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ML21104A074
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ACI
ACI-318 +  and ACI-307 +
ASME section
ASME Section III +
Accession number
ML21104A074  +
Atomic Element
Boron +, Nitrogen +, Oxygen +, Hydrogen +, Xenon +  and Zinc +
CFR
10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.44 +, 10 CFR 50 Appendix G +  and 10 CFR 50.54 +
Contact
Blake Purnell +
Correspondence
L-20-234, 3 to Updated Final Safety Analysis Report, Drawings - Part 7 of 7 (Redacted) +
Docket
05000346  +
Drawing
Drawing 1.5-6 +, Drawing 1.5-7 +, Drawing 1.5-8 +, Drawing 1.5-12 +  and Drawing 1.5-22 +
Effective date
October 16, 2003  +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Energy Harbor Nuclear Corp +
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ML21104A074 +, ML21104A074 +, ML21104A074 +, ML21104A074 +, ML21104A074 +, ML21104A074 +, ML21104A074 +, ML21104A074 +, ML21104A074 +  and ML21104A074 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
IEEE
IEEE 279 +, IEEE 279-1971 +  and IEEE 308 +
In package
ML21103A117 +
Isotope
H-3 +
Issue date
September 25, 2020  +
L
L-20-234, 3 to Updated Final Safety Analysis Report, Drawings - Part 7 of 7 (Redacted) +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
Chicago Bridge & Iron +
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14:48:27, 29 November 2024  +
Page count
67  +
Power source
4.16kV +  and 345kV +
Project stage
Request  +
Regulatory Issue Summary
RIS 2015-17, Review and Submission of Updates to Final Safety Analysis Reports, Emergency Preparedness Documents, and Fire Protection Documents +
SSC
S9N16-2 +, S9N16-3 +, S9N16-4 +, S9N16-1 +  and S6N370-2 +
Site
Davis Besse +
Site license
Davis Besse +
Start date
September 25, 2020  +
State
Ohio +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Turbine +, Shutdown Cooling +, Reactor Pressure Vessel +, Control Room Emergency Ventilation +, Shield Building +, Circulating Water System +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +, Containment Spray +, Low Pressure Coolant Injection +, Extraction steam +  and Emergency Feedwater System +
Title
3 to Updated Final Safety Analysis Report, Section 1, Introduction General Description of Station (Redacted)  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, Offsite Dose Calculation Manual +, Fire Barrier +, Incorporated by reference +, Loss of Offsite Power +, Earthquake +, Turbine Missile +, Fuel cladding +, Offsite Circuit +, Flow Induced Vibration +  and Overspeed +
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http://pbadupws.nrc.gov/docs/ML2110/ML21104A074.pdf  +
Ultimate Heat Sink
Cooling Tower +  and Lake Erie +
Vendor
Framatome +
 
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