ML032671104

Startup Report for Cycle 14 Measurement Uncertainty Recapture Power Uprate

ML032671104
Person / Time
Site:	Cook
Issue date:	09/16/2003
From:	Zwolinski J Indiana Michigan Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP:NRC:3902-02, TAC MB6751
Download: ML032671104 (8)

Text

Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 49107 1395 INDIANA MICHIGAN POWER September 16, 2003 AEP:NRC:3902-02 10 CFR 50.4 Docket No: 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P 1-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 2 STARTUP REPORT FOR CYCLE 14 MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE (TAC No. MB6751)

Reference:

Letter from J. F. Stang, NRC, to A. C. Bakken III, I&M, "Donald C. Cook Nuclear Plant, Unit 2 - Issuance of Amendment Regarding Measurement Uncertainty Recapture Power Uprate," dated May 2, 2003 Indiana Michigan Power Company, the licensee for Donald C. Cook Nuclear Plant (CNP) Unit 2, has implemented a power uprate of 1.66 percent from 3411 megawatts thermal (MWt) to 3468 MWt. This Measurement Uncertainty Recapture power uprate was implemented during the startup of Cycle 14, following the issuance of the referenced amendment, Unit 2 Operating License DPR-74 Amendment 259. This letter submits a summary report of the test results taken during the power escalation, in accordance with CNP Technical Specifications 6.9.1.1 through 6.9.1.3 This letter contains no new commitments. Should you have any questions, please contact Mr. Brian A. McIntyre, Manager of Regulatory Affairs, at (269) 697-5806.

Sincerely, John . Zwolinski Director, Design Engineering and Regulatory Affairs Attachment GJHIrdw

U. S. Nuclear Regulatory Commission AEP:NRC:3902-02 Page 2 c: K D. Curry, Ft. Wayne AEP, w/o attachment J. E. Dyer, NRC Region III J. T. King, MOSC, w/o attachment MDEQ - WHMDIHWRPS, w/o attachment NRC Resident Inspector M. A. Shuaibi, NRC Washington, DC

U. S. Nuclear Regulatory Commission AEP:NRC:3902-02 Page 3 bc: P. B. Cowan, w/o attachment M. J. Finissi, w/o attachment J. P. Gebbie, w/o attachment D. D. Goff D. R. Hafer, w/o attachment N. Haggerty, w/o attachment R. W. Hennen G. J. Hill D. W. Jenkins, w/o attachment G. John J. A. Kobyra, w/o attachment J. G. Kovarik B. A. McIntyre, w/o attachment D. H. Malin, w/o attachment J. E. Newmiller D. J. Poupard R. P. Powers, w/o attachment M. W. Rencheck, w/o attachment K W. Riches M. K Scarpello P. G. Schoepf, w/o attachment A. Verteramo M. G. Williams T. K. Woods J. A. Zwolinski, w/o attachment

ATTACHMENT TO AEP:NRC:3902-02 Donald C. Cook Nuclear Plant Unit 2 Startup Report for Cycle 14 Measurement Uncertainty Recapture Power Uprate Introduction Indiana Michigan Power Company (I&M) implemented Amendment 259 to the Donald C. Cook Nuclear Plant (CNP) Unit 2 Operating License (Reference 1) on May 9, 2003 while in a refueling outage between fuel Cycles 13 and 14. The amendment increases the licensed reactor core power level by 1.66 percent from 3411 megawatts thermal (MWt) to 3468 MWt. Reactor power was raised above 3411 MWt on June 26, 2003 and the new power level of 3468 MWt was achieved on June 27, 2003.

A summary report of appropriate plant power escalation testing results is required to be submitted in accordance with CNP Technical Specification (TS) 6.9.1.1(2). The summary report is required following an amendment to the license involving a planned increase in power level.

Furthermore, TS 6.9.1.2 requires that the startup report address each of the tests identified in the Final Safety Analysis Report (FSAR). The tests identified in the CNP Unit 2 FSAR are those that were performed at the beginning of Cycle 1. Only certain portions of the tests identified in the FSAR are applicable to the power uprate. The applicable tests performed are as follows:

• Nuclear Instrumentation (NI) Calibration Tests

• Reactor Coolant System (RCS) Loop Delta-Temperature Calibration Tests

• Core Performance Tests These tests are discussed further below.

This startup report is being submitted, as specified in TS 6.9.1.3, within 90 days following the completion of the startup test program. This startup report is complete for the power escalation testing associated with the Unit 2 Measurement Uncertainty Recapture (MUR) power uprate; thus, no supplementary reports are necessary.

TS 6.9.1.2 also states that any additional specific details required in license conditions based on other commitments be included in the startup report. Amendment 259 to the CNP Unit 2 Operating License required three items to be complete prior to the implementation of the amendment. The three items correspond to commitments made by I&M for the CNP Unit 2 MUR power uprate (Reference 2). These items were completed prior to implementing Amendment 259 to the CNP Unit 2 Operating License. A summary of these three items is as follows:

The first item was to install a leading edge flowmeter (LEFM) CheckPlus system. The design change for the installation was to include instrumentation rescaling, Updated Final to AEP:NRC:3902-02 Page 2 Safety Analysis Report (UFSAR) revision, maintenance and operational procedure revisions, training, monitoring iso-phase bus duct temperature, and implementation of the LEFM CheckPlus system out-of-service administrative technical requirements, as described in Reference 2. The design change for the CNP Unit 2 MUR power uprate and testing sequence procedures were prepared and performed in accordance with the approved CNP engineering modification process and included the items noted above.

The second item was to complete a formal engineering/reload safety evaluation of the effects of the power uprate on the UFSAR. The evaluation shall be reflected in the next update of the UFSAR submitted to the Nuclear Regulatory Commission (NRC) pursuant to 10 CFR 50.7 1(e). The reload safety evaluation and UFSAR update were completed as part of the design change documentation for the CNP Unit 2 MUR power uprate.

The third item was to complete an analysis of the steam dump valves flow capacity at the uprated power level. An analysis demonstrated that sufficient margin to trip exists with the installed steam dump valve flow capacity, therefore, changes/adjustments were not required. An update to the UFSAR regarding the steam dump valve flow capacity was completed as part of the design change documentation for the CNP Unit 2 NMR power uprate.

NI Calibration Tests The objective of these tests is to determine the difference between operable power range NI channels and thermal power as determined using the LEFM. Prior to the startup of Cycle 14, software changes were made to the computer program that calculates reactor power. These software changes reflected the changes in the power calorimetric calculation that were necessary to implement the use of the LEFM instrumentation as an input to the calorimetric calculation.

Power range NI channels were calibrated during Cycle 14 startup to reflect actual power levels prior to raising power to 3468 MWt. This calibration was performed using the procedures that implement the TS-required quarterly and daily calibrations of the power range NI channels. The power range NI channel calibration as well as intermediate range NI output currents and setpoints, were evaluated after raising power to 3468 MWt, and no further adjustments were required to these parameters.

RCS Loon Delta-Temperature Calibration Tests The objective of these tests is to evaluate the need to recalibrate the overtemperature delta-temperature (delta-T) and overpower delta-T channels and/or the need to normalize delta-T power indication. During the Cycle 14 refueling outage, adjustments were made to the delta-T amplifier gains to reflect the change in rated thermal power. These adjustments of the delta-T amplifier gains were evaluated during the Cycle 14 power ascension and after raising power to 3468 MWt. The delta-T gain adjustments met the test acceptance criteria and no immediate adjustments were required. New delta-T scaling data was calculated for each RCS loop based to AEP:NRC:3902-02 Page 3 upon data recorded with the plant actually operating at 3468 MWt. This new scaling data is subsequently used to normalize the delta-T channels consistent with actual reactor operation at 3468 MWt.

Core Performance Tests The objective of these tests is to verify that core performance margins are within design predictions for expected normal and abnormal rod configurations. The discussion of these tests is divided into the Low Power Physics Testing section and the Power Ascension Testing sections that follow.

Low Power Physics Testing Dynamic rod worth measurements were performed on June 19, 2003. The measured rod worth values for each control and shutdown rod bank were all within the acceptance criteria. The results of the measurements and the comparison to the predicted values are presented in Table 1.

The results of the dynamic rod worth measurements were used to confirm that excess shutdown margin exists during Cycle 14. During the rod worth testing, the all rods out (ARO) boron concentration was measured and compared to the predicted value, to verify the boron endpoint.

The results are as shown in Table 2. CNP Unit 2 Cycle 14 achieved initial criticality at 1831 hours0.0212 days <br />0.509 hours <br />0.00303 weeks <br />6.966955e-4 months <br /> on June .19, 2003. The isothermal temperature coefficient (ITC) measurement was performed and used to verify that the moderator temperature coefficient (MTC) limit is met for Cycle 14. The results of the TC/MTC testing are presented in Table 3. Low power physics testing for Cycle 14 was completed at 2305 hours0.0267 days <br />0.64 hours <br />0.00381 weeks <br />8.770525e-4 months <br /> on June 19, 2003.

Power Ascension Testing CNP Unit 2 Cycle 14 power ascension testing commenced with entry into Mode 1 on June 20, 2003, and was completed on June 30, 2003. To verify acceptable differences between measured and predicted peaking factors, flux map surveillance testing was performed during the Cycle 14 startup and after raising power to 3468 MWt. Acceptable differences between measured and predicted RCS boron concentrations were verified by reactivity anomaly surveillance testing. The results of the flux maps at, and just before, core operation at 3468 MWt, are presented in Table 4. The boron concentration measurement obtained during full power operation is presented in Table 5.

References

1. Letter from J. F. Stang, NRC, to A. C. Bakken III, I&M, "Donald C. Cook Nuclear Plant, Unit 2 - Issuance of Amendment Regarding Measurement Uncertainty Recapture Power Uprate," dated May 2, 2003

2. Letter from J. E. Pollock, I&M, to NRC Document Control Desk, 'Donald C. Cook Nuclear Plant Unit 2 License Amendment Request for Appendix K Measurement Uncertainty Recapture - Power Uprate Request," AEP:NRC:2902, dated November 15, 2002

Attachment to AEP:NRC:3902-02 Page 4 Table 1 - Rod Worth Measurements Acceptance Criterion: +/- 1% Delta k/k (+/- 1000 pcm) per TS Surveillance 4.1.1.2 Measured Predicted Measured Worth and Measured Worth Bank Worth WorthPredicted Worth and Predicted Worth (pcm) (pcm) Difference Percent Difference Control Bank A 235.1 263.3 -28.2 -10.7%

Control Bank B 589.1 583.2 5.9 1.0%

Control Bank C 660.6 718.7 -58.1 -8.1%

Control Bank D 1275.7 1329.9 -54.2 -4.1%

Shutdown Bank A 281.4 256.7 24.7 9.6%

Shutdown Bank B 924.2 978 -53.8 -5.5%

Shutdown Bank C 480.0 466.1 13.9 3.0%

Shutdown Bank D 486.1 460.3 25.8 5.6%

TOTAL 4932.2 5056.2 -124.0 -2.5%

Table 2 - ARO Critical Boron Concentration Acceptance Criterion: +/- 1% Delta k/k (+/- 1000 pcm) per TS Surveillance 4.1.1.2 Predicted and Predicted Value Measured Value Measured Boron ACore Reactivity (ppm) (pM) Concentration (C)

Difference

__1243____ 1274_31___8(ppm).3____ __

1243 1274 -31 258.3 Table 3 - ITC Acceptance Criterion: MTC5 TS 3.1.1.4 Limit (TS 3.1.1.4 Limit is * +5.0 pcm/F below 70% rated thermal power)

Measured ITC Doppler Temperature BOC MTC Predicted BOC MTC (pMF) Coefficient (DTC) (ITC - DTC) (pcm'0 F)

(pcmfOF) 0 (pcm/ F)

-2.97 -1.62 -1.35 -1.59 Most Limiting Predicted MTC Most Limiting Adjusted MTC at 5000 MWD/MTU at 5000 MWD/MTU (pcm'0 F) (PcmF)

+2.36 +2.60 to AEP:NRC:3902-02 Page 5 Table 4 - Power Distribution Measurements Review Criterion: Incore Quadrant Power Tilt S 1.02 Acceptance Criteria: Nuclear Enthalpy Rise Hot Channel Factor (FNWB) S TS 3.2.3 Limit Heat Flux Hot Channel Factor (FQ(Z)) S TS 3.2.2 Limit Incore Quadrant LMiting FAH pNA Most FQ(Z) FQ(Z)

Power Tilts FNA Limit Margin Q(Z) Limit Margin Before Core Operation at 0.99573 1.00279 3468 MWt 1.4690 1.5906 8.28% 2.0905 2.5078 19.96%

(Flux Map # 214-04 0.99702 1.00447 pcrfred 06126/03)

After Core Operation at 0.99858 1.00224 3468 MWt 1.4736 1.5799 7.21% 1.9725 2.3340 18.33%

(FuXMnp # 214-05 0.99572 1.00346 perfinmed 06/29103) _ _ _ _ _ _ _

Table 5 - Full Power Critical Boron Acceptance Criterion: +/- 1%Delta k/k (+/- 1000 pcm) per TS Surveillance 4.1.1.1.2 Predicted Boron and Burnup Predicted Boron Corrected Corrected Measured ACore Reactivity (MWD/MTU) (ppm) (ppm) Boron Difference (pcm)

(ppm) 302.4 774 788.2 -14.2 118.9 (performed 06/30103)

Legend of Terms ARO - all rods out BOC - beginning of cycle DTC - Doppler temperature coefficient ITC - isothermal temperature coefficient MTC - moderator temperature coefficient MWD/MTU - megawatt-days per metric ton of uranium ppm - parts per million pcm - percent millirho