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ML091040206
Show incoming properties 
Category
Calculation
ASME section
ASME Section IX +  and ASME Section III +
Accession number
ML091040206  +
Atomic Element
Boron +  and Lead +
CFR
10 CFR 50.48#c +  and 10 CFR 50 Appendix R +
Docket
05000269  +, 05000270  +  and 05000287  +
From
Duke Energy +  and Parker D +
Generic letter
NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +  and NRC Generic Letter 81-12, Fire Protection Rule (45 FR 76602, 11/19/80) +
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ML091040206 +, ML091040206 +, ML091040206 +, ML091040206 +, ML091040206 +, ML091040206 +, ML091040206 +, ML091040206 +, ML091040206 +, ML091040206 +  and ML091040206 +
Hours
8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +  and 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +
In package
ML091040234 +
Issue date
May 29, 2008  +
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>.
17:25:34, 14 January 2025  +
NEI
NEI 00-0 +, NEI 04-02, NFPA 805 Transition FAQ 10-0059, Rev 0 +  and NEI 00-01, Guidance for Post Fire Safe Shutdown Circuit Analysis +
NFPA
NFPA 805 +  and NFPA 605 +
NRC information notice
Information Notice 84-09 +
Page count
135  +
Power source
4.16KV +  and 4.16kV +
Procedure
ES +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.205 +
Regulatory Issue Summary
RIS 2004-03, NRC Regulatory Issues Summary (RIS) 2004-03, Revision 1: Risk-Informed Approach for Post-Fire Safe-Shutdown Circuit Inspection (Formerly RIS 2004-003) +
SSC
6SC-9291 +
Scram
Manual Scram +
Site
Oconee +
Start date
May 29, 2008  +
System
Steam Generator +, Feedwater +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Automatic Depressurization System +, Decay Heat Removal +, Safety Relief Valve +  and Control Rod +
Title
Calculation No. OSC-9291, Rev. 0, NFPA 805 Transition B-2 Table  +
To
Office of Nuclear Reactor Regulation +
Topic
Hot Short +, Safe Shutdown +, Shutdown Margin +, Fire Barrier +, Operator Manual Action +, Multiple Spurious Operation +, Emergency Lighting +, Thermoset +, Loss of Offsite Power +, Earthquake +, Fire Protection Program +  and Manual Operator Action +
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http://pbadupws.nrc.gov/docs/ML0910/ML091040206.pdf  +
 
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