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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
- ML20117N027 + (ML20117N027)
- ML20117N028 + (ML20117N028)
- HL-5237, Monthly Operating Repts for Aug 1996 for Ei Hatch Nuclear Plant Units 1 & 2 + (ML20117N033)
- 05000315/LER-1985-011, :on 850407,containment Purge Begun Per Approved Procedure Which Established More than on Purge Supply & Exhaust Path.Procedure Not Allowed Per Tech Spec 3.6.1.7. Procedures Changed + (ML20117N036)
- ML20117N038 + (ML20117N038)
- ML20117N039 + (ML20117N039)
- 05000414/LER-1996-003, Informs That Cover Sheet to LER 96-003,inadvertently Denoted Incorrectly Docket Number.Nrc Rept Forms 366 & 366A Correctly Identified Correct Docket Number + (ML20117N041)
- ML20117N048 + (ML20117N048)
- ML20117N051 + (ML20117N051)
- ML20117N058 + (ML20117N058)
- ML20117N065 + (ML20117N065)
- ML20117N066 + (ML20117N066)
- ML20117N069 + (ML20117N069)
- ML20117N071 + (ML20117N071)
- ML20117N086 + (ML20117N086)
- ML20117N092 + (ML20117N092)
- ML20117N095 + (ML20117N095)
- RBG-20790, Forwards Addl Info Requested in Response to Item 8 Re Tdi Diesel Generators at Facility.Info Revises 850411 Response & Completely Addresses All Items in Request + (ML20117N099)
- 3F0585-09, Forwards Relief Request 140,revised to Incorporate Alternate Exam for Reactor Vessel Support Skirt Weld.Request Applies to Requirements of ASME Boiler & Pressure Vessel Code,Section XI + (ML20117N107)
- ML20117N114 + (ML20117N114)
- ML20117N117 + (ML20117N117)
- W3P85-1289, Application for Amend to License NPF-38,providing Addl Method for Secondary Chemistry Control.Changes Should Be Granted on Emergency Basis.Fee Paid + (ML20117N135)
- ML20117N138 + (ML20117N138)
- ML20117N147 + (ML20117N147)
- 05000334/LER-1996-010, :on 960814,discovered Containment Piping Supports Out of Design Basis.Caused by Failure to Adhere to Design Engineering Piping Support Installation Guidelines. Installed & Modified Supports to Piping + (ML20117N150)
- ML20117N152 + (ML20117N152)
- ML20117N154 + (ML20117N154)
- ML20117N155 + (ML20117N155)
- ML20117N160 + (ML20117N160)
- ML20117N161 + (ML20117N161)
- ML20117N173 + (ML20117N173)
- RC-96-0231, Monthly Operating Rept for Aug 1996 for VC Summer Nuclear Station Unit 1 + (ML20117N174)
- 05000254/LER-1996-013, Forwards LER 96-013,Rev 0 IAW Requirements of 10CFR50.73(a)(2)(i)(B).Commitments Made by Ltr,Listed + (ML20117N194)
- 05000254/LER-1996-013-01, :on 960808,zebra Mussels Were Discovered on Fire Pump Suction Strainers.Caused by Inadequate Insp Frequency of Fire Pump Suction Strainers.Divers Removed & Cleaned Zebra Mussels from Fire Pump Suction Strainers + (ML20117N201)
- ML20117N208 + (ML20117N208)
- 05000443/LER-1996-003, :on 960521,Emergency Feedwater Pump Mechanical Seal Failure Occurred.Caused by Inadequate Predictive Maintenance Techniques.Seal Replaced,Inspected & Adjusted + (ML20117N212)
- ML20117N217 + (ML20117N217)
- 05000271/LER-1996-010, :on 960411,inadequate Design/Single Failure Evaluation During Design Change Identified Potential Loss of RHR Pump Min Flow Protection.Evaluation Performed.No Significant Safety Concerns Existed + (ML20117N228)
- ML20117N274 + (ML20117N274)
- ML20117N276 + (ML20117N276)
- ML20117N289 + (ML20117N289)
- ML20117N295 + (ML20117N295)
- ML20117N297 + (ML20117N297)
- ML20117N311 + (ML20117N311)
- ML20117N314 + (ML20117N314)
- 05000483/LER-1985-021, :on 850404,spacing Between Batteries End Cells & Stringers Did Not Meet Specified Criteria.Caused by Deficient Drawings.Fire Retardant Plywood Spacers Installed Between Battery End Cells & Stringers + (ML20117N317)
- 05000322/LER-1985-014, :on 850408,hourly Firewatch Patrol,Required by Tech Specs,Late by 10 Minutes for Emergency Diesel Generator Rooms.Caused by Computer Malfunction Which Denied Access to Rooms.Security Summoned to Permit Access + (ML20117N320)
- ML20117N323 + (ML20117N323)
- LIC-96-0126, Responds to NRC Re Violations Noted in Insp Rept 50-285/96-04 on 960602-0713.Corrective Actions:Three Operators Involved in Incident Have Been Counseled on SO-G-52 Working Hour Limitations,Completed in July 1996 + (ML20117N332)
- 05000366/LER-1985-012-01, :on 850409,unplanned Actuation of Reactor Protection Sys Occurred.Caused by Failure of Main Steam Line Radiation Detectors Due to Loose & Saturated Power Cables. Cables Replaced + (ML20117N336)
- JAFP-85-0414, Monthly Operating Rept for Apr 1985 + (ML20117N338)