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ML20181A434 +
BWRVIP-03 + and BWRVIP-190 +
Regulatory Guide 1.121 +, Regulatory Guide 1.190 +, IR 05000324/2007011 +, ML031470422 +, ML16190A241 +, ML003717179 +, ML031600712 +, Information Notice 1990-10, Primary Water Stress Corrosion Cracking of Inconel 600 +, Information Notice 1990-30, Ultrasonic Inspection Techniques for Dissimilar Metal Welds +, Information Notice 1990-04, Cracking of the Upper Shell-to-Transition Cone Girth Welds in Steam Generators, +, ML051860406 +, ML17187A204 +, ML100260948 +, ML15187A206 +, ML14073A059 +, ML14087A210 +, ML052710007 +, ML12297A333 +, ML031430208 +, ML12097A064 +, SBK-L-12023, Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Request for Additional Information - Set 18, RAI B.2.1.11-2 +, ML031130463 +, ML17188A158 +, ML081500814 +, ML19191A057 +, Information Notice 2013-20, Steam Generator Channel Head and Tubesheet Degradation +, NL-07-120, Response to Request for Additional Information Regarding Relief Request 3-43 for Temporary Repair to Service Water Pipe +, ML18291A828 +, ML19294A044 +, ML20044D902 +...
NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +, NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors +, NRC Generic Letter 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking + and NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +
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>.
ML20181A434 +, ML20181A434 +, ML20181A434 +, ML20181A434 +, ML20181A434 +, ML20181A434 + and ML20181A434 +
February 18, 2021 +
05000263/LER-2014-001, Regarding Primary System Leakage Found in Recirculation Pump Upper Seal Heat Exchanger + and 05000280/LER-1991-019, :on 910828,through-wall Crack Discovered in Component Cooling Water Supply to Reactor Shroud Cooler B.On 910827,RCS Loop B Instrumentation Behaved Erratically.Caused by Leak in Piping.Piping Will Be Replaced +
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>.
01:22:30, 11 December 2024 +
Information Notice 2006-27, Circumferential Cracking in the Stainless Steel Pressurizer Heater Sleeves of Pressurized Water Reactors +, Information Notice 97-46 +, Information Notice 94-63 +, Information Notice 97-19 +, Information Notice 84-18 +, Information Notice 80-38 +, Information Notice 91-05 +, Information Notice 97-88 +, Information Notice 82-37 +, Information Notice 85-65 +, Information Notice 90-04 +, Information Notice 90-10 +, Information Notice 96-11 +, Information Notice 85-24 +, Information Notice 89-33 +, Information Notice 94-87 +, Information Notice 2013-20, Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) +, Information Notice 2007-37, Buildup of Deposits in Steam Generators +, Information Notice 90-30 +, Information Notice 91-19 + and Information Notice 95-17 +
NUREG/CR-4513 +, NUREG-1544 +, NUREG-2181, Supplement. 1, Safety Evaluation Report Related to the License Renewal of Sequoyah Nuclear Plant Units 1 and 2 +, NUREG/CR-6001 +, 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-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +, NUREG-1557, Technical Info from Industry Repts Addressing License Renewal, Presented at 970817-22 14th Intl Conference on Structural Mechanics in Reactor Technology in Lyon,France +, NUREG-2191, Draft NUREG-2191 Vol 2 GALL-SLR Rev1 -12-14-24 +, NUREG-2205, Safety Evaluation Report - Related to the License Renewal of LaSalle County Station, Units 1 and 2 - Docket Nos. 50-373 and 50-374 - Exelon Generation Company, Llc +, NUREG-2221, Supplement 1, Technical Bases for Changes in the Subsequent License Renewal Guidance Documents, NUREG-2191, Revision 1, and NUREG-2192, Revision 1 Final Report + and NUREG-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report +
153 +
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Other +
February 18, 2021 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Standby Liquid Control +, Spray Pond +, Emergency Core Cooling System +, Control Rod + and Containment Spray +
SLR-ISG-2021-02-Mechanical - Updated Aging Management Criteria for Mechanical Portions of Subsequent License Renewal Guidance +
Boric Acid +, Ultimate heat sink +, Fire Barrier +, Coatings +, Incorporated by reference +, Aging Management +, Intergranular Stress Corrosion Cracking +, Microbiologically influenced corrosion +, Stress corrosion cracking +, License Renewal +, Subsequent License Renewal +, Subsequent License Renewal Application +, EVT-1 +, Fire Protection Program +, Dissimilar Metal Weld +, Scaffolding +, Backfit + and Power Uprate +
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