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ML21278A186
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Category
Updated Final Safety Analysis Report (UFSAR)
Accession number
ML21278A186  +
Atomic Element
Boron +  and Rhodium +
CFR
10 CFR 50 Appendix R +  and 10 CFR 50 Appendix A +
Correspondence
RS-232 +
Docket
05000317  +  and 05000318  +
Emergency Facility
Technical Support Center +
Equipment trip
Reactor Trip +
From
Exelon +
Generic letter
NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +  and NRC Generic Letter 88-17, Loss of Decay Heat Removal +
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ML21278A186 +, ML21278A186 +, ML21278A186 +, ML21278A186 +, ML21278A186 +, ML21278A186 +, ML21278A186 +, ML21278A186 +, ML21278A186 +  and ML21278A186 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
IEEE
IEEE 279 +
In package
ML21278A102 +
Issue date
September 7, 2021  +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
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>.
03:07:22, 28 November 2024  +
NEI
NEI 99-04, Guideline for Managing NRC Commitment Changes +
NUREG
NUREG-1342, Discusses New multi-plant Action MPA F-72, SPDS-Response to Generic Ltr 89-06, Initiated to Accurately Reflect Status of SPDS Issue in Sims.Procedures Should Be Followed by Affected Plants as Indicated +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
22  +
Power source
4kV +
Project stage
Request  +
RS
RS-232 +
Regulatory Guide
Regulatory Guide 1.97 +
Site
Calvert Cliffs +
Start date
September 7, 2021  +
System
Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Shutdown Cooling +, Safety Parameter Display System +, Decay Heat Removal +, Safety Relief Valve +, Control Rod +  and Containment Spray +
TS
TS-3.3.3.2 +  and TS-3.3.10 +
Title
2 to Updated Final Safety Analysis Report, Chapter 7, Section 7.5, Instrumentation Systems  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, Grab sample +, Earthquake +, Commercial Grade +, Fire Protection Program +  and Core Exit Thermocouple +
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http://pbadupws.nrc.gov/docs/ML2127/ML21278A186.pdf  +
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