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ML19309C309
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Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
ANSI code
ANSI N18.2 +  and ANSI 18.2 +
Accession number
ML19309C309  +
Atomic Element
Boron +, Oxygen +, Hydrogen +, Lead +  and Magnesium +
CFR
10 CFR 50 +, 10 CFR 50.54#f +  and 10 CFR 50.54#F +
Docket
05000329  +, 05000330  +, 00329  +  and 00333  +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Howell S +  and Consumers Energy +
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>.
ML19309C309 +, ML19309C309 +, ML19309C309 +, ML19309C309 +, ML19309C309 +, ML19309C309 +, ML19309C309 +, ML19309C309 +, ML19309C309 +, ML19309C309 +, ML19309C309 +  and ML19309C309 +
Hours
1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +
IEEE
IEEE 379 +
Issue date
April 1, 1980  +
Manufacturer
Westinghouse +
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08:32:17, 2 January 2025  +
NRC bulletin
NRC Bulletin 79-27 +
NUREG
NUREG-0500, Informs Comm of Comments Received Re NRC Survey Rept on Differing Prof opinions(NUREG-0500)& Staff Plans to Dev NRC Proposed Policy & Procedures.Provides Sched for Completion of Response Actions +, 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 +  and NUREG-0020, Responds to Encl Re Spent Fuel Storage Capacity at Plant.Spent Fuel Pool at Plant Has Sufficient Space to Accommodate Addl Fuel Storage Racks of Current Design +
Page count
100  +
Power source
24V +
Procedure
AM +, ST +, TOP +  and Emergency Plan +
Project stage
Other  +
Regulatory Guide
Regulatory Guide 1.97 +  and Regulatory Guide 1.29 +
SSC
2KI-22 +
Scram
Manual Scram +  and Automatic Scram +
Site
Midland +
Start date
April 1, 1980  +
State
Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Shutdown Cooling +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam +  and Containment Spray +
Title
Forwards Response to NRC Re Design Adequacy of B&W Sys.Reviews Will Be in Areas of Instrumentation & Controls & Can Be Accommodated within Current Const Schedule.Requests Restart of Review of OL Application  +
To
Office of Nuclear Reactor Regulation +  and Harold Denton +
Topic
Shutdown Margin +, Loss of Offsite Power +, Fuel cladding +, Core Exit Thermocouple +, Manual Operator Action +  and Loss of condenser vacuum +
Turbine component
Turbine bypass valve +
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http://pbadupws.nrc.gov/docs/ML1930/ML19309C309.pdf  +
 
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