JAFP-17-0001, Transmittal of Emergency Plan Updates
JAFP-16-0038, Transmittal of Emergency Plan Updates, Including Revision 56 to SAP-2 and Revision 21 to SAP-8
JAFP-17-0109, Emergency Plan Implementing Procedures EAP-2, Rev. 35, Personnel Injury and SAP-2, Rev. 63, Emergency Equipment Inventory
RS-15-159, Supplemental Information Related to Proposed 10 CFR 20.2002 Disposal Procedure
PNP 2013-075, Response to Request for Additional Information - License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors
BSEP 12-0140, Additional Information Supporting License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition)
JAFP-18-0027, Emergency Plan Updates. Includes SAP-2, Revision 63 and SAP-3, Revision 93
DCL-14-098, Diablo Canyon, Units 1 and 2 - Ninety-Day Response to NRC Request for Additional Information- National Fire Protection Association Standard 805
BSEP 10-0001, Letter Brunswick Initial Exam 2010-301 General Correspondence
BSEP 10-0025, Operating Test and Withdrawal Examination Reference Materials for Licensed Operator Initial Examinations 50-325-10-301 and 50-324-10-301
PLA-6241, Response to Request for Additional Information in Regard to Application for Renewed Operating Licenses NPF-14 and NPF-22
ND-19-0962, AP1000 Structural Reconciliation - Westinghouse Electric Company & Southern Nuclear Company Technical Exchange Meeting: August 13, 2019
NOC-AE-02001315, Conditional Exemption from Measurement of End of Life Moderator Temperature Coefficient
BECO-87-207, Provides Addl Info Re Second 10-yr Interval Inservice Insp Program Plan,Per Util 871002 Commitment & NRC 870714 Request.Attachment 2 Is Overall Revised Component Listing, Including 26 Addl Welds
JAFP-98-0142, Requests Exemption from Requirements of 10CFR70.24(a), Criticality Accident Requirements, as Plant Does Not Have Criticality Monitoring Sys for Handling & Storage of New (non-irradiated) Fuel in Conformance w/10CFR70.24(a)
BSEP-85-0545, Provides Supplemental Response to NRC Re Violations Noted in Insp Repts 50-324/83-11,50-325/83-11, 50-324/83-26 & 50-325/83-26.Info Provides Update of Fire Protection Program Status & Programmatic Changes
NSD-NRC-96-4688, Forwards Responses to NRC follow-on Questions Provided in 950907,1018 & s Re I&C Modeling in AP600 PRA
B13781, Advises That Util Requested That State of CT Dept of Environ Protection Issue Mod to NPDES Permit CT0003263.Mod Would Permit Discharges of Biocides & Sodium Nitrite from All Units at Facility
BYRON 2023-0002, Unit 2, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements
B12634, Forwards Response to NRC 861212 Question 5 Re NUREG-0737, Item II.D.1 Concerning Testing of PORVs & Safety Valves at Facility,Per Util & 870803 Telcon.Flow Rate Equal to Theoretical Flow for Fluid Transient Analysis
05000327/LER-1986-030, :on 860717,three Tech Spec Surveillance Requirements Not Performed.Caused by Procedure Inadequacy & Deficiency in Initial Writing of Section of Tech Spec.Tech Spec Change Will Be Submitted
05000321/LER-1988-013-02, :on 880904,reactor Feed Pump a Controller Malfunctioned Resulting in Decrease in Reactor Water Level. Caused by Poorly Soldered Connection on Converter Board. Connection Resoldered & Amplifier Replaced
05000409/LER-1985-011, :on 850427,reactor Scrammed Due to Low Water Level When Oncoming Reactor Feedwater Pump Did Not Respond Properly During Swap of Operating Feedwater Pumps.Caused by Erratic Operating Pump Control
05000327/LER-1991-020, :on 910722,LCOs 3.7.11.2 & 3.7.11.4 Entered When Fire Protection Spray,Sprinkler Sys & Hose Stations Discovered Inoperable.Caused by Personnel Error.Operations Review Team Evaluating Event
05000366/LER-1991-004, :on 910214,component Failure in Generator Exciter Caused Turbine Trip & Reactor Scram.Caused by Component Failure.Failed Component in Generator Exciter Sys Replaced
L-87-182, Forwards Integrated Schedule,Updating 861219 Application for Amends to Licenses DPR-31 & DPR-41.Issuance of Amends Anticipated within 1 Month
05000529/LER-1987-018-01, :on 871004,ESF Signal Initiated on Train B & cross-tripped Train a as Designed.Caused by Spurious Signal Due to Voltage Spike Caused by Electronic Noise.Plant Change Package Initiated
05000528/LER-1988-022, :on 880319,bolting Which Secures Gasket Retainer Plate Fractured.Caused by Bolts Not Meeting Spec Requirements.Changes Being Implemented to Replace Matl.W/
L-80-351, Forwards Comments on Suppl Info to Draft Effluent & Waste Disposal Semiannual Rept for 1978 Encl in
L-83-462, Semiannual Radioactive Effluent Release Rept,Jan-June 1983
MNS-16-008, Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima
05000206/LER-1989-016, :on 890703,air Flow Test of Lube Oil Reservoir & Conditioner Fire Protection Sys Revealed That Approx 20 of 78 Nozzles Plugged.Caused by Accumulation of Piping Corrosion Matl Inside Fire Spray Header
E900-05-014, Rev 0 to Calculation E900-05-014, SNEC Plant Area Open Land - OL1 - Survey Design, Appendix a to Final Status Survey Report for Saxton Nuclear Experimental Corp Open Land Area OL1
05000146/LER-2003-001, Failure to Verify Operability of the Containment Vessel Intrusion Alarm