IP 93800: Difference between revisions

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Latest revision as of 08:37, 25 September 2017

Inspection Procedure

NRC Inspection Procedures - IP 93800

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

Inspection Reports
[list of inspection reports]

	Site	Start date
IR 05000313/2013011	Arkansas Nuclear	7 June 2013
IR 05000458/2012010	River Bend	23 November 2012
IR 05000361/2012010	San Onofre	9 November 2012
IR 05000458/2012009	River Bend	7 August 2012
IR 05000482/2012009	Wolf Creek	6 August 2012
IR 05000361/2012007	San Onofre	18 July 2012
IR 05000261/2010004	Robinson	12 November 2010
IR 05000261/2010009	Robinson	2 July 2010
IR 05000348/2007010	Farley	19 December 2007
IR 05000277/2007404	Peach Bottom	5 November 2007

Findings
[list of findings]

	Quarter	Site	Title
05000313/FIN-2013011-04	2013Q2	Arkansas Nuclear	Main Feedwater Regulating Valve Maintenance Practices
05000313/FIN-2013011-01	2013Q2	Arkansas Nuclear	Control of Temporary Modification Associated with the Temporary Fire Pump
05000313/FIN-2013011-05	2013Q2	Arkansas Nuclear	Flood Barrier Effectiveness
05000313/FIN-2013011-09	2013Q2	Arkansas Nuclear	Effectiveness of Material Handling Program
05000313/FIN-2013011-03	2013Q2	Arkansas Nuclear	Procedural Controls Associated with Unit 1 Steam Generator Nozzle Dams
05000313/FIN-2013011-08	2013Q2	Arkansas Nuclear	Effectiveness of Shutdown Risk Management Program
05000313/FIN-2013011-10	2013Q2	Arkansas Nuclear	Causes and Corrective Actions Associated with the Dropped Heavy Load Event
05000313/FIN-2013011-07	2013Q2	Arkansas Nuclear	Timeliness of Emergency Action Level Determination
05000313/FIN-2013011-06	2013Q2	Arkansas Nuclear	Compensatory Measures for Firewater System Rupture
05000313/FIN-2013011-02	2013Q2	Arkansas Nuclear	Damage to Unit 1 and Unit 2 Structures, Systems and Components

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NRC Inspection Procedure