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ML16257A084
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Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI N13.1-1969 +, ANSI N101.4-72 +, ANSI N101.6-72 +  and ANSI/ANS-6.1.1-1991 +
ASME section
ASME Section XI +
Accession number
ML16257A084  +
Atomic Element
Boron +, Iodine +, Oxygen +, Lead +, Helium +  and Silicon +
CFR
10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50 Appendix J +  and 10 CFR 20.1003 +
DRN
DRN-99-2362 +, DRN-02-110 +, DRN-03-2066 +, DRN-05-144 +, DRN-99-1098 +, DRN-06-1029 +, DRN-02-407 +  and DRN-05-455 +
Docket
05000382  +, 00317  +, 00355  +  and 00336  +
Effective date
January 1, 1994  +
Engineering change
EC-12329 +  and EC-14275 +
From
Entergy +
General design criterion
GDC 63 +  and GDC 19, Control room +
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ML16257A084 +, ML16257A084 +, ML16257A084 +, ML16257A084 +, ML16257A084 +, ML16257A084 +, ML16257A084 +, ML16257A084 +, ML16257A084 +  and ML16257A084 +
Hours
2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +
IEEE
IEEE 279-1971 +, IEEE 308-1971 +  and IEEE 344-1971 +
In package
ML16256A115 +
Isotope
Cs-137 +, Kr-85 +  and N-16 +
Issue date
August 25, 2016  +
License amendment topic
Alternate Source Term +
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>.
01:20:55, 10 January 2025  +
Page count
38  +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.183 +, Regulatory Guide 1.45 +, Regulatory Guide 1.52 +, Regulatory Guide 1.21 +, Regulatory Guide 8.8 +, Regulatory Guide 8.10 +  and Regulatory Guide 1.69 +
SSC
1E-4 +, 6E-8 +, 3B-S +, 3A-S +, 07-06-319 +, 07-00-801 +, C163T-1971 +, 6A-L +, 07-02-407 +, W3F1-2016-0053, Redacted - Waterford Steam Electric Station, Unit 3, Revision 309 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components Equipment and Systems, Section 3.8, Figures 3.8-1 Through 3.8-47 +, 7x10-10 +  and 3A-H +
Site
Waterford +
Start date
August 25, 2016  +
State
Florida +
System
Steam Generator +, Reactor Coolant System +, Reactor Pressure Vessel +  and Shield Building +
Title
09 to Final Safety Analysis Report, Chapter 12, Radiation Protection, Section 12.3  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, High Radiation Area +, Offsite Dose Calculation Manual +, Anticipated operational occurrence +, Coatings +, Loss of Offsite Power +, Pressure boundary leak +  and Unidentified leak +
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http://pbadupws.nrc.gov/docs/ML1625/ML16257A084.pdf  +
 
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