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Plant-Specific Actions in Response to the Japan Nuclear Accident: Braidwood Station, Unit 2

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Photograph of Braidwood 2

NRC Documentation and Acknowledgement of Completion

Braidwood Station, Units 1 and 2 – Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned From the Fukushima Dai-Ichi Accident
Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-ichi Accident – Supplemental Information

Orders and Requests for Information Licensee Responses/Submittals

Orders
Order for Mitigation Strategies to Respond to Extreme Natural Events Resulting in the Loss of Power at Plants [+] Show More
Licensee Integrated Plan (due February 28, 2013) NRC Interim Staff Evaluation of Integrated Plans NRC Audit Plan NRC Audit Report Licensee Compliance Letter and Final Integrated Plan NRC Safety Evaluation of Integrated Plan NRC Inspection Report Status Updates by Licensee 1st update (due October 30, 2012) 2nd update (due September 1, 2013) 3rd update (due February 28, 2014) 4th update (due September 1, 2014) 5th update (due February 28, 2015)

** Order for Ensuring Reliable Hardened Containment Vents is not applicable to this plant **


Order for Enhancing Spent Fuel Pool Instrumentation [+] Show More
Licensee Integrated Plan (due February 28, 2013) NRC Interim Staff Evaluation of Integrated Plans NRC Audit Plan NRC Audit Report Licensee Compliance Letter NRC Safety Evaluation of Integrated Plan NRC Inspection Report Status Updates by Licensee 1st update (due October 30, 2012) 2nd update (due September 1, 2013) 3rd update (due February 28, 2014) 4th update (due September 1, 2014) 5th update (due February 28, 2015)

Request for Information

Request for Information for Seismic and Flooding Reevaluations and Walkdowns, and Reevaluations of Emergency Communications Systems and Staffing Levels
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Seismic Reevaluations
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- Licensee Hazard Evaluation
- NRC Staff Assessment of Hazard Evaluation
- Licensee Expedited Seismic Evaluation Process (ESEP) Report
- NRC Staff Assessment of ESEP Report
- Limited Scope Evaluations (as applicable for each reactor site)
  - Licensee High Frequency Evaluation
  - NRC Staff Assessment of High Frequency Evaluation
  - Licensee Spent Fuel Pool Evaluation
  - NRC Staff Assessment of Spent Fuel Pool Evaluation
- Licensee Seismic Probabilistic Risk Assessment (SPRA) Report (if required)
- NRC Staff Assessment of SPRA Report
- Licensee Reevaluated Hazard (Seismic) Mitigating Strategies Assessment
- NRC Staff Response to Reevaluated Hazard (Seismic) Mitigating Strategies Assessment

Flooding Reevaluations
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Seismic Walkdowns
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Flooding Walkdowns
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Reevaluations of Emergency Communications Systems
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- Licensee 60-day Schedule Deviations
- Licensee Communication Assessment
- Licensee Communication Assessment Supplement
- NRC Evaluation of Communication Assessment

Reevaluations of Staffing Levels
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- Licensee 60-day Schedule Deviations
- Licensee Response to Staffing Items 3-5
- Licensee Phase 1 Staffing Assessment (applicable only to multi-unit sites)
- NRC Evaluation of Phase 1 Staffing Assessment
- Licensee Phase 2 Staffing Assessment
- NRC Evaluation of Phase 2 Staffing Assessment

Page Last Reviewed/Updated Thursday, November 4, 2021

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Page Last Reviewed/Updated Thursday, November 4, 2021