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Category:Meeting Briefing Package/Handouts
MONTHYEARML24289A2352024-10-15015 October 2024 Supplemental Slides - SNC Presentation - Pre-Submittal Meeting on October 15, 2024 - Proposed Vogtle 3 and 4 PRHR LAR ML24283A2022024-10-0909 October 2024 Slides - SNC Presentation - Pre-Submittal Meeting on October 16, 2024 - Proposed Vogtle 3 and 4 Flexibility Modes LAR ML24282A9822024-10-0808 October 2024 Slides - SNC Presentation - Pre-Submittal Meeting on October 15, 2024 - Proposed Vogtle 3 and 4 Passive Residual Heat Removal Actuation Logic Changes License Amendment Request ML24164A2942024-06-17017 June 2024 Licensee Slides for Pre-submittal Meeting for VEGP Units 3 and 4 for a Proposed License Amendment Request Regarding TS 3.3.8 ML24158A3832024-06-0606 June 2024 SNC Slides - Vogtle 3 and 4 - TS 3-8-2 - Pre-Submittal Meeting - 06-27-2024 ML24120A2202024-04-30030 April 2024 Annual Assessment Meeting Presentation Slides - April 30, 2024 ML24089A1492024-04-0404 April 2024 Slides - SNC Presentation - Pre-Submittal Meeting on April 4, 2024 - Proposed Vogtle 3 and 4 TS 3.7.6 LAR ML24060A2732024-03-0707 March 2024 SNC Slides - Pre-Submittal Meeting on March 7, 2024 - Vogtle 3 & 4 TSTF-577 LAR ML24022A1192024-01-24024 January 2024 Slides - SNC Slides - Pre-Submittal Meeting on January 24, 2024 - Vogtle 3 & 4 Explosively Actuated Valves Relief Request ML23361A0812024-01-0808 January 2024 SNC Slides - Pre-Submittal Public Meeting on January 8, 2024 Related to Fleet QATR ML24004A1852024-01-0404 January 2024 SNC Slides - Pre-Submittal Public Meeting on January 8, 2024 Related to Fleet QATR Revised ML23257A2322023-09-28028 September 2023 SNC Presentation - Pre-Submittal Meeting on September 28, 2023 - Proposed Vogtle 3 and 4 TS 3.7.6 LAR ML23137A1162023-06-0202 June 2023 Draft Slides for Advisory Committee on Reactor Safeguards Subcommittee Meeting Regarding Use of Accident Tolerant Fuel Lead Test Assemblies ML23094A1402023-04-0404 April 2023 4 -- 2022 Aam Slides ML23055A0402023-02-24024 February 2023 VEGP, Unit 4, Potential License Amendment Request for Prior to Initial Criticality Overview Presentation ML23033A0232023-02-0202 February 2023 Dashboard Report 2-2-2023 ML22335A0372022-12-0101 December 2022 Dashboard Report 12-1-2022 ML22329A0192022-12-0101 December 2022 Southern Nuclear Company Slides - Pre-Submittal Meeting on December 1, 2022 - Vogtle SR 3.4.14.1 LAR and Alternative Relief Request 1 ML22332A5372022-11-28028 November 2022 Draft LAR 23-001 for 12-8-22 Public Meeting ML22332A0012022-11-28028 November 2022 SNC Slides - Pre-Submittal Meeting on November 30, 2022 - Vogtle TS 5.5.11 License Amendment Request ML22319A1242022-11-15015 November 2022 NRC Slides for November 15, 2022 Public Meeting on Part 52 Lessons Learned ML22319A0052022-11-15015 November 2022 NEI Slides for November 15 2022 Public Meeting on Part 52 Lessons Learned ML22319A1232022-11-15015 November 2022 Kozak Slides for November 15, 2022 Public Meeting on Part 52 Lessons Learned ML22251A0002022-09-30030 September 2022 Pre-Submittal Meeting on September 13, 2022 - Vogtle Online Monitoring LAR ML22265A0972022-09-22022 September 2022 Southern Nuclear Company Slides on Lessons Learned from Part 52 Implementation for Public Meeting on 9/27/2022 ML22265A0982022-09-22022 September 2022 NRC Slides on Part 52 Lessons Learned Construction Initiative for Public Meeting on 9/27/2022 ML22138A3952022-05-24024 May 2022 Slides - SNC Slides - Pre-Submittal Meeting on May 24, 2022 - Vogtle RR RWST Suction Check Valves ML22137A2812022-05-23023 May 2022 Slides - SNC Slides - Pre-Submittal Meeting on May 23, 2022 - Vogtle TS 3.8.1 and TSTF-163 LAR ML22126A0102022-05-11011 May 2022 Pre-Submittal Meeting on May 11, 2022 - Vogtle ATF LTAs LAR and Exemption Requests - Licensing Questions ML22123A3332022-05-10010 May 2022 Pre-Submittal Meeting 2: TSTF-51, TSTF-471, TSTF-490, and Alternative Source Term License Amendment Request - May 10, 2022 (EPID L-2022-LRM-0033)(slides) ML22110A1702022-04-20020 April 2022 4 2022 Annual Assessment Meeting.Final ML22021B6472022-01-27027 January 2022 Pre-Submittal for Westinghouse Increased Enrichment Accident Tolerant Fuel Lead Test Assemblies (EPID L-2022-LRM-0003) (Slides) ML21306A0242021-11-30030 November 2021 SNC Pre-Submittal Meeting for LAR to Relocate Augmented Piping Inspection Program Details from TSs to a Licensee Controlled Document for Farley Nuclear Plant, Units 1 & 2; and Vogtle Electric Generating Plant, Units 1 & 2 (EPID L-2021-LRM-0 ML21333A2172021-11-29029 November 2021 Readiness Group Presentation During 12-2-21 Public Meeting ML21230A2842021-08-18018 August 2021 SNC Slides - Vogtle MSIV Elimination LAR - Pre-submittal Meeting Part 2 - 08-25-2021 ML21193A0762021-07-0808 July 2021 ITAAC Related to Incore Instrument Thimble Assembly (Iita) ML21187A0972021-07-0808 July 2021 Late Filed Allegations (Lfa) Process ML21172A1312021-07-0101 July 2021 Pre-Submittal Meeting Alternate Source Term and TSTF-490 ML21193A0772021-06-24024 June 2021 Exemption from Operator Written Examination and Operating Test for Unit 4 Licenses, 6-24-21 Pre-submittal Meeting ML21085A4902021-05-19019 May 2021 Risk-informed Resolution of Generic Letter 2004-02 ML21064A3652021-03-0101 March 2021 Dashboard Report 3-1-2021 ML21027A2062021-02-28028 February 2021 Fixed 8-Hour Emergency Light Deviation Pre-Submittal Meeting, February 2021 (Slides) ML21057A0182021-02-26026 February 2021 Pre-Submittal Meeting Revise Technical Specification 3.2.1 Heat Flux Hot Channel Factor (Fq(Z)) (EPID L-2021-LRM-0023) (Slides) ML21036A1172021-02-0505 February 2021 SNC Slides - Pre-Submittal Meeting on February 16, 2021 - Beacon LAR ML20343A0742020-12-0202 December 2020 Dashboard Report 12-2-2020 ML20318A1032020-11-12012 November 2020 SNC ERO Staffing LAR RAI Responses ML20314A0962020-11-0202 November 2020 Dashboard Report 11/02/2020 ML20217L4312020-08-13013 August 2020 Edwin I Hatch, Units 1 and 2; and Vogtle Electric Plant, Units 1, 2, 3, and 4 - Meeting Slides a License Amendment Request for the Emergency Plan (EPID Nos L-2020-LLA-0150 and L-2020-LLA-051 ML20136A2832020-05-15015 May 2020 4 EOC Slides ML20114E3032020-04-23023 April 2020 Risk-Informed GL 2004--02 Pre-Submittal NRC Meeting - May 2020 2024-06-06
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24289A2352024-10-15015 October 2024 Supplemental Slides - SNC Presentation - Pre-Submittal Meeting on October 15, 2024 - Proposed Vogtle 3 and 4 PRHR LAR ML24283A2022024-10-0909 October 2024 Slides - SNC Presentation - Pre-Submittal Meeting on October 16, 2024 - Proposed Vogtle 3 and 4 Flexibility Modes LAR ML24282A9822024-10-0808 October 2024 Slides - SNC Presentation - Pre-Submittal Meeting on October 15, 2024 - Proposed Vogtle 3 and 4 Passive Residual Heat Removal Actuation Logic Changes License Amendment Request ML24164A2942024-06-17017 June 2024 Licensee Slides for Pre-submittal Meeting for VEGP Units 3 and 4 for a Proposed License Amendment Request Regarding TS 3.3.8 ML24158A3832024-06-0606 June 2024 SNC Slides - Vogtle 3 and 4 - TS 3-8-2 - Pre-Submittal Meeting - 06-27-2024 ML24120A2202024-04-30030 April 2024 Annual Assessment Meeting Presentation Slides - April 30, 2024 ML24089A1492024-04-0404 April 2024 Slides - SNC Presentation - Pre-Submittal Meeting on April 4, 2024 - Proposed Vogtle 3 and 4 TS 3.7.6 LAR ML24060A2732024-03-0707 March 2024 SNC Slides - Pre-Submittal Meeting on March 7, 2024 - Vogtle 3 & 4 TSTF-577 LAR ML24022A1192024-01-24024 January 2024 Slides - SNC Slides - Pre-Submittal Meeting on January 24, 2024 - Vogtle 3 & 4 Explosively Actuated Valves Relief Request ML23361A0812024-01-0808 January 2024 SNC Slides - Pre-Submittal Public Meeting on January 8, 2024 Related to Fleet QATR ML24004A1852024-01-0404 January 2024 SNC Slides - Pre-Submittal Public Meeting on January 8, 2024 Related to Fleet QATR Revised ML23304A2682023-11-0707 November 2023 License Amendment Request to Revise the Ultimate Heat Sink Mission Time Pre Submittal Meeting on November 7, 2023 ML23311A2452023-11-0707 November 2023 Pre-Submittal Meeting on November 7, 2023 - License Amendment Request to Revise the Ultimate Heat Sink Mission Time (Slides) ML23293A0052023-10-20020 October 2023 Lessons Learned from the ITAAC Hearing Process for Vogtle 3 and 4 ML23257A2322023-09-28028 September 2023 SNC Presentation - Pre-Submittal Meeting on September 28, 2023 - Proposed Vogtle 3 and 4 TS 3.7.6 LAR ML23137A1162023-06-0202 June 2023 Draft Slides for Advisory Committee on Reactor Safeguards Subcommittee Meeting Regarding Use of Accident Tolerant Fuel Lead Test Assemblies ML23094A1402023-04-0404 April 2023 4 -- 2022 Aam Slides ML23072A1802023-03-13013 March 2023 2023 RIC Powerpoint Slide Presentation, Vogtle 3: Journey from Construction to Operations ML23055A0402023-02-24024 February 2023 VEGP, Unit 4, Potential License Amendment Request for Prior to Initial Criticality Overview Presentation ML23033A0232023-02-0202 February 2023 Dashboard Report 2-2-2023 ML22335A5542022-12-0101 December 2022 Slides - SNC Slides - Pre-Submittal Meeting on December 1, 2022 - Vogtle SR 3.4.14.1 LAR and Alternative Relief Request - ML22335A0372022-12-0101 December 2022 Dashboard Report 12-1-2022 ML22329A0192022-12-0101 December 2022 Southern Nuclear Company Slides - Pre-Submittal Meeting on December 1, 2022 - Vogtle SR 3.4.14.1 LAR and Alternative Relief Request 1 ML22332A0012022-11-28028 November 2022 SNC Slides - Pre-Submittal Meeting on November 30, 2022 - Vogtle TS 5.5.11 License Amendment Request ML22319A1232022-11-15015 November 2022 Kozak Slides for November 15, 2022 Public Meeting on Part 52 Lessons Learned ML22319A0052022-11-15015 November 2022 NEI Slides for November 15 2022 Public Meeting on Part 52 Lessons Learned ML22319A1242022-11-15015 November 2022 NRC Slides for November 15, 2022 Public Meeting on Part 52 Lessons Learned ML22278A0382022-10-0505 October 2022 Dashboard Report 10-5-2022 ML22251A0002022-09-30030 September 2022 Pre-Submittal Meeting on September 13, 2022 - Vogtle Online Monitoring LAR ML22265A0972022-09-22022 September 2022 Southern Nuclear Company Slides on Lessons Learned from Part 52 Implementation for Public Meeting on 9/27/2022 ML22265A0982022-09-22022 September 2022 NRC Slides on Part 52 Lessons Learned Construction Initiative for Public Meeting on 9/27/2022 ML22206A1712022-07-25025 July 2022 Dashboard Report 7-25-2022 ML22206A1682022-07-25025 July 2022 Dashboard Report 7-25-2022 ML22201A0442022-07-20020 July 2022 Voices Dashboard Report for Vogtle Unit 3 as of July 20, 2022 ML22144A0502022-05-24024 May 2022 Dashboard Report 5-24-2022 ML22138A3952022-05-24024 May 2022 Slides - SNC Slides - Pre-Submittal Meeting on May 24, 2022 - Vogtle RR RWST Suction Check Valves ML22144A0492022-05-24024 May 2022 Dashboard Report 5-24-2022 ML22137A2812022-05-23023 May 2022 Slides - SNC Slides - Pre-Submittal Meeting on May 23, 2022 - Vogtle TS 3.8.1 and TSTF-163 LAR ML22126A0102022-05-11011 May 2022 Pre-Submittal Meeting on May 11, 2022 - Vogtle ATF LTAs LAR and Exemption Requests - Licensing Questions ML22123A3332022-05-10010 May 2022 Pre-Submittal Meeting 2: TSTF-51, TSTF-471, TSTF-490, and Alternative Source Term License Amendment Request - May 10, 2022 (EPID L-2022-LRM-0033)(slides) ML22126A0012022-05-0606 May 2022 SNC Slides - Pre-Submittal Meeting on May 11, 2022 - Vogtle ATF LTAs LAR and Exemptions ML22110A1702022-04-20020 April 2022 4 2022 Annual Assessment Meeting.Final ML22060A0062022-02-28028 February 2022 4Q 2021 Performance Summary U3 ML22021B6472022-01-27027 January 2022 Pre-Submittal for Westinghouse Increased Enrichment Accident Tolerant Fuel Lead Test Assemblies (EPID L-2022-LRM-0003) (Slides) ML22026A0582022-01-26026 January 2022 Dashboard Report 1-26-2022 ML21306A0242021-11-30030 November 2021 SNC Pre-Submittal Meeting for LAR to Relocate Augmented Piping Inspection Program Details from TSs to a Licensee Controlled Document for Farley Nuclear Plant, Units 1 & 2; and Vogtle Electric Generating Plant, Units 1 & 2 (EPID L-2021-LRM-0 ML21333A2172021-11-29029 November 2021 Readiness Group Presentation During 12-2-21 Public Meeting ML21230A2842021-08-18018 August 2021 SNC Slides - Vogtle MSIV Elimination LAR - Pre-submittal Meeting Part 2 - 08-25-2021 ML21197A0032021-08-0606 August 2021 Slides - SNC Slides - Pre-Submittal Meeting on August 13, 2021 - Vogtle TS 3.3.1 and 3.3.2 LAR ML21187A0972021-07-0808 July 2021 Late Filed Allegations (Lfa) Process 2024-06-06
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Page 1 of 6 Vogtle Evaluation of DEGB-Only Model versus Continuum Break Model Prepared by: Thomas Demey , Tim Sande Reviewed by: Kip Walker, Diane Jones Revision 0 , 7/2 2/2016 1. Purpose and Scope NUREG-1829 provides a table of LOCA frequencies as a function of break size. Although there is no explicit guidance related to the difference in partial breaks and double ended guillotine breaks (DEGBs) in the NUREG, there has been a lot of discussion around a statement in NUREG-1829 that a break of a given size is more likely to result from a complete rupture of a small pipe than a partial rupture of a larger pipe. Two different positions have been postulated for the types of breaks that could occur:
DEGB-only model
- If a pipe starts to break, the forces from the system operating pressure would cause the crack to propagate into a full DEGB and therefore partial breaks do not need to be evaluated. In this model, the higher frequency associated with small breaks is attributed to a greater likelihood of DEGBs on small diameter pipes.
Continuum break model
- A break of any size up to and including a DEGB can occur on any pipe. In this model, the higher frequency associated with small breaks is attributed to the combination of DEGBs on small diameter pipes and small breaks on large pipes.
Draft Regulatory Guide 1.229 requires that both models be evaluated as a sensitivity. During the NARWHAL NRC audit, the staff clarified that the two models that have been debated represent bounding assumptions regarding the frequency allocation. The DEGB-only model assumes that the frequency associated with a partial break is so low that it is negligible; the continuum break model assumes that the frequency of partial breaks is essentially the same as equivalent size DEGBs. The reality is likely somewhere between these two extremes. Therefore, by evaluating both models with their associated frequency allocations, the sensitivity of the risk quantification to the choice of break models can be determined.
This white paper describes the methodology for evaluating risk using the two break models and provides results for Vogtle based on the current NARWHAL model.
- 2. General Methodology If a licensee is using the threshold break approach for quantifying risk (where a bounding break size is determined and all larger breaks are assumed to fail), the DEGB
-only model will by definition result in a risk (CDF and LERF) result that is less than or equal to the continuum break model. Since the continuum break model evaluates the range of possible break sizes up to and including a DEGB at every weld, the smallest break that fails could be either a partial break or a DEGB. If it is a DEGB, the smallest break that fails with the DEGB
-only model would not change and the calculated risk would be the same. If the smallest break that fails in the continuum model is a partial break, the DEGB-only model would skip over that break size and predict that a larger DEGB is the smallest break that fails. This would result in a lower threshold break frequency and a lower overall risk. Therefore, if the threshold break methodology is being Page 2 of 6 used, the continuum break model can be used without performing a sensitivity analysis for the DEGB-only model.
If a licensee is using the conditional failure probability (CFP) approach for quantifying risk, it is necessary to consider both the continuum break model and the DEGB
-only model. The general methodology for doing this is described below:
- 1. The overall plant
-wide LOCA frequencies must be allocated to individual welds and break sizes using an acceptable allocation methodology (e.g., some form of a top
-down or hybrid LOCA frequency allocation). 2. GSI-191 failures (strainer, pump, and and/or core failures due to the effects of debris) must be evaluated for each break.
- 3. The PRA model categories (e.g., large breaks) should be broken up into size ranges where breaks within a given size range are assumed to have an equal probability. Note that every size range must include breaks that fall within the size range.
- 4. The CFP for a PRA category is calculated based on the combined CFPs for each size range along with the corresponding LOCA frequency weight associated with each category. For example, given a large break PRA category defined as breaks larger than or equal to 6 inches, the size ranges could be 6"
-15", 15"-25", and >25". Although the >25" category is most likely to experience GSI
-191 failures (due to the greater quantity of debris generated by the larger breaks), most of the frequency weight is associated with the smaller breaks in the 6"
-15" category.
- 5. The CFP values can then be used with the plant PRA model to calculate the risk associated with GSI
-191. These steps can be used to evaluate either the continuum break model or the DEGB
-only model. However, as noted in Step 3, every size range must include breaks that fall within the size range. Most plants have a surge line that is 12 to 14 inches in diameter and primary loop piping that is 27.5 inches or larger in diameter with no intermediate pipe sizes. Therefore, using a size range of 15"
-25" may be perfectly acceptable for evaluating the continuum break model, but it would not be acceptable for the DEGB
-only model since there are no DEGBs between 15 and 25 inches. This raises the question of how to distribute the frequency associated with breaks between the DEGB sizes if these break sizes are assumed to be impossible (as done in the DEGB-only model). If the size range is cut off right below the larger DEGB size, the frequency associated with the gap between the DEGB sizes will be attributed to the smaller beak size, which is generally less likely to fail (skewing the risk lower). If the size range is cut off right above the smaller DEGB size, the frequency associated with the gap between the DEGB sizes will be attributed to the larger break size, which is generally more likely to fail (skewing the risk higher). In general, the recommended approach is to select the midpoint between the DEGB sizes to avoid biasing the results in either direction.
- 3. NARWHAL Analysis of Continuum Breaks vs. DEGB
-only Breaks for Vogtle As an example calculation , two NARWHAL simulations were run using the current Vogtle model. The simulations evaluated the whole range of continuum break sizes for two equipment configurations (all pumps available and single train failure). To compare the DEGB
-only model to the continuum model, the partial breaks were simply filtered out of the results.
Page 3 of 6 Figure 1 shows the fiber accumulated on the RHR A and CS A strainers when all pumps are available. The graph on the left shows the data for the full set of breaks evaluated with the continuum model, and the graph on the right shows the results from just the DEGBs. Note the wide gap between the 12.8
-inch surge line breaks and the 27.5
-inch cold leg breaks.
Figure 1 - Fiber Load on RHR A and CS A Strainer s (all pumps available)
Figure 2 shows the CFP value as a function of break size for the various failure mechanisms. The only failures observed were flashing failures and strainer debris limit failures. The CFP values in this figure were simply calculated as the number of breaks that failed divided by the number of total breaks evaluated for a given break size. For the continuum break model, the 27.5-inch break size includes cold leg pipe DEGBs, as well as partial breaks on the hot leg and crossover leg piping (i.e., all pipes that can experience a 27.5
-inch break). This comparison shows that in general, the CFP value for the large break sizes is higher with the DEGB
-only model, which makes sense since DEGBs have a larger (spherical) ZOI volume compared to the partial break (hemispherical) ZOIs.
Figure 2 - Break Size
-Dependent CFPs (all pumps available)
Page 4 of 6 Figure 3 and Figure 4 show similar results for the case with single train failure.
Figure 3 - Fiber Load on RHR A and CS A Strainer s (single train failure)
Figure 4 - Break Size
-Dependent CFPs (single train failure)
The CFP values corresponding to the Vogtle PRA categories (small, medium, and large LOCAs) were calculated using the built-in CFP calculator in NARWHAL Version 1.0. The required inputs are shown in Table 1 for LOCA frequency values, Table 2 for the PRA categories, and Table 3 for the size ranges within the PRA categories. Note that three separate size ranges are used for the DEGB-only model. The first size range biases the results by assigning the frequency for break sizes between the surge line diameter (12.8 inches) and the cold leg diameter (27.5 inches) to the larger break sizes. Since the larger breaks are more likely to fail, this should generally result in a higher CFP value. The second size range biases the results to a lower CFP value by assigning the intermediate break range to the smaller break sizes. The third size range uses the approximate midpoint of 20 inches to provide an unbiased allocation of the intermediate frequencies to both the smaller and larger breaks sizes. The unbiased results are most appropriate for analyzing risk associated with the DEGB
-only model.
Page 5 of 6 Table 1 - LOCA Frequency Inputs for NARWHAL CFP Calculator Break Size Mean NUREG
-1829 Frequencies (yr
-1) 0.5 1.9E-03 1.625 4.2E-04 3 1.6E-05 7 1.6E-06 14 2.0E-07 31 2.9E-08 Table 2 - PRA Category Inputs for NARWHAL CFP Calculator LOCA Category Break Size Range (in)
Small 0.5 - 2 Medium 2 - 6 Large 6 - 43.84 Table 3 - Size Range Inputs for NARWHAL CFP Calculator Size Range Sizes (in) Continuum DEGB (Bias Max) DEGB (Bias Min) DEGB (Unbiased) Small 0.5 - 2 0.5 - 2 0.5 - 2 0.5 - 2 Medium 2 - 6 2 - 6 2 - 6 2 - 6 Large(1) 6 - 15 6 - 12 6 - 12 6 - 12 Large(2) 15 - 25 12 - 13 12 - 27 12 - 20 Large(3) 25 - 43.84 13 - 43.84 27 - 43.84 20 - 43.84 Table 4 - CFP Using Log Interpolation and Mean Quantile Case PRA Category Continuum CFP DEGB (Bias Max) CFP DEGB (Bias Min) CFP DEGB (Unbiased) CFP Two ECCS/CS Trains Small 0 0 0 0 Medium 0 0 0 0 Large 0.0118 0.0780 0.0101 0.0243 Single ECCS/CS Train Small 0 0 0 0 Medium 0 0 0 0 Large 0.0353 0.0816 0.0145 0.0286 Based on NUREG
-1829, the mean exceedance frequency for 6
-inch breaks is 5.2E
-06/year. The equipment configuration probabilities for large LOCAs at Vogtle are approximately 91% for no pump failures, 7% for one or two containment spray (CS) pump failures, and 2% for 1 residual heat removal (RHR) pump or 1 train failure. Assuming the CFP values for the single train case are applicable to both the CS pump failures and the RHR pump failures, the overall CDF can be estimated as shown below
Page 6 of 6 =5.210(0.910.0118+0.090.0353)=7.210 ()=5.210(0.910.0243+0.090.0286)=1.310 In this example, the DEGB
-only model results in a slightly higher CDF value. However, this could be different depending on plant
-specific conditions and assumptions.
- 4. Conclusions The continuum break model is bounding compared to the DEGB
-only model for licensees implementing the threshold break approach, and therefore the DEGB
-only model does not need to be explicitly evaluated for those plants.
Licensees implementing the CFP approach must evaluate both the continuum break model and the DEGB-only model to determine the risk sensitivity. Based on preliminary results for Vogtle, the difference in risk calculated from the two break models is relatively small.
It is important to note that the DEGB
-only results can be significantly biased depending on how the intermediate frequencies between DEGB sizes are allocated. A reasonable approach to get an unbiased value is to simply pick the midpoint between DEGB sizes.