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ML20062F922 +
10 CFR 21 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 71 +, 10 CFR 50.34 +, 10 CFR 50.57 +, 10 CFR 50.109 +, 10 CFR 50 Appendix E +, 10 CFR 73.50 +, 10 CFR 100.11 +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50 Appendix B Criterion XII, Control of Measuring and Test Equipment +, 10 CFR 50.34#a +, 10 CFR 50.34#b + and 10 CFR 50.34#b6v +
GDC 20 +, GDC 10 +, GDC 35 +, GDC 24 +, GDC 13 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +, GDC 19, Control room +, GDC 4, Environmental and dynamic effects design bases +, GDC 3, Fire protection + and GDC 5, Sharing of structures, systems, and components +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
ML20062F922 +, ML20062F922 +, ML20062F922 +, ML20062F922 +, ML20062F922 +, ML20062F922 +, ML20062F922 +, ML20062F922 +, ML20062F922 +, ML20062F922 +, ML20062F922 +, ML20062F922 +, ML20062F922 +, ML20062F922 + and ML20062F922 +
November 30, 1978 +
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>.
04:25:46, 17 December 2024 +
NUREG-0323 +, NUREG-0321 +, NUREG-0425 +, NUREG-0135 +, NUREG-0471, Responds to 781113 Request & Encl Generic Task Problem Descriptions(NUREG-0471)& NRC Prog for Resolution of Generic Issues Related to Nuc Pwr Plants(NUREG-0410). W/O Encl +, NUREG-0050, Forwards Documents Re 1975 Fire at Plant.Documents Provide Overview of Experience W/Significant Fire That Resulted in Spurious Component Operation,Loss of Control Functions & Erroneous Control Room Instrumentation Readings.W/O Encls +, NUREG-0484, Forwards SER Suppl Info on Applicant 830203 Submittal Re Applicability of Square Root of Sum of Squares Combination of Dynamic Responses.Method Applicable & Complies w/NUREG-0484 +, NUREG-0474, Forwards NUREG-0474 Re Safety of Pressure Suppression Containment Sys,Per 780615 Request.Rept Covers All Pressure Suppression Containment Designs in Use in Us.W/O Encl +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0410, Speech Entitled Shutdown Decay Heat Removal, for Presentation at 890418-20 NRC Regulatory Info Conference in Washington,Dc +, NUREG-0138, Exemption from GDC 17 Requirements Re LPCI Swing Bus Design +, NUREG-0397, Forwards Performance Appraisal Section Mgt Plan for 820419- 23,26-30 & 0510-13.Insps Are Integral Part of Revised NRC Insp Program Described in NUREG-0397 & Approved by NRC in June 1977 +, NUREG-0312, Advises That Util 1979 Mod & Insp Program Is Acceptable & Satisfies NUREG-0312 requirements.NUREG-0619 Will Address BWR Nozzle & Control Rod Drive Return Line Cracking Problem +, 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-0371, Forwards NUREG-0371,NUREG-0471 & NUREG-0600.W/o Encl + and 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 +
145 +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
Request +
Regulatory Guide 1.97 +, Regulatory Guide 1.75 +, Regulatory Guide 1.74 +, Regulatory Guide 1.58 +, Regulatory Guide 8.8 +, Regulatory Guide 1.120 +, Regulatory Guide 1.28 +, Regulatory Guide 1.64 +, Regulatory Guide 1.30 +, Regulatory Guide 1.39 +, Regulatory Guide 1.44 +, Regulatory Guide 1.38 +, Regulatory Guide 1.123 +, Regulatory Guide 1.115 +, Regulatory Guide 1.88 +, Regulatory Guide 1.116 + and Regulatory Guide 1.37, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants +
NEDO-21061 + and NEDO-21480 +
November 30, 1978 +
Washington +, California +, Massachusetts +, Virginia +, New Jersey +, New York +, Oklahoma +, Arkansas +, Vermont +, New Mexico + and Iowa +
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Reactor Pressure Vessel +, Core Spray +, Standby Liquid Control +, Remote shutdown +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Rod Sequence Control System +, Control Rod + and Containment Spray +
Reviews Status of All Contentions Raised by Intervenor Suffolk County in Proceedings Re Subj Facils.Tech Bases & Supporting Documentation for Each Contention Are Provided. Cert of Svc Encl +
Ultimate heat sink +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Post Accident Monitoring +, Operating Basis Earthquake +, Notice of Violation +, Stress corrosion cracking +, Earthquake +, Control of Heavy Loads +, Power Operated Valves +, Turbine Missile +, Fuel cladding +, Failure to Scram +, Affidavit + and Overspeed +
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