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3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Show incoming properties 
Category
Letter type:
Accession number
ML052450332  +
Atomic Element
Boron +, Iron +, Copper +, Carbon +, Hydrogen +, Lead +, Magnesium +, Aluminum +, Silicon +, Calcium +, Titanium +  and Zinc +
CFR
10 CFR 50.67 +, 10 CFR 50.46 +, 10 CFR 50.59 +, 10 CFR 50.34 Appendix A +, 10 CFR 50.54#f +  and 10 CFR 50.46#b5 +
Correspondence
PM-156 +
Docket
05000302  +  and 00302  +
Emergency Facility
Technical Support Center +  and Emergency Operations Facility +
Engineering change
EC-58982 +  and EC-59476 +
From
Young D +  and Progress Energy Florida +
Generic letter
NRC Generic Letter 04-02 +, NRC Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements +, NRC Generic Letter 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps +  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>.
3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +  and 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +
Issue date
August 30, 2005  +
Manufacturer
Westinghouse +
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>.
20:39:38, 15 January 2025  +
NEI
NEI 02-01 +  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 +  and NRC Bulletin 93-02 +
NUREG
NUREG/CR-6224, Requests That Encl Documents Be Available Through NRC PDR & Central Files.Documents Provided Background or Ref Info for Resolution of BWR Strainer Blockage Issue,As Ref by Draft NUREG/CR-6224, Parametric Study of Potential for Bwr.. +
PM
PM-156 +
Page count
35  +
Procedure
ES +, Emergency Operating Procedure +, SP-324 +, SP-175A +, SP-5953 +, SP-175 +  and SP-5903 +
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.
3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +
Project
TAC:MC4678 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.97 +, Regulatory Guide 1.1 +  and Regulatory Guide 1.82 +
SSC
3N0594-04 +, 3N0798-1 +, 3N1199-04 +, 3FO805-09 +, 3F0803-03, 60-Day Response to NRC Bulleting 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors +  and 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +
Site
Crystal River +
Site license
Crystal River +
Start date
August 30, 2005  +
State
Florida +
System
Steam Generator +, Reactor Coolant System +, Core Spray +, Emergency Core Cooling System +, Decay Heat Removal +  and Containment Spray +
Title
Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors  +
To
Document Control Desk +  and Office of Nuclear Reactor Regulation +
Topic
High Radiation Area +, Mission time +, Coatings +, High Energy Line Break +, Foreign Material Exclusion +, Exemption Request +  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/ML0524/ML052450332.pdf  +
Vendor
Framatome +
WCAP
WCAP-16406 +  and WCAP-16406-P +
Westinghouse report
WCAP-16406 +  and WCAP-16406-P +
 
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