INES Levels
INES N/A
INES 0
INES 1
INES 2
INES 3
INES 4
INES 5
INES 6
INES 7

INES 1: Anomaly

Impact on Defence-in-Depth
  • Overexposure of a member of the public in excess of statutory ­annual limits.
  • Minor problems with safety components with significant defence-in-depth remaining.
  • Low activity lost or stolen radioactive source, device or transport package.
(Arrangements for reporting minor events to the public differ from country to country. Also, it is difficult to ensure precise consistency in rating events between INES Level-1 and Below scale/Level-0)
Legenda & explanation
date title location 
1995-05-14SPURIOUS OPENING OF REACTOR COOLANT LIQUID RELIEF VALVECanadaBRUCE-5
1995-05-28ROUTINE SURVEILLANCE REVEALS: STEAM GENERATOR SAFETY VALVES OPEN AT HIGHER PRESSURE THAN SPECIFIED AT THE RINGHALS 2. 3 AND 4 PWRSSwedenRINGHALS-2
1995-06-02TURBINE/REACTOR TRIP CAUSED BY AN ERROR IN THE EH CONTROL SYSTEM OF THE TURBINE GENERATORSloveniaKRSKO
1995-06-07PERSONNEL IRRADIATION IN A THERMAL POWER PLANT DURING MAINTENANCE WORKSRomaniaTPP BORZESTI
1995-07-10UNINTENTIONAL RELEASE TO THE SEA OF A MINOR AMOUNT OF SLIGHTLYCONTAMINATED WATERSwedenBARSEBECK-1
1995-07-15ONE CLOSED VALVE IN THE CONTAINMENT PRESSURE RELIEF LINE TO THE ATMOSPHERE AND TWO CLOSED VALVES IN THE VENTING LINE TO THE EMERGENCY FILTERSwedenFORSMARK-2
1995-08-26DESIGN DEFICIENCIES IN DIESEL GENERATORS FOUND DURING EXTENDED TESTINGSwedenOSKARSHAMN-1
1995-10-31HIGH RADIATION LEVELS IN REACTOR BUILDINGUnited States of AmericaLASALLE-1
1995-11-10Non-closure of primary steam isolating valves on auto during total loss of power incidentIndiaTARAPUR-1
1995-11-15DEVIATION FROM TECHNICAL SPECIFICATIONSSwedenRINGHALS-4
1995-11-22AUTOMATIC REACTOR UNLOADING DUE TO SPURIOUS OPENINGS OF VALVES BETWEEN A GROUP OF ECCS PRESSURIZED TANKS AND REACTORLithuaniaIGNALINA-2
1995-11-30OVEREXPOSURE OF OPERATOR DURING CALIBRATION OF IN-CORE SENSORSLithuaniaIGNALINA-2
1995-12-08Secondary sodium leakage in the prototype fast breeder reactor MonjuJapanMONJU
1996-01-21A PART OF THE RESIDUAL HEAT REMOVAL SYSTEM - THE AUXILIARY CONDENSER - TEMPORARILY NOT AVAILABLESwedenOSKARSHAMN-1
1996-01-31Reactor scram followed by the actuation of safety valve in the reactor primary circuitRussian FederationNIIAR Inst., Dimitrovgrad
1996-02-06LOSS OF OFFSITE POWER AND SAFETY INJECTIONUnited States of AmericaCATAWBA-2
1996-02-28Internal Contamination of Several Workers While Cleaning up EquipmentSpainVANDELLOS-1
1996-03-04FAILURE OF A CONTAINMENT ISOLATION VALVE AT A PERIODICAL TESTSwedenOSKARSHAMN-1
1996-04-15Penetration of primary coolant and low level contamination of hermetic boxSlovakiaBOHUNICE-4
1996-04-16Violation of limits and conditions - a late test of emergency core cooling system pumpsCzech RepublicDUKOVANY-2
1996-04-19ECI impairment due to check valve failure resulting in forced outage of Pickering stationCanadaPICKERING-1
1996-04-21Spurious signal for actuation of the ESFAS caused by human errorCzech RepublicDUKOVANY-3
1996-04-24Radioactive contamination at the Unit N3UkraineCHERNOBYL-3
1996-04-30Exceeding allowed maximum primary coolant temperature during planned outageUkraineKHMELNITSKI-1
1996-05-15Small leak of radioactive water from auxiliary building no. 2BulgariaKOZLODUY-3
1996-05-16Disturbance of forced reactor coolant circulation in cold shutdown conditionBulgariaKOZLODUY-5
1996-05-24Failure to replace horizontal flux detector shielding after maintenanceCanadaPOINT LEPREAU
1996-06-12Degraded pressure subpression (PS) functionSwedenBARSEBECK-2
1996-07-08Violation of limts and conditions - a late test of spray pumpsCzech RepublicDUKOVANY-4
1996-07-12Degradation of essential service water (ES'W) for a year due to a defficient design modificationSpainASCO-1