05000259/FIN-2010002-08: Difference between revisions

Finding

Title

Licensee-Identified Violation

Description

Technical Specification 5.7.1.b, High Radiation Area, requires access to, and activities in, each HRA to be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s). Contrary to this, on May 25, 2009, a Modifications boilermaker was handling bags of mop heads in a contaminated area during cavity decontamination while loggedon to a dose-control, non-contaminated area RWP. The mop heads were reading 1500 mrem/hour on contact and 500 mrem/hour at 30 cm; the rad-trash bag constituted a mobile high radiation area being controlled by a health physics technician. The boilermaker failed to check-in with the control point on the refuel floor, where he would have been briefed on the radiological conditions, radiation protection measures, and placed on the appropriate RWP for the task. When the boilermaker received a dose rate alarm, the health physics technician covering the job immediately removed him from the area, having recognized that the boilermaker could not be on the correct RWP since he had received an alarm. This was identified in the licensees CAP as PER 172081. This finding was of very low safety significance because it did not involve ALARA planning and controls, did not involve an overexposure, did not pose a substantial potential for overexposure, and the ability to assess dose was not compromised

08
Site:	Browns Ferry
Report	IR 05000259/2010002 Section 4OA7
Date counted	Mar 31, 2010 (2010Q1)
Type:	NCV: Green
cornerstone	Mitigating Systems
Identified by:	Licensee-identified
Inspection Procedure:
Inspectors (proximate)	C Stancil T Ross H Gepford E Guthrie R Baldwin K Korth M Coursey
INPO aspect
'
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]

@@ Line 1: / Line 1: @@
 {{finding
-| title = LICENSEE-IDENTIFIED Violation
+| title = Licensee-Identified Violation
 | docket = 05000259, 05000260, 05000296
 | inspection report = IR 05000259/2010002

05000259/FIN-2010002-08: Difference between revisions

Latest revision as of 10:39, 30 May 2018

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05000259/FIN-2010002-08: Difference between revisions

Latest revision as of 10:39, 30 May 2018

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