https://ramtar.epri.com/index.php?action=history&feed=atom&title=Human_Reliability_Analysis 2026-04-19T07:11:25Z Revision history for this page on the wiki MediaWiki 1.39.6 https://ramtar.epri.com/index.php?title=Human_Reliability_Analysis&diff=307&oldid=prev 2025-01-24T18:23:31Z

<p>3 revisions imported</p> <table style="background-color: #fff; color: #202122;" data-mw="interface"> <tr class="diff-title" lang="en"> <td colspan="1" style="background-color: #fff; color: #202122; text-align: center;">← Older revision</td> <td colspan="1" style="background-color: #fff; color: #202122; text-align: center;">Revision as of 18:23, 24 January 2025</td> </tr><tr><td colspan="2" class="diff-notice" lang="en"><div class="mw-diff-empty">(No difference)</div> </td></tr></table>

Admin https://ramtar.epri.com/index.php?title=Human_Reliability_Analysis&diff=306&oldid=prev 2025-01-17T22:43:55Z

<p><span dir="auto"><span class="autocomment">HRA</span></span></p> <table style="background-color: #fff; color: #202122;" data-mw="interface"> <col class="diff-marker" /> <col class="diff-content" /> <col class="diff-marker" /> <col class="diff-content" /> <tr class="diff-title" lang="en"> <td colspan="2" style="background-color: #fff; color: #202122; text-align: center;">← Older revision</td> <td colspan="2" style="background-color: #fff; color: #202122; text-align: center;">Revision as of 22:43, 17 January 2025</td> </tr><tr><td colspan="2" class="diff-lineno" id="mw-diff-left-l8">Line 8:</td> <td colspan="2" class="diff-lineno">Line 8:</td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==HRA==</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==HRA==</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Assessment (HRA) is required as part of the final safety analysis report (FSAR) for any licensing application using any of the potential licensing pathways.</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Assessment (HRA) is required as part of the final safety analysis report (FSAR) for any licensing application using any of the potential licensing pathways.</div></td></tr> <tr><td class="diff-marker" data-marker="−"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #ffe49c; vertical-align: top; white-space: pre-wrap;"><div>Hamza and Diaconeasa introduced a framework for incorporating HRA in the early stages of design either at the pre-conceptual or conceptual design phase to develop significant operator actions early, thereby meeting the needs for advanced reactors in their current stage [[References| [30]]].  The PRA Standard for Advanced Non-LWR Nuclear (NLWR) Power Plants (not cooled by water) [[References| [6]]] specifies high-level and supporting technical requirements for 18 technical elements needed to create a full-scope PRA. Examples are Plant Operating States, Initiating Events Analysis, Event Sequences Analysis, Systems Analysis, and some less familiar ones such as Mechanistic Source Term Analysis, Radiogical Consequence Analysis and Risk Integration. Like the ASME/ANS Level 1 PRA Standard, the NLWR Standard includes two PRA Capability Categories, CC-I and CC-II. Human actions are incorporated throughout the standard. In stakeholder interviews it was determined that a there was particular concern for the development of operator actions in response to issues that cover multiple operator shifts and for errors of commission in relation to HRA as these may not be the dominant sources of human error for current <del style="font-weight: bold; text-decoration: none;">LWRs</del>, but could become dominant for advanced reactors.  Research Roadmap (EPRI [https://www.epri.com/research/products/000000003002026495 3002026495]) actions that support emphasizing the importance of EoCs as a source of human error for advanced reactors:</div></td><td class="diff-marker" data-marker="+"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #a3d3ff; vertical-align: top; white-space: pre-wrap;"><div>Hamza and Diaconeasa introduced a framework for incorporating HRA in the early stages of design either at the pre-conceptual or conceptual design phase to develop significant operator actions early, thereby meeting the needs for advanced reactors in their current stage [[References| [30]]].  The PRA Standard for Advanced Non-LWR Nuclear (NLWR) Power Plants (not cooled by water) [[References| [6]]] specifies high-level and supporting technical requirements for 18 technical elements needed to create a full-scope PRA. Examples are Plant Operating States, Initiating Events Analysis, Event Sequences Analysis, Systems Analysis, and some less familiar ones such as Mechanistic Source Term Analysis, Radiogical Consequence Analysis and Risk Integration. Like the ASME/ANS Level 1 PRA Standard, the NLWR Standard includes two PRA Capability Categories, CC-I and CC-II. Human actions are incorporated throughout the standard. In stakeholder interviews it was determined that a there was particular concern for the development of operator actions in response to issues that cover multiple operator shifts and for errors of commission in relation to HRA as these may not be the dominant sources of human error for current <ins style="font-weight: bold; text-decoration: none;">water reactors</ins>, but could become dominant for advanced reactors.  Research Roadmap (EPRI [https://www.epri.com/research/products/000000003002026495 3002026495]) actions that support emphasizing the importance of EoCs as a source of human error for advanced reactors:</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Enhancements to Licensing Process</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Enhancements to Licensing Process</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Industry Recommendations for Regulatory (NRC / CNSC) Guidance on Operator Staffing</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Industry Recommendations for Regulatory (NRC / CNSC) Guidance on Operator Staffing</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>A higher level of detail for these actions can be found in the [https://www.epri.com/research/products/000000003002026495 report] along with Table 3-2 which summarizes the methods to assess HRA’s impact on advanced reactor safety.</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>A higher level of detail for these actions can be found in the [https://www.epri.com/research/products/000000003002026495 report] along with Table 3-2 which summarizes the methods to assess HRA’s impact on advanced reactor safety.</div></td></tr> </table>

Admin https://ramtar.epri.com/index.php?title=Human_Reliability_Analysis&diff=305&oldid=prev 2025-01-17T22:43:16Z

<p><span dir="auto"><span class="autocomment">HRA</span></span></p> <table style="background-color: #fff; color: #202122;" data-mw="interface"> <col class="diff-marker" /> <col class="diff-content" /> <col class="diff-marker" /> <col class="diff-content" /> <tr class="diff-title" lang="en"> <td colspan="2" style="background-color: #fff; color: #202122; text-align: center;">← Older revision</td> <td colspan="2" style="background-color: #fff; color: #202122; text-align: center;">Revision as of 22:43, 17 January 2025</td> </tr><tr><td colspan="2" class="diff-lineno" id="mw-diff-left-l8">Line 8:</td> <td colspan="2" class="diff-lineno">Line 8:</td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==HRA==</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==HRA==</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Assessment (HRA) is required as part of the final safety analysis report (FSAR) for any licensing application using any of the potential licensing pathways.</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Assessment (HRA) is required as part of the final safety analysis report (FSAR) for any licensing application using any of the potential licensing pathways.</div></td></tr> <tr><td class="diff-marker" data-marker="−"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #ffe49c; vertical-align: top; white-space: pre-wrap;"><div>Hamza and Diaconeasa introduced a framework for incorporating HRA in the early stages of design either at the pre-conceptual or conceptual design phase to develop significant operator actions early, thereby meeting the needs for advanced reactors in their current stage [[References| [30]]].  The PRA Standard for Advanced Non-LWR Nuclear (NLWR) Power Plants [[References| [6]]] specifies high-level and supporting technical requirements for 18 technical elements needed to create a full-scope PRA. Examples are Plant Operating States, Initiating Events Analysis, Event Sequences Analysis, Systems Analysis, and some less familiar ones such as Mechanistic Source Term Analysis, Radiogical Consequence Analysis and Risk Integration. Like the ASME/ANS Level 1 PRA Standard, the NLWR Standard includes two PRA Capability Categories, CC-I and CC-II. Human actions are incorporated throughout the standard. In stakeholder interviews it was determined that a there was particular concern for the development of operator actions in response to issues that cover multiple operator shifts and for errors of commission in relation to HRA as these may not be the dominant sources of human error for current LWRs, but could become dominant for advanced reactors.  Research Roadmap (EPRI [https://www.epri.com/research/products/000000003002026495 3002026495]) actions that support emphasizing the importance of EoCs as a source of human error for advanced reactors:</div></td><td class="diff-marker" data-marker="+"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #a3d3ff; vertical-align: top; white-space: pre-wrap;"><div>Hamza and Diaconeasa introduced a framework for incorporating HRA in the early stages of design either at the pre-conceptual or conceptual design phase to develop significant operator actions early, thereby meeting the needs for advanced reactors in their current stage [[References| [30]]].  The PRA Standard for Advanced Non-LWR Nuclear (NLWR) Power Plants <ins style="font-weight: bold; text-decoration: none;">(not cooled by water) </ins>[[References| [6]]] specifies high-level and supporting technical requirements for 18 technical elements needed to create a full-scope PRA. Examples are Plant Operating States, Initiating Events Analysis, Event Sequences Analysis, Systems Analysis, and some less familiar ones such as Mechanistic Source Term Analysis, Radiogical Consequence Analysis and Risk Integration. Like the ASME/ANS Level 1 PRA Standard, the NLWR Standard includes two PRA Capability Categories, CC-I and CC-II. Human actions are incorporated throughout the standard. In stakeholder interviews it was determined that a there was particular concern for the development of operator actions in response to issues that cover multiple operator shifts and for errors of commission in relation to HRA as these may not be the dominant sources of human error for current LWRs, but could become dominant for advanced reactors.  Research Roadmap (EPRI [https://www.epri.com/research/products/000000003002026495 3002026495]) actions that support emphasizing the importance of EoCs as a source of human error for advanced reactors:</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Enhancements to Licensing Process</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Enhancements to Licensing Process</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Industry Recommendations for Regulatory (NRC / CNSC) Guidance on Operator Staffing</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Industry Recommendations for Regulatory (NRC / CNSC) Guidance on Operator Staffing</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>A higher level of detail for these actions can be found in the [https://www.epri.com/research/products/000000003002026495 report] along with Table 3-2 which summarizes the methods to assess HRA’s impact on advanced reactor safety.</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>A higher level of detail for these actions can be found in the [https://www.epri.com/research/products/000000003002026495 report] along with Table 3-2 which summarizes the methods to assess HRA’s impact on advanced reactor safety.</div></td></tr> </table>

Admin https://ramtar.epri.com/index.php?title=Human_Reliability_Analysis&diff=304&oldid=prev 2025-01-17T21:55:29Z

<p><span dir="auto"><span class="autocomment">Scope</span></span></p> <table style="background-color: #fff; color: #202122;" data-mw="interface"> <col class="diff-marker" /> <col class="diff-content" /> <col class="diff-marker" /> <col class="diff-content" /> <tr class="diff-title" lang="en"> <td colspan="2" style="background-color: #fff; color: #202122; text-align: center;">← Older revision</td> <td colspan="2" style="background-color: #fff; color: #202122; text-align: center;">Revision as of 21:55, 17 January 2025</td> </tr><tr><td colspan="2" class="diff-lineno" id="mw-diff-left-l4">Line 4:</td> <td colspan="2" class="diff-lineno">Line 4:</td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==Scope==</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==Scope==</div></td></tr> <tr><td class="diff-marker" data-marker="−"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #ffe49c; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Analysis for advanced reactors will cover operator actions that result in plant success as well as undesired end states related to human error. Since procedures for advanced reactors can vary widely between different designs and will be vastly different compared to <del style="font-weight: bold; text-decoration: none;">LWR </del>procedures, the associated operator actions will likely have high variability which will need to be addressed.</div></td><td class="diff-marker" data-marker="+"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #a3d3ff; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Analysis for advanced reactors will cover operator actions that result in plant success as well as undesired end states related to human error. Since procedures for advanced reactors can vary widely between different designs and will be vastly different compared to <ins style="font-weight: bold; text-decoration: none;">water reactor </ins>procedures, the associated operator actions will likely have high variability which will need to be addressed.</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==HRA==</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==HRA==</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Assessment (HRA) is required as part of the final safety analysis report (FSAR) for any licensing application using any of the potential licensing pathways.</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Assessment (HRA) is required as part of the final safety analysis report (FSAR) for any licensing application using any of the potential licensing pathways.</div></td></tr> <tr><td class="diff-marker" data-marker="−"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #ffe49c; vertical-align: top; white-space: pre-wrap;"><div>Hamza and Diaconeasa introduced a framework for incorporating HRA in the early stages of design either at the pre-conceptual or conceptual design phase to develop significant operator actions early, thereby meeting the needs for advanced reactors in their current stage [[References| [30]]].  The PRA Standard for Advanced Non-LWR Nuclear (NLWR) Power Plants [[References| [6]]] specifies high-level and supporting technical requirements for 18 technical elements needed to create a full-scope PRA. Examples are Plant Operating States, Initiating Events Analysis, Event Sequences Analysis, Systems Analysis, and some less familiar ones such as Mechanistic Source Term Analysis, <del style="font-weight: bold; text-decoration: none;">Radiological </del>Consequence Analysis and Risk Integration. Like the ASME/ANS Level 1 PRA Standard, the NLWR Standard includes two PRA Capability Categories, CC-I and CC-II. Human actions are incorporated throughout the standard. In stakeholder interviews it was determined that a there was particular concern for the development of operator actions in response to issues that cover multiple operator shifts and for errors of commission in relation to HRA as these may not be the dominant sources of human error for current LWRs, but could become dominant for advanced reactors.  Research Roadmap (EPRI [https://www.epri.com/research/products/000000003002026495 3002026495]) actions that support emphasizing the importance of EoCs as a source of human error for advanced reactors:</div></td><td class="diff-marker" data-marker="+"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #a3d3ff; vertical-align: top; white-space: pre-wrap;"><div>Hamza and Diaconeasa introduced a framework for incorporating HRA in the early stages of design either at the pre-conceptual or conceptual design phase to develop significant operator actions early, thereby meeting the needs for advanced reactors in their current stage [[References| [30]]].  The PRA Standard for Advanced Non-LWR Nuclear (NLWR) Power Plants [[References| [6]]] specifies high-level and supporting technical requirements for 18 technical elements needed to create a full-scope PRA. Examples are Plant Operating States, Initiating Events Analysis, Event Sequences Analysis, Systems Analysis, and some less familiar ones such as Mechanistic Source Term Analysis, <ins style="font-weight: bold; text-decoration: none;">Radiogical </ins>Consequence Analysis and Risk Integration. Like the ASME/ANS Level 1 PRA Standard, the NLWR Standard includes two PRA Capability Categories, CC-I and CC-II. Human actions are incorporated throughout the standard. In stakeholder interviews it was determined that a there was particular concern for the development of operator actions in response to issues that cover multiple operator shifts and for errors of commission in relation to HRA as these may not be the dominant sources of human error for current LWRs, but could become dominant for advanced reactors.  Research Roadmap (EPRI [https://www.epri.com/research/products/000000003002026495 3002026495]) actions that support emphasizing the importance of EoCs as a source of human error for advanced reactors:</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Enhancements to Licensing Process</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Enhancements to Licensing Process</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Industry Recommendations for Regulatory (NRC / CNSC) Guidance on Operator Staffing</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Industry Recommendations for Regulatory (NRC / CNSC) Guidance on Operator Staffing</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>A higher level of detail for these actions can be found in the [https://www.epri.com/research/products/000000003002026495 report] along with Table 3-2 which summarizes the methods to assess HRA’s impact on advanced reactor safety.</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>A higher level of detail for these actions can be found in the [https://www.epri.com/research/products/000000003002026495 report] along with Table 3-2 which summarizes the methods to assess HRA’s impact on advanced reactor safety.</div></td></tr> </table>

Admin https://ramtar.epri.com/index.php?title=Human_Reliability_Analysis&diff=283&oldid=prev 2024-07-17T15:38:30Z

<p></p> <table style="background-color: #fff; color: #202122;" data-mw="interface"> <col class="diff-marker" /> <col class="diff-content" /> <col class="diff-marker" /> <col class="diff-content" /> <tr class="diff-title" lang="en"> <td colspan="2" style="background-color: #fff; color: #202122; text-align: center;">← Older revision</td> <td colspan="2" style="background-color: #fff; color: #202122; text-align: center;">Revision as of 15:38, 17 July 2024</td> </tr><tr><td colspan="2" class="diff-lineno" id="mw-diff-left-l8">Line 8:</td> <td colspan="2" class="diff-lineno">Line 8:</td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==HRA==</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==HRA==</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Assessment (HRA) is required as part of the final safety analysis report (FSAR) for any licensing application using any of the potential licensing pathways.</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Assessment (HRA) is required as part of the final safety analysis report (FSAR) for any licensing application using any of the potential licensing pathways.</div></td></tr> <tr><td class="diff-marker" data-marker="−"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #ffe49c; vertical-align: top; white-space: pre-wrap;"><div>Hamza and Diaconeasa introduced a framework for incorporating HRA in the early stages of design either at the pre-conceptual or conceptual design phase to develop significant operator actions early, thereby meeting the needs for advanced reactors in their current stage [[References| [30]]].  The PRA Standard for Advanced Non-LWR Nuclear (NLWR) Power Plants [[References| [6]]] specifies high-level and supporting technical requirements for 18 technical elements needed to create a full-scope PRA. Examples are Plant Operating States, Initiating Events Analysis, Event Sequences Analysis, Systems Analysis, and some less familiar ones such as Mechanistic Source Term Analysis, <del style="font-weight: bold; text-decoration: none;">Radiogical </del>Consequence Analysis and Risk Integration. Like the ASME/ANS Level 1 PRA Standard, the NLWR Standard includes two PRA Capability Categories, CC-I and CC-II. Human actions are incorporated throughout the standard. In stakeholder interviews it was determined that a there was particular concern for the development of operator actions in response to issues that cover multiple operator shifts and for errors of commission in relation to HRA as these may not be the dominant sources of human error for current LWRs, but could become dominant for advanced reactors.  Research Roadmap (EPRI [https://www.epri.com/research/products/000000003002026495 3002026495]) actions that support emphasizing the importance of EoCs as a source of human error for advanced reactors:</div></td><td class="diff-marker" data-marker="+"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #a3d3ff; vertical-align: top; white-space: pre-wrap;"><div>Hamza and Diaconeasa introduced a framework for incorporating HRA in the early stages of design either at the pre-conceptual or conceptual design phase to develop significant operator actions early, thereby meeting the needs for advanced reactors in their current stage [[References| [30]]].  The PRA Standard for Advanced Non-LWR Nuclear (NLWR) Power Plants [[References| [6]]] specifies high-level and supporting technical requirements for 18 technical elements needed to create a full-scope PRA. Examples are Plant Operating States, Initiating Events Analysis, Event Sequences Analysis, Systems Analysis, and some less familiar ones such as Mechanistic Source Term Analysis, <ins style="font-weight: bold; text-decoration: none;">Radiological </ins>Consequence Analysis and Risk Integration. Like the ASME/ANS Level 1 PRA Standard, the NLWR Standard includes two PRA Capability Categories, CC-I and CC-II. Human actions are incorporated throughout the standard. In stakeholder interviews it was determined that a there was particular concern for the development of operator actions in response to issues that cover multiple operator shifts and for errors of commission in relation to HRA as these may not be the dominant sources of human error for current LWRs, but could become dominant for advanced reactors.  Research Roadmap (EPRI [https://www.epri.com/research/products/000000003002026495 3002026495]) actions that support emphasizing the importance of EoCs as a source of human error for advanced reactors:</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Enhancements to Licensing Process</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Enhancements to Licensing Process</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Industry Recommendations for Regulatory (NRC / CNSC) Guidance on Operator Staffing</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Industry Recommendations for Regulatory (NRC / CNSC) Guidance on Operator Staffing</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>A higher level of detail for these actions can be found in the [https://www.epri.com/research/products/000000003002026495 report] along with Table 3-2 which summarizes the methods to assess HRA’s impact on advanced reactor safety.</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>A higher level of detail for these actions can be found in the [https://www.epri.com/research/products/000000003002026495 report] along with Table 3-2 which summarizes the methods to assess HRA’s impact on advanced reactor safety.</div></td></tr> </table>

Admin https://ramtar.epri.com/index.php?title=Human_Reliability_Analysis&diff=273&oldid=prev 2024-07-10T16:32:29Z

<p></p> <table style="background-color: #fff; color: #202122;" data-mw="interface"> <col class="diff-marker" /> <col class="diff-content" /> <col class="diff-marker" /> <col class="diff-content" /> <tr class="diff-title" lang="en"> <td colspan="2" style="background-color: #fff; color: #202122; text-align: center;">← Older revision</td> <td colspan="2" style="background-color: #fff; color: #202122; text-align: center;">Revision as of 16:32, 10 July 2024</td> </tr><tr><td colspan="2" class="diff-lineno" id="mw-diff-left-l1">Line 1:</td> <td colspan="2" class="diff-lineno">Line 1:</td></tr> <tr><td colspan="2" class="diff-side-deleted"></td><td class="diff-marker" data-marker="+"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #a3d3ff; vertical-align: top; white-space: pre-wrap;"><div><ins style="font-weight: bold; text-decoration: none;">__FORCETOC__</ins></div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==Purpose==</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==Purpose==</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Analysis aims to identify ways in which plant operators can intervene in the success or failure of the plant functions and systems in response to an initiating event, given the procedures for the specific plant. As it relates to advanced reactors, HRA will be a crucial element not only once a plant is operational, but also in the design and licensing phase.</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Analysis aims to identify ways in which plant operators can intervene in the success or failure of the plant functions and systems in response to an initiating event, given the procedures for the specific plant. As it relates to advanced reactors, HRA will be a crucial element not only once a plant is operational, but also in the design and licensing phase.</div></td></tr> </table>

Admin https://ramtar.epri.com/index.php?title=Human_Reliability_Analysis&diff=249&oldid=prev 2024-07-09T19:05:26Z

<p><span dir="auto"><span class="autocomment">HRA</span></span></p> <table style="background-color: #fff; color: #202122;" data-mw="interface"> <col class="diff-marker" /> <col class="diff-content" /> <col class="diff-marker" /> <col class="diff-content" /> <tr class="diff-title" lang="en"> <td colspan="2" style="background-color: #fff; color: #202122; text-align: center;">← Older revision</td> <td colspan="2" style="background-color: #fff; color: #202122; text-align: center;">Revision as of 19:05, 9 July 2024</td> </tr><tr><td colspan="2" class="diff-lineno" id="mw-diff-left-l7">Line 7:</td> <td colspan="2" class="diff-lineno">Line 7:</td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==HRA==</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==HRA==</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Assessment (HRA) is required as part of the final safety analysis report (FSAR) for any licensing application using any of the potential licensing pathways.</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Assessment (HRA) is required as part of the final safety analysis report (FSAR) for any licensing application using any of the potential licensing pathways.</div></td></tr> <tr><td class="diff-marker" data-marker="−"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #ffe49c; vertical-align: top; white-space: pre-wrap;"><div>Hamza and Diaconeasa introduced a framework for incorporating HRA in the early stages of design either at the pre-conceptual or conceptual design phase to develop significant operator actions early, thereby meeting the needs for <del style="font-weight: bold; text-decoration: none;">ARs </del>in their current stage [[References| [30]]].  The PRA Standard for Advanced Non-LWR Nuclear (NLWR) Power Plants [[References| [6]]] specifies high-level and supporting technical requirements for 18 technical elements needed to create a full-scope PRA. Examples are Plant Operating States, Initiating Events Analysis, Event Sequences Analysis, Systems Analysis, and some less familiar ones such as Mechanistic Source Term Analysis, Radiogical Consequence Analysis and Risk Integration. Like the ASME/ANS Level 1 PRA Standard, the NLWR Standard includes two PRA Capability Categories, CC-I and CC-II. Human actions are incorporated throughout the standard. In stakeholder interviews it was determined that a there was particular concern for the development of operator actions in response to issues that cover multiple operator shifts and for errors of commission in relation to HRA as these may not be the dominant sources of human error for current LWRs, but could become dominant for <del style="font-weight: bold; text-decoration: none;">ARs</del>.  Research Roadmap (EPRI [https://www.epri.com/research/products/000000003002026495 3002026495]) actions that support emphasizing the importance of EoCs as a source of human error for <del style="font-weight: bold; text-decoration: none;">ARs</del>:</div></td><td class="diff-marker" data-marker="+"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #a3d3ff; vertical-align: top; white-space: pre-wrap;"><div>Hamza and Diaconeasa introduced a framework for incorporating HRA in the early stages of design either at the pre-conceptual or conceptual design phase to develop significant operator actions early, thereby meeting the needs for <ins style="font-weight: bold; text-decoration: none;">advanced reactors </ins>in their current stage [[References| [30]]].  The PRA Standard for Advanced Non-LWR Nuclear (NLWR) Power Plants [[References| [6]]] specifies high-level and supporting technical requirements for 18 technical elements needed to create a full-scope PRA. Examples are Plant Operating States, Initiating Events Analysis, Event Sequences Analysis, Systems Analysis, and some less familiar ones such as Mechanistic Source Term Analysis, Radiogical Consequence Analysis and Risk Integration. Like the ASME/ANS Level 1 PRA Standard, the NLWR Standard includes two PRA Capability Categories, CC-I and CC-II. Human actions are incorporated throughout the standard. In stakeholder interviews it was determined that a there was particular concern for the development of operator actions in response to issues that cover multiple operator shifts and for errors of commission in relation to HRA as these may not be the dominant sources of human error for current LWRs, but could become dominant for <ins style="font-weight: bold; text-decoration: none;">advanced reactors</ins>.  Research Roadmap (EPRI [https://www.epri.com/research/products/000000003002026495 3002026495]) actions that support emphasizing the importance of EoCs as a source of human error for <ins style="font-weight: bold; text-decoration: none;">advanced reactors</ins>:</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Enhancements to Licensing Process</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Enhancements to Licensing Process</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Industry Recommendations for Regulatory (NRC / CNSC) Guidance on Operator Staffing</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Industry Recommendations for Regulatory (NRC / CNSC) Guidance on Operator Staffing</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td></tr> <tr><td class="diff-marker" data-marker="−"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #ffe49c; vertical-align: top; white-space: pre-wrap;"><div>A higher level of detail for these actions can be found in the [https://www.epri.com/research/products/000000003002026495 report] along with Table 3-2 which summarizes the methods to assess HRA’s impact on <del style="font-weight: bold; text-decoration: none;">AR </del>safety.</div></td><td class="diff-marker" data-marker="+"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #a3d3ff; vertical-align: top; white-space: pre-wrap;"><div>A higher level of detail for these actions can be found in the [https://www.epri.com/research/products/000000003002026495 report] along with Table 3-2 which summarizes the methods to assess HRA’s impact on <ins style="font-weight: bold; text-decoration: none;">advanced reactor </ins>safety.</div></td></tr> </table>

Admin https://ramtar.epri.com/index.php?title=Human_Reliability_Analysis&diff=248&oldid=prev 2024-07-09T19:02:26Z

<p><span dir="auto"><span class="autocomment">Purpose</span></span></p> <table style="background-color: #fff; color: #202122;" data-mw="interface"> <col class="diff-marker" /> <col class="diff-content" /> <col class="diff-marker" /> <col class="diff-content" /> <tr class="diff-title" lang="en"> <td colspan="2" style="background-color: #fff; color: #202122; text-align: center;">← Older revision</td> <td colspan="2" style="background-color: #fff; color: #202122; text-align: center;">Revision as of 19:02, 9 July 2024</td> </tr><tr><td colspan="2" class="diff-lineno" id="mw-diff-left-l1">Line 1:</td> <td colspan="2" class="diff-lineno">Line 1:</td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==Purpose==</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==Purpose==</div></td></tr> <tr><td class="diff-marker" data-marker="−"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #ffe49c; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Analysis aims to identify ways in which plant operators can intervene in the success or failure of the plant functions and systems in response to an initiating event, given the procedures for the specific plant. As it relates to <del style="font-weight: bold; text-decoration: none;">AR's</del>, HRA will be a crucial element not only once a plant is operational, but also in the design and licensing phase.</div></td><td class="diff-marker" data-marker="+"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #a3d3ff; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Analysis aims to identify ways in which plant operators can intervene in the success or failure of the plant functions and systems in response to an initiating event, given the procedures for the specific plant. As it relates to <ins style="font-weight: bold; text-decoration: none;">advanced reactors</ins>, HRA will be a crucial element not only once a plant is operational, but also in the design and licensing phase.</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==Scope==</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==Scope==</div></td></tr> </table>

Admin https://ramtar.epri.com/index.php?title=Human_Reliability_Analysis&diff=230&oldid=prev 2024-07-08T15:54:26Z

<p><span dir="auto"><span class="autocomment">HRA</span></span></p> <table style="background-color: #fff; color: #202122;" data-mw="interface"> <col class="diff-marker" /> <col class="diff-content" /> <col class="diff-marker" /> <col class="diff-content" /> <tr class="diff-title" lang="en"> <td colspan="2" style="background-color: #fff; color: #202122; text-align: center;">← Older revision</td> <td colspan="2" style="background-color: #fff; color: #202122; text-align: center;">Revision as of 15:54, 8 July 2024</td> </tr><tr><td colspan="2" class="diff-lineno" id="mw-diff-left-l7">Line 7:</td> <td colspan="2" class="diff-lineno">Line 7:</td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==HRA==</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==HRA==</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Assessment (HRA) is required as part of the final safety analysis report (FSAR) for any licensing application using any of the potential licensing pathways.</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Assessment (HRA) is required as part of the final safety analysis report (FSAR) for any licensing application using any of the potential licensing pathways.</div></td></tr> <tr><td class="diff-marker" data-marker="−"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #ffe49c; vertical-align: top; white-space: pre-wrap;"><div>Hamza and Diaconeasa introduced a framework for incorporating HRA in the early stages of design either at the pre-conceptual or conceptual design phase to develop significant operator actions early, thereby meeting the needs for ARs in their current stage [[References| [30]]].  The PRA Standard for Advanced Non-LWR Nuclear (NLWR) Power Plants [[References| [6]]] specifies high-level and supporting technical requirements for 18 technical elements needed to create a full-scope PRA. Examples are Plant Operating States, Initiating Events Analysis, Event Sequences Analysis, Systems Analysis, and some less familiar ones such as Mechanistic Source Term Analysis, Radiogical Consequence Analysis and Risk Integration. Like the ASME/ANS Level 1 PRA Standard, the NLWR Standard includes two PRA Capability Categories, CC-I and CC-II. Human actions are incorporated throughout the standard. In stakeholder interviews it was determined that a there was particular concern for the development of operator actions in response to issues that cover multiple operator shifts and for errors of commission in relation to HRA as these may not be the dominant sources of human error for current LWRs, but could become dominant for ARs.  Research Roadmap actions that support emphasizing the importance of EoCs as a source of human error for ARs:</div></td><td class="diff-marker" data-marker="+"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #a3d3ff; vertical-align: top; white-space: pre-wrap;"><div>Hamza and Diaconeasa introduced a framework for incorporating HRA in the early stages of design either at the pre-conceptual or conceptual design phase to develop significant operator actions early, thereby meeting the needs for ARs in their current stage [[References| [30]]].  The PRA Standard for Advanced Non-LWR Nuclear (NLWR) Power Plants [[References| [6]]] specifies high-level and supporting technical requirements for 18 technical elements needed to create a full-scope PRA. Examples are Plant Operating States, Initiating Events Analysis, Event Sequences Analysis, Systems Analysis, and some less familiar ones such as Mechanistic Source Term Analysis, Radiogical Consequence Analysis and Risk Integration. Like the ASME/ANS Level 1 PRA Standard, the NLWR Standard includes two PRA Capability Categories, CC-I and CC-II. Human actions are incorporated throughout the standard. In stakeholder interviews it was determined that a there was particular concern for the development of operator actions in response to issues that cover multiple operator shifts and for errors of commission in relation to HRA as these may not be the dominant sources of human error for current LWRs, but could become dominant for ARs.  Research Roadmap <ins style="font-weight: bold; text-decoration: none;">(EPRI [https://www.epri.com/research/products/000000003002026495 3002026495]) </ins>actions that support emphasizing the importance of EoCs as a source of human error for ARs:</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Enhancements to Licensing Process</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Enhancements to Licensing Process</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Industry Recommendations for Regulatory (NRC / CNSC) Guidance on Operator Staffing</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Industry Recommendations for Regulatory (NRC / CNSC) Guidance on Operator Staffing</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>A higher level of detail for these actions can be found in the [https://www.epri.com/research/products/000000003002026495 report] along with Table 3-2 which summarizes the methods to assess HRA’s impact on AR safety.</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>A higher level of detail for these actions can be found in the [https://www.epri.com/research/products/000000003002026495 report] along with Table 3-2 which summarizes the methods to assess HRA’s impact on AR safety.</div></td></tr> </table>

Admin https://ramtar.epri.com/index.php?title=Human_Reliability_Analysis&diff=225&oldid=prev 2024-07-05T23:57:03Z

<p><span dir="auto"><span class="autocomment">HRA</span></span></p> <table style="background-color: #fff; color: #202122;" data-mw="interface"> <col class="diff-marker" /> <col class="diff-content" /> <col class="diff-marker" /> <col class="diff-content" /> <tr class="diff-title" lang="en"> <td colspan="2" style="background-color: #fff; color: #202122; text-align: center;">← Older revision</td> <td colspan="2" style="background-color: #fff; color: #202122; text-align: center;">Revision as of 23:57, 5 July 2024</td> </tr><tr><td colspan="2" class="diff-lineno" id="mw-diff-left-l7">Line 7:</td> <td colspan="2" class="diff-lineno">Line 7:</td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==HRA==</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>==HRA==</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Assessment (HRA) is required as part of the final safety analysis report (FSAR) for any licensing application using any of the potential licensing pathways.</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>Human Reliability Assessment (HRA) is required as part of the final safety analysis report (FSAR) for any licensing application using any of the potential licensing pathways.</div></td></tr> <tr><td class="diff-marker" data-marker="−"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #ffe49c; vertical-align: top; white-space: pre-wrap;"><div>Hamza and Diaconeasa introduced a framework for incorporating HRA in the early stages of design either at the pre-conceptual or conceptual design phase to develop significant operator actions early, thereby meeting the needs for ARs in their current stage [[References| [30]]].  The PRA Standard for Advanced Non-LWR Nuclear Power Plants [[References| [6]]] specifies technical requirements for <del style="font-weight: bold; text-decoration: none;">the </del>18 elements needed to create a full-scope PRA, <del style="font-weight: bold; text-decoration: none;">with </del>two PRA Capability Categories, CC-I and CC-II<del style="font-weight: bold; text-decoration: none;">, based on plant, site, or design-specific models</del>. Human actions are incorporated <del style="font-weight: bold; text-decoration: none;">into all 18 PRA elements, with one specific element responsible for HRA, which should be included in both capability categories to ensure </del>the <del style="font-weight: bold; text-decoration: none;">identification of risk significant events</del>. In stakeholder interviews it was determined that a there was particular concern for the development of operator actions in response to <del style="font-weight: bold; text-decoration: none;">multi-day </del>issues and for errors of commission in relation to HRA as these may not be the dominant sources of human error for current LWRs, but could become dominant for ARs.  Roadmap actions <del style="font-weight: bold; text-decoration: none;">supported </del>emphasizing the importance of EoCs as a source of human error for ARs:</div></td><td class="diff-marker" data-marker="+"></td><td style="color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #a3d3ff; vertical-align: top; white-space: pre-wrap;"><div>Hamza and Diaconeasa introduced a framework for incorporating HRA in the early stages of design either at the pre-conceptual or conceptual design phase to develop significant operator actions early, thereby meeting the needs for ARs in their current stage [[References| [30]]].  The PRA Standard for Advanced Non-LWR Nuclear <ins style="font-weight: bold; text-decoration: none;">(NLWR) </ins>Power Plants [[References| [6]]] specifies <ins style="font-weight: bold; text-decoration: none;">high-level and supporting </ins>technical requirements for 18 <ins style="font-weight: bold; text-decoration: none;">technical </ins>elements needed to create a full-scope PRA<ins style="font-weight: bold; text-decoration: none;">. Examples are Plant Operating States</ins>, <ins style="font-weight: bold; text-decoration: none;">Initiating Events Analysis, Event Sequences Analysis, Systems Analysis, and some less familiar ones such as Mechanistic Source Term Analysis, Radiogical Consequence Analysis and Risk Integration. Like the ASME/ANS Level 1 PRA Standard, the NLWR Standard includes </ins>two PRA Capability Categories, CC-I and CC-II. Human actions are incorporated <ins style="font-weight: bold; text-decoration: none;">throughout </ins>the <ins style="font-weight: bold; text-decoration: none;">standard</ins>. In stakeholder interviews it was determined that a there was particular concern for the development of operator actions in response to issues <ins style="font-weight: bold; text-decoration: none;">that cover multiple operator shifts </ins>and for errors of commission in relation to HRA as these may not be the dominant sources of human error for current LWRs, but could become dominant for ARs.  <ins style="font-weight: bold; text-decoration: none;">Research </ins>Roadmap actions <ins style="font-weight: bold; text-decoration: none;">that support </ins>emphasizing the importance of EoCs as a source of human error for ARs:</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Enhancements to Licensing Process</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Enhancements to Licensing Process</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Industry Recommendations for Regulatory (NRC / CNSC) Guidance on Operator Staffing</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>*Develop Industry Recommendations for Regulatory (NRC / CNSC) Guidance on Operator Staffing</div></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><br/></td></tr> <tr><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>A higher level of detail for these actions can be found in the [https://www.epri.com/research/products/000000003002026495 report] along with Table 3-2 which summarizes the methods to assess HRA’s impact on AR safety.</div></td><td class="diff-marker"></td><td style="background-color: #f8f9fa; color: #202122; font-size: 88%; border-style: solid; border-width: 1px 1px 1px 4px; border-radius: 0.33em; border-color: #eaecf0; vertical-align: top; white-space: pre-wrap;"><div>A higher level of detail for these actions can be found in the [https://www.epri.com/research/products/000000003002026495 report] along with Table 3-2 which summarizes the methods to assess HRA’s impact on AR safety.</div></td></tr> </table>

Admin