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ML20209F914
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Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
Accession number
ML20209F914  +
Atomic Element
Boron +
CFR
10 CFR 50 Appendix B +
Cross cutting aspect
H.2(n) +
Docket
05000285  +  and 00285  +
From
Omaha Public Power District +  and Andrews R +
Generic letter
NRC Generic Letter 83-37, NUREG-0737 Technical Specifications +, NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +  and NRC Generic Letter 82-28, Inadequate Core Cooling Instrumentation System +
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ML20209F914 +, ML20209F914 +, ML20209F914 +, ML20209F914 +, ML20209F914 +, ML20209F914 +, ML20209F914 +, ML20209F914 +, ML20209F914 +, ML20209F914 +, ML20209F914 +, ML20209F914 +, ML20209F914 +, ML20209F914 +  and ML20209F914 +
IEEE
IEEE 323-1974 +  and IEEE 344-1975 +
Issue date
June 27, 1985  +
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22:57:03, 6 December 2024  +
NUREG
NUREG/CR-2627 +, NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
60  +
Procedure
ES +, CH +, TOP +  and Emergency Operating Procedure +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.97 +
SSC
111umi-nating +
Site
Fort Calhoun +
Start date
June 27, 1985  +
State
Washington +, Nebraska +  and New Hampshire +
System
Reactor Coolant System +, Safety Parameter Display System +  and Qualified Safety Parameter Display System +
Title
Forwards Final Design Description for NUREG-0737,Item II.F.2, Inadequate Core Cooling Instrumentation, Per NRC .Document Undergoing Internal Review.Any Addl Info Will Be Submitted by 850719  +
To
Butcher E +  and Office of Nuclear Reactor Regulation +
Topic
Core Exit Thermocouple +
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http://pbadupws.nrc.gov/docs/ML2020/ML20209F914.pdf  +
 
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