ML12076A063

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Areva Document No. 51-9177317-000, Brunswick Unit 1 Cycle 19 SLMCPR Analysis with SAFLIM3D Methodology, Engineering Information Record, Enclosure 8 to BSEP 12-0031
ML12076A063
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Site: Brunswick Duke Energy icon.png
Issue date: 02/17/2012
From: Carr D G
AREVA NP
To:
Office of Nuclear Reactor Regulation
References
BSEP 12-0031 51-9177317-000
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BSEP 12-0031 Enclosure 8 AREVA Document No. 51-9177317-000."Brunswick Unit I Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)"

~.*flr~edDocunme~nt A AREVA 20004-018 (10/18/2010)

AREVA NP Inc.ENGINEERING INFORMATION RECORD Document No: 51 -9177317 -000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)Page 1 of 10 C>~;ntrcHed Docunierd.

A AREVA 20004-018 (10/18/2010) 51-9177317-000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)Safety Related?MZYES nIINO Does this document contain assumptions requiring verification?

[i] YES Z NO Does this document contain Customer Required Format? L] YES Z NO Signature Block PILP, R/LR, Pages/Sections Name and AIA-CRF, Prepared/Reviewed/

TitlelDiscipline Signature AIA-CRI Date Approved or Comments D.G. Carr, Supervisor P :21t'/I- p Thermal-Hydraulics Richland D.R. Tinkler, Engineer R Thermal-Hydraulics Richland _.. 2// .//y D.W. Pruitt, Manager A/A-CRI / / ,1.//Thermal-Hydraulics Richland A.B. Meginnis, Manager A/ A /Product Licensing A X20/(2./Note: P/LP designates Preparer (P), Lead Preparer (LP)R/LR designates Reviewer (R), Lead Reviewer (LR)A/A-CRF designates Approver (A), Approver of Customer Requested Format (A-CRF)A/A-CRI designates Approver (A), Approver -Confirming Reviewer Independence (A-CRI)Record of Revision Revision PageslSectionsl Brief Description I No. Paragraphs Changed Change Authorization 000 All Initial issue of document Page 2 L 51-9177317-000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)1.0 Purpose Reference 1 presents an AREVA methodology for determining the safety limit minimum critical power ratio (SLMCPR) that was recently approved by the NRC. The methodology is an update or extension of the previously approved methodology presented in Reference

2. The SLMCPR methodology was updated to incorporate full implementation of the ACE critical power correlation (References 3 and 4), a realistic fuel channel bow model (Reference 5), and expanded coupling with the MICROBURN-B2 core simulator (Reference 6). More detailed descriptions of these improvements are discussed in Reference
1. The purpose of this report is to provide SLMCPR results for Brunswick Unit 1 Cycle 19 using the Reference 1 methodology to support a change in the list of approved methodologies in the Technical Specifications and also a change in the Technical Specification SLMCPR values for two-loop operation (TLO) and single-loop operation (SLO).2.0 Methodology The analysis presented in this document used the methodology presented in Reference
1. The SLMCPR is defined as the minimum value of the critical power ratio which ensures that at least 99.9%of the fuel rods in the core are expected to avoid boiling transition during normal operation or an anticipated operational occurrence (AOO). The SLMCPR is determined using a statistical analysis that employs a Monte Carlo process that perturbs key input parameters used in the calculation of MCPR.The set of uncertainties used in the statistical analysis include both fuel-related and plant-related uncertainties.

The SLMCPR analysis is performed with a power distribution that conservatively represents expected reactor operating states that could both exist at the operating limit MCPR (OLMCPR) and produce a MCPR equal to the SLMCPR during an AOO. [I In the AREVA methodology, the effects of channel bow on the critical power performance are accounted for in the SLMCPR analysis.

Reference 1 discusses the application of a realistic channel bow model.Page 3 Con t~roNkld Dcumn 51-9177317-000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)3.0 Analysis The core loading and cycle depletion from the Brunswick Unit 1 Cycle 19 (BRK1-19) fuel cycle design report (Reference

7) was used as the basis of the SLMCPR analysis.

Figure 1 presents the core loading, including the assembly type, the cycle the fuel was originally loaded and the number of assemblies.

The BRK1-19 core is made up of ATRIUMTM 1OXM* and ATRIUM-10 fuel. Analyses were performed

[ ] for the Brunswick power/flow map for MELLLA operation as shown in Figure 2. The BSP regions shown in the power/map are based on the methods discussed in Reference

8. The radial power distribution

[] is presented in Figure 3.The ACE/ATRIUM 1OXM critical power correlation (Reference

4) is used for the ATRIUM 1OXM fuel while the SPCB critical power correlation (Reference
9) is used for the ATRIUM-10 fuel.The fuel- and plant-related uncertainties used in the BRK1-19 SLMCPR analysis are presented in Table 1. The radial and nodal power uncertainties used in the analysis include the effects of up to 40%of the TIP channels out-of-service, up to 50% of the LPRMs out-of-service, and a 2500 effective full power hour (EFPH) LPRM calibration interval.The BRK1-19 SLMCPR analysis supports a TLO SLMCPR of 1.07 and an SLO SLMCPR of 1.09.Table 2 presents a summary of the analysis results including the SLMCPR and the percentage of rods expected to experience boiling transition.

The percentages of the total number of fuel rods predicted to experience boiling transition in the overall Monte Carlo statistical evaluation associated with each nuclear fuel type are presented in Table 3. The results are for the []4.0 Discussion of Results Results of the SLMCPR analysis using the Reference 2 methodology based on the same BRK1-19 design step-through and the same fuel- and plant-related uncertaintiest are shown in Table 4. The results show a significant decrease in both the TLO and SLO SLMCPR limits with the Reference 1 methodology.

The SLMCPR differences are primarily a result of the following differences in the methodologies:

Implementation of the realistic channel bow model Explicit use of the [ ] as a result of the expanded coupling with MICROBURN-B2 The improved SLMCPR results with the Reference 1 methodology are consistent with the results presented in Tables 4-1 and 4-3 of Reference 1.* ATRIUM is a trademark of AREVA NP.t[Page 4

,Jc., ntro~ted Docum 1 n 51-9177317-000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)5.0 References

1. ANP-1 0307PA Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP, June 2011.2. ANF-524(P)(A)

Revision 2 and Supplements 1 and 2, ANF Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.3. ANP-10249PA Revision 1, ACE/ATRIUM-IO Critical Power Correlation, AREVA NP, September 2009.4. ANP-10298PA Revision 0, ACE/ATRIUM IOXM Critical Power Correlation, AREVA NP, March 2010.5. BAW-1 0247PA Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, AREVA NP, February 2008.6. EMF-2158(P)(A)

Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors:

Evaluation and Validation of CASMO-4 / MICROBURN-B2, Siemens Power Corporation, October 1999.7. ANP-3005(P)

Revision 0, Brunswick Unit I Cycle 19 Fuel Cycle Design, AREVA NP, June 2011.8. 0G02-0119-260, Backup Stability Protection (BSP) for Inoperable Option Ill Solution, GE Nuclear Energy, July 17, 2002.9. EMF-2209(P)(A)

Revision 3, SPCB Critical Power Correlation, AREVA NP, September 2009.10. EMF-2493(P), MICROBURN-B2 Based Impact of Failed/Bypassed LPRMs and TIPs, Extended LPRM Calibration Interval, and Single Loop Operation on Measured Radial Bundle Power Uncertainty, AREVA NP, December 2000.11. NEDO-20340, Process Computer Performance Evaluation Accuracy, General Electric, June 1974.12. NEDO-1 0958-A, General Electric BWR Thermal Analysis Basis (GETAB): Data, Correlation and Design Application, General Electric, January 1977.13. NEDO-24344, Brunswick Steam Electric Plant Units I and 2 Single-Loop Operation, General Electric, September 1981.14. Letter, H.D. Curet (AREVA) to H.J. Richings (NRC), "POWERPLEX Core Monitoring:

Failed or Bypassed Instrumentation and Extended Calibration," HDC:96:012, May 6, 1996 (38-9043714-000).

15. 0B21-1305 Revision 1, "Core Monitoring LPRM Uncertainty and Sensitivity Decay," Progress Energy, March 2009 (NRC Accession Number ML092370285).

Page 5

  • .ofl trolle'-d Doc.,:'-,--erJ 51-9177317-000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)Table 1 Fuel- and Plant-Related Uncertainties for BRKI-19 SLMCPR Analyses Parameter Uncertainty Reference Fuel-Related Uncertainties Plant-Related Uncertainties Feedwater flow rate 1.8%* 12 Feedwater temperature 0.8%* 12 Core pressure 0.8%*- § 11 Total core flow rate TLO 2.5% 12 SLO 6.0% 13.[I t Values from Reference 10 are a result of the application of the methodology discussed in Reference 14 to the base uncertainties presented in Reference
6. The.uncertainties presented support operation with up to 50% of the LPRMs out-of-service, up to 40% of the TIP channels out-of-service, and a 2500 EFPH LPRM calibration interval.

The bases of these values include a core monitoring LPRM detector uncertainty of 4.3% from Reference 15.Referenced plant uncertainties were rounded up to the nearest 0.1% before use.§ The core pressure uncertainty is taken in Reference 11 to be a more conservative value than accepted in Reference 12; therefore, the more conservative value is used.Page 6

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51-9177317-000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)Table 2 BRK1-19 Results Summary for SLMCPR Analysis (Reference 1 SAFLIM3D Methodology)

Percentage of Rods SLMCPR in Boiling Transition TLO -1.07 0.073 SLO -1.09 0.083 Table 3 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type Contribution of Total Rods Nuclear Predicted To Be Fuel Fuel BurnupinB(%

Type Design Status in BT TLO SLO 30 ATRIUM-10 Twice burned [31 ATRIUM-10 Twice burned 32 ATRIUM-10 Once burned 33 ATRIUM-10 Once burned 34 ATRIUM 1OXM Fresh 35 ATRIUM 1OXM Fresh ]Table 4 BRK1-19 Results Summary for SLMCPR Analysis (Reference 2 SAFLIM2 Methodology)

Percentage of Rods SLMCPR in Boiling Transition TLO -1.11 0.098 SLO -1.13 0.098 Page 7 or'..,~. tv L 51-9177317-000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)J: 1 2 3 4 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 I: 2 3 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 31 30 32 31 32 30 32 30 32 30 32 31 32 30 32 30 32 31 32 30 32 31 31 31 30 30 32 30 32 32 34 32 34 34 34 33 34 34 34 34 33 34 33 34 34 33 34 34 34 32 34 32 34 30 32 30 32 31 31 31 31 31 32 34 33 34 35 33 35 35 35 35 33 35 34 34 34 32 30 31 30 3 2 34 32 34 34 33 35 33 35 33 33 35 33 35 33 34 34 32 34 3 2 30 31 32 3 3 34 35 33 35 33 35 33 35 35 33 35 33 35 33 35 34 33 32 31 30 32 34 34 34 33 35 33 35 33 35 33 33 35 3 3 35 33 35 33 34 34 34 32 31 31 32 32 34 35 33 35 33 35 33-55 33 35 35 33 35 33 35 33 35 3 3 35 34 32 31 31 32 34 34 35 33 35 33 35 33 35 33 33 35 35 33 35 33 35 33 34 34 32 31 30 30 31 30 32 32 32 32 33 34 34 34 34 34 33 33 35 33 35 35 33 35 33 33 35 33 35 35 33 35 33 33 35 33 35 35 33 35 33 33 35 33 35 35 33 35 33 33 35 33 33 35 35 33 35 33 33 35 33 33 35 33 35 35 33 35 33 33 35 33 35 35 33 35 33 33 35 33 35 35 33 35 33 33 35 33 35 35 34 34 33 33 33 34 34 34 32 32 32 32 31 30 30 31 30 30 31 32 32 32 34 33 34 34 34 34 33 35 33 35 33 35 33 35 33 35 33 35 33 35 33 35 33 35 33 35 33 35 33 35 33 35 33 33 35 33 35 33 35 33 35 33 35 33 35 33 35 33 35 33 35 33 35 33 35 33 35 33 35 33 34 34 34 34 33 34 32 32 32 30 30 31 31 32 31 32 32 31 30 34 34 32 32 35 34 33 34 33 34 34 32 35 33 35 34 33 35 33 34 35 33 35 33 33 35 33 35 35 33 35 33 33 35 33 35 35 33 35 33 35 33 35 33 33 35 33 '5 35 33 35 33 33 35 33 35 35 33 35 33 33 35 33 34 35 33 35 34 33 34 34 32 35 34 33 34 34 34 32 32 32 32 31 30 32 31 30 31 30 31 32 30 34 32 33 32 34 34 35 34 33 34 35 34 33 34 35 33 35 33 33 34 35 34 33 34 35 34 34 34 33 32 34 32 32 30 30 31 31 31 31 31 32 34 34 34 34 34 34 34 32 32 31 30 31 31 32 30 32 31 3 30 32 31 32 30 32 30 3 31 32 30 32 31 31 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 Nuclear Fuel Cycle Number of Fuel Type Description Loaded Assemblies 30 ATRIUM-10 17 38 31 ATRIUM-10 17 46 32 ATRIUM-10 18 80 33 ATRIUM-10 18 162 34 ATRIUM 1OXM 19 96 35 ATRIUM 1OXM 19 138 Figure 1 Brunswick Unit 1 Cycle 19 Core Loading Map Page 8 51-9177317-000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)0 a-110.0 100.0 90.0 80.0 70.0 60.0 50.0 40.0 30.0 20.0 10.0 0n I v.v 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow Figure 2 Brunswick Unit I Power/Flow Map With Nominal Feedwater Temperature BSP Regions Page 9 Contro'led Doci tve nt 51-9177317-000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)J: 1 2 3 7 8 9 10 11 12 13 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 0.299 0.362 0.374 0.399 0.401 0.410 0.400 0.372 0.354 0.298 0.398 0.594 0.691 0.724 0.753 0.771 0.769 0.752 0.722 0.687 0.592 0.398 0.249 0.345 0.485 0.712 0.854 1.081 0.911 1.130 1.135 1.134 1.129 0.909 1.077 0.850 0.711 0.483 0.357 0.244 0.291 0.465 0.672 0.806 1.102 1.203 1.244 1.259 1.256 1.040 1.040 1.254 1.256 1.240 1.199 1.097 0.802 0.668 0.459 0.284 0.258 0.465 0.745 1.026 0.950 1.249 1.288 1.083 1.298 1.075 1.290 1.289 1 .073 1.294 1.079 1.282 1.243 0. 936 1.019 0.740 0.462 0.248 0.363 0.672 1 .025 1.017 1 .265 1.308 1.101 1.310 1.089 1 .301 1 .085 1 .085 1.298 1.085 1.303 1 .095 1 .301 1.258 1.014 1.018 0.668 0.357 0.492 0.807 0.940 1.265 1 .305 1 .096 1 .332 1.112 1.333 1.108 1.303 1.301 1.104 1 .326 1.097 1 .324 1.095 1.297 1.257 0.933 0.799 0.474 0.393 0.719 1.111l 1.256 1.311 1.100 1.313 1.118 1.333 1.110 1.323 1.079 1.079 1.318 1.106 1.325 1.110 1.304 1.091 1.301 1.246 1.102 0.712 0.385 0.306 0 .602 0.864 1.220 1 .301 1.101 1.319 1.100 1.316 1.087 1.310 1.082 1.294 1.292 1.076 1.302 1.085 1.307 1.093 1.308 1.087 1.291 1.211 0.857 0.597 0.301 0.361 0.702 1.105 1.271 1.093 1 .322 1.105 1.314 1.084 1.294 1 .065 1.284 1.054 1.056 1 .279 1 .065 1.287 1.074 1.302 1 .095 1.310 1.084 1.261 1 .097 0.696 0.359 0.400 0.747 0.936 1.295 1.340 1.113 1.336 1 .092 1.288 1.055 1 .260 1.038 1 .267 1.268 1.040 1.257 1.051 1.279 1.084 1.323 1.104 1.329 1.285 0.928 0.742 0.391 0.414 0.778 1.168 1.298 1 .107 1 .340 1.101 1.317 1.059 1.261 1.032 1.227 1.008 1.020 1.235 1.034 1.255 1.059 1.305 1.089 1.328 1.097 1.288 1.160 0.773 0.410 0.421 0.796 1.174 1.071 1.331 1.101 1 .322 1.076 1.284 1.047 1.243 0.997 0.987 1.210 1.003 1.241 1.042 1.276 1 .068 1.311 1.093 1.321 1.065 1.167 0.792 0.424 1 2 3 4 5 6 7 8 9 10 11 12 13 J:14 15 16 17 18 19 20 21 22 23 24 25 26 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 0.423 0.795 1.174 1 .070 1.332 1.101 1.323 1.076 1.286 1.048 1.248 1.005 1.213 0.985 0.994 1.240 1.042 1.278 1.068 1.313 1.092 1.322 1 .063 1.168 0.790 0.422 0.417 0.777 1.169 1.300 1.109 1.343 1.103 1 .321 1.063 1 .268 1.038 1.244 1.023 1.014 1.230 1.032 1.261 1.056 1.312 1.096 1 .334 1.101 1.292 1.163 0.773 0.415 0.395 0.745 0.935 1.299 1 .345 1.115 1.341 1.101 1.296 1.061 1.271 1.047 1.279 1.276 1.042 1.266 1.055 1.289 1.090 1.333 1.106 1.336 1.292 0.929 0.742 0.401 0.366 0.703 1.109 1.276 1.097 1.329 1.104 1.323 1.094 1.305 1.074 1.296 1.065 1.064 1.295 1.076 1.301 1.082 1.316 1.097 1.321 1.089 1.270 1.104 0.700 0.364 0.310 0.604 0.867 1.227 1.309 1 .107 1.329 1.109 1.328 1.091 1.323 1.091 1.311 1.311 1.091 1.323 1.095 1.324 1.103 1.323 1.101 1.304 1.222 0.864 0. 602 0.312 0.407 0.722 1.118 1 .265 1.322 1.106 1 .327 1.126 1.349 1.121 1.341 1.093 1.092 1.341 1.119 1.346 1.124 1.322 1.102 1.318 1.262 1.115 0.719 0.406 0.496 0.813 0.948 1.277 1.318 1.107 1.348 1.122 1.352 1.121 1.324 1.324 1.120 1.350 1.112 1.344 1.106 1.315 1.274 0.956 0.811 0-494 0.373 0. 678 1.034 1 .026 1.277 1.323 1.110 1.328 1.103 1.323 1.099 1.099 1.322 1.101 1.326 1.108 1.320 1.275 1.024 1 .032 0.676 0.366 0.254 0.468 0.750 1.034 0.946 1.262 1 .304 1.096 1.319 1.089 1.312 1 .312 1.089 1.317 1 .093 1.302 1.260 0.944 1.032 0.749 0.469 0.251 0.291 0.468 0.676 0.810 1.112 1.218 1.262 1.278 1.277 1.055 1 .056 1.276 1.277 1.260 1.216 1.111l 0.809 0.675 0.465 0.290 0.251 0.362 0.495 0.718 0.860 1.095 0.922 1.149 1.154 1.154 1.149 0. 921 1.094 0.860 0.716 0.489 0.364 0.252 0.401 0.598 0.694 0.735 0.765 0.782 0.783 0.765 0.736 0.694 0.598 0.399 0.304 0.360 0.386 0.420 0.414 0.415 0.419 0.385 0.359 0.302 14 15 16 17 18 19 20 21 22 23 24 25 26 Figure 3 Radial Power Distribution for Brunswick Unit 1 Cycle 19 SLMCPR[Page 10 BSEP 12-0031 Enclosure 10 AREVA Affidavit Regarding Withholding AREVA Document No. 51-9176407-000,"Brunswick Unit I Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology

-Operability Assessment (Proprietary Version)" from Public Disclosure AFFIDAVIT STATE OF WASHINGTON

)) ss.COUNTY OF BENTON 1. My name is Alan B. Meginnis.

I am Manager, Product Licensing, for AREVA NP Inc. and as such I am authorized to execute this Affidavit.

2. I am familiar with the criteria applied by AREVA NP to determine whether certain AREVA NP information is proprietary.

I am familiar with the policies established by AREVA NP to ensure the proper application of these criteria.3. I am familiar with the AREVA NP information contained in the report 51-9176407-000, "Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology

-Operability Assessment (Proprietary Version)," dated February 2012 and referred to herein as"Document." Information contained in this Document has been classified by AREVA NP as proprietary in accordance with the policies established by AREVA NP for the control and protection of proprietary and confidential information.

4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by AREVA NP and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.
5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure.

The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information." 6. The following criteria are customarily applied by AREVA NP to determine whether information should be classified as proprietary: (a) The information reveals details of AREVA NP's research and development plans and programs or their results.(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for AREVA NP.(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for AREVA NP in product optimization or marketability.(e) The information is vital to a competitive advantage held by AREVA NP, would be helpful to competitors to AREVA NP, and would likely cause substantial harm to the competitive position of AREVA NP.The information in the Document is considered proprietary for the reasons set forth in paragraphs 6(b), 6(d) and 6(e) above.7. In accordance with AREVA NP's policies governing the protection and control of information, proprietary information contained in this Document have been made available, on a limited basis, to others outside AREVA NP only as required and under suitable agreement providing for nondisclosure and limited use of the information.

8. AREVA NP policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.(j&~SUBSCRIBED before me this c>__O__I day of .,- 2012.Susan K. McCoy NOTARY PUBLIC, STATE OF WASHINGTON MY COMMISSION EXPIRES: 1/14/2016
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