10 CFR 50.73(a)(1), Submit an LER

General Reporting requirement to Submit an LER OR in the case of an invalid actuation of plant equipment (specific list see 10 CFR 50.73(a)(2)(iv)) a telephone call can be made in lieu of the LER. Most commonly know as the Invalid Actuation reporting criteria.

Unless otherwise specified, this part of the rule requires reporting of an event if it occurred within 3 years prior to discovery, regardless of the plant mode or power level and regardless of the significance of the structure, system, or component that initiated the event. In the case of an invalid actuation reported under 10 CFR 50.73(a)(2)(iv), the licensee may, at its option, provide a telephone notification to the NRC Operations Center within 60 days after discovery of the event instead of submitting a written LER.

NoteNote: This is used as a reporting criteria when a 60-day ENS report is made due to invalid actuation of systems

System Actuation Reporting Summary

	Valid	Invalid
Moved	ENS + LER	LER (as 60 day ENS)
Not moved	ENS + LER	None

4-hour (ENS)

While Critical or RPS (ie Scram)

8-hour (ENS)

10 CFR 50.72(b)(3)(iv)(A), System Actuation

60-day (LER)

10 CFR 50.73(a)(2)(iv)(A), System Actuation

60-day (ENS)

Allowance for invalid signals which actuated a system

10 CFR 50.73(a)(1), Submit an LER

System actuation list

System Actuation Reporting contains a list of applicable systems

Both list include:

(1) Reactor protection system (RPS) including: Reactor scram and reactor trip.

(2) General containment isolation signals affecting containment isolation valves in more than one system or multiple main steam isolation valves (MSIVs).

(3) Emergency core cooling systems (ECCS) for pressurized water reactors (PWRs) including: High-head, intermediate-head, and low-head injection systems and the low pressure injection function of residual (decay) heat removal systems.

(4) ECCS for boiling water reactors (BWRs) including: High-pressure and low-pressure core spray systems; high-pressure coolant injection system; low pressure injection function of the residual heat removal system.

(5) BWR reactor core isolation cooling system; isolation condenser system; and feedwater coolant injection system.

(6) PWR feedwater system or emergency feedwater system.

(7) Containment heat removal and depressurization systems, including containment spray and fan cooler systems.

(8) Emergency ac electrical power systems, including: Emergency diesel generators (EDGs); hydroelectric facilities used in lieu of EDGs at the Oconee Station; and BWR dedicated Division 3 EDGs.

Only 50.73: (9) Emergency service water systems that do not normally run and that serve as ultimate heat sinks.

v t e Reporting criterion
10 CFR 50.73#a1
10 CFR 50.72 10 CFR 50.72(a)(1)(i), Emergency Class Declaration 10 CFR 50.72(b)(1), 50.54(x) TS Deviation 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(2)(iv)(A), ECCS System Actuation 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.72(b)(3)(iv)(A), System Actuation 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.72(b)(3)(v), Loss of Safety Function 10 CFR 50.72(b)(3)(xii), Transport of a Contaminated Person Offsite 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness 10 CFR 50.73 10 CFR 50.73(a)(1), Submit an LER 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)(C), 50.54(x) TS Deviation 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 72 10 CFR 72.75(b)(2), Offsite Notification 10 CFR 72.75(c)(1), ISFSI Defect 10 CFR 72.75(c)(2), ISFSI Degradation 10 CFR 72.75(d)(1), ISFSI Safety System Functional Failure 10 CFR 73 10 CFR 73.71(b)(1), Safeguards Event 10 CFR 73.77, Cyber security event notifications Fitness for Duty 10 CFR 26.719, Reporting requirements Blind Performance Test 10 CFR 26.719(c)(2), false positive 10 CFR 26.719(c)(3), false negative 10 CFR 26.719(c)(1), 30 day report Other 10 CFR 21.21(a)(2), Interim Report for Comply or Defect in Component 10 CFR 21.21(d)(3)(i), Failure to Comply or Defect 10 CFR 70.50(a), SNM protective actions prevented 10 CFR 70.50(b)(1), SNM unplanned contamination 10 CFR 70.50(b)(2), SNM equipment failure 10 CFR 70.50(b)(3), SNM medical treatment 10 CFR 70.50(b)(4), SNM fire or explosion All reporting criteria
WEEKMONTHYEAR [Table view]
NUREG-1022, Event Reporting Guidelines for 10 CFR 50.72 and 10 CFR 50.73