IP 71111.18

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Inspection Procedure
IP 71111, Reactor Safety-Initiating Events, Mitigating Systems, Barrier Integrity

NRC Inspection Procedures - IP 71111.18

IP 37060, 10 CFR 50.69 Risk-Informed Category and Treatment of Structures, Systems, and Components 10 CFR 50.69 Risk-Informed Category and Treatment of Structures
IP 43004
IP 60853
IP 60854 (1)
IP 60855 (1) Operation of an Independent Spent Fuel Storage Installation
IP 60857, Review of 10 CFR 72.48 Evaluations Review of 10 CFR 72.48 Evaluations
IP 60858, Away-From-Reactor Independent Spent Fuel Storage Installation Inspection Guidance Away-From-Reactor Independent Spent Fuel Storage Installation Inspection Guidance
IP 71002, License Renewal Inspection License Renewal Inspection
IP 71003
IP 71004

IP 71111 (27) Reactor Safety-Initiating Events
IP 71114 (7) Reactor Safety Emergency Preparedness
IP 71124 (8) Radiation Safety-Public and Occupational
IP 71130 (10) Security
IP 71150
IP 71151
IP 71152, Problem Identification and Resolution (PI&R) Problem Identification and Resolution (PI&R)
IP 71152A
IP 71152S, Semiannual Trend Review Semiannual Trend Review
IP 71153, Event Followup Event Followup

IP 92702
IP 92709
IP 92722
IP 92723
IP 93800
IP 93812
IP 95001, Supplemental Inspection Response to Action Matrix Column 2 (Regulatory Response) Inputs Supplemental Inspection Response to Action Matrix Column 2 (Regulatory Response) Inputs
IP 95002
IP 95003
TI 2201/004

TI 2515/177
TI 2515/183
TI 2515/191, Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication, Staffing, Multi-Unit Dose Assessment Plans Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication
TI 2515/192
TI 2515/193, Inspection of the Implementation of EA-13-109: Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Inspection of the Implementation of EA-13-109: Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions
TI 2515/194
TI 2515/76
TI 2800/041

IP 71111, Reactor Safety-Initiating Events, Mitigating Systems, Barrier Integrity

Inspection Reports
[list of inspection reports]

	Site	Start date
IR 05000416/2025002	Grand Gulf	13 August 2025
IR 05000390/2025002	Watts Bar	13 August 2025
IR 05000220/2025002	Nine Mile Point	13 August 2025
IR 05000336/2025002	Millstone	12 August 2025
IR 05000298/2025002	Cooper	11 August 2025
IR 05000266/2025002	Point Beach	11 August 2025
IR 05000397/2025002	Columbia	11 August 2025
IR 05000250/2025002	Turkey Point	7 August 2025
IR 05000440/2025002	Perry	7 August 2025
IR 05000382/2025002	Waterford	6 August 2025

Findings
[list of findings]

	Quarter	Site	Title
05000266/FIN-2018003-02	2018Q3	Point Beach	Licensee-Identified Violation
05000315/FIN-2018002-03	2018Q2	Cook	Licensee-Identified Violation
05000272/FIN-2018002-01	2018Q2	Salem	Inadequate Design Change for Service Water Pumps
05000373/FIN-2018002-01	2018Q2	LaSalle	Failure to Implement a Preventative Maintenance Strategy for Residual Heat Removal Service Water Pump Shorting Relays
05000298/FIN-2018002-01	2018Q2	Cooper	Failure to Maintain Alarm Procedure for Service Water Booster Pump Ventilation Manual Actions
05000458/FIN-2018012-06	2018Q2	River Bend	Failure to Provide Adequate Procedures for Post-Scram Recovery
05000458/FIN-2018012-07	2018Q2	River Bend	Failure to Perform 10 CFR 50.59 Evaluation for Main Feedwater System Sparger Nozzle Damage
05000410/FIN-2018001-02	2018Q1	Nine Mile Point	Potential Inadequate 50.59 Evaluation for TS 3.3.1.1 Bases Change
05000282/FIN-2018001-02	2018Q1	Prairie Island	Questions Regarding the Corrective Action and Aging Management Programs Following the Discovery of 122 DDCLP FOST Vent Piping Degradation
05000390/FIN-2017004-02	2017Q4	Watts Bar	Inadequate Procedure for Temporary Configuration Changes

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NRC Inspection Procedure