BYRON 2014-0057, Startup Test Report for the Measurement Uncertainty Recapture (Mur) Power Uprate

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Startup Test Report for the Measurement Uncertainty Recapture (Mur) Power Uprate
ML14128A273
Person / Time
Site: Byron  Constellation icon.png
Issue date: 05/08/2014
From: Kearney F
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
1.10.0101, BYRON 2014-0057
Download: ML14128A273 (6)
v • d • e


Text

Byron Generating Station 4450 Nortn German Church Road Exelon Generation, May 8, 2014 LTR: BYRON 2014-0057 File: 1.10.0101 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NFP-66 NRC Docket Nos. STN 50-454 and STN 50-455

SUBJECT:

Byron Station, Units 1 and 2, Startup Test Report for the Measurement Uncertainty Recapture (MUR) Power Uprate

Reference:

Letter from Joel S. Wiebe, U.S. Nuclear Regulatory Commission, to Michael J. Pacilio, Exelon Nuclear, dated February 7, 2014, Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2 Issuance of Amendments Regarding Measurement Uncertainty Recapture Power Uprate.

On February 7, 2014, the NRC issued the referenced license amendment (Amendment 181)for Byron Station Units 1 and 2 that allowed an increase in the maximum reactor power level from 3586.6 Megawatts thermal (MWt) to 3645 MWt.

Enclosed for your information is the Byron Station, Units 1 and 2 Measurement Uncertainty Recapture (MUR) Mid Cycle Power Uprate Ascension Startup Report, which covers the power escalation testing conducted from February 7, 2014, through April 18, 2014. This report is submitted in accordance with Byron Station Technical Requirements Manual Section 5.3.a, which requires that a summary report of the plant startup and power escalation testing be submitted to the NRC for an amendment to the license involving a planned increase in power level.

If there are any questions regarding this matter, please contact Steve Gackstetter, Regulatory Assurance Manager, at (815)-406-2800.

Respectfully, Fa.earny Site Vice President Byron Nuclear Generating Station FAK/G DC/sg Enclosure cc: Regional Administrator NRC Region Ill NRC Senior Resident Inspector Byron Station

ATTACHMENT BYRON STATION, UNITS I AND 2 MID-CYCLE POWER UPRATE ASCENSION STARTUP REPORT 1 of 5

Byron Station, Units 1 and 2 Mid-Cycle Power Uprate Ascension Startup Report Executive Summary This mid-cycle Startup Summary Test Report is submitted to the NRC in accordance with the requirements of the Byron Station Technical Requirements Manual (TRM) Section 5.0, Administrative Controls, and Section 53.a, which requires the submittal of a Startup Report after an amendment to the license involving a planned increase in power level.

On February 7, 2014, the NRC issued License Amendment 181 for Byron Station, Units 1 and 2, which allowed an increase in the maximum reactor power level from 3586.6 megawatts thermal (MWt) to 3645 MWt. A mid-cycle power ascension test program was subsequently performed for both Unit 1 and Unit 2. The Byron Station mid-cycle Power Ascension Test Program was developed incorporating lessons learned from similar power uprate test programs performed at other nuclear plants.

The power ascension methodology used at Byron Station was to increase power in one phase.

Power was increased to a plateau where data was taken and system equipment performance evaluated to verify acceptable performance. Power ascension on both Byron Station units was initiated during mid-cycle operations. Plant modifications were performed in previous outages and after License Amendment approval. These actions allowed both Unit I and Unit 2 mid-cycle power ascensions activities to begin.

Byron Station Unit 1 power ascension occurred on February 12, 2014. Byron Station Unit 2 power ascension occurred on February 10, 2014.

Purpose This Power Uprate Startup Report is submitted to the NRC to satisfy the reporting requirements of the Byron Stations Technical Requirements Manual, paragraph 5.3.a, Startup Report, which requires this report to address the following items.

  • Include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.
  • Describe corrective actions required to obtain satisfactory operation.
  • Include any additional specific details required in license conditions based on other commitments.

Power Uprate Ascension Program Scope The power uprate test recommendations and acceptance criteria were based on the review of similar power uprate test programs performed at other nuclear plants, including the generic guidelines provided in Westinghouse Topical Report, WCAP-10263, A Review Plan for Uprating the License Power of a PWR Power Plant, dated January 1983. The power uprate master and supporting Design Change Packages (DCPs) for each unit specified the modification testing requirements for the plant setpoint scaling change request (SSCR) required for implementation of the power uprate program. The mid-cycle Power Uprate Ascension Test Program verified the following items:

  • Plant systems and equipment affected by power uprate are operating within design limits.
  • Nuclear fuel thermal limits are maintained within expected margins.
  • The feedwater heater drains and level control system is stable.
  • Radiation levels are acceptable and stable.

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Byron Station, Units I and 2 Mid-Cycle Power Uprate Ascension Startup Report Chemistry parameters are below the Action levels.

Prerequisites to Mid-Cycle Power Ascension Testing Prior to the commencement of the mid-cycle power ascension testing, special test procedures required the completion of numerous activities. These activities included the following items.

  • The applicable plant operating procedures, administrative procedures, surveillance test procedures, calibration procedures, chemical and radiological procedures and other similar procedures were reviewed and revised as necessary.
  • The applicable plant instrumentation setpoint changes or recalibrations were completed as determined by the power uprate master and support DCPs,
  • Plant modifications were reviewed to assure they were completed as required and had no issues which could affect the uprate test program.
  • The Out of Service Log and the Operation Configuration Change Log were reviewed to assure there were no conflicts with power uprate testing.
  • Baseline data was taken at the 3586.6 MWt power level (i.e., the pre-uprate power level).
  • A review was performed of the NRCs Safety Evaluation approving the proposed power uprate license amendment and associated Technical Specification (TS) changes.

Mid-Cycle Power Uprate Ascension Testing Mid-cycle power ascension was performed in accordance with a Byron Station Special Procedure (SPP) for each unit. Operator training and heightened level of awareness (HLA) briefings were completed prior to power ascension. Initial power ascension occurred in one power increment for both units. Following power increase, testing and equipment performance data was collected and evaluated in accordance with the established test acceptance criteria.

The following activities were performed.

  • Reactor fuel parameters were evaluated.
  • Feedwater heaters level control performance data was evaluated.
  • A selected set of equipment performance data (e.g., control room readings, local readings, and process computer information) was collected, and evaluated. Predictions made for performance at the next power level.
  • Chemistry evaluations were conducted.
  • Main generator stator internal temperature data was collected and evaluated.
  • Radiation surveys were performed and evaluated at the new power level.
  • Secondary plant and turbine/generator system performance was evaluated.
  • Automatic controls systems were evaluated.

Test Acceptance Criteria for Units I and 2 The power uprate test recommendations and acceptance criteria were based on the review of similar power uprate test programs performed at other nuclear plants and the power uprate master and support DCPs. During and after power ascension, test data was recorded, evaluated and compared to the performance acceptance criteria (i.e., design predictions or limits). If the test data satisfied the acceptance criteria, then system and component performance were determined to comply with their design requirements. Plant parameters during mid-cycle power ascension were evaluated using two levels of acceptance criteria. The 3 of 5

Byron Station, Units I and 2 Mid-Cycle Power Uprate Ascension Startup Report criteria associated with plant safety were classified as Level 1. The criteria associated with design expectations were classified as Level 2. The following paragraphs describe the actions taken if an individual criterion was not satisfied.

Level 1 Acceptance Criteria Equipment Performance.

Level 1 acceptance criteria normally relates to the values of process variables for components and systems determined during the design of the plant. If a Level 1 test criterion is not satisfied, the plant must be placed in a safe hold condition. Plant operating or test procedures or the Technical Specifications may guide the decision on the appropriate actions to be taken.

Resolution of the problem must be immediately pursued by equipment adjustments or through engineering evaluation, as appropriate. Following resolution, the applicable test steps must be repeated to verify that the Level 1 acceptance criterion is satisfied. A description of the problem must be included in the test report documenting successful completion of the test.

For the Byron Station power uprate, the following specific Level 1 acceptance criteria were established.

  • The Reactor Coolant System (RCS) average temperature is automatically maintained within +/- 1.5 °F of its reference temperature during steady state operations when the control rods are in the automatic mode of control.
  • The Turbine Driven Main Feedwater Pumps speed during steady state conditions do not exceed 5500 RPM.

All the above Level 1 criteria were met for both Units 1 and 2.

Level 2 Acceptance Criteria Equipment Performance.

If a Level 2 acceptance criteria limit is not satisfied, then startup testing may proceed after an investigation by testing, engineering, and operations personnel. The limits stated in this category are usually associated with expectations of system performance whose characteristics can be improved by equipment adjustments. For the Byron Station Power Uprate, the following specific Level 2 acceptance criteria were established. System and Equipment Level 2 acceptance limits are identified in various attachments of the appropriate SPP. Any limits that are exceeded will require a documented evaluation in the SPP Test Report. The Level 2 limits are usually associated with expectations of system performance whose characteristics can be improved by equipment adjustments.

  • Turbine Generator Temperature Monitoring System (TGTMS) Data within Acceptance Limits
  • Turbine Supervisory Vibration Data within Acceptance Limits
  • Delta Temperature power and calorimetric power are within plus or minus 2% of the plant process computer (PPC) indication.
  • Nuclear instrumentation and calorimetric power are within plus or minus 2%.
  • RCS pressure remains stable with no unexpected operation of pressurizer backup heaters during steady state power operation.

All the above Level 2 criteria were met for both Units I and 2, with the exception of two Unit 1 Power Range channels which required adjustment via a calorimetric after power ascension.

They were reading 102% and this was documented in the evaluation in the SPP Test Report.

Application of the UFSAR Initial Startup Test Program to the Byron Power Uprate Project Initial startup testing consisted of those single and multi-system tests that occurred during or after fuel loading and which demonstrated overall plant performance. This included such activities as pre-criticality tests, low-power tests (i.e including criticality tests), and power 4 of 5

Byron Station, Units 1 and 2 Mid-Cycle Power Uprate Ascension Startup Report ascension tests. This testing confirmed adequacy of the design bases and demonstrated, where possible, that the plant is capable of withstanding the design transients and postulated accidents. This category of tests was reviewed for applicability in developing the Byron Station Uprate Power Ascension Test Program to determine the initial data needed to be re-verified. It was determined that minimal data required re-verification based on the scope of the mid-cycle power ascension power uprate program. These were: Water Chemistry in accordance with Chemistry Action Levels, Radiations Surveys which were found to be acceptable after power ascension, and Power Ascension which a Special Test procedure was performed and reviewed.

Unit I and 2 Summary of Mid-Cycle Uprate Testing and Equipment Performance Results Systems most affected by increasing reactor power were monitored to assure acceptable performance and compliance with their specific Level I and 2 acceptance criteria

  • Condensate System Acceptable
  • Condenser Acceptable
  • Condensate Booster System Acceptable -
  • Heater Drain System Acceptable
  • Reactor Acceptable
  • Auxiliary Transformers Acceptable-
  • Generator Cooling System Acceptable -
  • Generator Condition Monitoring Acceptable-
  • Main Generator and Exciter Field Acceptable-
  • Isophase Bus Cooling Acceptable-
  • Reheater Systems Acceptable There were no unexpected conditions identified. The test evaluation report in the SPP describes on Unit 1 the two Power Range Channels that were required to be adjusted after Power Ascension. On both Unit I and Unit 2, TGTMS data was not available for a data point, but redundant points existed. In addition on Unit 1, the High Pressure Turbine Pressure instrument in the MCR was not working and agreed upon with the Shift Manager that redundant indication exists. Prior to the test, it was identified that a limit in the Unit 2 SPP data for Feedwater Pump Discharge Pressure had been mistakenly copied from the Unit 1 procedure, and was revised with test director and shift manager concurrence prior to test execution.

Conclusion Overall plant performance during power ascension and at the 3645 MWt power level was as expected and predicted with no significant performance concerns. Test procedures SPP-1 3-002 and SPP-1 3-003 were performed successfully.

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