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ML12054A692
Show incoming properties 
Category
Letter, License-Operating (New/Renewal/Amendments) DKT 50  and Safety Evaluation
ASME section
ASME Section III +
Accession number
ML12054A692  +
Act
Atomic Energy Act of 1954 +
Atomic Element
Lead +
CFR
10 CFR 50.67 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.59 +, 10 CFR 51 +, 10 CFR 50.92 +, 10 CFR 50.36#c2 +, 10 CFR 50.36#c +, 10 CFR 50.91#a +, 10 CFR 54.21#d +, 10 CFR 50.55a#g4 +, 10 CFR 50.55a#c1 +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +, 10 CFR 50.92#c +  and 10 CFR 50.71#e4 +
Contact
Jacqueline Thompson +
Docket
05000413  +, 05000414  +, 00413  +  and 00414  +
Document
ML11188A108 +, ML031070113 +, ML090370782 +, ML080450185 +, ML082100086 +, ML082100097 +, ML111310708 +, ML070570094 +, ML12054A692 +, ML101730389 +, ML093030490 +, ML101730391 +, ML12038A173 +, ML082400710 +, ML12019A250 +, ML053630145 +, ML11188A107 +, ML11195A067 +, ML053630140 +, ML102640537 +, ML111310704 +  and NL-09-1317, Supplemental Information for License Amendment Request to Revise Technical Specification Sections 5.5.9, Steam Generator (SG) Program and TS 5.6.10, Steam Generator Tube Inspection Report for Permanent Alternate Repair Criteria +
FR
77 FR 2766 +
From
Jacqueline Thompson +  and Plant Licensing Branch II +
General design criterion
GDC 15 +, GDC 14 +, GDC 30 +, GDC 31 +, GDC 32 +  and GDC 19, Control room +
Generic letter
NRC Generic Letter 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking +
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>.
ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +, ML12054A692 +...
Hours
4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +  and 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +
Issue date
March 12, 2012  +
Letter
ML102640537 +
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>.
00:50:30, 13 January 2025  +
NEI
NEI 97-06, Steam Generator Conditioning Monitoring Report +
NUREG
NUREG-1570, Summary of ACRS Subcommittees on Matls & Metallurgy and Severe Accidents Meeting on 970304-05 in Rockville,Md Re Staff Draft NUREG-1570, Risk Assessment of Severe Accident Induced Steam Generator Tube Rupture +  and NUREG-0844, Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl +
Page count
48  +
Person
Catherine Haney +  and Nancy Salgado +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
ML12054A692 +
Project
TAC:ME6670 +
Project reference
TAC:ME6670 +, TAC:ME3003 +, TAC:MD0197 +, TAC:ME1339 +  and TAC:ME4108 +
Project stage
Approval  +
Regulatory Guide
Regulatory Guide 1.121 +
SR
SR-3.4.13.1 +  and SR-3.4.13.2 +
Site
Catawba +
Site license
NPF-52 +  and NPF-35 +
Start date
March 12, 2012  +
State
North Carolina +, Washington +  and South Carolina +
System
Steam Generator +, Reactor Coolant System +, Main Steam Line +  and Control Rod +
TS
TS-3.4.13 +, TS-5.5.9 +, TS-3.4 +, TS-5.5.9.c +, TS-5.5.9.b +, TS-5.6.10 +, TS-5.6.8 +, TS-5.5.9.d +, TS-5.5.9.a +, TS-5.6.8.j +, TS-5.6.8.h +, TS-3.4.13.d +  and TS-5.6.B +
Title
Issuance of Amendment Nos. 267 and 263, Revise Technical Specifications for Permanent Alternate Repair Criteria for Steam Generator Tubes  +
To
Duke Energy +  and Morris J +
Topic
Safe Shutdown +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Finite Element Analysis +, Surveillance Frequency Control Program +, Stress corrosion cracking +, Eddy Current Testing +, Pressure Boundary Leakage +, Fire Protection Program +, Unidentified leakage +  and Operational leakage +
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/ML1205/ML12054A692.pdf  +
 
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