Licensee Event Report

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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


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

See also

LER list

by site

1 year

Site#CompanyEvent lists
Arkansas Nuclear 4 Entergy [Arkansas Nuclear events] [RSS]
Beaver Valley 2 FirstEnergy [Beaver Valley events] [RSS]
Bellefonte 0 Nuclear Development LLC [Bellefonte events] [RSS]
Belleville 0 Électricité de France [Belleville events] [RSS]
Big Rock Point 0 Consumers Power [Big Rock Point events] [RSS]
Blayais 0 Électricité de France [Blayais events] [RSS]
Braidwood 0 Exelon [Braidwood events] [RSS]
Brokdorf 0 Uniper [Brokdorf events] [RSS]
Browns Ferry 3 Tennessee Valley Authority [Browns Ferry events] [RSS]
Bruce 0 [Bruce events] [RSS]
Brunswick 4 Duke Energy [Brunswick events] [RSS]
Bugey 0 Électricité de France [Bugey events] [RSS]
Byron 0 Exelon [Byron events] [RSS]
Callaway 2 Ameren [Callaway events] [RSS]
Calvert Cliffs 0 Exelon [Calvert Cliffs events] [RSS]
Caorso 0 SOGIN [Caorso events] [RSS]
Catawba 0 Duke Energy [Catawba events] [RSS]
Cattenom 0 [Cattenom events] [RSS]
Changjiang 0 China National Nuclear Corporation [Changjiang events] [RSS]
Chinon 0 Électricité de France [Chinon events] [RSS]
Chooz 0 Électricité de France [Chooz events] [RSS]
Clinton 8 Exelon [Clinton events] [RSS]
Columbia 5 Energy Northwest [Columbia events] [RSS]
Comanche Peak 2 Luminant [Comanche Peak events] [RSS]
Cook 0 American Electric Power [Cook events] [RSS]
Cooper 0 Entergy [Cooper events] [RSS]
Cruas 0 Électricité de France [Cruas events] [RSS]
Crystal River 0 Duke Energy [Crystal River events] [RSS]
Dampierre 0 Électricité de France [Dampierre events] [RSS]
Darlington 0 [Darlington events] [RSS]
Davis Besse 2 Cleveland Electric [Davis Besse events] [RSS]
Diablo Canyon 0 Pacific Gas & Electric [Diablo Canyon events] [RSS]
Doel 0 Engie Electrabel [Doel events] [RSS]
Douglas Point 0 [Douglas Point events] [RSS]
Dresden 0 Exelon [Dresden events] [RSS]
Duane Arnold 0 NextEra Energy [Duane Arnold events] [RSS]
Dungeness 0 EDF Energy [Dungeness events] [RSS]
Farley 3 Southern Nuclear [Farley events] [RSS]
Fermi 2 DTE Energy [Fermi events] [RSS]
Fessenheim 0 Électricité de France [Fessenheim events] [RSS]
FitzPatrick 0 Exelon [FitzPatrick events] [RSS]
Flamanville 0 Électricité de France [Flamanville events] [RSS]
Fort Calhoun 0 Exelon [Fort Calhoun events] [RSS]
Fort Saint Vrain 0 Xcel Energy [Fort Saint Vrain events] [RSS]
Ginna 1 Exelon [Ginna events] [RSS]
Golfech 0 Électricité de France [Golfech events] [RSS]
Grand Gulf 5 Entergy [Grand Gulf events] [RSS]
Gravelines 0 Électricité de France [Gravelines events] [RSS]
Haddam Neck 0 Connecticut Light & Power Co [Haddam Neck events] [RSS]
Hallam 0 [Hallam events] [RSS]
Harris 0 Duke Energy [Harris events] [RSS]
Hartlepool 0 EDF Energy [Hartlepool events] [RSS]
Hatch 0 Southern Nuclear [Hatch events] [RSS]
Heysham 0 EDF Energy [Heysham events] [RSS]
Hinkley Point 0 EDF Energy [Hinkley Point events] [RSS]
Hope Creek 0 PSEG [Hope Creek events] [RSS]
Humboldt Bay 0 Pacific Gas and Electric [Humboldt Bay events] [RSS]
Hunterston 0 EDF Energy [Hunterston events] [RSS]
Indian Point 8 Entergy [Indian Point events] [RSS]
Kewaunee 0 Dominion [Kewaunee events] [RSS]
La Crosse 0 Dairyland Power Cooperative [La Crosse events] [RSS]
LaSalle 4 Exelon [LaSalle events] [RSS]
Limerick 0 Exelon [Limerick events] [RSS]
Maine Yankee 0 Maine Yankee Atomic Power Company [Maine Yankee events] [RSS]
McGuire 1 Duke Energy [McGuire events] [RSS]
Millstone 0 Dominion [Millstone events] [RSS]
Monticello 6 Xcel Energy [Monticello events] [RSS]
Nine Mile Point 3 Exelon [Nine Mile Point events] [RSS]
Nogent 0 Électricité de France [Nogent events] [RSS]
North Anna 0 Dominion [North Anna events] [RSS]
Oconee 1 Duke Energy [Oconee events] [RSS]
Oyster Creek 4 Exelon [Oyster Creek events] [RSS]
Palisades 1 Entergy [Palisades events] [RSS]
Palo Verde 1 Arizona Public Service [Palo Verde events] [RSS]
Paluel 0 Électricité de France [Paluel events] [RSS]
Peach Bottom 1 Exelon [Peach Bottom events] [RSS]
Penly 0 Électricité de France [Penly events] [RSS]
Perry 2 FirstEnergy [Perry events] [RSS]
Pickering 0 Ontario Power Generation [Pickering events] [RSS]
Pilgrim 11 Entergy [Pilgrim events] [RSS]
Point Beach 3 NextEra Energy [Point Beach events] [RSS]
Point Lepreau 0 NB Power [Point Lepreau events] [RSS]
Prairie Island 2 Xcel Energy [Prairie Island events] [RSS]
Quad Cities 4 Exelon [Quad Cities events] [RSS]
Rancho Seco 0 Sacramento Municipal Utility District [Rancho Seco events] [RSS]
River Bend 3 Entergy [River Bend events] [RSS]
Robinson 2 Duke Energy [Robinson events] [RSS]
Saint Lucie 5 NextEra Energy [Saint Lucie events] [RSS]
Saint-Alban 0 Électricité de France [Saint-Alban events] [RSS]
Saint-Laurent 0 Électricité de France [Saint-Laurent events] [RSS]
Salem 1 PSEG [Salem events] [RSS]
San Onofre 0 Southern California Edison [San Onofre events] [RSS]
Seabrook 0 NextEra Energy [Seabrook events] [RSS]
Sequoyah 0 Tennessee Valley Authority [Sequoyah events] [RSS]
Sizewell 0 EDF Energy [Sizewell events] [RSS]
South Texas 0 STP Nuclear Operating Company [South Texas events] [RSS]
Summer 5 South Carolina Electric & Gas Company [Summer events] [RSS]
Surry 1 Dominion [Surry events] [RSS]
Susquehanna 0 Talen Energy [Susquehanna events] [RSS]
Three Mile Island 0 Exelon [Three Mile Island events] [RSS]
Tianwan 0 Jiangsu Nuclear Power Corporation [Tianwan events] [RSS]
Torness 0 EDF Energy [Torness events] [RSS]
Tricastin 0 Électricité de France [Tricastin events] [RSS]
Turkey Point 1 NextEra Energy [Turkey Point events] [RSS]
Vermont Yankee 0 Entergy [Vermont Yankee events] [RSS]
Vogtle 1 Southern Nuclear [Vogtle events] [RSS]
Waterford 1 Entergy [Waterford events] [RSS]
Watts Bar 8 Tennessee Valley Authority [Watts Bar events] [RSS]
Wolf Creek 2 Wolf Creek Nuclear Operating Corporation [Wolf Creek events] [RSS]
Yankee Rowe 0 [Yankee Rowe events] [RSS]
Zion 0 Exelon [Zion events] [RSS]
 SiteReport dateReporting criterionSystem
05000454/LER-2017-001Byron10 CFR 50.73(a)(2)(ii)(A), Seriously DegradedReactor Coolant System
Reactor Pressure Vessel
05000269/LER-2017-001Oconee Nuclear Station Unit 19 August 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000323/LER-2017-001Diablo Canyon10 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
05000325/LER-2017-002Brunswick12 June 201710 CFR 50.73(a)(2)(iv)(A), System ActuationMain Turbine
Emergency Diesel Generator
05000395/LER-2017-004Summer10 CFR 50.73(a)(2)(iv)(A), System ActuationEmergency Diesel Generator
05000368/LER-2017-002Arkansas Nuclear One – Unit 2
Arkansas Nuclear
26 June 201710 CFR 50.73(a)(2)(iv)(A), System ActuationEmergency Diesel Generator
05000341/LER-2017-005Fermi10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an AccidentEmergency Equipment Cooling Water
High Pressure Coolant Injection
Emergency Diesel Generator
Residual Heat Removal
Reactor Core Isolation Cooling
Feedwater
05000352/LER-2017-001LimerickHVAC
05000287/LER-2017-001Oconee Nuclear Station Unit 3
Oconee
20 September 201710 CFR 50.73(a)(2)(iv)(A), System ActuationReactor Protection System
05000324/LER-2017-002Brunswick9 June 201710 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
05000458/LER-2017-009Docket Number
River Bend
13 November 201710 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive MaterialSecondary containment
Primary containment
Standby Gas Treatment System
05000397/LER-2017-003Columbia24 August 201710 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
05000286/LER-2017-002Docket Number
Indian Point
9 August 201710 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
05000316/LER-2017-001Cook19 May 201710 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
05000348/LER-2017-001Farley29 September 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsReactor Coolant System
05000250/LER-2017-001Turkey Point16 May 201710 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
05000498/LER-2017-002South Texas10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsControl Room Emergency Ventilation
HVAC
05000254/LER-2017-001Quad Cities22 March 201710 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive MaterialSecondary containment
Primary containment
Standby Gas Treatment System
Emergency Diesel Generator
05000440/LER-2017-006Perry10 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
05000425/LER-2017-002Vogtle10 CFR 50.73(a)(2)(iv)(A), System ActuationEmergency Diesel Generator
05000391/LER-2017-001Watts Bar3 May 201710 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material
05000293/LER-2017-005Pilgrim7 June 201710 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
05000388/LER-2017-002Susquehanna Steam Electric Station Unit 2 1 Of 4
Susquehanna
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsSecondary containment
Residual Heat Removal
Reactor Pressure Vessel
Shutdown Cooling
05000388/LER-2017-007Susquehanna10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive MaterialSecondary containment
05000446/LER-2017-003Comanche Peak Nuclear Power Plant, Unit 2
Comanche Peak
22 January 201810 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
05000327/LER-2017-001Sequoyah10 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
05000306/LER-2017-001Prairie Island29 November 201710 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)
05000410/LER-2017-001Nine Mile Point4 October 201710 CFR 50.73(a)(2)(iv)(A), System ActuationReactor Protection System
Main Turbine
05000325/LER-2017-001Brunswick22 March 201710 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
05000293/LER-2017-009Pilgrim15 November 201710 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
05000387/LER-2017-003Susquehanna Steam Electric Station Unit 2 05000-387
Susquehanna
10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive MaterialSecondary containment
HVAC
05000298/LER-2017-005Cooper10 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
05000461/LER-2017-007Clinton9 November 201710 CFR 50.73(a)(2)(iv)(A), System ActuationFeedwater
Main Turbine
Reactor Protection System
05000296/LER-2017-001Browns Ferry31 October 2017Residual Heat Removal
Reactor Core Isolation Cooling
High Pressure Coolant Injection
Core Spray
Core Standby Cooling System
05000374/LER-2017-004LaSalle14 July 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsReactor Pressure Vessel
05000387/LER-2017-001Susquehanna10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive MaterialSecondary containment
05000410/LER-2017-002Nine Mile Point29 November 201710 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive MaterialSecondary containment
Reactor Building Ventilation
Standby Gas Treatment System
05000247/LER-2017-002Indian Point22 August 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsAuxiliary Feedwater
Feedwater
05000272/LER-2017-001Salem8 January 201810 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsReactor Coolant System
05000327/LER-2017-002Sequoyah10 CFR 50.73(a)(2)(iv)(A), System ActuationEmergency Diesel Generator
05000219/LER-2017-003Oyster Creek31 August 2017Reactor Pressure Vessel
Feedwater
05000389/LER-2017-002Saint Lucie14 July 201710 CFR 50.73(a)(2)(iv)(A), System ActuationEmergency Diesel Generator
05000482/LER-2017-001Wolf Creek17 May 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000289/LER-2017-004Three 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
05000265/LER-2017-001Quad Cities14 July 201710 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an AccidentHigh Pressure Coolant Injection
Feedwater
Core Spray
Primary containment
05000366/LER-2017-002Hatch13 April 201710 CFR 50.73(a)(2)(iv)(A), System ActuationEmergency Diesel Generator
Secondary containment
Standby Gas Treatment System
Shutdown Cooling
05000298/LER-2017-003Cooper10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
05000266/LER-2017-003Point Beach13 December 201710 CFR 50.73(a)(2)(ii)(A), Seriously DegradedReactor Coolant System
05000346/LER-2017-002Davis Besse27 November 201710 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
05000412/LER-2017-001Beaver Valley2 May 201710 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
05000373/LER-2017-006LaSalle17 July 201710 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an AccidentCore Spray
Residual Heat Removal
Reactor Core Isolation Cooling
05000293/LER-2017-007Pilgrim10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000483/LER-2017-003Callaway10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(ii)
Primary containment
05000285/LER-2017-001Fort Calhoun11 May 2017Reactor Coolant System
05000423/LER-2017-001Millstone20 March 201710 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
05000220/LER-2017-001Nine Mile Point8 February 201710 CFR 50.73(a)(2)(iv)(A), System ActuationMain Turbine
High Pressure Coolant Injection
Reactor Pressure Vessel
Feedwater
05000313/LER-2017-001Arkansas Nuclear
Arkansas Nuclear One – Unit 1
26 June 201710 CFR 50.73(a)(2)(iv)(A), System ActuationEmergency Diesel Generator
Reactor Protection System
Feedwater
Reactor Coolant System
Main Turbine
05000440/LER-2017-003Perry10 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
05000254/LER-2017-004Quad Cities5 January 2018High Pressure Coolant Injection
Feedwater
Core Spray
05000293/LER-2017-001Pilgrim17 July 201710 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-2017-011Watts Bar23 October 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000498/LER-2017-001South Texas11 May 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000390/LER-2017-007Watts Bar3 November 201710 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
05000391/LER-2017-002Watts Bar12 May 201710 CFR 50.73(a)(2)(iv)(A), System ActuationReactor Protection System
Auxiliary Feedwater
Feedwater
05000324/LER-2017-001Brunswick18 May 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsSecondary containment
05000395/LER-2017-005Summer22 December 201710 CFR 50.73(a)(2)(iv)(A), System ActuationMain Turbine
Feedwater
05000263/LER-2017-002Monticello13 June 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsMain Steam Isolation Valve
Primary containment
05000390/LER-2017-008Watts Bar10 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
05000416/LER-2017-005Grand Gulf7 September 201710 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
05000374/LER-2017-002LaSalle31 March 201710 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an AccidentEmergency Diesel Generator
High Pressure Core Spray
Reactor Core Isolation Cooling
Core Standby Cooling System
05000254/LER-2017-002Quad Cities26 May 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsMain Steam Isolation Valve
Primary containment
05000390/LER-2017-004Watts Bar10 CFR 50.73(a)(2)(iv)(A), System ActuationAuxiliary Feedwater
05000461/LER-2017-008Clinton11 August 201710 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an AccidentHigh Pressure Core Spray
Reactor Core Isolation Cooling
Emergency Diesel Generator
05000219/LER-2017-005Oyster Creek3 January 201810 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsEmergency Diesel Generator
05000263/LER-2017-001Monticello13 June 201710 CFR 50.73(a)(2)(iv)(A), System ActuationFeedwater
Reactor Protection System
Primary containment
Primary Containment Isolation System
05000387/LER-2017-005Susquehanna10 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
05000293/LER-2017-004Pilgrim2 June 201710 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
05000461/LER-2017-003Clinton3 July 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsSecondary containment
Residual Heat Removal
Shutdown Cooling
Intermediate Range Monitor
Feedwater
Reactor Pressure Vessel
05000293/LER-2017-010Pilgrim3 August 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsCore Spray
Residual Heat Removal
Reactor Coolant System
05000388/LER-2017-00110 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive MaterialSecondary containment
05000440/LER-2017-005Perry4 October 201710 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
05000293/LER-2017-003Pilgrim13 November 201710 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
05000391/LER-2017-003Watts Bar22 May 201710 CFR 50.73(a)(2)(iv)(A), System ActuationTurbine Driven Main Feed Pump
Auxiliary Feedwater
Main Turbine
Feedwater
05000373/LER-2017-004LaSalle17 April 201710 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
05000260/LER-2017-003Browns Ferry30 May 2017Intermediate Range Monitor
Reactor Protection System
Reactor Core Isolation Cooling
Primary Containment Isolation System
05000461/LER-2017-009Clinton Power Station, Unit 1 .
Clinton
4 January 201810 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive MaterialSecondary containment
Standby Gas Treatment System
05000286/LER-2017-001Indian Point Unit 3
Indian Point
13 July 201710 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
05000354/LER-2017-001Hope Creek10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive MaterialSecondary containment
05000334/LER-2017-001Beaver Valley18 April 201710 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
05000397/LER-2017-004Columbia17 October 201710 CFR 50.73(a)(2)(iv)(A), System ActuationFeedwater
Reactor Pressure Vessel
Main Turbine
Main Steam Isolation Valve
05000388/LER-2017-004Susquehanna10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive MaterialSecondary containment
05000249/LER-2017-001Dresden10 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
05000346/LER-2017-001Davis Besse18 September 201710 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
05000280/LER-2017-001Surry11 October 201710 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
05000390/LER-2017-001Watts Bar9 January 201710 CFR 50.73(a)(2)(vii), Common Cause Inoperability
05000341/LER-2017-003Fermi21 July 201710 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
05000458/LER-2017-005River Bend5 June 201710 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
05000374/LER-2017-003LaSalle9 August 201710 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
05000286/LER-2017-003Indian Point Unit 3
Indian Point
29 August 201710 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
05000390/LER-2017-009Watts Bar10 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
05000311/LER-2017-001SalemEmergency Diesel Generator
05000366/LER-2017-001Hatch3 April 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsSecondary containment
Reactor Pressure Vessel
05000387/LER-2017-002Susquehanna10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive MaterialSecondary containment
05000397/LER-2017-005Columbia9 November 201710 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
05000261/LER-2017-002Robinson14 December 2017
05000293/LER-2017-013Pilgrim25 January 201810 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
05000397/LER-2017-001Columbia10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an AccidentHigh Pressure Core Spray
05000364/LER-2017-002Farley10 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
05000440/LER-2017-004Perry4 October 201710 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an AccidentHigh Pressure Core Spray
05000395/LER-2017-002Summer31 January 201810 CFR 50.73(a)(2)(iv)(A), System ActuationFeedwater
05000364/LER-2017-003Farley10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsReactor Coolant System
05000461/LER-2017-005Clinton28 September 201710 CFR 50.73(a)(2)(iv)(A), System ActuationReactor Protection System
05000298/LER-2017-002Cooper10 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
05000313/LER-2017-002Arkansas Nuclear One – Unit 1
Arkansas Nuclear
13 November 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsEmergency Diesel Generator
05000373/LER-2017-003LaSalle14 April 201710 CFR 50.73(a)(2)(iv)(A), System ActuationFeedwater
Reactor Protection System
Main Turbine
05000289/LER-2017-001Three Mile Island
Three Mile Island Unit 1
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsReactor Coolant System
05000482/LER-2017-002Wolf Creek31 May 201710 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
05000298/LER-2017-004Cooper10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an AccidentPrimary containment
05000364/LER-2017-005Joseph M Farley Nuclear Plant, Unit 2
Farley
11 January 201810 CFR 50.73(a)(2)()
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)
05000390/LER-2017-005Watts Bar10 July 201710 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
05000461/LER-2017-001Clinton21 April 201710 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive MaterialSecondary containment
Standby Gas Treatment System
05000219/LER-2017-001Oyster Creek10 CFR 50.73(a)(2)(iv)(A), System ActuationReactor Protection System
Main Turbine
05000266/LER-2017-001Point Beach16 November 201710 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
05000341/LER-2017-001Fermi6 March 201710 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
05000334/LER-2017-002Beaver Valley13 September 201710 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
05000331/LER-2017-001Duane Arnold27 March 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(v), Loss of Safety Function
Primary containment
05000483/LER-2017-002Callaway13 October 201710 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
05000388/LER-2017-010Susquehanna10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsCore Spray
Residual Heat Removal
05000255/LER-2017-002Palisades17 July 2017Reactor Protection System
05000416/LER-2017-001Grand Gulf28 March 201710 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an AccidentHigh Pressure Core Spray
Reactor Core Isolation Cooling
Residual Heat Removal
Core Spray
05000390/LER-2017-010Watts Bar16 October 201710 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
05000458/LER-2017-001River Bend3 April 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsPrimary containment
Reactor Pressure Vessel
High Pressure Core Spray
05000220/LER-2017-003Nine Mile Point2 November 201710 CFR 50.73(a)(2)(iv)(A), System ActuationReactor Protection System
High Pressure Coolant Injection
Feedwater
Reactor Pressure Vessel
Main Steam Isolation Valve
Core Spray
05000293/LER-2017-008Pilgrim2 November 201710 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
05000440/LER-2017-001Perry1 May 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsSecondary containment
Reactor Pressure Vessel
05000390/LER-2017-003Watts Bar3 March 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000219/LER-2017-002Oyster Creek31 August 2017Steam Jet Air Ejector
05000368/LER-2017-001Arkansas Nuclear One – Unit 2
Arkansas Nuclear
30 May 201710 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
05000325/LER-2017-003Brunswick2 August 201710 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an AccidentControl Room Emergency Ventilation
05000461/LER-2017-002Clinton10 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
05000266/LER-2017-002Point Beach13 December 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsAuxiliary Feedwater
Feedwater
Reactor Coolant System
05000366/LER-2017-003Hatch13 April 201710 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
05000306/LER-2017-003Prairie Island10 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
05000446/LER-2017-002Comanche Peak Nuclear Power Plant Unit 227 October 2017Auxiliary Feedwater
Reactor Protection System
05000219/LER-2017-004Oyster Creek16 February 201810 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsReactor Protection System
Main Turbine
05000263/LER-2017-005Monticello20 September 201710 CFR 50.73(a)(2)(iv)(A), System ActuationEmergency Diesel Generator
05000390/LER-2017-012Watts Bar10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsEmergency Diesel Generator
Residual Heat Removal
Reactor Coolant System
05000259/LER-2017-001Browns Ferry Nuclear Plant, Unit 121 February 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000373/LER-2017-001LaSalle8 February 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsReactor Core Isolation Cooling
High Pressure Core Spray
05000389/LER-2017-004Saint Lucie18 December 201710 CFR 50.73(a)(2)(iv)(A), System ActuationFeedwater
Auxiliary Feedwater
Reactor Protection System
05000458/LER-2017-002River Bend18 April 201710 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
05000373/LER-2017-007LaSalle18 August 201710 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an AccidentCore Spray
Reactor Pressure Vessel
Residual Heat Removal
Reactor Building Ventilation
05000364/LER-2017-001Farley21 August 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsEmergency Diesel Generator
05000366/LER-2017-004Edwin I Hatch Nuclear Plant Unit 224 August 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsReactor Pressure Vessel
Main Steam Isolation Valve
Reactor Protection System
05000440/LER-2017-007Perry10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an AccidentHigh Pressure Core Spray
Reactor Core Isolation Cooling
Core Spray
05000247/LER-2017-001Indian Point22 August 201710 CFR 50.73(a)(2)(iv)(A), System ActuationFeedwater
Main Turbine
Emergency Diesel Generator
Auxiliary Feedwater
Reactor Protection System
Reactor Coolant System
05000395/LER-2017-001Vc Summer.- Unit 1
Summer
24 July 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsFeedwater
05000443/LER-2017-001Seabrook10 CFR 50.73(a)(2)(iv)(A), System ActuationFeedwater
Reactor Protection System
05000289/LER-2017-003Three 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-2017-004Monticello16 August 201710 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an AccidentHigh Pressure Coolant Injection
Reactor Core Isolation Cooling
05000483/LER-2017-001Callaway
Docket Number
15 August 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000388/LER-2017-003Susquehanna10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive MaterialSecondary containment
05000416/LER-2017-002Grand Gulf3 October 201710 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
05000261/LER-2017-001Robinson2 June 201710 CFR 50.73(a)(2)(iv)(A), System ActuationAuxiliary Feedwater
Feedwater
05000389/LER-2017-003Saint Lucie18 December 2017Auxiliary Feedwater
05000458/LER-2017-007River Bend Station — Unit 1 05000-458
River Bend
10 CFR 50.73(a)(2)(iv)(A), System ActuationMain Turbine
Feedwater
Primary containment
Reactor Protection System
05000306/LER-2017-002Prairie Island11 December 201710 CFR 50.73(a)(2)(ii)(A), Seriously DegradedReactor Coolant System
05000390/LER-2017-015Watts Bar8 January 201810 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000341/LER-2017-004Fermi9 October 201710 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
05000388/LER-2017-005Susquehanna10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive MaterialSecondary containment
HVAC
05000461/LER-2017-010Clinton5 February 201810 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
05000289/LER-2017-002Three Mile Island Unit 1
Three Mile Island
6 February 201710 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
Reactor Coolant System
05000374/LER-2017-001LaSalle24 March 201710 CFR 50.73(a)(2)(iv)(A), System ActuationReactor Protection System
Feedwater
Main Turbine
Main Steam Isolation Valve
05000388/LER-2017-008Susquehanna10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsPrimary containment
05000446/LER-2017-001Comanche Peak22 January 201810 CFR 50.73(a)(2)(v), Loss of Safety FunctionAuxiliary Feedwater
Feedwater
05000255/LER-2017-001Palisades24 May 2017Emergency Diesel Generator
Auxiliary Feedwater
05000260/LER-2017-004Browns Ferry7 July 2017
05000389/LER-2017-001Saint Lucie27 April 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsEmergency Diesel Generator
05000293/LER-2017-012Pilgrim13 November 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsEmergency Diesel Generator
05000387/LER-2017-004Susquehanna10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive MaterialSecondary containment
HVAC
05000425/LER-2017-001Vogtle10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsEmergency Diesel Generator
05000286/LER-2017-004Indian Point20 December 201710 CFR 50.73(a)(2)(iv)(A), System ActuationAuxiliary Feedwater
Feedwater
Reactor Protection System
Emergency Diesel Generator
Reactor Coolant System
05000260/LER-2017-001Browns Ferry14 April 2017High Pressure Coolant Injection
Reactor Core Isolation Cooling
05000440/LER-2017-002Perry10 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
05000321/LER-2017-003Docket Number10 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
05000382/LER-2017-002Waterford Steam Electric Station, Unit 3
Waterford
18 September 201710 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
05000458/LER-2017-004River Bend22 May 201710 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
05000263/LER-2017-003Monticello14 June 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsMain Steam Isolation Valve
Primary containment
05000395/LER-2017-003Vc Summer - Unit 1
Summer
12 December 201710 CFR 50.73(a)(2)(iv)(A), System ActuationFeedwater
Reactor Coolant System
05000397/LER-2017-002Columbia10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsSecondary containment
Residual Heat Removal
Shutdown Cooling
Reactor Pressure Vessel
05000333/LER-2017-001FitzPatrick13 March 201710 CFR 50.73(a)(2)(ii)Reactor Coolant System
Residual Heat Removal
Shutdown Cooling
Primary containment
05000244/LER-2017-001Ginna15 June 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsMain Steam Safety Valve
05000461/LER-2017-004Clinton22 November 201710 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
05000335/LER-2017-002Saint Lucie28 September 201710 CFR 50.73(a)(2)(ii)(B), Unanalyzed ConditionReactor Coolant System
Shutdown Cooling
05000321/LER-2017-002Hatch7 April 201710 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an AccidentHigh Pressure Coolant Injection
Reactor Pressure Vessel
Residual Heat Removal
Core Spray
Reactor Core Isolation Cooling
05000388/LER-2017-00610 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive MaterialHVAC
Secondary containment
05000397/LER-2017-007Columbia30 November 201710 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
05000390/LER-2017-016Watts Bar Nuclear Plant. Unit 120 February 201810 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
05000296/LER-2017-002Browns Ferry10 CFR 50.73(a)(2)(ii)(B), Unanalyzed ConditionEmergency Diesel Generator
05000325/LER-2017-004Brunswick Steam Electric Plant (Bsep) Unit115 November 201710 CFR 50.73(a)(2)(iv)(A), System ActuationEmergency Diesel Generator
Primary Containment Isolation System
Reactor Building Ventilation
Secondary containment
Standby Gas Treatment System
05000259/LER-2017-002Browns Ferry
Browns Ferry Nuclear Plant, Unit 1
1 May 2017
05000390/LER-2017-013Watts Bar24 January 201810 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsSecondary containment
05000482/LER-2017-003Wolf Creek2 November 201710 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
05000395/LER-2017-006Vc Summer - Unit 1
Summer
15 December 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000298/LER-2017-001Cooper10 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
05000458/LER-2017-003River Bend9 May 201710 CFR 50.73(a)(2)(iv)(A), System ActuationFeedwater
Main Turbine
Main Steam Isolation Valve
Reactor Protection System
05000388/LER-2017-009Susquehanna10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive MaterialSecondary containment
05000324/LER-2017-003Brunswick3 August 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsReactor Coolant System
05000528/LER-2017-001Palo Verde
Palo Verde Nuclear Generating Station Unit 1
14 June 201710 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
05000278/LER-2017-001Peach Bottom21 December 201710 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
05000370/LER-2017-001McGuire26 June 201710 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
05000397/LER-2017-006Columbia9 November 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000293/LER-2017-006Pilgrim13 June 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsIntermediate Range Monitor
05000260/LER-2017-002Browns FerryPrimary containment
Reactor Core Isolation Cooling
05000390/LER-2017-006Watts Bar31 July 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000220/LER-2017-002Nine Mile Point10 CFR 50.73(a)(2)(iv)(A), System ActuationMain Turbine
05000416/LER-2017-004Grand Gulf13 July 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsFeedwater
High Pressure Core Spray
05000254/LER-2017-003Quad Cities17 November 201710 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an AccidentControl Room Emergency Ventilation
HVAC
05000341/LER-2017-002Fermi16 March 201710 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
05000391/LER-2017-006Watts Bar10 CFR 50.73(a)(2)(iv)(A), System ActuationAuxiliary Feedwater
Reactor Protection System
05000416/LER-2017-007Grand Gulf5 February 201810 CFR 50.73(a)(2)(iv)(A), System ActuationEmergency Diesel Generator
Secondary containment
Reactor Core Isolation Cooling
05000263/LER-2017-006Monticello12 January 201810 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
05000335/LER-2017-001Saint Lucie2 May 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
Reactor Coolant System
05000293/LER-2017-011A Ler Number
Pilgrim
15 August 2017Secondary containment
Primary containment
Standby Gas Treatment System
05000461/LER-2017-006Clinton1 August 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsSecondary containment
05000251/LER-2017-001Turkey Point7 November 201710 CFR 50.73(a)(2)(iv)(A), System ActuationFeedwater
Reactor Protection System
05000391/LER-2017-005Watts Bar Nuclear Plant. Unit 2
Watts Bar
10 CFR 50.73(a)(2)(iv)(A), System ActuationReactor Coolant System
Emergency Diesel Generator
05000390/LER-2017-002Watts Bar22 February 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000416/LER-2017-006Grand Gulf12 October 201710 CFR 50.73(a)(2)(i)(A), Completion of TS ShutdownResidual Heat Removal
05000387/LER-2017-007Susquehanna10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive MaterialSecondary containment
05000364/LER-2017-004Joseph M. Farley Nuclear Plant. Unit 2
Farley
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsAuxiliary Feedwater
Reactor Coolant System
Main Steam Isolation Valve
05000382/LER-2017-001Waterford4 May 201710 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an AccidentShutdown Cooling
Reactor Coolant System
05000373/LER-2017-005LaSalle18 April 201710 CFR 50.73(a)(2)(iv)(A), System ActuationFeedwater
Reactor Protection System
Reactor Pressure Vessel
Main Steam Isolation Valve
05000390/LER-2017-014Watts Bar20 December 201710 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an AccidentControl Room Emergency Ventilation
05000424/LER-2017-002Vogtle29 June 201710 CFR 50.73(a)(2)(iv)(A), System ActuationEmergency Diesel Generator
Residual Heat Removal
05000321/LER-2017-004Hatch10 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
05000293/LER-2017-002Pilgrim25 May 201710 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an AccidentHigh Pressure Coolant Injection
Reactor Core Isolation Cooling
Core Spray
Primary containment
05000387/LER-2017-006Susquehanna10 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
05000335/LER-2017-003Saint Lucie13 November 2017Reactor Protection System
05000277/LER-2017-001Peach Bottom10 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
05000334/LER-2017-003Beaver Valley4 January 201810 CFR 50.73(a)(2)(iv)(A), System ActuationAuxiliary Feedwater
Feedwater
Reactor Protection System
05000458/LER-2017-006River Bend13 July 201710 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an AccidentHigh Pressure Core Spray
05000247/LER-2017-003Indian Point Unit 2
Indian Point
23 August 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsReactor Protection System
05000391/LER-2017-004Watts Bar10 CFR 50.73(a)(2)(iv)(A), System ActuationReactor Protection System
Auxiliary Feedwater
05000458/LER-2017-00812 October 201710 CFR 50.73(a)(2)(iv), System ActuationFeedwater
Reactor Protection System
05000318/LER-2017-001Calvert Cliffs19 April 201710 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsReactor Coolant System
05000390/LER-2016-004Watts Bar23 May 201610 CFR 50.73(a)(2)(iv)(A), System ActuationAuxiliary Feedwater
Main Turbine
Reactor Protection System
05000282/LER-2016-003Prairie Island4 March 201610 CFR 50.73(a)(2)(ii)(B), Unanalyzed ConditionReactor Coolant System
05000220/LER-2016-002Nine Mile Point26 September 201610 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual HeatReactor Protection System
05000387/LER-2016-005Susquehanna10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive MaterialSecondary containment
... further results