Search by property

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

• NRC 2002-0030, License Amendment Request 226, Measurement Uncertainty Recapture Power Uprate  + (ML021700339)
• ML021700477  + (ML021700477)
• ML021700508  + (ML021700508)
• ML021700611  + (ML021700611)
• ML021700619  + (ML021700619)
• ML021700624  + (ML021700624)
• ML021700642  + (ML021700642)
• ML021700671  + (ML021700671)
• ML021700688  + (ML021700688)
• ML021700693  + (ML021700693)
• CNRO-2002-00024, Entergy Nuclear, Inc., Early Site Permit Application  + (ML021710017)
• ML021710018  + (ML021710018)
• ML021710019  + (ML021710019)
• LIC-02-0073, Closure of NRC TAC Issues for Fort Calhoun Station  + (ML021710030)
• LIC-02-0075, Announcement of New Licensing Manager  + (ML021710032)
• BSEP 02-0112, May 2002 Monthly Operating Report for Brunswick Steam Electric Plant, Units 1 & 2  + (ML021710040)
• ML021710045  + (ML021710045)
• L-02-071, May 2002 Monthly Operating Report for Beaver Valley Units 1 & 2  + (ML021710046)
• ML021710053  + (ML021710053)
• ML021710054  + (ML021710054)
• ML021710059  + (ML021710059)
• L-2002-105, Emergency Plan Implementing Procedure Changes  + (ML021710063)
• ML021710064  + (ML021710064)
• ML021710066  + (ML021710066)
• 05000456/LER-2002-001, Set Point Drift Causes Two of Three Pressurizer Safety Valve Lift Tests to Exceed Technical Specification Tolerance on April 8, 2002  + (ML021710070)

• ML021710074  + (ML021710074)

• 05000456/LER-2001-001-01, Three Main Steam Safety Valves Exceeded the Technical Specification Limit by Greater than 3% on September 19 and 20, 2001  + (ML021710077)
• ML021710080  + (ML021710080)
• ML021710092  + (ML021710092)
• ML021710096  + (ML021710096)
• ML021710108  + (ML021710108)
• 05000483/LER-2002-009, Flooding of Security Facilities on 05/12/2002  + (ML021710109)
• 05000237/LER-2002-002, Smoke Purge Mode Operation Prevents Safety Function of the Control Room Emergency Ventilation System on April 10, 2002  + (ML021710113)
• CPSES-200202322, Comanche Peak'S 30 Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity  + (ML021710118)
• ML021710118  + (ML021710118)
• RS-02-104, Registration of Use of Cask to Store Spent Fuel  + (ML021710119)
• ML021710130  + (ML021710130)
• ML021710133  + (ML021710133)
• ML021710134  + (ML021710134)
• ML021710138  + (ML021710138)
• ML021710144  + (ML021710144)
• ML021710146  + (ML021710146)
• ML021710150  + (ML021710150)
• L-2002-087, ASME Section XI Relief Request Nos. 30 & 31, Associated with Reactor Vessel Closure Head Repair, Additional Information  + (ML021710153)
• ML021710157  + (ML021710157)
• U-603558, Core Shroud Inspection Results  + (ML021710158)
• ML021710158  + (ML021710158)
• JPN-02-019, & James A. FitzPatrick Nuclear Power Plant Entergy Quality Assurance Program Manual  + (ML021710160)
• CNRO-2002-00037, Entergy Nuclear Northeast, Response to NRC Request for Additional Information on Application for Exemption from Definition of Total Effective Dose Equivalent  + (ML021710162)
• ML021710168  + (ML021710168)
• RS-02-111, Registration of Use of Cask to Store Spent Fuel  + (ML021710170)