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ML19345D998
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Category
INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE
Accession number
ML19345D998  +
Atomic Element
Iodine +
Docket
05000373  +, 05000374  +, 00373  +  and 00374  +
Engineering change
EC-503 +
Equipment trip
Turbine Trip +
From
Bournia A +  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>.
ML19345D998 +, ML19345D998 +, ML19345D998 +, ML19345D998 +, ML19345D998 +, ML19345D998 +, ML19345D998 +, ML19345D998 +, ML19345D998 +, ML19345D998 +, ML19345D998 +, ML19345D998 +, ML19345D998 +, ML19345D998 +, ML19345D998 +  and ML19345D998 +
IEEE
IEEE 27 +
Issue date
December 8, 1980  +
Letter
ML19209C856 +  and ML17192A875 +
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>.
14:32:37, 24 December 2024  +
NUREG
NUREG-0731, Summary of 860314 Meeting W/Util in Bethesda,Md Re Qualifications of Radiation Protection Manager as Compared to Qualifications Outlined in 1975 Rev 1 to Reg Guide 1.8, Personnel Selection & Training. Viewgraphs Encl +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, 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-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0727, Forwards Addendum to NUREG-0727, Fes Re Operation of Joseph M Farley Nuclear Plant,Units 1 & 2 +, NUREG-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +
Page count
33  +
Procedure
AM +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.3 +
Report
NEDO-21354 +
SSC
1UREG-0731 +  and 1UREG-0696 +
Scram
Manual Scram +
Site
LaSalle +
Start date
December 8, 1980  +
State
Maryland +  and Illinois +
System
Reactor Coolant System +, Feedwater +, Reactor Protection System +, Main Steam Isolation Valve +, Primary containment +, Shutdown Cooling +, HVAC +, Residual Heat Removal +, Standby Liquid Control +, Remote shutdown +, Safety Relief Valve +  and Control Rod +
Title
Notification of 801217 Meeting W/Util to Discuss All Open Items Re Facility Ser,Both TMI & non-TMI  +
To
Youngblood B +  and Office of Nuclear Reactor Regulation +
Topic
Emergency Lighting +, Scram Discharge Volume +, Shift Technical Advisor +  and Spill +
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http://pbadupws.nrc.gov/docs/ML1934/ML19345D998.pdf  +
 
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