BSEP 17-0019, Enclosure 2 - Response to Request for Additional Information Regarding License Amendment Request for Reactor Protection System (RPS) Electrical Protection Assembly (EPA) Electric Power Monitoring Surveillance Requirements (Srs) 3.3.8.2.
HBL-13-011, . License Termination Plan Technical Basis Document
3F1111-01, Document P23-1651-001, Rev. 0, Preliminary Decommissioning Cost Estimate for the Crystal River, Unit 3 Nuclear Generating Plant
DCL-09-021, Submittal of Decommissioning Funding Report
L-2018-193, Set 6 Responses to Request for Additional Information (RAI) on Subsequent License Renewal Application Safety Review
L-PI-05-073, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
L-03-092, National Pollutants Discharge Elimination System (NPDES) Monthly Report for April 2003
L-88-287, Forwards Summary of mgt-on-shift & Plant supervisor-nuclear Shift Repts for Wk Starting 880625,per NRC 871019 Order
BECO-88-031, Radioactive Effluent & Waste Disposal Rept,Including Radiological Impact on Humans,Jul-Dec 1987
RBG-20-430, Forwards Revs to Fsar.Revs Reflect Change in Calculations for UHS Max Temp Due to Revs in Plant Equipment Operation
BECO-91-045, Annual Dose Assessment to General Public from Radioactive Effluents,1990
BECO-LTR-92-036, Annual Dose Assessment to General Public from Radioactive Effluents,1991
1CAN069803, Forwards Relief Requests 1-98-001 & 1-98-002 Re Insps Performed During Second ten-yr ISI Interval at ANO-1,which Ending 970601
BECO-89-097, Forwards Response to Generic Ltr 89-06, Task Action Plan Item I.D.2,SPDS 10CFR50.54(F). Training of Plant Operators Expected to Begin in Sept.Sys Scheduled to Be Fully Operational by 891231,per Requirements of NUREG-0737
05000328/LER-1989-003-04, :on 890401,containment Ventilation Isolation Actuation & Momentary Loss of RHR Occurred.Caused by Removal of Power from Vital Instrument Power Board.Vital Inverters Verfied to Synchronize W/Instrument Board
05000285/LER-1988-021, :on 880902,determined That Control Room Panels W/O Smoke Detectors.Maint Order 88393 Issued to Install Smoke Detectors in Panels
B12635, Forwards Updated List of plant-specific Safety Issue Info Requested in NRC .Info Will Be Incorporated Into NRC Safety Issue Mgt Sys
B17038, Forwards Annual Rept That Identifies Changes Made to Regulatory Commitments for Period 970101-1231. Revised Regulatory Commitments,W/Cross Reference to Source Documentation,Encl
05000298/LER-1986-015, :on 860812,ESF Emergency Diesel Generator Start Challenged Due to 69 Kv Power Supply Substation Breaker Cycling.Caused by Fault Signal Due to Lightning.Generators Secured
05000374/LER-1986-009-05, :on 860511,w/synchronization to Grid at 15% Power,Primary Containment Isolation Sys Group I Isolation Occurred.Caused by Main Steam Line High Flow Signal.Main Steam Line Piping Walked Down.No Leaks Found
05000301/LER-1985-002-02, :on 851017,during Eleventh Refueling Outage, Total as-found Leakage Exceeded Tech Spec Limit of 0.06 La. Caused by Failure of Containment Isolation Valve 2-755A. Valve Inspected & Parts Repaired
05000237/LER-1986-012-05, :on 860521,full Scram Instead of Half Scram Occurred During Installation of Jumper Around Electrical Contact.Caused by Failure to Maintain Circuit Continuity. Vacuum & Scram Circuitry Reviewed
B17245, Updates NRC on Final Status of Compliance to RG 1.97,rev 2. No Action by NRC Requested.Verification of Instrumentation Installations Discrepancies Corrected,In Response to Notice of Deviation
05000344/LER-1988-028, :on 880916,while Establishing Conditions Necessary for Replacement of Transmitter PT-458,technician Erroneously Tripped Input Bistable from Another Transmitter. Caused by Deficiencies in Work Instructions
05000278/LER-1986-003, :on 860219,partial Containment Isolation Occurred When Plant Operator Removed Wrong Fuse While Applying Blocking Permit.Caused by Loose Fuse Label Strip. Label Secured W/Adhesive
05000409/LER-1986-005, :on 860124,high Pressure Svc Water/Alternate Core Spray Diesel 1A Removed from Svc to Replace Weeping Cooling Water Pump Discharge Hose.Surveillance Test Conducted Following Hose Replacement
05000267/LER-1986-006, :on 860117,reactor Scram Actuation Occurred During Test T-306.Caused by Personnel Error.Personnel Cautioned & Training on Performing Detailed Sys Reviews Will Be Conducted
05000336/LER-1988-009-01, :on 880607,CEA Dropped Into Core.Caused by Upper Gripper Coil Failure from Overheating Condition Resulting in Degraded Coil Insulation.Total of 60 Coils Either Replaced or New Coil Stack Installed
05000220/LER-1986-001, :on 860118,original Calculations for Jet Impingement Loading on ECCS Isolation Valves Found in Noncompliance W/Fsar.Caused by Break Inside Guard Pipe. Isolation Valves Will Be Replaced
05000220/LER-1985-010, :on 850815,accidental Initiation of Reactor Bldg Emergency Ventilation Sys Occurred.Caused by Electrical Spike Experienced by Channel 12 Reactor Bldg Ventilation Duct Monitor.Ventilation Sys Reset
05000301/LER-1985-003-01, :on 851022,exam of Steam Generator Tubes Revealed 53 Tubes Degraded Equal to or Greater than 40% & One Tube W/Undefined Signal.Cause Unstated.Tubes Plugged
05000341/LER-1985-047, :on 850729,valves Closed Causing Div I ECCS & Emergency Diesel Generators to Become Inoperable.Caused by Operator Error.No Corrective Action Required
05000364/LER-1985-005, :on 850127,prior to Integrated Leak Rate Testing of Containment,Grease Cover for Shop End of Containment Vertical Tendon V17 Found Deformed.Caused by Broken Field Anchor.Insp Program Initiated
LD-92-123, Forwards Section 17.3, Design Reliability Assurance Program Plan for Sys 80+ Standard Design, Rev 1 & Responses to 79 Issues Identified in Dser for Sys 80+
05000397/LER-1984-127, :on 841218,during Wiring Changes to Auxiliary Steam Sys,Automatic Isolation of Reactor Water Cleanup (RWCU) Sys Occurred.Logic Signal Reset & RWCU Sys Returned to Svc
05000397/LER-1984-130, :on 841220,during Review of Procedure to Verify Containment Integrity,Several Primary Containment Isolation Valves Not Verified in Accordance W/Tech Specs.Verification Procedure Revised
05000353/LER-1990-016-01, :on 900811,Tech Spec 3.7.6.4 Not Met Since Halon Sys Inoperable
05000416/LER-1983-027-99, /99X-0:on 830128,fire Door 1A215 Alarmed on Supervision Sys & Would Not Reset,Yet Verified Closed.Caused by Door Position Switch Out of Adjustment.Fire Watch Established.Switch Adjusted.Door Returned to Svc on 830201
B14462, Proposed Tech Specs 3.4.4 & 3.4.9.3 Addressing Issues in GL-90-06
PY-CEI-NRR-0329, Forwards Response to 850808 & 14 Ltrs Re Radwaste Solidification Sys.Responses Incorporated Into Rev 3 of Process Control Program.Proprietary NUS Process Svcs Repts FO-013 & SS-001 Withheld (Ref 10CFR2.790(b)(1))
05000334/LER-1981-064-03, /03L-0:on 810625,air Lock Outer Door Locking Ring Partially Rotated & Jammed in Place.Caused by Air Pressure on Seals Due to Open Leak Rate Test Panel Valve.Air Pressure Relieved & Leak Rate Test Successfully Performed
RBG-23671, Special Rept:On 860301,actuation of Div III ECCS Occurred Following Unit Scram.Caused by Feedwater Pump Trip Due to Voltage Transient in Associated 13.8-kV Switchgear. Evaluation Continuing
NUREG-0324, Forwards Crac Code Input for 790328-0402 at Site.Wind Speeds Corrected to 10 Meter Level Using Procedures Outlined in NUREG-0324
05000338/LER-1980-038-03, /03L-0:on 800409,during Power Escalation,Axial Flux Difference Deviated Greater than Limit for three-minute Duration.Caused by Overinsertion of Control Rods Resulting from Continued Dilution During Hold in Power Escalation
05000237/LER-1979-004-03, /03L-0 on 790111:LPCI Sys Full Flow Test Valve MO-2-1501-38B Failed While Securing D LPCI Pump.Caused by Broken Pinion Gear on Valve Operator Motor Shaft
BW060049, Radioactive Effluent Release Report
RNP-RA/17-0065, Refueling Outage 30 Steam Generator Tube Inspection Report
Information Notice 1994-42, Cracking in the Lower Region of the Core Shroud in Boiling-Water Reactors
05000397/LER-1984-123, :on 841202,normal Div I Critical Switchgear Room Cooling Lost Due to Manual Shutdown Caused by Vibration of Fan Unit.All Div I Equipment Declared Inoperable.Fan Shaft Replaced & Bearings Installed