ML18319A190

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Cycle 23 Core Operating Limits Report, Revision 0
ML18319A190
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 11/14/2018
From: Anthony Williams
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML18319A190 (18)
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Text

Tennessee Valley Authority, Sequoyah Nuclear Plant, P.O. Box 2000, Soddy Daisy, Tennessee 37384 November 14, 2018 10CFR50.4 ATTN: 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 23 CORE OPERATING LIMITS REPORT REVISION 0 In accordance with Sequoyah Nuclear Plant (SQN) Unit 2 Technical Specification (TS) 5.6.3.d, enclosed is the Unit 2 Cycle 23 Core Operating Limits Report (COLR), Revision 0 that was issued on October 28, 2018.

There are no new regulatory commitments in this letter. If you have any questions, please contact Jonathan Johnson, SQN Site Licensing Manager, at (423) 843-8129.

thony L. Williams Site Vice President Sequoyah Nuclear Plant Enclosure Sequoyah Unit 2 Cycle 23 Core Operating Limits Report cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector- SQN printed on recycled paper

ENCLOSURE SEQUOYAH UNIT 2 CYCLE 23 CORE OPERATING LIMITS REPORT

QA Record L36 181016 800 SEQUOYAH UNIT 2 CYCLE 23 CORE OPERATING LIMITS REPORT REVISION 0 October 2018 Prepared by:

Kofrie Yetzer/Jojti Sti^e, PWR iFuel Engineering/

/ io/zz/zB i°W/8 Date Verified by:

Andrew Whitener, PWR Fuel Engineering Date ' '

Reviewed by:

as OC*VQV f*£nCXXlcr Qtrnn Ritchie, PWR Fuel Engineering

/ IP / ?Z [\R Date jL/ c<

Brandon Catalanotto, Reactor Engineering Manager

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Date

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    • .A Plant Manager Date '

Date of PORC Affected Revision Approval Pages Reason for Revision See above All Initial Issue SEQUOYAH UNIT 2 Page 1 of 16 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 23 1.0 CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit 2 Cycle 23 has been prepared in accordance with the requirements ofTechnical 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 Moderator Temperature EOL MTC Limit 2.2.2 4 3.1.3 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 3.1.5 Shutdown Bank Insertion Limits 2.3 4 Shutdown Bank Insertion Limits SDM 2.1.4 3 Control Bank Insertion Limits 2.4 5 3.1.6 Control Bank Insertion Limits SDM 2.1.5 3 3.1.8 PHYSICS TESTS Exceptions -

SDM 2.1.6 3 MODE 2 RTP Fq 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 3.2.1 (FQ(X,Y,Z)) NSLOPEf2(AI) 2.5.5 6 f2(AI)

PSLOPE 2.5.6 6 FQ(X,Y,Z) Appropriate Factor 2.5.7 6 TS LCO 3.2.1 Required Action A.3 2.5.8 6 MAP(X,Y,Z) 2.6.1 6 RRH 2.6.2 6 Nuclear Enthalpy Rise Hot TRH 2.6.3 6 3.2.2 Channel Factor (FAH(X,Y)) FAH(X,Y) Appropriate Factor 2.6.4 7 TS 3.2.2 Required Action A.4 2.6.5 7 TS 3.2.2 Required Action B.1 2.6.6 7 AXIAL FLUX DIFFERENCE 3.2.3 AFD Limits 2.7 7 (AFD)

Reactor Trip System (RTS) QTNL, QTPL, QTNS, and QTPS 2.8.1 8 3.3.1 Instrumentation QPNL, QPPL, QPNS, and QPPS 2.8.2 9 3.9.1 Boron Concentration Refueling Boron Concentration 2.9 9 CORE OPERATING LIMITS 5.6.3 REPORT (COLR) Analytical Methods Table 1 10 SEQUOYAH UNIT 2 Page 2 of 16 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 23 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 For TS 3.1.1, SDM shall be > 1.6 %Ak/k in MODE 2 with keff < 1.0, MODE 3 and MODE 4.

2.1.2 For TS 3.1.1, SDM shall be > 1.0 %Ak/k in MODE 5.

2.1.3 For TS 3.1.4, SDM shall be > 1.6 %Ak/k in MODE 1 and MODE 2.

2.1.4 ForTS 3.1.5, SDM shall be > 1.6 %Ak/k in MODE 1 and MODE 2.

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

2.1.6 For TS 3.1.8, SDM shall be > 1.6 %Ak/k in MODE 2.

SEQUOYAH UNIT 2 Page 3 of 16 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 23 2.2 ModeratorTemperature Coefficient - MTC (TS 3.1.3) 2.2.1 The BOL MTC limit is:

less positive than 0.0 x10"5 Ak/k/°F.

2.2.2 The EOL MTC limit is:

less negative than or equal to -4.50 x 10"4 Ak/k/°F.

2.2.3 The 300 ppm Surveillance limit is:

less negative than or equal to -3.80 x 10"4 Ak/k/°F.

2.2.4 The 60 ppm Surveillance limit is:

less negative than or equal to -4.20 x 10"4 Ak/k/°F.

2.3 Shutdown Bank Insertion Limits (TS 3.1.5) 2.3.1 Each shutdown bankshall be withdrawn to a position as defined below:

Cycle Burnup Steps (MWd/mtU) Withdrawn

>0 > 225 to <, 231 SEQUOYAH UNIT 2 Page 4 of 16 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 23 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 bywithdrawal 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 2 Page 5 of 16 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 23 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= 1.3 2.5.4 PSLOPEAFD= 1.6 2.5.5 NSLOPEf2(AI)= 1.6 2.5.6 PSLOPE^" = 2.3 2.5.7 The appropriate factor for increase in FQM(X,Y,Z) for compliance with SR 3.2.1.2 and SR 3.2.1.3 is specified as follows:

For all burnups, use 2.0%

2.5.8 TS LCO 3.2.1 Required Action A.3 reduces the Overpower Delta-T Trip setpoints (value of K4) at least 1% (in ATspan) for each 1% that Fqc(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 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 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 / RATED THERMAL POWER SEQUOYAH UNIT 2 Page 6 of 16 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 23 2.6.4 The appropriate factor for increase in FAHM (X,Y) for compliance with SR 3.2.2.1 and SR 3.2.2.2 is specified as follows:

For all cycle burnups, use 2.0%

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

2.6.6 TS LCO 3.2.2 Required Action B.1 reduces the Overtemperature Delta-T setpoint (Ki term in Table 3.3.1-1) by >TRH multiplied by the fi(AI) minimum margin.

2.7 Axial Flux Difference - AFD (TS 3.2.3) 2.7.1 The AFD limits are specified in Figure 3.

SEQUOYAH UNIT 2 Page 7 of 16 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 23 2.8 Reactor Trip System Instrumentation (TS 3.3.1) 2.8.1 Trip Reset Term [fi(AI)] for Overtemperature Delta-T Trip The following parameters are required to specify the power level-dependent fi(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 2 Page 8 of 16 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 23 2.8.2 Trip Reset Term [f2(AI)] for Overpower Delta-TTrip 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's 3.9.1) 2.9.1 The refueling boron concentration shall be > 2100 ppm.

SEQUOYAH UNIT 2 Page 9 of 16 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 23 Table 1 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-10169P-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-10163P-A, Revision 0, "Core Operating Limit Methodology for Westinghouse-Designed PWRs," June 1989.

(Methodology for TS 3.3.1-Reactor Trip System Instrumentation [f^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), Revision 0 "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 ofAdvanced 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 forTS 3.2.1-Heat Flux Hot Channel Factor)

8. BAW-10241P-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 [f^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 [f^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 [f,(AI) limits])

11. BAW-10159P-A, "BWCMV Correlation ofCritical 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 [f^AI) 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 Page 10 of 16 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 23 Table 2 Maximum Allowa Die Peaking Lin Operation MAP(X,Y,Z) for <

AXIAL(X,Y) ELEVATION MAP(X,Y,Z) AXIAL(X.Y) ELEVATION MAP(X,Y,Z)

(FT) (FT) 1 1.7084 1 2.4093 2 1.7084 2 2.4077 3 1.7083 3 2.4068 4 1.7082 4 2.4063 5 1.7081 5 2.4050 1.03 6 1.7079 1.3 6 2.4043 7 1.7078 7 2.4034 8 1.7073 8 2.3923 9 1.7072 9 2.3053 10 1.7072 10 2.1479 11 1.7066 11 2.0305 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 I SEQUOYAH UNIT 2 Page 11 of 16 Revision 0

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COLR FOR SEQUOYAH UNIT 2 CYCLE 23 Table 2 (continued)

AXIAL(X,Y) ELEVATION MAP(X,Y,Z) AXIAL(X,Y) ELEVATION MAP(X,Y,Z)

(FT) (FT) 1 2.7475 1 2.8372 2 2.7275 2 2.7099 3 2.6457 3 2.7081 4 2.6125 4 2.6340 5 2.5774 5 2.6483 2.3 6 2.5707 2.5 6 2.6284 7 2.9015 7 3.0303 8 2.7773 8 2.8965 9 2.6757 9 2.8111 10 2.4740 10 2.7019 11 2.2722 11 2.3542 SEQUOYAH UNIT 2 Page 13 of 16 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 23 231 0.2 0.4 0.6 0.8 (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 <231 steps withdrawn.

Fullywithdrawn shall be the position as defined below, Cycle Burnup (MWd/mtU) Steps Withdrawn

>0 > 225 to < 231 This figure isvalid for operation at a RATED THERMAL POWER of3455 MWth when the LEFM is in operation.

If the LEFM becomes inoperable, then prior tothe 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 by3 steps withdrawn until the LEFM is returned to operation.

SEQUOYAH UNIT 2 Page 14 of 16 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 23 1.2 1.0 0.8 N 0.6 - _ _ _ _ _ ... U _ .. I i Elevation K(z)

(ft) 0.000 1.0000 0.4 6.285 1.0000 7.995 1.0000 9.705 1.0000 12.000 1.0000 0.2 0.0 4 6 8 10 12 Core Height (Feet)

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

SEQUOYAH UNIT 2 Page 15 of 16 Revision 0

COLR FOR SEQUOYAH UNIT 2 CYCLE 23 120 UJ I

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-10 o 10 Flux Difference (Al) %

FIGURE 3 AXIAL FLUX DIFFERENCE Limits As A Function of RATED THERMAL POWER For Burnup Range 0 EFPD to EOL (TS 3.2.3)

This figure isvalid for operation ata RATED THERMAL POWER of3455 MWth when the LEFM is in operation.

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

SEQUOYAH UNIT 2 Page 16 of 16 Revision 0

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