IP 71111.02

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

NRC Inspection Procedures - IP 71111.02

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 05000285/2014009	Fort Calhoun	18 September 2014
IR 05000395/2008007	Summer	7 January 2009
IR 05000275/2008004	Diablo Canyon	3 November 2008
IR 05000382/2008004	Waterford	31 October 2008
IR 05000272/2008003	Salem	5 August 2008
IR 05000259/2007007	Browns Ferry	25 January 2008
IR 05000266/2007007	Point Beach	22 January 2008
IR 05000272/2007004	Salem	9 November 2007
IR 05000354/2007004	Hope Creek	9 November 2007
IR 05000275/2007004	Diablo Canyon	26 October 2007

Findings
[list of findings]

	Quarter	Site	Title
05000482/FIN-2018002-01	2018Q2	Wolf Creek	Announcement of an NRC Inspectors Presence by Station Personnel
05000313/FIN-2018002-01	2018Q2	Arkansas Nuclear	Failure to Implement Procedural Guidance to Close Spent Fuel Pool Cooler Outlet Crosstie Valve
05000316/FIN-2018002-01	2018Q2	Cook	Steam Dump Closure Caused by Human Error
05000220/FIN-2018001-01	2018Q1	Nine Mile Point	Potential Failure to Submit an 8-Hour Event Notification for a Valid Actuation of HPC
05000315/FIN-2018001-02	2018Q1	Cook	Operation of Letdown System Leads to Voiding and Subsequent Relief Valve Lift
05000323/FIN-2018001-01	2018Q1	Diablo Canyon	Improper Troubleshooting Results in Reactor Trip Signal and Loss of Source Range Nuclear Instrument Power
05000423/FIN-2017004-01	2017Q4	Millstone	Failure to Maintain RCS Pressure during Solid Plant Cooldown
05000315/FIN-2017004-02	2017Q4	Cook	Unit 1 Letdown System Safety Valve Lift During Preparations for Cooldown
05000364/FIN-2017004-02	2017Q4	Farley	Failure to maintainan operable Oil Collection System on RCP 2B
05000272/FIN-2017004-02	2017Q4	Salem	Inadequate Reactor Vessel Head Removal Procedure

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NRC Inspection Procedure