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ML17171A262
Show incoming properties
Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI B31.1 +  and ANSI B31.7 +
ASME section
ASME Section XI +  and ASME Section III +
Accession number
ML17171A262  +
Atomic Element
Carbon +, Oxygen +, Molybdenum +  and Lead +
CFR
10 CFR 50 Appendix J +, 10 CFR 50.12 +, 10 CFR 50.61 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.3 +, 10 CFR 50.61#b2 +, 10 CFR 54.21#c1 +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii +, 10 CFR 50.55a#g6iiD +  and 10 CFR 50.55a#g6iiE +
Code case
ASME Code Case N-729-1 +, ASME Code Case N-722-1 +  and ASME Code Case N-770-1 +
Correspondence
L-2017-074, Redacted - St. Lucie, Unit 1, Updated Final Safety Analysis Report, Amendment No. 28, Chapter 12, Radiation Protection +, L-2015-272, 1301103.401, Revision 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L, May 2015 +, L-2011-253, Preparation and Scheduling of Operator Licensing Examinations +  and L-2002-222, Attachment 1, Supplemental Response to NRC Requests for Additional Information for Review of St. Lucie Units 1 & 2, License Renewal Application +
Docket
05000335  +
Document
ML12235A463 +, ML12181A019 +, ML16235A138 +  and L-2011-523, Response to NRC Steam Generator Tube Integrity and Chemistry Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request +
EPRI MRP
MRP-227 +
From
NextEra Energy +
Generic letter
NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +  and NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
ML17171A262 +, ML17171A262 +, ML17171A262 +, ML17171A262 +, ML17171A262 +, ML17171A262 +, ML17171A262 +, ML17171A262 +, ML17171A262 +  and ML17171A262 +
In package
ML17172A000 +
Issue date
May 3, 2017  +
L
L-2017-074, Redacted - St. Lucie, Unit 1, Updated Final Safety Analysis Report, Amendment No. 28, Chapter 12, Radiation Protection +, L-2015-272, 1301103.401, Revision 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L, May 2015 +, L-2011-253, Preparation and Scheduling of Operator Licensing Examinations +  and L-2002-222, Attachment 1, Supplemental Response to NRC Requests for Additional Information for Review of St. Lucie Units 1 & 2, License Renewal Application +
License amendment topic
License Renewal Application +
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>.
00:08:00, 9 January 2025  +
NEI
NEI 97-06, Steam Generator Conditioning Monitoring Report +
NFPA
NFPA 25 +
NRC bulletin
NRC Bulletin 88-11 +
NUREG
NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG/CR-6583 +, NUREG/CR-5999, Forwards Updated Fatigue Design Curves for Austenitic Stainless Steels in LWR Environments.Design Curves Being Provided in Advance of Future Update of NUREG/CR-5999 to Facilitate Efforts on Resolution of GSI-190 +, NUREG-1779, Safety Evaluation Report Related to License Renewal of St. Lucie Nuclear Plant, Units 1 & 2 +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +
Page count
23  +
Project stage
Request  +
Regulatory Issue Summary
RIS 2003-09, Environmental Qualification of Low-Voltage Instrumentation and Control Cables +
Site
Saint Lucie +
Start date
May 3, 2017  +
State
Idaho +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Auxiliary Feedwater +, Reactor Pressure Vessel +  and Main Steam +
TS
TS-5.6 +
Title
Updated Final Safety Analysis Report, Amendment No. 28, Chapter 18, Aging Management Programs and Time-Limited Aging Analyses Activities  +
To
Office of Nuclear Reactor Regulation +
Topic
Boric Acid +, Nondestructive Examination +, Aging Management +, Flow Accelerated Corrosion +, Microbiologically influenced corrosion +, Stress corrosion cracking +, Moisture barrier +, License Renewal +, EVT-1 +, Fire Protection Program +, Power Uprate +, Thermal fatigue +, Metamic +  and Leak-Before-Break +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
http://pbadupws.nrc.gov/docs/ML1717/ML17171A262.pdf  +
WCAP
WCAP-15973 +, WCAP-15973-P-A +  and WCAP-15793-P-A +
Westinghouse report
WCAP-15973 +, WCAP-15973-P-A +  and WCAP-15793-P-A +
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