Plant Fire-Induced Risk Model (Task 5)

Task Overview

Background

This task discusses steps for the development of a logic model that reflects plant response following a fire. Specific instructions have been provided for treatment of fire-specific procedures or preplans. These procedures may impact availability of functions and components, or include fire-specific operator actions (e.g., self-induced-station-blackout).

Purpose

This section describes the procedure for developing the Fire PRA Model to calculate CDF, CCDP, LERF, and CLERP for fire events. The procedure addresses the process of implementing temporary or permanent changes to the Internal Events PRA to quantify fire-induced core damage frequency (CDF), conditional core damage probability (CCDP), large early release frequency (LERF), and conditional large early release probability (CLERP), and for developing special models to address fire emergency procedures (FEPs). The procedure also addresses the transition from temporary changes to permanent changes to the Internal Events PRA Model during the development of the Fire PRA Model.

Scope

This procedure addresses the following major steps for developing the Fire PRA Model for calculating CDF/CCDP and LERF/CLERP for fire events.

• Step 1–Develop the Fire PRA CDF/CCDP Model.
• Step 2–Develop the Fire PRA LERF/CLERP Model.

Related Element of ASME/ANS PRA Standard

Fire PRA Plant Response Model (PRM)

Related EPRI 1011989 / NUREG/CR-6850 Appendices

None

Supplemental Guidance

The process for developing the Fire PRA logic model to calculate CDF/CCDP and LERF/CLERP model is largely unchanged from EPRI 1011989 / NUREG/CR-6850. However, it should be acknowledged that the addition of multiple spurious operations and/or alternate shutdown in the PRA model needs careful consideration to be appropriately placed into the model.

NEI 00-01 Revision 3

• 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 Revision 2

• Revision 2 of NEI 00-01 is endorsed in NRC RG 1.189, Fire Protection for Nuclear Power Plants Revision 2 October 2009
• NEI 00-01 documents the MSO Expert Panel Process and provides a list of generic MSOs applicable to both PWRs and BWRs.

EPRI/NRC-RES Fire Human Reliability Analysis Guidelines: Qualitative Guidance for Main Control Room Abandonment Scenarios (NUREG-1921 Supplement 1 / EPRI 3002009215)

Fire PRAs analyze a wide variety of fire-induced scenarios, one of which is fire damage rendering the main control room (MCR) either inhabitable or ineffective. As a result of this fire damage, operators cannot stay in the MCR and the command and control of the plant is transferred from the MCR to another location. This is commonly referred to a main control room abandonment (MCRA). MCRA is analyzed as a special case of fire HRA. While NUREG-1921/EPRI 1023001 briefly addressed abandonment, additional guidance and inputs are needed to properly address the unique contexts of abandonment scenarios.

EPRI 3002009215 / NUREG-1921 Supplement 1 provides more detailed consideration of the elements to model for main control room abandonment, including:

• Adding logic in the model to capture when the conditions requiring abandonment occur, whether due to a loss of control room habitability or a loss of the capability to reach a safe-and-stable state from the control room. i.e., loss of control (Page 3-2)
• Incorporating random failures of equipment required for remote shutdown
• Model logic for incorporating mitigatable fire-induced failures of equipment required for remote shutdown
• Modeling non-mitigatable fire-induced failures of equipment required for remote shutdown
• Model logic for capturing accident scenarios that create conditions beyond the capability of the remote shutdown equipment and/or procedures.

Refer to Section 3 of EPRI 3002009215 / NUREG-1921 Supplement 1 for more information on modeling alternate shutdown capability in the PRA logic model.