ML19301A471
| ML19301A471 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/24/2019 |
| From: | Rasmussen M Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19301A471 (18) | |
Text
Tennessee Valley Authority, Sequoyah Nuclear Plant, P.O. Box 2000, Soddy Daisy, Tennessee 37384 October 24, 2019 10CFR50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 1 Renewed Facility Operating License No. DPR-77 NRC Docket No. 50-327
Subject:
SEQUOYAH UNIT 1 CYCLE 24 CORE OPERATING LIMITS REPORT REVISION 0 In accordance with Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specification (TS) 5.6.3.d, enclosed is the Unit 1 Cycle 24 Core Operating Limits Report (COLR), Revision 0 that was issued on October 3, 2019.
There are no new regulatory commitments in this letter. Ifyou have any questions, please contact Andrew (Andy) McNeil, SQN Site Licensing Manager (acting) at (423) 843-8098.
Respectfully, to Matthew Rasmussen Site Vice President Sequoyah Nuclear Plant Enclosure Sequoyah Unit 1 Cycle 24 Core Operating Limits Report cc (Enclosure):
NRC Regional Administrator-Region II NRC Senior Resident Inspector - SQN printed on recycled paper
ENCLOSURE SEQUOYAH UNIT 1 CYCLE 24 CORE OPERATING LIMITS REPORT
QA Record Prepared by:
SEQUOYAH UNIT 1 CYCLE 24 CORE OPERATING LIMITS REPORT REVISION 0 September 2019 iStrange, PWR Fuel Engine John Verified by:
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Josh Elkins, PWR Fuel Engineering Reviewed by:
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Christine Setter, PWR Fuel Engineering Manager L36190924800 DateyW/q I
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\\\\>>EiicUs for fc 64xU^iofK m ftfc<o*n Brandon Catalanotto, Reactor Engineering Manage Approved by:
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/e>k//f Date Plant Manager Date Revision Date of PORC Approval Affected Pages Reason for Revision 0
See above All Initial Issue SEQUOYAH UNIT 1 Page 1 of 16 Revision 0
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 1.0 Core Operating Limits Report This CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit 1 Cycle 24 has been prepared in accordance with the requirements ofTechnical Specification (TS) 5.6.3.
The TSs affected by this Report are listed below.
TS Section Technical Specification COLR Parameter COLR Section COLR Page 3.1.1 SHUTDOWN MARGIN (SDM)
SDM 2.1 3
3.1.3 Moderator Temperature Coefficient(MTC)
BOL MTC Limit EOL MTC Limit 300 ppm Surveillance Limit 60 ppm Surveillance Limit 2.2.1 2.2.2 2.2.3 2.2.4 4
4 4
4 3.1.4 Rod Group Alignment Limits SDM 2.1.3 3
3.1.5 Shutdown Bank Insertion Limits Shutdown Bank Insertion Limits SDM 2.3 2.1.4 4
3 3.1.6 Control Bank Insertion Limits Control Bank Insertion Limits SDM 2.4 2.1.5 5
3 3.1.8 PHYSICS TESTS Exceptions - MODE2 SDM 2.1.6 3
3.2.1 Heat Flux Hot Channel Factor (FQ(X,Y,Z))
Fq K(Z)
NSLOPE^0 PSLOPEAFD NSLOPEf2<Al>
f (Al)
PSLOPE2 FQ(X,Y,Z) Appropriate Factor TS LCO 3.2.1 Required Action A.3 2.5.1 2.5.2 2.5.3 2.5.4 2.5.5 2.5.6 2.5.7 2.5.8 6
6 6
6 6
6 6
6 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FAH(X,Y))
MAP(X,Y,Z)
RRH TRH FAH(X,Y) Appropriate Factor TS 3.2.2 Required Action A.4 TS 3.2.2 Required Action B.1 2.6.1 2.6.2 2.6.3 2.6.4 2.6.5 2.6.6 6
6 6
7 7
7 3.2.3 AXIAL FLUX DIFFERENCE (AFD)
AFD Limits 2.7 7
3.3.1 Reactor Trip System (RTS)
Instrumentation QTNL, QTPL, QTNS, and QTPS QPNL, QPPL, QPNS, and QPPS 2.8.1 2.8.2 8
9 3.9.1 Boron Concentration Refueling Boron Concentration 2.9 9
5.6.3 CORE OPERATING LIMITS REPORT (COLR)
Analytical Methods Table 1 10 SEQUOYAH UNIT 1 Page 2 of 16 Revision 0
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 2.0 Operating Limits Thecycle-specific parameter limits for theTS listed in Section 1.0are presented in the following subsections. Theselimits have been developed using the NRC approved methodologies specified in TS 5.6.3. The versions ofthe topical reports, which describe the methodologies used for this cycle, are listed inTable 1.
The following abbreviations are used in this section:
BOLstands 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 ketf < 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 ForTS 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 1 Page 3 of 16 Revision 0
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 2.2 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.2.1 The BOL MTC limit is:
less positive than 2.2.2 The EOL MTC limit is:
less negative than or equal to
-0.34 x10"5 Ak/k/°F.
-4.50x104Ak/k/°F.
2.2.3 The 300 ppm Surveillance limit is:
less negativethan or equal to
-3.80 x 10'4 Ak/k/°F.
2.2.4 The 60 ppm Surveillance limit is:
less negativethan 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 bank shall be withdrawn to a position as defined below:
Cycle Burnup (MWd/mtU)
Steps Withdrawn
>0
> 225 to < 231 SEQUOYAH UNIT 1 Page 4 of 16 Revision 0
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 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 1 Page 5 of 16 Revision 0
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 2.5 Heat Flux HotChannel 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 PSLOPEf2(AI) =
2.3 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 cycle burnups > 592 MWd/mtU to 1303 MWd/mtU, use 2.61%.
For all other cycle 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 AT span) for each 1% that Fq (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 1 Page 6 of 16 Revision 0
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 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 bythe Fah minimum margin.
2.6.6 TS LCO 3.2.2 Required Action B.1 reduces the Overtemperature Delta-T setpoint (Ki term inTable 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 1 Page 7 of 16 Revision 0
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 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 specifythe 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 1 Page 8 of 16 Revision 0
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 2.8.2 Trip Reset Term [f2(AI)] 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 > 2123 ppm.
SEQUOYAH UNIT 1 Page 9 of 16 Revision 0
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 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 [fi(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 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-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 [fi(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-ft(Al) 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 [fi(AI) limits])
11.
BAW-10159P-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 [fi(AI) limits])
12.
BAW-10231P-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 1 Page 10 of 16 Revision 0
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 Table 2 Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation AXIAL(X,Y)
ELEVATION (FT)
MAP(X,Y,Z) 1 1.7084 2
1.7084 3
1.7083 4
1.7082 5
1.7081 1.03 6
1.7079 7
1.7078 8
1.7073 9
1.7072 10 1.7072 11 1.7066 1
1.8764 2
1.8761 3
1.8758 4
1.8755 5
1.8750 1.1 6
1.8746 7
1.8732 8
1.8731 9
1.8729 10 1.8733 11 1.8320 1
2.1327 2
2.1321 3
2.1315 4
2.1306 5
2.1295 1.2 6
2.1290 7
2.1286 8
2.1274 9
2.1254 10 2.0247 11 1.9355 SEQUOYAH UNIT 1 Page 11 of 16 AXIAL(X,Y)
ELEVATION (FT)
MAP(X,Y,Z) 1 2.4093 2
2.4077 3
2.4068 4
2.4063 5
2.4050 1.3 6
2.4043 7
2.4034 8
2.3923 9
2.3053 10 2.1479 11 2.0305 1
2.7078 2
2.6846 3
2.6349 4
2.5983 5
2.5933 1.4 6
2.6505 7
2.6394 8
2.5563 9
2.4572 10 2.2668 11 2.1190 1
2.8223 2
2.7591 3
2.6985 4
2.6542 5
2.6482 1.5 6
2.7162 7
2.7495 8
2.6507 9
2.5578 10 2.3791 11 2.2011 Revision 0
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 Table 2 (continued)
AXIAL(X,Y)
ELEVATION (FT)
MAP(X,Y,Z) 1 2.8935 2
2.8252 3
2.7571 4
2.7055 5
2.6985 1.6 6
2.7776 7
2.8428 8
2.7401 9
2.6471 10 2.4862 11 2.2766 1
2.9545 2
2.8786 3
2.8103 4
2.7522 5
2.7457 1.7 6
2.8308 7
2.9230 8
2.8209 9
2.7287 10 2.5873 11 2.3478 1
2.9942 2
2.9271 3
2.8570 4
2.7942 5
2.7875 1.8 6
2.8823 7
2.9967 8
2.8980 9
2.8027 10 2.6853 11 2.4156 SEQUOYAH UNIT 1 Page 12 of 16 AXIAL(X,Y)
ELEVATION (FT)
MAP(X,Y,Z) 1 3.0267 2
2.9676 3
2.8960 4
2.8345 5
2.8256 1.9 6
2.9291 7
3.0655 8
2.9714 9
2.8741 10 2.7780 11 2.4797 1
2.6005 2
2.5794 3
2.5536 4
2.5118 5
2.4500
>1.9 6
2.4520 7
2.6494 8
2.5446 9
2.4371 10 2.2595 11 2.0819 1
2.7049 2
2.6623 3
2.6375 4
2.5288 5
2.5460 2.1 6
2.5252 7
2.7990 8
2.6963 9
2.5830 10 2.4527 11 2.1796 Revision 0
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 Table 2 (continued)
AXIAL(X,Y)
ELEVATION (FT)
MAP(X,Y,Z) 1 2.7475 2
2.7275 3
2.6457 4
2.6125 5
2.5774 2.3 6
2.5707 7
2.9015 8
2.7773 9
2.6757 10 2.4740 11 2.2722 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 1 Page 13 of 16 Revision 0
o S
I 8-e (0
CO T3 Otr COLR FOR SEQUOYAH UNIT 1 CYCLE 24 (Fully Withdrawn Region)*
(.575,225)
??0 200 180 (1.0.182L 160-KC 140-
^
^
UAI\\
1?0
(.09,128W^
100-
^0.110)
R AMI/' r\\
80 L)AIN>\\ U 60 40 20-0
(.09,0)^/^
0.2 0.4 0.6 0.8 Fraction of RATED THERMAL POWER (Fully Inserted)
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 withinthe interval of >225 and <231steps withdrawn.
Fully withdrawn shall be the position as defined below, Cycle Burnup (MWd/mtU)
>0 Steps Withdrawn
> 225 to < 231 Thisfigure is valid foroperation at a RATED THERMAL POWER of3455 MWth when the LEFM is inoperation.
Ifthe LEFM becomes inoperable, then prior to the next NIS calibration, the maximum allowable powerlevelmust be reduced by 1.3% in power, and the rod insertionlimit lines must be increased by 3 steps withdrawn until the LEFM is returned to operation.
SEQUOYAH UNIT 1 Page 14 of 16 Revision 0
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 1.2 1.0 0.8-Elevation (ft) 0.000 K(z) 1.0000 6.285 7.995 9.705 12.000 1.0000 1.0000 1.0000 1.0000 bUe 0.4 0.2 0.0 4
6 8
Core Height (Feet) 10 FIGURE 2 K(Z) - Normalized FQ(X,Y,Z) as a Function of Core Height (TS 3.2.1) 12 SEQUOYAH UNIT 1 Page 15 of 16 Revision 0
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 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 is valid for operation at a RATED THERMAL POWER of 3455 MWth when the LEFM is in operation.
Ifthe LEFM becomes inoperable, then priorto the next NIS calibration, the maximum allowable power level must be reduced by 1.3% in power, and the AFD limitlines must be made more restrictive by 1% in AFD untilthe LEFM is returned to operation.
SEQUOYAH UNIT 1 Page 16 of 16 Revision 0