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ML18151A678
Show incoming properties
Category
CORRESPONDENCE-LETTERS  and OUTGOING CORRESPONDENCE
Accession number
ML18151A678  +
Agency
Virginia Department of Health +
Atomic Element
Carbon +, Lead +  and Bromine +
CFR
10 CFR 50.59 +
Cornerstone
Emergency Preparedness +
Docket
05000280  +, 05000281  +, 00280  +  and 00281  +
Equipment trip
Reactor Trip +  and Turbine Trip +
From
Gallo R +  and NRC (Affiliation Not Assigned) +
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>.
ML18151A678 +, ML18151A678 +, ML18151A678 +, ML18151A678 +, ML18151A678 +, ML18151A678 +, ML18151A678 +, ML18151A678 +, ML18151A678 +, ML18151A678 +, ML18151A678 +  and ML18151A678 +
In package
ML18151A679 +
Inspection procedure
IP 93808 +
Isotope
Cesium-137 +
Issue date
April 26, 1996  +
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>.
00:59:25, 6 January 2025  +
Page count
41  +
Procedure
Emergency Plan +
SSC
07-95-017 +
Scram
Manual Scram +
See also
IR 05000280/1996201 +
Site
Surry +
Site license
Surry +
Start date
April 26, 1996  +
State
Washington +  and Virginia +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Residual Heat Removal +, Control Rod +  and Auxiliary Feed Water +
Test
Bench test +
Title
Forwards Integrated Performance Assessment Process Insp Repts 50-280/96-201 & 50-281/96-201 on 960226-0308.No Violations Noted.Reduced NRC Insp Resources Recommended in Areas of Plant Support  +
To
Ohanlon J +  and Dominion +
Topic
Reactor Vessel Water Level +, High Radiation Area +, Temporary Modification +, Notice of Violation +, Foreign Material Exclusion +, Flow Accelerated Corrosion +, Operability Determination +, Fuel cladding +, Biofouling +, Through Wall Leak +, Core Exit Thermocouple +, Operability Assessment +  and Gas accumulation +
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http://pbadupws.nrc.gov/docs/ML1815/ML18151A678.pdf  +
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