IP 71153, Event Followup

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Inspection Procedure

NRC Inspection Procedures - IP 71153

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 71153, Event Followup

Inspection Reports
[list of inspection reports]

	Site	Start date
IR 05000382/2025402	Waterford	26 August 2025
IR 05000321/2025002	Hatch	14 August 2025
IR 05000413/2025002	Catawba	14 August 2025
IR 05000254/2025002	Quad Cities	14 August 2025
IR 05000416/2025002	Grand Gulf	13 August 2025
IR 05000220/2025002	Nine Mile Point	13 August 2025
IR 05000336/2025002	Millstone	12 August 2025
IR 05000458/2025002	River Bend	12 August 2025
IR 05000237/2025002	Dresden	12 August 2025
IR 05000498/2025002	South Texas 07201041	12 August 2025

Findings
[list of findings]

	Quarter	Site	Title
05000296/FIN-2018012-01	2018Q3	Browns Ferry	Failure to correct an inoperable 250V Shutdown Board Battery Charger
05000528/FIN-2018008-03	2018Q3	Palo Verde	Licensee-Identified Violation
05000528/FIN-2018008-02	2018Q3	Palo Verde	Licensee-Identified Violation
05000373/FIN-2018003-08	2018Q3	LaSalle	Failure to Implement Engineering Change Results in Reactor Coolant Boundary Leakage
05000390/FIN-2018003-07	2018Q3	Watts Bar	Licensee-Identified Violation
05000313/FIN-2018003-06	2018Q3	Arkansas Nuclear	Reactor Power Transient Caused by the Turbine Bypass Valve Failing Open
05000390/FIN-2018003-06	2018Q3	Watts Bar	Licensee-Identified Violation
05000313/FIN-2018003-05	2018Q3	Arkansas Nuclear	Failure to Maintain Main Feedwater Pump B Discharge Pressure in Band Caused a Reactor Trip
05000354/FIN-2018003-05	2018Q3	Hope Creek	Minor Violation
05000391/FIN-2018003-04	2018Q3	Watts Bar	Inadequate Sensitive Equipment Control Results in Unit 2 Reactor Trip on April 12, 2018

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NRC Inspection Procedure