05000368/FIN-2016009-02

Finding

Title

Inadequate Procedure Used as a Compensatory Measure

Description

The team identified a non-cited violation of License Condition 2.C.(3)(b), Fire Protection, for use of an inadequate procedure as a compensatory measure. Specifically, a procedure for providing temporary cooling to the safety parameter display system room when the normal room cooler is unavailable did not adequately address the impact of the temporary configuration on the ability to maintain safe and stable plant conditions for fires that require shutdown from outside the control room. The temporary room cooler did not have a power supply assured to remain available during a shutdown from outside the control room. The licensee entered this violation into their corrective action program as Condition Reports CR-ANO-2-2016-02143 and CR-ANO-C-2016-02638. In response to this issue, the licensee developed a thermal analysis of the safety parameter display system room temperature during this scenario and confirmed that the maximum room temperature would not challenge the operation to the safety parameter display system. The failure to provide an adequate procedure for use as a compensatory measure was a performance deficiency. The performance deficiency was more than minor because it was associated with the Mitigating Systems cornerstone attribute of procedure quality and adversely affected the associated cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events (fire) to prevent undesirable consequences. Specifically, loss of cooling to the safety parameter display system room could adversely affect the availability, reliability, and capability of the safety parameter display system which is required to respond to a fire resulting in the evacuation of the Unit 2 control room. A senior reactor analyst performed a detailed risk evaluation of this finding because IMC 0609, Appendix F, does not include explicit treatment of fires in the control room. An evaluation of the survivability of the safety parameter display system compared to the best estimate of the heatup of the room housing its equipment demonstrated that the safety parameter display system would survive with high probability until the plant reached a safe and stable condition for the postulated fires. As a result, the finding was determined to be of very low safety significance (Green). This finding did not have a cross-cutting aspect since it was not indicative of present performance in that the performance deficiency occurred more than three years ago.

02
Site:	Arkansas Nuclear
Report	IR 05000368/2016009 Section 1R05
Date counted	Jun 30, 2016 (2016Q2)
Type:	NCV: Green
cornerstone	Mitigating Systems
Identified by:	NRC identified
Inspection Procedure:	IP 71111.05
Inspectors (proximate)	G Pick G Werner H Barrett J Mateychick N Okonkwo R Deese S Alferink S Makor
Violation of:	License Condition - Fire Protection
INPO aspect
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v • d • e

Finding - Arkansas Nuclear - IR 05000368/2016009

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 05000368/2016009: 1 2 3 4

Finding List (Arkansas Nuclear) @ 2016Q2

CCA Matrix: 2016Q2

	Q	CCA	Title
05000313/FIN-2015003-02	2015Q3		Failure to Promptly Correct a Condition Adverse to Quality Involving Motor Control Center Bus Stabs
05000368/FIN-2015003-01	2015Q3	H.12	Failure to Follow Procedure Results in Increased Reactor Coolant Activity
05000313/FIN-2015004-03	2015Q4		Failure to Properly Translate the Design Requirements for the Unit 1 Decay Heat Vault Rooms Being Sealed (
05000313/FIN-2015004-01	2015Q4	H.13	Failure to Assess Risk for Switchyard Work
05000313/FIN-2015004-02	2015Q4	H.12	Failure to Identify and Correct Rain Water Accumulation in the Emergency Diesel Generator System Exhausts
05000368/FIN-2016001-02	2016Q1		Failure to Follow Design Control Requirements for Pump Seal Cooler Replacements
05000313/FIN-2016007-17	2016Q1		Determine Impact of Modifying Fire Seals for Flood Protection
05000313/FIN-2016007-14	2016Q1	H.3	Failure to Properly Implement the Corrective Action Program
05000368/FIN-2016007-08	2016Q1		Inadequate Flow Monitoring of Unit 2 Service Water to Emergency Feedwater Pump Suction Supply
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-2016007-05	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
05000313/FIN-2016001-01	2016Q1	H.4	Failure to Assess and Manage Hot Work Risk
05000313/FIN-2016007-15	2016Q1	P.1	Failure to Maintain Structural Design Clearances inside the Unit 1 and 2 Reactor Containment Buildings
05000368/FIN-2016001-04	2016Q1	H.12	Failure to Inject Service Water with Corrosion Inhibitors during Refueling Outages
05000313/FIN-2016007-11	2016Q1	P.5	Pressurizer Block Valve Not Installed in the Qualified Environmental Configuration
05000368/FIN-2016007-10	2016Q1	P.6	Failure to Develop an Operability Decision-Making Issue for Degraded Condition on Safety Injection Tank
05000313/FIN-2016007-02	2016Q1	P.6	Inadequate Effectiveness Reviews for Corrective Actions to Prevent Recurrence
05000313/FIN-2016007-01	2016Q1	P.3	Failure to Complete Extent of Condition Reviews for the Stator Drop Significant Condition Adverse to Quality Event
05000313/FIN-2016001-05	2016Q1	P.2	Failure to Identify and Repair Intermittent Card Failure Leads to a Reactor Trip
05000313/FIN-2016007-16	2016Q1	H.7	Failure to Properly Calibrate Unit 1 Reactor Building Atmospheric Particulate Radiation Monitor RE-7460
05000313/FIN-2016007-12	2016Q1	P.1	Failure to Perform Predictive Maintenance on Safety-Related Medium-Voltage Switchgear
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-2016007-13	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-2016007-09	2016Q1	H.5	Emergency Feedwater Pump Casing Wall Loss Not Monitored
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-2016009-01	2016Q2		Inadequate Loop Flow Testing
05000368/FIN-2016009-04	2016Q2		Failure to Adequately Establish Ignition Frequencies for the Risk-Informed Fire Protection Program
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
05000368/FIN-2016002-02	2016Q2		Failure to Clean Main Feedwater Lube Oil Reservoir Leads to Reactor Power Reduction
05000368/FIN-2016002-01	2016Q2	H.5	Failure to Incorporate Vendor Guidance in Work Order

Self-Identified List (Arkansas Nuclear)

	Q	Title
05000313/FIN-2015404-01	2015Q3	Licensee-Identified Violation
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

[Arkansas Nuclear Findings full list]

05000368/FIN-2016009-02

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