Pages that link to "10 CFR 50.60, Acceptance Criteria for Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation"

The following pages link to 10 CFR 50.60, Acceptance Criteria for Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation:

Displayed 50 items.

• 10 CFR 50.54, Conditions of licenses ‎ (← links)
• 10 CFR 50.60 (redirect page) ‎ (← links)
  • 10 CFR 50 ‎ (← links)
  • 10 CFR 52.47, Contents of Applications; Technical Information ‎ (← links)
  • 10 CFR 52.137, Contents of Applications; Technical Information ‎ (← links)
  • 05000373/FIN-2014002-01 ‎ (← links)
  • 05000456/FIN-2013008-01 ‎ (← links)
  • 05000456/FIN-2013008-02 ‎ (← links)
  • IR 05000456/2014010 ‎ (← links)
  • IR 05000456/2014005 ‎ (← links)
  • IR 05000456/2013008 ‎ (← links)
  • IR 05000259/2006007 ‎ (← links)
  • IR 05000373/2014002 ‎ (← links)
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  • NRC Generic Letter 1992-01 ‎ (← links)
  • Regulatory Guide 1.190 ‎ (← links)
  • Regulatory Guide 1.162 ‎ (← links)
  • ML18043A008 ‎ (← links)
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  • ML17289A715 ‎ (← links)
  • DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 5, Reactor Coolant System ‎ (← links)
  • L-2016-198, Redacted Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System ‎ (← links)
  • NL-15-169, Browns Ferry, Units 1, 2, and 3, Template of NRC Review Standard for Extended Power Uprates, RS-001 Safety Evaluation Template GDC Markup (Retyped) ‎ (← links)
  • ML12335A487 ‎ (← links)
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  • ML17305A419 ‎ (← links)
  • NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 4 - Reactor Coolant System - Design Basis ‎ (← links)
  • ML111360054 ‎ (← links)
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  • ML070680370 ‎ (← links)
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  • NL-07-008, Proposed Changes to Indian Point, Unit 3 Technical Specifications Regarding Updated Pressure-Temperature and Low Temperature Overpressure Protection System Limits ‎ (← links)
  • ML063350404 ‎ (← links)
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  • ML18227A338 ‎ (← links)
  • ML18211A569 ‎ (← links)
  • RS-14-129, Responses to NRC Requests for Additional Information, Set 19, Dated April 8, 2014, Related to the Braidwood Station, Units 1 and 2, and Byron Station, Units 1, and 2, License Renewal Application ‎ (← links)
  • ML18298A012 ‎ (← links)
  • ML18101A220 ‎ (← links)
  • ML18100A640 ‎ (← links)
  • ML18096B186 ‎ (← links)
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  • ML18064A616 ‎ (← links)
  • ML18058A955 ‎ (← links)
  • ML092990570 ‎ (← links)
  • L-09-072, Davis-Besse, Unit 1 - License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in ‎ (← links)
  • ML18153B999 ‎ (← links)
  • ML18153A835 ‎ (← links)
  • ML18153A732 ‎ (← links)
  • ML18153A678 ‎ (← links)
  • CNL-16-109, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates ‎ (← links)
  • L-13-223, License Amendment Request to Implement 10 CFR 50.61a. Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events. ‎ (← links)
  • RNP-RA/11-0038, Revision to Reactor Vessel Surveillance Capsule Removal Schedule ‎ (← links)
  • HNP-11-034, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule ‎ (← links)
  • L-2011-164, Renewed Facility Operating License No. NPF-16; Request for Exemption from 10 CFR 50 Appendix G Requirements for PT Limits ‎ (← links)
  • L-2011-075, Response to NRC Request for Additional Information (RAI) Regarding Extended Power Uprate License Amendment Request ‎ (← links)
  • L-2011-076, Response to NRC Request for Additional Information (RAI) Regarding Extended Power Uprate License Amendment Request ‎ (← links)
  • L-09-225, Supplemental Information Related to a License Amendment Request to Incorporate the Use of Alternate Methodologies for the Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves, and Request for Exemption From. ‎ (← links)
  • 2CAN091702, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule ‎ (← links)
  • 1CAN031403, Request for Exemption from Certain 10 CFR 50.61 and 10 CFR 50, Appendix G Requirements ‎ (← links)
  • L-2013-244, Reactor Vessel Material Surveillance Program - Revised Surveillance Capsule Withdrawal Schedule for X4 ‎ (← links)
  • NRC 2013-0022, Supplement to License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) ‎ (← links)
  • NRC 2013-0005, License Amendment Request 252, Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) ‎ (← links)
  • L-2009-222, Response to Request for Additional Information (RAI) Regarding Update to NRC Reactor Vessel Integrity Database and Exemption Request for Alternate Material Properties Bases Per 10 CFR 50.12 and 10 CFR 50.60 (B) ‎ (← links)
  • PLA-6507, License Renewal Application (LRA) Draft Safety Evaluation Report (SER) Comments ‎ (← links)
  • L-09-072, License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 Cfr. ‎ (← links)
  • L-2009-023, Update to NRC Reactor Vessel Integrity Database and Exemption Request for Alternate Material Properties Bases Per 10 CFR 50.12 and 10 CFR 50.60 (B) ‎ (← links)
  • NRC 2008-0029, Pressure and Temperature Limits Report ‎ (← links)
  • NRC 2008-0014, Pressure and Temperature Limits Report ‎ (← links)
  • NRC 2007-0092, Pressure and Temperature Limits Report ‎ (← links)
  • PLA-6277, Follow-up to Request for Additional Information for the Review of the License Renewal Application (LRA) Section 4.1.3 ‎ (← links)
  • HNP-07-032, License Renewal Application, Amendment 1: Changes Resulting from Responses to Requests for Additional Information, Site Audit Questions, and Applicant - Identified Changes ‎ (← links)
  • HNP-07-104, Responses to Requests for Additional Information - License Renewal Application Section 4.2 and Subsection B.2.17 ‎ (← links)
  • NRC 2007-0049, Supplement to License Amendment Request 251; Technical Specification 5.6.5., Reactor Coolant System Pressure and Temperature Limits Report ‎ (← links)
  • L-2006-037, Reactor Vessel Surveillance Capsule, Proposed Change in Withdrawal Schedule ‎ (← links)
  • ML19010A275 ‎ (← links)
  • TMI-13-105, Update 10 of the Post-Defueling Monitored Storage Safety Analysis Report ‎ (← links)
  • TMI-13-050, Re-issue of Update 9 of the Post-Defueling Monitored Storage Safety Analysis Report ‎ (← links)
  • TMI-12-183, Revision to the Pressure and Temperature Limit Curves and the Low Temperature Overpressure Protection Limits, and 10 CFR 50.12 Exemption Request - Initial Rt NDT Values for Linde 80 Welds ‎ (← links)
  • NRC-2012-0088, Federal Register Notice - Exemption ‎ (← links)
  • NRC-2011-0194, St. Lucie Nuclear Plant, Units 1 - Federal Register Notice - Exemption from the Requirement of 10 CFR Part 50, Appendix G ‎ (← links)
  • NRC-2010-0025, Environmental Assessment and Finding of No Significant Impact ‎ (← links)
  • ML18334A150 ‎ (← links)
  • ML18117A092 ‎ (← links)
  • ML18153A836 ‎ (← links)
  • NRC-2015-0184, Exemption ‎ (← links)
  • SBK-L-18151, Supplement 61 - Additional Changes to the NextEra Energy Seabrook License Renewal Application ‎ (← links)
  • RA-17-072, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition ‎ (← links)
  • LR-N17-0032, License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report ‎ (← links)
  • PNP 2014-049, License Amendment Request to Implement 10 CFR 50.61 a, Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events. ‎ (← links)
  • SBK-L-11186, License Amendment Request 11-06, Application to Revise the Applicability of the Reactor Coolant System Pressure - Temperature Limits and the Cold Overpressure Protection Setpoints ‎ (← links)
  • NLS2011015, License Amendment Request to Revise Technical Specification Pressure/Temperature Limit Curves and Surveillance Requirements ‎ (← links)
  • NRC 2011-0055, Units I and 2, Transmittal of Core Operating Limits and Pressure and Temperature Limits Reports ‎ (← links)
  • SBK-L-11015, Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Sets 6, 7 and 8 ‎ (← links)
  • BVY 10-071, Technical Specifications Proposed Change No. 293 Revised Reactor Vessel Pressure-Temperature Limitation Curves ‎ (← links)
  • RS-10-080, License Amendment Request Regarding Reactor Coolant System Pressure and Temperature Limit Curves ‎ (← links)
  • BSEP 18-0041, Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report ‎ (← links)
  • L-14-102, License Amendment Request 14-04, Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years ‎ (← links)
  • NOC-AE-11002742, Response to Requests for Additional Information for the License Renewal Application ‎ (← links)
  • NL-19-026, Technical Specifications Proposed Change - Permanently Defueled Technical Specifications ‎ (← links)
  • ML19095A602 ‎ (← links)
  • ML19035A006 ‎ (← links)
  • L-PI-16-049, Revision 34 to Updated Safety Analysis Report, Appendix L, Requirement of Renewed Operating Licenses ‎ (← links)
  • RA-19-0145, Revision to Reactor Vessel Surveillance Capsule Removal Schedule ‎ (← links)
  • ML19106A197 ‎ (← links)
  • ML19106A053 ‎ (← links)
  • ML19158A265 ‎ (← links)
  • L-PI-09-086, NSPM Comments on NRC Safety Evaluation Report with Open Items Related to Renewal of Operating Licenses ‎ (← links)
  • L-PI-08-097, Responses to NRC Requests for Additional Information Dated November 4, 2008 Regarding Application for Renewed Operating Licenses ‎ (← links)
  • SBK-L-06070, Reactor Vessel Surveillance Capsule Report ‎ (← links)
  • BSEP 06-0026, Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power ‎ (← links)
  • NG-05-2208, License Amendment Request Pursuant to 10 CFR 50.90: Revision to the Plant Reactor Pressure Vessel Material Surveillance Program (TSCR-081) ‎ (← links)
  • ML010650229 ‎ (← links)
  • RA-18-0036, License Amendment Request Proposing to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits ‎ (← links)
  • W3F1-2019-0001, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule ‎ (← links)
  • W3F1-2017-0065, License Amendment Request for Use of RAPTOR-M3G Code for Neutron Fluence Calculations ‎ (← links)
  • ML18285A594 ‎ (← links)
  • ML19282D892 ‎ (← links)
  • ML19275F299 ‎ (← links)
  • ML19269B775 ‎ (← links)
  • ML19114A191 ‎ (← links)
  • SRM-COMSECY-18-0016, Regulatory Basis for Appendix H to 10 CFR Part 50-Reactor Vessel Material Surveillance Program Requirements ‎ (← links)
  • COMSECY-18-0016, VR-COMSECY-18-0016: Request Approval to Use the Direct Final Rule Process to Revise the Testing and Reporting Requirements in Appendix Hof 10 CFR Part 50, Reactor Vessel Material Surveillance Program Requirements (RIN-3150-AK07) ‎ (← links)
  • ML19301D160 ‎ (← links)
  • ML19294A182 ‎ (← links)
  • ML15222A880 ‎ (← links)
  • ML15334A250 ‎ (← links)
  • ML053130275 ‎ (← links)
  • ML053070600 ‎ (← links)
  • ML053010167 ‎ (← links)
  • RS-05-103, License Amendment Request Regarding Reactor Coolant System Pressure and Temperature Limits Report and Request for Exemption from 10 CFR 50 .60, Acceptance Criteria for Fracture Prevention Measures For.. ‎ (← links)
  • ML052720270 ‎ (← links)
  • ML052570761 ‎ (← links)
  • ML052570452 ‎ (← links)
  • ML052200226 ‎ (← links)
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  • ML051820209 ‎ (← links)
  • ML051160277 ‎ (← links)
  • ML051030068 ‎ (← links)
  • SBK-L-05072, License Amendment Request 05-01 Request for Amendment to Facility Operating License NPF-86 Recapture of Zero-Power and Low Power Testing/Time ‎ (← links)
  • NRC-05-0011, Proposed License Amendment Request to Revise the Reactor Coolant System Pressure and Temperature Limit Curves in Technical Specification 3.4.10 ‎ (← links)
  • ML050690216 ‎ (← links)
  • ML050610038 ‎ (← links)
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  • ML19332E797 ‎ (← links)
  • ML19332D732 ‎ (← links)
  • ML19332D092 ‎ (← links)
  • NRC 2020-0001, Pressure Temperature Limits Report (PTLR) ‎ (← links)
  • ML19353B127 ‎ (← links)
  • ML19284A372 ‎ (← links)
  • ML15334A249 ‎ (← links)
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  • ML20045D638 ‎ (← links)
  • ML20045C085 ‎ (← links)
  • ML083050449 ‎ (← links)
  • NRC 2003-0018, Request for Exemptions to 10 CFR 50.61, Appendices G and H to 10 CFR 50, and Approval of PTS Application for Pbnp Unit 2 and Proposed Heatup and Cooldown Limit Curves for Pbnp Units 1 & 2 ‎ (← links)
  • ML050190317 ‎ (← links)
  • ML042960007 ‎ (← links)
  • GO2-04-164, License Amendment Request to Revise the Reactor Pressure Vessel Material Surveillance Program ‎ (← links)
  • ML042750322 ‎ (← links)
  • PLA-5811, Proposed Amendment No. 235 to License NFP-22: Changes to Reactor Pressure Vessel Pressure-temperature (P-T) Limits PLA-5811 ‎ (← links)
  • ML042600465 ‎ (← links)
  • ML042050505 ‎ (← links)
  • ML042050079 ‎ (← links)
  • ML041950277 ‎ (← links)
  • W3F1-2003-0075, Ses, Unit 3, License Amendment Request NPF-38-250, Revision to Pressure/Temperature and Low Temperature Overpressure Protection Limits for 32 Effective Full Power Years ‎ (← links)
  • ML041170401 ‎ (← links)
  • LR-N04-0136, Request for Change to Technical Specifications Pressure/Temperature Limits ‎ (← links)
  • ML040640687 ‎ (← links)
  • NL-03-2177, Request to Revise Technical Specifications and Pressure and Temperature Limits Report ‎ (← links)
  • ML040430633 ‎ (← links)
  • NLS2004005, License Amendment Request to Revise Technical Specification 3.4.9 Pressure Temperature (P/T) Curves Figures 3.4.9-1, 3.4.9-2, and 3.4.9-3 ‎ (← links)
  • ML040300882 ‎ (← links)
  • ML040210773 ‎ (← links)
  • ML040200757 ‎ (← links)
  • ML033370869 ‎ (← links)
  • ML033290015 ‎ (← links)
  • ML033210419 ‎ (← links)
  • ML033100141 ‎ (← links)
  • ML033070182 ‎ (← links)
  • ML032970341 ‎ (← links)
  • NRC 2003-0091, Request for Withdrawal, and Resubmittal, of Request for Exemptions to 10 CFR 50.61, Appendices G and H to 10 CFR 50, Approval of PTS Application for Pbnp Unit 2 and Withdrawal of Associated License Amendment Request (LAR) 235 and Submi ‎ (← links)
  • ML032460847 ‎ (← links)
  • ML032410159 ‎ (← links)
  • ML032400625 ‎ (← links)
  • ML032310536 ‎ (← links)
  • ML032300305 ‎ (← links)
  • ML032250621 ‎ (← links)
  • ML032250595 ‎ (← links)
  • ML20065F512 ‎ (← links)
  • ML032110180 ‎ (← links)
  • ML032060558 ‎ (← links)
  • ML032020218 ‎ (← links)
  • ML031990086 ‎ (← links)
  • ML031780107 ‎ (← links)
  • ML031640579 ‎ (← links)
  • ML031630942 ‎ (← links)
  • ML031610859 ‎ (← links)
  • ML031600548 ‎ (← links)
  • BSEP 03-0062, Request for License Amendments Re Implementation of the Boiling Water Reactor Vessel and Internals Project Reactor Pressure Vessel Integrated Surveillance Program to Address the Requirements of Appendix H to 10 CFR Part 50 ‎ (← links)
  • NL-03-093, Proposed Changes to Technical Specifications: Pressure-Temperature and Overpressure Protection System Limits for Up to 20 Effective Full Power Years ‎ (← links)
  • ML031540673 ‎ (← links)
  • ML031530734 ‎ (← links)
  • ML031400137 ‎ (← links)
  • ML031270262 ‎ (← links)
  • ML031110144 ‎ (← links)
  • ML030990129 ‎ (← links)
  • ML030900037 ‎ (← links)
  • ML030870156 ‎ (← links)
  • ML030860626 ‎ (← links)
  • ML030700189 ‎ (← links)
  • ML030640027 ‎ (← links)
  • ML030370431 ‎ (← links)
  • ML030350275 ‎ (← links)
  • ML030230522 ‎ (← links)
  • ML030220073 ‎ (← links)
  • NLS2002104, License Amendment Request, Adopt Integrated Reactor Vessel Material Surveillance Program ‎ (← links)
  • ML023610223 ‎ (← links)
  • ML023460587 ‎ (← links)
  • ML023460458 ‎ (← links)
  • RS-04-075, Request for a License Amendment to Incorporate Approved Pressure and Temperature Limits Report (PTLR) Methodology Into Technical Specifications ‎ (← links)
  • ML023250307 ‎ (← links)
  • ML023250201 ‎ (← links)
  • RS-02-196, Revised Request for Amendment to Technical Specifications Justification for the Continued Use of Technical Specifications, Section 3.4.11, RCS Pressure and Temperature (P/T) Limits. ‎ (← links)
  • ML023220573 ‎ (← links)
  • RS-02-167, Request for Amendment to Technical Specifications Justification for the Continued Use of Technical Specifications, Section 3.4.11, RCS Pressure and Temperature (P/T) Limits. ‎ (← links)
  • ML023010363 ‎ (← links)
  • L-2002-199, Reactor Vessel Surveillance Capsule Report of Test Results ‎ (← links)
  • ML022940024 ‎ (← links)
  • ML022910287 ‎ (← links)
  • ML033360889 ‎ (← links)
  • ML022680131 ‎ (← links)
  • ML032410177 ‎ (← links)
  • ML022630132 ‎ (← links)
  • ML022590527 ‎ (← links)
  • ML20059C340 ‎ (← links)
  • L-02-087, Withdrawal of License Amendment Request 297 ‎ (← links)
  • ML022540231 ‎ (← links)
  • ML022470065 ‎ (← links)
  • ML022100369 ‎ (← links)
  • RS-02-122, Justification for Continued Use of Technical Specifications, Section 3.4.11, RCS Pressure & Temperature (P/T) Limits. ‎ (← links)
  • ML021650244 ‎ (← links)
  • ML021280397 ‎ (← links)
  • ML021210033 ‎ (← links)
  • ML021000663 ‎ (← links)
  • NL-02-016, License Amendment Request (LAR 02-005), Conversion to Improved Standard Technical Specifications ‎ (← links)
  • ML020870784 ‎ (← links)
  • ML020840445 ‎ (← links)
  • ML020600333 ‎ (← links)
  • ML020510501 ‎ (← links)
  • ML020500138 ‎ (← links)
  • ML020430200 ‎ (← links)
  • ML020420477 ‎ (← links)
  • ML020360098 ‎ (← links)
  • ML020240007 ‎ (← links)
  • NL-02-006, Response to Request for Additional Information Indian Point 2 License Amendment Request for Reactor Coolant System Heatup and Cooldown Limitation Curves ‎ (← links)
  • NL-02-001, License Amendment Request - Detection of Technical Specifications for Reactor Vessel Material Surveillance Program ‎ (← links)
  • ML013520605 ‎ (← links)
  • ML013520568 ‎ (← links)
  • ML20087K933 ‎ (← links)
  • ML20087K674 ‎ (← links)
  • ML20087K143 ‎ (← links)
  • ML20087J284 ‎ (← links)
  • ML20087H357 ‎ (← links)
  • ML20087G325 ‎ (← links)
  • ML20087F351 ‎ (← links)
  • ML20086R183 ‎ (← links)
  • ML20073S782 ‎ (← links)
  • ML20073K379 ‎ (← links)
  • ML20073K376 ‎ (← links)
  • ML20101S932 ‎ (← links)
  • ML20101S185 ‎ (← links)
  • ML20101R524 ‎ (← links)
  • ML20101R393 ‎ (← links)
  • ML20101Q403 ‎ (← links)
  • ML20101N929 ‎ (← links)
  • ML20101N479 ‎ (← links)
  • ML20101N159 ‎ (← links)
  • ML20101M689 ‎ (← links)
  • ML20101M646 ‎ (← links)
  • ML20101M504 ‎ (← links)
  • ML20101M337 ‎ (← links)
  • NRC-92-0074, Forwards Response to Rev 1 to Generic Ltr 92-01 Re Reactor Vessel Structural Integrity.All Reactor Pressure Vessel Shell Plates,Used in Fabrication of Reactor Pressure Vessel, Were ASME SA 533-65,Grade B ‎ (← links)
  • ML20101L969 ‎ (← links)
  • ML20101L857 ‎ (← links)
  • ML20101L854 ‎ (← links)
  • ML20101L502 ‎ (← links)
  • ML20101K986 ‎ (← links)
  • ML20101J787 ‎ (← links)
  • ML20101H830 ‎ (← links)
  • ML20101F070 ‎ (← links)
  • ML20101D225 ‎ (← links)
  • ML20094P192 ‎ (← links)
  • ML20094N430 ‎ (← links)
  • ML20094M879 ‎ (← links)
  • ML20094M795 ‎ (← links)
  • ML20094M434 ‎ (← links)
• 10 CFR 50.1, Basis, Purpose, and Procedures Applicable ‎ (← links)
• 10 CFR 50.2, Definitions ‎ (← links)
• 10 CFR 50.3, Interpretations ‎ (← links)
• 10 CFR 50.4, Written Communications ‎ (← links)
• 10 CFR 50.5, Deliberate Misconduct ‎ (← links)
• 10 CFR 50.7, Employee Protection ‎ (← links)
• 10 CFR 50.8, Information Collection Requirements: Omb Approval ‎ (← links)
• 10 CFR 50.9, Completeness and Accuracy of Information ‎ (← links)
• 10 CFR 50.10, License Required; Limited Work Authorization ‎ (← links)
• 10 CFR 50.11, Exceptions and Exemptions From Licensing Requirements ‎ (← links)
• 10 CFR 50.12, Specific Exemptions ‎ (← links)
• 10 CFR 50.13, Attacks and Destructive Acts by Enemies of the United States; and Defense Activities ‎ (← links)
• 10 CFR 50.20, Two Classes of Licenses ‎ (← links)
• 10 CFR 50.21, Class 104 Licenses; for Medical Therapy and Research and Development Facilities ‎ (← links)
• 10 CFR 50.22, Class 103 Licenses; for Commercial and Industrial Facilities ‎ (← links)
• 10 CFR 50.23, Construction Permits ‎ (← links)
• 10 CFR 50.30, Filing of Application for Licenses; Oath Or Affirmation ‎ (← links)
• 10 CFR 50.31, Combining Applications ‎ (← links)
• 10 CFR 50.32, Elimination of Repetition ‎ (← links)
• 10 CFR 50.33, Contents of Applications; General Information ‎ (← links)
• 10 CFR 50.34, Contents of Applications; Technical Information ‎ (← links)
• 10 CFR 50.36, Technical Specifications ‎ (← links)
• 10 CFR 50.37, Agreement Limiting Access to Classified Information ‎ (← links)
• 10 CFR 50.38, Ineligibility of Certain Applicants ‎ (← links)
• 10 CFR 50.39, Public Inspection of Applications ‎ (← links)
• 10 CFR 50.40, Common Standards ‎ (← links)
• 10 CFR 50.41, Additional Standards for Class 104 Licenses ‎ (← links)
• 10 CFR 50.42, Additional Standard for Class 103 Licenses ‎ (← links)
• 10 CFR 50.43, Additional Standards and Provisions Affecting Class 103 Licenses and Certifications for Commercial Power ‎ (← links)
• 10 CFR 50.44, Combustible Gas Control for Nuclear Power Reactors ‎ (← links)
• 10 CFR 50.45, Standards for Construction Permits, Operating Licenses, and Combined Licenses ‎ (← links)
• 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors ‎ (← links)
• 10 CFR 50.47, Emergency Plans ‎ (← links)
• 10 CFR 50.48, Fire Protection ‎ (← links)
• 10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants ‎ (← links)
• 10 CFR 50.50, Issuance of Licenses and Construction Permits ‎ (← links)
• 10 CFR 50.51, Continuation of License ‎ (← links)
• 10 CFR 50.52, Combining Licenses ‎ (← links)
• 10 CFR 50.53, Jurisdictional Limitations ‎ (← links)
• 10 CFR 50.55, Conditions of Construction Permits, Early Site Permits, Combined Licenses, and Manufacturing Licenses ‎ (← links)
• 10 CFR 50.56, Conversion of Construction Permit to License; Or Amendment of License ‎ (← links)
• 10 CFR 50.57, Issuance of Operating License. ‎ (← links)
• 10 CFR 50.58, Hearings and Report of the Advisory Committee On Reactor Safeguards ‎ (← links)
• 10 CFR 50.59, Changes, Tests and Experiments ‎ (← links)
• 10 CFR 50.61, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events ‎ (← links)
• 10 CFR 50.62, Requirements for Reduction of Risk From Anticipated Transients Without Scram (Atws) Events for Light-Water-Cooled Nuclear Power Plants ‎ (← links)
• 10 CFR 50.63, Loss of All Alternating Current Power ‎ (← links)
• 10 CFR 50.64, Limitations On the Use of Highly Enriched Uranium (Heu) In Domestic Non-Power Reactors ‎ (← links)