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| <table class="wikitable sortable"> | | <table class="wikitable sortable"> |
| <th>[[:Category:Site|Site]]</th><th>#</th><th>[[:Category:Company|Company]]</th><th>Event lists</th> | | <th>[[:Category:Site|Site]]</th><th>#</th><th>[[:Category:Company|Company]]</th><th>Event lists</th> |
| {{#ask:[[Category:Site]] | | {{#ask:[[Category:Site]][[site type::Plant]] |
| |format=template | | |format=template |
| |link=none | | |link=none |
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| {{#ask:[[Category:Licensee Event Report]] | | {{#ask:[[Category:Licensee Event Report]] |
| |?site | | |?site |
| |?Report date | | |?start date |
| |?Reporting criterion | | |?Reporting criterion |
| |?System | | |?System |
| |sort=LER year | | |?topic |
| | |sort=start date |
| |order=descending | | |order=descending |
| |limit=250 | | |limit=50 |
| }} | | }} |
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 | Start date | Reporting criterion | System | Topic |
---|
05000318/LER-2023-004, Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer | Calvert Cliffs | 16 January 2024 | | Reactor Protection System | |
05000318/LER-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip | Calvert Cliffs | 8 January 2024 | | Steam Generator Feedwater Auxiliary Feedwater | |
05000318/LER-2023-002, Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer | Calvert Cliffs | 8 January 2024 | | Reactor Protection System | |
05000483/LER-2023-001, Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications | Callaway | 29 November 2023 | | | |
05000457/LER-2023-001, Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case | Braidwood | 17 November 2023 | | Auxiliary Feedwater | |
05000483/LER-2022-002, Forward LER 2022-002-00 for Callaway Plant, Unit 1, Containment Spray and Cooling Systems, and a Condition Which Could Have Prevented Fulfillment of the Safety Function of the Containment Spray System (Letter Only) | Callaway | 18 August 2022 | | Containment Spray | |
05000250/LER-2021-004, Cancelation of LER 2021-004, Through-Wall Leakage from Core Exit Thermocouple Tubing | Turkey Point | 28 March 2022 | | | Through-Wall Leakage |
05000318/LER-2022-001, Forwards LER 2022-001-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip Due to High Reactor Coolant System Pressure | Calvert Cliffs | 3 March 2022 | | Reactor Coolant System | |
05000318/LER-2021-003, Forward LER 2021-003-00 for Calvert Cliffs Nuclear Power Plant, Unit No. 2, Auxiliary Feedwater Pump Inoperable Due to Improper Reset of Trip Throttle Valve. Cover Letter Only | Calvert Cliffs | 23 September 2021 | | Auxiliary Feedwater | |
05000327/LER-2021-002, Letter Forwarding LER 2021-002-00 & LER 2021-001-00 for Sequoyah Nuclear Plant, Units 1 & 2 | Sequoyah | 22 September 2021 | | | |
05000327/LER-2021-001, & LER 2021-001-00 for Sequoyah Nuclear Plant, Units 1 & 2, Ice Bed Inoperable Due to Exceeding Surveillance Requirement Frequency | Sequoyah | 22 September 2021 | | | Safe Shutdown |
05000456/LER-2021-001, Forward LER 2021-001-00 for Braidwood Station, Unit 1, Train a and B Source Range Neutron Flux Trip Functions Bypassed During Plant Startup | Braidwood | 21 June 2021 | | | |
05000483/LER-2020-005, Forward LER 2020-005-00 for Callaway Plant, Unit 1, Inoperable Isolation Valve Between Safety-Related Essential Service Water and Nonsafety-Related Service Water | Callaway | 17 November 2020 | | Service water | |
05000281/LER-2020-001, Cancellation of LER 2020-001-00 for Surry Power Station Unit 2 Re Loss of Containment Cooling Affecting Containment Partial Pressure Indication | Surry | 6 November 2020 | | Reactor Coolant System | |
05000483/LER-2020-002, Submittal of LER 2020-002-00 for Callaway, Unit 1, Reactor Trip and AFW Actuation Following Spurious MFRV Closure | Callaway | 3 June 2020 | | Feedwater Auxiliary Feedwater | |
05000482/LER-2020-001, Transmittal of LER 2020-001-00 for Wolf Creek, Plant Shutdown Due to Inoperable Containment Purge Isolation Valves | Wolf Creek | 1 April 2020 | | | |
05000461/LER-2020-001, Submittal of LER 2020-001-00 for Clinton Power Station, Unit 1, Reportable Contraband Event | Clinton | 23 March 2020 | | | Contraband |
05000366/LER-2020-001 | Hatch | 2 March 2020 | | Primary containment | Large early release frequency |
05000423/LER-2019-001 | Millstone | 13 February 2020 | | Steam Generator Emergency Diesel Generator Auxiliary Feedwater Decay Heat Removal | |
05000280/LER-2019-002 | Surry | 4 February 2020 | | Service water Auxiliary Feedwater Main Steam | Safe Shutdown Unanalyzed Condition Tornado Missile Enforcement Discretion Tornado Generated Missile Tornado Missile Protection |
05000461/LER-2017-010 | Clinton | 9 December 2017 5 February 2018 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment Reactor Protection System Main Steam Isolation Valve Reactor Water Cleanup Standby Gas Treatment System Emergency Core Cooling System Control Rod | Unanalyzed Condition |
05000289/LER-2017-004 | Three Mile Island Three Mile Island Unit 1 | 5 February 2018 | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(i)(B), Prohibited by Technical Specifications | Emergency Diesel Generator | Safe Shutdown Unanalyzed Condition Enforcement Discretion Tornado Generated Missile Tornado Missile Protection |
05000388/LER-2017-010 | Susquehanna | 2 February 2018 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Core Spray Residual Heat Removal Low Pressure Coolant Injection | |
05000391/LER-2017-005 | Watts Bar Watts Bar Nuclear Plant. Unit 2 | 25 January 2018 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Reactor Coolant System Emergency Diesel Generator Emergency Core Cooling System | Safe Shutdown |
05000293/LER-2017-013 | Pilgrim | 26 November 2017 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 | Secondary containment Primary containment Standby Gas Treatment System | Mission time Recently irradiated fuel |
05000390/LER-2017-013 | Watts Bar | 6 September 2017 24 January 2018 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Secondary containment Auxiliary Building Gas Treatment System Shield Building | Safe Shutdown Safe Shutdown Earthquake Past operability Probabilistic Risk Assessment |
05000446/LER-2017-003 | Comanche Peak Comanche Peak Nuclear Power Plant, Unit 2 | 25 November 2017 22 January 2018 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | Steam Generator Feedwater Reactor Protection System Auxiliary Feedwater Main Turbine | |
05000498/LER-2017-002 | South Texas | 22 January 2018 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | HVAC Control Room Emergency Ventilation | Large early release frequency |
05000263/LER-2017-006 | Monticello | 14 November 2017 12 January 2018 | 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)(v), Loss of Safety Function | Reactor Coolant System Reactor Protection System Main Steam Isolation Valve Main Steam Line Main Steam | Safe Shutdown Half scram Fuel cladding |
05000306/LER-2017-003 | Prairie Island | 11 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)(i)(B), Prohibited by Technical Specifications | Service water Main Steam Isolation Valve Main Steam Line Containment Spray | |
05000364/LER-2017-005 | Farley Joseph M Farley Nuclear Plant, Unit 2 | 3 January 2017 11 January 2018 | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)() | | |
05000272/LER-2017-001 | Salem | 9 November 2017 8 January 2018 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Steam Generator Reactor Coolant System | Safe Shutdown |
05000390/LER-2017-015 | Watts Bar | 9 November 2017 8 January 2018 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | Safe Shutdown |
05000254/LER-2017-004 | Quad Cities | 7 November 2017 5 January 2018 | | Feedwater High Pressure Coolant Injection Core Spray Low Pressure Coolant Injection | |
05000461/LER-2017-009 | Clinton Clinton Power Station, Unit 1 . | 5 November 2017 4 January 2018 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | Secondary containment Service water Standby Gas Treatment System | |
05000334/LER-2017-003 | Beaver Valley | 7 November 2017 4 January 2018 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Steam Generator Feedwater Reactor Protection System Auxiliary Feedwater Control Rod | |
05000219/LER-2017-005 | Oyster Creek | 9 October 2017 3 January 2018 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Emergency Diesel Generator | Safe Shutdown Mission time |
05000296/LER-2017-002 | Browns Ferry | 29 December 2017 | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | Emergency Diesel Generator | Safe Shutdown Unanalyzed Condition Time of Discovery Large early release frequency |
05000249/LER-2017-001 | Dresden | 27 December 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)(i)(B), Prohibited by Technical Specifications | Reactor Pressure Vessel Standby Liquid Control Control Rod | Time of Discovery Enforcement Discretion Through Wall Leak |
05000364/LER-2017-004 | Farley Joseph M. Farley Nuclear Plant. Unit 2 | 22 December 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Steam Generator Reactor Coolant System Main Steam Isolation Valve Auxiliary Feedwater Main Steam Line | |
05000395/LER-2017-005 | Summer | 7 January 2017 22 December 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Steam Generator Feedwater Decay Heat Removal Main Condenser Control Rod | Large early release frequency |
05000364/LER-2017-003 | Farley | 20 December 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Reactor Coolant System | Time of Discovery |
05000278/LER-2017-001 | Peach Bottom | 23 October 2017 20 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 | Time of Discovery Pressure Boundary Leakage |
05000390/LER-2017-016 | Watts Bar Nuclear Plant. Unit 1 | 20 December 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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 | Emergency Diesel Generator Auxiliary Feedwater | Safe Shutdown Offsite Circuit |
05000390/LER-2017-014 | Watts Bar | 30 October 2017 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 | Safe Shutdown Probabilistic Risk Assessment |
05000286/LER-2017-004 | Indian Point | 3 November 2017 20 December 2017 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | Steam Generator Reactor Coolant System Feedwater Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater Permanent Magnet Generator Main Condenser Control Rod Main Steam | Temporary Modification |
05000364/LER-2017-002 | Farley | 19 December 2017 | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | Steam Generator Reactor Coolant System Main Steam Safety Valve Main Condenser Main Steam | |
05000395/LER-2017-006 | Summer Vc Summer - Unit 1 | 31 October 2017 15 December 2017 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | Grab sample |
05000261/LER-2017-002 | Robinson | 24 October 2017 14 December 2017 | | | Time of Discovery Contraband Scaffolding |
05000266/LER-2017-003 | Point Beach | 30 October 2017 13 December 2017 | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | Reactor Coolant System | Safe Shutdown Boric Acid |