HNP-12-094, Cycle 18 Startup Test Report

Cycle 18 Startup Test Report

ML12250A191
Person / Time
Site:	Harris
Issue date:	09/05/2012
From:	Corlett D Duke Energy Carolinas, Carolina Power & Light Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
HNP-12-094
Download: ML12250A191 (31)

Text

~ Duke David H. Corlett Supervisor, Licensing/Regulatory Programs

{#Energy Harris Nuclear Plant 5413 Shearon Harris Rd New Hill NC 27562-9300 919-362-3137 September 5, 2012 Serial: HNP-12-094 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400

Subject:

Cycle 18 Startup Test Report Ladies and Gentlemen:

In accordance with Technical Specification 6.9.1.1, Carolina Power & Light submits the enclosed Cycle 18 Startup Test Report for the Harris Nuclear Plant. The report is required following an amendment to the operating license involving an increase in power level within 90 days of resumption of commercial power operation.

This document contains no regulatory commitments.

Please refer any questions regarding this submittal to me at (919) 362-3137.

Sincerely, Enclosure cc: Mr. J.D. Austin, NRC Sr. Resident Inspector, HNP Ms. A. T. Billoch Colon, NRC Project Manager, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II

Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report August 13, 2012 CAROLINA POWER AND LIGHT COMANY Page 1 of 30

EXECUTIVE

SUMMARY

The Harris Technical Specifications Section 6.9(Reporting Requirements) provides the following guidance for conditions specifically requiring a startup report and items that should be addressed in the startup report.

STARTUP REPORT Section 6.9.1.1: A summary report of plant startup and power escalation testing shall be submitted following: (1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit.

The Startup Report shall address each of the tests identified in the Final Safety Analysis Report and shall 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. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

Startup Reports shall be submitted within: (1) 90 days following completion of the Startup Test Program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed.

The scope of this report was generated by reviewing the tests described in FSAR Chapter 14 and determining the impact ofMUR on these tests. The results ofthis review are addressed in Table 4.7.3 and covers the startup test program associated with the implementation of theM UR uprate.

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Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 Table of Contents Page 1.0 Introduction ................................................................................................................ 5 1.1 General ......................................................................................................................... 5 1.2 Cycle Description......................................................................................................... 6 1.3 Power Uprate ............................................................................................................... 6 2.0 Summary ..................................................................................................................... 6 3.0 Component & Initial Operation Test Summaries .................................................. 7 3.1 Protection System Engineered Safety Features Actuation Logic Test ........................ 7 3.2 Piping Thermal Expansion and Dynamic Effects Test ................................................ 8 4.0 Operational and Power Ascension Test Summaries .......................................... 8 4.1 Rod Drop Time Measurement ..................................................................................... 8 4.2 Reactor Coolant System Flow Measurement ............................................................... 8 4.3 Calibration of Nuclear Instrumentation Test ............................................................... 9 4.4 Flux Distribution Measurement Test ........................................................................... 9 4.5 Core Performance Test .............................................................................................. 10 4.6 Power Coefficient Measurement Test ........................................................................ 10 4.7 Control Rod Reactivity Worth Test ........................................................................... 11 4.8 Boron Endpoint Measurement - All Rods Out Test................................................... 11 4.9 RTD/TC Cross Calibration Test ................................................................................ 11 4.10 Plant Performance Test .............................................................................................. 12 4.11 Main Transformer, Isophase Bus Duct, and AC Distribution System Test ............... 12 4.12 HP Turbine replacement and Governor Valve Management Program ...................... 13 5.0 References ............................................................................................................. 14 Page 3 of 30

Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 List of Tables and Figures Page Table 4.1.1 Control Rod Drop Times ............................................................................... 16 Table 4.3.1 Intermediate Range Detector Set point Determination ................................. 17 Table 4.3.2 Power Range Detector Calibration Values ................................................... 17 Figure 4.4.1 Flux Map 482 Measured vs. Calculated Powers (30%) .............................. 18 Figure 4.4.2 Flux Map 483 Measured vs. Calculated Powers (75%) .............................. 19 Figure 4.4.3 Flux Map 484 Measured vs. Calculated Powers (100%) ............................. 20 Table 4.5.1 Flux Map Summary ..................................................................................... 21 Table 4.6.1 Reactivity Computer Checkout .................................................................... 22 Table 4.6.2 Low Power Physics Test Results Summary Endpoint, Control Rod Worth, HZP Temperature Coefficient, and Differential Boron Worth .................................................. 23 Figure 4.7.1 Integral Worth of the Reference Bank ......................................................... 24 Figure 4.7.2 Differential Worth of the Reference Bank ................................................... 25 Table 4.7.3 FSAR Chapter 14 Tests ............................................................................... 26 Page 4 of 30

Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 1.0 Introduction 1.1 General This startup report documents test results for Harris Nuclear Plant Unit 1, Cycle 18 and the implementation of a Measurement Uncertainty Recapture (MUR) uprate of 1.66%. The MUR(EC 74914)(Reference 5.35) allows a new maximum power level of 2948 MWt based on the installation of Cameron Check Plus leading edge flow meters (LEFMs) in refueling outage 16.

The system and component evaluations performed for MUR determined that the Nuclear Steam Supply System (NSSS) and Balance of Plant (BOP) systems to support RFO10 Steam Generator Replacement 5% stretch power uprate to 2900 MWt were evaluated for operation at 102% of 2900 MWt (2958 MWt) which bounds the MUR uprate operating conditions. Those evaluations determined that with the exception of the main transformers and isophase bus duct cooling system which would limit the maximum power output at certain plant conditions, other NSSS and BOP systems would support operation at the MUR conditions.

The main transformers were replaced and the isophase bus duct cooling system was upgraded to support operation at MUR conditions. In addition, the HP turbine was upgraded with a higher efficiency steam path to maximize the electrical output at the MUR conditions. No other changes to the NSSS and BOP system configurations, controls, and operation were required to support operation at MUR conditions. As such, routine system surveillance testing and monitoring system performance during startup and power ascension to MUR conditions is considered adequate to verify that systems continue to operate within their analyzed and design conditions.

This report primarily focuses on the results of the following evolutions:

Component & Initial Operation Tests Operational and Power Ascension Tests These evolutions were modeled after those described in Chapter 14 of the Harris FSAR. The evolutions were modified to eliminate testing that is no longer appropriate. Examples of tests that were judged to be inappropriate include low power flux mapping and boron worth measurements.

In the cases of boron worth measurement alternate testing described in ANSI 19.6.1 (Reference 5.15) was performed. Plant power ascension data demonstrates that HNP control systems can safely and effectively operate following a Measurement Uncertainty Recapture (MUR) power uprate. The Startup Test Program, defined by EPT-445 (Reference 5.12) collected plant data from power ascension and steady state operation to compare plant response with design predictions, specifications and operation at MUR uprated power.

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Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 1.2 Cycle Description The Cycle 18 core design consists of 72 fresh fuel assemblies, 69 once-burned assemblies, and 16 twice burned assemblies, all of the AREVA 17x17 High Thermal Performance (HTP) design with debris resistant FUELGUARDTM lower tie plate. The fresh fuel introduces use of a new cladding material, an AREVA advanced zirconium alloy named M5, in lieu of the Zircaloy-4 material that has been used for several cycles. The M5 material has a low corrosion rate in high burnup and high duty irradiation conditions, which is the primary driver for the cladding material change. The specifics for the core reload design are presented in the Engineering Change package for the Cycle 18 reload (Reference 5.29).

1.3 Power Uprate Harris Nuclear Plant recently uprated core power from 2900 MWt (NSSS power = 2912.4 MWt) to 2948 MW, (NSSS power = 2960.4 MWt). All references to reactor power are in percent of rated thermal power. The overall electrical output of the unit was increased approximately 30 MW due to the power uprate and upgrades of the high pressure turbine (Reference 5.33).

2.0 Summary Safe operation at the increased reactor power is supported by a combination of system evaluations (WCAP-17209-P) (Reference 5.28) and plant observations during power ascension (EPT-445)

(Reference 5.12). Safe operation within the analyzed bases was assured by the normal combination of control and protection instrumentation. Control and protection instrumentation using HP turbine inlet (first stage) pressure were rescaled consistent with the replacement HP Turbine and the power range nuclear instruments were recalibrated based on the MUR uprate conditions.

Monitoring the various plant system parameters and responses during power ascension verified there were no unanticipated changes in the system operation and systems continued to operate within design limits.

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Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 3.0 Component & Initial Operation Test Summaries 3.1 Protection System Engineered Safety Features Actuation Logic Test There were no changes required to the Reactor Protection System Engineered Safety Features Actuation Logic Test due to any RFO-17 modifications or the MUR uprate. There were however, calibration changes to the reactor control and protection instruments due to replacement of the HP Turbine rotor with a resultant increase in turbine inlet (first stage) pressure. In addition, changes were made to the power range NI cabinets due to the MUR uprate. The Power Range Neutron Flux High Setpoint was changed from 109% to 108%. The Total Allowance (TA) for the Power Range Neutron Flux High Setpoint was changed from 7.5 to 5.83 as well as the Allowable Value from 111.1% to 109.5%. The Total Allowance (TA) for the Power Range Neutron Flux Low Setpoint was changed from 8.3 to 7.83 as well as the Allowable Value from 27.1% to 26.8%. The Total Allowance (TA) for both the Power Range Neutron Flux High Positive Rate and the Power Range Neutron Flux High Negative Rate was changed from 2.5 to 2.33. The following MSTs were revised and used to perform the required recalibration of Intermediate and Power Range Nuclear Instruments:

MST-I0044 (Reference 5.20), Nuclear Instrumentation System Power Range N41 Calibration MST-I0045 (Reference 5.21), Nuclear Instrumentation System Power Range N42 Calibration MST-I0046 (Reference 5.22), Nuclear Instrumentation System Power Range N43 Calibration MST-I0047 (Reference 5.23), Nuclear Instrumentation System Power Range N44 Calibration MST-I0048 (Reference 5.24), Excore Nuclear Instrumentation System Intermediate Range N35 Calibration MST-I0049 (Reference 5.25), Excore Nuclear Instrumentation System Intermediate Range N36 Calibration MST-I0070 (Reference 5.36), Calibration of NIS Power Range Overpower Trip High Range Bistables EPT-093 (Reference 5.16) was used for the determination of the control and protection setpoints that use turbine first stage pressure as the basis for the setting. Plots of first stage turbine pressure versus reactor power and a linear regression curve were generated. Following the rescaling of the turbine first stage pressure instruments, the predicted first stage pressure versus reactor power matched the actual curve such that no changes to instrument setpoints were required. This is also substantiated by the fact that the Tref curve, which is also based upon first stage pressure, did not require any instrument re-scaling. The following MSTs were revised and used to perform the required recalibration of the turbine first stage pressure loop calibrations:

MST-I0067 (Reference 5.26), Turbine First Stage Pressure Loop (P-0447) Calibration MST-I0068 (Reference 5.27), Turbine First Stage Pressure Loop (P-0446) Calibration Page 7 of 30

Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 3.2 Piping Thermal Expansion and Dynamic Effects Test The accessible portions of the following Secondary Systems outside containment were walked down by Systems and Civil Engineering in accordance with plant procedure EGR-NGGC-0026 (Reference 5.17) and documented in EPT-445 (Reference 5.12). These walk downs included all branch lines, instrument lines, hangers and supports, as well as all vents and drains. Walk downs also monitored the lines for abnormal vibrations. These walkdowns verified no significant system changes resulted from the implementation of the MUR uprate.

• Main Steam System

• Steam Generator Blowdown System

• Main Feedwater System

• Condensate System

• Heater Vents and Drains System

• Extraction Steam System 4.0 Operational and Power Ascension Test Summaries 4.1 Rod Drop Time Measurement Test Rod drop tests were performed in accordance with plant procedure EST-724 (Reference 5.2) at hot full flow coolant conditions. Briefly, a bank is selected and pulled to the fully withdrawn position. Opening the reactor trip breakers, thus interrupting the circuit, then drops rods. The acceptance criteria, from Technical Specifications, require that the rod drop time from the beginning of the drop to dashpot entry be no greater than 2.7 seconds at full core flow and operating temperatures. All rod drop tests were completed within the acceptance criteria. Results of the rod drop testing are included in Table 4.1.1 of this report.

4.2 Reactor Coolant System Flow Measurement Test Reactor coolant system flow was measured using EST-709 (Reference 5.3). The HNP accident analyses are based on the most limiting RCS flow values (minimum or maximum). The Cycle 18 measured EST-709 flow is bounded by the various accident analysis values. The corresponding description and numerical values are as follows:

RCS Flow Description Flow (gpm)

Thermal Design (low) 277,800 1

Technical Specification Minimum 299,9982 Cycle 18 Measured Flow per EST-709 303,870 Mechanical Design Flow Limit 314,2312 1 293,540 x 1.022, where 1.022 is the RCS flow rate measurement uncertainty (2.1%) plus a penalty of 0.1% for minor undetected fouling of feedwater venturi.

2 EST-709(Reference 5.3).

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Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 Based upon the results of EST-709 (Reference 5.3), all nine of the reactor coolant flow protection loops required rescaling IAW Calc. HNP-I/INST-1010 (Reference 5.43). All channels are within the Tech. Spec. Allowance for RCS loop low flow trip setpoint. This rescaling was implemented into the applicable surveillance test and these channels are in the process of being recalibrated.

4.3 Calibration of Nuclear Instrumentation Test The Intermediate Range (IR) and Power Range (PR) detectors were adjusted prior to initial Cycle 18 startup per procedure EPT-008 [Reference 5.4]. The adjustments account for changes in core loading and reactivity from the previous cycle (17) to the new cycle (18), a methodology bias based upon data from the previous three cycles, and the increase in power due to the MUR. The methodology and calculations to determine the adjustment factor (also referred to as the R-factor) are detailed in calculation HNP-F/NFSA-0213 [Reference 5.6].

The IR adjustment factor for Cycle 18 was calculated to be 1.095. This pre-calculated value includes a bias multiplier of 0.964 based upon benchmark data (Reference 5.6). The Cycle 18 determined R-factor is applied to the N35 and N36 trip and rod stop setpoints from the last setpoint determination of Cycle 17. A post-startup setpoint determination was performed using procedure EPT-009 [Reference 5.5]. This data is included in Table 4.3.1. The actual IR trip setpoint, prior to recalibration, was determined to be 23.27% for N35 and 21.70% for N36. The Technical Specification maximum allowable limit is 30.9%.

The PR adjustment factor for Cycle 18 was calculated to be 0.817. This pre-calculated value includes a bias multiplier of 0.931 based upon benchmark data (Reference 5.6). The Cycle 18 determined R-factor is applied to the N41, N42, N43, and N44 top and bottom HFP normalized detector currents from the last incore/excore calibration performed in Cycle 17 using procedure EST-911 [Reference 5.11]. This data is included in Table 4.3.2.

4.4 Flux Distribution Measurement Test Core power distributions for Cycle 18 are measured by processing moveable detector traces with the INPAX-W code, which is a module of the POWERTRAX core monitoring system. Power distribution maps for the power ascension flux maps are included as Figures 4.4.1 through 4.4.3.

The initial low power flux map is taken near 30% power to verify core loading is as designed.

Map 482 was taken immediately after stabilizing power near 30% (before equilibrium xenon was established) for core verification. The maximum difference between measured and calculated powers was -5.2% (location F02), as shown in Figure 4.4.1. Map 484 taken near 100% power indicated that the limiting fuel assembly (location C10) had an F-dh (peak pin) fraction of limit of 0.913, see Table 4.5.1. The following flux maps passed acceptance criteria contained in FMP-200 (Reference 5.10).

• Map 482 @ 30% (verifying that the core was loaded as designed)

• Map 483 @ 75%

• Map 484 @ 100%

The Core Operating Limits Report (COLR)(PLP-106) [Reference 5.9] requires a minimum of 38 measured traces for all flux maps.

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Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 4.5 Core Performance Test The flux maps following core loading verification are taken to verify compliance with Technical Specification requirements and limits on hot channel factors, quadrant power tilts, and to establish allowed power levels for successive power ascension. The following flux maps were taken near 75% and 100% power, respectively.

• Map 483 @ 75%

• Map 484 @ 100%

All flux maps allowed full power operation with no additional intermediate power level maps other than those required per PLP-626 [Reference 5.1]. Table 4.5.1 includes pertinent statistics for evaluating map quality and monitoring of required core parameters.

The flux maps allowed power ascension and then full power operation based on meeting the applicable acceptance criteria.

4.6 Power Coefficient Measurement Test The RMAS reactivity computer is set up before LPPT using procedure EPT-026 [Reference 5.7].

Comparing period measurements to the startup rate indicated by the computer performed following initial criticality performs a checkout of the reactivity computer. The six-group constants input into the reactivity computer were provided by AREVA and are listed in Table 4.6.1.

The reactivity computer checkout requires that the average absolute difference between indicated and theoretical reactivity for the positive period measurements is less than 5%. Results of the reactivity computer checkout are included in Table 4.6.1.

The isothermal temperature coefficient (ITC) is measured at All Rods Out (ARO), HZP to verify that Technical Specification requirements limiting the ARO moderator temperature coefficient (MTC) to less than or equal to +5 pcm/oF. Should the MTC exceed the acceptance criteria, rod withdrawal limits for startup and power ascension must be established. The MTC is derived from the measured ITC using the equation below, where the doppler temperature coefficient (DTC) is

-1.50 pcm/oF (Reference 5.30).

ITC = MTC + DTC Low Power Physics Testing (LPPT) is performed under a single test procedure (EST-923)

(Reference 5.8). EST-923 covers:

• Initial criticality

• Reactivity computer period checks

• Test band determination (point of adding heat determination)

• ARO boron endpoint

• Temperature coefficient determination

• Control rod bank worth measurements (rod swap)

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Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 Results for Cycle 18 LPPT and the corresponding acceptance criteria are listed in Table 4.6.2.

Table 4.6.2 also contains test results from sections 4.7 and 4.8.

4.7 Control Rod Reactivity Worth Test The worths of the control and shutdown banks are measured using the rod swap technique. The reference bank (for Cycle 18, control bank B) was measured via boron swap. The remaining banks were measured fully inserted in the presence of the reference bank in a critical configuration.

The review criteria for the rod worths are as follows:

1 The absolute value of the percent difference between measured and predicted integral worth of the reference bank is less than 10%.

2 For all banks other than the reference bank, the absolute value of the percent difference between measured and predicted worths is less than 15% or the absolute value of the reactivity difference between measured and predicted worths is less than 100 pcm, whichever is greater.

The acceptance criterion requires that the sum of the measured worths be between 90% and 110%

of the sum of the predicted worths.

Results for Cycle 18 LPPT and the corresponding acceptance criteria are listed in Table 4.6.2.

Figures 4.7.1 and 4.7.2 graphically compare the predicted and measured integral and differential rod worths for the reference bank.

4.8 Boron Endpoint Measurement - All Rods Out Test The boron endpoint is measured at the Hot Zero Power (HZP), All Rods Out (ARO) condition.

The acceptance criterion for the boron endpoint measurement requires the HZP, ARO endpoint to be within 50 ppm of the predicted value.

Results for Cycle 18 Low Power Physics Testing (LPPT) and the corresponding acceptance criteria are listed in Table 4.6.2.

4.9 RTD/TC Cross Calibration Test EST-104 (Reference 5.19) is performed at three temperature plateaus, 350°F, 450°F, and approx 540°F. The Narrow Range and RVLIS Wide Range RTDs should have deviations of less than

+/-0.5°F and other Wide Range RTDs should have deviations of less than +/-1.0°F of the Narrow Range RCS Average Temperature. The acceptance criterion for operability of the Narrow Range and RVLIS Wide Range RTDs is +/-1.2°F. The acceptance criterion for operability of the other Wide Range RTDs is +/-1.7°F. All of the RCS Narrow Range RTDs and Wide Range RTDs with the exception of the RVLIS RTDs were found to have deviations of less than +/-0.5°F. The RVLIS RTDs TE-413A and TE-433 were found to exceed the +/-0.5°F criteria at the 540°F plateau; however, both remained well within the +/-1.2°F acceptance criteria for operability. At the 540°F plateau TE-413A was found to be 0.735°F and TE-433 was found to be 0.608°F. The RVLIS channels will be rescaled to reduce the deviations. (Reference 5.41 & 5.42)

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Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 4.10 Plant Performance Test The integrated power ascension program was coordinated by PLP-626 (Reference 5.1). An additional cycle specific procedure EPT-445 (Reference 5.12) was developed to collect key plant data during power ascension to verify acceptable operation of the plant as a result of the plant modifications performed during RFO-17 and the MUR uprate to the uprated power level (2948 MWt). In addition to the MUR, the following major modifications were completed during RF0-17:

Main Transformer Replacement (Reference 5.31)

Isophase Bus Duct Cooling System Upgrades (Reference 5.32)

HP Turbine Replacement (Reference 5.33)

Governor Valve Management Program (Reference 5.34)

Following RFO-17 during initial power ascension, key plant data was monitored at various appropriate power levels up to the original 2900 MWt where load was stabilized. The data was collected and compared to the previous 2900 MWt data to determine the impact of replacement of the HP Turbine. Power was then slowly increased to the MUR power level. No instability was observed in any of the plant systems during the power increase. Prior to and following the increase to MUR power level, system walkdowns were performed to identify any significant changes in piping vibrations and/or movement. None were observed.

Data was collected at the MUR power level to be used to establish a new baseline for plant parameters at uprated post modification conditions.

4.11 Main Transformer, Isophase Bus Duct, and AC Distribution Performance Test The main transformers and isophase bus duct cooling systems were replaced with larger capacity units to accommodate the power increase due to the MUR uprate. The larger capacity units will also accommodate the subsequent planned increase in generator output resulting from the replacement of the existing LP Turbines and Moisture Separator Reheaters (MSRs). Transformer and bus duct cooling operation was monitored during power ascension to MUR uprate conditions as part of the modification post installation testing. The operating data verified operation within the design conditions.

Flow balancing (Reference 5.39) and functional testing of affected alarm circuits (Reference 5.40) was performed as part of post installation testing on the Isophase Bus Duct system, leaving only bus duct temperature monitoring to be performed during power ascension (Reference 5.12).

Cooling system logic and alarm testing for the Main Transformers was performed as part of post installation testing, leaving only winding and oil temperature monitoring to be performed during power ascension. Current operations indicate that only three of the four cooling banks have been necessary with ambient temperatures above 100 °F.

To accommodate the physically larger main transformers minor changes to the fire protection spray headers was required. A full flow test was performed for each transformer to ensure the desired spray pattern was achieved. (Reference 5.37)

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Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 The following tables demonstrate the improved cooling capability of the modified Isophase Bus Duct Cooling and replacement Main Transformers at MUR operating conditions.

Isophase Bus Duct Parameter Pre RFO17 Post RFO17 Margin to Alarm (185 °F)* 22.9 °F 51.6 °F Peak Isophase Temperature 162.1 °F 133.4 °F Normal Service Water Temp 91.3 °F 93.2 °F Ambient Temperature 99.5 °F 102.2 °F Main Transformer Parameter Pre RFO17 Post RFO17 Margin to Alarm (110 °C)* 6.2 °C 39.2 °C Peak XFMR Winding Temp 103.8 °C 70.8 °C Ambient Temperature 99.5 °F 102.2 °F Note: Top oil temperature was not recorded for the old transformer.

• Alarm Setpoint The MUR power uprate had only a minimal affect on the station AC distribution system which is the source of power for the non-safety and safety-related buses. The 120 V bus loads are not power dependant and the MUR uprate did not impact the loads on the 480 V system. The increase in condensate, feedwater, and heater drain flows associated with the MUR resulted in a combined minimal load increase of 100 - 200 Hp on the 6.9 KV buses.

4.12 HP Turbine replacement and Governor Valve Management Program The original HP turbine rotor was replaced with a more efficient rotor design which combined with the MUR uprate resulted in a nominal increase in generator output of 29 MWe. The design of the replacement HP turbine rotor relocated the turbine first stage pressure instrument taps to outside the turbine which resulted in an increase in the nominal 0 - 100% power pressure range from 0 -

645 psig to 0 - 927 psig described previously in section 3.1. Although the range of the turbine first stage pressure operating band changed, the function and control of the first stage instruments continued to perform as originally designed once the original control and protection instruments were rescaled to the new operating band.

In addition to relocating the turbine first stage pressure taps, the design of the replacement HP turbine rotor resulted in the turbine governor valve control being changed from partial arc emission to full arc emission control. Following the re-programming of the turbine control valves for full arc emission, turbine generator control remained stable and turbine control and stop valve testing remained unchanged. The changes to the DEH system were verified to be acceptable in CM-C0004 (Reference 5.14), PM-I8001 (Reference 5.13), and SCP-006 (Reference 5.18).

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Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 5.0 References 5.1 PLP-626, Power Ascension Testing After a Refueling Outage 5.2 EST-724 "Shutdown and Control Rod Drop Test Using Computer" 5.3 EST-709 "Reactor Coolant System Flow Determination By Calorimetric" 5.4 EPT-008 "Intermediate and Power Range Detector Setpoint Determination" 5.5 EPT-009 "Intermediate Detector Setpoint Determination" 5.6 HNP-F/NFSA-0213, HNP Cycle 18 BOC NI Adjustment 5.7 EPT-026 "RMAS Setup and Operation" 5.8 EST-923 "Initial Criticality and Low Power Physics Testing" 5.9 PLP-106 "Core Operating Limits Report" 5.10 FMP-200 "Full Core Flux Map Review Checklist (POWERTRAX Version)"

5.11 EST-911 "Incore/Excore Detector Calibration Using POWERTRAX 5.12 EPT-445, Power Ascension Implementing Measurement Uncertainty Recapture (MUR)Power Uprate 5.13 PM-I8001 "DEH Computer Dynamic Simulation Test" 5.14 CM-C0004 "DEH Computer Reload and Restart" 5.15 ANSI 19.6.1 "Reload Startup Physics Test for Pressurized Water Reactors" 5.16 EPT-093 "Turbine First Stage Pressure Data" 5.17 EGR-NGGC-0026, System Walkdown Procedure 5.18 SCP-006 Throttle Valve and Governor Valve Calibration Procedure" 5.19 EST-104 Incore Thermocouple and RTD Cross Calibration Data Compilation 5.20 MST-I0044, Nuclear Instrumentation System Power Range N41 Calibration 5.21 MST-I0045, Nuclear Instrumentation System Power Range N42 Calibration 5.22 MST-I0046, Nuclear Instrumentation System Power Range N43 Calibration 5.23 MST-I0047, Nuclear Instrumentation System Power Range N44 Calibration 5.24 MST-I0048, Excore Nuclear Instrumentation System Intermediate Range N35 Calibration 5.25 MST-I0049, Excore Nuclear Instrumentation System Intermediate Range N36 Calibration 5.26 MST-I0067, Turbine First Stage Pressure Loop (P-0447) Calibration 5.27 MST-I0068, Turbine First Stage Pressure Loop (P-0446) Calibration 5.28 WCAP-17209-P, Rev. 2, Harris Nuclear Plant Measurement Uncertainty Recapture Power Uprate Engineering Report, April, 2012 5.29 EC 75840, HNP Cycle 18 Core Design and Safety Analysis, Revision 0.

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Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 5.30 POWERTRAX(HNP Cycle 18) 5.31 EC 74908, Main Transformer Replacement 5.32 EC 74909, Isophase Bus Duct Cooling System Upgrades.

5.33 EC 74907, HP Turbine replacement 5.34 EC 78849, DEH Modification Support for HP Turbine Replacement 5.35 EC 74914, Implement License Change for the MUR Uprate 5.36 MST-I0070, Calibration of NIS Power Range Overpower Trip High Range Bistables 5.37 WO 1905019-12, Spray Nozzle Verification for Main Transformers 5.38 EC 80467, Reconfigure Main Transformer Deluge System Nozzles/Detectors to support EC 74908, Main Transformer Replacement 5.39 EC74909-TAB-001, Isophase Bus Duct System Final Air Balancing Procedure 5.40 EC74909-FAC-001, Isophase Fan Air Cooling (FAC) Unit Functional Test 5.41 WO 2097501, Incorporate New Temperature Scaling in TE-01RC-0413ASBW 5.42 WO 2053341, 1PIC-01-0547, Update the Loop Scaling for TE-01RC-0433IW 5.43 HNP-I/INST-1010, Evaluation of RTS/ESFAS TECH SPEC Related Sepoints, Allowable Values, and Uncertainties.

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Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 Table 4.1.1 Control Rod Drop Times Control Banks Shutdown Banks Rod Core Time to Time to Rod Core Time to Time to Bottom of Bottom of Bank Location Dashpot Bank Location Dashpot Dashpot Dashpot Entry (sec) Entry (sec)

(sec) (sec)

CBA F2 1.54 2.13 SBA G3 - 1.99 B10 1.63 2.12 C9 - 1.98 K14 1.71 2.21 J13 - 1.97 P6 1.50 1.98 N7 - 1.95 K2 1.56 2.03 J3 - 1.96 B6 1.86 2.38 C7 - 2.00 F14 1.56 2.02 G13 - 1.94 P10 1.52 1.98 N9 - 1.95 CBB F4 1.51 1.97 SBB E5 - 1.91 D10 1.52 1.97 E11 - 1.93 K12 1.48 2.00 L11 - 1.89 M6 1.48 1.93 L5 - 1.89 K4 1.50 1.93 G7 - 1.86 D6 1.51 2.00 G9 - 1.94 F12 1.50 1.96 J9 - 1.87 M10 1.50 1.90 J7 - 1.90 CBC D4 1.51 1.98 SBC E3 - 1.98 D12 1.49 1.92 C11 - 2.02 M12 1.62 2.04 L13 - 2.08 M4 1.53 2.00 N5 - 2.00 H6 1.50 2.00 F8 1.48 1.90 H10 1.50 1.93 K8 1.48 1.92 CBD H2 1.50 1.96 B8 1.64 2.12 H14 1.51 1.99 P8 1.52 1.96 F6 1.52 1.96 F10 1.52 1.97 K10 1.52 1.96 K6 1.52 1.97 Page 16 of 30

Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 Table 4.3.1 Intermediate Range Detector Setpoint Determination Cycle Conditions N35 N36 Trip Rod Stop Trip Rod Stop 18 Predicted (initial startup) 7.983E-05 6.386E-05 6.876E-05 5.501E-05 (EPT-008) 18 Recalibrated (based on 8.060E-05 6.450E-05 7.540E-05 6.030E-05 actual Cycle 18 startup data)(EPT-009)

Table 4.3.2 Power Range Detector Calibration Values PR Detector Cycle 17 Currents1 Cycle 18 Currents2 N41 Top 188.3 153.8 Bottom 207.9 169.9 N42 Top 205.2 167.7 Bottom 232.3 189.8 N43 Top 230.0 188.0 Bottom 250.8 204.9 N44 Top 186.8 152.6 Bottom 221.4 180.9 1 Power Range data taken from applicable performance of EST-911. (Reference 5.11).

2 Power Range data taken from Cycle 18 performance of EPT-008. (Reference 5.4).

Page 17 of 30

Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 Figure 4.4.1 Flux Map 482 Measured vs. Calculated Powers (30%)

R P N M L K J H G F E D C B A l 0.263l 0.356l 0.261l 01 l 0.267l 0.372l 0.267l l -1.5l -4.5l -2.3l

______ ______l______l______l______l______ ______

l 0.308l 0.603l 1.034l 0.983l 1.025l 0.577l 0.302l Measured Power 02 l 0.309l 0.604l 1.035l 0.993l 1.043l 0.607l 0.311l Calculated Power l -0.3l -0.2l -0.1l -1.0l -1.8l -5.2l -3.0l Percent Difference

______l______l______l______l______l______l______l______l______

l 0.458l 1.092l 1.285l 1.251l 1.223l 1.254l 1.276l 1.089l 0.472l 03 l 0.476l 1.102l 1.288l 1.241l 1.212l 1.261l 1.295l 1.104l 0.476l l -3.9l -0.9l -0.2l 0.8l 0.9l -0.6l -1.5l -1.4l -0.8l

______l______l______l______l______l______l______l______l______l______l______

l 0.472l 1.082l 1.278l 1.262l 1.237l 1.239l 1.253l 1.260l 1.268l 1.090l 0.475l 04 l 0.476l 1.096l 1.287l 1.267l 1.236l 1.230l 1.254l 1.268l 1.282l 1.097l 0.476l l -0.8l -1.3l -0.7l -0.4l 0.1l 0.7l -0.1l -0.6l -1.1l -0.6l -0.2l

______l______l______l______l______l______l______l______l______l______l______l______l______

l 0.310l 1.098l 1.268l 1.279l 1.254l 1.098l 1.208l 1.111l 1.254l 1.286l 1.286l 1.102l 0.301l 05 l 0.310l 1.103l 1.281l 1.307l 1.270l 1.109l 1.202l 1.109l 1.262l 1.308l 1.288l 1.103l 0.310l l 0.0l -0.5l -1.0l -2.2l -1.3l -1.0l 0.5l 0.2l -0.6l -1.7l -0.2l -0.1l -3.0l l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.609l 1.298l 1.263l 1.242l 0.939l 1.159l 1.193l 1.162l 0.952l 1.270l 1.278l 1.298l 0.607l 06 l 0.606l 1.293l 1.267l 1.261l 0.955l 1.167l 1.175l 1.156l 0.955l 1.271l 1.268l 1.289l 0.604l l 0.5l 0.4l -0.3l -1.5l -1.7l -0.7l 1.5l 0.5l -0.3l -0.1l 0.8l 0.7l 0.5l

______l______l______l______l______l______l______l______l______l______l______l______l______l______l______

l 0.268l 1.051l 1.280l 1.262l 1.109l 1.146l 0.994l 1.083l 1.023l 1.177l 1.122l 1.264l 1.262l 1.047l 0.269l 07 l 0.267l 1.042l 1.259l 1.253l 1.109l 1.156l 1.017l 1.083l 1.018l 1.167l 1.110l 1.237l 1.242l 1.036l 0.267l l 0.4l 0.9l 1.6l 0.7l 0.0l -0.9l -2.3l 0.0l 0.5l 0.8l 1.1l 2.1l 1.6l 1.1l 0.7l l______l______l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.367l 0.994l 1.234l 1.244l 1.222l 1.175l 1.075l 0.998l 1.089l 1.194l 1.218l 1.251l 1.240l 0.998l 0.374l 08 l 0.371l 0.992l 1.211l 1.229l 1.202l 1.175l 1.083l 0.999l 1.083l 1.176l 1.203l 1.230l 1.212l 0.994l 0.372l l -1.1l 0.2l 1.9l 1.2l 1.6l 0.0l -0.7l -0.1l 0.6l 1.5l 1.2l 1.7l 2.3l 0.4l 0.5l l______l______l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.266l 1.037l 1.247l 1.238l 1.102l 1.160l 1.011l 1.082l 1.016l 1.141l 1.113l 1.265l 1.272l 1.044l 0.266l 09 l 0.266l 1.035l 1.240l 1.235l 1.109l 1.167l 1.018l 1.083l 1.018l 1.156l 1.110l 1.254l 1.261l 1.044l 0.268l l 0.0l 0.2l 0.6l 0.2l -0.6l -0.6l -0.7l -0.1l -0.2l -1.3l 0.3l 0.9l 0.9l 0.0l -0.8l l______l______l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.603l 1.281l 1.262l 1.259l 0.941l 1.141l 1.178l 1.167l 0.945l 1.262l 1.275l 1.296l 0.594l 10 l 0.604l 1.287l 1.267l 1.270l 0.955l 1.156l 1.175l 1.168l 0.955l 1.263l 1.269l 1.295l 0.607l l -0.2l -0.5l -0.4l -0.9l -1.5l -1.3l 0.3l -0.1l -1.1l -0.1l 0.5l 0.1l -2.2l l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.308l 1.096l 1.278l 1.290l 1.258l 1.118l 1.229l 1.116l 1.259l 1.306l 1.283l 1.102l 0.308l 11 l 0.309l 1.102l 1.287l 1.307l 1.262l 1.109l 1.203l 1.110l 1.271l 1.308l 1.282l 1.104l 0.311l l -0.3l -0.5l -0.7l -1.3l -0.3l 0.8l 2.1l 0.5l -1.0l -0.2l 0.1l -0.2l -1.0l l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.474l 1.090l 1.276l 1.275l 1.281l 1.251l 1.249l 1.272l 1.290l 1.096l 0.473l 12 l 0.476l 1.096l 1.281l 1.268l 1.254l 1.230l 1.237l 1.269l 1.289l 1.097l 0.477l l -0.4l -0.6l -0.4l 0.5l 2.1l 1.7l 1.0l 0.2l 0.1l -0.1l -0.8l l______l______l______l______l______l______l______l______l______l______l______l l 0.474l 1.100l 1.301l 1.276l 1.227l 1.256l 1.300l 1.109l 0.478l 13 l 0.476l 1.104l 1.295l 1.261l 1.212l 1.242l 1.289l 1.104l 0.477l l -0.4l -0.4l 0.5l 1.2l 1.2l 1.1l 0.8l 0.5l 0.2l l______l______l______l______l______l______l______l______l______l l 0.301l 0.608l 1.053l 0.999l 1.051l 0.612l 0.312l 14 l 0.310l 0.607l 1.044l 0.994l 1.036l 0.605l 0.310l l -3.0l 0.2l 0.9l 0.5l 1.4l 1.1l 0.6l l______l______l______l______l______l______l______l l 0.273l 0.376l 0.271l 15 l 0.267l 0.372l 0.267l l 2.2l 1.1l 1.5l l______l______l______l Page 18 of 30

Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 Figure 4.4.2 Flux Map 483 Measured vs. Calculated Powers (75%)

R P N M L K J H G F E D C B A l 0.287l 0.406l 0.287l 01 l 0.287l 0.406l 0.288l l 0.0l 0.0l -0.3l

______ ______l______l______l______l______ ______

l 0.311l 0.608l 1.053l 1.070l 1.058l 0.603l 0.311l Measured Power 02 l 0.313l 0.610l 1.054l 1.071l 1.061l 0.612l 0.314l Calculated Power l -0.6l -0.3l -0.1l -0.1l -0.3l -1.5l -1.0l Percent Difference

______l______l______l______l______l______l______l______l______

l 0.468l 1.060l 1.244l 1.228l 1.232l 1.246l 1.248l 1.062l 0.470l 03 l 0.472l 1.068l 1.249l 1.228l 1.215l 1.245l 1.256l 1.070l 0.472l l -0.9l -0.8l -0.4l 0.0l 1.4l 0.1l -0.6l -0.8l -0.4l

______l______l______l______l______l______l______l______l______l______l______

l 0.468l 1.048l 1.227l 1.228l 1.214l 1.218l 1.231l 1.228l 1.227l 1.055l 0.471l 04 l 0.471l 1.059l 1.240l 1.236l 1.217l 1.218l 1.234l 1.237l 1.236l 1.061l 0.473l l -0.6l -1.0l -1.1l -0.7l -0.2l 0.0l -0.2l -0.7l -0.7l -0.6l -0.4l

______l______l______l______l______l______l______l______l______l______l______l______l______

l 0.312l 1.060l 1.221l 1.253l 1.254l 1.111l 1.204l 1.116l 1.250l 1.267l 1.239l 1.068l 0.309l 05 l 0.313l 1.067l 1.234l 1.279l 1.268l 1.118l 1.201l 1.118l 1.262l 1.280l 1.242l 1.070l 0.313l l -0.3l -0.7l -1.1l -2.1l -1.1l -0.6l 0.2l -0.2l -1.0l -1.0l -0.2l -0.2l -1.3l l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.610l 1.250l 1.227l 1.239l 1.028l 1.193l 1.207l 1.184l 1.025l 1.265l 1.242l 1.256l 0.613l 06 l 0.611l 1.253l 1.235l 1.260l 1.042l 1.196l 1.192l 1.186l 1.043l 1.270l 1.238l 1.251l 0.610l l -0.2l -0.2l -0.7l -1.7l -1.4l -0.3l 1.2l -0.2l -1.8l -0.4l 0.3l 0.4l 0.5l

______l______l______l______l______l______l______l______l______l______l______l______l______l______l______

l 0.286l 1.060l 1.248l 1.235l 1.117l 1.181l 1.044l 1.109l 1.044l 1.195l 1.125l 1.238l 1.240l 1.062l 0.289l 07 l 0.287l 1.059l 1.243l 1.232l 1.117l 1.185l 1.050l 1.107l 1.050l 1.197l 1.119l 1.219l 1.229l 1.055l 0.287l l -0.3l 0.1l 0.4l 0.2l 0.0l -0.3l -0.6l 0.2l -0.6l -0.2l 0.5l 1.5l 0.9l 0.7l 0.7l l______l______l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.399l 1.069l 1.233l 1.229l 1.219l 1.195l 1.107l 1.028l 1.110l 1.203l 1.212l 1.232l 1.228l 1.074l 0.408l 08 l 0.405l 1.069l 1.213l 1.216l 1.200l 1.191l 1.107l 1.027l 1.108l 1.192l 1.202l 1.219l 1.216l 1.072l 0.406l l -1.5l 0.0l 1.6l 1.1l 1.6l 0.3l 0.0l 0.1l 0.2l 0.9l 0.8l 1.1l 1.0l 0.2l 0.5l l______l______l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.286l 1.054l 1.232l 1.223l 1.123l 1.195l 1.047l 1.109l 1.052l 1.185l 1.124l 1.243l 1.253l 1.064l 0.290l 09 l 0.287l 1.052l 1.226l 1.216l 1.118l 1.196l 1.050l 1.107l 1.050l 1.186l 1.119l 1.234l 1.246l 1.062l 0.288l l -0.3l 0.2l 0.5l 0.6l 0.4l -0.1l -0.3l 0.2l 0.2l -0.1l 0.4l 0.7l 0.6l 0.2l 0.7l l______l______l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.609l 1.244l 1.234l 1.264l 1.032l 1.171l 1.195l 1.196l 1.033l 1.264l 1.246l 1.261l 0.608l 10 l 0.609l 1.248l 1.236l 1.268l 1.042l 1.186l 1.192l 1.197l 1.043l 1.262l 1.238l 1.257l 0.612l l 0.0l -0.3l -0.2l -0.3l -1.0l -1.3l 0.3l -0.1l -1.0l 0.2l 0.6l 0.3l -0.7l l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.312l 1.063l 1.235l 1.267l 1.258l 1.124l 1.225l 1.122l 1.249l 1.283l 1.242l 1.073l 0.314l 11 l 0.312l 1.067l 1.240l 1.279l 1.261l 1.118l 1.202l 1.120l 1.270l 1.281l 1.237l 1.070l 0.314l l 0.0l -0.4l -0.4l -0.9l -0.2l 0.5l 1.9l 0.2l -1.7l 0.2l 0.4l 0.3l 0.0l l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.470l 1.056l 1.232l 1.241l 1.250l 1.233l 1.226l 1.238l 1.245l 1.065l 0.475l 12 l 0.472l 1.059l 1.235l 1.237l 1.234l 1.218l 1.219l 1.238l 1.243l 1.061l 0.473l l -0.4l -0.3l -0.2l 0.3l 1.3l 1.2l 0.6l 0.0l 0.2l 0.4l 0.4l l______l______l______l______l______l______l______l______l______l______l______l l 0.471l 1.067l 1.259l 1.254l 1.225l 1.238l 1.258l 1.074l 0.475l 13 l 0.472l 1.069l 1.255l 1.245l 1.216l 1.229l 1.251l 1.070l 0.473l l -0.2l -0.2l 0.3l 0.7l 0.7l 0.7l 0.6l 0.4l 0.4l l______l______l______l______l______l______l______l______l______l l 0.310l 0.614l 1.067l 1.074l 1.066l 0.616l 0.315l 14 l 0.314l 0.612l 1.062l 1.072l 1.055l 0.610l 0.313l l -1.3l 0.3l 0.5l 0.2l 1.0l 1.0l 0.6l l______l______l______l______l______l______l______l l 0.292l 0.409l 0.290l 15 l 0.288l 0.406l 0.287l l 1.4l 0.7l 1.0l l______l______l______l Page 19 of 30

Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 Figure 4.4.3 Flux Map 484 Measured vs. Calculated Powers (100%)

R P N M L K J H G F E D C B A l 0.306l 0.436l 0.306l 01 l 0.305l 0.436l 0.306l l 0.3l 0.0l 0.0l

______ ______l______l______l______l______ ______

l 0.314l 0.612l 1.063l 1.136l 1.065l 0.607l 0.314l Measured Power 02 l 0.316l 0.613l 1.063l 1.134l 1.069l 0.616l 0.317l Calculated Power l -0.6l -0.2l 0.0l 0.2l -0.4l -1.5l -1.0l Percent Difference

______l______l______l______l______l______l______l______l______

l 0.464l 1.029l 1.210l 1.217l 1.227l 1.229l 1.212l 1.031l 0.471l 03 l 0.468l 1.037l 1.215l 1.215l 1.217l 1.231l 1.221l 1.038l 0.469l l -0.9l -0.8l -0.4l 0.2l 0.8l -0.2l -0.7l -0.7l 0.4l

______l______l______l______l______l______l______l______l______l______l______

l 0.463l 1.015l 1.190l 1.205l 1.201l 1.214l 1.215l 1.201l 1.189l 1.024l 0.468l 04 l 0.468l 1.026l 1.202l 1.213l 1.203l 1.209l 1.218l 1.214l 1.199l 1.028l 0.469l l -1.1l -1.1l -1.0l -0.7l -0.2l 0.4l -0.2l -1.1l -0.8l -0.4l -0.2l

______l______l______l______l______l______l______l______l______l______l______l______l______

l 0.314l 1.025l 1.181l 1.233l 1.258l 1.121l 1.203l 1.125l 1.251l 1.246l 1.201l 1.038l 0.318l 05 l 0.316l 1.036l 1.196l 1.259l 1.270l 1.129l 1.201l 1.129l 1.264l 1.261l 1.204l 1.038l 0.316l l -0.6l -1.1l -1.3l -2.1l -1.0l -0.7l 0.2l -0.4l -1.0l -1.2l -0.2l 0.0l 0.6l l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.610l 1.208l 1.202l 1.252l 1.125l 1.219l 1.219l 1.209l 1.113l 1.265l 1.217l 1.222l 0.617l 06 l 0.614l 1.218l 1.211l 1.262l 1.131l 1.220l 1.204l 1.211l 1.133l 1.272l 1.215l 1.217l 0.614l l -0.7l -0.8l -0.7l -0.8l -0.5l -0.1l 1.2l -0.2l -1.8l -0.6l 0.2l 0.4l 0.5l

______l______l______l______l______l______l______l______l______l______l______l______l______l______l______

l 0.303l 1.060l 1.219l 1.213l 1.127l 1.208l 1.071l 1.128l 1.079l 1.220l 1.134l 1.222l 1.226l 1.071l 0.308l 07 l 0.305l 1.066l 1.228l 1.215l 1.127l 1.209l 1.076l 1.124l 1.077l 1.221l 1.130l 1.204l 1.216l 1.064l 0.306l l -0.7l -0.6l -0.7l -0.2l 0.0l -0.1l -0.5l 0.4l 0.2l -0.1l 0.4l 1.5l 0.8l 0.7l 0.6l l______l______l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.430l 1.129l 1.223l 1.213l 1.215l 1.207l 1.124l 1.051l 1.130l 1.215l 1.210l 1.221l 1.229l 1.143l 0.440l 08 l 0.435l 1.131l 1.214l 1.207l 1.199l 1.203l 1.124l 1.048l 1.124l 1.205l 1.201l 1.210l 1.218l 1.135l 0.436l l -1.2l -0.2l 0.7l 0.5l 1.3l 0.3l 0.0l 0.3l 0.5l 0.8l 0.7l 0.9l 0.9l 0.7l 0.9l l______l______l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.303l 1.057l 1.211l 1.202l 1.131l 1.220l 1.074l 1.127l 1.082l 1.214l 1.135l 1.227l 1.239l 1.076l 0.312l 09 l 0.305l 1.060l 1.213l 1.201l 1.128l 1.220l 1.076l 1.124l 1.077l 1.211l 1.129l 1.219l 1.231l 1.070l 0.306l l -0.7l -0.3l -0.2l 0.1l 0.3l 0.0l -0.2l 0.3l 0.5l 0.2l 0.5l 0.7l 0.6l 0.6l 1.9l l______l______l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.608l 1.202l 1.206l 1.266l 1.127l 1.199l 1.209l 1.226l 1.133l 1.269l 1.219l 1.226l 0.615l 10 l 0.612l 1.214l 1.212l 1.270l 1.132l 1.210l 1.205l 1.221l 1.133l 1.265l 1.214l 1.222l 0.616l l -0.7l -1.0l -0.5l -0.3l -0.4l -0.9l 0.3l 0.4l 0.0l 0.3l 0.4l 0.3l -0.2l l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.313l 1.028l 1.195l 1.249l 1.261l 1.133l 1.224l 1.136l 1.265l 1.266l 1.202l 1.042l 0.318l 11 l 0.315l 1.036l 1.202l 1.260l 1.263l 1.128l 1.201l 1.130l 1.272l 1.262l 1.199l 1.039l 0.317l l -0.6l -0.8l -0.6l -0.9l -0.2l 0.4l 1.9l 0.5l -0.6l 0.3l 0.2l 0.3l 0.3l l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.465l 1.022l 1.194l 1.214l 1.226l 1.222l 1.212l 1.216l 1.206l 1.025l 0.473l 12 l 0.468l 1.027l 1.197l 1.213l 1.218l 1.210l 1.204l 1.215l 1.205l 1.029l 0.469l l -0.6l -0.5l -0.3l 0.1l 0.7l 1.0l 0.7l 0.1l 0.1l -0.4l 0.8l l______l______l______l______l______l______l______l______l______l______l______l l 0.467l 1.037l 1.224l 1.238l 1.227l 1.224l 1.222l 1.040l 0.469l 13 l 0.468l 1.037l 1.220l 1.231l 1.218l 1.216l 1.217l 1.039l 0.469l l -0.2l 0.0l 0.3l 0.6l 0.7l 0.7l 0.4l 0.1l 0.0l l______l______l______l______l______l______l______l______l______l l 0.319l 0.619l 1.078l 1.144l 1.074l 0.618l 0.318l 14 l 0.317l 0.615l 1.069l 1.134l 1.064l 0.614l 0.316l l 0.6l 0.6l 0.8l 0.9l 0.9l 0.6l 0.6l l______l______l______l______l______l______l______l l 0.314l 0.441l 0.309l 15 l 0.306l 0.436l 0.306l l 2.5l 1.1l 1.0l l______l______l______l Page 20 of 30

Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 Table 4.5.1 Flux Map Summary1 Map # Burnup Date Time Power (%) CBD Boron (EFPD) (steps) (ppm) 482 0.22 6/09/2012 04:30:00 28.4 133 1875 483 0.63 6/10/2012 01:16:00 71.0 170 1664 484 3.55 6/13/2012 10:30:00 99.9 218 1420 Map # RMS Max FH Fraction to Max FQ Fraction to Axial Difference2 Limit, FH Limit, FQ Offset (%)

482 1.09% 1.612 0.776 2.552 0.529 -7.2 483 0.78% 1.560 0.853 2.353 0.693 -2.4 484 0.72% 1.515 0.913 2.160 0.895 -1.0 Map # Thimbles Thimbles Quadrant Power Tilt Ratio Used Required NW NE SW SE 482 45 38 0.996 1.000 1.000 1.004 483 42 38 0.996 1.000 1.001 1.004 484 43 38 0.995 1.000 1.000 1.005 1 Flux map summary data taken from respective INPAX runs [Reference 5.30]

2 RMS Difference = Measured Power - Calculated Power Page 21 of 30

Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 Table 4.6.1 Reactivity Computer Checkout Input Parameters to the Reactivity Computer1 Group 1

• 1 1 0.000218 0.000211 0.0128 2 0.001356 0.001315 0.0317 3 0.001231 0.001194 0.1205 4 0.002663 0.002583 0.3206 5 0.000976 0.000947 1.4025 6 0.000236 0.000229 3.8819 i 0.006680 0.006480 -----

Prompt Neutron Lifetime = 14.48 Importance Factor () = 0.97 Delayed Neutron Fraction (eff) = 0.006439 Positive Insertion Period Check2 Collection # time (sec) Period (sec) Calculated Measured  % Deviation Reactivity Reactivity 1 64.0 92.3 62.25 pcm 61.81 pcm -0.70 2 64.0 92.3 62.25 61.92 -0.52 3 65.0 93.7 61.51 61.44 -0.11 Average ----- ----- 62.00 61.73 -0.44 1 Reactivity computer inputs from Cycle 18 Powertrax [Reference 5.30].

2 Measured data from Cycle 18 (RFO17) performance of EST-923 [Reference 5.8].

Page 22 of 30

Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 Table 4.6.2 Low Power Physics Testing Results Summary Boron Endpoint (ppm) 1 Configuration Measured Predicted1 Difference Acceptance HZP, ARO 2132.2 2148 15.8 +/- 50 Control Rod Worths (pcm)

Bank Measured1 Predicted1 Difference Acceptance pcm  % Dev2 pcm  % Dev2 CBB 1288.58 1286 2.58 0.20 +/- 10 SBA 1094.45 1041 53.45 5.13 +/- 15 SBB 995.64 1004.93 -9.29 -0.92 +/- 15 SBC 259.01 261.14 -2.13 -0.82 +/- 100 CBA 291.43 335.48 -44.05 -13.13 +/- 100 CBC 831.84 856.5 -24.66 -2.88 +/- 15 CBD 1048.79 1051.11 -2.32 -0.22 +/- 15 M

Sum of Worths 5809.74 5836.16 /P = 0.9955 0.9 M/P 1.1 HZP Temperature Coefficient (pcm/oF)

RCS @ 2123 ppm Measured1 Predicted1 Difference Acceptance ITC -3.292 -3.887 0.595 Difference +/- 2 MTC -1.792 -2.387 0.595 Measured +5 1 Measured and predicted data obtained from Cycle 18 (RFO17) performance of EST-923 [Reference 5.8].

2  % Deviation = [(Measured - Predicted) / Predicted]

• 100 Page 23 of 30

Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 Figure 4.7.1 Integral Worth of the Reference Bank 1300 1200 1100 1000 900 800 Integral Rod Worth (pcm) 700 600 500 400 300 200 Measured 100 Predicted 0

0 25 50 75 100 125 150 175 200 225 Reference Bank Position (steps)

Page 24 of 30

Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 Figure 4.7.2 Differential Worth of the Reference Bank 10 9

8 7

Differential Rod Worth (pcm) 6 5

4 3

2 1 Measured Predicted 0

0 25 50 75 100 125 150 175 200 225 Reference Bank Position (steps)

Page 25 of 30

Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 Table 4.7.3 - FSAR Chapter 14 Tests Heat Tracing and Freeze Not impacted by MUR, system performance is monitored during routine Protection operation.

Main, Auxiliary and Start-up Minimal impact on system from MUR, system performance discussed in Transformer sections 4.11 6.9 kv Switchgear Minimal impact on system from MUR, system performance discussed in sections 4.11.

480 VAC Distribution Not impacted by MUR, system performance is monitored during routine operation.

120 V ESF Uninterruptible Not impacted by MUR, system performance is monitored during routine AC System operation.

Class 1E DC System Not impacted by MUR, system performance is monitored during routine operation.

Normal Emergency AC/DC Not impacted by MUR, system performance is monitored during routine Lighting System operation.

Communications System Not impacted by MUR, system performance is monitored during routine operation.

Annunciator System Not impacted by MUR, system performance is monitored during routine operation, maintenance, and surveillance tests.

Reactor Protection System Minimal impact on system from MUR, system performance discussed in Engineered Safety Features section 3.1.

Actuation Logic Reactor Protection System No impact on system from MUR,system performance discussed in Engineered Safety Features section 3.1.

Actuation Response Time Test Piping Vibration Minimal impact on system from MUR, system performance discussed in section 3.2.

Metal Impact Monitoring Not impacted by MUR, system performance is monitored during routine operation.

Radiation Monitoring System Not impacted by MUR, system performance is monitored during routine operation.

Excore Nuclear Minimal impact on system from MUR, system performance discussed in Instrumentation section 3.1 and 4.3.

(NIS)

Emergency Diesel Not impacted by MUR, system performance is monitored during routine operation and surveillance tests.

Fire Protection System Minimal impact on system from MUR, system performance discussed in section 4.11.

Normal Service Water Not impacted by MUR, system performance is monitored during routine operation.

Emergency Service Water Not impacted by MUR, system performance monitored during routine operation and surveillance tests.

Compressed and Instrument Not impacted by MUR, system performance is monitored during routine Air Systems operation.

Page 26 of 30

Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 Reactor Coolant System Not impacted by MUR, system performance is monitored during routine Hydrostatic Test operation and surveillance tests.

RTD/TC Cross Calibration Minimal impact on system from MUR, system performance discussed in Test section.

Pressurizer Relief Tank (PRT) System operation was reviewed and determined to be acceptable for Test MUR by analytical methods.

Safety Injection System Not impacted by MUR, system performance is monitored during routine Performance Test operation and surveillance tests.

High -Head Safety Injection Not impacted by MUR, system performance is monitored during routine System Check Valve Test startup and surveillance tests.

Safety Injection (SI) Not impacted by MUR, system performance is monitored during routine Accumulator Test operation startup and surveillance tests.

Residual Heat Removal System operation was reviewed and determined to be acceptable by System Cold Test analytical methods. Not impacted by MUR, system performance is monitored during routine startup and surveillance tests.

Residual Heat Removal System operation was reviewed and determined to be acceptable by System Hot Test analytical methods. Not impacted by MUR, system performance is monitored during routine startup and surveillance test.

Containment Spray System System operation was reviewed and determined to be acceptable by Test analytical methods.

Chemical and Volume Not impacted by MUR, system performance is monitored during routine Control Cold Test operation and surveillance tests.

Chemical and Volume System operation was reviewed and determined to be acceptable for Control Hot Test MUR by analytical methods. System performance is monitored during routine operation and surveillance tests.

Auxiliary Feedwater System Not impacted by MUR, system performance is monitored during routine Test operation and surveillance tests.

Fuel Handling Equipment Not impacted by MUR, system performance is monitored during fuel System Test transfers and surveillance tests.

Fuel Pool Cooling and Not impacted by MUR, system performance is monitored during normal Cleanup System Test operation.

Component Cooling Water Not impacted by MUR, system performance is monitored during normal operation.

Gaseous Waste Processing Not impacted by MUR, system performance is monitored during routine System Test operation and surveillance tests. System operation was reviewed and determined to be acceptable by analytical methods.

Solid Waste Processing Test Not impacted by MUR, system performance is monitored during routine operation.

Liquid Waste Processing Not impacted by MUR, system performance is monitored during routine System Test operation.

Containment Isolation Test Not impacted by MUR, system performance is monitored during routine startup and surveillance tests.

Containment Integrated Leak Not impacted by MUR. A scheduled Integrated Leak Rate Test was Rate performed and completed satisfactory.

Test and Structural Integrity Test Reactor Coolant System Hot Not impacted by MUR, system performance is monitored during routine Functional Test operation. System operation was reviewed and determined to be acceptable by analytical methods.

Page 27 of 30

Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 Piping Thermal Expansion Minimal impact on system from MUR, system performance discussed in and Dynamic Effects Test section 3.2.

Pressurizer Pressure and Not impacted by MUR, system performance is monitored during routine Level Control Test operation.

Main Steam System Test Not impacted by MUR, system performance is monitored during routine operation.

Feedwater System Test Not impacted by MUR, system performance is monitored during routine operation.

Condensate System Test Not impacted by MUR, system performance is monitored during routine operation.

Turbine Generator Test Not impacted by MUR. Turbine Testing described in section 4.12.

Generator performance is monitored during routine operation.

Circulating Water System Not impacted by MUR, system performance is monitored during routine Test operation.

Condenser Vacuum and Not impacted by MUR, system performance is monitored during routine Condensate Makeup System operation.

Waste Processing Computer Not impacted by MUR, system performance is monitored during routine Test operation.

Containment Ventilation and Not impacted by MUR, system performance is monitored during routine Cooling, Primary Shield and startup and surveillance tests.

Reactor Supports Cooling System Test Plant HVAC Test Not impacted by MUR, system performance is monitored during routine operation.

Engineered Safety Features System operation was reviewed and determined to be acceptable by Integrated Test testing described in sections 3.1.

Process Computer Test Not impacted by MUR, system performance is monitored during routine operation.

Boron Recycle Test Not impacted by MUR, system performance is monitored during routine operation.

Refueling Water Storage System operation was reviewed and determined to be acceptable by Tank Test analytical methods.

Primary Makeup Water Not impacted by MUR, system performance is monitored during routine System Test operation.

Rod Control System Test Not impacted by MUR, system performance is monitored during routine operation.

Passive Safety Injection Not impacted by MUR. System performance is monitored during System Check Valve Test routine startup and surveillance tests Containment Recirculation System operation was reviewed and determined to be acceptable for Sump Test MUR by analytical methods.

Containment Vacuum Relief System operation was reviewed and determined to be acceptable for Test MUR by analytical methods.

Combustible Gas Control System operation was reviewed and determined to be acceptable for System In Containment Test MUR by analytical methods.

Gross Failed Fuel Detection System operation was reviewed and determined to be acceptable for System Test MUR by analytical methods.

Essential Services Chilled Not impacted by MUR, system performance is monitored during routine Water System Test operation.

Page 28 of 30

Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 Stud Tensioner Hoist Load Not impacted by MUR, system performance is monitored during routine Test operation.

Polar Crane Test Summary Not impacted by MUR, system performance is monitored during routine operation.

Feedwater Heater Drain, System operation was reviewed and determined to be acceptable for Level and Bypass Control MUR by analytical methods. System performance was monitored during Systems Test routine operation.

Seismic Instrumentation Test Not impacted by MUR, system performance is monitored during routine operation.

Extraction Steam System Test System operation was reviewed and determined to be acceptable for MUR by analytical methods. System performance was monitored during routine operation.

Primary Sampling System Not impacted by MUR, system performance is monitored during routine Test operation.

Secondary Sampling System Not impacted by MUR, system performance is monitored during routine Test operation.

Loss of Instrument Air Test System operation was reviewed and determined to be acceptable for MUR by analytical methods.

Containment Building Hot Not impacted by MUR, system performance is monitored during routine Penetration Test operation.

Simulated Loss of On-Site System operation was reviewed and determined to be acceptable by Power Test analytical methods.

AC Distribution System System operation was reviewed and determined to be acceptable for Optimum Operating Voltage MUR by analytical methods. System performance was monitored during Test routine operation.

Auxiliary Feedwater Turbine System operation was reviewed and determined to be acceptable For Pump Two-Hour Run Test MUR by analytical methods.

Power Ascension Test Plant system operation was monitored and reviewed during power ascension. Refer to section 4.10.

Moveable Incore Detector Not impacted by MUR, system performance is monitored during routine Test startup and surveillance tests.

Rod Control and Position Not impacted by MUR, system performance is monitored during routine Indication System Test startup and surveillance tests.

Rod Drive Mechanism Minimal impact on system from MUR, system performance discussed in Timing Test section 4.1.

Rod Drop Time Measurement Minimal impact on system from MUR, system performance discussed in Test section 4.1.

Reactor Coolant System Flow Minimal impact on system from MUR, system performance discussed in Measurement Test section 4.2.

Reactor Coolant System Flow System operation was reviewed and determined to be acceptable by Coastdown Test analytical methods.

Calibration of Nuclear Minimal impact on system from MUR, system performance discussed in Instrumentation Test section 4.3.

Rod Control System Test System operation was reviewed and determined to be acceptable by analytical methods.

Flux Distribution Minimal impact on system from MUR, system performance discussed in Measurement Test section 4.4.

Core Performance Test Minimal impact on system from MUR, system performance discussed in section 4.5.

Page 29 of 30

Harris Nuclear Plant Unit 1, Cycle 18 Startup Test Report Revision 0 Power Coefficient Minimal impact on system from MUR, system performance discussed in Measurement Test section 4.6.

Control Rod Reactivity Worth Minimal impact on system from MUR, system performance discussed in Test section 4.7.

Boron Reactivity Worth Test Minimal impact on system from MUR, system performance discussed in section 4.8.

Automatic Rod Control Test System operation was reviewed and determined to be acceptable by analytical methods. System performance monitored during routine ops.

Steam Generator Moisture System operation was reviewed and determined to be acceptable for Carryover Test MUR by analytical methods.

Load Swing Test System operation was reviewed and determined to be acceptable for MUR by analytical methods.

Large Load Reduction From System operation was reviewed and determined to be acceptable for 75 Percent Power Test MUR by analytical methods.

Turbine Trip From 100 System operation was reviewed and determined to be acceptable for Percent Power Test MUR by analytical methods.

Remote Shutdown Test System operation was reviewed and determined to be acceptable for MUR by analytical methods.

Loss of Offsite Power Test System operation was reviewed and determined to be acceptable for MUR by analytical methods.

Pressurizer Heaters and Spray System operation was reviewed and determined to be acceptable for Valves Capability Test MUR by analytical methods.

Gross Failed Fuel Detection System operation was reviewed and determined to be acceptable for System Test MUR by analytical methods.

Pressurizer Continuous Spray Not impacted by MUR, system performance is monitored during routine Flow Verification Test operation.

Reactor Coolant System Not impacted by MUR, system performance is monitored during routine Leakrate Test operation and surveillance.

Natural Circulation Test Not impacted by MUR, system performance is monitored during routine Summary operation and surveillance.

Main Steam and Feedwater System operation was reviewed and determined to be acceptable for Systems Test MUR by analytical methods. System operation was monitored and reviewed during routine operation.

Shield Survey Test System operation was reviewed and determined to be acceptable for MUR by analytical methods. System operation was monitored and reviewed during routine operation.

Loss of Feedwater System operation was reviewed and determined to be acceptable for Heater(s) Test MUR by analytical methods.

Main Steam Isolation Valve Not impacted by MUR, system performance is monitored during routine Test startup and surveillance tests.

Steam Generator Test for System operation was reviewed and determined to be acceptable for Condensation Water Hammer MUR by analytical methods.

Steam Turbine-Driven and System operation was reviewed and determined to be acceptable for Motor-Driven Auxiliary FW MUR by analytical methods.

Pumps Endurance Test Resistance Temperature Test is no longer applicable with current RTD configuration Detector (RTD) Bypass Flow VerificationTest Page 30 of 30