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ML030760201
Show incoming properties 
Category
Graphics incl Charts and Tables
ASME section
ASME Section XI +  and ASME Section III +
Accession number
ML030760201  +
Atomic Element
Boron +, Iron +, Copper +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Chloride +, Lead +, Aluminum +, Silicon +  and Zinc +
CFR
10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 54 +, 10 CFR 54.3 +, 10 CFR 54.4 +, 10 CFR 54.4#a2 +, 10 CFR 54.4#a3 +, 10 CFR 54.4#a1 +  and 10 CFR 54.21#a1 +
Contact
Dudley N, NRR/DRIP/RLEP, 415-1154 +
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.4(f) +, H.2(f) +, H.3(f) +  and H.1(l) +
Docket
05000335  +  and 05000389  +
Document
ML022130182 +, ML0022130182 +, ML0222130182 +  and ML021780147 +
Drawing
SE-37-2 +  and SE-37-1 +
Emergency Facility
Technical Support Center +
FR
60 FR 22477 +
From
NRC/NRR/DRIP/RLEP +  and Dudley N +
General design criterion
GDC 44 +, GDC 2, Design bases for protection against natural phenomena +  and GDC 19, Control room +
Generic letter
NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +
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>.
ML030760201 +, ML030760201 +, ML030760201 +, ML030760201 +, ML030760201 +, ML030760201 +, ML030760201 +, ML030760201 +, ML030760201 +, ML030760201 +, ML030760201 +, ML030760201 +, ML030760201 +, ML030760201 +, ML030760201 +, ML030760201 +, ML030760201 +  and ML030760201 +
Issue date
March 13, 2003  +
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-2002-055, Request for Extension of Time in Which to Seek a Hearing February 25, 2002 Order Modifying Licenses +  and 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 +
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>.
16:51:04, 16 January 2025  +
NEI
NEI 97-06, Steam Generator Conditioning Monitoring Report +
NFPA
NFPA 72 +
NRC bulletin
NRC Bulletin 02-01 +, NRC Bulletin 80-11 +, NRC Bulletin 88-11 +  and NRC Bulletin 88-08 +
NRC information notice
Information Notice 92-20 +, Information Notice 90-04 +, Information Notice 85-24 +, Information Notice 86-67 +, Information Notice 1987-28, Air Systems Problems at U.S. Light Water Reactors +, Information Notice 2002-11, Recent Experience with Degradation of Reactor Pressure Vessel Head +  and Information Notice 2001-09, Main Feedwater System Degradation in Safety-Related ASME Code Class 2 Piping Inside the Containment of a Pressurized Water Reactor +
NUREG
NUREG/CR-6260 +, NUREG-1611 +, NUREG/CR-5999, Forwards Updated Fatigue Design Curves for Austenitic Stainless Steels in LWR Environments.Design Curves Being Provided in Advance of Future Update of NUREG/CR-5999 to Facilitate Efforts on Resolution of GSI-190 +, 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 +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +
Page count
72  +
Procedure
AM +  and ST +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.27 +
SSC
3C-1 +, 2HVS-5A +, 3C-4 +, 2HVE-41A +, 2L-7B +, 2HVE-9A +, 2HVS-4A +, 2HVE-12 +, 2L-7A +, 2HVE-6A +, 2HVE-13A +, 2HVE-13B +, 2HVS-5B +, 2L-1 +, 6F-7 +, 5A-205 +, 1HVAC-02 +, 2FDPR-25-123 +, 2FDPR-25-119 +, 27F-93F +  and 5A-136A +
Site
Saint Lucie +
Start date
March 13, 2003  +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Shield Building +, Circulating Water System +, Emergency Core Cooling System +, Decay Heat Removal +, Control Room Envelope +, Main Steam +, Containment Spray +  and Extraction steam +
Title
RAI Cross-Reference Table  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, High winds +, Ultimate heat sink +, Fire Barrier +, Tornado Missile +, Coatings +, Aging Management +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Moisture barrier +, License Renewal +, Biofouling +, Fire Protection Program +, Flow Induced Vibration +, Operational leakage +, Thermal fatigue +  and Leak-Before-Break +
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/ML0307/ML030760201.pdf  +
WCAP
WCAP-14574-A +  and WCAP-14574 +
Westinghouse report
WCAP-14574 +  and WCAP-14574-A +
 
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