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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

• ML021560516  + (ML021560516)
• BW020046, Notification of Modification Completion in Support of License Amendment to Revise Technical Specification Requirements Associated with the Boron Dilution Protection System  + (ML021560530)
• ML021560536  + (ML021560536)
• NRC-02-0034, Proposed License Amendment for the Revision of Control Room Emergency Filtration System Technical Specification Requirements During Movement of Recently Irradiated Fuel  + (ML021560537)
• 05000352/LER-2002-001, Re Inoperable Safeguard Battery Charger Discovered During Review of Completed Surveillance Test  + (ML021560539)
• 05000275/LER-2002-002, Re Steam Generator Tube Plugging Due to Stress Corrosion Cracking  + (ML021560548)
• ML021560550  + (ML021560550)
• RBG-45950, License Amendment Request Re Removal Operating Mode Restrictions for Performing Emergency Diesel Generator Testing  + (ML021560560)
• ML021560564  + (ML021560564)
• ML021560568  + (ML021560568)
• ML021560575  + (ML021560575)
• NRC-02-0036, Proposed Technical Specification Change (License Amendment) - Response Time Testing  + (ML021560577)
• LIC-02-0064, Withdrawal of Request for Hearing on Interim Safeguards and Security Compensatory Measures Order  + (ML021560578)
• ML021560591  + (ML021560591)
• ML021560599  + (ML021560599)
• ML021560605  + (ML021560605)
• ML021560606  + (ML021560606)
• ML021560650  + (ML021560650)
• ML021570003  + (ML021570003)
• ML021570004  + (ML021570004)
• ML021570006  + (ML021570006)
• ML021570007  + (ML021570007)
• ML021570009  + (ML021570009)
• NRC 2002-0043, and Point Beach, Units 1 & 2 - NRC Bulletin 2002-01: Reactor Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity - 60 Day Response  + (ML021570010)
• ML021570010  + (ML021570010)

• ML021570015  + (ML021570015)

• L-02-070, License Amendment Request No. 165 Re Modification of Design Feature 5.3.1, Criticality, to Increase the New Fuel (Fresh Fuel) Storage Racks Enrichment Limit to 5.00 Weight Percent  + (ML021570016)
• ML021570018  + (ML021570018)
• 05000269/LER-2002-003, Re Minor Reactor Pressure Vessel Head Leakage Due to Primary Water Stress Corrosion Cracking of an Alloy 600 Control Rod Drive Nozzle  + (ML021570019)
• CPSES-200202095, 60-Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.  + (ML021570021)
• ML021570021  + (ML021570021)
• 05000352/LER-2002-002, Re Inoperable Core Spray Internal Line Break Alarm Due to Instrument Zero Offset Change  + (ML021570025)
• VR-SECY-02-0088, Turkey Point Nuclear Plant, Units 3 & 4, Renewal of Full-Power Operating Licenses  + (ML021570026)
• ML021570032  + (ML021570032)
• ML021570035  + (ML021570035)
• 05000454/LER-2002-002, Re Two or Three Pressurizer Safety Valve Relief Tests Exceeded Required Tolerance Due to Setpoint Drift  + (ML021570037)
• WO 02-0027, April 2002 Monthly Operating Report for Wolf Creek Generating Station  + (ML021570038)
• CPSES-200202257, Change of Address Notification  + (ML021570040)
• ML021570042  + (ML021570042)
• ML021570043  + (ML021570043)
• ML021570058  + (ML021570058)
• ML021570060  + (ML021570060)
• L-02-065, License Amendment Request No. 301 Re Positive Moderator Temperature Coefficient  + (ML021570069)
• ML021570083  + (ML021570083)
• ML021570089  + (ML021570089)
• RIS 2002-09, Withdrawn NRC Regulatory Issue Summary 2002-009: Preparation and Scheduling of Operator Licensing Examinations  + (ML021570110)
• LIC-02-0068, Transmittal of Changes to Emergency Plan Implementing Procedures (EPIP) and Emergency Planning Forms (Epf)  + (ML021570115)
• L-02-058, Supplement to License Amendment Request Nos. 295 and 167 Re Creation of a Pressure and Temperature Limits Report for Each Unit, Per GL 96-03  + (ML021570119)
• ML021570119  + (ML021570119)
• 1CAN050202, Response to NRC Request to Modify ITS Bases 3.8.8 Re Shutdown and Correct Administrative Errors  + (ML021570121)
• DCL-02-063, Submittal of 60-day Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity  + (ML021570124)