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IR 05000445/2013007
Show incoming properties 
Category
Letter  and Inspection Report
Accession number
ML13214A346  +
Area
Switchyard +
Atomic Element
Hydrogen +  and Lead +
CFR
10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 2.390 +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50 Appendix B Criterion XI +, 10 CFR 50 Appendix B Criterion III, Design Control +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a +  and 10 CFR 50.71#e4 +
Contact
B. Patrick +, J. Taylor +, J. Hicks +, S. Harvey +, J. Brady +, G. Replogle +, K. Peters +, T. Hope +, G. Merka +, D. Volkening +, R. Flores +, J. Patton +, F. Madden +, D. Ambrose +, J. Bain +, T. Gibbs +, I. Ahmad +, J. Henderson +, K. Kirwin +, J. Lamarca +, L. Meller +, W. Reppa +, M. Shirey +, R. Sorrell +, D. Whitsitt +, L. Windham +, John Kramer +, Mike Williams +, Matthew Smith +, Desiree Davis +...
Cornerstone
Barrier Integrity +, Initiating Events +  and Mitigating Systems +
Cross cutting aspect
H.14 +, P.3 +, H.2(d) +  and P.2(b) +
Docket
05000445  +, 05000446  +, 00445  +  and 00446  +
Finding
05000446/FIN-2013007-02 +, 05000446/FIN-2013007-01 +, 05000446/FIN-2013007-03 +, 05000446/FIN-2013007-04 +, 05000446/FIN-2013007-05 +, 05000446/FIN-2013007-06 +, 05000446/FIN-2013007-07 +, 05000446/FIN-2013007-08 +, 05000446/FIN-2013007-09 +, 05000446/FIN-2013007-10 +  and 05000446/FIN-2013007-11 +
From
Thomas Farnholtz +  and Division of Reactor Safety IV +
Generic letter
NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +, IR 05000445/2013007 +...
Hours
2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
IEEE
IEEE 141 +  and IEEE-450 +
IP sample
IP 71111.21 +
Inspection Manual Chapter
NRC Inspection Manual 0609 +, NRC Inspection Manual 0612 Appendix B +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +, NRC Inspection Manual 0609/Appendix A +  and IMC 0305, Operating Reactor Assessment Program +
Inspection procedure
IP 71111.21 +
Inspection report
IR 05000445/2010006 +  and IR 05000445/2013007 +
Issue date
August 2, 2013  +
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>.
11:21:05, 11 January 2025  +
NRC information notice
Information Notice 92-18 +, Information Notice 97-90 +, Information Notice 95-05 +, Information Notice 2012-11, Age Related Capacitor Degradation +, Information Notice 2008-02, Findings Identified During NRC Component Design Bases Inspections +  and Information Notice 1997-90, Use of Nonconservative Acceptance Criteria in Safety-Related Pump Surveillance Tests +
NUREG
NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +
Page count
67  +
Power source
345kV +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
IR 05000445/2013007 +
Regulatory Issue Summary
RIS 2011-12, Rev. 1 - Adequacy of Station Electric Distribution System Voltages (Track Changes) +
Report number
7  +
SSC
1E-6 +, 1EB4-1 +, 1EB3-1 +  and 1AF-0032 +
Site
Comanche Peak +
Site license
Comanche Peak +  and NPF-89 +
Start date
August 2, 2013  +
State
Texas +  and Washington +
System
Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Residual Heat Removal +, Remote shutdown +, Emergency Core Cooling System +  and Containment Spray +
TS
TS-3.8.7 +  and TS-3.8.9 +
Title
IR 05000445-13-007; 05000446-13-007; 05/20/2013 - 06/20/2013; Comanche Peak Nuclear Power Plant, Units 1 and 2: Baseline Inspection, NRC Inspection Procedure 71111.21, Component Design Basis Inspection  +
To
Luminant +  and Flores R +
Topic
Safe Shutdown +, Probabilistic Risk Assessment +, Contingency analyzer +, Functionality Assessment +, Condition Adverse to Quality +, Significance Determination Process +, Loss of Offsite Power +, Operability Determination +  and Operability Assessment +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
http://pbadupws.nrc.gov/docs/ML1321/ML13214A346.pdf  +
Year
2,013  +
 
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