ML072740248

NFPA-805 Transition Pilot Plant FAQ 06-0011, Revision 2

ML072740248
Person / Time
Site:	Cook
Issue date:	09/20/2007
From:	Jutras T H Engineering Planning & Management
To:	Office of Nuclear Reactor Regulation
References
FAQ 06-0011, Rev 2, NEI 04-02
Download: ML072740248 (4)

Text

FAQ Number 06-0011 FAQ Revision 2 FAQ Title III.G.3 Transition Page 1 of 4 06-0011 clarify iii.g.3 fire area transition rev 2.doc Plant: D. C. Cook Date:September 20, 2007 Contact: Thomas Jutras (EPM) Phone:508-875-2121 X215 Email:thj@epm-inc.com Distribution: (NEI Internal Use) 805 TF FPWG RATF RIRWG BWROG PWROG Purpose of FAQ:

The purpose of this FAQ is to clarify that satisfying 10 CFR 50.48(c) will satisfy 10 CFR 50.48(a) and GDC3.

Is this Interpretation of 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, Appendix B, Section B.

2.2., (Page B-7, last paragraph)

Circumstances requiring guidance interpretation or new guidance:

The subject of transitioning Appendix R III.G.3/III.L areas is discussed in Section B.2.2 of NEI 04-02. However, the wording is not entirely clear. Confusion exists with regard to transitioning the areas as determi nistic or performance-based. Clarification is requested regarding the tr ansition of areas that currently comply with Section III.G.3 of Appendix R (with or without associated engineering evaluations and exemptions) to NFPA 805 as well as the need for a change evaluation.

Detail contentious points if licensee and NRC have not reached consensus on the facts and circumstances:

N/A Potentially relevant existing FAQ numbers:

FAQ 06-0012 addresses recovery actions which require change evaluations.

FAQ 07-0030 addresses evaluation of risk impact of recovery actions.

FAQ Number 06-0011 FAQ Revision 2 FAQ Title III.G.3 Transition Page 2 of 4 06-0011 clarify iii.g.3 fire area transition rev 2.doc Background 10 CFR 50 Appendix R, Section III.G.3 (and the corresponding section of NUREG 0800) was created to provide an acceptable means of demonstrating the ability to achieve and maintain safe shutdown in fire areas where the separation requirements of III.G.1/III.G.2 could not be met. Compliance for these areas involves the use of operator manual actions outside the Main Control Room, resulting in the need to utilize "recovery actions" as defined by NFPA 805, for these areas post-transition.

NFPA 805, Section 4.2.3.1 states, "Use of recovery actions to demonstrate the availability of a success path for the nuclear safety performance criteria automatically shall imply use of the performance-based approach as outlined in 4.2.4."

NFPA 805, Section 4.2.2 states, "The performance-based approach shall be permitted to utilize deterministic methods for simplifying assumptions within the fire area."

NFPA 805, Section 4.2.4 states, "When the use of recovery actions has resulted in the use of this approach, the additional risk presented by their use shall be evaluated."

Response Section:

Proposed resolution of FAQ and the basis for the proposal:

Revise NEI 04-02, Section B.2.2 to address the transition of III.G.3 areas using the performance-based approach. The per formance-based approach must include sufficient analyses (Thermal-Hydraulic, Fire Risk Evaluation [which may involve Fire Modeling], etc.) to demonstr ate that the available sa fe shutdown equipment and systems can meet the nuclear safety goals, nuclear safety objectives and the nuclear safety performance criteria in Chapter 1 of NFPA 805. The results of these analyses form the foundation for the av ailable time frames for recovery actions. The performance-based analysis should include a co mparison of the time available before failure of the nuclear safety performance crit eria to the timeline of required operator actions needed to achieve the nuclear safety performance criteria.

The reliability of the recovery actions should be addressed in the Fire PRA developed to support the transition. The risk associated with the impl ementation of recovery actions for these areas should be determined and prov ided in the transition report (see NEI 04-02, Section B.2.2.4

). Deterministic methods may be used to simp lify the analysis by verifying that the compliance strategy for the area meets the existing licensing basis, including approved exemptions, fire protection Existing Engineering Equivalency Evaluations (EEEEs, formerly Generic Letter 86-10 evaluations) and properly implemented Fire Protection Program (FPP) changes made under the Standard Fire Protection License Condition.

Note that exemptions, EEE Es and properly implement ed FPP changes must be reviewed to verify that the quality level and the basis for acceptability are still valid (see NEI 04-02 Sections 2.3.1 and 4.1.1). Also note that previous analysis has FAQ Number 06-0011 FAQ Revision 2 FAQ Title III.G.3 Transition Page 3 of 4 06-0011 clarify iii.g.3 fire area transition rev 2.doc demonstrated the ability to achieve the safe shutdown goals required by10 CFR 50 Appendix R,Section III.L. These same analyses should be capable of demonstrating the ability to achieve the NFPA 805 nuclear safe ty performance criteria for these areas.

For a III.G.3 fire area that fully meets the current licensing basis, a change evaluation would not be required and "Defense-in-Depth" and "Safety Margin" requirements of Sections 2.4.4.2 and 2.4.4.3 of NFPA 805 are "deemed to sati sfy". Also, if no changes were made, an uncertainty analysis is also not required per 10 CFR 50.48(c)(2)(iv).

It should be noted that it is expected that licensees transitioning to an NFPA 805-based Fire Protection Program will be developing a plant specific fire PRA (ref. RG 1.205) and the risk presented by the use of recovery actions in these areas will be determined as part of this effort (see NEI 04-02, Section B.2.2.4 and FAQ 07-0030)

If appropriate, provide proposed rewording of guidance for inclusion in the next Revision:

Replace NEI 04-02, Section B.2.2 (second paragraph) to state th e following (other paragraphs to remain as is:

Transition of a fire area that is governed by S ections III.G.3/III.L of 10 CFR 50 Appendix R is not treated differently than other plant fire areas. While alternative or dedicated shutdown capability was omitted from the deterministic requirements in Chapter 4 of NFPA 805, the transition of a fire area is not different. However, the current licensing basis for an alternative/dedicated shutdown fire area may be more explicit than other fire areas, since many licensees have detailed alt ernative/dedicated shutdown Safety Evaluation Reports. It may require more detailed documentation to ensure future change evaluations accurately capture the baseline configuration. For example, a dedicated shutdown methodology may credit a unique power source or pump that is not part of the plant's safety systems or post

-fire safe shutdown program. Post

-transition changes to this equipment or methodology would need to be accurately captured for assessment of risk impact.

Transition of a fire area that is governed by Sections III.G.3/III.L of 10 CFR 50 Appendix R (or applicable sections of NUREG-0800) will be performed using the performance-based approach. The performance-based approach must include sufficient analyses (Thermal-Hydraulic, Fire Risk Evaluation [which may include Fi re Modeling], etc.) to demonstrate that the available safe shutdown equipment and systems can meet the nucl ear safety goals, nuclear safety objectives and the nuclear safety performance criteria in Chapter 1 of NFPA 805. The results of these analyses form the foundation for the available time frames for recovery actions. The performance-based analyses should include a comparison of the time available before failure of the nuclear safety performance criteria to the ti meline of required opera tor actions needed to achieve the nuclear safety performa nce criteria. The reliability of the recovery actions should be addressed in the Fire PRA devel oped to support the transition.

The risk associated with the implementation of recovery actions for these areas should be determined and provided in the transition report. (See NEI 04-02, Section B.2.2.4)

FAQ Number 06-0011 FAQ Revision 2 FAQ Title III.G.3 Transition Page 4 of 4 06-0011 clarify iii.g.3 fire area transition rev 2.doc Deterministic methods may be used to simplify the analysis by verifying that the compliance strategy for the area meets the existing licensing basis, including approved exemptions, fire protection Existing Engineering Equivalency Evaluations (EEEEs, formerly Generic Letter 86-10 evaluations) and properly implemented Fire Protection Program (FPP) changes made under the Standard Fire Protection License Condition. Note that exemptions, EEEEs and properly implemented FPP changes must be reviewed to ve rify that the quality level and the basis for acceptability are still valid (see NEI 04-02 Sections 2.3.1 and 4.1.1). Also note that previous analyses have demonstrated the ability to ach ieve the safe shutdown goals required by 10 CFR 50 Appendix R, Section III.L. Theses same analyses may be capable of demonstrating the ability to achieve the nuclear safety performance criteria for these areas.

For alternative/dedicated shutdown fire areas that fully meet the current licensing basis, a change evaluation would not be required and "Defense-in-Depth" and "Safety Margin" requirements of Sections 2.4.4.2 and 2.4.4.3 of NFPA 805 are "deemed to satisfy" so no additional Defense-in-Depth or Safety Margin analyses are necessary. Also, if no changes were required to meet the nuclear safety performance criteria, an uncertainty analysis is also not required per 10 CFR 50.48(c)(2)(iv).

The current licensing basis for an alternative/dedicated shutdown fire area may be more explicit than other fire areas, since many licensees have detailed alternative/dedicated shutdown Safety Evaluation Reports. It may require more detailed documentati on to ensure future change evaluations accurately capture the baseline configuration. For example, a dedicated shutdown methodology may credit a unique power source or pump that is not part of the plant's safety systems or post-fire safe shutdown program. Post-transition changes to this equipment or methodology would need to be captured for assessment of risk impact and therefore, the alternate/dedicated shutdown strategy must be addressed in the fire PRA.