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ML23173A025 +
BWRVIP-75-A +, BWRVIP-190 +, BWRVIP-05 +, BWRVIP-27-A +, BWRVIP-47-A +, BWRVIP-48-A +, BWRVIP-49-A +, BWRVIP-139-A +, BWRVIP-74-A +, BWRVIP-14-A +, BWRVIP-60-A +, BWRVIP-59-A + and BWRVIP-52-A +
10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 2 +, 10 CFR 54 +, 10 CFR 2.390 +, 10 CFR 50.12 +, 10 CFR 50.49 +, 10 CFR 50.60 +, 10 CFR 50.65 +, 10 CFR 50.69 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.3 +, 10 CFR 50.55a +, 10 CFR 54.21#d +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii +, 10 CFR 54.21#c +, 10 CFR 54.21#c2 +, 10 CFR 54.21#cii +, 10 CFR 50.55a#a3 + and 10 CFR 54.21#ciii +
NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 81-11, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking (NUREG-0619) +, 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 + and NRC Generic Letter 98-05, Boiling Water Reactor Licensees Use of the BWRVIP-05 Report to Request Relief from Augmented Examination Requirements on Reactor Pressure Vessel Circumferential Shell Welds +
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>.
ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 +, ML23173A025 + and ML23173A025 +
April 10, 2023 +
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>.
07:59:35, 27 November 2024 +
NUREG/CR-6260 +, NUREG-1769, (3:3) Chpt 3 - End, Safety Evaluation Report Related to License Renewal of Peach Bottom Atomic Power Station, Units 2 & 3 +, 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-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, 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-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-2191, Draft NUREG-2191 Vol 2 GALL-SLR Rev1 -12-14-24 + and NUREG-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report +
1 +
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.
Supplement +
NEDC-33006P + and NEDC-32983P +
April 10, 2023 +
Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Control Room Emergency Ventilation +, Standby Liquid Control +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Control Rod + and Main Steam +
9 to Updated Final Safety Analysis Report, Appendix R, Second License Renewal UFSAR Supplement, Pages R-1 to R-89 - Redacted +
Fire Barrier +, Weld Overlay +, Hydrostatic +, Coatings +, High Energy Line Break +, Aging Management +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Main Steam Line Radiation Monitor +, License Renewal +, Earthquake +, Control of Heavy Loads +, Biofouling +, Flow Induced Vibration +, Power Uprate +, Stretch Power Uprate +, Measurement Uncertainty Recapture +, Thermography +, GNF3 +, Thermal fatigue +, Spill + and Pressure Temperature Limits Report +
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