05000458/FIN-2012004-04

Finding

Title

Inadequate Verification of Leading Edge Flow Meter Functionality

Description

The inspectors identified a finding for the licensees failure to calibrate the feed water Leading Edge Flow Meter (LEFM) CheckPlus System following maintenance activities. This resulted in an error in reactor feed water flow rate data used to calculate reactor core thermal power. This issue was entered into the licensees corrective action program as Condition Report CR-RBS-2012- 06274 This performance deficiency is more-than-minor and is therefore a finding because it was associated with the procedure quality attribute of the initiating events cornerstone and affected the cornerstone objective to limit the likelihood of those events that upset plant stability and challenge critical safety functions. The performance deficiency challenged the initiating events cornerstone objective by allowing the licensee to operate the plant outside of the prescribed analyzed uncertainty value, used in determining maximum core thermal power. Using NRC Inspection Manual Chapter 0609, Appendix A, The Significance Determination Process (SDP) for Findings at Power, the inspectors determined that this finding has very low safety significance (Green) because it did not cause a reactor trip and the loss of mitigation equipment relied upon to transition the plant from the onset of the trip to a stable shutdown condition. The inspectors determined that the apparent cause of this finding was that when the licensee had changed the flow meter maintenance work scope that required transducer replacement, they had not included the vendor verification requirement in the revised work order. Therefore, this finding has a cross-cutting aspect in the Human Performance area of Work Control because the licensee had failed to appropriately coordinate the impact of changes to the work scope or activity on the plant.

04
Site:	River Bend
Report	IR 05000458/2012004 Section 1R19
Date counted	Sep 30, 2012 (2012Q3)
Type:	Finding: Green
cornerstone	Initiating Events
Identified by:	NRC identified
Inspection Procedure:	IP 71111.19
Inspectors (proximate)	G Guerra P Elkmann A Barrett W Sifre J Laughlin R Hagar M Young G Larkin G Apger B Rice C Steely D Strickland
CCA	H.5, Work Management
INPO aspect	WP.1
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Finding - River Bend - IR 05000458/2012004

1(0)2(10)3(7)4(4)5(6)6(0)9(8)10(8)11(0)12(5)13(0)301(0)403(2)404(1)503(0)801(0)31(0)

IR 05000458/2012004: 1 2 3 4

Finding List (River Bend) @ 2012Q3

CCA Matrix: 2012Q3

	Q	CCA	Title
05000458/FIN-2011008-04	2011Q4		Station Blackout-Containment Venting
05000458/FIN-2011402-01	2011Q4	H.14	Security
05000458/FIN-2011008-09	2011Q4	H.9	Inadequate Simulator Fidelity for Emergency Diesel Generator Loading
05000458/FIN-2011008-08	2011Q4	P.5	Inadequate Emergency and Abnormal Procedures for Standby Diesel Generator Fail to Load Sequences
05000458/FIN-2011008-07	2011Q4	H.9	Inadequate Abnormal Procedure for Reducing Loads on Standby Diesel Generators
05000458/FIN-2011008-05	2011Q4		Inadequate Procedures for Monitoring Standby Service Water System Leakage
05000458/FIN-2011008-03	2011Q4		Failure to Establish Residual Heat Removal Heat Exchanger Testing Frequency
05000458/FIN-2011008-02	2011Q4	P.2	Failure to Use Conservative Design Assumptions in the Ultimate Heat Sink Inventory Calculation
05000458/FIN-2011008-01	2011Q4	P.2	Inadequate Testing of Division I and Division III Standby Diesel Generators
05000458/FIN-2011005-02	2011Q4	H.2	Failure to Adequately Monitor the Performance of the Control Building Chiller System
05000458/FIN-2011005-01	2011Q4	H.12	Standby Service Water Pump Motor Lubrication Deficiencies
05000458/FIN-2011008-06	2011Q4		Failure to Obtain NRC Approval for Change to Ultimate Heat Sink Inventory Requirements
05000458/FIN-2012002-03	2012Q1	H.14	Failure to Verify Assumptions used in Standby Equipment Room Temperature Analysis
05000458/FIN-2012002-04	2012Q1	H.7	Failure to Appropriately Set Reactor Core Isolation Cooling Flow Controller High Output Limit
05000458/FIN-2012002-06	2012Q1	H.7	Inadequate Maintenance Instructions for the Suppression Pool Cooling Isolation Valves
05000458/FIN-2012002-07	2012Q1	H.8	Failure to Perform a Radiation Survey
05000458/FIN-2012002-08	2012Q1	H.2	Failure to Control Access to a High Radiation Area
05000458/FIN-2012002-09	2012Q1		Failure to Properly Fabricate and Install the mid-Standard Turbine Shaft Brush
05000458/FIN-2012002-05	2012Q1	H.8	Inadequate Relief Valve Configuration Control Results in a Reactor Downpower
05000458/FIN-2012002-02	2012Q1	H.8	Failure to Appropriately Assess and Manage Risk for Internal Flooding Events
05000458/FIN-2012002-01	2012Q1	H.9	Failure to Adequately Monitor the Performance of the Digital Radiation Monitoring System
05000458/FIN-2012003-01	2012Q2	H.2	Failure to Follow Procedure to Protect Sensitive Plant Areas
05000458/FIN-2012003-02	2012Q2	H.13	Failure to Follow Severe Weather Operations Procedure
05000458/FIN-2012003-03	2012Q2	P.1	High Pressure Core Spray Diesel Generator Bearing Lubrication Deficiencies
05000458/FIN-2012003-04	2012Q2		Failure to Properly Assemble Turbine Control Valve Push ROD-SPRING Housing Coupling
05000458/FIN-2012003-05	2012Q2		Failure to Specify Manual Actions for Safety Relief Valve Operations During a Station Blackout Event
05000458/FIN-2012004-01	2012Q3		Improper Hydrogen Igniter Breaker Trip Coil Setting
05000458/FIN-2012010-02	2012Q3	H.14	Failure to Declare Reactor Core Isolation Cooling System Inoperable
05000458/FIN-2012009-08	2012Q3		Ability to Promptly Staff the Fire Brigade at All Times During Plant Operation
05000458/FIN-2012009-07	2012Q3		Onsite Safety Review Committee Implementation
05000458/FIN-2012009-06	2012Q3		Implementation of the Station Cable Reliability Program
05000458/FIN-2012009-05	2012Q3		Implementation of Vendor and Industry Recommended Relay Testing and Maintenance
05000458/FIN-2012009-04	2012Q3		Corrective Action Program Implementation for Prior Lockout Relay Failure in February 2011
05000458/FIN-2012009-03	2012Q3		Implementation of the Procedure for Infrequently Performed Tests or Evolutions
05000458/FIN-2012009-02	2012Q3		Past Operability of the Reactor Core Isolation Cooling System
05000458/FIN-2012009-01	2012Q3		Main Control Room Annunciator Control and Conduct of Operations
05000458/FIN-2012004-04	2012Q3	H.5	Inadequate Verification of Leading Edge Flow Meter Functionality
05000458/FIN-2012004-03	2012Q3	P.5	Failure to Appropriately Tune the Reactor Core Isolation Cooling Turbine Speed Controller
05000458/FIN-2012004-02	2012Q3	H.6	Untimely Corrective Actions to Ensure Reliability of the 480 Vac Molded Case Circuit Breakers and Unitized Motor Starters
05000458/FIN-2012010-03	2012Q3	H.14	Failure to Establish an Adequate Controlling Procedure for Stroking Safety Relief Valves at LOW Power
05000458/FIN-2012010-04	2012Q3	H.5	Failue to Implement Effective Corrective Actions for Lockout Relay Failures
05000458/FIN-2012010-05	2012Q3		Failure to Est Lockout Relays in Accordance with Vendor Testing Practices
05000458/FIN-2012010-06	2012Q3	P.5	Failure to Establish an Adequate Cable Reliability Program
05000458/FIN-2012010-01	2012Q3		Failure to Correct Spurious Isolation of Reactor Core Isolation Cooling System
05000458/FIN-2012010-07	2012Q3	H.13	Loss of Onsite Safety Review Committee Independence
05000458/FIN-2012010-08	2012Q3	H.7	Failure to Prevent Conflicts of Duty for Fire Brigade Members

Self-Identified List (River Bend)

	Q	Title
05000458/FIN-2012002-10	2012Q1	Licensee-Identified Violation
05000458/FIN-2012003-06	2012Q2	Licensee-Identified Violation
05000458/FIN-2012003-07	2012Q2	Licensee-Identified Violation
05000458/FIN-2012404-01	2012Q2	Security

[River Bend Findings full list]

05000458/FIN-2012004-04

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