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ML060790325
Show incoming properties
Category
Letter, Technical Specifications  and License-Application for Facility Operating License (Amend/Renewal) DKT 50
Accession number
ML060790325  +
Atomic Element
Lead +
Docket
05000336  +  and 00336  +
Equipment trip
Reactor Trip +
From
Dominion Nuclear Connecticut +  and Hartz L +
General design criterion
GDC 15 +
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>.
ML060790325 +, ML060790325 +, ML060790325 +, ML060790325 +, ML060790325 +, ML060790325 +, ML060790325 +, ML060790325 +, ML060790325 +, ML060790325 +, ML060790325 +, ML060790325 +  and ML060790325 +
Hours
8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +
Issue date
March 17, 2006  +
License number
DPR-065  +
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>.
15:49:39, 15 January 2025  +
NUREG
NUREG-1432 +
Page count
21  +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.83 +
SR
SR-4.4.4.1 +
SSC
07-05-430 +
Site
Millstone +
Site license
Millstone +
Start date
March 17, 2006  +
State
Connecticut +, Washington +  and Virginia +
System
Steam Generator +, Reactor Coolant System +, Feedwater +  and Emergency Core Cooling System +
TS
TS-3.4.4 +  and TS-6.23 +
Title
Proposed Revision to Technical Specifications (LBDCR 05-MP2-004) Pressurizer Water Level Limits  +
To
Office of Nuclear Reactor Regulation +  and Document Control Desk +
Topic
Boric Acid +, Anticipated operational occurrence +, Probabilistic Risk Assessment +  and Loss of Offsite Power +
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http://pbadupws.nrc.gov/docs/ML0607/ML060790325.pdf  +
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