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ML030690029
Show incoming properties 
Category
Letter, Technical Specification, Amendment  and License-Application for Facility Operating License (Amend/Renewal) DKT 50
ASME code
IWA-4720 +
ASME section
ASME Section XI +, ASME Section III +  and ASME Section II +
Accession number
ML030690029  +
Atomic Element
Boron +, Iodine +, Hydrogen +  and Lead +
CFR
10 CFR 50.72 +, 10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.59 +, 10 CFR 50.4 +, 10 CFR 50.90 +, 10 CFR 50.91 +, 10 CFR 50.92 +, 10 CFR 50.55a +, 10 CFR 50.73#a2iiA +, 10 CFR 50.72#b3iiA +, 10 CFR 50.72#b2 +, 10 CFR 50.36#c2ii +, 10 CFR 170.11#a1iii +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +  and 10 CFR 50.71#e +
Cornerstone
Barrier Integrity +
Docket
05000413  +, 05000414  +, 00413  +, 00414  +, 00282  +  and 00306  +
Equipment trip
Reactor Trip +
From
Duke Energy +  and Gordon Peterson +
General design criterion
GDC 14 +, GDC 30 +  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>.
ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +, ML030690029 +  and ML030690029 +
Hours
1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 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)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +  and 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +
Issue date
February 25, 2003  +
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>.
23:07:02, 23 March 2020  +
NEI
NEI 97-06, Steam Generator Conditioning Monitoring Report +
Page count
93  +
Procedure
ST +
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.
ML030690029 +
Project
TAC:MB7842 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.45 +  and Regulatory Guide 1.121 +
SR
SR-3.0.3 +, SR-3.4.13.1 +, SR-3.0.2 +, SR-3.4.18.2 +, SR-3.4.5.2 +, SR-3.4.6.2 +, SR-3.4.13.2 +  and SR-3.4.18.1 +
Site
Catawba +
Site license
NPF-52 +  and NPF-35 +
Start date
February 25, 2003  +
State
Washington +  and South Carolina +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Residual Heat Removal +, Main Steam Safety Valve +, Emergency Core Cooling System +, Main Steam Line +, Main Steam +  and Containment Spray +
TS
TS-3.4.14 +, TS-3.4.13 +, TS-5.5.9 +, TS-3.3.3 +, TS-3.4.5 +, TS-3.7.10 +, TS-3.4.4 +, TS-3.7.5 +, TS-3.4.8 +, TS-3.9.3 +, TS-3.4.1 +, TS-3.4.6 +, TS-3.4.7 +, TS-3.7.12 +, TS-3.4.15 +, TS-3.9.5 +, TS-3.7.13 +, TS-3.9.4 +, TS-3.4.17 +, TS-3.6.10 +, TS-5.6.8 +, TS-3.4.18 +  and TS-3.4.13.d +
Title
Application for Amendment to Licenses NPF-35 & NPF-52, to Change & Add Technical Specifications  +
To
Office of Nuclear Reactor Regulation +  and Document Control Desk +
Topic
Non-Destructive Examination +, Post Accident Monitoring +, Operating Basis Earthquake +, Nondestructive Examination +, Aging Management +, Stress corrosion cracking +, Loss of Offsite Power +, Fuel cladding +, Pressure Boundary Leakage +, Unidentified leakage +, Eddy-Current Testing +  and Operational leakage +
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http://pbadupws.nrc.gov/docs/ML0306/ML030690029.pdf  +
 
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