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ML20197J380
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Category
INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE
Accession number
ML20197J380  +
Agency
Energy Facility Site Evaluation Council +
Atomic Element
Boron +, Hydrogen +  and Lead +
CFR
10 CFR 50 Appendix J +
Docket
05000397  +, 05000460  +  and 00397  +
From
Office of Nuclear Reactor Regulation +  and Minners W +
Generic letter
NRC Generic Letter 82-26, NUREG-0744, REV. 1 - Pressure Vessel Material Fracture Toughness +
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ML20197J380 +, ML20197J380 +, ML20197J380 +, ML20197J380 +, ML20197J380 +, ML20197J380 +, ML20197J380 +, ML20197J380 +, ML20197J380 +, ML20197J380 +  and ML20197J380 +
Issue date
March 19, 1985  +
Manufacturer
Target Rock +
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17:22:49, 10 December 2024  +
NUREG
NUREG-1055, Further Response to FOIA Request for Three Categories of Records Re NUREG-1055.Forwards App C Documents +  and NUREG-0667, 06-10-80 Report on NUREG-0667 Transient Response of Babcock - Wilcox-Designed Reactors +
Page count
18  +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.8 +
SSC
M9R-OP +
Site
Columbia +  and Washington Public Power Supply System +
Start date
March 19, 1985  +
State
Washington +  and Maryland +
System
Steam Generator +, Feedwater +, Service water +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Standby Liquid Control +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +  and Main Steam +
TS
TS-4.6.1.2 +  and TS-4.6.2.1 +
Title
Forwards Suggested Response to DW Mazur 850215 Question 2 Re Future Licensability of Facility.Response Items Based on Commission 1985 Policy & Planning Guidance.Nj Palladino Also Forwarded  +
To
Adensam E +  and Office of Nuclear Reactor Regulation +
Topic
Offsite Dose Calculation Manual +, Stress corrosion cracking +, Excess Flow Check Valve +, Power Operated Valves +, Backfit +, Water hammer +  and Control Room Habitability +
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http://pbadupws.nrc.gov/docs/ML2019/ML20197J380.pdf  +
 
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