ML14223B221: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(5 intermediate revisions by the same user not shown)
Line 3: Line 3:
| issue date = 08/11/2014
| issue date = 08/11/2014
| title = IR 05000482-14-003, on 03/29/2014 & 06/27/2014, Wolf Creek Generating Station, Integrated Resident and Regional Report; Maintenance Risk Assessments and Emergent Work Control
| title = IR 05000482-14-003, on 03/29/2014 & 06/27/2014, Wolf Creek Generating Station, Integrated Resident and Regional Report; Maintenance Risk Assessments and Emergent Work Control
| author name = O'Keefe N F
| author name = O'Keefe N
| author affiliation = NRC/RGN-IV/DRP/RPB-B
| author affiliation = NRC/RGN-IV/DRP/RPB-B
| addressee name = Heflin A C
| addressee name = Heflin A
| addressee affiliation = Wolf Creek Nuclear Operating Corp
| addressee affiliation = Wolf Creek Nuclear Operating Corp
| docket = 05000482
| docket = 05000482
Line 14: Line 14:
| page count = 46
| page count = 46
}}
}}
See also: [[followed by::IR 05000482/2014003]]
See also: [[see also::IR 05000482/2014003]]


=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:UNITED STATES
[[Issue date::August 11, 2014]]
                            NUCLEAR REGULATORY COMMISSION
                                                REGION IV
                                          1600 E. LAMAR BLVD.
                                        ARLINGTON, TX 76011-4511
                                            August 11, 2014
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 05000482/2014003
Dear Mr. Heflin:
On June 27, 2014, the U.S. Nuclear Regulatory Commission completed an inspection at the
Wolf Creek Generating Station. On July 8, 2014, the Nuclear Regulatory Commission
inspectors discussed the results of this inspection with you and other members of your staff.
Inspectors documented the results of this inspection in the enclosed inspection report.
The Nuclear Regulatory Commission inspectors documented one finding of very low safety
significance (Green) in this report. This finding involved a violation of Nuclear Regulatory
Commission requirements. The Nuclear Regulatory Commission is treating this violation as
non-cited violation consistent with Section 2.3.2.a of the Nuclear Regulatory Commission
Enforcement Policy.
If you contest the violation or significance of the 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, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the
Nuclear Regulatory Commission resident inspector at the Wolf Creek Generating Station.
If you disagree with the 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 Regional Administrator, Region IV; and the Nuclear Regulatory
Commission resident inspector at the Wolf Creek Generating Station.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public
Inspections, Exemptions, Requests for Withholding, a copy of this letter, its enclosure, and your
response (if any) will be available electronically for public inspection in the NRCs Public


Adam C. Heflin, President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839
A. Heflin                                   -2-
Document Room or from the Publicly Available Records component of the Nuclear Regulatory
Commission Agencywide Documents Access and Management System. Agencywide
Documents Access and Management System is accessible from the Nuclear Regulatory
Commission Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic
Reading Room).
                                          Sincerely,
                                            /RA/
                                          Neil OKeefe, Chief
                                          Project Branch B
                                          Division of Reactor Projects
Docket Nos.: 50-482
License Nos: NPF-42
Enclosure:
Inspection Report 05000482/2014003
  w/Attachments
1. Supplemental Information
2. Public Radiation Safety Inspection Request
cc w/encl: Electronic Distribution to
  Wolf Creek Nuclear Operating Corporation


SUBJECT: WOLF CREEK GENERATING STATION - NRC INTEGRATED INSPECTION REPORT 05000482/2014003
            U.S. NUCLEAR REGULATORY COMMISSION
                              REGION IV
Docket:     05000482
License:    NPF-42
Report:    05000482/2014003
Licensee:  Wolf Creek Nuclear Operating Corporation
Facility:  Wolf Creek Generating Station
Location:  1550 Oxen Lane NE
            Burlington, Kansas
Dates:      March 29 through June 27, 2014
Inspectors: C. Peabody, Senior Resident Inspector
            R. Stroble, Resident Inspector
            L. Carson II, Senior Health Physicist
            N. Greene, PhD, Health Physicist
            P. Hernandez, Health Physicist
            J. ODonnell, Health Physicist
            D. Proulx, Senior Project Engineer
Approved    Neil OKeefe
    By:    Chief, Project Branch B
            Division of Reactor Projects
                                                    Enclosure


==Dear Mr. Heflin:==
                                            SUMMARY
On June 27, 2014, the U.S. Nuclear Regulatory Commission completed an inspection at the Wolf Creek Generating Station. On July 8, 2014, the Nuclear Regulatory Commission inspectors discussed the results of this inspection with you and other members of your staff.
IR 05000482/2014003; 03/29/2014 - 06/27/2014; Wolf Creek Generating Station, Integrated
 
Resident and Regional Report; Maintenance Risk Assessments and Emergent Work Control.
Inspectors documented the results of this inspection in the enclosed inspection report. The Nuclear Regulatory Commission inspectors documented one finding of very low safety significance (Green) in this report. This finding involved a violation of Nuclear Regulatory Commission requirements. The Nuclear Regulatory Commission is treating this violation as non-cited violation consistent with Section 2.3.2.a of the Nuclear Regulatory Commission Enforcement Policy.
The inspection activities described in this report were performed between March 29 and
 
June 27, 2014, by the resident inspectors at Wolf Creek Generating Station and inspectors from
If you contest the violation or significance of the 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, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the Nuclear Regulatory Commission resident inspector at the Wolf Creek Generating Station.
the Nuclear Regulatory Commission Region IV office. One finding of very low safety
 
significance (Green) is documented in this report. This finding involved a violation of Nuclear
If you disagree with the 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 Regional Administrator, Region IV; and the Nuclear Regulatory Commission resident inspector at the Wolf Creek Generating Station.
Regulatory Commission requirements. The significance of inspection findings is indicated by
 
their color (Green, White, Yellow, or Red), which is determined using Inspection Manual
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records component of the Nuclear Regulatory Commission Agencywide Documents Access and Management System. Agencywide Documents Access and Management System is accessible from the Nuclear Regulatory Commission Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Chapter 0609, Significance Determination Process. Their cross-cutting aspects are
 
determined using Inspection Manual Chapter 0310, Components Within the Cross-Cutting
Sincerely,/RA/
Areas. Violations of NRC requirements are dispositioned in accordance with the Nuclear
 
Regulatory Commission Enforcement Policy. The NRC's program for overseeing the safe
Neil O'Keefe, Chief Project Branch B Division of Reactor Projects Docket Nos.: 50-482 License Nos: NPF-42
operation of commercial nuclear power reactors is described in NUREG 1649, Reactor
 
Oversight Process.
===Enclosure:===
Findings
Inspection Report 05000482/2014003 w/Attachments 1. Supplemental Information 2. Public Radiation Safety Inspection Request cc w/encl: Electronic Distribution to Wolf Creek Nuclear Operating Corporation
 
Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket: 05000482 License: NPF-42 Report: 05000482/2014003 Licensee: Wolf Creek Nuclear Operating Corporation Facility: Wolf Creek Generating Station Location: 1550 Oxen Lane NE Burlington, Kansas Dates: March 29 through June 27, 2014 Inspectors: C. Peabody, Senior Resident Inspector R. Stroble, Resident Inspector L. Carson II, Senior Health Physicist N. Greene, PhD, Health Physicist P. Hernandez, Health Physicist J. O'Donnell, Health Physicist D. Proulx, Senior Project Engineer Approved By: Neil O'Keefe Chief, Project Branch B Division of Reactor Projects
 
=SUMMARY=
IR 05000482/2014003; 03/29/2014 - 06/27/2014; Wolf Creek Generating Station, Integrated Resident and Regional Report; Maintenance Risk Assessments and Emergent Work Control.
 
The inspection activities described in this report were performed between March 29 and June 27, 2014, by the resident inspectors at Wolf Creek Generating Station and inspectors from the Nuclear Regulatory Commission Region IV office. One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of Nuclear Regulatory Commission requirements. The significance of inspection findings is indicated by their color (Green, White, Yellow, or Red), which is determined using Inspection Manual Chapter 0609, "Significance Determination Process."  Their cross-cutting aspects are determined using Inspection Manual Chapter 0310, "Components Within the Cross-Cutting Areas."  Violations of NRC requirements are dispositioned in accordance with the Nuclear Regulatory Commission Enforcement Policy. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG 1649, "Reactor Oversight Process."
 
Findings  No findings were identified.
 
Licensee Identified Findings No findings were identified.
 
==PLANT STATUS==
Wolf Creek began the inspection period with the unit in Mode 5 (cold shutdown) for a planned mid-cycle outage. On May 8, 2014, the reactor was restarted then promptly shut down due to a leaking steam generator bowl drain valve inside containment. On May 10, 2014, the reactor was again restarted and promptly shut down due to a reactor coolant pump oil leak inside containment. On May 13, 2014, the reactor was restarted successfully, reached 100 percent power on May 15, 2014, and remained at that power level for the remainder of the inspection period.
 
=REPORT DETAILS=
 
==REACTOR SAFETY==
Cornerstones:  Initiating Events, Mitigating Systems, and Barrier Integrity
{{a|1R01}}
==1R01 Adverse Weather Protection==
{{IP sample|IP=IP 71111.01}}
Summer Readiness for Offsite and Alternate AC Power Systems
 
====a. Inspection Scope====
On May 2, 2014, the inspectors completed an inspection of the station's off-site and alternate-ac power systems. The inspectors inspected the material condition of these systems, including transformers and other switchyard equipment to verify that plant features and procedures were appropriate for operation and continued availability of off-site and alternate-ac power systems. The inspectors reviewed outstanding work orders and open condition reports for these systems. The inspectors walked down the switchyard to observe the material condition of equipment providing off-site power sources. The inspectors verified that the licensee's procedures included appropriate measures to monitor and maintain availability and reliability of the off-site and alternate-ac power systems.
 
These activities constituted one sample of summer readiness of off-site and alternate-ac power systems, as defined in Inspection Procedure 71111.01.
 
====b. Findings====
No findings were identified.
No findings were identified.
{{a|1R04}}
Licensee Identified Findings
==1R04 Equipment Alignment==
{{IP sample|IP=IP 71111.04}}
Partial Walkdown
 
====a. Inspection Scope====
The inspectors performed partial system walk-downs of the following risk-significant systems:
* April 7, 2014, residual heat removal shutdown cooling train B
* April 7, 2014, control room air conditioning system and control room emergency ventilation system train B
* June 17, 2014, safety injection system train A  The inspectors reviewed the licensee's procedures and system design information to determine the correct lineup for the systems. They visually verified that critical portions of the systems or trains were correctly aligned for the existing plant configuration.
 
These activities constituted three partial system walk-down samples as defined in Inspection Procedure 71111.04.
 
====b. Findings====
No findings were identified.
{{a|1R05}}
==1R05 Fire Protection==
{{IP sample|IP=IP 71111.05}}
===.1 Quarterly Inspection===
 
====a. Inspection Scope====
The inspectors evaluated the licensee's fire protection program for operational status and material condition. The inspectors focused their inspection on four plant areas important to safety:
* May 1, 2014, radiological controlled area and health physics office space
* May 1, 2014, lower cable spreading room
* May 7, 2014, upper cable spreading room
* May 8, 2014, auxiliary feedwater pump room train A  For each area, the inspectors evaluated the fire plan against defined hazards and defense-in-depth features in the licensee's fire protection program. The inspectors evaluated control of transient combustibles and ignition sources, fire detection and suppression systems, manual firefighting equipment and capability, passive fire protection features, and compensatory measures for degraded conditions. These activities constituted four quarterly inspection samples, as defined in Inspection Procedure 71111.05.
 
====b. Findings====
No findings were identified.
No findings were identified.
                                                -2-


===.2 Annual Inspection===
                                          PLANT STATUS
Wolf Creek began the inspection period with the unit in Mode 5 (cold shutdown) for a planned
mid-cycle outage. On May 8, 2014, the reactor was restarted then promptly shut down due to a
leaking steam generator bowl drain valve inside containment. On May 10, 2014, the reactor
was again restarted and promptly shut down due to a reactor coolant pump oil leak inside
containment. On May 13, 2014, the reactor was restarted successfully, reached 100 percent
power on May 15, 2014, and remained at that power level for the remainder of the inspection
period.
                                        REPORT DETAILS
1.      REACTOR SAFETY
        Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R01 Adverse Weather Protection (71111.01)
        Summer Readiness for Offsite and Alternate AC Power Systems
  a.  Inspection Scope
        On May 2, 2014, the inspectors completed an inspection of the stations off-site and
        alternate-ac power systems. The inspectors inspected the material condition of these
        systems, including transformers and other switchyard equipment to verify that plant
        features and procedures were appropriate for operation and continued availability of off-
        site and alternate-ac power systems. The inspectors reviewed outstanding work orders
        and open condition reports for these systems. The inspectors walked down the
        switchyard to observe the material condition of equipment providing off-site power
        sources. The inspectors verified that the licensees procedures included appropriate
        measures to monitor and maintain availability and reliability of the off-site and alternate-
        ac power systems.
        These activities constituted one sample of summer readiness of off-site and alternate-ac
        power systems, as defined in Inspection Procedure 71111.01.
  b.  Findings
        No findings were identified.
1R04 Equipment Alignment (71111.04)
        Partial Walkdown
  a.  Inspection Scope
        The inspectors performed partial system walk-downs of the following risk-significant
        systems:
            *  April 7, 2014, residual heat removal shutdown cooling train B
                                                -3-


====a. Inspection Scope====
          *  April 7, 2014, control room air conditioning system and control room emergency
On June 27, 2014, the inspectors completed their annual evaluation of the licensee's fire brigade performance. This evaluation included observation of an unannounced fire drill for 2016, control building non-vital switchgear room B on June 27, 2014.
              ventilation system train B
 
          *   June 17, 2014, safety injection system train A
During this drill, the inspectors evaluated the capability of the fire brigade members, the leadership ability of the brigade leader, the brigade's use of turnout gear and fire-fighting equipment, and the effectiveness of the fire brigade's team operation. The inspectors also reviewed whether the licensee's fire brigade met NRC requirements for training, dedicated size and membership, and equipment.
      The inspectors reviewed the licensees procedures and system design information to
 
      determine the correct lineup for the systems. They visually verified that critical portions
These activities constituted one annual inspection sample, as defined in Inspection Procedure 71111.05.
      of the systems or trains were correctly aligned for the existing plant configuration.
 
      These activities constituted three partial system walk-down samples as defined in
====b. Findings====
      Inspection Procedure 71111.04.
No findings were identified.
  b. Findings
{{a|1R11}}
      No findings were identified.
==1R11 Licensed Operator Requalification Program and Licensed Operator Performance==
1R05 Fire Protection (71111.05)
{{IP sample|IP=IP 71111.11}}
.1    Quarterly Inspection
Review of Licensed Operator Requalification
  a. Inspection Scope
 
      The inspectors evaluated the licensees fire protection program for operational status
====a. Inspection Scope====
      and material condition. The inspectors focused their inspection on four plant areas
On June 18, 2014, the inspectors evaluated a simulator scenario performed by an operating crew. The inspectors assessed the performance of the operators and the evaluators' critique of their performance.
      important to safety:
 
          *   May 1, 2014, radiological controlled area and health physics office space
These activities constitute completion of one quarterly licensed operator requalification program sample, as defined in Inspection Procedure 71111.11.
          *   May 1, 2014, lower cable spreading room
 
          *   May 7, 2014, upper cable spreading room
====b. Findings====
          *   May 8, 2014, auxiliary feedwater pump room train A
No findings were identified.
      For each area, the inspectors evaluated the fire plan against defined hazards and
{{a|1R13}}
      defense-in-depth features in the licensees fire protection program. The inspectors
==1R13 Maintenance Risk Assessments and Emergent Work Control==
      evaluated control of transient combustibles and ignition sources, fire detection and
{{IP sample|IP=IP 71111.13}}
      suppression systems, manual firefighting equipment and capability, passive fire
 
      protection features, and compensatory measures for degraded conditions.
====a. Inspection Scope====
      These activities constituted four quarterly inspection samples, as defined in Inspection
The inspectors reviewed two risk assessments performed by the licensee prior to changes in plant configuration and the risk management actions taken by the licensee in response to elevated risk:
      Procedure 71111.05.
* May 19-25, 2014, train A essential service water and emergency diesel generator planned maintenance outage
  b. Findings
* June 16-22, 2014, train B safety injection planned maintenance outage and train B containment spray planned maintenance outage  The inspectors verified that these risk assessments were performed timely and in accordance with the requirements of 10 CFR 50.65 (the Maintenance Rule) and plant procedures. The inspectors reviewed the accuracy and completeness of the licensee's risk assessments and verified that the licensee implemented appropriate risk management actions based on the result of the assessments.
      No findings were identified.
 
                                              -4-
The inspectors also observed portions of one emergent work activities that had the potential to affect the functional capability of mitigating systems:
* June 9-11, 2014, emergency diesel generator B governor testing failure and replacement The inspectors verified that the licensee appropriately developed and followed a work plan for these activities. The inspectors verified that the licensee took precautions to minimize the impact of the work activities on unaffected structures, systems, and components (SSCs).
 
Additionally, the inspectors reviewed the risk assessments associated with two planned maintenance activities performed during a time in the outage when the primary plant was in a water-solid condition that resulted in unplanned pressure transients.
* March 14, 2014, reactor coolant system pressure transient during bus switching
* April 1, 2014, reactor coolant system pressure transient during motor-operated valve testing  These activities constitute completion of four maintenance risk assessments and emergent work control inspection samples, as defined in Inspection Procedure 71111.13.  (Note: The March 14, 2014, sample was counted in Inspection Report 2014002).
 
====b. Findings====
No findings were identified.
{{a|1R15}}
==1R15 Operability Determinations and Functionality Assessments==
{{IP sample|IP=IP 71111.15}}
 
====a. Inspection Scope====
The inspectors reviewed four operability determinations that the licensee performed for degraded or nonconforming SSCs:
* April 5, 2014, operability determination of train B emergency diesel generator heating, ventilation, and air conditioning inlet damper hydramotor oil analysis
* April 23, 2014, operability determination of containment cooler corrosion extent of condition
* May 19, 2014, operability determination of NB01 under voltage surveillance failure
* June 11, 2014, operability determination of train B emergency diesel generator governor hydraulic actuator SKJ09B  The inspectors reviewed the timeliness and technical adequacy of the licensee's evaluations. Where the licensee determined the degraded SSC to be operable, the inspectors verified that the licensee's compensatory measures were appropriate to provide reasonable assurance of operability. The inspectors verified that the licensee had considered the effect of other degraded conditions on the operability of the degraded SSC. In the case of the containment cooler issues, the inspectors obtained the assistance of specialist inspectors from the Region IV office and experts from the Office of Nuclear Reactor Regulation. The NRC conducted several calls with licensee technical and management personnel. Based on NRC concerns, the licensee decided to perform hydrostatic testing of the remaining coolers to provide provide test data to support continued operabililty with continuing pitting corrosion. The inspectors observed one of the pressure tests and reviewed the revised operability determination.
 
These activities constitute completion of four operability review samples, as defined in Inspection Procedure 71111.15.
 
====b. Findings====
No findings were identified.
{{a|1R19}}
==1R19 Post-Maintenance Testing==
{{IP sample|IP=IP 71111.19}}
 
====a. Inspection Scope====
The inspectors reviewed four post-maintenance testing activities that affected risk-significant SSCs:
* April 14, 2014, essential service water train A flow balance
* April 15, 2014, emergency diesel generator train A jacket water leak
* April 23, 2014, reactor coolant pump C bump test and break away torque
* May 8, 2014, steam generator B bowl valve testing  The inspectors reviewed licensing and design basis documents for the SSCs and the maintenance and post-maintenance test procedures. The inspectors observed the performance of the post-maintenance tests to verify that the licensee performed the tests in accordance with approved procedures, satisfied the established acceptance criteria, and restored the operability of the affected SSCs.
 
These activities constitute completion of four post-maintenance testing inspection samples, as defined in Inspection Procedure 71111.19.
 
====b. Findings====
No findings were identified.
{{a|1R20}}
==1R20 Refueling and Other Outage Activities==
{{IP sample|IP=IP 71111.20}}
 
====a. Inspection Scope====
During the station's mid-cycle outage that concluded on May 13, 2014, the inspectors evaluated the licensee's outage activities. The inspectors verified that the licensee considered risk in developing and implementing the outage plan, appropriately managed personnel fatigue, and developed mitigation strategies for losses of key safety functions.
 
This verification included the following:
* Review of the licensee's outage plan prior to the outage
* Monitoring of shut-down and cool-down activities
* Verification that the licensee maintained defense-in-depth during outage activities
* Monitoring of heat-up and startup activities  These activities constitute completion of one planned outage sample outage activities sample, as defined in Inspection Procedure 71111.20.
 
====b. Findings====
No findings were identified.
{{a|1R22}}
==1R22 Surveillance Testing==
{{IP sample|IP=IP 71111.22}}
 
====a. Inspection Scope====
The inspectors observed six risk-significant surveillance tests and reviewed test results to verify that these tests adequately demonstrated that the SSCs were capable of performing their safety functions:  In-service tests:
* April 25, 2014, accumulator vent valve EPV0109  Reactor Coolant System Leak Detection:
* May 31, 2014, reactor coolant system water inventory balance  Other surveillance tests:
* March 28-29, 2014, train A engineered safety features actuating safety testing
* April 25-28, 2014, station blackout diesel functional testing
* May 6, 2014, containment closeout walkdown
* May 19, 2014, reactor coolant system xenon-133 specific activity determination The inspectors verified that these tests met technical specification requirements, that the licensee performed the tests in accordance with their procedures, and that the results of the test satisfied appropriate acceptance criteria.
 
These activities constitute completion of six surveillance testing inspection samples, as defined in Inspection Procedure 71111.22.
 
====b. Findings====
No findings were identified.
 
===Cornerstone:===
Emergency Preparedness
{{a|1EP6}}
==1EP6 Drill Evaluation==
{{IP sample|IP=IP 71114.06}}
Emergency Preparedness Drill Observation
 
====a. Inspection Scope====
The inspectors observed an emergency preparedness drill on June 18, 2014, to verify the adequacy and capability of the licensee's assessment of drill performance. The inspectors reviewed the drill scenario, observed the drill from the simulator and emergency operations facility, and attended the post-drill critique. The inspectors verified that the licensee's emergency classifications, off-site notifications, and protective action recommendations were appropriate and timely. The inspectors verified that any emergency preparedness weaknesses were appropriately identified by the licensee in the post-drill critique and entered into the corrective action program for resolution.
 
These activities constitute completion of one emergency preparedness drill observation sample, as defined in Inspection Procedure 71114.06.
 
====b. Findings====
No findings were identified.
 
==RADIATION SAFETY==
Cornerstones: Public Radiation Safety and Occupational Radiation Safety
{{a|2RS5}}
==2RS5 Radiation Monitoring Instrumentation==
{{IP sample|IP=IP 71124.05}}
 
====a. Inspection Scope====
The inspectors evaluated the accuracy and operability of the radiation monitoring equipment used by the licensee (1) to monitor areas, materials, and workers to ensure a radiologically safe work environment, and (2) to detect and quantify radioactive process streams and effluent releases. The inspectors interviewed licensee personnel, walked down various portions of the plant, and reviewed licensee performance in the following areas:
* Selected plant configurations and alignments of process, post-accident, and effluent monitors with descriptions in the Final Safety Analysis Report and the offsite dose calculation manual
* Select instrumentation, including effluent monitoring instrument, portable survey instruments, area radiation monitors, continuous air monitors, personnel contamination monitors, portal monitors, and small article monitors to examine their configurations and source checks
* Calibration and testing of process and effluent monitors, laboratory instrumentation, whole body counters, post-accident monitoring instrumentation, portal monitors, personnel contamination monitors, small article monitors, portable survey instruments, area radiation monitors, electronic dosimetry, air samplers, and continuous air monitors
* Audits, self-assessments, and corrective action documents related to radiation monitoring instrumentation since the last inspection  These activities constitute completion of one sample of radiation monitoring instrumentation as defined in Inspection Procedure 71124.05.
 
====b. Findings====
No findings were identified.
{{a|2RS6}}
==2RS6 Radioactive Gaseous and Liquid Effluent Treatment==
{{IP sample|IP=IP 71124.06}}
 
====a. Inspection Scope====
The inspectors evaluated whether the licensee maintained gaseous and liquid effluent processing systems and properly mitigated, monitored, and evaluated radiological discharges with respect to public exposure. The inspectors verified that abnormal radioactive gaseous or liquid discharges and conditions, when effluent radiation monitors are out-of-service, were controlled in accordance with the applicable regulatory requirements and licensee procedures. The inspectors verified that the licensee's quality control program ensured radioactive effluent sampling and analysis adequately quantified and evaluated discharges of radioactive materials. The inspectors verified the adequacy of public dose projections resulting from radioactive effluent discharges. The inspectors interviewed licensee personnel and reviewed or observed the following items:
* Radiological effluent release reports since the previous inspection and reports related to the effluent program issued since the previous inspection
* Effluent program implementing procedures, including sampling, monitor setpoint determinations, and dose calculations
* Equipment configuration and flow paths of selected gaseous and liquid discharge system components, filtered ventilation system material condition, and significant changes to their effluent release points, if any, and associated 10 CFR 50.59 reviews
* Selected portions of the routine processing and discharge of radioactive gaseous and liquid effluents (including sample collection and analysis)
* Controls used to ensure representative sampling and appropriate compensatory sampling
* Results of the inter-laboratory comparison program
* Effluent stack flow rates
* Surveillance test results of technical specification-required ventilation effluent discharge systems since the previous inspection
* Significant changes in reported dose values
* A selection of radioactive liquid and gaseous waste discharge permits
* Part 61 analyses and methods used to determine which isotopes are included in the source term
* Offsite dose calculation manual changes
* Meteorological dispersion and deposition factors
* Latest land use census
* Records of abnormal gaseous or liquid tank discharges
* Groundwater monitoring results
* Changes to the licensee's written program for identifying and controlling contaminated spills/leaks to groundwater
* Identified leakage or spill events and entries made into 10 CFR 50.75(g) records, if any, and associated evaluations of the extent of the contamination and the radiological source term
* Offsite notifications and reports of events associated with spills, leaks, or groundwater monitoring results
* Audits, self-assessments, reports, and corrective action documents related to radioactive gaseous and liquid effluent treatment since the last inspection  These activities constitute completion of one sample of radioactive gaseous and liquid effluent treatment, as defined in Inspection Procedure 71124.06.
 
====b. Findings====
No findings were identified.
{{a|2RS7}}
==2RS7 Radiological Environmental Monitoring Program==
{{IP sample|IP=IP 71124.07}}
 
====a. Inspection Scope====
The inspectors evaluated whether the licensee's radiological environmental monitoring program quantified the impact of radioactive effluent releases to the environment and sufficiently validated the integrity of the radioactive gaseous and liquid effluent release program. The inspectors verified that the radiological environmental monitoring program was implemented consistent with the licensee's technical specifications and offsite dose calculation manual, and that the radioactive effluent release program met the design objective in Appendix I to 10 CFR Part 50. The inspectors verified that the licensee's radiological environmental monitoring program monitored non-effluent exposure pathways, was based on sound principles and assumptions, and validated that doses to members of the public were within regulatory dose limits. The inspectors reviewed or observed the following items:
* Annual environmental monitoring reports and offsite dose calculation manual
* Selected air sampling and dosimeter monitoring stations
* Collection and preparation of environmental samples
* Operability, calibration, and maintenance of meteorological instruments
* Selected events documented in the annual environmental monitoring report which involved a missed sample, inoperable sampler, lost dosimeter, or anomalous measurement
* Selected structures, systems, or components that may contain licensed material and has a credible mechanism for licensed material to reach ground water
* Records required by 10 CFR 50.75(g)
* Significant changes made by the licensee to the offsite dose calculation manual as the result of changes to the land census or sampler station modifications since the last inspection
* Calibration and maintenance records for selected air samplers, composite water samplers, and environmental sample radiation measurement instrumentation
* Inter-laboratory comparison program results
* Audits, self-assessments, reports, and corrective action documents related to the radiological environmental monitoring program since the last inspection  These activities constitute completion of one sample of the radiological environmental monitoring program as defined in Inspection Procedure 71124.07.
 
====b. Findings====
No findings were identified.
{{a|2RS8}}
==2RS8 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation==
{{IP sample|IP=IP 71124.08}}
 
====a. Inspection Scope====
The inspectors evaluated the effectiveness of the licensee's programs for processing, handling, storage, and transportation of radioactive material. The inspectors interviewed licensee personnel and reviewed the following items:
* The solid radioactive waste system description, process control program, and the scope of the licensee's audit program
* Control of radioactive waste storage areas including container labeling/marking and monitoring containers for deformation or signs of waste decomposition
* Changes to the liquid and solid waste processing system configuration including a review of waste processing equipment that is not operational or abandoned in place
* Radio-chemical sample analysis results for radioactive waste streams and use of scaling factors and calculations to account for difficult-to-measure radionuclides
* Processes for waste classification including use of scaling factors and 10 CFR Part 61 analysis
* Shipment, packaging, surveying, labeling, marking, placarding, vehicle checking, driver instructing, and preparation of the disposal manifest
* Audits, self-assessments, reports, and corrective action reports on radioactive solid waste processing and radioactive material handling, storage, and transportation  performed since the last inspection  These activities constitute completion of one sample of radioactive solid waste processing, and radioactive material handling, storage, and transportation as defined in Inspection Procedure 71124.08.
 
====b. Findings====
No findings were identified.
 
==OTHER ACTIVITIES==
Cornerstones:  Initiating Events, Mitigating Systems, Barrier Integrity, Emergency Preparedness, Public Radiation Safety, Occupational Radiation Safety, and Security
{{a|4OA1}}
==4OA1 Performance Indicator Verification==
{{IP sample|IP=IP 71151}}
===.1 Reactor Coolant System Specific Activity (BI01)===
 
====a. Inspection Scope====
The inspectors reviewed the licensee's reactor coolant system chemistry sample analyses for the period of April 1, 2013, through March 31, 2014, to verify the accuracy and completeness of the reported data. The inspectors reviewed the surveillance paperwork for the reactor coolant system sample taken on May 19, 2014. The inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7, to determine the accuracy of the reported data.
 
These activities constituted verification of the reactor coolant system specific activity performance indicator, as defined in Inspection Procedure 71151.
 
====b. Findings====
No findings were identified.
 
===.2 Reactor Coolant System Identified Leakage (BI02)===
 
====a. Inspection Scope====
The inspectors reviewed the licensee's records of reactor coolant system identified leakage for the period of April 1, 2013 through March 31, 2014 to verify the accuracy and completeness of the reported data. The inspectors reviewed the performance of STS BB-006 "RCS Water Inventory Balance" on May 31, 2014. The inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7, to determine the accuracy of the reported data.
 
These activities constituted verification of the reactor coolant system leakage performance indicator, as defined in Inspection Procedure 71151.
 
====b. Findings====
No findings were identified.
{{a|4OA2}}
==4OA2 Problem Identification and Resolution==
{{IP sample|IP=IP 71152}}
===.1 Routine Review===
 
====a. Inspection Scope====
Throughout the inspection period, the inspectors performed daily reviews of items entered into the licensee's corrective action program and periodically attended the licensee's condition report screening meetings. The inspectors verified that licensee personnel were identifying problems at an appropriate threshold and entering these problems into the corrective action program for resolution. The inspectors verified that the licensee developed and implemented corrective actions commensurate with the significance of the problems identified. The inspectors also reviewed the licensee's problem identification and resolution activities during the performance of the other inspection activities documented in this report.
 
====b. Findings====
No findings were identified.
 
===.2 Semiannual Trend Review===
 
====a. Inspection Scope====
To verify that the licensee was taking corrective actions to address identified adverse trends that might indicate the existence of a more significant safety issue, the inspectors reviewed corrective action program documentation associated with the following licensee-identified trends:
* High backlogs in the design implementation and configuration control process area  Also, the inspectors identified the following trends that might indicate the existence of a more significant safety issue, and reviewed the licensee's response to them:
* Inadequate technical verification and validation of temporary and permanent plant modifications
* The licensee's corrective action program group is not trending data at a station-wide level (i.e., above the department level), nor are they prioritizing departmental issues and trends which are significantly affecting overall station performance  The NRC identified a theme in NRC inspection findings with cross-cutting aspects in maintaining design margins [H.6] during the 2013 End Of Cycle Assessment. The inspectors reviewed the licensee's response to that trend to verify that the licensee was taking appropriate actions to address it. These activities constitute completion of one semiannual trend review sample, as defined in Inspection Procedure 71152.
 
b. Observations and Assessments  The inspectors' review of the trends identified above produced the following observations and assessments:
* Design Control Backlogs. In July of 2013, an industry group assessment of station performance noted an unusually high number of open design change packages. The backlog included approximately 1700 change packages, some open since the early 1990s, including some SSCs with multiple open design changes. Some change packages had targeted completion dates that were beyond the expiration date of the plant operating license. Historically, the station has had challenges with design control, as noted in NRC inspection reports.
 
The licensee performed an apparent cause evaluation under Condition Reports 72164, 72166, and 72167 to identify the organizational causes. Among the licensee's conclusions, management oversight of configuration control was lacking, there was not an awareness of the vulnerability created by incomplete configuration changes, and there was no single owner of design change products to ensure configuration management documents are kept up to date. The licensee took corrective actions to develop a configuration management health plan to improve the design control program as well as developing a comprehensive backlog reduction strategy. The inspectors also noted that the licensee performed an aggregate risk assessment of the backlog to ensure that items with more significant safety impacts were addressed more quickly. The inspectors also noted that the backlog reduction program has reduced the number of open change packages to 400 at the end of June 2014, with a goal of less than 200 planned by January 2015.
* Findings with Design Margins Cross Cutting Aspect [H6]. A theme in findings with cross-cutting aspects in the area of maintaining design margins was identified during the NRC's 2013 End of Cycle Assessment for Wolf Creek. The licensee performed an apparent cause evaluation under Condition Reports 74508 and 78794. The inspectors noted that this trend was related to the larger problem of backlog management. Because this trend is related to other improvement efforts, the inspectors noted that the licensee has evaluated and taken actions related to this theme in the areas of corrective action, preventive maintenance, and procedure revision backlog reductions under Condition Reports 62394, 68194, and 78708. Most of the backlog improvement efforts were making a notable reduction. The inspectors observed that most backlog reduction efforts remained on target through the mid-cycle 20 outage in March and April of 2014. Overall outage management and scope control performance improvement was observed, and as a result, the corrective action and work order backlogs did not see the growth observed during previous outages. The licensee has taken corrective actions to establish and validate new internal performance indicators for the engineering and maintenance departments. Furthermore the licensee has scheduled actions to track these new indicators and backlogs to specific goals based on industry standards in the future. Also, while completing this trend review, the inspectors identified the following trends that the licensee had not previously identified. The inspectors also reviewed the licensee's response to these trends:
* Quality of Plant Modifications. Over the past 2 years, Wolf Creek has been implementing a large number of modifications. Additional non-safety related diesel generators and an auxiliary feed water pump were added to improve plant safety. The plant has also been addressing long standing corrosion and water hammer issues in the essential service water system by replacing piping above and below ground. Obsolete analog controllers have been replaced with digital control systems. However, the inspectors have observed a number of plant events and equipment failures associated with inadequate technical validation and verification associated with these modifications.
 
On May 2, 2013, an unplanned and uncontrolled 11 percent power increase occurred as a result of operator training deficiencies while swapping from the full arc to partial arc steam admission shortly after installing the new Westinghouse Ovation digital turbine controls. It was subsequently determined that additional functions and flexibilities of the new digital control system allowed operators to manipulate the plant in configurations prohibited by the old analog system, and that system response varied with power level, but this was not recognized and incorporated into procedures and training. Condition Report 68711, Non-Cited Violation NCV 05000482/2013003-05.
 
On May 28, 2013, and again on September 5, 2013, the turbine driven auxiliary feed water pump control system failed unexpectedly, rendering the pump incapable of operation. The digital control system positioner locked up and required replacement. It was later determined that an additional unused input to the positioner was experiencing noise, and if the noise came in at a certain point in the digital computer program's subroutine, the control software would crash. The problem was fixed by jumpering out the unused input connection and a vendor technical bulletin was issued to correct vulnerabilities at other nuclear power plants utilizing the same control system. Condition Reports 69721, 69754, and 73624.
 
On April 25, 2014, during station blackout diesel generator testing, the licensee was unable to connect the train A Class 1E 4kV distribution bus to the station blackout diesel generators due to a protective relay actuating to lock out the bus. The diesels had been declared functional and were credited in performance indicators and probabilistic risk assessment models since October 2013, when construction was completed but testing had not been fully completed. Troubleshooting as a result of the failed test found incorrect wiring of a protective relay to be the cause. Extent of condition inspections found that the train B bus connection was also wired incorrectly, and neither safety related bus would have been able to have been powered from the station blackout diesel generators. The licensee had intended to perform testing during the previous refueling outage, but construction delays caused work to extend beyond the outage. Plant conditions for this test necessitated the plant be shut down. The inspectors had engaged the licensee concerning their testing plan when construction was complete, but the licensee concluded that their quality checks were adequate to have a high confidence that testing to connect the generators to the safety buses would be adequate until plant conditions for the testing were available.
 
The inspectors concluded that those quality checks were inadequate, although this did not constitute a violation because the diesel generators and protective relaying were non-safety equipment and were not credited to meet any regulatory requirements. Condition Report 83379.
 
Not all of the validation and verification oversights resulted in plant events or failures. Some of the items were caught very late in the planning process, but still impacted regulatory commitments.
 
In February of 2014 the licensee commitment to correct long standing water hammer conditions in the essential service water system was delayed. The 2010 and 2012 Problem Identification and Resolution inspections have assessed cited violations regarding long-standing essential service water corrosion and water hammer issues not being addressed in a timely manner. Wolf Creek responded on the docket and committed to fixing the essential service water corrosion and water hammer issues by the spring 2014 mid-cycle outage. However, after over 3 years of planning, shortly before a modification was to be installed to correct the water hammer, it was discovered that the mitigating strategy would invalidate the essential service water design basis safety function to provide a source of auxiliary feed water during a design basis external event that compromises the condensate storage tank. This was documented in Condition Reports 53443 and 79619. The licensee concluded that there was inadequate contractor oversight during the modification development process. A revised modification was tentatively rescheduled for the next refueling outage.
 
On March 30, 2014, a containment cooler tube bundle failed (small tube leaks) as a result of water hammer during the engineered safety features actuation system testing. A similar failure occurred when the opposite train was tested a few weeks later. While reviewing the cause evaluation, the inspectors noted the failure mechanism was due to a combination of pitting corrosion and sudden pressure spike during the essential service water system water hammer. The ispectors determined that corrective actions to address corrosion in carbon steel essential service water piping had not addressed the copper-nickel containment cooler tubes. The inspectors reviewed the history of containment cooler degradation and noted that all 48 of the tube bundles had already been replaced due to widespread degradation in the late 1990s, and now the 2nd generation like-for-like replacements were beginning to fail. The problem was further complicated because non-destructive testing to monitor corrosion was not possible because the cooler design and complex cooler geometry prevented this. The licensee plans to correct the condition by replacing all coolers dueing the next outage, then replacing the original design with stainless steel cooler tubes that will allow for eddy current testing.
 
Condition Reports 81809 and 82904.
 
On November 18, 2011, an NRC Component Design Basis Inspection assessed NCV 05000482/2010007-01 for the failure to properly analyze the isolation between the safety-related and non-safety related portions of the component cooling water system. Portions of the non-safety piping leading to the rad waste building are non-seismically qualified, and should they fail, could result in a loss of inventory greater than can be accommodated by the component cooling water surge tanks. The inspector noted that the licensee promptly manually isolated this piping and has been working on installing a combination of check valves and orifices, for the past four years. The planned modification to correct this violation has been delayed a number of times since 2012 because the licensee has found problems with the design. Condition Reports 28237 and 85328.
 
The inspectors determined that the licensee was aware of these issues individually, but had not identified the collective trend. The licensee wrote Condition Report 85907 to evaluate and address this trend.
* Lack Trending and Prioritization above the Department Level. In reviewing the station roll-up reports that record corrective action program activities at the station and departmental levels, the inspectors noted that the analytical trending ends at the departmental summaries. The station corrective action staff was not summarizing analytical trends across divisions, nor were they giving additional priority to departmental trends which were having a significant impact on station performance.  (e.g. design control, procedure quality, etc.)      The inspectors reviewed additional documentation associated with station improvement initiatives and determined that at a station level, senior leadership was performing some station level trend analysis and setting station priorities based on the available data, but this was being done outside the corrective action program, and was not proceduralized and therefore would not continue when the improvement initiatives were completed. The licensee has written Condition Report 85905 to evaluate and address this issue.
 
The inspectors' assessment noted improved corrective action trending at the department level. The operations department continues to be a station leader in this area. The maintenance and engineering departments have made notable advancements in the past year to improve the quality of their corrective action program work products. The inspectors have also witnessed a significant improving trend in the quality, detail, and technical rigor, of apparent cause evaluations and root cause analyses performed by station personnel.
 
====c. Findings====
No findings were identified.


===.3 Annual Follow-up of Selected Issues===
.2    Annual Inspection
  a. Inspection Scope
      On June 27, 2014, the inspectors completed their annual evaluation of the licensees fire
      brigade performance. This evaluation included observation of an unannounced fire drill
      for 2016, control building non-vital switchgear room B on June 27, 2014.
      During this drill, the inspectors evaluated the capability of the fire brigade members, the
      leadership ability of the brigade leader, the brigades use of turnout gear and fire-fighting
      equipment, and the effectiveness of the fire brigades team operation. The inspectors
      also reviewed whether the licensees fire brigade met NRC requirements for training,
      dedicated size and membership, and equipment.
      These activities constituted one annual inspection sample, as defined in Inspection
      Procedure 71111.05.
  b. Findings
      No findings were identified.
1R11 Licensed Operator Requalification Program and Licensed Operator Performance
      (71111.11)
      Review of Licensed Operator Requalification
  a. Inspection Scope
      On June 18, 2014, the inspectors evaluated a simulator scenario performed by an
      operating crew. The inspectors assessed the performance of the operators and the
      evaluators critique of their performance.
      These activities constitute completion of one quarterly licensed operator requalification
      program sample, as defined in Inspection Procedure 71111.11.
  b. Findings
      No findings were identified.
1R13 Maintenance Risk Assessments and Emergent Work Control (71111.13)
  a. Inspection Scope
      The inspectors reviewed two risk assessments performed by the licensee prior to
      changes in plant configuration and the risk management actions taken by the licensee in
      response to elevated risk:
          *  May 19-25, 2014, train A essential service water and emergency diesel generator
              planned maintenance outage
                                              -5-


====a. Inspection Scope====
        *  June 16-22, 2014, train B safety injection planned maintenance outage and train
The inspectors selected one issues for an in-depth follow-up:
            B containment spray planned maintenance outage
* On May 1, 2014, below ground essential service water piping replacement to correct long standing corrosion issues. The inspectors assessed the licensee's problem identification threshold, cause analyses, extent of condition reviews and compensatory actions. The inspectors reviewed modifications paperwork and observed pipe fitting and welding activities in the field. The inspectors verified that the licensee appropriately prioritized the planned corrective actions and that these actions were adequate to correct the condition. These activities constitute completion of one annual follow-up sample as defined in Inspection Procedure 71152.
    The inspectors verified that these risk assessments were performed timely and in
    accordance with the requirements of 10 CFR 50.65 (the Maintenance Rule) and plant
    procedures. The inspectors reviewed the accuracy and completeness of the licensees
    risk assessments and verified that the licensee implemented appropriate risk
    management actions based on the result of the assessments.
    The inspectors also observed portions of one emergent work activities that had the
    potential to affect the functional capability of mitigating systems:
        *  June 9-11, 2014, emergency diesel generator B governor testing failure and
            replacement
    The inspectors verified that the licensee appropriately developed and followed a work
    plan for these activities. The inspectors verified that the licensee took precautions to
    minimize the impact of the work activities on unaffected structures, systems, and
    components (SSCs).
    Additionally, the inspectors reviewed the risk assessments associated with two planned
    maintenance activities performed during a time in the outage when the primary plant was
    in a water-solid condition that resulted in unplanned pressure transients.
        *  March 14, 2014, reactor coolant system pressure transient during bus switching
        *  April 1, 2014, reactor coolant system pressure transient during motor-operated
            valve testing
    These activities constitute completion of four maintenance risk assessments and
    emergent work control inspection samples, as defined in Inspection Procedure 71111.13.
    (Note: The March 14, 2014, sample was counted in Inspection Report 2014002).
  b. Findings
    No findings were identified.
1R15 Operability Determinations and Functionality Assessments (71111.15)
  a. Inspection Scope
    The inspectors reviewed four operability determinations that the licensee performed for
    degraded or nonconforming SSCs:
        *  April 5, 2014, operability determination of train B emergency diesel generator
            heating, ventilation, and air conditioning inlet damper hydramotor oil analysis
        *  April 23, 2014, operability determination of containment cooler corrosion extent of
            condition
                                              -6-


====b. Findings====
        *  May 19, 2014, operability determination of NB01 under voltage surveillance
No findings were identified.  
            failure
{{a|4OA6}}
        *  June 11, 2014, operability determination of train B emergency diesel generator
==4OA6 Meetings, Including Exit==
            governor hydraulic actuator SKJ09B
    The inspectors reviewed the timeliness and technical adequacy of the licensees
    evaluations. Where the licensee determined the degraded SSC to be operable, the
    inspectors verified that the licensees compensatory measures were appropriate to
    provide reasonable assurance of operability. The inspectors verified that the licensee
    had considered the effect of other degraded conditions on the operability of the
    degraded SSC.
    In the case of the containment cooler issues, the inspectors obtained the assistance of
    specialist inspectors from the Region IV office and experts from the Office of Nuclear
    Reactor Regulation. The NRC conducted several calls with licensee technical and
    management personnel. Based on NRC concerns, the licensee decided to perform
    hydrostatic testing of the remaining coolers to provide provide test data to support
    continued operabililty with continuing pitting corrosion. The inspectors observed one of
    the pressure tests and reviewed the revised operability determination.
    These activities constitute completion of four operability review samples, as defined in
    Inspection Procedure 71111.15.
  b. Findings
    No findings were identified.
1R19 Post-Maintenance Testing (71111.19)
  a. Inspection Scope
    The inspectors reviewed four post-maintenance testing activities that affected risk-
    significant SSCs:
        *  April 14, 2014, essential service water train A flow balance
        *  April 15, 2014, emergency diesel generator train A jacket water leak
        *  April 23, 2014, reactor coolant pump C bump test and break away torque
        *  May 8, 2014, steam generator B bowl valve testing
    The inspectors reviewed licensing and design basis documents for the SSCs and the
    maintenance and post-maintenance test procedures. The inspectors observed the
    performance of the post-maintenance tests to verify that the licensee performed the tests
    in accordance with approved procedures, satisfied the established acceptance criteria,
    and restored the operability of the affected SSCs.
    These activities constitute completion of four post-maintenance testing inspection
    samples, as defined in Inspection Procedure 71111.19.
                                              -7-


=====Exit Meeting Summary=====
  b. Findings
On June 5, 2014, the inspectors presented the results of the radiation safety inspection to  Mr. C. Reasoner, Engineering, Vice President, and other members of the licensee staff. The licensee acknowledged the issues presented. The licensee confirmed that any proprietary information reviewed by the inspectors had been returned or destroyed.
    No findings were identified.
1R20 Refueling and Other Outage Activities (71111.20)
  a. Inspection Scope
    During the stations mid-cycle outage that concluded on May 13, 2014, the inspectors
    evaluated the licensees outage activities. The inspectors verified that the licensee
    considered risk in developing and implementing the outage plan, appropriately managed
    personnel fatigue, and developed mitigation strategies for losses of key safety functions.
    This verification included the following:
        *    Review of the licensees outage plan prior to the outage
        *    Monitoring of shut-down and cool-down activities
        *    Verification that the licensee maintained defense-in-depth during outage activities
        *    Monitoring of heat-up and startup activities
    These activities constitute completion of one planned outage sample outage activities
    sample, as defined in Inspection Procedure 71111.20.
  b. Findings
    No findings were identified.
1R22 Surveillance Testing (71111.22)
  a. Inspection Scope
    The inspectors observed six risk-significant surveillance tests and reviewed test results
    to verify that these tests adequately demonstrated that the SSCs were capable of
    performing their safety functions:
    In-service tests:
        *    April 25, 2014, accumulator vent valve EPV0109
    Reactor Coolant System Leak Detection:
        *    May 31, 2014, reactor coolant system water inventory balance
    Other surveillance tests:
        *    March 28-29, 2014, train A engineered safety features actuating safety testing
        *    April 25-28, 2014, station blackout diesel functional testing
        *    May 6, 2014, containment closeout walkdown
        *    May 19, 2014, reactor coolant system xenon-133 specific activity determination
                                              -8-


On July 8, 2014, the inspectors presented the inspection results to Mr. A. Heflin, Chief Executive Officer, and other members of the licensee staff. The licensee acknowledged the issues presented. The licensee confirmed that any proprietary information reviewed by the inspectors had been returned or destroyed.
    The inspectors verified that these tests met technical specification requirements, that the
    licensee performed the tests in accordance with their procedures, and that the results of
    the test satisfied appropriate acceptance criteria.
    These activities constitute completion of six surveillance testing inspection samples, as
    defined in Inspection Procedure 71111.22.
  b. Findings
    No findings were identified.
    Cornerstone: Emergency Preparedness
1EP6 Drill Evaluation (71114.06)
    Emergency Preparedness Drill Observation
  a. Inspection Scope
    The inspectors observed an emergency preparedness drill on June 18, 2014, to verify
    the adequacy and capability of the licensees assessment of drill performance. The
    inspectors reviewed the drill scenario, observed the drill from the simulator and
    emergency operations facility, and attended the post-drill critique. The inspectors
    verified that the licensees emergency classifications, off-site notifications, and protective
    action recommendations were appropriate and timely. The inspectors verified that any
    emergency preparedness weaknesses were appropriately identified by the licensee in
    the post-drill critique and entered into the corrective action program for resolution.
    These activities constitute completion of one emergency preparedness drill observation
    sample, as defined in Inspection Procedure 71114.06.
  b. Findings
    No findings were identified.
2    RADIATION SAFETY
    Cornerstones: Public Radiation Safety and Occupational Radiation Safety
2RS5 Radiation Monitoring Instrumentation (71124.05)
  a. Inspection Scope
    The inspectors evaluated the accuracy and operability of the radiation monitoring
    equipment used by the licensee (1) to monitor areas, materials, and workers to ensure a
    radiologically safe work environment, and (2) to detect and quantify radioactive process
    streams and effluent releases. The inspectors interviewed licensee personnel, walked
    down various portions of the plant, and reviewed licensee performance in the following
    areas:
                                              -9-


1
        *  Selected plant configurations and alignments of process, post-accident, and
            effluent monitors with descriptions in the Final Safety Analysis Report and the
            offsite dose calculation manual
        *  Select instrumentation, including effluent monitoring instrument, portable survey
            instruments, area radiation monitors, continuous air monitors, personnel
            contamination monitors, portal monitors, and small article monitors to examine
            their configurations and source checks
        *  Calibration and testing of process and effluent monitors, laboratory
            instrumentation, whole body counters, post-accident monitoring instrumentation,
            portal monitors, personnel contamination monitors, small article monitors,
            portable survey instruments, area radiation monitors, electronic dosimetry, air
            samplers, and continuous air monitors
        *  Audits, self-assessments, and corrective action documents related to radiation
            monitoring instrumentation since the last inspection
    These activities constitute completion of one sample of radiation monitoring
    instrumentation as defined in Inspection Procedure 71124.05.
b.  Findings
    No findings were identified.
2RS6 Radioactive Gaseous and Liquid Effluent Treatment (71124.06)
  a. Inspection Scope
    The inspectors evaluated whether the licensee maintained gaseous and liquid effluent
    processing systems and properly mitigated, monitored, and evaluated radiological
    discharges with respect to public exposure. The inspectors verified that abnormal
    radioactive gaseous or liquid discharges and conditions, when effluent radiation monitors
    are out-of-service, were controlled in accordance with the applicable regulatory
    requirements and licensee procedures. The inspectors verified that the licensees
    quality control program ensured radioactive effluent sampling and analysis adequately
    quantified and evaluated discharges of radioactive materials. The inspectors verified the
    adequacy of public dose projections resulting from radioactive effluent discharges. The
    inspectors interviewed licensee personnel and reviewed or observed the following items:
        *  Radiological effluent release reports since the previous inspection and reports
            related to the effluent program issued since the previous inspection
        *  Effluent program implementing procedures, including sampling, monitor setpoint
            determinations, and dose calculations
        *  Equipment configuration and flow paths of selected gaseous and liquid discharge
            system components, filtered ventilation system material condition, and significant
            changes to their effluent release points, if any, and associated 10 CFR 50.59
            reviews
                                            - 10 -


=SUPPLEMENTAL INFORMATION=
        *  Selected portions of the routine processing and discharge of radioactive gaseous
          and liquid effluents (including sample collection and analysis)
        *  Controls used to ensure representative sampling and appropriate compensatory
          sampling
        *  Results of the inter-laboratory comparison program
        *  Effluent stack flow rates
        *  Surveillance test results of technical specification-required ventilation effluent
          discharge systems since the previous inspection
        *  Significant changes in reported dose values
        *  A selection of radioactive liquid and gaseous waste discharge permits
        *  Part 61 analyses and methods used to determine which isotopes are included in
          the source term
        *  Offsite dose calculation manual changes
        *  Meteorological dispersion and deposition factors
        *  Latest land use census
        *  Records of abnormal gaseous or liquid tank discharges
        *  Groundwater monitoring results
        *  Changes to the licensees written program for identifying and controlling
          contaminated spills/leaks to groundwater
        *  Identified leakage or spill events and entries made into 10 CFR 50.75(g) records,
          if any, and associated evaluations of the extent of the contamination and the
          radiological source term
        *  Offsite notifications and reports of events associated with spills, leaks, or
          groundwater monitoring results
        *  Audits, self-assessments, reports, and corrective action documents related to
          radioactive gaseous and liquid effluent treatment since the last inspection
  These activities constitute completion of one sample of radioactive gaseous and liquid
  effluent treatment, as defined in Inspection Procedure 71124.06.
b. Findings
  No findings were identified.
                                            - 11 -


==KEY POINTS OF CONTACT==
2RS7 Radiological Environmental Monitoring Program (71124.07)
  a. Inspection Scope
    The inspectors evaluated whether the licensees radiological environmental monitoring
    program quantified the impact of radioactive effluent releases to the environment and
    sufficiently validated the integrity of the radioactive gaseous and liquid effluent release
    program. The inspectors verified that the radiological environmental monitoring program
    was implemented consistent with the licensees technical specifications and offsite dose
    calculation manual, and that the radioactive effluent release program met the design
    objective in Appendix I to 10 CFR Part 50. The inspectors verified that the licensees
    radiological environmental monitoring program monitored non-effluent exposure
    pathways, was based on sound principles and assumptions, and validated that doses to
    members of the public were within regulatory dose limits. The inspectors reviewed or
    observed the following items:
        *  Annual environmental monitoring reports and offsite dose calculation manual
        *  Selected air sampling and dosimeter monitoring stations
        *  Collection and preparation of environmental samples
        *  Operability, calibration, and maintenance of meteorological instruments
        *  Selected events documented in the annual environmental monitoring report
            which involved a missed sample, inoperable sampler, lost dosimeter, or
            anomalous measurement
        *  Selected structures, systems, or components that may contain licensed material
            and has a credible mechanism for licensed material to reach ground water
        *  Records required by 10 CFR 50.75(g)
        *  Significant changes made by the licensee to the offsite dose calculation manual
            as the result of changes to the land census or sampler station modifications since
            the last inspection
        *  Calibration and maintenance records for selected air samplers, composite water
            samplers, and environmental sample radiation measurement instrumentation
        *  Inter-laboratory comparison program results
        *  Audits, self-assessments, reports, and corrective action documents related to the
            radiological environmental monitoring program since the last inspection
    These activities constitute completion of one sample of the radiological environmental
    monitoring program as defined in Inspection Procedure 71124.07.
                                              - 12 -


===Licensee Personnel===
  b. Findings
: [[contact::L. Aiken]], Health Physicist II
      No findings were identified.
: [[contact::D. Campbell]], Superintendent, Electrical Maintenance
2RS8 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage,
: [[contact::C. Carman]], Supervisor, Chemistry
      and Transportation (71124.08)
: [[contact::S. Carpenter]], Technician, Instruments and Controls
  a. Inspection Scope
: [[contact::B. Crow]], System Engineering
      The inspectors evaluated the effectiveness of the licensees programs for processing,
: [[contact::D. Dees]], Superintendent, Operations Support
      handling, storage, and transportation of radioactive material. The inspectors interviewed
: [[contact::D. Erbe]], Manager, Security
      licensee personnel and reviewed the following items:
: [[contact::R. Flannigan]], Manager, Nuclear Engineering
          *  The solid radioactive waste system description, process control program, and the
: [[contact::K. Fredrickson]], Engineer, Licensing
            scope of the licensees audit program
: [[contact::J. Freeman]], Supervisor, Operations
          *  Control of radioactive waste storage areas including container labeling/marking
: [[contact::C. Garcia]], Supervisor, Engineering
            and monitoring containers for deformation or signs of waste decomposition
: [[contact::D. Gibson]], Technician, Radiation Protection
          *  Changes to the liquid and solid waste processing system configuration including
: [[contact::M. Guyer]], Training
            a review of waste processing equipment that is not operational or abandoned in
: [[contact::R. Hammond]], Supervisor, Regulatory Support
            place
: [[contact::A. Heflin]], President and Chief Executive Officer
          *  Radio-chemical sample analysis results for radioactive waste streams and use of
: [[contact::S. Henry]], Manager, Integrated Plant Scheduling
            scaling factors and calculations to account for difficult-to-measure radionuclides
: [[contact::P. Herrman]], Manager, Programs Engineering
          *  Processes for waste classification including use of scaling factors and
: [[contact::R. Hobby]], Licensing Engineer
            10 CFR Part 61 analysis
: [[contact::S. Hossain]], Engineer, System Engineering
          *  Shipment, packaging, surveying, labeling, marking, placarding, vehicle checking,
: [[contact::B. Kiley]], Technician III, Chemistry
            driver instructing, and preparation of the disposal manifest
: [[contact::S. Koenig]], Manager, Regulatory Affairs
          *  Audits, self-assessments, reports, and corrective action reports on radioactive
: [[contact::R. Lane]], Superintendent, Operations
            solid waste processing and radioactive material handling, storage,
: [[contact::M. McMullen]], Design Engineer, Engineering
            and transportation performed since the last inspection
: [[contact::C. Medenciy]], Supervisor, Radiation Protection
      These activities constitute completion of one sample of radioactive solid waste
: [[contact::K. Miller]], Technician Level III, Instruments and Controls
      processing, and radioactive material handling, storage, and transportation as defined in
: [[contact::K. Mitchell]], Master Chemistry Technician
      Inspection Procedure 71124.08.
: [[contact::W. Muilenburg]], Supervisor, Licensing
  b. Findings
: [[contact::T. Rice]], Manager, Environmental Management
      No findings were identified.
: [[contact::D. Scrogum]], Systems Engineer, Engineering
4.   OTHER ACTIVITIES
: [[contact::M. Skiles]], Acting Manager, Radiation Protection
      Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity, Emergency
: [[contact::R. Smith]], Site Vice President
      Preparedness, Public Radiation Safety, Occupational Radiation Safety, and
: [[contact::S. Smith]], Plant Manager
      Security
: [[contact::T. Smith]], Manager, Project Construction Engineering
                                            - 13 -
: [[contact::J. Truelove]], Supervisor, Chemistry
: [[contact::L. Upson]], Manager, Strategic Initiatives
: [[contact::B. Vickery]], Manager, Financial Services
: [[contact::J. Yunk]], Manager, Corrective Actions


==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED==
4OA1 Performance Indicator Verification (71151)
.1    Reactor Coolant System Specific Activity (BI01)
  a.  Inspection Scope
      The inspectors reviewed the licensees reactor coolant system chemistry sample
      analyses for the period of April 1, 2013, through March 31, 2014, to verify the accuracy
      and completeness of the reported data. The inspectors reviewed the surveillance
      paperwork for the reactor coolant system sample taken on May 19, 2014. The
      inspectors used definitions and guidance contained in Nuclear Energy Institute
      Document 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7,
      to determine the accuracy of the reported data.
      These activities constituted verification of the reactor coolant system specific activity
      performance indicator, as defined in Inspection Procedure 71151.
  b.  Findings
      No findings were identified.
.2    Reactor Coolant System Identified Leakage (BI02)
  a. Inspection Scope
      The inspectors reviewed the licensees records of reactor coolant system identified
      leakage for the period of April 1, 2013 through March 31, 2014 to verify the accuracy and
      completeness of the reported data. The inspectors reviewed the performance
      of STS BB-006 RCS Water Inventory Balance on May 31, 2014. The inspectors used
      definitions and guidance contained in Nuclear Energy Institute Document 99-02,
      Regulatory Assessment Performance Indicator Guideline, Revision 7, to determine the
      accuracy of the reported data.
      These activities constituted verification of the reactor coolant system leakage
      performance indicator, as defined in Inspection Procedure 71151.
  b. Findings
      No findings were identified.
4OA2 Problem Identification and Resolution (71152)
.1    Routine Review
  a. Inspection Scope
      Throughout the inspection period, the inspectors performed daily reviews of items
      entered into the licensees corrective action program and periodically attended the
      licensees condition report screening meetings. The inspectors verified that licensee
      personnel were identifying problems at an appropriate threshold and entering these
      problems into the corrective action program for resolution. The inspectors verified that
                                              - 14 -


===Opened and Closed===
      the licensee developed and implemented corrective actions commensurate with the
: 05000482-2014003-01 NCV Failure to Assess and Manage Risk of Planned Outage Maintenance Activities During Solid Plant Operations
      significance of the problems identified. The inspectors also reviewed the licensees
(Section 1R13)    
      problem identification and resolution activities during the performance of the other
==LIST OF DOCUMENTS REVIEWED==
      inspection activities documented in this report.
==Section 1R01: Adverse Weather Protection==
  b. Findings
      No findings were identified.
.2    Semiannual Trend Review
  a. Inspection Scope
      To verify that the licensee was taking corrective actions to address identified adverse
      trends that might indicate the existence of a more significant safety issue, the inspectors
      reviewed corrective action program documentation associated with the following
      licensee-identified trends:
          *  High backlogs in the design implementation and configuration control process
              area
      Also, the inspectors identified the following trends that might indicate the existence of a
      more significant safety issue, and reviewed the licensees response to them:
          *  Inadequate technical verification and validation of temporary and permanent
              plant modifications
          *  The licensees corrective action program group is not trending data at a station-
              wide level (i.e., above the department level), nor are they prioritizing
              departmental issues and trends which are significantly affecting overall station
              performance
      The NRC identified a theme in NRC inspection findings with cross-cutting aspects in
      maintaining design margins [H.6] during the 2013 End Of Cycle Assessment. The
      inspectors reviewed the licensees response to that trend to verify that the licensee was
      taking appropriate actions to address it.
      These activities constitute completion of one semiannual trend review sample, as
      defined in Inspection Procedure 71152.
  b. Observations and Assessments
      The inspectors review of the trends identified above produced the following observations
      and assessments:
          *   Design Control Backlogs. In July of 2013, an industry group assessment of
              station performance noted an unusually high number of open design change
              packages. The backlog included approximately 1700 change packages, some
              open since the early 1990s, including some SSCs with multiple open design
              changes. Some change packages had targeted completion dates that were
                                              - 15 -


===Procedures===
    beyond the expiration date of the plant operating license. Historically, the station
: Number Title Revision STS
    has had challenges with design control, as noted in NRC inspection reports.
: NB-005 Breaker Alignment Verification 26
    The licensee performed an apparent cause evaluation under Condition
    Reports 72164, 72166, and 72167 to identify the organizational causes. Among
    the licensees conclusions, management oversight of configuration control was
    lacking, there was not an awareness of the vulnerability created by incomplete
    configuration changes, and there was no single owner of design change products
    to ensure configuration management documents are kept up to date. The
    licensee took corrective actions to develop a configuration management health
    plan to improve the design control program as well as developing a
    comprehensive backlog reduction strategy. The inspectors also noted that the
    licensee performed an aggregate risk assessment of the backlog to ensure that
    items with more significant safety impacts were addressed more quickly. The
    inspectors also noted that the backlog reduction program has reduced the
    number of open change packages to 400 at the end of June 2014, with a goal of
    less than 200 planned by January 2015.
  *  Findings with Design Margins Cross Cutting Aspect [H6]. A theme in findings
    with cross-cutting aspects in the area of maintaining design margins was
    identified during the NRCs 2013 End of Cycle Assessment for Wolf Creek. The
    licensee performed an apparent cause evaluation under Condition
    Reports 74508 and 78794. The inspectors noted that this trend was related to
    the larger problem of backlog management. Because this trend is related to
    other improvement efforts, the inspectors noted that the licensee has evaluated
    and taken actions related to this theme in the areas of corrective action,
    preventive maintenance, and procedure revision backlog reductions under
    Condition Reports 62394, 68194, and 78708. Most of the backlog improvement
    efforts were making a notable reduction. The inspectors observed that most
    backlog reduction efforts remained on target through the mid-cycle 20 outage in
    March and April of 2014. Overall outage management and scope control
    performance improvement was observed, and as a result, the corrective action
    and work order backlogs did not see the growth observed during previous
    outages. The licensee has taken corrective actions to establish and validate new
    internal performance indicators for the engineering and maintenance
    departments. Furthermore the licensee has scheduled actions to track these
    new indicators and backlogs to specific goals based on industry standards in the
    future.
Also, while completing this trend review, the inspectors identified the following trends
that the licensee had not previously identified. The inspectors also reviewed the
licensees response to these trends:
  *  Quality of Plant Modifications. Over the past 2 years, Wolf Creek has been
    implementing a large number of modifications. Additional non-safety related
    diesel generators and an auxiliary feed water pump were added to improve plant
    safety. The plant has also been addressing long standing corrosion and water
    hammer issues in the essential service water system by replacing piping above
    and below ground. Obsolete analog controllers have been replaced with digital
    control systems. However, the inspectors have observed a number of plant
    events and equipment failures associated with inadequate technical validation
                                    - 16 -


==Section 1R04: Equipment Alignment==
and verification associated with these modifications.
      On May 2, 2013, an unplanned and uncontrolled 11 percent power
      increase occurred as a result of operator training deficiencies while
      swapping from the full arc to partial arc steam admission shortly after
      installing the new Westinghouse Ovation digital turbine controls. It was
      subsequently determined that additional functions and flexibilities of the
      new digital control system allowed operators to manipulate the plant in
      configurations prohibited by the old analog system, and that system
      response varied with power level, but this was not recognized and
      incorporated into procedures and training. Condition Report 68711,
      Non-Cited Violation NCV 05000482/2013003-05.
      On May 28, 2013, and again on September 5, 2013, the turbine driven
      auxiliary feed water pump control system failed unexpectedly, rendering
      the pump incapable of operation. The digital control system positioner
      locked up and required replacement. It was later determined that an
      additional unused input to the positioner was experiencing noise, and if
      the noise came in at a certain point in the digital computer programs
      subroutine, the control software would crash. The problem was fixed by
      jumpering out the unused input connection and a vendor technical bulletin
      was issued to correct vulnerabilities at other nuclear power plants utilizing
      the same control system. Condition Reports 69721, 69754, and 73624.
      On April 25, 2014, during station blackout diesel generator testing, the
      licensee was unable to connect the train A Class 1E 4kV distribution bus
      to the station blackout diesel generators due to a protective relay
      actuating to lock out the bus. The diesels had been declared functional
      and were credited in performance indicators and probabilistic risk
      assessment models since October 2013, when construction was
      completed but testing had not been fully completed. Troubleshooting as a
      result of the failed test found incorrect wiring of a protective relay to be
      the cause. Extent of condition inspections found that the train B bus
      connection was also wired incorrectly, and neither safety related bus
      would have been able to have been powered from the station blackout
      diesel generators. The licensee had intended to perform testing during
      the previous refueling outage, but construction delays caused work to
      extend beyond the outage. Plant conditions for this test necessitated the
      plant be shut down. The inspectors had engaged the licensee concerning
      their testing plan when construction was complete, but the licensee
      concluded that their quality checks were adequate to have a high
      confidence that testing to connect the generators to the safety buses
      would be adequate until plant conditions for the testing were available.
      The inspectors concluded that those quality checks were inadequate,
      although this did not constitute a violation because the diesel generators
      and protective relaying were non-safety equipment and were not credited
      to meet any regulatory requirements. Condition Report 83379.
                                  - 17 -


===Procedures===
Not all of the validation and verification oversights resulted in plant events or
: Number Title Date CKL
failures. Some of the items were caught very late in the planning process,
: EM-120 Safety Injection System Lineup Checklist September 17, 2014
but still impacted regulatory commitments.
    In February of 2014 the licensee commitment to correct long standing
    water hammer conditions in the essential service water system was
    delayed. The 2010 and 2012 Problem Identification and Resolution
    inspections have assessed cited violations regarding long-standing
    essential service water corrosion and water hammer issues not being
    addressed in a timely manner. Wolf Creek responded on the docket and
    committed to fixing the essential service water corrosion and water
    hammer issues by the spring 2014 mid-cycle outage. However, after
    over 3 years of planning, shortly before a modification was to be installed
    to correct the water hammer, it was discovered that the mitigating strategy
    would invalidate the essential service water design basis safety function
    to provide a source of auxiliary feed water during a design basis external
    event that compromises the condensate storage tank. This was
    documented in Condition Reports 53443 and 79619. The licensee
    concluded that there was inadequate contractor oversight during the
    modification development process. A revised modification was tentatively
    rescheduled for the next refueling outage.
    On March 30, 2014, a containment cooler tube bundle failed (small tube
    leaks) as a result of water hammer during the engineered safety features
    actuation system testing. A similar failure occurred when the opposite
    train was tested a few weeks later. While reviewing the cause evaluation,
    the inspectors noted the failure mechanism was due to a combination of
    pitting corrosion and sudden pressure spike during the essential service
    water system water hammer. The ispectors determined that corrective
    actions to address corrosion in carbon steel essential service water piping
    had not addressed the copper-nickel containment cooler tubes. The
    inspectors reviewed the history of containment cooler degradation and
    noted that all 48 of the tube bundles had already been replaced due to
    widespread degradation in the late 1990s, and now the 2nd generation
    like-for-like replacements were beginning to fail. The problem was further
    complicated because non-destructive testing to monitor corrosion was not
    possible because the cooler design and complex cooler geometry
    prevented this. The licensee plans to correct the condition by replacing
    all coolers dueing the next outage, then replacing the original design with
    stainless steel cooler tubes that will allow for eddy current testing.
    Condition Reports 81809 and 82904.
    On November 18, 2011, an NRC Component Design Basis Inspection
    assessed NCV 05000482/2010007-01 for the failure to properly analyze
    the isolation between the safety-related and non-safety related portions of
    the component cooling water system. Portions of the non-safety piping
    leading to the rad waste building are non-seismically qualified, and should
    they fail, could result in a loss of inventory greater than can be
    accommodated by the component cooling water surge tanks. The
    inspector noted that the licensee promptly manually isolated this piping
    and has been working on installing a combination of check valves and
                              - 18 -


==Section 1R05: Fire Protection==
                      orifices, for the past four years. The planned modification to correct this
                      violation has been delayed a number of times since 2012 because the
                      licensee has found problems with the design. Condition Reports 28237
                      and 85328.
                      The inspectors determined that the licensee was aware of these issues
                      individually, but had not identified the collective trend. The licensee wrote
                      Condition Report 85907 to evaluate and address this trend.
          *  Lack Trending and Prioritization above the Department Level. In reviewing the
            station roll-up reports that record corrective action program activities at the
            station and departmental levels, the inspectors noted that the analytical trending
            ends at the departmental summaries. The station corrective action staff was not
            summarizing analytical trends across divisions, nor were they giving additional
            priority to departmental trends which were having a significant impact on station
            performance. (e.g. design control, procedure quality, etc.)
            The inspectors reviewed additional documentation associated with station
            improvement initiatives and determined that at a station level, senior leadership
            was performing some station level trend analysis and setting station priorities
            based on the available data, but this was being done outside the corrective
            action program, and was not proceduralized and therefore would not continue
            when the improvement initiatives were completed. The licensee has written
            Condition Report 85905 to evaluate and address this issue.
            The inspectors assessment noted improved corrective action trending at the
            department level. The operations department continues to be a station leader in
            this area. The maintenance and engineering departments have made notable
            advancements in the past year to improve the quality of their corrective action
            program work products. The inspectors have also witnessed a significant
            improving trend in the quality, detail, and technical rigor, of apparent cause
            evaluations and root cause analyses performed by station personnel.
  c.  Findings
      No findings were identified.
.3    Annual Follow-up of Selected Issues
  a. Inspection Scope
      The inspectors selected one issues for an in-depth follow-up:
          *  On May 1, 2014, below ground essential service water piping replacement to
            correct long standing corrosion issues.
            The inspectors assessed the licensees problem identification threshold, cause
            analyses, extent of condition reviews and compensatory actions. The inspectors
            reviewed modifications paperwork and observed pipe fitting and welding activities
            in the field. The inspectors verified that the licensee appropriately prioritized the
                                                - 19 -


===Procedures===
                planned corrective actions and that these actions were adequate to correct the
: Number Title Revision
                condition.
: AP 10-106 Fire Preplans 13
        These activities constitute completion of one annual follow-up sample as defined in
        Inspection Procedure 71152.
  b.  Findings
        No findings were identified.
4OA6 Meetings, Including Exit
Exit Meeting Summary
On June 5, 2014, the inspectors presented the results of the radiation safety inspection to
Mr. C. Reasoner, Engineering, Vice President, and other members of the licensee staff. The
licensee acknowledged the issues presented. The licensee confirmed that any proprietary
information reviewed by the inspectors had been returned or destroyed.
On July 8, 2014, the inspectors presented the inspection results to Mr. A. Heflin, Chief Executive
Officer, and other members of the licensee staff. The licensee acknowledged the issues
presented. The licensee confirmed that any proprietary information reviewed by the inspectors
had been returned or destroyed.
                                              - 20 -


==Section 1R11: Licensed Operator Requalification Program and Licensed Operator Performance==
                                  SUPPLEMENTAL INFORMATION
                                    KEY POINTS OF CONTACT
Licensee Personnel
L. Aiken, Health Physicist II
D. Campbell, Superintendent, Electrical Maintenance
C. Carman, Supervisor, Chemistry
S. Carpenter, Technician, Instruments and Controls
B. Crow, System Engineering
D. Dees, Superintendent, Operations Support
D. Erbe, Manager, Security
R. Flannigan, Manager, Nuclear Engineering
K. Fredrickson, Engineer, Licensing
J. Freeman, Supervisor, Operations
C. Garcia, Supervisor, Engineering
D. Gibson, Technician, Radiation Protection
M. Guyer, Training
R. Hammond, Supervisor, Regulatory Support
A. Heflin, President and Chief Executive Officer
S. Henry, Manager, Integrated Plant Scheduling
P. Herrman, Manager, Programs Engineering
R. Hobby, Licensing Engineer
S. Hossain, Engineer, System Engineering
B. Kiley, Technician III, Chemistry
S. Koenig, Manager, Regulatory Affairs
R. Lane, Superintendent, Operations
M. McMullen, Design Engineer, Engineering
C. Medenciy, Supervisor, Radiation Protection
K. Miller, Technician Level III, Instruments and Controls
K. Mitchell, Master Chemistry Technician
W. Muilenburg, Supervisor, Licensing
T. Rice, Manager, Environmental Management
D. Scrogum, Systems Engineer, Engineering
M. Skiles, Acting Manager, Radiation Protection
R. Smith, Site Vice President
S. Smith, Plant Manager
T. Smith, Manager, Project Construction Engineering
J. Truelove, Supervisor, Chemistry
L. Upson, Manager, Strategic Initiatives
B. Vickery, Manager, Financial Services
J. Yunk, Manager, Corrective Actions
                                                          Attachment 1


===Procedures===
                  LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
: Number Title Revision
Opened and Closed
: BD-EMG C-0 Loss of All AC Power 20
05000482-2014003- NCV        Failure to Assess and Manage Risk of Planned Outage
01                            Maintenance Activities During Solid Plant Operations
                              (Section 1R13)
                            LIST OF DOCUMENTS REVIEWED
Section 1R01: Adverse Weather Protection
Procedures
Number          Title                                                          Revision
STS NB-005      Breaker Alignment Verification                                26
Section 1R04: Equipment Alignment
Procedures
Number          Title                                                          Date
CKL EM-120      Safety Injection System Lineup Checklist                      September
                                                                                17, 2014
Section 1R05: Fire Protection
Procedures
Number           Title                                                         Revision
AP 10-106        Fire Preplans                                                  13
Section 1R11: Licensed Operator Requalification Program and Licensed Operator
Performance
Procedures
Number          Title                                                          Revision
BD-EMG C-0       Loss of All AC Power                                           20
Section 1R13: Maintenance Risk Assessments and Emergent Work Control
Procedures
Number          Title                                                          Revision/Date
AI 22C-013      Protected Equipment Program                                    11
                                            A1-2


==Section 1R13: Maintenance Risk Assessments and Emergent Work Control==
Procedures
Number            Title                                                        Revision/Date
AP 22B-001        Outage Risk Management                                      17
AP 21D-002        Evaluation for Potential Energy/Fluid Transfer Paths        11A
APF 22B-001-10 Shutdown Safety Function Status and Risk Assessment            March 14,
                  Summary                                                      2014 Night
                                                                              Shift
APF 22B-001-10 Shutdown Safety Function Status and Risk Assessment            April 1, 2014
                  Summary                                                      Day Shift
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment,          May 28, 2014
                  Schedule Week 2014-0211
APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment          June 11,
                  Schedule Week 2014-0212                                      2014
SYS PG-204        Energizing PG19 or PG20 from Alternate Power Source          21
TMP 14-002        CCW Train B Operations with Heat Exchanger Bypassed          0
Condition Reports
80870              81981
Work Order
12-359936-000      12-359637-000
Miscellaneous
Number        Title                                                        Revision/Date
ODM 2014-05    Operations Decision Making Documentation Form: Wolf          0
              Creek will maintain solid pressurizer conditions with reduced
              temperature and pressure control bands.
APF 22C-007    Shutdown Safety Contingency Planning Template: Decay          1
              Heat Removal Defense in Depth
M-EJ-A-001    Clearance Order: RHR to CVCS Centrifugal Charging            April 2, 2014
              Pumps Isolation Valve
              Work Week Manager Logs
              Control Room Logs
              Weekly Major Activity Summary Week 2014-208
              Weekly Major Activity Summary Week 2014-211
              Weekly Major Activity Summary Week 2014-212
                                            A1-3


===Procedures===
Miscellaneous
: Number Title Revision/DateAI 22C-013 Protected Equipment Program 11
Number         Title                                                   Revision/Date
===Procedures===
              Wolf Creek Shift Outage Update                          March 13,
: Number Title Revision/DateAP 22B-001 Outage Risk Management 17
                                                                      2014 Day Shift
: AP 21D-002 Evaluation for Potential Energy/Fluid Transfer Paths 11A
Section 1R15: Operability Determinations and Functionality Assessments
: APF 22B-001-10 Shutdown Safety Function Status and Risk Assessment Summary March 14, 2014 Night Shift
Procedures
: APF 22B-001-10 Shutdown Safety Function Status and Risk Assessment Summary April 1, 2014 Day Shift
Number            Title                                                Revision
: APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment, Schedule Week 2014-0211 May 28, 2014APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment Schedule Week 2014-0212 June 11, 2014 SYS
OE K-14-009        B-EDG Governor Hydraulic Actuator                    0
: PG-204 Energizing PG19 or PG20 from Alternate Power Source 21
STS IC-208A        4kV Loss of Voltage and Degraded Voltage TADOT NB01  5B
: TMP 14-002 CCW Train B Operations with Heat Exchanger Bypassed 0
                  Bus - Separation Group 1
===Condition Reports===
Condition Reports
: 80870 81981   
85015              81809              82266            84318
: Work Order
Engineering Disposition
: 12-359936-000 12-359637-000
Title                                                                  Revision
===Miscellaneous===
Containment Cooler Tube Pitting                                        1
: Number Title Revision/Date
Section 1R19: Post-Maintenance Testing
: ODM 2014-05 Operations Decision Making Documentation Form:
Procedures
: Wolf Creek will maintain solid pressurizer conditions with reduced temperature and pressure control bands. 0
Number           Title                                                 Revision/Date
: APF 22C-007 Shutdown Safety Contingency Planning Template:
STN EF-220A      ESW Train A Post-LOCA Flow Balance                    March 4, 2014
: Decay Heat Removal Defense in Depth 1 M-EJ-A-001 Clearance Order:
SYS BB-201        Reactor Coolant Pump Operation                        58
: RHR to CVCS Centrifugal Charging Pumps Isolation Valve April 2, 2014
SYS KJ-123-2      Post Maintenance Run of EDG A                         January 30,
: Work Week Manager Logs
                                                                        2014
: Control Room Logs Weekly Major Activity Summary Week 2014-208
Work Orders
: Weekly Major Activity Summary Week 2014-211
14-385808-006      11-347436-002      14-387407-002    14-386517-001
: Weekly Major Activity Summary Week 2014-212
                                            A1-4
===Miscellaneous===
: Number Title Revision/Date
: Wolf Creek Shift Outage Update March 13, 2014 Day Shift


==Section 1R15: Operability Determinations and Functionality Assessments==
Section 1R20: Refueling and Other Outage Activities
Procedures
Number          Title                                                          Date
NE 14-0005      Mid-Cycle 20 Level 1 Schedule and Outage Risk                  February 6,
                Assessment Report                                              2014
Section 1R22: Surveillance Testing
Procedures
Number        Title                                                          Revision/Date
STS BB-006    RCS Water Inventory Balance Using the NPIS Computer            12
STS CH-024    Reactor Coolant Dose Equivalent Xe-133 Determination          6A
STS IC-208A  4kv Loss of Voltage and Degraded Voltage TADOT NB01            5B
              Bus - Separation Group 1
STS KJ-001A  Integrated D/G and Safeguards Actuation Text Train A          March 14, 2014
STN KU-001A SBO DG NB01 Functional Test                                      March 28, 2014
STN EJ-002    Containment Inspection                                        20
Section 2RS5: Radiation Monitoring Instrumentation
Procedures
Number        Title                                                            Revision/Date
CHS AC-001    Accident Sampling                                                4A
WCIC-236      RMS Calibration Document                                          November 13,
                                                                                1995
STN SP-118    Channel Calibration Liquid Radwaste Discharge Radiation          8
              Monitor HB RE-0018
STN CH-010    Calibration of Liquid Radiation Monitors                          3B
STS CH-014    Calibration of Monitors GTRE21B and GHRE10B                      12
STN CH-021    Calibration of the Particulate Detector for Radiation Monitors    4A
              GTRE21A and GHRE10A
STN CH-022    Calibration of the Iodine Detector for Radiation Monitors        1B
              GTRE21A and GHRE10B
AP 07B-003    Offsite Dose Calculation Model                                    8
RPP 01-405    HP Instrument Program                                            30
                                            A1-5


===Procedures===
Procedures
: Number Title Revision OE K-14-009 B-EDG Governor Hydraulic Actuator 0 STS
Number         Title                                                       Revision/Date
: IC-208A 4kV Loss of Voltage and Degraded Voltage TADOT NB01 Bus - Separation Group 1 5B
RPP 03-407      Testing of Portal Monitors as Passive Whole Body Counters  1A
===Condition Reports===
RPP 05-707      Operation of Whole Body Counters                            8
: 85015 81809 82266 84318 
RPP 06-101      Eberline RO-2 and RO-2A Calibration                        6
: Engineering Disposition Title Revision Containment Cooler Tube Pitting 1
RPP 06-105      Eberline RO-20 Calibration                                  5
RPP 06-306      PM12 Calibration                                            8A
STN SP-118      Channel Calibration Liquid Radwaste Discharge Radiation    8
                Monitor HB RE-0018
STN CH-010      Calibration of Liquid Radiation Monitors                    3B
Condition Reports
00081759            00084854          00084863          00084815        00084820
00084817            00083254          00082997          00080994        00079621
00078962            00078548          00074873          00074445        00074219
00072691            00072303          00068426          00068295        00068064
00051785            00054489          00065431          00067627        00062921
Calibration Records
Number              Title                                                 Date
WO12360791000 Channel Calibration Digital High Range Area Monitor          February 4,
                    GTRE-0059 Calibration Source Drop                      2014
WO13381072000 Channel Calibration Digital High Range Area Radiation        January 28,
                    Monitor GTRE60                                        2014
WO12360792000 Channel Calibration Digital High Range Area Radiation        February 3,
                    Monitor GTRE60 Calibration Source Drop                2014
WO13381018000 Channel Calibration Digital High Range Area Radiation        January 24,
                    Monitor GTRE59                                        2014
11428              AMS4                                                  March 9, 2014
11748              AMS4                                                  March 9, 2014
11429              AMS4                                                  February 24,
                                                                          2014
                                              A1-6


==Section 1R19: Post-Maintenance Testing==
11376          PCM-1B                                          February 5,
                                                                2009
11379          PCM-1B                                          February 5,
                                                                2009
11378          PCM-1B                                          April 17, 2014
10240          PCM-1C                                          April 9, 2009
11005          SAM 11                                          January 29,
                                                                2014
11006          SAM 11                                          June 19, 2013
92874          RTM 110                                          March 23,
                                                                2014
92877          RTM 110                                          April 28, 2014
10260          ASP-1                                            February 6,
                                                                2014
93330          PM12                                            August 15,
                                                                2013
93573          PM12                                            February 5,
                                                                2014
11511          HD-29A                                          January 29,
                                                                2014
10242          PCM-2                                            December 9,
                                                                2013
10066          Whole Body Counter Calibration Certificate      July 18, 2011
13027          Whole Body Counter Calibration Certificate      September 15,
                                                                2008
Section 2RS6: Radioactive Gaseous and Liquid Effluent Treatment
Procedures
Number          Title                                            Revision
AI 07-007      Onsite Groundwater Protection Program Monitoring  14
AI 07B-001      Radioactive Releases                              19
AI 07B-020      Instructions for Composite Preparation            19
AI 07B-036      Liquid Release Permits Using RADEAS              01
AI 07B-037      Unit and Radwaste Vent Permits Using RADEAS      01
AI 07B-038      Unit and Radwaste Vent Permits Using RADEAS      01
                                          A1-7


===Procedures===
Procedures
: Number Title Revision/Date STN
Number           Title                                                     Revision
: EF-220A ESW Train A Post-LOCA Flow Balance March 4, 2014 SYS
AP 07B-003        Offsite Dose Calculation Manual                            08
: BB-201 Reactor Coolant Pump Operation 58
CHA RC-004        Gamma Isotopic, Total Curie Content and Dose Equivalent    15
: SYS
                  Iodine Determination
: KJ-123-2 Post Maintenance Run of EDG A January 30, 2014
CHS RW-G02        Radwaste Vent Sampling and/or Exchange of Filters          3C
===Work Orders===
CHS SJ-144A      SJ-144 Sampling Instructions                              0C
: 14-385808-006 11-347436-002 14-387407-002 14-386517-001
CHS TB-L03        Turbine Building Local Sampling - Mid-Frequency            06
RPP 07-111        Handling Cartridge Filters                                17
Condition Reports
00051966          00053930          00055466          00055535          00055538
00056233          00056574          00056887          00059243          00059832
00061757          00064627          00064667          00064798          00065779
00066655          00066920          00068803          00069832          00069959
00070420          00070826          00072303          00076226          00077621
00077802          00078707          00082909          00083740          00084346
10 CFR 50.75(g) Condition Reports
00084942
Gaseous and Liquid Release Permits
Permit No.                System                        Release Type Date
U1LC2014-080/2013060      Turbine Building Drains      Liquid        June 11, 2013
U1GB2014-093/2013081      Containment Purge Unit Vent  Gaseous      July 17, 2013
U1GB2014-099/2013087      Containment Purge Unit Vent  Gaseous      July 27, 2013
U1LC2014-091/2013071      Steam Generator Blowdown      Liquid        August 30, 2013
U1LC2014-110/2013090      Lime Sludge Pond              Liquid        November 19, 2013
U1GB2014-017/2014017      Containment Purge Unit Vent  Gaseous      February 4, 2014
U1LC2014-005/2014005      Steam Generator Blowdown      Liquid        March 1, 2014
U1GB2014-162/2014162      Containment Purge Unit Vent  Gaseous      April 7, 2014
                                            A1-8


==Section 1R20: Refueling and Other Outage Activities==
In-Place Filter Testing Records
Work Order          Test                                                      Date
STS PE-006          Charcoal Adsorber In-Place Leak Test Safety-Related Units December 10,
                    - FGK01B                                                  2013
STS PE-005          HEPA Filter In-Place Leak Test Safety-Related Units -    December 10,
                    FGK01B                                                    2013
STS PE-002          Charcoal Adsorbent Sampling for Nuclear Safety-Related    December 23,
                    Units - FGK01B                                            2013
STS PE-002          Charcoal Adsorbent Sampling for Nuclear Safety-Related    December 23,
                    Units - FGG02B                                            2013
STS PE-006          Charcoal Adsorber In-Place Leak Test Safety-Related Units February 24,
                    - FGK01A                                                  2014
STS PE-005          HEPA Filter In-Place Leak Test Safety-Related Units -    February 24,
                    FGK01A                                                    2014
Miscellaneous Documents
Number                Title                                                    Revision/Date
11.1A-3              USAR Figure: Potential Gaseous Release                  13
M-12HB01-5            WCNOC PID: Liquid Radwaste System                        20
M-12EG01              WCNOC PID: Component Cooling Water System                24
                      System Health Report: Radiation Monitoring              January 1 -
                                                                              September
                                                                              30, 2013
RA 13-0052            WCNOC 2013 Annual Radioactive Effluent Release
                      Report
RPF 02-210-05        50.75(g) Radiological Occurrence Worksheet for          June 2, 2014
                      Decommissioning Record
2013-011-EG00        Temporary Modification Order: EG System (A/B Trains),    August 19,
                      EGV0357 & EGV0310, EGV0324 & EGV0388                    2013
RA 14-0043            WCNOC 2014 Annual Radioactive Effluent Release          April 29, 2014
                      Report
                      WC Radiation Monitors Considered for Maintenance Rule    June 2, 2014
Section 2RS7: Radiological Environmental Monitoring Program
Procedures
Number                  Title                                                  Revision
AI 07B-004              Reporting Requirements of the Radiological            13
                        Environmental Monitoring Program
                                              A1-9


===Procedures===
Procedures
: Number Title Date
Number               Title                                                 Revision
: NE 14-0005 Mid-Cycle 20 Level 1 Schedule and Outage Risk Assessment Report February 6, 2014
AI 07B-005            Radiological Environmental Monitoring Program        20
                      Implementation
AI 07B-009            Collection, Preparation and Shipment of Sediment and  8
                      Soil Samples
AI 07B-011            Collection, Preparation and Shipment of Water Samples 15
AI 07B-012            Collection, Preparation and Shipment of Crop,        10
                      Vegetable, Fruit and Pasturage Samples
AI 07B-015            Land Use Census                                      11
AI 07B-034            Radiological Environmental Monitoring Program Air    11
                      Sampling
AI 07B-035            REMP Optically Stimulated Luminescence (OSL)          6
                      Dosimeters
AP 07B-003            Offsite Dose Calculation Manual                      8
AP 07B-004            Offsite Dose Calculation Manual (Radiological        20
                      Environmental Monitoring Program)
AP 07B-005            Ground Water Protection Program                      3
AP 07E-001            Validation of Meteorological Data                    3
STN CH-024            Quarterly/Yearly Dose Projections                    3
STS IC-890A          Channel Calibration of Wind Speed Meteorological      17
                      Instrumentation
STS IC-890B          Channel Calibration of Wind Direction/Deviation      17
                      Meteorological Instrumentation
STS IC-890C          Channel Calibration of 10M/60M Ambient and            20
                      Differential Temperature Instrumentation
STS IC-890D          Channel Calibration of Sonic Wind                    2
                      Speed/Direction/Deviation Meteorological
                      Instrumentation
Audits, Self-Assessments, and Surveillances
Number            Title                                                    Date
QH-2013-0654      NUPIC Audit Report of Landauer, Inc.                    December 16,
                                                                            2013
11-2049            Evaluation Report of F&J Specialty Products, Inc.        January 13,
                                                                            2013
SQL 13-44          Evaluation Report of Landauer, Inc. - Glenwood, IL      October 11,
                                                                            2013
QH-2013-0660      Ground Water Protective Initiative 5-Year Follow-up      December 16,
                  Assessment                                              2013
                                              A1-10


==Section 1R22: Surveillance Testing==
Audits, Self-Assessments, and Surveillances
Number            Title                                                        Date
Audit Report No:   Quality Assurance Audit Report of Environmental              April 17, 2014
14-03-ENV          Management Plans
Condition Reports
00051888            00052766            00054626          00070866          00082043
00083302            00084016            00084879          00084901          00084915
00084919            00084920
Calibration And Maintenance Records
Number                Title                                                    Date
WO 13-375743          Surveillance Test Routing Sheet: Channel Calibration of  April 20, 2014
                      60m 10m Differential Temperature
WO 13-375744          Surveillance Test Routing Sheet: Channel Calibration of  April 6, 2014
                      Wind Speed
WO 13-375741          Surveillance Test Routing Sheet: Channel Calibration of  April10, 2014
                      Wind Direction
WO 13-375742          Surveillance Test Channel Calibration of Sonic Wind      April 6, 2014
                      Speed/Direction/Deviation
Miscellaneous Documents
Number            Title                                                        Date
SA-10-004          Relative Deposition per Unit Area (D/Q) 3 Year Update        November 2,
                  (2007-2009)                                                  2010
                  2012 Annual Radiological Environmental Operating Report      April 27, 2013
                  2013 Annual Radiological Environmental Operating Report      April 15, 2012
QH-2011-0016      REMP Review of 2010 Wind Direction                          August 31,
                                                                                2011
QH-2012-0242      REMP Review of 2011 Wind Direction                          July 30, 2012
QH-2013-0016      REMP Review of 2012 Wind Direction                          August 14,
                                                                                2011
                                              A1-11


===Procedures===
Section 2RS8: Radioactive Solid Waste Processing and Radioactive Material Handling,
: Number Title Revision/Date STS
Storage, and Transportation
: BB-006 RCS Water Inventory Balance Using the NPIS Computer 12
Procedures
: STS
Number           Title                                                   Revisions
: CH-024 Reactor Coolant Dose Equivalent Xe-133 Determination 6A
AP 31A-100        Solid Radwaste Process Control Program                  7 and 8
: STS
RPP 07-110        Solid Radwaste Packaging                                9
: IC-208A 4kv Loss of Voltage and Degraded Voltage TADOT NB01 Bus - Separation Group 1 5B STS
RPP 07-111        Handling Filter Cartridges                              17 and 18
: KJ-001A Integrated D/G and Safeguards Actuation Text Train A March 14, 2014 STN
RPP 07-112        Processing Cartridge Filters                            5
: KU-001A SBO DG NB01 Functional Test March 28, 2014
RPP 07-131        Bead Resin/Activated Carbon Dewatering Procedures for    4
: STN
                  CNSI 14-215 or Smaller Liners
: EJ-002 Containment Inspection 20
RPP 07-212        Requirements of Radioactive Materials Stored Outdoors    0
Audits and Self-Assessments
Number            Title                                                    Date
QS-2014-0629      Quality Surveillance performed on the Radwaste Group by  February 26,
                  WCNOC and Tech Specialist from Nine Mile Point            2014
Condition Reports
00051881          00056346            00056839          00062522        00066895
00066920          00073358            00079817          00081750        00081752
00084772          00084856            00084857          00084880        00084932
00084951
Radiation Work Permits
Number            Title                                                    Revision
13-0121          ALARA Review Package                                      1
130121            Cartridge Filter Change-out                              000
130121            Cartridge Filter Change-out                              001
130121            Cartridge Filter Change-out                              002
140029            Resin Transfer to Primary Spent Resin Storage Tank        000
                  (THC08)
                                            A1-12


==Section 2RS5: Radiation Monitoring Instrumentation==
Radioactive Material Shipments
Number            Title                                              Revision
12R26              Radioactive Material LSA-I; UN 2912                1
13R30              Radioactive Material LSA-II; UN 3321              000
13R49              Radioactive Material LSA-II; UN 3321              001
14R18              Radioactive Material LSA-II; UN 3321              002
12R26              Radioactive Material LSA-I; UN 2912                000
Radioactive Waste Stream Characterization
Number            Title                                              Date
7                  Primary Resin (CVCS, SFP)                          April 15, 2013
7                  Primary Resin (CVCS, SFP)                          January 23,
                                                                      2014
13                Dry Active Waste                                  April 19, 2012
13                Dry Active Waste                                  March 4, 2014
Miscellaneous Documents
Number      Title                                                    Date
            Access Control Shift Log (01:25 to 17:39)                April 1, 2013
            Filter Characterization Reports                          August 20,
            (13F044, 13F046, 13F047, 13F048, 13F049, 13F051, 13F052, 2013
            13F053, 13F055, 13F058, 13F059, 13F060, 13F061, 13F097)
13-063ES    Characterization and Classification of Wolf Creek Excore May 31, 2013
            Detectors
36          Annual Radioactive Effluent Release Report              January 1,
                                                                    2012 -
                                                                    December 31,
                                                                    2012
37          Annual Radioactive Effluent Release Report              January 1,
                                                                    2013 -
                                                                    December 31,
                                                                    2013
HW12158    Training Course Regulations and Requirements            January 11,
01                                                                  2010
OTSC 13-    On the Spot Change to RPP 07-111 Rev 17                  April 3, 2013
0056
                                            A1-13


===Procedures===
Miscellaneous Documents
: Number Title Revision/DateCHS
Number     Title                                                           Date
: AC-001 Accident Sampling 4A
RPF 07-     Filter Information Log                                          April 3, 2014
: WCIC-236 RMS Calibration Document November 13, 1995 STN
111-01
: SP-118 Channel Calibration Liquid Radwaste Discharge Radiation Monitor HB
RPF 07-     Radioactive Shipment Log                                        2012
: RE-0018 8 STN
123-01
: CH-010 Calibration of Liquid Radiation Monitors 3B STS
RPF 07-     Radioactive Shipment Log                                        2013
: CH-014 Calibration of Monitors GTRE21B and GHRE10B 12
123-01
: STN
RPF 07-     Radioactive Shipment Log                                        2014
: CH-021 Calibration of the Particulate Detector for Radiation Monitors GTRE21A and GHRE10A 4A STN
123-01
: CH-022 Calibration of the Iodine Detector for Radiation Monitors GTRE21A and GHRE10B 1B
Section 4OA2: Problem Identification and Resolution
: AP 07B-003 Offsite Dose Calculation Model 8
Procedures
: RPP 01-405 HP Instrument Program 30
Number             Title                                                   Revision
===Procedures===
AP 05-005          Design, Implementation, and Configuration Control of     20
: Number Title Revision/DateRPP 03-407 Testing of Portal Monitors as Passive Whole Body Counters 1A
                    Modifications
: RPP 05-707 Operation of Whole Body Counters 8
AP 05-010          Design Drawings                                          9
: RPP 06-101 Eberline
AP 05F-001          Design Verification                                      3A
: RO-2 and
Condition Reports
: RO-2A Calibration 6
79619                53443              82904            70384            70383
: RPP 06-105 Eberline
69721                69754              73624            71624            74508
: RO-20 Calibration
78794                72166              72164            72167            68194
: 5
62394                78708
: RPP 06-306 PM12 Calibration 8A
Miscellaneous
: STN
Number         Title                                                       Revision/Date
: SP-118 Channel Calibration Liquid Radwaste Discharge Radiation Monitor HB
WM 14-0011      Letter from Wolf Creek Nuclear Operating Corp. to U.S.NRC:   May 8, 2014
: RE-0018 8 STN
                Docket No. 50-482: Change to Essential Service Water System
: CH-010 Calibration of Liquid Radiation Monitors 3B
                Water Hammer Mitigation Commitment
===Condition Reports===
WM 14-0013      Letter from Wolf Creek Nuclear Operating Corp. to U.S.NRC:   May 8, 2014
: 00081759
                Docket No. 50-482: Voluntary Commitment Regarding
: 00084854
                Containment Coolers at Wolf Creek Generating Station
: 00084863
                                            A1-14
: 00084815
: 00084820
: 00084817
: 00083254
: 00082997
: 00080994
: 00079621
: 00078962
: 00078548
: 00074873
: 00074445
: 00074219
: 00072691
: 00072303
: 00068426
: 00068295
: 00068064
: 00051785
: 00054489
: 00065431
: 00067627
: 00062921
: Calibration Records Number Title Date WO12360791000 Channel Calibration Digital High Range Area Monitor
: GTRE-0059 Calibration Source Drop February 4, 2014 WO13381072000 Channel Calibration Digital High Range Area Radiation Monitor GTRE60 January 28, 2014 WO12360792000 Channel Calibration Digital High Range Area Radiation Monitor GTRE60 Calibration Source Drop February 3, 2014 WO13381018000 Channel Calibration Digital High Range Area Radiation Monitor GTRE59 January 24, 2014 11428 AMS4 March 9, 2014 11748 AMS4 March 9, 2014 11429 AMS4 February 24, 2014 
: 11376
: PCM-1B February 5, 2009 11379
: PCM-1B February 5, 2009 11378
: PCM-1B April 17, 2014  
: 240
: PCM-1C April 9, 2009
: 11005
: SAM 11 January 29, 2014 11006
: SAM 11
: June 19, 2013 92874
: RTM 110 March 23, 2014 92877
: RTM 110 April 28, 2014
: 260
: ASP-1 February 6, 2014 93330 PM12 August 15, 2013 93573 PM12 February 5, 2014 11511
: HD-29A January 29, 2014 10242
: PCM-2 December 9, 2013 10066 Whole Body Counter Calibration Certificate July 18, 2011
: 13027 Whole Body Counter Calibration Certificate September 15, 2008


==Section 2RS6: Radioactive Gaseous and Liquid Effluent Treatment==
Miscellaneous
Number        Title                                                        Revision/Date
              Wolf Creek Corrective Action Program Station Roll-Up        March 6, 2014
              Performance Results 4th Quarter 2013
              Wolf Creek Corrective Action Program Station Roll-Up        June 6, 2014
              Performance Results 1st Quarter 2014
              Wolf Creek Rebuilding Plan                                  June 6, 2014
              Engineering Excellence Plan - Product Quality Strategic Area 00
              Wolf Creek Change Management Plan - Engineering Technical September 5,
              Rigor Improvement                                            2013
                                          A1-15


===Procedures===
                                The following items are requested for the
: Number Title Revision
                                    Public Radiation Safety Inspection
: AI 07-007 Onsite Groundwater Protection Program Monitoring 14
                                      Wolf Creek Generating Station
: AI 07B-001 Radioactive Releases 19
                                      June 2 through June 6, 2014
: AI 07B-020 Instructions for Composite Preparation 19
                                        Integrated Report 2014003
: AI 07B-036 Liquid Release Permits Using RADEAS 01
Inspection areas are listed in the attachments below.
: AI 07B-037 Unit and Radwaste Vent Permits Using RADEAS 01
Please provide the requested information on or before May 19, 2014.
: AI 07B-038 Unit and Radwaste Vent Permits Using RADEAS 01
        Please submit this information using the same lettering system as below. For example,
===Procedures===
        all contacts and phone numbers for Inspection Procedure 71124.01 should be in a
: Number Title Revision
        file/folder titled 1- A, applicable organization charts in file/folder 1- B, updated final
: AP 07B-003 Offsite Dose Calculation Manual 08 CHA
        safety analysis report
: RC-004 Gamma Isotopic, Total Curie Content and Dose Equivalent Iodine Determination 15 CHS
If information is placed on ims.certrec.com, please ensure the inspection exit date entered is at
: RW-G02 Radwaste Vent Sampling and/or Exchange of Filters 3C CHS
least 30 days later than the onsite inspection dates, so the inspectors will have access to the
: SJ-144A
information while writing the report.
: SJ-144 Sampling Instructions 0C
In addition to the corrective action document lists provided for each inspection procedure listed
: CHS
below, please provide updated lists of corrective action documents at the entrance meeting.
: TB-L03 Turbine Building Local Sampling - Mid-Frequency 06
The dates for these lists should range from the end dates of the original lists to the day of the
: RPP 07-111 Handling Cartridge Filters 17
entrance meeting.
===Condition Reports===
If more than one inspection procedure is to be conducted and the information requests appear
: 00051966
to be redundant, there is no need to provide duplicate copies. Enter a note explaining in which
: 00053930
file the information can be found.
: 00055466
If you have any questions or comments, please contact Louis Carson at (817) 200-1221 or
: 00055535
Louis.Carson@nrc.gov.
: 00055538
                          PAPERWORK REDUCTION ACT STATEMENT
: 00056233
  This letter does not contain new or amended information collection requirements subject
: 00056574
    to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information
: 00056887
      collection requirements were approved by the Office of Management and Budget,
: 00059243
                                      control number 3150-0011.
: 00059832
                                                                                            Attachment 2
: 00061757
: 00064627
: 00064667
: 00064798
: 00065779
: 00066655
: 00066920
: 00068803
: 00069832
: 00069959
: 00070420
: 00070826
: 00072303
: 00076226
: 00077621
: 00077802
: 00078707
: 00082909
: 00083740
: 00084346
: 10
: CFR 50.75(g) Condition Reports
: 00084942   
: Gaseous and Liquid Release Permits Permit No. System
: Release Type Date U1LC2014-080/2013060 Turbine Building Drains Liquid June 11, 2013 U1GB2014-093/2013081 Containment Purge Unit Vent Gaseous July 17, 2013
: U1GB2014-099/2013087 Containment Purge Unit Vent Gaseous July 27, 2013
: U1LC2014-091/2013071 Steam Generator Blowdown Liquid August 30, 2013
: U1LC2014-110/2013090 Lime Sludge Pond
: Liquid November 19, 2013
: U1GB2014-017/2014017 Containment Purge Unit Vent Gaseous February 4, 2014 U1LC2014-005/2014005 Steam Generator Blowdown Liquid March 1, 2014 U1GB2014-162/2014162 Containment Purge Unit Vent Gaseous April 7, 2014 
: In-Place Filter Testing Records Work Order Test
: Date STS
: PE-006 Charcoal Adsorber In-Place Leak Test Safety-Related Units - FGK01B December 10, 2013 STS
: PE-005 HEPA Filter In-Place Leak Test Safety-Related Units -
: FGK01B December 10, 2013 STS
: PE-002 Charcoal Adsorbent Sampling for Nuclear Safety-Related
: Units - FGK01B December 23, 2013 STS
: PE-002 Charcoal Adsorbent Sampling for Nuclear Safety-Related
: Units - FGG02B December 23, 2013 STS
: PE-006 Charcoal Adsorber In-Place Leak Test Safety-Related Units - FGK01A February 24, 2014 STS
: PE-005 HEPA Filter In-Place Leak Test Safety-Related Units -
: FGK01A February 24, 2014
===Miscellaneous Documents===
: Number Title Revision/Date 11.1A-3 USAR Figure: Potential Gaseous Release 13
: M-12HB01-5 WCNOC PID: Liquid Radwaste System 20 M-12EG01 WCNOC PID: Component Cooling Water System 24
: System Health Report: Radiation Monitoring January 1 - September
: 30, 2013
: RA 13-0052 WCNOC 2013 Annual Radioactive Effluent Release Report
: RPF 02-210-05 50.75(g) Radiological Occurrence Worksheet for Decommissioning Record June 2, 2014 2013-011-EG00 Temporary Modification Order:
: EG System (A/B Trains), EGV0357 & EGV0310, EGV0324 & EGV0388 August 19, 2013
: RA 14-0043 WCNOC 2014 Annual Radioactive Effluent Release Report April 29, 2014
: WC Radiation Monitors Considered for Maintenance Rule June 2, 2014


==Section 2RS7: Radiological Environmental Monitoring Program==
5. Radiation Monitoring Instrumentation (71124.05)
  Date of Last Inspection:        April 23, 2012
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 Nuclear Procurement Issues Committee
  (NUPIC) audits for contractor support and licensee event reports (LERs), written since
  date of 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 Specific Procedures will be requested by number after the inspector reviews
  the procedure indexes.
  1. Calibration of portable radiation detection instruments (for portable ion chambers)
  2. Whole body counter calibration
  3. Laboratory instrumentation quality control
F. A summary list of corrective action documents (including corporate and subtiered
  systems) written since date of 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. Effluent radiation monitors
  4. 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. Offsite dose calculation manual, technical requirements manual, or licensee controlled
  specifications which lists the effluent monitors and calibration requirements
H. Current calibration data for the whole body counters
I. Primary to secondary source calibration correlation for effluent monitors
J. A list of the point of discharge effluent monitors with the two most recent calibration
  dates and the work order numbers associated with the calibrations
K. Radiation Monitoring System health report for the previous 12 months
                                            A2-2


===Procedures===
6. Radioactive Gaseous and Liquid Effluent Treatment (71124.06)
: Number Title Revision
  Date of Last Inspection:       April 23, 2012
: AI 07B-004 Reporting Requirements of the Radiological Environmental Monitoring Program 13
A. List of contacts and telephone numbers for the following areas:
===Procedures===
  1. Radiological effluent control
: Number Title Revision
  2. Engineered safety feature air cleaning systems
: AI 07B-005 Radiological Environmental Monitoring Program Implementation 20
B. Applicable organization charts
: AI 07B-009 Collection, Preparation and Shipment of Sediment and Soil Samples 8
C. Audits, self-assessments, vendor or NUPIC audits of contractor support, and LERs
: AI 07B-011 Collection, Preparation and Shipment of Water Samples 15
  written since date of last inspection, related to:
: AI 07B-012 Collection, Preparation and Shipment of Crop, Vegetable, Fruit and Pasturage Samples 10
  1. Radioactive effluents
: AI 07B-015 Land Use Census 11
  2. Engineered Safety Feature Air cleaning systems
: AI 07B-034 Radiological Environmental Monitoring Program Air Sampling 11
D. Procedure indexes for the following areas
: AI 07B-035 REMP Optically Stimulated Luminescence (OSL) Dosimeters 6
  1. Radioactive effluents
: AP 07B-003 Offsite Dose Calculation Manual
  2. Engineered Safety Feature Air cleaning systems
: 8
E. Please provide specific procedures related to the following areas noted below.
: AP 07B-004 Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program) 20
  Additional Specific Procedures will be requested by number after the inspector reviews
: AP 07B-005 Ground Water Protection Program 3
  the procedure indexes.
: AP 07E-001 Validation of Meteorological Data 3
  1. Sampling of radioactive effluents
: STN
  2. Sample analysis
: CH-024 Quarterly/Yearly Dose Projections 3  
  3. Generating radioactive effluent release permits
: STS
  4. Laboratory instrumentation quality control
: IC-890A Channel Calibration of Wind Speed Meteorological Instrumentation 17 STS
  5. In-place testing of HEPA filters and charcoal adsorbers
: IC-890B Channel Calibration of Wind Direction/Deviation Meteorological Instrumentation 17 STS
  6. New or applicable procedures for effluent programs (e.g., including ground water
: IC-890C Channel Calibration of 10M/60M Ambient and Differential Temperature Instrumentation 20 STS
        monitoring programs)
: IC-890D Channel Calibration of Sonic Wind Speed/Direction/Deviation Meteorological Instrumentation 2
F. List of corrective action documents (including corporate and subtiered systems) written
: Audits, Self-Assessments, and Surveillances Number Title Date
  since date of last inspection, associated with:
: QH-2013-0654 NUPIC Audit Report of Landauer, Inc. December 16, 2013 11-2049 Evaluation Report of F&J Specialty Products, Inc. January 13, 2013
  1. Radioactive effluents
: SQL 13-44 Evaluation Report of Landauer, Inc. - Glenwood, IL October 11, 2013
  2. Effluent radiation monitors
: QH-2013-0660 Ground Water Protective Initiative 5-Year Follow-up Assessment December 16, 2013 
  3. Engineered Safety Feature Air cleaning systems
: Audits, Self-Assessments, and Surveillances Number Title Date Audit Report No: 14-03-ENV Quality Assurance Audit Report of Environmental Management Plans April 17, 2014
  NOTE: The lists should indicate the significance level of each issue and the search
===Condition Reports===
  criteria used. Please provide in document formats which are searchable so that the
: 00051888
  inspector can perform word searches.
: 00052766
G. 2012 and 2013 Annual Radioactive Effluent Release Report, or the two most recent
: 00054626
  reports.
: 00070866
H. Current Copy of the Offsite Dose Calculation Manual
: 00082043
I. Copy of the 2012 and 2013 interlaboratory comparison results for laboratory quality
: 00083302
  control performance of effluent sample analysis, or the two most recent results.
: 00084016
J. Effluent sampling schedule for the week of the inspection
: 00084879
K. New entries into 10 CFR 50.75(g) files since date of last inspection
: 00084901
L. Operations department (or other responsible department) log records for effluent
: 00084915
  monitors removed from service or out of service
: 00084919
M. Listing or log of liquid and gaseous release permits since date of last inspection
: 00084920
                                            A2-3
: Calibration And Maintenance Records
: Number Title Date
: WO 13-375743 Surveillance Test Routing Sheet: Channel Calibration of 60m 10m Differential Temperature April 20, 2014
: WO 13-375744 Surveillance Test Routing Sheet: Channel Calibration of Wind Speed April 6, 2014
: WO 13-375741 Surveillance Test Routing Sheet: Channel Calibration of Wind Direction April10, 2014
: WO 13-375742 Surveillance Test Channel Calibration of Sonic Wind Speed/Direction/Deviation April 6, 2014
===Miscellaneous Documents===
: Number Title Date
: SA-10-004 Relative Deposition per Unit Area (D/Q) 3 Year Update (2007-2009) November 2, 2010
: 2012 Annual Radiological Environmental Operating Report April 27, 2013
: 2013 Annual Radiological Environmental Operating Report
: April 15, 2012
: QH-2011-0016 REMP Review of 2010 Wind Direction August 31, 2011
: QH-2012-0242 REMP Review of 2011 Wind Direction July 30, 2012
: QH-2013-0016 REMP Review of 2012 Wind Direction August 14, 2011


==Section 2RS8: Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation==
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. Moreover, please provide a specific list of all effluent radiation
  monitors that were considered inoperable for 7 days or more since November 2011.
  If applicable, please provide the relative Special Report and condition report(s).
P. A list of all radiation monitors that are considered §50.65/Maintenance Rule equipment
Q. A list of all significant changes made to the Gaseous and Liquid Effluent Process
  Monitoring System since the last inspection. If applicable, please provide the
  corresponding updated final safety analysis report (UFSAR) section in which this change
  was documented.
R. A list of any occurrences in which a non-radioactive system was contaminated by a
  radioactive system. Please include any relative condition report(s).
                                            A2-4


===Procedures===
7. Radiological Environmental Monitoring Program (71124.07)
: Number Title Revisions
  Date of Last Inspection:         April 23, 2012
: AP 31A-100 Solid Radwaste Process Control Program 7 and 8
A. List of contacts and telephone numbers for the following areas:
: RPP 07-110 Solid Radwaste Packaging 9
  1. Radiological environmental monitoring
: RPP 07-111 Handling Filter Cartridges 17 and 18
  2. Meteorological monitoring
: RPP 07-112 Processing Cartridge Filters 5
B. Applicable organization charts
: RPP 07-131 Bead Resin/Activated Carbon Dewatering Procedures for CNSI 14-215 or Smaller Liners 4
C. Audits, self-assessments, vendor or NUPIC audits of contractor support, and LERs
: RPP 07-212 Requirements of Radioactive Materials Stored Outdoors 0 
  written since date of last inspection, related to:
: Audits and Self-Assessments Number Title Date
  1. Radiological environmental monitoring program (including contractor environmental
: QS-2014-0629 Quality Surveillance performed on the Radwaste Group by WCNOC and Tech Specialist from Nine Mile Point February 26, 2014
        laboratory audits, if used to perform environmental program functions)
===Condition Reports===
  2. Environmental TLD processing facility
: 00051881
  3. Meteorological monitoring program
: 00056346
D. Procedure index for the following areas:
: 00056839
  1. Radiological environmental monitoring program
: 00062522
  2. Meteorological monitoring program
: 00066895
E. Please provide specific procedures related to the following areas noted below.
: 00066920
  Additional Specific Procedures will be requested by number after the inspector reviews
: 00073358
  the procedure indexes.
: 00079817
  1. Environmental Program Description
: 00081750
  2. Sampling, collection, and preparation of environmental samples
: 00081752
  3. Sample analysis (if applicable)
: 00084772
  4. Laboratory instrumentation quality control
: 00084856
  5. Procedures associated with the Offsite Dose Calculation Manual
: 00084857
  6. Appropriate QA Audit and program procedures, and/or sections of the stations
: 00084880
        QA manual (which pertain to the REMP)
: 00084932
F. A summary list of corrective action documents (including corporate and subtiered
: 00084951     
  systems) written since date of last inspection, related to the following programs:
: Radiation Work Permits Number Title Revision 13-0121 ALARA Review Package 1
  1. Radiological environmental monitoring
: 130121 Cartridge Filter Change-out 000
  2. Meteorological monitoring
: 130121 Cartridge Filter Change-out 001
  NOTE: The lists should indicate the significance level of each issue and the search
: 130121 Cartridge Filter Change-out 002
  criteria used. Please provide in document formats which are searchable so that the
: 140029 Resin Transfer to Primary Spent Resin Storage Tank (THC08) 000 
  inspector can perform word searches.
: Radioactive Material Shipments Number Title Revision 12R26 Radioactive Material
G. Wind Rose data and evaluations used for establishing environmental sampling locations
: LSA-I;
H. Copies of the 2 most recent calibration packages for the meteorological tower
: UN 2912 1 13R30 Radioactive Material
  instruments
: LSA-II;
I. Copy of the 2012 and 2013 Annual Radiological Environmental Operating Report and
: UN 3321 000 13R49 Radioactive Material
  Land Use Census, and current revision of the Offsite Dose Calculation Manual, or the
: LSA-II;
  two most recent reports.
: UN 3321 001
J. Copy of the environmental laboratorys interlaboratory comparison program results for
: 14R18 Radioactive Material
  2012 and 2013, or the two most recent results, if not included in the annual radiological
: LSA-II;
  environmental operating report
: UN 3321 002
K. Data from the environmental laboratory documenting the analytical detection sensitivities
: 2R26 Radioactive Material
  for the various environmental sample media (i.e., air, water, soil, vegetation, and milk)
: LSA-I;
L. Quality Assurance audits (e.g., NUPIC) for contracted services
: UN 2912 000 
                                            A2-5
: Radioactive Waste Stream Characterization Number Title Date 7 Primary Resin (CVCS, SFP) April 15, 2013  
: Primary Resin (CVCS, SFP) January 23, 2014 13 Dry Active Waste April 19, 2012 13 Dry Active Waste March 4, 2014 
===Miscellaneous Documents===
: Number Title Date
: Access Control Shift Log (01:25 to 17:39) April 1, 2013
: Filter Characterization Reports (13F044, 13F046, 13F047, 13F048, 13F049, 13F051, 13F052, 13F053, 13F055, 13F058, 13F059, 13F060, 13F061, 13F097) August 20, 2013 13-063ES Characterization and Classification of Wolf Creek Excore Detectors May 31, 2013 36 Annual Radioactive Effluent Release Report January 1, 2012 - December 31, 2012 37 Annual Radioactive Effluent Release Report January 1, 2013 -
: December 31,  
: 2013 HW1215801 Training Course Regulations and Requirements
: January 11, 2010 OTSC 13-0056 On the Spot Change to
: RPP 07-111 Rev 17 April 3, 2013
===Miscellaneous Documents===
: Number Title Date
: RPF 07-111-01 Filter Information Log April 3, 2014
: RPF 07-123-01 Radioactive Shipment Log 2012
: RPF 07-123-01 Radioactive Shipment Log 2013
: RPF 07-123-01 Radioactive Shipment Log 2014


==Section 4OA2: Problem Identification and Resolution==
M. Current NEI Groundwater Initiative Plan and status
N. Technical requirements manual or licensee controlled specifications which lists the
  meteorological instruments calibration requirements
O. A list of Regulatory Guides and/or NUREGs that you are currently committed to relative
  to the Radiological Environmental Monitoring Program. Please include the revision
  and/or date for the committed item and where this can be located in your current
  licensing basis/UFSAR.
P. If applicable, per NEI 07-07, provide any reports that document any spills/leaks to
  groundwater since the last inspection.
                                          A2-6


===Procedures===
8.     Radioactive Solid Waste Processing, and Radioactive Material Handling, Storage,
: Number Title Revision
      and Transportation (71124.08)
: AP 05-005 Design, Implementation, and Configuration Control of Modifications 20
      Date of Last Inspection:       April 23, 2012
: AP 05-010 Design Drawings 9
A.     List of contacts and telephone numbers for the following areas:
: AP 05F-001 Design Verification 3A
      1. Solid Radioactive waste processing
===Condition Reports===
      2. Transportation of radioactive material/waste
: 79619 53443 82904 70384 70383 69721 69754 73624 71624 74508 78794 72166 72164 72167 68194 62394 78708
B.     Applicable organization charts (and list of personnel involved in solid radwaste
===Miscellaneous===
      processing, transferring, and transportation of radioactive waste/materials)
: Number Title Revision/Date
C.     Copies of audits, department self-assessments, and LERs written since date of last
: WM 14-0011 Letter from Wolf Creek Nuclear Operating Corp. to U.S.NRC:
      inspection related to:
: Docket No. 50-482: Change to Essential Service Water System Water Hammer Mitigation Commitment May 8, 2014
      1. Solid radioactive waste management
: WM 14-0013 Letter from Wolf Creek Nuclear Operating Corp. to U.S.NRC:
      2. Radioactive material/waste transportation program
: Docket No. 50-482: Voluntary Commitment Regarding Containment Coolers at Wolf Creek Generating Station May 8, 2014
D.     Procedure index for the following areas:
===Miscellaneous===
      1. Solid radioactive waste management
: Number Title Revision/Date
      2. Radioactive material/waste transportation
: Wolf Creek Corrective Action Program Station Roll-Up Performance Results 4th Quarter 2013 March 6, 2014 Wolf Creek Corrective Action Program Station Roll-Up Performance Results 1st Quarter 2014 June 6, 2014
E.     Please provide specific procedures related to the following areas noted below.
: Wolf Creek Rebuilding Plan June 6, 2014
      Additional Specific Procedures will be requested by number after the inspector reviews
: Engineering Excellence Plan - Product Quality Strategic Area 00
      the procedure indexes.
: Wolf Creek Change Management Plan - Engineering Technical Rigor Improvement September 5, 2013   
      1. Process control program
: The following items are requested for the Public Radiation Safety Inspection Wolf Creek Generating Station June 2 through June 6, 2014 Integrated Report
      2. Solid and liquid radioactive waste processing
: 2014003
      3. Radioactive material/waste shipping
: Inspection areas are listed in the attachments below.
      4. Methodology used for waste concentration averaging, if applicable
: Please provide the requested information on or before May 19, 2014.
      5. Waste stream sampling and analysis
: Please submit this information using the same lettering system as below.
F.     A summary list of corrective action documents (including corporate and subtiered
: For example, all contacts and phone numbers for Inspection Procedure 71124.01 should be in a file/folder titled "1- A," applicable organization charts in file/folder "1- B," updated final safety analysis report
      systems) written since date of last inspection related to:
: 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.
      1. Solid radioactive waste
: 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.
      2. Transportation of radioactive material/waste
: The dates for these lists should range from the end dates of the original lists to the day of the entrance meeting.
      NOTE: The lists should indicate the significance level of each issue and the search
: 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.
      criteria used. Please provide in document formats which are searchable so that the
: Enter a note explaining in which file the information can be found.
      inspector can perform word searches.
: If you have any questions or comments, please contact Louis Carson at (817) 200-1221 or Louis.Carson@nrc.gov.
G.     Copies of training lesson plans for 49CFR172, subpart H, for radwaste processing,
: 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.).
      packaging, and shipping.
: Existing information collection requirements were approved by the Office of Management and Budget, control number 3150-0011.
H.     A summary of radioactive material and radioactive waste shipments made from date of
: 5.
      last inspection to present
: Radiation Monitoring Instrumentation (71124.05)
I.     Waste stream sample analyses results and resulting scaling factors for 2012 and 2013,
: Date of Last Inspection: April 23, 2012 A. List of contacts and telephone numbers for the following areas: 1. Effluent monitor calibration
      or the two most recent results.
: 2. Radiation protection instrument calibration
J.     Waste classification reports if performed by vendors (such as for irradiated hardware)
: 3. Installed instrument calibrations
K.     A listing of all onsite radwaste storage facilities. Please include a summary or listing of
: 4. Count room and Laboratory instrument calibrations B. Applicable organization charts C. Copies of audits, self-assessments, vendor or Nuclear Procurement Issues Committee (NUPIC) audits for contractor support and licensee event reports (LERs), written since date of last inspection, related to: 
      the items stored in each facility, including the total amount of radioactivity and the
: 1. Area radiation monitors, continuous air monitors, criticality monitors, portable survey instruments, electronic dosimeters, teledosimetry, personnel contamination monitors, or whole body counters
      highest general area dose rate.
: 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.
Although it is not necessary to compile the following information, the inspector will also review:
: Additional Specific Procedures will be requested by number after the inspector reviews the procedure indexes.
L.     Training, and qualifications records of personnel responsible for the conduct of
: 1. Calibration of portable radiation detection instruments (for portable ion chambers) 2. Whole body counter calibration
      radioactive waste processing, package preparation, and shipping
: 3. Laboratory instrumentation quality control F. A summary list of corrective action documents (including corporate and subtiered systems) written since date of 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 
                                                A2-7
: 3. Effluent radiation monitors
: 4. 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. Offsite dose calculation manual, technical requirements manual, or licensee controlled specifications which lists the effluent monitors and calibration requirements H. Current calibration data for the whole body counters I. Primary to secondary source calibration correlation for effluent monitors
: J.
: A list of the point of discharge effluent monitors with the two most recent calibration dates and the work order numbers associated with the calibrations K. Radiation Monitoring System health report for the previous 12 months 
: 6. Radioactive Gaseous and Liquid Effluent Treatment (71124.06)
: Date of Last Inspection: April 23, 2012 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 date of 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 Specific Procedures will be requested by number after the inspector reviews the procedure indexes.
: 1. Sampling of radioactive effluents 2. Sample analysis 3. Generating radioactive effluent release permits
: 4. Laboratory instrumentation quality control
: 5. In-place testing of HEPA filters and charcoal adsorbers
: 6. New or applicable procedures for effluent programs (e.g., including ground water monitoring programs) F. List of corrective action documents (including corporate and subtiered systems) written since date of 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. 2012 and 2013 Annual Radioactive Effluent Release Report, or the two most recent reports. H. Current Copy of the Offsite Dose Calculation Manual I. Copy of the 2012 and 2013 interlaboratory 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 date of last inspection L. Operations department (or other responsible department) log records for effluent monitors removed from service or out of service M. Listing or log of liquid and gaseous release permits since date of 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.
: Moreover, please provide a specific list of all effluent radiation monitors that were considered inoperable for 7 days or more since November 2011.
: If applicable, please provide the relative Special Report and condition report(s). P. A list of all radiation monitors that are considered §50.65/Maintenance Rule equipment
: Q. A list of all significant changes made to the Gaseous and Liquid Effluent Process Monitoring System since the last inspection.
: If applicable, please provide the corresponding updated final safety analysis report (UFSAR) section in which this change was documented.
: R.
: A list of any occurrences in which a non-radioactive system was contaminated by a radioactive system.
: Please include any relative condition report(s). 
: 7. Radiological Environmental Monitoring Program (71124.07)
: Date of Last Inspection: April 23, 2012 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 date of 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 Specific Procedures will be requested by number after the inspector reviews the procedure indexes.
: 1. Environmental Program Description 2. Sampling, collection, and preparation of environmental samples 3. Sample analysis (if applicable) 
: 4. Laboratory instrumentation quality control
: 5. Procedures associated with the Offsite Dose Calculation Manual
: 6. Appropriate QA Audit and program procedures, and/or sections of the station's QA manual (which pertain to the REMP) F. A summary list of corrective action documents (including corporate and subtiered systems) written since date of 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. Wind Rose data and evaluations used for establishing environmental sampling locations H. Copies of the 2 most recent calibration packages for the meteorological tower instruments
: I. Copy of the 2012 and 2013 Annual Radiological Environmental Operating Report and Land Use Census, and current revision of the Offsite Dose Calculation Manual, or the two most recent reports. J. Copy of the environmental laboratory's interlaboratory comparison program results for 2012 and 2013, or the two most recent results, if not included in the annual radiological environmental operating report K. Data from the environmental laboratory documenting the analytical detection sensitivities for the various environmental sample media (i.e., air, water, soil, vegetation, and milk) L. Quality Assurance audits (e.g., NUPIC) for contracted services 
: M. Current NEI Groundwater Initiative Plan and status N.
: Technical requirements manual or licensee controlled specifications which lists the meteorological instruments calibration requirements O. A list of Regulatory Guides and/or NUREGs that you are currently committed to relative to the Radiological Environmental Monitoring Program.
: Please include the revision and/or date for the committed item and where this can be located in your current licensing basis/UFSAR.
: P. If applicable, per
: NEI 07-07, provide any reports that document any spills/leaks to groundwater since the last inspection.
: 8. Radioactive Solid Waste Processing, and Radioactive Material Handling, Storage, and Transportation (71124.08)
: Date of Last Inspection: April 23, 2012 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 date of 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 Specific Procedures will be requested by number after the inspector reviews the procedure indexes.
: 1. Process control program 2. Solid and liquid radioactive waste processing
: 3. Radioactive material/waste shipping
: 4. Methodology used for waste concentration averaging, if applicable  
: 5. Waste stream sampling and analysis F. A summary list of corrective action documents (including corporate and subtiered systems) written since date of 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 49CFR172, subpart H, for radwaste processing, packaging, and shipping. H. A summary of radioactive material and radioactive waste shipments made from date of last inspection to present I. Waste stream sample analyses results and resulting scaling factors for 2012 and 2013, or the two most recent results. J. Waste classification reports if performed by vendors (such as for irradiated hardware)  
: K. A listing of all onsite radwaste storage facilities.
: Please include a summary or listing of the items stored in each facility, including the total amount of radioactivity and the highest general area dose rate. Although it is not necessary to compile the following information, the inspector will also review:
: L. Training, and qualifications records of personnel responsible for the conduct of radioactive waste processing, package preparation, and shipping  
: A. Heflin -2-
: Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS).
: ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Sincerely,


/RA/ 
: Neil O'Keefe, Chief Project Branch B
: Division of Reactor Projects
: Docket Nos.:
: 50-482
: License Nos:
: NPF-42
: Enclosure:
: Inspection Report 05000482/2014003 w/Attachments 1.
: Supplemental Information
: 2.
: Public Radiation Safety Inspection Request


cc w/encl:
ML14223B221
: Electronic Distribution to Wolf Creek Nuclear Operating Corporation
  SUNSI Review    ADAMS  Yes      Non-Sensitive              Publicly Available            Keyword
By: NFO                  No      Sensitive                  Non-Publicly Available        NRC-002
OFFICE      SRI:DRP/B        RI:DRP/B            C:DRS/TSB          C:DRS/EB1          C:DRS/EB2
NAME        CPeabody/tk      RStroble            GMiller            TFarnholtz        JDixon
SIGNATURE /RA/                /RA/                /RA/              /RA/              /RA/
DATE        7/23/14          8/11/14              8/8/14            8/6/14            8/6/14
OFFICE      C:DRS/OB              C:DRS/PSB1              C:DRS/PSB2              BC:DRP/B
NAME        VGaddy                MHaire                  HGepford                NOKeeefe
SIGNATURE /RA/                      /RA/                    /RA/                    /RA/
DATE        8/6/14                8/8/14                  8/8/14                  8/11/14
                                   
Letter to Adam Heflin from Neil OKeefe, dated August 11, 2014
SUBJECT: WOLF CREEK GENERATING STATION - NRC INTEGRATED INSPECTION
REPORT 05000482/2014003
DISTRIBUTION:
Regional Administrator (Marc.Dapas@nrc.gov)
Deputy Regional Administrator (Kriss.Kennedy@nrc.gov)
Acting DRP Director (Troy.Pruett@nrc.gov)
Acting DRP Deputy Director (Michael.Hay@nrc.gov)
DRS Director (Anton.Vegel@nrc.gov)
DRS Deputy Director (Jeff.Clark@nrc.gov)
Senior Resident Inspector (Charles.Peabody@nrc.gov)
Resident Inspector (Raja.Stroble@nrc.gov)
WC Administrative Assistant (Carey.Spoon@nrc.gov)
Branch Chief, DRP/B (Neil.OKeefe@nrc.gov)
Senior Project Engineer, DRP/B (David.Proulx@nrc.gov)
Project Engineer, DRP/B (Fabian.Thomas@nrc.gov)
Public Affairs Officer (Victor.Dricks@nrc.gov)
Public Affairs Officer (Lara.Uselding@nrc.gov)
Project Manager (Fred.Lyon@nrc.gov)
Branch Chief, DRS/TSB (Geoffrey.Miller@nrc.gov)
RITS Coordinator (Marisa.Herrera@nrc.gov)
ACES (R4Enforcement.Resource@nrc.gov)
Regional Counsel (Karla.Fuller@nrc.gov)
Technical Support Assistant (Loretta.Williams@nrc.gov)
Congressional Affairs Officer (Jenny.Weil@nrc.gov)
RIV/ETA: OEDO (Anthony.Bowers@nrc.gov)
ROPreports
}}
}}

Latest revision as of 01:35, 4 November 2019

IR 05000482-14-003, on 03/29/2014 & 06/27/2014, Wolf Creek Generating Station, Integrated Resident and Regional Report; Maintenance Risk Assessments and Emergent Work Control
ML14223B221
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 08/11/2014
From: O'Keefe N
NRC/RGN-IV/DRP/RPB-B
To: Heflin A
Wolf Creek
C. Peabody
References
IR-14-003
Download: ML14223B221 (46)
v • d • e


See also: IR 05000482/2014003

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION IV

1600 E. LAMAR BLVD.

ARLINGTON, TX 76011-4511

August 11, 2014

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 05000482/2014003

Dear Mr. Heflin:

On June 27, 2014, the U.S. Nuclear Regulatory Commission completed an inspection at the

Wolf Creek Generating Station. On July 8, 2014, the Nuclear Regulatory Commission

inspectors discussed the results of this inspection with you and other members of your staff.

Inspectors documented the results of this inspection in the enclosed inspection report.

The Nuclear Regulatory Commission inspectors documented one finding of very low safety

significance (Green) in this report. This finding involved a violation of Nuclear Regulatory

Commission requirements. The Nuclear Regulatory Commission is treating this violation as

non-cited violation consistent with Section 2.3.2.a of the Nuclear Regulatory Commission

Enforcement Policy.

If you contest the violation or significance of the 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, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the

Nuclear Regulatory Commission resident inspector at the Wolf Creek Generating Station.

If you disagree with the 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 Regional Administrator, Region IV; and the Nuclear Regulatory

Commission resident inspector at the Wolf Creek Generating Station.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public

Inspections, Exemptions, Requests for Withholding, a copy of this letter, its enclosure, and your

response (if any) will be available electronically for public inspection in the NRCs Public

A. Heflin -2-

Document Room or from the Publicly Available Records component of the Nuclear Regulatory

Commission Agencywide Documents Access and Management System. Agencywide

Documents Access and Management System is accessible from the Nuclear Regulatory

Commission Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic

Reading Room).

Sincerely,

/RA/

Neil OKeefe, Chief

Project Branch B

Division of Reactor Projects

Docket Nos.: 50-482

License Nos: NPF-42

Enclosure:

Inspection Report 05000482/2014003

w/Attachments

1. Supplemental Information

2. Public Radiation Safety Inspection Request

cc w/encl: Electronic Distribution to

Wolf Creek Nuclear Operating Corporation

U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

Docket: 05000482

License: NPF-42

Report: 05000482/2014003

Licensee: Wolf Creek Nuclear Operating Corporation

Facility: Wolf Creek Generating Station

Location: 1550 Oxen Lane NE

Burlington, Kansas

Dates: March 29 through June 27, 2014

Inspectors: C. Peabody, Senior Resident Inspector

R. Stroble, Resident Inspector

L. Carson II, Senior Health Physicist

N. Greene, PhD, Health Physicist

P. Hernandez, Health Physicist

J. ODonnell, Health Physicist

D. Proulx, Senior Project Engineer

Approved Neil OKeefe

By: Chief, Project Branch B

Division of Reactor Projects

Enclosure

SUMMARY

IR 05000482/2014003; 03/29/2014 - 06/27/2014; Wolf Creek Generating Station, Integrated

Resident and Regional Report; Maintenance Risk Assessments and Emergent Work Control.

The inspection activities described in this report were performed between March 29 and

June 27, 2014, by the resident inspectors at Wolf Creek Generating Station and inspectors from

the Nuclear Regulatory Commission Region IV office. One finding of very low safety

significance (Green) is documented in this report. This finding involved a violation of Nuclear

Regulatory Commission requirements. The significance of inspection findings is indicated by

their color (Green, White, Yellow, or Red), which is determined using Inspection Manual

Chapter 0609, Significance Determination Process. Their cross-cutting aspects are

determined using Inspection Manual Chapter 0310, Components Within the Cross-Cutting

Areas. Violations of NRC requirements are dispositioned in accordance with the Nuclear

Regulatory Commission Enforcement Policy. The NRC's program for overseeing the safe

operation of commercial nuclear power reactors is described in NUREG 1649, Reactor

Oversight Process.

Findings

No findings were identified.

Licensee Identified Findings

No findings were identified.

-2-

PLANT STATUS

Wolf Creek began the inspection period with the unit in Mode 5 (cold shutdown) for a planned

mid-cycle outage. On May 8, 2014, the reactor was restarted then promptly shut down due to a

leaking steam generator bowl drain valve inside containment. On May 10, 2014, the reactor

was again restarted and promptly shut down due to a reactor coolant pump oil leak inside

containment. On May 13, 2014, the reactor was restarted successfully, reached 100 percent

power on May 15, 2014, and remained at that power level for the remainder of the inspection

period.

REPORT DETAILS

1. REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R01 Adverse Weather Protection (71111.01)

Summer Readiness for Offsite and Alternate AC Power Systems

a. Inspection Scope

On May 2, 2014, the inspectors completed an inspection of the stations off-site and

alternate-ac power systems. The inspectors inspected the material condition of these

systems, including transformers and other switchyard equipment to verify that plant

features and procedures were appropriate for operation and continued availability of off-

site and alternate-ac power systems. The inspectors reviewed outstanding work orders

and open condition reports for these systems. The inspectors walked down the

switchyard to observe the material condition of equipment providing off-site power

sources. The inspectors verified that the licensees procedures included appropriate

measures to monitor and maintain availability and reliability of the off-site and alternate-

ac power systems.

These activities constituted one sample of summer readiness of off-site and alternate-ac

power systems, as defined in Inspection Procedure 71111.01.

b. Findings

No findings were identified.

1R04 Equipment Alignment (71111.04)

Partial Walkdown

a. Inspection Scope

The inspectors performed partial system walk-downs of the following risk-significant

systems:

-3-

  • April 7, 2014, control room air conditioning system and control room emergency

ventilation system train B

  • June 17, 2014, safety injection system train A

The inspectors reviewed the licensees procedures and system design information to

determine the correct lineup for the systems. They visually verified that critical portions

of the systems or trains were correctly aligned for the existing plant configuration.

These activities constituted three partial system walk-down samples as defined in

Inspection Procedure 71111.04.

b. Findings

No findings were identified.

1R05 Fire Protection (71111.05)

.1 Quarterly Inspection

a. Inspection Scope

The inspectors evaluated the licensees fire protection program for operational status

and material condition. The inspectors focused their inspection on four plant areas

important to safety:

  • May 1, 2014, radiological controlled area and health physics office space
  • May 1, 2014, lower cable spreading room
  • May 7, 2014, upper cable spreading room

For each area, the inspectors evaluated the fire plan against defined hazards and

defense-in-depth features in the licensees fire protection program. The inspectors

evaluated control of transient combustibles and ignition sources, fire detection and

suppression systems, manual firefighting equipment and capability, passive fire

protection features, and compensatory measures for degraded conditions.

These activities constituted four quarterly inspection samples, as defined in Inspection

Procedure 71111.05.

b. Findings

No findings were identified.

-4-

.2 Annual Inspection

a. Inspection Scope

On June 27, 2014, the inspectors completed their annual evaluation of the licensees fire

brigade performance. This evaluation included observation of an unannounced fire drill

for 2016, control building non-vital switchgear room B on June 27, 2014.

During this drill, the inspectors evaluated the capability of the fire brigade members, the

leadership ability of the brigade leader, the brigades use of turnout gear and fire-fighting

equipment, and the effectiveness of the fire brigades team operation. The inspectors

also reviewed whether the licensees fire brigade met NRC requirements for training,

dedicated size and membership, and equipment.

These activities constituted one annual inspection sample, as defined in Inspection

Procedure 71111.05.

b. Findings

No findings were identified.

1R11 Licensed Operator Requalification Program and Licensed Operator Performance

(71111.11)

Review of Licensed Operator Requalification

a. Inspection Scope

On June 18, 2014, the inspectors evaluated a simulator scenario performed by an

operating crew. The inspectors assessed the performance of the operators and the

evaluators critique of their performance.

These activities constitute completion of one quarterly licensed operator requalification

program sample, as defined in Inspection Procedure 71111.11.

b. Findings

No findings were identified.

1R13 Maintenance Risk Assessments and Emergent Work Control (71111.13)

a. Inspection Scope

The inspectors reviewed two risk assessments performed by the licensee prior to

changes in plant configuration and the risk management actions taken by the licensee in

response to elevated risk:

planned maintenance outage

-5-

  • June 16-22, 2014, train B safety injection planned maintenance outage and train

B containment spray planned maintenance outage

The inspectors verified that these risk assessments were performed timely and in

accordance with the requirements of 10 CFR 50.65 (the Maintenance Rule) and plant

procedures. The inspectors reviewed the accuracy and completeness of the licensees

risk assessments and verified that the licensee implemented appropriate risk

management actions based on the result of the assessments.

The inspectors also observed portions of one emergent work activities that had the

potential to affect the functional capability of mitigating systems:

replacement

The inspectors verified that the licensee appropriately developed and followed a work

plan for these activities. The inspectors verified that the licensee took precautions to

minimize the impact of the work activities on unaffected structures, systems, and

components (SSCs).

Additionally, the inspectors reviewed the risk assessments associated with two planned

maintenance activities performed during a time in the outage when the primary plant was

in a water-solid condition that resulted in unplanned pressure transients.

valve testing

These activities constitute completion of four maintenance risk assessments and

emergent work control inspection samples, as defined in Inspection Procedure 71111.13.

(Note: The March 14, 2014, sample was counted in Inspection Report 2014002).

b. Findings

No findings were identified.

1R15 Operability Determinations and Functionality Assessments (71111.15)

a. Inspection Scope

The inspectors reviewed four operability determinations that the licensee performed for

degraded or nonconforming SSCs:

heating, ventilation, and air conditioning inlet damper hydramotor oil analysis

condition

-6-

failure

governor hydraulic actuator SKJ09B

The inspectors reviewed the timeliness and technical adequacy of the licensees

evaluations. Where the licensee determined the degraded SSC to be operable, the

inspectors verified that the licensees compensatory measures were appropriate to

provide reasonable assurance of operability. The inspectors verified that the licensee

had considered the effect of other degraded conditions on the operability of the

degraded SSC.

In the case of the containment cooler issues, the inspectors obtained the assistance of

specialist inspectors from the Region IV office and experts from the Office of Nuclear

Reactor Regulation. The NRC conducted several calls with licensee technical and

management personnel. Based on NRC concerns, the licensee decided to perform

hydrostatic testing of the remaining coolers to provide provide test data to support

continued operabililty with continuing pitting corrosion. The inspectors observed one of

the pressure tests and reviewed the revised operability determination.

These activities constitute completion of four operability review samples, as defined in

Inspection Procedure 71111.15.

b. Findings

No findings were identified.

1R19 Post-Maintenance Testing (71111.19)

a. Inspection Scope

The inspectors reviewed four post-maintenance testing activities that affected risk-

significant SSCs:

The inspectors reviewed licensing and design basis documents for the SSCs and the

maintenance and post-maintenance test procedures. The inspectors observed the

performance of the post-maintenance tests to verify that the licensee performed the tests

in accordance with approved procedures, satisfied the established acceptance criteria,

and restored the operability of the affected SSCs.

These activities constitute completion of four post-maintenance testing inspection

samples, as defined in Inspection Procedure 71111.19.

-7-

b. Findings

No findings were identified.

1R20 Refueling and Other Outage Activities (71111.20)

a. Inspection Scope

During the stations mid-cycle outage that concluded on May 13, 2014, the inspectors

evaluated the licensees outage activities. The inspectors verified that the licensee

considered risk in developing and implementing the outage plan, appropriately managed

personnel fatigue, and developed mitigation strategies for losses of key safety functions.

This verification included the following:

  • Review of the licensees outage plan prior to the outage
  • Monitoring of shut-down and cool-down activities
  • Verification that the licensee maintained defense-in-depth during outage activities
  • Monitoring of heat-up and startup activities

These activities constitute completion of one planned outage sample outage activities

sample, as defined in Inspection Procedure 71111.20.

b. Findings

No findings were identified.

1R22 Surveillance Testing (71111.22)

a. Inspection Scope

The inspectors observed six risk-significant surveillance tests and reviewed test results

to verify that these tests adequately demonstrated that the SSCs were capable of

performing their safety functions:

In-service tests:

Reactor Coolant System Leak Detection:

Other surveillance tests:

  • March 28-29, 2014, train A engineered safety features actuating safety testing
  • April 25-28, 2014, station blackout diesel functional testing
  • May 6, 2014, containment closeout walkdown

-8-

The inspectors verified that these tests met technical specification requirements, that the

licensee performed the tests in accordance with their procedures, and that the results of

the test satisfied appropriate acceptance criteria.

These activities constitute completion of six surveillance testing inspection samples, as

defined in Inspection Procedure 71111.22.

b. Findings

No findings were identified.

Cornerstone: Emergency Preparedness

1EP6 Drill Evaluation (71114.06)

Emergency Preparedness Drill Observation

a. Inspection Scope

The inspectors observed an emergency preparedness drill on June 18, 2014, to verify

the adequacy and capability of the licensees assessment of drill performance. The

inspectors reviewed the drill scenario, observed the drill from the simulator and

emergency operations facility, and attended the post-drill critique. The inspectors

verified that the licensees emergency classifications, off-site notifications, and protective

action recommendations were appropriate and timely. The inspectors verified that any

emergency preparedness weaknesses were appropriately identified by the licensee in

the post-drill critique and entered into the corrective action program for resolution.

These activities constitute completion of one emergency preparedness drill observation

sample, as defined in Inspection Procedure 71114.06.

b. Findings

No findings were identified.

2 RADIATION SAFETY

Cornerstones: Public Radiation Safety and Occupational Radiation Safety

2RS5 Radiation Monitoring Instrumentation (71124.05)

a. Inspection Scope

The inspectors evaluated the accuracy and operability of the radiation monitoring

equipment used by the licensee (1) to monitor areas, materials, and workers to ensure a

radiologically safe work environment, and (2) to detect and quantify radioactive process

streams and effluent releases. The inspectors interviewed licensee personnel, walked

down various portions of the plant, and reviewed licensee performance in the following

areas:

-9-

  • Selected plant configurations and alignments of process, post-accident, and

effluent monitors with descriptions in the Final Safety Analysis Report and the

offsite dose calculation manual

  • Select instrumentation, including effluent monitoring instrument, portable survey

instruments, area radiation monitors, continuous air monitors, personnel

contamination monitors, portal monitors, and small article monitors to examine

their configurations and source checks

  • Calibration and testing of process and effluent monitors, laboratory

instrumentation, whole body counters, post-accident monitoring instrumentation,

portal monitors, personnel contamination monitors, small article monitors,

portable survey instruments, area radiation monitors, electronic dosimetry, air

samplers, and continuous air monitors

  • Audits, self-assessments, and corrective action documents related to radiation

monitoring instrumentation since the last inspection

These activities constitute completion of one sample of radiation monitoring

instrumentation as defined in Inspection Procedure 71124.05.

b. Findings

No findings were identified.

2RS6 Radioactive Gaseous and Liquid Effluent Treatment (71124.06)

a. Inspection Scope

The inspectors evaluated whether the licensee maintained gaseous and liquid effluent

processing systems and properly mitigated, monitored, and evaluated radiological

discharges with respect to public exposure. The inspectors verified that abnormal

radioactive gaseous or liquid discharges and conditions, when effluent radiation monitors

are out-of-service, were controlled in accordance with the applicable regulatory

requirements and licensee procedures. The inspectors verified that the licensees

quality control program ensured radioactive effluent sampling and analysis adequately

quantified and evaluated discharges of radioactive materials. The inspectors verified the

adequacy of public dose projections resulting from radioactive effluent discharges. The

inspectors interviewed licensee personnel and reviewed or observed the following items:

  • Radiological effluent release reports since the previous inspection and reports

related to the effluent program issued since the previous inspection

  • Effluent program implementing procedures, including sampling, monitor setpoint

determinations, and dose calculations

  • Equipment configuration and flow paths of selected gaseous and liquid discharge

system components, filtered ventilation system material condition, and significant

changes to their effluent release points, if any, and associated 10 CFR 50.59

reviews

- 10 -

  • Selected portions of the routine processing and discharge of radioactive gaseous

and liquid effluents (including sample collection and analysis)

  • Controls used to ensure representative sampling and appropriate compensatory

sampling

  • Results of the inter-laboratory comparison program
  • Effluent stack flow rates
  • Surveillance test results of technical specification-required ventilation effluent

discharge systems since the previous inspection

  • Significant changes in reported dose values
  • A selection of radioactive liquid and gaseous waste discharge permits
  • Part 61 analyses and methods used to determine which isotopes are included in

the source term

  • Meteorological dispersion and deposition factors
  • Latest land use census
  • Records of abnormal gaseous or liquid tank discharges
  • Groundwater monitoring results
  • Changes to the licensees written program for identifying and controlling

contaminated spills/leaks to groundwater

  • Identified leakage or spill events and entries made into 10 CFR 50.75(g) records,

if any, and associated evaluations of the extent of the contamination and the

radiological source term

  • Offsite notifications and reports of events associated with spills, leaks, or

groundwater monitoring results

  • Audits, self-assessments, reports, and corrective action documents related to

radioactive gaseous and liquid effluent treatment since the last inspection

These activities constitute completion of one sample of radioactive gaseous and liquid

effluent treatment, as defined in Inspection Procedure 71124.06.

b. Findings

No findings were identified.

- 11 -

2RS7 Radiological Environmental Monitoring Program (71124.07)

a. Inspection Scope

The inspectors evaluated whether the licensees radiological environmental monitoring

program quantified the impact of radioactive effluent releases to the environment and

sufficiently validated the integrity of the radioactive gaseous and liquid effluent release

program. The inspectors verified that the radiological environmental monitoring program

was implemented consistent with the licensees technical specifications and offsite dose

calculation manual, and that the radioactive effluent release program met the design

objective in Appendix I to 10 CFR Part 50. The inspectors verified that the licensees

radiological environmental monitoring program monitored non-effluent exposure

pathways, was based on sound principles and assumptions, and validated that doses to

members of the public were within regulatory dose limits. The inspectors reviewed or

observed the following items:

  • Selected air sampling and dosimeter monitoring stations
  • Collection and preparation of environmental samples
  • Operability, calibration, and maintenance of meteorological instruments
  • Selected events documented in the annual environmental monitoring report

which involved a missed sample, inoperable sampler, lost dosimeter, or

anomalous measurement

  • Selected structures, systems, or components that may contain licensed material

and has a credible mechanism for licensed material to reach ground water

as the result of changes to the land census or sampler station modifications since

the last inspection

  • Calibration and maintenance records for selected air samplers, composite water

samplers, and environmental sample radiation measurement instrumentation

  • Inter-laboratory comparison program results
  • Audits, self-assessments, reports, and corrective action documents related to the

radiological environmental monitoring program since the last inspection

These activities constitute completion of one sample of the radiological environmental

monitoring program as defined in Inspection Procedure 71124.07.

- 12 -

b. Findings

No findings were identified.

2RS8 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage,

and Transportation (71124.08)

a. Inspection Scope

The inspectors evaluated the effectiveness of the licensees programs for processing,

handling, storage, and transportation of radioactive material. The inspectors interviewed

licensee personnel and reviewed the following items:

scope of the licensees audit program

  • Control of radioactive waste storage areas including container labeling/marking

and monitoring containers for deformation or signs of waste decomposition

  • Changes to the liquid and solid waste processing system configuration including

a review of waste processing equipment that is not operational or abandoned in

place

  • Radio-chemical sample analysis results for radioactive waste streams and use of

scaling factors and calculations to account for difficult-to-measure radionuclides

  • Processes for waste classification including use of scaling factors and

10 CFR Part 61 analysis

  • Shipment, packaging, surveying, labeling, marking, placarding, vehicle checking,

driver instructing, and preparation of the disposal manifest

  • Audits, self-assessments, reports, and corrective action reports on radioactive

solid waste processing and radioactive material handling, storage,

and transportation performed since the last inspection

These activities constitute completion of one sample of radioactive solid waste

processing, and radioactive material handling, storage, and transportation as defined in

Inspection Procedure 71124.08.

b. Findings

No findings were identified.

4. OTHER ACTIVITIES

Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity, Emergency

Preparedness, Public Radiation Safety, Occupational Radiation Safety, and

Security

- 13 -

4OA1 Performance Indicator Verification (71151)

.1 Reactor Coolant System Specific Activity (BI01)

a. Inspection Scope

The inspectors reviewed the licensees reactor coolant system chemistry sample

analyses for the period of April 1, 2013, through March 31, 2014, to verify the accuracy

and completeness of the reported data. The inspectors reviewed the surveillance

paperwork for the reactor coolant system sample taken on May 19, 2014. The

inspectors used definitions and guidance contained in Nuclear Energy Institute

Document 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7,

to determine the accuracy of the reported data.

These activities constituted verification of the reactor coolant system specific activity

performance indicator, as defined in Inspection Procedure 71151.

b. Findings

No findings were identified.

.2 Reactor Coolant System Identified Leakage (BI02)

a. Inspection Scope

The inspectors reviewed the licensees records of reactor coolant system identified

leakage for the period of April 1, 2013 through March 31, 2014 to verify the accuracy and

completeness of the reported data. The inspectors reviewed the performance

of STS BB-006 RCS Water Inventory Balance on May 31, 2014. The inspectors used

definitions and guidance contained in Nuclear Energy Institute Document 99-02,

Regulatory Assessment Performance Indicator Guideline, Revision 7, to determine the

accuracy of the reported data.

These activities constituted verification of the reactor coolant system leakage

performance indicator, as defined in Inspection Procedure 71151.

b. Findings

No findings were identified.

4OA2 Problem Identification and Resolution (71152)

.1 Routine Review

a. Inspection Scope

Throughout the inspection period, the inspectors performed daily reviews of items

entered into the licensees corrective action program and periodically attended the

licensees condition report screening meetings. The inspectors verified that licensee

personnel were identifying problems at an appropriate threshold and entering these

problems into the corrective action program for resolution. The inspectors verified that

- 14 -

the licensee developed and implemented corrective actions commensurate with the

significance of the problems identified. The inspectors also reviewed the licensees

problem identification and resolution activities during the performance of the other

inspection activities documented in this report.

b. Findings

No findings were identified.

.2 Semiannual Trend Review

a. Inspection Scope

To verify that the licensee was taking corrective actions to address identified adverse

trends that might indicate the existence of a more significant safety issue, the inspectors

reviewed corrective action program documentation associated with the following

licensee-identified trends:

  • High backlogs in the design implementation and configuration control process

area

Also, the inspectors identified the following trends that might indicate the existence of a

more significant safety issue, and reviewed the licensees response to them:

  • Inadequate technical verification and validation of temporary and permanent

plant modifications

  • The licensees corrective action program group is not trending data at a station-

wide level (i.e., above the department level), nor are they prioritizing

departmental issues and trends which are significantly affecting overall station

performance

The NRC identified a theme in NRC inspection findings with cross-cutting aspects in

maintaining design margins [H.6] during the 2013 End Of Cycle Assessment. The

inspectors reviewed the licensees response to that trend to verify that the licensee was

taking appropriate actions to address it.

These activities constitute completion of one semiannual trend review sample, as

defined in Inspection Procedure 71152.

b. Observations and Assessments

The inspectors review of the trends identified above produced the following observations

and assessments:

  • Design Control Backlogs. In July of 2013, an industry group assessment of

station performance noted an unusually high number of open design change

packages. The backlog included approximately 1700 change packages, some

open since the early 1990s, including some SSCs with multiple open design

changes. Some change packages had targeted completion dates that were

- 15 -

beyond the expiration date of the plant operating license. Historically, the station

has had challenges with design control, as noted in NRC inspection reports.

The licensee performed an apparent cause evaluation under Condition

Reports 72164, 72166, and 72167 to identify the organizational causes. Among

the licensees conclusions, management oversight of configuration control was

lacking, there was not an awareness of the vulnerability created by incomplete

configuration changes, and there was no single owner of design change products

to ensure configuration management documents are kept up to date. The

licensee took corrective actions to develop a configuration management health

plan to improve the design control program as well as developing a

comprehensive backlog reduction strategy. The inspectors also noted that the

licensee performed an aggregate risk assessment of the backlog to ensure that

items with more significant safety impacts were addressed more quickly. The

inspectors also noted that the backlog reduction program has reduced the

number of open change packages to 400 at the end of June 2014, with a goal of

less than 200 planned by January 2015.

  • Findings with Design Margins Cross Cutting Aspect [H6]. A theme in findings

with cross-cutting aspects in the area of maintaining design margins was

identified during the NRCs 2013 End of Cycle Assessment for Wolf Creek. The

licensee performed an apparent cause evaluation under Condition

Reports 74508 and 78794. The inspectors noted that this trend was related to

the larger problem of backlog management. Because this trend is related to

other improvement efforts, the inspectors noted that the licensee has evaluated

and taken actions related to this theme in the areas of corrective action,

preventive maintenance, and procedure revision backlog reductions under

Condition Reports 62394, 68194, and 78708. Most of the backlog improvement

efforts were making a notable reduction. The inspectors observed that most

backlog reduction efforts remained on target through the mid-cycle 20 outage in

March and April of 2014. Overall outage management and scope control

performance improvement was observed, and as a result, the corrective action

and work order backlogs did not see the growth observed during previous

outages. The licensee has taken corrective actions to establish and validate new

internal performance indicators for the engineering and maintenance

departments. Furthermore the licensee has scheduled actions to track these

new indicators and backlogs to specific goals based on industry standards in the

future.

Also, while completing this trend review, the inspectors identified the following trends

that the licensee had not previously identified. The inspectors also reviewed the

licensees response to these trends:

  • Quality of Plant Modifications. Over the past 2 years, Wolf Creek has been

implementing a large number of modifications. Additional non-safety related

diesel generators and an auxiliary feed water pump were added to improve plant

safety. The plant has also been addressing long standing corrosion and water

hammer issues in the essential service water system by replacing piping above

and below ground. Obsolete analog controllers have been replaced with digital

control systems. However, the inspectors have observed a number of plant

events and equipment failures associated with inadequate technical validation

- 16 -

and verification associated with these modifications.

On May 2, 2013, an unplanned and uncontrolled 11 percent power

increase occurred as a result of operator training deficiencies while

swapping from the full arc to partial arc steam admission shortly after

installing the new Westinghouse Ovation digital turbine controls. It was

subsequently determined that additional functions and flexibilities of the

new digital control system allowed operators to manipulate the plant in

configurations prohibited by the old analog system, and that system

response varied with power level, but this was not recognized and

incorporated into procedures and training. Condition Report 68711,

Non-Cited Violation NCV 05000482/2013003-05.

On May 28, 2013, and again on September 5, 2013, the turbine driven

auxiliary feed water pump control system failed unexpectedly, rendering

the pump incapable of operation. The digital control system positioner

locked up and required replacement. It was later determined that an

additional unused input to the positioner was experiencing noise, and if

the noise came in at a certain point in the digital computer programs

subroutine, the control software would crash. The problem was fixed by

jumpering out the unused input connection and a vendor technical bulletin

was issued to correct vulnerabilities at other nuclear power plants utilizing

the same control system. Condition Reports 69721, 69754, and 73624.

On April 25, 2014, during station blackout diesel generator testing, the

licensee was unable to connect the train A Class 1E 4kV distribution bus

to the station blackout diesel generators due to a protective relay

actuating to lock out the bus. The diesels had been declared functional

and were credited in performance indicators and probabilistic risk

assessment models since October 2013, when construction was

completed but testing had not been fully completed. Troubleshooting as a

result of the failed test found incorrect wiring of a protective relay to be

the cause. Extent of condition inspections found that the train B bus

connection was also wired incorrectly, and neither safety related bus

would have been able to have been powered from the station blackout

diesel generators. The licensee had intended to perform testing during

the previous refueling outage, but construction delays caused work to

extend beyond the outage. Plant conditions for this test necessitated the

plant be shut down. The inspectors had engaged the licensee concerning

their testing plan when construction was complete, but the licensee

concluded that their quality checks were adequate to have a high

confidence that testing to connect the generators to the safety buses

would be adequate until plant conditions for the testing were available.

The inspectors concluded that those quality checks were inadequate,

although this did not constitute a violation because the diesel generators

and protective relaying were non-safety equipment and were not credited

to meet any regulatory requirements. Condition Report 83379.

- 17 -

Not all of the validation and verification oversights resulted in plant events or

failures. Some of the items were caught very late in the planning process,

but still impacted regulatory commitments.

In February of 2014 the licensee commitment to correct long standing

water hammer conditions in the essential service water system was

delayed. The 2010 and 2012 Problem Identification and Resolution

inspections have assessed cited violations regarding long-standing

essential service water corrosion and water hammer issues not being

addressed in a timely manner. Wolf Creek responded on the docket and

committed to fixing the essential service water corrosion and water

hammer issues by the spring 2014 mid-cycle outage. However, after

over 3 years of planning, shortly before a modification was to be installed

to correct the water hammer, it was discovered that the mitigating strategy

would invalidate the essential service water design basis safety function

to provide a source of auxiliary feed water during a design basis external

event that compromises the condensate storage tank. This was

documented in Condition Reports 53443 and 79619. The licensee

concluded that there was inadequate contractor oversight during the

modification development process. A revised modification was tentatively

rescheduled for the next refueling outage.

On March 30, 2014, a containment cooler tube bundle failed (small tube

leaks) as a result of water hammer during the engineered safety features

actuation system testing. A similar failure occurred when the opposite

train was tested a few weeks later. While reviewing the cause evaluation,

the inspectors noted the failure mechanism was due to a combination of

pitting corrosion and sudden pressure spike during the essential service

water system water hammer. The ispectors determined that corrective

actions to address corrosion in carbon steel essential service water piping

had not addressed the copper-nickel containment cooler tubes. The

inspectors reviewed the history of containment cooler degradation and

noted that all 48 of the tube bundles had already been replaced due to

widespread degradation in the late 1990s, and now the 2nd generation

like-for-like replacements were beginning to fail. The problem was further

complicated because non-destructive testing to monitor corrosion was not

possible because the cooler design and complex cooler geometry

prevented this. The licensee plans to correct the condition by replacing

all coolers dueing the next outage, then replacing the original design with

stainless steel cooler tubes that will allow for eddy current testing.

Condition Reports 81809 and 82904.

On November 18, 2011, an NRC Component Design Basis Inspection

assessed NCV 05000482/2010007-01 for the failure to properly analyze

the isolation between the safety-related and non-safety related portions of

the component cooling water system. Portions of the non-safety piping

leading to the rad waste building are non-seismically qualified, and should

they fail, could result in a loss of inventory greater than can be

accommodated by the component cooling water surge tanks. The

inspector noted that the licensee promptly manually isolated this piping

and has been working on installing a combination of check valves and

- 18 -

orifices, for the past four years. The planned modification to correct this

violation has been delayed a number of times since 2012 because the

licensee has found problems with the design. Condition Reports 28237

and 85328.

The inspectors determined that the licensee was aware of these issues

individually, but had not identified the collective trend. The licensee wrote

Condition Report 85907 to evaluate and address this trend.

  • Lack Trending and Prioritization above the Department Level. In reviewing the

station roll-up reports that record corrective action program activities at the

station and departmental levels, the inspectors noted that the analytical trending

ends at the departmental summaries. The station corrective action staff was not

summarizing analytical trends across divisions, nor were they giving additional

priority to departmental trends which were having a significant impact on station

performance. (e.g. design control, procedure quality, etc.)

The inspectors reviewed additional documentation associated with station

improvement initiatives and determined that at a station level, senior leadership

was performing some station level trend analysis and setting station priorities

based on the available data, but this was being done outside the corrective

action program, and was not proceduralized and therefore would not continue

when the improvement initiatives were completed. The licensee has written

Condition Report 85905 to evaluate and address this issue.

The inspectors assessment noted improved corrective action trending at the

department level. The operations department continues to be a station leader in

this area. The maintenance and engineering departments have made notable

advancements in the past year to improve the quality of their corrective action

program work products. The inspectors have also witnessed a significant

improving trend in the quality, detail, and technical rigor, of apparent cause

evaluations and root cause analyses performed by station personnel.

c. Findings

No findings were identified.

.3 Annual Follow-up of Selected Issues

a. Inspection Scope

The inspectors selected one issues for an in-depth follow-up:

  • On May 1, 2014, below ground essential service water piping replacement to

correct long standing corrosion issues.

The inspectors assessed the licensees problem identification threshold, cause

analyses, extent of condition reviews and compensatory actions. The inspectors

reviewed modifications paperwork and observed pipe fitting and welding activities

in the field. The inspectors verified that the licensee appropriately prioritized the

- 19 -

planned corrective actions and that these actions were adequate to correct the

condition.

These activities constitute completion of one annual follow-up sample as defined in

Inspection Procedure 71152.

b. Findings

No findings were identified.

4OA6 Meetings, Including Exit

Exit Meeting Summary

On June 5, 2014, the inspectors presented the results of the radiation safety inspection to

Mr. C. Reasoner, Engineering, Vice President, and other members of the licensee staff. The

licensee acknowledged the issues presented. The licensee confirmed that any proprietary

information reviewed by the inspectors had been returned or destroyed.

On July 8, 2014, the inspectors presented the inspection results to Mr. A. Heflin, Chief Executive

Officer, and other members of the licensee staff. The licensee acknowledged the issues

presented. The licensee confirmed that any proprietary information reviewed by the inspectors

had been returned or destroyed.

- 20 -

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

L. Aiken, Health Physicist II

D. Campbell, Superintendent, Electrical Maintenance

C. Carman, Supervisor, Chemistry

S. Carpenter, Technician, Instruments and Controls

B. Crow, System Engineering

D. Dees, Superintendent, Operations Support

D. Erbe, Manager, Security

R. Flannigan, Manager, Nuclear Engineering

K. Fredrickson, Engineer, Licensing

J. Freeman, Supervisor, Operations

C. Garcia, Supervisor, Engineering

D. Gibson, Technician, Radiation Protection

M. Guyer, Training

R. Hammond, Supervisor, Regulatory Support

A. Heflin, President and Chief Executive Officer

S. Henry, Manager, Integrated Plant Scheduling

P. Herrman, Manager, Programs Engineering

R. Hobby, Licensing Engineer

S. Hossain, Engineer, System Engineering

B. Kiley, Technician III, Chemistry

S. Koenig, Manager, Regulatory Affairs

R. Lane, Superintendent, Operations

M. McMullen, Design Engineer, Engineering

C. Medenciy, Supervisor, Radiation Protection

K. Miller, Technician Level III, Instruments and Controls

K. Mitchell, Master Chemistry Technician

W. Muilenburg, Supervisor, Licensing

T. Rice, Manager, Environmental Management

D. Scrogum, Systems Engineer, Engineering

M. Skiles, Acting Manager, Radiation Protection

R. Smith, Site Vice President

S. Smith, Plant Manager

T. Smith, Manager, Project Construction Engineering

J. Truelove, Supervisor, Chemistry

L. Upson, Manager, Strategic Initiatives

B. Vickery, Manager, Financial Services

J. Yunk, Manager, Corrective Actions

Attachment 1

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened and Closed

05000482-2014003- NCV Failure to Assess and Manage Risk of Planned Outage

01 Maintenance Activities During Solid Plant Operations

(Section 1R13)

LIST OF DOCUMENTS REVIEWED

Section 1R01: Adverse Weather Protection

Procedures

Number Title Revision

STS NB-005 Breaker Alignment Verification 26

Section 1R04: Equipment Alignment

Procedures

Number Title Date

CKL EM-120 Safety Injection System Lineup Checklist September

17, 2014

Section 1R05: Fire Protection

Procedures

Number Title Revision

AP 10-106 Fire Preplans 13

Section 1R11: Licensed Operator Requalification Program and Licensed Operator

Performance

Procedures

Number Title Revision

BD-EMG C-0 Loss of All AC Power 20

Section 1R13: Maintenance Risk Assessments and Emergent Work Control

Procedures

Number Title Revision/Date

AI 22C-013 Protected Equipment Program 11

A1-2

Procedures

Number Title Revision/Date

AP 22B-001 Outage Risk Management 17

AP 21D-002 Evaluation for Potential Energy/Fluid Transfer Paths 11A

APF 22B-001-10 Shutdown Safety Function Status and Risk Assessment March 14,

Summary 2014 Night

Shift

APF 22B-001-10 Shutdown Safety Function Status and Risk Assessment April 1, 2014

Summary Day Shift

APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment, May 28, 2014

Schedule Week 2014-0211

APF 22C-003-01 On-Line Nuclear Safety and Generation Risk Assessment June 11,

Schedule Week 2014-0212 2014

SYS PG-204 Energizing PG19 or PG20 from Alternate Power Source 21

TMP 14-002 CCW Train B Operations with Heat Exchanger Bypassed 0

Condition Reports

80870 81981

Work Order

12-359936-000 12-359637-000

Miscellaneous

Number Title Revision/Date

ODM 2014-05 Operations Decision Making Documentation Form: Wolf 0

Creek will maintain solid pressurizer conditions with reduced

temperature and pressure control bands.

APF 22C-007 Shutdown Safety Contingency Planning Template: Decay 1

Heat Removal Defense in Depth

M-EJ-A-001 Clearance Order: RHR to CVCS Centrifugal Charging April 2, 2014

Pumps Isolation Valve

Work Week Manager Logs

Control Room Logs

Weekly Major Activity Summary Week 2014-208

Weekly Major Activity Summary Week 2014-211

Weekly Major Activity Summary Week 2014-212

A1-3

Miscellaneous

Number Title Revision/Date

Wolf Creek Shift Outage Update March 13,

2014 Day Shift

Section 1R15: Operability Determinations and Functionality Assessments

Procedures

Number Title Revision

OE K-14-009 B-EDG Governor Hydraulic Actuator 0

STS IC-208A 4kV Loss of Voltage and Degraded Voltage TADOT NB01 5B

Bus - Separation Group 1

Condition Reports

85015 81809 82266 84318

Engineering Disposition

Title Revision

Containment Cooler Tube Pitting 1

Section 1R19: Post-Maintenance Testing

Procedures

Number Title Revision/Date

STN EF-220A ESW Train A Post-LOCA Flow Balance March 4, 2014

SYS BB-201 Reactor Coolant Pump Operation 58

SYS KJ-123-2 Post Maintenance Run of EDG A January 30,

2014

Work Orders

14-385808-006 11-347436-002 14-387407-002 14-386517-001

A1-4

Section 1R20: Refueling and Other Outage Activities

Procedures

Number Title Date

NE 14-0005 Mid-Cycle 20 Level 1 Schedule and Outage Risk February 6,

Assessment Report 2014

Section 1R22: Surveillance Testing

Procedures

Number Title Revision/Date

STS BB-006 RCS Water Inventory Balance Using the NPIS Computer 12

STS CH-024 Reactor Coolant Dose Equivalent Xe-133 Determination 6A

STS IC-208A 4kv Loss of Voltage and Degraded Voltage TADOT NB01 5B

Bus - Separation Group 1

STS KJ-001A Integrated D/G and Safeguards Actuation Text Train A March 14, 2014

STN KU-001A SBO DG NB01 Functional Test March 28, 2014

STN EJ-002 Containment Inspection 20

Section 2RS5: Radiation Monitoring Instrumentation

Procedures

Number Title Revision/Date

CHS AC-001 Accident Sampling 4A

WCIC-236 RMS Calibration Document November 13,

1995

STN SP-118 Channel Calibration Liquid Radwaste Discharge Radiation 8

Monitor HB RE-0018

STN CH-010 Calibration of Liquid Radiation Monitors 3B

STS CH-014 Calibration of Monitors GTRE21B and GHRE10B 12

STN CH-021 Calibration of the Particulate Detector for Radiation Monitors 4A

GTRE21A and GHRE10A

STN CH-022 Calibration of the Iodine Detector for Radiation Monitors 1B

GTRE21A and GHRE10B

AP 07B-003 Offsite Dose Calculation Model 8

RPP 01-405 HP Instrument Program 30

A1-5

Procedures

Number Title Revision/Date

RPP 03-407 Testing of Portal Monitors as Passive Whole Body Counters 1A

RPP 05-707 Operation of Whole Body Counters 8

RPP 06-101 Eberline RO-2 and RO-2A Calibration 6

RPP 06-105 Eberline RO-20 Calibration 5

RPP 06-306 PM12 Calibration 8A

STN SP-118 Channel Calibration Liquid Radwaste Discharge Radiation 8

Monitor HB RE-0018

STN CH-010 Calibration of Liquid Radiation Monitors 3B

Condition Reports

00081759 00084854 00084863 00084815 00084820

00084817 00083254 00082997 00080994 00079621

00078962 00078548 00074873 00074445 00074219

00072691 00072303 00068426 00068295 00068064

00051785 00054489 00065431 00067627 00062921

Calibration Records

Number Title Date

WO12360791000 Channel Calibration Digital High Range Area Monitor February 4,

GTRE-0059 Calibration Source Drop 2014

WO13381072000 Channel Calibration Digital High Range Area Radiation January 28,

Monitor GTRE60 2014

WO12360792000 Channel Calibration Digital High Range Area Radiation February 3,

Monitor GTRE60 Calibration Source Drop 2014

WO13381018000 Channel Calibration Digital High Range Area Radiation January 24,

Monitor GTRE59 2014

11428 AMS4 March 9, 2014

11748 AMS4 March 9, 2014

11429 AMS4 February 24,

2014

A1-6

11376 PCM-1B February 5,

2009

11379 PCM-1B February 5,

2009

11378 PCM-1B April 17, 2014

10240 PCM-1C April 9, 2009

11005 SAM 11 January 29,

2014

11006 SAM 11 June 19, 2013

92874 RTM 110 March 23,

2014

92877 RTM 110 April 28, 2014

10260 ASP-1 February 6,

2014

93330 PM12 August 15,

2013

93573 PM12 February 5,

2014

11511 HD-29A January 29,

2014

10242 PCM-2 December 9,

2013

10066 Whole Body Counter Calibration Certificate July 18, 2011

13027 Whole Body Counter Calibration Certificate September 15,

2008

Section 2RS6: Radioactive Gaseous and Liquid Effluent Treatment

Procedures

Number Title Revision

AI 07-007 Onsite Groundwater Protection Program Monitoring 14

AI 07B-001 Radioactive Releases 19

AI 07B-020 Instructions for Composite Preparation 19

AI 07B-036 Liquid Release Permits Using RADEAS 01

AI 07B-037 Unit and Radwaste Vent Permits Using RADEAS 01

AI 07B-038 Unit and Radwaste Vent Permits Using RADEAS 01

A1-7

Procedures

Number Title Revision

AP 07B-003 Offsite Dose Calculation Manual 08

CHA RC-004 Gamma Isotopic, Total Curie Content and Dose Equivalent 15

Iodine Determination

CHS RW-G02 Radwaste Vent Sampling and/or Exchange of Filters 3C

CHS SJ-144A SJ-144 Sampling Instructions 0C

CHS TB-L03 Turbine Building Local Sampling - Mid-Frequency 06

RPP 07-111 Handling Cartridge Filters 17

Condition Reports

00051966 00053930 00055466 00055535 00055538

00056233 00056574 00056887 00059243 00059832

00061757 00064627 00064667 00064798 00065779

00066655 00066920 00068803 00069832 00069959

00070420 00070826 00072303 00076226 00077621

00077802 00078707 00082909 00083740 00084346

10 CFR 50.75(g) Condition Reports

00084942

Gaseous and Liquid Release Permits

Permit No. System Release Type Date

U1LC2014-080/2013060 Turbine Building Drains Liquid June 11, 2013

U1GB2014-093/2013081 Containment Purge Unit Vent Gaseous July 17, 2013

U1GB2014-099/2013087 Containment Purge Unit Vent Gaseous July 27, 2013

U1LC2014-091/2013071 Steam Generator Blowdown Liquid August 30, 2013

U1LC2014-110/2013090 Lime Sludge Pond Liquid November 19, 2013

U1GB2014-017/2014017 Containment Purge Unit Vent Gaseous February 4, 2014

U1LC2014-005/2014005 Steam Generator Blowdown Liquid March 1, 2014

U1GB2014-162/2014162 Containment Purge Unit Vent Gaseous April 7, 2014

A1-8

In-Place Filter Testing Records

Work Order Test Date

STS PE-006 Charcoal Adsorber In-Place Leak Test Safety-Related Units December 10,

- FGK01B 2013

STS PE-005 HEPA Filter In-Place Leak Test Safety-Related Units - December 10,

FGK01B 2013

STS PE-002 Charcoal Adsorbent Sampling for Nuclear Safety-Related December 23,

Units - FGK01B 2013

STS PE-002 Charcoal Adsorbent Sampling for Nuclear Safety-Related December 23,

Units - FGG02B 2013

STS PE-006 Charcoal Adsorber In-Place Leak Test Safety-Related Units February 24,

- FGK01A 2014

STS PE-005 HEPA Filter In-Place Leak Test Safety-Related Units - February 24,

FGK01A 2014

Miscellaneous Documents

Number Title Revision/Date

11.1A-3 USAR Figure: Potential Gaseous Release 13

M-12HB01-5 WCNOC PID: Liquid Radwaste System 20

M-12EG01 WCNOC PID: Component Cooling Water System 24

System Health Report: Radiation Monitoring January 1 -

September

30, 2013

RA 13-0052 WCNOC 2013 Annual Radioactive Effluent Release

Report

RPF 02-210-05 50.75(g) Radiological Occurrence Worksheet for June 2, 2014

Decommissioning Record

2013-011-EG00 Temporary Modification Order: EG System (A/B Trains), August 19,

EGV0357 & EGV0310, EGV0324 & EGV0388 2013

RA 14-0043 WCNOC 2014 Annual Radioactive Effluent Release April 29, 2014

Report

WC Radiation Monitors Considered for Maintenance Rule June 2, 2014

Section 2RS7: Radiological Environmental Monitoring Program

Procedures

Number Title Revision

AI 07B-004 Reporting Requirements of the Radiological 13

Environmental Monitoring Program

A1-9

Procedures

Number Title Revision

AI 07B-005 Radiological Environmental Monitoring Program 20

Implementation

AI 07B-009 Collection, Preparation and Shipment of Sediment and 8

Soil Samples

AI 07B-011 Collection, Preparation and Shipment of Water Samples 15

AI 07B-012 Collection, Preparation and Shipment of Crop, 10

Vegetable, Fruit and Pasturage Samples

AI 07B-015 Land Use Census 11

AI 07B-034 Radiological Environmental Monitoring Program Air 11

Sampling

AI 07B-035 REMP Optically Stimulated Luminescence (OSL) 6

Dosimeters

AP 07B-003 Offsite Dose Calculation Manual 8

AP 07B-004 Offsite Dose Calculation Manual (Radiological 20

Environmental Monitoring Program)

AP 07B-005 Ground Water Protection Program 3

AP 07E-001 Validation of Meteorological Data 3

STN CH-024 Quarterly/Yearly Dose Projections 3

STS IC-890A Channel Calibration of Wind Speed Meteorological 17

Instrumentation

STS IC-890B Channel Calibration of Wind Direction/Deviation 17

Meteorological Instrumentation

STS IC-890C Channel Calibration of 10M/60M Ambient and 20

Differential Temperature Instrumentation

STS IC-890D Channel Calibration of Sonic Wind 2

Speed/Direction/Deviation Meteorological

Instrumentation

Audits, Self-Assessments, and Surveillances

Number Title Date

QH-2013-0654 NUPIC Audit Report of Landauer, Inc. December 16,

2013

11-2049 Evaluation Report of F&J Specialty Products, Inc. January 13,

2013

SQL 13-44 Evaluation Report of Landauer, Inc. - Glenwood, IL October 11,

2013

QH-2013-0660 Ground Water Protective Initiative 5-Year Follow-up December 16,

Assessment 2013

A1-10

Audits, Self-Assessments, and Surveillances

Number Title Date

Audit Report No: Quality Assurance Audit Report of Environmental April 17, 2014

14-03-ENV Management Plans

Condition Reports

00051888 00052766 00054626 00070866 00082043

00083302 00084016 00084879 00084901 00084915

00084919 00084920

Calibration And Maintenance Records

Number Title Date

WO 13-375743 Surveillance Test Routing Sheet: Channel Calibration of April 20, 2014

60m 10m Differential Temperature

WO 13-375744 Surveillance Test Routing Sheet: Channel Calibration of April 6, 2014

Wind Speed

WO 13-375741 Surveillance Test Routing Sheet: Channel Calibration of April10, 2014

Wind Direction

WO 13-375742 Surveillance Test Channel Calibration of Sonic Wind April 6, 2014

Speed/Direction/Deviation

Miscellaneous Documents

Number Title Date

SA-10-004 Relative Deposition per Unit Area (D/Q) 3 Year Update November 2,

(2007-2009) 2010

2012 Annual Radiological Environmental Operating Report April 27, 2013

2013 Annual Radiological Environmental Operating Report April 15, 2012

QH-2011-0016 REMP Review of 2010 Wind Direction August 31,

2011

QH-2012-0242 REMP Review of 2011 Wind Direction July 30, 2012

QH-2013-0016 REMP Review of 2012 Wind Direction August 14,

2011

A1-11

Section 2RS8: Radioactive Solid Waste Processing and Radioactive Material Handling,

Storage, and Transportation

Procedures

Number Title Revisions

AP 31A-100 Solid Radwaste Process Control Program 7 and 8

RPP 07-110 Solid Radwaste Packaging 9

RPP 07-111 Handling Filter Cartridges 17 and 18

RPP 07-112 Processing Cartridge Filters 5

RPP 07-131 Bead Resin/Activated Carbon Dewatering Procedures for 4

CNSI 14-215 or Smaller Liners

RPP 07-212 Requirements of Radioactive Materials Stored Outdoors 0

Audits and Self-Assessments

Number Title Date

QS-2014-0629 Quality Surveillance performed on the Radwaste Group by February 26,

WCNOC and Tech Specialist from Nine Mile Point 2014

Condition Reports

00051881 00056346 00056839 00062522 00066895

00066920 00073358 00079817 00081750 00081752

00084772 00084856 00084857 00084880 00084932

00084951

Radiation Work Permits

Number Title Revision

13-0121 ALARA Review Package 1

130121 Cartridge Filter Change-out 000

130121 Cartridge Filter Change-out 001

130121 Cartridge Filter Change-out 002

140029 Resin Transfer to Primary Spent Resin Storage Tank 000

(THC08)

A1-12

Radioactive Material Shipments

Number Title Revision

12R26 Radioactive Material LSA-I; UN 2912 1

13R30 Radioactive Material LSA-II; UN 3321 000

13R49 Radioactive Material LSA-II; UN 3321 001

14R18 Radioactive Material LSA-II; UN 3321 002

12R26 Radioactive Material LSA-I; UN 2912 000

Radioactive Waste Stream Characterization

Number Title Date

7 Primary Resin (CVCS, SFP) April 15, 2013

7 Primary Resin (CVCS, SFP) January 23,

2014

13 Dry Active Waste April 19, 2012

13 Dry Active Waste March 4, 2014

Miscellaneous Documents

Number Title Date

Access Control Shift Log (01:25 to 17:39) April 1, 2013

Filter Characterization Reports August 20,

(13F044, 13F046, 13F047, 13F048, 13F049, 13F051, 13F052, 2013

13F053, 13F055, 13F058, 13F059, 13F060, 13F061, 13F097)

13-063ES Characterization and Classification of Wolf Creek Excore May 31, 2013

Detectors

36 Annual Radioactive Effluent Release Report January 1,

2012 -

December 31,

2012

37 Annual Radioactive Effluent Release Report January 1,

2013 -

December 31,

2013

HW12158 Training Course Regulations and Requirements January 11,

01 2010

OTSC 13- On the Spot Change to RPP 07-111 Rev 17 April 3, 2013

0056

A1-13

Miscellaneous Documents

Number Title Date

RPF 07- Filter Information Log April 3, 2014

111-01

RPF 07- Radioactive Shipment Log 2012

123-01

RPF 07- Radioactive Shipment Log 2013

123-01

RPF 07- Radioactive Shipment Log 2014

123-01

Section 4OA2: Problem Identification and Resolution

Procedures

Number Title Revision

AP 05-005 Design, Implementation, and Configuration Control of 20

Modifications

AP 05-010 Design Drawings 9

AP 05F-001 Design Verification 3A

Condition Reports

79619 53443 82904 70384 70383

69721 69754 73624 71624 74508

78794 72166 72164 72167 68194

62394 78708

Miscellaneous

Number Title Revision/Date

WM 14-0011 Letter from Wolf Creek Nuclear Operating Corp. to U.S.NRC: May 8, 2014

Docket No. 50-482: Change to Essential Service Water System

Water Hammer Mitigation Commitment

WM 14-0013 Letter from Wolf Creek Nuclear Operating Corp. to U.S.NRC: May 8, 2014

Docket No. 50-482: Voluntary Commitment Regarding

Containment Coolers at Wolf Creek Generating Station

A1-14

Miscellaneous

Number Title Revision/Date

Wolf Creek Corrective Action Program Station Roll-Up March 6, 2014

Performance Results 4th Quarter 2013

Wolf Creek Corrective Action Program Station Roll-Up June 6, 2014

Performance Results 1st Quarter 2014

Wolf Creek Rebuilding Plan June 6, 2014

Engineering Excellence Plan - Product Quality Strategic Area 00

Wolf Creek Change Management Plan - Engineering Technical September 5,

Rigor Improvement 2013

A1-15

The following items are requested for the

Public Radiation Safety Inspection

Wolf Creek Generating Station

June 2 through June 6, 2014

Integrated Report 2014003

Inspection areas are listed in the attachments below.

Please provide the requested information on or before May 19, 2014.

Please submit this information using the same lettering system as below. For example,

all contacts and phone numbers for Inspection Procedure 71124.01 should be in a

file/folder titled 1- A, applicable organization charts in file/folder 1- B, updated final

safety analysis report

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.

Attachment 2

5. Radiation Monitoring Instrumentation (71124.05)

Date of Last Inspection: April 23, 2012

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 Nuclear Procurement Issues Committee

(NUPIC) audits for contractor support and licensee event reports (LERs), written since

date of 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 Specific Procedures will be requested by number after the inspector reviews

the procedure indexes.

1. Calibration of portable radiation detection instruments (for portable ion chambers)

2. Whole body counter calibration

3. Laboratory instrumentation quality control

F. A summary list of corrective action documents (including corporate and subtiered

systems) written since date of 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. Effluent radiation monitors

4. 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. Offsite dose calculation manual, technical requirements manual, or licensee controlled

specifications which lists the effluent monitors and calibration requirements

H. Current calibration data for the whole body counters

I. Primary to secondary source calibration correlation for effluent monitors

J. A list of the point of discharge effluent monitors with the two most recent calibration

dates and the work order numbers associated with the calibrations

K. Radiation Monitoring System health report for the previous 12 months

A2-2

6. Radioactive Gaseous and Liquid Effluent Treatment (71124.06)

Date of Last Inspection: April 23, 2012

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 date of 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 Specific Procedures will be requested by number after the inspector reviews

the procedure indexes.

1. Sampling of radioactive effluents

2. Sample analysis

3. Generating radioactive effluent release permits

4. Laboratory instrumentation quality control

5. In-place testing of HEPA filters and charcoal adsorbers

6. New or applicable procedures for effluent programs (e.g., including ground water

monitoring programs)

F. List of corrective action documents (including corporate and subtiered systems) written

since date of 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. 2012 and 2013 Annual Radioactive Effluent Release Report, or the two most recent

reports.

H. Current Copy of the Offsite Dose Calculation Manual

I. Copy of the 2012 and 2013 interlaboratory 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 date of last inspection

L. Operations department (or other responsible department) log records for effluent

monitors removed from service or out of service

M. Listing or log of liquid and gaseous release permits since date of last inspection

A2-3

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. Moreover, please provide a specific list of all effluent radiation

monitors that were considered inoperable for 7 days or more since November 2011.

If applicable, please provide the relative Special Report and condition report(s).

P. A list of all radiation monitors that are considered §50.65/Maintenance Rule equipment

Q. A list of all significant changes made to the Gaseous and Liquid Effluent Process

Monitoring System since the last inspection. If applicable, please provide the

corresponding updated final safety analysis report (UFSAR) section in which this change

was documented.

R. A list of any occurrences in which a non-radioactive system was contaminated by a

radioactive system. Please include any relative condition report(s).

A2-4

7. Radiological Environmental Monitoring Program (71124.07)

Date of Last Inspection: April 23, 2012

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 date of 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 Specific Procedures will be requested by number after the inspector reviews

the procedure indexes.

1. Environmental Program Description

2. Sampling, collection, and preparation of environmental samples

3. Sample analysis (if applicable)

4. Laboratory instrumentation quality control

5. Procedures associated with the Offsite Dose Calculation Manual

6. Appropriate QA Audit and program procedures, and/or sections of the stations

QA manual (which pertain to the REMP)

F. A summary list of corrective action documents (including corporate and subtiered

systems) written since date of 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. Wind Rose data and evaluations used for establishing environmental sampling locations

H. Copies of the 2 most recent calibration packages for the meteorological tower

instruments

I. Copy of the 2012 and 2013 Annual Radiological Environmental Operating Report and

Land Use Census, and current revision of the Offsite Dose Calculation Manual, or the

two most recent reports.

J. Copy of the environmental laboratorys interlaboratory comparison program results for

2012 and 2013, or the two most recent results, if not included in the annual radiological

environmental operating report

K. Data from the environmental laboratory documenting the analytical detection sensitivities

for the various environmental sample media (i.e., air, water, soil, vegetation, and milk)

L. Quality Assurance audits (e.g., NUPIC) for contracted services

A2-5

M. Current NEI Groundwater Initiative Plan and status

N. Technical requirements manual or licensee controlled specifications which lists the

meteorological instruments calibration requirements

O. A list of Regulatory Guides and/or NUREGs that you are currently committed to relative

to the Radiological Environmental Monitoring Program. Please include the revision

and/or date for the committed item and where this can be located in your current

licensing basis/UFSAR.

P. If applicable, per NEI 07-07, provide any reports that document any spills/leaks to

groundwater since the last inspection.

A2-6

8. Radioactive Solid Waste Processing, and Radioactive Material Handling, Storage,

and Transportation (71124.08)

Date of Last Inspection: April 23, 2012

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 date of 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 Specific Procedures will be requested by number after the inspector reviews

the procedure indexes.

1. Process control program

2. Solid and liquid radioactive waste processing

3. Radioactive material/waste shipping

4. Methodology used for waste concentration averaging, if applicable

5. Waste stream sampling and analysis

F. A summary list of corrective action documents (including corporate and subtiered

systems) written since date of 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 49CFR172, subpart H, for radwaste processing,

packaging, and shipping.

H. A summary of radioactive material and radioactive waste shipments made from date of

last inspection to present

I. Waste stream sample analyses results and resulting scaling factors for 2012 and 2013,

or the two most recent results.

J. Waste classification reports if performed by vendors (such as for irradiated hardware)

K. A listing of all onsite radwaste storage facilities. Please include a summary or listing of

the items stored in each facility, including the total amount of radioactivity and the

highest general area dose rate.

Although it is not necessary to compile the following information, the inspector will also review:

L. Training, and qualifications records of personnel responsible for the conduct of

radioactive waste processing, package preparation, and shipping

A2-7

ML14223B221

SUNSI Review ADAMS Yes Non-Sensitive Publicly Available Keyword

By: NFO No Sensitive Non-Publicly Available NRC-002

OFFICE SRI:DRP/B RI:DRP/B C:DRS/TSB C:DRS/EB1 C:DRS/EB2

NAME CPeabody/tk RStroble GMiller TFarnholtz JDixon

SIGNATURE /RA/ /RA/ /RA/ /RA/ /RA/

DATE 7/23/14 8/11/14 8/8/14 8/6/14 8/6/14

OFFICE C:DRS/OB C:DRS/PSB1 C:DRS/PSB2 BC:DRP/B

NAME VGaddy MHaire HGepford NOKeeefe

SIGNATURE /RA/ /RA/ /RA/ /RA/

DATE 8/6/14 8/8/14 8/8/14 8/11/14

Letter to Adam Heflin from Neil OKeefe, dated August 11, 2014

SUBJECT: WOLF CREEK GENERATING STATION - NRC INTEGRATED INSPECTION

REPORT 05000482/2014003

DISTRIBUTION:

Regional Administrator (Marc.Dapas@nrc.gov)

Deputy Regional Administrator (Kriss.Kennedy@nrc.gov)

Acting DRP Director (Troy.Pruett@nrc.gov)

Acting DRP Deputy Director (Michael.Hay@nrc.gov)

DRS Director (Anton.Vegel@nrc.gov)

DRS Deputy Director (Jeff.Clark@nrc.gov)

Senior Resident Inspector (Charles.Peabody@nrc.gov)

Resident Inspector (Raja.Stroble@nrc.gov)

WC Administrative Assistant (Carey.Spoon@nrc.gov)

Branch Chief, DRP/B (Neil.OKeefe@nrc.gov)

Senior Project Engineer, DRP/B (David.Proulx@nrc.gov)

Project Engineer, DRP/B (Fabian.Thomas@nrc.gov)

Public Affairs Officer (Victor.Dricks@nrc.gov)

Public Affairs Officer (Lara.Uselding@nrc.gov)

Project Manager (Fred.Lyon@nrc.gov)

Branch Chief, DRS/TSB (Geoffrey.Miller@nrc.gov)

RITS Coordinator (Marisa.Herrera@nrc.gov)

ACES (R4Enforcement.Resource@nrc.gov)

Regional Counsel (Karla.Fuller@nrc.gov)

Technical Support Assistant (Loretta.Williams@nrc.gov)

Congressional Affairs Officer (Jenny.Weil@nrc.gov)

RIV/ETA: OEDO (Anthony.Bowers@nrc.gov)

ROPreports

Retrieved from "https://kanterella.com/w/index.php?title=ML14223B221&oldid=2046036"