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ML17206A057
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Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI/ANS 3.1-1978 +, ANSI N45.2.6 +, ANSI N18.1-1971 +, ANSI/ANS 3.1-1993 +, ANSI N45.2.9 +, ANSI N45.2-1971 +, ANSI/ANS 3.1 1978 +, ANSI N45.2 1971 +, ANSI N18.7 1976 +, ANSI/ANS 4.5 1980 +, ANSI N45.2-1978 +, ANSI N45.2.13-1976 +, ANSI N45.2.9-1974 +, ANSI N45.2.5-1974 +, ANSI N45.2.9 1974 +, ANSI N45.2.5 1974 +, ANSI N45.2.6 1978 +, ANSI N45.2.4 1972 +, ANSI N45.2.11 1974 +, ANSI N45.2.1 1973 +, ANSI N45.2.2 1972 +, ANSI N45.2.3 1973 +, ANSI N45.2.10 1973 +, ANSI N45.2.13 1976 +, ANSI N45.2.23 1978 +, ANSI N45.2.12 1977 +, ANSI N45.2.8 1975 +  and ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +
ASME section
ASME Section XI +  and ASME Section III +
Accession number
ML17206A057  +
Atomic Element
Lead +
CFR
10 CFR 50.73 +, 10 CFR 55 +, 10 CFR 21 +, 10 CFR 20 +, 10 CFR 50.48 +, 10 CFR 50 Appendix B +, 10 CFR 72.74 +, 10 CFR 50.59 +, 10 CFR 72 +, 10 CFR 26.41 +, 10 CFR 72.48 +, 10 CFR 72.75 +, 10 CFR 73 Appendix B +, 10 CFR 73 Appendix C +, 10 CFR 50.54 +, 10 CFR 50.54#t +, 10 CFR 50.54#p3 +, 10 CFR 72.140#d +, 10 CFR 72.140#b +, 10 CFR 72.72#d +, 10 CFR 50.55a#9 +, 10 CFR 50.59#11 +, 10 CFR 73.55#m1 +, 10 CFR 73.56#n1 +, 10 CFR 73.56#n2 +, 10 CFR 72.48#c +, 10 CFR 72.48#3 +, 10 CFR 72.48#b +, 10 CFR 72.48#6 +, 10 CFR 50.71#e +...
Cornerstone
Emergency Preparedness +
Correspondence
DCL-17-038, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 8, Electric Power +
DCL
DCL-17-038, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 8, Electric Power +
Docket
05000275  +  and 05000323  +
Drawing
Drawing 17.5-1 +
From
Pacific Gas & Electric +
General design criterion
GDC 1, Quality standards and records +, GDC 3, Fire protection +  and GDC 5, Sharing of structures, systems, and components +
Generic letter
NRC Generic Letter 82-21, Fire Protection Audits +  and NRC Generic Letter 88-18, Plant Record Storage on Optical Disks +
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>.
ML17206A057 +, ML17206A057 +, ML17206A057 +, ML17206A057 +, ML17206A057 +, ML17206A057 +, ML17206A057 +, ML17206A057 +, ML17206A057 +  and ML17206A057 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
In package
ML17206A046 +
Issue date
December 31, 2016  +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
21:40:12, 8 January 2025  +
NUREG
NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +
Page count
67  +
Power source
4kV +
Procedure
ES-202 +  and CP-189-1995 +
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.
ML17206A057 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.97 +, Regulatory Guide 1.74 +, Regulatory Guide 1.33 +, Regulatory Guide 4.15 +, Regulatory Guide 1.58 +, Regulatory Guide 1.8 +, Regulatory Guide 8.8 +, Regulatory Guide 1.144 +  and Regulatory Guide 1.123 +
SNM license
SNM-2511 +
Site
Diablo Canyon +
Start date
December 31, 2016  +
TS
TS-5.2.1.c +, TS-5.4.1 +, TS-5.1.1 +  and TS-5.2.1.d +
Title
Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 17, Quality Assurance  +
To
Office of Nuclear Reactor Regulation +
Topic
Fitness for Duty +, Offsite Dose Calculation Manual +, Nondestructive Examination +, Condition Adverse to Quality +, FLEX +, Process Control Program +, Safeguards Contingency Plan +, Commercial Grade +, Fire Protection Program +  and Grace period +
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http://pbadupws.nrc.gov/docs/ML1720/ML17206A057.pdf  +
 
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