BSEP 17-0078, Request for License Amendment - DC Sources - Operating Surveillance Requirement (SR) 3.8.4.5
LG-14-067, 2013 Annual Radioactive Effluent Release Report
BSEP 14-0028, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi A
BSEP 12-0127, Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident
RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 8, Electric Power
L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, List of Effective Pages
L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary
LG-18-052, Submittal of Annual Radioactive Effluent Release Report No. 43
CP-200801606, Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Introduction Through Attachment a
LIC-06-0004, Attachment 1, Engineering Analysis (EA-FC-04-010) Recommendations for Implementing of Compensatory Actions in Response to NRC Bulletin 2003-01
3F1203-03, License Amendment Request No. 281, Revision 0 Regarding Revised Improved Technical Specification (ITS) 3.7.5, Emergency Feedwater System
DCL-04-051, Units I and 2, 2003 Annual Radiological Environmental Operating Report
NOC-AE-21003792, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)
BSEP-87-0065, Annual Rept of Facility Changes,Tests & Experiments,1986
BSEP-88-0609, Annual Rept of Facility Operation,Changes,Tests & Experiments for 1987
AECM-87-0165, Semiannual Radioactive Effluent Release Rept for Jan-June 1987
AECM-85-0274, Semiannual Effluent Release Rept,Jan-June 1985
RBG-37400, Forwards Rev 5 to River Bend Station Updated Sar. Rev Covers Period 910301-920301
AECM-85-0054, Semiannual Radioactive Effluent Release Rept,Jul-Dec 1984
AECM-84-0150, Semiannual Radioactive Effluent Release Rept,Jul-Dec 1983
AECM-84-0438, Semiannual Radioactive Effluent Release Rept, Jan-June 1984
GO2-83-353, Final & Interim Deficiency Repts Re Class IE Cables in Seismic Category 1 Raceways & Standby Gas Treatment Sys Damper.Next Rept by 830718
BECO-LTR-96-028, Annual Dose Assessment to General Public from Radioactive Effluents from Jan-Dec 1995
BW240053, Revised 2022 Annual Radioactive Effluent Release Report
05000325/LER-2024-002, Re Automatic Start of Emergency Diesel Generator Due to Emergency Bus De-energization
05000267/LER-1987-026, :on 871111,loss of Instrument Bus 2 Resulted in Scram Actuations.Caused by Low Trip Setting on Backup Power Supply Breaker.Transformer in Battery Charger 1B Replaced & Overcurrent Trip Setting Raised
05000325/LER-1988-006-01, :on 880219,several Bolt Head Failures of silicon-bronze Carriage Bolts in 125-volt & 250-volt Dc Switchboards Identified.Caused by Igscc.Bolts Replaced W/ Bolts Made from Mild Carbon Steel
NSD-NRC-97-4937, Forwards Draft AP600 SSAR App 1B.Response to RAI Re Severe Accident Mitigation Design Alternatives Also Encl
05000325/LER-1983-016-03, /03L-0:on 830425,routine Surveillance Revealed Electrolyte Levels of 125-volt Dc Div I & II Battery Cells Out of Allowable Level Band Mark.Caused by Changes in Ambient Battery Room Temps
05000325/LER-1982-074-03, /03L-0:on 820623,electrolyte Level in Pilot Cell of Div II Battery 1B-1 Found Higher than Max Level Mark on Cell.Caused by Battery Room Ambient Temp Increase Following Filling to Max Level Mark
05000325/LER-1983-005-03, /03L-0:on 830119,during Normal Operation,Measured Specific Gravity of Pilot Cell for Div I Battery 1A-1 Was 1.166 & 1.167 for Div II Battery 1B-1.Caused by Age of Pilot Cells.Cells Replaced.Batteries Returned to Svc
05000325/LER-1990-012-01, :on 900705,determined That 18-month Surveillance on Battery 1A-1 Exceeded Surveillance Time Interval.Probably Caused by Tech Spec Change & Rescheduling of Outage.Personnel Counseled
05000325/LER-1982-038-03, /03L-0:on 820419,reactor Scrammed Due to Opening of 125-volt Battery Charger Output Breaker While Removing Electrical Clearance on Div II Battery.Caused by Operator Error.Breaker Reclosed & Power Restored to 1B-1 Bus
BW180045, 2017 Radioactive Effluent Release Report
05000315/LER-1995-002-01, :on 950620,21,22 & 23,nine MSSVs Lift Settings Found to Exceed TS Limit.Caused by Mild Galling Between Disc & Nozzle Components.Eight of MSSVs W/Initial High Lift Setpoint Had Subsequent Lifts within TS Limit
L-99-209, Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included
GO2-85-255, Forwards Request for Relief for Exams Found Impractical During Preservice Insp Program.Written Response Granting Relief from ASME Section XI Requirements Requested
05000335/LER-1990-007-01, :on 900524,excessive Unisolable Leak Discovered on Hydraulic Control Valve in Digital Electrohydraulic Control Sys.Caused by Ruptured O-rings Inside Hydraulic Control Valve.Startup Breaker Replaced
L-81-203, Responds to 810306 Request for Addl Info Re Util Original Response to IE Bulletin 80-06, Engineered Safety Feature (ESF) Reset Controls. Table of Components Actuated on Sais, Reflecting Recent Safety Sys Mods,Encl
L-83-376, Submits Addl Info Supporting 830216 Request for Amend to License DPR-67 Revising Surveillance Requirements of 125-volt Dc Batteries in Conjunction W/Sys Mods,In Response to NRC Request.Unit 1 Dc Sys Modified Identically to Unit 2
L-88-349, Forwards Comments on Plant License Exam Administered on 880726,in Response to NRC .Answer Key to Accept, Loss of Power to Monitor as Addl Functional Feature of Blue Fail Light Needs Mod
HNP-12-119, Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
NRC-87-0084, Suppl 4 to Fermi 2 Nuclear Power Plant,Interim Startup Test Rept