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IR 05000382/2004004
Show incoming properties 
Category
Letter  and Inspection Report
Accession number
ML043100257  +
Area
Switchyard +
Atomic Element
Iron +, Hydrogen +  and Tin +
CFR
10 CFR 50 +, 10 CFR 2.390 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 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 50.49#j +  and 10 CFR 50.65#a4 +
CR
CR-WF3-2004-02847 +, CR-WF3-2004-02251 +, CR-WF3-1999-00486 +, CR-WF3-2004-02547 +, CR-WF3-2004-02497 +, CR-WF3-2004-02468 +, CR-WF3-2004-02217 +, CR-WF3-2002-00778 +  and CR-WF3-2004-00185 +
Contact
K. Burke +, G. Pierce +, R. Madjerich +, J. Laque +, R. Osborne +, C. Fugate +, J. Holman +, K. T. Walsh +, P. Fresneda +, W. Brian +, S. S. Anders +, N. T. Brumfield +, R. A. Dodds +, J. J. Lewis +, A. J. Harris +, B. L. Houston +, T. G. Mitchell +, R. J. Murillo +, K. J. Peters +, R. D. Peters +, R. J. Porter +, J. E. Venable +, A. E. Wemett +  and W. B. Jones +
Cornerstone
Emergency Preparedness +, Barrier Integrity +, Initiating Events +  and Mitigating Systems +
Docket
05000382  +  and 00382  +
Finding
05000382/FIN-2004004-03 +, 05000382/FIN-2004004-05 +, 05000382/FIN-2004004-04 +, 05000382/FIN-2004004-06 +, 05000382/FIN-2004001-00 +, 05000382/FIN-2004004-01 +, 05000382/FIN-2004004-02 +, 05000382/FIN-2004002-04 +  and 05000382/FIN-2003011-02 +
From
William Jones +  and Division of Nuclear Materials Safety IV +
Generic letter
NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability +  and NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +
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 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +, IR 05000382/2004004 +...
IP
TI 2515/154 +  and TI 2515/159 +
IP sample
IP 71111.12 +, IP 71111.01 +, IP 71111.04 +, IP 71111.06 +, IP 71111.22 +, IP 71111.05 +, IP 71111.13 +, IP 71111.19 +, IP 71151 +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71153, Event Followup +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 71111.07, Heat Sink Performance +, IP 71111.23 +, IP 71111.07B +, IP 71111.16 +  and IP 71152, Problem Identification and Resolution (PI&R) +
Inspection Manual Chapter
NRC Inspection Manual 0609 +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +  and NRC Inspection Manual 0612, Power Reactor Inspection Reports +
Inspection report
IR 05000382/2004004 +  and IR 05000382/200402 +
Issue date
November 5, 2004  +
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>.
04:49:52, 16 January 2025  +
NUREG
NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG-0787, Safety Evaluation Report Related to the Operation of Waterford Steam Electric Station, Unit 3 (Redacted) +  and NUREG-1600, PR-MISC - 62FR06677 - (NUREG-1600) Policy and Procedure for Enforcement Actions, Policy Statement Amendment +
Page count
39  +
Regulatory Guide
Regulatory Guide 1.160 +
Report number
4  +
Site
Waterford +
Site license
Waterford +
Start date
November 5, 2004  +
State
Texas +, Washington +  and Louisiana +
System
Reactor Coolant System +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Main Transformer +, Main Turbine +, Shutdown Cooling +, Emergency Core Cooling System +, Main Steam +  and Containment Spray +
TS
TS-3.8.4 +
Title
NRC Integrated Inspection Report 05000382-04-004  +
To
Entergy +  and Venable J +
Topic
Safe Shutdown +, Ultimate heat sink +, Temporary Modification +, Significance Determination Process +, Biofouling +, Fire Protection Program +, Downpower +  and Manual Operator Action +
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/ML0431/ML043100257.pdf  +
Year
2,004  +
 
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