05000313/FIN-2016008-01

Finding

Title

Failure to Verify the Adequacy of Motor Operated Valve Thermal Overload Devices

Description

Green. The team identified a Green non-cited violation of 10 CFR Part 50, Appendix B, Criterion III, Design Control, which states, in part, design control measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews, by the use of alternate or simplified calculational methods, or by the performance of a suitable testing program. Specifically, prior to December 2, 2016, the licensee failed to use appropriate assumptions in thermal overload device calculations and failed to establish a suitable periodic test program for safety-related Unit 1 motor operated valve thermal overload device trip setpoints, as discussed in Regulatory Guide 1.106, Regulatory Position C.2. In response to this issue, the licensee demonstrated reasonable assurance of operability by using the results of the 18-month high pressure injection system valve testing which required multiple stroking of block valves to obtain various flows without tripping the thermal overload devices. This finding was entered into the licensees corrective action program as Condition Reports CR-ANO-C-2016-5017 and CR-ANO-1-2016-5130. The team determined that the failure to meet the intent of Regulatory Guide 1.106, Regulatory Position C.2 was a performance deficiency. The finding was determined to be more than minor because it was associated with the Mitigating Systems Cornerstone attribute of equipment performance and affected the cornerstone objective of ensuring the availability, reliability, and capability of mitigating systems to respond to initiating events to prevent undesirable consequences. Specifically, the failure to verify the adequacy of the design and perform suitable testing for thermal overload device setpoint drift did not ensure that the safety-related motor operated valves would be available to throttle the associated system flows during a design basis accident. In accordance with Inspection Manual Chapter 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power, dated June 19, 2012, Exhibit 2, Mitigating Systems Screening Questions, the issue screened as having very low safety significance (Green) because it was a design or qualification deficiency that did not represent a loss of operability or functionality; did not represent an actual loss of safety function of the system or train; did not result in the loss of one or more trains of non-technical specification equipment; and did not screen as potentially risk-significant due to seismic, flooding, or severe weather. This finding had a cross-cutting aspect in the area of problem identification and resolution associated with evaluations because the licensee failed to thoroughly evaluate issues to ensure that resolutions address causes and extent of conditions commensurate with their safety significance. Specifically, the licensee failed to thoroughly evaluate Condition Report CR-ANO-1-2016-0778 which documented NRC inspector concerns associated with design and testing of motor operated valve thermal overload devices [P.2].

01
Site:	Arkansas Nuclear
Report	IR 05000313/2016008 Section 1R21
Date counted	Dec 31, 2016 (2016Q4)
Type:	NCV: Green
cornerstone	Mitigating Systems
Identified by:	NRC identified
Inspection Procedure:	IP 71111.21
Inspectors (proximate)	G George G Nicely H Freeman I Anchondo J Kirkland M Yeminy N Okonkwo R Deese T Farnholtz
Violation of:	10 CFR 50 Appendix B Criterion III, Design Control
CCA	P.2, Evaluation
INPO aspect	PI.2
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Finding - Arkansas Nuclear - IR 05000313/2016008

1(6)2(3)3(1)4(4)5(0)6(0)7(21)8(6)9(4)10(0)11(0)301(0)401(0)402(0)403(0)404(2)405(0)11(1)

IR 05000313/2016008: 1 2 3 4 5 6

Finding List (Arkansas Nuclear) @ 2016Q4

CCA Matrix: 2016Q4

	Q	CCA	Title
05000313/FIN-2016007-15	2016Q1	P.1	Failure to Maintain Structural Design Clearances inside the Unit 1 and 2 Reactor Containment Buildings
05000368/FIN-2016007-05	2016Q1		Failure to Include Unit 2 Service Water Pump Supports in the ASME Code Section XI Inservice Inspection Program
05000368/FIN-2016001-03	2016Q1		Blocked Drain Results in Emergency Feedwater Pump Inoperability
05000368/FIN-2016001-02	2016Q1		Failure to Follow Design Control Requirements for Pump Seal Cooler Replacements
05000368/FIN-2016007-07	2016Q1		Failure to Maintain Service Water Design Cooling to the Unit 2 High Pressure Safety Injection Pump Seal and Bearing Coolers
05000368/FIN-2016007-08	2016Q1		Inadequate Flow Monitoring of Unit 2 Service Water to Emergency Feedwater Pump Suction Supply
05000313/FIN-2016007-14	2016Q1	H.3	Failure to Properly Implement the Corrective Action Program
05000313/FIN-2016007-17	2016Q1		Determine Impact of Modifying Fire Seals for Flood Protection
05000313/FIN-2016001-01	2016Q1	H.4	Failure to Assess and Manage Hot Work Risk
05000313/FIN-2016007-12	2016Q1	P.1	Failure to Perform Predictive Maintenance on Safety-Related Medium-Voltage Switchgear
05000313/FIN-2016007-11	2016Q1	P.5	Pressurizer Block Valve Not Installed in the Qualified Environmental Configuration
05000313/FIN-2016007-02	2016Q1	P.6	Inadequate Effectiveness Reviews for Corrective Actions to Prevent Recurrence
05000368/FIN-2016001-04	2016Q1	H.12	Failure to Inject Service Water with Corrosion Inhibitors during Refueling Outages
05000313/FIN-2016007-03	2016Q1	H.14	Inadequate Operating Experience Evaluations
05000313/FIN-2016007-04	2016Q1	H.14	Inadequate Control of Monitoring for Wall Loss in the Service Water System
05000313/FIN-2016007-06	2016Q1	H.6	Failure to Correct Degraded Unit 2 Train B Emergency Diesel Generator Heat Exchangers Service Water Flow and Degraded Unit 1 Containment Coatings
05000313/FIN-2016007-09	2016Q1	H.5	Emergency Feedwater Pump Casing Wall Loss Not Monitored
05000313/FIN-2016007-13	2016Q1	H.1	Failure to Update Probabilistic Risk Assessment Model in a Timely Manner Results in Failure to Submit Complete and Accurate Information
05000313/FIN-2016007-16	2016Q1	H.7	Failure to Properly Calibrate Unit 1 Reactor Building Atmospheric Particulate Radiation Monitor RE-7460
05000313/FIN-2016001-05	2016Q1	P.2	Failure to Identify and Repair Intermittent Card Failure Leads to a Reactor Trip
05000313/FIN-2016007-01	2016Q1	P.3	Failure to Complete Extent of Condition Reviews for the Stator Drop Significant Condition Adverse to Quality Event
05000368/FIN-2016007-10	2016Q1	P.6	Failure to Develop an Operability Decision-Making Issue for Degraded Condition on Safety Injection Tank
05000368/FIN-2016009-03	2016Q2	H.3	Failure to Ensure that the Assumptions in the Engineering Analysis Remain Valid
05000368/FIN-2016009-02	2016Q2		Inadequate Procedure Used as a Compensatory Measure
05000313/FIN-2016009-01	2016Q2		Inadequate Loop Flow Testing
05000368/FIN-2016002-02	2016Q2		Failure to Clean Main Feedwater Lube Oil Reservoir Leads to Reactor Power Reduction
05000368/FIN-2016009-04	2016Q2		Failure to Adequately Establish Ignition Frequencies for the Risk-Informed Fire Protection Program
05000368/FIN-2016002-01	2016Q2	H.5	Failure to Incorporate Vendor Guidance in Work Order
05000313/FIN-2016003-04	2016Q3		EA-16-143, Enforcement Discretion for Tornado-Generated Missile Protection Noncompliances
05000313/FIN-2016008-06	2016Q4	P.1	Readiness to Cope with External Flooding
05000313/FIN-2016008-01	2016Q4	P.2	Failure to Verify the Adequacy of Motor Operated Valve Thermal Overload Devices
05000313/FIN-2016404-02	2016Q4	P.3	Security
05000313/FIN-2016404-01	2016Q4	P.2	Security
05000313/FIN-2016008-05	2016Q4		Failure to Ensure Safety Systems Would Survive Sustained Degraded Voltage Conditions
05000313/FIN-2016008-04	2016Q4		Failure to Perform an Adequate Emergency Feedwater Pump Suction Transfer Design Calculation or Testing (EA 2017-017)
05000313/FIN-2016008-03	2016Q4		Failure to Monitor Startup Transformers 1, 2, and 3 Voltage Regulator/Tap Changer Function
05000368/FIN-2016011-01	2016Q4	H.5	Failure to Ensure Adequate Lubication for Emergency Diesel Generator Bearing
05000313/FIN-2016008-02	2016Q4		Failure to Incorporate NRC Safety Guide 9 Criteria into Surveillance Procedures
05000313/FIN-2016004-02	2016Q4		Failure to Design Pipe Support for Vibration
05000313/FIN-2016004-01	2016Q4	H.12	Failure to Pre-plan Walkdown to Avoid Impacting Safety Bus

Self-Identified List (Arkansas Nuclear)

	Q	Title
05000313/FIN-2016001-06	2016Q1	Licensee-Identified Violation
05000313/FIN-2016007-18	2016Q1	Licensee-Identified Violation
05000313/FIN-2016007-19	2016Q1	Licensee-Identified Violation
05000368/FIN-2016007-20	2016Q1	Licensee-Identified Violation
05000313/FIN-2016007-21	2016Q1	Licensee-Identified Violation
05000368/FIN-2016002-03	2016Q2	Licensee-Identified Violation
05000313/FIN-2016004-03	2016Q4	Licensee-Identified Violation
05000313/FIN-2016004-04	2016Q4	Licensee-Identified Violation

[Arkansas Nuclear Findings full list]

05000313/FIN-2016008-01

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