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ML21104A354
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Category
Updated Final Safety Analysis Report (UFSAR)
ASME section
ASME Section III +  and ASME Section IX +
Accession number
ML21104A354  +
Agency
American Society of Civil Engineers +
Atomic Element
Iron +, Nitrogen +, Hydrogen +  and Lead +
CFR
10 CFR 50 Appendix A +, 10 CFR 100 +  and 10 CFR 50 +
Code case
ASME Code Case N-411 +
Contact
Blake Purnell +
Correspondence
L-20-234, 3 to Updated Final Safety Analysis Report, Drawings - Part 7 of 7 (Redacted) +
Docket
05000346  +
Equipment trip
Reactor Trip +  and Turbine Trip +
From
Energy Harbor Nuclear Corp +
General design criterion
GDC 2, Design bases for protection against natural phenomena +  and GDC 4, Environmental and dynamic effects design bases +
Generic letter
NRC Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements +
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ML21104A354 +, ML21104A354 +, ML21104A354 +, ML21104A354 +, ML21104A354 +, ML21104A354 +, ML21104A354 +, ML21104A354 +, ML21104A354 +  and ML21104A354 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
In package
ML21103A117 +
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
Westinghouse +  and General Electric +
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09:10:23, 16 March 2025  +
NFPA
NFPA 30 +
NUREG
NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +
Page count
192  +
Power source
4.16kV +
Procedure
ES +, TP +  and CP +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.45 +, Regulatory Guide 1.26 +, Regulatory Guide 1.29 +  and Regulatory Guide 1.46 +
Regulatory Issue Summary
RIS 2015-17, Review and Submission of Updates to Final Safety Analysis Reports, Emergency Preparedness Documents, and Fire Protection Documents +
SSC
3B-1 +, 3C-1 +, 3A-1 +, 3D-1 +, D1PA-structu +  and D1NA-structu +
Scram
Manual Scram +  and Automatic Scram +
Site
Davis Besse +
Start date
September 25, 2020  +
State
California +  and Arkansas +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Turbine +, HVAC +, Shield Building +, Circulating Water System +, Main Steam Safety Valve +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +, Extraction steam +  and Emergency Feedwater System +
Title
3 to Updated Final Safety Analysis Report, Section 3, Design Criteria- Structures, Components, Equipment, and Systems, Part 1 of 3 (Redacted)  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, High winds +, Tornado Missile +, Safe Shutdown Earthquake +, Hydrostatic +, Operating Basis Earthquake +, High Energy Line Break +, Abnormal operational transient +, Design basis earthquake +, Feedwater Heater +, Loss of Offsite Power +, Earthquake +, Commercial Grade +, Turbine Missile +, GOTHIC +  and Leak-Before-Break +
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http://pbadupws.nrc.gov/docs/ML2110/ML21104A354.pdf  +
Ultimate Heat Sink
Cooling Tower +
WCAP
WCAP-7897 +
Westinghouse report
WCAP-7897 +
 
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