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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
- GNRO-2003/00075, Response to Request for Additional Information Shutdown Cooling System Isolation Instrumentation + (ML033640504)
- L-2003-286, Response to NRC RAI Regarding Station Blackout Analysis + (ML033640526)
- ML033640539 + (ML033640539)
- NOC-AE-03001656, Proposed Emergency Change to Technical Specification 3.8.1.1 to Support Diesel Generator Inspections + (ML033640545)
- ML033640545 + (ML033640545)
- WO 03-0068, Response to NRC Bulletin 2003-04, Rebaselining of Data in the Nuclear Materials Management and Safeguards System + (ML033640559)
- ML033640559 + (ML033640559)
- 3F1203-15, Final Response to Request for Additional Information Related to Crystal River Unit 3 - Revised Appendix R Exemption Request - Fire Area CC-164-121 + (ML033640567)
- ML033640569 + (ML033640569)
- ML033640570 + (ML033640570)
- ML033640573 + (ML033640573)
- ML033640576 + (ML033640576)
- WO 03-0062, Response to RAI for the Revision to Technical Specifications 3.8.1, AC Sources - Operating and 3.8.4, DC Sources - Operating + (ML033640577)
- PLA-5682, Final Response to January 7, 2003 NRC Order Modifying Licenses EA-02-261 Compliance with All Compensatory Measures, PLA-5682 + (ML033640579)
- NRC-03-0098, Oscillation Power Range Monitor Operability at Option III Plants + (ML033640581)
- ML033640582 + (ML033640582)
- ML033640583 + (ML033640583)
- L-2003-306, Order (EA-03-009) Relaxation Request - Examination Coverage of Reactor Pressure Vessel Head Penetration Nozzles + (ML033640584)
- ML033640585 + (ML033640585)
- HNP-03-150, Partial Withdrawal of License Amendment Request Regarding Administrative Revision to the Technical Specification Index + (ML033640587)
- ML033640589 + (ML033640589)
- ML033640590 + (ML033640590)
- ML033640591 + (ML033640591)
- LR-N03-0526, Letter Informing NRC Regarding Plans to Enable the Oscillation Power Range Monitor (OPRM) Trip Function for the Hope Creek + (ML033640592)
- ML033640592 + (ML033640592)
- ML033640594 + (ML033640594)
- ML033640595 + (ML033640595)
- L-2003-234, NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity Inspection Results. + (ML033640596)
- ML033640596 + (ML033640596)
- CPSES-200302701, 60 Day Response Regarding NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity and Report on RCS Conoseal Leakage + (ML033640598)
- GO2-03-185, Implementation of the Performance Demonstration Methods Supplement Ten (10) Qualification Requirements for Dissimilar Metal Welds + (ML033640600)
- ML033640602 + (ML033640602)
- L-2003-308, NRC Order EA-03-009, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Results + (ML033640605)
- ML033640607 + (ML033640607)
- RA-03-187, Registration of Spent Dry Cask in Use at the Maine Yankee Independent Spent Fuel Storage Installation + (ML033640610)
- ML033640613 + (ML033640613)
- DCL-03-165, 90-Day Response to NRC Bulletin 2003-04, Rebaselining of Data in the Nuclear Materials Management and Safeguards System. + (ML033640619)
- ML033640619 + (ML033640619)
- ML033640623 + (ML033640623)
- B19025, Revised Emergency Plan Procedures + (ML033640625)
- RS-03-238, Stations - Additional Information for the Review of the License Renewal Applications + (ML033640630)
- RS-03-230, Schedule for Completing Actions to Implement Long-Term Stability Solution + (ML033640632)
- ULNRC-04917, Revision of License Amendment Request OL-1225 Regarding Proposed Changes to Technical Specifications for Extension of Required Action Completion Times for Diesel Generators + (ML033640633)
- ULNRC-04909, Response to RAI Regarding License Amendment Request OL-1228 (Revision to Technical Specification Surveillance Requirements 3.8.1 and 3.8.4) + (ML033640634)
- ULNRC-04928, Responses to RAIs on the Proposed Revision to Technical Specification (TS) 1.1, Definitions, TS 3.7.3, Main Feedwater Isolation Valves (Mfivs), and Steam Generator Tube Rupture with Overfill Re-Analysis + (ML033640635)
- 05000443/LER-2003-002, Regarding Reactor Trip Following the Loss of a Main Feed Pump + (ML033640636)
- ML033640639 + (ML033640639)
- ML033640662 + (ML033640662)
- ML033640671 + (ML033640671)
- ML033640677 + (ML033640677)
- ML033650050 + (ML033650050)