Text

Cycle 21 Core Operating Limits Report
	ML15364A010
Person / Time
Site:	Sequoyah
Issue date:	12/23/2015
From:	Schwarz C; Tennessee Valley Authority
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML15364A010 (19)
	v • d • e

Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 December 23, 2015 10 CFR 50.4 ATT-N: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 2 Renewed Facility Operating License No. DPR-79 NRC Docket No. 50-328

Subject:

Sequoyah Unit 2 Cycle 21 Core Operating Limits Report In accordance with Sequoyah Nuclear Plant (SQN) Unit 2 Technical Specification (TS) 5.6.3.d, enclosed is the Unit 2 Cycle 21 Core Operating Limits Report (COLR), Revision 0 that was issued on November 27, 2015.

SQN has completed the transition from the Mark-BW fuel design to the Advanced W17 HTP fuel design in Unit 2. Accordingly, the COLR only includes core operating limits associated with the use of Advanced W17 HTP fuel. Limited Mark-BW fuel assemblies remain viable for use in Unit 2 core designs. Although a mixed core using Mark-EW fuel is not expected, future core designs will apply TS 5.6.3 for determining the core operating limits.

4oo(

U.S.

Page Nuclear 2 Regulatory Commission December 23, 2015 There are no new regulatory commitments in this letter. Ifyou have any questions, please contact Michael McBrearty, SQN Site Licensing Manager at (423) 843-7170.

Respectfully, Site Vice President Sequoyah Nuclear Plant Enclosure Sequoyah Unit 2 Cycle 21 Core Operating Limits Report cc (Enclosure):

NRC Regional Administrator - Region [I NRC Senior Resident Inspector - SQN

ENCLOSURE SEQUOYAH UNI r 2 CYCLE 21 CORE OPERATING LIMITS REPORT

C-.

QA Record L36 151119 800 SEQUOYAH UNIT 2 CYCLE 21 CORE OPERATING LIMITS REPORT REVISION 0 November 2015 Prepared by:

Kelly R." K ne r, *PWR F'**uel Eng ineer*'*ing*

I /lzo/l2.05 Date I~'j 10 _ \

Christine A. Setter, PWR Fuel Engineering Date Verified by:

Jor E.SrngEgnern Reviewed by:.

Kathlee*. Cunningham, PWR Fuel Engineering Manager Date Brandon 5 Catalanott, Reco Enieig Manager Date Approved by:

cQ~~sb0A4 ii 1241201Ž.

r~a/*/a-an*POC ,," ,JDate Cair~

Date Date of PORC Affected Revision Approval JPages jReason for Revision 0 11/27115 j All jInitial issue.

SEQUOYAH-UNIT 2Pae1o16Rvin0 Page 1 of 16 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 21 1.0 CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit 2 Cycle 21 has been prepared in accordance with the requirements of Technical Specification (TS) 5.6.3.

The TSs affected by this Report are listed below:

TS COLR COLR Section Technical Specification COLR Parameter Section Page 3.1.1 SHUTDOWN MARGIN (SDM) SDM, 2.1 3 BOL MTC Limit 2.2.1 4 3.1.3 Moderator Temperature EOL MTC Limit 2.2.2 4 Coefficient (MTC) 300 ppm Surveillance Limit 2.2.3 4 60 ppm Surveillance Limit 2.2.4 4 3.1.4 Rod Group Alignment Limits SDM 2.1.3 3 InetinLiisShutdown Bank Insertion Limits 2.3 4 3.1.5 Shutdown Bank SnsMrioniimi3 3..6 CotrlBak nsrio Lmis Control Bank Insertion Limits 2.4 5 3.1.6_ Contro[Bnk Inserton Limit SOM 2.1.5 3 3.1.8 PHYSICS TESTS Exceptions- SDM 2.1.6 3

_____MODE 2 RIP 2.5.1 6 K(Z) 2.5.2 6 NSLOPEAFD 2.5.3 6 Heat Flux Hot Channel Factor PSLOPEAFD 2.5.4 6 I.. (F0 (X,Y,Z)) NSLOPEf 2 (AI) 2.5.5 6 PSLOPEf2 (AI) 2.5.6 6 FQ(X,Y,Z) Appropriate Factor 2.5.7 6

_____________________ITS LCO 3.2.1 Required" Action A.3 2.5.8 6 MAP(X,YZ) 2.6.1 6 RRH 2.6.2 6 3.2.2 Nuclear Enthalpy Rise Hot TRH 2.6.3 6 Channel Factor (FAH(X,Y)) FAH(X,Y) Appropriate Factor 2.6.4 7 ITS 3.2.2 Required Action A.4 2.6.5 7

__________________ITS 3.2.2 Required Action B.1 2.6.6 7 323 AXIAL FLUX DIFFERENCE AOLmt .

______ (AFD) _ _ _ _ _ _ _ _ _ _ _

3.3.1 Reactor Trip System (RTS) QTNL, QTPL, OTNS, and QTPS 2.8.1 8

____Instrumentation QPNL, QPPL, QPNS, and QPPS 2.8.2 9 3.9.1 Boron Concentration Refueling Boron Concentration 2.9 9 5.6.3_

563 CORE REPORT OPERATING (COLR) LIMITS Aayia ehd Analytical Methods 2.0 SEQUOYAH UNIT 2Pae2o16Rvsn0Page 2 of 16 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 21 2.0 OPERATING LIMITS The cycle-specific parameter limits for the TS listed in section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in TS 5.6.3. 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 EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER 2.1 SHUTDOWN MARGIN - SDM (TS 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8) 2.1.1 ForTS 3.1.1, SOM shall be>Ž1.6 %Ak/k in MODE 2 with keff < 1.0, MODE 3 and MODE 4 2.1.2 For TS 3.1.1, SDM shall beŽ> 1.0 %Ak/k in MODES5.

2.1.3 For TS 3.1.4, SDM shall be Ž 1.6 %Alk/

in MODE 1 and MODE 2.

2.1.4 For TS 3.1.5, 5DM shall be Ž 1.6 %Alkk in MODE 1 and MODE 2.

2.1.5 For TS 3.1.6, SDM shall be Ž 1.6 %Ak'Jk in MODE 1 and MODE 2 with keff > 1.0.

2.1.6 For TS 3.1.8, 5DM shall be >Ž1.6 %Alkk in MODE 2.

SEQUOYAH UNIT 2Pae3o16Rvsn0Page 3 of 16 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 21 2.2 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.2.1 The BOL MTC limit is:

less positive than 0.O0 x 105 Ak/k/0F.

2.2.2 The EOL MTC limit is:

less negative than or equal to -4.50 x 10.. ARk/kPF.

2.2.3 The 300 ppm Surveillance limit is:

less negative than or equal to 2.2.4 The 60 ppm Surveillance limit is:

less negative than or equai to -4.15 x10-4 Ak/k/0 F.

2,3 Shutdown Bank Insertion Limits (TS 3.1.5) 2.3.1 Each shutdown bank shall be withdrawn to a position as defined below:

SEQUOYAH UNIT 2Pae4o16Rvsn0Page 4 of 16 Revision 0

/

COLR FOR SEQUOYAH UNIT 2 CYCLE 21 2.4 Control Bank Insertion Limits (TS 3.1.6) 2.4.1 The control banks shall be limited in physical insertion as shown in Figure 1.

2.4.2 Each control bank shall be considered fully withdrawn from the core at > 225 steps.

2.4.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C, and Bank D. The control banks shall be sequenced in reverse order upon insertion.

2.4.4 Each control bank not fully withdrawn from the core shall be operated with the following overlap as a function of full out position.

Full Out Position (steps) Bank Overlap (steps) Bank Difference (steps) 225 97 128 226 98 128 227 99 128 228 100 128 229 101 128 230 102 128 231 103 128 SEQUOYAH UNIT 2Pae5o16Rvsn0Page 5 of 16 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 21 2.5 Heat Flux Hot Channel Factor- FQ(X,Y,Z) (TS 3.2.1)

RTP 2.5.1 FQ = 2.62 2.5.2 K(Z) is provided in Figure 2 2.5.3 NSLOPEAFD = 1.17 2.5.4 PSLOPEAFD = 1.55 2.5.5 NSLOPEf 2(AI1)= 1.41 2.5.6 PSLOPEV2(AI) = 2.20 M

2.5.7 The appropriate factor for increase in FQ (X,Y,Z) for compliance with SR 3.2.1.2 and SR 3.2.1.3 is specified as follows:

For all cycle burnups, use 2.0%

2.5.8 ITS LCO 3.2.1 Required Action A.3 reduces the Overpower Delta T Trip setpoints (value of K4 ) at least 1% (in AT span) for each 1% that Fac(X,Y,Z) exceeds its limit.

2.6 Nuclear Enthalpy Rise Hot Channel Factor - FAH(X,Y) (TS 3.2.2) 2.6.1 MAP(X,Y,Z) is provided in Table 2.

2.6.2 RRH= 3.34 when 0.8 <P<*1.0 RRH=1.67 whenP*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 2.6.3 TRH =0.0334 when 0.8 < P

1.0 TRH = 0.0167 when P_*0.8 Where TRH = Reduction in Overtemperature Delta T K1 setpoint required to compensate for each 1% that FAH(X,Y) exceeds its limit.

P = THERMAL POWER I RATED THERMAL POWER SEQUOYAH UNIT 2Pae6o16Rvsn0 Revision 0

/ COLR FOR SEQUOYAH UNIT 2 CYCLE 21

",2.6.4 The appropriate factor for increase in FAHM (X,Y) for compliance

-. wthS 3.2.2.1 and SR 3.2.2.2 is specified as follows:

For all cycle burnups, use 2.0%

2.6.5 ITS 3.2.2 Required Action A.4 reduces the Overtemperature Delta T setpoint (Ki term in Table 3.3.1-1) by > TRH multiplied times the FAH minimum margin.

2.6.6 ITS 3.2.2 Required Action B.1 reduces the Overtemperature Delta T setpoint (Ki term in Table 3.3.1-1) by Ž-TRH multiplied times the fi(Al) minimum margin.

2.7 Axial Flux Difference - AFD (TB 3.2.3) 2.7.1 The AFD limits are specified in Figure 3 SEQUOYAH UNIT 2Pae7o16Rvsn0Page 7 of 16 Revision

COLR FOR SEQUOYAH UNIT 2 CYCLE 21 2.8 Reactor Trip System Instrumentation (TS 3.3.1) 2.8.1 Trip Reset Term [f1(AI)] for Overtemperature Delta-T Trip The following parameters are required to specify the power level-dependent fl(AI) trip reset term limits for Table 3.3.1-1 (function 6), Overtemperature Delta-T trip function:

2.8.1.1 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.

2.8.1.2 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.

2.8.1.3 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).

2.8.1.4 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 2Pae8o16Rvsn0Page 8 of 16 Revision 0

COLR FOR SEQUOYAH UNIT 2CYCLE 21 2.8.2 Trip Reset Term [f2 (Al)] for Overpower Delta-T Trip

~The following parameters are required to specify the power level-dependent f2(AI) trip reset term limits for Table 3.3.1-1 (function 7), Overpower Delta-T trip function:

2.8.2.1 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.

2.8.2.2) 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.

2.8.2.3 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).

2.8.2.4 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).

2.9 Boron Concentration (TS 3.9.1) 2.9.1 The refueling boron concentration shall be > 2058 ppm.

SEQUOYAH UNiT 2 Pgso Page 9 of 16 6Rvso Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 21 Table I COLR Methodology Topical Reports

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

(Methodology for TS 3.1.1-SHUTDOWN MARGIN, 3.1.3-Moderator Temperature Coefficient, 3.9.1-Boron Concentration)

2. 'BAW-1 01 69P-A, Revision 0, "RSG Plant Safety Analysis-B&W Safety Analysis Methodology for Recirculating Steam Generator Plants," October 1989.

(Methodology for TS 3.1 .3-Moderator Temperature Coefficient)

3. BAW-1 01 63P-A, Revision 0, "Core Operating Limit Methodology for Westinghouse-Designed PWRs," June 1989.

(Methodology for TS 3.3.1-Reactor Trip System Instrumentation [f1 (AI), f2(AI) limits],

3.1.5-Shutdown Bank Insertion Limits, 3.1.6-Control Bank Insertion Limits, 3.2.1-Heat Flux Hot Channel Factor, 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.2.3-AXIAL FLUX DIFFERENCE)

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

(Methodology for TS 3.2.1-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 TS 3.2.1-Heat Flux Hot Channel Factor)

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

(Methodology for TS 3.2.1-Heat Flux Hot Channel Factor)

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

(Methodology for TS 3.2.1-Heat Flux Hot Channel Factor)

8. BAW-1 0241 P-A, Revision 1, "BHTP DNB Correlation Applied with LYNXT," July 2005.

(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-Reactor Trip System Instrumentation [f1(AI) limits])

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

(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-Reactor Trip System Instrumentation [f1(AI) limits])

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

January 1996.

(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-Reactor Trip System Instrumentation [f1(AI) limits])

11. BAW-1 01 59P-A, "BWCMV Correlation of Critical Heat Flux in Mixing Vane Grid Fuel Assemblies," August 1990.

(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-Reactor Trip System Instrumentation [f1 (Al) limits])

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

(Methodology for TS 3.3.1-Reactor Trip System Instrumentation [f2(AI) limits])

SEQUOYAH UNIT 2 Pg Page 100oof 16 6Rvso Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 21 Table 2 Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation Advanced W17 HTPTM Fuel (TS 3.2.2)

AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) 1 1.8764 1 2.7078 2 1.8761 2 2.6846 3 1.8758 3 2.6349 4 1.8755 4 2.5983 5 1.8750 5 2.5933 1.1 6 1.8746 1.4 6 2.6505 7 1.8732 7 2.6394 8 1.8731 8 2.5563 9 1.8729 9 2.4572 10 1.8733 10 2.2668 11 1.8320 11 2.1190 1 2.1327 1 2.8223 2 2.1321 2 2.7591 3 2.1315 3 2.6985 4 2.1306 4 2.6542 5 2.1295 5 2.6482 1.2 6 2.1290 1.5 6 2.7162 7 2.1286 7 2.7495 8 2.1274 8 2.6507 9 2.1254 9 2.5578 10 2.0247 10 2.3791 11 1.9355 11 2.2011 1 2.4093 1 2.8935 2 2.4077 2 2.8252 3 2.4068 3 2.7571 4 2.4063 4 2.7055 5 2.4050 5 2.6985 1.3 6 2.4043 1.6 6 2.7776 7 2.4034 7 2.8428 8 2.3923 8 2.7401 9 2.3053 9 2.6471 10 2.1479 10 2.4862 11 2.0305 __ __ _ _11 2.2766 SEQUOYAH UNIT 2 Pg Page 111oof 16 6Rvso Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 21 Table 2 (continued)

AXIAL(X,Y) Elevation.(ft) MAP(XYZ) AXIAL(X,Y) Elevation ft) MAP(X,Y,Z) 1 2.9545 1 2.6005 2 2.8786 2 2.5794 3 2.8103 3 2.5536 4 2.7522 4 2.5118 5 2.7457 5 2.4500 1.7 6 2.8308 >1.9 6 2.4520 7 2.9230 7 2.6494 8 2.8209 8 2.5446 9 2.7287 9 2.4371 10 2.5873 10 2.2595

__ _ _ _ _11 2.3478 11 2.0819 1 2.9942 1 2.7049 2 2.9271 2 2.6623 3 2.8570 3 2.6375 4 2.7942 4 2.5288 5 2.7875 5 2.5460 1.8 6 2.8823 2.1 6 2.5252 7 2.9967 7 2.7990 8 2.8980 8 2.6963 9 2.8027 9 2.5830 10 2.6853 10 2.4527 11 2.4156 11 2.1796 1 3.0267 1 2.7475 2 2.9676 2 2.7275 3 2.8960 3 2.6457 4 2.8345 4 2.6125 5 2.8256 5 2.5774 1.9 6 2.9291 2.3 6 2.5707 7 3.0655 7 2.9015 8 2.9714 8 2.7773 9 2.8741 9 2.6757 10 2.7780 10 2.4740 11 2.4797 ______ 11 2.2722 SEQUOYAH UNIT 2 Pg Page 122oof 166Rvso Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 21 Table 2 (continued)

AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) 1 2.8372 2 2.7099 3 2.7081 4 2.6340 5 2.6483 2.5 6 2.6284 7 3.0303 8 2.8965 9 2.8111 10 2.7019

______ 11 2.3542 SEQUOYAH UNIT 2 Pg Page 133oof 16 6Rvso Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 21 2 *2 .1 (Fully W-ithdrawn Region)' (.575 225) ________

2

-)00 2

[80 / (1"0'182),I I

1 0

,40 --- ___-- __A_

09 m

n,,

40 ______

6 .090 ________ ________ ________ _______ _

0 0.2 0.4 0.6 0.8 I (Fully Inserted)

Fraction of Rated Thermal Power FIGURE 1 Rod Bank Insertion Limits Versus Thermal Power, Four Loop Operation (TS 3.1.6)

Fully withdrawn region shall be the condition where shutdown and control banks are at a position within the interval of >225 and <23lsteps withdrawn, inclusive.

Fully withdrawn shall be the position as defined below, Cycle Burnun (MWd/mtU') Steps Withdrawn

> 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 144oof 166Rvso Pg Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 21 I I I I I I I I L-----F------L-----F------F-I I I Elevation K(z)

(ft) I I 0.000 1.0000 I 6.285 1.0000 III 7.995 1.0000 9.705 1.0000 12.000 1.0000 I I 0 2 4 6 8 10 12 Core Height (Feet)

FIGURE 2 K(Z) - Normalized F0 (X,Y,Z) as a Function of Core Height (TS 3.2.1)

SEQUOYAH UNIT 2 Pg Page 155oof 16 6Rvso Revision 0

2

.1 C

.1~

COLR FOR SEQUOYAH UNIT 2 CYCLE 21 120 110 100 90 80 O

70 60 I-

-C 50 O'

40 30 20 10 0

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

FIGURE 3 Axial Fiux Difference Limits As A Function of Rated Thermal Power For Burnup Range 0 EFPD to EOL (TS 3.2.3)

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 AFO limit lines must be made more restrictive by 1% in AFO until the LEFM is returned to oj)eration.

SEQUOYAH UNIT 2 Pg 166oof 16 Page 6Rvso Revision 0

Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 December 23, 2015 10 CFR 50.4 ATT-N: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 2 Renewed Facility Operating License No. DPR-79 NRC Docket No. 50-328

Subject:

Sequoyah Unit 2 Cycle 21 Core Operating Limits Report In accordance with Sequoyah Nuclear Plant (SQN) Unit 2 Technical Specification (TS) 5.6.3.d, enclosed is the Unit 2 Cycle 21 Core Operating Limits Report (COLR), Revision 0 that was issued on November 27, 2015.

SQN has completed the transition from the Mark-BW fuel design to the Advanced W17 HTP fuel design in Unit 2. Accordingly, the COLR only includes core operating limits associated with the use of Advanced W17 HTP fuel. Limited Mark-BW fuel assemblies remain viable for use in Unit 2 core designs. Although a mixed core using Mark-EW fuel is not expected, future core designs will apply TS 5.6.3 for determining the core operating limits.

4oo(

U.S.

Page Nuclear 2 Regulatory Commission December 23, 2015 There are no new regulatory commitments in this letter. Ifyou have any questions, please contact Michael McBrearty, SQN Site Licensing Manager at (423) 843-7170.

Respectfully, Site Vice President Sequoyah Nuclear Plant Enclosure Sequoyah Unit 2 Cycle 21 Core Operating Limits Report cc (Enclosure):

NRC Regional Administrator - Region [I NRC Senior Resident Inspector - SQN

ENCLOSURE SEQUOYAH UNI r 2 CYCLE 21 CORE OPERATING LIMITS REPORT

C-.

QA Record L36 151119 800 SEQUOYAH UNIT 2 CYCLE 21 CORE OPERATING LIMITS REPORT REVISION 0 November 2015 Prepared by:

Kelly R." K ne r, *PWR F'**uel Eng ineer*'*ing*

I /lzo/l2.05 Date I~'j 10 _ \

Christine A. Setter, PWR Fuel Engineering Date Verified by:

Jor E.SrngEgnern Reviewed by:.

Kathlee*. Cunningham, PWR Fuel Engineering Manager Date Brandon 5 Catalanott, Reco Enieig Manager Date Approved by:

cQ~~sb0A4 ii 1241201Ž.

r~a/*/a-an*POC ,," ,JDate Cair~