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ML20028H394
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Category
CORRESPONDENCE-LETTERS  and OUTGOING CORRESPONDENCE
Accession number
ML20028H394  +
Agency
Environmental Protection Agency +
Atomic Element
Oxygen +, Hydrogen +  and Lead +
CFR
10 CFR 50 Appendix B +, 10 CFR 73 +, 10 CFR 50.34#f +  and 10 CFR 50.3a#f +
Docket
05000605  +  and 00605  +
Equipment trip
Reactor Trip +
From
Scaletti D +  and Office of Nuclear Reactor Regulation +
General design criterion
GDC 56 +
Generic letter
NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 85-06, Quality Assurance Guidance for ATWS Equipment That is Not Safety-Related +, NRC Generic Letter 88-03, Resolution of Generic Safety Issue 93, "Steam Binding of Auxiliary Feedwater Pumps" +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-22, Potential for Increased Roof Loads and Plant Area Flood Runoff Depth Due to Recent Change in Probable Maximum Precipitation Criteria Developed by the National Weather Service +, NRC Generic Letter 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f) +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +
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ML20028H394 +, ML20028H394 +, ML20028H394 +, ML20028H394 +, ML20028H394 +, ML20028H394 +, ML20028H394 +, ML20028H394 +, ML20028H394 +  and ML20028H394 +
Hours
2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +
Issue date
December 20, 1990  +
Manufacturer
General Electric +  and Target Rock +
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>.
22:43:52, 20 December 2024  +
NUREG
NUREG-1289, Submits Revised Agenda for CRGR Meeting 141 on 880714 in Bethesda,Md.Items for Review Include Proposed Generic Ltr on Instrument Air Problems & Proposed Draft Rule to Require College Degrees for Senior Reactor Operators +, NUREG-0803, Forwards Request for Addl Info to Be Transmitted to Applicant Re Internally Generated Missiles & NUREG-0803 +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-0844, Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl +, NUREG-1296, Thermal Overload Protection for Electric Motors on Safety-Related motor-Operated Valves - Generic Issue II.E.6.1 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0609, Forwards Request for Addl Info on Generic Ltr 84-04,Safety Evaluation of Westinghouse Topical Repts Dealing W/ Eliminating of Postulated Pipe Breaks in PWR Primary Main Loops. Response Requested by 840731 +, NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +, NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +
Page count
23  +
Procedure
AM +
Project stage
RAI  +
Regulatory Guide
Regulatory Guide 1.97 +, Regulatory Guide 1.143 +, Regulatory Guide 1.7 +, Regulatory Guide 1.106 +  and Regulatory Guide 1.6 +
Scram
Manual Scram +
Site
05000605 +
Start date
December 20, 1990  +
State
Maryland +, Washington +  and California +
System
Steam Generator +, Feedwater +, Primary containment +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, Standby Gas Treatment System +, Main Steam Line +, Safety Relief Valve +, Main Steam +  and Containment Spray +
Title
Forwards Request for Addl Info Re Application for Certification of Advanced BWR Design  +
To
Marriott P +  and GENERAL ELECTRIC CO. +
Topic
Reactor Vessel Water Level +, Design basis earthquake +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Loss of Offsite Power +, Containment high range radiation monitor +, Control of Heavy Loads +  and Offsite Circuit +
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http://pbadupws.nrc.gov/docs/ML2002/ML20028H394.pdf  +
 
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