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ML21055A067
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ASME section
ASME Section III +
Accession number
ML21055A067  +
Atomic Element
Boron +, Iodine +, Uranium +, Gadolinium +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Xenon +, Zirconium +, Lead +, Helium +, Beryllium +, Aluminum +, Chromium +, Tin +, Antimony +  and Hafnium +
CFR
10 CFR 50 Appendix A +, 10 CFR 50 Appendix K +, 10 CFR 20 Appendix A +  and 10 CFR 50.62 +
Correspondence
NRC-21-0002, 3 to Updated Final Safety Analysis Report, Drawing 6M721-2847, System Diagram Control Center Air Conditioning Air Side Reactor Building +  and NRC-04-0074, Proposed License Amendment Request to Revise Technical Specification 2.1, Safety Limit Minimum Critical Power Ratio +
Docket
05000341  +, 07200071  +, 00265  +, 00277  +  and 00341  +
Equipment trip
Turbine Trip +
From
DTE Energy +
Fuel cladding
Zircaloy +
General design criterion
GDC 12 +, GDC 27 +, GDC 2, Design bases for protection against natural phenomena +, GDC 4, Environmental and dynamic effects design bases +  and GDC 26, Reactivity control system redundancy and capability +
Generic letter
NRC Generic Letter 94-02, Long-Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in BWRs +
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ML21055A067 +, ML21055A067 +, ML21055A067 +, ML21055A067 +, ML21055A067 +, ML21055A067 +, ML21055A067 +, ML21055A067 +, ML21055A067 +, ML21055A067 +, ML21055A067 +, ML21055A067 +  and ML21055A067 +
Hours
6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +
In package
ML21055A091 +
Isotope
U-238 +  and N16 +
Issue date
February 2, 2021  +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
General Electric +  and Honeywell +
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>.
10:04:40, 16 March 2025  +
NRC
NRC-21-0002, 3 to Updated Final Safety Analysis Report, Drawing 6M721-2847, System Diagram Control Center Air Conditioning Air Side Reactor Building +  and NRC-04-0074, Proposed License Amendment Request to Revise Technical Specification 2.1, Safety Limit Minimum Critical Power Ratio +
NRC bulletin
NRC Bulletin 80-07 +
NUREG
NUREG/CR-3052, Amends 141 & 77 to Licenses DPR-57 & NPF-5,respectively Modifying Tech Specs to Permit Only One Recirculation Loop in Operation & to Implement Jet Pump Suveillance Recommendations of NUREG/CR-3052 +
Page count
192  +
Procedure
SAP +, TOP +  and Emergency Plan +
Project reference
TAC:77676 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.190 +  and Regulatory Guide 1.99 +
Report
NEDO-31960 +, NEDO-10802 +, NEDO-10527 +, NEDC-32410P +, NEDC-32505P +, NEDC-32694P +, NEDC-32601P +, NEDE-32906P +, NEDC-32868P +, NEDC-32983P +, NEDO-24154 +, NEDO-20953A +, NEDO-20340 +, NEDO-30130 +, NEDE-10958 +, NEDC-20994 +, NEDE-21156 +, NEDC-30921 +, NEDO-20566 +, NEDO-10958 +, NEDE-20566 +, NEDE-20944 +, NEDO-10602 +, NEDO-20939 +, NEDO-20946 +, NEDO-20964 +, NEDC-31843P +, NEDO-10299A +, NEDO-10722A +, NEDO-21215 +...
SSC
3D-Monicor +
Scram
Automatic Scram +  and Manual Scram +
Site
Fermi +  and 07200071 +
Site license
Quad Cities +  and NPF-43 +
Start date
February 2, 2021  +
State
Ohio +, California +  and New York +
System
Reactor Coolant System +, Feedwater +, Reactor Protection System +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Reactor Water Cleanup +, Shield Building +, Standby Liquid Control +, Intermediate Range Monitor +, Core Standby Cooling System +, Emergency Core Cooling System +, Main Steam Line +, Control rod blade +, Main Condenser +  and Control Rod +
TS
TS-2.1 +
Title
3 to Updated Final Safety Analysis Report, Chapter 4, Reactor  +
To
Office of Nuclear Material Safety and Safeguards +  and Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Shutdown Margin +, Reactor Vessel Water Level +, Safety Limit Minimum Critical Power Ratio +, Grab sample +, Anticipated operational occurrence +, Tornado Missile +, Safe Shutdown Earthquake +, Finite Element Analysis +, Abnormal operational transient +, Feedwater Heater +, Scram Discharge Volume +, Intergranular Stress Corrosion Cracking +, Feedwater Controller Failure +, Stress corrosion cracking +, Overtravel +, Earthquake +, Fuel cladding +, Power change +, Power Uprate +, Eddy Current Test +, GNF3 +, Water rod +, Basic Component +  and Pressure Temperature Limits Report +
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http://pbadupws.nrc.gov/docs/ML2105/ML21055A067.pdf  +
 
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