HNP-15-065, Submits Cycle 20 Startup Test Report

From kanterella
Jump to navigation Jump to search
Submits Cycle 20 Startup Test Report
ML15217A565
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 08/05/2015
From: Brewer H
Duke Energy Progress
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-15-065
Download: ML15217A565 (31)
v • d • e


Text

a'8.(

H. Duncan Brewer Director, Nuclear Organizational Effectiveness ENERGYe Harris Nuclear Plant 5413 Shearon Harris Road New Hill NC 27562-9300 919.362.2000 August5,2015 Serial: HNP-15-065 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant (HNP), Unit 1 Docket No. 5HQHZHGLicense No. NPF-63

Subject:

&\FOHStartup Test Report Ladies and Gentlemen:

In accordance with 7HFKQLFDOSpecification 6.9.1.1, Duke Energy Progress, Inc. (Duke Energy) submits the HQFORVHG&\FOHStartup Test Report for the Shearon Harris Nuclear Plant, Unit 1.

The report is required IROORZLQJLQVWDOODWLRQof IXHOthat has a different design or has been manufactured by a different fuel VXSSOLHU

This document contains no regulatory commitments.

Please refer any questions regarding this submittal to John Caves at (919) 362-2406.

H. Duncan Brewer

Enclosure:

&\FOHStartup Test Report cc: Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Ms. M. %DULOODV NRC Project Manager, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II

HNP-15-065 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400 / RENEWED LICENSE NO. NPF-63 Enclosure Cycle 20 Startup Test Report (30 pages including cover)

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report July 30, 2015 DUKE ENERGY PROGRESS, INC.

Page 1 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 Table of Contents Page 1.0 Introduction ................................................................................................................ 5 1.1 General ......................................................................................................................... 5 1.2 Cycle Description......................................................................................................... 6 2.0 Summary ..................................................................................................................... 7 3.0 Component & Initial Operation Test Summaries .................................................. 8 3.1 Fuel Handling Equipment System Test ....................................................................... 8 4.0 Operational and Power Ascension Test Summaries .......................................... 9 4.1 Reactor Coolant System Flow Measurement ............................................................... 9 4.2 Calibration of Nuclear Instrumentation Test ............................................................... 9 4.3 Flux Distribution Measurement Test ......................................................................... 10 4.4 Core Performance Test .............................................................................................. 11 4.5 Power Coefficient Measurement Test ........................................................................ 11 4.6 Control Rod Reactivity Worth Test ........................................................................... 12 4.7 Boron Endpoint Measurement - All Rods Out Test................................................... 12 5.0 References ............................................................................................................. 13 Page 3 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 List of Tables and Figures Page Figure 1.2.1 Harris Cycle 20 Full Core Loading Pattern ................................................... 14 Table 4.2.1 Intermediate Range Detector Set point Determination ................................. 15 Table 4.2.2 Power Range Detector Calibration Values ................................................... 15 Figure 4.3.1 Flux Map 521 Measured vs. Calculated Powers (30%) .............................. 16 Figure 4.3.2 Flux Map 522 Measured vs. Calculated Powers (75%) .............................. 17 Figure 4.3.3 Flux Map 523 Measured vs. Calculated Powers (100%) ............................. 18 Table 4.4.1 Flux Map Summary ..................................................................................... 19 Table 4.5.1 Reactivity Computer Checkout .................................................................... 20 Table 4.5.2 Low Power Physics Test Results Summary Endpoint, Control Rod Worth, and HZP Temperature Coefficient.................................................................................................... 21 Figure 4.6.1 Integral Worth of the Reference Bank ......................................................... 22 Figure 4.6.2 Differential Worth of the Reference Bank ................................................... 23 Table 4.6.3 FSAR Chapter 14 Tests ............................................................................... 24 Page 4 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 1.0 Introduction 1.1 General This startup report documents test results for Harris Nuclear Plant Unit 1, Cycle 20 and the introduction of a Lead Test Assembly (LTA) program featuring fuel of a different design. EC 95161 (Reference 5.1) implements the Cycle 20 core design, which contains 8 LTAs of the AREVA GAIA mechanical design. An evaluation was performed in EC 98982 (Reference 5.2) to validate that receipt, storage, and handling of the GAIA LTAs are acceptable with current site equipment and procedures.

The GAIA fuel design is similar to the resident AREVA Advanced HTP (High Thermal Performance) fuel design in form, function, and material. However, the GAIA LTA is differentiated from the AREVA Advanced HTP assembly by several key design features:

  • The GAIA structural spacer grids feature a new mixing vane design for improved thermal hydraulic performance. Fuel rod stability is based upon the HTP spacer grid spring line contact with springs located at the four corners of each cell. The grids are fabricated with the M5 alloy, which has been used as cladding material for two previous HNP fuel regions.
  • The GAIA assembly contains three Intermediate GAIA Mixers (IGMs) based on a proven mid span mixing grid design to further augment thermal hydraulic performance. The IGMs are also fabricated with the M5 alloy.
  • The GAIA assembly features the GRIPTM bottom nozzle assembly for maximum filtering efficiency and serviceability, as well as a reconstitutable top nozzle, which is typical of the nozzles used on Advanced HTP 17x17 fuel. The GRIPTM bottom nozzle is a combination of AREVA FUELGUARD technology, used in the current HTP product, and TRAPPER technology, which provides a low p.
  • The GAIA guide and instrumentation tubes are fabricated from the Q12TM quaternary alloy.

This alloy is a variation on the M5 alloy, differing primarily by the presence of small quantities of tin and iron in Q12TM. The tin improves resistance to thermal creep, and iron is key to maintaining excellent corrosion performance.

  • Small differences in the fuel pellet, fuel rod, fuel assembly, and guide/instrument tube dimensions.

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 5.3) was performed. Plant power ascension data demonstrates that HNP core monitoring systems can safely and accurately measure core behavior following implementation of the LTA program.

Page 5 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 1.2 Cycle Description The Cycle 20 core consists of 56 fresh AREVA (Advanced HTP) assemblies, along with 93 previously irradiated HTP assemblies. Additionally, Cycle 20 introduces 8 fresh LTAs, all of the AREVA GAIA mechanical design. The specifics for the core reload design are presented in the Engineering Change package for the Cycle 20 reload (Reference 5.1).

The Cycle 20 full core loading pattern (Reference 5.15) is shown in Figure 1.2.1, with the GAIA LTAs displayed by fresh fuel index ZA7. The GAIA LTAs are incorporated into the core loading pattern such that they remain non-limiting with regard to power production and peaking during normal operation and transients. Additionally, the GAIA LTAs were restricted from core locations in which Rod Cluster Control Assemblies (RCCAs) are also located.

Page 6 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 2.0 Summary Safe operation with the LTAs is supported by evaluation of the core loading pattern such that it will operate safely within the bounds defined in Technical Specifications, and that installed safety systems and procedures remain effective at mitigating the consequences of events and accidents described in Chapter 15 of the FSAR. The reload safety evaluation, as documented by the reload Engineering Change package (Reference 5.1), validates safe operation of the Cycle 20 loading pattern and, by extension, the LTAs within the loading pattern.

Monitoring the various core parameters and responses during low power physics testing and power ascension verified there were no unanticipated changes in reactor physics or power distribution with respect to the designed core, that the core can operate within design limits, and that systems available for reactivity control and core monitoring are not impacted.

Page 7 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 3.0 Component & Initial Operation Test Summaries 3.1 Fuel Handling Equipment System Test EC 98982 (Reference 5.2) contains an evaluation validating that receipt, storage, and handling of the GAIA LTAs is acceptable with current site equipment and procedures. The LTA fuel assembly to handling tool/gripper interfaces were verified to be acceptable, dimensionally, and a functional test with the new-fuel tool and a GAIA top nozzle was completed prior to manufacture and shipment.

Movement of the GAIA LTAs to the reactor vessel during the refueling outage was completed without issues.

Page 8 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 4.0 Operational and Power Ascension Test Summaries 4.1 Reactor Coolant System Flow Measurement Test The GAIA LTAs were evaluated in Reference 5.1 with respect to influence on core pressure drop, and were not expected to impact RCS flow significantly. Reactor coolant system flow was measured using EST-709 (Reference 5.5). The HNP accident analyses are based on the most limiting RCS flow values (minimum or maximum). The Cycle 20 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 Technical Specification Minimum1 299,9982 Cycle 20 Measured Flow per EST-709 302,827 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 5.5).

4.2 Calibration of Nuclear Instrumentation Test The Intermediate Range (IR) and Power Range (PR) detectors were adjusted prior to initial Cycle 20 startup per procedure EPT-008 [Reference 5.7]. The adjustments account for changes in instrumentation response due to changes in loading pattern design and core leakage from the previous cycle (19) to the new cycle (20). The methodology and calculations to determine the adjustment factor (also referred to as the R-factor) and any calculation biases are detailed in calculation HNP-F/NFSA-0252 [Reference 5.8]. The GAIA LTAs are modeled explicitly in the physics code used to model the core power distribution, and therefore, any impact to the calibration is implicit in the supplied adjustment factors.

The Cycle 20 predicted Intermediate Range setpoints for the N35 and N36 detectors are compared to the actual calibrated IR setpoint installed for Cycle 19 by procedure EPT-009 [Reference 5.6].

This data is included in Table 4.2.1.

The Cycle 20 Power Range (PR) 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 19 using procedure EST-911 [Reference 5.9]. This data is included in Table 4.2.2.

Page 9 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 4.3 Flux Distribution Measurement Test Testing of the Movable Incore Detector System was effectively accomplished by exercising the system for performance of core flux mapping and power distribution measurement.

Core power distributions for Cycle 20 are measured by processing moveable detector traces with the INPAX-W code, which is a module of the POWERTRAX core monitoring system. The INPAX-W code uses the physics code PRISM to supply calculated reaction rates, assembly power distributions, and local peaking factors. The GAIA LTAs are modeled explicitly in PRISM, allowing for best-estimate calculated reaction rates for signal-to-power conversion in INPAX-W.

Power distribution maps for the power ascension flux maps are included as Figures 4.3.1 through 4.3.3. It should be noted that the GAIA LTAs are in the following core locations, per the core loading pattern shown in Figure 1.2.1:

  • F-13, C-10, C-06, F-03, K-03, N-06, N-10, K-13 Two of these locations (F-13 and N-10) are directly measurable by the Movable Incore Detector system.

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

Map 521 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 -5.9% (location R08), as shown in Figure 4.3.1.

Map 523 taken near 100% power exhibited a limiting assembly (location D07) enthalpy rise hot channel factor (FH) of 1.536, including uncertainties, or 0.925 fraction of limit. The following flux maps passed acceptance criteria contained in FMP-200 (Reference 5.10).

  • Map 521 @ 30% (verifying that the core was loaded as designed)
  • Map 522 @ 75%
  • Map 523 @ 100%

The Core Operating Limits Report (COLR, PLP-106) [Reference 5.11] requires a minimum of 38 measured traces for all flux maps.

Page 10 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 4.4 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 522 @ 75%
  • Map 523 @ 100%

All flux maps allowed full power operation with no additional intermediate power level maps other than those required per PLP-626 [Reference 5.12]. Table 4.4.1 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.

4.5 Power Coefficient Measurement Test The RMAS reactivity computer is set up before LPPT using procedure EPT-026 [Reference 5.13].

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 4.5.1.

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 4.5.1.

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 accounted for as a calculated predicted value.

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

(Reference 5.14). EST-923 covers:

  • Initial criticality
  • Reactivity computer period checks
  • Test band determination (point of adding heat determination)
  • ARO boron endpoint Page 11 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0

  • Temperature coefficient determination

Results for Cycle 20 LPPT and the corresponding acceptance criteria are listed in Table 4.5.2.

Table 4.5.2 also contains test results from sections 4.6 and 4.7.

4.6 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 20, control bank B) was measured via boron dilution. 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 20 LPPT and the corresponding acceptance criteria are listed in Table 4.5.2.

Figures 4.6.1 and 4.6.2 graphically compare the predicted and measured integral and differential rod worths for the reference bank.

4.7 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 20 Low Power Physics Testing (LPPT) and the corresponding acceptance criteria are listed in Table 4.5.2.

Page 12 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 5.0 References 5.1 EC 95161, Revision 1, HNP Cycle 20 Core Design and Safety Analysis.

5.2 EC 98982, Revision 0, GAIA Lead Assembly Fuel Receipt (H1C20).

5.3 ANSI 19.6.1 "Reload Startup Physics Test for Pressurized Water Reactors."

5.4 NOT USED 5.5 EST-709 "Reactor Coolant System Flow Determination By Calorimetric."

5.6 EPT-009 Intermediate Range Detector Setpoint Verification.

5.7 EPT-008 "Intermediate and Power Range Detector Setpoint Determination."

5.8 HNP-F/NFSA-0252, HNP Cycle 20 BOC NI Adjustment.

5.9 EST-911 "Incore/Excore Detector Calibration Using POWERTRAX.

5.10 FMP-200 "Full Core Flux Map Review Checklist (POWERTRAX Version)."

5.11 PLP-106 "Technical Specification Equipment List Program and Core Operating Limits Report."

5.12 PLP-626, Power Ascension Testing After a Refueling Outage.

5.13 EPT-026 "RMAS Setup and Operation."

5.14 EST-923 "Initial Criticality and Low Power Physics Testing."

5.15 HNP-F/NFSA-0243, HNP Cycle 20 Loading Pattern and Core Models.

5.16 POWERTRAX (HNP Cycle 20)

Page 13 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 Figure 1.2.1 Harris Cycle 20 Full Core Loading Pattern R P N M L K J H G F E D C B A Y12 Y62 Y13 1 F-14 D-12 K-14 1 Y65 Z27 ZA44 ZA38 ZA43 Z24 Y72 2 J-13 F-05 ---- ---- ---- K-05 G-13 2

--- --- ZA5 ZA5 ZA5 --- ---

Y25 ZA52 ZA60 Z39 Z62 Z44 ZA59 ZA51 Y32 3 D-13 ---- ---- B-07 H-14 P-07 ---- ---- M-13 3

--- ZA6 ZA7 --- --- --- ZA7 ZA6 ---

Y26 Z46 ZA32 Z54 ZA24 Z18 ZA23 Z61 ZA31 Z49 Y31 4 C-12 E-13 ---- F-13 ---- D-09 ---- K-13 ---- N-11 N-12 4

--- --- ZA4 --- ZA3 --- ZA3 --- ZA4 --- ---

Y66 ZA53 ZA33 Z16 ZA16 Z09 ZA02 Z02 ZA15 Z15 ZA30 ZA50 Y71 5 C-07 ---- ---- J-04 ---- J-10 ---- G-10 ---- D-07 ---- ---- N-07 5

--- ZA6 ZA4 --- ZA3 --- ZA1 --- ZA3 --- ZA4 ZA6 ---

Z25 ZA61 Z58 ZA17 Z13 ZA08 Z34 ZA07 Z12 ZA14 Z57 ZA58 Z26 6 L-10 ---- C-10 ---- L-08 ---- D-11 ---- H-05 ---- N-10 ---- E-10 6

--- ZA7 --- ZA3 --- ZA2 --- ZA2 --- ZA3 --- ZA7 ---

Y15 ZA45 Z45 ZA25 Z03 ZA09 Z52 Z31 Z51 ZA06 Z08 ZA22 Z38 ZA42 Y10 7 B-10 ---- J-14 ---- F-07 ---- N-05 D-05 E-03 ---- K-07 ---- G-14 ---- P-10 7

--- ZA5 --- ZA3 --- ZA2 --- --- --- ZA2 --- ZA3 --- ZA5 ---

Y64 ZA39 Z63 Z19 ZA03 Z35 Z32 Z01 Z30 Z37 ZA01 Z21 Z65 ZA37 Y60 8 D-04 ---- B-08 G-04 ---- E-04 L-04 H-08 E-12 L-12 ---- J-12 P-08 ---- M-12 8

--- ZA5 --- --- ZA1 --- --- --- --- --- ZA1 --- --- ZA5 ---

Y14 ZA46 Z40 ZA26 Z06 ZA10 Z53 Z33 Z50 ZA05 Z05 ZA21 Z43 ZA41 Y11 9 B-06 ---- J-02 ---- F-09 ---- L-13 M-11 C-11 ---- K-09 ---- G-02 ---- P-06 9

--- ZA5 --- ZA3 --- ZA2 --- --- --- ZA2 --- ZA3 --- ZA5 ---

Z28 ZA62 Z55 ZA18 Z10 ZA11 Z36 ZA12 Z11 ZA13 Z60 ZA57 Z23 10 L-06 ---- C-06 ---- H-11 ---- M-05 ---- E-08 ---- N-06 ---- E-06 10

--- ZA7 --- ZA3 --- ZA2 --- ZA2 --- ZA3 --- ZA7 ---

Y67 ZA54 ZA34 Z17 ZA19 Z04 ZA04 Z07 ZA20 Z14 ZA29 ZA49 Y70 11 C-09 ---- ---- M-09 ---- J-06 ---- G-06 ---- G-12 ---- ---- N-09 11

--- ZA6 ZA4 --- ZA3 --- ZA1 --- ZA3 --- ZA4 ZA6 ---

Y27 Z47 ZA35 Z59 ZA27 Z20 ZA28 Z56 ZA36 Z48 Y30 12 C-04 C-05 ---- F-03 ---- M-07 ---- K-03 ---- L-03 N-04 12

--- --- ZA4 --- ZA3 --- ZA3 --- ZA4 --- ---

Y28 ZA55 ZA63 Z42 Z64 Z41 ZA64 ZA56 Y29 13 D-03 ---- ---- B-09 H-02 P-09 ---- ---- M-03 13

--- ZA6 ZA7 --- --- --- ZA7 ZA6 ---

Y68 Z22 ZA47 ZA40 ZA48 Z29 Y69 14 J-03 F-11 ---- ---- ---- K-11 G-03 14

--- --- ZA5 ZA5 ZA5 --- ---

Y09 Y58 Y16 Serial Number 15 F-02 M-04 K-02 Previous Core Location 15

--- --- --- Fresh Fuel Index R P N M L K J H G F E D C B A Fresh Fuel Number of Bundle Serial Index Assemblies Numbers Fuel Type Description ZA1 4 ZA01 - ZA04 HTP 4.70 CZE 24 pins at 8 w/o Gd2O3 + 4 pins at 2 w/o Gd2O3 ZA2 8 ZA05 - ZA12 HTP 4.70 CZE 20 pins at 8 w/o Gd2O3 + 8 pins at 2 w/o Gd2O3 ZA3 16 ZA13 - ZA28 HTP 4.70 CZE 20 pins at 8 w/o Gd2O3 + 4 pins at 2 w/o Gd2O3 ZA4 8 ZA29 - ZA36 HTP 4.95 CZE 16 pins at 8 w/o Gd2O3 + 8 pins at 4 w/o Gd2O3 ZA5 12 ZA37 - ZA48 HTP 4.95 CZE 16 pins at 4 w/o Gd2O3 ZA6 8 ZA49 - ZA56 HTP 4.95 CZE 4 pins at 4 w/o Gd2O3 ZA7 8 ZA57 - ZA64 GAIA LTA 4.45 CZE 4 pins at 8 w/o Gd2O3 + 16 pins at 6 w/o Gd2O3 Page 14 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 Table 4.2.1 Intermediate Range Detector Setpoint Determination Cycle Conditions N35 N36 Trip Rod Stop1 Trip Rod Stop1 19 Installed (EPT-009) 8.420E-05 6.736E-05 6.990E-05 5.592E-05 20 Predicted (initial 8.471E-05 6.777E-05 7.947E-05 6.358E-05 startup)

(EPT-008) 1 Rod Stop setpoints are 80% of the trip values, per EPT-008.

Table 4.2.2 Power Range Detector Calibration Values PR Detector Cycle 19 Currents1 Cycle 20 Currents2 N41 Top 177.2 148.9 Bottom 194.5 163.5 N42 Top 190.3 159.9 Bottom 214.7 180.4 N43 Top 215.4 181.0 Bottom 234.1 196.7 N44 Top 174.8 146.9 Bottom 205.2 172.5 1 Power Range data taken from applicable performance of EST-911. (Reference 5.9).

2 Power Range data taken from Cycle 20 performance of EPT-008. (Reference 5.7).

Page 15 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 Figure 4.3.1 Flux Map 521 Measured vs. Calculated Powers (30%)

R P N M L K J H G F E D C B A l 0.253l 0.321l 0.253l 01 l 0.252l 0.323l 0.252l l 0.4l -0.6l 0.4l

______ ______l______l______l______l______ ______

l 0.326l 0.604l 0.988l 0.997l 0.989l 0.610l 0.330l Measured Power 02 l 0.327l 0.604l 0.983l 0.988l 0.983l 0.605l 0.329l Calculated Power l -0.3l 0.0l 0.5l 0.9l 0.6l 0.8l 0.3l Percent Difference

______l______l______l______l______l______l______l______l______

l 0.408l 1.188l 1.190l 1.304l 1.315l 1.298l 1.193l 1.197l 0.420l 03 l 0.408l 1.192l 1.190l 1.296l 1.305l 1.296l 1.191l 1.195l 0.411l l 0.0l -0.3l 0.0l 0.6l 0.8l 0.2l 0.2l 0.2l 2.1l

______l______l______l______l______l______l______l______l______l______l______

l 0.408l 0.941l 1.280l 1.294l 1.313l 1.213l 1.319l 1.298l 1.285l 0.957l 0.413l 04 l 0.410l 0.947l 1.283l 1.304l 1.320l 1.221l 1.322l 1.304l 1.285l 0.948l 0.408l l -0.5l -0.6l -0.2l -0.8l -0.5l -0.7l -0.2l -0.5l 0.0l 0.9l 1.2l

______l______l______l______l______l______l______l______l______l______l______l______l______

l 0.327l 1.191l 1.272l 1.158l 1.228l 1.122l 1.164l 1.142l 1.240l 1.176l 1.305l 1.210l 0.334l 05 l 0.328l 1.194l 1.284l 1.186l 1.245l 1.146l 1.173l 1.147l 1.245l 1.187l 1.284l 1.193l 0.328l l -0.3l -0.3l -0.9l -2.4l -1.4l -2.1l -0.8l -0.4l -0.4l -0.9l 1.6l 1.4l 1.8l l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.599l 1.182l 1.290l 1.232l 0.973l 1.138l 1.112l 1.150l 0.977l 1.251l 1.322l 1.212l 0.616l 06 l 0.604l 1.190l 1.303l 1.244l 0.978l 1.144l 1.118l 1.149l 0.978l 1.245l 1.304l 1.191l 0.605l l -0.8l -0.7l -1.0l -1.0l -0.5l -0.5l -0.5l 0.1l -0.1l 0.5l 1.4l 1.7l 1.8l

______l______l______l______l______l______l______l______l______l______l______l______l______l______l______

l 0.247l 0.974l 1.284l 1.310l 1.136l 1.145l 1.220l 1.114l 1.226l 1.149l 1.156l 1.350l 1.323l 1.004l 0.259l 07 l 0.252l 0.982l 1.294l 1.321l 1.146l 1.148l 1.216l 1.113l 1.216l 1.144l 1.146l 1.321l 1.296l 0.984l 0.252l l -2.0l -0.8l -0.8l -0.8l -0.9l -0.3l 0.3l 0.1l 0.8l 0.4l 0.9l 2.1l 2.0l 2.0l 2.7l l______l______l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.305l 0.982l 1.293l 1.207l 1.161l 1.108l 1.108l 1.093l 1.116l 1.112l 1.183l 1.242l 1.338l 1.038l 0.337l 08 l 0.323l 0.987l 1.304l 1.220l 1.172l 1.117l 1.113l 1.095l 1.113l 1.118l 1.173l 1.221l 1.306l 0.988l 0.323l l -5.9l -0.5l -0.9l -1.1l -0.9l -0.8l -0.5l -0.2l 0.3l -0.5l 0.8l 1.7l 2.4l 4.8l 4.2l l______l______l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.247l 0.974l 1.284l 1.305l 1.122l 1.131l 1.203l 1.110l 1.230l 1.143l 1.153l 1.342l 1.320l 1.008l 0.257l 09 l 0.252l 0.982l 1.295l 1.320l 1.145l 1.144l 1.216l 1.113l 1.216l 1.149l 1.147l 1.322l 1.296l 0.984l 0.252l l -2.0l -0.8l -0.9l -1.1l -2.0l -1.1l -1.1l -0.3l 1.1l -0.5l 0.5l 1.5l 1.8l 2.4l 1.9l l______l______l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.600l 1.187l 1.289l 1.228l 0.968l 1.126l 1.109l 1.147l 0.979l 1.253l 1.321l 1.208l 0.606l 10 l 0.604l 1.189l 1.303l 1.245l 0.978l 1.149l 1.118l 1.144l 0.979l 1.245l 1.304l 1.191l 0.605l l -0.7l -0.2l -1.1l -1.4l -1.0l -2.0l -0.8l 0.3l 0.0l 0.6l 1.3l 1.4l 0.2l l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.325l 1.180l 1.269l 1.168l 1.236l 1.140l 1.168l 1.144l 1.240l 1.186l 1.300l 1.211l 0.332l 11 l 0.327l 1.191l 1.283l 1.186l 1.245l 1.147l 1.173l 1.146l 1.245l 1.187l 1.285l 1.195l 0.329l l -0.6l -0.9l -1.1l -1.5l -0.7l -0.6l -0.4l -0.2l -0.4l -0.1l 1.2l 1.3l 0.9l l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.404l 0.937l 1.274l 1.299l 1.336l 1.221l 1.323l 1.308l 1.292l 0.963l 0.426l 12 l 0.408l 0.947l 1.285l 1.304l 1.322l 1.221l 1.321l 1.304l 1.284l 0.948l 0.411l l -1.0l -1.1l -0.9l -0.4l 1.0l 0.0l 0.2l 0.3l 0.6l 1.6l 3.5l l______l______l______l______l______l______l______l______l______l______l______l l 0.407l 1.184l 1.187l 1.295l 1.298l 1.298l 1.204l 1.200l 0.413l 13 l 0.411l 1.194l 1.191l 1.296l 1.305l 1.296l 1.190l 1.193l 0.408l l -1.0l -0.8l -0.3l -0.1l -0.5l 0.2l 1.2l 0.6l 1.2l l______l______l______l______l______l______l______l______l______l l 0.326l 0.602l 0.980l 0.990l 0.984l 0.608l 0.330l 14 l 0.328l 0.605l 0.983l 0.988l 0.984l 0.604l 0.328l l -0.6l -0.5l -0.3l 0.2l 0.0l 0.7l 0.6l l______l______l______l______l______l______l______l l 0.246l 0.322l 0.252l 15 l 0.252l 0.323l 0.252l l -2.4l -0.3l 0.0l l______l______l______l Page 16 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 Figure 4.3.2 Flux Map 522 Measured vs. Calculated Powers (75%)

R P N M L K J H G F E D C B A l 0.276l 0.362l 0.277l 01 l 0.276l 0.361l 0.276l l 0.0l 0.3l 0.4l

______ ______l______l______l______l______ ______

l 0.331l 0.612l 1.008l 1.080l 1.011l 0.621l 0.335l Measured Power 02 l 0.332l 0.613l 1.008l 1.081l 1.009l 0.614l 0.333l Calculated Power l -0.3l -0.2l 0.0l -0.1l 0.2l 1.1l 0.6l Percent Difference

______l______l______l______l______l______l______l______l______

l 0.408l 1.147l 1.156l 1.276l 1.303l 1.277l 1.161l 1.153l 0.420l 03 l 0.407l 1.147l 1.157l 1.276l 1.301l 1.276l 1.158l 1.150l 0.410l l 0.2l 0.0l -0.1l 0.0l 0.2l 0.1l 0.3l 0.3l 2.4l

______l______l______l______l______l______l______l______l______l______l______

l 0.409l 0.919l 1.237l 1.259l 1.282l 1.194l 1.288l 1.263l 1.234l 0.930l 0.412l 04 l 0.409l 0.921l 1.233l 1.265l 1.290l 1.205l 1.292l 1.266l 1.236l 0.923l 0.408l l 0.0l -0.2l 0.3l -0.5l -0.6l -0.9l -0.3l -0.2l -0.2l 0.8l 1.0l

______l______l______l______l______l______l______l______l______l______l______l______l______

l 0.331l 1.147l 1.225l 1.140l 1.230l 1.129l 1.163l 1.146l 1.236l 1.149l 1.252l 1.163l 0.341l 05 l 0.332l 1.148l 1.234l 1.168l 1.246l 1.151l 1.171l 1.153l 1.247l 1.169l 1.235l 1.148l 0.332l l -0.3l -0.1l -0.7l -2.5l -1.3l -1.9l -0.7l -0.6l -0.9l -1.7l 1.4l 1.3l 2.6l l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.608l 1.150l 1.256l 1.240l 1.071l 1.171l 1.136l 1.178l 1.066l 1.243l 1.279l 1.174l 0.625l 06 l 0.613l 1.156l 1.265l 1.245l 1.080l 1.174l 1.136l 1.179l 1.081l 1.247l 1.267l 1.158l 0.613l l -0.8l -0.5l -0.7l -0.4l -0.8l -0.3l 0.0l -0.1l -1.4l -0.3l 0.9l 1.4l 1.9l

______l______l______l______l______l______l______l______l______l______l______l______l______l______l______

l 0.273l 0.996l 1.260l 1.281l 1.146l 1.179l 1.251l 1.139l 1.247l 1.173l 1.155l 1.313l 1.293l 1.031l 0.282l 07 l 0.276l 1.007l 1.274l 1.290l 1.152l 1.178l 1.239l 1.134l 1.239l 1.175l 1.152l 1.291l 1.277l 1.009l 0.276l l -1.1l -1.1l -1.1l -0.7l -0.5l 0.1l 1.0l 0.4l 0.6l -0.2l 0.3l 1.7l 1.2l 2.1l 2.1l l______l______l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.359l 1.064l 1.279l 1.191l 1.165l 1.132l 1.134l 1.117l 1.136l 1.126l 1.174l 1.213l 1.304l 1.106l 0.370l 08 l 0.360l 1.079l 1.299l 1.203l 1.170l 1.136l 1.134l 1.115l 1.134l 1.137l 1.171l 1.205l 1.301l 1.081l 0.361l l -0.3l -1.4l -1.6l -1.0l -0.4l -0.4l 0.0l 0.2l 0.2l -1.0l 0.3l 0.7l 0.2l 2.3l 2.4l l______l______l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.274l 0.997l 1.262l 1.276l 1.129l 1.165l 1.233l 1.135l 1.249l 1.175l 1.155l 1.302l 1.287l 1.025l 0.283l 09 l 0.276l 1.007l 1.275l 1.289l 1.151l 1.174l 1.239l 1.134l 1.239l 1.179l 1.153l 1.292l 1.277l 1.009l 0.277l l -0.7l -1.0l -1.0l -1.0l -1.9l -0.8l -0.5l 0.1l 0.8l -0.3l 0.2l 0.8l 0.8l 1.6l 2.1l l______l______l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.609l 1.156l 1.253l 1.229l 1.067l 1.169l 1.135l 1.179l 1.079l 1.250l 1.278l 1.172l 0.622l 10 l 0.612l 1.156l 1.265l 1.246l 1.080l 1.179l 1.137l 1.175l 1.081l 1.247l 1.267l 1.159l 0.614l l -0.5l 0.0l -1.0l -1.4l -1.2l -0.9l -0.2l 0.3l -0.2l 0.2l 0.9l 1.1l 1.3l l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.329l 1.138l 1.221l 1.147l 1.238l 1.151l 1.172l 1.154l 1.249l 1.163l 1.248l 1.167l 0.338l 11 l 0.331l 1.146l 1.233l 1.168l 1.246l 1.153l 1.171l 1.152l 1.247l 1.169l 1.236l 1.151l 0.333l l -0.6l -0.7l -1.0l -1.8l -0.6l -0.2l 0.1l 0.2l 0.2l -0.5l 1.0l 1.4l 1.5l l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.404l 0.913l 1.226l 1.264l 1.307l 1.208l 1.298l 1.276l 1.245l 0.939l 0.430l 12 l 0.407l 0.922l 1.235l 1.266l 1.292l 1.205l 1.291l 1.267l 1.235l 0.923l 0.410l l -0.7l -1.0l -0.7l -0.2l 1.1l 0.2l 0.5l 0.7l 0.8l 1.7l 4.7l l______l______l______l______l______l______l______l______l______l______l______l l 0.407l 1.143l 1.157l 1.278l 1.293l 1.284l 1.178l 1.161l 0.414l 13 l 0.410l 1.150l 1.158l 1.276l 1.301l 1.277l 1.158l 1.149l 0.408l l -0.7l -0.6l -0.1l 0.2l -0.6l 0.5l 1.7l 1.0l 1.4l l______l______l______l______l______l______l______l______l______l l 0.331l 0.613l 1.011l 1.080l 1.019l 0.622l 0.336l 14 l 0.333l 0.614l 1.009l 1.081l 1.009l 0.614l 0.332l l -0.6l -0.2l 0.2l -0.1l 1.0l 1.3l 1.2l l______l______l______l______l______l______l______l l 0.282l 0.363l 0.279l 15 l 0.276l 0.361l 0.276l l 2.1l 0.6l 1.1l l______l______l______l Page 17 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 Figure 4.3.3 Flux Map 523 Measured vs. Calculated Powers (100%)

R P N M L K J H G F E D C B A l 0.293l 0.390l 0.294l 01 l 0.292l 0.385l 0.292l l 0.3l 1.3l 0.7l

______ ______l______l______l______l______ ______

l 0.334l 0.617l 1.018l 1.138l 1.021l 0.623l 0.338l Measured Power 02 l 0.334l 0.617l 1.017l 1.135l 1.017l 0.618l 0.336l Calculated Power l 0.0l 0.0l 0.1l 0.3l 0.4l 0.8l 0.6l Percent Difference

______l______l______l______l______l______l______l______l______

l 0.408l 1.115l 1.133l 1.260l 1.296l 1.261l 1.138l 1.123l 0.423l 03 l 0.407l 1.116l 1.134l 1.259l 1.293l 1.260l 1.136l 1.121l 0.410l l 0.2l -0.1l -0.1l 0.1l 0.2l 0.1l 0.2l 0.2l 3.1l

______l______l______l______l______l______l______l______l______l______l______

l 0.407l 0.902l 1.205l 1.236l 1.265l 1.187l 1.271l 1.242l 1.203l 0.915l 0.413l 04 l 0.409l 0.906l 1.203l 1.242l 1.272l 1.194l 1.274l 1.244l 1.207l 0.908l 0.408l l -0.5l -0.4l 0.2l -0.5l -0.6l -0.6l -0.2l -0.2l -0.3l 0.8l 1.2l

______l______l______l______l______l______l______l______l______l______l______l______l______

l 0.332l 1.111l 1.190l 1.127l 1.235l 1.139l 1.164l 1.152l 1.238l 1.136l 1.219l 1.132l 0.345l 05 l 0.335l 1.117l 1.204l 1.159l 1.250l 1.157l 1.171l 1.159l 1.252l 1.161l 1.205l 1.119l 0.335l l -0.9l -0.5l -1.2l -2.8l -1.2l -1.6l -0.6l -0.6l -1.1l -2.2l 1.1l 1.1l 2.9l l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.609l 1.122l 1.229l 1.244l 1.152l 1.195l 1.149l 1.199l 1.140l 1.244l 1.254l 1.150l 0.630l 06 l 0.616l 1.133l 1.241l 1.249l 1.159l 1.196l 1.149l 1.201l 1.160l 1.252l 1.244l 1.136l 0.618l l -1.1l -1.0l -1.0l -0.4l -0.6l -0.1l 0.0l -0.2l -1.8l -0.6l 0.8l 1.2l 1.9l

______l______l______l______l______l______l______l______l______l______l______l______l______l______l______

l 0.290l 1.002l 1.237l 1.259l 1.150l 1.201l 1.266l 1.155l 1.268l 1.196l 1.160l 1.292l 1.275l 1.045l 0.299l 07 l 0.291l 1.014l 1.256l 1.271l 1.157l 1.200l 1.253l 1.147l 1.254l 1.197l 1.158l 1.273l 1.261l 1.018l 0.292l l -0.3l -1.2l -1.5l -1.0l -0.6l 0.1l 1.0l 0.7l 1.1l -0.1l 0.2l 1.5l 1.1l 2.6l 2.3l l______l______l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.388l 1.119l 1.269l 1.179l 1.163l 1.145l 1.150l 1.134l 1.154l 1.142l 1.173l 1.199l 1.289l 1.154l 0.392l 08 l 0.384l 1.132l 1.290l 1.192l 1.169l 1.148l 1.147l 1.129l 1.148l 1.150l 1.172l 1.195l 1.294l 1.135l 0.386l l 1.0l -1.2l -1.7l -1.1l -0.5l -0.3l 0.3l 0.4l 0.5l -0.7l 0.1l 0.3l -0.4l 1.6l 1.5l l______l______l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.290l 1.006l 1.246l 1.255l 1.131l 1.187l 1.251l 1.153l 1.270l 1.199l 1.159l 1.278l 1.264l 1.027l 0.296l 09 l 0.291l 1.015l 1.257l 1.270l 1.156l 1.196l 1.253l 1.147l 1.254l 1.201l 1.159l 1.274l 1.260l 1.018l 0.292l l -0.3l -0.9l -0.9l -1.2l -2.2l -0.8l -0.2l 0.5l 1.3l -0.2l 0.0l 0.3l 0.3l 0.9l 1.4l l______l______l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.614l 1.137l 1.231l 1.234l 1.150l 1.198l 1.153l 1.205l 1.162l 1.253l 1.248l 1.143l 0.623l 10 l 0.616l 1.132l 1.241l 1.250l 1.159l 1.200l 1.149l 1.197l 1.160l 1.252l 1.244l 1.136l 0.618l l -0.3l 0.4l -0.8l -1.3l -0.8l -0.2l 0.3l 0.7l 0.2l 0.1l 0.3l 0.6l 0.8l l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.333l 1.109l 1.192l 1.140l 1.244l 1.160l 1.176l 1.164l 1.259l 1.155l 1.213l 1.132l 0.339l 11 l 0.334l 1.116l 1.203l 1.159l 1.250l 1.158l 1.171l 1.158l 1.252l 1.161l 1.206l 1.120l 0.336l l -0.3l -0.6l -0.9l -1.7l -0.5l 0.2l 0.4l 0.5l 0.6l -0.5l 0.6l 1.1l 0.9l l______l______l______l______l______l______l______l______l______l______l______l______l______l l 0.405l 0.899l 1.196l 1.241l 1.286l 1.198l 1.281l 1.254l 1.213l 0.921l 0.429l 12 l 0.407l 0.906l 1.205l 1.243l 1.273l 1.195l 1.272l 1.244l 1.205l 0.908l 0.410l l -0.5l -0.8l -0.8l -0.2l 1.0l 0.3l 0.7l 0.8l 0.7l 1.4l 4.4l l______l______l______l______l______l______l______l______l______l______l______l l 0.407l 1.112l 1.134l 1.260l 1.284l 1.268l 1.153l 1.128l 0.413l 13 l 0.409l 1.119l 1.135l 1.259l 1.293l 1.260l 1.135l 1.118l 0.408l l -0.5l -0.6l -0.1l 0.1l -0.7l 0.6l 1.6l 0.9l 1.2l l______l______l______l______l______l______l______l______l______l l 0.334l 0.617l 1.021l 1.138l 1.031l 0.626l 0.339l 14 l 0.335l 0.617l 1.017l 1.135l 1.017l 0.617l 0.335l l -0.3l 0.0l 0.4l 0.3l 1.4l 1.4l 1.2l l______l______l______l______l______l______l______l l 0.300l 0.389l 0.296l 15 l 0.292l 0.385l 0.292l l 2.7l 1.0l 1.4l l______l______l______l Page 18 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 Table 4.4.1 Flux Map Summary1 Map # Burnup Date Time Power CBD Boron (EFPD) (%) (steps) (ppm) 521 0.13 5/15/2015 23:30:00 28.2 134 1958 522 0.67 5/17/2015 03:30:00 72.7 177 1664 523 2.77 5/19/2015 09:30:00 99.8 218 1464 Map # RMS Max FH Fraction Max FQ Fraction Axial Difference2 to Limit, to Limit, Offset (%)

FH FQ 521 1.15% 1.651 0.795 2.563 0.532 -8.7 522 0.95% 1.582 0.870 2.315 0.699 -1.6 523 0.95% 1.536 0.925 2.146 0.889 -1.6 Map # Thimbles Thimbles Quadrant Power Tilt Ratio Used Required NW NE SW SE 521 48 38 0.994 1.007 0.992 1.007 522 47 38 0.995 1.004 0.994 1.007 523 45 38 0.994 1.004 0.995 1.007 1 Flux map summary data taken from respective INPAX-W runs [Reference 5.16]

2 RMS Difference = Measured Power - Calculated Power Page 19 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 Table 4.5.1 Reactivity Computer Checkout Input Parameters to the Reactivity Computer1 Group 1

  • 1 1 0.000215 0.000208 0.0128 2 0.001341 0.001301 0.0317 3 0.001218 0.001181 0.1207 4 0.002629 0.002550 0.3209 5 0.000966 0.000937 1.4022 6 0.000235 0.000228 3.8778 i 0.006603 0.006405 -----

Prompt Neutron Lifetime = 14.26 Importance Factor () = 0.97 Delayed Neutron Fraction (eff) = 0.006405 Positive Insertion Period Check2 Collection # time (sec) Period (sec) Calculated Measured  % Deviation Reactivity Reactivity (pcm) (pcm) 1 48.1 69.4 76.283 75.793 -0.64 2 48.9 70.6 75.327 75.334 0.01 3 49.8 71.8 74.391 74.384 -0.01 4 51.9 74.8 72.151 72.684 0.74 Average 49.7 71.6 74.538 74.549 0.02 1 Reactivity computer inputs from Cycle 20 Powertrax [Reference 5.16].

2 Measured data from Cycle 20 (RFO19) performance of EST-923 [Reference 5.14].

Page 20 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 Table 4.5.2 Low Power Physics Testing Results Summary Boron Endpoint (ppm)

Configuration Measured1 Predicted1 Difference Acceptance HZP, ARO 2144 2139 5.0 +/- 50 Control Rod Worths (pcm)

Bank Measured1 Predicted1 Difference Acceptance Pcm  % Dev2 pcm  % Dev2 CBB 1288.673 1244.000 -44.673 3.59 +/- 10 SBA 1067.412 1022.000 45.412 4.44 +/- 15 SBB 983.048 1019.000 -35.952 -3.53 +/- 15 SBC 305.787 315.000 -9.213 -2.92 +/- 100 CBA 277.476 309.000 -31.524 -10.2 +/- 100 CBC 775.020 812.000 -36.980 -4.55 +/- 15 CBD 1005.793 1024.000 -18.207 -1.78 +/- 15 M

Sum of 5703.208 5745.000 /P = 0.9927 0.9 M/P 1.1 Worths HZP Temperature Coefficient (pcm/oF)

RCS @ 2132 ppm Measured1 Predicted1 Difference Acceptance ITC -3.571 -4.051 0.480 Difference +/- 2 MTC -2.051 -2.531 0.480 Measured +5 1 Measured and predicted data obtained from Cycle 20 performance of EST-923 [Reference 5.14].

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

  • 100 Page 21 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 Figure 4.6.1 Integral Worth of the Reference Bank 1300 1200 1100 1000 900 Integral Rod Worth (pcm) 800 700 600 500 400 300 200 Measured 100 Predicted 0

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

Page 22 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 Figure 4.6.2 Differential Worth of the Reference Bank 9

8 7

Differential Rod Worth (pcm/step) 6 5

4 3

2 Measured 1

Predicted 0

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

Page 23 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 Table 4.6.3 - FSAR Chapter 14 Tests Heat Tracing and Freeze Not impacted by LTA program.

Protection Main, Auxiliary and Start- Not impacted by LTA program.

up Transformer 6.9 kv Switchgear Not impacted by LTA program.

480 VAC Distribution Not impacted by LTA program.

120 V ESF Uninterruptible Not impacted by LTA program.

AC System Class 1E DC System Not impacted by LTA program.

Normal Emergency AC/DC Not impacted by LTA program.

Lighting System Communications System Not impacted by LTA program.

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

Reactor Protection System Not impacted by LTA program.

Engineered Safety Features Actuation Logic Reactor Protection System No impact on system from LTA program, system performance is Engineered Safety Features monitored during routine operation.

Actuation Response Time Test Piping Vibration No impact on system from LTA program, system performance is monitored during routine operation.

Metal Impact Monitoring No impact on system from LTA program, system performance is monitored during routine operation.

Radiation Monitoring No impact on system from LTA program, system performance is System monitored during routine operation.

Excore Nuclear No impact on system from LTA program, system performance is Instrumentation (NIS) monitored during routine operation.

Emergency Diesel No impact on system from LTA program, system performance is monitored during routine operation and surveillance tests.

Fire Protection System No impact on system from LTA program, system performance is monitored during routine operation.

Normal Service Water No impact on system from LTA program, system performance is monitored during routine operation.

Emergency Service Water No impact on system from LTA program, system performance is monitored during routine operation and surveillance tests.

Compressed and No impact on system from LTA program, system performance is Instrument Air Systems monitored during routine operation.

Page 24 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 Reactor Coolant System No impact on system from LTA program, system performance is Hydrostatic Test monitored during routine operation and surveillance tests.

RTD/TC Cross Calibration No impact on system from LTA program, system performance is Test monitored during routine operation and surveillance tests.

Pressurizer Relief Tank No impact on system from LTA program, system performance is (PRT) Test monitored during routine operation.

Safety Injection System No impact on system from LTA program, system performance is Performance Test monitored during routine operation and surveillance tests.

High -Head Safety No impact on system from LTA program, system performance is Injection System Check monitored during routine operation and surveillance tests.

Valve Test Safety Injection (SI) No impact on system from LTA program, system performance is Accumulator Test monitored during routine operation and surveillance tests.

Residual Heat Removal No impact on system from LTA program, system performance is System Cold Test monitored during routine operation and surveillance tests.

Residual Heat Removal No impact on system from LTA program, system performance is System Hot Test monitored during routine operation and surveillance tests.

Containment Spray System No impact on system from LTA program, system performance is Test monitored during routine operation and surveillance tests.

Chemical and Volume No impact on system from LTA program, system performance is Control Cold Test monitored during routine operation and surveillance tests.

Chemical and Volume No impact on system from LTA program, system performance is Control Hot Test monitored during routine operation and surveillance tests.

Auxiliary Feedwater No impact on system from LTA program, system performance is System Test monitored during routine operation and surveillance tests.

Fuel Handling Equipment LTA dimensions evaluated for compatibility prior to manufacture System Test & shipment. See discussion in Section 3.1.

Fuel Pool Cooling and No impact on system from LTA program, system performance is Cleanup System Test monitored during routine operation and surveillance tests.

Component Cooling Water No impact on system from LTA program, system performance is monitored during routine operation.

Gaseous Waste Processing No impact on system from LTA program, system performance is System Test monitored during routine operation and surveillance tests.

Solid Waste Processing No impact on system from LTA program, system performance is Test monitored during routine operation.

Liquid Waste Processing No impact on system from LTA program, system performance is System Test monitored during routine operation.

Containment Isolation Test No impact on system from LTA program, system performance is monitored during routine operation and surveillance tests.

Containment Integrated Not impacted by LTA program.

Leak Rate Test and Structural Integrity Test Reactor Coolant System No impact on system from LTA program, system performance is Hot Functional Test monitored during routine operation and surveillance tests.

Piping Thermal Expansion No impact on system from LTA program, system performance is Page 25 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 and Dynamic Effects Test monitored during routine operation.

Pressurizer Pressure and No impact on system from LTA program, system performance is Level Control Test monitored during routine operation.

Main Steam System Test No impact on system from LTA program, system performance is monitored during routine operation.

Feedwater System Test No impact on system from LTA program, system performance is monitored during routine operation.

Condensate System Test No impact on system from LTA program, system performance is monitored during routine operation.

Turbine Generator Test No impact on system from LTA program, system performance is monitored during routine operation.

Circulating Water System No impact on system from LTA program, system performance is Test monitored during routine operation.

Condenser Vacuum and No impact on system from LTA program, system performance is Condensate Makeup monitored during routine operation.

System Waste Processing No impact on system from LTA program, system performance is Computer Test monitored during routine operation.

Containment Ventilation No impact on system from LTA program, system performance is and Cooling, Primary monitored during routine operation.

Shield and Reactor Supports Cooling System Test Plant HVAC Test No impact on system from LTA program, system performance is monitored during routine operation.

Engineered Safety Features No impact on system from LTA program, system performance is Integrated Test monitored during routine operation.

Process Computer Test No impact on system from LTA program, system performance is monitored during routine operation.

Boron Recycle Test No impact on system from LTA program, system performance is monitored during routine operation.

Refueling Water Storage No impact on system from LTA program, system performance is Tank Test monitored during routine operation.

Primary Makeup Water No impact on system from LTA program, system performance is System Test monitored during routine operation.

Rod Control System Test No impact on system from LTA program, system performance is monitored during routine operation.

Passive Safety Injection No impact on system from LTA program, system performance is System Check Valve Test monitored during routine operation.

Containment Recirculation No impact on system from LTA program, system performance is Sump Test monitored during routine operation.

Containment Vacuum No impact on system from LTA program, system performance is Relief Test monitored during routine operation.

Combustible Gas Control No impact on system from LTA program, system performance is System In Containment monitored during routine operation.

Page 26 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 Test Gross Failed Fuel No impact on system from LTA program, system performance is Detection System Test monitored during routine operation.

Essential Services Chilled No impact on system from LTA program, system performance is Water System Test monitored during routine operation.

Stud Tensioner Hoist Load No impact on system from LTA program, system performance is Test monitored during routine operation.

Polar Crane Test Summary No impact on system from LTA program, system performance is monitored during routine operation.

Feedwater Heater Drain, No impact on system from LTA program, system performance is Level and Bypass Control monitored during routine operation.

Systems Test Seismic Instrumentation No impact on system from LTA program.

Test Extraction Steam System No impact on system from LTA program.

Test Primary Sampling System No impact on system from LTA program.

Test Secondary Sampling No impact on system from LTA program.

System Test Loss of Instrument Air Test No impact on system from LTA program.

Containment Building Hot No impact on system from LTA program.

Penetration Test Simulated Loss of On-Site No impact on system from LTA program.

Power Test AC Distribution System No impact on system from LTA program, system performance is Optimum Operating monitored during routine operation.

Voltage Test Auxiliary Feedwater No impact on system from LTA program.

Turbine Pump Two-Hour Run Test Moveable Incore Detector Minimal impact on system from LTA program, due to different Test materials and dimensions of the GAIA instrument tube. System performance is discussed in Section 4.4.

Rod Control and Position No impact from LTA program, since the LTAs were not loaded in Indication System Test rodded core locations.

Rod Drive Mechanism No impact from LTA program, since the LTAs were not loaded in Timing Test rodded core locations.

Rod Drop Time No impact from LTA program, since the LTAs were not loaded in Measurement Test rodded core locations.

Reactor Coolant System Minimal impact on system from LTA program, due to different Flow Measurement Test pressure drop associated with GAIA assemblies. system performance discussed in section 4.1.

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

Page 27 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 Calibration of Nuclear Minimal impact on system from LTA program, system Instrumentation Test performance discussed in section 4.2.

Rod Control System Test No impact on system from LTA program, system performance is monitored during routine operation.

Flux Distribution Minimal impact on system from LTA program, system Measurement Test performance discussed in section 4.3.

Core Performance Test Minimal impact on system from LTA program, system performance discussed in section 4.4.

Power Coefficient Minimal impact on system from LTA program, system Measurement Test performance discussed in section 4.5.

Control Rod Reactivity Minimal impact on system from LTA program, system Worth Test performance discussed in section 4.6.

Boron Reactivity Worth Minimal impact on system from LTA program, system Test performance discussed in section 4.7.

Automatic Rod Control No impact on system from LTA program.

Test Steam Generator Moisture No impact on system from LTA program.

Carryover Test Load Swing Test No impact on system from LTA program.

Large Load Reduction No impact on system from LTA program.

From 75 Percent Power Test Turbine Trip From 100 No impact on system from LTA program.

Percent Power Test Remote Shutdown Test No impact on system from LTA program.

Loss of Offsite Power Test No impact on system from LTA program.

Pressurizer Heaters and No impact on system from LTA program.

Spray Valves Capability Test Gross Failed Fuel No impact on system from LTA program.

Detection System Test Pressurizer Continuous Not impacted by LTA program, system performance is monitored Spray Flow Verification during routine operation.

Test Reactor Coolant System No impact on system from LTA program, system performance is Leakrate Test monitored during routine operation and surveillance.

Natural Circulation Test No impact on system from LTA program, system performance is Summary monitored during routine operation and surveillance.

Main Steam and Feedwater No impact on system from LTA program, system performance is Systems Test monitored during routine operation and surveillance.

Shield Survey Test No impact on system from LTA program, system performance is monitored during routine operation and surveillance.

Loss of Feedwater No impact on system from LTA program.

Heater(s) Test Page 28 of 29

Harris Nuclear Plant Unit 1, Cycle 20 Startup Test Report Revision 0 Main Steam Isolation No impact on system from LTA program.

Valve Test Steam Generator Test for No impact on system from LTA program.

Condensation Water Hammer Steam Turbine-Driven and No impact on system from LTA program.

Motor-Driven Auxiliary FW Pumps Endurance Test Resistance Temperature Test is no longer applicable with current RTD configuration Detector (RTD) Bypass Flow VerificationTest Secondary Sampling No impact on system from LTA program.

System Test Page 29 of 29

Retrieved from "https://kanterella.com/w/index.php?title=HNP-15-065,_Submits_Cycle_20_Startup_Test_Report&oldid=2447575"