ML062140072
| ML062140072 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/24/2006 |
| From: | Jensen J Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:6132-01 | |
| Download: ML062140072 (18) | |
Text
z INDIANA MICHIGAN POWER*A unit of American Electric Power Indiana Michigan Power Cook Nuclear Plant One Cook Place Bridgman, MI 49106 AEPcom July 24, 2006 AEP:NRC:6132-01 10 CFR 50.4 Docket No.: 50-315 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-PI-17 Washington, D. C. 20555-0001 Donald C. Cook Nuclear Plant Unit 1 Unit 1 Cycle 20 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 in the referenced letter 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 exemption 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 Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement," have been met; and, 2. The Most Negative 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 1. There are no new commitments made in this submittal.
U. S. Nuclear Regulatory Commission Page 2 AEP:NRC:6132-01 Should you have any questions, please contact Ms. Susan D. Simpson, Regulatory Affairs Manager, at (269) 466-2428.Sincerl Joseph N. Jensen Site Support Services 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 1, Cycle 20 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 1 to AEP:NRC:6132-01 PLANT DATA USED TO CONFIRM BENCHMARK REQUIREMENTS Attachment I to AEP:NRC:6132-01 Page 2 Plant Data Used to Confirm Benchmark Requirements To facilitate the review of this information, a list of abbreviations 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 1 Cycle 20 core characteristics with the requirements for use of the Conditional Exemption of the Most Negative EOL MTC Measurement methodology and presents plant data demonstrating 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 1 Cycle 20 core design and relevant analyses.
Also, the Unit 1 Cycle 20 core design does not represent a major change in core fuel design and the MTC calculation-to-measurement physics database shows no significant effect on the predictive correction.
Therefore, the predictive correction of -3 pcnm/F remains valid for this cycle. The Unit 1 Cycle 20 core meets both of the above requirements.
Attachment 1 to AEP:NRC:6132-01 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 and Total Control Bank Worths Attachment 1 to AEP:NRC:6132-01 Page4 Table 1 Benchmark Criteria for Application of the 300 ppm MTC Conditional Exemption Methodology (per 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%+/-2%+/- 1000 pcm* 2 pcm/0 F* 15 % or +/- 100 pcm+/- 10%
Attachment 1 to AEP:NRC:6132-01 Page 5 Table 2 Flux Map Data:Assembly Powers Assembly Power Determination Map Date Power (Maximum Magnitude of Relative Error)(%) Measured Predicted IPredicted
-10% of Acceptable Power Power Measuredl Predicted 120-01 4/28/2005 47.15 1.006 1.042 0.036 0.104 Yes 120-02 4/29/2005 88.26 0.427 0.410 0.017 0.041 Yes 120-03 5/1/2005 99.90 0.463 0.442 0.021 0.044 Yes 120-04 5/5/2005 99.91 0.416 0.395 0.021 0.040 Yes 120-05 5/16/2005 99.89 0.417 0.397 0.020 0.040 Yes 120-06 6/15/2005 99.91 0.409 0.393 0.016 0.039 Yes 120-07 7/18/2005 99.90 1.147 1.106 0.041 0.111 Yes 120-08 8/15/2005 99.86 1.140 1.101 0.039 0.110 Yes 120-09 9/12/2005 99.92 1.135 1.095 0.040 0.110 Yes 120-10 10/17/2005 99.85 1.128 1.090 0.038 0.109 Yes 120-11 11/14/2005 99.94 0.341 0.329 0.012 0.033 Yes 120-12 12/12/2005 99.95 0.344 0.332 0.012 0.033 Yes 120-13 1/16/2006 99.95 1.132 1.087 0.045 0.109 Yes 120-14 2/13/2006 99.85 1.138 1.090 0.048 0.109 Yes 120-15 3/13/2006 99.87 1.146 1.094 0.052 0.109 Yes 120-16 4/17/2006 99.85 1.155 1.100 0.055 0.110 Yes 120-17 5/15/2006 99.96 1.161 1.105 0.056 0.111 Yes Acceptance Criterion:
+/- 0.1 or 10%.
Attachment 1 to AEP:NRC:6132-01 Page 6 Table 3 Flux Map Data: Core Tilt Criteria Top Hlalf Incore Quadrant Power Tilt Map # Power (%) Maximum Tilt Minimum Tilt Acceptable 120-01 47.15 1.01356 0.98540 Yes 120-02 88.26 1.00960 0.98957 Yes 120-03 99.90 1.00921 0.99106 Yes 120-04 99.91 1.00878 0.99196 Yes 120-05 99.89 1.00719 0.99230 Yes 120-06 99.91 1.00600 0.99641 Yes 120-07 99.90 1.00624 0.99554 Yes 120-08 99.86 1.00373 0.99673 Yes 120-09 99.92 1.00388 0.99786 Yes 120-10 99.85 1.00070 0.99864 Yes 120-11 99.94 1.00065 0.99914 Yes 120-12 99.95 1.00139 0.99796 Yes 120-13 99.95 1.00415 0.99711 Yes 120-14 99.85 1.00482 0.99577 Yes 120-15 99.87 1.00511 0.99615 Yes 120-16 99.85 1.00623 0.99606 Yes 120-17 99.96 1.00599 0.99397 Yes Bottom Half Incore Quadrant Power Tilt Map # Power (%) Maximum Tilt Minimum Tilt Acceptable 120-01 47.15 1.00941 0.99475 Yes 120-02 88.26 1.01173 0.99388 Yes 120-03 99.90 1.01095 0.99394 Yes 120-04 99.91 1.00930 0.99425 Yes 120-05 99.89 1.00913 0.99459 Yes 120-06 99.91 1.00660 0.99617 Yes 120-07 99.90 1.00307 0.99570 Yes 120-08 99.86 1.00255 0.99744 Yes 120-09 99.92 1.00385 0.99781 Yes 120-10 99.85 1.00480 0.99664 Yes 120-11 99.94 1.00386 0.99813 Yes 120-12 99.95 1.00301 0.99800 Yes 120-13 99.95 1.00708 0.99678 Yes 120-14 99.85 1.00768 0.99587 Yes 120-15 99.87 1.00803 0.99667 Yes 120-16 99.85 1.00906 0.99573 Yes 120-17 99.96 1.00825 0.99510 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 Attachment 1 to AEP:NRC:6132-01 Page 7 Table 4 Core Reactivity Balance Data Unit 1 Cycle 20 Boron Letdown Curve Date Burnup Delta Acceptable (MWD/MTU)
Reactivity (pcm)4-May-05 223.6 -297.4 Yes 17-May-05 713.3 -54.0 Yes 24-May-05 976.1 72.1 Yes 31-May-05 1242.1 116.1 Yes 6-Jun-05 1467.7 167.3 Yes 15-Jun-05 1808.4 191.1 Yes 18-Jul-05 2990.7 258.2 Yes 16-Aug-05 4079.8 394.8 Yes 13-Sep-05 5135.2 528.4 Yes 18-Oct-05 6408.6 573.1 Yes 15-Nov-05 7465.4 648.5 Yes 13-Dec-05 8519.5 682.9 Yes 17-Jan-06 9835.0 706.0 Yes 14-Feb-06 10893.6 687.2 Yes 14-Mar-06 11946.6 669.6 Yes 18-Apr-06 13269.3 580.1 Yes 16-May-06 14319.7 492.6 Yes Acceptance Criteria:
+/- 1000 pcm Attachment 1 to AEP:NRC:6132-01 Page 8 Table 5 Low Power Physics Test Data (BOL, HZP): ITC Measured ITC Predicted ITC ITC Error (M-P) Acceptable (pcn/0 F) (pcm/°F) (pcnm°F)-1.42 -0.693 -0.727 Yes Acceptance Criteria:
ITC error within +/- 2 pcm/°F Table 6 Low Power Physics Test Data (BOL. IIZP): Individual and Total Control Bank Worths Measured Predicted Delta Worth Worth %Error Worth Worth (M-P) (M-P)xl00
% Acceptable (pcm) (pem) (pcm) P Shutdown Bank A 898.2 888.0 10.2 1.1% Yes Shutdown Bank B 981.5 947.7 33.8 3.6% Yes Shutdown Bank C 341.0 316.3 24.7 7.8% Yes Shutdown Bank D 308.3 321.6 -13.3 -4.1% Yes Control Bank A 938.9 906.0 32.9 3.6% Yes Control Bank B 449.9 436.7 13.2 3.0% Yes Control Bank C 544.5 540.8 3.7 0.7% Yes Control Bank D 868.9 835.2 33.7 4.0% Yes Total Measured 5331.2 5192.3 138.9 2.7% Yes Worth _ I I 1 _ _Acceptance Criteria: Individual bank rod worth % error within +/-15%or Delta Worth within +/-100 pcm.Acceptance Criteria:
Total Measured Worth % error within +/-10%
Attachment 2 to AEP:NRC:6132-01 MOST NEGATIVE END OF LIFE MODERATOR TEMPERATURE COEFFICIENT LIMIT REPORT FOR DONALD C. COOK NUCLEAR PLANT UNIT 1, CYCLE 20 Attachment 2 to AEP:NRC:6132-01 Page 2 Most Negative End of Life Moderator Temperature Coefficient Limit Report for Donald C. Cook Unit 1, Cycle 20 To facilitate the review of this information, a list of abbreviations 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 Reactor Coolant System 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 pcm 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 EOL MTC limit in CNP Technical Specification 3.1.3. This document also summarizes the methodology used for determining if a HFP 300 ppm MTC measurement is required.PRECAUTIONS AND LIMITATIONS:
The EOL MTC exemption data presented in this document apply to CNP Unit 1 Cycle 20 only and may not be used for other operating cycles.
Attachment 2 to AEP:NRC:6132-01 Page 3 The following reference is applicable to this document: WCAP-13749-P-A, "Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement," March, 1997.PROCEDURE:
All core performance benchmark criteria listed in Table I 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 surveillances 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 Tables 3 and 4, and Figure 1. This methodology is also described in the referenced document.
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.
Attachment 2 to AEP:NRC:6132-01 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%+/-4%+/-2%.1000 pcm+/- 2 pcm/°F* 15 %or +/- 100 pcm+/- 10%
Attachment 2 to AEP:NRC:6132-01 Page 5 Table 2 Algorithm for Determining the Revised Predicted Near-EOL 300 ppm MTC The Revised Predicted MTC = Predicted MTC + AFD Correction
-3 pcmn/°F 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 the following:
0 pcm/°F or (AAFD
- AFD Sensitivity)
AAFD is the measured AFD minus the predicted AFD from an incore flux map taken at or near the burnup corresponding to 300 ppm.AFD Sensitivity
= 0.05 pcm / 'F / %AAFD Predictive Correction is -3 pcmn/F, as included in the equation for the Revised Predicted MTC.
Attachment 2 to AEP:NRC:6132-01 Table 3 Worksheet for Calculating the Revised Predicted Near-EOL 300 ppm MTC Page 6 Unit: 1, Cycle 20 Date: 6/2/2006 Time: 5:42 Reference for Cycle-Specific MTC Data: CNP, Unit 1 Cycle 20, 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 Bumup of most recent HFP, equilibrium conditions incore flux map B.2 Measured HFP AFD at burnup (B.1)Reference incore flux map: Map # 120-17 Date: 5/15/06 B.3 Predicted HFP AFD at burnup (B. 1)B.4 MTC Sensitivity to AFD B.5 AFD Correction, more negative of the following:
0 pcm/°F or [B.4 *(B.2 -B.3)]Part C. Revised Prediction C. 1 Revised Prediction (A.2 + B.5 -3 pcrn/°F)C.2 Surveillance Limit (COLR 2.2.2b)14953.4 MWD/MTU-20.958 pcm/°F 14284.0 MWD/MTU-1.811 %AFD-2.059 % AFD 0.05 pcm/F/%AAFD 0.000 pcm/°F-23.958 pcm/°F-38.4 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.
Attachment 2 to AEP:NRC:6132-01 Page 7 Table 4 Data Collection and Calculations Required to Complete the Table 3 Worksheet of the Most Negative Moderator Temperature Coefficient Limit Report Data at the 300 ppm Boron Point:* RCS Boron at 300 ppm at 5:42 on 6t2/2006* Burnup at 300 ppm: 14953.4 MWD/MTU (A.1)* Predicted MTC: -20.958 pcn/°F (A.2)Data from Last Flux Map: 0 Flux Map Number: 120-17 (B.2)* Reactor Power (RP): 99.96% RTP 0 Bumup: 14284.0 MWD/MTU (B.1)* Measured Axial Flux Difference (MAFD): -1.811% (B.2)MAFD = Measured Axial Offset
- RP / 100%= -1.812%
- 99.96% / 100%--1.811%Predicted Axial Flux Difference (PAFD): -2.059% (B.3)PAFD = Predicted Axial Offset
- RP / 100%= -2.06%
- 99.96% / 100%= -2.059%A AFD = (MAFD-PAFD)
= (-1.811% + 2.059%)= 0.248%Determination of the Revised Predicted MTC AFD Sensitivity:
0.05 pcm/°F/ %AAFD (B.4)AFD Correction:
0.000 pcm/°F (B.5)where: AFD Correction is the more negative of the following:
0 pcm/°F or (AAFD
- AFD Sensitivity) 0 pcm/°F or (0.248%
- 0.05 pcm/°F/ %AAFD)0 pcm/°F or 0.012 pcm/rF.'.0 pcn/°F Revised Predicted MTC = Predicted MTC + AFD Correction
+ Predictive Correction
= -20.958 pcm/°F + 0 pcm/nF -3 pcm/°F= -23.958 pcm/°F (C.1)
Attachment 2 to AEP:NRC:6132-01 Page 8 Figure 1 Unit 1 Cycle 20 Predicted HFP ARO 300 ppm MTC Versus Burnup-1.98E-04
[LL0 -2.OOE-04ý2" -2.02E-04 4----2.04E-04-2.06E-04 0~CD E-2.1 0E-04 0--2.12E-04-2.14E-04 r 12000 13000 14000 15000 16000 Cycle Burnup (MWD/MTU)Burnup (MWDIMTU)
MTC (Ak/k/*F)12000 -2.0020E-4 13320 -2.0458E-4 14320 -2.0770E-4 15320 -2.1064E-4 16000 -2.1256E-4