ML18319A190
| ML18319A190 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  (DPR-079) |
| Issue date: | 11/14/2018 |
| From: | Anthony Williams Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18319A190 (18) | |
Text
Tennessee Valley Authority, Sequoyah Nuclear Plant, P.O. Box 2000, Soddy Daisy, Tennessee 37384 November 14, 2018 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 10CFR50.4
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 Prepared by:
SEQUOYAH UNIT 2 CYCLE 23 CORE OPERATING LIMITS REPORT REVISION 0 October 2018 Kofrie Yetzer/JojtiSti^e, PWR iFuel Engineering/
Verified by:
Andrew Whitener, PWR Fuel Engineering Reviewed by:
Qtrnn Ritchie, as PWR Fuel Engineering OC*VQV f*£nCXXlcr jL/ c<
Brandon Catalanotto, ReactorEngineering Manager
^proved lay:
.A Plant Manager Revision Date of PORC Approval See above SEQUOYAH UNIT 2 Affected Pages All Reason for Revision Initial Issue Page 1 of 16 L36 181016 800
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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 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 -
MODE 2 SDM 2.1.6 3
3.2.1 Heat Flux Hot Channel Factor (FQ(X,Y,Z))
RTP Fq K(Z)
NSLOPEAFD PSLOPEAFD NSLOPEf2(AI) f2(AI)
PSLOPE 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 2 Page 2 of 16 Revision 0
COLR FOR SEQUOYAH UNIT 2 CYCLE 23 2.0 OPERATING LIMITS The cycle-specificparameter limits forthe TS listed in Section 1.0 are presented inthe following subsections. These limits have been developed usingthe NRC approved methodologies specified inTS 5.6.3. The versions ofthe topical reports, whichdescribe the methodologies used for this cycle, are listed in Table 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 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
2.2 COLR FOR SEQUOYAH UNIT 2 CYCLE 23 ModeratorTemperature Coefficient - MTC (TS 3.1.3) 0.0 x10"5 Ak/k/°F.
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
-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 Eachshutdown bankshall be withdrawn to a position as defined below:
Cycle Burnup (MWd/mtU)
Steps 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 physicalinsertion as shown in Figure 1.
2.4.2 Each control bankshallbe 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 coreshall be operated with the following overlapas a function offull 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 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 PSLOPE^" =
2.3 2.5.7 The appropriate factor for increase in FQM(X,Y,Z) for compliance withSR 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) foreach 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 powerreduction 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 bythe 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 ReactorTrip System Instrumentation (TS 3.3.1) 2.8.1 Trip ResetTerm [fi(AI)] for Overtemperature Delta-T Trip The following parameters are required tospecify the power level-dependent fi(AI) trip resetterm 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 tripsetpoint 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 foreach 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 percentreduction in Overtemperature Delta-T trip setpointfor 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 limitat 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 TS3.3.1-Reactor Trip System Instrumentation [f^AI), f2(AI) limits],
3.1.5-Shutdown BankInsertion Limits, 3.1.6-Control BankInsertion Limits, 3.2.1-Heat Flux Hot Channel Factor,3.2.2-Nuclear Enthalpy Rise HotChannel Factor, 3.2.3-AXIAL FLUXDIFFERENCE) 4.
EMF-2328(P)(A), Revision 0 "PWR Small Break LOCA Evaluation Model," March 2001.
(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 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 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 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 forTS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-Reactor TripSystem 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 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 2 Page 11 of 16 MAP(X,Y,Z) for <Operation 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 I
Revision 0
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COLR FOR SEQUOYAH UNIT 2 CYCLE 23 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 2 Page 13 of 16 Revision 0
231 (Fully Inserted)
COLR FOR SEQUOYAH UNIT 2 CYCLE 23 0.2 0.4 0.6 0.8 Fraction of RATED THERMAL POWER FIGURE 1 Rod Bank Insertion Limits Versus THERMAL POWER, Four Loop Operation (TS 3.1.6)
- Fullywithdrawn region shall be the condition where shutdown and control banks are at a positionwithin the intervalof >225 and <231 steps withdrawn.
Fullywithdrawn shall be the position as defined below, Cycle Burnup (MWd/mtU)
>0 Steps Withdrawn
> 225 to < 231 This figure isvalid for operation ata RATED THERMAL POWER of3455 MWth when theLEFM isin operation.
If theLEFM becomes inoperable, then prior tothenext NIS calibration, themaximum allowable power level must be reduced by1.3% 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
1.2 1.0 0.8 N
0.6 0.4 0.2 0.0 COLR FOR SEQUOYAH UNIT 2 CYCLE 23 U
.. I i
Elevation K(z)
(ft) 0.000 1.0000 6.285 1.0000 7.995 1.0000 9.705 1.0000 12.000 1.0000 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 2 Page 15 of 16 Revision 0
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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 by1.3% in power, and theAFD limit lines must bemade more restrictive by1% in AFD until the LEFM is returned to operation.
SEQUOYAH UNIT 2 Page 16 of 16 Revision 0