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Category:Letter type:NOC
MONTHYEARNOC-AE-240040, Application for Order Consenting to Direct Transfer of Licenses2024-07-31031 July 2024 Application for Order Consenting to Direct Transfer of Licenses NOC-AE-240040, Operator Licensinq Examination Schedule Revision 32024-05-15015 May 2024 Operator Licensinq Examination Schedule Revision 3 NOC-AE-240040, Annual Dose Report for 20232024-04-29029 April 2024 Annual Dose Report for 2023 NOC-AE-240040, Financial Assurance for Decommissioning - 2024 Update2024-03-28028 March 2024 Financial Assurance for Decommissioning - 2024 Update NOC-AE-240040, Unit L & 2, Supplement to Modify the Implementation Date for License Amendment Request to Revise Alternate Source Term Dose Calculation2024-02-0808 February 2024 Unit L & 2, Supplement to Modify the Implementation Date for License Amendment Request to Revise Alternate Source Term Dose Calculation NOC-AE-230039, Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/20230032023-12-12012 December 2023 Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/2023003 NOC-AE-230040, Update Foreign Ownership, Control, or Influence (FOCI)2023-12-0505 December 2023 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-230039, Submittal of Update Foreign Ownership, Control or Influence (FOCI)2023-07-11011 July 2023 Submittal of Update Foreign Ownership, Control or Influence (FOCI) NOC-AE-220039, Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 252023-02-0606 February 2023 Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 25 NOC-AE-220038, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask2022-06-23023 June 2022 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask NOC-AE-210038, Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 252022-01-0404 January 2022 Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 25 NOC-AE-21003858, 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes2021-12-0606 December 2021 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes NOC-AE-21003853, Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-12-0303 December 2021 Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003848, Unit 1 Cycle 24 Core Operating Limits Report2021-11-18018 November 2021 Unit 1 Cycle 24 Core Operating Limits Report NOC-AE-21003846, Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-11-0404 November 2021 Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003842, 10 CFR 50.59 Summary Report2021-09-23023 September 2021 10 CFR 50.59 Summary Report NOC-AE-21003841, Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25)2021-09-23023 September 2021 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25) NOC-AE-21003832, Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-0909 September 2021 Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003812, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-08-10010 August 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003825, Update of Foreign Ownership, Control, or Influence Information (FOCI)2021-08-0505 August 2021 Update of Foreign Ownership, Control, or Influence Information (FOCI) NOC-AE-21003824, Update Foreign Ownership, Control, or Influence (FOCI)2021-07-29029 July 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003823, Update Foreign Ownership Control or Influence (FOCI)2021-07-28028 July 2021 Update Foreign Ownership Control or Influence (FOCI) NOC-AE-21003820, Nuclear Insurance Protection2021-07-20020 July 2021 Nuclear Insurance Protection NOC-AE-21003819, Inservice Inspection Summary Report - 2RE212021-07-15015 July 2021 Inservice Inspection Summary Report - 2RE21 NOC-AE-21003816, Commitment Change Summary Report2021-06-30030 June 2021 Commitment Change Summary Report NOC-AE-21003814, Technical Specification Bases Control Program2021-06-24024 June 2021 Technical Specification Bases Control Program NOC-AE-21003810, Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy NOC-AE-21003811, Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy NOC-AE-21003806, Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval2021-05-20020 May 2021 Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval NOC-AE-21003801, Annual Dose Report for 20202021-04-26026 April 2021 Annual Dose Report for 2020 NOC-AE-21003802, 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report2021-04-26026 April 2021 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report NOC-AE-21003804, Operator Licensing Examination Schedule2021-04-21021 April 2021 Operator Licensing Examination Schedule NOC-AE-21003800, Radioactive Effluent Release Report2021-04-19019 April 2021 Radioactive Effluent Release Report NOC-AE-21003799, Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan2021-04-15015 April 2021 Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan NOC-AE-21003795, Cycle 22 Core Operating Limits Report2021-04-15015 April 2021 Cycle 22 Core Operating Limits Report NOC-AE-21003796, Update Foreign Ownership, Control, or Influence (FOCI)2021-04-15015 April 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003790, Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter)2021-03-31031 March 2021 Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter) NOC-AE-21003791, Financial Assurance for Decommissioning - 2021 Update2021-03-31031 March 2021 Financial Assurance for Decommissioning - 2021 Update NOC-AE-210037, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-21003792, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-200037, License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications2021-03-11011 March 2021 License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications NOC-AE-21003784, Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing2021-03-0808 March 2021 Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing NOC-AE-21003786, Annual Fitness for Duty Performance Report for 20202021-03-0101 March 2021 Annual Fitness for Duty Performance Report for 2020 NOC-AE-21003785, Evidence of Financial Protection2021-02-23023 February 2021 Evidence of Financial Protection NOC-AE-21003781, Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts2021-01-27027 January 2021 Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts NOC-AE-21003780, Submittal of Update Foreign Ownership, Control, or Influence (FOCI)2021-01-0707 January 2021 Submittal of Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-20003778, Changes to South Texas Project Electric Generating Station Emergency Plan2020-12-17017 December 2020 Changes to South Texas Project Electric Generating Station Emergency Plan NOC-AE-20003777, STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency2020-12-10010 December 2020 STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency NOC-AE-20003766, Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan2020-12-0202 December 2020 Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan NOC-AE-20003767, Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-16016 November 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic 2024-07-31
[Table view] Category:Startup Test Report
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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)