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ML022030456
Show incoming properties 
Category
Request for Additional Information (RAI)
Accession number
ML022030456  +
Atomic Element
Carbon +, Oxygen +, Hydrogen +, Chloride +  and Lead +
CFR
10 CFR 50 +, 10 CFR 54 +, 10 CFR 54.4 +, 10 CFR 54.4#a2 +, 10 CFR 54.4#a1 +  and 10 CFR 50.54#a +
Contact
Dudley N, NRR/DRIP/RLEP, 415-1154 +
Cornerstone
Emergency Preparedness +
Correspondence
L-86-181, Forwards Final Core Support Barrel Insp Rept,Post-Cycle 6. Condition of Core Support Barrel Same as Found During post- Cycle 5 Insp.Barrel Acceptable for long-term Svc +, L-2002-061, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity +, L-11 +  and L-10 +
Cross cutting aspect
H.2(f) +  and H.3(f) +
Docket
05000335  +, 05000389  +, 00335  +  and 00389  +
Emergency Facility
Technical Support Center +
From
Dudley N +  and Division of Regulatory Improvement Programs +
General design criterion
GDC 19, Control room +
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>.
ML022030456 +, ML022030456 +, ML022030456 +, ML022030456 +, ML022030456 +, ML022030456 +, ML022030456 +, ML022030456 +, ML022030456 +, ML022030456 +, ML022030456 +, ML022030456 +, ML022030456 +  and ML022030456 +
Issue date
July 18, 2002  +
L
L-86-181, Forwards Final Core Support Barrel Insp Rept,Post-Cycle 6. Condition of Core Support Barrel Same as Found During post- Cycle 5 Insp.Barrel Acceptable for long-term Svc +, L-2002-061, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity +, L-11 +  and L-10 +
Letter
L-2002-061, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity +
License amendment topic
License Renewal Application +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
22:29:35, 16 January 2025  +
NRC bulletin
NRC Bulletin 02-01 +
NRC information notice
Information Notice 90-04 +
NUREG
NUREG-1061, Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl +
Page count
27  +
Procedure
ST +
Project stage
RAI  +
SSC
2HVS-5A +, 2HVE-41A +, 2L-7B +, 2HVE-9A +, 2HVS-4A +, 2L-7A +, 2HVE-6A +, 2HVE-13A +, 2HVE-13B +, 2L-8 +, 2L-11 +, 2HVE-11 +, 2FDPR-25-123 +  and 2FDPR-25-119 +
Site
Saint Lucie +
Start date
July 18, 2002  +
State
Washington +, Virginia +  and Florida +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, HVAC +, Shield Building +, Emergency Core Cooling System +, Control Room Envelope +  and Main Steam +
Title
Request for Additional Information, Review of Sections 2.0, 3.0, 4.0, & Appendix B of Application for Renewed Operating Licenses  +
To
NextEra Energy +  and Stall J +
Topic
Boric Acid +, Fire Barrier +, Aging Management +, Stress corrosion cracking +, License Renewal +  and Leak-Before-Break +
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http://pbadupws.nrc.gov/docs/ML0220/ML022030456.pdf  +
 
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