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ML20092C167
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Category
CORRESPONDENCE-LETTERS  and INCOMING CORRESPONDENCE
ANSI code
ANSI C37.90 +, ANSI C96.1 +, ANSI C63.12 +  and ANSI C37.90.2 +
Accession number
ML20092C167  +
Atomic Element
Lead +
Correspondence
L 20555 +  and SECY-91294 +
Docket
05000605  +
Equipment trip
Reactor Trip +
From
GENERAL ELECTRIC CO. +  and Recasha Mitchell +
General design criterion
GDC 1, Quality standards and records +  and GDC 3, Fire protection +
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>.
ML20092C167 +, ML20092C167 +, ML20092C167 +, ML20092C167 +, ML20092C167 +, ML20092C167 +, ML20092C167 +, ML20092C167 +, ML20092C167 +, ML20092C167 +, ML20092C167 +  and ML20092C167 +
IEEE
IEEE 279 +, IEEE 7 +, IEEE 338 +, IEEE 829 +, IEEE 730 +  and IEEE 348 +
Issue date
February 3, 1992  +
L
L 20555 +
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>.
16:31:33, 13 December 2024  +
NUREG
NUREG-0993 +, NUREG-985 +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, NUREG-0572, Response in Support of Jf Doherty Contention 46 Re Control Rods Leading to Fuel Damage.Contention Involves New Info Appearing in ACRS Review of LERs 1976-78 rept,NUREG-0572. Certificate of Svc Encl +, NUREG-0977, Requests Util Review of NUREG-0977 Re ATWS Events to Identify & Explain Apparent Inconsistencies Based on Latest Available Info & Provide Basis for Relevance of New Info +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +
Page count
45  +
Procedure
ST +  and ESP +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.33 +, Regulatory Guide 1.106 +  and Regulatory Guide 1.89 +
SECY
SECY-91294 +
SSC
7A-1 +  and 299X701-015 +
Scram
Manual Scram +  and Automatic Scram +
Site
05000605 +
Start date
February 3, 1992  +
State
Washington +
System
Feedwater +, Secondary containment +, Reactor Protection System +, Main Turbine +, HVAC +, Fuel Pool Cooling and Cleanup +, Remote shutdown +, Main Steam Line +, Control Rod +  and Main Steam +
Title
Forwards Nonproprietary Responses to Addl Items of Concern Noted in Draft SER for Chapter 7.Advises That GE Will Amend Advanced BWR SSAR W/Responses in Future Amend  +
To
Pierson R +, Office of Nuclear Reactor Regulation +  and Office of Information Resources Management +
Topic
Fire Barrier +, Coatings +  and Affidavit +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
http://pbadupws.nrc.gov/docs/ML2009/ML20092C167.pdf  +
 
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