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ML17164A314
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Category
Quality Assurance Program
ACI
ACI-318 +  and ACI-349 +
ANSI code
ANSI N45.2 +, ANSI/ANS 3.1-1981 +, ANSI 3.1-1981 +, ANSI 18.7 +, ANSl/ANS-3.1-1981 +, NQA-1-1994 +, ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +  and ANSl/ANS-N18.1-1971 +
ASME section
ASME Section XI +, ASME Section I +, ASME Section IV +  and ASME Section VIII +
Accession number
ML17164A314  +
Atomic Element
Oxygen +  and Lead +
CFR
10 CFR 21 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 Appendix B +, 10 CFR 72 +, 10 CFR 71 +, 10 CFR 50.71 +, 10 CFR 73.55 +, 10 CFR 72.212 +, 10 CFR 50.54#t +, 10 CFR 73.55#m +  and 10 CFR 71.106#b +
Cornerstone
Emergency Preparedness +
Cross cutting aspect
H.3(s) +  and H.1(r) +
Docket
05000272  +, 05000311  +  and 05000354  +
Equipment trip
Reactor Trip +
Exelon procedure
HU-AA-1101 +, NO-AA-10 +, NO-AA-400-001 +  and NO-AA-1 +
From
PSEG +
General design criterion
GDC 3, Fire protection +
Generic letter
NRC Generic Letter 89-02, Actions to Improve the Detection of Counterfeit and Fraudulently Marketed Products +
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ML17164A314 +, ML17164A314 +, ML17164A314 +, ML17164A314 +, ML17164A314 +, ML17164A314 +, ML17164A314 +, ML17164A314 +, ML17164A314 +  and ML17164A314 +
Hours
2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +
INPO document
INPO-10-007 +
In package
ML17157B235 +
Issue date
February 24, 2017  +
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>.
00:20:30, 9 January 2025  +
NUREG
NUREG/CR-6407 +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
144  +
Procedure
SP +, ESP +  and CP-189 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.33 +, Regulatory Guide 1.143 +, Regulatory Guide 1.26 +, Regulatory Guide 4.15 +, Regulatory Guide 1.8 +, Regulatory Guide 1.29 +, Regulatory Guide 1.120 +, Regulatory Guide 1.142 +  and Regulatory Guide 1.31 +
SSC
2A-1 +, 2A-3 +, 1day-to +  and 9lE7-fn +
Site
Salem +  and Hope Creek +
Start date
February 24, 2017  +
State
New Jersey +
System
Primary containment +, Reactor Recirculation Pump +  and Decay Heat Removal +
Title
Enclosures 1 & 2: PSEG Nuclear, LLC Quality Assurance Topical Report, NO-AA-10, Revision 86  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Fitness for Duty +, Shutdown Margin +, Non-Destructive Examination +, Offsite Dose Calculation Manual +, Commercial Grade Dedication +, Safe Shutdown Earthquake +, Nondestructive Examination +, Temporary Modification +, Cyber Security +, Emergency Lighting +, Condition Adverse to Quality +, FLEX +, Aging Management +, Foreign Material Exclusion +, Shift Technical Advisor +, Process Control Program +, Operability Determination +, License Renewal +, Commercial Grade +, Fire Protection Program +  and Basic Component +
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http://pbadupws.nrc.gov/docs/ML1716/ML17164A314.pdf  +
 
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