Pages that link to "NUREG/CR-6413"
Jump to navigation
Jump to search
The following pages link to NUREG/CR-6413:
Displayed 40 items.
- ML16293A584 (← links)
- ML15334A240 (← links)
- ML15222A848 (← links)
- ML15154B077 (← links)
- ML12055A166 (← links)
- ML110910250 (← links)
- ML18085A164 (← links)
- ML18085A161 (← links)
- L-2015-160, WCAP-17939-NP, Revision 0, Analysis of Capsule 97 Degrees from the Florida Power & Light Company St. Lucie, Unit 2, Reactor Vessel Radiation Surveillance Program, Part 1 of 3 (← links)
- ML110730084 (← links)
- ML110060693 (← links)
- ML101740061 (← links)
- ML091550271 (← links)
- ML063250415 (← links)
- ML061040593 (← links)
- L-2011-029, Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Reactor Materials Issues - Round 1 (← links)
- PNP 2011-044, Response to Request for Additional Information for Pressurized Thermal Shock Evaluation (← links)
- W3F1-2019-0022, Resubmittal of Reactor Vessel Material Surveillance Program Capsule Test Results (← links)
- SRM-COMSECY-18-0016, Regulatory Basis for Appendix H to 10 CFR Part 50-Reactor Vessel Material Surveillance Program Requirements (← links)
- NL-04-092, Capsule X Material Surveillance Report (← links)
- NL-04-042, Reactor Vessel Material Surveillance Program: Preliminary Analysis Results for Capsule X (← links)
- W3F1-2003-0020, Submittal of Second Reactor Vessel Surveillance Capsule Report (← links)
- ML023460503 (← links)
- DCL-03-052, Rev 0 to WCAP-15958, Analysis of Capsule V from Pacific Gas & Electric Co Diablo Canyon Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix a Through E (← links)
- ML030710172 (← links)
- L-2002-082, Part 2 of 2, St. Lucie, Unit 1 - Reactor Vessel Surveillance Capsule, Report of Test Results - Revision 1, Appendix B, Charpy V-Notch Plots for Each Capsule Using Hyperbolic Tangent Curve-Fitting Method (← links)
- ML021190357 (← links)
- ML20108F000 (← links)
- ML20138E000 (← links)
- ML20246G422 (← links)
- LR-N20-0072, License Amendment Request to Amend Tech Specs to Revise and Relocate the Reactor Coolant System Pressure & Temperature Limits & Pressurizer Overpressure Protection System Limits to a Pressure & Temperature Limits Report (← links)
- ML21175A300 (← links)
- ML21210A325 (← links)
- ML20329A264 (← links)
- L-PI-22-005, WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 5 Through Appendix D (← links)
- WBL-20-004, Analysis of Capsule U from Watts Bar Unit 2 Reactor Vessel Radiation Surveillance Program (← links)
- L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) (← links)
- L-PI-23-007, Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) (← links)
- L-PI-23-002, WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 7 of 7) (← links)
- L-2021-142, Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 (← links)