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ML19208C501
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Category
OPERATING LICENSES & AMENDMENTS  and TEXT-LICENSE APPLICATIONS & PERMITS
ASME section
ASME Section III +  and ASME Section XII +
Accession number
ML19208C501  +
Act
Atomic Energy Act of 1954 +
Atomic Element
Boron +, Sodium +  and Lead +
CFR
10 CFR 51 +
Docket
05000321  +  and 00321  +
Equipment trip
Turbine Trip +
From
Ippolito T +  and Office of Nuclear Reactor Regulation +
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>.
ML19208C501 +, ML19208C501 +, ML19208C501 +, ML19208C501 +, ML19208C501 +, ML19208C501 +, ML19208C501 +, ML19208C501 +, ML19208C501 +, ML19208C501 +  and ML19208C501 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
In package
ML19208C502 +
Issue date
August 6, 1979  +
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>.
04:30:11, 5 January 2025  +
Page count
24  +
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ML19208C501 +
Project stage
Other  +
Report
NEDo-24175 +  and NEDO-24175 +
SR
SR-3.11 +
SSC
E0C4-during +  and E0C4-2000 +
Scram
Manual Scram +
Site
Hatch +
Site license
Hatch +
Start date
August 6, 1979  +
State
Washington +  and Georgia +
System
Reactor Coolant System +, Feedwater +, Secondary containment +, Reactor Protection System +, Primary containment +, Reactor Pressure Vessel +, Core Standby Cooling System +, Main Steam Line +, Rod Worth Minimizer +, Rod Sequence Control System +  and Control Rod +
TS
TS-2.1.A +
Title
Amend 69 to License DPR-57,changing Tech Specs to Permit Operation of Facility During Cycle 4 w/164 Reload Fuel Assemblies & to Permit Mod of Average Power Range Monitor Trip Sys by Adding Thermal Power Monitor  +
Topic
Reactor Vessel Water Level +, Hydrostatic +, Abnormal operational transient +, Scram Discharge Volume +, Fuel cladding +, Unidentified leakage +  and Overspeed +
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http://pbadupws.nrc.gov/docs/ML1920/ML19208C501.pdf  +
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