Individuals use a consistent, systematic approach to make decisions. Risk insights are incorporated as appropriate.
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ONS-2017-006, Emergency Plan Revision 2016-003
ONS-2017-001, Submittal of Emergency Plan Program Procedure HP/O/B/1009/001 Rev 045
ONS-2017-030, Emergency Plan Revision 2017-002. Part 2 of 2
ONS-2017-071, Emergency Plan Revision 2017-003, Figure P1
MNS-17-039, Emergency Implementing Procedures Plan, Revision 17-1
NRC 2012-0051, Response to Inspection Report 05000266/2012503 and 05000301/2012503, Emergency Preparedness Preliminary White Finding
MNS-14-058, Inservice Inspection Report, End of Cycle 22 Refueling Outage
RA-13-120, Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process
ONS-2017-030, Oconee Nuclear Station Emergency Plan Revision 2017-002. Part 1 of 2
RA-10-065, Response to Draft Request for Additional Information License Amendment Request Regarding Relocation of Selected Technical Specification Surveillance Frequencies to a Licensee Controlled Document
RA-09-065, Application for Technical Specifications Change Regarding Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (Adoption of TSTF-425, Rev 3)
CNS-16-069, Submittal of Emergency Plan, Revision 16-2
ONS-2016-085, Submittal of Emergency Plan Revision 2016-002
RA-19-0434, Emergency Plan, Revision 19-05
ONS-2018-006, Summary of Changes to Emergency Plan
ND-19-1095, Emergency Action Levels and Basis
BSEP-98-0015, Provides Plans for re-inspection of Core Shroud for Unit 1. Reinspections Planned for Upcoming Refueling Outage 11,which Is Presently Scheduled to Begin on 980425,per GL 94-03
JAFP-85-0299, 1984 Radiological Environ Surveillance Rept
SECY-22-0028, Enclosure 5 - NRC Response to Public Comments on Appendices F-I for NUREG-BR-0058
RA-20-0122, Emergency Plan Revision 20-03
RA-23-0063, Notification of Deviation from BWRVIP Guidelines
IMC 0310, Aspects within the Cross-Cutting Areas
05000259/LER-1989-015-01, :on 890627,both Doors of Unit 1 Airlock Opened Simultaneously for 5 Constituting Breach of Secondary Containment.Caused by Weld Failure on Door Lock Mechanisms. Bracket Reattached & Door Operation Verified
05000344/LER-1987-010, :on 870511,power to 230-kV Bus V-82 Lost Due to Inadvertent Actuation of Bus Differential Relays.Caused by Failure of Meter & Relaying Technicians to Bypass Bus Differential Relays.Power Restored
05000413/LER-1985-052, :on 850814,boron Concentration of Upper Head Injection Not Verified Every 6 H as Required by Upper Head Injection Operating Procedure.Caused by Personnel Error. Boron Concentration Sample Ordered
05000413/LER-1988-022, :on 880811,discovered Failure to Retest Containment Isolation Valve Following Installation to Verify That Valve Properly Closed.Caused by Failure to Follow Appropriate Procedures.Training Initiated
05000302/LER-1985-020, :on 851009,both MSIVs from Steam Generator B Automatically Closed Due to Spurious Emergency Feedwater Initiation & Control Actuation.Caused by Low Steam Generator Level Indication.Trip Module Replaced
05000387/LER-1985-026, :on 850624,during Testing of HPCI Sys,Oil Leak Discovered on HPCI Steam Stop Valve Oil Supply Flange. Caused by Loose Nuts Securing Stop Valve Oil Supply Flange. Nuts Torqued & Leak Test Performed
05000313/LER-1996-007-02, :on 960912,automatic Reactor Trip & Emergency Feedwater Sys Actuation Occurred When Two RCP Motors de-energized.Caused by Defective Fuse in Electrical Bus Undervoltage Circuit.Fuse Replaced
05000254/LER-1996-020-01, :on 960907,CR Emergency Filtration Sys Declared Inoperable.Caused by Operator Knowledge Weakness.Operators Declared CR Emergency Filtration Sys Inoperable & Entered 14-day LCO
L-96-503, Requests That Annual Fees for FY97 for SNM-1067 Be Assessed Per 10CFR171.16-1,Category 14
05000321/LER-1985-002, :on 850113,safety Relief Valve B Failed to Open.Caused by Open Links.Links Closed
LD-92-024, Forwards Response to NRC Request for Addl Info on Electrical Distribution Sys Design,In Ref to NRC Review of CESSAR
05000250/LER-1984-014, :on 840424,turbine Operator Taking Standby Static Inverter a Out of Svc Erroneously Opened Output Breaker of Adjacent Static Inverter,Causing Reactor Trip. Plant Stabilized & Instruments Replaced
05000416/LER-1991-005-03, :on 910617,fault Occurred on B-phase of Breaker J5232,resulting in Loss of Power to Two balance-of-plant & ESF Buses.Caused by Generation of Main Turbine Trip Signal. High Pressure Tanks Replaced
ST-HL-AE-5780, Forwards Response to 970912 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. W/38 Oversize Drawings
LIC-95-0018, Forwards OPPD Annual Accounting for Period of Jan-Dec 1994, as Required by FCS Decommissioning Funding Plan Trust Agreement
05000254/LER-1994-001-04, :on 940102,inadvertent Insertion of Control Rod H-1 from Position 48 to 14 Occurred During Instrument Maint Surveillance.Cause Not Determined.Crd H-1 Inserted Into Position 00 & HCU Rebuilt
05000353/LER-1993-002, :on 930124,discovered That EDG Inoperable Since 930119 Due to Improperly Connected Wires in Circuit Breaker. Wires Restored to Proper Position & Tested Satisfactorily. Procedural & Training Changes Also Implemented
05000285/LER-1990-002, :on 900226,inadvertent Actuation of Containment Isolation Actuation Signal Occurred W/Plant in Refueling Shutdown Condition.Caused by Accidental Actuation of Lockout Relay by Craftsman.Mod Procedure Revised
05000285/LER-1990-008, :on 900306,electrician Was Connecting Leads as Part of Control Room Ventilation Mod & Caused Short Circuit While Working on Energized Circuit.Caused by Electrician Error.Enhanced General Guidelines Issued
05000278/LER-1990-001-03, :on 900108,HPCI Sys Declared Inoperable During Surveillance Testing When Start Time Exceeded 25 S.Caused by Inadequate Calibr Procedure Which Allowed Setting of 18 S. Ramp Generator & Signal Converter Replaced
BSEP-90-0128, Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989
W3P81-2041, Forwards Info to Close Out SER Items Re Steam Voiding in Reactor Vessel Analysis,Loss of Offsite Power or Tripping of Reactor Coolant Pumps During Main Steam Line Break & Clarification of Transient Anaysis W/Potential Fuel Damage
ST-HL-AE-3126, Application for Amends to Licenses NPF-76 & NPF-80,deleting Surveillance Requirement 4.5.1.1.d to Require That Each Safety Injection Accumulator Isolation Valve Open Automatically When RCS Pressure Exceeds P-11 Setpoint
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
NUREG-1433, Part 1- Edwin I. Hatch, Units 1 & 2, License Amendments, Replace Current Technical Specification & Associated Bases
NRC-13-0002, Proposed License Amendment to Revise the Fermi 2 Licensing Bases for Protection from Tornado-Generated Missiles
RA-21-0105, Emergency Plan Revision 21-1 and Associated 10 CFR 50.54(q) Review Forms
NRC Inspection Manual 0310, Components Within the Cross-Cutting Areas
HL-5579, Forwards Proprietary & non-proprietary Response to 980210 RAI Re License Amend Request to Increase Authorized Max Power Level to 2,763 Mwt.Topical Rept NEDO-32749 Encl. Proprietary Info Withheld
TSTF-23-02, TSTF Response to Request for Additional Information on TSTF-592,Revise Automatic Depressurization System (ADS) Instrumentation Requirements and Submission of Revision 1