05000482/FIN-2011002-14

Finding

Title

Licensee-Identified Violation

Description

Technical Specification Table 3.3.2.1, function 8.a, requires two trains of the P-4 interlock to be operable in Modes 1, 2, and 3. Function 8.a does not provide a required action for both trains of engineered safety features actuation system interlocks inoperable. Wolf Creek Technical Specification 3.0.3 requires the plant to be in Mode 4 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> when there is no required action specified for a limiting condition of operation that cannot be met. Contrary to the above, with both channels of the P-4 input to the Turbine Trip function defeated in Mode 3, Wolf Creek did not take action to place the unit in Mode 4 on November 6-8, 2006, May 10, 2008, April 30, 2009, and November 18, 2009. Using Inspection Manual Chapter 0609.04, Phase 1 Initial Screening and Characterization of Findings, the issue screened to a Phase 2 significance determination because it involved an actual loss of safety function. A Phase 2 significance determination could not be performed using the Risk Informed Inspection Notebook for Wolf Creek Generating Station since the pre-solved worksheet did not address the P-4 interlock. Using a Phase 3 analysis, a senior reactor analyst calculated the core damage probability to be less than 1E-7 per year, or of very low safety significance (Green). This issue was entered in the licensees corrective action program as Condition Report 23108.

14
Site:	Wolf Creek
Report	IR 05000482/2011002 Section 4OA7
Date counted	Mar 31, 2011 (2011Q1)
Type:	NCV: Green
cornerstone	Mitigating Systems
Identified by:	Licensee-identified
Inspection Procedure:
Inspectors (proximate)	G Guerra C Smith L Carson G Miller B Tindell C Long C Peabody A Fairbanks D Reinert C Alldredge
INPO aspect
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v • d • e

Finding - Wolf Creek - IR 05000482/2011002

1(0)2(14)3(12)4(9)5(6)6(2)7(6)8(0)9(2)402(0)403(0)25(0)

IR 05000482/2011002: 1 2 3 4 5 6 7 8 9 10 11 12 13 14

Finding List (Wolf Creek) @ 2011Q1

CCA Matrix: 2011Q1

	Q	CCA	Title
05000482/FIN-2010004-02	2010Q3	H.7	Failure to Correct Degraded Vital Switchgear Cooler Wiring
05000482/FIN-2010006-09	2010Q3	P.3	Failure to Translate Design Information into a Procedure
05000482/FIN-2010006-08	2010Q3	P.2	Notice of Unusual Event Due to Loss of Both Emergency Diesel Generators
05000482/FIN-2010006-07	2010Q3	P.1 P.1(a)	Failure to Determine if a Deficiency Existed in the Ultimate Heat Sink
05000482/FIN-2010006-05	2010Q3	P.2	Failure to Perform Adequate Evaluation for Significant Conditions
05000482/FIN-2010006-04	2010Q3	H.7	Failure to Update an Operability Evaluation
05000482/FIN-2010006-03	2010Q3	P.1 P.1(a)	Failure to Adequately Monitor Control Room Deficiencies
05000482/FIN-2010006-02	2010Q3	P.3	Unqualified Scaffolding Erected Near Safety-Related Equipment
05000482/FIN-2010006-01	2010Q3	H.7	Failure to Resolve Degraded Conditions in a Timely Manner
05000482/FIN-2010004-01	2010Q3		Failure to Establish Conditions to Open a Main Steam Isolation Value that Resulted in a Feedwater Isolation
05000482/FIN-2010005-07	2010Q4	P.1	Failure to Have Adequate Procedures for Meteorological Monitoring
05000482/FIN-2010005-05	2010Q4	P.1	Failure to Identify Boric Acid Leak on Instrument Lines to Reactor Coolant System
05000482/FIN-2010005-06	2010Q4	H.12	Failure to Have Procedures to Prevent Draining Radioactive Systems into Nonradioactive Systems
05000482/FIN-2010005-11	2010Q4	H.1	Inadequate Simulation Facility Fidelity
05000482/FIN-2010005-08	2010Q4	P.5	Inadequate Procedures for Establishing Feedwater Preheat
05000482/FIN-2010005-09	2010Q4	P.5	Inadequate Procedures to Ensure Proper Main Feed Pump Speed During Startup
05000482/FIN-2010007-01	2010Q4		Inadequate Design of Component Cooling Water Safety/Nonsafety Isolation
05000482/FIN-2010007-02	2010Q4	H.7	Failure to Perform Tornado Damper Testing
05000482/FIN-2010007-03	2010Q4		Inadequate Auxiliary Feedwater Pump Suction Line Break Analysis and Design
05000482/FIN-2010007-04	2010Q4		Emergency Diesel Generator Specified Rating did not Address Engine Operation at Design Basis Extreme Meteorological Temperature Conditions
05000482/FIN-2010007-05	2010Q4	H.9	Failure to Translate Design Requirements to Operating Procedures for the Transfer of Residual Heat Removal and Containment Spray Suction to the Containment Recirculation Sumps
05000482/FIN-2010005-01	2010Q4	H.14	Failure to Properly Identify and Evaluate Degraded Piping in the Train A Essential Service Water System
05000482/FIN-2010005-02	2010Q4	H.14	Failure to Account for Water Hammer Stresses in Essential Service Water System Calculations
05000482/FIN-2010005-03	2010Q4	H.7	Failure to Maintain Operator Licensing Examination Integrity
05000482/FIN-2010005-04	2010Q4	P.2	Failure to Evaluate Corrosion Mechanism in Accordance with Code Case N513
05000482/FIN-2010005-10	2010Q4	H.7	Inadequate Procedure for Steam Generator Hi-Hi Turbine Trip
05000482/FIN-2010008-04	2010Q4	P.2	Failure to Identify and Correct Inadequate RHR Fill and Vent Procedures
05000482/FIN-2010008-03	2010Q4	P.2	Failure to Perform an Adequate Operability Evaluation
05000482/FIN-2010008-02	2010Q4		Inadequate Procedure for Fill and Vent of the Component Cooling Water System
05000482/FIN-2010008-01	2010Q4	H.14	Failure to Promptly Identify and Correct a Condition Adverse to Quality
05000482/FIN-2011002-11	2011Q1	H.4 H.5	Failure to Follow Radiation Work Permit Instructions
05000482/FIN-2011002-10	2011Q1	H.13	Repetitive Failure to Enter Technical Specifications for Auxiliary Feedwater Suction Valve Testing
05000482/FIN-2011002-09	2011Q1	H.5	Inadequate Clearance Order Disables Power Operated Relief Valve Low temperature Overpressure Function
05000482/FIN-2011002-08	2011Q1	P.3	Inadequate Fill and Vent of Component Cooling Water
05000482/FIN-2011002-07	2011Q1	H.4 H.5	Failure to Verify Ultimate Heat Sink Sedimentation Levels within Design Bases
05000482/FIN-2011002-06	2011Q1	P.2	Failure to Perform an Operability Determination for Degradation of the Fuel Oil Storage Tank
05000482/FIN-2011002-05	2011Q1		Inadequate Calculation for Vital Switchgear Cooling
05000482/FIN-2011002-04	2011Q1	P.2	Failure to Follow 10 CFR 50.65 a(2) for Main Control Board Annunciator Power Supply Failures
05000482/FIN-2011002-03	2011Q1	P.2	Failure to Monitor the Performance of Nonsafety-Related Systems and Components Used in the Plant Emergency Operating Procedures under 10 CFR 50.65 Programs
05000482/FIN-2011002-02	2011Q1	H.5	Inadequate Clearance Order Isolated Cooling to Inservice Safety-Related Equipment
05000482/FIN-2011002-01	2011Q1	H.14	Inadequate Design Control of the Fuel Oil Storage Tank Fill System
05000482/FIN-2011006-01	2011Q1	H.9 H.2(b)	Failure to Trend Emergency Diesel Generator Chemistry Parameters Results in an Unplanned Technical Specification Entry

Self-Identified List (Wolf Creek)

	Q	Title
05000482/FIN-2010004-03	2010Q3	Licensee-Identified Violation
05000482/FIN-2011006-02	2011Q1	N/A
05000482/FIN-2011002-12	2011Q1	Licensee-Identified Violation
05000482/FIN-2011002-13	2011Q1	Licensee-Identified Violation
05000482/FIN-2011002-14	2011Q1	Licensee-Identified Violation

[Wolf Creek Findings full list]

05000482/FIN-2011002-14

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