ML093020058
| ML093020058 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 10/21/2009 |
| From: | Kammer M SCANA Corp |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| FAQ-09-0057 | |
| Download: ML093020058 (7) | |
Text
FAQ Number 09-0057 FAQ Revision 1 FAQ Title New Shutdown Strategy Page 1 of 7 Plant: VC Summer Date:October 21, 2009 Contact: Mike Kammer Phone: (803) 345-4000 Email: MKammer@scana.com Distribution: (NEI Internal Use) 805 TF FPWG RATF RIRWG BWROG PWROG Purpose of FAQ:
The purpose of this FAQ is to provide an alter native transition evaluation for plants that use the Self-Induced Station Blac kout (SISBO) strategy in th eir existing Fire Protection (FP) program and have committed to: make a change to their current FP progr am by using an Alternate Shutdown Strategy (e.g. eliminate SISBO), incorporate the new strategy in the post-transition FPP, effectively eliminating SISBO post-transition, and model the Alternate Shutdown Strategy in the FPRA as the baseline for the
transition process.
In addition, since NEI 04-02 addresses trans itioning the CLB as the only means of satisfying the NFPA 805 goals as codified in 10 CFR 50.48(c), this FAQ proposes updates to specifically allow this alternative transition approach.
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):
Section 2.3.1 Section 4.1.1 Section 4.3.1 Section 4.3.2 Section 5.3.1 Appendix J, Section J.5
FAQ Number 09-0057 FAQ Revision 1 FAQ Title New Shutdown Strategy Page 2 of 7 Circumstances requiring guidance interpretation or new guidance:
The above sections from NEI 04-02 es tablish some important concepts:
When transitioning to NFPA 80 5, the existing Appendix R program serves as the baseline for all evaluations, with certain permitted exceptions. Specifically, Sect ion 4.1.1 states:
"The extent to which the pre-transitional fire protection licensing basis can be incorporated into the new NFPA 805 licensing basis is determined by the extent to which the fire protection CLB can be shown to comply with the
requirements in NFPA 805. However, exceptions are permitted for the following licensee specific deviations from NFPA 805 requirements: "Alternatives from the fundamental fi re protection program attributes of NFPA 805 Chapter 3 [NFPA 805 Chapt er 3 Section 3.1] previously reviewed and approved by the NRC. "Exemptions/deviations from 10 CFR 50 Appendix R / NUREG 0800 [NFPA 805 Figure 2.2] previously reviewed and approved by the NRC. Note the licensee will review these exemptions/deviations during the transition process to ensure the basis for acceptability is still valid. "Existing Engineering Equivalency Evaluations [NFPA 805 Figure 2.2]. Note the licensee will review these equivalency evaluat ions during the transition process to ensure the quality level and the basis for acceptability
is still valid."
Note that for each Chapter 3 element, the licensee must: demonstrate compliance (for example, via previous NRC approval, Engineering Equivalency Evaluations, or minor clarifications), make a change to achieve compliance, or request NRC approval (for example, via "10 CFR 50.
48(c)(4)" or 10 CFR 50.48(c)(2)(vii)").
Figure 4-2 in section 4.3.1 shows that the existing fundamental fire protection program and design elements is evaluated against the NFPA 805 Chapter 3
requirements. If an element fails to meet those requirements and is not a previously approved alternative, then it must be br ought into compliance through a design or
operational change or a license amendment request.
Figure 4-3 in section 4.3.2 shows that the "e xisting" fire area compliance strategy is
subjected to the area-by-area transition process and that if it does not meet the deterministic requirements then it w ould be treated through a performance-based approach per Section 4.2.4 of NFPA805 (either via the use of fi re modeling or the use of a fire risk evaluation).
FAQ Number 09-0057 FAQ Revision 1 FAQ Title New Shutdown Strategy Page 3 of 7 Section 5.3.1 discusses the application of fire risk evaluations, and quotes from NFPA 805 as follows:
"In the event of a change to a previous ly approved fire protection program element, a risk-inform ed plant fire risk 1 evaluation shall be performed and the results used as described in 2.4.4 to ens ure that the public risk associated with fire-induced nuclear fuel damage accidents is low and the adequate defense-in-depth and safety margins are maintain ed. [NFPA 805, Section 2.2.9]"
Section 5.3.1 and Appendix J, Section J5, indi cate that such fire risk evaluations, and other fire risk evaluations, would us e a FPRA representing the "existing" program as the baseline for comparison and for demonstrating that a change was risk neutral or risk reducing.
The implication or assumptions resulting from the above text from NEI 04-02 for a plant that uses a SISBO strategy is as follows:
the existing program to be used for the compliance assessment would be the SISBO program; the elimination of the SISBO stra tegy would be a change, and hence be subject to a fire risk evaluation; the baseline for this fire risk evaluati on would have to be a FPRA representing the SISBO strategy; and all other fire risk evaluations would al so use the SISBO FPRA as a baseline for fire risk evaluation.
Discussion A major benefit to the nuclear industry of the risk informed regulation in NFPA 805 is that it provides a driving force for ut ilities to abandon strategies that, although they comply with Appendix R requirements, take actions that inherently increase plant risk. The Self Induced Station Blackout (SISBO) approach is an example of such a strategy that, in order to meet deterministic requirements, purposefully removes offsite power and a train of Engineered Safety Feature equipment to reduce the likelihood of spurious operation.
Using NFPA 805 as the driver, plants that e liminate the SISBO stra tegy in favor of an approach that optimizes available equip ment are inherently reducing the plant risk due to fire. However, because NFPA 805 is the driver for performing a new Fire PRA that complies with RG1.200, many plants only have old IPEEE Fire PRAs (which do not comply with RG 1.200) that show the fire risk associated with their Appendix R fire protection stra tegy. As a result, plants that are revising their overall 1 Note that this passage currently reads "change evaluation." This FAQ has updated terminology to conform with the latest draft of R.G. 1.205.
FAQ Number 09-0057 FAQ Revision 1 FAQ Title New Shutdown Strategy Page 4 of 7 Safe Shutdown Strategy will be developing a new Fire PRA to reflect the revised overall strategy and will not have a comparable assessment of the fire risk under their Appendix R Program (CLB
). It is not cost-effectiv e to develop two fire PRAs just to make the comparison, especially when the existing, deterministic (CLB) compliance strategy is to be abandoned.
A plant may make the decision that it will eliminate SISBO and many associated operator actions as part of the transition process to NFPA 805. As a result, the FPRA being developed to support the NFPA 805 transition fire risk evaluations and post transition change evaluations would logically reflect the plant operations after these changes have been made. Hence, the FPRA will not be reflective of the current Appendix R program, but of a revised shutdown strat egy. As a result there will be no baseline FPRA that meets the requirements of the soon-to-be-issued RG 1.200 addendum for FPRA capability per ASME/ANS-RA-2009, and thus no basis for the transition/fi re risk evaluation showing t hat elimination of SISBO and associated operator actions is "risk neutral or risk reducing". Further, other fire risk evaluations resulting from the transition process will not have a baseline FPRA for the current Appendi x R program against which to compar e the impact of the change.
It is believed that transiti oning to NFPA805 will provide long term benefit to the Fire Protection Program, and a plant would appr oach this project as an opportunity to improve risk in this area. In addition, there would be little value in developing a full Fire PRA for a strategy the station intends to abandon. While it is understandably desirable to quantitatively defi ne risk improvements, the additional expense to re baseline the existing Appendix R strategy is not co st beneficial.
Detail contentious points if licensee and NRC have not reached consensus on the facts and circumstances:
Project goals were established to improve t he Fire Protection Program by revising
the Appendix R shutdown approach. While the new approach may be beneficial from a regulatory standpoint, the specific directions found in NEI 04-02 may be challenged from a "comparable" risk standpoint. NRC may not accept the elimination of SISBO as r epresenting an "allowable" deviation from Appendix R for the purpose of establishing the baseline for the pre-transition prog ram. This could also lead to NRC not accepting change analyses unless "comparable" risk insights are made available in the LAR.
This includes assuming that the starting point for the NFPA805 fire risk evaluations (after elim ination of SISBO and associated manual operator actions to the extent practical) is risk neutral or risk reducing versus Appendix R program. Potentially relevant existing FAQ numbers:
06-0012 08-0054 08-0055 FAQ Number 09-0057 FAQ Revision 1 FAQ Title New Shutdown Strategy Page 5 of 7 Response Section:
Proposed resolution of FAQ and the basis for the proposal:
Proposed Alternative: The replacement of SISBO with a symptom-based fire protection strategy will be accepted as risk reducing or risk neutral without a requirement to quantify the exact reduction in fire risk. T he FPRA performed for the non-SISBO case would constitute the baseline PRA for all fire risk evaluations performed to suppor t the NFPA 805 transition.
Discussion In virtually all areas of nuclear power plant emergency response except for fire, nuclear plants follow symptom-oriented emergency procedures. This is
recognized as the most appropriate m anner of responding to plant accident conditions. The use of SISBO and asso ciated operator actions is an event-oriented approach, which ex isted prior to the post-TM I transition to symptom-oriented in the 1980's. By its very nature, eliminating SI SBO (and numerous associated operator actions) allows plants to better protect the critical safety functions in the event of a serious fire. The completion of comprehensive circuit analysis for both NSP and FPRA as part of the NFPA 805 transition process obviates the reason why SISBO was originally used at these plants. Therefore, elimination of SI SBO and numerous associated operator actions should be deemed risk-neutral or risk reducing when comprehensive circuit analysis is
being performed as part of NFPA 805 transition. Quantifying the exact reduction in fire risk should not be required.
Since this will be the new baseline risk for fire, and since this constitutes an improvement over the Appen dix R case, the non-SISBO ca se should constitute the baseline PRA for all fire risk evaluations performed to support the NFPA 805
transition, including any subsequent fire risk evaluations.
If appropriate, provide proposed rewording of guidance for inclusion in the next Revision:
Revise NEI 04-02 Section 4.1.1 Transition Process Overview Modify as follows (new text in bold italic
). The extent to which the pre-transitional fire protection licensing basis can be incorporated into the new NFPA 805 licensing basis is determined by the extent to which the fire protection CLB can be shown to comply with the FAQ Number 09-0057 FAQ Revision 1 FAQ Title New Shutdown Strategy Page 6 of 7
requirements in NFPA 805. However, exceptions are permitted for the following licensee specific deviations from NFPA 805 requirements:
Alternatives from the fundamental fire protection program attributes of NFPA 805 Chapter 3 [NFPA 805 Chapt er 3 Section 3.1] previously reviewed and approved by the NRC. Exemptions/deviations from 10 CFR 50 Appendix R / NUREG 0800 [NFPA 805 Figure 2.2] previously reviewed and approved by the NRC. Note the licensee will review these exemptions/deviations during the transition process to ensure the basis for acceptability is still valid. Existing Engineering Equi valency Evaluations [NF PA 805 Figure 2.2]. Note the licensee will review these equivalency evaluat ions during the transition process to ensure the quality level and the basis for acceptability is still valid.
In cases where alternate shutdown strategies and equipment are
selected to support evaluation of the plant against the performance criteria of NFPA805, Chapter 1, compliance with the deterministic requirements [NFPA805, section 4.2.3] or the performance based approach [NFPA805, section 4.2.4] sh all be performed consistent with the requirements of the standard. For this case, An engineering evaluation sh all indicate the strategy (1) satisfies the performance criteria, perfo rmance objectives, and goals for
nuclear safety and radiological release; (2) maintains safety margins (3) maintains post-fire de fense-in-depth (fire prevention, fire suppression, and post-fire safe shutdown capability); and (4)
a qualitative assessment of the ch ange in risk comparing the current CLB (and shutdown strategy) and the new shutdown
strategy shall conclude that the new strategy/ associated equipment is risk-neutral or risk reducing.
2 For areas where a risk based evaluation has been performed (NFPA805, section 4.2.4.2) utiliz ing an alternative safe shutdown strategy, the fire PRA representing the alternat ive safe shutdown strategy shall be the baseline and shall be used as a basis for
future fire risk evaluations [NFPA 805, section 2.4.4] to perform quantitative assessments of deviat ions from the deterministic requirements of Chapter 4.
2 The purpose of item 4 is to establish that it is not necessary to perform a fire risk evaluation to demonstrate that the new shutdown strategy selected for transition is risk reducing versus the CLB. For example, if the CLB is SISBO, and the new strategy is non-SISBO, it is not necessary to perform a fire risk evaluation to show that the non SISBO strategy is risk reducing versus the SISBO strategy. This can be documented by qualitative assessment.
FAQ Number 09-0057 FAQ Revision 1 FAQ Title New Shutdown Strategy Page 7 of 7 Revise NEI 04-02 Figure 4-3, "Fire Ar ea by Fire Area Transition Process (Simplified)"
Revise Entry Box to ExistingFireAreaComplianceStrategyFireAreaComplianceStrategy Revise NEI 04-02, Section 4.3.2, Nuclear Safety Performance Criteria Transition Review The fire area by fire area review determines whether the CLB is intact or the revised shutdown strategy is documented adequately to support the transition.
The review is intended to identify and document how each fire area: -