05000259/FIN-2010002-04

Finding

Title

Inadequate Surveillance Procedure To Ensure All Relevant RPV Metal Temperatures Were Monitored During RPV Hydrostatic/In-service Leak Testing

Description

The inspectors identified a noncited violation of Technical Specifications (TS) 5.4.1.a for failure to establish an adequate surveillance procedure to ensure all relevant reactor pressure vessel (RPV) metal temperatures of all four RPV regions were being monitored during the Unit 3 RPV in-service leak test pursuant with TS Surveillance Requirement (SR) 3.4.9.1, RCS Pressure and Temperature Limits. The licensee subsequently verified all required RPV temperatures were within TS 3.4.9 limits. This issue was entered into the licensees corrective action program as PERs 223539 and 224778. This finding was determined to be of greater than minor significance because it was associated with the Initiating Events Cornerstone attribute of Procedure Quality, and adversely affected the cornerstone objective to limit the likelihood of those events that upset plant stability and challenge critical safety functions during shutdown. More specifically, the procedure used by operators to monitor RCS and RPV temperatures, during the RPV in-service leak test, lacked sufficient details to ensure all relevant RPV temperatures would be monitored to meet TS SR 3.4.9.1 which could increase the likelihood of a low temperature overpressure event. The finding was determined to be of very low safety significance according to Inspection Manual Chapter 0609, Phase I - Initial Screening and Characterization of Findings, because it did not actually exceed the TS limit or adversely affect any mitigating systems. The cause of this finding was directly related to the cross-cutting aspect of Complete and Accurate Procedures in the Resources component of the Human Performance area because the applicable surveillance procedure lacked sufficient details and guidance to ensure all relevant RPV metal temperatures would be monitored pursuant to TS SR 3.4.9.1 [H.2.(c)]

04
Site:	Browns Ferry
Report	IR 05000259/2010002 Section 1R21
Date counted	Mar 31, 2010 (2010Q1)
Type:	NCV: Green
cornerstone	Initiating Events
Identified by:	NRC identified
Inspection Procedure:	IP 71111.21
Inspectors (proximate)	C Stancil T Ross H Gepford E Guthrie R Baldwin K Korth M Coursey
CCA	H.7, Documentation
INPO aspect	WP.3
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v • d • e

Finding - Browns Ferry - IR 05000259/2010002

2(8)3(0)4(7)5(3)6(6)8(0)201(0)301(0)402(0)502(0)

IR 05000259/2010002: 1 2 3 4 5 6 7 8

Finding List (Browns Ferry) @ 2010Q1

CCA Matrix: 2010Q1

	Q	CCA	Title
05000259/FIN-2009006-01	2009Q3	P.2	Standby Gas Treatment Subsystem A Inoperable Beyond the Technical Specification Allowed Outage Time
05000259/FIN-2009004-01	2009Q3		Unit 3 Reactor Core Isolation Cooling Pump Flow Oscillations
05000259/FIN-2009009-04	2009Q4	P.2	Failure to Meet the Requirements of 10 CFR Part 50, Appendix R, Section III.G.1 for 20 Fire Areas
05000259/FIN-2009005-03	2009Q4	H.7	Inadequate Operating Procedures Cause Partial Loss of Reactor Feedwater Which Results In Unit 2 Manual Reactor Scram
05000259/FIN-2009008-02	2009Q4		Violation of 10CFR50, Appendix B, Criterion V for Inadequate Procedure for Emergency Equipment Cooling Water System Flow Balancing
05000259/FIN-2009008-01	2009Q4	P.5	Violation of Technical Specification 5.4.1 for Failure to Develop Adequate Procedures to Ensure Tornado Depressurization Protection of the Emergency Diesel Generators
05000259/FIN-2009005-04	2009Q4	P.1 P.1(a)	Unit 2 RCIC System Inoperable Beyond the Technical Specification Allowed Outage Time
05000259/FIN-2009009-02	2009Q4	H.5	Failure to Establish Adequate Compensatory Measures for an Out-of-Service Hose Station
05000259/FIN-2009009-01	2009Q4	H.5	Deficiencies with Emergency Lighting Units
05000259/FIN-2009008-03	2009Q4		Safety-Related Molded Case Circuit Breakers
05000259/FIN-2009009-03	2009Q4	P.3	Failure to Protect Cables of Systems Necessary to Achieve and/or Maintain Post-Fire Safe Shutdown Conditions for Fire Areas Subject to the Requirements of 10 CFR Part 50, Appendix R, Section III.G.2
05000259/FIN-2009005-02	2009Q4	P.3	Failure to Report a Safety System Functional Failure Per 10 CFR 50.73
05000259/FIN-2009005-01	2009Q4	P.2	Failure to Report an Automatic RPS Actuation While Shutdown Per 10 CFR 50.73
05000259/FIN-2010002-05	2010Q1	P.3	Untimely Corrective Actions to Restore Compliance of EECW Pump In-Service Testing with ASME OM Code Requirements
05000259/FIN-2010002-01	2010Q1	P.2	Failure to Effectively Maintain Performance of the A3 EECW Pump as Required by 10 CFR 50.65(a)(2)
05000259/FIN-2010002-04	2010Q1	H.7	Inadequate Surveillance Procedure To Ensure All Relevant RPV Metal Temperatures Were Monitored During RPV Hydrostatic/In-service Leak Testing
05000259/FIN-2010002-03	2010Q1	H.12	Operators Failed to Correctly Monitor and Assess RPV Beltline Temperatures During RPV Hydrostatic/In-service Leak Test
05000259/FIN-2010002-02	2010Q1	H.8	New Fuel Receipt Inspection and Refueling Operations Supervised By Non-qualified Senior Reactor Operators

Self-Identified List (Browns Ferry)

	Q	Title
05000259/FIN-2009004-02	2009Q3	Licensee-Identified Violation
05000259/FIN-2009004-03	2009Q3	Licensee-Identified Violation
05000259/FIN-2009004-04	2009Q3	Licensee-Identified Violation
05000259/FIN-2009006-02	2009Q3	Licensee-Identified Violation
05000259/FIN-2009008-04	2009Q4	Licensee-Identified Violation
05000259/FIN-2010002-07	2010Q1	Licensee-Identified Violation
05000259/FIN-2010002-06	2010Q1	Licensee-Identified Violation
05000259/FIN-2010002-08	2010Q1	Licensee-Identified Violation

[Browns Ferry Findings full list]

05000259/FIN-2010002-04

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