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LR-N09-0072, Updated 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
Letter type:LR
ASME section
ASME Section II +
Accession number
ML091000557  +
Atomic Element
Boron +, Iron +, Copper +, Carbon +, Sodium +, Hydrogen +, Lead +, Aluminum +, Silicon +, Calcium +  and Zinc +
CFR
10 CFR 50.46 +, 10 CFR 50.59 +, 10 CFR 50.65 +, 10 CFR 50.54#f +, 10 CFR 50.65#a4 +  and 10 CFR 50.71#e +
Committee
Advisory Committee on Reactor Safeguards +
Correspondence
L 91 +  and L 86 +
Cross cutting aspect
S.1(t) +, S.3(s) +  and S.8(n) +
Docket
05000272  +, 05000311  +, 00272  +  and 00311  +
Document
ML073110389 +, ML080230234 +, ML073520891 +, ML073520295 +, ML080380214 +, ML080800469 +, ML083300079 +, ML082170506 +, ML081640193 +, ML0726007425 +, ML053200277 +  and ML082040013 +
Exelon procedure
CC-AA-102 +, CC-AA-112 +, MA-AA-716-008 +, OP-AA-1 +, CC-AA-1 +, OP-AA-101-112-1002 +  and CC-AA-102-1001 +
From
PSEG +  and Braun R +
Generic letter
NRC Generic Letter 04-02 +, NRC Generic Letter 04-01 +, 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>.
LR-N09-0072, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, LR-N09-0072, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, LR-N09-0072, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, LR-N09-0072, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, LR-N09-0072, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, LR-N09-0072, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, LR-N09-0072, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, LR-N09-0072, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, LR-N09-0072, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, LR-N09-0072, Updated 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 LR-N09-0072, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +
Hours
0.00278 d (0.0667 hours, 3.968254e-4 weeks, 9.132e-5 months)  +, 3.009259e-4 d (0.00722 hours, 4.298942e-5 weeks, 9.893e-6 months)  +, 2.893519e-4 d (0.00694 hours, 4.133598e-5 weeks, 9.5125e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 1.62037e-4 d (0.00389 hours, 2.314815e-5 weeks, 5.327e-6 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 0.0333 d (0.8 hours, 0.00476 weeks, 0.0011 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +
Inspection Manual Chapter
NRC Inspection Manual 4712 +  and NRC Inspection Manual 4713 +
Issue date
March 31, 2009  +
L
L 91 +  and L 86 +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
19:00:25, 12 March 2020  +
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. +
NUREG
NUREG/CR-6914 +, NUREG/CR-6773 +, NUREG/CR-3616 +, NUREG/CR-6808 +, NUREG/CR-6772 +, NUREG/CR-2791 +, NUREG/CR-6762 +, NUREG/CR-6916 +, 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 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and 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.. +
Page count
291  +
Person
Richard Ennis +
Power source
4V +
Procedure
CH +, MP +  and Emergency Operating Procedure +
Project reference
TAC:MC4712 +  and TAC:MD6353 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.82 +
Report
NEDO-32686 +
SSC
3c-1 +, 3SA-096 +, 3b-1 +, 3c-2 +, 3h-2 +, 3e-3 +, 6S1-2258 +, 6S2-2249 +, 3d-2 +, 3h-1 +, 3h-3 +, 3h-4 +, 3h-5 +, 3h-6 +, 3j-1 +, 3j-2 +, 3k-1 +, 3k-2 +, 3o-1 +, 3o-3 +, 3o-4 +, 3o-5 +, 3o-7 +, 3g-3 +, 6S0-1 +, 3b-2 +, 3b-3 +, 3c-3 +, 3c-4 +, 3c-5 +...
Site
Salem +
Site license
Salem +
Start date
March 31, 2009  +
State
Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Main Steam Line +, Control Rod +, Main Steam +  and Containment Spray +
TS
TS-4.5.2.c +
Test
Bench test +
Title
Updated 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
Boric Acid +, High Radiation Area +, Ultimate heat sink +, Mission time +, Grab sample +, Hydrostatic +, Coatings +, Operating Basis Earthquake +, Temporary Modification +, High Energy Line Break +, Design basis earthquake +, Foreign Material Exclusion +, Exemption Request +, Earthquake +, Fuel cladding +  and Scaffolding +
Training curricula
J-MDC-2092 +, J-MEE-1978 +  and J-MEE-1 +
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/ML0910/ML091000557.pdf  +
WCAP
WCAP-16568-P +, WCAP-16406-P +, WCAP-16793 +, WCAP-16793-NP +, WCAP-16530-NP +, WCAP-16530-NP-A +, WCAP-16530 +, WCAP-16785-NP +, WCAP-16710-P +, WCAP-16727-NP +  and WCAP-16503-NP +
Westinghouse report
WCAP-16568-P +, WCAP-16406-P +, WCAP-16793 +, WCAP-16793-NP +, WCAP-16530-NP +, WCAP-16530-NP-A +, WCAP-16530 +, WCAP-16785-NP +, WCAP-16710-P +, WCAP-16727-NP +  and WCAP-16503-NP +
 
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