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ML23129A272
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ASME section
ASME Section VI +  and ASME Section XIV +
Accession number
ML23129A272  +
Atomic Element
Nitrogen +, Hydrogen +  and Lead +
CFR
10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 5 +, 10 CFR 54 +, 10 CFR 54.4#a1 +  and 10 CFR 50.46#b +
Docket
05000298  +
From
Nebraska Public Power District +
Generic letter
NRC Generic Letter 08-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems +
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ML23129A272 +, ML23129A272 +, ML23129A272 +, ML23129A272 +, ML23129A272 +, ML23129A272 +, ML23129A272 +, ML23129A272 +, ML23129A272 +  and ML23129A272 +
In package
ML23129A261 +
Issue date
April 20, 2023  +
Manufacturer
General Electric +
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>.
10:01:57, 27 November 2024  +
NRC bulletin
NRC Bulletin 96-03 +
Page count
1  +
Person
None none +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.49 +
Report
NEDO-10329 +, NEDO-32686 +, NEDO-30832 +, NEDE-23785 +, NEDO-24011 +, NEDO-20566 +, NEDC-32914P +, NEDC-32687P +, NEDO-24045 +, NEDO-21335 +, NEDO-21337 +, NEDO-21702 +  and NEDC-32919P +
SSC
002N7432-Rl +
Site
Cooper +
Start date
April 20, 2023  +
System
Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Primary Containment Isolation System +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Automatic Depressurization System +, Core Standby Cooling System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +  and Low Pressure Coolant Injection +
TS
TS-5.5.2 +
Test
Bench test +
Title
1 to Updated Safety Analysis Report, Section VI, Emergency Core Cooling Systems  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Reactor Vessel Water Level +, Stroke time +, Internal Flooding +, Aging Management +, Abnormal operational transient +, Local Leak Rate Testing +, Design basis earthquake +, MELLLA +, License Renewal +, Earthquake +, Turbine Missile +, Exclusive Use +, Overspeed +, Water hammer +  and Gas accumulation +
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http://pbadupws.nrc.gov/docs/ML2312/ML23129A272.pdf  +
 
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