Licensee Event Report

If a criteria is reached according to NUREG-1022 then a Licensee to the NRC must submit a Licensee Event Report to explain what happened.

Reporting Criteria

10 CFR 50.73(a)(1), Submit an LER
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications (Text
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Any operation or condition which was prohibited by the plant's Technical Specifications)
10 CFR 50.73(a)(2)(i)(C), 50.54(x) TS Deviation
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material
10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability

Writing LERs

Explain exactly what happened during the entire event or condition, including how systems,components, and operating personnel performed. Do not cover specific hardware problems in excessive detail. Describe unique characteristics of a plant as well as other characteristics that influenced the event (favorably or unfavorably).

Avoid using plant-unique terms and abbreviations, or, as a minimum, clearly define them.
- The audience for LERs is large and does not necessarily know the details of each plant.
Include the root causes, the plant status before the event, and the sequence of occurrences.
Describe the event from the perspective of the Operator (i.e., what the operator saw, did, perceived, understood, or misunderstood).
If several systems actuate during an event, describe all aspects of the complete event, including all actuations sequentially, and those aspects that by themselves would not be reportable.
- For example, if a single component failure (generally not reportable) occurs following a reactor scram (reportable), describe the component failure in the narrative of the LER for the reactor scram.
It is necessary to discuss the performance and status of equipment.
Paraphrase pertinent sections of the latest submitted Safety analysis report (SAR) rather than referencing them because not all organizations or individuals have access to SARs.
Extensive cross-referencing would be time consuming considering the large number of LERs and reviewers that read each LER.
Ensure that each component's safety-significant effect on the event or condition is clearly and completely described.
Do not use statements such as "this event is not significant with respect to the health and safety of the public" without explaining the basis for the conclusion.

Specific information that should be included, as appropriate, is described in paragraphs 50.73(b).

Submissions of LERs

Section 50.73(d) of the NUREG-1022 states that submmissions must be done with Form NRC 366 as described by section 50.4. Submissions are to be done within 60 days of the event. If that happens to be a weekend or a holiday then it must be the next working day. If a Licensee knows that a report will be late or needs an additional day or so to complete the report, the situation should be discussed with the appropriate NRC regional office. See Section 2.5 for further discussion of discovery date.

LER Forwarding Letter and Cancellations

The cover letter forwarding an LER to the NRC should be signed by a responsible official. There is no prescribed format for the letter. The date the letter is issued and the report date should be the same. Licensees are encouraged to include the NRC resident inspector and the Institute of Nuclear Power Operations (INPO) in their distribution. Multiple LERs can be forwarded by one forwarding letter. Cancellations of LERs submitted should be made by letter. The letter should state that the LER is being canceled (i.e., formally withdrawn). The bases for the cancellation should be explained so that the staff can understand and review the reasons supporting the determination. The notice of cancellation will be filed and stored with the LER and acknowledgement made in various automated data systems. The LER will be removed from the LER data base.

Voluntary LERs

Indicate information-type LERS (i.e., Voluntary LERs) by checking the "Other" block in Item 11 of the LER form and type "Voluntary Report" in the space immediately below the block. Also give a sequential LER number to the voluntary report as noted in Section 5.2.4(5). Because not all requirements of 50.73(b), "Contents," may pertain to some voluntary reports, licensees should develop the content of such reports to best present the information associated with the situation being reported. See Section 2.7 for additional discussion of Voluntary LERs.

How To Find LERs

NRC Website search - Good for industry searching of LERs

LER list

by site

1 year

Site	Company	Event lists
05200046		[05200046 events]	[RSS]
99902060		[99902060 events]	[RSS]
Arkansas Nuclear	Entergy	[Arkansas Nuclear events]	[RSS]
Beaver Valley	FirstEnergy	[Beaver Valley events]	[RSS]
Belleville	Électricité de France	[Belleville events]	[RSS]
Big Rock Point	Consumers Power	[Big Rock Point events]	[RSS]
Blayais	Électricité de France	[Blayais events]	[RSS]
Braidwood	Exelon	[Braidwood events]	[RSS]
Brokdorf	Uniper	[Brokdorf events]	[RSS]
Browns Ferry	Tennessee Valley Authority	[Browns Ferry events]	[RSS]
Bruce		[Bruce events]	[RSS]
Brunswick	Duke Energy	[Brunswick events]	[RSS]
Bugey	Électricité de France	[Bugey events]	[RSS]
Byron	Exelon	[Byron events]	[RSS]
Callaway	Ameren	[Callaway events]	[RSS]
Calvert Cliffs	Exelon	[Calvert Cliffs events]	[RSS]
Caorso	SOGIN	[Caorso events]	[RSS]
Catawba	Duke Energy	[Catawba events]	[RSS]
Cattenom		[Cattenom events]	[RSS]
Changjiang	China National Nuclear Corporation	[Changjiang events]	[RSS]
Chinon	Électricité de France	[Chinon events]	[RSS]
Chooz	Électricité de France	[Chooz events]	[RSS]
Clinton	Exelon	[Clinton events]	[RSS]
Columbia	Energy Northwest	[Columbia events]	[RSS]
Comanche Peak	Luminant	[Comanche Peak events]	[RSS]
Cook	American Electric Power	[Cook events]	[RSS]
Cooper	Entergy	[Cooper events]	[RSS]
Cruas	Électricité de France	[Cruas events]	[RSS]
Crystal River	Duke Energy	[Crystal River events]	[RSS]
Dampierre	Électricité de France	[Dampierre events]	[RSS]
Darlington		[Darlington events]	[RSS]
Davis Besse	Cleveland Electric	[Davis Besse events]	[RSS]
Diablo Canyon	Pacific Gas & Electric	[Diablo Canyon events]	[RSS]
Doel	Engie Electrabel	[Doel events]	[RSS]
Douglas Point		[Douglas Point events]	[RSS]
Dresden	Exelon	[Dresden events]	[RSS]
Duane Arnold	NextEra Energy	[Duane Arnold events]	[RSS]
Dungeness	EDF Energy	[Dungeness events]	[RSS]
Farley	Southern Nuclear	[Farley events]	[RSS]
Fermi	DTE Energy	[Fermi events]	[RSS]
Fessenheim	Électricité de France	[Fessenheim events]	[RSS]
FitzPatrick	Exelon	[FitzPatrick events]	[RSS]
Flamanville	Électricité de France	[Flamanville events]	[RSS]
Fort Calhoun	Exelon	[Fort Calhoun events]	[RSS]
Fort Saint Vrain	Xcel Energy	[Fort Saint Vrain events]	[RSS]
Ginna	Exelon	[Ginna events]	[RSS]
Golfech	Électricité de France	[Golfech events]	[RSS]
Grand Gulf	Entergy	[Grand Gulf events]	[RSS]
Gravelines	Électricité de France	[Gravelines events]	[RSS]
Haddam Neck	Connecticut Light & Power Co	[Haddam Neck events]	[RSS]
Hallam		[Hallam events]	[RSS]
Harris	Duke Energy	[Harris events]	[RSS]
Hartlepool	EDF Energy	[Hartlepool events]	[RSS]
Hatch	Southern Nuclear	[Hatch events]	[RSS]
Heysham	EDF Energy	[Heysham events]	[RSS]
Hinkley Point	EDF Energy	[Hinkley Point events]	[RSS]
Hope Creek	PSEG	[Hope Creek events]	[RSS]
Humboldt Bay	Pacific Gas and Electric	[Humboldt Bay events]	[RSS]
Hunterston	EDF Energy	[Hunterston events]	[RSS]
Indian Point	Entergy	[Indian Point events]	[RSS]
Kennett Square	Exelon	[Kennett Square events]	[RSS]
Kewaunee	Dominion	[Kewaunee events]	[RSS]
La Crosse	Dairyland Power Cooperative	[La Crosse events]	[RSS]
LaSalle	Exelon	[LaSalle events]	[RSS]
Limerick	Exelon	[Limerick events]	[RSS]
MIT Nuclear Research Reactor		[MIT Nuclear Research Reactor events]	[RSS]
Maine Yankee	Maine Yankee Atomic Power Company	[Maine Yankee events]	[RSS]
McGuire	Duke Energy	[McGuire events]	[RSS]
Millstone	Dominion	[Millstone events]	[RSS]
Monticello	Xcel Energy	[Monticello events]	[RSS]
Nine Mile Point	Exelon	[Nine Mile Point events]	[RSS]
Nogent	Électricité de France	[Nogent events]	[RSS]
North Anna	Dominion	[North Anna events]	[RSS]
North Carolina State University		[North Carolina State University events]	[RSS]
NuScale		[NuScale events]	[RSS]
Nuclear Energy Institute		[Nuclear Energy Institute events]	[RSS]
Oconee	Duke Energy	[Oconee events]	[RSS]
Oyster Creek	Exelon	[Oyster Creek events]	[RSS]
Palisades	Entergy	[Palisades events]	[RSS]
Palo Verde	Arizona Public Service	[Palo Verde events]	[RSS]
Paluel	Électricité de France	[Paluel events]	[RSS]
Peach Bottom	Exelon	[Peach Bottom events]	[RSS]
Penly	Électricité de France	[Penly events]	[RSS]
Perry	FirstEnergy	[Perry events]	[RSS]
Pickering	Ontario Power Generation	[Pickering events]	[RSS]
Pilgrim	Entergy	[Pilgrim events]	[RSS]
Point Beach	NextEra Energy	[Point Beach events]	[RSS]
Point Lepreau	NB Power	[Point Lepreau events]	[RSS]
Portsmouth Gaseous Diffusion Plant		[Portsmouth Gaseous Diffusion Plant events]	[RSS]
Prairie Island	Xcel Energy	[Prairie Island events]	[RSS]
Quad Cities	Exelon	[Quad Cities events]	[RSS]
Rancho Seco	Sacramento Municipal Utility District	[Rancho Seco events]	[RSS]
Rensselaer Polytechnic Institute		[Rensselaer Polytechnic Institute events]	[RSS]
River Bend	Entergy	[River Bend events]	[RSS]
Robinson	Duke Energy	[Robinson events]	[RSS]
Saint Lucie	NextEra Energy	[Saint Lucie events]	[RSS]
Saint-Alban	Électricité de France	[Saint-Alban events]	[RSS]
Saint-Laurent	Électricité de France	[Saint-Laurent events]	[RSS]
Salem	PSEG	[Salem events]	[RSS]
San Onofre	Southern California Edison	[San Onofre events]	[RSS]
Seabrook	NextEra Energy	[Seabrook events]	[RSS]
Sequoyah	Tennessee Valley Authority	[Sequoyah events]	[RSS]
Sizewell	EDF Energy	[Sizewell events]	[RSS]
South Texas	STP Nuclear Operating Company	[South Texas events]	[RSS]
Summer	South Carolina Electric & Gas Company	[Summer events]	[RSS]
Surry	Dominion	[Surry events]	[RSS]
Susquehanna	Talen Energy	[Susquehanna events]	[RSS]
Three Mile Island	Exelon	[Three Mile Island events]	[RSS]
Tianwan	Jiangsu Nuclear Power Corporation	[Tianwan events]	[RSS]
Torness	EDF Energy	[Torness events]	[RSS]
Tricastin	Électricité de France	[Tricastin events]	[RSS]
Turkey Point	NextEra Energy	[Turkey Point events]	[RSS]
University of Florida Training Reactor facility		[University of Florida Training Reactor facility events]	[RSS]
University of Texas at Austin		[University of Texas at Austin events]	[RSS]
Vallecitos	GEH Hitachi	[Vallecitos events]	[RSS]
Vermont Yankee	Entergy	[Vermont Yankee events]	[RSS]
Vogtle	Southern Nuclear	[Vogtle events]	[RSS]
Washington State University		[Washington State University events]	[RSS]
Waterford	Entergy	[Waterford events]	[RSS]
Watts Bar	Tennessee Valley Authority	[Watts Bar events]	[RSS]
Wolf Creek	Wolf Creek Nuclear Operating Corporation	[Wolf Creek events]	[RSS]
Yankee Rowe		[Yankee Rowe events]	[RSS]
Zion	Exelon	[Zion events]	[RSS]

	Site	Report date	Reporting criterion	System
05000440/LER-2017-005	Perry	4 October 2017	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Secondary containment
05000269/LER-2017-001	Oconee Nuclear Station Unit 1	9 August 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v), Loss of Safety Function	Service water
05000325/LER-2017-002	Brunswick	12 June 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Main Turbine Emergency Diesel Generator
05000373/LER-2017-004	LaSalle Lasalle	17 April 2017	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Secondary containment Primary containment
05000368/LER-2017-002	Arkansas Nuclear One – Unit 2 Arkansas Nuclear	26 June 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Emergency Diesel Generator
05000461/LER-2017-003	Clinton	3 July 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Secondary containment Residual Heat Removal Shutdown Cooling Intermediate Range Monitor Feedwater Reactor Pressure Vessel Reactor Water Cleanup
05000341/LER-2017-005	Fermi		10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Emergency Equipment Cooling Water High Pressure Coolant Injection Emergency Diesel Generator Residual Heat Removal Reactor Core Isolation Cooling Feedwater Service water
05000287/LER-2017-001	Oconee Nuclear Station Unit 3 Oconee	20 September 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Reactor Protection System
05000458/LER-2017-009	Docket Number River Bend	13 November 2017	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment Primary containment Standby Gas Treatment System
05000346/LER-2017-001	Davis Besse	18 September 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition	Emergency Diesel Generator
05000286/LER-2017-002	Docket Number Indian Point	9 August 2017	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor	Reactor Coolant System Feedwater Residual Heat Removal
05000461/LER-2017-009	Clinton Power Station, Unit 1 . Clinton	4 January 2018	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment Standby Gas Treatment System Service water
05000316/LER-2017-001	Cook	19 May 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Residual Heat Removal
05000354/LER-2017-001	Hope Creek		10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment
05000250/LER-2017-001	Turkey Point	16 May 2017	10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function	Emergency Diesel Generator Reactor Protection System Steam Generator
05000397/LER-2017-004	Columbia	17 October 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Feedwater Reactor Pressure Vessel Main Turbine Main Steam Isolation Valve
05000390/LER-2017-009	Watts Bar		10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition	Residual Heat Removal Emergency Diesel Generator
05000391/LER-2017-001	Watts Bar	3 May 2017	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material
05000293/LER-2017-005	Pilgrim	7 June 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	High Pressure Coolant Injection Primary containment Main Steam Isolation Valve Secondary containment
05000390/LER-2017-001	Watts Bar	9 January 2017	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
05000388/LER-2017-007	Susquehanna		10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment
05000458/LER-2017-005	River Bend	5 June 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
05000254/LER-2017-001	Quad Cities	22 March 2017	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment Primary containment Standby Gas Treatment System Emergency Diesel Generator
05000397/LER-2017-001	Columbia		10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	High Pressure Core Spray Service water
05000327/LER-2017-001	Sequoyah		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment Shield Building
05000306/LER-2017-001	Prairie Island	29 November 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)(b) 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(ii)
05000387/LER-2017-002	Susquehanna		10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment
05000325/LER-2017-001	Brunswick	22 March 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Emergency Diesel Generator
05000397/LER-2017-005	Columbia	9 November 2017	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Secondary containment Reactor Core Isolation Cooling
05000293/LER-2017-009	Pilgrim	15 November 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat	Primary containment Shutdown Cooling Residual Heat Removal Primary Containment Isolation System
05000461/LER-2017-005	Clinton	28 September 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Reactor Protection System
05000296/LER-2017-001	Browns Ferry	31 October 2017		Residual Heat Removal Reactor Core Isolation Cooling High Pressure Coolant Injection Core Spray Core Standby Cooling System
05000387/LER-2017-001	Susquehanna		10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment
05000373/LER-2017-003	LaSalle Lasalle	14 April 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Feedwater Reactor Protection System Main Transformer
05000247/LER-2017-002	Indian Point	22 August 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Auxiliary Feedwater Feedwater Steam Generator
05000440/LER-2017-004	Perry	4 October 2017	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	High Pressure Core Spray
05000272/LER-2017-001	Salem	8 January 2018	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Reactor Coolant System Steam Generator
05000389/LER-2017-004	Saint Lucie	18 December 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Feedwater Auxiliary Feedwater Reactor Protection System Steam Generator
05000298/LER-2017-005	Cooper		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability	Primary containment Primary Containment Isolation System
05000219/LER-2017-003	Oyster Creek	31 August 2017		Reactor Pressure Vessel Feedwater
05000341/LER-2017-001	Fermi	6 March 2017	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor	Reactor Protection System Main Steam Isolation Valve Reactor Coolant System
05000289/LER-2017-004	Three Mile Island Three Mile Island Unit 1		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition	Emergency Diesel Generator
05000482/LER-2017-002	Wolf Creek	31 May 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition	Emergency Diesel Generator
05000265/LER-2017-001	Quad Cities	14 July 2017	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	High Pressure Coolant Injection Feedwater Core Spray Primary containment
05000364/LER-2017-005	Joseph M Farley Nuclear Plant, Unit 2 Farley	11 January 2018	10 CFR 50.73(a)(2)() 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)
05000298/LER-2017-003	Cooper		10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
05000461/LER-2017-001	Clinton	21 April 2017	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment Standby Gas Treatment System Service water
05000416/LER-2017-001	Grand Gulf	28 March 2017	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	High Pressure Core Spray Reactor Core Isolation Cooling Residual Heat Removal Core Spray
05000373/LER-2017-006	LaSalle Lasalle	17 July 2017	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Core Spray Residual Heat Removal Reactor Core Isolation Cooling
05000293/LER-2017-007	Pilgrim		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000331/LER-2017-001	Duane Arnold	27 March 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v), Loss of Safety Function	Primary containment
05000285/LER-2017-001	Fort Calhoun	11 May 2017		Reactor Coolant System
05000483/LER-2017-002	Callaway	13 October 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition	Auxiliary Feedwater Main Steam Safety Valve Emergency Diesel Generator Steam Generator Service water
05000266/LER-2017-003	Point Beach	13 December 2017	10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded	Reactor Coolant System
05000440/LER-2017-001	Perry	1 May 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Secondary containment Reactor Pressure Vessel Reactor Water Cleanup
05000220/LER-2017-001	Nine Mile Point	8 February 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Main Turbine High Pressure Coolant Injection Reactor Pressure Vessel Feedwater
05000313/LER-2017-001	Arkansas Nuclear Arkansas Nuclear One – Unit 1	26 June 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Emergency Diesel Generator Reactor Protection System Feedwater Reactor Coolant System Main Turbine Steam Generator
05000368/LER-2017-001	Arkansas Nuclear One – Unit 2 Arkansas Nuclear	30 May 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition	Emergency Diesel Generator
05000254/LER-2017-004	Quad Cities	5 January 2018		High Pressure Coolant Injection Feedwater Core Spray
05000458/LER-2017-001	River Bend	3 April 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Primary containment Reactor Pressure Vessel High Pressure Core Spray
05000293/LER-2017-001	Pilgrim	17 July 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment Standby Gas Treatment System HVAC Reactor Pressure Vessel Core Standby Cooling System
05000390/LER-2017-007	Watts Bar	3 November 2017	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v), Loss of Safety Function	Control Room Emergency Ventilation Reactor Coolant System Shield Building Emergency Gas Treatment System
05000324/LER-2017-001	Brunswick	18 May 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Secondary containment
05000390/LER-2017-012	Watts Bar		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Emergency Diesel Generator Residual Heat Removal Reactor Coolant System
05000263/LER-2017-002	Monticello	13 June 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Main Steam Isolation Valve Primary containment
05000461/LER-2017-002	Clinton		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition	Emergency Diesel Generator Residual Heat Removal
05000390/LER-2017-008	Watts Bar		10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v), Loss of Safety Function	Primary containment Shield Building Emergency Gas Treatment System
05000366/LER-2017-003	Hatch	13 April 2017	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded	Primary containment
05000374/LER-2017-002	LaSalle Lasalle	31 March 2017	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Emergency Diesel Generator High Pressure Core Spray Reactor Core Isolation Cooling Core Standby Cooling System
05000446/LER-2017-002	Comanche Peak Nuclear Power Plant Unit 2	27 October 2017		Auxiliary Feedwater Reactor Protection System Steam Generator
05000366/LER-2017-004	Edwin I Hatch Nuclear Plant Unit 2	24 August 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Reactor Pressure Vessel Main Steam Isolation Valve Reactor Protection System
05000219/LER-2017-005	Oyster Creek	3 January 2018	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Emergency Diesel Generator
05000263/LER-2017-001	Monticello	13 June 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Feedwater Reactor Protection System Primary containment Primary Containment Isolation System
05000373/LER-2017-001	LaSalle Lasalle	8 February 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Reactor Core Isolation Cooling High Pressure Core Spray
05000293/LER-2017-004	Pilgrim	2 June 2017	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Standby Gas Treatment System Secondary containment Primary containment Reactor Building Ventilation
05000458/LER-2017-002	River Bend	18 April 2017	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor	HVAC Emergency Diesel Generator
05000254/LER-2017-002	Quad Cities	26 May 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Main Steam Isolation Valve Primary containment
05000483/LER-2017-001	Callaway Docket Number	15 August 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Service water
05000293/LER-2017-010	Pilgrim	3 August 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Core Spray Residual Heat Removal Reactor Coolant System
05000388/LER-2017-001			10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment
05000395/LER-2017-001	Vc Summer.- Unit 1 Summer	24 July 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Feedwater Steam Generator
05000293/LER-2017-003	Pilgrim	13 November 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Primary containment Core Spray
05000443/LER-2017-001	Seabrook		10 CFR 50.73(a)(2)(iv)(A), System Actuation	Feedwater Reactor Protection System Steam Generator
05000391/LER-2017-003	Watts Bar	22 May 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Turbine Driven Main Feed Pump Auxiliary Feedwater Main Turbine Feedwater
05000458/LER-2017-007	River Bend Station — Unit 1 05000-458 River Bend		10 CFR 50.73(a)(2)(iv)(A), System Actuation	Main Turbine Feedwater Primary containment Reactor Protection System Reactor Water Cleanup
05000286/LER-2017-001	Indian Point Unit 3 Indian Point	13 July 2017	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability	Residual Heat Removal Reactor Coolant System
05000334/LER-2017-001	Beaver Valley	18 April 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition	Main Steam Safety Valve
05000341/LER-2017-004	Fermi	9 October 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat	Residual Heat Removal Emergency Diesel Generator Service water
05000388/LER-2017-004	Susquehanna		10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment
05000416/LER-2017-002	Grand Gulf	3 October 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Standby Gas Treatment System
05000249/LER-2017-001	Dresden		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor	Standby Liquid Control Reactor Pressure Vessel
05000260/LER-2017-003	Browns Ferry	30 May 2017		Intermediate Range Monitor Reactor Protection System Reactor Core Isolation Cooling Primary Containment Isolation System
05000280/LER-2017-001	Surry	11 October 2017	10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded	Reactor Coolant System
05000389/LER-2017-001	Saint Lucie	27 April 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Emergency Diesel Generator
05000374/LER-2017-003	LaSalle Lasalle	9 August 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(iv)(A), System Actuation	High Pressure Core Spray Reactor Core Isolation Cooling Reactor Pressure Vessel Main Steam Isolation Valve Reactor Protection System
05000461/LER-2017-010	Clinton	5 February 2018	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(iv)(A), System Actuation	Secondary containment Standby Gas Treatment System Reactor Protection System Main Steam Isolation Valve Reactor Water Cleanup
05000286/LER-2017-003	Indian Point Unit 3 Indian Point	29 August 2017	10 CFR 50.73(a)(2)(V)(B) 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat	Feedwater Auxiliary Feedwater Steam Generator Service water
05000374/LER-2017-001	LaSalle Lasalle	24 March 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Reactor Protection System Feedwater Main Turbine Main Steam Isolation Valve
05000311/LER-2017-001	Salem			Emergency Diesel Generator
05000446/LER-2017-001	Comanche Peak	22 January 2018	10 CFR 50.73(a)(2)(v), Loss of Safety Function	Auxiliary Feedwater Feedwater Steam Generator
05000440/LER-2017-002	Perry		10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor	Main Turbine Reactor Protection System
05000261/LER-2017-002	Robinson	14 December 2017
05000293/LER-2017-013	Pilgrim	25 January 2018	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Standby Gas Treatment System Secondary containment Primary containment
05000387/LER-2017-004	Susquehanna		10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment HVAC
05000364/LER-2017-002	Farley		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v), Loss of Safety Function	Main Steam Safety Valve Reactor Coolant System Steam Generator
05000425/LER-2017-001	Vogtle		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Emergency Diesel Generator
05000366/LER-2017-001	Hatch	3 April 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Secondary containment Reactor Pressure Vessel
05000397/LER-2017-002	Columbia		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Secondary containment Residual Heat Removal Shutdown Cooling Reactor Pressure Vessel
05000395/LER-2017-002	Summer	31 January 2018	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Feedwater Steam Generator
05000364/LER-2017-003	Farley		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Reactor Coolant System
05000382/LER-2017-002	Waterford Steam Electric Station, Unit 3 Waterford	18 September 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor	Main Turbine Emergency Diesel Generator Feedwater Reactor Protection System Reactor Coolant System Auxiliary Feedwater Main Transformer Steam Generator
05000298/LER-2017-002	Cooper		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v), Loss of Safety Function	Main Steam Isolation Valve
05000458/LER-2017-004	River Bend	22 May 2017	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat	High Pressure Core Spray Primary containment
05000313/LER-2017-002	Arkansas Nuclear One – Unit 1 Arkansas Nuclear	13 November 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Emergency Diesel Generator
05000298/LER-2017-004	Cooper		10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Primary containment
05000390/LER-2017-005	Watts Bar	10 July 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Emergency Diesel Generator Reactor Coolant System
05000325/LER-2017-004	Brunswick Steam Electric Plant (Bsep) Unit1	15 November 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Emergency Diesel Generator Primary Containment Isolation System Reactor Building Ventilation Secondary containment Standby Gas Treatment System Service water
05000219/LER-2017-001	Oyster Creek		10 CFR 50.73(a)(2)(iv)(A), System Actuation	Reactor Protection System Main Turbine
05000461/LER-2017-004	Clinton	22 November 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded	Main Steam Isolation Valve Primary containment Feedwater
05000266/LER-2017-001	Point Beach	16 November 2017	10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000321/LER-2017-002	Hatch	7 April 2017	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	High Pressure Coolant Injection Reactor Pressure Vessel Residual Heat Removal Core Spray Reactor Core Isolation Cooling
05000289/LER-2017-001	Three Mile Island Three Mile Island Unit 1		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Reactor Coolant System
05000397/LER-2017-007	Columbia	30 November 2017	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Secondary containment Emergency Diesel Generator
05000388/LER-2017-009	Susquehanna		10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment
05000388/LER-2017-010	Susquehanna		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Core Spray Residual Heat Removal
05000528/LER-2017-001	Palo Verde Palo Verde Nuclear Generating Station Unit 1	14 June 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Auxiliary Feedwater
05000255/LER-2017-002	Palisades	17 July 2017		Reactor Protection System
05000390/LER-2017-013	Watts Bar	24 January 2018	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Secondary containment Shield Building
05000390/LER-2017-010	Watts Bar	16 October 2017	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(iv)(A), System Actuation	Auxiliary Feedwater
05000395/LER-2017-006	Vc Summer - Unit 1 Summer	15 December 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000334/LER-2017-002	Beaver Valley	13 September 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor	Emergency Diesel Generator
05000390/LER-2017-006	Watts Bar	31 July 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000220/LER-2017-003	Nine Mile Point	2 November 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Reactor Protection System High Pressure Coolant Injection Feedwater Reactor Pressure Vessel Main Steam Isolation Valve Core Spray
05000293/LER-2017-008	Pilgrim	2 November 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat	Primary containment
05000370/LER-2017-001	McGuire	26 June 2017	10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded	Reactor Coolant System
05000390/LER-2017-003	Watts Bar	3 March 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000397/LER-2017-006	Columbia	9 November 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000219/LER-2017-002	Oyster Creek	31 August 2017		Steam Jet Air Ejector
05000391/LER-2017-006	Watts Bar		10 CFR 50.73(a)(2)(iv)(A), System Actuation	Auxiliary Feedwater Reactor Protection System
05000266/LER-2017-002	Point Beach	13 December 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Auxiliary Feedwater Feedwater Reactor Coolant System Steam Generator
05000306/LER-2017-003	Prairie Island		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Main Steam Isolation Valve Service water
05000335/LER-2017-001	Saint Lucie	2 May 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded	Reactor Coolant System
05000219/LER-2017-004	Oyster Creek	16 February 2018	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Reactor Protection System Main Turbine
05000416/LER-2017-004	Grand Gulf	13 July 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Feedwater High Pressure Core Spray
05000263/LER-2017-005	Monticello	20 September 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Emergency Diesel Generator Service water
05000325/LER-2017-003	Brunswick	2 August 2017	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Control Room Emergency Ventilation
05000259/LER-2017-001	Browns Ferry	21 February 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000382/LER-2017-001	Waterford	4 May 2017	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Shutdown Cooling Reactor Coolant System Steam Generator
05000373/LER-2017-007	LaSalle Lasalle	18 August 2017	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Core Spray Reactor Pressure Vessel Residual Heat Removal Reactor Building Ventilation
05000461/LER-2017-006	Clinton	1 August 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Secondary containment Reactor Water Cleanup
05000364/LER-2017-001	Farley	21 August 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Emergency Diesel Generator Service water
05000391/LER-2017-005	Watts Bar Nuclear Plant. Unit 2 Watts Bar		10 CFR 50.73(a)(2)(iv)(A), System Actuation	Reactor Coolant System Emergency Diesel Generator
05000440/LER-2017-007	Perry		10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	High Pressure Core Spray Reactor Core Isolation Cooling Core Spray
05000416/LER-2017-006	Grand Gulf	12 October 2017	10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown	Residual Heat Removal
05000387/LER-2017-006	Susquehanna		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Secondary containment
05000289/LER-2017-003	Three Mile Island Unit 1 Three Mile Island		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Primary containment
05000263/LER-2017-004	Monticello	16 August 2017	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	High Pressure Coolant Injection Reactor Core Isolation Cooling
05000390/LER-2017-014	Watts Bar	20 December 2017	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Control Room Emergency Ventilation
05000388/LER-2017-003	Susquehanna		10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment
05000424/LER-2017-002	Vogtle	29 June 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Emergency Diesel Generator Residual Heat Removal
05000247/LER-2017-001	Indian Point	22 August 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Feedwater Main Turbine Emergency Diesel Generator Auxiliary Feedwater Reactor Protection System Reactor Coolant System Steam Generator
05000458/LER-2017-008		12 October 2017	10 CFR 50.73(a)(2)(iv), System Actuation	Feedwater Reactor Protection System
05000261/LER-2017-001	Robinson	2 June 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Auxiliary Feedwater Feedwater Steam Generator
05000389/LER-2017-003	Saint Lucie	18 December 2017		Auxiliary Feedwater Steam Generator
05000334/LER-2017-003	Beaver Valley	4 January 2018	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Auxiliary Feedwater Feedwater Reactor Protection System Steam Generator
05000306/LER-2017-002	Prairie Island	11 December 2017	10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded	Reactor Coolant System
05000458/LER-2017-006	River Bend	13 July 2017	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	High Pressure Core Spray
05000390/LER-2017-015	Watts Bar	8 January 2018	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000289/LER-2017-002	Three Mile Island Unit 1 Three Mile Island	6 February 2017	10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded	Reactor Coolant System
05000388/LER-2017-008	Susquehanna		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Primary containment
05000352/LER-2017-001	Limerick			HVAC
05000255/LER-2017-001	Palisades	24 May 2017		Emergency Diesel Generator Auxiliary Feedwater Service water
05000454/LER-2017-001	Byron		10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded	Reactor Coolant System Reactor Pressure Vessel
05000260/LER-2017-004	Browns Ferry	7 July 2017
05000323/LER-2017-001	Diablo Canyon		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v), Loss of Safety Function	Reactor Coolant System Feedwater Steam Generator
05000388/LER-2017-005	Susquehanna		10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment HVAC
05000395/LER-2017-004	Summer		10 CFR 50.73(a)(2)(iv)(A), System Actuation	Emergency Diesel Generator
05000348/LER-2017-001	Farley	29 September 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Reactor Coolant System
05000286/LER-2017-004	Indian Point	20 December 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Auxiliary Feedwater Feedwater Reactor Protection System Emergency Diesel Generator Reactor Coolant System Steam Generator Permanent Magnet Generator
05000498/LER-2017-002	South Texas		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Control Room Emergency Ventilation HVAC
05000260/LER-2017-001	Browns Ferry	14 April 2017		High Pressure Coolant Injection Reactor Core Isolation Cooling
05000324/LER-2017-002	Brunswick	9 June 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Primary containment Emergency Diesel Generator Residual Heat Removal
05000321/LER-2017-003	Docket Number		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment Primary containment
05000397/LER-2017-003	Columbia	24 August 2017	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Secondary containment HVAC
05000293/LER-2017-012	Pilgrim	13 November 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Emergency Diesel Generator
05000388/LER-2017-002	Susquehanna Steam Electric Station Unit 2 1 Of 4 Susquehanna		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Secondary containment Residual Heat Removal Reactor Pressure Vessel Shutdown Cooling Reactor Water Cleanup
05000263/LER-2017-003	Monticello	14 June 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Main Steam Isolation Valve Primary containment
05000395/LER-2017-003	Vc Summer - Unit 1 Summer	12 December 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Feedwater Reactor Coolant System Main Transformer
05000440/LER-2017-006	Perry		10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	High Pressure Core Spray
05000333/LER-2017-001	FitzPatrick	13 March 2017	10 CFR 50.73(a)(2)(ii)	Reactor Coolant System Residual Heat Removal Shutdown Cooling Primary containment
05000425/LER-2017-002	Vogtle		10 CFR 50.73(a)(2)(iv)(A), System Actuation	Emergency Diesel Generator
05000244/LER-2017-001	Ginna	15 June 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Main Steam Safety Valve
05000410/LER-2017-001	Nine Mile Point	4 October 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Reactor Protection System Main Turbine
05000335/LER-2017-002	Saint Lucie	28 September 2017	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition	Reactor Coolant System Shutdown Cooling
05000388/LER-2017-006			10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	HVAC Secondary containment
05000387/LER-2017-003	Susquehanna Steam Electric Station Unit 2 05000-387 Susquehanna		10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment HVAC
05000390/LER-2017-016	Watts Bar Nuclear Plant. Unit 1	20 February 2018	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(iv)(A), System Actuation	Auxiliary Feedwater Emergency Diesel Generator
05000446/LER-2017-003	Comanche Peak Nuclear Power Plant, Unit 2 Comanche Peak	22 January 2018	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function	Feedwater Auxiliary Feedwater Reactor Protection System Main Turbine Steam Generator
05000296/LER-2017-002	Browns Ferry		10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition	Emergency Diesel Generator
05000259/LER-2017-002		1 May 2017
05000482/LER-2017-003	Wolf Creek	2 November 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition	Main Steam Safety Valve Main Turbine Main Steam Isolation Valve Steam Generator
05000327/LER-2017-002	Sequoyah		10 CFR 50.73(a)(2)(iv)(A), System Actuation	Emergency Diesel Generator
05000298/LER-2017-001	Cooper		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat	Residual Heat Removal Low Pressure Cooling Injection Shutdown Cooling Reactor Pressure Vessel Service water
05000461/LER-2017-007	Clinton	9 November 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Feedwater Main Turbine Reactor Protection System
05000458/LER-2017-003	River Bend	9 May 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Feedwater Main Turbine Main Steam Isolation Valve Reactor Protection System
05000374/LER-2017-004	LaSalle Lasalle	14 July 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Reactor Pressure Vessel
05000324/LER-2017-003	Brunswick	3 August 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Reactor Coolant System
05000410/LER-2017-002	Nine Mile Point	29 November 2017	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment Reactor Building Ventilation Standby Gas Treatment System
05000366/LER-2017-002	Hatch	13 April 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Emergency Diesel Generator Secondary containment Standby Gas Treatment System Shutdown Cooling
05000293/LER-2017-006	Pilgrim	13 June 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Intermediate Range Monitor
05000260/LER-2017-002	Browns Ferry			Primary containment Reactor Core Isolation Cooling
05000389/LER-2017-002	Saint Lucie	14 July 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Emergency Diesel Generator
05000220/LER-2017-002	Nine Mile Point		10 CFR 50.73(a)(2)(iv)(A), System Actuation	Main Turbine
05000482/LER-2017-001	Wolf Creek	17 May 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Service water
05000278/LER-2017-001	Peach Bottom	21 December 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded	Reactor Coolant System Residual Heat Removal
05000483/LER-2017-003	Callaway		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)	Primary containment
05000254/LER-2017-003	Quad Cities	17 November 2017	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Control Room Emergency Ventilation HVAC
05000341/LER-2017-002	Fermi	16 March 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)	High Pressure Coolant Injection Reactor Core Isolation Cooling Feedwater Primary containment
05000346/LER-2017-002	Davis Besse	27 November 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat	Feedwater Auxiliary Feedwater Main Steam Safety Valve Main Steam Isolation Valve Steam Generator Service water
05000416/LER-2017-007	Grand Gulf	5 February 2018	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Emergency Diesel Generator Secondary containment Reactor Core Isolation Cooling Main Transformer
05000412/LER-2017-001	Beaver Valley	2 May 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat	Service water
05000263/LER-2017-006	Monticello	12 January 2018	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor	Reactor Protection System Main Steam Isolation Valve Reactor Coolant System
05000440/LER-2017-003	Perry		10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v), Loss of Safety Function	Primary containment Shield Building
05000251/LER-2017-001	Turkey Point	7 November 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Feedwater Reactor Protection System Steam Generator
05000390/LER-2017-002	Watts Bar	22 February 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000390/LER-2017-011	Watts Bar	23 October 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000387/LER-2017-007	Susquehanna		10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material	Secondary containment
05000423/LER-2017-001	Millstone	20 March 2017	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	Secondary containment
05000364/LER-2017-004	Joseph M. Farley Nuclear Plant. Unit 2 Farley		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Auxiliary Feedwater Reactor Coolant System Main Steam Isolation Valve Steam Generator
05000341/LER-2017-003	Fermi	21 July 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function	Residual Heat Removal Service Water Residual Heat Removal Reactor Pressure Vessel Emergency Diesel Generator Service water
05000293/LER-2017-011	A Ler Number Pilgrim	15 August 2017		Secondary containment Primary containment Standby Gas Treatment System
05000416/LER-2017-005	Grand Gulf	7 September 2017	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
05000321/LER-2017-004	Hatch		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition	Emergency Diesel Generator
05000498/LER-2017-001	South Texas	11 May 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000293/LER-2017-002	Pilgrim	25 May 2017	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	High Pressure Coolant Injection Reactor Core Isolation Cooling Core Spray Primary containment
05000391/LER-2017-002	Watts Bar	12 May 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Reactor Protection System Auxiliary Feedwater Feedwater Steam Generator
05000335/LER-2017-003	Saint Lucie	13 November 2017		Reactor Protection System
05000395/LER-2017-005	Summer	22 December 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Feedwater Steam Generator
05000373/LER-2017-005	LaSalle Lasalle	18 April 2017	10 CFR 50.73(a)(2)(iv)(A), System Actuation	Feedwater Reactor Protection System Reactor Pressure Vessel Main Steam Isolation Valve
05000387/LER-2017-005	Susquehanna		10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(iv)(A), System Actuation	Reactor Protection System Secondary containment Reactor Building Ventilation Standby Gas Treatment System Main Turbine High Pressure Coolant Injection Reactor Core Isolation Cooling Reactor Pressure Vessel Feedwater Reactor Coolant System
05000247/LER-2017-003	Indian Point Unit 2 Indian Point	23 August 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Reactor Protection System
05000391/LER-2017-004	Watts Bar		10 CFR 50.73(a)(2)(iv)(A), System Actuation	Reactor Protection System Auxiliary Feedwater Steam Generator
05000390/LER-2017-004	Watts Bar		10 CFR 50.73(a)(2)(iv)(A), System Actuation	Auxiliary Feedwater Steam Generator
05000318/LER-2017-001	Calvert Cliffs	19 April 2017	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Reactor Coolant System
05000461/LER-2017-008	Clinton	11 August 2017	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident	High Pressure Core Spray Reactor Core Isolation Cooling Emergency Diesel Generator Service water
05000277/LER-2017-001	Peach Bottom		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition	Emergency Diesel Generator
05000219/LER-2016-004	Oyster Creek		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Reactor Pressure Vessel Main Steam Isolation Valve
05000354/LER-2016-006	Hope Creek		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications	Reactor Protection System Primary Containment Isolation System Primary containment Reactor Coolant System
05000352/LER-2016-003	Limerick	18 May 2016	10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded	Reactor Coolant System Shutdown Cooling Primary containment Core Spray Residual Heat Removal
05000272/LER-2016-001	Salem	5 July 2016		Reactor Coolant System
... further results

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