
Number Title Revision/Date
AP 06-002 Radiological Emergency Response Plan, August 7, 2018 18B
AP 06-004 Equipment Important to Emergency Response, January 18, 8
2018
AP 17C-024 Emergency Planning Responsibilities, September 30, 2015 13
AP 17C-028 Emergency Response Duties and Responsibilities, 15
September 24, 2015
AP 21A-002 Diverse and Flexible Coping Mitigation Strategies Program 3
APF 06-002-01 Emergency Action Levels 17B
EPP 06-009 Drill and Exercise Requirements, January 24, 2017 11
EPP 06-018 Maintenance of Emergency Facilities and Communications 13
Checks, November 29, 2016
EPP 06-021 Training Programs, November 28, 2017 12
EPP 06-023 Emergency Response Facility Functionality, December 16, 3
2015
Tool Kit 010 Dosimeter Annual Calibration (RDDs and PICs) April 13, 2017
Condition Reports
109918 111604 111626 112435 113322
113710 114405 115932 116368 116717
117040 117446 119507 119903 120017
20356 123795 123980 124428 124498
25031 125976
Work Orders
2-352615-000 15-408018-000
Miscellaneous
Number Title Revision/Date
CFR 50.54Q Screenings/Evaluations for AP 06-004, October 16,
Equipment Important to Emergency Preparedness, R7 2017
CFR 50.54Q Screenings/Evaluations for EPP 06-001, July 30, 2018
Control Room Operations, R10
Miscellaneous
Number Title Revision/Date
CFR 50.54Q Screenings/Evaluations for EPP 06-003, October 16,
Emergency Operations Facility Operations, R13 2017
CFR 50.54Q Screenings/Evaluations for EPP 06-007, October 16,
Emergency Notifications, R16 2017
CFR 50.54Q Screenings/Evaluations for EPF 06-018- August 2, 2017
09, Offsite Monitoring Inventory Checklist, R29
CFR 50.54Q Screenings/Evaluations for EPF 06-018- August 2, 2017
2, Emergency Operations Facility Checklist, R30
CFR 50.54Q Screenings/Evaluations for EPP 06-021, November 16,
Training Programs, R19 2017
Annual PMP Checks November 16,
2017
Control Room Inventory Checklist March 13, 2018
Control Room Inventory Checklist October 5, 2017
Emergency Planning Monthly Communications Checklist December 5,
2016
Emergency Planning Monthly Communications Checklist March 21, 2017
Emergency Planning Quarterly Communications February 27,
Checklist 2017
Emergency Planning Quarterly Communications February 28,
Checklist 2018
Emergency Response Facility Functionality Evaluation October 11,
2017
Offsite Medical Emergency Supplies Inventory Checklist December 14,
2016
Offsite Medical Emergency Supplies Inventory Checklist April 23, 2018
Offsite Monitoring Inventory Checklist December 15,
2016
Offsite Monitoring Inventory Checklist March 13, 2018
Offsite Monitoring Inventory Checklist, Post-Exercise March 1, 2018
Technical Support Center Inventory Checklist September 8,
2016
Technical Support Center Inventory Checklist July 21, 2017
Technical Support Center Inventory Checklist October 5, 2017
Miscellaneous
Number Title Revision/Date
Technical Support Center Inventory Checklist, Post- September 25,
Exercise 2017
Topeka Joint Information Clearinghouse Inventory February 16,
Checklist 2017
Topeka Joint Information Clearinghouse Inventory February 28,
Checklist 2018
Topeka Joint Information Clearinghouse Inventory March 30, 2017
Checklist, Post-Exercise
Wolf Creek Joint Information Clearinghouse Inventory March 30, 2017
Checklist
Wolf Creek Joint Information Clearinghouse Inventory February 28,
Checklist 2018
16-SA-02 Evaluation Report for the Exercise Conducted December 14,
December 7, 2016 2016
17-04-EP Quality Assurance Audit Report June 8, 2017
17-EVAL Evaluation Report for the Exercise Conducted December 12,
November 14, 2017 2017
17-PRE-01 Evaluation Report for the Exercise Conducted September 25,
September 19, 2017 2017
17-PRE-02 Evaluation Report for the Exercise Conducted December 12,
October 24, 2017 2017
17-SA-01 Evaluation Report for the Exercise conducted February March 13, 2017
14, 2017
17-SA-01 Evaluation Report for the Exercise Conducted February February 20,
13, 2018 2018
17-SA-02 Evaluation Report for the Exercise Conducted March 14, April 3, 2017
2017
17-SA-02 Evaluation Report for the Exercise Conducted April 18, August 15, 2017
2017
17-SA-02 Evaluation Report for the Exercise Conducted July 18, August 15, 2017
2017
18-05-EP Quality Assurance Audit Report June 20, 2018
18-SA-01 Evaluation Report for the Exercise Conducted
February 27, 2018
CE1235610 Lesson Plan: Offsite Dose Projection using EDCP, 13A
August 14, 2018
Miscellaneous
Number Title Revision/Date
QH-2016-1348 NRC Emergency Preparedness Cornerstone Assessment
QH-2016-1357 ERO Membership Review by Organization October 5, 2016
QH-2017-1426 Monticello 50.54(q) Review March 8, 2017
QH-2017-1427 Monticello ERO Team Change Briefing March 8, 2017
QH-2017-1438 Assessment of Chemistry and RP use within the On Shift March 8, 2017
Staffing Assessment
QH-2017-1464 INPO Drill and Exercise Scenario Seminar Trip Report April 24, 2017
QH-2017-1558 Emergency Planning NRC Inspection Readiness October 5, 2017
QH-2018-1681 Emergency Response Personnel Training Self- June 26, 2018
Assessment
71114.06Drill Evaluation
Procedures
Number Title Revision
EPP 06-006 Protective Action Recommendations 9A
Condition Reports
26171 126183 126184 126185 126186
26189 126190 126192 126193 126195
26197 126198 126199 126200 126201
26202 126203 126204 126205 126206
26207 126208 126210 126212 126213
Miscellaneous Documents
Number Title Revision/Date
18-SA-02 Wolf Creek Generating Station - Emergency Planning Drill August 28,
2018
APF 06-002-01 Emergency Action Levels 17B
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment: August 27 to
2018-309 September 2,
2018
EPF 06-007-01 Wolf Creek Generating Station Emergency Notification - August 28,
Message #: CR-001 2018
Miscellaneous Documents
Number Title Revision/Date
EPF 06-007-01 Wolf Creek Generating Station Emergency Notification - August 28,
Message #: EOF-002 2018
EPF 06-007-01 Wolf Creek Generating Station Emergency Notification - August 28,
Message #: EOF-003 2018
EPF 06-007-01 Wolf Creek Generating Station Emergency Notification - August 28,
Message #: EOF-004 2018
EPF 06-007-01 Wolf Creek Generating Station Emergency Notification - August 28,
Message #: TSC-001 2018
Scenario 16-06 Requalification Exam 1
71124.05Radiation Monitoring Instrumentation
Procedures
Number Title Revision
AI 02E-009 Instructions for Intrinsic Germanium Detector Energy 13A
Calibration
AI 02E-010 Instructions for IG Detector Efficiency Calibration 7A
AI 03-008 Control Chart Development, Use and Review Using Lab 6
Stats
AP 02-008 Verification of Analytical Performance 14
AP 02E-001 Chemistry Calibration Program 36
AP 23-006 System Engineering Program 27A
AP 25A-001 Radiation Protection Manual 18
RPP 01-405 HP Instrument Program 34
RPP 03-407 Testing of Portal Monitors as Passive Whole Body Counters 1A
RPP 05-306 PM12 Operation 6
RPP 05-707 Operation of Whole Body Counters 9
RPP 06-103 Ludlum 9-4 Calibration 0
RPP 06-113 MGP Telepole Calibration 3
RPP 06-222 Escort Elf Calibration 2
RPP 06-306 PM12 Calibration 9
RPP 06-315 Eberline PCM-1B Calibration 10
RPP 06-317 Eberline PCM-2 Calibration 5
Procedures
Number Title Revision
RPP 06-319 SAM11 Calibration 1
RPP 06-707 Calibration of WBC Detectors Using Ortec Renaissance 4
Software
RPP 06-715 Whole Body Counter Quality Control 9
RPP 06-825 J. L. Shephard Multi-Source Calibration System Operation 8A
STS IC-452B Channel Calibration New Fuel Storage Facility Criticality 4A
Monitor SDRE-0035
STS IC-454B Channel Calibration Spent Fuel Pool Criticality Monitor Area 11
Radiation Monitor SDRE-0038
STS SP-292 Channel Calibration of Condenser Air Discharge Monitor GE 3
RE-0092
Audits, Self-Assessments, and Surveillances
Number Title Date
18-01-RP/PC Quality Assurance Audit Report: Radiation Protection and February 15,
Process Control (RP & PC) 2018
QA-2017-0387 Quality Assessment: Radiation Protection (RP) Equipment December 29,
Calibration Controls 2017
Condition Reports
107189 107190 107191 107193 113038
113556 116717 118252 118867 120567
20963 121150
Miscellaneous Documents
Number Title Revision/Date
System Health Report: Radiation Monitoring January 1,
2018, through
June 30, 2018
10066 WBC Calibration Certificate GI Detector
10066 WBC Calibration Certificate Lung Detector
10066 WBC Calibration Certificate Thyroid Detector
10178 Telepole
242 PCM-2
Miscellaneous Documents
Number Title Revision/Date
256 ASP-1
257 ASP-1
11005 SAM 11
11075 Shepherd Calibrator
11377 PCM-1B
11451 Radeco H809V-1
13027 WBC Calibration Certificate Lower Detectors
13027 WBC Calibration Certificate Upper/Lower Detectors
217 Ludlum 9-4
219 Ludlum 9-4
2160566 Liquid Scintillator
Chapter 11 Updated Safety Analysis Report: Radioactive Waste 29
Management
WO 16-427623- Minor Maintenance Containment Atmospheric Radiation November 15,
001 Monitor GTRE0032 2016
WO 16-427623- Routine Maintenance Containment Purge Exhaust November 15,
003 Radiation Monitor GTRE0033 2016
WO 18-42244 Channel Calibration High Range Area Radiation Monitor
GTRE60
WO 18-422785 Channel Calibration High Range Area Monitor GTRE-0059
WO 18-422892 Channel Calibration High Range Area Radiation Monitor
GTRE59
WO 18-422893 Channel Calibration High Range Area Radiation Monitor
GTRE60
WO 18-434709 Channel Calibration of Condenser Air Discharge Monitor
GE RE-0092
71124.06Radioactive Gaseous and Liquid Effluent Treatment
Procedures
Number Title Revision
AP 02E-001 Chemistry Calibration Program 38
AP 07B-003 Offsite Dose Calculation Manual 9
CHS AC-001 Accident Sampling 4C
Procedures
Number Title Revision
CHS AX-G01 Unit Vent Sampling and/or Exchange of Filters 10
STN BM-054 Steam Generator Blowdown System Surge Tank Discharge 7C
Flow to Lake Channel Calibration
STN CH-021 Calibration of the Particulate Detector for Radiation Monitors 5
GTRE21A and GHRE10A
STN CH-022 Calibration of the Iodine Detector for Radiation Monitors 2
GTRE21A and GHRE10A
STN HB-1085 Liquid Radwaste System Discharge Line Flow Rate 5
Calibration
STN SP-118 Channel Calibration Liquid Radwaste Discharge Radiation 9
Monitor HB RE-0018
STN SP-195 Channel Calibration Hi/Lo TDS Discharge to Waste Water 7
Treatment Radiation Monitor HF RE-0095
STS CH-014 Calibration of Monitors GT RE-21B and GH RE-10B 13
STS PE-002 Charcoal Adsorbent Sampling for Nuclear Safety Related 15
Units
STS PE-006 Charcoal Adsorber In-Place Leak Test Safety Related Units 16
Audits and Self-Assessments
Number Title Date
18-03-ENV QA Audit: Environmental Management April 17, 2018
Condition Reports
107421 107983 108892 111266 112928
113578 113944 116717 118486 123726
26072
Effluent Release Permits
Permit Number Type Release System Date
U1GB2018-111 Gas Containment Purge August 12, 2018
U1GC2018-110 Gas Radwaste Vent August 9, 2018
U1LB2018-067 Liquid THF04A July 14, 2018
U1LC2018-065 Liquid Steam Generator Blowdown July 3, 2018
Calibrations and Surveillances
Work Order System Date
GH-RE-10A March 20, 2018
GH-RE-10B December 13,
2016
GT-RE-21A February 19,
2018
GT-RE-21B October 3, 2017
16-418841-000 BM-054 March 2, 2017
17-421198-000 HF RE-0095 June 26, 2017
17-423608-000 HB-RE-0018 July 18, 2017
17-431311-000 FGG02B January 9, 2018
17-433703-000 FGG02A June 18, 2018
18-435515-000 HB-1085 August 13, 2018
Miscellaneous Documents
Number Title Date
15-CHL-008 Certificate of Calibration- Standard Reference Source July 1, 2015
101145
Simulated Gas in 130G GA-MA Gas Beaker
16-CHL-005 Certificate of Calibration- Standard Reference Source January 1, 2016
2600
47mm Diameter Simulated Filter in Snap Falcon Petri
2016 Annual Radioactive Effluent Release Report April 25, 2017
2017 Annual Radioactive Effluent Release Report April 25, 2018
71124.07Radiological Environmental Monitoring Program
Procedures
Number Title Revision
AI 07-007 Onsite Groundwater Protection Program Monitoring 17
AI 07B-002 Review of Radiological Environmental Lab Analysis 12
AI 07B-009 Collection, Prep, and Shipment of Sediment 10
AI 07B-011 Collection, Prep, and Ship of Water 17
AI 07B-015 Land Use Census 12
Procedures
Number Title Revision
AI 07B-034 Radiological Environmental Monitoring Program Air 15
Sampling
AI 07B-035 REMP OSL Dosimeters 8
AP 07B-005 Ground Water Protection Program 4
STS IC-890A Wind Speed Meteorological Instrumentation Channel 18
Calibration
STS IC-890D Sonic Wind-Direction-Deviation Meteorological 3
Instrumentation Channel Calibration
Audits, Self-Assessments, and Surveillances
Number Title Date
28 Evaluation Report (NUPIC) of ATI Environmental, Inc. June 16, 2017
4059 Evaluation Report (NUPIC) of Landauer (4059) June 16, 2017
Audit 18-03 Quality Assurance Audit Report, Environmental March 29,
Management: K15-002 2018
QH-2017-1456 AI 07B-034, Radiological Environmental Monitoring March 30,
Program Air Sampling 2018
QH-2017-1456 Radiological Environmental Monitoring Program (REMP) April 24, 2017
contracted services per AI 07B-005, Section 6.12
QH-2018-1391 Review of the KDHE REMP Report December 6,
2016
QH-2018-1684 REMP Review of 2015 through 2017 Wind Directions June 7, 2018
Condition Reports
101560 106475 115681 118440
Calibrations and Surveillances
Number Title Date
3302 Digital Venturi Calibrator March 7, 2017
3302 Digital Venturi Calibrator March 13,
2018
W0 17-432379 Channel Calibration Sonic Wind Speed April 20, 2018
W0 17-432382 Channel Calibration Wind Direction March 26,
2018
Calibrations and Surveillances
Number Title Date
W0 17-432417 Channel Calibration Wind Speed Meteorological March 26,
Instrumentation 2018
Miscellaneous Documents
Number Title Revision/Date
Environmental Resources Management: Risk Assessment August 20,
for Systems, Structures, and Components, Groundwater 2008
Protection Initiative, Wolf Creek
Review of Radiological Environmental Lab Analysis 12
Results
Technical Requirements Manual 25
Wolf Creek Generating Station Power Block - Ground
Water Monitoring Network
2008 Preliminary Hydrology Study, Wolf Creek Generating December 18,
Station, Environmental Resources Management 2007
2009 Coffey County Lake - Ground Water Monitoring Network October 9,
Documentation Report, Delta Consultants 2009
2016 Annual Radioactive Effluent Release Report April 25, 2017
2016 Annual Radiological Environmental Operating Report April 24, 2017
2017 Annual Radioactive Effluent Release Report April 25, 2018
2017 Annual Radiological Environmental Operating Report April 25, 2018
2018 Digital Flow Meter Calibration Verification, AIF 07B-034-01 1
71124.08Radioactive Solid Waste Processing, and Radioactive Material Handling, Storage,
and Transportation
Procedures
Number Title Revision
AP 31A-100 Solid Radwaste Process Control Program 8
HW1215801 Regulations and Requirements 12A
HW1215802 Regulatory Awareness for Hazardous Material Handlers 0
HW8115901 Wolf Creek Hazardous Material Transportation Security 4
Plan
RPP 07-110 Solid Radwaste Packaging 10
Procedures
Number Title Revision
RPP 07-112 Processing Cartridge Filters 5
RPP 07-123 Preparation and Shipment of Radioactive Waste and 8
Material
RPP 07-131 Bead Resin/Activated Carbon Dewatering Procedure For 5
Energy Solutions14-215 or Smaller Liners, Utilizing
Energy Solutions Self-Engaging Dewatering System
Audits and Self-Assessments
Number Title Date
18-01-RP/PC Quality Assurance Audit Report: Radiation Protection and February 15,
Process Control (RP & PC) 2018
Condition Reports
2184 97750 97752 110270 113038
114455 119333 119745 119751 119765
119766 120567
Radioactive Material and Waste Shipments
Number Type Title Date
16R02 Dry Active UN2912, Radioactive Material, LSA-I, 7, A(U) February 9, 2016
Waste
16R15 Resins UN3321, Radioactive Material, LSA-II, 7, A(U) May 18, 2016
16R16 Filters; UN3321, Radioactive Material, LSA-II, 7, C June 1, 2016
Resin
16R32 Dry Active UN3321, Radioactive Material, LSA-II, 7, A(U) September 15,
Waste 2016
16R59 Resin UN3321, Radioactive Material, LSA-II, 7, RQ, B October 14, 2016
16R64 Resin UN3321, Radioactive Material, LSA-II, 7, A(U) October 23, 2016
17R04 Dry Active UN2912, Radioactive Material, LSA-I, 7, A(U) February 16, 2017
Waste
17R14 Dry Active UN3321, Radioactive Material, LSA-II, 7, A(U) May 24, 2017
Waste
17R15 Resin UN3321, Radioactive Material, LSA-II, 7, A(U) June 22, 2017
Radioactive Material and Waste Shipments
Number Type Title Date
17R17 Dry Active UN2912, Radioactive Material, LSA-I, 7, A(U) July 12, 2017
Waste
17R31 Dry Active UN3321, Radioactive Material, LSA-II, 7, A(U) September 18,
Waste; 2017
Resin
Waste Stream Analysis - Nuclide Distribution Reports
Number Title Date
29898001 Cation Resin July 17, 2017
29998002 BTRS Resin August 2, 2017
446223001 RCS Filters March 1, 2018
446223002 SFP Filters February 28, 2018
446223003 Dry Active Waste March 12, 2018
447547001 CVCS Resins March 27, 2018
447769002 Drum Dryer Waste Tank March 31, 2018
Radiological Surveys
Number Title Date
M-20180321-11 High Level Radwaste Storage March 21, 2018
M-20180326-10 Low Level Radwaste Storage March 26, 2018
M-20180523-9 RCA Yard May 23, 2018
M-20180611-3 Owens Corning June 11, 2018
M-20180721-1 New Radwaste Building July 21, 2018
M-20180728-7 RCA Yard July 28, 2018
Miscellaneous Documents
Number Title Revision/Date
2016 Annual Radioactive Effluent Release Report April 25, 2017
2017 Annual Radioactive Effluent Release Report April 25, 2018
Spent Fuel Pool Inventory: Tri-Nuke Filters August 23, 2018
Miscellaneous Documents
Number Title Revision/Date
Wolf Creek Updated Safety Analysis Report - Chapter 30
11.4 and Chapter 12.2.1
RPF 07-123-01 Radioactive Shipment Log: 2016, 2017, 2018
71151Performance Indicator Verification
Procedures
Number Title Revision
AI 26A-004 Emergency Planning Performance Indicators, May 2, 2016 8
AP 26A-001 Reportable Events, Evaluation and Documentation, July 24, 20
2014
AP 34-003 Performance Indicator Program, August 17, 2010 0
EPP 06-005 Emergency Classification, February 23, 2016 8
EPP 06-006 Protective Action Recommendations, December 14, 2017 9A
EPP 06-007 Emergency Notifications, October 18, 2017 25
EPP 06-019 Alert and Notification System Sirens, October 2, 2016 9A
Condition Reports
110999 116997 118425 119906 120323
26201 127496 127526
Miscellaneous Documents
Number Title Revision/Date
MSPI Derivation Report - MSPI System: MSPI Cooling August 2018
Water System; MSPI Element: Performance Limit Exceeded
(PLE)
MSPI Derivation Report - MSPI System: MSPI Cooling August 2018
Water System; MSPI Element: Unavailability Index (UAI)
MSPI Derivation Report - MSPI System: MSPI Cooling August 2018
Water System; MSPI Element: Unreliability Index (URI)
MSPI Derivation Report - MSPI System: MSPI Emergency August 2018
AC Power System; MSPI Element: Performance Limit
Exceeded (PLE)
MSPI Derivation Report - MSPI System: MSPI Emergency August 2018
AC Power System; MSPI Element: Unavailability Index
(UAI)
Miscellaneous Documents
Number Title Revision/Date
MSPI Derivation Report - MSPI System: MSPI Emergency August 2018
AC Power System; MSPI Element: Unreliability Index (URI)
MSPI Derivation Report - MSPI System: MSPI High August 2018
Pressure Injection System; MSPI Element: Performance
Limit Exceeded (PLE)
MSPI Derivation Report - MSPI System: MSPI High August 2018
Pressure Injection System; MSPI Element: Unavailability
Index (UAI)
MSPI Derivation Report - MSPI System: MSPI High August 2018
Pressure Injection System; MSPI Element: Unreliability
Index (URI)
MSPI Unavailability for Chemical & Volume Control System Printed
BG-07A September 11,
2018
MSPI Unavailability for Chemical & Volume Control System Printed
BG-07B September 11,
2018
MSPI Unavailability for Component Cooling Water System Printed
EG-01A September 11,
2018
MSPI Unavailability for Component Cooling Water System Printed
EG-01B September 11,
2018
MSPI Unavailability for Essential Service Water EF-01A Printed
September 11,
2018
MSPI Unavailability for Essential Service Water EF-01B Printed
September 11,
2018
MSPI Unavailability for High Pressure Coolant Injection Printed
System EM-01A September 11,
2018
MSPI Unavailability for High Pressure Coolant Injection Printed
System EM-01B September 11,
2018
MSPI Unavailability for Standby Diesel Engine System KJ- Printed
01A September 11,
2018
Miscellaneous Documents
Number Title Revision/Date
MSPI Unavailability for Standby Diesel Engine System KJ- Printed
01B September 11,
2018
Unavailability Data July 2017
through June
2018
Unreliability Data July 2017
through June
2018
EDI 23M-050 Engineering Desktop Instruction Monitoring Performance to May 17, 2017
Criteria and Goals - System: BG - 112594
EDI 23M-050 Engineering Desktop Instruction Monitoring Performance to February 12,
Criteria and Goals - System: BG - CR 118860 2018
EDI 23M-050 Engineering Desktop Instruction Monitoring Performance to May 3, 2018
Criteria and Goals - System: BG - CR 121938
EDI 23M-050 Engineering Desktop Instruction Monitoring Performance to May 16, 2018
Criteria and Goals - System: BG - CR 122610
EDI 23M-050 Engineering Desktop Instruction Monitoring Performance to August 9,
Criteria and Goals - System: EF - CR 125201 2018
EDI 23M-050 Engineering Desktop Instruction Monitoring Performance to December 5,
Criteria and Goals - System: EG - CR 120591 2017
EDI 23M-050 Engineering Desktop Instruction Monitoring Performance to May 17, 2017
Criteria and Goals - System: EM - CR 112588
EDI 23M-050 Engineering Desktop Instruction Monitoring Performance to May 17, 2017
Criteria and Goals - System: EM - CR 112594
EDI 23M-050 Engineering Desktop Instruction Monitoring Performance to April 27, 2017
Criteria and Goals - System: KJ - CR 112131
EDI 23M-050 Engineering Desktop Instruction Monitoring Performance to October 1,
Criteria and Goals - System: KJ - CR 115725 2017
EDI 23M-050 Engineering Desktop Instruction Monitoring Performance to December 5,
Criteria and Goals - System: KJ - CR 117441 2017
EDI 23M-050 Engineering Desktop Instruction Monitoring Performance to September 5,
Criteria and Goals - System: NB - CR 126025 2018
EDI 23M-050 Engineering Desktop Instruction Monitoring Performance to October 1,
Criteria and Goals - System: NG - CR 115725 2017
WCNOC-163 NEI 99-02 Reactor Oversight Process Performance 12
Indicators - Mitigating System Performance Index (MSPI)
Basis Document
Miscellaneous Documents
Number Title Revision/Date
WCRE-34 Fourth Ten Year Interval Inservice Testing Bases Document 3
71152Problem Identification and Resolution
Procedures
Number Title Revision
AP 10-104 Breach Authorization 35
AP 10-104 Breach Authorization 37A
AP 15C-002 Procedure Use and Adherence 43
AP 23-009 Control Room Envelope Habitability Program 2
STS PE-004 Aux Building and Control Room Pressure Test 16
SYS AE-150 Main Feedwater Pump Reset 2
SYS AE-150 Main Feedwater Pump Reset 3
SYS GK-122 Manual CRVIS Line-Up 24
Drawings
Number Title Revision
M-12GG01 Piping & Instrumentation Diagram Fuel Building HVAC 8
M-12GL02 Piping & Instrumentation Diagram Auxiliary Building HVAC 17
M-12GT01 Piping & Instrumentation Diagram Containment Purge 29
Systems HVAC
M-1H1531 Heating Ventilating and Air Cond. Auxiliary Building El. 5
2047-6 Area-3
Condition Reports
29602 61246 90956 90975 110377
119330 120056 120151 122180 123289
Work Orders
2-355727-011 15-397077-000 17-421482-000 17-421482-001 17-423496-000
17-428518-000 17-428518-001 18-437033-006
Miscellaneous Documents
Number Title Revision/Date
U.S. Nuclear Regulatory Commission Regulatory 1
Guide 1.117: Tornado Design Classification
AIF 10-001-02 SCBA Inspection [3.2.1] Completed
March 1, 2018
AIF 28A-100-12 Wolf Creek Generating Station Basic Cause Evaluation - February 20,
CR 90975 2015
AIF 28A-100-12 Wolf Creek Generating Station Basic Cause Evaluation - April 5, 2018
CR 120056
APF 29B-003-01 Surveillance Test Routing Sheet (STRS) - Aux Building and Completed
Control Room Pressure Test - Train A - STS PE-004 March 15,
2018
APF 29B-003-01 Surveillance Test Routing Sheet (STRS) - Aux Building and Completed
Control Room Pressure Test - Train B - STS PE-004 March 7, 2018
APF 29B-003-01 Surveillance Test Routing Sheet (STRS) - Aux Building and Completed
Control Room Pressure Test - Train B - STS PE-004 March 15,
2018
CR 120056 Evidence and Action Matrix B CRVIS Pressure Issue March 5, 2018
K01-048 03146 Material Safety Data Sheet: Ventilation Smoke Tube - P/N
458480
WCRE Boundary Matrix 0
WCRE-35 Boundary Matrix 3
The following items are requested for the
Public Radiation Safety Inspection
at Wolf Creek
Dates of Inspection: August 20, 2018 to August 23, 2018
Integrated Report 2018003
Inspection areas are listed in the attachments below.
Please provide the requested information on or before August 6, 2018.
Please submit this information using the same lettering system as below. For example, all
contacts and phone numbers for Inspection Procedure 71124.05 should be in a file/folder titled
5- A, applicable organization charts in file/folder 5- B, etc.
If information is placed on ims.certrec.com, please ensure the inspection exit date entered is at
least 30 days later than the onsite inspection dates, so the inspectors will have access to the
information while writing the report.
In addition to the corrective action document lists provided for each inspection procedure listed
below, please provide updated lists of corrective action documents at the entrance meeting.
The dates for these lists should range from the end dates of the original lists to the day of the
entrance meeting.
If more than one inspection procedure is to be conducted and the information requests appear
to be redundant, there is no need to provide duplicate copies. Enter a note explaining in which
file the information can be found.
If you have any questions or comments, please contact Louis Carson at (817) 200-1221 or
Louis.Carson@nrc.gov.
PAPERWORK REDUCTION ACT STATEMENT
This letter does not contain new or amended information collection requirements subject
to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information
collection requirements were approved by the Office of Management and Budget,
control number 3150-0011.
5. Radiation Monitoring Instrumentation (71124.05)
Date of Last Inspection: May 23, 2016
A. List of contacts and telephone numbers for the following areas:
1. Effluent monitor calibration
2. Radiation protection instrument calibration
3. Installed instrument calibrations
4. Count room and Laboratory instrument calibrations
B. Applicable organization charts
- C. Copies of audits, self-assessments, vendor or NUPIC audits for contractor support and
LERs, performed since the date of the last inspection related to:
1. Area radiation monitors, continuous air monitors, criticality monitors, portable survey
instruments, electronic dosimeters, teledosimetry, personnel contamination monitors,
or whole body counters
2. Installed radiation monitors
D. Procedure index for:
1. Calibration, use, and operation of continuous air monitors, criticality monitors,
portable survey instruments, temporary area radiation monitors, electronic
dosimeters, teledosimetry, personnel contamination monitors, and whole body
counters.
2. Calibration of installed radiation monitors
E. Please provide specific procedures related to the following areas noted below.
Additional procedures may be requested by number after the inspector reviews the
procedure index.
1. Calibration of portable ion chambers
2. Whole body counter calibration
3. Laboratory instrumentation quality control
F. A summary list of corrective action documents (including corporate and sub-tiered
systems) written since the date of the last inspection, related to the following programs:
1. Area radiation monitors, continuous air monitors, criticality monitors, portable survey
instruments, electronic dosimeters, teledosimetry, personnel contamination monitors,
whole body counters
2. Installed radiation monitors
3. Count room radiation instruments
NOTE: The lists should indicate the significance level of each issue and the search
criteria used. Please provide in document formats which are searchable so that
the inspector can perform word searches.
G. Most recent calibration data for the whole body counters.
H. Radiation Monitoring System health report for the previous 12 months
6. Radioactive Gaseous and Liquid Effluent Treatment (71124.06)
Date of Last Inspection: May 23, 2016
A. List of contacts and telephone numbers for the following areas:
1. Radiological effluent control
2. Engineered safety feature air cleaning systems
B. Applicable organization charts
written since the date of the last inspection, related to:
1. Radioactive effluents
2. Engineered Safety Feature Air cleaning systems
D. Procedure indexes for the following areas
1. Radioactive effluents
2. Engineered Safety Feature Air cleaning systems
E. Please provide specific procedures related to the following areas noted below.
Additional procedures may be requested by number after the inspector reviews the
procedure indexes.
1. Sampling of radioactive effluents
2. Effluent monitor setpoint determination
3. Generating radioactive effluent release permits
4. Laboratory instrumentation quality control
5. In-place testing of HEPA filters and charcoal adsorbers
F. List of corrective action documents (including corporate and sub-tiered systems) written
since the date of the last inspection, associated with:
1. Radioactive effluents
2. Effluent radiation monitors
3. Engineered Safety Feature Air cleaning systems
NOTE: The lists should indicate the significance level of each issue and the search
criteria used. Please provide in document formats which are searchable so that
the inspector can perform word searches.
two most recent reports.
H. Current revision of the Offsite Dose Calculation Manual
I. The 2016 and 2017 inter-laboratory comparison results for laboratory quality control
performance of effluent sample analysis, or the two most recent results.
J. Effluent sampling schedule for the week of the inspection
K. New entries into 10 CFR 50.75(g) files since the date of the last inspection
L. Operations department (or other responsible dept.) log records for effluent monitors
removed from service or out of service
M. Listing or log of liquid and gaseous release permits since the date of the last inspection
N. A list of the technical specification-required air cleaning systems with the two most
recent surveillance test dates of in-place filter testing (of HEPA filters and charcoal
adsorbers) and laboratory testing (of charcoal efficiency) and the work order numbers
associated with the surveillances
- O. System Health Report for radiation monitoring instrumentation. Also, please provide a
specific list of all effluent radiation monitors that were considered inoperable for 7 days
or more since the date of the last inspection. If applicable, please provide the relative
Special Report and condition report(s).
P. A list of significant changes made to the gaseous and liquid effluent process monitoring
system since the date of the last inspection. If applicable, please provide the
corresponding UFSAR section in which this change was documented.
Q. A list of any occurrence in which a non-radioactive system was contaminated by a
radioactive system since the date of the last inspection. Please include any relevant
condition report(s).
7. Radiological Environmental Monitoring Program (71124.07)
Date of Last Inspection: May 23, 2016
A. List of contacts and telephone numbers for the following areas:
1. Radiological environmental monitoring
2. Meteorological monitoring
B. Applicable organization charts
written since the date of the last inspection, related to:
1. Radiological environmental monitoring program (including contractor environmental
laboratory audits, if used to perform environmental program functions)
2. Environmental TLD processing facility
3. Meteorological monitoring program
D. Procedure index for the following areas:
1. Radiological environmental monitoring program
2. Meteorological monitoring program
E. Please provide specific procedures related to the following areas noted below.
Additional procedures may be requested by number after the inspector reviews the
procedure indexes.
1. Sampling, collection and preparation of environmental samples
2. Sample analysis (if performed onsite)
3. Laboratory instrumentation quality control
F. A summary list of corrective action documents (including corporate and sub-tiered
systems) written since the date of the last inspection, related to the following programs:
1. Radiological environmental monitoring
2. Meteorological monitoring
NOTE: The lists should indicate the significance level of each issue and the search
criteria used. Please provide in document formats which are searchable so that
the inspector can perform word searches.
G. Copies of the two most recent calibration packages for the meteorological tower
instruments
H. Copies of the 2016 and 2017 Annual Radiological Environmental Operating Reports and
Land Use Census, and current revision of the Offsite Dose Calculation Manual.
I. Copy of the environmental laboratorys inter-laboratory comparison program results for
2016 and 2017, or the two most recent results, if not included in the annual radiological
environmental operating report
J. Data from the environmental laboratory documenting the analytical detection sensitivities
for the various environmental sample media (i.e., air, water, soil, vegetation, and milk)
- K. Quality Assurance audits (e.g., NUPIC) for contracted services
L. Current NEI Groundwater Initiative Plan and status
M. Technical requirements manual or licensee controlled specifications which list the
meteorological instruments calibration requirements
- N. If applicable, per NEI 07-07, provide any reports that document any spills/leaks to
groundwater since the date of the last inspection.
8. Radioactive Solid Waste Processing, and Radioactive Material Handling, Storage,
and Transportation (71124.08)
Date of Last Inspection: May 23, 2016
A. List of contacts and telephone numbers for the following areas:
1. Solid Radioactive waste processing
2. Transportation of radioactive material/waste
B. Applicable organization charts (and list of personnel involved in solid radwaste
processing, transferring, and transportation of radioactive waste/materials)
- C. Copies of audits, department self-assessments, and LERs written since the date of the
last inspection related to:
1. Solid radioactive waste management
2. Radioactive material/waste transportation program
D. Procedure index for the following areas:
1. Solid radioactive waste management
2. Radioactive material/waste transportation
E. Please provide specific procedures related to the following areas noted below.
Additional procedures may be requested by number after the inspector reviews the
procedure indexes.
2. Solid and liquid radioactive waste processing
3. Radioactive material/waste shipping
4. Waste stream sampling and analysis
F. A summary list of corrective action documents (including corporate and sub-tiered
systems) written since the date of the last inspection, related to:
1. Solid radioactive waste
2. Transportation of radioactive material/waste
NOTE: The lists should indicate the significance level of each issue and the search
criteria used. Please provide in document formats which are searchable so that
the inspector can perform word searches.
- G. Copies of training lesson plans for 49 CFR 172 subpart H, for radwaste processing,
packaging, and shipping.
H. A summary of radioactive material and radioactive waste shipments made from the date
of the last inspection, to present
or the two most recent results.
J. A listing of onsite radwaste storage facilities. Please include a summary or list of the
items stored in each facility.
SUNSI Review ADAMS: Non-Publicly Available Non-Sensitive Keyword:
By: NHT Yes No Publicly Available Sensitive NRC-002
OFFICE SRI:DRP/B RI: DRP/B C:DRS/OB C:DRS/PSB2 C:DRS/EB1 C:DRS/EB2
NAME DDodson FThomas VGaddy HGepford TFarnholtz GWerner
SIGNATURE DED FDT vgg hjg TRF GEW
DATE 10/31/18 10/30/18 10/22/18 10/22/18 10/22/2018 10/22/2018
OFFICE BC:DRP/B
NAME NTaylor
SIGNATURE NHT
DATE 11/7/2018