Traditional Enforcement Violation

A Traditional Enforcement Violation (TEV) is a type of NRC finding used in lieu of using the normal Reactor Oversight Process; most typically for not performing a regulatory process properly (eg. Reportabilities).

Compare the violation with examples in the Enforcement Policy to determine if the violation rises to SL-IV or above and thus constitutes a non-minor traditional enforcement violation.

NoteNote: In addition, Traditional enforcement violations are not assessed for cross-cutting aspects.

impacted the regulatory process

Examples:

• Failure to provide complete and accurate information
• Failure to receive prior NRC approval for changes in licensed activities
• Failure to notify the NRC of changes in licensed activities
• Failure to perform 10 CFR 50.59 analyses
• Reporting failure, etc.

actual safety consequences

Examples:

• Actual onsite or offsite releases of radiation exceeding regulatory limits
• Onsite or offsite radiation exposures exceeding regulatory limits
• Accidental criticalities
• Core damage
• Loss of significant safety barriers
• Loss of control of radiological material exceeding regulatory limits for public dose
• Radiological emergencies

SL-IV or greater violation with no associated performance deficiency

Circumstances may arise where enforcement discretion should be considered or exercised to either escalate or mitigate enforcement sanctions or otherwise refrain from taking enforcement action for a particular violation. The Enforcement Policy and Enforcement Manual describe situations where this may apply. Specific circumstances may include:

• Specific cases for which temporary Enforcement Guidance Memoranda prescribes enforcement discretion
• Non-minor violations absent a performance deficiency
• Violations identified during extended shutdowns or work stoppages
• Violations involving old design issues
• Violations identified because of previous enforcement action
• Violations involving certain discrimination issues

For example: ISFSI facilities are not subject to the SDP and are not subject to the Reactor Oversight Process, so violations identified at ISFSIs are assessed using traditional enforcement.

Additional Inspection

A TEV falls under three categories: actual consequences, willfulness, or the potential for impacting the regulatory process.

IP 92723, 3 Level IV TEV

This procedure provides the follow up for three or more Severity Level (SL) IV violations when all occur within a single traditional enforcement area of willfulness, impeding the regulatory process or actual consequence during any 12-month period.

IP 92722, 2 Level III or a I or II TEV

This procedure provides the follow up response for the following:

• Any Severity Level I and II violation in the traditional enforcement areas of willfulness, impeding the regulatory process or actual consequence.
• Two or more Severity Level III violations in the traditional enforcement areas of willfulness, impeding the regulatory process or actual consequence in any 12 month period.

List

	Significance	Site	Title
05000275/FIN-2018404-03	Severity level IV	Diablo Canyon	Licensee-Identified Violation
05000528/FIN-2018008-03	Severity level IV	Palo Verde	Licensee-Identified Violation
05000390/FIN-2018003-06	Severity level IV	Watts Bar	Licensee-Identified Violation
05000313/FIN-2018003-03	Severity level IV	Arkansas Nuclear	Failure to Provide Complete and Accurate Information in a License Amendment Request to Change Emergency Action Level Requirements
05000287/FIN-2018003-03	Severity level IV	Oconee	Main Steam Relief Valve As-Found Lift Pressure Prohibited by Technical Specifications
05000482/FIN-2018003-02	Severity level IV	Wolf Creek	Failure to Submit a Licensee Event Report for a Condition Prohibited by Technical Specifications
05000269/FIN-2018003-02	Severity level IV	Oconee	Failure to Make a 60 Day Notification of an Actuation of an Emergency AC Power Source
05000237/FIN-2018003-02	Severity level IV	Dresden	Licensee-Identified Violation
05000298/FIN-2018003-01	Severity level IV	Cooper	Failure to Provide Complete and Accurate Information in a License Amendment Request
05000369/FIN-2018003-01	Severity level IV	Mcguire McGuire	Failure to Adequately Document the Basis for a Change to the Emergency Plan
05000269/FIN-2018003-01	Severity level IV	Oconee	Failure to Maintain the Effectiveness of the Emergency Plan
05000348/FIN-2018003-01	Severity level IV	Farley	Unit 1 Pressurizer Safety Valve Lift Pressure Outside of Technical Specification Tolerance Band
05000296/FIN-2018003-01	Severity level IV	Browns Ferry	Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints
05000443/FIN-2018003-01	Severity level IV	Seabrook	Pressurizer Safety Valve Outside of Technical Specification Limits
05000446/FIN-2018011-01	Severity level III	Comanche Peak	Failure to Maintain a Quality Record Complete and Accurate in All Material Respects
05000266/FIN-2018003-01	Severity level IV	Point Beach	Failure to Perform Evaluations to Ensure that the Fabrication of Dry Cask Storage Systems Meets the Requirements of the Loading Certificate of Compliance
05000254/FIN-2018003-02	Severity level IV	Quad Cities	Failure to Follow Procedures for Forced Helium Dehydration of a Multipurpose Canister
05000333/FIN-2018411-02	Severity level IV	FitzPatrick	Security
05000348/FIN-2018014-02	Severity level IV	Farley	Failure to Provide Complete and Accurate Information Related to System Operator Rounds
05000348/FIN-2018014-01	Severity level IV	Farley	Failure to Complete System Operator Rounds as Required per Procedures
05000296/FIN-2018002-02	Severity level IV	Browns Ferry	Inoperable Residual Heat Removal (RHR) Pump Results in Condition Prohibited by Technical Specifications
05000269/FIN-2018002-02	Severity level IV	Oconee	Failure to Coordinate a No-later-than Arrival Time for the Shipment of a Category 2 Quantity of Radioactive Material
05000390/FIN-2018002-02	Severity level IV	Watts Bar	Licensee-Identified Violation
05000286/FIN-2018002-01	Severity level IV	Indian Point	Reactor Pressure Boundary Leakage Due to Weld Failure in Reactor Vessel Head Penetration #3
05000369/FIN-2018002-01	Severity level IV	McGuire	Licensee-Identified Violation
05000400/FIN-2018002-03	Severity level IV	Harris	Failure to Adequately Document Changes to the Emergency Plan
05000293/FIN-2018002-03	Severity level IV	Pilgrim	480V Bus B6 Auto Transfer Function Degraded Due to Time Delay Relay Failure
05000482/FIN-2018002-01	Severity level IV	Wolf Creek	Announcement of an NRC Inspectors Presence by Station Personnel
05000458/FIN-2018002-01	Severity level IV	River Bend	Failure to Correct Inadequate Technical Specification Pressure Temperature Curves
05000458/FIN-2018012-04	Severity level IV	River Bend	Failure to Submit a Licensee Event Report for a Manual Scram
05000458/FIN-2018012-07	Severity level IV	River Bend	Failure to Perform 10 CFR 50.59 Evaluation for Main Feedwater System Sparger Nozzle Damage
05000397/FIN-2018401-01	Severity level IV	Columbia	Security
05000254/FIN-2018001-01	Severity level IV	Quad Cities	Repeat Use of Written Exams During Licensed Operator Requalification Examinations
05000440/FIN-2018001-01	Severity level IV	Perry	Failure to Notify the NRC within 60 Days of a Condition Prohibited by Technical Specifications
05000219/FIN-2018001-01	Severity level IV	Oyster Creek	Untimely Licensee Event Report for Reportable Conditions Associated with the No. 2 Emergency Diesel Generator
05000382/FIN-2018001-01	Severity level IV	Waterford	Failure to Obtain NRC Staff Authorization Prior to Changing a Procedure that Impacts Implementation of Technical Specifications
05000498/FIN-2018001-04	Severity level IV	South Texas	Licensee-Identified Violation
05000397/FIN-2018401-02	Severity level IV	Columbia	Security
05000498/FIN-2018001-03	Severity level IV	South Texas	Licensee-Identified Violation
05000461/FIN-2017004-04	Severity level IV	Clinton	Failure to Perform an Evaluation in Accordance with 10 CFR 72.48 for Changes Made to the Time-to-Boil Calculation
05000331/FIN-2017004-02	Severity level IV	Duane Arnold	Failure to Evaluate Site Fire and Explosion Hazards in Accordance with 10 CFR 72.212(b) (6)
05000348/FIN-2017009-01	Severity level IV	Farley	Failure to Report a Condition Which was Prohibited by Technical Specifications
05000416/FIN-2017007-04	Severity level IV	Grand Gulf	Failure to Update the Final Safety Analys is Report
05000382/FIN-2017008-03	Severity level IV	Waterford	Two Examples of Failure to Submit and Receive Prior Authorization of Alternatives to ASME OM Code Leak Testing Requirements
05000341/FIN-2017003-01	Severity level IV	Fermi	Failure to Satisfy 10 CFR 50.73 Reporting Requirements for Primary Containment Isolation Valve Actuations
05000382/FIN-2017010-01	Severity level IV	Waterford	Failure to Evaluate Departures from Approved Methodologies for Reactor Vessel Fluence
05000498/FIN-2017010-02	Severity level IV	South Texas	Failure to Perform Required 50.54(q) Evaluations prior to Implementing Changes to the Emergency Plan
05000272/FIN-2017003-01	Severity level IV	Salem	Expiration of Periodic Inservice Testing of 14 Service Water Pump
05000346/FIN-2017003-04	Severity level IV	Davis Besse	Failure to Perform 10 CFR 50.59 Evaluation
05000397/FIN-2017003-02	Severity level IV	Columbia	Failure to Report Unplanned Valid Reactor Protection System Actuation
... further results