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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-87-399, Advises That Util Will Need Addl Time to Respond to NRC Requesting Status of Completion/Implementation Dates of Approved Regulatory Initiatives.Response in Form of Marked Up Listing Will Be Provided by 871007 + (16:58:15, 7 January 2025)
- L-87-401, Provides Update to 870515 Response to Generic Ltr 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors + (16:58:17, 7 January 2025)
- IR 05000250/1987036 + (16:58:28, 7 January 2025)
- ML17342A939 + (16:58:30, 7 January 2025)
- ML17342A937 + (16:58:32, 7 January 2025)
- 05000251/LER-1987-018, :on 870711,operation in Excess of 24 H W/ Greater than 2% Calculated Quadrant Power Tilt Ratio W/O Running Flux Map or Reducing Overpressure,Overtemp Occurred. Caused by Personnel Error.Procedure Updated + (16:58:34, 7 January 2025)
- L-87-391, Provides Info as Performance Enhancement Program Quarterly Update,Per NRC 860812 Order.Details of Info Provided at 870730 Meeting.Major Topics Discussed at Meeting Listed + (16:58:35, 7 January 2025)
- ML17342A932 + (16:58:38, 7 January 2025)
- IR 05000250/1987040 + (16:58:40, 7 January 2025)
- ML17342A929 + (16:58:42, 7 January 2025)
- ML17342A927 + (16:58:44, 7 January 2025)
- ML17342A924 + (16:58:45, 7 January 2025)
- L-87-392, Forwards Comments on NRC Salp.Plant Operations,Radiological Controls,Maint,Security & Safeguards,Outages,Training & Qualification Effectiveness & Engineering Support Addressed + (16:58:46, 7 January 2025)
- ML17342A922 + (16:58:48, 7 January 2025)
- ML17342A921 + (16:58:50, 7 January 2025)
- ML17342A920 + (16:58:51, 7 January 2025)
- ML17342A918 + (16:58:52, 7 January 2025)
- ML17342A917 + (16:58:53, 7 January 2025)
- ML17342A916 + (16:58:54, 7 January 2025)
- L-87-387, Forwards Select Sys Assessment Progress Summary for Aug 1987 + (16:59:01, 7 January 2025)
- L-87-386, Forwards Response to NRC 870818 Request for Addl Info Re Util Response to IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings + (16:59:06, 7 January 2025)
- ML17342A911 + (16:59:11, 7 January 2025)
- L-87-380, Forwards Response to Generic Ltr 87-12.Util Requested Westinghouse Owners Group to Evaluate Time Response for Loss of RHR W/Estimates of Potential Core Damage & Radioactive Releases.Info Will Be Provided When Available + (16:59:12, 7 January 2025)
- ML17342A907 + (16:59:18, 7 January 2025)
- ML17342A906 + (16:59:20, 7 January 2025)
- ML17342A904 + (16:59:22, 7 January 2025)
- IR 05000250/1987032 + (16:59:24, 7 January 2025)
- L-87-373, Forwards Response to NRC Bulletin 87-001, Thinning of Pipe Walls in Nuclear Power Plants. All Piping Inspected for Wall Thinning Designed & Fabricated in Accordance W/Ansi B31.1 + (16:59:25, 7 January 2025)
- ML17342A897 + (16:59:30, 7 January 2025)
- ML17342A895 + (16:59:32, 7 January 2025)
- ML17342A894 + (16:59:33, 7 January 2025)
- L-87-372, Special Rept:On 860930 & 1001,schedular Exemptions for Safe Shutdown Mods Expired Due to Large Number of Mods Being Performed.Plant Continues to Implement Compensatory Measures as Applicable.Rept Will Be Updated on 30-day Basis + (16:59:34, 7 January 2025)
- L-87-371, Responds to Violations Noted in Insp Repts 50-250/87-33 & 50-251/87-33.Corrective Actions:Reducer & Branch Line to Isolation Valves & Steam Trap Socolet Replaced & Procedure ONOP-12308.2 Re Power Range Nuclear Instrumentation Updated + (16:59:37, 7 January 2025)
- ML17342A891 + (16:59:42, 7 January 2025)
- 05000250/LER-1987-022, :on 870731,operator Demonstrated Known Spurious & Spiking Problem in Nuclear Instrumentation Sys Intermediate Range Channels,By Opening Drawer for Sys. Caused by Faulty Locking mechanism.W/870831 1tr + (16:59:46, 7 January 2025)
- L-87-361, Semiannual Radioactive Effluent Release Rept Jan-June 1987 + (16:59:48, 7 January 2025)
- 05000251/LER-1987-021-01, :on 870729,process Radiation Monitor Spiked High Actuating Containment Vent & Control Room Ventilation Isolation Logic.Caused by Work Being Performed on Condenser Air Ejector Radiation Monitor.Drawer Reset + (16:59:52, 7 January 2025)
- ML17342A886 + (16:59:54, 7 January 2025)
- L-87-363, Advises That at Time of Next Blackness Testing & Surveillance of Boraflex Max Fuel Enrichment Will Be Less than 4.1%.Util Will Not Store Fuel W/Enrichment Greater than 4.1% Prior to Surveillance + (16:59:55, 7 January 2025)
- ML17342A884 + (16:59:55, 7 January 2025)
- L-87-355, Responds to NRC 870609 Request for Addl Info Re Use of Boraflex in Spent Fuel Storage Racks.Results of Blackness Testing of Boraflex Panels Did Not Indicate Existence of Gaps,Voids or Other Spatial Distribution Anomalies + (16:59:58, 7 January 2025)
- 05000251/LER-1987-020-01, :on 870728,discovered That Steam Generator 4A Feedwater Flow Control Valve Actuator Stem Not Properly Engaged W/Control Valve Stem.Caused by Improperly Matched Coupler Halves.Set Screw Inserted Into Block + (17:00:02, 7 January 2025)
- L-87-357, Responds to Violations Noted in Insp Repts 50-250/87-32 & 50-251/87-32.Corrective Actions:Steps Taken to Assure That Operators in Compliance Prior to Assuming Shift Duties & Operators Will Be Scheduled to Rept to Training Bldg + (17:00:04, 7 January 2025)
- NUREG/CR-4982, Board Notification 87-013:forwards Final NUREG/CR-4982, Severe Accidents in Spent Fuel Pools in Support of Generic Issue 82, Per Commitment of 870327 Board Notification 87-005.W/o Encl + (17:00:07, 7 January 2025)
- 05000251/LER-1987-014, :on 870711,water Dripping from Auxiliary Feedwater(Afw) Steam Line Discovered & on 870717,AFW Train 1 Declared Inoperable.Cause of Leak Unknown.Affected Piping & Fitting Replaced + (17:00:13, 7 January 2025)
- L-87-346, Forwards Jul 1987 Summary Progress Rept of Select Sys Assessment + (17:00:15, 7 January 2025)
- ML17342A874 + (17:00:18, 7 January 2025)
- ML17342A873 + (17:00:20, 7 January 2025)
- ML17342A872 + (17:00:21, 7 January 2025)
- L-87-350, Responds to NRC Re Violations Noted in Insp Repts 50-250/87-14 & 50-251/87-16.Corrective Actions:Containment Leaks Will Be Inspected & Documented for Evaluation & Safety Review Enhancements Performed.Civil Penalty Payment Encl + (17:00:22, 7 January 2025)
- L-87-336, Advises That Westinghouse Has Informed Util of Input Error Where Three high-head Safety Injection Pumps Assumed in Large Break LOCA Analysis.Licensee Evaluating Design Changes to Mitigate Increases in Peak Clad Temps + (17:00:24, 7 January 2025)