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ML19120A469
Show incoming properties 
Category
Letter  and Safety Evaluation
ASME code
IWB-2500 +
ASME section
ASME Section XI +
Accession number
ML19120A469  +
Atomic Element
Boron +, Iodine +, Sodium +, Lead +, Aluminum +, Silicon +, Calcium +  and Tin +
CFR
10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 50.65 +, 10 CFR 50.69 +, 10 CFR 50.55a +, 10 CFR 50.55a#g6iiF +  and 10 CFR 50.46#a1 +
Code case
ASME Code Case N-770-2 +
Contact
Markley M +
Cornerstone
Emergency Preparedness +  and Initiating Events +
Correspondence
SECY-10-113 +  and SECY-12-0093 +
Docket
05000424  +, 05000425  +, 00424  +  and 00425  +
Document
Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.45 +, ML15127A669 +, ML071700658 +, ML061510621 +, ML083430462 +, ML090970525 +, ML17033A023 +, ML042360586 +, ML103570354 +, ML082250436 +, ML12349A378 +, ML112440046 +, NL-16-2382, License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process +, ML17116A096 +, NL-17-1201, Response to Supplemental Information Needed for Acceptance of Systematic Risk-Informed Assessment of Debris Technical Report +, ML031600259 +, ML121310648 +, ML053550265 +, ML041550661 +, ML043280641 +, ML050550138 +, ML050550156 +, ML081150379 +, ML073110389 +, ML080230234 +, ML13198A250 +, ML111330278 +, ML081060300 +...
FR
51 FR 30028 +
From
Markley M +  and Plant Licensing Branch II +
General design criterion
GDC 38 +, GDC 41 +, GDC 35 +, GDC 14 +, GDC 30 +, GDC 31 +, GDC 32 +  and GDC 1, Quality standards and records +
Generic letter
NRC Generic Letter 04-02 +
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>.
ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +, ML19120A469 +...
Hours
5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
Issue date
September 30, 2019  +
Letter
ML17033A023 +, CAC:MF9350 +, CAC:MF9861 +, NL-17-1201, Response to Supplemental Information Needed for Acceptance of Systematic Risk-Informed Assessment of Debris Technical Report +, ML13130A103 +, CAC:RP9268 +, ML18023A251 +, ML17332A147 +, ML18150A160 +, NL-10-1252, R14 Inservice Inspection Summary Report +, ML18114A812 +, ML18032A208 +, ML18332A443 +  and NL-17-1848, Systematic Risk-Informed Assessment of Debris Technical Report, SNC Response to NRC Request for Additional Information (Rals 1-3) +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
General Electric +  and 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>.
07:48:06, 5 January 2025  +
NEI
NEI 00-02 +, NEI 05-04 +, NEI 12-13 +, 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 06-09, Risk-Managed Technical Specifications (RMTS) Guidelines +
NRC LIC
LIC-109, Acceptance Review Procedures +, LIC-500 +  and LIC-101 +
NRC bulletin
NRC Bulletin 03-01 +
NUREG
NUREG/CR-6928 +, NUREG-1855, Summary of 7/18/19 Public Meeting with Nuclear Energy Institute to Discuss Application of NUREG-1855, Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decision Making +, 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-0897, Forwards Susceptibility of ERCO-SIL 36S Insulation Pillows to Debris Formation Under Exposure to Energetic Jet Flows & Bouyancy,Transport & Head Loss Characteristics of ERCO-SIL 36S Insulation Pillows for Nuclear.. +, NUREG-1829, White Paper on Continued Applicability of NUREG-1829 +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +
Page count
112  +
Person
Bryce Lehman +, John Tsao +, Mirela Gavrilas +, Mary Drouin +, Michael Orenak +, Keith Tetter +, Andrea Russell +, Paul Klein +, Matthew Yoder +  and Stephen Smith +
Procedure
AM +  and Emergency Operating Procedure +
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.
ML19120A469 +
Project
CAC:MF9685 +
Project reference
CAC:ME9555 +, CAC:MF8488 +, CAC:MF9685 +, CAC:MF9861 +, TAC:MC4689 +  and TAC:MD1119 +
Project stage
Approval  +
RAS
RAS 2008 +
Regulatory Guide
Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.45 +, Regulatory Guide 1.82 +  and Regulatory Guide 1.17 +
SECY
SECY-10-113 +  and SECY-12-0093 +
SSC
4b-related +
Site
Vogtle +
Start date
September 30, 2019  +
State
Illinois +, Washington +  and New Mexico +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam +  and Containment Spray +
TS
TS-3.4.13 +
Title
Final Safety Evaluation for Vogtle Electric Generating Plant, Units 1 and 2 Systematic Risk-Informed Assessment of Debris Technical Report  +
To
Southern Nuclear +  and Gayheart C +
Topic
Boric Acid +, Mission time +, Fire Barrier +, Weld Overlay +, Internal Flooding +, Probabilistic Risk Assessment +, Coatings +, Finite Element Analysis +, Foreign Material Exclusion +, Large early release frequency +, Stress corrosion cracking +, Earthquake +, Fuel cladding +, Dissimilar Metal Weld +, Core Exit Thermocouple +, Unidentified leakage +, Power Uprate +, Water hammer +  and Gas accumulation +
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/ML1912/ML19120A469.pdf  +
WCAP
WCAP-16568-P +, WCAP-16406-P-A +, WCAP-16530-NP +, WCAP-16530-NP-A +, WCAP-16793-NP-A +  and WCAP-17788-P +
Westinghouse report
WCAP-16568-P +, WCAP-16406-P-A +, WCAP-16530-NP +, WCAP-16530-NP-A +, WCAP-16793-NP-A +  and WCAP-17788-P +
 
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