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ML090210242
Show incoming properties 
Category
Meeting Briefing Package/Handouts  and Slides and Viewgraphs
ASME section
ASME Section III +
Accession number
ML090210242  +
Atomic Element
Boron +  and Lead +
CFR
10 CFR 50 +  and 10 CFR 50.90 +
Docket
05000482  +
Equipment trip
Reactor Trip +
From
Wolf Creek +
General design criterion
GDC 55 +
Generic letter
NRC Generic Letter 80-14, LWR Primary Coolant System Pressure Isolation Valves +  and NRC Generic Letter 87-06, Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves +
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ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +, ML090210242 +  and ML090210242 +
In package
ML090210167 +
Issue date
January 15, 2009  +
Manufacturer
Westinghouse +
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18:39:46, 14 January 2025  +
NUREG
NUREG-0881, Safety Evaluation Accepting Licensee Submittals & Addl Info on Environ Qualification & Design for Instrumentation,Per Reg Guide 1.97 +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +
Page count
39  +
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ML090210242 +
Project
TAC:ME0280 +
Project reference
TAC:ME0280 +
Project stage
Meeting  +
Site
Wolf Creek +
Start date
January 15, 2009  +
TS
TS-3.6.3 +
Title
Licensee Slides, January 15, 2009, Category 1 Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Changes to Post Fire Shutdown Unresolved Items Analysis Methods Pre-Application for Wolf Creek Generating Station  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Operator Manual Action +  and Pre-application +
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http://pbadupws.nrc.gov/docs/ML0902/ML090210242.pdf  +
 
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