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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
- ENS 40605 +
- ENS 44037 +
- IR 05000275/2004003 +
- NUREG-1927 +
- ML17047A038 +
- ML16109A337 +
- NL-16-2707, Units 1 and 2; Fourth 10-year Interval In-service Inspection Program ISI Program Update: Notification of Impractical ASME Code Requirements (NL-16-2707) +
- ML003717179 +
- ML062440478 +
- ML12270A258 +
- ML18040A316 +
- ML17059B677 +
- NL-15-2270, Response to Request for Additional Information for Alternative HNP-ISI-ALT-5-01 +
- ML103010104 +
- ML15334A223 +
- ML15222A825 +
- ML15175A193 +
- HNP-15-039, Relief Request I3R-15 Revision 2, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Third Ten-Year Interval +
- HNP-15-034, Relief Request I3R-15 Revision and Supplement, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program - Third Ten-Year Interval +
- HNP-15-010, Relief Request I3R-15, Reactor Vessel Closure Head Nozzle Repair Technique Inservice Inspection Program - Third Ten-Year Interval +
- ML092330231 +
- ML092320124 +
- ML063050504 +
- ML062010210 +
- ML101440381 +
- ML12334A659 +
- HNP-13-119, Relief Request I3R-13, Reactor Vessel Closure Head Nozzle 37, Inservice Inspection Program - Third Ten-Year Interval +
- ML043130170 +
- ML101660468 +
- GNRO-2012/00109, Stress Analysis Summary Demonstrating That the Nozzle to Safe-End DMW, N06B-KB, Will Perform Its Intended Design Function After Weld Overlay Installation +
- HNP-12-060, Relief Request I3R-09 Reactor Vessel Closure Head Nozzle Repairs Inservice Inspection Program - Third Interval, Request for Additional Information Response +
- ML12118A484 +
- ML12080A142 +
- ML120190748 +
- HNP-18-045, Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval +
- ML17265A740 +
- ML17292B659 +
- ML17292B658 +
- ML17292B615 +
- LR-N17-0088, Redacted - Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 3, Design of Structures, Components, Equipment and Systems, Sections 3.1 Through 3.5 +
- LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 5, Reactor Coolant System and Connected Systems +
- ML12088A430 +
- RA-10-096, Submittal of Analytical Evaluation for a Reactor Recirculation Line Weld +
- DCL-10-120, Response to NRC Letter Dated August 26, 2010, Request for Additional Information (Set 17) for License Renewal Application +
- LR-N10-0192, Response to NRC Request for Additional Information Dated May 14, 2010 Related to Aging Management Program B.2.1.6, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel +
- ML091400101 +
- ML091190637 +
- ML042450041 +
- SBK-L-10027, Inservice Inspection Examination Report for Inspections Conducted Prior to and During the Thirteenth Refueling Outage That Concluded on November 12, 2009 +
- ML091530151 +