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Home NRC Library Document Collections Events, Reports Associated with Part 21 Reports

50.73 Licensee Event Reports that may report Defects and Noncompliance

For persons licensed to operate a nuclear power plant under 10 CFR part 50 or part 52, the evaluation of potential defects and appropriate reporting of defects under §§ 50.72, 50.73, or § 73.71 satisfies each person's evaluation, notification, and reporting obligation to report defects under 10 CFR Part 21. There is no rule that requires a licensee to mention Part 21 when using these alternate reporting means. In order to improve the sharing of Operating Experience with the industry, and increase reactor safety, the NRC will now post certain 50.73 Licensee Event Reports to the table located on this page when the report identifies the existence of a manufacturing defect that has or could cause a loss of safety function. It is important to note that the information contained in a Licensee Event Report (LER) is provided by the licensee, and has not been verified by the NRC to constitute a defect as described in 10 CFR Part 21. The information presented in the following table is provided for information purposes only, and licensees are not required to take any specific action based upon the information provided therein.

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Licensee Event Reports that may report Defects and Noncompliance

LER Number Licensee Description Report Date Accession No
333202400201 James A. FitzPatrick Nuclear Power Plant Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation 11/22/2024 ML24327A097
483202400200 Callaway Plant Unit 1 Concurrent Inoperability of Control Room Air Conditioning System Train and Opposite Train Emergency Diesel Generator Results in Condition Prohibited by Technical Specifications Limiting Conditions for Operation 3.7.11, 3.8.1, and 3.0.3 10/01/2024 ML24275A213
423202400602 Millstone Power Station Unit 3 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting In a Condition Prohibited byTechnical Specifications 09/26/2024 ML24270A029
387202400200 Susquehanna Steam Electric Station Unit 1 B Diesel Generator Inoperable due to Failed Excitation System Linear Reactor 09/16/2024 ML24260A227
498202400300 South Texas Project, Unit 1 Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump 07/01/2024 ML24183A174
498202400301 South Texas Project. Unit 1 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 06/19/2024 ML24171A011
321202400100 Edwin I. Hatch Nuclear Plant, Unit 2 Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La) 04/15/2024 ML24100A863
355202300301 R.E. Ginna Nuclear Power Plant, Unit 1 Manual Reactor Trip due to Degraded Condenser Vacuum
from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater
Actuation due to low Steam Generator Level		 03/07/2024 ML24067A253
366202300100 Edwin I. Hatch Nuclear Plant, Unit 2 Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La) 04/05/2023 ML23095A088
266202100100 Point Beach Nuclear Plant Unit 1 Main Feedwater Pump Trip Results in Manual Reactor Trip 09/28/2021 ML21271A271
416202000401 Grand Gulf Nuclear Station, Unit 1 Automatic Reactor Scram Due To Reactor Feed Pump Trip 08/18/2021 ML21231A137
265202000100 Quad Cities Nuclear Power Station, Unit 2

Loss of Both Divisions of Residual Heat Removal Low Pressure Coolant Injection Due to Swing Bus Failure to Transfer

 05/19/2020 ML20140A093
317201800100 Calvert Cliffs Nuclear Power Plant, Unit 2 Both Unit 2 Emergency Diesel Generators Inoperable Due to Depressurization in Common Air Start Headers 10/07/2018 ML18345A048
315201800100 Donald C. Cook Nuclear Plant Unit 1 Unit 1 East Essential Service Water Pump Inoperable Longer Than
Allowed by Technical Specifications		 05/31/2018 ML18155A305
440201800100 Perrv Nuclear Power Plant Loss of Safety Function and Violation of Technical Specifications due to diode failure 03/28/2018 ML18088A060
254201700400 Quad Cities Nuclear Power Station Unit 1 Unit 1 HPCI Did Not Trip Due to Wear Debris in the Turbine Stop Valve Oil Resetting Solenoid 01/05/2018 ML18005A276
458201700200 River Bend Station Loss of Safety Function of Onsite Electrical Distribution Due to Malfunction of Control Building HVAC System (LER) 04/18/2017 ML17116A297

Page Last Reviewed/Updated Tuesday, April 15, 2025