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

• ML17306B348  + (ML17306B348)
• ML17306B349  + (ML17306B349)
• ML17306B350  + (ML17306B350)
• ML17306B351  + (ML17306B351)
• ML17306B352  + (ML17306B352)
• ML17306B355  + (ML17306B355)
• ML17306B356  + (ML17306B356)
• ML17306B363  + (ML17306B363)
• ML17306B364  + (ML17306B364)
• ML17306B366  + (ML17306B366)
• ML17306B368  + (ML17306B368)
• ML17306B369  + (ML17306B369)
• ML17306B371  + (ML17306B371)
• ML17306B374  + (ML17306B374)
• ML17306B377  + (ML17306B377)
• ML17306B378  + (ML17306B378)
• ML17306B380  + (ML17306B380)
• ML17306B381  + (ML17306B381)
• ML17306B384  + (ML17306B384)
• ML17306B386  + (ML17306B386)
• ML17306B388  + (ML17306B388)
• 05000529/LER-1993-001-03, :on 930314,reactor Manually Tripped Following Steam Generator Tube Rupture.Investigation Team Formed & Investigation Initiated Per Incident Investigation Program. Results Will Be Provided in Supplemental LER  + (ML17306B389)
• ML17306B391  + (ML17306B391)
• ML17306B398  + (ML17306B398)
• ML17306B399  + (ML17306B399)

• ML17306B401  + (ML17306B401)

• ML17306B402  + (ML17306B402)
• ML17306B405  + (ML17306B405)
• ML17306B409  + (ML17306B409)
• ML17306B411  + (ML17306B411)
• ML17306B413  + (ML17306B413)
• ML17306B415  + (ML17306B415)
• IR 05000529/1993014  + (ML17306B417)
• ML17306B419  + (ML17306B419)
• ML17306B421  + (ML17306B421)
• ML17306B423  + (ML17306B423)
• ML17306B424  + (ML17306B424)
• 05000530/LER-1992-005-01, Forwards LER 92-005-01 Re Main Steam Safety Valve as-found Relief Settings Out of Tolerance Limits in TS 3.7.1.1.Suppl Updates Valve Testing Schedule in Section Iii.B & Provides Main Steam & Pressurizer Safety Valve Test Res  + (ML17306B425)
• ML17306B426  + (ML17306B426)
• 05000530/LER-1992-005-02, :on 921023,determined That 11 of 20 Main Steam Safety Valve as-found Relief Setpoints Out of TS 3.7.1.1 Tolerance from 921010-23.Possibly Caused by Setpoint Drift. Valves Will Be Removed & Shipped to Offsite Facility  + (ML17306B427)
• ML17306B432  + (ML17306B432)
• ML17307A010  + (ML17307A010)
• NMP2L2658, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water  + (ML17307A015)
• SBK-L-17164, Spent Fuel Pool Integrity Evaluation Summary Supplemental Report in Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the .  + (ML17307A016)
• NMP2L2660, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change  + (ML17307A019)
• SBK-L-17180, 8, Revised Alkali-Silica Reaction Aging Management Program  + (ML17307A027)
• ML17307A033  + (ML17307A033)
• ML17307A034  + (ML17307A034)
• ML17307A036  + (ML17307A036)
• ML17307A037  + (ML17307A037)
• ML17307A040  + (ML17307A040)