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
- CPSES-200401771, Transmittal of Units 1 and 2 Inservice Testing Plan for Pumps and Valves, Revision 0 (ASME OM Code 1998 Edition, 1999 and 2000 Addenda, Interval Start Date - August 3,2004, Second Interval) + (ML042230167)
- NL-04-1426, Additional Information Request Related to Request for Technical Specification Changes DC Sources - Operating + (ML042230170)
- NL-04-1367, Response to Third Request for Additional Information Related to Request to Revise Technical Specifications - Containment Equipment Hatch + (ML042230172)
- ML042230173 + (ML042230173)
- ML042230177 + (ML042230177)
- ML042230182 + (ML042230182)
- CY-04-160, Registration of Spent Fuel Dry Cask in Use at the Haddam Neck Plant: (HNP) Independent Spent Fuel Storage Installation (ISFSI + (ML042230186)
- ML042230195 + (ML042230195)
- ML042230196 + (ML042230196)
- ML042230205 + (ML042230205)
- ML042230207 + (ML042230207)
- ML042230212 + (ML042230212)
- ML042230214 + (ML042230214)
- 05000456/LER-2004-002, Regarding 1 C Reactor Containment Fan Cooler Discovered to Be Inoperable Greater than Required Technical Specification Allowed Outage Time + (ML042230220)
- 05000440/LER-2003-004-02, Regarding Emergency Service Water Pump Upper Shaft Coupling Sleeve Failure + (ML042230224)
- 05000440/LER-2003-005-01, 1 for Perry Nuclear Power Plant Regarding Technical Specification Violation/Loss of Safety Function Due to Air Bound Water-Leg Pump + (ML042230230)
- ML042230236 + (ML042230236)
- GNRO-2004/00045, Fitness for Duty (FFD) Six-Month Report + (ML042230255)
- 05000339/LER-2004-004, Regarding Reactor Trip Due to Incorrect Cell Switch Contact Configuration on Bypass Reactor Trip Breaker + (ML042230263)
- 05000272/LER-2004-003, Regarding Completion of Plant Shutdown to Comply with Technical Specifications - 3.6.1.1 Containment Integrity + (ML042230276)
- LR-N04-0341, First Revised NRC Order EA-03-009: Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Post Outage Inspection Results + (ML042230280)
- LR-N04-0326, Response to Request for Additional Information Request for Change to Technical Specifications Pressure/Temperature Limits + (ML042230287)
- LR-N04-0337, Loss of Coolant Accident Peak Clad Temperature Annual Report + (ML042230290)
- ML042230293 + (ML042230293)
- ML042230326 + (ML042230326)
- ML042230333 + (ML042230333)
- ML042230335 + (ML042230335)
- ML042230366 + (ML042230366)
- ML042230368 + (ML042230368)
- NL-04-1408, Request for Technical Specifications Change Steam Generator Program - Revision I + (ML042230373)
- GO2-04-137, Request for Amendment to Technical Specifications for One-Time Extension of Containment Leak Rate Test Interval + (ML042230382)
- ML042230388 + (ML042230388)
- ML042230493 + (ML042230493)
- IR 05000259/2004007 + (ML042240003)
- ML042240009 + (ML042240009)
- IR 05000266/2004005 + (ML042240036)
- ML042240039 + (ML042240039)
- ML042240045 + (ML042240045)
- ML042240048 + (ML042240048)
- ML042240056 + (ML042240056)
- ML042240058 + (ML042240058)
- NLS2004100, Nebraska Public Power District Response to Request for Additional Information + (ML042240060)
- ML042240084 + (ML042240084)
- ML042240093 + (ML042240093)
- ML042240097 + (ML042240097)
- ML042240103 + (ML042240103)
- ML042240114 + (ML042240114)
- ML042240158 + (ML042240158)
- ML042240161 + (ML042240161)
- ML042240163 + (ML042240163)
- PNO-III-04-010, Palisades Shut Down to Repair Control Rod Drive Mechanism Leakage + (ML042240168)