05000259/FIN-2010002-02

Finding

Title

New Fuel Receipt Inspection and Refueling Operations Supervised By Non-qualified Senior Reactor Operators

Description

The inspectors identified a noncited violation of Technical Specifications 5.4.1.a for the failure to comply with operating procedures for Unit 3 new fuel receipt inspection and refueling operations that required the Fuel Handling Supervisor (FHS) to be trained and certified. During Unit 3 new fuel receipt inspections and refueling operations unqualified senior reactor operators (SRO) were allowed to supervise fuel handling activities. The unqualified SROs were subsequently re-qualified or not allowed to supervise fuel handling activities until qualified. This issue was entered into the licensees corrective action program as problem evaluation reports 220410 and 220791. This finding was determined to be of greater than minor significance because it was associated with the Barrier Integrity Cornerstone attribute of Human Performance, and adversely affected the cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events. Specifically, the use of unqualified FHS(s) to supervise new fuel receipt inspection and core refueling operations would reduce the level of assurance that fuel handling activities were accomplished safely and error free to prevent inadvertent fuel damage. The finding was evaluated and determined to be of very low safety significance using Inspection Manual Chapter 0609, Appendix G, Shutdown Operations Significance Determination Process, Attachment 1, Phase 1 Operational Checklists, Checklist 7, because it did not involve any human performance errors that resulted in fuel assembly damage, inappropriate core alteration, loss of reactor coolant and/or spent fuel pool inventory, or reduction of any safe shutdown mitigation capability. The cause of this finding was directly related to the cross-cutting aspect of Procedural Compliance in the Work Practices component of the Human Performance area because neither the night shift FHS or relief FHS(s) complied with the operating procedure requirements that all personnel supervising new fuel receipt inspections and/or refueling operations must be qualified [(H.4(b)

02
Site:	Browns Ferry
Report	IR 05000259/2010002 Section 1R20
Date counted	Mar 31, 2010 (2010Q1)
Type:	NCV: Green
cornerstone	Barrier Integrity
Identified by:	NRC identified
Inspection Procedure:	IP 71111.2
Inspectors (proximate)	C Stancil T Ross H Gepford E Guthrie R Baldwin K Korth M Coursey
CCA	H.8, Procedure Adherence
INPO aspect	WP.4
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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-2010002-02

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