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ML20073H264
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Category
TEXT-SAFETY REPORT  and FUEL CYCLE RELOAD REPORTS
ASME section
ASME Section III +
Accession number
ML20073H264  +
Atomic Element
Boron +, Hydrogen +, Xenon +  and Lead +
CFR
10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 60 +, 10 CFR 50.69 +, 10 CFR 60.59 +, 10 CFR 10018 +, 10 CFR 5159 +, 10 CFR 50#M +  and 10 CFR 10#C +
Cornerstone
Initiating Events +
Correspondence
L 103 +, LD-87-013, Informs That CESEC-III Computer Code Applicable to Analysis of FSAR Chapter 14 Events (Excluding ATWS) for Facility. Models Included in Code Applicable to Operating Conditions at Plant & Cover All Features of Facility NSSS +  and LD-82-001, Forwards Proprietary & Nonproprietary Versions of Cesec Digital Sumulation of C-E Nsss. Proprietary Version Available in Central Files Only +
Cross cutting aspect
S.2(f) +  and S.0(f) +
Docket
05000285  +  and 00382  +
Engineering change
EC-111 +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Omaha Public Power District +
Generic letter
NRC Generic Letter 86-06, Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps" +
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ML20073H264 +, ML20073H264 +, ML20073H264 +, ML20073H264 +, ML20073H264 +, ML20073H264 +, ML20073H264 +, ML20073H264 +, ML20073H264 +  and ML20073H264 +
In package
ML19298E441 +
Issue date
March 31, 1991  +
L
L 103 +
LD
LD-82-001, Forwards Proprietary & Nonproprietary Versions of Cesec Digital Sumulation of C-E Nsss. Proprietary Version Available in Central Files Only +  and LD-87-013, Informs That CESEC-III Computer Code Applicable to Analysis of FSAR Chapter 14 Events (Excluding ATWS) for Facility. Models Included in Code Applicable to Operating Conditions at Plant & Cover All Features of Facility NSSS +
Manufacturer
Westinghouse +
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08:46:22, 15 December 2024  +
NRC information notice
Information Notice 90-49 +
Page count
138  +
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ML20073H264 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.121 +
Scram
Manual Scram +  and Automatic Scram +
Site
Fort Calhoun +
Start date
March 31, 1991  +
State
Connecticut +  and Maine +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Steam Safety Valve +, Main Steam Line +, Control Rod +  and Main Steam +
Title
Rev 3 to Omaha Public Power District Nuclear Analysis Reload Core Analysis Methodology - Transient & Accident Methods & Verification  +
Topic
Boric Acid +, Shutdown Margin +, Anticipated operational occurrence +, Loss of Offsite Power +, Fuel cladding +, Coast down +  and Overspeed +
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http://pbadupws.nrc.gov/docs/ML2007/ML20073H264.pdf  +
 
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