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IR 05000259/2011003
Show incoming properties 
Category
Letter  and Inspection Report
ASME section
ASME Section III +
Accession number
ML112210368  +
Area
Switchyard +
Atomic Element
Hydrogen +  and Platinum +
CFR
10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 50.63 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 50.65 +, 10 CFR 50.54 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a2 +  and 10 CFR 50.65#a4 +
Contact
D. Hughes +, T. Marlow +, K. Polson +, S. Bono +, B. Bruce +, M. McAndrew +, J. Colvin +, G. Doyle +, J. Morris +, K. Groom +, P. Donahue +, M. Rasmussen +, W. Baker +, M. Durr +, J. Emens +, A. Yarbrough +, J. Boyer +, W. Byrne +, M. Ellet +, R. King +, R. Norris +, D. Kettering +, A. Feltman +, S. Kelly +, J. Underwood +, O. Brooks +, N. Gannon +, D. Malinowski +, W. Nurnberger +, W. Pearce +...
Cornerstone
Emergency Preparedness +, Barrier Integrity +, Initiating Events +  and Mitigating Systems +
Docket
05000259  +, 05000260  +, 05000296  +, 00259  +, 00260  +  and 00296  +
Document
IR 05000259/2011009 +  and ML111530328 +
Finding
05000259/FIN-2011003-02 +  and 05000259/FIN-2010005-02 +
From
Eugene Guthrie +  and Reactor Projects Region 2 Branch 6 +
Generic letter
NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +
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IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +, IR 05000259/2011003 +...
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
IP
TI 2515/183 +  and TI 2515/184 +
Inspection Manual Chapter
NRC Inspection Manual 0609 +, NRC Inspection Manual 0612 Appendix B +, IMC 0305, Operating Reactor Assessment Program +  and IMC 0310, Aspects within the Cross-Cutting Areas +
Inspection procedure
IP 71152, Problem Identification and Resolution (PI&R) +
Inspection report
IR 05000259/2010004 +, IR 05000259/2010005 +, IR 05000259/2011002 +  and IR 05000259/2011003 +
Issue date
August 8, 2011  +
LER
05000259/LER-2010-002, Drywell Pressure Instrument Channel Inoperability Due to Improper Tubing Slope +, 05000259/LER-2010-005, Regarding Main Steam Relief Valves As-Found Setpoints Exceeded Technical Specification Lift Pressure Values +  and 05000296/LER-2010-003, Multiple Test Failures of Excess Flow Check Valves +
Licensing Basis Document
Updated Final Safety Analysis Report +
Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
09:55:09, 13 January 2025  +
NEI
NEI 99-02, Regulatory Assessment Performance Indicator Guideline +
NUREG
NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +
Page count
47  +
Power source
4kV +
Procedure
Emergency Plan +
Regulatory Issue Summary
RIS 2005-20, Rev. 1: Revision to NRC Inspection Manual Part 9900 Technical Guidance, Operability Determinations & Functionality Assessments for Resolution of Degraded or Nonconforming Conditions Adverse to Quality or Safety +
Report number
3  +
SSC
N1E-003 +
Scram
Automatic Scram +
Site
Browns Ferry +
Site license
Browns Ferry +
Start date
August 8, 2011  +
State
Tennessee +  and Washington +
System
Reactor Coolant System +, Secondary containment +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Control Room Emergency Ventilation +, Automatic Depressurization System +, Emergency Equipment Cooling Water +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Control Room Envelope +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +
TS
TS-3.4.3 +  and TS-3.3.1.1 +
Title
IR 05000259-11-003, 05000260-11-003, 05000296-11-003; 04/01/2011 - 06/30/2011; Browns Ferry Nuclear Plant, Units 1, 2 and 3; Annual Heat Sink Performance, Operability Evaluations  +
To
Tennessee Valley Authority +  and Rod Krich +
Topic
Reactor Vessel Water Level +, Fire Barrier +, Post Accident Monitoring +, Hydrostatic +, Past operability +, Temporary Modification +, Functionality Assessment +, Condition Adverse to Quality +, B.5.b +, Corrosion bonding +, Significance Determination Process +, Feedwater Heater +, Scram Discharge Volume +, Loss of Offsite Power +, Excess Flow Check Valve +, Operability Determination +, Severe Accident Management Guideline +, Downpower +, Overspeed trip +, Overspeed +  and Reactive Inspection +
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http://pbadupws.nrc.gov/docs/ML1122/ML112210368.pdf  +
Work order
WO 112212918 +  and WO 111972393 +
Year
2,011  +
 
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