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ML20081H062
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Category
TEXT-SAFETY REPORT  and QUALITY ASSURANCE PROGRAM
ANSI code
ANSI N45.2.6 +, ANSI N18.1-1971 +, ANSI N45.2 +, ANSI N45.2.11 +, ANSI N45.2.1 +, ANSI N45.2.2 +, ANSI N45.2.8 +, ANSI N101.4-1972 +, ANSI N45.2.12 +, ANSI N45.2.9 +, ANSI N45.2.3 +, ANSI N45.2.10 +, ANSI N45.2.13 +, ANSI N45.2.23 +, ANSI N18.1 +, ANSI N5.9 +, ANSI N18.1 1971 +, ANSI N18.7 - 1976 +, ANSI 18.7 - 1976 +, ANSI B45.2 +, ANSI N45.2 - 1972 +, ANSI N45.23-1973 +, ANSI N45.1.10 +, ANSI N45.2.3-1973 +, ANSI N45.2.6-1978 +, ANSI N45.2.9-1974 +, ANSI N45.2.2 - 1972 +, ANSI N45.2.6-1973 +, ANSI N45.2.12.-1977 +, ANSI N45.2.4 - 1972 +...
ASME section
ASME Section XI +
Accession number
ML20081H062  +
Atomic Element
Nickel +, Copper +, Nitrogen +, Oxygen +, Cadmium +, Lead +, Mercury +  and Zinc +
CFR
10 CFR 50 Appendix B +
Code case
ASME Code Case N-424 +  and ASME Code Case N-356 +
Cornerstone
Emergency Preparedness +
Docket
05000302  +  and 00302  +
From
Duke Energy +
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ML20081H062 +, ML20081H062 +, ML20081H062 +, ML20081H062 +, ML20081H062 +, ML20081H062 +, ML20081H062 +, ML20081H062 +, ML20081H062 +  and ML20081H062 +
In package
ML20081H060 +
Issue date
March 20, 1995  +
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>.
12:53:59, 14 December 2024  +
Page count
103  +
Procedure
Emergency Plan +
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.
ML20081H062 +  and ML20081H062 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.74 +, Regulatory Guide 1.33 +, Regulatory Guide 1.8 +, Regulatory Guide 1.54 +, Regulatory Guide 1.30 +, Regulatory Guide 1.144 +, Regulatory Guide 1.123 +, Regulatory Guide 1.88 +  and Regulatory Guide 1.37, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants +
SSC
17S-1 +
Site
Crystal River +
Start date
March 20, 1995  +
State
Florida +
System
Reactor Coolant System +  and Primary containment +
TS
TS-5.6.1.1 +  and TS-5.1.1 +
Title
Rev 20 to QA Program  +
Topic
Safe Shutdown +, Non-Destructive Examination +, Offsite Dose Calculation Manual +, Coatings +, Nondestructive Examination +, Shift Technical Advisor +, Process Control Program +, License Renewal +, Commercial Grade +  and Fire Protection Program +
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http://pbadupws.nrc.gov/docs/ML2008/ML20081H062.pdf  +
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