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CP-200800265, Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Show incoming properties 
Category
Report, Technical  and Letter type:CP
Accession number
ML080660596  +
Agency
American Society of Civil Engineers +
Atomic Element
Iron +, Hydrogen +, Lead +, Aluminum +, Zinc +  and Tin +
CFR
10 CFR 50 Appendix A +, 10 CFR 50.46 +  and 10 CFR 5#O +
Correspondence
TXX-05162 +, TXX-05047 +, TXX-03130 +, TXX-98249 +, TXX-03 130 +, TXX-07164 +, TXX-08033 +, TXX-06062 +, TXX-06180 +, TXX-05 162 +, TXX-07 156 +, TXX-05 118 +, TXX-07 149 +  and TXX-07 164 +
Cross cutting aspect
P.3(e) +  and P.3(j) +
Docket
05000445  +, 05000446  +, 00445  +  and 00446  +
From
Luminant +  and Blevins M +
General design criterion
GDC 35 +
Generic letter
NRC Generic Letter 04-02 +  and NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment +
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>.
CP-200800265, Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, CP-200800265, Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, CP-200800265, Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, CP-200800265, Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, CP-200800265, Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, CP-200800265, Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, CP-200800265, Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, CP-200800265, Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, CP-200800265, Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, CP-200800265, Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, CP-200800265, Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, CP-200800265, Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, CP-200800265, Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +  and CP-200800265, Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +
Inspection Manual Chapter
NRC Inspection Manual 4777 +
Issue date
February 29, 2008  +
Manufacturer
Westinghouse +  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>.
22:49:35, 14 January 2025  +
NEI
NEI 02-01 +, NEI 04-0 +  and NEI 04-07, Response to Request No. 2 in NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +
NRC bulletin
NRC Bulletin 03-01 +
NUREG
NUREG/CR-69 +, NUREG-0797, Summary of Meeting on 890905 in Rockville,Md to Discuss Ground Motion Estimates for Criner Tectonic Structure of Southern Oklahoma Aulacongen in Wichita Tectonic Province, Per Section 2.5.2 of Fsar.Viewgraphs Encl +  and NUREG/CR-6369, Forwards Second Transmittal of NUREG/CR-6369, Drywell Debris Transport Study, & Suppls . Pages 2-12,3-8 & C-19 of Incoming Submittal Not Included +
Page count
124  +
Procedure
EP-5.01 +
Project reference
TAC:MC4776 +  and TAC:MD4676 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.97 +, Regulatory Guide 1.82 +  and Regulatory Guide 1.54 +
Report
NEDO-32686 +
SR
SR-3.5.2.8 +
SSC
2ENR-2007-00274 +, 7ENR-2007-00274 +, 1ENR-2007-00274 +, 8ENR-2007-00274 +, 9ENR-2007-00274 +, 5ENR-2007-00274 +, 31k-3 +, 31k-4 +, 16ENR-2007-00274 +, 16ENR-2007 +, 16ENR-2007-00 +, 31k-5 +, 31k-2 +, 5ENR-2007-002 +, 5ENR-2007-0027 +, 3ENR-2007-00274 +, 15ENR-2007-00274 +, 15ENR-2007-002 +, 15ENR-2007 +, 7ENR-2007 +, 9ENR-2007-002 +, 16ENR-2007-002 +  and 1ENR-2007 +
Site
Comanche Peak +
Start date
February 29, 2008  +
State
Washington +  and Texas +
System
Steam Generator +, Feedwater +, Emergency Core Cooling System +  and Containment Spray +
TS
TS-3.3.2 +  and TS-3.6.7 +
TXX
TXX-05162 +, TXX-05047 +, TXX-03130 +, TXX-98249 +, TXX-03 130 +, TXX-07164 +, TXX-08033 +, TXX-06062 +, TXX-06180 +, TXX-05 162 +, TXX-07 156 +, TXX-05 118 +, TXX-07 149 +  and TXX-07 164 +
Title
Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors  +
To
Office of Nuclear Reactor Regulation +  and Document Control Desk +
Topic
Safe Shutdown Earthquake +, Hydrostatic +, Coatings +, Operating Basis Earthquake +  and Scaffolding +
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/ML0806/ML080660596.pdf  +
WCAP
WCAP-16568-P +, WCAP-16406-P +, WCAP-16793 +, WCAP-16793-NP +, WCAP-16530-NP +, WCAP-16785-NP +  and WCAP-165 +
Weld alloy
ER308 +  and ER308L +
Westinghouse report
WCAP-16568-P +, WCAP-16406-P +, WCAP-16793 +, WCAP-16793-NP +, WCAP-16530-NP +, WCAP-16785-NP +  and WCAP-165 +
 
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