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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
- ML19325E053 + (ML19325E053)
- ML19325E054 + (ML19325E054)
- IR 05000213/1989015 + (ML19325E056)
- ML19325E058 + (ML19325E058)
- ML19325E059 + (ML19325E059)
- JPN-89-068, Forwards Response to NRC 890518 Request for Addl Info Re Util 890117 Proposed Tech Specs Change Re Containment Isolation Valves.Proposed Tech Spec Page 186 Also Encl + (ML19325E061)
- ML19325E063 + (ML19325E063)
- ML19325E070 + (ML19325E070)
- ML19325E072 + (ML19325E072)
- ML19325E074 + (ML19325E074)
- ML19325E076 + (ML19325E076)
- ML19325E077 + (ML19325E077)
- ML19325E078 + (ML19325E078)
- IR 05000219/1989023 + (ML19325E080)
- IR 05000002/1989002 + (ML19325E081)
- NLS8900400, Responds to Generic Ltr 89-16 Re Installation of Hardened Wetwell Vent.Hardened Vent Will Be Installed at Facility. Installation of Vent Would Further Reduce Risk of Loss of DHR Sequence + (ML19325E082)
- ML19325E085 + (ML19325E085)
- ML19325E086 + (ML19325E086)
- B13357, Application for Amend to License NPF-49,changing Tech Specs Re Reactor Vessel Pressure/Temp Limits + (ML19325E087)
- ML19325E088 + (ML19325E088)
- ML19325E089 + (ML19325E089)
- ML19325E092 + (ML19325E092)
- ML19325E094 + (ML19325E094)
- ML19325E096 + (ML19325E096)
- ML19325E097 + (ML19325E097)
- BECO-89-153, Responds to NRC Re Violations Noted in Insp Rept 50-293/89-07.Corrective Actions:Terminal Block Replaced, post-work Functional Test of Ref Temp Switches Performed & Procedure Tp 88-78 Revised to Correct Relay Numbers + (ML19325E098)
- ML19325E099 + (ML19325E099)
- ML19325E101 + (ML19325E101)
- ML19325E102 + (ML19325E102)
- ML19325E105 + (ML19325E105)
- ML19325E106 + (ML19325E106)
- ML19325E107 + (ML19325E107)
- ML19325E108 + (ML19325E108)
- ML19325E110 + (ML19325E110)
- ML19325E111 + (ML19325E111)
- ML19325E112 + (ML19325E112)
- NUREG/CR-5404, Forwards Draft NUREG/CR-5404, Auxiliary Feedwater Sys Aging Study Vol 1:Operating Experience & Current Monitoring Practices & Final Shoreham Nuclear Power Station PRA-Based Sys Insp Plans. W/O Shoreham Nuclear Power Station.. + (ML19325E113)
- ML19325E114 + (ML19325E114)
- ST-HL-AE-3187, Responds to Generic Ltr 83-28,Action Item 2.2.1, Equipment Classification & Vendor Interface (Programs for All Safety-Related Components). Contractor Work Requests Used to Initiate Contractor Work + (ML19325E116)
- ML19325E117 + (ML19325E117)
- ML19325E118 + (ML19325E118)
- ML19325E119 + (ML19325E119)
- ST-HL-AE-3078, Proposed Tech Spec Table 4.3-1 Re Reactor Trip Sys Instrumentation Surveillance Requirements + (ML19325E120)
- ML19325E121 + (ML19325E121)
- ML19325E122 + (ML19325E122)
- ML19325E123 + (ML19325E123)
- ML19325E124 + (ML19325E124)
- ML19325E126 + (ML19325E126)
- ML19325E128 + (ML19325E128)
- ML19325E129 + (ML19325E129)
- ML19325E130 + (ML19325E130)