ML13010A386

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Cycle 19 Core Operating Limits Report
ML13010A386
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 01/08/2013
From: James Shea
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L36 121128 801
Download: ML13010A386 (17)
v • d • e


Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 January 8, 2013 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 2 Facility Operating License No. DPR-79 NRC Docket No. 50-328

Subject:

Sequoyah Nuclear Plant Unit'2 Cycle 19 Core Operating Limits Report In accordance with the Sequoyah Nuclear Plant Unit 2 Technical Specifications 6.9.1.14.c, enclosed is the Unit 2 Cycle 19 Core Operating Limits Report, Revision 0.

There are no new regulatory commitments in this letter. If you have any questions, please contact Rusty Proffitt at (423) 843-7170.

Respectfully, J. W. Shea Vice President, Nuclear Licensing

Enclosure:

Sequoyah Nuclear Plant Unit 2 Cycle 19 Core Operating Limits Report cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - SQN

ENCLOSURE SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 19 CORE OPERATING LIMITS REPORT

QA Record L36 121128 801 SEQUOYAH UNIT 2 CYCLE 19 CORE OPERATING LIMITS REPORT REVISION 0 November 2012 Prepared by:

Zh~, r~t2~

M. D. Porter, PWR Fuel Engineering Date Verified by:

K. D. Sissom, PWR'Fuel Engineering Date Reviewed by:

D. M. Brown, PWR Fuel Engineering Manager Date B. S. Catalanotto, Reactor Engineering Manager Date Approved by:

PORC hhirr'Aaak ( Date Plant-Manager Date Revision 0 Pages affected All Reason for Revision: Initial Issue SEQUOYAH-UNIT 2 Page I of 15 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 19 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Sequoyah Unit 2 Cycle 19 has been prepared in accordance with the requirements of Technical Specification (TS) 6.9.1.14.

The TSs affected by this Report are listed below:

TABLE 2.2-1 f1 (Al) trip reset function for OTAT Trip (QTNL, QTPL) and rates of trip setpoint decrease per percent Al (QTNS, QTPS)

TABLE 2.2-1 f2 (AI) trip reset function for OPAT Trip (QPNL, QPPL) and rates of trip setpoint decrease per percent Al (QPNS, QPPS) 3/4.1.1.3 Moderator Temperature Coefficient (MTC) 3/4.1.3.5 Shutdown Rod Insertion Limit 3/4.1.3.6 Control Rod Insertion Limits 3/4.2..1 Axial Flux Difference (AFD) 3/4.2.2 Heat Flux Hot Channel Factor (FQ(X,Y,Z))

3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor (FAH(X,Y))

2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in TS 6.9.1.14. The versions of the topical reports which describe the methodologies used for this cycle are listed in Table 1.

The following abbreviations are used in this section:

BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero THERMAL POWER EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER 2.1 Moderator Temperature Coefficient - MTC (Specification 3/4.1.1.3) 2.1.1 The MTC limits are:

The BOL/ARO/HZP MTC shall be less positive than 0 Aklk/ 0F (BOL limit). With the measured value more positive than -0.39 x10 5 Ak/kf F (as-measured MTC limit),

establish control rod withdrawal limits to ensure the MTC remains less positive than 0 Ak/klfF for all times in core life.

The EOL/ARO/RTP MTC shall be less negative than or equal to -4.5 X 10"4 Ak/IkIF.

SEQUOYAH-UNIT 2 Page 2 of 15 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 19 2.1.2 The 300 ppm surveillance limit is:

The measured 300 ppm/ARO/RTP MTC should be less negative than or equal to

-3.75 x 10-4 Ak/kI 0F.

2.2 Shutdown Rod Insertion Limit (Specification 314.1.3.5) 2.2.1 The shutdown rods shall be withdrawn to a position as defined below:

Cycle Burnup Steps Withdrawn (MWd/mtU)

>0 > 225 to < 231 2.3 Control Rod Insertion Limits (Specification 3/4.1.3.6) 2.3.1 The control rod banks shall be limited in physical insertion as shown in Figure 1.

2.4 Axial Flux Difference - AFD (Specification 3/4.2.1) 2.4.1 The axial flux difference (AFD) limits (AFDLiamil) are provided in Figure 2.

2.5 Heat Flux Hot Channel Factor - F_(X,Y,Z) (Specification 3/4.2.2)

Fo (X,YZ) shall be limited by the following relationships:

FaRTP F0 (X,Y,Z) -

  • K(Z) for P > 0.5 P

F0RTP FQ (X,Y,Z) <

  • K(Z) for P _ 0.5 0.5 THERMAL POWER where P =

RATED THERMAL POWER 2.5.1 F0 RTP = 2.62 2.5.2 K(Z) is provided in Figure 3 SEQUOYAH-U NIT 2 Page 3 of 15 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 19 The following parameters are required for core monitoring per the Surveillance Requirements of Specification 3/4.2.2:

2.5.3 NSLOPEAFD = 1.32 where NSLOPEAFD = Negative AFD limit adjustment required to compensate for each 1% that FQ (X,Y,Z) exceeds BODES.

2.5.4 PSLOPEAF = 1.77 where PSLOPEAFD = Positive AFD limit adjustment required to compensate for each 1% that FQ(X,Y,Z) exceeds BODES.

2.5.5 NSLOPEf2t ( ') = 1.75 where NSLOPEf2(AI) = Adjustment to negative OPAT f2(AI) limit required to compensate for each 1% that FQ(X,Y,Z) exceeds BCDES.

2.5.6 PSLOPE12(M,) = 2.00 where PSLOPE2(A" Adjustment to positive OPAT f2(AI) limit required to compensate for each 1% that Fo(X,Y,Z) exceeds BCDES.

2.5.7 BQNOM(X,Y,Z) = Nominal design peaking factor, increased by an allowance for the expected deviation between the nominal design power distribution and the measurement.

2.5.8 BQDES(X,Y,Z) = Maximum allowable design peaking factor which ensures that the FQ (X,Y,Z) limit will be preserved for operation within the LCO limits, including allowances for calculational and measurement uncertainties.

2.5.9 BCDES(XY,Z) = Maximum allowable design peaking factor which ensures that the centerline fuel melt limit will be preserved for operation within the LCO limits, including allowances for calculational and measurement uncertainties.

BQNOM(X,YZ), BQDES(XY,Z), and BCDES(X,Y,Z) data bases are provided for input to the plant power distribution analysis codes on a cycle specific basis and are determined using the methodology for core limit generation described in the references in Specification 6.9.1.14.

2.5.10 The increase in FoM(X,Y,Z) for compliance with the 4.2.2.2.e Surveillance Requirements is defined as follows:

For cycle burnups: 0 to 3429 MWd/mtU, use 2.0%

For cycle bumups: > 3429 to 4651 MWd/mtU, use 2.8%

For cycle bumups: > 4651 to 20483 MWd/mtU, use 2.0 %

SEQUOYAH-UNIT 2 Page 4 of 15 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 19 2.6 Nuclear Enthalpy Rise Hot Channel Factor - FNH(X,Y) (Specification 3/4.2.3)

FAH(X,Y) shall be limited by the following relationship:

FH(X,Y) < MAP(X,YZ) / AXIAL(X,Y) 2.6.1 MAP(X,Y,Z) is provided in Tables 2a and 2b.

AXIAL(X,Y) is the axial peak from the normalized axial power shape.

The following parameters are required for core monitoring per the Surveillance Requirements of Specification 3/4.2.3:

FAHR M(X,Y) < BHNOM(X,Y) where FAHR M(X,Y) = FIHM(X,Y) / [MAPM / AXIAL(X,Y)]

FAHM(X,Y) is the measured radial peak at location X,Y.

MAPM is the value of MAP(X,Y,Z) obtained from Tables 2a and 2b for the measured peak.

2.6.2 BHNOM(X,Y) = Nominal design radial peaking factor, increased by an allowance for the expected deviation between the nominal design power distribution and the measurement.

2.6.3 BHDES(X,Y) = Maximum allowable design radial peaking factor which ensures that the FAH (X,Y) limit will be preserved for operation within the LCO limits, including allowances for calculational and measurement uncertainties.

2.6.4 BRDES(X,Y) = Maximum allowable design radial peaking factor which ensures that the steady state DNBR limit will be preserved for operation within the LCO limits, including allowances for calculational and measurement uncertainties.

BHNOM(X,Y), BHDES(X,Y) and BRDES(X,Y) databases are provided for input to the plant power distribution analysis computer codes on a cycle specific basis and are determined using the methodology for core limit generation described in the references in Specification 6.9.1.14.

2.6.5 RRH = 3.34 when 0.8 < P < 1.0 RRH = 1.67 when P < 0.8 where RRH = Thermal power reduction required to compensate for each 1% that FAH(X,Y) exceeds its limit, P = Thermal Power / Rated Thermal Power SEQUOYAH-UNIT 2 Page 5 of 15 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 19 2.6.6 TRH = 0.0334 when 0.8 < P < 1.0 TRH = 0.0167 when P < 0.8 where TRH = Reduction in OTAT K1 setpoint required to compensate for each 1%

FAH(X,Y) exceeds its limit.

P = Thermal Power / Rated Thermal Power 2.6.7 All cycle burnups shall use a 2% increase in FHM(X,Y) for compliance with the 4.2.3.2.d.1 Surveillance Requirement.

3.0 REACTOR CORE PROTECTIVE LIMITS 3.1 Trip Reset Term [f1(AI for Overtemperature Delta-T Trip (Specification 2.2.1)

The following parameters are required to specify the power level-dependent f1(A1) trip reset term limits for the Overtemperature Delta-T trip function:

3.1.1 QTNL=-20%

where QTNL = the maximum negative Al setpoint at rated thermal power at which the trip setpoint is not reduced by the axial power distribution.

3.1.2 QTPL =+5%

where QTPL = the maximum positive Al setpoint at rated thermal power at which the trip setpoint is not reduced by the axial power distribution.

3.1.3 QTNS=2.50%

where QTNS = the percent reduction in Overtemperature Delta-T trip setpoint for each percent that the magnitude of Al exceeds its negative limit at rated thermal power (QTNL).

3.1.4 QTPS = 1.40%

where QTPS = the percent reduction in Overtemperature Delta-T trip setpoint for each percent that the magnitude of Al exceeds its positive limit at rated thermal power (QTPL).

SEQUOYAH-UNIT 2 Page 6 of 15 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 19 3.2 Trio Reset Term [f,(AI)l for Overpower Delta-T Trip (Specification 2.2.1)

The following parameters are required to specify the power level-dependent f2(Al) trip reset term limits for the Overpower Delta-T trip function:

3.2.1 QPNL = -25%

where QPNL = the maximum negative Al setpoint at rated thermal power at which the trip setpoint is not reduced by the axial power distribution.

3.2.2 QPPL = +25%

where QPPL = the maximum positive Al setpoint at rated thermal power at which the trip setpoint is not reduced by the axial power distribution.

3.2.3 QPNS = 1.70%

where QPNS = the percent reduction in Overpower Delta-T trip setpoint for each percent that the magnitude of Al exceeds its negative limit at rated thermal power (QPNL).

3.2.4 QPPS = 1.70%

where QPPS = the percent reduction in Overpower Delta-T trip setpoint for each percent that the magnitude of Al exceeds its positive limit at rated thermal power (QPPL).

SEQUOYAH-UNIT 2 Page 7 of 15 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 19 Table 1 COLR Methodology Topical Reports

1. BAW-10180-A, Revision 1, "NEMO-Nodal Expansion Method Optimized," March 1993.

(Methodology for Specification 3/4.1.1.3-Moderator Temperature Coefficient)

2. BAW-10169P-A, Revision 0, "RSG Plant Safety Analysis-B&W Safety Analysis Methodology for Recirculating Steam Generator Plants," October 1989.

(Methodology for Specification 3/4.1.1.3-Moderator Temperature Coefficient)

3. BAW-10163P-A, Revision 0, "Core Operating Limit Methodology for Westinghouse-Designed PWRs," June 1989.

(Methodology for Specifications 2.2.1-Reactor Trip Instrumentation Setpoints [fi(ll), f2 (AI) limits],

3/4.1.3.5-Shutdown Rod Insertion Limit, 3/4.1.3.6-Control Rod Insertion Limits, 3/4.2.1-Axial Flux Difference, 3/4.2.2-Heat Flux Hot Channel Factor, 3/4.2.3-Nuclear Enthalpy Rise Hot Channel Factor)

4. EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model," March 2001.

(Methodology for Specification 3/4.2.2-Heat Flux Hot Channel Factor)

5. BAW-10227P-A, Revision 1, "Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel," June 2003.

(Methodology for Specification 3/4.2.2-Heat Flux Hot Channel Factor)

6. BAW-10186P-A, Revision 2, "Extended Burnup Evaluation," June 2003.

(Methodology for Specification 3/4.2.2-Heat Flux Hot Channel Factor)

7. EMF-2103P-A, Revision 0, "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," April 2003.

(Methodology for Specification 3/4.2.2-Heat Flux Hot Channel Factor)

8. BAW-10241P-A, Revision 1, "BHTP DNB Correlation Applied with LYNXT," July 2005.

(Methodology for Specification 3/4.2.3-Enthalpy Rise Hot Channel Factor)

9. BAW-10199P-A, Revision 0, "The BWU Critical Heat Flux Correlations," August 1996.

(Methodology for Specification 3/4.2.3-Enthalpy Rise Hot Channel Factor)

10. BAW-10189P-A, "CHF Testing and Analysis of the Mark-BW Fuel Assembly Design," January 1996.

(Methodology for Specification 3/4.2.3-Enthalpy Rise. Hot Channel Factor)

11. BAW-10159P-A, "BWCMV Correlation of Critical Heat Flux in Mixing Vane Grid Fuel Assemblies,"

August 1990.

(Methodology for Specification 3/4-2.3-Enthalpy Rise Hot Channel Factor)

12. BAW-10231P-A, Revision 1, 'COPERNIC Fuel Rod Design Computer Code," January 2004.

(Methodology for Specification 2.2.1-Reactor Trip Instrumentation Setpoints)

SEQUOYAH-UNIT 2 Page 8 of 15 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 19 Table 2a Maximum Allowable Peaking Limits MAP(X,YZ) for Operation Advanced W17 HTP Fuel AXIAL(X,Y) ELEVATION (ft) MAP(X,YZ) AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) 1 1.8128 1 2.5969 2 1.8125 2 2.5380 3 1.8122 3 2A4827 4 1.8119 4 2.4411 5 1.8115 5 2.4315 1.1 6 1.8109 1.4 6 2.4800 7 1.8106 7 2.5356 8 1.8104 8 2.4447 9 1.8098 9 2.3555 10 1.8092 10 2.1738 11 1.7599 11 2,0238 1 2.0671 1 2.6723 2 2.0664 2 2.6061 3 2.0656 3 2.5417 4 2.0649 4 2.4913 5 2.0642 5 2.4801 1.2 6 2.0636 1.5 6 2.5380 7 2.0624 7 2.6273 8 2.0615 8 2.5311 9 2.0457 9 2.4447 10 1.9492 10 2.2772 11 1.8589 11 2.0975 1 2.3433 1 2.7308 2 2.3419 2 2.6605 3 2.3412 3 2.5947 4 2.3397 4 2.5371 5 2.3389 5 2.5234 1.3 6 2.3381 1.6 6 2.5906 7 2.3357 7 2.7077 8 2.3130 8 2.6117 9 2.1886 9 2.5240 10 2.0643 10 2.3758 11 1.9439 11 S 2.1662 SEQUOYAH-UNIT 2 Page 9 of 15 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 19 Table 2a (continued)

AXIAL(XY) ELEVATION (ft) MAP(X,Y,Z) AXIAL(X,Y) ELEVATION (ft) MAP(XY,Z) 1 2.7664 1 2.4339 2 247083 2 2.4060 3 2.6380 3 2.3856 4 2.5791 4 2.3423 5 2.5639 5 2.3114 1.7 6 2.6359 >1.9 6 2.6006 7 2.7795 7 2.5003 8 2.6870 8 2.4004 9 2.5798 9 2.2989 10 2.4726 10 2.1483 11 2.2304 11 1.9630 1 2.7963 1 2.5057 2 2.7466 2 2.4754 3 2.6775 3 2.4449 4 2.6172 4 2.3591 5 2.6010 5 2.4205 1.8 6 2.6802 2.1 6 2.7643 7 2.8456 7 2.6474 8 2.7552 8 2.5360 9 2.6648 9 2.4400 10 2.5655 10 2.3277 11 2.2931 -11 2.0549 1 2.8235 1 2.5380 2 2.7739 2 2.5216 3 2.7125 3 2.4619 4 2.6523 4 2.4294 5 2.6328 5 2.4290 1.9 6 2.7200 2.3 6 2.8222 7 2.9065 7 2.7334 8 2.8193 8 2.6234 9 2.7288 9 2.5186 10 2.6384 10 2.4215 11 2.3482 11 2.1250 SEQUOYAH-UNIT 2 Page 10 of 15 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 19 Table 2a (continued)

AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) AXIAL(X,Y) ELEVATION (ft) MAP(XY,Z) 1 2.6440 1 2.2448 2 2.5160 2 2.5535 3 2.5045 3 2.4678 4 2.4488 4 2.3229 5 2.5803 5 2.8913 2.5 6 2.9481 3.1 6 3.1515 7 2.8544 7 3.0181 8 2.7286 8 2.9699 9 2.6450 9 2.8941 10 2.5527 10 2.7819 11 2.1731 11 2.1866 1 2.5554 1 2.0228 2 2.5529 2 2.5172 3 2.5197 3 2.4007 4 2.4375 4 2.2195 5 2.5643 5 3.0496 2.7 6 2.9839 3.3 6 3.2226 7 2.8837 7 3.1446 8 2.7939 8 3.0350 9 2.7040 9 2.9688 10 2.5997 10 2.8533 11 2.1995 11 2.1473 1 2.4223 1 1.7563 2 2.5653 2 2.4566 3 2.5075 3 2.3062 4 2.3955 4 2.0854 5 2.7295 5 3.2045 2.9 6 3.0921 3.5 6 3.2929 7 3.0070 7 3.2627 8 2.8896 8 3.0846 9 2.8058 9 3.0299 10 2.6974 10 2.9117 11 2.2039 11 2.0862 SEQUOYAH-UNIT 2 Page 11 of 15 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 19 Table 2b Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation Mark-BW Fuel AXIAL( X,Y) ELEVATION (ft) MAP(X,Y,Z) AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) 2 1.9343 2 2.8143 4 1.9300 4 2.9856 1.1 6 1.9234 1.9 6 3.0073 8 1.9115 8 2.8509 10 1.8894 10 2.7048 2 2.1663 2 2.4405 4 2.1558 4 2.4405 1.2 6 2.1410 >1.9 6 2.7376 8 2.1153 8 2.5906 10 2.0582 10 2.3456 2 2.4023 2 2.5881 4 2.3825 4 2.5881 1.3 6 2.3599 2.2 6 2.9899 8 2.3100 8 2.7800 10 2.1760 10 2.5367 2 2.6453 2 2.6111 4 2.6136 4 2.6111 1.4 6 2.5610 2.6 6 3.2947 8 2.4199 8 3.2055 10 2.2787 10 2.8049 2 2.7189 2 2.9142 4 2.8181 4 2.9142 1.5 6 2.6735 3.0. 6 4.0216 8 2.5280 8 3.6527 10 2.3749 10 3.1711 2 2.7720 2 2.9618 4 2.9219 4 2.9618 1.7 6 2.8641 3.5 6 4.2351 8 2.7064 8 3.7452 10 2.5539 10 3.3214 SEQUOYAH-UNIT 2 Page 12 of 15 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 19

(. . .2. .. -.-- - --- ( ... ..

1 80 160 -. ..... -

.. ......T .. ..

200 ................ i o 10 "BANK1C r- 140 ~------- - ---------- - --

0 D. 120 ---- --------------- I ------.

(0,110) 100 ------------- ---------. , -..

j /*BANK D 80 -*-------------

f C-

"- 60 ...---..................

40 ---

0.4 0.6 0.8 0 0.2 I

(Fully Inserted)

Fraction of Rated Thermal Power FIGURE 1 Rod Bank Insertion Limits Versus Thermal Power, Four Loop Operation control banks are

  • Fully withdrawn region shall be the condition where shutdown and

<231 steps withdrawn, inclusive.

at a position Within the interval of >225 and Fully withdrawn shall be the position as defined below, Cycle Burnuo (MWd/mtU) Steps With~drawn

->0 >_225 to <231 This figure is valid for operation at a rated thermal power of 3455 MWth when the LEFM is in operation.

If the LEFM becomes inoperable, then prior to the next NIS calibration, the maximum allowable power level must be reduced by 1.3% in power, and the rod insertion limit lines must be increased by 3 steps withdrawn until the LEFM is returned to operation.

SEQUOYAH-UNIT 2 Page 13 of 15 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 19 120 110 --- -n-- - __,

lo t  !/ I \J'"°-- iI - -

1 (431Q.) $,1 00)

Unacceptable I _ Unacceptable 90 -- I* . .. ' -"- - ' 0 -; Operaati~ni - -F -perati-on 80 I / : ~Acceptable= I _ *_ _ _

0 / operation I I-60 1-4 7 50 -- I-I 0 40 - L 30 _ _ --

20 - _

10 -T----

0

-50 -40 -30 -20 -10 0 10 20 30 40 50 Flux Difference (Al) %

FIGURE 2 Axial Flux Difference Limits As A Function of Thermal Power For Burnup Range of 0 EFPD to EOL This figure is valid for operation at a rated thermal power of 3455 MWth when the LEFM is in operation.

If the LEFM becomes inoperable, then prior to the next NIS calibration, the maximum allowable power level must be reduced by 1.3% in power, and the AFD limit lines must be made more restrictive by 1% in AFD Until the LEFM is returned to operation.

Revision 0 Page 14 of 15 SEQUOYAH-UNIT 2 SEQUOYAH-UNIT 2 Page 14 of 15 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 19 1.2 1.0 0.8 Elevation K(z) 0.000 1.0000 0.4 ....-------- ---6-85 1,0000--" -- -

7.995 1.0000 9.705 1.0000 12.000 1.0000 0.2 ------ - - - - - - - - - -- - - -- - - - -I r - - - - - - - - - - - - - - - - - - - - - - - -

0.0 0 2 4 6 8 10 12 Core Height (Feet)

FIGURE 3 K(Z) - Normalized FQ(X,Y,Z) as a Function of Core Height For Mk-BW and Advanced W17 HTP Fuel SEQUOYAH-UNIT 2 Page 15 of 15 Revision 0

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