IP 71111.01

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

NRC Inspection Procedures - IP 71111.01

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 05000413/2025002	Catawba	14 August 2025
IR 05000254/2025002	Quad Cities	14 August 2025
IR 05000321/2025002	Hatch	14 August 2025
IR 05000390/2025002	Watts Bar	13 August 2025
IR 05000220/2025002	Nine Mile Point	13 August 2025
IR 05000454/2025002	Byron	13 August 2025
IR 05000282/2025002	Prairie Island	13 August 2025
IR 05000336/2025002	Millstone	12 August 2025
IR 05000373/2025002	LaSalle	11 August 2025
IR 05000317/2025002	Calvert Cliffs	11 August 2025

Findings
[list of findings]

	Quarter	Site	Title
05000416/FIN-2018002-01	2018Q2	Grand Gulf	Failure to Institute Effective Corrective Action to Preclude Repetition
05000313/FIN-2018001-01	2018Q1	Arkansas Nuclear	Failure to Establish Adequate Criteria for Flood Seal Testing
05000395/FIN-2017004-01	2017Q4	Summer	Failure to Accomplish Station Procedures for Severe Weather
05000259/FIN-2017003-01	2017Q3	Browns Ferry	Degraded EDG Flood Door Seals
05000382/FIN-2017002-01	2017Q2	Waterford	Failure to Prepare the Site for Impending Adverse Weather
05000336/FIN-2017001-01	2017Q1	Millstone	Failure to Maintain CST Temperature in Accordance with Procedural Requirements
05000390/FIN-2017001-01	2017Q1	Watts Bar	Failure to Maintain the Abnormal Operating Instruction for Tornados
05000410/FIN-2016002-01	2016Q2	Nine Mile Point	Ineffective Corrective Action Results in Water Intrusion to Battery Switchgear Room
05000461/FIN-2016002-01	2016Q2	Clinton	Material Unsecure in the Secured Material Zone
05000280/FIN-2016001-01	2016Q1	Surry	Failure to Perform a 10 CFR 50.59 Evaluation for Blocking Ventilation to Main Steam Valve Houses

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NRC Inspection Procedure