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ML041040023
Show incoming properties
Category
Letter, Code Relief or Alternative  and License-Application for Facility Operating License (Amend/Renewal) DKT 50
Accession number
ML041040023  +
Atomic Element
Lead +
CFR
10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50.90 +, 10 CFR 50.92 +, 10 CFR 51.22 +, 10 CFR 50.55a +, 10 CFR 50.55a#a3 +  and 10 CFR 51.22#c9 +
Docket
05000440  +  and 00440  +
From
FirstEnergy +  and Kanda W +
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>.
ML041040023 +, ML041040023 +, ML041040023 +, ML041040023 +, ML041040023 +, ML041040023 +, ML041040023 +, ML041040023 +, ML041040023 +, ML041040023 +, ML041040023 +, ML041040023 +  and ML041040023 +
Hours
1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +
Issue date
March 31, 2004  +
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>.
08:38:39, 16 January 2025  +
NUREG
NUREG-0626, Forwards NUREG-0645,Vols 1-2, Rept of Bulletins & Orders Task Force & NUREG-0626, Generic Evaluation of Feedwater Transients & Small Break LOCAs in GE-Designed Operating Plants & Near Term OL Applications. W/O Encl +  and NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +
Page count
28  +
Procedure
AM +
Project reference
TAC:MB2256 +, TAC:MB5138 +  and TAC:M74784 +
Project stage
Request  +
Report
NEDC-31753P +  and NEDO-32291 +
SR
SR-3.5.1.7 +, SR-3.4.4.1 +, SR-3.5.1.6 +, SR-3.5.1.8 +, SR-3.5.1.5 +, SR-3.6.1.6.1 +, SR-3.6.1.6.2 +, SR-3.3.5.1.6 +, SR-3.4.4.2 +, SR-3.4.4.3 +  and SR-3.3.6.4.4 +
SSC
1B21-F047D +, 1B21-FO41A +, I4the-SIRV-dicc +  and 11B21-F0411B +
Site
Perry +
Start date
March 31, 2004  +
State
Ohio +, Pennsylvania +  and Washington +
System
Feedwater +, Main Turbine +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Automatic Depressurization System +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Main Steam +  and Low Pressure Coolant Injection +
TS
TS-3.3.5.1 +
Test
Bench test +
Title
License Amendment Request Pursuant to 10 CFR 50.90 and Relief Request Pursuant to 10 CFR 50.55a(a)(3) Related to the Testing of Safety/Relief Valves  +
To
Office of Nuclear Reactor Regulation +  and Document Control Desk +
Topic
Foreign Material Exclusion +, Affidavit +  and Subsequent actuation +
Turbine component
Turbine bypass valve +
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http://pbadupws.nrc.gov/docs/ML0410/ML041040023.pdf  +
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