ML062140122

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NF-BEX-06-167-NP, Rev, 2, Dresden Unit 3 Cycle 20 Slmcpr.
ML062140122
Person / Time
Site: Dresden Constellation icon.png
Issue date: 07/21/2006
From:
Westinghouse
To:
Office of Nuclear Reactor Regulation
References
NF-BEX-06-167-NP, Rev 2
Download: ML062140122 (35)
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Westinghouse Non-Proprietary Class 3 NF-BEX-06-167 Rev. 2 NP-Attachment Dresden Unit 3 Cycle 20 SLMCPR Westinghouse Electric Company Nuclear Fuel 4350 Northern Pike Monroeville, PA 15146

© 2006 Westinghouse Electric Company LLC, All Rights Reserved Page I of 35

Westinghouse Non-Proprietary Class 3 1.0 Introduction This document contains a description of the safety limit minimum critical power ratio (SLMCPR) evaluation for Dresden 3 (DNPS3) Cycle 20, as well as identification of the critical power ratio (CPR) correlation for Global Nuclear Fuel (GNF) GE14 fuel and the "conservative Adder" required by SER restriction 7 of Reference 3. As discussed below, dual and single recirculation loop SLMCPRs of 1.10 and 1.11, respectively, will be applied to the GE14 fuel in Dresden 3 Cycle 20. Dual and single recirculation loop SLMCPRs of 1.12 and 1.14, respectively, have been calculated for the Westinghouse SVEA-96 Optima2 assemblies in Dresden 3 Cycle 20.

The GNF NRC-approved methodology (References 1 and 2) was used previously to determine the appropriate SLMCPR values for the currently operating DNPS3 Cycle 19, which contains GNF GE14 and Framatome-ANP (FANP) ATRIUM-9B fuel assemblies. Consistent with the GNF methodology, the resulting Cycle 19 SLMCPRs apply to all fuel types in the core, such that the same SLMCPRs are applied to both the GEl4 and ATRIUM-9B fuel assemblies.

For D3 Cycle 20, Exelon Generation Company, LLC (EGC) will load Westinghouse SVEA-96 Optima2 fuel. Therefore, the Westinghouse NRC-approved methodology described in Reference 3 and further clarified in the response to request for additional information (RAI)

D13 of Reference 4, was used to determine the SLMCPRs for Cycle 20. Further clarification of the Westinghouse SLMCPR methodology was also provided to the NRC in support of the transition to SVEA-96 Optima2 fuel in the Quad Cities and Dresden Units as follows:

The response to NRC Request 19 in Reference 9 which supported the Licensing Amendment Request for transition to SVEA-96 Optima2 fuel in the Dresden and Quad Cities plants provided in Reference 8, The technical information supporting the Quad Cities 2 Technical Specification SLMCPR changes transmitted by Reference 10 as supplemented by the clarifying information in Reference 11.

The same SLMCPR methodology described in these references was followed for the DNPS3 Cycle 20 SLMCPR evaluations. Unlike the GNF methodology, [

The EGC proposed license amendment to use the Westinghouse methodology for core reload evaluations at the Dresden and Quad Cities units was submitted to the NRC in Reference 8.

This submittal was approved by the NRC and supported the QC2 startup with a reload core containing SVEA-96 Optima2 fuel (i.e., Cycle 19). It also supports the DNPS3 Cycle 20 with a reload core containing SVEA-96 Optima2 fuel.

NF-BEX-06-167 Rev. 2 NP-Attachment Page 2 of 35

Condition 7 in the NRC safety evaluation for Reference 3 requires that a conservative factor applied to the GE14 operating limit minimum critical power ratio (OLMCPR) be identified in licensee applications. The value of this factor for DNPS3, Cycle 20, is [ ]a,c which was also used for the QC2 Cycle 19 licensing analysis.

2.0 GE14 SLMCPR for DNPS3 Cycle 20 Consistent with the Westinghouse methodology described in Reference 3, the treatment of the SLMCPR in mixed cores containing non-Westinghouse fuel I Ia,c DNPS3 Cycle 19 contained 524 GEl4 fuel assembles and 200 ATRIUM-9B fuel assemblies. As shown in Figure 2, all of the ATRIUM-9B fuel assemblies were in their third cycle of operation in Cycle 19 and were loaded on or near the core periphery (within the outer four rows), while the GE14 fuel was loaded in the central part of the core. Therefore, the Atrium fuel CPRs were substantially greater than those for the GE14 fuel and the SLMCPR for Cycle 19 was established by contributions from the GEl4 fuel assemblies. I Ia,c The Cycle 19 SLMCPR was determined by GNF based on plant- and cycle-specific analyses using GNF's NRC-approved methodology and uncertainties (References 1 and 2) as supplemented with DNPS3-specific uncertainties. The GNF evaluation used the GEXL14 correlation for GE14 fuel. The GNF evaluation confirmed that the dual-loop and single-loop SLMCPRs of 1.10 and 1.11, respectively, in Reference 5 bounded the calculated Cycle 19 results and, therefore, continued to be appropriate for Cycle 19. [

]a,C A comparison between the Cycle 19 and 20 cores is shown in Table 1.

3.0 SVEA-96 Optima2 SLMCPR for Cycle 20 In establishing the SLMCPR for Westinghouse SVEA-96 Optima2 fuel assemblies, it is assumed that [

ac I a,c a Reference Core design (SVEA-96 Optima2 bundle designs, core loading pattern and state point depletion strategy) that represents realistic current plans for the Cycle 20 loading and operation. The Reference Core loading pattern for Cycle 20 is shown in Figure 1. The Reference Core design was generated via collaboration between EGC and Westinghouse based on EGC's cycle assumptions and design goals. The Reference Core was designed to meet the cycle energy requirements, to satisfy all licensing requirements, to provide adequate thermal margins and NF-BEX-06-167 Rev. 2 NP-Attachment Page 3 of 35

operational flexibility, and to meet other design and manufacturing criteria established by EGC and Westinghouse.

In general, the calculated SLMCPR is dominated by the flatness of the assembly CPR distribution across the core and the flatness of the relative pin CPR distribution based on the pin-by-pin power/R-factor distribution in each bundle. Greater flatness in either parameter yields more rods susceptible to boiling transition and thus a higher SLMCPR.

The calculation of the SLMCPR as a function of cycle exposure captures the interplay between the relative fuel assembly CPR and bundle relative pin-by-pin CPR distributions established from the power/R-factor distributions and allows a determination of the maximum (limiting)

SLMCPR for the entire cycle. This limiting SLMCPR is applied throughout the entire cycle.

The SVEA-96 Optima2 SLMCPR for DNPS3 Cycle 20 was determined as a function of cycle exposure based on radial assembly power distributions at least as flat as the cycle exposure-dependent radial power distributions from [

I a,c Accordingly, the SVEA-96 Optima2 SLMCPR for dual recirculation loop (DLO) operation was calculated at 100% power and 100% flow at 15 cycle exposures throughout the cycle to assure that the limiting SLMCPR was identified. In addition, the dual recirculation loop SLMCPRs were calculated at 100% power at the minimum allowed core flow at rated power (95.3% flow) and a maximum core flow at rated power of 108% flow at the maximum 100%

core flow SLMCPR cycle bumup point to confirm that a limiting SLMCPR had been established. Figure 3 shows a current DNPS3 power-to-flow map which is applicable to Cycle

20. While, as shown in Figure 3, DNPS3 Cycle 20 is not licensed for a maximum core flow of 108 %, a flow window 95.3% to 108 % of rated core flow was analyzed.

Single recirculation loop (SLO) SVEA-96 Optima2 SLMCPR calculations were also performed. These SLMCPR calculations were performed at I Ia,¢ The single loop calculations used the same procedure as the dual loop cases, except that the single loop cases applied a larger uncertainty for the core flow.

The SLMCPR results for Cycle 20 are plotted in Figure 4. As shown in Figure 4, the dual recirculation loop SLMCPR I NF-BEX-06-167 Rev. 2 NP-Attachment Page 4 of 35

]a,c the interplay between the assembly relative CPRs and the relative fuel rod CPRs. In general, as the fraction of assembly or fuel rod CPRs in the vicinity of the minimum assembly or fuel rod CPR increases, the number of rods with a potential for experiencing dryout increases. Therefore, a larger SLMCPR is required to assure that less than 0. 1%of the rods are in dryout.

While control rod patterns at individual state points required to maintain margins to thermal limits may perturb the trend, experience has shown that the assembly CPR distributions tend to become [

]a,c Therefore, the peak SLMCPR tends to occur when the assembly CPR and rod CPR distributions combine to place the maximum number of fuel rod CPRs close to the minimum CPR.

This behavior is shown for the DNPS3, Cycle 20 SLMCPR by the relative assembly CPR and relative fuel rod histograms shown in Figures 5 through 15 and 16 through 25, respectively. In Figures 5 through 15, assembly types RA20, RB20, and RC20 refer to the SVEA-96 Optima2 assembly types loaded in Cycle 20. Assembly type [

I a'c Inspection of the DLO histograms in Figures 5 through 15 and the relative fuel rod CPR histograms in Figures 16 through 25 leads to the following observations, which explain the SLMCPR behavior in Figure 4:

1. [

NF-BEX-06-167 Rev. 2 NP-Attachment Page 5 of 35

I a'c Therefore, the dual recirculation loop SLMCPR results at rated conditions in Figure 4 can be explained in terms of [

aIc As noted above, the continued adequacy of a dual recirculation loop SLMCPR of [

I ac The single recirculation loop (SLO) results calculated at aIc In addition to the strong dependence on assembly CPR and relative fuel rod CPR distributions, the SLMCPR is strongly dependent on the distribution of assembly and relative fuel pin CPRs about their mean values leading to an overall distribution of fuel rod CPRs relative to their NF-BEX-06-167 Rev. 2 NP-Attachment Page 6 of 35

mean values. The wider these distributions, the higher the SLMCPR must be to prevent 0.1%

of the fuel rods from experiencing boiling transition. The distributions of fuel rod CPRs relative to their mean values are determined by the uncertainties relative to the mean CPRs.

Accordingly, the uncertainties used in establishing the SVEA-96 Optima2 SLMCPR for Cycle 20 are shown in Table 2.

4.0 Westinghouse CPR Correlation for GE14 Fuel The Westinghouse CPR correlation for GE14 fuel used in the DNPS3 reload design and licensing analyses is the same as that used for QC2 Cycle 19 and described in the Response to NRC Request 8 in Reference 9. Further clarification of the correlation was provided in the response to NRC Request 2 in Reference 11 as well as in Reference 12.

a,c The determination of this value was also based on EGC's plans to continue to monitor the CPR performance of GEl4 fuel using the GNF GEXL14 correlation within the POWERPLEX-I1I online core monitoring system rather than the USAG14 correlation. This approach is consistent with Westinghouse's NRC-approved methodology per Reference 3.

5.0 References

1. Letter, Frank Akstulewicz (NRC) to Glen A. Watford (GE), "Acceptance for Referencing of Licensing Topical Reports NEDC-32601P, Methodology and Uncertainties for Safety Limit MCPR Evaluations; NEDC-32694P, Power Distribution Uncertainties for Safety Limit MCPR Evaluation; and Amendment 25 to NEDE-2401 I-P-A on Cycle Specific Safety Limit MCPR," (TAC Nos. M97490, M99069, and M97491), March 11, 1999.
2. General Electric BWR Thermal Analysis Basis (GETAB): Data, Correlation, and Design Application, NEDO- 10958-A, January 1977.
3. Licensing Topical Report, Reference Safety Report for Boiling Water Reactor Reload Fuel, CENPD-300-P-A, July 1996.
4. CENPD-389-P-A, lOxlO SVEA Fuel Critical Power Experiments and CPR Correlations: SVEA-96+,

August 1999.

5. Dresden Technical Specifications, Section 2.1.1.2
6. WCAP- 16081-P-A, IOx 10 SVEA Fuel Critical Power Experiments and CPR Correlation: SVEA-96 Optima2, March 2005.
7. Letter, Jason S. Post (GE) to NRC, Part 21 60 Day Interim Report Notification: Critical Power Determination for GEl4 and GE12 Fuel With Zircaloy Spacers, MFN 05-058 Rev 1, June 24, 2005, and GE Energy - Nuclear, 10 CFR Part 21 Communication, 60-Day Interim Report Notification and Transfer of Information, Critical Power Determination for GEN4 and GE12 Fuel With Zircaloy Spacers, SC05-04 Rev 1, June 24, 2005.
8. Letter, Patrick R. Simpson (Exelon Generation Company, LLC) to NRC, Request for License Amendment Regarding Transition to Westinghouse Fuel, dated June 15, 2005.

NF-BEX-06-167 Rev. 2 NP-Attachment Page 7 of 35

9. RS-06-009, Additional Information Supporting Request for License Amendment Regarding Transition to Westinghouse Fuel, January 26, 2006.
10. Letter from Patrick R. Simpson, Exelon Nuclear, to U.S. NRC, "Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit", QCNPS, Unit 2, Decemberl5, 2005.
11. RS-06-024, "Additional Information Supporting Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit", QCNPS, Unit 2, February 13, 2006.
12. RS-06-038, "Additional Information Supporting Request for Licensing Amendment Request Regarding Transition to Westinghouse Fuel and Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit", March 3, 2006.

NF-BEX-06-167 Rev. 2 NP-Attachment Page 8 of 35

Table I Comparison of Cycle 19 and 20 Cores Description Dresden 3 Dresden 3 Cycle 19 Cycle 20 Number of Bundles in Core 724 724 Limiting Cycle Exposure Point N/A (GNF proprietary) Near EOC Cycle Exposure at Limiting Point, EFPH N/A (GNF proprietary) 12,989 EFPH Reload Fuel Type GEl4 SVEA-96 Optima2 Reload Batch Average Weight % Enrichment 3.98 w/o 3.90 w/o Reload Batch Fraction (%) 33.1% 33.7%

Batch Fraction of SVEA-96 Optima2 Fuel 00.0% 33.7%

Batch Fraction of GNF GEl4 Fuel 72.4% 66.3%

Batch Fraction of FANP ATRIUM-9B Fuel 27.6% 00.0%

Core Average Weight % Enrichment 3.96 w/o 3.99 w/o Calculated Safety Limit MCPR (DL0) 1.10 for all fuel types Ia,c Calculated Safety Limit MCPR (SLO) 1.11 for all fuel types 1a,c NF-BEX-06-167 Rev. 2 NP-Attachment Page 9 of 35

Table 2 - Uncertainties used in Dresden 3 Cycle 20 SVEA-96 Optima2 SLMCPR Determination

- a,c NF-BEX-06-167 Rev. 2 NP-Attachment Page 10 of 35

1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 53 55 57 59 4 3 4 3 3 4 3 4 4 4 3 3 3 3 3 3 4 4 4 3 4 34 7 9 9 7 43 4 3 4 4 4 4 4 5 5 4 4 4 4 3 3 4 3 9 6 3 6 5 8 8 5 6 3 6 9 3 4 3 3 4 3 3 4 9 6 5 6 5 8 3 3 8 5 6 5 6 9 4 3 3 4 4 3 4 4 9 6 7 7 69 4 4 3 4 8 8 7 7 69 9 3 3 3 7 67 6 73 3 3 3 9 6 77 7 7 7 4 4 9 6 7 7 7 8 7 8 7 6 7 8 7 8 7 7 7 6 9 4 4 6

4 3 3 6 5 6 7 8 5 5 8 7 6 7 8 7 6 5 6 3 3 4 7 6 7 8 67 7 7 6 6 7 78 4 3 3 65 3678 8 7 7 5 6 9 7 3 4 7 7 4 3 9 7 5 8 5 6 7 8 7 7 8 7 7 8 7 7 8 7 6 5 8 5 7 9 3 4 4 3 9 5 8 3 8 7 6 5 6 7 7 7 7 7 7 6 5 6 7 8 3 8 5 9 3 4 4 3 9 5 8 3 8 7 6 5 6 7 7 7 7 7 7 6 5 6 7 8 3 8 5 9 3 4 4 3 9 7 5 8 5 6 7 8 7 7 8 7 7 8 7 7 8 7 6 5- 8 5 7 9 3 5677 4 4 3 7 ~6 5 7 78 7 7 7 7 86 4 4 3 397 36 6 6 6 7 8 7 6 3 3 4 4 3 3 6 5 6 7 8 7 87877 6 7 8 5 5 8 7 6 7 8 7 6 5 6 3 3 4 4 4 9 6 7 7 7 8 7 8 7 6 6 7 8 7 8 7 7 7 6 9 4 4 3 3 3 9 6 7 7 7 7 7 7 619 3 3 3 4 3 4 4 9 6 7 6 5 8 8 5 56 7 6 9 4 4 3 4 4 3 3 4 9 6 5 63 5 8 8 5 6 5 6 9 4 3 3 4 3 3 4 3 9 3 3 6 3 6 5 8 8 5 6 3 6 9 3 4 3 3 4 4 4 4 5 5 4 4 4 4 9 3 3 4 3 4 9 9 4 3 4 4 4 3 3 3 3 3 3 4 4 4 3 4 3 3 4 3 4 Designation Bundle Type Bundle Name # Assem ID Range Cycle First Loaded 6 Optima2 Opt2-3.90-1 0G8.00,/6.00-4GZ8.00-2G6.00 104 DSA061-DSA164 20 8 Optima2 Opt2-3.88-1 0G8.0016.00-6GZ8.00-2G6.00 80 DSA165-DSA244 20 9 Optima2 Opt2-3.93-14GZ6.00 60 OSA001-DSA060 20 3 GE14 GE14-P 10DNAB411-4G7.0/9G6.0-100T-145-T6-2553 140 JLD109-JLD256 18 4 GE14 GE14-P 10DNAB408-16GZ-100T-145-T6-2554 100 JLD257-JLD392 18 5 GE14 GE14-P1 ODNAB406-1 8GZ-100T-145-T6-2809 48 JLN649-JLN696 19 7 GEl4 GE14-P10DNAB396-18GZ-100T-145-T6-2808 192 JLN457-JLN648 19 Figure I - Dresden 3 Cycle 20 - Reference Loading Pattern NF-BEX-06-167 Rev. 2 NP-Attachment Page lII of 35

1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 53 55 57 59 60 2 19 2 1 i1i 1 2 19 2 58 19 2 3 3 2 1 1 2 3 3 2 19 19 2 19 19 2 19 2 1 4 1 52 4 1 4 1 2 4 52 2 2 2 3 4 3 3 1 3 3 33 3 3 1 3 3 4 3 2 2 2 2 2 1 3 5 5 5 4 5 5 5 5 4 5 5 5 3 1 2 2 7 4 4 7 7 7 3 3 2 1 19 19 1 2 71471 5 3 3 2 3 3 2 3 3 5 74 3 747 7 7 7 7 5 7 7 4 7 4 7 4 7 414 7 7 4 7 3 19 1 4 47 47 4 7 7 5 4 1 19 5 7 3 7 3 7 4 7 4 7 7 4 19 1 4 3 7 3 7 5 3 4 1 19 74 737 2 23T 13 5 7 7 4 4 4 7 714 3 1 3 22 19 3 1 4 73 3 74 7 F4777] 5 1 2 3 19 2 3 3 2 3 5 7 7 4 7 4 4 7 4 7 7 5 3 2 3 3 2 7 4 7 3 3 7 4 7 1 4 2 4 3 5 7 3 7 4 7 4 7 7 4 7 4 7 3 7 5 3 4 2 4 1 4 7 7 4 14 714 713 714 7 _J37 417 317 417 4_7 311 1 1 1 1 4 2 4 3 5 7 3 7 4 7 4 7 7 4 7 4 7 3 7 5 3 4 2 4 1 4 7 7 4 2 3 3 2 3 5 7 7 4 7 -4 7 3 7 4 4 7 3 7 4 7 4 7 7 5 3 2 3 3 2 19 3 12 11 1 32 3 19 5 7 4 7 4737 74 7 4 74 2 2 313 = 7 747474375 3 13 2 2 4 74 7 317 74 3 7 4 19 1 4 3 5 7 3 7 3 7 4 7 4 7 7 4 3 4 1 19 47 4 7 3 73 7 5 19 1 4 5 7 7 4 7 4 7 4 7 4 4 7 4 1 19 2 3 3 5 7 4 17 7 5 3 3 2 37 j 7 19 1 2 3 37777 7 7 2 1 19 2 2 1 3 5 5 5 4 5 5 5 7 7 5 5 313347 5 4 5 5 5 3 7322 1 2 2 2 2 3 4 3 3 1 3 3 1 3 3 4 3 2 2 2 3 3 3 3 2 1 4 1 4 113] 2 2 2 13 14 1 4 1 2 19 2 19 1I 3 21 3 2 1 1 2 6 3 2 3 1 19 2 19 4 19 2 3 3 4 1 11 4 3 3 2 19 2 19 2 I 111 1 2 2 19 2 Fuel Type Bundle Name # Assem ID Range Cycle First Loaded 19 SPC ATRIUM-9B 3.62 12Gd5.0/12Gd6.0/1OGd5.0 32 A3Y017-A3Y176 16 1 SPC ATRIUM-9B 3.78 1lGd5.0/11Gd6.0/10Gd7.0 84 A3ZOO1-A3Z112 17 2 SPCATRIUM-9B 3.78 11Gd5.01I1Gd7.0111Gd8.0/lOGd8.O 84 A3Z113-A3Z240 17 3 GE14-P10DNAB411-4G7.0/9G6.0-1 00T-145-T6-2553 148 JLD109-JLD256 18 4 GE14-P10DNAB408-16GZ-1 00T-145-T6-2554 136 JLD257-JLD392 18 5 GE14-P1 ODNAB406-1 8GZ-1 00T-145-T6-2809 48 JLN649-JLN696 19 7 GE14-P1 0DNAB396-18GZ-1 0OT-145-T6-2808 192 JLN457-JLN648 19 Figure 2 Dresden 3 Cycle 19 - Reference Loading Pattern NF-BEX-06-167 Rev. 2 NP-Attachment Page 12 of 35

0 10 2) 30 40 50 60 70 80 90 NXO 110 Con4ow( 0 /

Figure 3 - DNPS Power Flow Map (Nominal Feedwater Temperature)

NF-BEX-06-167 Rev. 2 NP-Attachment Page 13 of 35

ac Figure 4 Dresden 3 Cycle 20 SLMCPR Results for SVEA-96 Optima2 Fuel NF-BEX-06-167 Rev. 2 NP-Attachment Page 14 of 35

Figure 5 - Assembly Histograms a.c NF-BEX-06-167 Rev. 2 NP-Attachment Page 15 of 35

Figure 6 - Assembly Histograms ac NF-BEX-06-! 67 Rev. 2 NP-Attachment Page 16 of 35

Figure 7 - Assembly Histograms ac NF-BEX-06-167 Rev. 2 NP-Attachment Page 17 of 35

Figure 8 - Assembly Histograms ac NF-BEX-06-167 Rev. 2 NP-Attachment Page 18 of 35

Figure 9 - Assembly Histograms a.C NF-BEX-06-167 Rev. 2 NP-Attachment Page 19 of 35

Figure 10 -Assembly Histograms ac NF-BEX-06-167 Rev. 2 NP-Attachment Page 20 of 35

Figure 11 -Assembly Histograms a.c NF-BEX-06-167 Rev. 2 NP-Attachment Page 21 of 35

Figure 12 - Assembly Histograms axc NF-BEX-06-167 Rev. 2 NP-Attachment Page 22 of 35

Figure 13 - Assembly Histograms axc NF-BEX-06-167 Rev. 2 NP-Attachment Page 23 of 35

Figure 14 -Assembly Histograms a.C NF-BEX-06-167 Rev. 2 NP-Attachment Page 24 of 35

Figure 15 - Assembly Histograms

-- I a,c NF-BEX-06-167 Rev. 2 NP-Attachment Page 25 of 35

Figure 16- Assembly Histograms

- ac NF-BEX-06-167 Rev. 2 NP-Attachment Page 26 of 35

Figure 17- Assembly Histograms ac NF-BEX-06-167 Rev. 2 NP-Attachment Page 27 of 35

- Figure 18 - Assembly Histograms .a*C NF-BEX-06-167 Rev. 2 NP-Attachment Page 28 of 35

Figure 19- Assembly Histograms a,c NF-BEX.06-167 Rev. 2 NP-Attachment Page 29 of 35

Figure 20 - Assembly Histograms ac NF-BEX-06-167 Rev. 2 NP-Attachment Page 30 of 35

Figure 21 - Assembly Histograms ac NF-BEX-06-167 Rev. 2 NP-Attachment Page 31 of 35

Figure 22 - Assembly Histograms a,c NF-BEX-06-167 Rev. 2 NP-Attachment Page 32 of 35

Figure 23 - Assembly Histograms a,c NF-BEX-06-167 Rev. 2 NP-Attachment Page 33 of 35

Figure 24 - Assembly Histograms ac NF-BEX-06-167 Rev. 2 NP-Attachment Page 34 of 35

Figure 25 - Assembly Histograms ac NF-BEX-06-1 67 Rev. 2 NP-Attachment Page 35 of 35

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