NOC-AE-16003330, Transmittal of Information of Foreign Ownership, Control, or Influence (FOCI)
LR-N13-0172, Enclosure 1 - Salem Nuclear Generating Station Unit 1 Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic
LR-N13-0156, Response to RAI for Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
RA07-045, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
L-05-067, Letter Transmitting Firstenergy Corp. 2004 Annual Report
L-2019-033, Response to Requests for Additional Information Subsequent License Renewal Application Safety Review Revision 1, Set 8 First Submittal Responses
NRC 2002-0069, Filing of Owners Inservice Inspection Summary Report
IA-85-735, Responds to 850415 Request for Investigative Rept Re Facility.Info Cannot Be Released Arbitrarily.Info Can Be Obtained by Forwarding FOIA Request to J Felton at Listed Address
RBG-30603, Radiological Environ Operating Rept for River Bend Operating Station for 1988
A98034, 1997 Annual 10CFR50.59 Summary Rept
ST-HL-AE-5689, Application for Amend to License NPF-76,incorporating Revs to TS 3.7.1.6, Atmospheric Steam Relief Valves, to Ensure Automatic Feature of SG Power Operated Relief Valve Remains Operable During Modes 1 & 2
U-602573, Forwards Five Copies of Rev 22 of Physical Security Plan. Encl Withheld
ST-HL-AE-3826, Forwards Endorsements 3,8,9,10,11 & 12 to Maelu Policy M-113,Endorsements 1-5 & 7-12 to Maelu Policy M-116, Endorsements 2,3,7,8,9 & 10 to Nelia Policy N-113 & Endorsements 1-10 to Nelia Policy N-116
ST-HL-AE-3916, Requests Exemption from Requirements of 10CFR50.62, Eliminating Requirements for Specific ATWS Mitigating Sys Actuation Circuitry.Proprietary Pages to Rev 0 to WCAP-12385 Encl.Encl Withheld
LIC-95-0018, Forwards OPPD Annual Accounting for Period of Jan-Dec 1994, as Required by FCS Decommissioning Funding Plan Trust Agreement
B17141, Application for Amend to License NPF-49,incorporating Rev Into Chapters 2,3 & 9 of Fsar,Adding New Sump Pump Subsys to Address Groundwater Inleakage Through Containment Basemat
05000498/LER-1988-041, :on 880710,high Toxic Gas Alarm Occurred W/O Automatic Actuation of Control Room Ventilation to Recirculation Mode.Caused by Incorrect Configuration of Wiring.Wiring Corrected
05000336/LER-1992-012-01, :on 920706,inadvertent ESAS Actuation Occurred Resulting in Partial Loss of Normal Power & Undervoltage Actuation of Facility Z1.Caused by Deenergizing ESAS Sensor Cabinet.Power Restored to Vital 4,160-volt Bus
05000397/LER-1984-093, :on 840824,false Hi Chlorine Signal from Control Room Ventilation Chlorine Detector Actuated Control Room Emergency Filtration Sys.Caused by Depletion of Chlorine Sensitive Tape.Tape Replaced
05000280/LER-1976-002-03, /03L:on 760318,auxiliary Feedpump Discharge Valve MOV-FW-151A Failed to Open When Main Feedpump Breakers Opened.Caused by Timing Relay Plunger Failure to Activate Micro Switch.Timing Relay & Switch Replaced
05000272/LER-1983-062-99, /99X-0:on 831122,triaxial time-history Accelograph Inside Bioshield on 81-ft Elevation of Containment Bldg Failed.Cause Not Stated.Accelerometer Will Be Replaced During Next Outage
05000281/LER-1983-034-03, /03L-0:on 830813,w/unit at Constant Speed Drive, Periodic Snubber Functional Testing Revealed 23 Snubbers Failed to Meet Required Acceptance Criteria.Caused by Seal Degradation & Scored Piston/Body
05000244/LER-1983-012-03, /03L-1:on 830323,individual Doors for Personnel Hatch Had Higher Leak Rate than Allowed.Caused by Incorrect Maint Procedure on 821007 Requiring Only Door Seal Leak Testing.Procedure Revised.Other Procedures Reviewed
05000334/LER-1982-057-03, /03L-0:on 821130,pump CH-P-1A Shut/Down After Discovery of Low Control Room Readings for Charging,Seal Flow & Running Current During Operability Test.Component Inspected.No Apparent Problems Identified
05000321/LER-1978-086-03, /03L-0:on 781016,peak LHGR Rose to 100.2% After Calibr.Caused by Spatial Xenon Variations Which Induced Slightly Nonconservative Calculation of LHGR in Affected Region
05000254/LER-1982-004-03, /03L-0:on 820307,reactor Core Isolation Cooling Steam Line Was Isolated When High Steam Line Differential Pressure Alarm Received.Caused by Instrument Drift of Pressure Switch DPIS-1-1360-1A.Switch Recalibr
05000280/LER-1982-011-03, /03L-0:on 820126,three Incidents of Unsampled Release from Subsurface Drains to Discharge Canal Occurred. Caused by Operator Error.Administrative Controls Established to Notify Health Physics Prior to Pumping of Drains
RBG-36828, Gulf States Utils Co Annual Rept,1991. Audited Financial Statements for Cajun Electric Power Cooperative,Inc Also Encl
B14521, Forwards Request for Relief from ASME Code Section XI Requirements to Make Interim Repairs to Leak in Svc Water Sys Piping Line SWP-003-067-3 as Alternative to IWA-7000 Replacement,Per GL 90-05
05000260/LER-1981-060-03, /03L-0:on 811103,while Performing Mmi 40, Connection from Pressure Gauge to Bladder in Accumulator 24 Broke,Rendering Pump a Inoperable.Caused by Connector Being Overtightened.Bladder Replaced
05000280/LER-1982-097-32, /03L-0:on 821014,auxiliary Feed Pumps Prevented from Automatically Starting on Loss of Both Normal Feed Pump Motors.Caused by Incomplete Design Change W/Improper Documentation.Jumpers Installed in Control Circuitry
05000335/LER-1983-025-03, /03L-0:on 830419,31-day Fire Station Insp Interval Exceeded.Caused by Personnel Oversight.Personnel Advised of Importance of Performing Required Insps
05000280/LER-1981-053-03, /03L-0:on 810816,shaft of Standby Pump 2-SW-P-10B Found to Be Rotating Backwards Due to Failure of Check Valve L-SW-108 to Seat Properly.Caused by Wear Resulting in Excessive Play & Binding in Disc
05000280/LER-1981-016-03, /03L-0:on 810615,primary Sys Chloride Concentration Exceeded Tech Specs.Apparently Caused by Personnel Working on Minor Repairs to Closure Stud Hole on Reactor Vessel Flange.All Sources of Makeup Water Checked
05000327/LER-1980-077-03, /03L-0:on 800525,B Train RHR & B Train Containment Spray Pumps Were Inoperable Because Valve FCV-63-73 Failed to Open.Caused by Valve Failing to Actuate Interlock Limit Switch
05000338/LER-1980-021-03, /03L-0:on 800202,w/unit in Mode 1,emergency Diesel Generator 1H Tripped on High Crankcase Pressure During Manual Start to Verify Diesel Operability.Cause Unknown. Generator Restarted.Vendor Investigating
05000302/LER-1979-051-03, /03L-0 on 790516:while Performing Daily Shutdown Surveillance SP-301,fire Svc Tank Level Discovered to Be 3,600 Gallons Below Min Allowed.Caused by Improper Design. Alarm Setpoint Raised to Tech Spec Limit
05000338/LER-1980-001-01, /01T-0:on 800118,during Review for IE Bulletin 79-14,letdown Lines 3/4-CH-275-1502Q1 & 3/4-CH-123-1502-Q2 Reported Overstressed.Caused by Incorrect Valve Weights Used in Pipe Stress Calculations
CNL-17-104, Response to Request for Additional Information Regarding Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04)
L-PI-09-015, Submittal of Inservice Inspection Examination Summary Report, Interval 4, Period 2, Outage 1, Refueling Outage, Dates: 09-19-2008 to 11-01-2008 Unit 2, Fuel Cycle 24:12-15-2006 to 11-01-2008
L-05-150, Discharge Monitoring Report (NPDES) Permit No. PA0025615
0CAN042501, (Ano), Units 1 and 2, Emergency Plan On-Shift Staffing Analysis, Revision 4
A06401, Forwards Responses to Questions on Pumps & Valves Inservice Testing Program,Per 870602 & 03 Meetings
LD-88-222, Forwards Corrections of Typos & Incorporates Clarifications & Technical Revs Suggested by Into Application for Amend to License SNM-1067
05000313/LER-1980-039-03, During Monthly Surveillance on Lead H Purge Sys,Exhaust Fan VEF-37A Tripped.Caused by Short in Control Sys Which Caused Rectifier to Fail & Fuse to Blow