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ML20198L754 +
BVY 98-102 +, BVY 97-40 +, BVY 98-69 +, BVY 98-33 +, BVY 98-123 +, BVY 97-152 +, BVY 98-73 +, BVY-98-73 +, BVY 98 52 +, BVY 98 73 +, BVY 97-57 +, BVY 97-67 +, BVY 98-71 + and BVY-98-123, Responds to NRC Re Violations Noted in Insp Rept 50-271/98-80.Corrective Actions:Completed Formal Engineering Analysis of Radiological Dose Consequences & Approved Bmo in Conjunction W/Rev 1 of SE Performed for Temporary Mod +
10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 100 +, 10 CFR 50.63 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 50.2 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50 Appendix B Criterion XI +, 10 CFR 50 Appendix B Criterion XII, Control of Measuring and Test Equipment +, 10 CFR 50.55a +, 10 CFR 50.73#A + and 10 CFR 50.71#e +
BVY 98-102 +, BVY 97-40 +, BVY 98-69 +, BVY 98-33 +, BVY 98-123 +, BVY 97-152 +, BVY 98-73 +, BVY-98-73 +, BVY 98 52 +, BVY 98 73 +, BVY 97-57 +, BVY 97-67 +, BVY 98-71 + and BVY-98-123, Responds to NRC Re Violations Noted in Insp Rept 50-271/98-80.Corrective Actions:Completed Formal Engineering Analysis of Radiological Dose Consequences & Approved Bmo in Conjunction W/Rev 1 of SE Performed for Temporary Mod +
NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability +, NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment + and NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +
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>.
IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +, IR 05000271/1998013 +...
December 23, 1998 +
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>.
15:09:40, 10 December 2024 +
NUREG-1606, Summary of CRGR Meeting 310 on 970909 Re Proposed Rev 1 to GL 91-18,proposed Amends to 10CFR50.55a & Proposed GL on Lab Testing of nuclear-grade Activated Charcoal.Attendee List & Presentation Matl,Encl +, NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report + and NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +
43 +
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 +
13 +
December 23, 1998 +
Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Main Transformer +, Main Turbine +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Standby Liquid Control +, Residual Heat Removal Service Water +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam + and Low Pressure Coolant Injection +
Insp Rept 50-271/98-13 on 981011-1121.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support +
Time of Discovery +, Offsite Dose Calculation Manual +, Fire Barrier +, Stroke time +, Tornado Missile +, Probabilistic Risk Assessment +, Temporary Modification +, High Energy Line Break +, Tornado Generated Missile +, Tornado Missile Protection +, Notice of Violation +, Systematic Assessment of Licensee Performance +, Operability Determination +, Battery sizing +, Power-Operated Valves + and Hardened vent +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.