IR 05000482/2017008
| ML17325A098 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 11/20/2017 |
| From: | Werner G E NRC/RGN-IV/DRS/EB-2 |
| To: | Heflin A C Wolf Creek |
| Werner G E | |
| References | |
| IR 2017008 | |
| Preceding documents: |
|
| Download: ML17325A098 (31) | |
Text
November 20, 2017
Mr. Adam C. Heflin, President, Chief Executive Officer, and Chief Nuclear Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839
SUBJECT: WOLF CREEK GENERATING STATION
- NUCLEAR REGULATORY COMMISSION TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000482/2017008
Dear Mr. Heflin:
On October 19, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Wolf Creek Generating Station and discussed the results of this inspection with Mr. D. Mand, Director Engineering, and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC team documented two finding s of very low safety significance (Green) in this report. Both of t hese finding s involved violations of NRC requirements. The NRC is treating th e s e violation s as non-cited violation s consistent with Section 2.3.2.a of the Enforcement Policy.
If you contest the violations or significance of the violations in this report
, you should provide a written 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 NRC resident inspector at the Wolf Creek Generating Station. If you disagree with a cross-cutting aspect assignment or a finding not associated with a regulatory requirement in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001, with copies to the Regional Administrator, Region IV , and the NRC resident inspector at the Wolf Creek Generating Station
. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading
-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, "Public Inspections, Exemptions, Requests for Withholding.
"
Sincerely,/RA/ Gregory E. Werner, Chief Engineering Branch 2 Division of Reactor Safety Docket No.
50-482 License No. NPF-42
Enclosure:
Inspection Report No. 05000482/2017008
w/Attachment:
Supplemental Information
Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket: 05000482 License: NPF-42 Report Nos.:
05000482/2017 008 Licensee: Wolf Creek Nuclear Operating Corporation Facility: Wolf Creek Generating Station Location: P.O. Box 411 Burlington, KS 66839 Dates: October 2 through October 19, 2017 Team Leader:
J. Mateychick, Senior Reactor Inspector Inspectors:
B. Correll , Reactor Inspector G. Pick, Senior Reactor Inspector S. Makor , Reactor Inspector Accompanying Personnel:
Ms. Noletu Moti , Chief Inspector, National Nuclear Regulator of the Republic of South Africa Approved By:
Gregory E. Werner , Chief Engineering Branch 2 Division of Reactor Safety
2
SUMMARY
IR 05000 482/20 17008; 10/02/2017
- 10/19/2017
- Wolf Creek Generating Station
- Fire Protection (Triennial) The report covers a two-week triennial fire protection team inspection by specialist inspectors from Region IV.
T wo finding s which were non-cited violation s were documented. The significance of inspection findings is indicated by their color (i.e., Green, White, Yellow, or Red) and determined using Inspection Manual Chapter 0609, "Significance Determination Process," dated April 29, 2015
. Cross-cutting aspects are determined using Inspection Manual Chapter 0310, "Aspects within the Cross-Cutting Areas," dated December 4, 2014
. All violations of NRC requirements are dispositioned in accordance with the NRC's Enforcement Policy , dated November 1, 20 16. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG
-1649, "Reactor Oversight Process
," Revision 6.
A. NRC-Identified and Self-Revealing Findings
Cornerstone: Mitigating Systems
- Green.
The team identified a non-cited violation of License Condition 2.C.(5) for failure to implement and maintain in effect all provisions of the approved fire protection program. Specifically, the licensee failed to adequately evaluate the potential impacts on post-fire safe shutdown of two motor operated valves spuriously closing due to fire damage.
The failure to adequate ly evaluate the impact of pressure operated relief valve block valves spuriously closing on post-fire safe shutdown was a performance deficiency. The performance deficiency was more than minor because it was associated with the protection against external events (fire) attribute of the Mitigating Systems cornerstone and it adversely affected the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences.
Because the finding affected the ability to reach and maintain safe shutdown conditions in case of a fire that led to control room evacuation and because the Phase 2 methodology of Inspection Manual Chapter 0609, Appendix F, was not appropriate for this finding, a senior reactor analyst performed a Phase 3 evaluation to determine the risk significance.
The analyst determined this finding was of very low risk significance (Green).
There is no cross-cutting aspect associated with this finding since the performance deficiency is not reflective of present performance (i.e., the performance deficiency occurred more than 3 years ago).
(Section 1R05.01)
- Green.
The team identified a non-cited violation of License Condition 2.C.(5
) for failure to provide emergency lighting along alternate routes plant operators are allowed to take during implementation of the procedure for control room evacuation due to fire.
The failure to provide 8
-hour emergency lights along alternate routes used by operators during control room evacuation due to fire is a performance deficiency.
The performance deficiency was more than minor because it was associated with the protection against external factors attribute of the Mitigating 3 Systems cornerstone and adversely affected the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences.
The team evaluated this finding using Inspection Manual Chapter 0609, Appendix F, "Fire Protection Significance Determination Process," dated September 20, 2013, because it affected the ability to reach and maintain safe shutdown conditions in case of a fire.
The team assigned the finding to the post-fire safe shutdown category since it impacted the alternate shutdown element.
The issue screened to Green because the reactor would be able to achieve and maintain hot shutdown because the operators are required to carry flashlights.
Specifically, the team had reasonable assurance that the operators would be able to complete the evacuation procedure using handheld flashlights to access safe shutdown equipment.
The finding is assigned a cross-cutting aspect in the area of human performance, associated with training, because the operators are not being trained on the access and egress routes that are provided with 8-hour emergency lights during implementation of the control room evacuation procedure due to fire to ensure the time critical actions can be met (H.9).
(Section 1R05.08)
B. Licensee-Identified Violations
None 4
REPORT DETAILS
REACTOR SAFETY
Cornerstones:
Initiating Events, Mitigating Systems, and Barrier Integrity
1R05 Fire Protection
This report presents the results of a triennial fire protection inspection conducted at Wolf Creek Generating Station in accordance with NRC Inspection Procedure 71111.05T, "Fire Protection (Triennial)
," dated January 31, 2013
. The inspection team evaluated the implementation of the approved fire protection program in selected risk
-significant areas with an emphasis on the procedures, equipment, fire barriers, and systems that ensure the post-fire capability to safely shutdown the plant.
Inspection Procedure 71111.05T requires the selection of three to five fire areas and one or more mitigating strategies for review. The inspection team used the fire hazards analysis section of the Wolf Creek Generating Station Individual Plant Examination of External Events to select the following three risk-significant fire areas (inspection samples) for review:
Fire Area Description A-8 Auxiliary Building 2000' Elevation
- General Area A-17 South Electrical Penetration Room A-21 Train B Control Room Ventilation Room The inspection team evaluated the licensee's fire protection program using the applicable requirements
, which include d the plant's technical specifications, Operating License Condition 2.C.(5), NRC safety evaluations, 10 CFR 50.48, and Branch Technical Position 9.5-1. The team also reviewed related documents that included the Updated Safety Analysis Report , Section 9.5; the fire hazards analysis; and the post
-fire safe shutdown analysis. Specific documents reviewed by the team are listed in the attachment.
Three fire area inspection samples and four mitigating strategy samples were completed.
.0 1 Protection of Safe Shutdown Capabilities
a. Inspection Scope
The team reviewed the piping and instrumentation diagrams, safe shutdown equipment list, safe shutdown design basis documents, and the post-fire safe shutdown analysis to verify that the licensee properly identified the components and systems necessary to achieve and maintain safe shutdown conditions for fires in the selected fire areas. The team observed walkdowns of the procedures used for achieving and maintaining safe shutdown in the event of a fire to verify that the procedures properly implemented the safe shutdown analysis provisions.
For each of the selected fire areas, the team reviewed the separation of redundant safe shutdown cables, equipment, and components located within the same fire area. The team also reviewed the licensee's method for meeting the requirements of 10 CFR 50.48 , Branch Technical Position 9.5-1, Appendix A
, and 10 CFR Part 50, Appendix R, Section III.G. Specifically, the team evaluated whether at least one post-fire safe shutdown success path remained free of fire damage in the event of a fire. In addition, the team verified that the licensee met applicabl e license commitments.
b. Findings
Introduction:
The team identified a Green non
-cited violation of License Condition 2.C.(5) for failure to implement and maintain in effect all provisions of the approved fire protection program. Specifically, the licensee failed to adequately evaluate the potential impacts on post-fire safe shutdown of two motor operated valves spuriously closing due to fire damage.
Description:
The licensee's post-fire safe shutdown analysis, Calculation XX-E-013, Revision 4, includes evaluations of power operated relief valves PCV
-455A and PCV-456A , and power operated relief valve block valves HV
-8000A and HV-8000B. Review of control circuits associated with power operated relief valve block valves HV
-8000A and HV-8000B identified the potential for the valves to spuriously close due to the fire damage during a control room fire. The licensee's post-fire safe shutdown analysis did not address spurious closure to these valves. The team identified three concerns that could impact the post-fire safe shutdown of the plant.
1) Control circuit fire damage includes conductor combinations wh i ch could energize the valve's closing coil while bypassing the valve's torque and limit switches. This scenario would keep the valve's motor energized after the valve was fully closed. The motor would develop elevated torque in the stalled condition compared to normal valve operation. The potential impact of such elevated torque on the valves has not been evaluated. A small fraction of motor operated valves are subject to damage at stall torque including potential loss of pressure boundary integrity. This could result in reactor coolant system leakage as the power operated relief valve block valves HV
-8000A and HV
-8000B are the first valves in lines connected to the pressurizer.
2) For a fire in the control room resulting in a control room evacuation, hot shutdown conditions would be established using Procedure OFN RP-017, "Control Room Evacuation," Revision 49A. Cold shutdown would be achieved using Procedure OFN RP-017A, "Hot Standby to Cold Shutdown from Outside the Control Room Due to Fire," Revision 11C. Procedure OFN RP
-017A installs temporary control circuit jumpers and manual electrical switches at an electrical panel to allow operation of two excess letdown valves and power operated relief valve PCV-456A. The power operated relief valve would be used to reduce reactor coolant system pressure during the cooldown. Spurious closure of power operated relief valve block valve HV
-8000B would isolate power operated relief valve PCV-456A. Procedure OFN RP
-017A does not address the potential for power operated relief valve block valve HV
-8000B being closed and no valve position indication or controls have been provided outside of the control room.
3) Normally during a cooldown, cold overpressure protection is provided by an automatic system
. The automatic system would not be available following a fire in the control room. Procedure OFN RP
-017A, Step 18, stations an operator at the temporary switch to manual ly operate power operated relief valve PCV-456A as directed by the operator at the auxiliary shutdown panel to provide cold overpressure protection when the cold leg temperature decreases below 375 °F. This function would not be effective if power operated relief valve block valve HV-8000B was closed. The licensee entered this issue into the corrective action program as Condition Reports 00116489 and 00116786.
The licensee established an hourly fire watch in the area of the control room behind the main control panel area as a compensatory measure. The control room main control panel area is continuously manned by operators. The licensee used the control room simulator to perform a cooldown from hot shutdown conditions to the temperature and pressure where the residual heat removal system could be initiated. The simulator personnel used only the systems and components credited to be available in Procedure OFN RP
-017A , and power operated relief valve P CV-456A was not utilized. The cooldown took an extended period of almost 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />. The plant was maintained in a safe condition throughout the cooldown.
Analysis.
The failure to adequate ly evaluate the impact of power operated relief valve block valves spuriously closing on post-fire safe shutdown was a performance deficiency. The performance deficiency was more than minor because it was associated with the protection against external events (fire) attribute of the Mitigating Systems cornerstone and it adversely affected the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences.
The team evaluated this finding using Inspection Manual Chapter 0609, Appendix F, "Fire Protection Significance Determination Process," dated September 20, 2013.
Because it affected the ability to reach and maintain safe shutdown conditions in case of a fire that led to control room evacuation and the Phase 2 methodology of Inspection Manual Chapter 0609, Appendix F, was not appropriate for this finding, a senior reactor analyst performed a Phase 3 evaluation to determine the risk significance.
The senior reactor analyst assigned a generic fire ignition frequency for the control room (FIF CR), which was slightly higher than the value in Calculation AN 029, "Control Room Fire Analysis," Revision 1. The analyst multiplied the fire ignition frequency by a severity factor (SF) and a non
-suppression probability indicating that operators failed to extinguish the fire within 20 minutes, assuming a 2
-minute detection that required a control room evacuation (NP CRE). The resulting control room evacuation frequency (F EVAC) was: F EVAC = FIF CR
- SF
- NP CRE = 1.09E-2/year
- 0.1
- 1.30E
-2 = 1.42E-5/year The control room had a total of 103 cabinets. The analyst determined that a single fire in four of these cabinets could lead to the spurious operation of a power operated relief valve block valve. Therefore, a bounding change in core damage frequency for a control room fire that leads to evacuation and the spurious operation of a power operated relief valve block valve (FEVAC+SPURIOUS) was determined to be:
FEVAC+SPURIOUS = F EVAC
- 4 / 103 = 1.42E-5/year
- 4 / 103 = 5.51 E-7/year This frequency was considered to be bounding since it assumed:
1) A fire in any of the applicable cabinets would cause the spurious operation of a power operated relief valve block valve 2) The conditional core damage probability given a control room fire with evacuation and the spurious operation of a power operated relief valve block valve was equal to one 3) The performance deficiency accounted for the entire change in core damage frequency (i.e., the baseline core damage frequency for this event was zero)
In accordance with the guidance in Inspection Manual Chapter 0609, Appendix H, "Containment Integrity Significance Determination Process
," dated May 6, 2004, the senior reactor analyst screened the performance deficiency for its potential risk contribution to large early release frequency since the bounding change in core damage frequency provided a risk significance estimate greater than 1E
-7/yr. Given that Wolf Creek has a large, dry containment and that control room evacuation sequences do not include steam generator tube ruptures or intersystem loss of coolant accidents, the analyst determined that this example was not significant with respect to large early release frequency. The analyst determined this finding was of very low risk significance (Green). There is no cro ss-cutting aspect associated with this finding since the performance deficiency is not reflective of present performance (i.e., the performance deficiency occurred more than three years ago).
Enforcement
- License Condition 2.C.(5) states, "The Operating Corporation shall maintain in effect all provisions of the approved fire protection program as described in the standardized nuclear unit power plant system plant (SNUPPS) Final Safety Analysis Report (FSAR)for the facility through Revision 17, the Wolf Creek site addendum through Revision 15, as approved in the Significant Event Report (SER) through Supplement 5, Amendment No. 189, Amendment No. 191, Amendment No. 193, Amendment No. 205, and Amendment No. 2 14." Updated Safety Analysis Report Appendix 9.5E compare s the fire protection program to 10 CFR 50, Appendix R, requirements. Appendix R
,Section III.L, "Alternative and Dedicated Shutdown Capability," requires the ability to achieve and maintain hot standby conditions and achieve cold shutdown conditions within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The comparison table, the licensee states: (1) The auxiliary shutdown panel provides a means of achieving and maintaining hot shutdown, and (2)cold shutdown can be achieved and maintained from outside the control room by additional manual operator actions at local control sites.
Contrary to the above, from initial operation to October 19, 2017, the licensee failed to fully implement the approved fire protection program. Specifically, the licensee failed to adequately evaluate the impact of the power operated relief valve block valves HV-8000A and HV
-8000B spuriously closing on post-fire safe shutdown and the impact on the ability to achieve and maintain hot standby conditions and achieve cold shutdown conditions within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
. Because this violation was of very low safety significance , has been entered into the corrective action program as Condition Reports 00116489 and 00116786, and the licensee has a fire watch in the control room as a compensatory measure until corrective actions can be taken
, this violation is being treated as a non-cited violation, consistent with Section 2.3.2.a of the NRC Enforcement Policy:
NCV 05000482/201 7 008-01, "Inadequate Evaluation of Spurious Valve Operation
."
.02 Passive Fire Protection
a. Inspection Scope
The team walked down accessible portions of the selected fire areas to observe the material condition and configuration of the installed fire area boundaries (including walls, fire doors
, and fire dampers)
, and verify that the electrical raceway fire barriers were appropriate for the fire hazards in the area. The team compared the installed configurations to the approved construction details, supporting fire tests, and applicable license commitments.
The team reviewed inspection records for a sample of penetration seals, fire doors, and fire dampers in the selected fire areas.
b. Findings
No findings were identified.
.03 Active Fire Protection
a. Inspection Scope
The team reviewed the design, maintenance, testing, and operation of the fire detection and suppression systems in the selected fire areas. The team verified the automatic detection systems and the manual and automatic suppression systems were installed, tested , and maintained in accordance with the National Fire Protection Association code of record or approved deviations
, and that each suppression system was appropriate for the hazards in the selected fire areas.
The team walked down accessible portions of the detection and suppression systems in the selected fire areas. The team also walked down major system support equipment in other areas (e.g., fire pumps and Halon supply systems) to assess the material condition of these systems and components.
The team reviewed the flow and pressure tests for the electric and diesel fire pumps to verify that the pumps met their design requirements. The team also reviewed the halon suppression functional tests to verify that the system capability met the design requirements. The team assessed the fire brigade capabilities by reviewing training and qualification records. The team also reviewed pre
-fire plans and smoke removal plans for the selected fire areas to determine if appropriate information was provided to fire brigade members and plant operators to identify safe shutdown equipment and instrumentation
, and to facilitate suppression of a fire that could impact post-fire safe shutdown capability.
The team observed an unannounced fire drill and subsequent drill critique on October 17, 2017, using the guidance contained in Inspection Procedure 71111.05AQ, "Fire Protection Annual/Quarterly
," dated September 30, 2010. The team observed fire brigade members fight a simulated fire in the turbine building. The team verified that the licensee identified problems, openly discussed them in a self
-critical manner at the drill debrief, and identified appropriate corrective actions. Specific attributes evaluated included: (1) proper wearing of turnout gear and self
-contained breathing apparatus; (2) proper use and layout of fire hoses; (3)employment of appropriate firefighting techniques; (4)sufficient firefi ghting equipment was brought to the scene; (5) effectiveness of fire brigade leader communications, command, and control; (6) search for victims and propagation of the fire into other areas; (7)smoke removal operations; (8)utilization of pre-planned strategies; (9)adherence to the pre
-planned drill scenario; and (10)drill objectives.
b. Findings
No findings were identified.
.0 4 Protection from Damage from Fire Suppression Activities
a. Inspection Scope
The team performed plant walkdowns and document reviews to verify that redundant trains of systems required for hot shutdown, which are located in the same fire area, would not be subject to damage from fire suppression activities or from the rupture or inadvertent operation of fire suppression systems. Specifically, the team verified:
A fire in one of the selected fire areas would not directly, through production of smoke, heat, or hot gases, cause activation of suppression systems that could potentially damage all redundant safe shutdown trains
.
A fire in one of the selected fire areas
, or the inadvertent actuation or rupture of a fire suppression system would not directly cause damage to all redundant trains (e.g., sprinkler-caused flooding of other than the locally affected train)
.
Adequate drainage was provided in areas protected by water suppression systems.
b. Findings
No findings were identified.
.0 5 Alternative Shutdown Capability
a. Inspection Scope
Review of Methodology The team reviewed the safe shutdown analysis, operating procedures, piping and instrumentation drawings, electrical drawings, the Updated Safety Analysis Report, and other supporting documents to verify that hot and cold shutdown could be achieved and maintained from outside the control room for fires that require evacuation of the control room , with or without offsite power available.
The team conducted plant walkdowns to verify that the plant configuration was consistent with the description contained in the safe shutdown and fire hazards analyses. The team focused on ensuring the adequacy of systems selected for reactivity control, reactor coolant makeup, reactor decay heat removal, process monitoring instrumentation, and support systems functions.
The team also verified that the systems and components credited for shutdown would remain free from fire damage. Finally, the team verified that the transfer of control from the control room to the alternative shutdown location would not be affected by fire-induced circuit faults (e.g., by the provision of separate fuses and power supplies for alternative shutdown control circuits).
Review of Operational Implementation The team verified that licensed and non
-licensed operators received training on alternative shutdown procedures. The team also verified that sufficient personnel to perform an alternative shutdown were trained and available onsite at all times, exclusive of those assigned as fire brigade members.
The team performed a timed walkdown of the alternative shutdown procedure with licensed and non
-licensed operators to determine the adequacy of the procedure. The team verified that the operators could reasonably be expected to perform specific actions within the time required to maintain plant parameters within specified limits. Time critical actions that were verified included restoring electrical power, establishing control at the remote shutdown and local shutdown panels, establishing reactor coolant makeup, and establishing decay heat removal.
The team also reviewed the periodic testing of the alternative shutdown transfer capability and instrumentation and control functions to verify that the tests were adequate to demonstrate the functionality of the alternative shutdown capability.
b. Findings
No findings were identified.
.0 6 Circuit Analysis
a. Inspection Scope
The team reviewed the post-fire safe shutdown analysis to verify that the licensee identified the circuits that may impact the ability to achieve and maintain safe shutdown. The team verified, on a sample basis, that the licensee properly identified the cables for equipment required to achieve and maintain hot shutdown conditions in the event of a fire in the selected fire areas. The team verified that these cables were either adequately protected from the potentially adverse effects of fire damage or were analyzed to show that fire
-induced circuit faults (e.g., hot shorts, open circuits, and shorts to ground) would not prevent safe shutdown.
The team's evaluation focused on the cables of selected components from the auxiliary feedwater, chemical volume and control, essential service water, main steam atmospheric vent, and main steam isolation systems. For the sample of components selected, the team reviewed electrical elementary and block diagrams
, and identified power, control, and instrument cables necessary to support their operation. In addition, the team reviewed cable routing information to verify that fire protection features were in place as needed to satisfy the separation requirements specified in the fire protection license basis. Specific components reviewed by the team are listed in the attachment.
b. Findings
No findings were identified.
.07 Communications
a. Inspection Scope
The team inspected the contents of designated emergency storage lockers and reviewed the alternative shutdown procedure to verify that portable radio communications and fixed emergency communications systems were available, operable, and adequate for the performance of designated activities. The team verified the capability of the communication systems to support the operators in the conduct and coordination of their required actions. The team also verified that the design and location of communications equipment such as repeaters and transmitters would not cause a loss of communications during a fire. The team discussed system design, testing, and maintenance with the system engineer.
b. Findings
No findings were identified.
.0 8 Emergency Lighting
a. Inspection Scope
The team reviewed the portion of the emergency lighting system required for alternative shutdown to verify that it was adequate to support the performance of manual actions required to achieve and maintain hot shutdown conditions
, and to illuminate access and egress routes to the areas where manual actions would be required. The team evaluated the locations and positioning of the emergency lights during a walkdown of the alternative shutdown procedure.
The team verified that the licensee installed emergency lights with an 8
-hour capacity, maintained the emergency light batteries in accordance with manufacturer recommendations, and tested and performed maintenance in accordance with plant procedures and industry practices.
b. Findings
Introduction.
The team identified a Green non-cited violation of License Condition 2.C.(5) for the failure to provide emergency lighting along alternate routes potentially taken by plant operators performing a post-fire safe shutdown following a control room evacuation due to fire.
Specifically, the licensee does not train operators performing a post-fire safe shutdown to use the routes provided with emergency lighting.
Description.
During a fire in the control room requiring evacuation, the operators would enter Procedure OFN RP
-017, "Control Room Evacuation," Revision 49A. The procedure directed operators to perform local actions in the plant and the auxiliary shutdown panel to bring the plant to a stable, hot standby condition. This procedure was required to be implemented with and without offsite power available. Without offsite power, the normal plant lighting would be lost and the operators would be required to rely on emergency lighting units. Title 10 CFR Part 50, Appendix R, Section III.J requires emergency lighting units
, with at least an 8
-hour battery power supply
, be provided in all areas needed for operation of safe shutdown equipment
, and in access and egress routes thereto. The licensee provided 8-hour battery powered emergency lighting for all required safe shutdown components and had demonstrated using plant lighting drawings to have emergency lighting units along credited access and egress routes for the safe shutdown components for each OFN R P-017 operator attachment. The plant operators were unaware of these credited access and egress routes because the licensee did not provide training to the plant operators to take the credited, lighted paths , and allowed the operators to take alternate routes to access safe shutdown components.
During a control room fire requiring evacuation and coincident with a loss of offsite power, the operators would be required to implement Procedure OFN RP-017 using the emergency lighting provided t o satisfy the requirements of Appendix R,Section III.J. The operators would be expected to traverse these designated lighted paths to ensure the plant is brought to a safe shutdown condition within the times assumed in the thermal-hydraulic analysis, SA 006, "RETRAN-3D Post-Fire Safe Shutdown (PFSSD) Consequence Evaluation for a Postulated Control Room Fire," Revision 3. Because the licensee did not train the operators on where these credited, lighted routes are located, the licensee could not ensure the time
-critical operator actions can be completed during an actual control room evacuation due to fire, coincident with a loss of offsite power and normal lighting. The licensee did not provide 8
-hour battery powered emergency lighting along the alternate routes taken by the operators during walk downs of Procedure OFN RP-017. The licensee entered this issue into the corrective action program as Condition Report 00116410 to address the training of the operators on the lighted routes or to provide emergency lighting along these alternate routes that meet 10 CFR Part 50, Appendix R, Section III.J, to ensure the procedure was implemented in the required times.
Analysis.
The failure to provide 8-hour emergency lights along all access and egress paths operators are allowed to take while performing a post-fire safe shutdown is a performance deficiency. The performance deficiency was more than minor because it was associated with the protection against external factors attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. The team evaluated this finding using Inspection Manual Chapter 0609, Appendix F, "Fire Protection Significance Determination Process," dated September 20, 2013, because it affects the ability to reach and maintain safe shutdown conditions in case of a fire. The team assigned the finding to the post-fire safe shutdown category since it impacted the alternate shutdown element. The issue screened to Green in Inspection Manual Chapter 0609, Appendix F, Attachment 1, Question 1.3.1 A
, because the operators are required to carry flashlights during normal day-to-day operations. Specifically, the team had reasonable assurance that the operators would be able to complete the evacuation procedure using handheld flashlights to access safe shutdown equipment. The finding is assigned a cross
-cutting aspect in the area of huma n performance, associated with training, because the operators are not being trained on the access and egress routes that are provided with 8-hour emergency lights during implementation of the control room evacuation procedure due to fire, to ensure the time critical actions can be met (H.9).
Enforcement.
License Condition 2.C.(5) states , "The Operating Corporation shall maintain in effect all provisions of the approved fire protection program as described in the SNUPPS Final Safety Analysis Report for the facility through Revision 17, the Wolf Creek site addendum through Revision 15, as approved in the SER through Supplement 5, Amendment No. 189, Amendment No. 191, Amendment No. 193, Amendment No. 205, and Amendment No. 214.
" Updated Safety Analysis Report , Section 9.5.3.2.3
, "Emergency Lighting System," states in part, "In the event of a control room evacuation, the emergency lighting provides access to the areas and lighting within the areas where operator actions are required. These provisions meet the requirements of 10 CFR 50, Appendix R, Paragraph III.J.
" Title 10 Part 50, Appendix R,Section III.J requires emergency lighting units
, with at least an 8-hour battery power supply
, be provided in all areas needed for operation of safe shutdown equipment
, and in access and egress routes thereto.
Contrary to the above, the licensee failed to provide emergency lighting along all access and egress routes to safe shutdown equipment. Specifically, prior to October 2017 Wolf Creek Generating Station did not provide emergency lighting along the access routes operators took when performing Procedure OFN RP
-017, "Control Room Evacuation," Revision 49A.
Because this finding was of very low safety significance and has been entered into the licensee's corrective action program as Condition Report 00116410, and the licensee was evaluating training to ensure operators took the credited access and egress routes , this violation is being treated as a non-cited violation consistent with Section 2.3.2.a of the NRC Enforcement Policy:
-02 , "Failure to Provide Adequate Emergency Lighting."
.0 9 Cold Shutdown Repairs
a. Inspection Scope
The team verified that the licensee identified repairs needed to reach and maintain cold shutdown and had dedicated repair procedures, equipment, and materials to accomplish the se repairs. Using these procedures, the team evaluated whether these components could be repaired in time to bring the plant to cold shutdown within the time frames specified in their design and licensing bases. The team verified that the repair equipment, components, tools, and materials needed for the repairs were available and accessible onsite.
b. Findings
No findings were identified.
.1 0 Compensatory Measures
a. Inspection Scope
The team verified that compensatory measures were implemented for out-of-service, degraded, or inoperable fire protection and post-fire safe shutdown equipment, systems, or features (e.g., detection and suppression systems and equipment; passive fire barriers; or pumps, valves, or electrical devices providing safe shutdown functions). The team also verified that the short
-term compensatory measures compensated for the degraded function or feature until appropriate corrective action could be taken
, and that the licensee was effective in returning the equipment to service in a reasonable period of time.
b. Findings
No findings were identified.
.1 1 Review and Documentation of Fire Protection Program Changes
a. Inspection Scope
The team reviewed changes made to the approved fire protection program since November 6
, 2014. The team verified that the changes did not constitute an adverse effect on the ability to safely shutdown.
b. Findings
No findings were identified.
.1 2 Control of Transient Combustibles and Ignition Sources
a. Inspection Scope
The team reviewed the licensee's approved fire protection program, implementing procedures and programs
, for the control of ignition sources and transient combustibles. The team assessed the licensee's effectiveness in preventing fires and in controlling combustible loading within limits established in the fire hazards analysis. The team performed plant walkdowns to independently verify that transient combustibles and ignition sources were being properly controlled in accordance with the administrative controls.
b. Findings
No findings were identified.
.13 Alternative Mitigation Strategy Inspection Activities
a. Inspection Scope
The team reviewed the licensee's implementation of guidance and strategies intended to maintain or restore core, containment, and spent fuel pool cooling capabilities under the circumstances associated with the potential loss of large areas of the plant due to explosions or fire as required by 10 CFR 50.54(hh)(2).
The team verified that the licensee implemented and maintain ed adequate procedures, maintain ed and test ed equipment necessary to properly implement the strategies, and ensure d station personnel were knowledgeable and capable of implementing the procedures. The team performed a visual inspection of portable equipment used to implement the strategy to ensure the availability and material readiness of the equipment, including the adequacy of portable pump trailer hitch attachments, and verify the availability of onsite vehicles capable of towing the portable pump. The team assessed the offsite ability to obtain fuel for the portable pump and foam used for firefighting efforts. The strategy and procedure selected for this inspection sample included: Attachment P - Manual Operation of the Turbine
-Driven Auxiliary Feedwater Pump Attachment R - Auxiliary Feedwater Alternate Suction from Fire Protection Standpipe Attachment V - Containment Flood Using Fire Protection Hydrant W - Containment Flood Using Fire Truck Four mitigating strategy samples were completed.
b. Findings
No findings were identified.
OTHER ACTIVITIES
[OA]
4OA2 Problem Identification and Resolution
Corrective Actions for Fire Protection Deficiencies
a. Inspection Scope
The team selected a sample of condition reports associated with the licensee's fire protection program to verify that the licensee had an appropriate threshold for identifying deficiencies. The team reviewed the corrective actions proposed and implemented to verify that they were effective in correcting identified deficiencies.
The team evaluated the quality of recent engineering evaluations through a review of condition reports , calculations, and other documents during the inspection.
b. Findings
No findings were identified.
4OA3 Follow-up of Events and Notices of Enforcement Discretion
(Closed) Licensee Event Report 05000 482/2014-005-00: Post-Fire Safe Shutdown Latent Design Issue May Impact Ability to Achieve Safe Shutdown
. This licensee event report documented that during a review of external operating experience, the licensee identified that portions of the control circuits for the turbine generator direct current emergency lube oil pump and the emergency direct current seal oil pump were not properly fused to prevent overload and possible secondary fires that could impact the ability to achieve post
-fire safe shutdown. The licensee determined that the control circuit design for the turbine generator direct current emergency lube oil pump and the emergency direct current seal oil pump needed to be considered for post-fire safe shutdown impact. The licensee documented the issue in Condition Report 88168. As an immediate corrective action and as a compensatory measure, the licensee established roving fire watches in the fire areas containing the circuits. The licensee developed Change Package Engineering Disposition, 014816, which will provide permanent protection by installing control power fuses on the turbine generator direct current emergency lube oil pump and the emergency direct current seal oil pump circuit s. The licensee plans to install the design change in the spring of 2018 during outage.
The team performed a detailed review of the information in this license event report, the condition report, design documents, and drawings related to the planned circuit modifications. The team discussed the issue with plant personnel to gain an understanding of the actions taken to address the issue. The team determined the modification will correct the deficiency. The team verified that the licensee established appropriate compensatory measures, corrective actions, and planned modifications.
No violation of NRC requirements were identified.
Findings No findings were identified.
4OA6 Meetings, Including Exit
Exit Meeting Summary
The team presented the inspection results to Mr. D. Mand, Director Engineering, and other members of the licensee staff at an exit meeting on October 19, 2017. The licensee acknowledged the findings presented.
The inspectors verified that no proprietary information was retained by the inspectors or documented in this report.
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- D. Bowers, Manager Maintenance
- M. Boyce, Director Engineering Projects
- A. Broyles, Manager Information Services
- A. Bush, Information Services Technician
- K. Clark, Fire Protection Technician
- J. Cuffe, Supervisor Radiation Protection
- G. Earhart, Fire Protection Engineer
- J. Edwards, Manager Operations
- R. Fincher, Manager Quality
- B. Fox, Contract Fire Protection Engineer
- K. Gibbon, Fire Protection Engineer
- C. Hafenstine, Manager Nuclear and Regulatory Affairs
- D. Hall, Manager Strategic Projects
- P. Herrman, Manager Design Engineering
- R. Jung, Fire Brigade Instructor
- J. Keating, Reactor Operator, Operations Support
- J. Knust, Licensing
- D. Mand, Director Engineering
- J. McCoy, Vice President Engineering
- N. Mefford, Senior Nuclear Station Operator
- A. Mey er, Reactor Operator
- W. Mulenburg, Supervisor Licensing
- M. Parsons, Senior Nuclear Station Operator
- M. Payne, Reactor Operator
- G. Pendergrass, Manager Performance Improvement
- E. Peterson, Employee Concerns Program Coordinator
- M. Skiles, Manager Security
- T. Slenker, Supervisor Operations Support
- S. Smith, Plant Manager
- J. Strahm, Senior Reactor Operator
- J. Suter, Fire Protection Supervisor
- G. Turner, Reactor Operator
- W. Wilkins, Fire Protection
Engineer
NRC Personnel
- D. Dodson, Senior Resident Inspector
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened and Closed
-01 NCV Inadequate
Evaluation of Spurious Valve Operation (Section 1R05.01)
-0 2 NCV Failure to Provide Adequate Emergency Lighting
(Section 1R05.08)
LIST OF DOCUMENTS REVIEWED
Cable Routing Data Components
- BBPCV455A BBPCV456A BBHV8000A BBHV8000B BGLCV0112C
- NB0209 NB0212
Calculations
- Number Title Revision E-1F9905 Fire Hazard Analysis
- FL-03 Flooding of Individual Auxiliary Bldg Rooms 1
- KC-M-006 Water-Based Fire Protection System
& Standpipe Hydraulic Calculation
- WCNOC-CP-002 Wolf Creek Fire Protection Transient Analysis With
- RETRAN-3D 1
- XX-E-013 PFSSD Analysis 4
- Completed Surveillance Tests Number Title Date
- MEC-004 Fire Extinguisher Inspections (Special Scope
- ESW & Power Block)
- July 6, 2015
- MEC-004 Fire Extinguisher Inspections (Special Scope
- ESW & Power Block)
- September 12, 2016
- MEC-004 Fire Extinguisher Inspections (Special Scope
- ESW & Power Block)
- April 24, 2017 STN
- FP-204 Fire Protection System C
-Factor Test September 14, 2009 STN
- FP-204 Fire Protection System C
-Factor Test June 18, 2015
- Completed Surveillance Tests Number Title Date STN
- Wet-Pipe October 19, 2016 STN
- FP-208 Hose Rack Visual Inspection July 6, 2017 STN
- FP-209 Fire Pump Performance
& Sequential Start Test June 20, 2017 STN
- FP-211 Diesel Fire Pump
- 1FP01PB Monthly Operation
& Fuel Level Check June 6, 2016 STN
- FP-211 Diesel Fire Pump
- 1FP01PB Monthly Operation
& Fuel Level Check August 29, 2016 STN
- FP-211 Diesel Fire Pump
- 1FP01PB Monthly Operation
& Fuel Level Check April 28, 2017 STN
- FP-211 Diesel Fire Pump
- 1FP01PB Monthly Operation
& Fuel Level Check September 28, 2017 STN
- FP-212 Electric Motor
-Driven Fire Pump
- 1FP01PA Monthly Operation June 20, 2015 STN
- FP-212 Electric Motor
-Driven Fire Pump
- 1FP01PA Monthly Operation August 16, 2016 STN
- FP-212 Electric Motor
-Driven Fire Pump
- 1FP01PA Monthly Operation April 11, 2017 STN
- FP-212 Electric Motor
-Driven Fire Pump
- 1FP01PA Monthly Operation September 14, 2017 STN
- FP-216 Spray & Sprinkler System Functional Testing
- Pre-Action October 21, 2016 STN
- FP-225 Fire Barrier Inspection May 23, 2016 STN
- FP-404A Halon Main Bank Tank Weight
& Pressure Checks September 23, 2016 STN F P-404B Halon Reserve Bank Tank Weight
& Pressure Checks August 10, 2017 STN
- FP-405B Halon System South Electrical Penetration Room (KC 226) May 3, 2016
- Completed Surveillance Tests Number Title Date STN
& Hose Reracking February 3, 2017 STS
- RP-004 Auxiliary Shutdown Panel
& Control Switch Test November 15, 20
- RP-004 Auxiliary Shutdown Panel
& Control Switch Test May 6, 20 15 STN
- FP-431 Fire Hose Station Valve Operability
& Hose Replacement/Hydro September 23, 20 15 STN
- FP-440 Fire Door Visual Inspection August 3, 20
- STN
& Drop Test July 28, 20
- STN
- FP-452 Fire Barrier Penetration Seals Inspection April 17, 20
- STN
- FP-600 Fire Pump Diesel Fuel Storage Tank September 14, 20 17 STN
- FP-817A Trip Actuating Device Operational Test for Bechtel Zones 100, 103, 104, 105, 106, 107, 112, 113, & 114 August 8, 20
- STN
- FP-817D Trip Actuating Device Operational Test for Bechtel Zones 108, 109, 110, 101, 117, 118, & 119 January 4, 20
Condition Reports
- 98488
- 00116392*
- 00116315*
- 00116369*
- 00116410*
- 00116408*
- 00116406*
- 00116405*
- 00116404*
- 00116411*
- 00116419*
- 00116418*
- 00116483
- 00116425*
- 00116423*
- 00116420*
- 00116489*
- 00105031
- 00105032
- 00105003
- 00105034
- 00113882
- 00115586
- 00116830* *Issued as a result of inspection activities.
Drawings
- Number Title Revision
- CD-7W Condensate Transfer
& Storage System, Condensate Storage Tank Level
- CD-170W Sh2 of 2
- Auxiliary Feedwater System Auxiliary Feedpump Suction Pressure Turbine Driven Pump
- E-1F1301 Fire Detection/Protection System
- Auxiliary Bldg
- EL 2000'-0" 6 E-1F1401 Fire Detection/Protection System
- Auxiliary Bldg
- EL 2026'-0" 5
Drawings
- Number Title Revision E-1F1501 Fire Detection/Protection System
- Auxiliary Bldg
- EL 2047'-6" 2 E-1F9301 PFSSD Logic Diagram Reactor Coolant Makeup Function
- E-1L8900 Lighting Notes, Symbols
, & Details 78 E-1C8900 Communication System Notes, Symbols, & Details
- E-1L1101 Lighting, Grounding, & Communications Auxiliary & Reactor Bldgs Plan 1974'
-0" 13 E-1L1202 Lighting, Grounding, &
- Communications Auxiliary & Reactor Bldgs Plan 1988'
-0" & 2013'-0" 06 E-1L1303 Lighting, Grounding, & Communications Auxiliary & Reactor Bldgs Plan 2000'
-0" 33 E-1L1404 Lighting, Grounding, & Communications Auxiliary & Reactor Bldgs Plan 2026'
-0" 17 E-1L1505 Lighting, Grounding, & Communications Auxiliary & Reactor Bldgs Plan 20 47'-6" 16 E-1L3101 Lighting, Grounding, & Communications Comm. Corr, Control & Diesel Generator Bldgs Plan 1974'
-0" & 1984'-0" 23 E-1L3302 Lighting, Grounding, & Communications Comm. Corr, Control & Diesel Generator Bldgs Plan
- 2000'-0" & 2016'-0" 21 E-1L3604 Lighting, Grounding, & Communications Comm. Corr, Control & Diesel Generator Bldgs Plan
- 2047'-6" 30 E-1L4302 Lighting, Grounding, & Communications Turbine Bldg Ground Floor Plan 2000'-0" 11 E-1L4401 Lighting, Grounding, & Communications Turbine Bldg Mezzanine Floor Plan 2033
'-0" 11 E-1L4402 Lighting, Grounding, & Communications Turbine Bldg Mezzanine Floor Plan 2033'
-0" 06 E-1RI321(Q) Raceway Plan Auxiliary Bldg Area 2 EL. 2000'
-0" 2 E-1R1341 Raceway Plan Auxiliary Bldg Area 4 EL. 2000'
-0" 03
Drawings
- Number Title Revision E-1R1431 Raceway Plan Auxiliary Bldg Area-3 EL. 2026'
-0" 03 E-1R1433A Exposed Conduit Auxiliary Bldg Area-3 EL. 2026'
-0" 12 E-1R1433C Exposed Conduit Aux Bldg Area 3 EL 2026
- E-1R1901 Raceway Sects. & Dets Auxiliary Bldg 0 E-13AL07B Schematic Diagram Instrumentation & Alarms (SH. 2B)
- E-13AP02 Schematic Diagram Condensate Transfer & Storage Alarms & Instrumentation
- E-13BB40 Schematic Diagram Pressurizer Power Relief Valves
- E-13BG12A Schematic Diagram Volume Control Tank Outlet Isolation Valve 8 E-13KJ03A Schematic Diagram Diesel Gen. KKJ01B Engine Control (Start/Stop Circuit)
- E-13NB14 Class IE Bus NB02 Feeder B
rkr. 152NB0209
- E-13NB15 Schematic Diagram Class IE Bus NB02 Feeder Brkr. 152NB0212
- M-0023, Sheet Piping & Instrumentation Diagram Fire Protection System (FP)
- M-0023, Sheet Piping & Instrumentation Diagram Fire Protection System (FP)
- M-12AB01, Sheet 1
- Piping & Instrumentation Diagram Main Steam System
- M-12AB02 Piping & Instrumentation Diagram Main Steam System
- M-12AL01, Sheet 1
- Piping & Instrumentation Diagram Auxiliary Feedwater
- System 28 M-12BB01, Sheet 1
- Piping & Instrumentation Diagram Reactor Coolant System
- M-12BB02 Piping & Instrumentation Diagram Reactor Coolant System
- M-12BG01 Piping & Instrumentation Diagram Chemical
& Volume Control System 19
Drawings
- Number Title Revision M-12BG02 Piping & Instrumentation Diagram Chemical
& Volume Control System 18 M-12BG03 Piping & Instrumentation Diagram Chemical
& Volume Control System 48 M-12BG04 Piping & Instrumentation Diagram Chemical
& Volume Control System 07 M-12BG05 Piping & Instrumentation Diagram Chemical
& Volume Control System 24 M-12BM01 Piping & Instrumentation Diagram Steam Generator Blowdown System
- M-12BN01 Piping & Instrumentation Diagram Borated Refueling Water Storage System
- M-12BN01 Piping & Instrumentation Diagram Steam Generator Blowdown System
- M-12EF01 Piping & Instrumentation Diagram Essential Service Water System 29 M-12EF02 Piping & Instrumentation Diagram Essential Service Water System 42 M-12EG01 Piping & Instrumentation Component Cooling Water System
- M-12EG02 Piping & Instrumentation Component Cooling Water System
- M-12EG03 Piping & Instrumentation Component Cooling Water System
- M-12KC01 Piping & Instrumentation Diagram Fire Protection Turbine Bldg 20 M-12KC02 Piping & Instrumentation Diagram Fire Protection
- M-12KC03 Piping & Instrumentation Diagram Fire Protection
- M-12KC05 Piping & Instrumentation Diagram Fire Protection
- M-650A-00006 North & South Area Cable Chases
- Auxiliary Bldg W08
Drawings
- Number Title Revision M-650A-00047 Lower Cable Spreading Room Area EL 2032'
-0" Pre-action System W10 M-650A-00052 Auxiliary Bldg Cable Trays EL 2000'
-0" W08 M-658-00058 Electrical Penetration Room #1 (South Penetration) Auxiliary Bldg
- EL 2026'-0" W04
- WIP-E-13CB03-002-A-1 Schematic Diagram Emergency Bearing Oil Pump
- WIP-E-13CD02-003-A-1 Schematic Diagram Emergency Seal Oil Pump 00
- WIP-E-13CD04-002-A-1 Schematic Diagram Hydrogen Seal Oil Alarms
- WIP-E-13CD05-001-A-1 Schematic Diagram Emergency Seal Oil Pump
- WIP-M-830-00015-W12-A-1 Outline Schematic & Connection Diagram for
- IC-4061-TI D.C. Magnetic Starter
- WIP-M-840-00009-W13-A-1 Schematic Diagram (Hydrogen
& Stator Cooling)
- 8025-C-KG1202 Site Plan 57
- Engineering Information Records Number Title Revision E-1F9915 Design Basis Document for ORN RP
-017, Control Room Evacuation
- SA-08-006
- RETRAN-3D PFSSD Consequence Evaluation for a Postulated Control Room Fire
- E-1L8900 Lighting Notes, Symbols, & Details
- E-1C8900 Communication Notes, Symbols, & Details
Miscellaneous Documents
- Number Title Revision/Date
- AP 10-106 Fire Areas
- 8, 17, & 21 Fire Preplans
- 18A E-1F9900 PFSSD Operator Manual Actions
Miscellaneous Documents
- Number Title Revision/Date E-1F9910 PFSSD Area Analysis
- E-1F9915 Design Basis Document for Procedure OFN RP
-017 9 EPRI
- TR-106826 Battery Performance Monitoring by Internal Ohmic Measurements December 1996 Lesson Plan LO1732427 OFN
- RP-017, Control Room Evacuation
- 013 Lesson Plan LR5002020 OFN
- RP-017 SRO/RO Actions
- 2 Lesson Plan
- NFPA 25 - 2002
- St andard for the Inspection, Testing, & Maintenance of Water-Based Fire Protection Systems
- NRC Letter Singal to Sunseri Wolf Creek Generating Station
- Issuance of Amendment RE:
- License Amendment Request for Use of Fire
-Resistive Electric Cable
(TAC No. ME2966) November 30, 2010 NRC Letter Singal to Sunseri Wolf Creek Generating Station
- Issuance of Amendment RE:
- Deviation From Fire Protection Requirements (TAC No. ME0797)
- December 16, 2010 NRC Letter Singal to Sunseri Wolf Creek Generating Station
- Issuance of Amendment RE:
- Removing High/Low Pressure Designation From the Pressurizer Power
-Operated Relief Valves (TAC No. ME3766)
- March 9, 2011 NRC Letter Lyon to Sunseri Wolf Creek Generating Station
- Issuance of Amendment RE:
- Deviation From Fire Protection Requirements for Volume Control Outlet Valves
- August 23, 2013 NRC Letter Lyon to Heflin Wolf Creek Generating Station
- Issuance of Amendment RE:
- Revise the Fire Protection Program Related to Alternative Shutdown Capability
- September 11, 2015
Miscellaneous Documents
- Number Title Revision/Date 2001
- QH-2017-1504 Fire Protection Program Quick Hit Assessment Report
- USAR Appendix 9.5A Design Comparison to Regulatory Positions of Regulatory Guide 1.120, Revision 1, dated November 1977
titled , "Fire Protection Guidelines for Nuclear Power Plants
" 30 USAR Appendix 9.5B Fire Hazards Analysis
- CFR 50 Appendix R
- USAR Section
- 9.5.1 Fire Protection Systems
- WCNOC-171 PFSSD Associated Circuits Study List of fire protection codes committed to by Wolf Creek
- List of modifications reviewed by fire protection personnel since last triennial List of deviations from the fire codes Maintenance Rule performance criteria
& system status
- Wolf Creek Fire Protection Program Regulatory Bases 4
Procedures
- Number Title Revision
- AI 26A-003 Regulatory Evaluations (Other Than 10 CFR 50.59)
- AP 05-001 Change Package Planning
& Implementation
- AP 05-005 Design, Implementation, & Configuration Control of Modifications
- AP 10-100 Fire Protection Program
- 20A
Procedures
- Number Title Revision
- AP 10-102 Control of Combustible Materials
- AP 10-103 Fire Protection Impairment Control
- AP 10-105 Fire Protection Training
& Drills 22
& Adherence 42A
& Generation Risk Assessment
- EDMG-001 Extensive Damage Mitigation Guideline (EDMG)
- EDMG-T01 EDMG Tool Box
- IP-ENG-001 Standard Design Process
- MPE
- BA-010 Preventive Maintenance on Teledyne Emergency Lighting 26 OFN
- KC-016 Fire Response
- OFN
- RP-017 Control Room Evacuation
- 49A OFN
- RP-017A Hot Standby to Cold Shutdown from Outside the Control Room Due to Fire
- 11C STN
- GP-009 Emergency Radio
& Equipment Check
& Verification
Vendor Document
- Number Title Revision H-409B-28 Motorola
- MCS 2000 Models II & III User Guide
- W01
Work Orders
- 13-366874-000 13-366880-000 14-395892-000 14-396226-000 15-408746-000 15-408746-050 15-408746-051 15-408746-054 15-408746-055 15-408746-064 15-408746-073 15-408746-080 5-409192-0001 16-117085-000 16-117085-000 16-410063-000 16-411189-000 16-412934-00 16-413319-000 16-414877-000 16-416416-000 16-417181-000 16-417458-000 16-417777-001 16-418207-001 16-418842-000 16-420346-000 16-420347-000 16-420377-000 16-420378-000 16-420614-000 16-420670-000 16-420703-000 17-422275-000 17-422280-000 17-423414-000 17-420951-000 17-426953-000 17-426954-000
- SUNSI Review By:
- JMM ADAMS
- Yes
- No Publicly Available Non-Publicly Available Non-Sensitive
- Sensitive Keyword:
- NRC-002 OFFICE DRS/EB2 DRS/EB2 DRS/EB2 DRS/EB2 DRS/PSB2 BC:DRP/B BC:DRS/EB2
- NAME BCorrell SMakor GPick JMateychick
- DLoveless NTaylor GWerner SIGNATURE /RA/ /RA/ /RA/ /RA/ /RA/ /RA - D Proulx Acting for/ /RA/ DATE 11/9/17 11/9/17 11/09/17 11/08/2017
- 11/14/2017
- 11/20/17 11/20/2017