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ML20098F217
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Category
NUREG REPORTS, REGULATORY GUIDES & STD. REVIEW PLANS-TEXT  and STANDARD REVIEW PLANS
ASME section
ASME Section III +
Accession number
ML20098F217  +
From
Office of Nuclear Reactor Regulation +
General design criterion
GDC 50 +, GDC 16 +, GDC 13 +, GDC 53 +  and GDC 4, Environmental and dynamic effects design bases +
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>.
ML20098F217 +, ML20098F217 +, ML20098F217 +, ML20098F217 +, ML20098F217 +  and ML20098F217 +
Issue date
August 31, 1984  +
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>.
11:56:07, 13 December 2024  +
NUREG
NUREG-800 +, NUREG-07 +, NUREG-0302, Ack Receipt of Re 10CFR21.Part 21 Only Requires That Internal Procedures for Evaluating & Reporting Identify Responsible Officer.Rev 1 to NUREG-0302 Encl to Clarify Issue.W/O Encl +, 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-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0718, Forwards Final Rule on Licensing Requirements for Pending CP & Mfg License Applications & NUREG-0718,Revision 2.SER Comparison to New Requirements Revealed Util Commitments & CP Conditions Conform to Nureg.W/O NUREG +, NUREG-0808, Forwards Safety Evaluation Accepting Revised Safety Relief Valve & Condensation Oscillation Loads Per NUREG-0802 & NUREG-0808 & Temp Cutoff Value Used for Elimination of Data Base for Load Computations +, NUREG-0978, Informs That CRGR Meeting 44 on 830803 Rescheduled for 830810 in Bethesda,Md.Proposed NUREG-0978 Re Generic Issue B-10, Behavior of BWR Mark III Containments, Will Be Discussed +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +
Page count
9  +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
ML20098F217 +
Regulatory Guide
Regulatory Guide 1.3 +  and Regulatory Guide 1.97 +
Start date
August 31, 1984  +
State
Maryland +, Washington +  and Virginia +
System
Reactor Coolant System +
Title
Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Revision 6 to Section 6.2.1.1.C, Pressure-Suppression Type BWR Containments  +
Topic
High Energy Line Break +
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http://pbadupws.nrc.gov/docs/ML2009/ML20098F217.pdf  +
 
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