RA-17-072, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
LIC-14-0077, CFR 50.59 Report, Quality Assurance (QA) Program Changes, Technical Specification Basis Changes, and Updated Safety Analysis Report (Usar)Revision
RA-11-026, Revision of the Core Operating Limits Report for Reload 22, Cycle 23, Revision 6
RBG-47773, Supplement to License Renewal Application
NOC-AE-09002457, Nuclear Decommissioning Trust Fund Agreements (Updated)
RA-08-106, Issuance of the Oyster Creek Core Operating Limits Report for Cycle 22, Revision 4
RA-08-064, Issuance of Core Operating Limits Report for Cycle 21, Revision 3
L-PI-08-052, License Amendment Request (LAR) to Revise the Loss of Coolant Accident (LOCA) and Main Steam Line Break (MSLB) Accident Dose Consequences Analyses and Affected Technical Specifications (TS)
CPSES-200101489, Submittal of Unit 1 Eighth Refueling Outage (1RF08) Inservice Inspection (ISI) Summary Report (Unit 1: 1986 Edition of ASME Code, Section XI, No. Addenda, Interval Start Date - August 13, 2000
LIC-04-0047, License Amendment Request, Application for Technical Specification Improvement to Implement a Risk Informed Alternative to the Existing Restoration Period for the High Pressure Safety Injection System
CPSES-200400143, Submittal of Unit 2 Seventh Refueling Outage (2RF07) Inservice Inspection (ISI) Summary Report (Unit 2:1986 Edition of ASME Code, Section XI, No Addenda, Interval Start Date - August 3, 1993, First Interval)
L-2003-292, Revised Emergency Plan Implementing Procedures
LIC-03-0077, License Amendment Request, Addition of Diesel Generator Fuel Oil, Diesel Generating Lubrication Oil, and Diesel Generator Starting Air Requirements
LIC-03-0037, License Amendment Request, Low Pressure Safety Injection System Allowed Outage Time, Replacement Attachment
CPSES-200300365, Submittal of Ninth Refueling Outage Inservice Inspection Summary Report (Unit 1: 1986 Edition of ASME Code, Section XI, No.Addenda, Interval Start Date - August 13, 2000, Second Interval, First Period, Second Outage)
LIC-02-0120, Attachment 2, Pump and Value Inservice Testing Program Plan, Fourth Ten-Year Interval, Rev 0
CPSES-200202716, (CPSES)-Unit 2, Submittal of Unit 2 Sixth Refueling Outage (2RFO6) Inservice Inspection (ISI) Summary Report
LIC-02-0044, Revision to License Amendment Request, Allowance to Perform Recirculation Actuation Logic Channel Functional Test
LIC-02-0040, License Amendment Request, Allowance to Perform Recirculation Actuation Logic Channel Functional Test
NL-02-037, Technical Specification Bases Changes
NL-02-024, Submittal of Technical Specifications Bases Changes for Indian Point Unit 2
05000272/LER-1982-093, Forwards LER 82-093/03L-0.Detailed Event Analysis Encl
NL-20-012, Application to Revise Provisional Operating License and Technical Specifications
LIC-99-0045, Forwards Application for Amend to License DPR-40,proposing to Relocate pressure-temp Curves,Predicated NDTT Shift Curve & LTOP Limits & Values from FCS TS to OPPD Controlled Document.Rev 3 to TR CE NPSD-683 & Supporting TSs Encl
1CAN088803, Application for Amend to License DPR-51,revising Variable Low Pressure Trip Setpoint for Reactor Protection Sys.Fee Paid
LIC-97-0070, Forwards Revs to USAR for Fort Calhoun Station. Attachment B Is Provided to Describe Revs to USAR Other than Revs Resulting from 10CFR50.59 Changes
LIC-96-0077, Forwards Application for Amend to License DPR-40,adding LCO for Trisodium Phosphate & Increase Min Required Amount of Trisodium Phosphate Contained in Containment Sump Mesh Baskets
LIC-95-0112, Forwards Application for Amend to License DPR-40 Re Extension of Allowed Outage Time for an Inoperable LPSI Pump from 24 H to Seven Days
LIC-95-0119, Forwards Amend to License DPR-40,requesting Change to Provide Addl Restrictions on Operation of CCW Sys Heat Exchangers to Ensure CCW Sys Temps Maintained within Analyzed Design Basis
LIC-95-0100, Forwards Amend to License DPR-40,revising TSs 2.3,3.1,3.2, 3.3 & 3.6 of Plant TS
RA-22-0057, License Amendment Request to Address Technical Specifications Mode Change Limitations
RA-08-060, Transmittal of Supplemental Response - Amergen Application to Revise Technical Specifications Secondary Containment Operability Requirements During Refueling
05000280/LER-1975-016, Updated LER 75-16/010:on 750822 & 23,channel II Protection Drifted in Nonconservative Direction.Caused by Moisture Accumulation Between Senson Insulation & Copper Lead Wire. All RTDs Replaced W/Improved Versions
05000285/LER-1987-021, :on 870602,during Reactor Startup Operations Personnel Discovered That Offsite Power Low Signal Still in Bypass at RCS Temp of 530 F.Caused by Inconsistency Between Procedure & Tech Specs
05000219/LER-1987-009, :on 870207,flow Biased APRM Setpoints for Scram & Rod Block Setpoints Exceeded Tech Specs.Caused by Inadequate Maint & Testing of Recirculation Pumps
L-2003-046, Emergency Plan Implementing Procedure
05000219/LER-1985-021, :on 851119,during Performance of APRM Surveillance Test & Calibr Procedure,Aprm Flow Converter Trip Setpoint Exceeded Tech Spec Acceptance Criteria.Caused by Setpoint Drift.Setpoint Reset
05000285/LER-1984-021, :on 841017,sample from Safety Injection & Refueling Water Tank Yielded Low Boron Concentration.Change Made to Test ST-CHEM-1,F.2 to Notify Supervisor When Boron Concentration Falls Below 1,740 Ppm
05000250/LER-1984-028, :on 841030,min Degree of Redundancy for Reactor Protection Sys overtemp-delta Temp & overpower-delta Temp Reactor Trip Features Less than Tech Spec Requirements. Caused by Incorrect Variable Setpoints
05000251/LER-1976-001-03, /03L:on 760130,channel 2 Overtemp delta-T Reactor Trip Setpoint Exceeded Tech Spec Limit by One Degree.Caused by Failure of Two Filter Capacitors in Signal Summator. Capacitors Replaced
05000285/LER-1976-029-03, /03L:on 760831,reactor Coolant Sampled & Analyses Indicated I-131 Equivalent 2.075 Uci Per Gram.Caused by Power Transient.Numercial Limit Exceeded But All Conditions of Tech Spec Fulfilled
05000281/LER-1976-001-03, /03L:on 760217,channel III Overtemp Setpoint Drifted 9% in Nonconservative Direction.Caused by Outputs of Summator TM-2-432 High Even Though Inputs Were Correct. Summator Replaced
05000287/LER-1983-014-03, /03L-0:on 831226,discovered Channel B Reactor Protective Sys a Hot Leg Temp Instrument Indicating More than 3 F Lower than Other Channels.Caused by Deficiency. Resistance Temp Detector Bridge Calibr
05000280/LER-1983-016-03, /03L-0:on 830310,undervoltage (UV) Relay Setpoints for Bus a & Phase A-B UV Relay Setpoint for Bus C Indicated Less than Tech Specs.Caused by Instrument Drift.Undervoltage Relays Reset
05000219/LER-1993-007-01, :on 931117,discovered Failure to Perform APRM Surveillance W/Max Recirculation Flow.Caused by Misunderstanding of TS Requirements.Aprm Channel Tested W/ Simulated Flows to Compliance W/Ts Limits
05000285/LER-1982-009-03, /03L-0:on 820411,while Exchanging Component Cooling Water Heat Exchangers,Associated Outlet Valves HCV-490B,HCV-491B & HCV-492B Failed to Open.Cause Not stated.HCV-491B Reassembled & Tested
05000255/LER-1982-008-03, /03L-0:on 820205,during Routine Surveillance to Verify Reactor Protection Sys Trip Setpoints,Thermal Margin/ Low Pressure Trip Was 1,747 Psia.Caused by Temp Change or Movement of Panel.Instrument Recalibr
05000285/LER-1993-005, :on 930422,determined That Incident Reportable in That SIRWT Recirculation Piping Associated w/MR-FC-83-046 Used Between Dec 1986 & 1992 Refueling Outage in Unacceptable Configuration
05000287/LER-1981-006, Forwards LER 81-006/03X-1.Detailed Event Analysis Encl
05000311/LER-1983-006-04, /04L-0:on 830408,decreased Sensitivity of Channel 2R41C Plant Vent Noble Gas Monitor Rendered Waste Gas Discharge Line Automatic Isolation Feature Inoperable.Caused by Leakage on Monitor Sample Lines & Internal Connections
05000285/LER-1989-020, :on 891012,determined That Two of Four Component Cooling Water HXs Simultaneously Inoperable for More than 24 H.Caused by Inadequate Controls Re Return of Equipment to Svc.Standing Order Revised
05000219/LER-1976-022-03, /03L-0:on 760910,acceptance Criteria in Procedures 629 & 614 for Low & low-low Reactor Level Trip Points Found Less Conservative than Tech Specs.Caused by Faulty Surveillance Test Procedure.Trip Point Settings Calibr
LIC-06-0088, License Amendment Request (LAR) Change of Containment Building Sump Buffering Agent from Trisodium Phosphate to Sodium Tetraborate
05000280/LER-2075-017, Re Failure Low of Loop C Hot Leg RTD, Causing Protection Signals to Fail Low
05000280/LER-2075-016-01, Submit Updated Abnormal Occurrence Report No. AO-S1-75-16 Re Channel II T/Tavg Protection Drift in Nonconservative Direction
05000255/LER-2078-005, License Event Report 1978-005-00 Re Steam Generator Level Instrumentation
05000255/LER-1980-019-01, /01T-0:on 800609,during Tech Spec Review,Tech Spec 3.3 Determined to Provide Too Little Borated Water for Safety Injection.Caused by Imprecise Wording of Tech Spec. Low Level Alarm Setpoint Changed,Tech Spec Under Evaluation
GO2-84-338, Reactor Containment Bldg Integrated Leak Rate Test. W/
05000285/LER-2012-012-01, Regarding Multiple Safety Injection Tanks Rendered Inoperable
LIC-07-0082, License Amendment Request (LAR) Permanent Use of Sodium Tetraborate as the Containment Building Sump Buffering Agent
LIC-05-0083, License Amendment Request (Lar), Tri-sodium Phosphate Volume
LIC-04-0045, Unit No. I License Amendment Request (Lar), Trisodium Phosphate Volume
LIC-03-0104, Technical Specifications Updated for NRC Comments on Pending Amendment Request on the Pressure-Temperature Limits Report
LIC-02-0124, License Amendment Request, Removal of Allowance to Perform Recirculation Actuation Logic Channel Functional Test
LIC-02-0048, Supplemental Information Supporting License Amendment Request, Allowance to Perform Recirculation Actuation Logic Channel Functional Test
LIC-02-0097, License Amendment Request, Low Pressure Safety Injection System Allowed Outage Time
LIC-04-0102, Request for Additional Information (RAI) Regarding License Amendment Request (Lar), Trisodium Phosphate (TSP) Dodecahydrate Volume
1CAN078803, Application for Amend to License DPR-51,changing Tech Specs Re Cycle-9 Operational Requirements.Cycle 9 Reload Analysis Rept Included for Technical Support.Fee Paid
05000219/LER-1980-028-03, /03L-0:on 800730,while Performing Monthly Surveillance Testing of Reactor High Pressure Scram Sensors, REO3C & REO3D Were Found to Trip at Lower than Specified Pressure Values.Caused by Sensor Repeatability
LIC-95-0109, Forwards Application for Amends to License DPR-40,proposing Ts,By Allowing Up to 24 Hours to Restore Safety Injection Tank Operability If Inoperable.Also,Forwards, Joint Applications Rept for SIT Aot/Sti Extension
05000250/LER-1992-003-02, :on 920322,discovered That Plant Operated W/O Proper Transmitter Calibr Prior to 910826,per NRC Info Notice 91-075.Caused by Inadequate Procedures.Calibr Procedures Will Be Revised
LIC-13-0001, License Amendment Request 13-01, Revision to Technical Specifications Sections 2.0.1 and 2.7 for Inoperable System, Subsystem or Component Due to Inoperable Power Source
05000267/LER-1995-006-02, :on 950903,TS Violation Occurred Due to Failure to Meet Minimum Degree of Redundancy.Caused by Equipment Malfunction.Completed Actions to Remove Channel PT-446 from Svc Per Procedure Owp
05000281/LER-1975-013-01, /01T:on 750720,channel of Change Protection Found Not Conservative.Caused by Failure of Cold Leg Low Level Amplifier.Amplifier Replaced & Channel Calibr