NOC-AE-02001344, Cycle 11 Power Uprate Startup Testing Summary Report

Cycle 11 Power Uprate Startup Testing Summary Report

ML021910352
Person / Time
Site:	South Texas
Issue date:	07/02/2002
From:	Jordan T South Texas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NOC-AE-02001344
Download: ML021910352 (5)

Text

Nuclear Operating Company South Texas Proecd Electric Germrtin$Station P.O Box 289 Wadsworth Txas 77483 July 2, 2002 NOC-AE-02001344 File No.: G25 10CFR50.36 STI: 31457955 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 South Texas Project Unit 1 Docket No. STN 50-498 Unit 1 Cycle 11 Power Uprate Startup Testing Summary Report South Texas Project Technical Specification 6.9.1.1 requires a summary report of appropriate plant startup and power escalation testing results following an amendment to the license involving a planned increase in power level. During Cycle 11, South Texas Project Unit 1 implemented a power uprate of 1.4% from 3800 Megawatts Thermal to 3853 Megawatts Thermal following issuance of Amendment 138 to the Operating License.

The attachment to this letter is a summary report of the test results taken during the power ascension. No corrective actions were required to obtain satisfactory operation.

There are no new licensing commitments contained in this letter. If there are any questions, please contact Mr. R. L. Prater at (361) 972-8425 or me at (361) 972-7902.

T. I.J.ordan Vice President, Engineering & Technical Services kjt/

Attachment:

South Texas Project Unit 1 Cycle 11 Power Uprate Summary Testing Report j 2 0

NOC-AE-02001344 Page 2 cc:

(paper copy) (electronic copy)

Ellis W. Merschoff A. H. Gutterman, Esquire Regional Administrator, Region IV Morgan, Lewis & Bockius LLP U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 M. T. Hardt/W. C. Gunst Arlington, Texas 76011-8064 City Public Service U. S. Nuclear Regulatory Commission Mohan C. Thadani Attention: Document Control Desk U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike R. L. Balcom Rockville, MD 20852 Reliant Energy, Inc.

Richard A. Ratliff A. Ramirez Bureau of Radiation Control City of Austin Texas Department of Health 1100 West 49th Street C. A. Johnson Austin, TX 78756-3189 AEP - Central Power and Light Company Cornelius F. O'Keefe Jon C. Wood U. S. Nuclear Regulatory Commission Matthews & Branscomb P. O. Box 289, Mail Code: MN1 16 Wadsworth, TX 77483 C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704

Attachment NOC-AE-02001344 Page 1 of 3 ATTACHMENT SOUTH TEXAS PROJECT UNIT 1 CYCLE 11 POWER UPRATE

SUMMARY

TESTING REPORT

Attachment NOC-AE-02001344 Page 2 of 3 South Texas Project Unit 1 Cycle 11 Power Uprate Summary Testing Report Introduction South Texas Project implemented Amendment 138 to the Unit 1 Operating License for a mid-cycle power uprate on May 13, 2002. Reactor power was raised to the new maximum power level of 3853 megawatts thermal on May 16, 2002. A summary report of appropriate plant power escalation testing results follows.

Only certain portions of the following tests identified in Section 14.2.12.3 of the Updated Final Safety Analysis Report were applicable to the power uprate. These affected tests were:

14. Radiation Survey Test

15. Nuclear Instrumentation Calibration Test

22. Evaluations of Core Performance Test Radiation Survey Test The objective of this test was to verify shielding effectiveness by measuring neutron and gamma radiation dose levels at selected points throughout the plant. For the power uprate, neutron and gamma surveys were performed at selected locations in the Reactor Containment Building after power was raised to 3853 megawatts. The surveys indicated no change in dose rates when compared to surveys performed before the power uprate.

Nuclear Instrumentation Calibration Test The objective of this test was to calibrate the power-range channels to reflect actual power levels. Prior to raising power to 3853 megawatts, software changes were made to the computer program that was used to perform the calculation of reactor power. These software changes reflected the changes in the power calculation methodology that was used to justify the increase in licensed power level. Power-range channels were calibrated to reflect actual power levels both before and after raising power to 3853 megawatts using the procedure to daily calibrate the power range channels in accordance with Technical Specifications.

Evaluations of Core Performance Test The objective of this test was to verify that core performance margins are within design predictions for expected normal and abnormal rod configurations. Prior to raising power to 3853 megawatts, adjustments were made to delta-temperature amplifier gains to reflect the change in rated thermal power. These adjustments of the delta-temperature amplifier gains were evaluated after raising power to 3853 megawatts and no further adjustments were required. Monthly surveillances were completed the week prior to the power uprate. The flux map surveillance was used to ensure there was sufficient peaking factor margin to raise power 1.4%. Monthly surveillances were also completed the third week after power uprate. The flux map surveillance was used to ensure acceptable peaking factors and a core reactivity balance was used to verify acceptable differences between measured and predicted RCS boron concentrations. The results of these flux map surveillances are tabulated on the following page.

Attachment NOC-AE-02001344 Page 3 of 3 I. POWER DISTRIBUTION MEASUREMENTS:

Design Review Criteria Incore Quadrant Power Tilt < 1.02 (DRC): Assembly Power Error < +/-1_0% [(M-P)/P] or

< +/--0.1 (M-P), which ever is greater Acceptance Criteria FDHN < Technical Specification (TS) 3.2.3 Limit (AC): Fxy*5 TS 3.2.2 Limit Most Most Largest Incore Quadrant LimitingFDHN FDHN Limiting Fxy Fxy Assembly Power Tilts Lmtn Limit Margin Limit Margin Power FDHNY Error Before Uprate 0.99732 0.99456 10.3%

FluxMap# 111010 1.4351 1.53 6.20% 1.6198 1.7744 8.71% 0.3%

performed 518/02 1.00787 1.00025 0.049 After Uprate 0.99859 0.99744 Flux Map# 111011 performed6/3/02 1.00139 1.00258 FDHN: Nuclear Enthalpy Rise Hot Channel Factor Incore Tilt: Measured Incore Tilt in Excess of Designed Core Asymmetry II. FULL POWER CRITICAL BORON (PPM):

Design Review Criteria (DRC): +/-50 ppm Acceptance Criteria (AC): +/-1000 pcm Burnup Measured Predicted Pass/Fail Pass/Fail (EFPD) (M) (P) (M-P) DRC AC Before Uprate 13.1070 61.0 ppm F*

Burnup: 193.561 EFPD 1138.0 1077.0 408.7 pcm F*

After Uprate 1036.0 981.5 54.5 ppm F* P Burnup: 220.275 EFPD -370.6 pcm_

A Measured minus Predicted error greater than 50 ppm is expected during long runs at full power due to Boron-10 depletion. B-10 depletion occurs when a B-10 atom absorbs a neutron that results in a Li-7 atom and an alpha particle. B-10 depletion causes the B-10/B-1I ratio to decrease and results in a less negative Differential Boron Worth (DBW)