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ML19309C033
Show incoming properties 
Category
INTERROGATORIES; RESPONSES TO INTERROGATORIES  and LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
ASME section
ASME Section III +
Accession number
ML19309C033  +
Agency
Environmental Protection Agency +  and Federal Emergency Management Agency +
Atomic Element
Hydrogen +, Lead +  and Silver +
CFR
10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.55 +, 10 CFR 50.55a#h +, 10 CFR 12.720 +  and 10 CFR 32.744 +
Cornerstone
Emergency Preparedness +
Docket
05000289  +  and 00289  +
From
Swartz L +  and NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) +
General design criterion
GDC 35 +, GDC 13 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +, GDC 4, Environmental and dynamic effects design bases +  and GDC 1, Quality standards and records +
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ML19309C033 +, ML19309C033 +, ML19309C033 +, ML19309C033 +, ML19309C033 +, ML19309C033 +, ML19309C033 +, ML19309C033 +, ML19309C033 +, ML19309C033 +, ML19309C033 +, ML19309C033 +  and ML19309C033 +
IEEE
IEEE 323 +, IEEE 323-1974 +  and IEEE 279 +
Intervenor
Union of Concerned Scientists +
Issue date
March 31, 1980  +
Letter
ML16245A452 +
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08:35:41, 2 January 2025  +
NRC bulletin
NRC Bulletin 79-18, Audibility Problems Encountered on Evacuation of Personnel from High-Noise Areas +
NUREG
NUREG/CR-1219 +, NUREG/CR-0138 +, NUREG/CR-0165 +, NUREG-034 +, NUREG-0565, Forwards Topical Rept Evaluation of BAW-10092P,Rev 3 & BAW-10154 B&W Owners Group Small Break LOCA Evaluation model,CRAFT2 (Rev 3).Two Confirmatory Issues Identified. Response Requested within 45 Days of Ltr Receipt +, NUREG-0635, Forwards SER Re TMI Item II.K.3.30 for C-E Plants,Per Conditional Acceptance of CEN-203(P),Rev 1, Response to NRC Action Plan Item II.K.3.30 Justification of Small Break LOCA Methods +, NUREG-0175 +, NUREG-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +, NUREG-0560, Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress +, 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 +, NUREG-0153, NRC Staff Response to ASLB Questions Concerning Generic Safety Issues.Conclusions in Perkins SER Re Issuance of Const Permits Will Not Be Affected by Results of Generic Tasks.W/Certificate of Svc.Supporting Documents Encl +, NUREG/CR-0400, Forwards NRC Policy Statement Re Reactor Safety Study,Review by the Lewis Committee (NUREG/CR-0400) & Survey of NRC Uses of WASH-1400.All Documents Have Been Furnished to ASLB & Aslab Panel Members.W/O Encl +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +
Page count
99  +
Regulatory Guide
Regulatory Guide 1.47 +, Regulatory Guide 1.70 +  and Regulatory Guide 1.89 +
Site
Crane +
Start date
March 31, 1980  +
State
Connecticut +, Maryland +, Washington +, Massachusetts +, Virginia +, South Carolina +, Michigan +, Indiana +, Arkansas +  and Delaware +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Auxiliary Feedwater +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Control Rod +  and Containment Spray +
Title
Response to Ucs First & Second Sets of Interrogatories. Includes Bibliography of Class 9 Accident Studies & NRC Position on Ucs Contentions.Prof Qualifications & Affidavits Encl  +
To
UNION OF CONCERNED SCIENTISTS +
Topic
Reactor Vessel Water Level +, Anticipated operational occurrence +, High Energy Line Break +, Loss of Offsite Power +, Backfit +  and Affidavit +
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http://pbadupws.nrc.gov/docs/ML1930/ML19309C033.pdf  +
 
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