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ET 05-0018, Operating Corporation, 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:ET
Accession number
ML052510441  +
Atomic Element
Sodium +  and Lead +
CFR
10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.71 +  and 10 CFR 50.54#f +
Correspondence
WO 03-0049, Response to NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors +, WM 05-0007, Operating Corporation, Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +  and WM 04-0050, Response to NRC Request for Additional Information Related to Bulletin 2003-01 +
Docket
05000482  +
From
Wolf Creek +  and Garrett T +
General design criterion
GDC 38 +, GDC 41 +  and 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>.
ET 05-0018, Operating Corporation, Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, ET 05-0018, Operating Corporation, Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, ET 05-0018, Operating Corporation, Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, ET 05-0018, Operating Corporation, Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, ET 05-0018, Operating Corporation, Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, ET 05-0018, Operating Corporation, Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, ET 05-0018, Operating Corporation, Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, ET 05-0018, Operating Corporation, Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, ET 05-0018, Operating Corporation, Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, ET 05-0018, Operating Corporation, Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +  and ET 05-0018, Operating Corporation, Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
Issue date
August 31, 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>.
20:34:37, 15 January 2025  +
NEI
NEI 02-01 +, 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. +  and NEI 99-04, Guideline for Managing NRC Commitment Changes +
NUREG
NUREG/CR-6808 +
Page count
28  +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.82 +
Regulatory Issue Summary
RIS 2000-17, Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff +
Site
Wolf Creek +
Start date
August 31, 2005  +
State
Kansas +  and Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Residual Heat Removal +, Emergency Core Cooling System +, Main Steam +  and Containment Spray +
Title
Operating Corporation, Response to 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
Mission time +, Fire Barrier +, Coatings +, High Energy Line Break +  and Exemption Request +
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/ML0525/ML052510441.pdf  +
WCAP
WCAP-16406-P +
WM
WM 04-0050, Response to NRC Request for Additional Information Related to Bulletin 2003-01 +  and WM 05-0007, Operating Corporation, Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +
WO
WO 03-0049, Response to NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors +
Westinghouse report
WCAP-16406-P +
 
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