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ML20198R333
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Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
ASME section
ASME Section II +
Accession number
ML20198R333  +
Atomic Element
Boron +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Chloride +, Lead +  and Silver +
CFR
10 CFR 50 +  and 10 CFR 50.49 +
Docket
05000289  +  and 00289  +
Drawing
FE-7A +
Equipment trip
Reactor Trip +
From
FirstEnergy +  and Hukill H +
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>.
ML20198R333 +, ML20198R333 +, ML20198R333 +, ML20198R333 +, ML20198R333 +, ML20198R333 +, ML20198R333 +, ML20198R333 +, ML20198R333 +, ML20198R333 +, ML20198R333 +, ML20198R333 +  and ML20198R333 +
IEEE
IEEE 279 +
Issue date
June 5, 1986  +
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14:17:01, 10 December 2024  +
NUREG
NUREG-737 +, NUREG-0103, Safety Evaluation Supporting Relief from Inservice Insp Requirements of ASME Boiler & Pressure Vessel Code Requiring Quarterly Stroke Testing of RCS Valves & Denying Relief from Code Requirements for Valve RC-11 Testing +, NUREG-0801, Forwards Comments on Program Plan for Detailed Control Room Design Review (Dcrdr).Program Plan Addresses All Required Elements of DCRDR.In-progress Audit Not Planned +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
53  +
Procedure
ST-79 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.97 +, Regulatory Guide 1.100 +, Regulatory Guide 1.28 +, Regulatory Guide 1.118 +, Regulatory Guide 1.64 +, Regulatory Guide 1.30 +, Regulatory Guide 1.89 +, Regulatory Guide 1.144 +, Regulatory Guide 1.38 +, Regulatory Guide 1.123 +, Regulatory Guide 1.146 +  and Regulatory Guide 1.37, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants +
SSC
N0n-Comment +
Site
Crane +
Site license
Crane +
Start date
June 5, 1986  +
State
Pennsylvania +  and Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Residual Heat Removal +, Shield Building +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Control Rod +, Main Steam +, Containment Spray +  and Emergency Feedwater System +
TS
TS-4.4.3.2 +  and TS-4.6 +
Title
Forwards Response to NRC Evaluation of Plant Conformance to Reg Guide 1.97 Re Emergency Response Capability.Schedule of Plant Mods Also Encl.Mods Scheduled for Completion During Cycle 7 Refueling Outage  +
To
Stolz J +  and Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, Grab sample +, Commercial Grade +  and Fuel cladding +
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/ML2019/ML20198R333.pdf  +
 
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