RS-14-238, Transmittal of Proprietary Meeting Slides

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Transmittal of Proprietary Meeting Slides
ML14237A526
Person / Time
Site: Dresden, Quad Cities  Constellation icon.png
Issue date: 08/25/2014
From: Simpson P R
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML14237A525 List:
References
RS-14-238
Download: ML14237A526 (46)
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Text

Exelon Generation

,. 4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office Attachment 1 contains proprietary information.

Withhold from public disclosure under 10 CFR 2.390. When Attachment 1 is separated, the remainder of the Attachments and this cover letter are decontrolled.

RS-14-238 August 25, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265 Transmittal of Proprietary Meeting Slides T he purpose of this letter is to transmit the proprietary slides generated by AREVA, Inc. for Dresden Nuclear Power Station (DNPS) and Quad Cities Nuclear Power Station (QCNPS) in support of the pre-submittal meeting conducted on August 19, 2014. The pre-submittal meeting was conducted to discuss the planned Exelon Generation Company, LLC (E GC) amendment request to transition to ATRIUM 10XM fuel at DNPS and QCNPS. This letter provides a copy of the August 19, 2014, presentation material, wh i ch AREVA, Inc. considers to contain proprietary information.

The proprietary information is identified by bracketed text. AREVA requests that the proprietary information in Attachment 1 to this letter be withheld from public disclosure, in accordance with the requirements of 10 CFR 2.390, "Public inspections, exemptions, requests for withholding," paragraph (a)(4). A signed affidavi t supporting this request is provided in Attachment 2 to this letter. Attachment 3 to th i s letter provides a non-proprietary version of the presentation. Attachment 1 contains proprietary information.

Withhold from public disclosure under 1 O CFR 2.390. When Attachment 1 is separated, the remainder of the Attachments and this cover letter are decontrolled.

August 25, 2014 U.S. Nuclear Regulatory Commission Page2 There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. Timothy A. Byam at (630) 657-2818.

Respectfully, Patrick R. Simpson Manager -Licensing Attachments:

1. Fuel Transition License Amendment Request Pre-Submittal Meeting Presentation (Proprietary), dated August 19, 2014 2. AREVA, Inc. Affidavit
3. Fuel Transition License Amendment Request Pre-Submittal Meeting Presentation Proprietary), dated August 19, 2014 Attachment 1 contains proprietary information.

Withhold from public disclosure under 10 CFR 2.390. When Attachment 1 is separated, the remainder of the Attachments and this cover letter are decontrolled.

Attachment 1 contains proprietary information.

Withhold from public disclosure under 10 CFR 2.390. When Attachment 1 is separated, the remainder of the Attachments and this cover letter are decontrolled.

ATTACHMENT 2 AREVA, Inc. Affidavit Attachment 1 contains proprietary information.

Withhold from public disclosure under 10 CFR 2.390. When Attachment 1 is separated, the remainder of the Attachments and this cover letter are decontrolled.

AFFIDAVIT STATE OF WASHINGTON ) ) SS. COUNTY OF BENTON ) 1. My name is Alan B. Meginnis.

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

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

I am familiar with the policies established by AREVA to ensure the proper application of these criteria.

3. I am familiar with the AREVA information contained in the Exelon Generation Company, LLC Dresden and Quad Cities Stations Presentation "Fuel Transition License Amendment Request Pre-Submittal Update Meeting," dated August 19, 2014 and referred to herein as "Document." Information contained in this Document has been classified by AREVA as proprietary in accordance with the policies established by AREVA 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 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 1 O CFR 2.390(a)(4) "Trade secrets and commercial or financial information." 6. The following criteria are customarily applied by AREVA to determine whether information should be classified as proprietary: (a) The information reveals details of AREVA'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. (d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for AREVA in product optimization or marketability. (e) The information is vital to a competitive advantage held by AREVA, would be helpful to competitors to AREVA, and would likely cause substantial harm to the competitive position of AREVA. 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'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 only as required and under suitable agreement providing for nondisclosure and limited use of the information.

8. AREVA 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. SUBSCRIBED before me this ;l. I day of 2014. Susan K. McCoy NOTARY PUBLIC, STATE OFWA HINGTON MY COMMISSION EXPIRES: 1/14/2016 Attachment 1 contains proprietary information.

Withhold from public disclosure under 10 CFR 2.390. When Attachment 1 is separated, the remainder of the Attachments and this cover letter are decontrolled.

ATIACHMENT3 Fuel Transition License Amendment Request Pre-Submittal Meeting Presentation (Non-Proprietary), dated August 19, 2014 Attachment 1 contains proprietary information.

Withhold from public disclosure under 10 CFR 2.390. When Attachment 1 is separated, the remainder of the Attachments and this cover letter are decontrolled.

Fuel Transition License Amendment Request Pre-Submittal Update Meeting Exelon Generation Company, LLC Dresden and Quad Cities Stations August 19, 2014 ,.----Exelon Generation.

Meeting Agenda

  • Background
  • Critical Power Correlation For OPTIMA2
  • Review and Status Update *Schedule
  • Questions

.,,,__ 1 Exelon Generation Background

  • Dresden Nuclear Power Station (DNPS) and Quad Cities Nuclear Power Station (QCNPS) are both Gene ral Electric BWR/3 reactors with Mark I containments
  • Current power levels -DNPS Units 2 and 3 -2957 MWt -QCNPS Units 1 and 2 -2957 MWt
  • Renewed Operating License expires -DNPS Unit 2 -12/22/2029

-DNPS Unit 3 -01/12/2031

-QCNPS Units 1 and 2 -12/14/2032

  • DNPS and QCNPS fuel transition project began in December 2012 when AREVA was awarded a contract fo r fuel beginning in 2016
  • April 2013 through present ARE VA has be en collecting and evaluating plant data needed for fuel transition
  • In June 2013 fuel transition LAR planning activities began 2 Exelon Generation Critical Power Correlation for OPTIMA2
  • Application of EMF-2245(P)(A)

-Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel

  • Method describes a process for generating additive constants for resident fuel using an NRC AREVA critical power correlation
  • Two methods described
  • Direct and Indirect method
  • Direct method is used when experimental test data is available for resident fuel
  • Indirect method is used when experimental test data is not available and involves using a calculated critical power database
  • Critical power is calculated using co-resident fuel vendor's NRC approved critical power correlation
  • Using co-variance, a combined standard deviation is calculated using both the standard deviation of the AREVA correlation applied to the database, and the standard deviation of the co-resident fuel vendor's a pp roved correlation 3 ,=:' Exelon Generation Critical Power Correlation for OPTIMA2
  • Indirect method used in the QCNPS and DNPS application
  • Calculated critical power database was constructed using the Westinghouse approved OPTIMA2 correlation . [ ]
  • The first step in the process is to select the AREVA critical power correlation to be used . [ ] -4 Exelon Generation Critical Power Correlation for OPTIMA2
  • Next step is a partition of the data . [ 5
  • Consistent with the process u sed in d eveloping additive constants for AREVA fuel, the data i s rando mly divided into two sets -The first set of defining da ta contains [ ] . [ ] -Second set contains the remain i ng [ ] -All data points are used to evaluate the mean and uncertainty of the correlation

] ,,,,_, ExelonGeneration.

Critical Power Correlation for OPTIMA2 6

  • F-effect i ve captures the local rod peaking effects an d consists of two par ts
  • FEFFO -Depends solely on the rod local peak i ng of i n t e rest, an d i t s surrounding neighbors

-Calculated using the methods described in Section 2.3 from EMF-2209PA, "SPCB Critical Power Correlation"

  • Additive constant C e) -Accounts for other local effects of spacing and geometry [ ,,,,,.,., ] Exelon Generation Critical Power Correlation for OPTIMA2 7 . [ 1 * [ ] calculations are performed using the defining and validating data set
  • ECPR is the figure of merit and is defined as the AREVA calculated critica I power divided by the data base critica I power
  • ECPR and standard deviation are calculated for each set of data, and the combined data set . [ ]
  • Combined data set ECPR and standard deviation are used to define the overall statistics of the method -Exelon Generation

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N cc :E -.... Q. 0 .. 0 -.... c 0 *-ca -Cl) .. .. 0 (.) .. Cl) 0 Q. -ca (.) *-*-.. (.) ,....., ........

  • c 0 ........ Q) c Q) (!) c: 0 -.I Q) x w , , , N ..-I N cc -Ii: 0 .. 0 .... c 0 *-..., ca -Cl) .. .. 0 (.) .. Cl) 0 a.. -ca (.) *-.., *-.. (.) ...... __.
  • c: 0 -+--' <O L.. Q) c: <lJ (.') c: .9 C1' >< w , , , M ...

N C( :E -0 .. 0 c 0 *-.. ca -CD .. .. 0 CJ .. CD 0 Q. -ca u *-.. *-.. CJ L c 0 +-' ro L.. <l> c <l> (!) c: 0 __, cu x w , , , '<1 N ct :E -Ii: 0 ... 0 'I-c 0 *-...., (1S -4> ... .. 0 CJ ... 4> 0 -ca u *-...., *-... CJ

  • c 0 +-' Q) c Q) (!) c: 0 (I) >< w , , , IO .-!

Critical Power Correlation for OPTIMA2

  • Overall additive constant uncer tainty is determined using the indirect method defined in EMF-2245P A I ,__,., J 1 6 Exelon Generation Critical Power Correlation for OPTIMA2
  • OPTIMA2 with [ ] statist i cs Parameter Value [ ] 17 .=' Exelon Generation Critical Power Correlation for OPTIMA2
  • OPTIMA2 with [ ] bounds Parameter Range Pressure (psia) [ Inlet subcoolinfl (Btu/lbm)

Inlet assembly mass flux (Mlbm/hr-ft2)

] [ r -] 18 Exelon Generation Critical Power Correlation for OPTIMA2

  • OPTIMA2 with [ ] bounds Pa r a m eter Ran g e [ ] 19 Exelon Generation Critical Power Correlation for OPTIMA2
  • Summary 20
  • Statistics show acceptable fit can b e achieved for OPTIMA2 with [ ]
  • Best-estimate additive constants ha v e b e en determined

[ ] . [ ]

  • Bounds of the [ ] co rrelation for application to OPTIMA2 conservatively set to the m ore limiting of the range of the approved [ ] correlation and the range of data in the OPTIMA2 critical power database ,,,,_, Exelon G eneration Critical Power Correlation for OPTIMA2
  • Safety Limit MCPR for QCNPS a n d D N PS using SAFLIM3D
  • ANP-10307PA, "AREVA MCP R Sa fety Limit Methodology for Boiling Water Reactors" . [ ] -21 ExelonGeneration.

Critical Power Correlation for OPTIMA2 22 Sub-assembly Outlet Tie Plate Sub-assembly Inlet Tie Plate -Exelon Generation Critical Power Correlation for OPTIMA2

  • MICROBURN-82 is used to [ ]
  • Given core overa 11 boundary conditions

[ ] . [ ] ,.._, 23 Exelon Generation.

Critical Power Correlation for OPTIMA2

  • For each Monte Carlo trial [ 82 [ ] ] perform MICROBURN-2 4
  • Perturb system and core conditions and assembly radial and axial power profiles including uncertainties from channel bow -Randomly perturbed system uncertainties that are applicable to QCNPS and DNPS
  • e.g. feedwater flow, feedwater temperature, pressure -Core uncertainties determined from uncertainty i n POWERPLEX predicted power and flows
  • e.g. radial bundle power, axial power , assembly flow . [ ] _, Exelon Generation Critical Power Correlation for OPTIMA2
  • For each Monte Carlo tria I [ 82 [ . [ ] 25 ] (continued)

] perform MICROBURN-

-Exelon Generation N c( :E -t: 0 .. 0 'Imm c 0 *-.... ca -Cl) ... ... 0 () .. Cl) 0 0.. -ca u *-.. *-... (.) .__.

  • c 0 +-' cu I.... Q) c Q) (!) c: 0 ....I Q) >< w , , , <O N N c( :E -0 .. 0 c 0 *-.. ca -Cl) .. .. 0 (.) .. Cl) 0 0.. -ca () *-.. *-.. (.) .__
  • c 0 +-' (lJ L.. (lJ c (lJ (..') c ..9 cu x w , , , .... N N cc :E -0 .. 0 'I-c 0 *-..., ca -Cl) .. .. 0 (.) .. Cl) 0 a.. -ca () *-..., *-.. (.) -* c: 0 +-' co 1...... (JJ c: Q) 0 c: 0 -Cl) >< LU l i t CX) N N cc ::e -0 .. 0 'I-c 0 *-.... ca -G) .. .. 0 (.) .. G) == 0 a.. -ca (.) *-.... *-.. (.) ....... * . c 0 "+; co L.... Q) c Q) (!) c: 0 ...... Q) >< LU , , , Ol N N c( :E -0 .. 0 'Im c 0 *-..., ca -CD .. .. 0 (.) .. Q) 0 0. -ca () *-+' *-.. (.) ........
  • c 0 +-' co L.... Q) c QJ (.!) c:: B UJ 'I t 0 C')

N cc :E -I-Q. 0 .. 0 .... c 0 *-..., ca -Q) .. .. 0 (.) .. Cl) 0 >i Q. "'"" co -E ca E (.) *-:J ..., Cf) *-.. (.) * ........

  • c 0 *.;:::; co L.... Q) c Q) (!) c: 0 w t 1 , .-t C")

May 19, 2014 Pre-Submittal Meeting Summary

  • Key Points -Exelon will utilize an established transition process followed by industry -One License Amendment Request will be submitted for both DNPS and QCNPS
  • Follow-up Issues 32 -Finalize approach on channel bow and verify it will be submitted as part of the LAR as a plant specific method
  • Channel Bow evaluation will be performed using approved methodologies
  • The approach and results of the evaluation will be discussed in the LAR for plant specific application
  • This discussion is intended to support NRC review and resolution in the subsequent safety evaluation

Exelon Generation May 19, 2014 Pre-Submittal Meeting Summary

  • F ollow-up Issues (continued) 33 -Finalize approach to completing the Spent Fuel Pool (SFP) Criticality Safety Analysis (CSA) for DNPS and QCNPS (i.e., analysis for only one station and implementation under 50.59 at the other)
  • A separate LAR will be submitted to address SFP CSA for DNPS Units 2 and 3 only (submittal scheduled for October 2014)
  • QCNPS Units 1 and 2 criticality changes will be completed under 10 CFR 50.59 using the QCNPS rack insert application currently under review as a basis
  • DNPS SFP CSA analysis will follow the same methodology used in the QCNPS rack insert application currently under review -S tatus and schedule for release of the draft and final SRP revision for reactivity insertion accidents
  • Use of 230 cal/gram as the appropriate upper limit for coolability
  • LAR approach to be used depends on schedule for issuance of the revised SRP ,,,,_, Exelon G eneration May 19, 2014 Pre-Submittal Meeting Summary
  • Follow-up Issues (continued) 34 -Address any maneuvering restr ic t ion s associated with the new fuel and how those restrictions accou nt for current Westinghouse fuel
  • Both Westinghouse fuel a nd ATRIUM 10XM fuel utilize barrier cladding
  • There will be no changes to Westinghouse maneuvering restrictions
  • Exelon intends to apply W estinghouse and AREVA specific fuel conditioning rules to West inghouse and AREVA fuel respectively

---Exelon Generation Westinghouse Non-Proprietary

-Class 3 Critical Power Correlation for OPTIMA2

  • Follow-up Issues (continued) 35 -Evaluate Westinghouse Methods for Thermal Con ductivity Degradation (TCD) Issue
  • With transit i on to AREVA fuel, Westinghouse will continue to hold LOCA analysis of record for Westinghouse fuel loaded in the core with inputs from steady-state fuel rod performance analyses.
  • Westinghouse prov i ded response to NRC reques t re gar din g e v a lu a tion of TCD using West i nghouse methods in letter LTR-N RC-12-18, dated February 17, 2012.
  • Westinghouse LOCA analyses for Dresden and Quad Cities use methods as discussed in letter LTR-NRC-12-18.

TCD is accounted for in these analyses.

..._, Exelon Generation Fuel Transition LAR Schedule

  • Fuel Transition Schedule (Consistent with 08/2 7 /13 and 05/19/14 Meetings)

-LAR Submittal:

February 2015 -Amendment Need Date: March 2016 -QCNPS Unit 2 implementation:

March 2016 -DNPS Unit 3 implementation:

November 2016 -QCNPS Unit 1 implementation:

March 2017 -DNPS Unit 2 implementation:

November 2017 -36 Exelon G eneration Fuel Transition LAR Schedule Concurrent Reviews

  • Spent Fuel Pool (SFP) Criticality Safety Analysis (CSA) LAR -SFP CSA for ATRIUM 10XM will follow the same methodology used in the QCNPS rack insert application currently under review -QCNPS SFP CSA for ATRIUM 10XM will be completed under 10 CFR 50.59 -DNPS SFP CSA for ATRIUM 10XM will be submitted as a LAR (SFP CSA LAR)
  • Submittal scheduled for October 2014 -Fuel Transition LAR does not depend on NRC approval of SFP CSA LAR -SFP CSA LAR does not depend on NRC approval of Fuel Transition LAR
  • Alternative Source Term (AST) 3 7 -If accident dose increases by more than 10% as a result of fuel transition, AST analysis will require revision and results will be included in the fuel transition LAR -Preliminary evaluation has determined there will be no impact to source term design basis -.=:' Exelon Generation Cf) z 0 -ln LJ.J => O' c: 0
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