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ML20234E328
Show incoming properties 
Category
CORRESPONDENCE-LETTERS  and INCOMING CORRESPONDENCE
Accession number
ML20234E328  +
Atomic Element
Nitrogen +  and Lead +
Correspondence
NRC-87-95 +
Docket
05000266  +, 05000301  +, 00266  +, 00301  +, 00350  +  and 00750  +
From
Fay C +  and WEC Energy Group +
Generic letter
NRC Generic Letter 87-12, Loss of Residual Heat Removal While the Reactor Coolant System is Partially Filled +
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>.
ML20234E328 +, ML20234E328 +, ML20234E328 +, ML20234E328 +, ML20234E328 +, ML20234E328 +, ML20234E328 +, ML20234E328 +, ML20234E328 +  and ML20234E328 +
Issue date
September 18, 1987  +
Manufacturer
Westinghouse +
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>.
11:39:32, 3 December 2024  +
NRC
NRC-87-95 +
NUREG
NUREG-1269 +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +
Operating procedure
OP-7A +, OP-4D +, OP-5A +, OP-40 +  and OP-4A +
Page count
17  +
Procedure
ST +, SP +  and AOP-9C +
SSC
A0P-9C +
Site
Point Beach +
Start date
September 18, 1987  +
State
Washington +, Michigan +  and Wisconsin +
System
Steam Generator +, Reactor Coolant System +, Residual Heat Removal +  and Decay Heat Removal +
Title
Responds to Generic Ltr 87-12, Loss of RHR While RCS Partially Filled. Each Facility Operated Annually in Partially Drained Condition to Permit Preparation for & Recovery from Core Refueling Operation  +
To
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) +
Topic
Boric Acid +, Reactor Vessel Water Level +  and Core Exit Thermocouple +
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http://pbadupws.nrc.gov/docs/ML2023/ML20234E328.pdf  +
 
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