ML072410398
| ML072410398 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/20/2007 |
| From: | Peifer M Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:7132, WCAP-13749-P-A | |
| Download: ML072410398 (18) | |
Text
INDIANA MICHIGAN POWER' A unit of American Electric Power Indiana Michigan Power Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 AERcom AEP:NRC:7132 10 CFR 50.4 August 20, 2007 Docket No.:
50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-Pl-17 Washington, D. C. 20555-0001 Donald C. Cook Nuclear Plant Unit 2 Unit 2 Cycle 16 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 (ML051650282).
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 Benchunark 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 second of the three submittals for Unit 2. There are no new commitments made in this submittal.
U. S. Nuclear Regulatory Commission Page 2 AEP:NRC:7132 Should you have any questions, please contact Ms. Susan D. Simpson, Regulatory Affairs Manager, at (269) 466-2428.
Sincerely,
-Mark A. Peife" 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 2, Cycle 16 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 to AEP:NRC:7132 PLANT DATA USED TO CONFIRM BENCHMARK REQUIREMENTS
Attachment I to AEP:NRC:7132 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 beginming 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 16 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 2 Cycle 16 core design and relevant analyses. Also, the Unit 2 Cycle 16 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 pcn-/0 F remains valid for this cycle. The Unit 2 Cycle 16 core meets both of the above requirements.
Attachment I to AEP:NRC:7132 Page 3 The following reference is applicable to this attaclunent:
Letter from J. D. Peralta, NRC, to J. A. Gresham, Westinghouse Electric Company, "NRC Staff Interpretation of WCAP-16260-P-A with Respect to Two Previously Approved Topical Reports WCAP-8846-A, WCAP-13749-P-A and Their Associated Safety Evaluations,"
dated May 23, 2006 (ML061420313).
The following data tables are provided in support of the benchmark criteria:
- Table I - 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): Total Control Bank Worth
Attachment I to AEP:NRC:7 132 PPage 4 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 NA*
+10%
Not required when "The Spatially Corrected Inverse Count Rate (SCICR) Method for Subcritical Reactivity Measurement" (WCAP-1 6260-P-A) has been performed; see the referenced letter.
Attaclhmient I to AEP:NRC:7132 Page 5 Table 2 Flux Map Data:Assembly Powers Assembly Power Determination Map Date Power (Maximum Magnitude of Relative Error)
(%)
Measured Predicted
[Predicted -
10% of Acceptable Power Power Measuredl Predicted 216-01 5/7/2006 27.82 1.254 1.364 0.110 0.136 YES 216-02 5/7/2006 44.74 0.322 0.297 0.025 0.030 YES 216-03 5/9/2006 85.38 0.326 0.306 0.020 0.031 YES 216-04 5/12/2006 99.89 0.392 0.363 0.029 0.036 YES 216-05 6/5/2006 99.91 0.394 0.362 0.032 0.036 YES 216-06 7/10/2006 99.88 0.403 0.367 0.036 0.037 YES 216-07 8/7/2006 99.83 0.413 0.376 0.037 0.038 YES 216-08 8/30/2006 99.85 0.327 0.306 0.021 0.031 YES 216-09 9/18/2006 99.85 0.426 0.396 0.030 0.040 YES 216-10 10/9/2006 99.91 0.434 0.407 0.027 0.041 YES 216-11 11/6/2006 99.87 0.445 0.422 0.023 0.042 YES 216-12 12/4/2006 99.86 0.464 0.436 0.028 0.044 YES 216-13 1/8/2007 99.96 0.480 0.451 0.029 0.045 YES 216-14 2/5/2007 99.86 0.492 0.463 0.029 0.046 YES 216-15 3/5/2007 99.87 0.503 0.473 0.030 0.047' YES 216-16 4/9/2007..
99.84 0.514 0.484 0.030 0.048 YES 216-17 5/7/2007 99.88 0.525 0.493 0.032 0.049 YES 216-18 6/4/2007 99.88 0.531 0.500 0.031 0.050 YES Acceptance Criterion: +/- 0.1 or 10%.
Attachmient I to AEP:NRC:7132 Table 3 Flux Map Data: Core Tilt Criteria Page 6 Top Half Incore Quadrant Power Tilt Map #
Power (%)
Maximum Tilt Minimum Tilt Acceptable 216-01 27.82 1.01180 0.99005 Yes 216-02 44.74 1.00847 0.99439 Yes 216-03 85.38 1.01137 0.99214 Yes 216-04 99.89 1.01049 0.99265 Yes 216-05 99.91 1.01396 0.99181 Yes 216-06 99.88 1.01366 0.99042 Yes 216-07 99.83 1.01210 0.99170 Yes 216-08 99.85 1.00830 0.99312 Yes 216-09 99.85 1.00533 0.99535 Yes 216-10 99.91 1.00137 0.99733 Yes 216-11 99.87 1.00436 0.99740 Yes 216-12 99.86 1.00575 0.99527 Yes 216-13 99.96 1.00778 0.99397 Yes 216-14 99.86 1.00758 0.99380 Yes 216-15 99.87 1.00663 0.99517 Yes 216-16 99.84 1.00661 0.99421 Yes 216-17 99.88 1.00455 0.99620 Yes 216-18 99.88 1.00491 0.99484 Yes Bottom Half Incore Quadrant Power Tilt Map #
Power (%)
Maximum Tilt Minimum Tilt Acceptable 216-01 27.82 1.01103 0.98717 Yes 216-02 44.74 1.00781 0.99230 Yes 216-03 85.38 1.00812 0.99230 Yes 216-04 99.89 1.00769 0.99214 Yes 216-05 99.91 1.01345 0.98857 Yes 216-06 99.88 1.01772 0.98664 Yes 216-07 99.83 1.01485 0.98788 Yes 216-08 99.85 1.00919 0.98912 Yes 216-09 99.85 1.00716 0.99166 Yes 216-10 99.91 1.00560 0.99433 Yes 216-11 99.87 1.00185 0.99799 Yes 216-12 99.86 1.00431 0.99682 Yes 216-13 99.96 1.00505 0.99402 Yes 216-14 99.86 1.00618 0.99450 Yes 216-15 99.87 1.00337 0.99703 Yes 216-16 99.84 1.00455 0.99658 Yes 216-17 99.88 1.00410 0.99754 Yes 216-18 99.88 1.00188 0.99774 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 I to AEP:NRC:7 132 Table 4 Core Reactivity Balance Data Page 7 U~nit 2 Cvcle 16 Boron Letdi~wn Curve Date Burnup Delta Acceptable (MWD/MTU)
Reactivity (pcm)
May 17, 2006 383.63
-218.0 Yes May 20, 2006 511.65
-149.0 Yes May 23, 2006 641.05
-86.3 Yes May 28, 2006 854.59
-19.0 Yes May 31, 2006 985.76 58.5 Yes June 4, 2006 1155.42 113.0 Yes June 7, 2006 1288.38 138.2 Yes June 12, 2006 1502.67 164.2 Yes July 10, 2006 2704.14 289.2 Yes August 8, 2006 3950.28 446.5 Yes August 30, 2006 4900.68 552.6 Yes September 19, 2006 5742.92 601.8 Yes October 10, 2006 6641.31 716.0 Yes November 7, 2006 7846.16 791.3 Yes December 5, 2006 9,049.26 781.4 Yes January 9, 2007 10552.30 762.5 Yes February 6, 2007 11756.10 785.4 Yes March 6, 2007 12959.50 686.1 Yes April 10, 2007 14462.90 596.4 Yes May 8, 2007 15663.90 536.3 Yes June 5, 2007 16866.30 410.5 Yes Acceptance Criterion: +/- 1000 pcm to AEP:NRC:7132 Page 8 Table 5 Low Power Physics Test Data (BOL. HZP): ITC Measured ITC Predicted ITC ITC Error (M-P)
Acceptable (pc m/0 F)
(pc mi/F)
(pc mi0 F)
-1.469
-2.151 0.682 Yes Acceptance Criterion: ITC error within +/- 2 pcmi0 F Table 6 Low Power Physics Test Data (BOL. HZP): Total Control Bank Worth Measured Predicted Delta Worth Worth %Error Worth Worth (M-P)
(M-P)xl00%
Acceptable (pcm)
(pcm)
(pcm)
P Total Measured 5630 5704
-74.5
-1.31%
Yes Worth Acceptance Criterion: Total Measured Worth % error within +/-10%
to AEP:NRC:7132 MOST NEGATIVE END OF LIFE MODERATOR TEMPERATURE COEFFICIENT LIMIT REPORT FOR DONALD C. COOK NUCLEAR PLANT UNIT 2, CYCLE 16 to AEP:NRC:7132 Page 2 Most Negative End of Life Moderator Temperature Coefficient Limit Report for Donald C. Cook Unit 2, Cycle 16 To facilitate the review of this information, a list of abbreviations used in this attachnment 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 2 Cycle 16 only and may not be used for other operating cycles.
to AEP:NRC:7132 Page 3 The following references are applicable to this attachment:
- 1. WCAP-13749-P-A, "Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement," March, 1997.
- 2. Letter from J. D. Peralta, NRC, to J. A. Gresham, Westinghouse Electric Company, "NRC Staff Interpretation of WCAP-16260-P-A with Respect to Two Previously Approved Topical Reports WCAP-8846-A, WCAP-13749-P-A and Their Associated Safety Evaluations," dated May 23. 2006 (ML061420313).
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 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:7132 PPage 4 Table I 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%
22%
+/- 1000 pcm
+/- 2 pcm/°F NA*
+/- 10%
Not required when "The Spatially Corrected Inverse Count Rate (SCICR) Method for Subcritical Reactivity Measurement" (WCAP-16260-P-A) has been performed; see Reference 2.
to AEP:NRC:7132 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/°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 pcm/°F, as included in the equation for the Revised Predicted MTC.
to AEP:NRC:7132 Table 3 Worksheet for Calculating the Revised Predicted Near-EOL 300 ppm MTC Page 6 Unit:
2, Cycle 16 Date:
6/19/2007 Time:
20:11 Reference for Cycle-Specific MTC Data:
CNP, Unit 2 Cycle 16, 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 17488.3 MWD/MTU
-24.61 pcrn/F 16826.7 MWD/MTU B.2 Measured HFP AFD at bumup (B. 1)
Reference incore flux map:
Map #
216-18 Date:
6/04/07
-2.23
% AFD B.3 Predicted HFP AFD at bumup (B. 1)
-1.12
% AFD B.4 MTC Sensitivity to AFD 0.05 pcm/°F/%AAFD B.5 AFD Correction, more negative of the following:
0 pcm/0 F or [B.4 *(B.2 - B.3)]
-0.06 pcm/°F Part C. Revised Prediction C.1 Revised Prediction (A.2 + B.5 - 3 pcrnI/F)
-27.67 pcm/°F C.2 Surveillance Limit (COLR 2.2.2b)
-32.0 pcrn/°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:7132 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 20:11 on 6/19/2007 Bumup at 300 ppm: 17488.3 MWD/MTU (A.1)
Predicted MTC: -24.61 pcm/0 F (A.2)
Data from Last Flux Map 0
Flux Map Number: 216-18 (B.2)
Reactor Power (RP): 99.88% RTP Burnup: 16826.7 MWD/MTU (B.1) 0 Measured Axial Flux Difference (MAFD): -2.23% (B.2)
MAFD = Measured Axial Offset
- RP / 100%
= -2.232%
- 99.88% / 100%
= -2.23%
Predicted Axial Flux Difference (PAFD): -1.12% (B.3)
PAFD = Predicted Axial Offset
- RP / 100%
=-1.12%
- 99.88% / 100%
= -1.12%
A AFD= (MAFD-PAFD)
= (-2.23% - -1.12%)
= -1.11%
Determination of the Revised Predicted MTC AFD Sensitivity: 0.05 pcm/°F/ %AAFD (11.4)
AFD Correction: -0.06 pcm/°F (B.5) where: AFD Correction is the more negative of the following:
0 pcm!°F or (AAFD
- AFD Sensitivity) 0 pcm/0 F or (-1.11%
- 0.05 pcmn/°F/ %AAFD) 0 pcm/0 F or -0.06 pcm/°F
.'.-0.06 pcm/°F Revised Predicted MTC = Predicted MTC + AFD Correction -3 pcm/°F
-24.61 pcm/°F + -0.06 pcm!°F -3 pcmi/F
= -27.67 pcm/°F (C.1) to AEP:NRC:7132 Page 8 Figure 1 Predicted HFP ARO 300 ppm MTC Versus Burnup Unit 2 Cycle 16
-2.40E-04
-2.42E-04
-2.44E-04
-2.46E-04.
L)
. -2.48E-04 E
-2.50E-04
-0
-2.52E-04
-2.54E-04 16000 17000 18000 19000 Cycle Burnup (MWDIMTU) 20000 Burnup (MWDIMTU)
MTC (AkIkI=F) 16000
-2.4118E-4 17000
-2.4444E-4 18000
-2.4777E-4 19000
-2.5075E-4 20000
-2.5360E-4