Note: This applies only to data entered prior to the 2003 ORPS Redesign.

Group 1 - Facility Condition

A. Nuclear Criticality Safety

Unusual Occurrence

Violation of the double contingency criticality specifications such that no valid controls are available to prevent a criticality accident.

Off-Normal

Any nuclear criticality safety violation or infraction of procedures not covered by other reporting criteria. For example, violation of a single contingency such that only one valid criticality control remains in place.

B. Fires/Explosions

Unusual Occurrence

Any fire or explosion within primary confinement/containment boundaries of a nuclear facility.

Off-Normal

  1. Any fire or explosion not required to be reported as an Unusual Occurrence that activates a fire suppression system (e.g., halon discharge, sprinkler heads activating) or disrupts normal facility operations.
  2. An unplanned fire that takes longer than 10 minutes to extinguish following the arrival of fire protection personnel; this does not include fires that do not disrupt normal facility operations and which are in the initial or beginning stage that can be controlled or extinguished by portable fire extinguishers, Class II standpipe, or small hose systems without the need for protective clothing or breathing apparatus.

C. Safety Status Degradation

Unusual Occurrence

  1. Any violation or noncompliance of an approved Technical Safety Requirement (Technical Specification or Operational Safety Requirement) or other operational safety limit defined by the contractor/DOE.
  2. Discovery of an incorrectly derived Technical Safety Requirement (Technical Specification or Operational Safety Requirement) or other operational safety limit defined by the contractor/DOE.
  3. Any operation outside the authorization basis of the facility or process.
  4. Any occurrence that would prevent immediate facility or offsite emergency response capabilities.
  5. Discovery of an actual Unreviewed Safety Question (USQ) which reveals a currently existing inadequacy in the approved authorization basis.

Off-Normal

  1. Discovery of a condition that leads the facility operating personnel to limit facility operations, either self-imposed or due to the identification of a potential degradation of the authorization bases of a facility or process. This includes the discovery of analytical errors, omissions, or inadequacies that present the potential for a USQ.
  2. Discovery of a potential USQ that could affect the present or future operation of the facility. Routine USQ determinations due to planned system or operational modifications are not reportable under this criteria.

D. Loss of Control of Radioactive Material/Spread of Radioactive Contamination

Unusual Occurrence

  1. Identification of radioactive contamination offsite in excess of 100 times any of the surface contamination levels specified in DOE 5400.5, RADIATION PROTECTION OF THE PUBLIC AND THE ENVIRONMENT, Figure IV-1, that has not been previously identified and formally documented. For the first group listed in Figure IV- 1 (i.e., transuranics...) use the values specified in Table 1 (provided as Appendix B to this Manual) of the EH-412 memorandum "Application of DOE 5400.5 Requirements for Release and Control of Property Containing Residual Radioactive Material", dated November 17, 1995.
  2. Loss of accountability of a sealed source or identification of lost radioactive material that exceeds 100 times the quantities specified in DOE N 441.1, RADIOLOGICAL PROTECTION FOR DOE ACTIVITIES.
  3. Any fissile material in a process or nonprocess system outside primary confinement boundaries not designed or expected to accommodate such material.

Off-Normal

  1. Any unplanned spill of liquids in excess of one gallon contaminated with radioactive material in concentrations greater than five times the Derived Concentration Guide values listed in DOE 5400.5, Figure III-1.
  2. Identification of radioactive contamination outside a radiological area (as defined in 10 CFR 835, Occupational Radiation Protection) or radiological buffer area established for contamination control, but within a Controlled Area, in excess of 10 times the total contamination levels in 10 CFR 835, Appendix D. For tritium, until a total contamination value is specified by 10 CFR 835 Appendix D, report contaminations in excess of 10 times 10,000 dpm/100cm2.
  3. Identification of radioactive contamination onsite that is not located within a Controlled Area, Fixed Contamination Area, or Soil Contamination Area, and is in excess of two times the total contamination levels in 10 CFR 835, Occupational Radiation Protection, Appendix D. For tritium, until a total contamination value is specified by 10 CFR 835 Appendix D, report contaminations in excess of 2 times 10,000 dpm/100cm2.
  4. Identification of radioactive contamination offsite in excess of any of the surface contamination levels specified in DOE 5400.5, Figure IV-1, that has not been previously identified and formally documented. For the first group listed in Figure IV- 1 (i.e., transuranics...) use the values specified in Table 1 (provided as Appendix B to this Manual) of the EH-412 memorandum "Application of DOE 5400.5 Requirements for Release and Control of Property Containing Residual Radioactive Material", dated November 17, 1995.
  5. Loss of accountability of a sealed source or identification of lost radioactive material that exceeds ten times and is less than 100 times the quantities specified in DOE N 441.1, RADIOLOGICAL PROTECTION FOR DOE ACTIVITIES.
  6. Loss of accountability of a sealed source or identification of lost radioactive material that is one to ten times the quantities specified in DOE N 441.1, RADIOLOGICAL PROTECTION FOR DOE ACTIVITIES.

E. Safety Structure/System/Component Degradation

Unusual Occurrence

Performance degradation of any Safety Class Structure, System, or Component (SSC) that prevents satisfactory performance of its design function when it is required to be operable or in operation.

Off-Normal

  1. Performance degradation of any Safety Class SSC that prevents satisfactory performance of its design function when it is not required to be operable or in operation.
  2. Performance degradation of any nuclear or nonnuclear Safety Significant SSC that prevents satisfactory performance of its design function when it is required to be operable or in operation.

F. Violation/Inadequate Procedures

Unusual Occurrence

  1. Maintenance performed on Safety Class SSC without meeting the required plant conditions for nonavailability resulting in a performance degradation.
  2. Incorrect maintenance (including calibration) on or unauthorized modifications to Safety Class SSC that was required to be operable or in operation and results in a performance degradation.

Off-Normal

  1. Any violation resulting in actual equipment damage in excess of $10,000.
  2. Use of inadequate procedures or deviations from written procedures that result in adverse effects on performance, safety, or reliability.
  3. Incorrect maintenance (including calibration) on or unauthorized modifications to Safety Significant SSC required to be operable or in operation.

G. Oversight Activities

Unusual Occurrence

Any internal/external oversight activity discovering unsatisfactory operation, testing, maintenance, or modification of any Safety Class SSC that is required to be operable or in operation.

Off-Normal

Any internal/external oversight activity discovering unsatisfactory operation, testing, maintenance, or modification of any Safety Significant SSC required to be operable or in operation.

H. Operations

This section should be augmented to include specific events that interfere with the safe, efficient, and productive operation of the facility, system, or process as approved by DOE. Each facility should conduct a comprehensive assessment to identify the facility's unique potential events.

Unusual Occurrence

  1. Actuation of Safety Class SSC or their alarms resulting from an actual unsafe condition. Inadvertent alarms are not required to be reported unless an actuation of a Safety Class SSC occurs and the actuation is considered significant as defined by the approved facility procedures. Actuation of continuous air monitoring systems identified as Safety Class equipment do not have to be reported if their actuation was found to be due to radon-thoron effects on the system or their actuation is expected due to maintenance tasks and other planned operations in the facility where the potential for release of radioactivity is anticipated to occur and the workers are appropriately protected.
  2. Loss of incoming alternating current power and failure of any backup emergency power system to operate, when the backup emergency power system supplies power to a Safety Class SSC.
  3. Weather conditions/natural phenomenon causing serious disruption of facility activities.
  4. Loss of process ventilation system serving a confinement function, which results in the loss of confinement.
  5. Any facility evacuation (excluding office space) in response to an actual occurrence, not including a precautionary evacuation for an event that can be controlled and mitigated by employees or maintenance personnel assigned to the affected facility or activity.

Off-Normal

  1. Any unplanned and unexpected change in a process condition or variable adversely affecting safety, security, environment, or health protection performance sufficient to require termination of a procedure in a reactor or nonreactor facility.
  2. Any unplanned electrical outages or unexpected consequences from a planned outage which seriously disrupt normal operations of a facility and/or may prevent the facility from meeting approved operating goals.
  3. Any unplanned outages of service systems (i.e., cooling water, steam, phones, communication systems, etc.) or unexpected consequences from a planned outage which: a) disrupt normal operations for one week or longer, and b)which adversely affect safety, security, environment or health protection performance.
  4. Loss of any process ventilation system serving a confinement function which does not result in the loss of confinement.
  5. Actuation of Safety Significant SSC or their alarms resulting from an actual unsafe condition. Inadvertent alarms are not required to be reported. Actuation of continuous air monitoring systems identified as Safety Significant equipment does not have to be reported if their actuation was found to be due to radon-thoron effects on the system or their actuation is expected due to maintenance tasks and other planned operations in the facility where the potential for release of radioactivity is anticipated to occur and the workers are appropriately protected.

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