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ML18221A210
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI 18.1 +, ANSI N18.1-1971 +, ANSI 18.1-1971 +, NQA-1-1994 +  and ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +
Accession number
ML18221A210  +
CFR
10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 2 +, 10 CFR 50.65 +, 10 CFR 72.48 +, 10 CFR 50.54#q +, 10 CFR 50.54#i +  and 10 CFR 55.59#c5 +
Cornerstone
Emergency Preparedness +  and Physical Protection +
Docket
05000395  +
From
South Carolina Electric & Gas Company +
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ML18221A210 +, ML18221A210 +, ML18221A210 +, ML18221A210 +, ML18221A210 +, ML18221A210 +, ML18221A210 +, ML18221A210 +, ML18221A210 +, ML18221A210 +, ML18221A210 +, ML18221A210 +, ML18221A210 +, ML18221A210 +  and ML18221A210 +
In package
ML18221A142 +
Issue date
May 31, 2018  +
Letter
IR 05000395/1980032 +  and ML19297C081 +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
Westinghouse +
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>.
20:14:09, 5 January 2025  +
NUREG
NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +
Page count
69  +
Procedure
Emergency Operating Procedure +  and SAP-131 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.8 +, Regulatory Guide 1.28 +  and Regulatory Guide 1.64 +
SSC
07-16-009 +, 17S-1 +, 07-11-004 +, 13A-1 +, 12aA-7 +, 13A-2 +, 07-01-117 +, 07-03-024 +, 07-10-006 +, 07-98-150 +, 07-98-152 +  and 07-11-040 +
Site
Summer +
Start date
May 31, 2018  +
State
Virginia +  and South Carolina +
System
Steam Generator +  and Feedwater +
Title
Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Fitness for Duty +, High winds +, Shutdown Margin +, High Radiation Area +, Anticipated operational occurrence +, Probabilistic Risk Assessment +, Shift Technical Advisor +, Maintenance Rule Program +, Fatigue Rule +  and Fire Protection Program +
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http://pbadupws.nrc.gov/docs/ML1822/ML18221A210.pdf  +
 
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