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Category:- No Document Type Applies
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2022-02-16
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FAQ Number 06-0005 Revision 2 FAQ Title Definition of a Fire Protection Program (FPP) Change Plant: Harris Nuclear Submittal Date: 10/8/07 Plant Submitter Robert Rishel Phone: 919.546.2662 Contact:
Submitter Robert.rishel@pgnmail.com Email:
Distribution: (NEI Internal Use) 805 TF FPWG RATF RIRWG BWROG PWROG
Subject:
Definition of a Fire Protection Program (FPP) Change Is this interpretation of current guidance? Yes / No Proposed new guidance not in NEI 04-02? Yes / No Details:
NEI 04-02 guidance needing interpretation (include section, paragraph, and line numbers as applicable):
NEI 04-02 Sections 4.4 and 5.3 require revision to clarify what is considered a fire protection program-related change with respect to a Fire PRA.
Circumstances requiring guidance interpretation or new guidance:
Implementation of an NFPA 805 FPP change process requires that the plant have an acceptable fire PRA in order to use the risk acceptance criteria (Regulatory Guide 1.205 Section C.3.1).
Changes to the plants internal events PRA and therefore the Fire PRA occur for various reasons (e.g., model updates, etc). Not all these changes should be considered fire protection program changes subject to the NEI 04-02 change process. Clarification is required to delineate that changes to the Fire PRA should not be considered a FPP-related change.
Note: This FAQ was submitted as Revision 1 on October 26, 2006 (ML0631805444). NRC comments were provided on August 23, 2007 (ML072400021). The comments recommended the FAQ be divided into 3 different FAQs, with one of the issues being how the Fire PRA will be addressed with respect to the FPP. Revision 2 of FAQ 06-0005 is focused on how the Fire PRA will be addressed with respect to the FPP.
Page 1 of 3 FAQ 06-0005 FPP Changes (PRA) Rev 2.doc
FAQ Number 06-0005 Revision 2 FAQ Title Definition of a Fire Protection Program (FPP) Change Detail contentious points if licensee and NRC have not reached consensus on the facts and circumstances:
The area where agreement is requested is statement that changes in the Fire PRA are not considered a FPP-related change.
Potentially relevant existing FAQ numbers:
FAQ 06-0014, Cumulative Risk Response Section:
Proposed resolution of FAQ and the basis for the proposal:
Changes in the fire PRA and the underlying Level I and Level II PRA are not FPP-related changes and also are not considered a plant change.
Basis:
The PRA itself (data, logic, supporting documentation and analysis) is built to reflect the facility as designed and operated. Thus, a change to the PRA itself cannot be a change to the structures, systems, or components or plant procedures and is not a fire protection program-related change. An example of potential changes in the fire PRA would be revising an equipment reliability rate or changing the PRA logic for accident sequences that are not of interest to the Fire PRA (e.g., equipment dependencies for a steam generator tube rupture accident sequence). Plant changes, such as adding an additional high pressure injection pump to the facility and the associated PRA revision is a plant change. If the Nuclear Safety Capability Assessment will not be revised as a result of this change to include this new pump as a success path credited to meet the nuclear safety performance criteria, then it is not considered a fire protection program-related change, and as such, would require the NRC pre-approval per the requirements of RG1.205, if used to offset a FPP-related change with an associated risk increase.
If appropriate, provide proposed rewording of guidance for inclusion in next revision.
See attached changes to Revision 1 of NEI 04-02, Section 5.3.2 (Add as a note after Item 4 at the top of page 46 of NEI 04-02 Revision 1).
Page 2 of 3 FAQ 06-0005 FPP Changes (PRA) Rev 2.doc
Attachment to FAQ 06-0005 Revision 2 Excerpt from NEI 04-02 Revision 1 5.3.2 Defining the Change
Note: Changes to the PRA model, which includes the documentation, data elements and associated logic, do not necessarily constitute a Fire Protection Program-related change.
Additionally, any plant equipment or procedures that are used in the fire PRA or the underlying Level I and Level II PRA, but are not specifically included as part of the nuclear safety capability assessment, are not considered Fire Protection Program-related. The PRA itself (data, logic, supporting documentation and analysis) is built to reflect the facility as designed and operated. Thus a change to the PRA itself would not be a change to the structures, systems, or components or plant procedures and is not a Fire Protection Program-related change.
Page 3 of 3 FAQ 06-0005 FPP Changes (PRA) Rev 2.doc
