ML060620513

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Cycle 15 End of Life Moderator Temperature Coefficient Limit Report
ML060620513
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 02/20/2006
From: Jensen J
Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP:NRC:6132
Download: ML060620513 (18)
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{{#Wiki_filter:INDIANA MICHIGAN PaWER' A unit of American Electric Power Indiana Michigan Power Cook Nuclear Plant One Cook Place Bridgman, MI 49106 AERcom February 20, 2006 AEP:NRC:6132 Docket No.: 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, D. C. 20555-0001 Donald C. Cook Nuclear Plant Unit 2 Unit 2 Cycle 15 End of Life Moderator Temperature Coefficient Limit Report

Reference:

Letter from J. N. Jensen, Indiana Michigan Power Company, to U. S. Nuclear Regulatory Commission Document Control Desk, "Supplement to License Amendment Request on the Conditional Exemption from Measurement of End of Life Moderator Temperature Coefficient," AEP:NRC:5132-01, dated June 2, 2005. Indiana Michigan Power Company, the licensee for the Donald C. Cook Nuclear Plant: (CNP), made a commitment to submit the following information for the first three uses of the WCAP-13749-P-A methodology for each unit at CNP as a condition for approval of the conditional elimination of the most negative end of life moderator temperature coefficient measurement technical specification change:

1. A summary of the plant data used to confirm that the Benchmark Criteria of Table 3-2 of WCAP-13749-P-A, Safety Evaluation Supporting the Conditional Elimination of the Most Negative EOL Moderator Temperature Coefficient Measurement, have been met; and,
2. The Most Negative End Of Life Moderator Temperature Coefficient Limit Report (as found in Appendix D of WCAP-13749-P-A).

The information is attached. This transmittal is the first of the three submittals for Unit 2. There are no new commitments made in this submittal. Aoe

U. S. Nuclear Regulatory Commission AE P:NRC:6132 Page 2 Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Supervisor, at (269) 466-2649. Sincerely, 416seph N. Jensen Site Vice President KS/rdw Attachments: 1. 2. Plant Data Used to Confirm Benchmark Requirements Most Negative End of Life Moderator Temperature Coefficient Limit Report for Donald C. Cook Nuclear Plant Unit 2, Cycle 15 C: J. L. Caldwell, NRC Region III K. D. Curry, Ft. Wayne AEP, w/o attachments J. T. King, MPSC MDEQ - WHMD/RPMWS NRC Resident Inspector P. S. Tam, NRC Washington, DC

Attachment Ito AEP:NRC:6132 PLANT DATA USED TO CONFIRM BENCHMARK REQUIREMENTS to AEP:NRC:6132 Page 2 Plant Data Used to Confirm Benchmark Requirements To facilitate the review of this information, a list of acronyms used in this attachment is provided. OF Degrees Fahrenheit Percent BOL Beginning of Life CNP Donald C. Cook Nuclear Plant EOL End of Life HZP Hot Zero Power ITC Isothermal Temperature Coefficient M Measured MTC Moderator Temperature Coefficient MTU Metric Tons of Uranium MWD Megawatt-Day NRC Nuclear Regulatory Commission pcm. Percent-millirho P Predicted This attachment presents a comparison of the CNP Unit 2 Cycle 15 core characteristics with the requirements for use of the Conditional Exemption of the Most Negative EOL MTC Measurement Methodology and presents plant data that support that the Benchmark Criteria presented in WCAP-13749-P-A are met. The Conditional Exemption of the Most Negative EOL MTC measurement methodology is described in WCAP-13749-P-A. This report was approved by the NRC with two requirements:

  • only PHOENIX/ANC calculation methods are used for the individual plant analyses relevant to determinations for the EOL MTC plant methodology, and
  • the predictive correction is reexamined if changes in core fuel designs or continued MTC calculation/measurement data show significant effect on the predictive correction.

The PHOENIX/ANC calculation methods were used for the CNP Unit 2, Cycle 15, core design and relevant analyses. Also, the Unit 2, Cycle 15, core design does not represent a major change in core fuel design. Therefore, the Predictive Correction of -3 pcm/IF remains valid for this cycle. The Unit 2 Cycle 15 core meets both of the above requirements. to AEP:NRC:6132 Page 3 The following data tables are provided in support of the benchmark criteria: Table 1 - Benchmark Criteria for Application of the 300 ppm MTC Conditional Exemption Methodology (per WCAP-13749-P-A)

  • Table 2 - Flux Map Data: Assembly Powers
  • Table 3 - Flux Map Data: Core Tilt Criteria
  • Table 4 - Core Reactivity Balance Data
  • Table 5 - Low Power Physics Test Data (BOL, HZP): ITC
  • Table 6 - Low Power Physics Test Data (BOL, HZP): Individual Control Bank Worth to AEP:NRC:6132 Page 4 Table 1 Benchmark Criteria for Application of the 300 ppm MTC Conditional Exemption Methodolo2v (ler WCAP-13749-P-A)

Parameter Criteria Assembly Power (Measured Normal Reaction Rate) Measured Incore Quadrant Power Tilt (Low Power) Measured Incore Quadrant Power Tilt (Full Power) Core Reactivity Difference BOL HZP ITC Individual Control Bank Worth Total Control Bank Worth +0.1 or 10% +/-4% i2 % t 1000 pcm + 2 pcm/IF + 15 % or + 100 pcm i 10% to AEP:NRC:6132 Page 5 Table 2 Flux Map Data:Assemblv Powers Assembly Power Determination Map Date Power (Maximum Magnitude of Relative Error) (%) Measured Predicted Predicted - 10°, of Acceptable Power Power Measuredl Predi cted 215-01 11/10/2004 26.76 1.189 1.280 0.091 0.128 YES 215-02 11/11/2004 44.88 1.123 1.197 0.074 0.120 YES 215-03 11/13/2004 85.88 1.132 1.197 0.065 0.120 YES 215-04 11/16/2004 99.84 1.145 1.202 0.057 0.120 YES 215-05 Map was discarded as the repeat data for Detector A and Detector F did not satisfy the processing critera. 215-06 12/13/2004 99.95 0.477 0.455 0.022 O.C46 YES 215-07 1/3/2005 99.89 0.988 1.032 0.044 0.103 YES 215-08 1/10/2005 99.82 0.373 0.356 0.017 O.C36 YES 215-09 1/17/2005 99.72 0.336 0.322 0.014 0.032 YES 215-10 1/26/2005 99.83 0.4 72 0.448 0.024 0.045 YES 215-11 2/14/2005 99.82 0.374 0.355 0.019 0.036 YES 215-12 3/15/2005 100.04 0.372 0.354 0.018 0.035 YES 215-13 4/11/2005 99.81 0.373 0.352 0.021 0.035 YES 215-14 5/9/2005 99.88 0.995 1.039 0.044 0.104 YES 215-15 6/6/2005 99.89 1.004 1.041 0.037 0.104 YES 215-16 7/11/2005 99.89 0.390 0.372 0.018 0.037 YES 215-17 8/8/2005 99.91 0.398 0.378 0.020 0.038 YES 215-18 9/6/2005 99.80 1.108 1.052 0.056 0.105 YES 215-19 10/10/2005 99.97 1.120 1.056 0.064 0.106 YES 215-20 11/7/2005 99.93 0.395 0.370 0.025 0.037 YES 215-21 12/5/2005 99.94 0.405 0.377 0.028 0.038 YES Acceptance Criteria: +/- 0.1 or 10%. to AEP:NRC:6132 Page 6 Table 3 Flux Man Data: Core Tilt Criteria Top Half Incore Quadrant Power Tilt Map # Power (%) Maximum Tilt Minimum Tilt Acceptable 215-01 26.76 1.00347 0.99430 Yes 215-02 44.88 1.00799 0.99566 Yes 215-03 85.88 1.00714 0.99414 Yes 215-04 99.84 1.00614 0.99275 Yes 215-05 Map was discarded as the repeat data for Detector A and Detector F did not satisfy the processing criteria. 215-06 99.95 1.00590 0.99213 Yes 215-07 99.89 1.00503 0.99196 Yes 215-08 99.82 1.00632 0.99248 Yes 215-09 99.72 1.00511 0.99212 Yes 215-10 99.83 1.00581 0.99290 Yes 215-11 99.82 1.00638 0.99083 Yes 215-12 100.04 1.00923 0.98839 Yes 215-13 99.81 1.00549 0.99370 Yes 215-14 99.88 1.00595 0.99393 Yes 215-15 99.89 1.00412 0.99434 Yes 215-16 99.89 1.00245 0.99752 Yes 215-17 99.91 1.00333 0.99633 Yes 215-18 99.80 1.00172 0.99637 Yes 215-19 99.97 1.00133 0.99831 Yes 215-20 99.93 1.00287 0.99645 Yes 215-21 99.94 1.00361 0.99422 Yes Bottom Half Incore Quadrant Power Tilt Map # Power (%) Maximum Tilt Minimum Tilt Acceptable 215-01 26.76 1.00667 0.99430 Yes 215-02 44.88 1.00528 0.99331 Yes 215-03 85.88 1.00622 0.99204 Yes 215-04 99.84 1.00620 0.99146 Yes 215-05 Map was discarded as the repeat data for Detector A and Detector F did not satisfy t processing criteria. 215-06 99.95 1.00484 0.99315 Yes 215-07 99.89 1.00322 0.99657 Yes 215-08 99.82 1.00609 0.99365 Yes 215-09 99.72 1.00601 0.99329 Yes 215-10 99.83 1.00780 0.99327 Yes 215-11 99.82 1.00744 0.99549 Yes 215-12 100.04 1.00386 0.99599 Yes 215-13 99.81 1.00207 0.99677 Yes 215-14 99.88 1.00320 0.99676 Yes 215-15 99.89 1.00373 0.99675 Yes 215-16 99.89 1.00327 0.99563 Yes 215-17 99.91 1.00492 0.99746 Yes 215-18 99.80 1.00475 0.99697 Yes 215-19 99.97 1.00433 0.99520 Yes 215-20 99.93 1.00483 0.99615 Yes 215-21 99.94 1.00396 0.99578 Yes Acceptance Criteria: High power maps - maximum power tilt: 1.02; minimum power tilt: 0.98 Low power maps - maximum power tilt: 1.04; minimum power tilt: 0.96 to AEP:NRC:6132 Page 7 Table 4 Core Reactivity Balance Data Unit 2 Cycle 15 Boron Letdown Curve Date Burnup Delta Acceptable MWD/MTlJ) Reactivity (pcm) 18-Nov-04 265.6 -400.1 Yes 21-Nov-04 396.2 -318.8 Yes 5-Dec-04 698.7 -125.1 Yes 9-Dec-04 871.1 -54.1 Yes 12-Dec-04 1,000.6 -0.8 Yes 16-Dec-04 1,171.9 34.0 Yes 19-Dec-04 1,301.5 62.7 Yes 22-Dec-04 1,429.7 92.1 Yes 5-Jan-05 2,031.2 151.9 Yes 19-Jan-05 2,632.1 228.4 Yes 16-Feb-05 3,750.7 297.2 Yes 15-Mar-05 4,923.7 434.2 Yes 13-Apr-05 6,166.2 537.4 Yes 10-May-05 7,328.0 644.0 Yes 7-Jun-05 8,524.3 706.7 Yes 12-Jul-05 10,028.0 738.0 Yes 9-Aug-05 11,230.6 786.0 Yes 6-Sep-05 12,432.6 749.9 Yes 11-Oct-05 13851.6 449.6 Yes 6-Nov-05 14969.9 426.6 Yes 6-Dec-05 16092.9 173.3 Yes Acceptance Criteria: +/- 1000 pcm to AEP:NRC:6132 Page 8 Table 5 Low Power Physics Test Data (BOL. HZP): ITC Measured ITC Predicted ITC ITC Error (M-P) Acceptable (pcm/0F) (pcm/0F) (pcm/0F) -1.811 -0.174 -1.637 Y Acceptance Criteria: ITC error within +/- 2 pcm/0 F Table 6 Low Power Physics Test Data (BOL, HZP): Individual Control Bank Worth Measured Predicted Delta Worth Worth %ErroDr Worth Worth (M-P) (M-P)x1 00/° Acceptable (pcmz) (pc n) (Pcm) P Shutdown Bank A 259.3 258.4 0.9 0.3 Y Shutdown Bank B 758.6 769.3 -10.7 -1.4 Y Shutdown Bank C 408.6 408.6 0.0 0.0 Y Shutdown Bank D 417.2 410.1 7.1 1.7 Y Control Bank A 415.0 398.3 16.7 4.2 Y Control Bank B 599.0 603.1 -4.1 -0.7 Y Control Bank C 759.8 751.6 8.2 1.1 Y Control Bank D 1220.7 1182.1 38.6 3.3 Y Total Measured 4838.2 4781.5 56.7 1.2 Y W orth Acceptance Criteria: Individual bank rod worth % error within +/-15% or Delta Worth within +/-100 pcm. Total Measured Worth % error within +/-10% Acceptance Criteria: to AEP:NRC:6132 MOST NEGATIVE END OF LIFE MODERATOR TEMPERATURE COEFFICIENT LIMIT REPORT FOR DONALD C. COOK NUCLEAR PLANT UNIT 2, CYCLE 15 to AEP:NRC:6132 Page 2 Most Negative End of Life Moderator Temperature Coefficient Limit Report for Donald C. Cook Unit 2, Cycle 15 (Measured 300 ppm Bumup, as per WCAP-13749-P-A, Appendix D) To facilitate the review of this information, a. list of acronyms used in this attachment is provided. OF Degrees Fahrenheit A Delta Percent AFD Axial Flux Difference ARO All Rods Out BOL Beginning of Life CB Boron Concentration CNP Donald C. Cook Nuclear Plant COLR Core Operating Limits Report EOL End of Life HFP Hot Full Power HZP Hot Zero Power ITC Isothermal Temperature Coefficient M Measured MTC Moderator Temperature Coefficient MTU Metric Tons of Uranium MWD Megawatt-Day pcrn Percent-millirho ppm Parts Per Million P Predicted RCS Reactor Coolant System RTP Reactor Thermal Power PURPOSE: The purpose of this document is to present cycle-specific best estimate data for use in confirming the most negative end of life MTC limit in. Technical Specification 3.1.3. This document also summarizes the methodology used for determining if a HFP 300 ppm MTC measurement is required. to AEP:NRC:6132 Page 3 PRECAUTIONS AND LIMITATIONS: The EOL MTC elimination data presented in this document apply to CNP Unit 2 Cycle 15 only and may not be used for other operating cycles. The following reference is applicable to this document:

1. Fetterman, R. J., Slagle, W. H., Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement, WCAP-13749-P-A, March, 1997.

PROCEDURE: All core performance benchmark criteria listed in Table 1 must be met for the current operating cycle. These criteria are confirmed from startup physics test results and routine HFP CB and incore flux map surveillance performed during the cycle. If all core performance benchmark criteria are met, then the Revised Predicted MTC may be calculated per the algorithm given in Table 2. The required cycle specific data are provided in Table 2 and Figure 1. This methodology is also described in Reference 1 If all core performance benchmark criteria are met, and the Revised Predicted MTC is less negative than COLR Limit 2.2.2b, then a measurement is not required. to AEP:NRC:6132 Page 4 Table 1 Benchmark Criteria for Application of the 300 ppm MTC Conditional Exemption Methodology Parameter Criteria Assembly Power (Measured Normal Reaction Rate) Measured Incore Quadrant Power Tilt (Low Power) Measured Incore Quadrant Power Tilt (Full Power) Core Reactivity Difference BOL HZP ITC Individual Control Bank Worth Total Control Bank Worth +/-0.1 or 10% +/-2% +/- 1000 pcm +/- 2 pcm/0F +/- 15 % or +/- 100 pcm +/-10% to AEP:NRC:6132 Page 5 Table 2 Algorithm for Determining the Revised Predicted Near-EOL 300 ppm MTC The Revised Predicted MTC = Predicted MTC + AFD Correction - 3 pcm/0F where: Predicted MTC is calculated from Figure 1 at the burnup corresponding to the measurement of 300 ppm at RTP conditions, AFD Correction is the more negative value of: { 0 pcm/IF, ( AAFD

  • AFD Sensitivity) }

AAFD is the measured AFD minus the predicted AFD from ;M incore flux map taken at or near the burnup corresponding to 300 ppm. AFD Sensitivity = 0.05 pcm / TF / %AAFD Predictive Correction is -3 pcm/IF, as included in the equation for the Revised Predicted MTC. to AEP:NRC:6132 Table 3 Worksheet for Calculating the Revised Predicted Near-EOL 300 ppm MTC Page 6 Unit: 2, Cycle 15 Date: 01/01/2006 Time: 16:23 Reference for Cycle-Specific MTC Data: CNP, Unit 2 Cycle 15, COLR Part A. Predicted MTC A. 1 Cycle Average Burnup corresponding to the HFP ARO equilibrium xenon CB of 300 ppm. A.2 Predicted HFP ARO MTC corresponding to burnup (A.1) Part B. AFD Correction B.1 Burnup of most recent HFP, equilibrium conditions incore flux map B.2 Measured HFP AFD at burnup (B 1) Reference incore flux map: ID: 215-21 Date: 12/05/0.5 B.3 Predicted HFP AFD at burnup (B.1) B.4 MTC Sensitivity to AFD B.5 AFD Correction, more negative of { 0 pcm/IF, B.4 *(B.2 - B.3)} Part C. Revised Prediction C.1 Revised Prediction (A.2 + B.5 -3) C.2 Surveillance Limit (COLR 2.2.2b) 17217.0 MWD/IV[TU -24.09 pcm/°F 16053.4 MWD/M/[TU -2.168 % AFD -1.18 % AFD 0.05 pcm/ 0F/%AAFD -0.049 pcm/°F -27.14 pcm/°F -32.0 pcm/°F If C. 1 is less negative than C.2, then the HFP 300 ppm MTC measurement is not required per Technical Specification Surveillance Requirement 3.1.3.2. to AEP:NRC:6132 Page 7 Figure 1 Unit 2 Cycle 15 Predicted HFP ARO 300 ppm MTC Versus Burnup -2.28E-04 u -2.30E-04 H i k -2.32E-04 - -2.34E - C g -2.36E-04 0 -2.38E-04 .E -2.40E-04 0 EL -242E 04-= = = = = ^ E -2.46E _ -2.48E _ 14000 15000 16000 17000 18000 19000 Cycle Burnup (MWDIMTU) Burnup (MWDIMTU) MTC (AkIkifF) 14000 -2.2855E-4 15916 -2.3615E-4 16916 -2.3984E-4 17916 -2.4325E-4 19000 -2.4679E-4 to AEP:NRC:6132 Page 8 Table 4 Data Collection and Calculations Required to Complete the Table 3 Worksheet of the Most Negative Moderator Tem )erature Coefficient Limit Report Data at the 300 ppm Boron Point: RCS Boron at 300 ppm at 1623 on 01/01/06 Burnup at 300 ppm: 17217 MWD/MTU (A.1) Predicted MTC: -24.09 pcm/IF (A.2) Data from Last Flux Map: Flux Map Number: 215-21 (B.2) Reactor Power (RP): 99.94% RTP Bumup: 16053.4 MWD/MTU (B.1) Measured Axial Flux Difference (M}FD): -2.168% (B.2) MAFD = Measured Axial Offset

  • RiP / 100%

= -2.169%

  • 99.94% / 100%

= -2.168% Predicted Axial Flux Difference (PAFD): -1.18% (B.3) A AFD = (MAFD-PAFD) =(-2.168% + 1.18%) = -0.988% Determination of the Revised Predicted MTC AFD Sensitivity: 0.05 pcm/IF/ %AAFD AFD Correction: -0.049 pcm/IF (B.5) where: AFD Correction is the more negative of the following: 0 pcm/IF or (AAFD

  • AFD Sensitivity) 0 pcm/IF or (-0.988%
  • 0.05 pcm/0F/ %AAFD) 0 pcm/IF or -0.049 pcm/IF

-0.049 pcm/nF Revised Predicted MTC = Predicted MTC + AFD Correction - 3 pcm/IF = -24.09/0F - 0.049 1)cm/IF - 3 pcm/IF =-27.14/°F (C.1)}}

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