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Press Release-05-009, NRC Extends Opportunity to Request Use of New Standard for Addressing Existing Fire Protection Issues
PMNS20180840, Public Meeting with Nuclear Energy Institute to Discuss Use of New Probabilistic Risk Assessment Methods Following Issuance of an Amendment to Utilize a Risk-Informed Process
PMNS20180136, Public Meeting Between U.S. Nuclear Regulatory Commission Staff and Industry to Continue Discussions Between the NRC and Industry RISK-INFORMED Steering Committees
HNP-06-067, HNP-06-067, FAQs Requesting Additional Guidance or Clarification Regarding Transition to NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants. April 2007 FAQ Emails
RS-06-083, 60-Day Response to Generic Letter 2006-03, Potentially Nonconforming Hemyc and MT Fire Barrier Configurations.
PMNS20181141, Meeting with the Nuclear Energy Institute (NEI) and Other Industry Representatives to Discuss Use of New Probabilistic Risk Assessment (PRA) Methods Following Issuance of an Amendment to Use a Risk-Informed Process
PMNS20190332, Public Meeting with Nuclear Energy Institute to Discuss Use of New Probabilistic Risk Assessment Methods Following Issuance of an Amendment to Utilize a Risk-Informed Process
PMNS20190786, Public Meeting with the Nuclear Energy Institute to Discuss the Use of New Probabilistic Risk Assessment Methods Following the Issuance of an Amendment to Utilize a Risk-Informed Process
PMNS20190943, Public Meeting with the Nuclear Energy Institute to Discuss Changes to a Proposed Licensing Condition Regarding the Use of New Probabilistic Risk Assessment Methods Following the Issuance of a License Amendment to Utilize Risk-Informed
PMNS20200178, Public Meeting to Discuss Proposed Revisions to Technical Specifications Task Force (TSTF)-505 License Condition Regarding Newly Developed Probabilistic Risk Assessment (PRA) Methods
RS-04-015, Comment (160) of Melissa Nolan Regarding Draft Criteria on Manual Actions to Achieve Post-Fire Safe Shutdown
PMNS20210644, Meeting Between NRC and Industry Representatives to Exchange Information Pertaining to Risk Insights Obtained from Reviews of the Duane Arnold Energy Center (DAEC) Derecho on August 10, 2020
PMNS20200380, Public Meeting to Discuss NRC Information Needs to Review Amendment Requests Related to Technical Specifications Task Force (TSTF)-505
Information Notice 2023-01, Risk Insights from High Energy Arcing Fault Operating Experience and Analyses
PMNS20211316, Public Meeting to Discuss Proposed Revisions to Regulatory Guide (RG) 1.201, an Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities
PMNS20210653, Public Meeting to Discuss Licensee Interest in Adopting Regulatory Guide (RG) 1.200, Revision 3 for Risk-Informed Programs Previously Approved Under RG 1.200, Revision 2
PMNS20210643, Public Meeting to Discuss Technical Specification Changes to Technical Specifications Task Force (TSTF)-505 to Incorporate Regulatory Guide (RG) 1.200, Revision 3
PMNS20201194, Public Meeting to Discuss Revision to Regulatory Guide (RG) 1.200, an Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities
PMNS20200472, Public Meeting to Discuss NRC Technical Specification Changes to Technical Specifications Task Force (TSTF)-505 That Would Allow Licensee Control of Newly Developed PRA Methods in Accordance with Regulatory Guide (RG) 1.200
PMNS20240961, NRC Public Meeting to Discuss LWR Reactor Accident Analysis Modenization Efforts
SECY-24-0070, Weekly Information Report Week Ending August 16, 2024
SECY-24-0080, Weekly Information Report Week Ending September 20, 2024
PMNS20240805, Public Meeting to Discuss ANSI/ANS-30.3-2022, American National Standard Light Water Reactor Risk-Informed, Performance-Based Design
SECY-24-0084, Weekly Information Report Week Ending October 4, 2024
PMNS20191346, Public Meeting to Discuss Proposed Revisions to Regulatory Guide (RG) 1.200, an Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities
PMNS20181257, Meeting with the Nuclear Energy Institute (NEI) and Other Industry Representatives to Discuss NRC Feedback on NEI 17-07, Performance of PRA Peer Review Using the Asme/Ans PRA Standard
NUREG-2225, Basis for the Treatment of Potential Common-Cause Failure in the Significance Determination Process
OIG-17-A-26, Status of Recommendations: Evaluation of Proposed NRC Modifications to the Probabilistic Risk Assessment Process, Dated August 7, 2018
PMNS20180873, (Copied from E. Millers meeting- Update All Fields!)
SECY-08-0171, Task 5 of SECY-08-0171. Please Share This Email on Reg Perf Metric with the Participants of the Monday Afternoons Call
SECY-25-0003, Weekly Information Report Week Ending January 3, 2025
SECY-24-0100, Weekly Information Report Week Ending November 29, 2024
SECY-24-0068, Weekly Information Report Week Ending August 9, 2024
SECY-24-0077, Weekly Information Report Week Ending September 6, 2024
SECY-25-0060, Weekly Information Report Week Ending June 20, 2025