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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
- L-83-317, Confirms That GE AK-2 Scram Breakers Used at San Onofre Also in Use at Facility + (ML17213B391)
- L-83-309, Reschedules 830520 Meeting on Plant Recovery Program - Loose Parts Monitor & ex-core Detector,For 830603,w/followup Documentation to Be Provided by 830606 + (ML17213B392)
- L-83-315, Forwards Equipment Qualification Radiation Dose Map Development, in Response to 830406 Request.Rept Presents Assumptions & Methodology Used in Creating Dose Maps & Two Illustrative Dose Points + (ML17213B393)
- ML17213B394 + (ML17213B394)
- ML17213B395 + (ML17213B395)
- L-83-328, Forwards Summary of Calculations Performed to Determine Flood Level Inside Containment,In Response to NRC Request for Addl Info Re Util + (ML17213B396)
- L-83-324, Forwards Resolution of Item I.C Re Remote Shutdown Demonstration Prior to Initial Criticality,Per Region II Request.Item Closed.Requests Region II Be Notified of Concurrence Following Review + (ML17213B397)
- L-83-325, Forwards Addl Info Re Turbine Trip Circuitry at Facility. Turbine Manual Trip Initiated in Control Room by Depressing Pushbutton PB/170 Located on Rtg Board 201 + (ML17213B398)
- IR 05000259/2017502 + (ML17214A013)
- RA17-072, Post Accident Monitoring Report + (ML17214A018)
- IR 05000334/2017002 + (ML17214A025)
- ML17214A027 + (ML17214A027)
- ML17214A028 + (ML17214A028)
- ML17214A029 + (ML17214A029)
- ML17214A034 + (ML17214A034)
- ML17214A036 + (ML17214A036)
- ML17214A038 + (ML17214A038)
- ML17214A050 + (ML17214A050)
- ML17214A071 + (ML17214A071)
- ML17214A085 + (ML17214A085)
- ML17214A088 + (ML17214A088)
- ML17214A092 + (ML17214A092)
- ML17214A099 + (ML17214A099)
- ML17214A100 + (ML17214A100)
- ML17214A101 + (ML17214A101)
- ML17214A102 + (ML17214A102)
- ML17214A104 + (ML17214A104)
- ML17214A115 + (ML17214A115)
- 05000298/LER-1917-003, Re Mispositioned Control Room Emergency Filter System Supply Fan Damper Causes Loss of Safety Function + (ML17214A117)
- ML17214A118 + (ML17214A118)
- L-83-326, Forwards Responses to Addl Info Requested in 830421 Safety Evaluation on Environ Qualification of safety-related Electrical Equipment + (ML17214A138)
- L-83-323, Forwards St Lucie 1 & 2 & Turkey Point 3 & 4 Detailed Control Room Design Reviews Program Plan, Fulfilling 830415 Commitment Per NUREG-0737,Suppl 1 + (ML17214A139)
- L-83-321, Forwards Revised FSAR Table 7.3-9 Indicating Effects ESF Actuation Sys Devices Have on Plant Operation.Table Will Be Incorporated Into Amend 14 to FSAR Scheduled for 830808 + (ML17214A140)
- L-83-332, Forwards List of Resolved License Conditions for Initial criticality.Post-fuel Load Initial Test Program Initiated, Including Criticality & Low Power Testing Described in Chapter 14 to FSAR + (ML17214A141)
- ML17214A142 + (ML17214A142)
- ML17214A144 + (ML17214A144)
- ML17214A145 + (ML17214A145)
- L-83-333, Fulfills Commitment Made in Re Investigating Feasibility of Performing Demonstration Test for Loss of Ac Power.Util Developed Three Addl Preoperational Tests to Demonstrate Ability to cross-connect Diesel Generators + (ML17214A146)
- L-83-336, Forwards Justification for Interim Operation Re Qualification of Conax Assembly Used in Inadequate Core Cooling Instrumentation.Test Exposure to Dbe/Loca Conditions Successfully Completed + (ML17214A151)
- ML17214A153 + (ML17214A153)
- ML17214A155 + (ML17214A155)
- ML17214A158 + (ML17214A158)
- L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting + (ML17214A160)
- L-83-346, Application to Amend License DPR-67,revising Tech Specs to Extend Testing Cycle of Valves Utilized as Part of Turbine Overspeed Protection Sys.Change Based on Vendor Recommendation + (ML17214A161)
- ML17214A162 + (ML17214A162)
- ML17214A163 + (ML17214A163)
- L-83-351, Advises That Sentence in Util 810914 Response to Human Engineering Discrepancy A.I.3 Re Key Storage Stating, Remote Shutdown Panel SIS Block Keys Will Be Maintained at RAB Control Access Point, Should Be Deleted + (ML17214A164)
- L-83-354, Application for Mod to License Condition 2.C.7 for License NPF-16,changing Requirement from Prior to Exceeding 50% of Rated Thermal Power to Prior to Completion of Startup Testing. Mod Requested Due to Testing Delays at San Onofre + (ML17214A165)
- L-83-355, Advises That post-reactor Trip Procedures Will Be Modified to Include Addl Criteria for post-reactor Trip Review. Procedures Will Be Available Onsite for NRC Concurrence within 60 Days Following Approval of Full Power OL + (ML17214A167)
- ML17214A168 + (ML17214A168)
- ML17214A170 + (ML17214A170)