DCL-14-041, Response Update to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.3 Seismic
RC-14-0032, Virgil C. Summer Unit 1, License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. Attachments Iii, Iv, V & Vi: Technical Bases for Proposed EALs (Clean Copy), NEI 99-01 Revision 6 EA
RC-14-0032, Virgil C. Summer Unit 1, License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. EPP-108, Enclosure 1, Revision 01 (Draft E)
RS-12-154, Attachment D to Proto-Power Calculation 97-195, Revision a
NL-08-019, LTR-PAFM-08-4, Revision 0, Technical Basis to Support Extension of Surveillance Interval for Planned Visual Inspection of the Indian Point, Unit 2 Bmi Nozzles
NL-16-135, Report No. R-P1812, Wall Thickness Profile Sheet. (Sketch)
RA09-012, Evaluation of the Water Spray System in the Overlab Area Fire Zone 4F3
L-2019-033, Response to Requests for Additional Information Subsequent License Renewal Application Safety Review Revision 1, Set 8 First Submittal Responses
RS-19-017, Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control
ND-19-1095, Emergency Action Levels and Basis
JPN-04-012, 2003 Annual Report, and, Securities and Exchange Commission Form 10-K Submittal for All Entergy Nuclear Operations, Inc. Plants. Financial Results Through Investor Information
RC-96-0182, Responds to RAI Re GL 95-07, Pressure Locking and Thermal Binding of Safety-Related Power Operated Gate Valves
LIC-95-0018, Forwards OPPD Annual Accounting for Period of Jan-Dec 1994, as Required by FCS Decommissioning Funding Plan Trust Agreement
LD-91-071, Responds to NRC Requests for Addl Info for Review of C-E SSAR-Design Certification Rept.Proposed Revs to SSAR Encl
L-PI-21-023, Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report
05000338/LER-1989-008-01, :on 890414,determined That Less than Design Svc Water Sys Flow Available to Recirculational Spray Hxs.Caused by Inadequate Maint Procedures,Resulting in Missetting of Mechanical Stops.Stops & Limit Switches Reset
05000412/LER-1987-021, :on 870722,operations Personnel Observed Difference Between RCS Pressure Protection Channels & RCS Pressure Control Channels.Caused by Protection Channels Drifting Out of Calibr.Transmitters Recalibr
0CAN049802, Monthly Operating Repts for Mar 1998 for Arkansas Nuclear One,Units 1 & 2
05000251/LER-1986-013-01, :on 860722 & 24,while Performing Maint on Safeguard Relays,Phase a Containment Isolation Actuated. Caused by Inadvertent Relay Actuation.Actuation Signal Reset & Valves Reopened
05000423/LER-1987-008, :on 870307,reactor Trip Occurred Due to lo-lo Steam Generator Level in Steam Generator D.Caused by Failure of Solenoid Valve.Solenoid Valve Replaced & Tested for Operability
05000322/LER-1988-005, :on 880509,meteorological Instrumentation Out of Calibr.Caused by Inability of Installed Instrumentation to Meet Tolerence of Reg Guide.Investigation Being Conducted by Instrumentation & Control
05000321/LER-1988-012-01, :on 880826,HPCI Sys Declared Inoperable Due to Malfunctioning Sys Flow Controller.Caused by Loose Fastener on Intermediate Gear in Gearing Mechanism of Controller. Gear Placed in Gear Train
05000348/LER-1988-006, :on 880301,determined That Hydrogen Accumulating in Supply Line from RHR Pump.Caused by Piping Configuration in Layout of Train Supply Line A.Hydrogen Vented from Piping.Periodic Program Initiated
05000313/LER-1988-003, :on 880217,reactor Tripped on Low RCS Pressure. Caused by Unplanned Regulating Rod Group Insertion. Programmer for Group 7 Replaced,Temporary Mod Installed & Drive Clutch Adjustment Made to CV-2625
05000323/LER-1985-008-01, :on 850913,while Unit in Cold Shutdown, Automatic Isolation of Containment Ventilation Sys Occurred. Investigation Continuing.Alarm Reset & Gaseous Radiation Monitor Isolation Valves Returned to Position
05000250/LER-1985-033, :on 851016,discrepancy Discovered Between Assumptions Used in Most Current Westinghouse LOCA Analysis & Fsar.Sufficient Margin Exists Between Reported Values of Peak Clad Temp & ECCS Acceptance Criteria
05000263/LER-1984-028, :on 840914,reactor Protection Sys B Motor Generator Set Overload/Overtemp Relay open-circuited.Cause Unknown.Power Restored & Relays a & B Replaced
05000263/LER-1984-017, :on 840425,control Room HVAC Transferred to Emergency Mode When Ammonia Monitor Tape Cassette Ran Out Causing Spurious Monitor Trip.Caused by Failure to Replace Cassette as Scheduled.Procedure Revised
TXX-9210, Forwards Rev 13 to Comanche Peak Steam Electric Station Emergency Plan. Rev in Ref to Corporate Ofc Emergency Response & Support,Departmental Reorganization & Emergency Response Facility Computer Sys & Digital RMS
05000280/LER-1983-004-03, /03L-0:on 830202,w/Units 1 & 2 at 88% & 100% Respectively,Emergency Diesel Generator 3 Declared Inoperable Due to Leaking Cooling Water Pump.Caused by Worn Shaft Seal.Seal Replaced & Generator Tested Satisfactorily
ELV-03028, Monthly Operating Repts for Jul 1991 for Vogtle Electric Generating Plant Units 1 & 2
JPN-91-037, Forwards Response to NRC 901120 Request for Addl Info Re Proposed Changes to Tech Specs on Spent Fuel Pool Storage Capacity.Holtec Rept HI-91614 Encl
U-601120, Responds to NRC Bulletin 87-002, Fastener Testing to Determine Conformance W/Applicable Matl Specs. Attachments Provide Info Re Util Program for Verification of Chemical & Mechanical Quality of Fasteners Used at Plant
05000327/LER-1993-009, :on 930417,TS Surveillance Not Performed for Three Pipe Support Snubbers Because of Omission of Snubbers from Surveillance Instruction for Visual Insp.Snubbers Visually Inspected & Functionally Tested
05000280/LER-1981-049-03, /03L-0:on 810730,review of Test Program Revealed Sensitized Pipe Supplied by Containment Spray Pump 2-CS-P-1A Was Being Flushed for Less than Min Time Required.Caused by Inadvertent Change of Flush Time for Pump Piping
05000346/LER-1977-113-03, /03L-1:on 771216,auxiliary Feedwater Valves AF 599 & AF 608 Discovered Closed & Breakers to Motor Operated Valves Ms 107A,AF 3871 & AF 3872 Open,Resulting in Inoperability of Auxiliary Feedwater Trains
NUREG-0227, Partial Draft of Nuclear Power Plant Operating Experience - 1978, Section 3.0, Plant Outages. Portions of NUREG-0483, NUREG-0366 & NUREG-0227 (Plant Operating Experience for 1977,1976 & 1974-75,respectively) Encl
05000280/LER-2078-016-03, L for Surry Unit 2 Failure of a Redundant Heat Tracing Circuit on Boron Injection Tank Inlet Pipe
05000280/LER-1980-027-03, /03L-0:on 800512,discharge Valve for 1-LW-P-5A Was Inadvertenly Left Open,Causing Unsampled Release from 1-LW-TK-11A Thru Gravity Flow.Caused by Discharge Valve 1-LW-247 Inadvertently Left Opened.Release Terminated
PLA-7757, Final Integrated Plan to Comply with June 06, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (NRC-Order EA-13-109), Revision 1
L-PI-16-038, ISFSI - Transmittal of 2015 Annual Radiological Environmental Monitoring Program Report
CNS-16-016, Emergency Plan Implementing Procedures, Including Revision 035 to RP/0/A/5000/001 and Revision 036 to RP/0/A/5000/001
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-2014-109, 120-Day Response to Request for Additional Information Re License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants
MNS-14-012, Relief Request 13-MN-003 Limited Weld Examinations
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
PLA-6510, Engineering Report 0000-0101-0766-NP-R0, Main Steam Line Limit Curve Adjustment During Power Ascension
L-PI-08-033, 2007 Annual Radiological Environmental Monitoring Program (REMP) Report
L-PI-07-035, 2006 Annual Radiological Environmental Monitoring Program (REMP) Report
HCH-2007-052, Notice of Noncompliance and Affirmative Defense of Laboratory Error
ET 06-0011, CFR 50.55a Requests I2R-34, I2R-35, I2R-36, I2R-37, and I2R-38 for the Second Inservice Inspection Program Interval
U-603660, 2003 Annual Radiological Environmental Operating Report
L-03-178, National Pollutants Discharge Elimination System (NPDES) Monthly Report Permit No. PA0025615
NG-05-0436, Supplement to the Response to a Notice of Violation Contained in Inspection Report 5000331/2005011
NSD-NRC-97-5348, Forwards Assessment on Surge Line Flooding Effect on Low Power & Shutdown Risk in Response to 970905 Telcon Request