Search by property
Jump to navigation
Jump to search
This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
List of results
- ML070170460 + (10CFR21 for FMEA and Pre-installation Setup of Woodward Digital Reference Unit (Dru); Fairbanks Morse Engine Reporting Id 06-05)
- ML040150618 + (10CFR26, Unsatisfactory Fitness-for-Duty Blind Performance Testing Incident)
- DCL-17-059, 10CFR26.719(c) Notification - Testing Error for Two Specimens + (10CFR26.719(c) Notification - Testing Error for Two Specimens)
- NL-20-1362, 10CFR26.719(c)(1) 30-Day Report for Blind Performance Test Results Inconsistent with Sample Provided + (10CFR26.719(c)(1) 30-Day Report for Blind Performance Test Results Inconsistent with Sample Provided)
- RA-22-0058, 10CFR26.719(c)(1) Report - Unsatisfactory Performance of a Health and Human Services Certified Lab + (10CFR26.719(c)(1) Report - Unsatisfactory Performance of a Health and Human Services Certified Lab)
- ML20035H542 + (10CFR50 App G Equivalent Margin Analysis for Low Upper Shelf Energy in BWR/2 Through BWR/6 Vessels)
- ML18142A221 + (10CFR50 App R Rept - App A,Summary Comparison of 1984 App R Reanalysis & 1980-1982 Post-Fire Safe Shutdown Review)
- ML20214Q977 + (10CFR50,App R Compliance Assessment Rept for San Onofre Generating Station Units 2 & 3. Requests for Exemptions from 10CFR50,App R Requirements Encl)
- ML20064C013 + (10CFR50,App R Supplementary Info Rept to Vols I & II Submitted to NRC 820628)
- ML19319D802 + (10CFR50,Reactor Containment Leakage Testing for Water-Cooled Power Reactors. Specifies Min Containment Leakage Test Requirements)
- ML023250106 + (10CFR50.46 (a) (3) (II) Report of Changes to Calculated Peak Clad Temperature)
- ML051300138 + (10CFR50.46 30 Day and Annual ECCS Report)
- ML021340157 + (10CFR50.46 30-Day Report for Changes to Emergency Core Cooling System Performance Analysis)
- ML021270329 + (10CFR50.46 Annual ECCS Report)
- ML041940389 + (10CFR50.46 Annual ECCS Report for R. E. Ginna Nuclear Power Plant)
- ULNRC-04751, 10CFR50.46 Annual Report ECCS Evaluation Model Revisions + (10CFR50.46 Annual Report ECCS Evaluation Model Revisions)
- ML023010207 + (10CFR50.46 Annual Report ECCS Evaluation Model Revisions)
- ML20101M268 + (10CFR50.46 Annual Rept)
- ML20101U395 + (10CFR50.46 Annual Rept - ECCS Evaluation Model Revisions, for June 1991 to June 1992)
- ML20137N399 + (10CFR50.46 ECCS Evaluation Model 1996 Annual Rept)
- 3F1104-05, 10CFR50.46 Loss-Of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report + (10CFR50.46 Loss-Of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report)
- 3F1103-04, 10CFR50.46 Loss-of-Coolant Accident Evaluation Model Change and Peak Clad Temperature Change Report + (10CFR50.46 Loss-of-Coolant Accident Evaluation Model Change and Peak Clad Temperature Change Report)
- ML20099A697 + (10CFR50.46 Margin Utilization Byron & Braidwood Station, Units 1 & 2, Constituting Annual Rept of Results of ECCS Evaluation Models for Period Ending 910725)
- LR-N12-0301, 10CFR50.46 Report + (10CFR50.46 Report)
- LR-N07-0261, 10CFR50.46 Report, Informing of Changes in the Application of the Emergency Core Cooling System Evaluation Modes + (10CFR50.46 Report, Informing of Changes in the Application of the Emergency Core Cooling System Evaluation Modes)
- LR-N11-0275, 10CFR50.46 Reports Changes in the Application of the Emergency Core Cooling System Evaluation Models + (10CFR50.46 Reports Changes in the Application of the Emergency Core Cooling System Evaluation Models)
- NOC-AE-02001441, 10CFR50.46 Thirty Day Report of Significant ECCS Model Changes + (10CFR50.46 Thirty Day Report of Significant ECCS Model Changes)
- ML023570351 + (10CFR50.46 Thirty Day Report of Significant ECCS Model Changes)
- BVY 03-111, 10CFR50.46(a)(3)(ii) Annual Report for 2003 + (10CFR50.46(a)(3)(ii) Annual Report for 2003)
- ML050260294 + (10CFR50.46(a)(3)(ii) Annual Report for 2004)
- BVY 06-002, 10CFR50.46(a)(3)(ii) Annual Report for 2005 + (10CFR50.46(a)(3)(ii) Annual Report for 2005)
- BVY 07-006, 10CFR50.46(a)(3)(ii) Annual Report for 2006 + (10CFR50.46(a)(3)(ii) Annual Report for 2006)
- BVY 10-001, 10CFR50.46(a)(3)(ii) Annual Report for 2009 + (10CFR50.46(a)(3)(ii) Annual Report for 2009)
- BVY 12-003, 10CFR50.46(a)(3)(ii) Annual Report for 2011 + (10CFR50.46(a)(3)(ii) Annual Report for 2011)
- BVY 14-003, 10CFR50.46(a)(3)(ii) Annual Report for 2013 + (10CFR50.46(a)(3)(ii) Annual Report for 2013)
- BVY 10-033, 10CFR50.46(a)(3)(ii) Report Covering Initial Operation of Plant Cycle 28 Commencing in May 2010 + (10CFR50.46(a)(3)(ii) Report Covering Initial Operation of Plant Cycle 28 Commencing in May 2010)
- 05000352/FIN-2003006-01 + (10CFR50.54(Q) Violation for Decreasing the Effectiveness of the Plan by Changing Eals That Address Toxic Gas Without Prior NRC Approval)
- RC-03-0220, 10CFR50.54(a)(3) / 10CFR50.59 Biennial Report + (10CFR50.54(a)(3) / 10CFR50.59 Biennial Report)
- RS-17-059, 10CFR50.54(q)(5) Procedure Change Summary Analysis, Rev. 27 to EP-AA-1003, Radiological Emergency Plan Annex and Rev. 28 to EP-AA-1000, Standardized Radiological Emergency Plan + (10CFR50.54(q)(5) Procedure Change Summary Analysis, Rev. 27 to EP-AA-1003, Radiological Emergency Plan Annex and Rev. 28 to EP-AA-1000, Standardized Radiological Emergency Plan)
- ML080720668 + (10CFR50.54(w)(3) Annual Reporting of Property Damage Insurance)
- ML020880239 + (10CFR50.54(w)(3) Reporting Requirements, Nuclear Property and Decontamination Liability Insurance)
- ML19322D654 + (10CFR50.55(e) Interim Repts - Settlement of Diesel Generator Foundations & Bldg. Consists of 781107,1221, 790105,0223,0403,0625,0810 & 0905 Repts Referenced by Amend 72 to OL & Cp.Oversize Drawings Encl)
- ML032880448 + (10CFR50.55a Alternative Repair Request for the Second 10-Year Interval of the Inservice Program: Relief Request 23, Revision 1, Pressurizer Nozzle Repair, Preheated Band Examination Methods)
- ML032681105 + (10CFR50.55a Alternative Repair Request for the Second 10-Year Interval of the Inservice Inspection Program: Relief Request 23, Revision 1, Temper Bead Post Weld Examination Methods)
- L-MT-21-039, 10CFR50.55a Request Associated with the Sixth Inservice Testing Ten-Year Interval (L-MT-21-039) + (10CFR50.55a Request Associated with the Sixth Inservice Testing Ten-Year Interval (L-MT-21-039))
- EPID:L-2021-LLR-0061 + (10CFR50.55a Request Associated with the Sixth Inservice Testing Ten-Year Interval (L-MT-21-039))
- ET 14-0018, 10CFR50.55a Request I3R-10 for Third Inservice Inspection Program Interval + (10CFR50.55a Request I3R-10 for Third Inservice Inspection Program Interval)
- ET 12-0010, 10CFR50.55a Request Number I3R-07, Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds + (10CFR50.55a Request Number I3R-07, Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds)
- B18993, 10CFR50.55a Request RR-89-46 to Use ASME Code Case N-597-1 for Analytical Evaluation of Pipe Wall Thinning as an Alternative to ASME Code Section XI + (10CFR50.55a Request RR-89-46 to Use ASME Code Case N-597-1 for Analytical Evaluation of Pipe Wall Thinning as an Alternative to ASME Code Section XI)
- L-MT-23-008, 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003) + (10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003))
- L-MT-11-055, 10CFR50.55a Requests Associated with the Fifth Inservice Testing Ten-Year Lnterval + (10CFR50.55a Requests Associated with the Fifth Inservice Testing Ten-Year Lnterval)
- L-MT-11-056, 10CFR50.55a Requests Associated with the Fifth Inservice Inspection Ten-Year Interval + (10CFR50.55a Requests Associated with the Fifth Inservice Inspection Ten-Year Interval)