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3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability
Show incoming properties 
Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
ANSI code
ANSI N45.2.2 +
ASME section
ASME Section IV +
Accession number
ML20081J075  +
Atomic Element
Silicon +  and Lead +
CFR
10 CFR 21 +, 10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 100.11 +  and 10 CFR 100.117 +
Correspondence
L-26 +, L 44 +, L 35 +, RA 800 +  and PM-118 +
Cross cutting aspect
P.1(g) +, S.6(l) +, P.4(t) +  and P.3(n) +
Docket
05000302  +  and 00302  +
Emergency Facility
Technical Support Center +
Engineering change
EC-240 +, EC-212 +  and EC-345 +
Equipment trip
Reactor Trip +
From
Duke Energy +  and Westafer G +
General design criterion
GDC 1, Quality standards and records +
Generic letter
NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +
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>.
3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability +, 3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability +, 3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability +, 3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability +, 3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability +, 3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability +, 3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability +, 3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability +, 3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability +, 3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability +, 3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability +, 3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability +, 3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability +, 3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability +, 3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability +  and 3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
IEEE
IEEE 308 +, IEEE 344-1975 +  and IEEE 382-1972 +
Issue date
November 4, 1983  +
L
L-26 +, L 44 +  and L 35 +
Letter
ML20069H547 +
Manufacturer
Westinghouse +, Honeywell +, Limitorque +  and 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>.
12:51:02, 14 December 2024  +
NUREG
NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, 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 +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +
PM
PM-118 +
Page count
116  +
Power source
4V +
Procedure
AM +, ES +, ST +, CH +, SP +, CP +, Emergency Plan +, CP-113 +, SP-110 +, SP-5095 +  and CP-115 +
Project stage
Request  +
RA
RA 800 +
Regulatory Guide
Regulatory Guide 1.26 +
SSC
W3f-g +, 10CFR21-YES +, A3V-5 +, 480V-2300VDC +, 695C150-1 +, 695C159-1 +, 549D409-2 +, 3c-C +, 3F1183-3 +  and 3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability +
Scram
Manual Scram +
Site
Crystal River +
Site license
Crystal River +
Start date
November 4, 1983  +
State
Washington +, Florida +  and Arkansas +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, HVAC +, Emergency Feedwater Initiation and Control +  and Control Rod +
Title
Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability  +
To
Eisenhut D +  and Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Overtravel +, Commercial Grade +  and Hardened grease +
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/ML2008/ML20081J075.pdf  +
 
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