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ML13038A714
Show incoming properties 
Category
Letter  and Inspection Report
ASME section
ASME Section III +
Accession number
ML13038A714  +
Atomic Element
Carbon +  and Hydrogen +
CFR
10 CFR 50 Appendix R +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 2.390 +, 10 CFR 50.54 +, 10 CFR 50.48#c +  and 10 CFR 50.48#b +
Cornerstone
Barrier Integrity +, Initiating Events +  and Mitigating Systems +
Cross cutting aspect
H.7 +
Docket
05000275  +, 05000323  +, 00275  +  and 00323  +
Document
ML13038A714 +  and ML112010657 +
Drawing
FP-5 +
Equipment trip
Turbine Trip +  and Reactor Trip +
Finding
05000275/FIN-2012008-01 +, 05000275/FIN-2012008-02 +, 05000323/FIN-2012008-01 +  and 05000323/FIN-2012008-02 +
From
Geoffrey Miller +  and NRC/RGN-IV/DRS/EB2 +
Generic letter
NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +
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>.
ML13038A714 +, ML13038A714 +, ML13038A714 +, ML13038A714 +, ML13038A714 +, ML13038A714 +, ML13038A714 +, ML13038A714 +, ML13038A714 +, ML13038A714 +  and ML13038A714 +
Inspection Manual Chapter
NRC Inspection Manual 0609 +, NRC Inspection Manual 0609/Appendix F +, IMC 0305, Operating Reactor Assessment Program +  and IMC 0310, Aspects within the Cross-Cutting Areas +
Inspection procedure
IP 71111.05T +
Inspection report
IR 05000275/2012008 +
Issue date
February 7, 2013  +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
16:14:06, 11 January 2025  +
NFPA
NFPA 805 +
NRC information notice
Information Notice 92-18 +
NUREG
NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +  and NUREG-6850 +
Page count
42  +
Power source
4kV +
Procedure
MP +, CP +  and CP-M10 +
SSC
1E-4 +, 3BB-100 +, 3BB-115 +, 3CC-100 +, 3CC-115 +, 52-1F-05 +, 52-1F-66 +, 52-1F-50 +, 52-1F-38 +  and 52-1F-39 +
See also
IR 05000275/2012008 +
Site
Diablo Canyon +
Site license
Diablo Canyon +
Start date
February 7, 2013  +
State
Texas +, Washington +  and California +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Transformer +, Shutdown Cooling +, HVAC +, Residual Heat Removal +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Auxiliary Feed Water +  and Main Steam +
TS
TS-5.4.1.d +
Title
IR 05000275-12-008 & 05000323-12-008, October 22 to December 20, 2012, Pacific Gas and Electric Company; Diablo Canyon Power Plant, Units 1 and 2; Triennial Fire Protection Team Inspection  +
To
Pacific Gas & Electric +  and Halpin E +
Topic
Hot Short +, Safe Shutdown +, Unanalyzed Condition +, Fire Barrier +, Enforcement Discretion +, Probabilistic Risk Assessment +, Multiple Spurious Operation +, Emergency Lighting +, B.5.b +, Significance Determination Process +, Loss of Offsite Power +, Time Critical Operator Action +  and Fire Protection Program +
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http://pbadupws.nrc.gov/docs/ML1303/ML13038A714.pdf  +
 
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