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ML17130A273
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ACI
ACI-318 +
ANSI code
ANSI B31.1 +, ANSI B16.5 +, ANSI B31.1.0 +, ANSI B31.1-1967 +, ANSI B31.1-1973 +, ANSI B31.1-1977 +  and ANSI B31.1 - 1980 +
ASME section
ASME Section XI +, ASME Section III +, ASME Section I +, ASME Section IX +, ASME Section II +  and ASME Section VIII +
Accession number
ML17130A273  +
Atomic Element
Nitrogen +, Carbon +, Hydrogen +, Molybdenum +  and Lead +
Code case
ASME Code Case N-411-1 +
Correspondence
ND-3600 +
Docket
05000277  +, 05000278  +, 00237  +  and 00249  +
From
Exelon +
Generic letter
NRC Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements +
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ML17130A273 +, ML17130A273 +, ML17130A273 +, ML17130A273 +, ML17130A273 +, ML17130A273 +, ML17130A273 +, ML17130A273 +, ML17130A273 +  and ML17130A273 +
In package
ML17130A259 +
Issue date
April 6, 2017  +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
Limitorque +
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>.
13:28:35, 9 January 2025  +
ND
ND-3600 +
Page count
107  +
Procedure
SP +, TP +, SP-66 +, ES-5 +  and SP-5 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.84 +  and Regulatory Guide 1.60 +
SSC
07-14-14A +
Site
Peach Bottom +
Start date
April 6, 2017  +
System
Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Fuel Pool Cooling and Cleanup +, Standby Liquid Control +, Core Standby Cooling System +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam +  and Extraction steam +
Title
6 to Updated Final Safety Analysis Report, Appendix a, Pressure Integrity of Piping and Equipment Pressure Parts  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Hydrostatic +, Operating Basis Earthquake +, Nondestructive Examination +, High Energy Line Break +, Scram Discharge Volume +, Intergranular Stress Corrosion Cracking +, Loss of Offsite Power +, Excess Flow Check Valve +, Earthquake +, Liquid penetrant +, Dissimilar Metal Weld +, Power Uprate +  and Eddy Current Test +
Trip
Turbine Control Valve Fast Closure +
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http://pbadupws.nrc.gov/docs/ML1713/ML17130A273.pdf  +
 
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