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ML19340B369
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Category
CORRESPONDENCE-LETTERS, NRC TO UTILITY  and OUTGOING CORRESPONDENCE
ANSI code
ANSI 3.1 +
Accession number
ML19340B369  +
Atomic Element
Iodine +, Nitrogen +, Hydrogen +  and Silver +
Docket
05000416  +  and 05000417  +
Emergency Facility
Technical Support Center +
From
Tedesco R +  and Office of Nuclear Reactor Regulation +
General design criterion
GDC 19, Control room +
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>.
ML19340B369 +, ML19340B369 +, ML19340B369 +, ML19340B369 +, ML19340B369 +, ML19340B369 +, ML19340B369 +, ML19340B369 +, ML19340B369 +, ML19340B369 +, ML19340B369 +, ML19340B369 +, ML19340B369 +, ML19340B369 +  and ML19340B369 +
Isotope
N-16 +
Issue date
September 22, 1980  +
Letter
IR 05000417/1979030 +
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23:44:27, 24 December 2024  +
NUREG
NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, NUREG-0594, Forwards NUREG-0594, Occupational Radiation Exposure at Commercial Nuclear Power Reactors 1978, Re NRC 800729 Response to Tx Pirg Interrogatories & Production of Documents.W/O Encl +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +
Page count
25  +
Regulatory Guide
Regulatory Guide 1.97 +, Regulatory Guide 1.3 +, Regulatory Guide 8.8 +  and Regulatory Guide 8.9 +
Site
Grand Gulf +
Start date
September 22, 1980  +
State
Maryland +, Washington +  and Mississippi +
System
Secondary containment +, Primary containment +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Liquid Control +, Safety Relief Valve +  and Containment Spray +
Title
Forwards Request for Addl Info Re Radiological Controls. Requests Amend to FSAR to Reflect Responses to Encl Requests  +
To
Mcgaughy J +  and MISSISSIPPI POWER & LIGHT CO. +
Topic
Respirator fit test +
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http://pbadupws.nrc.gov/docs/ML1934/ML19340B369.pdf  +
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