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
November 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
Enclosure
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number:
05000482
License Number:
Report Number:
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
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 Systems Green NCV 05000482/2018003-01 Closed H.14 - Human Performance,
Conservative Bias 71152 -
Problem 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 Applicable Severity Level IV NCV 05000482/2018003-02 Closed Not Applicable 71152 -
Problem 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 NCV 05000482/2018003-01 Closed H.14 - Human Performance, Conservative Bias
71152 - Problem
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.
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 NCV 05000482/2018003-02 Closed Not Applicable
71152 - Problem
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.
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
STS PE-049E
Train A Essential Service Water System in Vaults Pressure
Test
Drawings
Number
Title
Revision
10466-A-1330
Access Control Floor Plan, El. 1984-0
C-1C3902
Control Building Area 1 Concrete Neat Lines and
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
Details Sht. 1
C-K208
E.S.
- W.S. Yard Pipeline Valve House Plans, Sections, and
Details Sht. 1
Condition Reports
21699
24381
24382
24383
24397
24409
24988
25177
25196
25197
26267
26345
Miscellaneous Documents
Number
Title
Revision
014592
Field Change Notice - Change Package Title: ESW Below
Ground Plant Tie-In Approval and Component Abandonment
Miscellaneous Documents
Number
Title
Revision
014592
Field Change Notice - Change Package Title: ESW Below
Ground Plant Tie-In Approval and Component Abandonment
10466-C107-1
Bechtel: Technical Specification for Purchase of Waterstops
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
Approval and Component Abandonment - Package
- 014592
APF 05-002-05
Engineering Disposition: ESW Below Ground Plant Tie-In
Approval and Component Abandonment - Package
- 014592
APF 05-007-01
Safety Classification Analysis - Change Package #013503
71111.04Equipment Alignment
Procedures
Number
Title
Revision
AI 15C-006
Management Oversight Requirements for Infrequently
Performed and Potentially Degrading Evolutions
Control of Locked Component Status
Operability Determination and Functionality Assessment
CKL AL-120
Auxiliary Feedwater Normal Lineup
CKL BG-120
Chemical and Volume Control System Normal Valve Lineup 41
CKL BG-130
Chemical and Volume Control System Switch and Breaker
Lineup
31A
CKL EM-120
Safety Injection System Lineup Checklists
CKL KJ-121
Diesel Generator NE01 and NE02 Valve Checklist
40B
MGM MOOP-01
Relief Valve Bench Testing
Slave Relay Test K645 Train A Containment Spray
SYS NB-200
Transferring XNB01 Supply Between SL7 and #7
Transformer
SYS NP-201
Transferring NB01 Power Sources
Drawings
Number
Title
Revision
E-1001
Single Line Diagram Site Area Loads
E-11001
Main Single Line Diagram
E-11005
List of Loads Supplied by Emergency Diesel Generator
E-11010
DC Main Single Line Diagram
E-11010A
DC Main Single Line Diagram (PK03 and PK04 BUS)
E-12KJ01
Standby Generation Engine and Governor Control Logic
Diagram
E-12NE01
Standby Generation Excitation Control Logic Diagram
E-12NE02
Logic Diagram Standby Gen. System Protection
E-K1001
Single Line Diagram Essential Service Water System
KD-7496
One Line Diagram
KD-7496
One Line Diagram
KD-7750
Wolf Creek Substation General Plan
M-12AL01
Piping & Instrumentation Diagram Auxiliary Feedwater
System
M-12AP01
Piping & Instrumentation Diagram Condensate Storage and
Transfer System
M-12BG03
Piping and Instrumentation Diagram Chemical & Volume
Control System
M-12EJ01
Piping and Instrumentation Diagram Residual Heat
Removal System
M-12EM01
Piping & Instrumentation Diagram High Pressure Coolant
Injection System
M-12EM01
Piping & Instrumentation Diagram High Pressure Coolant
Injection System
M-12EM02
Piping & Instrumentation Diagram High Pressure Coolant
Injection System
M-12EM03
Piping & Instrumentation Diagram High Pressure Coolant
Injection System Test Line
M-12KJ04
Piping & Instrumentation Diagram, Standby Diesel
Generator B, Cooling Water System
M-12KJ05
Piping & Instrumentation Diagram, Standby Diesel
Generator B, Intake Exhaust, F.O. & Start Air Sys.
Drawings
Number
Title
Revision
M-12KJ06
Piping & Instrumentation Diagram, Standby Diesel
Generator B, Lube Oil System
M-724-00323
Crosby Valve & Gage Co. Drawing DS-C-60705, Titled -
Nozzle Type Relief Valve
W05
Condition Reports
25096
25097
25253
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,
SY124 Cable PMT
August 20,
2018
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment:
Schedule Week 2018-308
August 20 to
26, 2018
M-724-00811
Installation, Operation and Maintenance Instructions for
Anderson Greenwood Crosby Style Pressure Relief Valves
W01
71111.05AQFire Protection Annual/Quarterly
Procedures
Number
Title
Revision
AP 10-105
Fire Protection Training and Drills
AP 10-105
Fire Protection Training and Drills
AP 10-106
Fire Preplans
18A
AP 10-107
Fire Event Investigation and Reporting
OFN KC-016
Fire Response
Condition Reports
25027
25028
25752
26417
26418
26419
26517
26518
26527
26528
26529
26530
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
SRO/RO/BOP Review: Day Shift
September 7,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review: Night Shift
September 7,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review: Night Shift
September 8,
2018
APF 30E-003-02 Training Attendance
September 10,
2018
E1F9905
Fire Hazard Analysis
EPF 06-007-01
Wolf Creek Generating Station Emergency Notification
FL1224000
Fire Brigade Leader/Incident Commander
No. 18
Coffey County Emergency Management Office Contingency
Plan Implementing Procedure
OBSR 2018-
27
Observation Card: Fire Protection - Fire Brigade Drill
August 10,
2018
XX-X-004
Combustible Fire Loading For Each Room in the Various
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
C-K210
ESWS Yard Pipelines and Elect. Duct Banks Sections and
Details
C-K212
E.S.W.S. Yard Pipelines and Elec. Duct Banks Plan and
Sections
C-K212
E.S.W.S. Yard Pipelines and Elec. Duct Banks Plan and
Sections
E-KR0231
Raceway Plot Plan Essential Service Water System Plan
and Sections
E-KR0231
Raceway Plot Plan Essential Service Water System Plan
and Sections
71111.11Licensed Operator Requalification Program and Licensed Operator Performance
Procedures
Number
Title
Revision
AI 21-016
Operator Time Critical Actions Validation
AI 30B-005
Conduct of Simulator Activities for Licensed Operator
Training
AI 30B-15
Licensed Operator Requalification Exam Guidelines
AI 30C-001
Continued Assurance of Simulator Fidelity
AI 30C-004
Simulator Real Time Capacity Testing
5B
AI 30C-005
Simulator Steady State Testing
9A
AI 30C-006
Simulator Transient Testing
AI 30C-007
Simulator Core Testing
AI 30C-008
Scenario Based Testing
2A
AI 30E-13
Written and Oral Examinations
26A
AI 30E-15
Just in Time Training
AI 30E-23
Remediation
Licensed Operator Requalification Training Program
GEN 00-004
Power Operation
Power Range Adjustment to Calorimetric
SYS MA-200
Placing the Switchyard in a Ring Bus Configuration
Drawings
Number
Title
Revision
KD-7496
One Line Diagram
Condition Reports
105145
105841
2616
114281
115643
116660
117338
117340
117341
117414
117619
20012
20582
23951
Miscellaneous Documents
Number
Title
Revision/Date
Rose Hill Line Return to 100%
August 17,
2018
Ops Requal Walk-through Exam Prep Checklist
Simulator Examination Preparation Checklist
Simulator Security Checklist
Sequestering Checklist
Simulator Setup Checklist
JPM Exam Simulator Setup Checklist
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review: Day Shift
August 16,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review: Night Shift
August 16,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review: Night Shift
August 17,
2018
APF 29B-003-01 Surveillance Test Routing Sheet: STS SE-001
Completed
August 17,
2018
2018 Exam -Week 2
June 2018
Remediation
Plan
February 2017
February 2017
Remediation
Plan
February 2018
February 2018
Remediation
Plan
January 2017
January 2017
Miscellaneous Documents
Number
Title
Revision/Date
Remediation
Plan
March 2018
March 2018
Remediation
Plan
September 2016
September
2016
Scenario 16-06
Requalification Exam
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
Temps
November 15,
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
AI 22C-013
Protected Equipment Program
On-Line nuclear Safety and Generation Risk Assessment
Risk Management Contingency Planning
Qualitative Risk Management
4B
SYS NN-200A
Transferring NN01 and NN03 Buses Between Power
Sources
Drawings
Number
Title
Revision
M-12BG01
Piping & Instrumentation Diagram, Chemical and Volume
Control System
Condition Reports
21823
2610
2858
23047
23103
25743
Work Orders
17-426767-000
Miscellaneous Documents
Number
Title
Revision/Date
Evidence and Action Matrix: CR 122858/SWO 18-439146-
000/001
May 3, 2018
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
GN
January 1 -
June 30, 2017
System Health Report - Containment Cooling - System
GN
July 1 -
December 31,
2017
System Health Report - Containment Cooling - System
GN
January 1 -
June 30, 2018
System Health Report - Instrument AC Power - System
NN
January 1 -
June 30, 2017
System Health Report - Instrument AC Power - System
NN
July 1 -
December 31,
2017
System Health Report - Instrument AC Power - System
NN
January 1 -
June 30, 2018
APF 15C-002-01 Procedure Cover Sheet: Transferring NN01 and NN03
Buses Between Power Sources
EDI 23M-050
Engineering Desktop Instruction Monitoring Performance
to Criteria and Goals: System NN
May 21, 2018
GN
Maintenance Rule Final Scope Evaluation: Containment
Cooling System - GN-01
Printed
September 18,
2018
GN
Maintenance Rule Final Scope Evaluation: Containment
Cooling System - GN-02
Printed
September 18,
2018
GN
Maintenance Rule Final Scope Evaluation: Containment
Cooling System - GN-03
Printed
September 18,
2018
GN
Maintenance Rule Final Scope Evaluation: Containment
Cooling System - GN-04
Printed
September 18,
2018
GN
Maintenance Rule Final Scope Evaluation: Containment
Cooling System - GN-05
Printed
September 18,
2018
Miscellaneous Documents
Number
Title
Revision/Date
GN
Maintenance Rule Final Scope Evaluation: Containment
Cooling System - GN-06
Printed
September 18,
2018
GN
Maintenance Rule Final Scope Evaluation: Containment
Cooling System - GN-07
Printed
September 18,
2018
GN
Maintenance Rule Final Scope Evaluation: Containment
Cooling System - GN-08
Printed
September 18,
2018
NN
Maintenance Rule Final Scope Evaluation: Instrument AC
Power System - 120V (Class IE Power System) - NN01
Printed
August 15,
2018
NN
Maintenance Rule Final Scope Evaluation: Instrument AC
Power System - 120V (Class IE Power System) - NN02
Printed
August 15,
2018
71111.13Maintenance Risk Assessments and Emergent Work Control
Procedures
Number
Title
Revision
AI 15C-006
Management Oversight Requirements for Infrequently
Performed and Potentially Degrading Evolutions
CWD-1
Welding Program Manual
SYS NB-200
Transferring XNB01 Supply Between SL7 and #7
Transformer
SYS NB-200
Transferring XNB01 Supply Between SL7 and #7
Transformer
Drawings
Number
Title
Revision
C-1C6311
Fuel Building Conc. Neat Line & Reinforcing Plan Floor
El. 2,047-6
KD-7496
One Line Diagram
M-618.4-00010
M-12EF01
Piping & Instrumentation Diagram Essential SVC Water
System
Drawings
Number
Title
Revision
M-12EF02
Piping & Instrumentation Diagram Essential SVC Water
System
M-12EG01
Piping & Instrumentation Diagram Component Cooling
Water System
M-12EG02
Piping & Instrumentation Diagram Component Cooling
Water System
M12EG03
Piping & Instrumentation Diagram Component Cooling
Water System
M-12EM02
Piping & Instrumentation Diagram High Pressure Coolant
Injection System
M-K2EF01
Piping & Instrumentation Diagram Essential Service Water
System
M-K2EF03
Piping & Instrumentation Diagram Essential Service Water
System
Condition Reports
25201
25205
25224
25239
25245
25249
25250
25251
25252
25280
25372
25563
25637
25638
25716
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
16-4162460926 - Evaluation of Fuel Building for Loads
From Installation of the Cask Handling Crane (HKE14 -
Change Package 15044)
June 25, 2018
APF 05C-004-01 WCNOC - Basic Engineering Disposition - Cask
Handling Crane Modification: SARENs Heavy Lift Unit
(HLU)
August 28, 2018
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
SRO/RO/BOP Review - Day Shift
August 24, 2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Night Shift
August 25, 2018
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk
Assessment: 2018-0305
July 30 to
August 5, 2018
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk
Assessment: 2018-0308
August 20 to
August 26, 2018
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment
2018-0309
August 27 to
September 2,
2018
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk
Assessment: 2018-0313
September 24 to
September 30,
2018
APF 28A-001-01 Performance Improvement Request
PIR 982987
71111.15Operability Determinations and Functionality Assessments
Procedures
Number
Title
Revision
Temporary Configuration Changes
Operability Determination and Functionality Assessment
CNT-MM-303
Temporary Support Guidelines
CWD-1
Welding Program Manual
Drawings
Number
Title
Revision
M-12BG05
Piping & Instrumentation Diagram Chemical and Volume
Control System
M-12EF01
Piping & Instrumentation Diagram Essential SVC Water
System
M-12EF02
Piping & Instrumentation Diagram Essential SVC Water
System
M-12EF06
Piping Isometric Essential Service Water Sys. [System] Aux.
[Auxiliary] Bldg. [Building] A & B Train Supply & Return
Drawings
Number
Title
Revision
M-12EG01
Piping & Instrumentation Diagram Component Cooling
Water System
M-12EG02
Piping & Instrumentation Diagram Component Cooling
Water System
M-12EG03
Piping & Instrumentation Diagram Component Cooling
Water System
M18BG35A(Q)
Hanger Details Small Pipes Misc. and Boric Acid Storage
Tanks Vents - Auxiliary Building
M-19BG35(Q)
Hanger Location Drawing Small Pipe Misc. and Boric Acid
Storage Tanks Vents-Auxiliary Building
M-K2EF01
Piping & Instrumentation Diagram Essential Service Water
System
M-K2EF03
Piping & Instrumentation Diagram Essential Service Water
System
Condition Reports
23902
23903
23905
23906
23907
23908
24948
25201
25205
25224
25243
25361
25374
25468
25487
25552
25560
25561
25638
25641
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
Wolf Creek Generating Station - Basic Cause Evaluation:
BGLT0106 Temporary Support Usage
September 8,
2018
APF 05C-004-01
Basic Engineering Disposition - Evaluation of the Use of a
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-
C527/112 (Q)
CNTF-MM-300-02 Section I Generic Inspection Item Instructions
CNTF-MM-300-07 Section VI - Small Bore/MS 25W Supports - Pipe
Support: BG35-C257/112 (Q)
CNTF-MM-303-01 Temporary Supports - Pipe Support: BG35-C527/112 (Q)
DG-C-002
Wolf Creek Nuclear Operating Corporation - Design
Guide: Evaluation Criteria for Temporary Acceptance of
Flaws in Moderate Energy Class 2 or 3 Piping
NK-E-001
25 VDC [Volt Direct Current] Class 1E Battery System
Sizing, Voltage Drop and Short Circuit Studies
OE EF-18-003
Operability Evaluation
OE NK-18-005
Operability Evaluation
WCRE-34
Fourth 10-Year Interval Inservice Testing Basis Document
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
DCP 14269
Configuration Summary
DCP 14269
Design Input Data Sheet
DCP 14269
Design Verification Report, SGK05 Permanent
Compensatory Modifications
DCP 14269
Engineering Screening, SGK05 Permanent Compensatory
Modifications
DCP 14269
Post Modification Testing Plan
71111.19Post Maintenance Testing
Procedures
Number
Title
Revision
QCP-20-540
VT-1 Visual Examination
STS BG-100A
Centrifugal Charging System A Train Inservice Pump Test
STS EG-100A
Component Cooling Water Pumps A/C Inservice Pump Test 33A
SYS EG-120
Component Cooling Water System
Drawings
Number
Title
Revision
M-12EG01
Piping & Instrumentation Diagram Component Cooling
Water System
Condition Reports
26021
26025
26036
26037
26038
26039
26040
26041
26734
Work Orders
18-441467-000
18-441467-003
Miscellaneous Documents
Number
Title
Revision/Date
18-025
Section XI Program Final Work Order Completion Review
Signature Sheet: Work Order Number 18-441467-003
July 31, 2018
APF 15C-002-01 Procedure Cover Sheet - Component Cooling Water
System
APF 16A-003-01 ASME Section XI Repair/Replacement Plan Wolf Creek
Generating Station - Plan No. 2018-025
July 22, 2018
APF 22C-008-01 Qualitative Risk Screening
July 22, 2018
APF 29B-003-01 Surveillance Test Routing Sheet - Component Cooling
Water Pumps A/C Inservice Pump Test
August 13,
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,
2018, Inservice Inspection Program Relief Request From
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
August 28,
2018
71111.22Surveillance Testing
Procedures
Number
Title
Revision
STS BG-210
CVCS Inservice Check Valve Test
Containment Spray Additive Tank NAOH Concentration
7A
STS EJ-100B
RHR System Inservice Pump A Test
STS EN-005
Containment Spray Additive Tank Volume Verification
STS IC-459
Channel Calibration Spray Additive Tank Level Loop
ENLP0015
6C
Drawings
Number
Title
Revision
10466-J-110-
149-W08
Instrument Loop Diagram - Containment Spray System
Spray Additive Tank Full Range Level (Train A)
M-105B-0005
A6 ODX13Y-8 LG Contain Spray Additive Tank
M-105B-00018
Details-Containment Spray Additive Tank
Condition Reports
24979
25017
26396
Miscellaneous Documents
Number
Title
Revision/Date
APF 05-002-05
Engineering Disposition: Use of EN-LG-22 for Tech Spec
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
for Tech Spec Surveillance
APF 05-004-01
Design Specification for Shop Fabricated Tanks (ASME III):
M-105B
LER 2000-001-00 Surveillance Method Results in Low NaOH Level in the
Spray Additive Tank
March 13,
2000
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
EPP 06-019
Alert and Notification System Sirens, October 2, 2016
9A
EPP 06-022
Tone Alert Radio Maintenance/Compensating Measures,
April 4, 2014
5A
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
May 7, 2008
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
Operating Company
May 7, 2008
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,
2015
Condition Reports
115983
24451
Miscellaneous Documents
Number
Title
Date
16-Q3 Quarterly Callout Test Conducted September 12,
2016
September 13,
2016
16-Q4 Quarterly Callout Test Conducted December 8,
2016
December 8,
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,
2017
September 20,
2017
17-Q4 Quarterly Callout Test Conducted November 27,
2017
November 29,
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,
2018
Emergency Planning Responsibilities, September 30, 2015
Emergency Response Duties and Responsibilities,
September 24, 2015
Diverse and Flexible Coping Mitigation Strategies Program
APF 06-002-01
Emergency Action Levels
17B
EPP 06-009
Drill and Exercise Requirements, January 24, 2017
EPP 06-018
Maintenance of Emergency Facilities and Communications
Checks, November 29, 2016
EPP 06-021
Training Programs, November 28, 2017
EPP 06-023
Emergency Response Facility Functionality, December 16,
2015
Tool Kit 010
Dosimeter Annual Calibration (RDDs and PICs)
April 13, 2017
Condition Reports
109918
111604
111626
2435
113322
113710
114405
115932
116368
116717
117040
117446
119507
119903
20017
20356
23795
23980
24428
24498
25031
25976
Work Orders
2-352615-000
15-408018-000
Miscellaneous
Number
Title
Revision/Date
CFR 50.54Q Screenings/Evaluations for AP 06-004,
Equipment Important to Emergency Preparedness, R7
October 16,
2017
CFR 50.54Q Screenings/Evaluations for EPP 06-001,
Control Room Operations, R10
July 30, 2018
Miscellaneous
Number
Title
Revision/Date
CFR 50.54Q Screenings/Evaluations for EPP 06-003,
Emergency Operations Facility Operations, R13
October 16,
2017
CFR 50.54Q Screenings/Evaluations for EPP 06-007,
Emergency Notifications, R16
October 16,
2017
CFR 50.54Q Screenings/Evaluations for EPF 06-018-
09, Offsite Monitoring Inventory Checklist, R29
August 2, 2017
CFR 50.54Q Screenings/Evaluations for EPF 06-018-
2, Emergency Operations Facility Checklist, R30
August 2, 2017
CFR 50.54Q Screenings/Evaluations for EPP 06-021,
Training Programs, R19
November 16,
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
Checklist
February 27,
2017
Emergency Planning Quarterly Communications
Checklist
February 28,
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-
Exercise
September 25,
2017
Topeka Joint Information Clearinghouse Inventory
Checklist
February 16,
2017
Topeka Joint Information Clearinghouse Inventory
Checklist
February 28,
2018
Topeka Joint Information Clearinghouse Inventory
Checklist, Post-Exercise
March 30, 2017
Wolf Creek Joint Information Clearinghouse Inventory
Checklist
March 30, 2017
Wolf Creek Joint Information Clearinghouse Inventory
Checklist
February 28,
2018
16-SA-02
Evaluation Report for the Exercise Conducted
December 7, 2016
December 14,
2016
17-04-EP
Quality Assurance Audit Report
June 8, 2017
17-EVAL
Evaluation Report for the Exercise Conducted
November 14, 2017
December 12,
2017
17-PRE-01
Evaluation Report for the Exercise Conducted
September 19, 2017
September 25,
2017
17-PRE-02
Evaluation Report for the Exercise Conducted
October 24, 2017
December 12,
2017
17-SA-01
Evaluation Report for the Exercise conducted February
14, 2017
March 13, 2017
17-SA-01
Evaluation Report for the Exercise Conducted February
13, 2018
February 20,
2018
17-SA-02
Evaluation Report for the Exercise Conducted March 14,
2017
April 3, 2017
17-SA-02
Evaluation Report for the Exercise Conducted April 18,
2017
August 15, 2017
17-SA-02
Evaluation Report for the Exercise Conducted July 18,
2017
August 15, 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,
August 14, 2018
13A
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
Staffing Assessment
March 8, 2017
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-
Assessment
June 26, 2018
71114.06Drill Evaluation
Procedures
Number
Title
Revision
EPP 06-006
Protective Action Recommendations
9A
Condition Reports
26171
26183
26184
26185
26186
26189
26190
26192
26193
26195
26197
26198
26199
26200
26201
26202
26203
26204
26205
26206
26207
26208
26210
26212
26213
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:
2018-309
August 27 to
September 2,
2018
EPF 06-007-01
Wolf Creek Generating Station Emergency Notification -
Message #: CR-001
August 28,
2018
Miscellaneous Documents
Number
Title
Revision/Date
EPF 06-007-01
Wolf Creek Generating Station Emergency Notification -
Message #: EOF-002
August 28,
2018
EPF 06-007-01
Wolf Creek Generating Station Emergency Notification -
Message #: EOF-003
August 28,
2018
EPF 06-007-01
Wolf Creek Generating Station Emergency Notification -
Message #: EOF-004
August 28,
2018
EPF 06-007-01
Wolf Creek Generating Station Emergency Notification -
Message #: TSC-001
August 28,
2018
Scenario 16-06
Requalification Exam
71124.05Radiation Monitoring Instrumentation
Procedures
Number
Title
Revision
AI 02E-009
Instructions for Intrinsic Germanium Detector Energy
Calibration
13A
AI 02E-010
Instructions for IG Detector Efficiency Calibration
7A
AI 03-008
Control Chart Development, Use and Review Using Lab
Stats
AP 02-008
Verification of Analytical Performance
Chemistry Calibration Program
AP 23-006
System Engineering Program
27A
Radiation Protection Manual
RPP 01-405
HP Instrument Program
RPP 03-407
Testing of Portal Monitors as Passive Whole Body Counters 1A
RPP 05-306
PM12 Operation
RPP 05-707
Operation of Whole Body Counters
RPP 06-103
Ludlum 9-4 Calibration
RPP 06-113
MGP Telepole Calibration
RPP 06-222
Escort Elf Calibration
RPP 06-306
PM12 Calibration
RPP 06-315
Eberline PCM-1B Calibration
RPP 06-317
Eberline PCM-2 Calibration
Procedures
Number
Title
Revision
RPP 06-319
SAM11 Calibration
RPP 06-707
Calibration of WBC Detectors Using Ortec Renaissance
Software
RPP 06-715
Whole Body Counter Quality Control
RPP 06-825
J. L. Shephard Multi-Source Calibration System Operation
8A
STS IC-452B
Channel Calibration New Fuel Storage Facility Criticality
Monitor SDRE-0035
4A
STS IC-454B
Channel Calibration Spent Fuel Pool Criticality Monitor Area
Radiation Monitor SDRE-0038
Channel Calibration of Condenser Air Discharge Monitor GE
RE-0092
Audits, Self-Assessments, and Surveillances
Number
Title
Date
18-01-RP/PC
Quality Assurance Audit Report: Radiation Protection and
Process Control (RP & PC)
February 15,
2018
QA-2017-0387
Quality Assessment: Radiation Protection (RP) Equipment
Calibration Controls
December 29,
2017
Condition Reports
107189
107190
107191
107193
113038
113556
116717
118252
118867
20567
20963
21150
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
Management
WO 16-427623-
001
Minor Maintenance Containment Atmospheric Radiation
Monitor GTRE0032
November 15,
2016
WO 16-427623-
003
Routine Maintenance Containment Purge Exhaust
Radiation Monitor GTRE0033
November 15,
2016
Channel Calibration High Range Area Radiation Monitor
GTRE60
Channel Calibration High Range Area Monitor GTRE-0059
Channel Calibration High Range Area Radiation Monitor
GTRE59
Channel Calibration High Range Area Radiation Monitor
GTRE60
Channel Calibration of Condenser Air Discharge Monitor
GE RE-0092
71124.06Radioactive Gaseous and Liquid Effluent Treatment
Procedures
Number
Title
Revision
Chemistry Calibration Program
Offsite Dose Calculation Manual
CHS AC-001
Accident Sampling
4C
Procedures
Number
Title
Revision
CHS AX-G01
Unit Vent Sampling and/or Exchange of Filters
STN BM-054
Steam Generator Blowdown System Surge Tank Discharge
Flow to Lake Channel Calibration
7C
STN CH-021
Calibration of the Particulate Detector for Radiation Monitors
GTRE21A and GHRE10A
STN CH-022
Calibration of the Iodine Detector for Radiation Monitors
GTRE21A and GHRE10A
STN HB-1085
Liquid Radwaste System Discharge Line Flow Rate
Calibration
STN SP-118
Channel Calibration Liquid Radwaste Discharge Radiation
Monitor HB RE-0018
STN SP-195
Channel Calibration Hi/Lo TDS Discharge to Waste Water
Treatment Radiation Monitor HF RE-0095
Calibration of Monitors GT RE-21B and GH RE-10B
STS PE-002
Charcoal Adsorbent Sampling for Nuclear Safety Related
Units
STS PE-006
Charcoal Adsorber In-Place Leak Test Safety Related Units
Audits and Self-Assessments
Number
Title
Date
18-03-ENV
QA Audit: Environmental Management
April 17, 2018
Condition Reports
107421
107983
108892
111266
2928
113578
113944
116717
118486
23726
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
101145
Simulated Gas in 130G GA-MA Gas Beaker
July 1, 2015
16-CHL-005
Certificate of Calibration-Standard Reference Source
2600
47mm Diameter Simulated Filter in Snap Falcon Petri
January 1, 2016
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
AI 07B-002
Review of Radiological Environmental Lab Analysis
AI 07B-009
Collection, Prep, and Shipment of Sediment
AI 07B-011
Collection, Prep, and Ship of Water
AI 07B-015
Land Use Census
Procedures
Number
Title
Revision
AI 07B-034
Radiological Environmental Monitoring Program Air
Sampling
AI 07B-035
Ground Water Protection Program
STS IC-890A
Wind Speed Meteorological Instrumentation Channel
Calibration
STS IC-890D
Sonic Wind-Direction-Deviation Meteorological
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
Management: K15-002
March 29,
2018
QH-2017-1456
AI 07B-034, Radiological Environmental Monitoring
Program Air Sampling
March 30,
2018
QH-2017-1456
Radiological Environmental Monitoring Program (REMP)
contracted services per AI 07B-005, Section 6.12
April 24, 2017
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
Instrumentation
March 26,
2018
Miscellaneous Documents
Number
Title
Revision/Date
Environmental Resources Management: Risk Assessment
for Systems, Structures, and Components, Groundwater
Protection Initiative, Wolf Creek
August 20,
2008
Review of Radiological Environmental Lab Analysis
Results
Technical Requirements Manual
Wolf Creek Generating Station Power Block - Ground
Water Monitoring Network
2008
Preliminary Hydrology Study, Wolf Creek Generating
Station, Environmental Resources Management
December 18,
2007
2009
Coffey County Lake - Ground Water Monitoring Network
Documentation Report, Delta Consultants
October 9,
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
Solid Radwaste Process Control Program
HW1215801
Regulations and Requirements
2A
HW1215802
Regulatory Awareness for Hazardous Material Handlers
HW8115901
Wolf Creek Hazardous Material Transportation Security
Plan
RPP 07-110
Solid Radwaste Packaging
Procedures
Number
Title
Revision
RPP 07-112
Processing Cartridge Filters
RPP 07-123
Preparation and Shipment of Radioactive Waste and
Material
RPP 07-131
Bead Resin/Activated Carbon Dewatering Procedure For
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
Process Control (RP & PC)
February 15,
2018
Condition Reports
2184
97750
97752
110270
113038
114455
119333
119745
119751
119765
119766
20567
Radioactive Material and Waste Shipments
Number
Type
Title
Date
16R02
Dry Active
Waste
UN2912, Radioactive Material, LSA-I, 7, A(U)
February 9, 2016
16R15
Resins
UN3321, Radioactive Material, LSA-II, 7, A(U)
May 18, 2016
16R16
Filters;
Resin
UN3321, Radioactive Material, LSA-II, 7, C
June 1, 2016
16R32
Dry Active
Waste
UN3321, Radioactive Material, LSA-II, 7, A(U)
September 15,
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
Waste
UN2912, Radioactive Material, LSA-I, 7, A(U)
February 16, 2017
17R14
Dry Active
Waste
UN3321, Radioactive Material, LSA-II, 7, A(U)
May 24, 2017
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
Waste
UN2912, Radioactive Material, LSA-I, 7, A(U)
July 12, 2017
17R31
Dry Active
Waste;
Resin
UN3321, Radioactive Material, LSA-II, 7, A(U)
September 18,
2017
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
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
Reportable Events, Evaluation and Documentation, July 24,
2014
AP 34-003
Performance Indicator Program, August 17, 2010
EPP 06-005
Emergency Classification, February 23, 2016
EPP 06-006
Protective Action Recommendations, December 14, 2017
9A
EPP 06-007
Emergency Notifications, October 18, 2017
EPP 06-019
Alert and Notification System Sirens, October 2, 2016
9A
Condition Reports
110999
116997
118425
119906
20323
26201
27496
27526
Miscellaneous Documents
Number
Title
Revision/Date
MSPI Derivation Report - MSPI System: MSPI Cooling
Water System; MSPI Element: Performance Limit Exceeded
(PLE)
August 2018
MSPI Derivation Report - MSPI System: MSPI Cooling
Water System; MSPI Element: Unavailability Index (UAI)
August 2018
MSPI Derivation Report - MSPI System: MSPI Cooling
Water System; MSPI Element: Unreliability Index (URI)
August 2018
MSPI Derivation Report - MSPI System: MSPI Emergency
AC Power System; MSPI Element: Performance Limit
Exceeded (PLE)
August 2018
MSPI Derivation Report - MSPI System: MSPI Emergency
AC Power System; MSPI Element: Unavailability Index
(UAI)
August 2018
Miscellaneous Documents
Number
Title
Revision/Date
MSPI Derivation Report - MSPI System: MSPI Emergency
AC Power System; MSPI Element: Unreliability Index (URI)
August 2018
MSPI Derivation Report - MSPI System: MSPI High
Pressure Injection System; MSPI Element: Performance
Limit Exceeded (PLE)
August 2018
MSPI Derivation Report - MSPI System: MSPI High
Pressure Injection System; MSPI Element: Unavailability
Index (UAI)
August 2018
MSPI Derivation Report - MSPI System: MSPI High
Pressure Injection System; MSPI Element: Unreliability
Index (URI)
August 2018
MSPI Unavailability for Chemical & Volume Control System
BG-07A
Printed
September 11,
2018
MSPI Unavailability for Chemical & Volume Control System
BG-07B
Printed
September 11,
2018
MSPI Unavailability for Component Cooling Water System
EG-01A
Printed
September 11,
2018
MSPI Unavailability for Component Cooling Water System
EG-01B
Printed
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
System EM-01A
Printed
September 11,
2018
MSPI Unavailability for High Pressure Coolant Injection
System EM-01B
Printed
September 11,
2018
MSPI Unavailability for Standby Diesel Engine System KJ-
01A
Printed
September 11,
2018
Miscellaneous Documents
Number
Title
Revision/Date
MSPI Unavailability for Standby Diesel Engine System KJ-
01B
Printed
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
Criteria and Goals - System: BG - 112594
May 17, 2017
EDI 23M-050
Engineering Desktop Instruction Monitoring Performance to
Criteria and Goals - System: BG - CR 118860
February 12,
2018
EDI 23M-050
Engineering Desktop Instruction Monitoring Performance to
Criteria and Goals - System: BG - CR 121938
May 3, 2018
EDI 23M-050
Engineering Desktop Instruction Monitoring Performance to
Criteria and Goals - System: BG - CR 122610
May 16, 2018
EDI 23M-050
Engineering Desktop Instruction Monitoring Performance to
Criteria and Goals - System: EF - CR 125201
August 9,
2018
EDI 23M-050
Engineering Desktop Instruction Monitoring Performance to
Criteria and Goals - System: EG - CR 120591
December 5,
2017
EDI 23M-050
Engineering Desktop Instruction Monitoring Performance to
Criteria and Goals - System: EM - CR 112588
May 17, 2017
EDI 23M-050
Engineering Desktop Instruction Monitoring Performance to
Criteria and Goals - System: EM - CR 112594
May 17, 2017
EDI 23M-050
Engineering Desktop Instruction Monitoring Performance to
Criteria and Goals - System: KJ - CR 112131
April 27, 2017
EDI 23M-050
Engineering Desktop Instruction Monitoring Performance to
Criteria and Goals - System: KJ - CR 115725
October 1,
2017
EDI 23M-050
Engineering Desktop Instruction Monitoring Performance to
Criteria and Goals - System: KJ - CR 117441
December 5,
2017
EDI 23M-050
Engineering Desktop Instruction Monitoring Performance to
Criteria and Goals - System: NB - CR 126025
September 5,
2018
EDI 23M-050
Engineering Desktop Instruction Monitoring Performance to
Criteria and Goals - System: NG - CR 115725
October 1,
2017
WCNOC-163
NEI 99-02 Reactor Oversight Process Performance
Indicators - Mitigating System Performance Index (MSPI)
Basis Document
Miscellaneous Documents
Number
Title
Revision/Date
WCRE-34
Fourth Ten Year Interval Inservice Testing Bases Document
71152Problem Identification and Resolution
Procedures
Number
Title
Revision
AP 10-104
Breach Authorization
AP 10-104
Breach Authorization
37A
Procedure Use and Adherence
AP 23-009
Control Room Envelope Habitability Program
STS PE-004
Aux Building and Control Room Pressure Test
SYS AE-150
Main Feedwater Pump Reset
SYS AE-150
Main Feedwater Pump Reset
SYS GK-122
Manual CRVIS Line-Up
Drawings
Number
Title
Revision
M-12GG01
Piping & Instrumentation Diagram Fuel Building HVAC
M-12GL02
Piping & Instrumentation Diagram Auxiliary Building HVAC
M-12GT01
Piping & Instrumentation Diagram Containment Purge
Systems HVAC
M-1H1531
Heating Ventilating and Air Cond. Auxiliary Building El.
2047-6 Area-3
Condition Reports
29602
246
90956
90975
110377
119330
20056
20151
2180
23289
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
Guide 1.117: Tornado Design Classification
AIF 10-001-02
SCBA Inspection [3.2.1]
Completed
March 1, 2018
Wolf Creek Generating Station Basic Cause Evaluation -
CR 90975
February 20,
2015
Wolf Creek Generating Station Basic Cause Evaluation -
CR 120056
April 5, 2018
APF 29B-003-01 Surveillance Test Routing Sheet (STRS) - Aux Building and
Control Room Pressure Test - Train A - STS PE-004
Completed
March 15,
2018
APF 29B-003-01 Surveillance Test Routing Sheet (STRS) - Aux Building and
Control Room Pressure Test - Train B - STS PE-004
Completed
March 7, 2018
APF 29B-003-01 Surveillance Test Routing Sheet (STRS) - Aux Building and
Control Room Pressure Test - Train B - STS PE-004
Completed
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
WCRE-35
Boundary Matrix
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
C.
Audits, self-assessments, vendor or NUPIC audits of contractor support, and LERs
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.
G.
Annual Radioactive Effluent Release Reports for calendar years 2016 and 2017, or the
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
C.
Audits, self-assessments, vendor or NUPIC audits of contractor support, and LERs
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
I.
Waste stream sample analysis results and resulting scaling factors for 2016 and 2017,
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
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
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