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ML110060484
Show incoming properties 
Category
Operating Procedures
Accession number
ML110060484  +
Atomic Element
Boron +, Hydrogen +  and Lead +
CFR
10 CFR 50 Appendix R +, 10 CFR 50 Appendix A +  and 10 CFR 50 +
Docket
05000272  +  and 05000311  +
Emergency Facility
Technical Support Center +
Equipment trip
Reactor Trip +  and Turbine Trip +
From
PSEG +
Generic letter
NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +, NRC Generic Letter 81-21, Natural Circulation Cooldown +  and NRC Generic Letter 81-12, Fire Protection Rule (45 FR 76602, 11/19/80) +
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ML110060484 +, ML110060484 +, ML110060484 +, ML110060484 +, ML110060484 +, ML110060484 +, ML110060484 +, ML110060484 +  and ML110060484 +
Hours
2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +
Issue date
January 28, 2009  +
LER
05000272/LER-99-009 +
Manufacturer
Westinghouse +
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>.
05:36:58, 14 January 2025  +
NRC information notice
Information Notice 2005-14, Fire Protection Findings on Loss of Seal Cooling to Westinghouse Reactor Coolant Pumps +
NUREG
NUREG-0050, Forwards Documents Re 1975 Fire at Plant.Documents Provide Overview of Experience W/Significant Fire That Resulted in Spurious Component Operation,Loss of Control Functions & Erroneous Control Room Instrumentation Readings.W/O Encls +
Page count
155  +
Power source
4kV +  and 115V +
Procedure
ST +, CH +, IMP +, Emergency Operating Procedure +, EP-EP.ZZ-0202 +, EOP-LOP +  and CH-SA.RC-0222 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.68.2 +
SSC
12FA-AB-122A +, 2EE-0147 +, 2EC-3396 +, 2EC-3546 +, 1CCDC-34 +, 1CCDC-36 +, 1CCDC-32 +, 1CDCDG-10 +, 1CDCDG-7 +, 1CDCDG-9 +, 1DAE23-LT2 +, 1DAE23-LT3 +, 1FI-128A +, 12AFI1-A +, 13AFI1-AiS +, 14AFll-AiS +, 12AFII-A +, 13AFII-A +, 14AFII-A +, I1SWI22-A +, 11GB4-14GB4 +, Y2EP6A-T1 +, Y2EP6A-T2 +, I1MSI8-AlS +, 13MSI8-AlS +, 13MS169-AlS +, 12MSI8-AlS +, 14MSI8-AlS +, 12MS171-AlS +, 12MS169-AlS +...
Scram
Manual Scram +
Site
Salem +
Start date
January 28, 2009  +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Main Turbine +, Shutdown Cooling +, Residual Heat Removal +, Remote shutdown +, Decay Heat Removal +, Control Room Envelope +, Main Steam +  and Containment Spray +
Title
Salem/Operations, S1.OP-AB.CR-0002(Q), Rev. 24, Control Room Evacuation Due to Fire in the Control Room, Relay Room, 460/230V Switchgear Room, or 4KV Switchgear Room  +
To
Office of Nuclear Reactor Regulation +
Topic
Hot Short +, Safe Shutdown +, Boric Acid +, Shutdown Margin +, Notice of Violation +, Shift Technical Advisor +, Fire Protection Program +, Scaffolding +, Overspeed trip +, Water hammer +  and Control Room Habitability +
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http://pbadupws.nrc.gov/docs/ML1100/ML110060484.pdf  +
 
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