(Task SI 502-4) Format & Content of Plant-Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactors
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GO2-04-125, Request for Permanent Relief from Inservice Inspection Requirements of 10 CFR 50.55(g) for the Volumetric Examination of Circumferential Reactor Pressure Vessel Welds
JAFP-16-0137, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1), Implementation of BWRVIP-05 at James A. FitzPatrick Nuclear Power Plant
BSEP 18-0015, Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations
NLS2105025, 10 CFR 50.55a Requests for Fifth Ten-Year Inservice Inspection Interval
NUREG-2123 Volume 2, Safety Evaluation Report Related to the License Renewal of Columbia Generating Station
NL-11-0242, Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i), HNP-ISI-ALT-11
RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix a - Application of NRC Regulatory Guides
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 18.0 - Response to NUREG-0737 Clarification of TMI Action Plan Requirements
NLS2009063, Response to Request for Additional Information for License Renewal Application
RA-09-015, Proposed Relief Request to the Requirements of 10 CFR 50.55a Concerning Reactor Pressure Vessel Circumferential Shell Welds
W3F1-2008-0060, . Request for Alternative W3-ISI-006 and Proposed Alternative to Extend the Second 10-Year Inservice Inspection Interval for Reactor Vessel Internal Weld Examinations
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment and Systems
CNRO-2007-00020, Request for Alternative W3-ISI-003, Proposed Alternative to Extend the Second 10 - Year Inservice Inspection Interval for Reactor Vessel Internal Weld Examinations
NL-07-0270, Proposed Alternative for RPV Circumferential Weld Examinations
CNL-18-123, Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second Ten Year Interval Request for Relief 1-ISI-27
NRC Generic Letter 89-21, Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements
NL-05-0720, Request for Relief to Extend the Third 10-Year Inservice Inspection Interval for the Reactor Vessel Weld Examination
NL-04-1764, Third 10-Year Interval Inservice Inspection Program Submittal of Revised Relief Request RR-38
NL-03-0704, Measurement Uncertainty Recapture Power Uprate Request for Additional Information Response
PLA-7895, Relief Request 4RR-02, Revision 1 (PLA-7895)
LD-91-065, Forwards Response to Request for Addl Info Re Std SAR Design Certification
LIC-90-0202, Comment on Proposed Rule 10CFR50, Fracture Toughness Requirements for Protection Against Thermal Shock Events. Recommends That Use of Credible Surveillance Data Be Allowed to Establish Consistent Calculational Method W/Reg Guide
BECO-89-178, Forwards Response to Generic Ltr 89-21, Request for Info Re Status of Implementation of USI Requirements
L-89-415, Forwards Status of Implementation of USI for Which Final Technical Resolution Has Been Achieved,Per Generic Ltr 89-21, Request for Implementation of USI Requirements
CNL-16-072, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection and Augmented Programs, Unit 2 Fifth Ten Year Interval Request for Relief 2-ISI-30 and Unit 3 Fourth Ten Year Interval Request
CNL-15-125, American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (Lsi) and Augmented Program, Second Ten Year Interval Request for Relief 1-ISI-27
NRC 2004-0111, License Renewal Application Response to Request for Additional Information
NRC 2004-0085, License Renewal Application Revised Information
NL-04-0478, Third 10-Year Interval Inservice Inspection Program Submittal of Relief Requests (RR) RR-38, RR-39, and RR-40