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ML20024E688
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Category
MEETING MINUTES & NOTES--CORRESPONDENCE  and MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
Accession number
ML20024E688  +
Atomic Element
Boron +, Cobalt +, Nickel +, Copper +, Hydrogen +  and Lead +
Cornerstone
Emergency Preparedness +
Docket
05000443  +  and 05000444  +
FR
47 FR 43474 +  and 48 FR 10962 +
From
Advisory Committee on Reactor Safeguards +
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>.
ML20024E688 +, ML20024E688 +, ML20024E688 +, ML20024E688 +, ML20024E688 +, ML20024E688 +, ML20024E688 +  and ML20024E688 +
IEEE
IEEE 323 +
Issue date
July 7, 1983  +
Manufacturer
Westinghouse +
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04:19:21, 21 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-0801, Forwards Comments on Program Plan for Detailed Control Room Design Review (Dcrdr).Program Plan Addresses All Required Elements of DCRDR.In-progress Audit Not Planned +, NUREG-0896, Forwards Sser 8 (NUREG-0896),addressing Issues Re 5% Low Power License.W/O Encl +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0666, 03-17-81 NUREG-0666, a Probabilistic Safety Analysis of DC Power Supply Requirements at Nuclear Power Plants +
Page count
33  +
Procedure
ST +, CH +  and Emergency Operating Procedure +
Project stage
Meeting  +
Regulatory Guide
Regulatory Guide 1.97 +, Regulatory Guide 1.8 +  and Regulatory Guide 1.133 +
Scram
Automatic Scram +  and Manual Scram +
Site
Seabrook +
Start date
July 7, 1983  +
State
Washington +, New Hampshire +  and Maine +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Safety Parameter Display System +, Remote shutdown +, Decay Heat Removal +  and Containment Spray +
Title
Summary of ACRS Subcommittee on Seabrook Station 830401-02 Meetings in Hampton Beach,Nh Re Application by Util for OLs  +
To
Advisory Committee on Reactor Safeguards +
Topic
Safe Shutdown +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Shift Technical Advisor +, Systematic Assessment of Licensee Performance +, Earthquake +, Potassium iodide +  and Control Room Habitability +
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http://pbadupws.nrc.gov/docs/ML2002/ML20024E688.pdf  +
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