ML19345D252
| ML19345D252 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/09/2019 |
| From: | Rasmussen M Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EPID L-2019-LLA-0239 | |
| Download: ML19345D252 (22) | |
Text
Tennessee Valley Authority, Sequoyah Nuclear Plant, P.O. Box 2000, Soddy Daisy, Tennessee 37384 December 9, 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 REVISIONS 1 AND 2
Reference:
- 1. NRC letter to TVA, "Sequoyah Nuclear Plant, Unit 1 - Issuance of Exigent Amendment No. 348 to Operate One Cycle with One Control Rod Removed (EPID L-2019-LLA-0239); dated November 21, 2019.
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), Revisions 1 and 2 that were issued on November 15 and 21, 2019, respectively. These revisions were developed to support a core design and operation with one of 53 full-length control rod assemblies removed during the cycle. Revision 1 of the COLR permitted operation in Mode 6 without the control rod assembly and Revision 2 supports all Modes of operation without the control rod assembly. Removal of the control rod assembly was approved via a license amendment granted by Reference 1.
printed on recycled paper
U.S. Nuclear Regulatory Commission Page 2 December 9, 2019 There are no new regulatory commitments in this letter. If you have any questions, please contact Jeffrey Sowa, SQN Site Licensing Manager at (423) 843-8129.
Respectfully, Matthew Rasmussen Site Vice President Sequoyah Nuclear Plant Enclosures
- 1. Sequoyah Unit 1 Cycle 24 Core Operating Limits Report, Revision 1
- 2. Sequoyah Unit 1 Cycle 24 Core Operating Limits Report, Revision 2 cc (Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector- SQN
ENCLOSURE 1 SEQUOYAH UNIT 1 CYCLE 24 CORE OPERATING LIMITS REPORT REVISION 1
QA Record L36 191108 802 SEQUOYAH UNIT 1 CYCLE 24 MODE 6 CORE OPERATING LIMITS REPORT REVISION 1 November 2019 Prepared by:
/ U/\ f2o\S Josbf Elkins, PWR Fuel Engineering Date Verified by:
in A. Ritchie,, PWRTFuel Engineering Engineer Date Reviewed by Christine Setter, PWR Fuel Engineering Manager Date Brandon S. Catalanotto, Reactor Engineering Manager I ISt/lK n / ia/n Date Approved by:
<r Kcnt<M Ufiflh^-
PORp-Chairman c f -tiki"* / // lullnDate ant Manager
/ //vavy Date Date of PORC Affected Revision Approval Pages Reason for Revision 10/3/2019 All Initial issue.
Loading assembly without an RCCA in core location H-08 See above All Applicable toMode 6 only.
SEQUOYAH UNIT 1 Page 1 of 2 Revision 1
MODE 6 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 ofthe Technical Specification (TS) 5.6.3.
The TSs affected by this report are listed below:
3.1.1 SHUTDOWN MARGIN (SDM) 3.1.3 Moderator Temperature Coefficient (MTC) 3.1.4 Rod Group Alignment Limits 3.1.5 Shutdown Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.1.8 PHYSICS TESTS Exceptions - MODE 2 3.2.1 Heat Flux Hot Channel Factor(FQ(X,Y,Z))
3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FAH(X,Y))
3.2.3 AXIAL FLUX DIFFERENCE (AFD) 3.3.1 Reactor Trip System (RTS) Instrumentation 3.9.1 Boron Concentration 5.6.3 CORE OPERATING LIMITS REPORT (COLR) 2.0 OPERATING LIMITS This COLR is only valid for MODE 6. The cycle-specific parameter limits for specifications 3.1.1, 3.1.3, 3.1.4, 3.1.5, 3.1.6, 3.1.8, 3.2.1, 3.2.2, 3.2.3 and 3.3.1 are not applicable in MODE 6 and are not provided. The parameter limit for 3.9.1 is provided in thefollowing subsection. This limit has been developed using the NRC approved NEMO methodology specified in TS 5.6.3. The version ofthetopical report for the NEMO methodology is BAW-10180-A, Rev. 1.
2.1 BORON CONCENTRATION (TS 3.9.1) 2.1.1 The refueling boron concentration shall be k 2181 ppm.
SEQUOYAH UNIT 1 Page 2 of 2 Revision 1
ENCLOSURE 2 SEQUOYAH UNIT 1 CYCLE 24 CORE OPERATING LIMITS REPORT REVISION 2
QA Record L36 191119 801 SEQUOYAH UNIT 1 CYCLE 24 CORE OPERATING LIMITS REPORT REVISION 2 November 2019 Prepared by:
Jamel Sell fer ^^~^^j^^^^-^ / li/zo \lo Korrie Yetzer, PWR Fuel Engineeri
\<\
Date Verified by:
/ l\/TP>llbtq (J#hn Ritchie, PWR Fuel Engineering Date Reviewed by:
CBB11HK i. ckflflfr Christine Setter, PWR Fuel Engineering Manager i-ji/io/ioia Date Brandon Catalanotto, Reactor Engineering Manager Date p<<Lv~ fe<-UttOW^
Approved by:
fte<7tfa*t 2*^>>o j *J;///*<< <r. fi/?i//t Date fO^" Plant Manager ~
Z//2///9 Date Date of PORC Affected Revision Approval Pages Reason for Revision 0 10/3/2019 All Initial Issue 11/15/2019 All Loading assembly without an RCCA in core location H-08.
Applicable to Mode6 only.
See above All Supports implementation of amended Technical Specification (TS) 4.2.2, "Control Rod Assemblies/' which would permit the SQN1 Cycle 24 (U1C24) core to contain 52 full length control rods with no full length control rod assembly in core location H-08JSQN-TS-19-05).
SEQUOYAH UNIT 1 Page 1 of 16 Revision 2
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 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 BOL MTC Limit 2.2.1 4 EOL MTC Limit 3.1.3 Moderator Temperature Coefficient (MTC) 2.2.2 4 300 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 3.1.5 Shutdown Bank Insertion Limits Shutdown Bank Insertion Limits 2.3 4 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 - MODE 2 SDM 2.1.6 RTP Fq 2.5.1 6 K(Z) 2.5.2 6
-AFD NSLOPE 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 PSLOPEf2(AI) 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 3.2.2 Nuclear Enthalpy Rise Hot Channel TRH 2.6.3 6 Factor (F.H(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 3.2.3 AXIAL FLUX DIFFERENCE (AFD) AFD Limits 2.7 Reactor Trip System (RTS) QTNL, QTPL, QTNS, andQTPS 2.8.1 8 3.3.1 Instrumentation QPNL, QPPL, QPNS, andQPPS 2.8.2 9 3.9.1 Boron Concentration Refueling Boron Concentration 2.9 5.6.3 CORE OPERATING LIMITS REPORT (COLR) Analytical Methods Table 1 10 SEQUOYAH UNIT 1 Page 2 of 16 Revision 2
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 2.0 Operating Limits The cycle-specific parameter limits for theTS 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 ofthe topical reports, which describe the methodologies used forthis 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, SDM shall be > 1.6 %Ak/k in MODE 2 with keff < 1.0, MODE 3 and MODE 4.
2.1.2 ForTS 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 For TS 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 ForTS 3.1.8, SDM shall be > 1.6 %Ak/k in MODE 2.
SEQUOYAH UNIT 1 Page 3 of16 Revision 2
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 -0.34 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 bank shall be withdrawn to a position as defined below:
Cycle Burnup Steps (MWd/mtU) Withdrawn
>0 * > 225 to £231 SEQUOYAH UNIT 1 Page 4 of 16 Revision 2
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 banksshall 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 1 Page 5 of 16 Revision 2
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 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 PSLOPEf2(AI) = 2.3 2.5.7 The appropriate factor for increase in FQ (X,Y,Z) for compliance M.
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 2
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 by the Fah minimum margin.
2.6.6 TS LCO 3.2.2 Required Action B.1 reduces the Overtemperature Delta-T setpoint (K, 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 1 Page 7 of 16 Revision 2
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 2.8 Reactor Trip System Instrumentation (TS 3.3.1) 2.8.1 Trip Reset Term [f^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-Ttrip 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-Ttrip 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 2
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 >2181 ppm.
SEQUOYAH UNIT 1 Page 9 of 16 Revision 2
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 Methodologyfor 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)
(Methodology forTS 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 forTS 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 forTS 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 forTS 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 forTS 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 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 [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 1 Page 10 of 16 Revision 2
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 Table 2 Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation 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 SEQUOYAH UNIT 1 Page 11 of 16 Revision 2
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COLR FOR SEQUOYAH UNIT 1 CYCLE 24 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 1 Page 13 of 16 Revision 2
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 231 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.
Fully withdrawn shall be the position as defined below, Cycle Burnup (MWd/mtLh Steps Withdrawn
>0 > 225 to < 231 This figure is valid for operation ata 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 1 Page 14 of 16 Revision 2
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 1.2 1.0 0.8 Sae 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 h 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 1 Page 15 of 16 Revision 2
COLR FOR SEQUOYAH UNIT 1 CYCLE 24 120 tc iii
§ Q.
-J CC UJ X
r-Q LU CC
-10 0 10 20 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.
If the LEFM becomes inoperable, then prior to the next NIS calibration, the maximum allowable power level must be reduced by 1.3 /o in power, and theAFD limit lines must bemade more restrictive by 1% in AFD until the LEFM is returned to operation.
SEQUOYAH UNIT 1 Page 16 of 16 Revision 2