L-14-124, Submittal of Discharge Monitoring Report for February 2014, Permit No. PA0025615
L-14-036, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
BVY-97-111, Monthly Operating Rept for Aug 1997 for Vermont Yankee Nuclear Power Station
3F1187-01, Forwards Crystal River Unit 3 Pra. Util Intends to Use PRA Model as Tool to Evaluate Proposed & Actual Plant Mods as Well as Other Applications for Risk Impact to Operation of Facility
B11502, Radiological Environ Monitoring Program,Annual Environ Operating Rept for 1984
B11501, Point Site,Radiological Environ Monitoring Program Annual Environ Operating Rept,Part B,1984
BVY-98-081, Monthly Operating Rept for May 1998 for Vermont Yankee Nuclear Power Station
BVY-98-068, Monthly Operating Rept for Apr 1998 for Vermont Yankee Nuclear Power Station
BVY-98-122, Monthly Operating Rept for July 1998 for Vermont Yankee Nuclear Power Station
BVY-98-098, Monthly Operating Rept for June 1998 for Vermont Yankee Nuclear Power Station
BVY-99-127, Monthly Operating Rept for Sept 1999 for Vermont Yankee Nuclear Power Station.With
BVY-98-053, Monthly Statistical Rept for Mar 1998 for Vynp
BVY-99-112, Monthly Operating Rept for Aug 1999 for Vermont Yankee.With
BVY-99-102, Monthly Operating Rept for July 1999 for Vermont Yankee. with
BVY-99-090, Monthly Operating Rept for June 1999 for Vermont Yankee Nuclear Power Station.With
BVY-99-046, Monthly Operating Rept for Mar 1999 for Vermont Yankee Nuclear Power Station.With
BVY-99-077, Monthly Operating Rept for May 1999 for Vermont Yankee Nuclear Power Station.With
L-84-240, Forwards Written Responses & Ref Matls to Substantiate Statements Made During 840907 Exit Interview Re Reactor & Senior Reactor Operating Exams on 840905
0CAN019202, Forwards Revs to NIS-2 Forms, Owners Rept of Repairs or Replacements, Due to Need for Corrections.Forms Were Originally Part of ISI Outage Summary Rept,Submitted by
05000328/LER-1989-009-03, :on 890629,Limiting Condition for Operation 3.0.3 Entered Due to Failure to Comply W/Action Statement in Tech Spec.On 890504,discovered That Ice Condenser Bed Temp Recorder Not Printing
HL-5778, Ei Hatch Nuclear Plant Radiological Environ Operating Rept for 1998. with
05000254/LER-1987-006-08, :on 870403,HPCI Sys Inoperable.Caused by Loose Soldered Connection on Solenoid Valve Coil SV-8.Solenoid Coil Replaced & HPCI Turbine Remote Reset Verified.Solenoid Valves SV-8 & SV-12 Replacement Planned
05000265/LER-1987-008-10, :on 870630,cable Tunnel Sprinkler Sys out-of-svc for Greater than 14 Days.Caused by Need to Perform Sys Enhancements to Ensure That Sys Consistent W/ NFPA Code Requirements
05000339/LER-1988-001-03, :on 881104,steam Driven Auxiliary Feedwater Pump Inadvertently Started While Being Removed from Svc for Preplanned Maint.Caused by Personnel Error.Steam Supply Isolated.Human Performance Evaluation Underway
05000155/LER-1985-008-01, :on 851114,upscale/downscale Reactor Protection Sys Actuation Occurred.Caused by Electrical Noise.No Adverse Safety Consequences Occurred
HBL-93-038, Forwards Comments on Proposed Draft Order 93-15 & Monitoring & Reporting Program 93-15,per NPDES Permit CA0005622.Calculation for Dilution Factor Used to Determine Effluent Limitations in Previous Orders Will Be Sent
BVY-93-027, Monthly Operating Rept for Feb 1993 for Vermont Yankee Nuclear Power Station
05000395/LER-1989-019, :on 891203,as Result of Plant Trip on 891202, Results of Reactor Coolant Sample Not Reviewed & Recognized as Being Out of Tolerance.Caused by Personnel Error.Another Sample of RCS Taken & Analyzed,Per Tech Spec
05000277/LER-1981-027-03, /03L-0:on 810424,during Maint Outage,Hydraulic Snubbers SS-5-A,S5-A1,S5-D3 & 1-GG-5-27 Found to Have Empty Reservoirs.Caused by Deterioration of Snubber Piston Seals of Grinnell Models AN-1372B & AH-1373A.Snubbers Rebuilt
05000324/LER-1989-021-01, :on 891225,electrical Protection Assembly Output Breakers Associated W/Bus a of Reactor Protection Sys Tripped Open.Cause of Trip Unknown.Voltage & Frequency Output of Motor Generator a Monitored
05000282/LER-1989-014, :on 890905,operations Personnel Recalled That SP1093.1 Performed Two Wks Previously Instead of SP1093.2. Caused by Personnel Error in Selecting Incorrect Procedure. Proper Notifications Made & SP1093.2 Performed
05000272/LER-1987-016-01, :on 871102,power Operated Relief Stop Valve 1PR6 Cabling Found Degraded.Caused by Inadequate Design Review.Degraded Cable Replaced & Equipment Qualification Preventive Maint Requirements Upgraded
05000333/LER-1917-004, Regarding Safety Relief Valves Out of Tolerance
B18610, Application for Amendment to NPF-49 to Modify Technical Specification Requirements for Missed Surveillances in Specification 4.0.3 & Modify Associated Technical Specification Bases
BVY-99-035, Monthly Operating Rept for Feb 1999 for Vermont Yankee Nuclear Station.With
NSD-NRC-97-5348, Forwards Assessment on Surge Line Flooding Effect on Low Power & Shutdown Risk in Response to 970905 Telcon Request
05000352/LER-1986-040, :on 860723,RWCU Sys Isolated Twice as Result of Regenerative HX Room Temp Exceeding 122 F Setpoint.Caused by Ventilation Sys Being Removed from Svc & Failure of Pressure Safety Relief Valve