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ML20215J253
Show incoming properties
Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and ENGINEERING/CONSTRUCTION/CONSULTING FIRM TO NRC
ASME section
ASME Section XI +
Accession number
ML20215J253  +
Atomic Element
Boron +, Nitrogen +  and Sodium +
CFR
10 CFR 50.55a#g5iii +
Docket
05000289  +  and 00289  +
Equipment trip
Reactor Trip +
From
INC. +, EG&G IDAHO +, IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY +  and Obenchain C +
Generic letter
NRC Generic Letter 84-15, Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability +
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>.
ML20215J253 +, ML20215J253 +, ML20215J253 +, ML20215J253 +, ML20215J253 +, ML20215J253 +, ML20215J253 +, ML20215J253 +, ML20215J253 +, ML20215J253 +, ML20215J253 +, ML20215J253 +, ML20215J253 +, ML20215J253 +, ML20215J253 +, ML20215J253 +, ML20215J253 +  and ML20215J253 +
Hours
1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +
Issue date
February 17, 1987  +
Letter
ML20207E571 +
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>.
03:05:26, 4 December 2024  +
NRC form
NRC Form 189 +
NUREG
NUREG-0703, Forwards Three Consultant Repts Prepared in Support of NUREG-0703, Potential Threat to Licensed Nuclear Activities from Insiders +
Page count
2  +
Procedure
SP +  and EP-1202-37 +
Project stage
Request  +
SSC
8S-V30A +
Site
Crane +
Start date
February 17, 1987  +
State
Maryland +, Washington +  and Idaho +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Decay Heat Removal +, Main Condenser +  and Main Steam +
TS
TS-3.1.12.3 +  and TS-4.5.2 +
Test
Bench test +
Title
Forwards Suppl 1 to EGG-NTA-7296, Supplemental Technical Evaluation Rept,Pump & Valve Inservice Testing Program, TMI-1. Proposed Program in Accordance W/Established NRC Requirements W/Noted Exceptions  +
To
Carrington M +  and Office of Nuclear Reactor Regulation +
Topic
Boric Acid +  and Stroke time +
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http://pbadupws.nrc.gov/docs/ML2021/ML20215J253.pdf  +
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