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 |
| 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 |
| 298202400200 |
Cooper Nuclear Station |
Technical Specifications Prohibited Condition for Inoperable Service
Water Booster Pump |
03/04/2024 |
ML24064A255 |
| 259202300101 |
Browns Ferry Nuclear Plant, Unit 1 |
High Pressure Coolant Injection System Inoperable Due to a Torn
Valve Diaphragm |
06/13/2023 |
ML23164A134 |
| 366202300100 |
Edwin I. Hatch Nuclear Plant, Unit 2 |
Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La) |
04/05/2023 |
ML23095A088 |
| 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 |
| 263201800200 |
Monticello Nuclear Generating Plant |
C Outboard Main Steam Isolation Valve Delayed Closure Due to
Foreign Material in the Air Valve |
02/14/2019 |
ML19046A002 |
| 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 |
| 440201800200 |
Perrv Nuclear Power Plant |
Failed Fuse Leads to Loss of Safety Function |
08/23/2018 |
ML18236A294 |
| 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 |
| 528201800300 |
Palo Verde Nuclear Generating Station (PVNGS) Unit 1 |
Condition Prohibited by Technical Specification 3.7.4 Due to Inoperable Atmospheric Dump Valve |
05/14/2018 |
ML18129A420 |
| 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 Monday, March 18, 2024