ML18192A913

Revision 27 to Updated Final Safety Analysis Report, Chapter 4, Appendix 4A, Tables

ML18192A913
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Site:	Oconee
Issue date:	12/31/2017
From:	Duke Energy Carolinas
To:	Office of Nuclear Reactor Regulation
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Text

Oconee Nuclear Station UFSAR Appendix 4A. Tables Appendix 4A. Tables

Oconee Nuclear Station UFSAR Table 4-1 (Page 1 of 5)

Table 4-1. Core Design, Thermal, and Hydraulic Data Reactor Rated Heat Output, MWt 2,568 Vessel Coolant Inlet Temperature, 100% power, F 557.8 Vessel Coolant Outlet Temperature, 100% power, F 602.4 Core Outlet Temperature, 100% power 606.2 Core Operating Pressure, psia 2200 Reactor Coolant flow, % design flow 108.5 Note: The following parameters specified below are based on the fuel assembly nomenclature.

Core and Fuel Assemblies 1 Total Number of Fuel Assemblies in Core 177 Number of Fuel Rods per Fuel Assembly 208 Number of Control Rod Guide Tubes per Assembly 16 Number of In-Core Instrumentation Positions per Fuel Assembly 1 Fuel Rod Outside Diameter, in.

Mk-B10 0.430 Mk-B11, Mk-B11A 0.416 Mk-B-HTP 0.430 Clad Thickness, in.

Mk-B10 to B10E 0.0265 Mk B-10F, Mk B-10G, and Mk B-10L 0.0250 Mk-B11, Mk-B11A 0.0240 Mk-B-HTP 0.0250 Fuel Rod Pitch, in. 0.568 Fuel Assembly Pitch Spacing, in. 8.587 Fuel Assembly Overall Length (Typical), in.

Mk-B2 to B10L, Mk-B11 and Mk-B11A 165.695 Mk-B-HTP 165.895 Unit Cell Metal/Water Ratio (Volume Basis) 0.82 Fuel Material UO2 (31 DEC 2009)

Oconee Nuclear Station UFSAR Table 4-1 (Page 2 of 5)

Form Dished-End, Cylindrical Pellets Pellet Diameter, in.

MK B-10 to B-10E 0.3700 MK B-10F, MK B-10G, and MK B-10L 0.3735 Mk-B11, Mk-B11A 0.3615 Mk-B-HTP 0.3735 Active Length, in.

MK B10 to B-10E 140.5 - 140.7 MK B-10F, MK B-10G, and MK B-10L 142.3 Mk-B11, Mk-B11A 143.05 Mk-B-HTP 143.0 Density, % of Theoretical Mk B-10 to B-10E 95.0 Mk B-10F, Mk B-10G, and Mk B-10L 96.0 Mk-B11, Mk-B11A 96.0 Mk-B-HTP 96.0 2

Heat Transfer and Fluid Flow at Rated Power Total Heat Transfer Surface in Core, ft2 Mk-B10 to B-10E 48,525 Mk-B10F, Mk-B10G and Mk-B10L 49,147 Mk-B11, Mk-B11A 47,797 Mk-B-HTP 49,389 2

Average Heat Flux, Btu/hr-ft Mk-B10 to B-10E 175.7 x 103 Mk-B10F, Mk-B10G and Mk-B10L 173.5 x 103 Mk-B11, Mk-B11A 178.4 x 103 Mk-B-HTP 177.5 x 103 Maximum Heat Flux, Btu/hr-ft2 Mk-B10 to B-10E 452 x 103 Mk-B10F, Mk-B10G and Mk-B10L 446 x 103 Mk-B11, Mk-B11A 458 x 103 MK-B-HTP 456 x 103 (31 DEC 2009)

Oconee Nuclear Station UFSAR Table 4-1 (Page 3 of 5)

Average Power Density in Core, kW/ l Mk-B10 to B-10E 85.46 Mk-B10F, Mk-B10G and Mk-B10L 84.38 Mk-B11, Mk-B11A 83.94 Mk-B-HTP 83.97 Average Thermal Output, kW/ft of Fuel Rod Mk-B10, Mk-B10D, and Mk-B10E 5.8 Mk-B10F, Mk-B10G, Mk-B10L, Mk-B11 and Mk-B11A 5.7 Mk-B-HTP 5.7 Maximum Thermal Output, kW/ft of Fuel Rod Mk-B10, Mk-B10D and Mk-B10E 14.9 Mk-B10F, Mk-B10G and Mk-B10L 14.7 Mk-B11, Mk-B11A 14.6 Mk-B-HTP 14.6 Average Core Fuel Temperature, F Mk-B10,Mk-B10D and Mk-B10E 1215 Mk-B10F, Mk-B10G and Mk-B10L 1162 Mk-B11, Mk-B11A 1175 Mk-B-HTP 1162 Total Reactor Coolant Flow, lb/hr (108.5% Design Flow) 142.3 x 106 Core Flow Area (Effective for Heat Transfer), ft2 Mk-B10 though Mk-B10L 49.645 Mk-B11, Mk-B11A 52.032 Mk-B-HTP 49.620 Core Coolant Average Velocity, fps (108.5% Design Flow)

Mk-B10 through Mk-B10L (7.00% Bypass Flow) 15.94 Mk-B11, Mk-B11A (7.50% Bypass Flow) 15.13 Mk-B-HTP (6.49% Bypass Flow) 16.04 Power Distribution Maximum/Average Power Ratio, Radial x Local (Fh Nuclear) 1.714 Maximum/Average Power Ratio, Axial (Fz Nuclear) 1.5 cos Overall Power Ratio (Fq Nuclear) 2.57 Power Generated in Fuel and Cladding, % 97.3 (31 DEC 2009)

Oconee Nuclear Station UFSAR Table 4-1 (Page 4 of 5)

Hot Channel Factors Power Peaking Factor (FQ)

Mk-B10, Mk-B10D and Mk-B10E 1.0107 Mk-B10F, Mk-B10G and Mk-B10L 1.0132 Mk-B11, Mk-B11A 1.0133 Mk-B-HTP 1.0132 Hot Spot Maximum/Average Heat Flux Ratio (Fq nuc and mech)

Mk-B10, Mk-B10D and Mk-B10E 2.71 Mk-B10F to B10L ,Mk-B11 and Mk-B11A 2.72 Mk-B-HTP 2.64 Flow Area Reduction Factor(FA) for MK-B10 through Mk-B10L, Mk-B11, Mk-B11A, and MK-B-HTP Unit/CRGT Bundle Cells 0.98 IGT Bundle Cells 0.97 DNB Data Design Overpower (% Rated Power) 112 CHF Correlation Mk-B10 through Mk-B10L BWC Mk-B11, Mk-B11A BWU-Z with FB11 Multiplier Mk-B-HTP BHTP DNB Limit - Non SCD Mk-B10 through Mk-B10L 1.18 Mk-B11, Mk-B11A 1.19 Mk-B-HTP Proprietary DNB Limit - SCD Mk-B10 through Mk-B10L 1.43 Mk-B11, Mk-B11A 1.33 Mk-B-HTP 1.34 Typical minimum DNBR Mk-B10 through Mk-B10L 2.47 Mk-B11, Mk-B11A 2.76 Mk-B-HTP 2.58 (31 DEC 2009)

Oconee Nuclear Station UFSAR Table 4-1 (Page 5 of 5)

Note:

1. Parameters are based on cold dimensions for each of the respective fuel assembly designs, as applicable.

2. Based on reference peaking and active fuel length for each fuel rod type specified at BOL conditions.

(31 DEC 2009)

Oconee Nuclear Station UFSAR Table 4-2 (Page 1 of 2)

Table 4-2. Fuel Assembly Components Item Material Dimensions (In)

Fuel Clad (in.)

Mk B-10 through B10E Zircaloy-4 0.430 OD x 0.377 ID Mk B-10F through Mk B-10L Zircaloy-4 0.430 OD x 0.380 ID Mk-B11, Mk-B11A M5 0.416 OD x 0.368 ID Mk-B-HTP M5 0.430 OD x 0.380 ID Fuel Rod Length (Typical), in.

Mk-B10 to B10L 154.16 Mk-B11, Mk-B11A 155.30 Mk-B-HTP 155.00 Fuel Assembly:

Overall Length B10, B11 and B11A (Typical), 165.695 in.

Overall Length B-HTP (Typical), in. 165.895 Control Rod Guide Tube (in.)

Mk-B10 to Mk-B10L Zircaloy-4 0.530 OD x 0.016 wall Mk-B11 Zircaloy-4 0.530 OD x 0.016 wall Mk-B11A M5 0.530 OD x 0.016 wall Mk-B-HTP M5 0.530 OD x 0.016 wall Instrumentation Tube (in.)

Mk-B10 to B10L Zircaloy-4 0.493 OD x 0.441 ID Mk-B11, Mk-B11A Zircaloy-4 0.493 OD x 0.441 ID Mk-B-HTP M5 0.493 OD x 0.400 ID End Fittings Mk-B10 to B10L Stainless Steel (Castings)

Mk-B11, Mk-B11A Stainless Steel Mk-B-HTP Stainless Steel End Spacer Grid Mk B-10 to Mk B-10L Inconel-718 0.020 thick exteriors 0.018 thick interiors (31 DEC 2009)

Oconee Nuclear Station UFSAR Table 4-2 (Page 2 of 2)

Item Material Dimensions (In)

Mk-B11, Mk-B11A Inconel-718 0.020 thick exteriors 0.018 thick interiors Mk-B-HTP Inconel-718 Intermediate Spacer Grid 0.025 thick exteriors 0.013 thick exteriors MK-B10 to MK-B10L Zircaloy-4 0.021 thick exteriors 0.018 thick interiors Mk-B11, Mk-B11A Zircaloy-4 0.021 thick exteriors 0.018 thick interiors Mk-B-HTP M5 0.026 thick exteriors 0.014 thick interiors Spacer Sleeve Mk-B10 to B10L Zircaloy-4 0.554 OD x 0.502 ID Mk-B11, Mk-B11A Zircaloy-4 0.554 OD x 0.502 ID Mk-B-HTP M5 0.554 OD x 0.502 ID Fuel Assembly Design: Fuel Assembly Burnup Mk B-10 through Mk B-10L, Mk-B11, Mk-B11A, Consistent with a Maximum and Mk-B-HTP rod burnup of 62,000 MWD/MTU (Reference 15) of Section 4.2.5 Note:

1. Typical geometry. Batch specific is reported in individual reload reports.

2. Mk-B9 fuel rods are used in Mk-B10 and Mk-B10D/E fuel assembly designs. Mk-B10 design fuel rods are used in Mk-B10F/G/L fuel assembly designs (See Table 4-23).

(31 DEC 2009)

Oconee Nuclear Station UFSAR Table 4-3 (Page 1 of 2)

Table 4-3. Nuclear Design Data Oconee I Oconee II Oconee III Fuel Assembly Volume Fractions (Mk-B11, Mk-B11A)

Fuel 0.291 0.291 0.291 Moderator 0.607 0.607 0.607 Zircaloy (includes M5 cladding) 0.091 0.091 0.091 Void 0.011 0.011 0.011 1.000 1.000 1.000 (Mk-B-HTP)

Fuel 0.310 0.310 0.310 Moderator 0.582 0.582 0.582 Zircaloy (includes M5 cladding) 0.097 0.097 0.097 Void 0.011 0.011 0.011 1.000 1.000 1.000 Total UO2 (Metric Tons)

First Cycle 94.1 93.1 93.1 Deleted Row per 2008 Update Equilibrium (Mk-B11, Mk-B11A) 92.2 92.2 92.2 1

Equilibrium (Mk-B-HTP) 98.2 / 97.8 98.2 / 97.8 98.2 / 97.8 Core Dimensions, in.

Equivalent Diameter 128.9 128.9 128.9 Deleted Row per 2008 Update Nominal Active Height (Mk-B11, B11A) 143.1 143.1 143.1 Nominal Active Height (Mk-B-HTP) 143.0 143.0 143.0 Unit Cell H2O to U Atomic Ratio (Fuel Assembly)

Cold 2.85 2.88 2.88 Hot 2.04 2.06 2.06 Full-Power Lifetime, Days First Cycle 309 440 479 Equilibrium Cycle2 480 / 700 480 / 700 480 / 700 Fuel Irradiation, MWD/MTU First Cycle Average 9,582 14,396 14,978 (31 DEC 2012)

Oconee Nuclear Station UFSAR Table 4-3 (Page 2 of 2)

Oconee I Oconee II Oconee III Deleted Row per 2008 Update Equilibrium Cycle Average (Mk-B11 & B11A) 15,172 15,172 15,172 Equilibrium Cycle Average (Mk-B-HTP)3 14,241 / 20,854 14,241 / 20,854 14,241 / 20,854 Fuel Loading, wt% U-235 Core Average First Cycle 2.10 2.62 2.56 First Reload Average 3.15 2.64 2.54 Typical Core Average Equilibrium Cycle Nominal Loading3 4.00 / 4.74 4.00 / 4.74 4.00 / 4.74 3

Radial-Zoned Loading 3.70 / N/A 3.70 / N/A 3.70 / N/A Axial Blanket Loading 2.00-2.50 2.00-2.50 2.00-2.50 Control Data Control Rod Material Ag-In-Cd Ag-In-Cd Ag-In-Cd Number of Full Length CRA's 61 61 61 Control Rod Cladding Material INC-625 INC-625 INC-625 APSR Material INC-600 INC-600 INC-600 Number of APSR's 8 8 8 APSR Cladding Material SS 304 SS 304 SS 304 Note:

1. The first value is for LEU HTP fuel. The second value is for Gadolinia-bearing HTP fuel.

2. 480 EFPD is the equilibrium 18 month cycle length; 700 EFPD is the equilibrium 24 month cycle length.

3. The first value is typical of 18 month cycles and the second value is typical of 24 month cycles.

(31 DEC 2012)

Oconee Nuclear Station UFSAR Table 4-4 (Page 1 of 1)

Table 4-4. Typical Fuel Cycle Excess Reactivity, HFP Samarium 18 Month Cycle Excess Reactivity (%k/k) at Specified Condition1 Cycle Time 70°F, No (EFPD) Xe 300°F, No Xe HZP, No Xe HFP, No Xe 0 18.58 17.33 15.10 13.11 50 17.88 16.65 14.35 12.43 100 17.18 15.96 13.59 11.48 200 15.39 14.19 11.64 9.24 300 13.61 12.43 9.69 6.99 450 10.66 9.44 6.57 3.38 480 9.92 8.68 5.72 2.59 24 Month Cycle Excess Reactivity (%k/k) at Specified Condition2 Cycle Time 60°F, No (EFPD) Xe 300°F, No Xe HZP, No Xe HFP, No Xe 0 16.77 15.57 13.06 11.07 50 16.16 15.00 12.54 10.55 100 15.55 14.42 12.02 10.03 200 14.93 13.87 11.44 9.37 300 14.31 13.32 10.86 8.70 400 13.36 12.35 9.74 7.44 500 12.05 11.01 8.31 5.83 693 8.92 7.86 4.99 2.50 Note:

1. 18 Month Data from 0 to 300 EFPD were derived with CRG-8 at 30% WD, and data from 450 to 480 EFPD were derived with CRG-8 at 100% WD.

2. 24 Month Data from 0 to 500 EFPD were derived with CRG-8 at 35%WD, and data at 693 EFPD were derived with CRG-8 at 100% WD.

(31 DEC 2012)

Oconee Nuclear Station UFSAR Table 4-5 (Page 1 of 1)

Table 4-5. Effective Multiplication Factor keff Single Fuel Assembly1 Hot 0.77 Cold2 0.87 Note:

1. Based on an enrichment of 3.5 weight percent.

2. A center-to-center assembly pitch of 21 in. is required for this keff in cold, unborated water with no xenon or samarium.

(31 DEC 2000)

Oconee Nuclear Station UFSAR Table 4-6 (Page 1 of 1)

Table 4-6. Shutdown Margin Calculation for Typical Oconee Fuel Cycle 18 Month Cycle BOC, %k/k EOC, %k/k Available Rod Worth Total rod worth, HZP 7.76 8.65 Worth reduction due to burnup of poison material -0.40 -0.40 Maximum stuck rod, HZP -1.17 -1.55 Net worth 6.19 6.70 Less 10% uncertainty 0.62 0.67 Total available worth 5.57 6.03 Required Rod Worth Power deficit, HFP to HZP 1.34 3.01 Max allowable inserted rod worth 0.40 0.53 Total required worth 1.74 3.54 Shutdown margin (total available worth minus total required worth) 3.83 2.49 24 Month Cycle BOC, %k/k EOC, %k/k Available Rod Worth Total rod worth, HZP 8.11 8.65 Worth reduction due to burnup of poison material -0.40 -0.40 Maximum stuck rod, HZP -1.39 -1.50 Net worth 6.31 6.75 Less 10% uncertainty 0.63 0.67 Total available worth 5.68 6.07 Required Rod Worth Power deficit, HFP to HZP 1.55 3.02 Max allowable inserted rod worth 0.36 0.48 Total required worth 1.91 3.50 Shutdown margin (total available worth minus total required worth) 3.77 2.57 Note:

1. Required shutdown margin is 1.00% k/k.

2. The power deficit calculation was done with a three-dimensional code.

(31 DEC 2012)

Oconee Nuclear Station UFSAR Table 4-7 (Page 1 of 1)

Table 4-7. Moderator Temperature Coefficient (For the First Cycle)

Conditions Oconee I Oconee II Oconee III

1. Core size, no. fuel assemblies 177 177 177

2. Core average enrichment w/o U-235 2.10 2.62 2.56

3. Avg Power density, MWt/assembly 14.508 14.508 14.508

4. Initial critical conditions (hot full power, clean)

a. Boron concentration, ppm 1200 1341 1291

b. CRA inserted worth, % k/k a 2.1 1.0 1.0

c. Burnable poison worth, % k/k 0.0 4.0 4.0

d. Moderator temperature coefficient, +0.27 +0.03 -0.01

[10-4 (k/k)/F]b

5. Threshold value of moderator temperature +1 >+1 >+1 coefficient, [10-4 (k/k)/F]c

6. Moderator temperature coefficient at hot -0.30 -0.50 -0.54 full power, equilibrium xenon, BOL,

[10-4 (k/k)/F]b

7. Most positive value of moderator +0.9 +0.9 +0.9 temperature coefficient used in safety analysis,

[10-4 (k/k)/F]c

8. Most negative value of moderator -3.5 -3.5 -3.5 temperature coefficient used in safety analyses

[10-4 (k/k)/F]c Note:

a. Inserted rod worth shown for Oconee 1 results from 3-D calculations and reflects transient group worth, APSR's, and partial Doppler insertion.

b. See Section 4.3.2.4.4.

c. Value is applicable to current safety analyses.

(31 DEC 2009)

Oconee Nuclear Station UFSAR Table 4-8 (Page 1 of 1)

Table 4-8. BOL Distributed-Temperature Moderator Coefficients, 100% Power, 1200 ppm Boron (O1C01)

Tout (°F) m ( x10 4 )

Type of Temperature Change Tin (°F) °F m

1. Tinconstant, Tout change 554.03 554.03 606.90 609.33 +0.14

2. Tin and Tout change 554.03 555.00 606.90 607.73 +0.27

3. Tin change Tout constant 554.03 551.20 606.90 606.79 +0.36 (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 4-9 (Page 1 of 1)

Table 4-9. BOL Distributed-Temperature Moderator Coefficients, vs Power, No Xenon 4

m ( x 10 )

°F m Typical 18 Month Reload

% Power Oconee 1, Cycle 1 Cycle

(% Full Power) (1200 ppm) (Boron Search) 0 - +0.44 (2010 ppm) 15 +0.42 +0.13 (1991 ppm) 60 +0.30 -0.08 (1905 ppm) 95 - -0.23 (1845 ppm) 100 +0.27 -0.25 (1837 ppm)

Typical 24 Month Reload

% Power Oconee 1, Cycle 1 Cycle

(% Full Power) (1200 ppm) (Boron Search) 0 -- +0.08 (1975 ppm) 15 +0.42 --

20 -- -0.36 (1915 ppm) 60 +0.30 --

80 -- -0.64 (1808 ppm) 100 +0.27 -0.73 (1771 ppm)

(31 DEC 2012)

Oconee Nuclear Station UFSAR Table 4-10 (Page 1 of 1)

Table 4-10. BOL Distributed-Temperature Moderator Coefficient, 100% Full Power

( x 10 4 )

m °F m 0 Days (NoXe) 4 Days (EqXe)

Oconee 1, Cycle 1 +0.27 (1200 ppm) -0.30 (920 ppm)

Typical 18 Month Reload Cycle -0.25 (1837 ppm) -0.59 (1481 ppm)

Typical 24 Month Reload Cycle -0.73 (1771 ppm) -1.07 (1374 ppm)

(31 DEC 2012)

Oconee Nuclear Station UFSAR Table 4-11 (Page 1 of 1)

Table 4-11. Power Coefficients of Reactivity p ( x 10 4 )

%P Oconee 1, Cycle 1 Typical 18 Month Reload Power (% Full Power) (1200 ppm) Cycle (Boron search) 15 -2.04 -1.24 (1991 ppm) 60 -1.56 -1.10 (1905 ppm) 100 -1.11 -1.07 (1837 ppm)

Oconee 1, Cycle 1 Typical 24 Month Reload Power (% Full Power) (1200 ppm) Cycle (Boron search) 15 -2.04 -1.43 (1930 ppm) 60 -1.56 -1.35 (1842 ppm) 100 -1.11 -1.32 (1774 ppm)

(31 DEC 2012)

Oconee Nuclear Station UFSAR Table 4-12 (Page 1 of 1)

Table 4-12. pH Characteristics 7

Li, ppm Tmod, °F Boron Concen., ppm pH Units 0.5 70 1,800 5.0 2.0 70 1,800 5.6 0.5 580 1,200 7.0 2.0 580 1,200 7.5 0.5 580 17 7.2 2.0 580 17 7.8 0.5 70 17 7.9 2.0 70 17 8.5 (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 4-13 (Page 1 of 1)

Table 4-13. Design Methods Unit Initial Cycle Design Methods 1 16 Section 4.3.3.1.1 2 15 Section 4.3.3.1.1 3 16 Section 4.3.3.1.1 (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 4-14 (Page 1 of 1)

Table 4-14. Deleted per 1999 Update (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 4-15 (Page 1 of 1)

Table 4-15. Deleted per 1997 Update (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 4-16 (Page 1 of 1)

Table 4-16. Internals Vent Valve Materials Valve Part Name Material and Form Material Specification No.

Valve Body 304 S.S. Casting 1 ASTM A351-CF8 Valve Disc 304 S.S. Casting 1 ASTM A351-CF8 2

Disc Shaft 431 S.S. Bar ASTM A276 Type 431 Cond.

T Shaft Bushings Stellite No. 6 Retaining Rings (Top and 15-5 pH (H1100) S.S. AMS 5658 Bottom) forgings Ring Jack Screws A-286 Superalloy S.S. 3 AMS 5737 C Jackscrew Bushings 431 S.S. Bar ASTM A276 Type 431 Cond.

A Misc. Fasteners, covers, 304 S.S. plate bar, etc. ASTM A240 ASTM A276 locking devices, etc.

Note:

1. Carbide solution annealed, Cmax 0.08%, Comax 0.2%

2. Heat treated and tempered to Brinnel Hardness Number (BHN) range of 290-320.

3. Heat treated to produce a BHN of 248 min.

The hinge assembly consists of a shaft, two valve body journal receptacles, two halve disc journal receptacles, and four flanged shaft journals (bushings). Loose clearances are used between the shaft and journal inside diameters, and between the journal outside diameters and their receptacles. The hinge assembly is shown and the clearance gaps are identified in Figure 4-30. The bushing clearances are listed in Table 4-17.

The valve disc hinge journal contains integral exercise lugs for remote operation of the disc with the valve installed in the core support shield.

(31 DEC 2000)

Oconee Nuclear Station UFSAR Table 4-17 (Page 1 of 2)

Table 4-17. Vent Valve Shaft & Bushing Clearances Clearance Gaps are illustrated in Figure 4-30 A. Cold Clearance Dimensions @ 70°F Bushing I.D. 1.500 to 1.505 Shaft O.D. 1.490 to 1.485

.010 to .020 clearance (Gaps 1, 2, 7 & 8)

Body I.D. 2.000 to 2.003 Bushing O.D. 1.997 to 1.995

.003 to .008 clearance (Gaps 3, 4, 5 & 6)

Bushing End Clearance Gaps 9 + 10 Body Lugs 5.752 to 5,75 Disc Hub 4.746 to 6 1.006 to 4,74

.996 to 2 0.10 to 1.01 4

.992 0.22 End Clearance (Gaps 9 + 10)

Bushing .249 x4=

Flange .248 x4= .996

.992 B. Hot Clearance Differential Change from 70 to 580°F Shaft: A286 9.8 x 106 in/in/F Bushing: Stellite #6 8.1 x 106 Bodies: CF8 Stainless 9.82 x 106 T = 580 - 70 = 510 Shaft D = DT = 1.5 (9.8 x 106) 510 .0075 Bushing I.D. = .0062 6

1.5 (8.1 x 10 ) .0013 decrease 510

Bushing O.D. = 2 (8.1 x 106) 510 = .0083 Body I.D. = 2 (9.82 x 106) 510 = .010

+.0017 increase Bushing Endplay Hot (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 4-17 (Page 2 of 2)

CF8 Body L = 1 (9.82 x 106) 510 .0050 Stellite # 6 Bushing Flange = .0041

= 1 (8.1 x 106) 510 .0009 increase

=

(31 DEC 2000)

Oconee Nuclear Station UFSAR Table 4-18 (Page 1 of 1)

Table 4-18. Control Rod Assembly Data Item Data Number of CRA 61 A. Standard CRA Design Number of Control Rods per Assembly 16 Outside Diameter of Control Rod, in. 0.440 Cladding Thickness, in. 0.021 Cladding Material Type 304 SS, Cold-Worked End Plug Material Type 304 SS, Annealed Spider Material SS Grade CF3M Poison Material 80% Ag, 15% In, 5% Cd Female Coupling Material Type 304 SS, Annealed Length of Poison Section, in. 134 Stroke of Control Rod, in. 139 B. Plant-Life CRA Design1 Number of Control Rods per Assembly 16 Outside Diameter of Control Rod, in. 0.441 Cladding Thickness, in. 0.023 Cladding Material Inconel 625 End Plug Material Inconel 625 Spider Material SS Grade CF3M Poison Material 80% Ag, 15% In, 5% Cd Female Coupling Material Type 304 SS, Annealed Length of Poison Section, in. 139 Stroke of Control Rod, in. 139 Note:

1. The plant-life CRA is prepressurized with Helium.

(31 DEC 2000)

Oconee Nuclear Station UFSAR Table 4-19 (Page 1 of 1)

Table 4-19. Axial Power Shaping Rod Assembly Data Item Data Gray APSR Design Number of Axial Power Shaping Rod Assemblies 8 Number of Axial Power Shaping Rods per Assembly 16 Outside Diameter of Axial Power Shaping Rod, in. 0.440 Cladding Thickness, in. 0.027 Cladding Material Type 304 SS, Stainless Steel Cold-Worked Plug Material Type 304 or Type 308 SS, Annealed Poison Material Inconel - 600 Spider Material SS Grade CF3M Female Coupling Material Type 304 SS, Annealed Length of Poison Section, in. 63 Stroke of Control Rod, in. 139 (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 4-20 (Page 1 of 1)

Table 4-20. Burnable Poison Rod Assembly Data Item Data Number of Burnable Poison Rods per Assembly 16 Outside Diameter of Burnable Poison Rod, in. 0.430 Cladding Thickness, in. 0.035 Cladding Material Zircaloy-4, Cold Worked End Cap Material Zircaloy-4, Annealed Poison Material B4C in. Al2O3 Length of Poison Section, in. 1 126 / 123.2 Spider Material SS Grade CF3M Coupling Mechanism Material Type 304 SS, Annealed Note:

1. The poison length was 126 in the feed fuel up through cycle O1C27. The length changed to 123.2 beginning with the feed fuel in O2C26 to align with the gadolinia-bearing fuel which was introduced in O2C26.

(31 DEC 2012)

Oconee Nuclear Station UFSAR Table 4-21 (Page 1 of 1)

Table 4-21. Control Rod Drive Mechanism Design Data Axial Power Shim Safety Shaping Type Roller Nut Drive Roller Nut Drive Quantity 61 8 Location Top-mounted Top-mounted Direction of Trip Down Does not trip Velocity of Normal (Run) Withdrawal and 30 30 Insertion, in./min.

Velocity of Jog Withdrawal and Insertion 3 3 in./min.

Maximum Travel Time for Trip 2/3 Insertion, sec 1.401 Drive has no trip function 3/4 Insertion, sec 1.521 Drive has no trip function Length of Stroke, in. 139 139 Design Pressure, psig 2,500 2,500 Design Temperature, °F 650 650 Weight of Mechanism (App.) 940 lb 940 lb Note:

1. These time values include rod motion only. The Technical Specification surveillance requirement for maximum control rod drop time includes, in addition, 0.14 seconds from the time the control rod drive breakers receive the signal to trip to the beginning of rod motion. This is appropriate since the elapsed time measured in the test begins with that signal to trip the CRD Breaker.

(31 DEC 2000)

Oconee Nuclear Station UFSAR Table 4-22 (Page 1 of 1)

Table 4-22. Fuel Assembly / APSR Compatibility Type of APSR Coupling- Spider Assembly Required for Mk-B10, Mk-B11, Mk-B11A and Plant and Unit Drive Type MK-B-HTP Fuel Designs Deleted row(s) per 2002 Update.

Oconee Unit 1&2 Type C APSR Drive2 Mk-B Standard OR Extended Coupling Oconee Unit 3 Type C APSR Drive Mk-B Standard OR Extended Coupling Note:

1. The length of the Mk-B Standard and Extended Coupling APSR Hubs is 7.0 in. (nom.) and 7.57 in. (nom.), respectively. The length equals the sum of the female coupling, spider, and lower hub B, which is the distance from the bottom seating surface to the top of the female coupling.

2. Type C APSR Drive has R4C position indicators and hydraulic tension closures.

(31 DEC 2013)

Oconee Nuclear Station UFSAR Table 4-23 (Page 1 of 1)

Table 4-23. Fuel Assembly Design Descriptions Assembly Cage Rod Clad Axial Zoned HDS 2 UEF 3 Debris Designation Design Desig Material Blanket Enrichment Design Attachment Filter n

Mk-B10 B10 B9 Zirc-4 No No Cruciform Lock Nut Plug/Grid Mk-B10D B10 B9 Zirc-4 1 No No Cruciform Lock Nut Plug/Grid Mk-B10E B10 B9 Zirc-4 Yes No Cruciform Lock Nut Plug/Grid Mk-B10F B10 B10 Zirc-4 Yes No Cruciform Lock Nut Plug/Grid Mk-B10G B10 B10 Zirc-4 Yes No Cruciform Quick Disconnect Plug/Grid Mk-B10L B10 B10 Zirc-4 Yes Yes Cruciform Quick Disconnect Plug/Grid Mk-B11 B11 B11 M5 Yes Yes Cruciform Quick Disconnect Plug/Grid Mk-B11A B11 B11 M5 Yes Yes Cruciform Quick Disconnect Plug/Grid Mk B-HTP HTP HTP M5 Yes Yes Cruciform Recon Crimp Fuel Guard Top Hat Nut Note:

1. Consumer's or Smud Cladding

2. HDS = Hold Down Spring

3. UEF = Upper End Fitting (31 DEC 2009)

Oconee Nuclear Station UFSAR Table 4-24 (Page 1 of 1)

Table 4-24. Design Information for Current Demonstration Programs vs Typical FAs Parameter WH-177 LTA Mk-B11A MK-B-HTP Hold-down Spring 3-leaf Cruciform Cruciform Rod Array 15 X 15 15 X 15 15 X 15 Rods per Assembly 208 208 208 Rod Pitch, in. 0.568 0.568 0.568 Fuel Weight (as UO2), lbs. 1149 1012 1080 Fuel Assembly weight (wet), lbs 1323 1304 1378 Number of Grids per Assembly 11 8 8 Composition of end grids Inconel 718 Inconel 718 Inconel 718 Intermediate Support Grids Yes No No Number of Guide Thimbles per Assembly 16 16 16 Composition of Guide Thimbles ZIRLOTM M5 M5 Fuel Rod Outside Diameter, in. 0.422 0.416 0.430 TM Clad Material ZIRLO M5 M5 Fuel Pellet Material UO2 UO2 UO2/UO2-Gd Fuel Enrichments, wt% <5 <5 <5 Overall FA Length, in 166.1 165.7 165.8 (31 DEC 2013)