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Category:Report
MONTHYEARML24292A1502024-10-21021 October 2024 SSHAC Level 1 Demonstration Project ML24292A1392024-10-21021 October 2024 Applying a Graded Approach and Adapting Guidance on Site Characterization of External Hazards for Advanced Reactor and Microreactor Applications ML24292A1532024-10-21021 October 2024 Simulation of Physics-Based 0-10 Hz Synthetic Ground Motion Using High - Performance Computing Supporting Refinements to Regional Ground Motion Models for CEUS ML24213A2512024-09-23023 September 2024 A Case Study for Building Systems Theoretic Process Analysis at the Nuclear Regulatory Commission (NRC) ML24032A0102023-09-30030 September 2023 FY2023 University Nuclear Leadership Program (Unlp) Research and Development Award Executive Summaries ML23122A3062023-05-0303 May 2023 NRC Scientific Computer Code Investment Plan Public ML23030B8382023-02-0101 February 2023 Use of High Entropy Alloys (Heas) in Future Nuclear Applications ML22356A2072023-01-31031 January 2023 Volume 1 - Human Performance Test Facility ML22356A2082023-01-31031 January 2023 Volume 2 - Comparing Operator Workload and Performance Between Digitized and Analog Simulated Environments ML22356A2092023-01-31031 January 2023 Volume 3 - Supplemental Exploratory Analysis of Sensitivity of Workload Measures Ril 2022-11 ML22241A0392022-09-22022 September 2022 737 Max Digital Lessons Learned Report ML22192A0462022-09-0202 September 2022 Regulatory Considerations in Use of Digital Twin Technologies for Nuclear Reactor Application ML22235A6432022-09-0202 September 2022 Project Summary of Digital Twin Regulatory Viability in Nuclear Reactor Applications ML22143A9292022-06-0101 June 2022 NRC Technical Assessment of Electron Beam Welding ML22118A0902022-05-0505 May 2022 U.S. Nuclear Regulatory Commission Technical Assessment of Cold Spray ML22048B5932022-04-12012 April 2022 Attachment -1 Table - EDG Trips Bypass at Various Plants Based on TSs and FSARs ML21314A2282022-03-0808 March 2022 Impacts of Embrittlement on Reactor Pressure Vessel Integrity from a Risk-Informed Perspective Final Report ML21361A2612021-12-31031 December 2021 Letter Report - TLR-RES/DE/REB-2021-17, Technical Challenges and Gaps in Digital Twin Enabling Technologies for Nuclear Reactor Applications ML21361A1762021-12-31031 December 2021 Ril 2021-18, Report on High Energy Arcing Fault Experiments, Experimental Results from Open Box Enclosures (NIST Tn 2198) (SAND2021-16075 R) ML21292A1882021-11-17017 November 2021 Technical Assessment of Additive Manufacturing-Laser Directed Energy Deposition ML21312A0862021-11-0808 November 2021 2021 Research Grant Executive Summaries ML21280A3632021-10-26026 October 2021 Watermarked for ACRS - Response to Public Comments on Proposed RG 1.244 -10-7 ML21266A0452021-09-28028 September 2021 Probabilistic Leak-Before-Break Evaluations of Pressurized-Water Reactor Piping Systems Using the Extremely Low Probability of Rupture Code ML21175A1432021-07-21021 July 2021 Office of Nuclear Regulatory Research FY2021-23 Planned Research Activities ML21174A1832021-06-25025 June 2021 RES Addendum to ANL-13/08 ML21109A1232021-05-31031 May 2021 TLR-RES/DE/CIB-2021-07, Additional Technical Information in Support of the Review of Subpart a, Graphite Materials ML21145A0882021-05-24024 May 2021 Fellowship Executive Summaries ML21145A0902021-05-24024 May 2021 Trade School and Community College Scholarship Executive Summary ML21145A0892021-05-24024 May 2021 Scholarship Executive Summaries ML21145A0872021-05-24024 May 2021 Faculty Development Executive Summaries ML21155A1352021-05-24024 May 2021 Trade School and Community College Scholarship Executive Summary ML21155A1342021-05-24024 May 2021 Scholarship Executive Summaries ML21155A1332021-05-24024 May 2021 Fellowship Executive Summaries ML21155A1322021-05-24024 May 2021 Faculty Development Executive Summaries ML21113A0812021-05-0606 May 2021 Ril AMT Workshop Summary ML21097A0632021-04-0707 April 2021 Fy 2020 Research and Development Grant Executive Summaries ML21084A0412021-03-31031 March 2021 Tlr RES DE CIB-CMB-2021-04, Corrosion in Gas-Cooled Reactors ML21084A0392021-03-31031 March 2021 TLR-RES/DE/CIB-CMB-2021-03, Technical Assessment of Materials Compatibility in Molten Salt Reactors ML21088A0132021-03-31031 March 2021 TLR-RES/DE/CIB-CMB-2021-05 - Status of Anlwr Research Activities - Materials Chemistry and Component Integrity ML21088A0472021-03-31031 March 2021 NRC Non-Light Water Reactor (non-LWR) Vision and Strategy, Volume 5 - Radionuclide Characterization, Criticality, Shielding, and Transport in the Nuclear Fuel Cycle ML20345A0032021-01-19019 January 2021 TLR-RES/DE/CIB-2020-11, Basis for a Potential Alternative to Revision 2 of Regulatory Guide 1.99 ML20351A2042021-01-0808 January 2021 NRC Technical Assessment of Additive Manufacturing - Laser Powder Bed Fusion ML20287A1982021-01-0101 January 2021 Public Comment Dispositions on DG-1370 for Regulatory Guide (RG) 1.191, Rev 1, Fire Protection Program for Nuclear Power Plants During Decommissioning ML20308A7442020-11-0303 November 2020 NRC Non-Light Water Reactor (Non-LWR) Vision and Strategy, Volume 5 Radionuclide Characterization, Criticality, Shielding, and Transport in the Nuclear Fuel Cycle, Draft ML20311A2622020-10-19019 October 2020 Technical Letter Report - TLR-RES/DE/CIB-2020-06, Evaluation of PWSCC Subcritical Crack Growth in Complex Geometries Using Abaqus Xfem ML20245E1862020-09-30030 September 2020 RIL-2020-09, International Workshop on Advanced Non-Light Water Reactor - Materials and Component Integrity ML20227A3882020-09-11011 September 2020 Enclosure 1 - Table FY2019 Risk-Informed Activitity Website Links ML20227A3902020-09-11011 September 2020 Enclosure 3 - Risk Explanation FY2020 Risk-Informed Activity Website ML20245E4572020-09-0101 September 2020 Draft Preface ML20164A2132020-07-31031 July 2020 Response to Comments on DG-3036 for RG 3.15, Rev 2, Standard Format and Content of License Applications for Receipt and Storage of Unirradiated Power Reactor Fuel and Associated Radioactive Material at a Nuclear Power Plant 2024-09-23
[Table view]Some use of "" in your query was not closed by a matching "". Category:Miscellaneous
MONTHYEARML24292A1502024-10-21021 October 2024 SSHAC Level 1 Demonstration Project ML24292A1392024-10-21021 October 2024 Applying a Graded Approach and Adapting Guidance on Site Characterization of External Hazards for Advanced Reactor and Microreactor Applications ML24292A1532024-10-21021 October 2024 Simulation of Physics-Based 0-10 Hz Synthetic Ground Motion Using High - Performance Computing Supporting Refinements to Regional Ground Motion Models for CEUS ML24032A0102023-09-30030 September 2023 FY2023 University Nuclear Leadership Program (Unlp) Research and Development Award Executive Summaries ML22048B5932022-04-12012 April 2022 Attachment -1 Table - EDG Trips Bypass at Various Plants Based on TSs and FSARs ML21314A2282022-03-0808 March 2022 Impacts of Embrittlement on Reactor Pressure Vessel Integrity from a Risk-Informed Perspective Final Report ML21312A0862021-11-0808 November 2021 2021 Research Grant Executive Summaries ML21280A3632021-10-26026 October 2021 Watermarked for ACRS - Response to Public Comments on Proposed RG 1.244 -10-7 ML21155A1322021-05-24024 May 2021 Faculty Development Executive Summaries ML21145A0902021-05-24024 May 2021 Trade School and Community College Scholarship Executive Summary ML21145A0892021-05-24024 May 2021 Scholarship Executive Summaries ML21145A0882021-05-24024 May 2021 Fellowship Executive Summaries ML21145A0872021-05-24024 May 2021 Faculty Development Executive Summaries ML21155A1352021-05-24024 May 2021 Trade School and Community College Scholarship Executive Summary ML21155A1342021-05-24024 May 2021 Scholarship Executive Summaries ML21155A1332021-05-24024 May 2021 Fellowship Executive Summaries ML20287A1982021-01-0101 January 2021 Public Comment Dispositions on DG-1370 for Regulatory Guide (RG) 1.191, Rev 1, Fire Protection Program for Nuclear Power Plants During Decommissioning ML20164A2132020-07-31031 July 2020 Response to Comments on DG-3036 for RG 3.15, Rev 2, Standard Format and Content of License Applications for Receipt and Storage of Unirradiated Power Reactor Fuel and Associated Radioactive Material at a Nuclear Power Plant NUREG-2233, EPRI 3002016054 Comments Resolution2020-03-31031 March 2020 NUREG-2233 EPRI 3002016054 Comments Resolution ML19156A1282020-02-0606 February 2020 Public Comments Rg 1.151 ML20015A3362020-01-16016 January 2020 Status of Recommendations: Audit of Nrc'S Process for Developing and Coordinating Research Activities (OIG-19-A-06) (RES Response) ML19175A0482019-12-19019 December 2019 Public Comments on Rg 1.180 ML19248C6472019-12-0404 December 2019 Enclosure 4 - Staff Report Documenting Technical Basis for the Alternative FHA Model NUREG-2178, Comment Resolution - NUREG-2178 Vol 2 Final2019-08-31031 August 2019 Comment Resolution - NUREG-2178 Vol 2 Final ML19101A3962019-06-30030 June 2019 DG-1329 (RG-1.8 R-4) Public Comment Response ML19162A4022019-06-13013 June 2019 01_04_Exercise_C Task 5 MSO Analysis ML19162A4052019-06-13013 June 2019 01_05_Exercise_B Task 7 Cutset Analysis Print Color ML18172A1912018-08-22022 August 2018 Assessment Plan - Enclosure 2 ML18172A1902018-08-22022 August 2018 Assessment Plan - Enclosure 1 ML16315A1272018-06-30030 June 2018 Public Comment Resolutions for DG-1309 ML17319A5502017-12-0707 December 2017 NRC Non-Light Water Reactor Vision and Strategy - Strategy 2 Near-Term Implementation Action Plan Progress Report for Fiscal Year 2017 ML17278A7592017-10-0505 October 2017 Soarca Sequoyah Updated Draft Executive Summary ML23123A3512017-10-0202 October 2017 Response to SRM-22-0009: Proposed Limited Revision to Policy Statement on Criteria for Reporting Abnormal Occurrences ML16214A1992016-08-11011 August 2016 an Assessment of Core Damage Frequency for Byron/Braidwood Backit Appeal Review ML15097A0762015-04-0606 April 2015 Soarca Peach Bottom 2005 Site File ML12024A0782011-12-28028 December 2011 State-of-the-Art Reactor Consequence Analysis (Soarca); Exclusive Summary for the Full NUREG for Peach Bottom and Surry ML1120701442011-07-26026 July 2011 Draft Letter Report, Entitled Risk-Informing EP Oversight: Evaluation of EALs Using Saphia Pilot Study of Peach Bottom and Surry ML0209305252002-03-31031 March 2002 SMSAB-02-01: Analysis Report: Comparison Between TRAC-M Version 3782 and RELAP5 MOD 3.2.2 Gamma Calculations of Selected Pressurized Thermal Shock Scenarios of the Oconee Unit 1 Plant 2024-10-21
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BWR4 RHR System MSO Analysis The PRA credits the RHR system in 5 ways. The first is LPCI with the RHR pumps taking suction from the suppression pool. The second is LPCI with the RHR pumps taking suction from the CST.
The third is containment pressure control with drywell sprays. The fourth is decay heat removal with suppression pool cooling. The fifth is decay heat removal with shutdown cooling. (Refer Figures 1 through 3 of System Drawings Handout).
RHR System Modes Modeled in the PRA
- 1. LPCI injection with suction on the suppression pool is credited in the PRA model for low pressure injection before a primary containment vent (if required) and after a successful primary containment vent.
- 2. The drywell sprays are credited for drywell pressure and temperature control in the PRA model.
- 3. Suppression pool cooling is credited for decay heat removal in PRA model.
- 4. Shutdown cooling is credited for decay heat removal in the PRA model only after a successful primary containment vent. The mode of shutdown cooling modeled in both models is through the SDC suction valves from the RPV.
Postulated MSOs BWR4 HPCI MSO Analysis The fire PRA credits the HPCI system in 2 ways. The first is initial short term (<4 hours) high pressure injection to the RPV with suction on the CST. The second is long term (>4 hours) high pressure injection to the RPV with suction on the suppression pool. (Refer Figure 4 of System Drawings Handout).
HPCI System Modes Modeled in the PRA HPCI is credited in both the PRA model for injection to the RPV for both the short term (initial source) and long term accident sequences. The short term model credits only the CST as a
suction source. The long term model credits the suppression pool as a suction source but requires successful suppression pool cooling.
Postulated MSOs Electrical System MSO Analysis Electrical System Modes Modeled in the PRA The PRA credits the availability of power from the 480V and Higher AC Electric Power System.
A study was performed to determine the impact on the offsite power system of the potential overload conditions due to multiple spurious breaker actuations. The study concluded that the offsite power transformers could be overloaded if two buses are connected. This is not modeled in the PRA due to low probability of multiple spurious operation of breakers (Refer Figure 5 of System Drawings Handout).
Postulated MSOs