ML13052A742

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Renewed Operating License, Cycle 28 Startup Testing Report
ML13052A742
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 02/14/2013
From: Gillespie T, Nicholas Hernandez
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13052A742 (34)
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Text

T. PRESTON GILLESPIE, Jr.

Vice President PdkvEnergy Oconee Nuclear Station Duke Energy ONO1 VP / 7800 Rochester Hwy.

Seneca, SC 29672 864-873-4478 February 14, 2013 864-873-4208 fax T.Gillespie@duke-energy.com Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Duke Energy Carolinas, LLC Oconee Nuclear Station, Unit 1 Docket Numbers 50-269 Renewed Operating License DPR-38 Unit 1 Cycle 28 Startup Testing Report Pursuant to the requirements in Section 16.13.9, "Startup Report," from the Selected Licensee Commitments (SLC) Manual, Duke Energy Carolinas, LLC (Duke Energy) hereby submits to the Nuclear Regulatory Commission (NRC) the Oconee Nuclear Station Unit 1, Cycle 28 (01C28) Startup Testing Report. SLC 16.13.9 requires [in part]

that Duke Energy submit a startup report if modifications may have significantly altered the nuclear, thermal or hydraulic performance of the unit and that the report be submitted within 90 days following the completion of the startup test program.

The basis of the attached startup report is to provide the Staff with the satisfactory results from the 01C28 startup tests which incorporate the unit's first:

  • 24-month cycle,
  • Full core loading of AREVA Mark B-HTP fuel,
  • Cycle to contain fuel with Gadolinia in batch quantities.

If you have any questions or require additional information, please contact Stephen C.

Newman, Senior Engineer, Oconee Regulatory Affairs, at (864) 873-4388.

This letter and its attachment do not contain NRC commitments.

Sincerely, T. Preston Gillespie, Jr.

Vice President Oconee Nuclear Station Attachment www.duke-energy.corn

"i Nuclear Regulatory Commission February 14, 2013 Page 2 cc: Mr. Victor McCree, Regional Administrator U.S. Nuclear Regulatory Commission, Region I1 Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Mr. John P. Boska, Project Manager (By electronic'mail only)

U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation One White Flint North, M/S O-8G9A 11555 Rockville Pike Rockville, MD 20852-2746 Senior Resident Inspector Oconee Nuclear Station Ms. Susan E. Jenkins, Manager Radioactive & Infectious Waste Management SC Dept. of Health and Env. Control 2600 Bull St.

Columbia, SC 29201

DUKE ENERGY OCONEE NUCLEAR STATION OCONEE 1 CYCLE 28 STARTUP TESTING REPORT Part 1: Fuel and Core Design Part 2: Zero Power Physics Test Part 3: Power Escalation Test Prepared by: Nicolas Hemandez

OCONEE 1 CYCLE 28 Startup Testing Report Table of Contents Pa~rt 1: Fuel aiti~d reAlQesign Section Page 1.0 Summary 1 Figure 1 01C28 Final Core Load Map . 3 Figure 2 Fuel Pin Type Axial Profiles with Enrichment Table. for Oconee 1 4 Batch 30 Figure 3 Oconee 1 Cycle 28 Gad Pattern & Fuel Pin Map, Batch 30A 7 Figure 4 Oconee 1 Cycle 28 Gad Pattern & Fuel Pin Map, Batch 30B 8 Figure 5 Oconee 1 Cycle 28 Gad Pattern & Fuel Pin Map, Batch 30C 9 Figure 6 Oconee 1 Cycle 28 Gad Pattern & Fuel Pin Map, Batch 30D 10 Figure 7 Oconee 1 Cycle 28 Gad Pattern &-Fuel Pin Map, Batch 30E' 11i Figure 8 Oconee 1 Cycle 28 Gad Pattern & Fuel Pin Map, Batch 30F 12 Figure 9 Oconee 1 Cycle 28 Gad Pattern & Fuel Pin Map, Batch 30G 13 Figure 10 Oconee 1 Cycle 28 Gad Pattern & Fuel Pin Map, Batch 30H 14 2.0 Introduction and Summary .15 2.1 Approach to Criticality 15 2.2 Pre-Physics Measurements 16 2.3 Physics Testing 16

  • Part Po*3 1 wer E"a l -,i ":(i '...

3.Q Introduction and Summary 18 3.1f. NSSS Heat Balance/ RCS Flow Verification , 18 3.2 Core Power Distribution .19 3.3 Power Imbalance Detector Correlation 19 3.4 All Rods Out Critical Boron Measurement at Power 20 1.0 All-Rods-Out Critical Boron Concentration and Differential Boron 21 Worth Results 2.0 Integral Group Rod Worth Measurements 22 3.0 Reactivity Coefficients 23 4.0' NSSS Heat Balance/ RCS Flow Verification 24 5.0 Radial Peaking Factor Comparison at IMPT 25 5.1 Total Peaking Factor Comparison at IMPT 26 5.2 Radial Peaking Factor Comparison at FPT 27 5.3 Total Peaking Factor Comparison at FPT 28

.6.0 Core Power Distribution Data Summary at IMPT and FPT 29 7.0 Core Symmetry Results at LPT 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 1: Fuel and Core Design 1.0 Summary The Unit 1 Cycle 28 (O1C28) core consists of 177 Mk B-HTP fuel assemblies, each of which is a 15 by 15 array containing 208 fuel pins, 16 guide tubes and one incore instrument guide tube. The fuel consists of dished-end, cylindrical pellets of uranium dioxide. Both the reinserted fuel and fresh fuel are clad in M5 and have M5 guide tubes.

The 0 1C28 fuel assemblies have nominal. fuel loading of 488.5 kg uranium, with minor reductions in batches with Gadolinium content.

The 01 C28 core loading for this cycle consists of the following:

45 fresh Mk B-HTP fuel assemblies with 4.44 wt% U-235 each with various Gadolinia (Gad) loadings and layouts (designated Batches 30A, 30B, 30C, 30D, 30E, 30F, 30G).

Description of these fuel assemblies is provided in figures 2 - 9.

28 fresh Mk B-HTP fuel assemblies with 4.14 wt% U-235 each with a Gadolinia (Gad) loading and layout (designated Batch 30H). Description of these fuel assemblies is provided in figure 10.

68 reinserted Mk B-HTP fuel assemblies with 4.17 wt% U-235 each containing 16 radially zoned reduced enrichment fuel pins at 3.87 wt% U-235 (designated Batch 29) 28 reinserted Mk B-HTP fuel assemblies with 3.46 wt% U-235 each containing 16 radially zoned reduced enrichment fuel pins at 3.16 wt%.U-235 (designated Batch 28C) 8 reinserted Mk B-HTP fuel assemblies with 3.76 wt% U-235 each containing 16 radial zoned reduced enrichment fuel pins at 3.46 wt% U-235 (designated Batch 28D)

Figure 1 shows the batch loading pattern.

All non-Gad pins have. 6.05 inch blanket regions (top and bottom) enriched to 2.50 wt%

U-235. All Gad pins have 9.9 inch blanket regions (top and bottom) enriched to 2.50 wt%

U-235. The core periphery is composed of Batch 29, 28C, and 28D assemblies. All batches of fuel assemblies are distributed throughout the core interior except Batch 28D fuel assemblies which are located only on the periphery of the core. No fuel assemblies or burnable poison rod assemblies from the spent fuel pool are being used in 0 1C28.

Oconee 1 Cycle 28 will operate in a rods-out, feed and bleed mode. Core reactivity control is supplied mainly by soluble boron and is supplemented by 61 full length Ag-In-Cd control rods, Gadolinia which is incorporated into some of the fuel pellets, & 36 fresh burnable poison rod assemblies (BPRAs). In addition to the full length control rods, eight Inconel Page 1 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 1: Fuel and Core Design (gray) axial power shaping rods (APSRs) are provided for additional control of the axial power distribution.

Oconee 1 Cycle 28 is the third 24 Month Cycle at Oconee. It also isthe third full core at Oconee made up entirely of Mk-B-HTP fuel and the third Oconee cycle to contain fuel with Gadolinia in batch quantities. Oconee 2 Cycle 26 was the, first Oconee cycle to implement all of those changes. 24 Month Cycle designs allow the three-unit Oconee site to reduce refueling outages by one every other year, resulting-in a significant cost savings.

24 Month Cycle designs generally require more feed assemblies than 18 month designs. To design an efficient 24 Month Cycle, Gadolinia integral burnable absorber is necessary to allow feed fuel assemblies to reside in control rod locations. This allows movement of the feed fuel away from the core periphery and reduces the cycle leakage. To obtain more, accurate calculation results for Gadolinia, the CASMO-3 code was upgraded to the newer version CASMO-4. License Amendment Requests (LARs) for the transition to Gadolinia burnable absorber, CASMO-4 code, and 24-month design cycles were approved prior to cycle startup.

Page 2 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 1: O1C28 Final Core Load Map MX

- T - ~-~r I 5 - "-" -57 A

28C I 28C 1 29 1 28C I 28C NJODOH UDMC65.JDMDI4J*3DM JDMD0I JDMD01 JDMDI0 UDMC25 NJODOR C2AWl 02ALI 02AXI 28D) 1 29 3wC 301..

3ftA 301 30C.

29 1 28D.

C [w F30 T BF4V C2AM1 29 C2ANI BF5) 29 I300D C30A 302 30F 28C NJODOP JDMD41 UDMCI UDMC3 UDMC6 JDMD4 UDMC3 MDS UDMC27UDMC24UDMC23 MD42 NJODON C2CG A07T BF53 C2CH BFSD A07X C2CJ 28D 13OF 29 29 29 30H 29 3011H1 29 29 29 30F 28D

...... ............. Ufl5QQ IJNL) U M5V U IIL VUU L JUMUI1 W-UMO, UUMCLU" UUM1334 7UMtC I I C35C C2API BF5L C2CF BF4M C350 BF5N C2AR1 C35P 29 - 30E 29 29 30H 29 30H 29 30H 29 29 30E 29 NJOCWT JDMDI/ UDMD2.UDMC26PJDMD4]UDMCI 4DMD72I NJOCX5 rDMD5OUDMC07 IDMD61 UDMCOI UDMD26UDMDI8 NJOCWV F C2AY1 BFI5E A07N BF5P C2C71 BF4U C2AJI BF5H C2C81 BF5R A07Y BF4W C2AZ1 28C 30C 30D 29 301H 29T301 28C 30H129 30H 29 30D 30C 28C 4JOCW UDMDO* UDMC3" DMD6 UDMC2 JDMDI PNJOCXA UDMC58 NJOCWE DMDS UDMC06 DMD54UDMCI7,DMDI 0NJOCWR G C2ATI BF57 C351 BF58 C2AKI C2CE BF54 C352 BF55 C2AUI 28C 30B 29 30H 29 30H 28C 29 28C 30H 29 30H 29 30B 28C JDMC44 UDMDO2 UDMCl 5 UDMC40 UDMD56 NJOCX2 UDMC48 UDMD45 UDMC49 NJOCXT UDMD46 UDMCSO UDMC09 MD03 UDMC52 H C2C9I C2CK BF4N C2CR OCR C2CU BF4P C2CL C2CAI 29 30A 29 29 30H 28C 29 30G 29 28C 30H 29 29 30A 29 NJOCXD UDMDII UDMC47 DMD65 UDMC0. UDMD5.3 NJOCWP UDMC66 NJOCXN UDMD52 UDMCI8 DMUD0 UDMC68 MD05 NJOCX9 K C2AV1 BF50 C362 BF52 C2CV C2CW BF4T C35N BF5C C2C21 28C 30B 29 30H 29 30H 28C 29 28C 301-I 29 30H 29 30B 28C

'4JOCWH UDMDI1 UDMD27 UDMC6I UDMD69 UDMC67 UDM NJOCXK UDMD73 UDMC3 5 UDMD63 UDMCI 9UDMD21 UDMD13 NJOCX3 L C2Cll BF4Y A07J BF5T C2CC BF4X C2CX BFSG C2CD BFSK A080 BF5F C35K 28C 30C 30D 29 30H 29 30H1 28C 30H 29 30H 29 30D 30C 28C 4LIII'.J~tjMD6IUDMC3i5I~S UDMC21J)VWU 9UDC1 9

M C35E C2C31 BF5U C35R IBF4R C356 BF5M C2C41 C361 2? IO 29 29 301H29  ? 30H1 29 3014 29 29 10R 29 NJOD03 UDMD4 UDMC0.JUDMC63JUDMC55 3MD71UDMC42 -DMD49 UDMC4 UDMC33 UDMC57JUDMD31 NJODOA N C2CM A07G BF5A C2CN BF5J A07E C31C 28D 30Fj 29 29 29 30H 291 30H 29 29 291 30F 128D NJOCWL TDMD44*DMD3b jDMD2 IUDMC34UDMC431UDMC22kJDMD23:DMD3 I JDMD391 NJODOO I 0 __ C35H BF59 C2C51 C2C61 BF56I3 28C I 30F 30E 30D 29 29 29 30D) 30E 30F I 28C 1 NJODOCIUDM-iL JDMD2(rDMDI lDMD04 *DMD01 IDMDI5 UDMC451 NJODOZT' P C305L 30 0 1030M 28D) 29 , 3CI308 3()A I 0r3OC 29128D1 28D 1 29 R __

28C I I I

29 29 I

2RC 28C 28C 28C I

I I

!i I

I 12 1

13 2 3 4 5 6 7 8 9 10 14 Is (Z)

DFuel Control Component ID & Type (A = APSR, B = BPRA**, C = CRA)

ID Fuel Batch Mte: All fuel batches are Mk-B-HTP fuel assemblies.

    • All BPRAs are Mk-B5:

BF4M - BF4R = 2.00 wt% BaC BPRA BF4T - BF5J = 2.50 wt% BEC BPRA BF5K - BF5U = 3.00 wt% B 4C BPRA Note: Fresh fuel assemblies are shaded. All other fuel assemblies are from OIC27.

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Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 2: Pin Type Axial Profiles with Enrichment Table for Oconee 1 Batch 30 Pin Type: 1 Pin Type: 2 Pin Type: 3 143.0 in A 143.0 in A 143.0 in A 136.95 in 133.1 in 133.1 in B C D 9.9 in 9.9 in 6.05 in A A A 0 in 0 in 0 in Axial Zone Index Axial Zone Enrichment Gad w/o A 2.50 (Blanket) 0.0 B 4.44 (Primary) 0.0 C 3.55 (Gad Carrier) 4.0 D 3.10 (Gad Carrier) 6.0 E 2.66 (Gad Carrier) 8.0 F 3.77 (Gad Carrier) 2.0 G 4.14 (Primary) 0.0 H 3.31 (Gad Carrier) 4.0 Page 4 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 2: Pin Type Axial Profiles with Enrichment Table for Oconee 1 Batch 30 (Continued)

Pin Type: 4 Pin Type: 5 Pin Type: 6 143.0 in A 143.0 in A 143.0 in F 133.1 in 133.1 in 133.1 in E F 9.9 in 9.9 in 9.9 in A A 0 in 0 in I 0 in Axial Zone Index Axial Zone Enrichment Jaa w/o A 2.50 (Blanket) 0.0 B 4.44 (Primary) 0.0 C 3.55 (Gad Carrier) 4.0 D 3.10 (Gad Carrier) 6.0 E 2.66 (Gad Carrier) 8.0 F 3.77 (Gad Carrier) 2.0 G 4.14 (Primary) 0.0 H 3.31 (Gad Carrier) 4.0 Page 5 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 2: Pin Type Axial Profiles with Enrichment Table for Oconee 1 Batch 30 (Continued)

Pin Type: 7 143.0 in A 133.1 in H

9.9 in A

0 in Axial Zone Index Axial Zone Enrichment Gad w/o A 2.50 (Blanket) 0.0 B 4.44 (Primary) 0.0 C 3.55 (Gad Carrier) 4.0 D 3.10 (Gad Carrier) 6.0 E 2.66 (Gad Carrier) 8.0 F 3.77 (Gad Carrier) 2.0 G 4.14 (Primary) 0.0 H 3.31 (Gad Carrier) 4.0 Page 6 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 3: Oconee 1 Cycle 28 Fuel Pin Map, Batch 30A 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 0 1 1 2 1 21 1 1 2 1 1 1 1 1 1 1 1 1 1 1 1 Q 1 1 1 1 2 1 1 2 1 1 1 1 2 1 1 2 1 1 1 01 1 1 1 1 1 C 1 1 1 1 1 1 1 1 2 1 1 1 1 1 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 1 1 11 1 2 1 1 2 1 1 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 21 1 1 1 1 1 1 1 1 1 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 O No "BPRA" Note: Pin type numbers are defined in Figure 2.

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Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 4: Oconee 1 Cycle 28 Fuel Pin Map, Batch 30B 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 1 1 3 1 1 1 1Q 1 1 1 1 1 1 1 1 1 1 3 1 1 1 1 1 10 1 10CD11 10D1 10 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 1 1 3 1 1i ll~jj 1 1 3 1 1 3 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 10 1 1 0 1 1 1 0 1 1 0 1 1 1 1 1 1 3 1 1 3 1 1 3 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 1 1 110 1 1 1 0I1 1 1 3 1 1 1 1 1 1 1 1 1 3 1 1 1 1 1 1d 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 NO BPRA Note: Pin type numbers are defined in Figure 2.

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Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 5: Oconee 1 Cycle 28 Gad Pattern & Fuel Pin Map, Batch 30C 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 Q9 1 1 Q1 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 1 1 1 1 1 1 1 1 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 Q9 1 1 1 1 1 1 1 Q9 1 1 1 1 1 1 11 1 1 1 1 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 O NO BPRA Note: Pin type numbers are defined in Figure 2.

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Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 6: Oconee 1 Cycle 28 Gad Pattern & Fuel Pin Map, Batch 30D 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 1 1 1 1 1 1 1 1 1 1 1 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1

11 1 1 1 1 1 2 1 1 1 1 1 1 1 1 1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 1 1 l 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 "BPRA" rod (2.50 wt % B4C)

Note: Pin type numbers are defined in Figure 2.

Page 10 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 7: Oconee 1 Cycle 28 Gad Pattern & Fuel Pin Map, Batch 30E 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 1 1 2 1 1 1 1 1 2 1 1 2 1 1 1 1 1 11 1 1 1 1 1 1 2 1 1 4 1 1 4 1 1 4 1 1 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 4 1 1 4I1I 1 1 4 1 1 12 1 1 1 1 1 1 1 1 0 1 1 1 1 1 2 1 1 4 1 1 1 1 1 2 1 1 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 1 1 1 1 1 1 1 2 1 1 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 O NO BPRA Note: Pin type numbers are defined in Figure 2.

Page 11 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 8: Oconee 1 Cycle 28 Gad Pattern & Fuel Pin Map, Batch 30F 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 51 1 1 1 1 1 1§5 1 111 01 1 1 1 1 10 1 011 1 1 ~ 1 1 5 1 1 1 1 5 1 1 1 1 1 1 111 1 111 1 1 1 1 1 1 1 5D 1 1 1 1 1 1 1 1 11 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D 1 1i 5 1 1 1 1 i.

1 1 I 1 5 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 E NO BPRA Note: Pin type numbers are defined in Figure 2.

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Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 9: Oconee 1 Cycle 28 Gad Pattern & Fuel Pin Map, Batch 30G 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 4 1 1 1 1 4 1 1 1 1 4 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 14 1 1 1 1 4 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 4 1 1 1 1 4 1 1 1 1 4 1 1 1 11 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 Q NO BPRA Note: Pin type numbers are defined in Figure 2.

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Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 10: Oconee 1 Cycle 28 Gad Pattern & Fuel Pin Map, Batch 30H 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 7 6 6 6 6 6 6 6 6 6 6 6 7 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 7 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 7 6 6 M 6 6 7 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 (6 6 6 6 6 6 6 6 6 6 6 6 6 6 7 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 (D 6 6 6 (D 6 6 6 6 6 6 7 6 6 6 6 6 6 6 6 6 6 6 7 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 "BPRA" rod (2.00, 2.50, or 3.00 wt % B4C)

Note: Pin type numbers are defined in Figure 2.

Page 14 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 2: Zero Power Physics Test 2.0 Introduction and Summary The Oconee 1 Cycle 28 Zero Power Physics Test (ZPPT) was conducted on November 29th, 2012 per station procedure PT/0/A/071 1/001. This testing was conducted to verify the nuclear parameters upon which the Oconee 1 Cycle 28 core design, safety analysis and Technical Specifications are based.

Zero Power Physics Testing measurements were made with reactor power, Reactor Coolant System (RCS) pressure and RCS temperature as required by procedure. The following nuclear parameters were measured:

(a) All-Rods-Out Critical Boron Concentration (Enclosure 1.0)

(b) Differential Boron Worth (Enclosure 1.0)

(c) Integral Rod Worth for Control Rod Groups 6 and 7 (Enclosure 2.0)

(d) Temperature and Moderator Coefficients of Reactivity (Enclosure 3.0)

The AREVA Reactivity Measurement and Analysis System (RMAS) was used to record RCS temperature, wide range power levels and control rod positions. Reactivity was calculated by the RMAS computer.

On November 29th, 2012 at 16:41, ZPPT was declared complete. All acceptance criteria were met.

2.1 Approach to Criticality

'The full RCS temperature and pressure necessary for unit startup were achieved and rod withdrawal for the Control Rod Drive Trip Time Test (CRDTTT) began at 07:00 on November 28th, 2012. The CRDTTT was performed at Mode 3, hot standby conditions

(>250'F and> 1% Ak/k shutdown) per station procedure PT/0/A/0300/001. Each control rod group was individually withdrawn. The CRDTTT was satisfactorily completed. at 09:50 on November 28th, 2012.

Rod withdrawal for approach to criticality began on November 28th, 2012 at 23:40. The estimated, critical position was calculated, to be Group 7 at .77% per station procedure PT/1/A/I 103/015. Criticality was achieved at 02:55 on November 29th, 2012 with rod Groups 1-6 at 100% wd (withdrawn), Group 7 at 69% wd, Group 8 at 35% wd, an RCS average temperature of 532 'F, and an RCS boron concentration of 1953 ppmB. Due to lower than ideal (for ZPPT) Group 7 control rod position, shortly after going critical Page 15 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 2: Zero Power Physics Test additional boron was added to the RCS such that the unit was critical at 1963 ppmB and Group 7 at 76% wd prior to proceeding on to pre-physics measurements.

2.2 Pre-Physics Measurements After establishing stable conditions with the reactor critical, reactor power was slowly increased to perform the reactimeter checkout and approach the Point Of Adding sensible Heat (POAH). The POAH was found to be 0.08% FP per the wide range NIs. From the sensible heat determination, the Upper testing limit on the wide range NIs (as indicated on the Control Room Chart Recorder) was established for ZPPT.

An on-line OAC reactimeter checkout Was performed for both a positive and negative power ramp. The positive rampinvolved a reactivity change of +425 ýLp and the measured doubling times were within 0.38% of the predicted doubling times. The negative ramp involved a reactivity change of about -284 ptp and the measured doubling times were within 0.3 1% of the predicted doubling times. The measured doubling times were well within the

+/-5% acceptance criteria for the positive ramp and the +/-7% acceptance criteria for the negative ramp.

2.3 Physics Testing A. Essentially All Rods Out (EARO) Boron Concentration Measurement The RCS EARO boron concentration was calculated starting from a configuration of Groups 1-6 at 100% wd, Group 7 at 77.3% wd, and APSR Group 8 at 35% wd. The control rods were moved to their essentially all rods out position (Groups 1-6 at 100% wd, Group 7 at -80%, Group 8 at 35% wd) and the associated reactivity change was converted to a boron equivalent in ppmB. The all rods out boron concentration was then calculated and verified to be within procedure acceptance criteria. Refer to Enclosure 1.0 for more detailed results.

B. Reactivity Coefficient Measurements The temperature coefficient measurement was made while maintaining equilibrium boron concentration in the RCS, with control rod Group 7 withdrawn to 77.4% wd and with APSR Group 8 at35%wd. This test measured the reactivity change associated with a ramp 'increase in RCS temperature of approximately 3.13 °F and a subsequent decrease of 3.03 OF. The data from the two temperature ramps was averaged using the AT magnitudes as weighting factors. The change in reactivity was divided by the change in RCS temperature to calculate the temperature coefficient. The measured temperature coefficient was corrected for the difference in RCS average test temperature and reference temperature (532 OF). The moderator temperature coefficient was calculated by subtracting the Page 16 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 2: Zero Power Physics Test predicted Doppler coefficient from the measured isothermal temperature coefficient. The isothermal and moderator temperature coefficient were verified to be within the procedure acceptance criteria. Refer to Enclosure 3.0 for more detailed results.

C. Control Rod Integral Worths and Differential Boron Worth Measurement Predicted data was used for Group 7 from 100.to 80% wd. The worth of Group 7 from -80 to 77.3 % wd was measured during the EARO test. The worth of Group 7 from 77.3 to 0.0% wd, all of Group 6, and the top part of Group 5 was measured by steadily deborating the RCS and compensating for the resulting positive reactivity addition by inserting control rods (with no rod overlap). The reactivity changes resulting from the discrete control rod insertions were summed for each group to obtain the group integral rod worth. Each of the measured groups passed their individual acceptance criteria and total rod worth (group 7's worth and group 6's worth added together) passed its acceptance criteria. Refer to Enclosure 2.0 for more detailed results.

The differential boron worth was calculated by dividing the rod worths of the measured groups inserted between the initial and final boron samples by'the corresponding change in RCS boron concentration. The initial value for the boron concentration was recorded at EARO critical equilibrium conditions. The final value of boron concentration was recorded as reactivity approached steady-state. The measured differential boron worth met procedure acceptance criteria. Refer to Enclosure 1.0 for more detailed results.

Page 17 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 3: Power Escalation Test 3.0 Introduction and Summary The Oconee 1 Cycle 28 Power Escalation Test was performed between November 29th, 2012 and December 4th, 2012 per station procedure PT/0/A/081 1/001. Testing was, performed at 10% Full Power (FP), 20% FP, 40% FP, 51% FP, 73% FP, 99%FP, and 100% FP to verify nuclear parameters upon which the Oconee 1 Cycle 28 core design,,

safety analysis and Technical Specifications are based. The following tests and verifications were performed:

(a) Initial Core Symmetry Check at 20% FP (Enclosure 7.0);,

(b) NSSS Heat Balance at 20% FP, 73% FP, and 1000/u FP (Enclosure 4.0);

(c) Incore Detector Checkout at 10% FP, 40% FP, and 99%FP; (d) Power Imbalance Detector Correlation Slope Measurement at 73% FP; (e) Core Power Distribution at 5 1% FP, and 100% FP (Enclosures 5.0 through 5.3 and 6.0);

(f)" All-Rods-OutCritical Boron Concentration at 100% FP (Enclosure 1.0).

The unit reached the Low Power Testing (LPT) plateau at 19:00 on 11/29/12. Testing at.

the LPT plateau was, completed at 09:30 on 11/30/12. The unit reached the Intermediate Power Testing (IMPT) plateau at 21:00 on 11/30/12. Testing at the IMPT plateau was completed at 05:40 on 12/01/12. The unit reached the Full Power Testing (FPT) plateau at 13:17 on 12/01/12. Full Power Testing (FPT), consisting of Incore Detector Checkout, Core Power Distribution, NSSS Heat Balance, All-Rods-Out Critical Boron, RCS Flow Calculation/Calibration, and update of the RPS RCS Reference Flow was performed at this plateau. FPT was concluded at 16:04 on 12/04/12. Power Escalation Testing was declared complete at 16:54 on 12/04/12.

3.1 NSSS Heat Balance/RCS Flow Verification Off-line (non-OAC) secondary heat balance calculations were performed at 20% FP, 73%

FP and 100% FP. An off-line primary heat balance was performedat 100% FP. These tests verified the accuracy of theon-line primary and secondary-side heat balance calculations. On-line calculations are another term for calculations performed by the OAC (operator aid computer) or plant computer program. The plant on-line computer accuracy was verified by performing an off-line calculation using the same inputs that feed the on-line computer. The on-line and off-line results were compared for the same period, and verified to agree within 2% FP. This same method was used to verify that RCS flow was Page 18 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 3: Power Escalation Test greater than the required flow per the Core Operating Limits Report (COLR).

Normalization of the plant computer RCS flow constants (used to calculate flow from the primary delta-P instrumentation) was performed during FPT and the on-line power calculations were then verified to agree within 2% FP. Refer to Enclosure 4.0 for more detailed results.

3.2 Initial Core Symmetry Check and Core Power Distribution Initial Core Symmetry Check was conducted at 20%. Core Power Distribution tests were conducted at 51% FP and at 100% FP. These tests verified that reactor power imbalance, quadrant power tilt and radial/total power peaks did not exceed their respective specified limits.

Specific checks were made as follows:

Incore imbalance was compared to the error adjusted imbalance LOCA limit curve and was verified to be within specified limits (based on Core Operating Limits' Report).

The maximum positive quadrant power tilt was verified to be less than the error adjusted Core Operating Limits Report limit.

As a prerequisite to performing these tests, PT/0/A/0302/006 (Review andlControl of Incore Instrumentation Signals) was performed at .10% FP, 40% FP and 99% FP to identify

  • and evaluate erroneous Self Powered Neutron Detector signals.

The results of the initial core symmetry check which occurred at 20% FP can be found in Enclosure 7.0.

The core power distribution tests measure and compare the predicted, values of radial and total peaking factors at 51% FP and 100% FP. All acceptance criteria were satisfied. Refer to Enclosures 5.0 - 5.3 along with Enclosure 6.0.for more detailed results.

3.3 Power Imbalance Detector Correlation The Power Imbalance Detector Correlation was performed at 73% FP. The purpose of this test was to measure the excore to incore power imbalance correlation slopes for NI Channels 5, 6, 7, and 8, and to verify these slopes met acceptance criteria.

The excore/incore imbalance correlation slope for each NI Channel (5-8) was determined by a least squares fit of excore to incore imbalance indications. A total of 17 incore Page 19 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Part 3: Power Escalation Test imbalance points (updates/measurements) which ranged between -10.13% and +2.76% FP were used. All the slopes were verified to meet acceptance criteria.

3.4 All Rods Out Critical Boron Measurement at Power The All Rods Out Critical Boron at Power measurement was made at 100% FP, and the difference between measured and predicted reactivity (in terms of ppmB) was verified to be acceptable. Refer to Enclosure 1.0 for more detailed results.

Page 20 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Enclosure 1.0 ALL-RODS-OUT CRITICAL BORON CONCENTRATION AND DIFFERENTIAL BORON WORTH RESULTS Zero Power ARO At-Power ARO Differential Boron Critical Boron Critical Boron Worth Concentration Concentration CONDITIONS Initial Critical 100% FP Initial State:

0 EFPD 1.0 EFPD Gp 7 @ 77% wd Gp 8 @ 35% wd Gp 7 @ 77.3% wd Gp 7@ 86.3% wd 1963 ppmB Gp 8 @ 35% wd Gp 8 @ 35% wd 1960 ppmB 1484 ppmB Final State:

@ EARO, Gp 5 @ 91% wd Gp 8 @ 35% wd 1703 ppmB MEASURED 1983 ppmB 1404 ppmB -0.00672 %Ak/k ppmB VALUE @ ARO PREDICTED 1978 ppmB 1405 ppmB -0.00667 °Ak%/k ppmB VALUE @ ARO DEVIATION -5 ppmB* +1 ppmB* -0.71%**

ACCEPTANCE +15% dev. from Predicted + 50 ppmB Predicted +/- 50 ppmB preded CRITERIA predicted

  • (Predicted - Measured) ** (Predicted -Measured)
  • 100 Measured Page 21 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Enclosure 2.0 INTEGRAL GROUP ROD WORTH MEASUREMENTS PARAMETER MEASURED PREDICTED VALUE VALUE DEVIATION* ACCEPTANCE

(%Ak/k) (%Ak/k) (%) CRITERION Gp 7 -0.9696 -0.9690 -0.1 + 15% Deviation Integral Worth Gp-6 -0.8895 -0.9640 +8.4 + 15%Deviation Integral Worth Gp 6, & 7 -1.8592 -1.9330 +4.0 + 10% Deviation Integral Worth

% Deviation = Predicted - Measured.* 100 Measured Page 22 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Enclosure 3.0 REACTIVITY COEFFICIENTS PARAMETER CONDITIONS MEASURED PREDICTED DEVIATION ACCEPTANCE VALUE VALUE (Meas-Pred CRITERIA Hot Zero Power Tave=533.6 F -0.15111 E-4 Ak -0.13312 E-4 Ak +0.0180 E-4 Ak Measured -Predicted =

Temperature Gp 7 @ 77.4% wd k OF k OF k OF +0.2E-4 Ak Coefficient Gp 8 @ 35% wd k OF (ARO) 1966 ppmB Hot Zero Power Tave=533.6 F +0.01455 E-4 Ak +0.03254 E-4 Ak .+0.0180 E-4 Ak Measured - Predicted =

Moderator Gp 7 @ 77.4% wd k OF k OF k OF +0.2E-4 Ak Temperature Gp 8 @ 35% wd k OF Coefficient 1966 ppmB (ARO) and Measured <+0.5E-4 Ak k OF Page 23 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Enclosure 4.0 NSSS HEAT BALANCE/RCS FLOW VERIFICATION Test Plant Plant OfflineI Offline'I RCS Plateau Computer Computer Calculated Calculated Flow 1,2 Online Online Sec. Primary Secondary. (%DF)

Primary Power Level Power Level Power Level Power Level (%FP)

(%FP) "

LPT 19.74 20.15 19.71 20.09 115.38 IMPT .72.14 72.99. 72.18 72.90 114.16 FPT 99.32 99.53 99.51 99.44 113.57

'Calculated by the POWCALC SDQA spreadsheet.

2Required to be > Core Operating Limit Report.RCS flow of 108.5 % Design Flow (DF)

Page 24 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Enclosure 5.0 RADIAL PEAKING FACTORS AT IMPT 8 9 10. 11 12 13 14 15 1,1,Gp4 2,2 3,4,Gp3 4,10 5,14,Gp7 6,21 7,30,Gp6 8,37 1.37 1.16 1.03 1.29 -1.18 1.21 1.10 0.49 H 1.36 1.13 1.01 1.26. 1.18 1.17 1.12 0.48 0.4% 3.0% .1.7% 1.9% 0.3% 3.2% -1.9% 0.5%

9,3,Gp3 10,6+8 11,1nnerGpl 12,15+20 13,22+29,Gp5 14,31+36 15,45 1.01 1.23 1.36 1.21 1.05 0.39

ý1.29 K 0.98 1.23 1.38 1.28 1.21 i.05 0.40 2.4% 0.1% -1.8% 0.3% 0.4% -0.3% -1.9%

0.1%

1.23 1.38

-1.8% 1.28 0.3% 1.21 0.4% 1.05

-0.3% 0.40

-1.9%

16,12,Gp6 17,17+18 18,24+27,Gp8 19,Outer 20,38+44,Gp4 21,46 Predicted 1.32 1.33 1.26 1.20 0.95 0.28 Measured L 1.31 1.30 1.27 1.21 0.96, 0.28

% Dev 0.9% 2.7% -0.8% -0.2% -0.8%. 0.9%

22,26,Gp5 23,33+34 24,40+42,Gp2 25,49 1.35 1.30 .1.09 0.59 M 1.36 1.30 1.09 0.59

-0.8% -0.3% 0.1% 0.1%

26,41,Gp7 27,48 28,51 1.01 0.89 0.29 N 1.04 0.91 0.30

-2.8% -2.9% -3.5%

29,52

% Dev. = Predicted - Measured

  • 100 0.34 Measured 0.34

-0.8%

Core Conditions Power 51 %FP Group 5 100% wd Group 6 100%wd Group 7 60% wd Group 8 35% wd Incore Imbalance -7.16 RCS Boron 1715 ppmB Max 1/8 Core % Deviation is +3.2% at H13 Acceptance criteria: <+15% of Predicted Min 1/8 Core % Deviation is -3.50/o at N14 Acceptance criteria: >-15% of Predicted Maximum Peak Deviation is +0.9% Acceptance Criteria: <+5% of Predicted Root Mean Square of Deviations is 1.9% Acceptance Criteria: <7.5%

Page'25 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Enclosure 5.1 TOTAL PEAKINGFACTORS AT IMPT 8 9 10 11 , 12 13 14 15 1,1 ,Gp4 2,2 3,4,Gp3 4,10 5,14,Gp7 6,21 7,30,Gp6 8,37 1.69 1.43 1.28 1.69 1.74 1.63' 1.44 0.63 H 1.81 1.40 1.24 1.65 1.68 1.55 1.47 0.61,

-6.6% 2.1% 3.4% 2.4% 3.4% 5.0% -1.7% 3.0%

9,3,Gp3 10,6+8 11,1nnerGpl 12,15+20 13,22+29,Gp5 14,31+36 15,46 -

1.23 1.55 1.72 1,61. 1.37 0.50 K 1.20 1.57 1.79 1.73 1.60 1.37' 0 ZU 2.6% -1.5% '1.5% -0.4% -1.5%

1%

0.5%'

-0.4% 0.%

0.6% 01 0.1%

16,12,Gp6 17,17+18 18,24+27,Gp8 19,Outer 20,38+44,Gp4 21,46 Predicted 1.68 1.72 1.68 1:59 1.26 0.36 Measured L 1.66 1.69 1.71 1.59 1.26 0.35

% Dev 1.4% 2.2% -1.8% 0.1% -0.5% 3.2%'

22,26,Gp5 23,33+34 24,40+42,Gp2 25,49 1.78 1.77 1.47 0.78 M 1.80 1.82 1.46 0.77

-1.2% -3.0% 0.6% 1.0%

26,41,Gp7 27,48 28,51 1.52 1.25 .0.39 1.56 1.30 0.40'

-2.3% -3.8% -2.2%

29,52

% Dev. = Predicted - Measured

  • 100 0.48 Measured 0 0.46 3.0%

Core Conditions Power 51 %FP Group 5 100% wd Group 6 100%wd Group.7 60%wd Group 8 35%wd Incore Imbalance ' -7.16 RCS Boron 1715 ppmB Max 1/8 Core % Deviation is +5.0% at H13 Acceptance criteria: <+20% of Predicted Min 1/8 Core % Deviation is -6.6% at H8 Acceptance criteria:' >-20% of Predicted-Maximum Peak Deviation is +2.5% Acceptance Criteria: <+7.5% of Predicted Page 26 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Enclosure 5.2 RADIAL PEAKING FACTORS AT FPT 8 9 10 11 12 13 14 15 1,1,Gp4 2,2 3,4,Gp3 4,10 5,14,Gp7 6,21 7,30,Gp6 8,37 1.30 1.12 1.00 1.27 1.29 1.23 1.09 0.50 H 1.30 1.11 1.00 1.25 1.27 1.18 1.11 0.50 0.3% 1.3% 0.4% 1.9% , 1.6% '4.0% -1.7% -0.6%

13,22+29,Gp5 9,3,Gp3 10,6+8 11, Inner, Gpl 12,15+20 14,31+36 15,45 0.98 1.19 1.33 1.28 1.21 1.04 0.40 K 0.97 1.21 1.36 1.28 1.20 1.05 0.41 0.9% -1.1% -1.9% 0.4% 1.0% -0.7% -2.7%

16,12,Gp6 17,17+18 18,24+27,Gp8 19,Outer 20,38+44,Gp4 21,46 Predicted 1.28 1.29 1.24 1.18 0.95 0.29 Measured L 1.27 1.26 1.24 1.18 0.96 0.29

%Dev 0.4% 2.8% -0.4% 0.1% -0.6% 0.,0%

22,26,Gp5 23,33+34 24,40+42,Gp2 25,49 1.33 1.31 1.10 0.60 M 1.34 1.32 1.10 0.60

-0.7% -0.2% 0.6% 0.7%

26,41,Gp7 27,48 28,51 1.13 0.94 0.31 N 1.15 0.96 0.32

.- 1.5% -2.2% -2.2%

29,52

% Dev. = Predicted - Measured

  • 100 0.38 Measured 0 0.38

-1.3%

Core Conditions Power 100 %FP Group 5 100% wd Group 6 100%wd Group 7 91% wd Group 8 35% wd Incore Imbalance -3.97 RCS Boron 1398 ppmB Max 1/8 Core % Deviation is +4.0% at H13 Acceptance criteria: <+ 15% of Predicted Min 1/8 Core % Deviation is -2.7% at K15 Acceptance criteria: >-15% of Predicted

. Maximum Peak Deviation is +1.8% Acceptance Criteria: <+5% of Predicted Root Mean Square of Deviations is 1.8% Acceptance Criteria: <7.5%

Page 27 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Enclosure 5.3 TOTAL PEAKING FACTORS AT FPT 8 9 10 11 12 13 14 15 1,1,Gp4 2,2 3,4,Gp3 A 4,10 5,14,Gp7 6,21 7,30,Gp6 T 8,37 1.48 1.26 1.12 1.45 1.49 1.41 1.26 0.56 H 1.49 1.26 1.11 1.44 1.45 1.34 1.28 0.56

-0.9% 0.0% 0.7% 0.3% 2.6% 5.1% -1.9% 0.5%

9,3,Gp3 11,1nnerGpl 12,15+20 13,22+29,Gp5 14,31+36 15.45 1.09 1.34 1. 51 1.47 1.39 1.19 0.45 K 1.08 1.38 1.65 1.48 1.38 1.20* 0.46 1.0% -3.0% -2.4% -0.7.% 0.6% -0.5% -2.2%

16,12;Gp6 17,17+18 18,24+27,Gp8 19, Outer 20,38+44,Gp4 21,46 Predicted 1.45 1.47 1.46 1.36 1.10 0.32 Measured L 1.44 1.45 1.49 1.37 1.11 0.32

%Dev 0.4% 1.3% -1.8%. -0.3% -1.3% 0.9%

22,26,Gp5 23,33+34 24,40+42,Gp2 25,49.

1.53 1.52 1.27 0.69 M 1.54 1.58 1.28 0.69

-0.8% -3.7% '1

-0.2% +

0.0%

26,41,Gp7 27,48 28,51 1.32 1.10 0.36 N 1.35 1.13 0.37

-1.9%

-3.1%

-4.1%

29,52

% Dev. = Predicted - Measured

  • 100 0.43 Measured 0 0.43

-0.5%

Core Conditions Power 100 %FP Group 5 100%wd Group 6 100%wd Group 7 91%wd Group 8 35%wd Incore Imbalance -3.97 RCS Boron 1398 ppmB Max 1/8 Core % Deviation is +5.1% at H 13 Acceptance criteria: <+20% of Predicted Min 1/8 Core % Deviation is -4.1% at N14 Acceptance criteria: >-20% of Predicted Maximum Peak Deviation is +3.3% Acceptance Criteria: <+7.5% of Predicted Page 28 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Enclosure 6.0 CORE POWER DISTRIBUTION DATA

SUMMARY

AT IMPT AND FPT PLATEAUS Power Level 51 100

(% FP)

Group 7/8 60/35 91/35 Positions (% wd)

RCS Boron 1715' 1398 Concentration (ppmB)

Incore Imbalance -7.16 -3.97

(% FP)

Page 29 of 30

Oconee 1 Cycle 28 STARTUP TESTING REPORT Enclosure 7.0 Core Symmetry Results at LPT

% Deviation= Highest-Lowest/AVG

  • 100%

Detector Assembly Detector Assembly Number Power  % Dev Number Power  % Dev 6 3 .60 24 3.69 8 3.74 27 3.66 AVG 3.67 3.81 AVG 3.68 0.82 5 4 .02 23 3.47 7 4.03 28 3.49 9 4.00 32 3.47 11 4 .02 35 3.43 13 4 .08 39 3.44 16 3 .98 43 3.43 19 3 .99 47 3.41 25 4 .08 50 3.42 AVG 4.03 2.48 AVG 3.45 2.32 44 2.72 38 2.70 AVG 2.71 0.74 15 3.63 33 3.56 20 3.58 34 3.65 AVG 3.61 1.39 AVG 3.61 2.50 29 3.40 42 2.96 22 3.39 40 3.04 AVG 3.40 0.29 AVG 3.00 2.67 31 2.99 36 2.94 AVG 2.97 1.69 17 3.81 18 3.80 AVG 3.81 0.26 Page 30 of 30

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