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

• ML12237A303  + (ML12237A303)
• ML12237A304  + (ML12237A304)
• ML12237A305  + (ML12237A305)
• ML12237A306  + (ML12237A306)
• ML12237A307  + (ML12237A307)
• ML12237A308  + (ML12237A308)
• ML12237A309  + (ML12237A309)
• ML12237A310  + (ML12237A310)
• ML12237A311  + (ML12237A311)
• ML12237A320  + (ML12237A320)
• L-MT-12-055, License Amendment Request: Revise Renewed Facility Operating License & Technical Specifications to Clarify Fuel Storage Capacity, Remove Obsolete Information and Make Minor Corrections and Miscellaneous Editorial Changes  + (ML12237A321)
• ML12237A332  + (ML12237A332)
• ML12237B197  + (ML12237B197)
• 3F0812-02, Response to Second Request for Additional Information to Support NRC Electrical Engineering Branch (Eeeb) Technical Review of the CR-3 Extended Power Uprate LAR  + (ML12240A009)
• 3F0812-03, Response to Request for Additional Information to Support NRC Safety Issues Resolution Branch (Ssib) Technical Review of the CR-3 Extended Power Uprate LAR  + (ML12240A010)
• 3F0812-05, Interim Report of the Evaluation of a Deviation Pursuant to 10 CFR 21.21(a)(2)  + (ML12240A011)
• 05000278/LER-2012-002, Regarding Failure of Primary Containment Isolation Valve Due to Foreign Material Results in Condition Prohibited by TS  + (ML12240A012)
• ML12240A015  + (ML12240A015)
• ML12240A023  + (ML12240A023)
• ML12240A024  + (ML12240A024)
• 05000341/LER-2012-003, Regarding Reactor Scram Due to Degrading Condenser Vacuum  + (ML12240A026)
• SVPLTR 12-0043, Review of Analytical Evaluation of Reactor Pressure Vessel Closure Flange Weld Indication  + (ML12240A044)
• ML12240A045  + (ML12240A045)
• ML12240A046  + (ML12240A046)
• ML12240A047  + (ML12240A047)

• ML12240A048  + (ML12240A048)

• ML12240A049  + (ML12240A049)
• 05000445/LER-2012-002, For Comanche Peak, Regarding Failure of Safety Related Breaker Control Devices Due to a Common Cause  + (ML12240A050)
• CP-201200881, Relief Request No. E-1 for Containment Electrical Penetrations (Second IWE Interval End Date: September 9, 2011)  + (ML12240A051)
• TXX-1211, Relief Request No. P-1 for Unit 1 and Unit 2 Inservice Testing Plan for Pumps and Valves (ASME OM Code 2004 Edition, Through 2006 Addenda Third Interval Start Date: August 3, 2013)  + (ML12240A052)
• ML12240A053  + (ML12240A053)
• ML12240A056  + (ML12240A056)
• ML12240A068  + (ML12240A068)
• ML12240A075  + (ML12240A075)
• ML12240A077  + (ML12240A077)
• NRC-2012-0265, G20110221/EDATS:OEDO-2011-0226/2.206 - Director' Decision to Entergy Nuclear Operations, Inc., Fire Safety Regulations at Indian Point, Units 1, 2 and 3  + (ML12240A077)
• ML12240A080  + (ML12240A080)
• ML12240A088  + (ML12240A088)
• ML12240A099  + (ML12240A099)
• ML12240A105  + (ML12240A105)
• ML12240A106  + (ML12240A106)
• ML12240A107  + (ML12240A107)
• OI 3-2011-007, Ltr. 7/19/12, Zionsolutions, LLC, Re NRC Office of Investigations Report No. 3-2011-007  + (ML12240A116)
• ML12240A119  + (ML12240A119)
• ML12240A123  + (ML12240A123)
• IR 05000315/2011010  + (ML12240A132)
• ML12240A139  + (ML12240A139)
• LIC-12-0120, Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition, at Fort Calhoun Station  + (ML12240A151)
• ML12240A174  + (ML12240A174)
• ML12240A177  + (ML12240A177)
• ML12240A180  + (ML12240A180)