10 CFR 50.69(g)

(g) Reporting. The licensee shall submit a licensee event report under § 50.73(b) for any event or condition that prevented, or would have prevented, a RISC-1 or RISC-2 SSC from performing a safety significant function.

What form does the reporting use?

Checkbox located on LER form NRC Form 366

NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report

Main article: NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report

Licensees reporting under 10 CFR 50.72 and 10 CFR 50.73 for events involving design basis functions that are also associated with Risk-Informed Safety Class (RISC)-1 or RISC-2 structures, systems, and components (SSCs) for licensees that receive NRC authority to use 10 CFR 50.69, “Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors,” are also required to report under 10 CFR 50.69(g) for events involving RISC-1 or RISC-2 SSCs that perform functions credited for beyond design basis mitigation. Reporting events involving RISC-1 or RISC-2 that perform credited beyond design basis functions is distinct from, and in addition to, events involving credited design basis functions for RISC-1 or RISC-2 SSCs. The criteria in 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) do not apply to RISC-3 or RISC-4 SSCs for licensees that are authorized to use 10 CFR 50.69.

IP 37060

The inspector should review licensee event reports for the selected SSCs to verify the licensee is appropriately reporting equipment deficiencies and events consistent with the requirement of 10 CFR 50.69(g). For RISC-1 and -2 SSCs confirm the licensee is implementing reporting requirements not required by 10 CFR 50.69(g), i.e., 10 CFR part 21, 50.72, and 50.73 reporting requirements. Only RISC-3 and RISC-4 SSCs are excluded from 10 CFR part 21, 50.72, and 50.73 reporting requirements.

Title 10 CFR 50.69(g) provides a new reporting requirement applicable to events or conditions that prevented, or would have prevented, a RISC-1 or RISC-2 SSC from performing a safety significant function. Most events involving these SSCs will meet existing 10 CFR 50.72 and 73 reporting criteria. However, it is possible for events and conditions to arise that impact whether RISC-1 or RISC-2 SSCs would perform beyond design-basis functions consistent with the performance capability credited in the categorization process.

v t e Reporting criterion
10 CFR 50.69#g
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 50.69(g), RISC-1 or RISC-2 categorized components 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
[Table view]
NUREG-1022, Event Reporting Guidelines for 10 CFR 50.72 and 10 CFR 50.73

10 CFR 50.69(g)

What form does the reporting use?

NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report

IP 37060

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