IR 05000482/2018001
ML18131A017 | |
Person / Time | |
---|---|
Site: | Wolf Creek ![]() |
Issue date: | 05/14/2018 |
From: | Nick Taylor NRC/RGN-IV/DRP/RPB-B |
To: | Heflin A Wolf Creek |
Taylor N | |
References | |
IR 2018001 | |
Download: ML18131A017 (32) | |
Text
May 14, 2018
SUBJECT:
WOLF CREEK GENERATING STATION - NRC INTEGRATED INSPECTION REPORT 05000482/2018001
Dear Mr. Heflin:
On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Wolf Creek Generating Station. On April 25, 2018, the NRC inspectors discussed the results of this inspection with Mr. C. Reasoner, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
NRC inspectors documented one finding of very low safety significance (Green) in this report.
This finding involved a violation of NRC requirements. The NRC is treating this violation as a non-cited violation consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or significance of this non-cited violation, 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 05000482/2018001 w/ Attachments:
1. Supplemental Information 2. Request for Information
Enclosure U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number:
05000482
License Number:
Report Number:
Enterprise Identifier: I-2018-001-0012
Licensee:
Wolf Creek Nuclear Operating Corporation
Facility:
Wolf Creek Generating Station
Location:
1550 Oxen Lane NE
Burlington, KS 66839
Inspection Dates:
January 1, 2018, to March 31, 2018
Inspectors:
D. Dodson, Senior Resident Inspector
F. Thomas, Resident Inspector
D. Bradley, Senior Resident Inspector, Callaway
Approved By:
N. Taylor, Chief, Project Branch B, Division of Reactor Projects
SUMMARY
The 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.
List of Findings and Violations
Inadequate Functionality Assessment Associated with the Emergency Excess Letdown Flowpath Cornerstone Significance Cross-cutting Aspect Report Section Mitigating Systems
Green NCV 05000482/2018001-01 Closed
[H.14] - Human Performance,
Conservative Bias 71111.15 -
Operability Determinations and Functionality Assessments The inspectors identified a Green finding and associated non-cited violation of 10 CFR Part 50,
Appendix B, Criterion V, Instructions, Procedures, and Drawings, when the licensee failed to adequately implement the operability determination and functionality assessment procedure.
Specifically, the licensee failed to document a functionality assessment of sufficient scope to address the capability of a safety-related excess letdown heat exchanger to pressurizer relief tank isolation valve and the excess letdown system to perform their specified safety functions, which resulted in the licensee failing to recognize that two independent Technical Requirements Manual required boration injection subsystems were not functional.
PLANT STATUS
Wolf Creek Generating Station began the inspection period at rated thermal power. On March 30, 2018, a plant shutdown was completed to begin Refueling Outage
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
71111.01 - Adverse Weather Protection
Impending Severe Weather (1 Sample)
The inspectors evaluated readiness for impending adverse weather conditions for extreme low temperatures on January 2 and 3, 2018.
71111.04 - Equipment Alignment
Partial Walkdown (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) turbine-driven auxiliary feedwater train on February 6, 2018
- (2) residual heat removal pump B on March 21, 2018
Complete Walkdown (1 Sample)
The inspectors evaluated system configurations during a complete walkdown of the component cooling water system on February 23, 2018.
71111.05AQ - Fire Protection Annual/Quarterly
Quarterly Inspection (5 Samples)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) fire area A-16, general area, elevation 2,026 feet on January 30, and March 28, 2018
- (2) fire area A-18, electrical penetration room (north), elevation 2,026 feet on January 30, 2018
- (3) fire area A-17, electrical penetration room (south), elevation 2,026 feet on March 28, 2018
- (4) fire area A-26, decontamination area for I&C shop, elevation 2,026 feet on March 28, 2018
- (5) fire area A-27, reactor trip switchgear, motor-generator sets, load centers, rod control and rod-drive power supply control cabinets 125 volt direct current panel on March 28, 2018.
71111.06 - Flood Protection Measures
Internal Flooding (1 Sample)
The inspectors evaluated internal flooding mitigation protections in rooms 1203 and 1203A, Pipe Space B on January 9, 2018.
71111.07 - Heat Sink Performance
Heat Sink (1 Sample)
The inspectors evaluated containment spray train A room cooler (SGL13A) performance on January 17, 2018.
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance
Operator Requalification (1 Sample)
The inspectors observed and evaluated licensed operator simulator requalification activities that included a loss of all alternating current power during shutdown scenario on February 22, 2018.
Operator Performance (1 Sample)
The inspectors observed and evaluated operator performance during end of life core moderator temperature coefficient measurement activities on February 5, 2018.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness (1 Sample)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
Auxiliary building heating ventilation and air conditioning (GL) system including safety-related pump and electrical penetration room coolers on January 29, 2018.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) reactor partial trip alarm troubleshooting and main generator transformer B loss of two cooling groups on January 4, 2018
- (2) emergent maintenance on Class 1E electrical equipment air conditioning unit train A on January 24, 2018
- (3) planned maintenance on component cooling water train B on March 5, 2018
- (4) emergent maintenance associated with the failed control room envelope pressure test on March 6, 2018
- (5) emergent maintenance on Class 1E electrical equipment air conditioning unit train B on March 12, 2018.
71111.15 - Operability Determinations and Functionality Assessments
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) auxiliary building elevation 1988 foot south pipe chase drain functionality with three clogged floor drains on January 10, 2018
- (2) 125 volt direct current to 120 volt alternating current NN15 inverter operability after a high voltage alarm would not clear on January 18, 2018
- (3) emergency diesel generator A lubrication oil leakage on January 31, 2018
- (4) Class 1E electrical equipment air conditioning unit train B operability following a step controller failure on February 12, 2018
- (5) reactor coolant pump A standpipe not filling on the expected frequency on February 25, 2018
- (6) Technical Specification 3.7.10 mitigating actions to ensure the control room envelope occupant radiological exposures would not exceed limits and control room envelope occupants are protected from chemical and smoke hazards while the control room envelope was inoperable on March 6, 2018
- (7) excess letdown heat exchanger outlet to pressurizer relief tank isolation valve functionality after failed stoke testing on March 12, 2018
- (8) station blackout diesel generator functionality after post maintenance testing on March 20, 2018.
71111.19 - Post Maintenance Testing
The inspectors evaluated the following post maintenance tests:
- (1) Class 1E electrical equipment air conditioning unit train A following planned maintenance on January 24, 2018
- (2) motor-driven auxiliary feedwater train B pump discharge to steam generators A and D auxiliary feed water flow regulating valve testing following planned maintenance on February 6, 2018
- (3) component cooling water pump A following planned maintenance on February 15, 2018
- (4) residual heat removal pump A following planned maintenance on March 21, 2018.
71111.20 - Refueling and Other Outage Activities (Partial Sample)
The inspectors evaluated Refueling Outage 22 activities from March 30 to 31, 2018. The inspectors completed inspection procedure Sections 03.01.a, 03.01.b, and 03.01.c.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Routine
- (1) STS IC-926B, Component Cooling Water System Automatic Valve Actuation Train B, Revision 6B, on January 4, 2018
- (2) STS IC-915B, Channel Operational Test Train B Component Cooling Water System Non-Nuclear Safety-Related Isolation, Revision 8A, on January 8, 2018
- (3) STS IC-926A, Component Cooling Water System Automatic Valve Actuation Train A, Revision 8A, on February 12, 2018
- (4) STS IC-217, [Reactor Coolant Pump] Loss of Voltage and Underfrequency [Trip Actuation Device Operational Testing], on March 5, 2018
- (5) STS PE-004, Auxiliary Building and Control Room Pressure Tests, Revision 16, on March 5 and March 12, 2018.
71114.06 - Drill Evaluation
Emergency Planning Drill (1 Sample)
The inspectors evaluated the emergency preparedness drill on February 27,
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification
The inspectors verified licensee performance indicator submittals listed below:
- (1) IE01: Unplanned Scrams per 7000 Critical Hours Sample (01/01/2017-12/31/2017)
- (2) IE03: Unplanned Power Changes per 7000 Critical Hours Sample (01/01/2017-12/31/2017)
- (3) IE04: Unplanned Scrams with Complications (USwC) Sample (01/01/2017-12/31/2017).
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) On February 8, 2018, the unit vent tornado damper failed to meet acceptance criteria for initial breakaway torque. This issue was documented in Condition Report 119330.
- (2) On May 11, 2017, Condition Report 112960 documented that pressurizer safety valve 88010As as-found lift setting was 3.2 percent below the nominal setpoint.
INSPECTION RESULTS
Inadequate Functionality Assessment Associated with the Emergency Excess Letdown Flowpath Cornerstone Significance Cross-cutting Aspect Report Section Mitigating Systems
Green NCV 05000482/2018001-01 Closed
[H.14] - Human Performance, Conservative Bias
71111.15 - Operability
Determinations and Functionality Assessments The inspectors identified a Green finding and associated non-cited violation of 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, when the licensee failed to adequately implement the operability determination and functionality assessment procedure. Specifically, the licensee failed to document a functionality assessment of sufficient scope to address the capability of a safety-related excess letdown heat exchanger to pressurizer relief tank isolation valve and the excess letdown system to perform their specified safety functions, which resulted in the licensee failing to recognize that two independent Technical Requirements Manual required boration injection subsystems were not functional.
Description:
On March 12, 2018, the licensee was performing Procedure STN BB-201, Exercise of BB HV-8157A and BB HV-8157B, Revision 3, which tests and exercises the excess letdown heat exchanger to pressurizer relief tank isolation valves (BB HV-8157A and BB HV-8157B). The BB HV-8157B valve did not stroke fully closed as expected. Step 6.1.1 of Procedure STN BB-201 states, If the valve cannot be fully exercised, then valve shall be declared inoperable and corrective action initiated.
Condition Report 120287 was documented on March 12, 2018, reporting the valve failure. The immediate functionality assessment stated, The redundant path of excess letdown is still available. The system is functional but degraded. The system functionality is maintained by having a second redundant flow path for excess letdown. The inspectors noted that Section 6.4.7 of Procedure AP 26C-004, Operability Determination and Functionality Assessment, Revision 35, states, The scope of a functionality assessment must be sufficient to address the capability of SSCs to perform their specified functionsThe following things should be considered when performing functionality assessments: codes, standards and system requirements controlling the SSC.
The inspectors questioned the licensee concerning the immediate functionality determinations adequacy, and the licensee revised the functionality determination for the excess letdown heat exchanger to pressurizer relief tank isolation valve (8157B) and changed the determination to non-functional. The immediate functionality determination was updated to state:
The above screening gives an adequate justification for why the excess letdown po[r]tion of the [chemical and volume control system] remains functional but degraded. However, screening should be based on the component, not the system. Since BBHV8157B cannot be relied upon to go to the closed position using normal remote controls, the valve is considered nonfunctional. The system remains functional but degraded.
The inspectors also noted that Section 3.1.9, Boration Injection System - Operating, of the Technical Requirements Manual, requires two boration injection subsystems to be functional in MODES 1, 2, and 3. Section 3.1.9 of the Technical Requirements Manual Bases describes what is required for a boration injection subsystem to be considered functional. Specifically, both subsystems require the safety-related excess letdown flow path. Also, two independent boration injection subsystems are required to ensure single functional capability in the event an assumed failure renders one of the boration injection subsystems nonfunctional.
Updated Safety Analysis Report Section 7.4.3.3 describes the applicable single failure analysis. It states, The capability of the [residual heat removal system] to accommodate a single component failure and still perform a safety grade cooldown is demonstrated in the failure mode and effects analysis (FMEA) of the [residual heat removal] system for safety-related cold shutdown operations provided as Table 7.4-4. Table 7.4-4, Residual Heat Removal - Safety Related Cold Shutdown Operations - Failure Modes and Effects Analysis (FMEA), describes the function of the excess letdown to pressurizer relief tank isolation valves (8157A and 8157B), stating, Provides safety grade letdown flow path. Hence, in order for the safety-related excess letdown flowpath to the pressurizer relief tank to meet its safety function, either 8157A or 8157B must be functional and capable of opening.
The inspectors again questioned the updated immediate functionality determinations adequacy. Specifically, considering that 8157A and 8157B are parallel valves, that 8157B was non-functional, and assuming a design basis single failure (for example, assume 8157A fails to open or its power supply fails), the safety-related excess letdown flowpath would be non-functional, and both Technical Requirements Manual independent boration injection subsystems would be impacted. With the excess letdown heat exchanger to pressurizer relief tank isolation valve 8157B non-functional, current language in the Technical Requirements Manual would require one boration injection subsystem to be declared non-functional.
Corrective Actions: On March 20, 2018, the licensee changed the functionality assessment the excess letdown heat exchanger to pressurizer relief tank isolation valve (8157B) was determined to be non-functional. In response to the inspectors questions concerning system functionality and design basis information, the licensee initiated Condition Reports 120628 and 120822. The licensee restored the B train excess letdown heat exchanger to pressurizer relief tank isolation valve to service on April 9, 2018.
Corrective Action References: Condition Reports 120287, 120628, 120822 and 122411.
Performance Assessment:
Performance Deficiency: The licensee failed to document a functionality assessment of sufficient scope to address the capability of the safety-related excess letdown heat exchanger to pressurizer relief tank isolation valve and excess letdown system to perform their specified safety functions.
Screening: The inspectors determined the performance deficiency was more than minor because it adversely affected the equipment performance attribute of the Mitigating Systems Cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences (i.e., core damage).
Specifically, the safety-related excess letdown heat exchanger to pressurizer relief tank isolation valve and excess letdown system were inappropriately determined to be functional but degraded and non-conforming, which resulted in the licensee failing to recognize that two independent Technical Requirements Manual required boration injection subsystems were not functional.
Significance: The inspectors assessed the significance of the finding using Exhibit 2, Mitigating Systems 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 is not a deficiency affecting the design or qualification of a mitigating SSC that maintained its operability or functionality; the finding does not represent a loss of system and/or function; the finding does not represent an actual loss of function of at least a single train for greater than its Technical Specification-allowed outage time; and the finding does not represent an actual loss of function of one or more non-Technical Specification trains of equipment designated as high safety-significant. 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, and a proposed action was not determined to be safe in order to proceed, rather than unsafe in order to stop. Specifically, leaders did not take a conservative approach to decision making, particularly when information was incomplete or conditions were unusual when completing the functionality determination associated with the subject valve and system, which resulted in the valve and system being determined to be functional.
Enforcement:
Violation: Title 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, requires, in part, that activities affecting quality shall be accomplished in accordance with documented instructions, procedures, or drawings of a type appropriate to the circumstances. Licensee Procedure AP 26C-004, Operability Determination and Functionality Assessment, Revision 35, an Appendix B quality related procedure, provides instructions for performing functionality assessments. Procedure AP 26C-004, Section 6.4.7, states, in part, that the scope of a functionality assessment must be sufficient to address the capability of SSCs to perform their specified functions, and codes, standards, and system requirements controlling the SSC should be considered when performing functionality assessments.
Contrary to the above, from March 12, 2018, until April 9, 2018, the scope of a functionality assessment was not sufficient to address the capability of SSCs to perform their specified functions, and codes, standards, and system requirements controlling the SSC were not considered when performing functionality assessments. Specifically, the functionality assessment associated with the excess letdown heat exchanger outlet to pressurizer relief tank isolation valve and excess letdown system was not adequate and did not adequately consider design basis information, which caused the licensee to fail to identify non-functionality of safety-related SSCs.
Disposition: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On April 25, 2018, the inspector presented the quarterly resident inspector inspection results to Mr. C. Reasoner, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Section 1R01: Adverse Weather Protection
Procedures
Number
Title
Revision
SYS EF-205
ESW/Circ Water Cold Weather Operations
Miscellaneous
Number
Title
Date
96-0316
Performance Improvement Request
Initiated
February 5,
1996
2006-0006
Performance Improvement Request
Initiated
January 4,
2006
APF 15C-002-01 Procedure Cover Sheet - ESW/Circ Water Cold Weather
Operations - SYS EF-205
Completed
December 26,
2017
APF 15C-002-01 Procedure Cover Sheet - ESW/Circ Water Cold Weather
Operations - SYS EF-205
Completed
January 2,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Day Shift
January 19,
2018
APF 29B-003-01 Surveillance Test Routing Sheet - ESW Train B Warming
Line Verification - STN EF-020B
Completed
January 3,
2018
Docket No 50-482: Response to Enforcement Action
EA 96-124
July 31, 1996
Section 1R04: Equipment Alignment
Procedures
Number
Title
Revision
CKL Al-120
Auxiliary Feedwater Normal Lineup
CKL EG-120
Component Cooling Water System Valve, Switch and
Breaker Lineup
CKL EJ-120
RHR System Lineup
45B
Drawings
Number
Title
Revision
M-06EG07
Component Coolant Wtr. Sys. Aux. Bldg.
M-12AL01
Piping & Instrumentation Diagram Auxiliary Feedwater
System
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
M-12EJ01
Piping and Instrumentation Diagram Residual Heat
Removal System
M-12FC02
Piping & Instrumentation Diagram Auxiliary Feedwater
Pump Turbine
M-13EG07
Piping Isometric Component Cooling Water Sys. Aux. Bldg.
Common Header
M-15EG07
Hanger Location Drawing Component Cooling Water Sys
Aux. Bldg. Common Header
Condition Reports
119280
119401
20586
Section 1R05: Fire Protection
Procedures
Number
Title
Revision
AP 10-106
Fire Preplans
18A
CKL ZL-001
Auxiliary Building Reading Sheets
103
Condition Reports
119366
20782
20783
20784
Miscellaneous
Number
Title
Revision
E-1F9905
Fire Hazard Analysis
XX-X-004
Calculation Cover Sheet - Combustible Fire Loading For
Each Room In The Various Fire Areas at WCNOC
Section 1R06: Flood Protection Measures
Procedures
Number
Title
Revision
ALR 00-094F
Misc Sumps Lev Hi
Drawings
Number
Title
Revision
M-12EJ01
Piping and Instrumentation Diagram Residual Heat
Removal System
M-13LF02
Piping Isometric Sump Discharge Auxiliary Bldg.
Condition Reports
118576
118586
118587
118592
118593
Miscellaneous
Number
Title
Revision
FL-03
Flooding of Individual Auxiliary Building Rooms
Section 1R07: Heat Sink Performance
Procedures
Number
Title
Revision
Heat Exchanger Program
Work Orders
17-428729-000
17-428729-002
17-428729-003
17-428729-005
17-428737-000
Miscellaneous
Number
Title
Date
GL-05
Maintenance Rule Final Scope Evaluation
Printed
March 27,
2018
Section 1R11: Licensed Operator Requalification Program
Procedures
Number
Title
Revision
AP 21-001
Conduct of Operations
STS RE-006
EOL Core MTC Measurement
20B
Power Range Adjustment to Calorimetric
Miscellaneous
Number
Title
Revision/Date
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Day Shift
February 2,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Day Shift
February 3,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Night Shift
February 3,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Night Shift
February 4,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Night Shift
February 5,
2018
APF 29B-003-01 Surveillance Test Routing Sheet - EOL Core MTC
Measurement
Completed
February 5,
2018
EPF 06-007-01
Wolf Creek Generating Station Emergency Notification
(Drill)
February 22,
2018
LR5004005
Loss of All AC While Shutdown - Licensed Operator
Requal
Section 1R12: Maintenance Effectiveness
Drawings
Number
Title
Revision/Date
M-12GL01
Piping and Instrumentation Diagram Auxiliary Building
M-612.00062
Carrier Air Handling Units and Room Coolers
Imaged May
2017
Condition Reports
10539
114660
117759
Miscellaneous
Number
Title
Date
GL Room Cooler PM Schedule
Maintenance Rule Expert Panel Meeting Agenda
November 1,
2017
114660
Functional Failure Determination Checklist
August 17,
2017
GL-01
Maintenance Rule Final Scope Evaluation
Printed
January 29,
2018
GL-02
Maintenance Rule Final Scope Evaluation
Printed
January 29,
2018
GL-03
Maintenance Rule Final Scope Evaluation
Printed
January 29,
2018
GL-04
Maintenance Rule Final Scope Evaluation
Printed
January 29,
2018
GL-05
Maintenance Rule Final Scope Evaluation
Printed
January 29,
2018
GL-06
Maintenance Rule Final Scope Evaluation
Printed
January 29,
2018
GL-07
Maintenance Rule Final Scope Evaluation
Printed
January 29,
2018
GL-08
Maintenance Rule Final Scope Evaluation
Printed
January 29,
2018
GL-09
Maintenance Rule Final Scope Evaluation
Printed
January 29,
2018
Section 1R13: Maintenance Risk Assessment and Emergent Work Controls
Procedures
Number
Title
Revision
On-Line Nuclear Safety and Generation Risk Assessment
Procedures
Number
Title
Revision
OFN AF-025
Unit Limitations
STS BB-201B
Cycle Test of PORV Block Valve BB HV-800B
STS IC-447
Channel Calibration Nuclear Instrumentation System Power
Range Incore-Excore
STS MT-024B
Functional Test of 480 and 120 Volt Molded Case Circuit
Breakers
Drawings
Number
Title
Revision
M-622.1A-00142 SGK05A Terminal and Pressure Switch Enclosure Layout
W03
Condition Reports
118499
118938
118939
118940
118953
118958
118959
118963
118964
Work Orders
17-422791-003
17-427320-000
18-434985-000
18-435758-000
18-435758-001
Miscellaneous
Number
Title
Date
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Day Shift
January 23,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Night Shift
January 23,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Day Shift
January 24,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Night Shift
January 24,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Night Shift
January 25,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Night Shift
January 26,
2018
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment:
18-0101
January 4,
2018
Miscellaneous
Number
Title
Date
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment:
18-0111
March 13,
2018
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment:
2018-0110
February 15,
2018
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment:
2018-0104
January 10,
2018
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment -
2018-0122
February 14,
2018
APF 29B-003-01 Surveillance Test Routing Sheet - STS IC-447
Completed
January 4,
2018
APF 29B-003-01 Surveillance Test Routing Sheet - STS PE-004 (Train B)
Completed
March 7,
2018
Section 1R15: Operability Evaluations
Procedures
Number
Title
Revision
AI 16C-006
Troubleshooting
AI 28B-005
Evidence and Action Matrix
AP 12-003
Operability Determination and Functionality Assessment
OFN BB-005
RCP Malfunctions
STN BB-201
Exercise of BB HV-8157A and BB HV-8157B
STS BG-001
Boron Injection Flow Path Verification
STS KJ-005A
Manual/Auto Start, Sync and Loading of EDG NE01
67A
STS PE-004
Auxiliary Building and Control Room Pressure Test
SYS GK-122
Manual CRVIS Line-Up
SYS OPS-001
Weekly Equipment Rotation and Readings
80A
Drawings
Number
Title
Revision
E-13GG01
Schematic Diagram Emergency Exhaust Fans
E-13GG03
Schematic Diagram Emergency Exhaust Heating Coils
Drawings
Number
Title
Revision
E-13GG15
Schematic Diagram Emergency Exhaust Cross Connection
J-02GG14B (Q)
Fuel Building HVAC Spent Fuel Pool Normal/Emergency
Exhaust Radioactivity Sample Valve
M-12BB02
Piping & Instrumentation Diagram Reactor Coolant System
M-12BB03
Piping and Instrumentation Diagram Reactor Coolant System 15
M-12BG01
Piping & Instrumentation Diagram Chemical and Volume
Control System
M-12BL01
Piping & Instrumentation Diagram Reactor Make-Up Water
System
M-12GG01
Piping Instrumentation Diagram Fuel Building HVAC
M-12GT01
Piping & Instrumentation Diagram Containment Purge
Systems HVAC
M-12HB01
Piping and Instrumentation Diagram Liquid Radwaste
System
M-12LF01
Piping & Instrumentation Diagram Auxiliary Building Floor
and Equipment Drain System
M-12LF03
Piping & Instrumentation Diagram Auxiliary Building Floor
and Equipment Drain System
M-1H1531
Heating Ventilating and Air Cond. Auxiliary Building El. 2047-
Area-3
M-1H6311
Heating Ventilating & Air Cond. Fuel Building El. 2047-6 &
2065-0 Area 1
M-622.1A-00001 SGK05A & SGK05B Air Conditioner Refrigeration Schematic W12
M-622.1A-00002 SGK05A & SGK05B Air Conditioner Electrical Schematic
W13
M-622.1A-00003 SGK05A & SGK05B Air Conditioner Electrical Schematic
W09
M-622.1A-00257 Step Controllers
W01
M-712-00063
Reactor Coolant Pump Data Sheets
W04
M-OPIII
Embedded Drainage Systems (LF) Auxiliary Building EL.
1967-0 & 1974-0 Area I
Condition Reports
24199
90975
107789
110377
117283
118586
118587
118592
118827
118830
Condition Reports
118831
118910
118922
119069
119085
119330
119334
119442
119446
119487
119616
119822
119859
119860
119861
20053
20056
20071
20179
20181
20246
20287
20408
20409
20410
20411
20489
20535
20664
20722
Work Orders
16-411783-010
17-428518-000
18-436340-000
18-436340-002
Miscellaneous
Number
Title
Revision/Date
107363
Functional Failure Determination Checklist
October 12,
2016
118585
Function Failure Determination Checklist
January 28,
2018
AIF 10-001-02
SCBA Inspection
Completed
March 1, 2018
APF 05-002-05
Engineering Disposition - EDG Water, Lube Oil, and Fuel
Oil Leakage Guidance
APF 05C-004-01 Basic Engineering Disposition - Review of Regulatory and
License Basis Documents to evaluate the requirements of
Operability Determination when Safety Related or
Technical Specification Equipment is exposed to a hazard
APF 21-001-02
Control Room Turnover checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Night Shift
March 14,
2018
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment:
2018-0112
February 14,
2018
APF30B-004-01
Wolf Creek Nuclear Operating Corporation Essential
Required Reading - SBO Power Equipment Center (PEC)
April 1, 2018
GG-01
Maintenance Rule Final Scope Evaluation
Printed
March 22,
2018
GG-02
Maintenance Rule Final Scope Evaluation
Printed
March 22,
2018
Miscellaneous
Number
Title
Revision/Date
GG-03
Maintenance Rule Final Scope Evaluation
Printed
March 22,
2018
GG-04
Maintenance Rule Final Scope Evaluation
Printed
March 22,
2018
Section 1R19: Post-Maintenance Testing
Procedures
Number
Title
Revision
STN AL-201
Auxiliary Feedwater System Valve Test
STN EG-205A
Component Cooling Water System Valve Test
STS EG-100A
Component Cooling Water Pumps A/C [Air Conditioning]
Inservice Pump Test
33A
STS EG-208A
EG TV-029 CCW [Component Cooling Water] HX [Heat
Exchanger] A Temperature Control Valve Inservice Valve
Test
STS EJ-100A
RHR [Residual Heat Removal] System Inservice Pump A
Test
STS IC-540A
Channel Calibration Auxiliary Feedwater System Steam
Generator A
Drawings
Number
Title
Revision/Date
E-13GK13
Schematic Diagram Class 1E Electrical Equipment A/C [Air
Conditioning] Unit
M-12AL01
Piping & Instrumentation Diagram Auxiliary Feedwater
System
M-12AL01
Piping & Instrumentation Diagram Auxiliary Feedwater
System
M-622.1-00036
Electric Motor Data Sheet
March 3, 1977
M-622.1A-00002 SKG05A & SGK05B Air Conditioner Electrical Schematic
W13
M-622.1A-00142 SGK05A Terminal and Pressure Switch Enclosure Layout
W03
Condition Reports
118881
118901
118920
118953
118958
118959
118963
118964
119289
Work Orders
15-407137-000
Miscellaneous
Number
Title
Revision/Date
WCGS Standing Order 1 - Valve Setup and Operation
36121
Preventative Maintenance Work Instruction
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment
January 23,
2018
APF 29B-003-01 Surveillance Test Routing Sheet - Auxiliary Feedwater
System Valve Test
Completed
February 6,
2018
Section 1R20: Refueling and Other Outage Activities
Procedures
Number
Title
Revision
GEN 00-004
Power Operation
GEN 00-005
Minimum Load To Hot Standby
SYS AE-320
Turbine Driven Main Feedwater Pump Shutdown
28A
SYS AF-121
Heater Drain Pump Operation
Section 1R22: Surveillance Testing
Procedures
Number
Title
Revision
AP 23-009
Control Room Envelope Habitability Program
STS EG-100B
Component Cooling Water Pumps B/D Inservice Pump Test 29
STS IC-217
RCP Loss of Voltage and Underfrequency TADOT
15C
STS IC-915B
Channel Operational Test Train B Component Cooling
Water System Non-Nuclear Safety-Related Isolation
8A
STS IC-926A
Component Cooling Water System Automatic Valve
Actuation Train A
8A
Procedures
Number
Title
Revision
STS IC-926B
Component Cooling Water System Automatic Valve
Actuation Train B
6B
STS PE-004
Auxiliary Building and Control Room Pressure Test
Drawings
Number
Title
Revision
E-13EG01D
Schematic Diagram Component Cooling Water Pump D
E-13EG08A
Schematic Diagram Component Cooling Water Supply
Return From Radwaste Building
E-13EG11
Schematic Diagram Annunciation and Instrumentation
E-13EG20
Schematic Diagram Pass CCW Isolation Valves
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
Condition Reports
118493
118551
118552
119412
20061
20064
20148
20151
20408
20409
20410
20411
Work Orders
17-431050-000
17-431170-000
17-431759-000
17-432247-000
Miscellaneous
Number
Title
Date
APF 29B-003-01 Surveillance Test Routing Sheet - STS IC-217
Completed
March 5,
2018
APF 29B-003-01 Surveillance Test Routing Sheet - STS IC-926B
Completed
January 4,
2018
Miscellaneous
Number
Title
Date
APF 30B-004-01 Wolf Creek Nuclear Operating Corporation Essential
Required Reading: 18-0010 Accuracy of WCRE-35
March 7,
2018
Section 1EP6: Drill Evaluation
Procedures
Number
Title
Revision
EPP 06-006
Protective Action Recommendations
9A
Condition Reports
119869
119870
119871
119872
119874
119877
119878
119879
119883
119885
119886
119887
119888
119889
119897
119901
119903
119904
119906
119911
119941
20017
20227
20323
Miscellaneous
Number
Title
Revision/Date
18-SA-01
Wolf Creek Generating Station - Emergency Planning Drill
February 27,
2018
APF 06-002-01
Emergency Action Levels
17A
CR-001
Wolf Creek Generating Station Emergency Notification
(Drill)
February 27,
2018
EOF-001
Wolf Creek Generating Station Emergency Notification
(Drill)
February 27,
2018
EOF-002
Wolf Creek Generating Station Emergency Notification
(Drill)
February 27,
2018
EOF-003
Wolf Creek Generating Station Emergency Notification
(Drill)
February 27,
2018
EOF-004
Wolf Creek Generating Station Emergency Notification
(Drill)
February 27,
2018
TSC-001
Wolf Creek Generating Station Emergency Notification
(Drill)
February 27,
2018
Section 4OA1: Performance Indicator Verification
Miscellaneous
Number
Title
Revision
Regulatory Assessment Performance Indicator Guideline
Section 4OA2: Identification and Resolution of Problems
Procedures
Number
Title
Revision
STS MT-005
Pressurizer Code Safety Valve Operability
Drawings
Number
Title
Revision
M-1H1531
Heating Ventilating and Air Cond. Auxiliary Building El.
2047-6 Area-3
Condition Reports
90975
110377
2960
118910
119330
Work Orders
17-428518-001
Miscellaneous
Number
Title
Date
Email from NWS
Technologies to
Wolf Creek
<EXTERNAL> RE: Wolf Creek PSV failure - Questions
from our NRC Resident Inspector
November
30, 2017
P.O. # 692145
SR
Valve Serial Number N60446-00-0001; Traveler 14-381
Testing
Completed
January 2015
PO # 779245
Valve Serial Number N60446-00-0001; Traveler 17-41
Testing
Completed
August 2017
NRC Letter to
Otto L. Maynard
Wolf Creek Generating Station - Issuance of Amendment
RE: Pressurizer Safety Valves (TAC NO. MA6969)
March 23,
2000
White Paper
Pressurizer Safety Valve NRC Follow-up Questions and
Answers
White Paper
Why PZR Safety Valve Failure is NOT a Part 21 Issue
Initial Request for Information
Integrated Inspection
Wolf Creek Nuclear Generating Station
Inspection Report: 05000482/2018001
Inspection Dates: January 1 - March 31, 2018
Inspection Procedure: Integrated Inspection Procedures
Lead Inspector: Douglas Dodson, Senior Resident Inspector
I.
Information Requested Prior to December 22, 2017
The following information should be provided in electronic format (Certrec IMS
preferred), to the attention of Douglas Dodson by December 22, 2017, to facilitate the
reduction in the items to be selected for a final list during inspection preparation. The
inspection team will finalize its sample selections and will provide an additional
information request with specific items. This information shall be made available by
December 22, 2017. The specific items selected from the lists shall be available and
ready for review on the day indicated in this request. *Please provide requested
documentation electronically in pdf files, Excel, or other searchable formats, if possible.
The information should contain descriptive names, and be indexed and hyperlinked to
facilitate ease of use. Information in lists should contain enough information to be
easily understood by someone who has knowledge of pressurized water reactor
technology. If requested documents are large and/or only hard copy formats are
available, please inform the inspector(s), and provide subject documentation.
1. Any pre-existing evaluation or list of component cooling water system components
and associated calculations with low design margins.
2. A list of high risk component cooling water system maintenance rule components
and functions based on engineering or expert panel judgment.
3. A list of component cooling water system related operating experience evaluations
for the last 3 years.
4. A list of all component cooling water system time-critical operator actions in
procedures.
5. A list of permanent and temporary modifications related to component cooling water
system sorted by component.
6. A list of current component cooling water system related operator work
arounds/burdens.
7. A list of the component cooling water system design calculations, which provide the
design margin information for components.
8. List of component cooling water system root cause evaluations associated with
component failures or design issues initiated/completed in the last 5 years.
9. A list of any component cooling water system common-cause failures of
components in the last 3 years.
10. An electronic copy of the component cooling water system design bases documents
and any open, pending, or recently completed changes. Although not an exhaustive
list, please include any open, pending, or recently completed (last 3 years) changes
to temporary modifications, permanent modifications, engineering change
packages, and/or procedure change packages. Specifically, please include any
open, pending, or recently completed changes to emergency operating, abnormal
operating, normal operating, alarm response, system alignment, surveillance, or
other procedure.
11. An electronic copy of the component cooling water system System Health notebook.
2. A copy of component cooling water system related audits completed in the last 2
years.
13. A list of component cooling water system motor operated valves (MOVs) in the
program, design margin and risk ranking.
14. A list of component cooling water system air operated valves (AOVs) in the valve
program, design margin and risk ranking.
15. Component cooling water system structure, system, and components maintenance
rule category, scoping, unavailability data, unreliability data, functional failure
evaluations, (a)(1) determinations, (a)(1) goals, and any supporting basis
documentation.
16. A list of component cooling water system licensee contacts for the inspection team
with pager or phone numbers.
17. An excel spreadsheet of component cooling water system related PRA human
action basic events or risk ranking of operator actions from your site specific PSA
sorted by RAW and FV. Provide copies of your human reliability worksheets for
these items.
18. In so far as there are recent or pending changes, please provide an Excel
spreadsheet of component cooling water system related equipment basic events
(with definitions) including importance measures sorted by risk achievement worth
(RAW) and Fussell-Vesely (FV) from your internal events probabilistic risk
assessment (PRA). Include basic events with RAW value of 1.3 or greater.
19. In so far as there are recent or pending changes, please provide a list of the top 50
cut-sets from your PRA.
20. In so far as there are recent or pending changes, please provide copies of PRA
system notebooks, and the latest PRA summary document.
21. In so far as there are recent or pending changes, and if you have an external events
or fire PSA model, provide the information requested in items 17-19 for external
events and fire, as it relates to the component cooling water system.
2. In so far as there are recent or pending changes, please provide a copy of the Wolf
Creek Nuclear Generating Station IPEEE changes, if available electronically.
SUNSI Review:
ADAMS:
Non-Publicly Available
Non-Sensitive
Keyword:
By: NHT/rdr
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
JDrake
SIGNATURE
/RA/
/RA/
/RA/
/RA/
/RA/
/RA/
DATE
5/9/2018
5/10/18
5/3/18
5/3/18
5/3/2018
5/9/18
OFFICE
TL:DRS/IPAT
SRI/DRP/B
BC:DRP/B
NAME
GGeorge
DBradley
NTaylor
SIGNATURE
/RA -
HFreeman for/
/RA/
/RA/
DATE
5/10/18
5/7/18
5/14/18
May 14, 2018
Mr. Adam
- C. Heflin, President
and Chief Executive Officer
Wolf Creek Nuclear Operating Corporation
P.O. Box 411
Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION - NRC INTEGRATED INSPECTION
REPORT 05000482/2018001
Dear Mr. Heflin:
On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection
at your Wolf Creek Generating Station. On April 25, 2018, the NRC inspectors discussed the
results of this inspection with Mr.
- C. Reasoner, Site Vice President, and other members of your
staff. The results of this inspection are documented in the enclosed report.
NRC inspectors documented one finding of very low safety significance (Green) in this report.
This finding involved a violation of NRC requirements. The NRC is treating this violation as a
non-cited violation consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or significance of this non-cited violation, 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.
A. Heflin
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 05000482/2018001
w/ Attachments:
1. Supplemental Information
2. Request for Information
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number:
05000482
License Number:
Report Number:
Enterprise Identifier: I-2018-001-0012
Licensee:
Wolf Creek Nuclear Operating Corporation
Facility:
Wolf Creek Generating Station
Location:
1550 Oxen Lane NE
Burlington, KS 66839
Inspection Dates:
January 1, 2018, to March 31, 2018
Inspectors:
- D. Dodson, Senior Resident Inspector
- F. Thomas, Resident Inspector
- D. Bradley, Senior Resident Inspector, Callaway
Approved By:
- N. Taylor, Chief, Project Branch B, Division of Reactor Projects
SUMMARY
The 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.
List of Findings and Violations
Inadequate Functionality Assessment Associated with the Emergency Excess Letdown
Flowpath
Cornerstone
Significance
Cross-cutting Aspect Report Section
Mitigating
Systems
Green
Closed
[H.14] - Human
Performance,
Conservative Bias
71111.15 -
Operability
Determinations
and Functionality
Assessments
The inspectors identified a Green finding and associated non-cited violation of 10 CFR Part 50,
Appendix B, Criterion V, Instructions, Procedures, and Drawings, when the licensee failed to
adequately implement the operability determination and functionality assessment procedure.
Specifically, the licensee failed to document a functionality assessment of sufficient scope to
address the capability of a safety-related excess letdown heat exchanger to pressurizer relief
tank isolation valve and the excess letdown system to perform their specified safety functions,
which resulted in the licensee failing to recognize that two independent Technical
Requirements Manual required boration injection subsystems were not functional.
PLANT STATUS
Wolf Creek Generating Station began the inspection period at rated thermal power. On
March 30, 2018, a plant shutdown was completed to begin Refueling Outage 22.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in
effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with
their attached revision histories are located on the public website at http://www.nrc.gov/reading-
rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared
complete when the IP requirements most appropriate to the inspection activity were met
consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection
Program - Operations Phase. The inspectors 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
71111.01 - Adverse Weather Protection
Impending Severe Weather (1 Sample)
The inspectors evaluated readiness for impending adverse weather conditions for extreme
low temperatures on January 2 and 3, 2018.
71111.04 - Equipment Alignment
Partial Walkdown (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following
systems/trains:
(1) turbine-driven auxiliary feedwater train on February 6, 2018
(2) residual heat removal pump B on March 21, 2018
Complete Walkdown (1 Sample)
The inspectors evaluated system configurations during a complete walkdown of the
component cooling water system on February 23, 2018.
71111.05AQ - Fire Protection Annual/Quarterly
Quarterly Inspection (5 Samples)
The inspectors evaluated fire protection program implementation in the following selected
areas:
(1) fire area A-16, general area, elevation 2,026 feet on January 30, and March 28, 2018
(2) fire area A-18, electrical penetration room (north), elevation 2,026 feet on January 30,
2018
(3) fire area A-17, electrical penetration room (south), elevation 2,026 feet on March 28,
2018
(4) fire area A-26, decontamination area for I&C shop, elevation 2,026 feet on March 28,
2018
(5) fire area A-27, reactor trip switchgear, motor-generator sets, load centers, rod control
and rod-drive power supply control cabinets 125 volt direct current panel on March 28,
2018.
71111.06 - Flood Protection Measures
Internal Flooding (1 Sample)
The inspectors evaluated internal flooding mitigation protections in rooms 1203 and 1203A,
Pipe Space B on January 9, 2018.
71111.07 - Heat Sink Performance
Heat Sink (1 Sample)
The inspectors evaluated containment spray train A room cooler (SGL13A) performance on
January 17, 2018.
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance
Operator Requalification (1 Sample)
The inspectors observed and evaluated licensed operator simulator requalification activities
that included a loss of all alternating current power during shutdown scenario on February 22,
2018.
Operator Performance (1 Sample)
The inspectors observed and evaluated operator performance during end of life core moderator
temperature coefficient measurement activities on February 5, 2018.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness (1 Sample)
The inspectors evaluated the effectiveness of routine maintenance activities associated
with the following equipment and/or safety significant functions:
Auxiliary building heating ventilation and air conditioning (GL) system including safety-
related pump and electrical penetration room coolers on January 29, 2018.
71111.13 - Maintenance Risk Assessments and Emergent Work Control (5 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent
work activities:
(1) reactor partial trip alarm troubleshooting and main generator transformer B loss of two
cooling groups on January 4, 2018
(2) emergent maintenance on Class 1E electrical equipment air conditioning unit train A on
January 24, 2018
(3) planned maintenance on component cooling water train B on March 5, 2018
(4) emergent maintenance associated with the failed control room envelope pressure test
on March 6, 2018
(5) emergent maintenance on Class 1E electrical equipment air conditioning unit train B on
March 12, 2018.
71111.15 - Operability Determinations and Functionality Assessments (8 Samples)
The inspectors evaluated the following operability determinations and functionality
assessments:
(1) auxiliary building elevation 1988 foot south pipe chase drain functionality with three
clogged floor drains on January 10, 2018
(2) 125 volt direct current to 120 volt alternating current NN15 inverter operability after a
high voltage alarm would not clear on January 18, 2018
(3) emergency diesel generator A lubrication oil leakage on January 31, 2018
(4) Class 1E electrical equipment air conditioning unit train B operability following a step
controller failure on February 12, 2018
(5) reactor coolant pump A standpipe not filling on the expected frequency on February 25,
2018
(6) Technical Specification 3.7.10 mitigating actions to ensure the control room envelope
occupant radiological exposures would not exceed limits and control room envelope
occupants are protected from chemical and smoke hazards while the control room
envelope was inoperable on March 6, 2018
(7) excess letdown heat exchanger outlet to pressurizer relief tank isolation valve
functionality after failed stoke testing on March 12, 2018
(8) station blackout diesel generator functionality after post maintenance testing on
March 20, 2018.
71111.19 - Post Maintenance Testing (4 Samples)
The inspectors evaluated the following post maintenance tests:
(1) Class 1E electrical equipment air conditioning unit train A following planned maintenance
on January 24, 2018
(2) motor-driven auxiliary feedwater train B pump discharge to steam generators A and D
auxiliary feed water flow regulating valve testing following planned maintenance on
February 6, 2018
(3) component cooling water pump A following planned maintenance on February 15, 2018
(4) residual heat removal pump A following planned maintenance on March 21, 2018.
71111.20 - Refueling and Other Outage Activities (Partial Sample)
The inspectors evaluated Refueling Outage 22 activities from March 30 to 31, 2018. The
inspectors completed inspection procedure Sections 03.01.a, 03.01.b, and 03.01.c.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Routine (5 Samples)
(1) STS IC-926B, Component Cooling Water System Automatic Valve Actuation Train B,
Revision 6B, on January 4, 2018
(2) STS IC-915B, Channel Operational Test Train B Component Cooling Water System
Non-Nuclear Safety-Related Isolation, Revision 8A, on January 8, 2018
(3) STS IC-926A, Component Cooling Water System Automatic Valve Actuation Train A,
Revision 8A, on February 12, 2018
(4) STS IC-217, [Reactor Coolant Pump] Loss of Voltage and Underfrequency [Trip
Actuation Device Operational Testing], on March 5, 2018
(5) STS PE-004, Auxiliary Building and Control Room Pressure Tests, Revision 16, on
March 5 and March 12, 2018.
71114.06 - Drill Evaluation
Emergency Planning Drill (1 Sample)
The inspectors evaluated the emergency preparedness drill on February 27, 2018.
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification (3 Samples)
The inspectors verified licensee performance indicator submittals listed below:
(1) IE01: Unplanned Scrams per 7000 Critical Hours Sample (01/01/2017-12/31/2017)
(2) IE03: Unplanned Power Changes per 7000 Critical Hours Sample (01/01/2017-
2/31/2017)
(3) IE04: Unplanned Scrams with Complications (USwC) Sample (01/01/2017-12/31/2017).
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program
related to the following issues:
(1) On February 8, 2018, the unit vent tornado damper failed to meet acceptance criteria for
initial breakaway torque. This issue was documented in Condition Report 119330.
(2) On May 11, 2017, Condition Report 112960 documented that pressurizer safety valve
88010As as-found lift setting was 3.2 percent below the nominal setpoint.
INSPECTION RESULTS
Inadequate Functionality Assessment Associated with the Emergency Excess Letdown
Flowpath
Cornerstone
Significance
Cross-cutting Aspect
Report Section
Mitigating
Systems
Green
Closed
[H.14] - Human
Performance,
Conservative Bias
71111.15 -
Operability
Determinations
and Functionality
Assessments
The inspectors identified a Green finding and associated non-cited violation of 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, when the licensee
failed to adequately implement the operability determination and functionality assessment
procedure. Specifically, the licensee failed to document a functionality assessment of
sufficient scope to address the capability of a safety-related excess letdown heat exchanger
to pressurizer relief tank isolation valve and the excess letdown system to perform their
specified safety functions, which resulted in the licensee failing to recognize that two
independent Technical Requirements Manual required boration injection subsystems were
not functional.
Description: On March 12, 2018, the licensee was performing Procedure STN BB-201,
Exercise of BB HV-8157A and BB HV-8157B, Revision 3, which tests and exercises the
excess letdown heat exchanger to pressurizer relief tank isolation valves (BB HV-8157A and
BB HV-8157B). The BB HV-8157B valve did not stroke fully closed as expected. Step 6.1.1
of Procedure STN BB-201 states, If the valve cannot be fully exercised, then valve shall be
declared inoperable and corrective action initiated.
Condition Report 120287 was documented on March 12, 2018, reporting the valve
failure. The immediate functionality assessment stated, The redundant path of
excess letdown is still available. The system is functional but degraded. The system
functionality is maintained by having a second redundant flow path for excess
letdown. The inspectors noted that Section 6.4.7 of Procedure AP 26C-004,
Operability Determination and Functionality Assessment, Revision 35, states, The
scope of a functionality assessment must be sufficient to address the capability of
SSCs to perform their specified functionsThe following things should be considered
when performing functionality assessments: codes, standards and system
requirements controlling the SSC.
The inspectors questioned the licensee concerning the immediate functionality
determinations adequacy, and the licensee revised the functionality determination for the
excess letdown heat exchanger to pressurizer relief tank isolation valve (8157B) and changed
the determination to non-functional. The immediate functionality determination was updated
to state:
The above screening gives an adequate justification for why the excess
letdown po[r]tion of the [chemical and volume control system] remains
functional but degraded. However, screening should be based on the
component, not the system. Since BBHV8157B cannot be relied upon to go to
the closed position using normal remote controls, the valve is considered
nonfunctional. The system remains functional but degraded.
The inspectors also noted that Section 3.1.9, Boration Injection System - Operating, of the
Technical Requirements Manual, requires two boration injection subsystems to be functional
in MODES 1, 2, and 3. Section 3.1.9 of the Technical Requirements Manual Bases describes
what is required for a boration injection subsystem to be considered functional. Specifically,
both subsystems require the safety-related excess letdown flow path. Also, two independent
boration injection subsystems are required to ensure single functional capability in the event
an assumed failure renders one of the boration injection subsystems nonfunctional.
Updated Safety Analysis Report Section 7.4.3.3 describes the applicable single failure
analysis. It states, The capability of the [residual heat removal system] to accommodate a
single component failure and still perform a safety grade cooldown is demonstrated in the
failure mode and effects analysis (FMEA) of the [residual heat removal] system for safety-
related cold shutdown operations provided as Table 7.4-4. Table 7.4-4, Residual Heat
Removal - Safety Related Cold Shutdown Operations - Failure Modes and Effects Analysis
(FMEA), describes the function of the excess letdown to pressurizer relief tank isolation
valves (8157A and 8157B), stating, Provides safety grade letdown flow path. Hence, in
order for the safety-related excess letdown flowpath to the pressurizer relief tank to meet its
safety function, either 8157A or 8157B must be functional and capable of opening.
The inspectors again questioned the updated immediate functionality determinations
adequacy. Specifically, considering that 8157A and 8157B are parallel valves, that 8157B
was non-functional, and assuming a design basis single failure (for example, assume 8157A
fails to open or its power supply fails), the safety-related excess letdown flowpath would be
non-functional, and both Technical Requirements Manual independent boration injection
subsystems would be impacted. With the excess letdown heat exchanger to pressurizer relief
tank isolation valve 8157B non-functional, current language in the Technical Requirements
Manual would require one boration injection subsystem to be declared non-functional.
Corrective Actions: On March 20, 2018, the licensee changed the functionality assessment
the excess letdown heat exchanger to pressurizer relief tank isolation valve (8157B) was
determined to be non-functional. In response to the inspectors questions concerning system
functionality and design basis information, the licensee initiated Condition Reports 120628
and 120822. The licensee restored the B train excess letdown heat exchanger to pressurizer
relief tank isolation valve to service on April 9, 2018.
Corrective Action References: Condition Reports 120287, 120628, 120822 and 122411.
Performance Assessment:
Performance Deficiency: The licensee failed to document a functionality assessment of
sufficient scope to address the capability of the safety-related excess letdown heat exchanger
to pressurizer relief tank isolation valve and excess letdown system to perform their specified
safety functions.
Screening: The inspectors determined the performance deficiency was more than minor
because it adversely affected the equipment performance attribute of the Mitigating Systems
Cornerstone objective to ensure the availability, reliability, and capability of systems that
respond to initiating events to prevent undesirable consequences (i.e., core damage).
Specifically, the safety-related excess letdown heat exchanger to pressurizer relief tank
isolation valve and excess letdown system were inappropriately determined to be functional
but degraded and non-conforming, which resulted in the licensee failing to recognize that two
independent Technical Requirements Manual required boration injection subsystems were
not functional.
Significance: The inspectors assessed the significance of the finding using Exhibit 2,
Mitigating Systems 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 is not a deficiency affecting the design or qualification of a
mitigating SSC that maintained its operability or functionality; the finding does not represent a
loss of system and/or function; the finding does not represent an actual loss of function of at
least a single train for greater than its Technical Specification-allowed outage time; and the
finding does not represent an actual loss of function of one or more non-Technical
Specification trains of equipment designated as high safety-significant. 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, and a
proposed action was not determined to be safe in order to proceed, rather than unsafe in
order to stop. Specifically, leaders did not take a conservative approach to decision making,
particularly when information was incomplete or conditions were unusual when completing
the functionality determination associated with the subject valve and system, which resulted
in the valve and system being determined to be functional.
Enforcement:
Violation: Title 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and
Drawings, requires, in part, that activities affecting quality shall be accomplished in
accordance with documented instructions, procedures, or drawings of a type appropriate to
the circumstances. Licensee Procedure AP 26C-004, Operability Determination and
Functionality Assessment, Revision 35, an Appendix B quality related procedure, provides
instructions for performing functionality assessments. Procedure AP 26C-004, Section 6.4.7,
states, in part, that the scope of a functionality assessment must be sufficient to address the
capability of SSCs to perform their specified functions, and codes, standards, and system
requirements controlling the SSC should be considered when performing functionality
assessments.
Contrary to the above, from March 12, 2018, until April 9, 2018, the scope of a functionality
assessment was not sufficient to address the capability of SSCs to perform their specified
functions, and codes, standards, and system requirements controlling the SSC were not
considered when performing functionality assessments. Specifically, the functionality
assessment associated with the excess letdown heat exchanger outlet to pressurizer relief
tank isolation valve and excess letdown system was not adequate and did not adequately
consider design basis information, which caused the licensee to fail to identify non-
functionality of safety-related SSCs.
Disposition: This violation is being treated as a non-cited violation, consistent with
Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On April 25, 2018, the inspector presented the quarterly resident inspector inspection results to
Mr.
- C. Reasoner, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Section 1R01: Adverse Weather Protection
Procedures
Number
Title
Revision
SYS EF-205
ESW/Circ Water Cold Weather Operations
Miscellaneous
Number
Title
Date
96-0316
Performance Improvement Request
Initiated
February 5,
1996
2006-0006
Performance Improvement Request
Initiated
January 4,
2006
APF 15C-002-01 Procedure Cover Sheet - ESW/Circ Water Cold Weather
Operations - SYS EF-205
Completed
December 26,
2017
APF 15C-002-01 Procedure Cover Sheet - ESW/Circ Water Cold Weather
Operations - SYS EF-205
Completed
January 2,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Day Shift
January 19,
2018
APF 29B-003-01 Surveillance Test Routing Sheet - ESW Train B Warming
Line Verification - STN EF-020B
Completed
January 3,
2018
Docket No 50-482: Response to Enforcement Action
EA 96-124
July 31, 1996
Section 1R04: Equipment Alignment
Procedures
Number
Title
Revision
CKL Al-120
Auxiliary Feedwater Normal Lineup
CKL EG-120
Component Cooling Water System Valve, Switch and
Breaker Lineup
CKL EJ-120
RHR System Lineup
45B
Drawings
Number
Title
Revision
M-06EG07
Component Coolant Wtr. Sys. Aux. Bldg.
M-12AL01
Piping & Instrumentation Diagram Auxiliary Feedwater
System
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
M-12EJ01
Piping and Instrumentation Diagram Residual Heat
Removal System
M-12FC02
Piping & Instrumentation Diagram Auxiliary Feedwater
Pump Turbine
M-13EG07
Piping Isometric Component Cooling Water Sys. Aux. Bldg.
Common Header
M-15EG07
Hanger Location Drawing Component Cooling Water Sys
Aux. Bldg. Common Header
Condition Reports
119280
119401
20586
Section 1R05: Fire Protection
Procedures
Number
Title
Revision
AP 10-106
Fire Preplans
18A
CKL ZL-001
Auxiliary Building Reading Sheets
103
Condition Reports
119366
20782
20783
20784
Miscellaneous
Number
Title
Revision
E-1F9905
Fire Hazard Analysis
XX-X-004
Calculation Cover Sheet - Combustible Fire Loading For
Each Room In The Various Fire Areas at WCNOC
Section 1R06: Flood Protection Measures
Procedures
Number
Title
Revision
ALR 00-094F
Misc Sumps Lev Hi
Drawings
Number
Title
Revision
M-12EJ01
Piping and Instrumentation Diagram Residual Heat
Removal System
M-13LF02
Piping Isometric Sump Discharge Auxiliary Bldg.
Condition Reports
118576
118586
118587
118592
118593
Miscellaneous
Number
Title
Revision
FL-03
Flooding of Individual Auxiliary Building Rooms
Section 1R07: Heat Sink Performance
Procedures
Number
Title
Revision
Heat Exchanger Program
Work Orders
17-428729-000
17-428729-002
17-428729-003
17-428729-005
17-428737-000
Miscellaneous
Number
Title
Date
GL-05
Maintenance Rule Final Scope Evaluation
Printed
March 27,
2018
Section 1R11: Licensed Operator Requalification Program
Procedures
Number
Title
Revision
AP 21-001
Conduct of Operations
STS RE-006
EOL Core MTC Measurement
20B
Power Range Adjustment to Calorimetric
Miscellaneous
Number
Title
Revision/Date
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Day Shift
February 2,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Day Shift
February 3,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Night Shift
February 3,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Night Shift
February 4,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Night Shift
February 5,
2018
APF 29B-003-01 Surveillance Test Routing Sheet - EOL Core MTC
Measurement
Completed
February 5,
2018
EPF 06-007-01
Wolf Creek Generating Station Emergency Notification
(Drill)
February 22,
2018
LR5004005
Loss of All AC While Shutdown - Licensed Operator
Requal
Section 1R12: Maintenance Effectiveness
Drawings
Number
Title
Revision/Date
M-12GL01
Piping and Instrumentation Diagram Auxiliary Building
M-612.00062
Carrier Air Handling Units and Room Coolers
Imaged May
2017
Condition Reports
10539
114660
117759
Miscellaneous
Number
Title
Date
GL Room Cooler PM Schedule
Maintenance Rule Expert Panel Meeting Agenda
November 1,
2017
114660
Functional Failure Determination Checklist
August 17,
2017
GL-01
Maintenance Rule Final Scope Evaluation
Printed
January 29,
2018
GL-02
Maintenance Rule Final Scope Evaluation
Printed
January 29,
2018
GL-03
Maintenance Rule Final Scope Evaluation
Printed
January 29,
2018
GL-04
Maintenance Rule Final Scope Evaluation
Printed
January 29,
2018
GL-05
Maintenance Rule Final Scope Evaluation
Printed
January 29,
2018
GL-06
Maintenance Rule Final Scope Evaluation
Printed
January 29,
2018
GL-07
Maintenance Rule Final Scope Evaluation
Printed
January 29,
2018
GL-08
Maintenance Rule Final Scope Evaluation
Printed
January 29,
2018
GL-09
Maintenance Rule Final Scope Evaluation
Printed
January 29,
2018
Section 1R13: Maintenance Risk Assessment and Emergent Work Controls
Procedures
Number
Title
Revision
On-Line Nuclear Safety and Generation Risk Assessment
Procedures
Number
Title
Revision
OFN AF-025
Unit Limitations
STS BB-201B
Cycle Test of PORV Block Valve BB HV-800B
STS IC-447
Channel Calibration Nuclear Instrumentation System Power
Range Incore-Excore
STS MT-024B
Functional Test of 480 and 120 Volt Molded Case Circuit
Breakers
Drawings
Number
Title
Revision
M-622.1A-00142 SGK05A Terminal and Pressure Switch Enclosure Layout
W03
Condition Reports
118499
118938
118939
118940
118953
118958
118959
118963
118964
Work Orders
17-422791-003
17-427320-000
18-434985-000
18-435758-000
18-435758-001
Miscellaneous
Number
Title
Date
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Day Shift
January 23,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Night Shift
January 23,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Day Shift
January 24,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Night Shift
January 24,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Night Shift
January 25,
2018
APF 21-001-02
Control Room Turnover Checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Night Shift
January 26,
2018
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment:
18-0101
January 4,
2018
Miscellaneous
Number
Title
Date
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment:
18-0111
March 13,
2018
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment:
2018-0110
February 15,
2018
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment:
2018-0104
January 10,
2018
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment -
2018-0122
February 14,
2018
APF 29B-003-01 Surveillance Test Routing Sheet - STS IC-447
Completed
January 4,
2018
APF 29B-003-01 Surveillance Test Routing Sheet - STS PE-004 (Train B)
Completed
March 7,
2018
Section 1R15: Operability Evaluations
Procedures
Number
Title
Revision
AI 16C-006
Troubleshooting
AI 28B-005
Evidence and Action Matrix
AP 12-003
Operability Determination and Functionality Assessment
OFN BB-005
RCP Malfunctions
STN BB-201
Exercise of BB HV-8157A and BB HV-8157B
STS BG-001
Boron Injection Flow Path Verification
STS KJ-005A
Manual/Auto Start, Sync and Loading of EDG NE01
67A
STS PE-004
Auxiliary Building and Control Room Pressure Test
SYS GK-122
Manual CRVIS Line-Up
SYS OPS-001
Weekly Equipment Rotation and Readings
80A
Drawings
Number
Title
Revision
E-13GG01
Schematic Diagram Emergency Exhaust Fans
E-13GG03
Schematic Diagram Emergency Exhaust Heating Coils
Drawings
Number
Title
Revision
E-13GG15
Schematic Diagram Emergency Exhaust Cross Connection
J-02GG14B (Q)
Fuel Building HVAC Spent Fuel Pool Normal/Emergency
Exhaust Radioactivity Sample Valve
M-12BB02
Piping & Instrumentation Diagram Reactor Coolant System
M-12BB03
Piping and Instrumentation Diagram Reactor Coolant System 15
M-12BG01
Piping & Instrumentation Diagram Chemical and Volume
Control System
M-12BL01
Piping & Instrumentation Diagram Reactor Make-Up Water
System
M-12GG01
Piping Instrumentation Diagram Fuel Building HVAC
M-12GT01
Piping & Instrumentation Diagram Containment Purge
Systems HVAC
M-12HB01
Piping and Instrumentation Diagram Liquid Radwaste
System
M-12LF01
Piping & Instrumentation Diagram Auxiliary Building Floor
and Equipment Drain System
M-12LF03
Piping & Instrumentation Diagram Auxiliary Building Floor
and Equipment Drain System
M-1H1531
Heating Ventilating and Air Cond. Auxiliary Building El. 2047-
Area-3
M-1H6311
Heating Ventilating & Air Cond. Fuel Building El. 2047-6 &
2065-0 Area 1
M-622.1A-00001 SGK05A & SGK05B Air Conditioner Refrigeration Schematic W12
M-622.1A-00002 SGK05A & SGK05B Air Conditioner Electrical Schematic
W13
M-622.1A-00003 SGK05A & SGK05B Air Conditioner Electrical Schematic
W09
M-622.1A-00257 Step Controllers
W01
M-712-00063
Reactor Coolant Pump Data Sheets
W04
M-OPIII
Embedded Drainage Systems (LF) Auxiliary Building EL.
1967-0 & 1974-0 Area I
Condition Reports
24199
90975
107789
110377
117283
118586
118587
118592
118827
118830
Condition Reports
118831
118910
118922
119069
119085
119330
119334
119442
119446
119487
119616
119822
119859
119860
119861
20053
20056
20071
20179
20181
20246
20287
20408
20409
20410
20411
20489
20535
20664
20722
Work Orders
16-411783-010
17-428518-000
18-436340-000
18-436340-002
Miscellaneous
Number
Title
Revision/Date
107363
Functional Failure Determination Checklist
October 12,
2016
118585
Function Failure Determination Checklist
January 28,
2018
AIF 10-001-02
SCBA Inspection
Completed
March 1, 2018
APF 05-002-05
Engineering Disposition - EDG Water, Lube Oil, and Fuel
Oil Leakage Guidance
APF 05C-004-01 Basic Engineering Disposition - Review of Regulatory and
License Basis Documents to evaluate the requirements of
Operability Determination when Safety Related or
Technical Specification Equipment is exposed to a hazard
APF 21-001-02
Control Room Turnover checklist - On-Coming CRS/WC
SRO/RO/BOP Review - Night Shift
March 14,
2018
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment:
2018-0112
February 14,
2018
APF30B-004-01
Wolf Creek Nuclear Operating Corporation Essential
Required Reading - SBO Power Equipment Center (PEC)
April 1, 2018
GG-01
Maintenance Rule Final Scope Evaluation
Printed
March 22,
2018
GG-02
Maintenance Rule Final Scope Evaluation
Printed
March 22,
2018
Miscellaneous
Number
Title
Revision/Date
GG-03
Maintenance Rule Final Scope Evaluation
Printed
March 22,
2018
GG-04
Maintenance Rule Final Scope Evaluation
Printed
March 22,
2018
Section 1R19: Post-Maintenance Testing
Procedures
Number
Title
Revision
STN AL-201
Auxiliary Feedwater System Valve Test
STN EG-205A
Component Cooling Water System Valve Test
STS EG-100A
Component Cooling Water Pumps A/C [Air Conditioning]
Inservice Pump Test
33A
STS EG-208A
EG TV-029 CCW [Component Cooling Water] HX [Heat
Exchanger] A Temperature Control Valve Inservice Valve
Test
STS EJ-100A
RHR [Residual Heat Removal] System Inservice Pump A
Test
STS IC-540A
Channel Calibration Auxiliary Feedwater System Steam
Generator A
Drawings
Number
Title
Revision/Date
E-13GK13
Schematic Diagram Class 1E Electrical Equipment A/C [Air
Conditioning] Unit
M-12AL01
Piping & Instrumentation Diagram Auxiliary Feedwater
System
M-12AL01
Piping & Instrumentation Diagram Auxiliary Feedwater
System
M-622.1-00036
Electric Motor Data Sheet
March 3, 1977
M-622.1A-00002 SKG05A & SGK05B Air Conditioner Electrical Schematic
W13
M-622.1A-00142 SGK05A Terminal and Pressure Switch Enclosure Layout
W03
Condition Reports
118881
118901
118920
118953
118958
118959
118963
118964
119289
Work Orders
15-407137-000
Miscellaneous
Number
Title
Revision/Date
WCGS Standing Order 1 - Valve Setup and Operation
36121
Preventative Maintenance Work Instruction
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment
January 23,
2018
APF 29B-003-01 Surveillance Test Routing Sheet - Auxiliary Feedwater
System Valve Test
Completed
February 6,
2018
Section 1R20: Refueling and Other Outage Activities
Procedures
Number
Title
Revision
GEN 00-004
Power Operation
GEN 00-005
Minimum Load To Hot Standby
SYS AE-320
Turbine Driven Main Feedwater Pump Shutdown
28A
SYS AF-121
Heater Drain Pump Operation
Section 1R22: Surveillance Testing
Procedures
Number
Title
Revision
AP 23-009
Control Room Envelope Habitability Program
STS EG-100B
Component Cooling Water Pumps B/D Inservice Pump Test 29
STS IC-217
RCP Loss of Voltage and Underfrequency TADOT
15C
STS IC-915B
Channel Operational Test Train B Component Cooling
Water System Non-Nuclear Safety-Related Isolation
8A
STS IC-926A
Component Cooling Water System Automatic Valve
Actuation Train A
8A
Procedures
Number
Title
Revision
STS IC-926B
Component Cooling Water System Automatic Valve
Actuation Train B
6B
STS PE-004
Auxiliary Building and Control Room Pressure Test
Drawings
Number
Title
Revision
E-13EG01D
Schematic Diagram Component Cooling Water Pump D
E-13EG08A
Schematic Diagram Component Cooling Water Supply
Return From Radwaste Building
E-13EG11
Schematic Diagram Annunciation and Instrumentation
E-13EG20
Schematic Diagram Pass CCW Isolation Valves
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
Condition Reports
118493
118551
118552
119412
20061
20064
20148
20151
20408
20409
20410
20411
Work Orders
17-431050-000
17-431170-000
17-431759-000
17-432247-000
Miscellaneous
Number
Title
Date
APF 29B-003-01 Surveillance Test Routing Sheet - STS IC-217
Completed
March 5,
2018
APF 29B-003-01 Surveillance Test Routing Sheet - STS IC-926B
Completed
January 4,
2018
Miscellaneous
Number
Title
Date
APF 30B-004-01 Wolf Creek Nuclear Operating Corporation Essential
Required Reading: 18-0010 Accuracy of WCRE-35
March 7,
2018
Section 1EP6: Drill Evaluation
Procedures
Number
Title
Revision
EPP 06-006
Protective Action Recommendations
9A
Condition Reports
119869
119870
119871
119872
119874
119877
119878
119879
119883
119885
119886
119887
119888
119889
119897
119901
119903
119904
119906
119911
119941
20017
20227
20323
Miscellaneous
Number
Title
Revision/Date
18-SA-01
Wolf Creek Generating Station - Emergency Planning Drill
February 27,
2018
APF 06-002-01
Emergency Action Levels
17A
CR-001
Wolf Creek Generating Station Emergency Notification
(Drill)
February 27,
2018
EOF-001
Wolf Creek Generating Station Emergency Notification
(Drill)
February 27,
2018
EOF-002
Wolf Creek Generating Station Emergency Notification
(Drill)
February 27,
2018
EOF-003
Wolf Creek Generating Station Emergency Notification
(Drill)
February 27,
2018
EOF-004
Wolf Creek Generating Station Emergency Notification
(Drill)
February 27,
2018
TSC-001
Wolf Creek Generating Station Emergency Notification
(Drill)
February 27,
2018
Section 4OA1: Performance Indicator Verification
Miscellaneous
Number
Title
Revision
Regulatory Assessment Performance Indicator Guideline
Section 4OA2: Identification and Resolution of Problems
Procedures
Number
Title
Revision
STS MT-005
Pressurizer Code Safety Valve Operability
Drawings
Number
Title
Revision
M-1H1531
Heating Ventilating and Air Cond. Auxiliary Building El.
2047-6 Area-3
Condition Reports
90975
110377
2960
118910
119330
Work Orders
17-428518-001
Miscellaneous
Number
Title
Date
Email from NWS
Technologies to
Wolf Creek
<EXTERNAL> RE: Wolf Creek PSV failure - Questions
from our NRC Resident Inspector
November
30, 2017
P.O. # 692145
SR
Valve Serial Number N60446-00-0001; Traveler 14-381
Testing
Completed
January 2015
PO # 779245
Valve Serial Number N60446-00-0001; Traveler 17-41
Testing
Completed
August 2017
NRC Letter to
Otto L. Maynard
Wolf Creek Generating Station - Issuance of Amendment
RE: Pressurizer Safety Valves (TAC NO. MA6969)
March 23,
2000
White Paper
Pressurizer Safety Valve NRC Follow-up Questions and
Answers
White Paper
Why PZR Safety Valve Failure is NOT a Part 21 Issue
Initial Request for Information
Integrated Inspection
Wolf Creek Nuclear Generating Station
Inspection Report: 05000482/2018001
Inspection Dates: January 1 - March 31, 2018
Inspection Procedure: Integrated Inspection Procedures
Lead Inspector: Douglas Dodson, Senior Resident Inspector
I.
Information Requested Prior to December 22, 2017
The following information should be provided in electronic format (Certrec IMS
preferred), to the attention of Douglas Dodson by December 22, 2017, to facilitate the
reduction in the items to be selected for a final list during inspection preparation. The
inspection team will finalize its sample selections and will provide an additional
information request with specific items. This information shall be made available by
December 22, 2017. The specific items selected from the lists shall be available and
ready for review on the day indicated in this request. *Please provide requested
documentation electronically in pdf files, Excel, or other searchable formats, if possible.
The information should contain descriptive names, and be indexed and hyperlinked to
facilitate ease of use. Information in lists should contain enough information to be
easily understood by someone who has knowledge of pressurized water reactor
technology. If requested documents are large and/or only hard copy formats are
available, please inform the inspector(s), and provide subject documentation.
1. Any pre-existing evaluation or list of component cooling water system components
and associated calculations with low design margins.
2. A list of high risk component cooling water system maintenance rule components
and functions based on engineering or expert panel judgment.
3. A list of component cooling water system related operating experience evaluations
for the last 3 years.
4. A list of all component cooling water system time-critical operator actions in
procedures.
5. A list of permanent and temporary modifications related to component cooling water
system sorted by component.
6. A list of current component cooling water system related operator work
arounds/burdens.
7. A list of the component cooling water system design calculations, which provide the
design margin information for components.
8. List of component cooling water system root cause evaluations associated with
component failures or design issues initiated/completed in the last 5 years.
9. A list of any component cooling water system common-cause failures of
components in the last 3 years.
10. An electronic copy of the component cooling water system design bases documents
and any open, pending, or recently completed changes. Although not an exhaustive
list, please include any open, pending, or recently completed (last 3 years) changes
to temporary modifications, permanent modifications, engineering change
packages, and/or procedure change packages. Specifically, please include any
open, pending, or recently completed changes to emergency operating, abnormal
operating, normal operating, alarm response, system alignment, surveillance, or
other procedure.
11. An electronic copy of the component cooling water system System Health notebook.
2. A copy of component cooling water system related audits completed in the last 2
years.
13. A list of component cooling water system motor operated valves (MOVs) in the
program, design margin and risk ranking.
14. A list of component cooling water system air operated valves (AOVs) in the valve
program, design margin and risk ranking.
15. Component cooling water system structure, system, and components maintenance
rule category, scoping, unavailability data, unreliability data, functional failure
evaluations, (a)(1) determinations, (a)(1) goals, and any supporting basis
documentation.
16. A list of component cooling water system licensee contacts for the inspection team
with pager or phone numbers.
17. An excel spreadsheet of component cooling water system related PRA human
action basic events or risk ranking of operator actions from your site specific PSA
sorted by RAW and FV. Provide copies of your human reliability worksheets for
these items.
18. In so far as there are recent or pending changes, please provide an Excel
spreadsheet of component cooling water system related equipment basic events
(with definitions) including importance measures sorted by risk achievement worth
(RAW) and Fussell-Vesely (FV) from your internal events probabilistic risk
assessment (PRA). Include basic events with RAW value of 1.3 or greater.
19. In so far as there are recent or pending changes, please provide a list of the top 50
cut-sets from your PRA.
20. In so far as there are recent or pending changes, please provide copies of PRA
system notebooks, and the latest PRA summary document.
21. In so far as there are recent or pending changes, and if you have an external events
or fire PSA model, provide the information requested in items 17-19 for external
events and fire, as it relates to the component cooling water system.
2. In so far as there are recent or pending changes, please provide a copy of the Wolf
Creek Nuclear Generating Station IPEEE changes, if available electronically.
SUNSI Review:
ADAMS:
Non-Publicly Available
Non-Sensitive
Keyword:
By: NHT/rdr
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
JDrake
SIGNATURE
/RA/
/RA/
/RA/
/RA/
/RA/
/RA/
DATE
5/9/2018
5/10/18
5/3/18
5/3/18
5/3/2018
5/9/18
OFFICE
TL:DRS/IPAT
SRI/DRP/B
BC:DRP/B
NAME
GGeorge
DBradley
NTaylor
SIGNATURE
/RA -
HFreeman for/
/RA/
/RA/
DATE
5/10/18
5/7/18
5/14/18