RNP-RA/17-0065, Refueling Outage 30 Steam Generator Tube Inspection Report
NOC-AE-16003330, Transmittal of Information of Foreign Ownership, Control, or Influence (FOCI)
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 4, Reactor
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Sections 4.3.1 to 4.3-61
NL-12-168, Indian Point Energy Center - Engineering Report No. IP-RPT-12-00039, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 1 of 4
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 6.0 - Engineered Safety Features
ULNRC-06328, Revision of TS 5.6.5, Core Operating Limits Report (Colr), to Allow the Use of the Paragon and Nexus Core Design Methods (LDCN 16-0011)
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 3 - Design Basis
RBG-31793, Forwards Audited Financial Statements for Cajun Electric Power Cooperative,Inc
NOC-AE-04001753, Application for Order Approving Transfers of Control of Licenses and Conforming License Amendments
IA-84-843, Safety Evaluation Supporting Amend 25 to License DPR-75
VPN-076-98, Forwards Final Rept of Matl Properties of Neutron Shielding Matl to Be Used in Trojan ISFSI & Test Repts That Verified Matl Properties
IA-85-647, Responds to Appeal Re Denial of Info Re FOIA Request for Documents Re Plant.Forwards Documents Listed on App
2CAN088915, Requests Relief from ASME Section XI Code Requirements Limiting Exams
A06207, Forwards Responses to 861106 Request for Addl Info Re Util Request for Relief from Certain Code Category B-J Weld Inservice Insp Requirements.Isometric Drawings Encl
RBG-23496, Gulf State Util Co 1985 Annual Rept
L-PI-21-023, Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report
VPN-034-98, Application for Amend to License NPF-1,deleting Number of License Conditions & TS Requirements as Prerequisite to Implementing Requested Amend to Transfer of Nuclear Sf from Existing 10CFR50 Licensed Area to Proposed 10CFR72 ISFSI
05000395/LER-1986-011, :on 860629,reactor Tripped from 90% Power. Caused by Inadvertent Feedwater Isolation Valve Closure Due to Momentary Loss of Electrical Power to Normally Energized Solenoid Valve.Connector & Valve Replaced
05000354/LER-1986-009-01, :on 860425,technician Moved Adjacent intermediate-range Monitor Cable While Checking Wire Identification Numbers in Preamplifier Cabinet,Causing Spike of Scram Signal.Addl Training Scheduled
05000352/LER-1988-016, :on 880507,Channel B Reactor Protection Sys 1/2 Scram & Various Nuclear Steam Supply Shutoff Sys Isolations Occurred.Caused by Overheating of Fuse Due to Inadequate Contact.Fuse Replaced
05000483/LER-1984-004, :on 840617,ESFAS Inadvertently Actuated.Caused by Spurious Electronic Signals & Incompatibility Between Software & Hardware in RM-80 Microprocessing Unit for Radiation Monitors.Sys Reset
1CAN068502, Forwards Addl Info Re Second 10-yr Inservice Insp Program & Relief Requests,Per 850308 & 0204 Transmittals,Respectively, in Response to 850506 Request
05000265/LER-1984-007, :on 840610,during Turbine Test Qcs 5600-1, Control Valve 4 Immediately Fast Closed When Test Switch Depressed.Caused by 90% Closed Limit Switch Remaining Engaged.Line & Switch Will Be Examined
05000254/LER-1984-014-04, :on 840808,while Starting Shutdown Cooling Mode of RHR Sys,Lpci Valves 1-1001-29A & B Would Not Open. Caused by Personnel Error.Valve Stems Removed & Being Replaced
05000373/LER-1984-017, :on 840308,ammonia/chlorine Monitors OAE-VC091A & OAE-VC091B for HVAC Sys Alarmed.Alarms Could Not Be Reset. Train B Ammonia/Chlorine Detectors Discovered Frozen & Train a Detector Also Inoperable
W3P86-0040, Semiannual Radioactive Effluent Release Rept,Jul-Dec 1985
HL-1668, Proposed Tech Specs 3/4.4.6.1.1-.3 Revising Reactor Vessel Temp & Pressure Limits
05000155/LER-1980-048-01, /01T-0:on 801219,150 Splices & Five Terminal Block Defects Were Found.Caused by Installation of Faulty Equipment in Original Const.Splices & Blocks Repaired or Replaced
AEP-NRC-2024-20, Updated Final Safety Analysis Report (Ufsar), Revision 32, Chapter 3, Reactor (Unit 2)
L-88-311, Forwards Response to NRC Bulletin 87-002,Suppl 2 Re Fastener Testing to Determine Conformance W/Applicable Matl Specs, Consisting of Primary Suppliers,Secondary Suppliers & non-safety Suppliers Lists
L-PI-16-038, ISFSI - Transmittal of 2015 Annual Radiological Environmental Monitoring Program Report
L-PI-15-039, ISFSI - 2014 Annual Radioloqical Environmental Monitoring Program (REMP) Report
L-PI-14-043, Independent Spent Fuel Storage Installation, 2013 Annual Radiological Environmental Monitoring Program (REMP) Report
L-PI-11-040, Independent Spent - 2010 Annual Radiological Environmental Monitoring Program (REMP) Report
L-PI-09-103, Corrections to the 2007 Annual Radiological Environmental Monitoring Program (REMP) Report and the 2007 Annual Radioactive Effluent Report
L-PI-08-033, 2007 Annual Radiological Environmental Monitoring Program (REMP) Report
L-PI-07-035, 2006 Annual Radiological Environmental Monitoring Program (REMP) Report
L-06-166, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for October 2006
L-2007-045, In-Service Inspection Plans, Use of Structural Weld Overlays as an Alternative Repair Technique Third Ten-Year Interval Unit 2 Relief Request 10
VPN-069-200, Trojan Nuclear Plant Final Survey Report for Remaining Plant Secondary Systems
ND-21-0486, 0 to Updated Final Safety Analysis Report, Chapter 4, Reactor
NUREG/CR-5176, Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants