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ML22278A233
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Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI B31.1 +
ASME section
ASME Section III +
Accession number
ML22278A233  +
CFR
10 CFR 50 Appendix A +, 10 CFR 50 Appendix B +, 10 CFR 50.49 +  and 10 CFR 50.69 +
Docket
05000352  +  and 05000353  +
From
Constellation +
General design criterion
GDC 1, Quality standards and records +
Generic letter
NRC Generic Letter 81-07, Control of Heavy Loads +  and NRC Generic Letter 85-11, Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612 +
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ML22278A233 +, ML22278A233 +, ML22278A233 +, ML22278A233 +, ML22278A233 +, ML22278A233 +, ML22278A233 +, ML22278A233 +, ML22278A233 +  and ML22278A233 +
IEEE
IEEE 344 +, IEEE 382 +, IEEE 323 +, IEEE 279 +, IEEE 344-1975 +  and IEEE 334 +
In package
ML22278A223 +
Issue date
September 19, 2022  +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
Cutler-Hammer +, Westinghouse +, Valcor +, Fisher Controls +, Mercoid +, Target Rock +, Magnetrol +  and Westronics +
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>.
20:33:07, 27 November 2024  +
NRC bulletin
NRC Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or over Safety-Related Equipment +
NUREG
NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, 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
28  +
Power source
4kV +  and 4.16kV +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.100 +
Report
NEDE-24788 +
Site
Limerick +
Site license
NPF-27 +
Start date
September 19, 2022  +
System
Feedwater +, Secondary containment +, Reactor Protection System +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Intermediate Range Monitor +, Remote shutdown +, Main Steam Line +  and Main Steam +
Title
Rev. 21 to Updated Final Safety Analysis Report, Chapter 3, Sections 3.10, Qualification of Seismic Category I Instrumentation and Electrical Equipment  +
To
Office of Nuclear Reactor Regulation +
Topic
Anticipated operational occurrence +, Excess Flow Check Valve +  and Control of Heavy Loads +
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http://pbadupws.nrc.gov/docs/ML2227/ML22278A233.pdf  +
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