Fire PRA Component Selection (Task 2) - Revision history

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2020-04-27T13:44:12Z

Supplemental Guidance

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User at 14:16, 12 March 2020

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Supplemental Guidance

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 ==Supplemental Guidance==
-There is no supplemental guidance associated with Fire PRA Component Selection (Task 2). The analyst however should review the following documents to ensure that the component selection is complete:
+There is no supplemental guidance associated with Fire PRA Component Selection (Task&nbsp;2). The analyst however should review the following documents to ensure that the component selection is complete:
-*[https://www.nrc.gov/docs/ML0917/ML091770265.pdf NEI 00-01]
+*[https://www.nrc.gov/docs/ML0917/ML091770265.pdf NEI&nbsp;00&#8209;01]
-**NEI 00-01 documents the MSO Expert Panel Process and provides a list of generic MSOs applicable to both PWRs and BWRs.
+**NEI&nbsp;00&#8209;01 documents the MSO Expert Panel Process and provides a list of generic MSOs applicable to both PWRs and BWRs.
-**[https://www.nrc.gov/docs/ML1129/ML112910147.pdf NEI 00-01 '''Revision 3'''] provides an updated list of generic MSOs applicable for both PWRs and BWRs.
+**[https://www.nrc.gov/docs/ML1129/ML112910147.pdf NEI&nbsp;00&#8209;01 '''Revision&#8209;3'''] provides an updated list of generic MSOs applicable for both PWRs and BWRs.
-**Parts of [https://www.nrc.gov/docs/ML0917/ML091770265.pdf NEI 00-01 '''Revision 2'''] are endorsed in NRC [https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML17340A875 RG 1.189, ''Fire Protection for Nuclear Power Plants''] Revision 3 February 2018
+**Parts of [https://www.nrc.gov/docs/ML0917/ML091770265.pdf NEI&nbsp;00&#8209;01 '''Revision&nbsp;2'''] are endorsed in NRC [https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML17340A875 RG&#8209;1.189, ''Fire Protection for Nuclear Power Plants''] Revision&nbsp;3 February&nbsp;2018
-*[https://www.epri.com/#/pages/product/000000000001023001/ EPRI/NRC-RES Fire Human Reliability Analysis Guidelines (NUREG-1921 / EPRI 1023001)]
+*[https://www.epri.com/#/pages/product/000000000001023001/ EPRI/NRC-RES Fire Human Reliability Analysis Guidelines (NUREG&#8209;1921 / EPRI&nbsp;1023001)]
 **The Fire PRA should include equipment and instrumentation required for operator actions credited in the Fire HRA
-*[https://www.epri.com/#/pages/product/000000003002009215/ EPRI/NRC-RES Fire Human Reliability Analysis Guidelines: Qualitative Guidance for Main Control Room Abandonment Scenarios (NUREG-1921 Supplement 1 / EPRI 3002009215)]
+*[https://www.epri.com/#/pages/product/000000003002009215/ EPRI/NRC-RES Fire Human Reliability Analysis Guidelines: Qualitative Guidance for Main Control Room Abandonment Scenarios (NUREG&#8209;1921 Supplement&nbsp;1 / EPRI&nbsp;3002009215)]
 **The Fire PRA should include equipment and instrumentation required for shutdown outside the control room.

@@ Line 55: / Line 55: @@
 There is no supplemental guidance associated with Fire PRA Component Selection (Task 2). The analyst however should review the following documents to ensure that the component selection is complete:
-*[https://www.nrc.gov/docs/ML1129/ML112910147.pdf NEI 00-01]
+*[https://www.nrc.gov/docs/ML0917/ML091770265.pdf NEI 00-01]
 **NEI 00-01 documents the MSO Expert Panel Process and provides a list of generic MSOs applicable to both PWRs and BWRs.
 **[https://www.nrc.gov/docs/ML1129/ML112910147.pdf NEI 00-01 '''Revision 3'''] provides an updated list of generic MSOs applicable for both PWRs and BWRs.

@@ Line 56: / Line 56: @@
 *[https://www.nrc.gov/docs/ML1129/ML112910147.pdf NEI 00-01]
-**[https://www.nrc.gov/docs/ML1129/ML112910147.pdf NEI 00-01 '''Revision 3'''] documents the MSO Expert Panel Process and provides an updated list of generic MSOs applicable to both PWRs and BWRs.
+**NEI 00-01 documents the MSO Expert Panel Process and provides a list of generic MSOs applicable to both PWRs and BWRs.
 **Parts of [https://www.nrc.gov/docs/ML0917/ML091770265.pdf NEI 00-01 '''Revision 2'''] are endorsed in NRC [https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML17340A875 RG 1.189, ''Fire Protection for Nuclear Power Plants''] Revision 3 February 2018
 *[https://www.epri.com/#/pages/product/000000000001023001/ EPRI/NRC-RES Fire Human Reliability Analysis Guidelines (NUREG-1921 / EPRI 1023001)]

@@ Line 55: / Line 55: @@
 There is no supplemental guidance associated with Fire PRA Component Selection (Task 2). The analyst however should review the following documents to ensure that the component selection is complete:
-*[https://www.nrc.gov/docs/ML1129/ML112910147.pdf NEI 00-01 Revision 3]
+*[https://www.nrc.gov/docs/ML1129/ML112910147.pdf NEI 00-01]
-**NEI 00-01 Revision 3 documents the MSO Expert Panel Process and provides an updated list of generic MSOs applicable to both PWRs and BWRs.
+**[https://www.nrc.gov/docs/ML1129/ML112910147.pdf NEI 00-01 '''Revision 3'''] documents the MSO Expert Panel Process and provides an updated list of generic MSOs applicable to both PWRs and BWRs.
-*[https://www.nrc.gov/docs/ML0917/ML091770265.pdf NEI 00-01 Revision 2]
+**Parts of [https://www.nrc.gov/docs/ML0917/ML091770265.pdf NEI 00-01 '''Revision 2'''] are endorsed in NRC [https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML17340A875 RG 1.189, ''Fire Protection for Nuclear Power Plants''] Revision 3 February 2018
 *[https://www.epri.com/#/pages/product/000000000001023001/ EPRI/NRC-RES Fire Human Reliability Analysis Guidelines (NUREG-1921 / EPRI 1023001)]
 **The Fire PRA should include equipment and instrumentation required for operator actions credited in the Fire HRA
 *[https://www.epri.com/#/pages/product/000000003002009215/ EPRI/NRC-RES Fire Human Reliability Analysis Guidelines: Qualitative Guidance for Main Control Room Abandonment Scenarios (NUREG-1921 Supplement 1 / EPRI 3002009215)]
 **The Fire PRA should include equipment and instrumentation required for shutdown outside the control room.

@@ Line 13: / Line 13: @@
 This procedure addresses creating the Fire PRA Component List, which needs to span (a) equipment that, if affected by a fire, will cause an initiating event such that the appropriate
 fire-induced initiators can be defined; (b) all equipment necessary to support those mitigating functions and operator actions that are credited in the analysis in response to any initiator, as
-well as (c) that equipment which can be a source of undesirable responses adverse to safety during a fire-induced accident sequence, such as a component that can spuriously operate .
+well as (c) that equipment which can be a source of undesirable responses adverse to safety during a fire-induced accident sequence, such as a component that can spuriously operate.
 The terms “equipment” or “components” as used in this procedure are considered synonymous and meant to include plant components such as valves, fans, pumps, etc.; structures; barriers;
 indicators; alarms; and other devices as appropriate. It is recommended that all the equipment credited in the Internal Events PRA (especially equipment in electrically diverse systems) be
@@ Line 58: / Line 58: @@
 **NEI 00-01 Revision 3 documents the MSO Expert Panel Process and provides an updated list of generic MSOs applicable to both PWRs and BWRs.
 *[https://www.nrc.gov/docs/ML0917/ML091770265.pdf NEI 00-01 Revision 2]
-**Revision 2 of NEI 00-01 is endorsed in NRC [https://www.nrc.gov/docs/ML0925/ML092580550.pdf RG 1.189, ''Fire Protection for Nuclear Power Plants''] Revision 2 October 2009
+**Parts of Revision 2 of NEI 00-01 are endorsed in NRC [https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML17340A875 RG 1.189, ''Fire Protection for Nuclear Power Plants''] Revision 3 February 2018
 **NEI 00-01 documents the MSO Expert Panel Process and provides a list of generic MSOs applicable to both PWRs and BWRs.
 *[https://www.epri.com/#/pages/product/000000000001023001/ EPRI/NRC-RES Fire Human Reliability Analysis Guidelines (NUREG-1921 / EPRI 1023001)]

@@ Line 33: / Line 33: @@
 successful operator actions (e.g., such as carrying out the Emergency Operating Procedures (EOPs), following specific Fire Emergency Procedures (FEPs), or to credit certain recovery
 actions), or the failure of which could cause inappropriate operator actions, should also be added to the Fire PRA Component List. Examples could be remote
-shutdown panel (or areas) equipment and controls, pump room high temperature alarms, certain plant parameter indications with no or little redundancy in the indication, among others.
+shutdown panel (or areas) equipment and controls, pump room high temperature alarms, or certain plant parameter indications with no or little redundancy in the indication, among others.
 Because a key emphasis of the Fire PRA Component List is to identify and track relevant cables in Task 3 that could be affected by fires in the plant, the list need not contain passive/mechanical

@@ Line 28: / Line 28: @@
 only relate to one or two categories. For example, the residual heat removal (RHR) high-low pressure interfacing valves in a pressurized water reactor (PWR) may not be needed to perform
 a safety function if the shutdown cooling mode is not credited in the fire analysis. However, fire-induced opening of these valves, if they remain powered, could cause an interfacing-systems LOCA (initiator) and possibly cause environmental-related failure of other systems that are credited in the analysis. For this reason, and because such a failure could potentially lead to a high
-consequence event involving both core damage and containment bypass (see more on such cases in Section 2.5.6), the RHR interfacing valves would be on the Fire PRA Component List.
+consequence event involving both core damage and containment bypass, the RHR interfacing valves would be on the Fire PRA Component List.
 Similarly, a limited set of mitigating equipment, as well as instrumentation and diagnostic equipment such as indicators, lights, alarms, and similar devices considered necessary to support