BSEP-97-0526, Notification That Individual Holding License SOP-20430-2, Has Experienced Change in Medical Status.Copy of Proprietary Revised NRC Form 396 Is Attached.Encl Withheld
05000316/LER-2077-001, Letter Reporting of Unplanned Release of Low Level Radioactive Gas
L-77-231, Response to Request for Additional Information Re Large Scale Topographical Map in Compliance with Appendix I to 10 CFR 50
L-76-001, Letter Responding to IE Bulletin 76-01 Concerning Integrity of Isolation Condensers Tubes
L-76-428, Provide Model Tech Spec Re Steam Generator Tube Surveillance Requirements
L-26-161, Advising Inspection on Safety Related Hydraulic Pipe Restraints Located Outside of Containment on 3/20/1976 Was in Satisfactory Condition
L-76-233, Letter Regarding Condition of License E.2 Supplemental Information
L-76-106, Letter Enclosing a Construction Incident Report Relating to Low Fluid Levels in Six Hydraulic Seismic Snubbers
L-77-187, 9/23/1977 Letter Endorsement Nos. 15 and 16 to Maelu Policy MS-59, Representing Nuclear Energy Liability (Suppliers and Transporters Form) Coverage at Turkey Point and St. Lucie Plants
L-76-418, Transmittal of Request to Amend Appendix a of Facility Operating License
L-76-429, Letter Transmitting Proposed Amendment to Facility Operating Licenses, Based on Result of re-evaluation of ECCS Cooling Performance Calculated in Accordance with an Approved Westinghouse Evaluation Model
05000259/LER-2077-001, Relief Valve on Pump Discharge Opened at Lower than Set Pressure During Performance of Surveillance Instruction 4.4.A.1 on Standby Liquid Control Pump 3A
05000260/LER-2077-008, For Browns Ferry Nuclear Plant, Unit 2, Random Failure of Two Isolation Valves in One Traversing Incore Probe (Txp) Tube Could Not Have Been Closed If Required Between 2045 Hours on 3/16/1977, & 0100 Hours on 3/17/1977
05000259/LER-2077-005, A & B RPS MG Sets Failed to Trip During Startup Test, ST1 31, Loss of T-G, and Off Site Power Test
05000259/LER-2076-017, HPCI Turbine Steam Supply Valve 2-FCV-73-16 Failed to Open During Performance of an Operability Surveillance Instruction
05000250/LER-2077-005, Letter Request to Amend Appendix a of Facility Operating Licenses. Proposal Submitted to Satisfy Commitment Made in Reportable Occurrence Report 250-77-5 of 05/02/1977
L-76-169, Letter Submitting Additional Reload Information Concerning Florida Power and Light Companys Reload Submittal for Core Cycle 3 of Unit 4
05000316/LER-2076-009, Re Failure of Wind Speed & Direction Indication & LER 1976-009-00 Re Failure of Wind Direction System at Microwave Tower
05000316/LER-2077-002, Letter Abnormal Environmental Occurrence of Total Residual Chlorine at the Condensate Outlet Exceeding the 0.10 Ppm Limit in Violation of Appendix B Technical Specifications Section 2.2.1.2
05000316/LER-2077-015, And LER-1977-015-00 for Donald C. Cook, Unit 1 - Water Hammer Resulting in Failure of Two Seismic Snubbers, and Causing a Crack in Weld Between Auxiliary Feedwater Pipe to Second Steam Generator and a Pipe Support
05000316/LER-2077-006, Concerning Hydraulic Shock & Sway Suppressor (Serial 11928) Attached to Wrong Pipe
05000316/LER-2077-038, Re Closure of W. CTS Heat Exchanger Inlet Valve During Routine Surveillance Test
05000316/LER-2077-021, Isolation Time Not Verified Following Maintenance on Third Steam Generator Sample Isolation Valve, DCR-303
05000316/LER-2076-059, Iodine Spike Following Power Transient, Violation of Limit Specified in Technical Specification 3.4.8
05000316/LER-2077-004, Re Failure of Cooling Coil on CPN-4
05000316/LER-2077-023, Two Instances of Failure to Have Temporary Changes Reviewed by the Pnsrc and Approved by the Plant Manager in Violation of Appendix a Technical Specification 6.8.3.c
05000244/LER-2077-008, B Steam Generator Tube Leak
05000244/LER-2077-003, Abnormal Degradation of Steam Generator Tubes
05000244/LER-2078-009, For R. E. Ginna, Bus 18 Breaker from a Emergency Generator Overcurrent Relay
L-77-111, Response to Request for Additional Information Steam Generator Operating History
L-76-437, Florida Power & Light Co.S Response to NRCs Letter of 8/1/1976 Concerning Anticipated Transients Without Scram
05000335/LER-2076-030, During Plant Startup/Heatup from Cold Iron Shutdown Conditions, Plant Experienced Over-Pressure Transient When First RCP Was Started
05000335/LER-2077-007, During Routine Surveillance, CEA 7 Was Found to Be Inoperable. CEA 7 Is a Shutdown CEA
05000335/LER-2077-016, For St. Lucie Unit 1, Low Steam Generator Pressure Trips Received on Channel a RPS and Channel a MSIS
05000237/LER-1977-023, For Dresden Unit 2 Regarding Discovery of the 12% APRM Upscale Rod Block Trip Setting to Be at 12.5% for APRM Channel One Due to Setpoint Drift