ML12251A004

Oconee Nuclear Station, Unit 3 - Unit 3 Cycle 27 Startup Testing Report

ML12251A004
Person / Time
Site:	Oconee
Issue date:	09/05/2012
From:	Gillespie T P Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
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Download: ML12251A004 (30)

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1.Z Duke T. PRESTON GILLESPIE, JR.E~nergy Vice President Oconee Nuclear Station Duke Energy ONO VP / 7800 Rochester Hwy.Seneca, SC 29672 864-873-4478 864-873-4208 fax T. Gillespie@duke-energy.

com September 5, 2012 U. S. Nuclear Regulatory Commission Washington, DC 20555 Attention:

Document Control Desk

Subject:

Duke Energy Carolinas, LLC Oconee Nuclear Station, Unit 3 Docket Numbers 50-287 Unit 3 Cycle 27 Startup Testing Report Pursuant to the requirements in Section 16.13.9, "Startup Report," from the Selected Licensee Commitments Manual, Duke Energy Carolinas, LLC hereby submits to the Nuclear Regulatory Commission (NRC) the Oconee Nuclear Station Unit 3, Cycle 27 (03C27) Startup Testing Report. The report provides the Staff with the satisfactory results from the 03C27 startup tests that incorporate the unit's first 24-month cycle, full core loading of AREVA Mark B-HTP fuel, and first cycle to contain fuel with Gadolinia in batch quantities.

If you have any questions or require additional information, please contact Kent Alter, Oconee Regulatory Affairs Group, at (864) 873-3255.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 Nuclear Regulatory Commission September 5, 2012 Page 2 cc: Mr. Victor McCree, Regional Administrator U.S. Nuclear Regulatory Commission, Region II 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 NRC 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 POWER COMPANY OCONEE NUCLEAR STATION OCONEE 3 CYCLE 27 STARTUP TESTING REPORT Part 1: Fuel and Core Design Part 2: Zero Power Physics Test Part 3: Power Escalation Test Prepared by: Nicolas Hernandez OCONEE 3 CYCLE 27 Startup Testing Report Table of Contents Part 1.:, Fuel and Core Design Section Page 1.0 Summary 1 Figure 1 03C27 Final Core Load Map 3 Figure 2 Rod Type Axial Profiles with Enrichment Table for Oconee 3 Batch 29 4 Figure 3 Oconee 3 Cycle 27 Rod Type Map, Batch 29A 6 Figure 4 Oconee 3 Cycle 27 Rod Type Map, Batch 29B 7 Figure 5 Oconee 3 Cycle 27 Rod Type Map, Batch 29C 8 Figure 6 Oconee 3 Cycle 27 Rod Type Map, Batch 29D 9 Figure 7 Oconee 3 Cycle 27 Rod Type Map, Batch 29E 10 SPart 2: Zero Power Physics' Test 2.0 Introduction and Summary 11 2.1 Approach to Criticality 11 2.2 Pre-Physics Measurements 12 2.3 Physics Testing 12.... _ ..... ......... .Part 3: Power EscalationTest, .... ... ..__3.0 Introduction and Summary 14 3.1 NSSS Heat Balance/ RCS Flow Verification 14 3.2 Core Power Distribution 15 3.3 Power Imbalance Detector Correlation 15 3.4 All Rods Out Critical Boron Measurement at Power 16 Enclosures, 1.0 All-Rods-Out Critical Boron Concentration and Differential Boron Worth 17 Results 2.0 Integral Group Rod Worth Measurements 18 3.0 Reactivity Coefficients 19 4.0 NSSS Heat Balance/ RCS Flow Verification 20 5.0 Radial Peaking Factor Comparison at IMPT 21 5.1 Total Peaking Factor Comparison at IMPT 22 5.2 Radial Peaking Factor Comparison at FPT 23 5.3 Total Peaking Factor Comparison at FPT 24 6.0 Core Power Distribution Data Summary at IMPT and FPT 25 7.0 Core Symmetry Results at LPT 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Part 1: Fuel and Core Design 1.0 Summary The Unit 3 Cycle 27 (03C27) core consists of 177 Mk B-HTP fuel assemblies, each of which is a 15 by 15 array containing 208 fuel rods, 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 03C27 fuel assemblies have nominal fuel loading of 490 kg uranium, with minor reductions in batches with Gadolinium content.The 03C27 core loading for this cycle consists of the following:

72 fresh Mk B-HTP fuel assemblies with 4.37 wt% U-235 each with various Gadolinia (Gad) loadings and layouts (designated Batches 29A, 29B, 29C, 29D, 29E). Description of the Gadolinia assemblies is provided in figures 2 -7.64 reinserted Mk B-HTP fuel assemblies with 3.87 wt% U-235 each containing 16 radially zoned reduced enrichment fuel pins at 3.57 wt% U-235 (designated Batch 28)16 reinserted Mk B-HTP fuel assemblies with 4.14 wt% U-235 each containing 16 radially zoned reduced enrichment fuel pins at 3.84 wt% U-235 (designated Batch 27B)25 reinserted Mk B-HTP fuel assemblies with 3.63 wt% U-235 each containing 16 radial zoned reduced enrichment fuel pins at 3.33 wt% U-235 (designated Batch 27C)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 coreperiphery is composed of Batch 27B and 27C assemblies.

All batches of fuel assemblies are distributed throughout the core interior including a Batch 27C fuel assembly that is located in the center of the core. No fuel assemblies or burnable poison rods from the spent fuel pool are being used in 03C27.Cycle 27 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, & 40 burnable poison rod assemblies (BPRAs). In addition to the full length control rods, eight Inconel (gray) axial shaping rods (APSRs) are provided for additional control of the axial power distribution.

Page 1 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Part 1: Fuel and Core Design Oconee 3 Cycle 27 is the second 24 Month Cycle at Oconee. It also is the second full core at Oconee made up entirely of Mk-B-HTP fuel and the second Oconee cycle to contain fuel with Gadolinia in batch quantities.

Oconee 2 Cycle 26 was the first Oconee 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 and CASMO-4 were submitted, and both were approved prior to cycle startup. The ability to operate the cycle for its full 24 month design life is dependent upon NRC approval of an LAR currently under their review.24 Month Cycles with Gadolinia and CASMO-4 code methods are planned for all three Oconee Units.Page 2 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 1: 03C27 Final Core Load Map Figure 1 Oconee 3 Cycle 27 Final Core Load Map ONEI-0400-76 (Rev. 23)Page 5 of 5-- -- ~ '-r r -NJOCEN INJOCE9 I I,1CE2 INIOCCK 2713 2C 27(2 27C2 NJACEP 27A3 NJOCE.I I NTCC'LEC B 4 9D1 k I W7 .v j NJILCE0 NJOC0I 27(2 2713 27B 27(NI 27C 9L sýýnU~:21 UDP'FAI)4 rUIDPA1,NU]'4 lVDý: J0AJ PC', NJ\IC1.Cý21' P B F-1 T] C 184 I C2E9 V 29 2C 2A 29A 29'\ C Q! ,) 27 TI T) -Uf"A22 0J0PA06 UfDPA31 IJDPAA1 Q 4'f')C ,UD A34 I1tJPA1I UD PAI.' NiOCFV 273 21A ( 2IDN 2BAO7 I 2N C2DP 28A 2 A72A C2 DU2__18l~A 28l~A 28,'A r 9A [SA IL2__ L28A.1 28A I )1 27 I tJ~U 'IJ~ U r.L tIrv/t r"£jJLrI -" >1> 'V~f~ Wltc~mI J~tU 1~CE MCC 4*4L1A 3LIP47U ] 11 ID12 1 1. L 77(' C213 (W C 2H F4] C9 4i4AC J7( I; F ~;2A 7ISJA ý6xt A ')) i-Q' -3 A I ?A I~ 27(F K 1.'IJOCEW UcX':(1fA~53 .JOPAO., UVPOO UDP36, bUki5:2 (PA5ý 4IP$dItUDAAI ULIPA46 fl5L NJCE 8I~ U3. A07H B1'k :I6 ClOT .3ýFfl CIS8C b tE :21)V 1i MI"ýC7Rý Blýý C',27B3 191)V C& 28A 111A 218A 29A, i8 ~4 ~ A '9A~ 2x!% 1ý) 2~ 71 N4j<WCTE L' AO WI I L UC'Aj. VI I P1 1JT)P21 UDPA55 U10PA23; UDPA.54 UL)PIC)1 TD4G '1P9 PA16 -7J'NJrICDK C2'F7 Pr'. l2)Y ;BFI 2' -4 C 4C2CQ C2PI ý'i I , (-20-27C 299~A29~ ~A -,9ý 28A 28Al~A 29A lA 1) % 29A 2 13 27C IIIIICDD I,. P UOPA¶ -OAE 'U0IPCH U IJOPA0 ULWPAL3 N'1VXZIL UDPA12 UDPA5O, 1tW~~ LDA2 tf)'431 ~ N$C2 DX J11F4 I-, 2CA (,2F. E C2lf. I l~~ C"FZE 27C 2-0I'ý 28 IA 29AL 219A 28A 28A 27C2 28A I 2A -J" 28A 28A I2) P3 27C NICTl~I'3 IUDIA I un413"n W),A0 UbX)OLA V[)PmA ýJ DrA59 LJDP .WIP 1: II~rt IJPAS DPA29 I I- NIOC139 C2(i! 111`3Tv C,2F AýIW4 C2G2 C22607 "11F46- TX IW M C220 8 22!0\fl 2S l')A 28A 29Vý 7ýlA 28A ~ A ~ ~' ~A 2S)~ ~ A ' 911 27C.N.OE 3 l 1 9 1),PC I IrFr VP n~2 IJPI f"'. jrPAYIý I~ '1P,$ -3 (P'A 1 1)1"::41 00lnrfeO N;CCP1 c'C2i LI) IIIn A17F 13148 (-2,'ED F14O 0 23 .jl C 2G6 i*-4U fli: W' $. 26A 27B 29D C:t s,% -'9"k l2lA 21 A SA ' 'llA MA, IA '2 9C 441491 27B3 (Y)M Nj 0 -6E C (310 D B F44 I C2 FY i3Il I (220 ;I C34T 2 L T,6 I2FW 27C2 L 2ýE A l2A ')RA l'fi<~/A' l2A I 2-%~ 1lA 1,'c29&- 2RA I 28lA I'Ký291 A 27C NJCG-S25 '7 lA XI)'~ DA1 4p2 ~llASU 4 IWA421 UDPA49 UIDPAH3O hlrllýC'R jNJOCEIK N-1*EG UV71I1c" I -)p(2I E I____________

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`UVPA371 ;-DA63 1DAJ 1 27(2 '59D ~--29E C>2 4V lClA VSA Fl F 7(7j 2 9 E JWAj 234A (23A 28A 27C ! <*,-I I -I ), 1 2.-. -t NJOCET N I 7B R I 3 I : 4 O.CE3 I,,UL)K JCA 5 ( -GI I 1 fI IAU' NMNXIC t OcEE j~$;[ 1~ -12~ :-rc,ý -I 27(2 ~ ~ ~ ~ ~~~n I 7l.2r'f 2lIA2( 27E, I I........ % _/ {.o 1 " 27C rý )CFA.27 C" Ii I WrJC04I NI KZEI'27C j 27B 9 10)II 11 13 14 S Fuel ID D Contral Component ID & Type (A APSR, m , BPRAIý, C ý;CRA), (Otn~iks indicaLT tehiI1SeI RPRA)F Fuel Batch Nowe. All fuel batches =re Mk-8--1ITP

All 8PRAs are Mk-BS3 BF3F f-l3Y = .250 wtIW fl,C IDIRA BF40 -eF4L =u3.00 Wtrnb H 4 C hEfRA Notc: Fresh fwel agsembhes3 avo shadeti. All othier RIO~ e~bi are tromi 03C26, Page 3 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 2: Rod Type Axial Profiles with Enrichment Table for Oconee 3 Batch 29 Rod Type: 1 Rod Type: 2 Rod Type: 3 143.0 in A 143.0 in .A 143.0 in 136.95 in .A 133.1 in 133.1 in I B C D 9.9 in 9.9 in 6.05 in 0 in A A A Axial Zone Index A B C D E F G 0 in I Axial Zone Enrichmei 2.50 (Blanket)4.37 (Primary)3.05 (Gad Carrier)2.84 (Gad Carrier)3.49 (Gad Carrier)3.71 (Gad Carrier)2.62 (Gad Carrier)Gad w/o 0.0 0.0 6.0 7.0 4.0 3.0 8.0 0 in Page 4 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 2: Rod Type Axial Profiles with Enrichment Table for Oconee 3 Rod Type: 4 Rod Type: 5 143.0 in A 143.0 in A Batch 29 (Continued)

Rod Type: 6 143.0 in A I 133.1 in 133.1 in 133.1 in E F G 9.9 in 0 in 9.9 in 9.9 in A A A AXial tone inaex A B C D E F G G in Axial Zone Enrichment 2.50 (Blanket)4.37 (Primary)3.05 (Gad Carrier)2.84 (Gad Carrier)3.49 (Gad Carrier)3.71 (Gad Carrier)2.62 (Gad Carrier)Gad w/o 0.0 0.0 6.0 7.0 4.0 3.0 8.0 0 in Page 5 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 3: Oconee 3 Cycle 27 Gad Pattern "4.37-8B6" Rod Map, Batch 29A 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 -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 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 1 j:::2 a: 1 1 1 1 :i :i 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 @ 1 1 @ 1 1l 1 1 l l 1 1 1 1 1 1 1 K 2,1 1 .1.1.1.1 1 1 0@ 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 1 1 1 1 1 1 1"BPRA" rod (2.5, 3.0 w/o B 4 C)Note: Rod type numbers are defined in Figure 2.Page 6 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 4: Oconee 3 Cycle 27 Gad Pattern "4.37 12B7" Rod Map, Batch 29B 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 I 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 1 1 1 33 1 1 0 1 1 1 1 1 1 1 1 01 1 1 1 1 ,3', 1 1 1 1 1 1 1 13 ;; 1 1 1 1 1 1 1 0 1 1 1 0 1 1 1 1 1 1 1 3 1 1 1 1 1 1 1 l 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 I 1 113 1 1 1 1 ' 1 0 31 l~ 1 1 1 1 1 01 1 1 1 1 :.;.:,, 10 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 O NO BPRA Note: Rod type numbers are defined in Figure 2.Page 7 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 5: Oconee 3 Cycle 27 Gad Pattern "4.37-8B4" Rod Map, Batch 29C 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 .4 1 1 1 1 1 1 1 1 1 1 1 4 1 1 1 1 1 11 4 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 14 1 1 1 1 1 1 1 1 1 1 1 0 1 ..1.1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 I 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 1 1 1 1 1 1 1 " 4: 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1"BPRA" rod (2.5 w/o B 4 C)Note: Rod type numbers are defined in Figure 2.Page 8 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 6: Oconee 3 Cycle 27 Gad Pattern "4.37-8B3" Rod Map, Batch 29D Q NO BPRA Note: Rod type numbers are defined in Figure 2.Page 9 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Part 1: Fuel and Core Design Figure 7: Oconee 3 Cycle 27 Gad Pattern "4.37 12B8" Rod Map, Batch 29E Q NO BPRA Note: Rod type numbers are defined in Figure 2.Page 10 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Part 2: Zero Power Physics Test 2.0 Introduction and Summary The Oconee 3 Cycle 27 Zero Power Physics Test (ZPPT) was conducted on June 6th, 2012 per station procedure PT/0/A/07 11/001. This testing was conducted to verify the nuclear parameters upon which the Oconee 3 Cycle 27 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 5, 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 June 6th, 2012 at 23:19, 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 21:45 on June 5th, 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 23:30 on June 5, 2012.Rod withdrawal for approach to criticality began on June 6, 2012 at 10:38. The estimated critical position was calculated to be Group 7 at 80% per station procedure PT/3/A/1 103/015. Criticality was achieved at 14:35 on June 6, 2012 with rod Groups 1-6 at 100% wd (withdrawn), Group 7 at 85% wd, Group 8 at 35% wd, an RCS average temperature of 532 OF, and an RCS boron concentration of 1934 ppmB.Page 11 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Part 2: Zero Power Physics Test 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 0.156% 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 ramp involved a reactivity change of +481 ýtp and the measured doubling times were within 0.66% of the predicted doubling times. The negative ramp involved a reactivity change of about -255 [tp and the measured doubling times were within 1.22% 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 87.1% 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 90%, 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 86.9% wd and with APSR Group 8 at 35% wd. This test measured the reactivity change associated with a ramp increase in RCS temperature of approximately 2.92 OF and a subsequent decrease of 3.14 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 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.Page 12 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Part 2: Zero Power Physics Test C. Control Rod Integral Worths and Differential Boron Worth Measurement The worth of Group 7 from 87.1 to 90% wd was measured during the EARO test. The remaining worth of Group 7 and all of Group 6 and Group 5 was measured by steadily deborating the RCS and compensating for the resulting positive reactivity addition by inserting control rods from 87.1% wd on Group 7 to 0% wd on Group 5 (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 and group 5'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 13 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Part 3: Power Escalation Test 3.0 Introduction and Summary The Oconee 3 Cycle 27 Power Escalation Test was performed between June 7th, 2012 and June 9th, 2012 per station procedure PT/0/A/08 11/001. Testing was performed at 11 % Full Power (FP), 19% FP, 40% FP, 47% FP, 73% FP and 100% FP to verify nuclear parameters upon which the Oconee 3 Cycle 27 core design, safety analysis and Technical Specifications are based. The following tests and verifications were performed: (a) Initial Core Symmetry Check at 19% FP (Enclosure 7.0);(b) NSSS Heat Balance at 19% FP, 73% FP, and 100% FP (Enclosure 4.0);(c) Incore Detector Checkout at 11% FP, 40% FP, and 100%FP;(d) Power Imbalance Detector Correlation Slope Measurement at 73% FP;(e) Core Power Distribution at 47% FP, and 100% FP (Enclosures 5.0 through 5.3 and 6.0);(f) All-Rods-Out Critical Boron Concentration at 100% FP (Enclosure 1.0).The unit reached the Low Power Testing (LPT) plateau at 04:56 on 06/07/12.

Testing at the LPT plateau was completed at 12:48 on 06/07/12.

The unit reached the Intermediate Power Testing (IMPT) plateau at 05:00 on 06/08/12.

Testing at the IMPT plateau was completed at 12:23 on 06/08/12.

The unit reached the Full Power Testing (FPT) plateau at 20:02 on 06/08/12.

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 15:09 on 06/14/12.

Power Escalation Testing was declared complete at 15:20 on 06/14/12.3.1 NSSS Heat Balance/RCS Flow Verification Off-line (non-OAC) secondary heat balance calculations were performed at 19% FP, 73%FP and 100% FP. An off-line primary heat balance was performed at 100% FP. These tests verified the accuracy of the on-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 greater than the Page 14 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Part 3: Power Escalation Test 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 19%. Core Power Distribution tests were conducted at 47% 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 and Control of Incore Instrumentation Signals) was performed at 11% FP, 40% FP and 100% FP to identify and evaluate erroneous Self Powered Neutron Detector signals.The results of the initial core symmetry check which occurred at 19% 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 47% 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 14 incore imbalance Page 15 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Part 3: Power Escalation Test points (updates/measurements) which ranged between -10.56% and +0.45% 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 16 of 26 Oconee 3 Cycle 27 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 1.3 EFPD Gp 7 @ 87% wd Gp 8 @ 35% wd Gp 7 @ 87.1% wd Gp 7 @ 90.1% wd 1933 ppmB Gp 8 @ 35% wd Gp 8 @ 35% wd 1934 ppmB 1405 ppmB Final State:@ EARO Gp 4 @ 86% wd Gp 8 @ 35% wd 1526 ppmB MEASURED 1944 ppmB 1372 ppmB -0.00699 %"k/k ppmB VALUE PREDICTED 1956 ppmB 1389 ppmB -0.00677 %Ak/k ppmB VALUE A DEVIATION

+12 ppmB* +17 ppmB* -3.18°**ACCEPTANCE

+15% dev. from CRITERIA Predicted

+50 ppmB Predicted

+/-50 ppmB predicted* (Predicted -Measured)

• • (Predicted-Measured)

• 100 Measured Page 17 of 26 Oconee 3 Cycle 27 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 -0.8921 -0.8980 +0.7 + 15% Deviation Integral Worth Gp 6 -0.8649 -0.9240 +6.8 + 15% Deviation Integral Worth Gp 5 -1.0883 -1.0930 +0.4 + 15% Deviation Integral Worth Gp 5, 6, & 7 -2.8453 -2.9150 +2.5 + 10% Deviation Integral Worth* % Dev. = Predicted

-Measured

• 100 Measured Page 18 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Enclosure 3.0 REACTIVITY COEFFICIENTS PARAMETER CONDITIONS MEASURED PREDICTED DEVIATION ACCEPTANCE VALUE VALUE (Meas-Pred)

CRITERIA Hot Zero Power Tave=533.1 F -0.15556 E-4 Ak -0.14317 E-4 Ak -0.01239 E-4 Ak Measured -Predicted

=Temperature Gp 7 @ 86.9% wd k OF k OF k OF +0.2E-4 Ak Coefficient Gp 8 @ 35% wd k OF (ARO) 1934 ppmB Hot Zero Power Tave=533.1 F +0.00994 E-4 Ak +0.02234 E-4 Ak -0.01239 E-4 Ak Measured -Predicted

=Moderator Gp 7 @ 86.9% wd k °F k OF k OF +0.2E-4 Ak Temperature Gp 8 @ 35% wd k OF Coefficient 1934 ppmB (ARO) and Measured <+0.5E-4 Ak k OF Page 19 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Enclosure 4.0 NSSS HEAT BAIANCE/RCS FLOW VERIFICATION Test Plant Plant OfflineI OfflineI 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 19.13 19.19 19.09 19.11 114.43 IMPT 72.36 72.99 72.36 72.91 113.66 FPT 99.31 99.89 99.48 99.81 113.51'Calculated by the POWCALC SDQA spreadsheet.

2Required to be > Core Operating Limit Report RCS flow of 108.5 % Design Flow (DF)Page 20 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Enclosure 5.0 RADIAL PEAKING FACTORS AT IMPT 8 9 10 11 12 13 14 15 H 1,1,Gp4 2,2 3,4,Gp3 4,10 5,14,Gp7 6,21 7,30,Gp6 8,37 1.13 1.36 1.27 1.25 1.02 1.11 1.12 0.41 1.12 1.31 1.23 1.21 1.04 1.13 1.14 0.40 1.0% 4.0% 3.4% 3.0% -2.2% -1.4% -1.9% 2.2%9.3,Gp3 1.31 1.28 2.1%10,6+8 1.33 1.30 1.9%11 ,Inner,Gpl 1.21 1.21 0.2%12,15+20 1.22 1.23-0.9%13,22+29,Gp 5 1.15 1.17-2.0%14,31+36 1.11 1.13-1.0%15,45 0.40 0.41-1.5%K Predicted Measured% Dev 16,12,Gp6 1.25 1.24 0.8%17,17+18 1.27 1.24 3.0%18,24+27,Gp 8 1.15 1.14 0.9%19,Outer 1.21 1.22-0.8%20,38+44,Gp 4 1.07 1.11-3.2%21,46 0.30 0.29 3.9%L 22,26,Gp5 1.20 1.21-0.6%23,33+34 1.20 1.21-0.6%24,40+42,Gp 2 1.19 1.21-1.4%25,49 0.53 0.53-0.5%M.4 .4 .4 26,41 ,Gp7 1.03 1.04-0.5%27,48 0.99 0.99 0.5%28,51 0.29 0.30-2.9%N% Dev. = Predicted

-Measured

• 100 Measured 29.52 0.38 0.39-2.8%0 Core Conditions Power 47 %FP Group 5 100% wd Group 6 100%wd Group 7 52% wd Group 8 35% wd Incore Imbalance

-8.35 RCS Boron 1666 ppmB Max 1/8 Core % Deviation is +4.0% at H09 Acceptance criteria:

<+15% of Predicted Min 1/8 Core % Deviation is -3.2% at L14 Acceptance criteria:

>-15% of Predicted Maximum Peak Deviation is -4.0% Acceptance Criteria:

<+5% of Predicted Root Mean Square of Deviations is 2.8% Acceptance Criteria:

<7.5%Page 21 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Enclosure 5.1 TOTAL PEAKING FACTORS AT IMPT 8 9 10 -11 12 13 14 15 H 1,1,Gp4 2,2 3,4,Gp3 4,10 5,14,Gp7 6,21 7,30,Gp6 8,37 1.38 1.69 1.60 1.66 1.57 1.54 1.51 0.54 1.41 1.64 1.55 1.62 1.58 1.51 1.52 0.52-2.1% 2.8% 3.1% 2.2% -0.7% 1.7% -0.8% 3.4%9,3,Gp3 1.62 1.58 2.6%10,6+8 1.67 1.68-0.6%11 ,Inner,Gpl 1.59 1.57 1.4%12,15+20 1.67 1.69-1.1%13,22+29,Gp 5 1.55 1.56-0.1%14,31+36 1.50 1.52-0.8%15,45 0.53 0.54-1.3%K______ ______ 4 4------+Predicted Measured% Dev 16,12,Gp6 1.60 1.61-0.9%17,17+18 1.67 1.65 1.6%18,24+27,Gp 8 1.58 1.60-1.2%19,Outer 1.64 1.69-2.9%20,38+44,Gp 4 1.46 1.54-5.2%21,46 0.40 0.38 4.9%L 22,26,Gp5 1.64 1.61 1.8%23,33+34 1.72 1.74-1.3%24,40+42,Gp 2 1.69 1.74-3.1%25,49 0.73 0.73-0.6%M________ ________ I. I.26,41,Gp7 1.70 1.72-1.2%27,48 1.50 1.54-2.7%28,51 0.41 0.40 3.4%N% Dev. = Predicted

-Measured

• 100 Measured 29,52 0.57 0.58-2.4%0 Core Conditions Power 47%FP Group 5 100% wd Group 6 100%wd Group 7 52% wd Group 8 35% wd Incore Imbalance

-8.35 RCS Boron 1666 ppmB Max 1/8 Core % Deviation is +4.9% at LI5 Acceptance criteria:

<+20% of Predicted Min 1/8 Core % Deviation is -5.2% at L14 Acceptance criteria:

>-20% of Predicted Maximum Peak Deviation is +1.3% Acceptance Criteria:

<+7.5% of Predicted Page 22 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Enclosure 5.2 RADIAL PEAKING FACTORS AT FPT 8 9 10 11 12 13 14 15 H 1,1,Gp4 2,2 3,4,Gp3 4,10 5,14,Gp7 6,21 7,30,Gp6 8,37 1.06 1.27 1.20 1.23 1.15 1.14 1.11 0.42 1.06 1.24 1.19 1.20 1.15 1.15 1.12 0.41 0.1% 2.5% 1.1% 2.2% 0.2% -1.0% -1.3% 1.5%9,3,Gp3 1.22 1.21 0.9%10,6+8 1.24 1.25-0.2%11,1nner,Gpl 1.18 1.19-0.2%12,15+20 1.22 1.23-0.8%13,22+29,Gp 5 1.15 1.17-2.1%14,31 +36 1.10 1.11-0.8%15,45 0.41 0.42-2.1%K+ +--------------F 4~ +/- 18,24+27,Gp Predicted Measured%Dev 16,12,Gp6 1.19 1.20-0.7%17,17+18 1.23 1.21 1.9%18,24+27,Gp 8 1.14 1.13 1.1%19,Outer 1.19 1.19-0.1%20,35+44,Gp 4 1.06 1.08-2.2%21,46 0.31 0.30 3.0%L 22,26,Gp5 1.20 1.22-1.3%23,33+34 1.24 1.24 0.6%24,40+42,Gp 2 1.21 1.21 0.4%25,49 0.55 0.55-0.7%M______ 4 +26,41 ,Gp7 1.21 1.19 1.8%27,48 1.07 1.06 1.3%28,51 0.32 0.32-0.9%N% Dev. = Predicted

-Measured

• 100 Measured 29,52 0.43 0.44-3.4%0 Core Conditions Power 100 %FP Group 5 100% wd Group 6 100%wd Group 7 92% wd Group 8 35% wd Incore Imbalance

-2.68 RCS Boron 1358 ppmB Max 1/8 Core % Deviation is +3.0% at L15 Acceptance criteria:

<+15% of Predicted Min 1/8 Core % Deviation is -3.4% at 013 Acceptance criteria:

>-15% of Predicted Maximum Peak Deviation is -2.1% Acceptance Criteria:

<+5% of Predicted Root Mean Square of Deviations is 2.3% Acceptance Criteria:

<7.5%Page 23 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Enclosure 5.3 TOTAL PEAKING FACTORS AT FPT 8 9 10 11 12 13 14 15 H 1,1,Gp4 2,2 3,4,Gp3 4,10 5,14,Gp7 6,21 7,30,Gp6 8,37 1.20 1.45 1.37 1.38 1.33 1.31 1.28 0.48 1.17 1.45 1.33 1.36 1.33 1.31 1.29 0.46 2.9% -0.1% 2.6% 1.5% -0.3% -0.3% -0.8% 3.9%9,3,Gp3 1.39 1.34 3.5%10,6+8 1.40 1.42-1.5%11,Inner,Gpl 1.34 1.32 1.2%12,15+20 1.39 1.40-0.7%13,22+29,Gp 5 1.31 1.31 0.2%14,31+36 1.27 1.28-0.2%15,45 0.47 0.47 0.6%K Predicted Measured%Dev 16,12,Gp6 1.34 1.36-1.5%17,17+18 1.39 1.38 1.2%18,24+27,Gp 8 1.32 1.33-0.5%19,Outer 1.38 1.41-2.1%20,38+44,Gp 4 1.24 1.29-4.0%21,46 0.35 0.34 4.1%L+I. + + +22,26,Gp5 1.38 1.36 1.7%23,33+34 1.45 1.46-0.2%24,40+42,Gp 2 1.42 1.44-1.2%25,49 0.63 0.63-0.3%M 26,41 ,Gp7 1.44 1.43 0.9%27,48 1.28 1.29-0.7%28,51 0.37 0.38-3.4%N% Dev. = Predicted

-Measured

• 100 Measured 29,52 0.50 0.50-0.8%0 Core Conditions Power 100 %FP Group 5 100% wd Group 6 100%wd Group 7 92% wd Group 8 35% wd Incore Imbalance

-2.68 RCS Boron 1358 mpmB Max 1/8 Core % Deviation is +4.1% at LI 5 Acceptance criteria:

<+20% of Predicted Min 1/8 Core % Deviation is -4.0% at L14 Acceptance criteria:

>-20% of Predicted Maximum Peak Deviation is +0.2% Acceptance Criteria:

<+7.5% of Predicted Page 24 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Enclosure 6.0 CORE POWER DISTRIBUTION DATA

SUMMARY

AT IMPT AND FPT PLATEAUS Power Level 47 100 (% FP)Group 7/8 52/35 92/35 Positions

(% wd)RCS Boron 1666 1358 Concentration (ppmB)Incore Imbalance

-8.35 -2.68 (% FP)Page 25 of 26 Oconee 3 Cycle 27 STARTUP TESTING REPORT Enclosure 7.0 Core Symmetry Results at LPT% Deviation=

Highest-Lowest/AVG

• 100%Detector Number Assembly Power Detector Number% Dev 6 8 AVG 5 7 9 11 13 16 19 25 AVG 3.78 3.54 3.66 3.37 3.36 3.31.3.32 3.27 3."26 3.35 3.32 6.56 3.31 24 27 AVG 23 28 32 35 39 43 47 50 AVG 44 38 AVG 33 34 AVG 42 40 AVG Assembly Power 3.08 3.06 3.07 3.35* 3.31 3.40 S 3..25 3.09*: 3.10 3.12 3.31 3.24 2.85 3.01 2.93 3.12 3.12 3.12 3.13 3.10 3.12 0.65 9.56% Dev 15 20 AVG 29 22 AVG 31 36 AVG 17 18 AVG 3.29 3.29 3.09 3.16 3.13 2.99:2.98 2.99 3.38 3.39 3.39 0.30 5.46 0.00 0.96 2.24 0.34 0.30 Page 26 of 26