ML14127A174

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Startup Report for the Measurement Uncertainty Recapture Power Uprate
ML14127A174
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 05/07/2014
From: Kanavos M
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BW140039, TAC MF2418, TAC MF2419, TAC MF2420, TAC MF2421
Download: ML14127A174 (20)
v • d • e


Text

May 7,2014 BW140039 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457

Subject:

Braidwood Station, Units 1 and 2 Startup Report for the Measurement Uncertainty Recapture Power Uprate

Reference:

Letter from J. S. Wiebe (U. S. Nuclear Regulatory Commission) to M. J. Pacilio (Exelon Generation Company, LLC), "Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2 -Issuance of Amendments Regarding Measurement Uncertainty Recapture Power Uprate (T AC Nos. MF2418.

MF2419, MF2420, and MF2421)," dated February 7,2014 Enclosed is the Braidwood Station, Units 1 and 2 Startup Report for the Measurement Uncertainty Recapture (MUR) Power Uprate. This Report is submitted in accordance with Technical Requirements Manual, Section 5.3.a, "Startup Report."

The referenced license amendment revised the Operating License and Technical Specifications (TSs) to implement an increase of approximately 1.63 percent in rated thermal power from 3586.6 megawatts thermal (MWt) to 3645 MWt. The changes were based on increased feedwater flow measurement accuracy achieved by utilizing the Cameron International CheckPlus1M Leading Edge Flow Meter (LEFM) ultrasonic flow measurement instrumentation.

Braidwood Station, Unit 1 commenced increasing power on February 14, 2014 in accordance with Special Test Procedure SPP 13-001, "Braidwood Unit 1, MUR Power Uprate Project Power Ascension Procedure," and attained the ascension plateau on February 14, 2014. Braidwood Station, Unit 2 commenced increasing power on February 12, 2014 in accordance with Special Test Procedure SPP 13-002, "Braidwood Unit 2, MUR Power Uprate Project Power Ascension Procedure," and attained the ascension plateau on February 12, 2014. Attached is the combined Startup Report for Braidwood Station, Units 1 and 2 including a summary of testing and equipment performance results for each unit. Also attached are core parameters at the ascension plateau for each unit.

U. S. Nuclear Regulatory Commission May 7,2014 Page 2 Should you have any questions concerning this letter, please contact Mr. Philip Raush, Regulatory Assurance Manager, at (815) 417-2800.

Respectfully,

~;C..--

Mark Kanavos Site Vice President Braidwood Station Attachments: 1) Braidwood Station, Units 1 and 2, Margin Uncertainty Recapture Power Uprate, Startup Report

2) Braidwood Station, Units 1 and 2, Core Parameters at MUR Ascension Plateau cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector, Braidwood Station NRC Project Manager, NRR - Braidwood and Byron Stations Illinois Emergency Management Agency - Division of Nuclear Safety

ATTACHMENT 1 BRAIDWOOD STATION, UNITS 1 AND 2 MARGIN UNCERTAINTY RECAPTURE POWER UPRATE STARTUP REPORT

Braidwood Station, Units 1 and 2 Margin Uncertainty Recapture Power Uprate Startup Report INDEX Section Description Page

--- Executive Summary 1-ii 1.0 Purpose 1 2.0 MUR Power Uprate Program Scope 1 2.1 Program Development 1 2.2 Prerequisites to MUR Power Ascension Testing 2 2.3 MUR Power Ascension Testinq 2 2.4 T est Acceptance Criteria 3 3.0 Unit 1 Summary of Testing and Equipment Performance 5 Results 3.1 Unit 1 Power Ascension Chronological Sequence of Events. 5 3.2 Unit 1 Control System Performance 5 3.3 Unit 1 System and Equipment Performance Results 6 3.4 Unit 1 Review and Approval of Testing at MUR Power Uprate 7 Plateau of 3645 MWt.

4.0 Unit 2 Summary of Testing and Equipment Performance 8 Results 4.1 Unit 2 Power Ascension Chronoloqical Sequence of Events. 8 4.2 Unit 2 Control System Performance 8 4.3 Unit 2 System and Equipment Performance Results 9 4.4 Unit 2 Review and Approval of Testing at MUR Power Uprate 9 Plateau of 3645 MWt.

5.0 Application of the USFAR Initial Startup Test Program to 10 the Braidwood MUR Power Uprate Project.

5.1 General Discussion 10 5.1.1 Preoperational Tests 10 5.1.2 Initial Startup Tests 11 5.1.3 Comparison of USFAR Startup Tests to Power Ascension 11 Tests 6.0 Full Power Capability 12 1-i

Executive Summary Technical Requirements Manual Section 5.3.a, "Startup Report," requires the submittal of a startup report within 90 days following resumption of commercial power operations after an amendment to the license involving a planned increase in power level.

On February 7,2014, the Nuclear Regulatory Commission issued License Amendment No. 174 for Braidwood Station, Units 1 and 2, which allowed an increase in the maximum reactor power level from 3586.6 megawatts thermal (MWt) to 3645 MWt.

Braidwood Station, Unit 1 commenced increasing power on February 14, 2014 in accordance with Special Test Procedure SPP 13-001, "Braidwood Unit 1, MUR Power Uprate Project Power Ascension Procedure." The Unit 1 full power uprate power ascension load ramp was successfully completed on February 14, 2014 with all acceptance criteria being satisfied.

Braidwood Station, Unit 2 commenced increasing power on February 12, 2014 in accordance with Special Test Procedure SPP 13-002, "Braidwood Unit 2, MUR Power Uprate Project Power Ascension Procedure." The Unit 2 full power uprate power ascension load ramp was successfully completed on February 12, 2014 with all acceptance criteria being satisfied.

1-ii

Braidwood Station, Units 1 and 2 Margin Uncertainty Recapture Power Uprate Startup Report 1.0 Purpose This Power Uprate Startup Report is submitted to the NRC to satisfy the reporting requirements of the Braidwood Stations's Technical Requirements Manual, Section 5.3.a, "Startup Report," which requires this report to address the following items.

1. Address each of the tests identified in the Updated Final Safety Analysis Report.
2. Include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values
3. Describe corrective actions required to obtain satisfactory operation.
4. Include any additional specific details required in license conditions based on other commitments.

2.0 Measurement Uncertainty Recovery (MUR) Power Ascension Program Scope 2.1 Program Development The development of the MUR power ascension test recommendations and acceptance criteria was based on previous power uprates at Braidwood Station and the generic guidelines provided in WCAP-10263, "A Review Plan for Uprating the License Power of a PWR Power Plant," dated 1983.

The MUR Power Ascension Test Program verified the following items:

  • Automatic control systems and equipment affected by the MUR power ascension are maintained within selected operating limits.
  • Chemistry parameters are below the "Action" levels.
  • The feedwater heater level control system is stable.
  • Selected Area Radiation Surveys have been updated and found acceptable.

1

Braidwood Station, Units 1 and 2 Margin Uncertainty Recapture Power Uprate Startup Report 2.2 Prerequisites to MUR Power Ascension Testing Prior to the commencement of the MUR power ascension testing, a special test procedure required the completion of numerous activities. These activities included the following items:

  • The applicable plant instrument setpoint changes or recalibrations were completed as determined by the MUR Power Design Consideration Summary package (DCS).
  • Plant Modifications required to support operation at the MUR power level were closed out.
  • The Limiting Condition for Operation (LCO) Log, Clearance Order Log, open Adverse Condition Monitoring Plans (ACMP), and open Operability Evaluation (OpEvals) Tracking Logs were reviewed to assure there was no effect on MUR power ascension testing.
  • Baseline Data was taken at 3586.6 megawatts thermal (MWt).
  • Review of the NRC's Safety Evaluation approving the proposed MUR power license amendment and associated Technical Specification (TS) changes.

2.3 MUR Power Ascension Testing MUR power ascension was performed in accordance with a Braidwood Station Special Procedure (SPP). A heighten Level of Awareness (HLA) briefing was completed with operations and other appropriate plant personnel prior to power ascension.

Power was increased from 3586.6 MWt to the MUR power level of 3645 MWt. The ramp was stopped on both units when the MUR power calorimetric limit was met. Following the power increase, testing and equipment performance data was collected and evaluated in accordance with established test acceptance criteria. At the 2: 99.8% and

$. 100.0% MUR power plateau, the following activities were performed:

  • Reactor fuels parameters were evaluated.
  • Automatic control systems were evaluated.
  • Chemistry evaluations were performed.

2

Braidwood Station, Units 1 and 2 Margin Uncertainty Recapture Power Uprate Startup Report

  • Feedwater heater level control performance data was evaluated.
  • Main generator stator internal temperature data were collected and evaluated.
  • Radiation surveys were performed and evaluated.
  • Secondary plant and turbine/generator system performance were evaluated.
  • Condensate/Condensate booster system performance was evaluated.
  • A select set of equipment performance data (e.g. plant process computer points, control room readings and local readings) were collected and evaluated.

2.4 Test Acceptance Criteria General Discussion The development of the MUR power ascension test recommendations and acceptance criteria was based on previous power uprates at Braidwood Station and the generic guidelines provided in WCAP-10263, A Review Plan for Uprating the License Power of a PWR Power Plant," dated 1983.

Following the load increase in power to ? 99.8% and.:5 100.0% calorimetric power, test data recorded at the new power level were evaluated and compared to performance acceptance criteria (Le. 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 the MUR power ascension were evaluated using two levels of acceptance criteria. The 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 required to be taken if an individual criterion was not satisfied.

Level 1 Acceptance Criteria If a Level 1 Acceptance Criteria is not satisfied, then suspend the procedure and place the plant in a status judged satisfactory by the Shift Manager, using plant procedures and Technical Specifications. Resolution of the problem must be immediately pursued 3

Braidwood Station, Units 1 and 2 Margin Uncertainty Recapture Power Uprate Startup Report by equipment adjustments or through an engineering evaluation process, as appropriate, and recorded in the Sequence of Events Log. Following resolution, the applicable portion of the procedure must be repeated to verify that the Level 1 acceptance limit is satisfied. A description of the problem must be included in the Test Report documenting the successful completion.

For the Braidwood Station MUR power ascension, the following specific level 1 acceptance criteria were established:

  • Reactor Coolant System (RCS) average temperature is automatically maintained within +/- 1.5 of of its reference temperature (Tref) during steady state operations when the control rods are in automatic control.
  • Steam Generator (SG) feedwater regulating valve position <90% maintained in automatic control and SG water level maintained in automatic control.
  • The turbine driven main feedwater pump speed during steady state conditions does not exceed 5500 RPM.
  • Heater drain tank Level is <90 inches and stable at or near the MUR power level.
  • System and Equipment Level 1 Operating Limits identified in applicable SPP Attachments that are exceeded will be documented in the SPP Test Evaluation.

All the above Level 1 criteria were met for both Units 1 and 2 following the MUR power ascension.

Level 2 Acceptance Criteria If a Level 2 Administrative Criteria or any Operating Limit is not satisfied, then implementation of the procedure may proceed after an investigation and agreement by the Test Director, Engineering Management, and Operations Management personnel.

The limits stated in this category are associated with expectations of system performance whose characteristics can be improved by equipment adjustments.

If a Level 2 Operating limit cannot be satisfied, the Test Director may choose to document that result with a full explanation. This report must discuss alternative actions, as well as concluding recommendations to facilitate evaluation by station management.

The Test Director will log the results in the Sequence of Events Log and will indicate who was contacted for resolution and indicate the Issue Report number.

For the Braidwood Station MUR power ascension, the following specific level 2 acceptance criteria were established:

Equipment Performance

  • System and Equipment Level 2 acceptance limits are identified in various attachments of the appropriate SPP. Any limits that were exceeded required a documented evaluation in the SPP Test Report.

4

Braidwood Station, Units 1 and 2 Margin Uncertainty Recapture Power Uprate Startup Report Turbine Generator Temperature Monitoring System (TGTMS)

  • TGTMS Data are within Acceptance Limits.
  • Turbine Supervisory Vibration Data are within Acceptance Limits.

Plant Instrumentation

  • RCS delta temperature (Delta T) power and calorimetric power are within +/- 2%

based on the plant process computer (PPC) indication.

  • Nuclear instrumentation and calorimetric power are within +/- 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 1 and 2 following the MUR power ascension.

3.0 Unit 1 Summary of Testing and Equipment Performance Results 3.1 Unit 1 Power Ascension Chronological Sequence of Events.

No. Event Description Date 1 Obtained Baseline Data at 3586 MWe Plateau 2/13/2014 2 Completed Heighten Level of Awareness (HLA) 12/13/2014 Brief 3 Commenced ramp to ~ 99.8% and 2/14/1014 00:17 S 100.0% calorimetric power 4 Completed ramp to ~ 99.8% and 2/14/2014 03:19 S 100.0% calorimetric power 5 Completed review and signoff of testing for the 4/3/2014 MUR power ascension plateau 3.2 Unit 1- Control System Performance Results Control Systems most affected by the MUR power ascension were monitored to assure acceptable performance and compliance with their specific Level 1 and 2 acceptance criteria. The following table summarizes these control systems.

5

Braidwood Station, Units 1 and 2 Margin Uncertainty Recapture Power Uprate Startup Report Level 1 Level 2 Tuning No. Control System Description Acceptance Acceptance Adjustment Criteria Criteria Required 1 Reactor Coolant System Satisfied Satisfied None 2 Feedwater System Satisfied Satisfied None 3 Steam Generator water level Satisfied None None 4 Turbine Driven Main Feedwater Satisfied Satisfied None Pump 5 Heater Drain Tank Level Satisfied None None 6 Main Turbine Satisfied Satisfied None 7 Steam Flow I Feedwater Flow None Satisfied None Mismatch 3.3 Unit 1 - System Equipment Performance Results Level 1 Level 2 Equipment No. System Description Operating Operating Performance Limits Limits 1 Condensate System None Satisfied (2) Satisfied 2 Condenser None Satisfied Satisfied 3 Condensate Booster System None Satisfied(2) Satisfied 4 Feedwater System Satisfied Satisfied Satisfied 5 Heater Drain System Satisfied Satisfied Satisfied 6 Reactor Satisfied Satisfied (1 )(3) Satisfied 7 Reactor Coolant System Satisfied Satisfied Satisfied 8 Main Steam System Satisfied None Satisfied 9 Main Turbine Satisfied Satisfied Satisfied 10 Generator Cooling System None Satisfied Satisfied 11 Generator None Satisfied Satisfied Notes: 1) Power Range N42 PR2 Full Power Meter (% reactor power) indicated 99%.

The administrative limit was < 102% and within +2,-0% of calorimetric power.

Calorimetric power was 99.9%; therefore, the value was below the allowable

-0%. The Nuclear Instrumentation (Nt) meters are checked daily during the performance of 1 BwOSR 3.3.1.2-1, "Unit One Power Range High Flux Setpoint Daily Channel Calibration (Computer Calorimetric)." If the instrument is below the -0% tolerance it is adjusted to within tolerance. The MUR value was within the acceptance criteria of +1- 2% of calorimetric power.

This condition is acceptable and no additional actions required.

2) 10 Condensate and Condensate Booster (CD/CB) pump data was outside operating limits because it was not in-service. Braidwood Station has an installed spare CDICB pump; therefore, this is the expected condition.

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Braidwood Station, Units 1 and 2 Margin Uncertainty Recapture Power Uprate Startup Report

3) Delta T power and calorimetric power per level 2 acceptance criteria shall be within +/-2%. All indications met this criteria except Loop 1D Delta T indicator which indicates 102%, while calorimetric indicates 99.9%, a difference of 2.1 %. Instrument 1TI-0441 A scale is marked every 2% and, therefore, can be read to 1%. A 0.1 % digit is not a significant digit and, therefore, the 2.1 %

difference can be rounded to 2%. 1BwlSR 3.3.1.10-2, "Unit 1 Reactor Coolant System Temperature Instrumentation Alignment," directs rescaling the loop if it is out of tolerance by +3/-1 %. Considering that the loop is within tolerance and the recorded difference outside of acceptance criteria is below significant digit for this instrument, the difference is rounded to 2% and meets acceptance criteria.

3.4 Unit 1 - Review and Approval of Testing at MUR Power Plateau

1. Reactor Fuel Parameters: Fuel Thermal margins were found acceptable for continued operation at the full power uprate MUR ascension plateau as demonstrated by full power testing. See Attachment 2 for core parameters at the MUR ascension plateau (Le., plant parameters, fluxmap results, full power ilT and loop Tavg , and RCS flow results).
2. Automatic Control Systems: All automatic control systems were acceptable for continued operation at the MUR power ascension plateau.
3. Chemistry Approval: RCS, Condensate and Feedwater chemistry did not reach Chemistry Action Levels.
4. Feedwater and Main Steam Parameters: The turbine driven main feedwater pump speed, feedwater control valve pOSition, and steam generator water level met acceptance criteria. Feedwater pump, condensate pump and condensate booster pump suction pressure exceeded NPSH requirements. Feedwater heater level control performance was taken and evaluated to be acceptable.
5. Main Generator Parameters: Generator stator temperature and bus bar temperatures satisfied acceptance criteria limits. Generator conditions were also satisfactory for continued operation at the MUR power plateau.
6. Radiation Protection Approval: Surveys were performed and all radiological conditions were found acceptable for operation at the MUR power plateau.
7. Condensate / Condensate Booster System Approval: CD and CB pump pressures, flows, temperatures and motor amps were found acceptable.
8. Secondary Plant and Turbine/Generator Systems Approval: System and equipment data were reviewed and found acceptable.

7

Braidwood Station, Units 1 and 2 Margin Uncertainty Recapture Power Uprate Startup Report

9. Vibration Data: CondensatelCondensate BoosterlHeater Drain/Feedwater Pumps: Vibration data was reviewed and found acceptable. The vibration data supports the conclusion that adequate NPSH is available to these pumps.
10. Main Control Room Instrumentation: Zone Banding was reviewed and no changes were required.

4.0 Unit 2 Summary of Testing and Equipment Performance Results 4.1 Unit 2 Power Ascension Chronological Sequence of Events.

No. Event Description Date 1 Obtained Baseline Data at 3586 MWe Plateau 02/12/2014 16:07 2 Completed Heighten Level of Awareness (HLA) 02/12/2014 Brief (prior to ramp and at shift turnover) 3 Commenced ramp to.2: 99.8% and 2/1212014 16:42

.:::. 100.0% calorimetric power 4 Completed ramp to .2: 99.8% and 2/12/2014 21 :00

.:::. 100.0% calorimetric power 5 Completed review and signoff of testing for the 4/03/2014 MUR power ascension plateau 4.2 Unit 2- Control System Performance Results Control Systems most affected by the MUR power ascension were monitored to assure acceptable performance and compliance with their specific Level 1 and 2 acceptance criteria. The following table summarizes these control systems.

Level 1 Level 2 Tuning No. Control System Description Acceptance Acceptance Adjustment Criteria Criteria Required 1 Reactor Coolant System Satisfied Satisfied None 2 Feedwater System i Satisfied Satisfied None 3 Steam Generator water level Satisfied None None 4 Turbine Driven Main Feedwater Satisfied Satisfied None Pump 5 Heater Drain Tank Level Satisfied( 1) None Yes (1) 6 Main Turbine Satisfied Satisfied None 7 Steam Flow 1 Feedwater Flow None Satisfied None Mismatch Note 1) The MUR power ascension uncovered one latent issue. 2TY-CB017B had drifted out of calibration low by approximately 50 psig. Pre MUR there was sufficient NPSH such that the instrument drift had no apparent effect on operation. MUR caused a 7 psig reduction of feedwater pump NPSH which 8

Braidwood Station, Units 1 and 2 Margin Uncertainty Recapture Power Uprate Startup Report combined with the instrument drift resulted in sporadic feedwater pump NPSH low alarms, minor offsets in heater drain tank level and a NPSH actuation during a heater drain pump swap. Operating NPSH margin pre MUR was 179 psig. NPSH margin post MUR is 172 psig. Therefore, adequate margin is available above the loop setpoints. The card was replaced and no additional actions are required.

4.3 Unit 2 - System Equipment Performance Results No. System Description Level 1 Level 2 Equipment Operating Operating Performance Limits Limits 1 Condensate System None Satisfied( 1) Satisfied 2 Condenser None Satisfied Satisfied 3 Condensate Booster System None Satisfied( 1) Satisfied 4 Feedwater System Satisfied Satisfied Satisfied 5 Heater Drain System Satisfied Satisfied Satisfied 6 Reactor Satisfied Satisfied Satisfied 7 Reactor Coolant System Satisfied Satisfied Satisfied 8 Main Steam System Satisfied None Satisfied 9 Main Turbine Satisfied Satisfied Satisfied 10 Generator Cooling System None Satisfied Satisfied 11 Generator None Satisfied Satisfied Note 1) 20 COICB pump data was outside operating limits because it was not in-service. Braidwood station has an installed spare COICB pump; therefore, this is the expected condition.

4.4 Unit 2 - Review and Approval of Testing at MUR Power Plateau

1. Reactor Fuel Parameters: Fuel Thermal margins were found acceptable for continued operation at the full power uprate MUR ascension plateau as demonstrated by full power testing. See Attachment 2 for core parameters at the MUR ascension plateau (Le., plant parameters, fluxmap results, full power AT and loop and RCS flow results).
2. Automatic Control Systems: All automatic control systems were acceptable for continued operation at the MUR power ascension plateau.
3. Chemistry Approval: RCS, Condensate and Feedwater chemistry did not reach Chemistry Action Levels.
4. Feedwater and Main Steam Parameters: The turbine driven main feedwater pump speed, feedwater control valve position, and steam generator water level met acceptance criteria. Feedwater pump, condensate pump and condensate booster pump suction pressure exceeded NPSH requirements. Feedwater heater level control performance was taken and evaluated to be acceptable.

9

Braidwood Station, Units 1 and 2 Margin Uncertainty Recapture Power Uprate Startup Report

5. Main Generator Parameters: Generator stator temperature and bus bar temperatures satisfied acceptance criteria limits. Generator conditions were also satisfactory for continued operation at the MUR power plateau.
6. Radiation Protection Approval: Surveys were performed and all radiological conditions were found acceptable for operation at the MUR power plateau.
7. Condensate / Condensate Booster System Approval: CD and CB pump pressures, flows, temperatures and motor amps were found acceptable.
8. Secondary Plant And Turbine/Generator Systems Approval: System and equipment data were reviewed and found acceptable.
9. Vibration Data: Condensate/Condensate Booster/Heater Drain/Feedwater Pumps: Vibration data was reviewed and found acceptable. The vibration data supports the conclusion that adequate NPSH is available to these pumps.
10. Main Control Room Instrumentation: Zone Banding was reviewed and no changes were required.

5.0 Application of the UFSAR Initial Startup Test Program to the Braidwood MUR Power Ascension Test Program 5.1 General Discussion The development of the MUR power ascension test recommendations and acceptance criteria is based on previous power uprate testing performed at Braidwood Station. The previous power uprate tests were based on a review of similar tests performed at other nuclear plants; Westinghouse Topical report, WCAP-10263, "A Review Plan for Uprating the license Power of a PWR Power Plant," dated 1983; and Section 7, "Output Determination," of the Westinghouse "Revised Proposal for Power Uprate," dated August 23,1999. WCAP-10263 recommends that a test program be developed on a plant specific basis addressing the significance of hardware modifications and the magnitude of the power uprate. The Braidwood Station hardware upgrades were limited to instrument setpoint changes and minor equipment modifications that were completed as part of the plant modification process.

The Updated Final Safety Analysis Report (UFSAR) Chapter 14, "Initial Test Program,"

addresses the Braidwood Station initial test program. The initial test program included both preoperational and initial startup testing. Each of these programs is discussed in the following paragraphs:

5.1.1 Preoperational Tests Preoperational testing consisted of system performance tests performed prior to core load on completed systems prior to final acceptance. These tests demonstrated the capability of structures, systems and components to meet safety related performance requirements.

10

Braidwood Station, Units 1 and 2 Margin Uncertainty Recapture Power Uprate Startup Report This category of tests is now conducted as part of the post modification testing process.

The MUR power ascension modification tests were successfully completed as part of the modification process and work control process.

5.1.2 Initial Startup Tests Initial startup testing consisted of those single and mUlti-system tests that occurred during or after fuel loading which demonstrated overall plant performance. This included such activities as precritical tests, low power tests (i.e., including criticality tests), and power ascension tests. This testing confirmed the design bases and demonstrated, where possible, that the plant is capable of withstanding the anticipated transients and postulated accidents.

This category of tests was reviewed for applicability in developing the Braidwood Station MUR power ascension test program.

5.1.3 Comparison of UFSAR Startup Tests to MUR Power Ascension Tests The following table addresses each of the initial power ascension tests and their applicability to the Braidwood Station MUR power ascension test program. Tests identified with a 'Yes" were incorporated into the Braidwood Station MUR power ascension test program.

Required in MUR Test No. Startup Test Title Power Ascension Acceptance Criteria I (1 ) T est Procedure Same as UFSAR 14.2 - 62 Initial Core Load No N/A 14.2 - 63 Control Rod Drives No N/A

~~

14.2 - 64 Rod Position Indicators N/A

, 14.2 - 65 Reactor Trip Circuit N/A 14.2 - 66 Rod Drop Measurements No N/A 14.2 - 67 Incore Flux Monitor System No N/A 14.2 - 68 Nuclear Instruments No N/A 14.2 - 69 Reactor Coolant System Pressure No N/A 14.2 - 70 Reactor Coolant System Flow No N/A 14.2 - 71 Pressurizer Effectiveness No N/A 14.2 - 72 Water Chemistry Yes (2) N/A 14.2 - 73 Radiation Surveys Yes (3) N/A 14.2 - 74 Effluent Radiation Monitors No N/A I 14.2 - 75 Initial Criticality No N/A 14.2 - 76 Power Ascension Yes (4) N/A 14.2 - 77 Moderator Temperature Reactivity No N/A Coefficient Measurement 14.2 - 78 Control Rod Reactivity Worth No N/A Measurement 14.2 - 79 Boron Reactivity Worth No N/A Measurement 14.2 - 80 Flux Distribution Measurement No N/A 14.2 - 81 Pseudo Rod Ejection No N/A 11

Braidwood Station, Units 1 and 2 Margin Uncertainty Recapture Power Uprate Startup Report 14.2 - 82 Power Reactivity Coefficient No N/A Measurement 14.2 - 83 Core Performance Evaluation No N/A 14.2-84 Flux Asymmetry Evaluation No N/A 14.2 - 85 Power Plant Trip No N/A 14.2 - 86 Shutdown from outside the Control No N/A Room 14.2 - 87 Loss of Off Site Power No N/A 14.2-88 10% Load Swing No N/A 14.2 - 89 50% Load Swing No N/A 14.2-90 RTD Cross-Calibration No N/A 14.2 - 91 Turbine Trip from 25% Power No N/A Notes: (1) USFAR Chapter 14 table numbers (2) Water Chemistry at MUR power in accordance with Chemistry Action Levels.

(3) Radiation Surveys done in certain specific areas.

(4) Special Test Procedure at MUR power was implemented.

6.0 Full Power Capability Power was raised on Unit 1 and Unit 2 until ~ 99.8% and .:s 100.0% calorimetric power was reached. The full power level of 3645 MWt was obtained. The results of the MUR power ascension test indicate that the plant can safely operate at the current MUR power levels. No additional supplemental startup test reports are required for either of the Braidwood Station Units.

12

ATTACHMENT 2 BRAIDWOOD STATION, UNITS 1 AND 2 CORE PARAMETERS AT MUR ASCENSION PLATEAU

Braidwood Station, Units 1 and 2 Core Parameters at MUR Ascension Plateau Unit 1 Cycle 18 Plant Data Map 10: bd1c18m05 Date of Map: 2/14/2014 Cycle Burnup: 135.5 EFPO Power Level: 99.9%

Control Rod Position: 220 steps FI uxmap Resu ts Core Average Axial Offset -4.73%

Quadrant Power Tilt Ratios:

Quadrant (N41): 1.014 Quadrant (N42): 0.996 Quadrant (N43): 0.993 Quadrant (N44): 0.998 Max. Nuclear Enthalpy Rise Hot Channel Factor 1.5086 Nuclear Enthalpy Rise Hot Channel Factor Limit 1.7005 Max. Steady State Heat Flux Channel Factor 2.1177 Steady State Heat Flux Channel Factor Limit 2.6026 Max. Transient Heat Flux Channel Factor 2.1600 Transient Heat Flux Channel Factor Limit 2.3390 Loo LlT and TAVG at Hot Full Power 1A 60.217 587.104 1B 60.366 586.7 1C 60.470 587.628 10 60.661 586.539 RCSFI owvs, Acceplance t C n'tena RCS LOOP Measured Flow Minimum Flow (gpm) Requirement (gpm) 1A 99,839 1B 99,575 1C 101,694 10 97,705 Total 398,813 ~ 386,000 1

Braidwood Station, Units 1 and 2 Core Parameters at MUR Ascension Plateau Unit 2 Cycle 17 Plant Data Map 10: bd2c17m10 Date of Map: 2/13/2014 Cycle 8umup: 451.2 EFPD Power Level: 99.9%

Control Rod Position: 220 FI uxmap Resu Its Core Average Axial Offset -1.58%

Quadrant Power Tilt Ratios:

Quadrant (N41): 1.000 Quadrant (N42): 1.001 Quadrant (N43): 0.999 Quadrant (N44): 1.001 Max. Nuclear Enthalpy Rise Hot Channel Factor 1.4788 Nuclear Enthalpy Rise Hot Channel Factor Limit 1.7005 Max. Steady State Heat Flux Channel Factor 1.9058 Steady State Heat Flux Channel Factor Limit 2.6026 Max. Transient Heat Flux Channel Factor 1.9439 Transient Heat Flux Channel Factor Limit 2.0013 Loop ilT an dTAVG at Hot FliP u ower Loop ilTeFl TAVG eFl 2A 61.761 581.021 28 61.267 581.005 2C 62.062 581.000 2D 61.259 580.974 RCSFI owvs. Acceptance C' ntena RCS LOOP Measured Flow Minimum Flow (gpm) Requirement (gpm) 2A 97,886 28 100,831 2C 96,978 2D 101,471 Total 397,166 ~ 386,000 2

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