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ML19011A325
Show incoming properties
Category
Letter, License-Operating (New/Renewal/Amendments) DKT 50  and Safety Evaluation
Accession number
ML19011A325  +
Act
Atomic Energy Act of 1954 +
Atomic Element
Boron +  and Sodium +
CFR
10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 30 +, 10 CFR 51 +, 10 CFR 50.62 +, 10 CFR 50.90 +, 10 CFR 73.21 +, 10 CFR 50.54#p +, 10 CFR 50.36#c2 +, 10 CFR 50.36#c5 +, 10 CFR 50.36#c +, 10 CFR 50.62#c4 +, 10 CFR 50.62#e +, 10 CFR 73.55#51 +, 10 CFR 51.22#b +  and 10 CFR 51.22#c9 +
Contact
Tobin J, NRR/DORL/LPL1 +
Cornerstone
Physical Protection +
Correspondence
SECY-92-223 +
Docket
05000277  +, 05000278  +, 00277  +  and 00278  +
Document
ML003763736 +, ML16034A372 +, Information Notice 2001-13, Inadequate Standby Liquid Control System Relief Valve Margin +, ML17286A013 +, ML18150A387 +, ML18312A407 +, ML18340A185 +  and ML19011A325 +
Equipment trip
Reactor Trip +
FR
36 FR 3255 +, 32 FR 10213 +  and 83 FR 55564 +
From
Jennifer Tobin +  and Plant Licensing Branch I +
General design criterion
GDC 41 +, GDC 15 +, GDC 14 +, GDC 30 +, GDC 31 +, GDC 28 +, GDC 29 +, GDC 37 +, GDC 42 +  and GDC 9 +
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>.
ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +, ML19011A325 +...
Hours
2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 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)  +
Issue date
February 26, 2019  +
Letter
05000278/LER-2004-002, Loss of High Pressure Coolant Injection System Automatic High Level Trip as a Result as a Result of Lifted Lead +, JAFP-18-0052, Proposed Alternative to Utilize Code Case N-879 +, ML062750099 +, LR-N06-0249, Units 2 and 3, Nuclear Facilities, NRC Decommissioning Funding Status Report +, ML18338A083 +  and ML043020352 +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
General Electric +  and Target Rock +
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>.
11:08:43, 5 January 2025  +
NRC information notice
Information Notice 2001-13, Inadequate Standby Liquid Control System Relief Valve Margin +
Page count
27  +
Procedure
TP +
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.
ML19011A325 +
Project
EPID:L-2018-LLA-0151 +
Project reference
CAC:MF9289 +  and EPID:L-2018-LLA-0151 +
Project stage
Approval  +
Report
NEDE-32906P +
SECY
SECY-92-223 +
SSC
004N6240-NP +
Site
Peach Bottom +
Site license
Peach Bottom +
Start date
February 26, 2019  +
State
Washington +  and Pennsylvania +
System
Reactor Coolant System +, Feedwater +, High Pressure Coolant Injection +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Pressure Vessel +, Automatic Depressurization System +, Standby Liquid Control +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +  and Control Rod +
TS
TS-3.5.1 +, TS-3.4.3 +  and TS-2.1.2 +
Title
Issuance of Amendment Nos. 323 and 326 to Revise Technical Specifications to Allow Continued Operation with Two Safety Relief Valves/Safety Valves Out of Service  +
To
Exelon +  and Bryan Hanson +
Topic
Reactor Vessel Water Level +, Anticipated operational occurrence +, Cyber Security +, Safeguards Contingency Plan +, Fuel cladding +, Fire Protection Program +, Power change +, Power Uprate +  and Measurement Uncertainty Recapture +
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/ML1901/ML19011A325.pdf  +
Vendor
GE Hitachi Nuclear Energy +
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