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ML20072H086
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Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
ANSI code
ANSI N18.1-1971 +  and ANSI N18.7-1971 +
Accession number
ML20072H086  +
Agency
Federal Emergency Management Agency +
Atomic Element
Boron +  and Lead +
CFR
10 CFR 73 +, 10 CFR 2.206 +, 10 CFR 50.44 +, 10 CFR 50 Appendix E +, 10 CFR 50.55a +, 10 CFR 70.24 +, 10 CFR 50.54#p +, 10 CFR 73.55#d9 +  and 10 CFR 50#s2 +
Cross cutting aspect
P.1(m) +
Docket
05000374  +  and 00374  +
Emergency Facility
Technical Support Center +
From
Exelon +  and Schroeder C +
Generic letter
NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +
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ML20072H086 +, ML20072H086 +, ML20072H086 +, ML20072H086 +, ML20072H086 +, ML20072H086 +, ML20072H086 +, ML20072H086 +, ML20072H086 +, ML20072H086 +, ML20072H086 +, ML20072H086 +, ML20072H086 +, ML20072H086 +, ML20072H086 +, ML20072H086 +, ML20072H086 +  and ML20072H086 +
Issue date
March 18, 1983  +
Letter
ML20027E131 +  and IR 05000373/1979029 +
Manufacturer
General Electric +
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10:13:01, 15 December 2024  +
NRC bulletin
NRC Bulletin 80-11 +
NUREG
NUREG-0519, Safety Evaluation of Final in-plant Safety/Relief Valve Test Evaluation Rept Per SER (NUREG-0519).Design Adequate to Accommodate Loads Associated W/Activation of One or More Safety Relief Valves +, NUREG-0803, Forwards Request for Addl Info to Be Transmitted to Applicant Re Internally Generated Missiles & NUREG-0803 +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, 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 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0808, Forwards Safety Evaluation Accepting Revised Safety Relief Valve & Condensation Oscillation Loads Per NUREG-0802 & NUREG-0808 & Temp Cutoff Value Used for Elimination of Data Base for Load Computations +
Page count
64  +
Person
L. O. DelGeorge +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.97 +
Report
NEDE-21175P +  and NEDE-21175 +
Site
LaSalle +
Start date
March 18, 1983  +
State
Illinois +  and Idaho +
System
Reactor Core Isolation Cooling +, Primary containment +, Safety Parameter Display System +, HVAC +, Core Spray +, Residual Heat Removal +, Automatic Depressurization System +, Intermediate Range Monitor +, Emergency Core Cooling System +, Control rod blade +  and Control Rod +
TS
TS-6.1.C +
Title
Forwards Review of Implementation Status of Unit 1 License Conditions as Potentially Applicable to Unit 2. Documentation,Corrections of Deficiencies & Testing Will Be Completed by Unit 2 OL Issuance  +
To
Schwencer A +  and Office of Nuclear Reactor Regulation +
Topic
Hydrostatic +, Operating Basis Earthquake +  and Shift Technical Advisor +
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http://pbadupws.nrc.gov/docs/ML2007/ML20072H086.pdf  +
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