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| number = ML15328A052
| number = ML15328A052
| issue date = 11/16/2015
| issue date = 11/16/2015
| title = Sequoyah, Unit 1 Cycle 21 and Unit 2 Cycle 20 Core Operating Limits Reports, Revision No. 1
| title = Cycle 21 and Unit 2 Cycle 20 Core Operating Limits Reports, Revision No. 1
| author name = Carlin J T
| author name = Carlin J
| author affiliation = Tennessee Valley Authority
| author affiliation = Tennessee Valley Authority
| addressee name =  
| addressee name =  
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 November 16, 201510 CFR 50.4ATTN: Document Controi DeskU.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2Renewed Facility Operating License Nos. DPR-77 and DPR-79NRC Docket Nos. 50-327 and 50-328
{{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 November 16, 2015 10 CFR 50.4 ATTN: Document Controi Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328


==Subject:==
==Subject:==
Sequoyah Unit I Cycle 21, and Unit 2 Cycle 20 Core Operating Limits Reports, Revision No. 1


==References:==
==References:==
: 1. Letter from NRC to TVA, "Sequoyah Nuclear Plant, Units 1 and 2
                          -  Issuance of Amendments for the Conversion to the Improved Technical Specifications with Beyond Scope Issues (TAC Nos.
MF3128 and MF3129)," dated September 30, 20015 (ML15238B460)
In accordance with Sequoyah Nuclear Plant (SQN) Units 1 and 2 Technical Specifications (TSs) 5.6.3.d, enclosed is the Unit 1 Cycle 21 Core Operating Limits Report (COLR), Revision 1, and Unit 2 Cycle 20OCOLR, Revision 1. In accordance with TSs 5.6.3.d, the COLRs are required to be provided to the Nuclear Regulatory Commission (NRC) within 30 days of issuance for each reload cycle. Sequoyah Units 1 and 2 were issued license amendment Nos. 334 and 327, respectively for improved standard TSs (Reference 1). These license amendments resulted in the revisions to each of the COLRs as discussed in Enclosure 1. The revised COLRs became effective on October 21, 2016.
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.
Soso


Sequoyah Unit I Cycle 21, and Unit 2 Cycle 20 Core Operating Limits Reports, Revision No. 11. Letter from NRC to TVA, "Sequoyah Nuclear Plant, Units 1 and 2-Issuance of Amendments for the Conversion to the ImprovedTechnical Specifications with Beyond Scope Issues (TAC Nos.MF3128 and MF3129),"
U.S. Nuclear Regulatory Commission Page 2 November 16, 2015 Sequoyah Nuclear Plant Enclosures
dated September 30, 20015(ML1 5238B460)
: 1.     Units 1 and 2 Core Operating Limits Report Changes
In accordance with Sequoyah Nuclear Plant (SQN) Units 1 and 2 Technical Specifications (TSs) 5.6.3.d, enclosed is the Unit 1 Cycle 21 Core Operating LimitsReport (COLR), Revision 1, and Unit 2 Cycle 20OCOLR, Revision
: 2.      Sequoyah Unit I Cycle 21 Core Operating Limits Report, Revision 1
: 1. In accordance with TSs 5.6.3.d, the COLRs are required to be provided to the Nuclear Regulatory Commission (NRC) within 30 days of issuance for each reload cycle. SequoyahUnits 1 and 2 were issued license amendment Nos. 334 and 327, respectively forimproved standard TSs (Reference 1). These license amendments resulted in therevisions to each of the COLRs as discussed in Enclosure
: 3.      Sequoyah Unit 2 Cycle 20 Core Operating Limits Report, Revision 1 ZTK: DVG Enclosures cc (Enclosures):
: 1. The revised COLRsbecame effective on October 21, 2016.There are no new regulatory commitments in this letter. If you have any questions, please contact Jonathan
NRC Regional Administrator - Region II NRC Senior Resident Inspector - SQN
: Johnson, SQN Site Licensing Manager at (423) 843-8129.
Soso U.S. Nuclear Regulatory Commission Page 2November 16, 2015Sequoyah Nuclear PlantEnclosures 1.2.3.Units 1 and 2 Core Operating Limits Report ChangesSequoyah Unit I Cycle 21 Core Operating Limits Report, Revision 1Sequoyah Unit 2 Cycle 20 Core Operating Limits Report, Revision 1ZTK: DVGEnclosures cc (Enclosures):
NRC Regional Administrator  
-Region IINRC Senior Resident Inspector  
-SQN ENCLOSURE1I SEQUOYAH UNITS 1 AND 2CORE OPERATING LIMITS REPORT CHANGESThe following describes the changes made to each Units' Core Operating Limits Report(COLR), as result of the NRC review and approval of License Amendment Request for theconversion of the Sequoyah Technical Specification (TS) to Improved Standard Technical Specification, NUREG-1 431, Revision 4.1. Acronyms for All Rods Out (ARO) and Hot Zero THERMAL POWER (HZP) wereremoved from the COLRs.2. In Section 1.0, a table was added to assist user of the COLRs.3. Section 2.0 was updated to align the new TSs Reporting Requirements
: Section, 5.6.3,"Core Operating Limits Report".4. In Section 2.1 the Cycle-Specific Parameter Limits were relocated from the TSs to theCOLRs. These parameters involve the Shutdown Margin requirements with references to the associated Limiting Condition for Operation (LCO).5. 60 ppm Moderator Temperature Coefficient limits were added in "Section


===2.2 consistent===
ENCLOSURE1I SEQUOYAH UNITS 1 AND 2 CORE OPERATING LIMITS REPORT CHANGES The following describes the changes made to each Units' Core Operating Limits Report (COLR), as result of the NRC review and approval of License Amendment Request for the conversion of the Sequoyah Technical Specification (TS) to Improved Standard Technical Specification, NUREG-1 431, Revision 4.
with the NOTE in TSs LCO 3.1.3, "Moderator Temperature Coefficient,"
: 1. Acronyms for All Rods Out (ARO) and Hot Zero THERMAL POWER (HZP) were removed from the COLRs.
Surveillance Requirement 3.1.3.2.6. Control Bank Insertion Limits requirement were added in Section 2.4 as necessary forTSs LCO 3.1.6, "Control Bank Insertion Limits,"
: 2. In Section 1.0, a table was added to assist user of the COLRs.
Surveillance Requirements.
: 3. Section 2.0 was updated to align the new TSs Reporting Requirements Section, 5.6.3, "Core Operating Limits Report".
: 7. Section 2.5 was revised to add information relocated from previous TSs for consistency with approved TSs LCO 3.2.1, "Heat Flux Hot Channel Factor (Fq(X, Y, Z))".8. Section 2.6 was revised to add information relocated from previous TSs for consistency with approved TSs LCO 3.2.2, 'Nuclear Enthalpy Rise Hot Channel Factor F&H(X, Y)".9. Power Distribution Limits coefficient
: 4. In Section 2.1 the Cycle-Specific Parameter Limits were relocated from the TSs to the COLRs. These parameters involve the Shutdown Margin requirements with references to the associated Limiting Condition for Operation (LCO).
: 5. 60 ppm Moderator Temperature Coefficient limits were added in "Section 2.2 consistent with the NOTE in TSs LCO 3.1.3, "Moderator Temperature Coefficient," Surveillance Requirement 3.1.3.2.
: 6. Control Bank Insertion Limits requirement were added in Section 2.4 as necessary for TSs LCO 3.1.6, "Control Bank Insertion Limits," Surveillance Requirements.
: 7. Section 2.5 was revised to add information relocated from previous TSs for consistency with approved TSs LCO 3.2.1, "Heat Flux Hot Channel Factor (Fq(X, Y, Z))".
: 8. Section 2.6 was revised to add information relocated from previous TSs for consistency with approved TSs LCO 3.2.2, 'Nuclear Enthalpy Rise Hot Channel Factor F&H(X


==Subject:==
==Subject:==
Sequoyah Unit I Cycle 21, and Unit 2 Cycle 20 Core Operating Limits Reports, Revision No. 1


==References:==
==References:==
: 1. Letter from NRC to TVA, "Sequoyah Nuclear Plant, Units 1 and 2
                          -  Issuance of Amendments for the Conversion to the Improved Technical Specifications with Beyond Scope Issues (TAC Nos.
MF3128 and MF3129)," dated September 30, 20015 (ML15238B460)
In accordance with Sequoyah Nuclear Plant (SQN) Units 1 and 2 Technical Specifications (TSs) 5.6.3.d, enclosed is the Unit 1 Cycle 21 Core Operating Limits Report (COLR), Revision 1, and Unit 2 Cycle 20OCOLR, Revision 1. In accordance with TSs 5.6.3.d, the COLRs are required to be provided to the Nuclear Regulatory Commission (NRC) within 30 days of issuance for each reload cycle. Sequoyah Units 1 and 2 were issued license amendment Nos. 334 and 327, respectively for improved standard TSs (Reference 1). These license amendments resulted in the revisions to each of the COLRs as discussed in Enclosure 1. The revised COLRs became effective on October 21, 2016.
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.
Soso
U.S. Nuclear Regulatory Commission Page 2 November 16, 2015 Sequoyah Nuclear Plant Enclosures
: 1.      Units 1 and 2 Core Operating Limits Report Changes
: 2.      Sequoyah Unit I Cycle 21 Core Operating Limits Report, Revision 1
: 3.      Sequoyah Unit 2 Cycle 20 Core Operating Limits Report, Revision 1 ZTK: DVG Enclosures cc (Enclosures):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - SQN
ENCLOSURE1I SEQUOYAH UNITS 1 AND 2 CORE OPERATING LIMITS REPORT CHANGES The following describes the changes made to each Units' Core Operating Limits Report (COLR), as result of the NRC review and approval of License Amendment Request for the conversion of the Sequoyah Technical Specification (TS) to Improved Standard Technical Specification, NUREG-1 431, Revision 4.
: 1. Acronyms for All Rods Out (ARO) and Hot Zero THERMAL POWER (HZP) were removed from the COLRs.
: 2. In Section 1.0, a table was added to assist user of the COLRs.
: 3. Section 2.0 was updated to align the new TSs Reporting Requirements Section, 5.6.3, "Core Operating Limits Report".
: 4. In Section 2.1 the Cycle-Specific Parameter Limits were relocated from the TSs to the COLRs. These parameters involve the Shutdown Margin requirements with references to the associated Limiting Condition for Operation (LCO).
: 5. 60 ppm Moderator Temperature Coefficient limits were added in "Section 2.2 consistent with the NOTE in TSs LCO 3.1.3, "Moderator Temperature Coefficient," Surveillance Requirement 3.1.3.2.
: 6. Control Bank Insertion Limits requirement were added in Section 2.4 as necessary for TSs LCO 3.1.6, "Control Bank Insertion Limits," Surveillance Requirements.
: 7. Section 2.5 was revised to add information relocated from previous TSs for consistency with approved TSs LCO 3.2.1, "Heat Flux Hot Channel Factor (Fq(X, Y, Z))".
: 8. Section 2.6 was revised to add information relocated from previous TSs for consistency with approved TSs LCO 3.2.2, 'Nuclear Enthalpy Rise Hot Channel Factor F&H(X, Y)".
: 9. Power Distribution Limits coefficient definitions, such as BQNOM and BHDES, were eliminated as these are defined in the TS Bases.
: 10. The boron concentration limit for TSs LCO 3.9.1, 'Boron Concentration," were added to the COLRs consistent with the approved TVA License Amendment Request.
ENCLOSURE 2 SEQUOYAH UNIT 1 CYCLE 21 CORE OPERATING LIMITS REPORT REVISION 1
QA Record                                                                            QARcordL36 151009 802 SEQUOYAH UNIT 1 CYCLE 21 CORE OPERATING LIMITS REPORT REVISION 1 October 2015 Prepared by:
Christine A. Setter, PWR Fuel Engineering                                            Date Verified by:
John E. Strange, P    R Fuel Engineering Reviewed by:
Date Kathl&*i',A  unningham, PW        Fuengneig ManagerL Date radnS. Catalanotto, Reactor Engineering Manager Approved by:
                                                                            /  '&,/S Date Revision Pages affected    All Reason for Revision: *Update for Improved Technical Specifications ('ITS) Implementation SEQUOYAH-UNIT 1Pae1o16Rvsn1                  Page 1 of 16                                Revision 1
COLR FOR SEQUOYAH UNIT 1 CYCLE 21 1.0        CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit I 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 3.3 Moderator Temperature                    EOL MTC Limit            "2.2.2            4 313 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 Shutdown Bank Insertion Limits        2.3  4 3.1.5    Shutdown Bank Insertion LimitsSD2.4                                                    3 CotoS BnDnsrinMiit                    2.14  5 3.1.6rConrolnBanknnsertion imitstSD                                          2.1. 3 3.1.8      PHYSICS TESTS Exceptions-                SDM                                  2.1.6  3 MODE 2                      -___________                                      __
FQ                                  2.5.1  6 K(Z)                                2.5.2  6 NSLOPEAFD                            2.5.3  6 321 Heat Flux Hot Channel Factor              PSLOPEAFD                            2.5.4  6 321 (F0 (X,Y,Z))                              NSLOPEf 2 (Al)                      2.5.5  6 PSLOPEf 2 (AI)                      2.5.6  6 FQ(X,YZ) Appropriate Factor          2.5.7  6 ITS 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                TRH2.3                                      6 3.2.2263 Channel Factor (FAH(XY))                  FAH(X,Y) Appropriate Factor                  6 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 3.2.3    AXIAL FLUX DIFFERENCE                    AFD Limits                            2.7    7 (AFD)___
3.3.1    Reactor Trip System (RTS)                QTNL, QTPL, QTNS, 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    CORE REOT(OR  OPERATING LIMITS                Aayia        ehd nltclMtos2.0                              3 SEQUOYAH-UNIT 1Pae2o16Rvsn1Page 2 of 16                                                Revision 1
COLR FOR SEQUOYAH UNIT 1 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  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  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 %Alk/
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                    ae3o Page        6Rvso 3 of 16                        Revision 1
COLR FOR SEQUOYAH UNIT 1 CYCLE 21 2.2  Moderator Temperature Coefficient    - MTC (TS 3.1.3) 2.2.1  The BOL MTC limit is: ,*
less positive than                -0.05 x10-5 Ak/k/ 0 F.
2.2.2  The EOL MTC limit is:
less negative than or equal to    -4.50 x 10.4 Ak/k/&deg;F.
2.2.3  The 300 ppm Surveillance limit is:
less negative than or equal to      -3.74 x 10-4 Ak/k/&deg;F.
2.2.4  The 60 ppm Surveillance limit is:
less negative than or equal to      -4.15 xl10  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 1                ae4o page        6Rvso 4 of 16                        Revision 1
COLR FOR SEQUOYAH UNIT 1 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 1                    ae 5 off16Rvso Page      16                          Revision 1
COLR FOR SEQUOYAH UNIT 1 CYCLE 21 2.5    Heat Flux Hot Channel Factor - FQ(X,Y,Z) (TS 3.2.1) 2.5.1    FQRT-          2.62 2.5.2    K(Z) is provided in Figure 2 2.5.3    NSLOPEAFD =          1.21 2.5.4    PSLOPEAFD =          1.55 2.5.5    NSLOPEf2 (AI) =      1.48 2.5.6    PSLOPEf 2(AI) =      2.00 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 cycle burn ups, use 2.0%
2.5.8    ITS LCO 3.2.1 Required Action A.3 reduces the Overpower Delta T Trip setpoints (value of K< 4) at least 1% (in AT span) 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        whenP<0.8 P = THERMAL POWER / RATED THERMAL POWER RRH = Thermal power reduction required to compensate for each 1% that FAH(X,Y) exceeds its limit.
2.6.3    TRH = 0.0334 when 0.8 < P < 1.0 TRH = 0.0167 when P < 0.8 P = THERMAL POWER / RATED THERMAL POWER TRH = Reduction in Overtemperature Delta T K1 setpoint required to compensate for each 1% that FAH(X,Y) exceeds its limit.
SEQUOYAH-UNIT 1Pae6o16RvsnIPage 6 of 16                                Revision 1
COLR FOR SEQUOYAH UNIT 1 CYCLE 21 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  ITS 3.2.2 Required Action A.4 reduces the Overtemperature Delta T setpoint (K1 term in Table 3.3.1-1) by > TRH multiplied by the FAH min margin.
      *2.6.6  ITS 3.2.2 Required Action B.1 reduces the Overtemperature Delta T setpoint (K1 term in Table 3.3.1-1) by >-TRH multiplied by the f1(Al) min margin.
2.7    AXIAL FLUX DIFFERENCE      - AFD (TS 3.2.3) 2.7.1  The AFD limits are specified in Figure 3 SEQUOYAH-UNIT 1Pae7o16RvsnIPage 7 of 16                            Revision 1
COLR FOR SEQUOYAH UNIT 1 CYCLE 21 2.8    Reactor Trip System Instrumentation (TS *3.3.1) 2.8.1        Trip Reset Term [f1(Al)] for Overtemperature Delta-T Trip
      *The following parameters are required to specify the power level-dependent f1(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                      ae8o Page    8 of 166Rvso                    Revision 1
COLR FOR SEQUOYAH UNIT 1 CYCLE 21 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 z 2080 ppm.
SEQUOYAH-UNIT 1                      ae9o Page    9 of 166Rvso                    Revision 1
COLR FOR SEQUOYAH UNIT 1 CYCLE 21 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 [f1 (AI), f2(AI) limits],
3.1.5-Shutdown Bank Insertion Limits, 3.1.6-Control Bank Insertion Limits, 3.2.1-Heat F~lux 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-Hleat 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])
1 1. BAW-10159P-A, "BWCMV Correlation of Critical Heat Fluxin 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(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                    ae110 off16Rvso Page          16                      Revision 1
COLR FOR SEQUOYAH UNIT 1 CYCLE 21 Table 2 Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation (TS 3.2.2)
AXlAL(X,Y)    ELEVATION (ft) MAP(X,Y,Z)        AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) 1          1.8128                          1          2.5969 2          1.8125                          2          2.5380 3          1.8122.                          3          2.4827 4          1.8119                          4          2.4411 5          1.8115                          5          2.4315 1.1            6          1.8109            1.4          6          2.4800 7          1.8106                          7          2.5356 8          1.8104                          8          2.4447 9          1.8098                          9          2.3555 10          1.8092                          10          2.1738 11          1.7599                          11          2.0238 1          2.0671                          1          2.6723 2          2.0664                          2          2.6061 3          2.0656                          3          2.5417 4          2.0649                          4          2.4913 5          2.0642                          5          2.4801 1.2            6          2.0636            1.5          6          2.5380 7          2.0624                          7          2.6273 8          2.0615                          8          2.5311 9          2.0457                          9          2.4447 10          1.9492                          10          2.2772 11        - 1.8589                          11          2.0975 1          2.3433                          1          2.7308 2            2.3419                          2          2.6605 3          2.3412                          3          2.5947 4            2.3397                          4          2.5371 5            2.3389                          5          2.5234 1.3            6            2.3381            1.6          6          2.5906 7            2.3357                          7          2.7077 8          2.3130                          8          2.6117 9            2.1886                          9          2.5240 10          2.0643                          10          2.3758
______11                    1.9439                          11          2.1662 SEQUOYAH-UNIT 1                    ae111 off16Rvso Page        16                    Revision 1
Uont in    CYCEd2 2EUA TableFO Table 2 (continued)
AXIAL(X,Y)  ELEVATION(ft) MAP(X,Y,Z)      AXIAL(X,Y)      ELEVATION (if) MAP(X,Y,Z) 1        2.7664                                1          2.4339 2        2.7083                                2          2.4060 3        2.6380                                3          2.3856 4        2.5791                                4          2.3423 5        2.5639                                5          2.3114 1.7            6        2.6359              >1.9            6          2.6006 7        2.7795                                7          2.5003 8        2.6870                                8          2.4004 9    "  2.5798                                9          2.2989 10        2.4726                              10          2.1483 11        2.2304                              11    .      1.9630 1        2.7963                                1          2.5057 2        2.7466                                2          2.4754 3        2.6775                                3          2.4449 4        2.6172                              4          2.3591 5        2.6010                                5          2.4205 1.8            6        2.6802              2.1            6          2.7643 7        2.8456                                7          2.6474 8        2.7552                                8          2.5360 9        2.6648                              9          2.4400 10        2.5655                              10          2.3277 11        2.2931                              11          2.0549 1        2.8235                                1          2.5380 2        2.7739                              2          2.5216 3        2.7125                              3          2.4619 4        2.6523                              4          2.4294 5        2.6328                              5          2.4290 1.9          6        2.7200              2.3            6          2.8222 7        2.9065                              7          2.7334 8        2.8193                              8          2.6234 9        2.7288                              9          2.5186 10        2.6384                              10          2.4215
______11                2.3482                _____11                    2.1250 SEQUOYAH-UNIT I1ae1          Page 12 off16Rvso 16                        Revision 1
2 2EUA    UcnItinCYCEd TableFO Table 2 (continued)
AXIAL(X,Y)  ELEVATION (ft) MAP(X,Y,Z)      AXIAL(X,Y)  ELEVATION (ft) MAP(X,Y,Z) 1        2.6440                            1          2.2448 2        2.5160                            2          2.5535 3        2.5045                            3          2.4678 4        2.4488                          4          2.3229 5        2.5803                            5          2.8913 2.5            6        2.9481            3.1            6          3.1515 7        2.8544                            7          3.0181 8        2.7286                            8          2.9699 9        2.6450                            9          2.8941 10        2.5527                          10          2.7819 11        2.1731                          11          2.1866 1        2.5554                            1          2.0228 2        2.5529                            2          2.5172 3        2.5197                            3          2.4007 4        2.4375                          4          2.2195 5        2.5643                            5          3.0496 2.7            6        2.9839            3.3            6          3.2226 7        2.8837                            7          3.1446 8        2.7939                            8          3.0350 9        2.7040                            9          2.9688 10        2.5997                          10          2.8533 11        2.1995                          11          2.1473 1        2.4223                            1          1.7563 2        2.5653                          2          2.4566 3        2.5075                          3          2.3062 4          2.3955                          4          2.0854 5        2.7295                          5          3.2045 2.9            6        3.0921            3.5          6          3.2929 7          3.0070                          7          3.2627 8        2.8896                          8          3.0846 9        2.8058                          9          3.0299 10        2.6974
* 10          2.9117
_____11                2.2039              _____11                  2.0862 SEQUOYAH-UNIT 1              Pg 13 Page    3oof 16 6Rvso                Revision 1
COLR FOR SEQUOYAH UNIT 1 CYCLE 21 231
{Fu]* %%%hdr'a*.* RegiGn)*                (.575*225}
220                      p Regior~
(FuI~y Withdn~wn                -        (575~225)
                'Inn I 14160/'*B 0-
                                                  /      ABANK                            D Cl) 820 rm 0
400 20                                                                          __ _  _ _ _
40 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 &#x17d;225 and <231 steps withdrawn, inclusive.
Fully withdrawn shall be the position as defined below Cycle Burnup (MWd/mtU)                                Steps Withdrawn
                        >0                                            ->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 1                                  ae114 off16Rvso Page      16                            Revision 1
COLR FOR SEQUOYAH UNIT 1 CYCLE 21 1.2 1.0 Eeaio        K        Iz) 0.8
(          )
0.00    1000 6,25  1000 0.6
                                \                        I 0.4                                        I i
I Elvaio          K!z 0.2 0.0 0        2              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 1 Rvso
COLR FOR SEQUOYAH UNIT 1 CYCLE 21 120                  COLR FOR SEQUOYAH UNIT 1 CYCLE 21 I          II      I        I 110 100 (710) UnaccieptableI_
90
                                                              -        -  hOpe rationI a.
0  80 0
0.
70                                            -        _                                                                            -. I_
          'I 60 I-a'U  50 II-0  40 30
                              ]
I      q            L I
20            I                    I S I        I1 10 I                    I 0                                '      !      i      '
                    -50    -40    -30    -20    -10      0      10      20    30    40    50 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% in power, and the AFD limit lines must be made more restrictive by 1% in AFD until the LEFM is returned to operation.
SEQUOYAH-UNIT 1                          Pg 166oof 16 Page          6Rvso                        Revision 1
ENCLOSURE 3 SEQUOYAH UNIT 2 CYCLE 20 CORE OPERATING LIMITS REPORT REVISION 1
QA Record                                                                              QARcordL36 151009 803 SEQUOYAH UNIT 2 CYCLE 20 CORE OPERATING LIMITS REPORT REVISION I October 2015 Prepared by:
Christine A. Setter, PWR Fuel Engineering                                          Date Verified by:
Jol*E.Strange., P,5R* Fuel Engineering                                /            DatO!e Reviewed by:
K    *he1A.Cnigam, PWR Fuel Engineering Manager                                    Date Brandon S. Catalanotto, Reactor Engineering Manager                                Date/
                                                                                      /
Approved by:
PORC Chairman                                                                      Date Plant Manager                                                                'Date Revision .. _1 Pages affected    All Reason for Revision: Update for Improved Technical Specifications (ITS) Implementation SEQUOYAH-UNJT 2Pae1o17Rvsn1                Page 1 of 17                                    Revision 1
COLR FOR SEQUOYAH UNIT 2 CYCLE 20 1.0        CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit 2 Cycle 20 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    4 313 Moderator Temperature                  EOL MTC Limit                        2.2.2    4 Coefficient (MTC)                    300Oppm 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 Shutdown Bank Insertion Limits        2.3      4 3.1.5      Shutdown Bank Insertion LimitsSD214                                                  3 CotoS anDnetinLmt                    2..4      5 3.1.6rCntrolnBnkIInsetionnLiitsiSs                                        2.14    3 3.1.8      PHYSICS TESTS Exceptions          -  SDM                                  2.1.6    3 MODE 2 FTP                                2.5.1    6 K(Z)                                  2.5.2    6 NSLOPEAFD                            2.5.3    6 321 Heat Flux Hot ChanneiFactor            PSLOPEAFD                            2.5.4    6 (F0 (X,Y,Z))                          NSLOPEf 2 (AI)                        2.5.5    6 PSLOPEf 2 (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,Y,Z)                            2.6.1    6 RRH                                  2.6.2    6 322 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)                                _  _  _  _  _  _ _  _  _  _ _
331 Reactor Trip System (RTS)              QTNL, QTPL, QTNS, 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    CORE REOT(OR  OPERATING LlMITS              Aayia nltclMtos2.0 ehd                              3 SEQUOYAH-UNIT 2Pae2o17Risn1 Page 2 of 17                                              Revision 1
COLR FoR SEQUOYAH UNIT 2 CYCLE 20 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        - SOM (TS 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8) 2.1.1  For TS 3.1.1, SOM 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  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  For TS 3.1.8, SDM shall, be >_.1.6 %Ak/k in MODE 2.
SEQUOYAH-UNIT 2Pae3o17RvsnIPage 3 of 17                                .Revision 1
COLR FOR SEQUOYAH UNIT 2 CYCLE 20 2.2  Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.2.1  The BOL MTC limit is:
less positive than                -0.16 x10-5 Ak/k/&deg;F.
2.2.2  The EOL MTC limit is:
less negative than or equal to    -4.50 x 10 A Ak/k/&deg;F.
2.2.3  The 300 ppm Surveillance limit is:
less negative than or equal to    -3.75 x 104 Ak/k/&deg;F.
2.2.4  The 60 ppm Surveillance limit is:
less negative than or equal to    -4.20 x10A Ak/k/&deg;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:
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COLR FOR SEQUOYAH UNIT 2 CYCLE 20 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 0. 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            Bank Overlap                Bank Difference (ts)          (steps)                    (steps) 225                          9712 226                          9812 227                          99                            128__________
228                        100                            128 229                        101                            128 230                        102                            128 231                        103                          "128 SEQUOYAH-UNIT 2Pae5o17RvsnIPage 5 of 17                                  Revision 1
COLR FOR SEQUOYAH UNIT 2 CYCLE 20 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 =      1.44 2.5.4    PSLOPEAFD =      1.76-2.5.5    NSLOPEf 2(/I) = 1.48 2.5.6    PSLOPEf 2(AI) = 2.98 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:            0 to 3312 MWd/mtU,    use 2.0%
For cycle burnups:      > 3312 to 3864 MWd/mtU,      use 2.12%
For cycle* burnups:              > 386,4 MWd/mtU,  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 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 Tables 2a and 2b.
2.6.2    RRH  =  3.34  when 0.8  <  P_* 1.0 RRHIl.67        whenP<0.8 P  = THERMAL POWER / RATED THERMAL POWER RRH    =  Thermal power reduction required to compensate for each
                          *1% that FAH(X,Y) exceeds its limit.
2.6.3    TRH  =  0.0334 when 0.8    <  P < 1.0 TRH  =  0.01 67 when P  < 0.8 P = THERMAL POWER I RATED THERMAL POWER TRH = Reduction in Overtemperature Delta T K1 setpoint required to compensate for each 1% that FAH(X,Y) exceeds its limit.
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COLR FOR SEQUOYAH UNIT 2 CYCLE 20 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  ITS 3.2.2 Required Action A.4 reduces the overtemperature Delta T setpoint (K1 term in Table 3.3.1-1) by > TRH multiplied by the  FAN  min margin.
2.6.6  ITS 3.2.2 Required Action 8.1 reduces the Overtemperature Delta T setpoint (K1 term in Table 3.3.1-1) by > TRH multiplied by the f1 (Al) min margin.
2.7  AXIAL FLUX DIFFERENCE      - AFD (TS 3.2.3) 2.7.1  The AFD limits are specified in Figure 3 SEQUOYAH-UNIT 2Pae7o17RvsnI Page 7 of 17                            Revision 1
COLR FOR SEQUOYAH UNIT 2 CYCLE 20 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 f1(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 AlI 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 2Pae8o17Rvsn1Page 8 of 17                                    Revision 1
COLR FOR SEQUOYAH UNIT 2 CYCLE 20 2.8.2      Trip Reset Term [fz(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 > 2000 ppm.
SEQUOYAH-UNIT 2Pae9o17Rvsn1                                                Revision 1 Page 9 of 17
COLR FOR SEQUOYAH UNIT 2 CYCLE 20 Table 1 COLR Methodology Topical Reports
: 1. BAW-1 0180-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-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-1 0227P-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(Al) 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(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(Al) limits])
SEQUOYAH-UNIT 2                  Pg Page 100oof 17  7Rvso                  Revision 1
CQLR FOR SEQUOYAH UNIT 2 CYCLE 20 Table 2a Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation Advanced W17 HTP TM Fuel (TS 3.2.2)
AXIAL(X,Y)    ELEVATION (ft) MAP(X,Y,Z)      AXIAL(X,Y)    ELEVATION (ft) MAP(X,Y,Z) 1        1.8128                            1          2.5969 2          1.8125                            2          2.5380 3          1.8122                            3          2.4827 4          1.8119                            4          2.4411 5          1.8115                            5          2.4315 1.1              6          1.8109            1.4              6          2.4800 7          1.8106                            7          2.5356 8          1.8104                            8          2.4447 9          1.8098                            9          2.3555 10        1.8092                            10          2.1738
______11                  1.7599                            11          2.0238 1        2.0671                            1          2.6723 2          2.0664                            2          2.6061 3          2.0656                            3          2.5417 4          2.0649                            4          2.4913 5          2.0642                            5          2.4801 1.2              6          2.0636            1.5              6          2.5380 7          2.0624                            7          2.6273 8          2.0615                            8          2.5311 9          2.0457                            9          2.4447 10          1.9492                            10          2.2772
_____11                    1.8589                            11          2.0975 1          2.3433                            1          2.7308 2          2.3419                            2          2.6605 3          2.3412                            3.          2.5947 4          2.3397                            4          2.5371 5          2.3389                            5          2.5234 1.3              6          2.3381            1.6            6          2.5906
                    -7          2.3357                            7          2.7077 8          2.3130                            8          2.6117 9          2.1886                            9          2.5240 10          2.0643                            10          2.3758
______11                    1.9439            __  __ _11                  2.1662 SEQUOYAH-UNIT 2Pae1of7eisnI Page 11 of 17                            Revision 1
YCed 20 CO    ablFO2OaH UcnIti2n Table 2a (continued)
AXIAL(X,Y)  ELEVATION (ft)  MAP(X,Y,Z)      AXlAL(X,Y)      ELEVATION (ft) MAP(X,Y,Z) 1          ,2.7664                              1          2.4339 2            2.7083                              2          2.4060 3            2.6380                              3          2.3856 4            2.5791                              4          2.3423 5            2.5639                              5          2.3114 1.7            6            2.6359,          >1.9              6          2.6006 7            2.7795                              7          2.5003 8            2.6870                              8          2.4004 9            2.5798                              9          2.2989 10            2.4726                              10          2.1483 11            2.2304            _____11                      1.9630 1            2.7963                              1          2.5057 2            2.7466                              2          2.4754 3            2.6775                              3          2.4449 4            2.6172                              4          2.3591 5            2.6010                              5          2.4205 1.8            6            2.6802            2.1                6          2.7643 7            2.8456                              7          2.6474 8            2.7552                              8          2.5360 9            2.6648                              9          2.4400 10            2.5655                              10          2.3277 11            2.2931            _____11                      2.0549 1            2.8235                              1          2.5380 2            2.7739                              2          2.5216 3            2.7125                              3          2.4619 4            2.6523                              4          2.4294 5            2.6328                              5          2.4290 1.9            6            2.7200            2.3                6          2.8222 7            2.9065                              7          2.7334 8            2.8193                              8          2.6234 9            2.7288                              9          2.5186 10            2.6384                              10          2.4215
_____11                    2.3482            _____11                      2.1250 SEQUOYAH-UNIT 2Pae1of7                                                Revision 1 Page 12 of 17
2 2OaH UcnIti2nCYLEd TableFO Table 2a (continued)
AXIAL(X,Y)  ELEVATION (ft) MAP(X,Y,Z)        AXIAL(X,Y)  ELEVATION (ft)  MAP(X,Y,Z) 1          2.6440                            1          2.2448 2          2.5160                            2          2.5535
              '  3          2.5045                            3          2.4678 4          2.4488                            4          2.3229 5          2.5803                            5          2.8913 2.5.          6          2.9481              3.1            6          3.1515 7          2.8544                            7          3.0181 8          2.7286                            8          2.9699 9          2.6450                            9          2.8941 10          2.5527                            10          2.7819
_____11                  2.1731                            11          2.1866 1          2.5554                            1          2.0228 2          2.5529                            2          2.5172 3          2.5197                            3          2.4007 4          2.4375                            4          2.2195 5          2.5643                            5          3.0496 2.7            6          2.9839              3.3            6          3.2226 7          2.8837                            7          3.1446 8          2.7939                            8          3.0350 9          2.7040                            9          2.9688 10        .2.5997                            10          2.8533 11          2.1995                            11          2.1473 1          2.4223                            1.          1.7563 2          2.5653                            2          2.4566 3          2.5075                            3          2.3062 4          2.3955                            4          2.0854 5          2.7295                            5          3.2045 2.9            6          3.0921              3.5            6          3.2929 7          3.0070                            7          3.2627 8          2.8896                            8          3.0846 9          2.8058                            9          .3.0299 10          2.6974                            10.          2.9117
_____11                  2.2039              _____11                  2.0862 SEQUOYAH-UNIT 2                Pg Page 133f7Rvso of 17                      Revision 1
COLR FOR SEQUOYAH UNIT 2 CYCLE 20 Table 2b Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation Mark-BW Fuel (TS 3.2.2)
AXIAL(X,Y)      ELEVATION (ft) MAP(X,Y,Z)      AXIAL(X,Y) ELEVATION (ft)  MAP(X,Y,Z) 2        1.9343                          2            2.8143 4        1.9300                          4            2.9856 1.1                6        1.9234            1.9          6            3.0073 8        1.9115                          8            2.8509 10        1.8894                        10            2.7048 2        2.1663                          2            2.4405 4        2.1558                          4            2.4405 1.2                6        2.1410            >1.9          6            2.7376 8        2.1153                          8            2.5906
                      '10        2,0582                        10            2.3456 2        *2.4023                          2            2.5881 4        2.3825                          4            2.5881 1.3                6        2.3599            2.2          6            2.9899 8        2.3100                          8            2.7800
_______10                    2.1760                        10            2.5367 2        2.6453                          2            2.6111 4        2.6136                          4            2.6111 1.4                6        2.5610            2.6          6            3.2947 8        2.4199                          8            3.2055 10        2.2787                        10            2.8049 2        2.7189                          2            2.9142 4        2.8181                          4            2.9142 1.5                6        2.6735                36                    4.0216 8        2.5280                          8            3.6527 10        2.3749                        10            3.1711 2        2.7720                          2            2.9618 4        2.9219                          4            2.9618 1.7                6        2.8641            3.5          6            4.2351 8        2.7064                          8            3.7452 10        2.5539                        10            3.3214 SEQUOYAH-UNIT 2                  Pg 144oof 17 Page        7Rvso                Revision 1
COLR FOR SEQUOYAH UNIT 2 CYCLE 20 r-                  /~-          BA K C/
* 140
        &          (u1208 w100                                                                              _______
        -*                                                                        BANK 0D Z80 40                              /
20, 0 {.09,o)            ________          ________            _______          _______
0                0.2              0.A              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, inclusive.
Fully withdrawn shall be the position as defined below, Cycle Burnup (MWd/mtU)                                Steps Withdrawn
                    &#x17d;0                                            &#x17d; 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 LEEM 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                              Pg Page 155oof 17  7Rvso                      Revision 1


Sequoyah Unit I Cycle 21, and Unit 2 Cycle 20 Core Operating Limits Reports, Revision No. 11. Letter from NRC to TVA, "Sequoyah Nuclear Plant, Units 1 and 2-Issuance of Amendments for the Conversion to the ImprovedTechnical Specifications with Beyond Scope Issues (TAC Nos.MF3128 and MF3129),"
COLR FOR SEQUOYAH UNIT 2 CYCLE 20 1.2 I              2          2  I I            2          I  I
dated September 30, 20015(ML1 5238B460)
                            -        2 1.0                                          I          I  I I              I          I 2         I 0.8          4-----2 2              2          2 I              2        2    I 2          2 0.6 Elevation      K(z)
In accordance with Sequoyah Nuclear Plant (SQN) Units 1 and 2 Technical Specifications (TSs) 5.6.3.d, enclosed is the Unit 1 Cycle 21 Core Operating LimitsReport (COLR), Revision 1, and Unit 2 Cycle 20OCOLR, Revision
(ft) 0.000      1.0000 0.4 6.285      1.0000  -~----------
: 1. In accordance with TSs 5.6.3.d, the COLRs are required to be provided to the Nuclear Regulatory Commission (NRC) within 30 days of issuance for each reload cycle. SequoyahUnits 1 and 2 were issued license amendment Nos. 334 and 327, respectively forimproved standard TSs (Reference 1). These license amendments resulted in therevisions to each of the COLRs as discussed in Enclosure
2        7.995      1.0000      2         2    2 2        9.705      1.0000    2          2    2 12.000      1.0000                2    2 0.2            -             2              2          I 2              2          2  2 2              2          2  2 I.             2          2  2 2               I              I          2   I I          I    I 0.0 0        2                 4            6              10          12 Core Height (Feet)
: 1. The revised COLRsbecame effective on October 21, 2016.There are no new regulatory commitments in this letter. If you have any questions, please contact Jonathan
FIGURE 2 K(Z) - Normalized FQ(X,Y,Z) as a Function of Core Height (TS 3.2.1 )
: Johnson, SQN Site Licensing Manager at (423) 843-8129.
SEQUOYAH-UNIT 2                       Page 166oof 17 Pg              7Rvso          Revision 1
Soso U.S. Nuclear Regulatory Commission Page 2November 16, 2015Sequoyah Nuclear PlantEnclosures 1.2.3.Units 1 and 2 Core Operating Limits Report ChangesSequoyah Unit I Cycle 21 Core Operating Limits Report, Revision 1Sequoyah Unit 2 Cycle 20 Core Operating Limits Report, Revision 1ZTK: DVGEnclosures cc (Enclosures):
NRC Regional Administrator
-Region IINRC Senior Resident Inspector
-SQN ENCLOSURE1I SEQUOYAH UNITS 1 AND 2CORE OPERATING LIMITS REPORT CHANGESThe following describes the changes made to each Units' Core Operating Limits Report(COLR), as result of the NRC review and approval of License Amendment Request for theconversion of the Sequoyah Technical Specification (TS) to Improved Standard Technical Specification, NUREG-1 431, Revision 4.1. Acronyms for All Rods Out (ARO) and Hot Zero THERMAL POWER (HZP) wereremoved from the COLRs.2. In Section 1.0, a table was added to assist user of the COLRs.3. Section 2.0 was updated to align the new TSs Reporting Requirements
: Section, 5.6.3,"Core Operating Limits Report".4. In Section 2.1 the Cycle-Specific Parameter Limits were relocated from the TSs to theCOLRs. These parameters involve the Shutdown Margin requirements with references to the associated Limiting Condition for Operation (LCO).5. 60 ppm Moderator Temperature Coefficient limits were added in "Section


===2.2 consistent===
COLR FOR SEQUOYAH UNIT 2 CYCLE 20 120 110 100
with the NOTE in TSs LCO 3.1.3, "Moderator Temperature Coefficient,"
                          --- K-I I        II
Surveillance Requirement 3.1.3.2.6. Control Bank Insertion Limits requirement were added in Section 2.4 as necessary forTSs LCO 3.1.6, "Control Bank Insertion Limits,"
                                                - - - L I --
Surveillance Requirements.
II
: 7. Section 2.5 was revised to add information relocated from previous TSs for consistency with approved TSs LCO 3.2.1, "Heat Flux Hot Channel Factor (Fq(X, Y, Z))".8. Section 2.6 was revised to add information relocated from previous TSs for consistency with approved TSs LCO 3.2.2, 'Nuclear Enthalpy Rise Hot Channel Factor F&H(X, Y)".9. Power Distribution Limits coefficient definitions, such as BQNOM and BHDES, wereeliminated as these are defined in the TS Bases.10. The boron concentration limit for TSs LCO 3.9.1, 'Boron Concentration,"
                                                                            -V---
were added tothe COLRs consistent with the approved TVA License Amendment Request.
I I
ENCLOSURE 2SEQUOYAH UNIT 1 CYCLE 21CORE OPERATING LIMITS REPORT REVISION 1
K-I
QA RecordQA RcordL36 151009 802SEQUOYAH UNIT 1 CYCLE 21CORE OPERATING LIMITS REPORTREVISION 1October 2015Prepared by:Christine A. Setter, PWR Fuel Engineering Verified by:John E. Strange, P R Fuel Engineering Reviewed by:
[-.
unningham, PW Fue ngneig ManagerLradnS. Catalanotto, Reactor Engineering ManagerApproved by:DateDateDate/ '&,/SDateRevisionPages affected AllReason for Revision:
Uaccept be_/
*Update for Improved Technical Specifications
90          - -tperatD-     7     -n-I-
('ITS) Implementation SEQUOYAH-UNIT 1Pae1o16Rvsn1 Page 1 of 16Revision 1
80      -   -I----/.         --   &deg;PecirainI          II           i  I _
COLR FOR SEQUOYAH UNIT 1 CYCLE 211.0 CORE OPERATING LIMITS REPORTThis CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit I Cycle 21has 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 COLRSection Technical Specification COLR Parameter Section Page3.1.1 SHUTDOWN MARGIN (SDM) SDM 2.1 3BOL MTC Limit 2.2.1 43.3 Moderator Temperature EOL MTC Limit "2.2.2 4313 Coefficient (MTC) 300 ppm Surveillance Limit 2.2.3 4________________60 ppm Surveillance Limit 2.2.4 43.1.4 Rod Group Alignment Limits SDM 2.1.3 3Shutdown Bank Insertion Limits 2.3 43.1.5 Shutdown Bank Insertion LimitsSD2.4 3CotoS BnDnsrinMiit 2.14 53.1.6rConrolnBanknnsertion imitstSD 2.1. 33.1.8 PHYSICS TESTS Exceptions-SDM 2.1.6 3MODE 2 -___________
70
__FQ 2.5.1 6K(Z) 2.5.2 6NSLOPEAFD 2.5.3 6321 H eat Flux Hot Channel Factor PSLOPEAFD 2.5.4 6321 (F0(X,Y,Z))
                                                                      --       --   i28,o      -
NSLOPEf2(Al) 2.5.5 6PSLOPEf2(AI) 2.5.6 6FQ(X,YZ)
60       * -- I--/t- ---               I 1-S1 50
Appropriate Factor 2.5.7 6ITS LCO 3.2.1 Required Action A.3 2.5.8 6MAP(X,Y,Z) 2.6.1 6RRH 2.6.2 6Nuclear Enthalpy Rise Hot TRH2.3 63.2.2263 6Channel Factor (FAH(XY))
              *6=
FAH(X,Y)
                'U
Appropriate Factor 2.6.4 7ITS 3.2.2 Required Action A.4 2.6.5 7ITS 3.2.2 Required Action B.1 2.6.6 73.2.3 AXIAL FLUX DIFFERENCE AFD Limits 2.7 7(AFD)___3.3.1 Reactor Trip System (RTS) QTNL, QTPL, QTNS, and QTPS 2.8.1 8Instrumentation QPNL, QPPL, QPNS, and QPPS 2.8.2 93.9.1 Boron Concentration Refueling Boron Concentration 2.9 9CORE OPERATING LIMITS Aayia ehd5.6.3 REOT(OR nltclMtos2.0 3SEQUOYAH-UNIT 1Pae2o16Rvsn1 Page 2 of 16Revision 1
(-4b,5o) I         I 40 30              I2 20
COLR FOR SEQUOYAH UNIT 1 CYCLE 212.0 .OPERATING LIMITSThe cycle-specific parameter limits for the TS listed in section 1 .0 are presented inthe following subsections.
                                                        ---             1--K 10
These limits have been developed using the NRCapproved methodologies specified in TS 5.6.3. The versions of the topical reportswhich 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 LifeEOL stands for End of Cycle LifeRTP stands for RATED THERMAL POWER2.1 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/kin 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/kin MODE 5.2.1.3 For TS 3.1.4, SDM shall be > 1.6 %Ak/kin MODE 1 and MODE 2.2.1.4 For TS 3.1.5, SDM shall be >-1.6 %Ak/kin MODE 1 and MODE 2.2.1.5 For TS 3.1.6, SDM shall be --.1.6 %Alk/in MODE 1 and MODE 2 with keff> 1.0.2.1.6 For TS 3.1.8, SDM shall be _> 1.6 %Ak/kin MODE 2.SEQUOYAH-UNIT 1 ae3o 6RvsoPage 3 of 16Revision 1
* l--
COLR FOR SEQUOYAH UNIT 1 CYCLE 212.2Moderator Temperature Coefficient
I           -I 0v                                          I.
-MTC (TS 3.1.3)2.2.1 The BOL MTC limit is: less positive than2.2.2 The EOL MTC limit is:less negative than or equal to2.2.3 The 300 ppm Surveillance limit is:less negative than or equal to2.2.4 The 60 ppm Surveillance limit is:less negative than or equal to-0.05 x10-5 Ak/k/0F.-4.50 x 10.4 Ak/k/&deg;F.-3.74 x 10-4 Ak/k/&deg;F.-4.15 xl10 Ak/k/0F.2.3Shutdown Bank Insertion Limits (TS 3.1.5)2.3.1 Each shutdown bank shall be withdrawn to a position as definedbelow:SEQUOYAH-UNIT 1 ae4o 6Rvsopage 4 of 16Revision 1
                        -50        -40    -30    -20    -10     0     10      20    30  40    50 Flux Difference (hl) %
COLR FOR SEQUOYAH UNIT 1 CYCLE 212.4Control Bank Insertion Limits (TS 3.1.6)2.4.1 The control banks shall be limited in physical insertion as shown inFigure 1.2.4.2 Each cOntrol bank shall be considered fully withdrawn from the coreat>__225 steps.2.4.3 The control banks shall be operated in sequence by withdrawal ofBank A, Bank B, Bank C, and Bank D. The control banks shall besequenced in reverse order upon insertion.
FIGURE 3 AXIAL FLUX DIFFERENCE Limits As A Function of RATED THERMAL. POWER
2.4.4 Each control bank not fully withdrawn from the core shall be operatedwith the following overlap as a function of full out position.
                                          .For Burnup Range 0 EFPD to EOL (TS 3.2.3)
Full Out Position (steps) Bank Overlap (steps) Bank Difference (steps)225 97 128226 98 128227 99 128228 100 128229 101 128230 102 128231 103 128SEQUOYAH-UNIT 1 ae f16RvsoPage 5 of 16Revision 1
This figure is valid for operation at a RATED THERMAL POWER of 3455 MWth when the LEFM is in oPeration.
COLR FOR SEQUOYAH UNIT 1 CYCLE 212.5 Heat Flux Hot Channel Factor -FQ(X,Y,Z)
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 AFD limit lines must be made more restrictive by 1% in AFO until the LEFM is returned to operation.
(TS 3.2.1)2.5.1 FQRT- 2.622.5.2 K(Z) is provided in Figure 22.5.3 NSLOPEAFD
SEQUOYAH-UNIT 2                               Pg Page 17 7oof 17 7Rvso                    Revision 1}}
= 1.212.5.4 PSLOPEAFD
= 1.552.5.5 NSLOPEf2(AI) = 1.482.5.6 PSLOPEf2(AI) = 2.002.5.7 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 cycle burn ups, use 2.0%2.5.8 ITS LCO 3.2.1 Required Action A.3 reduces the Overpower Delta TTrip setpoints (value of K<4) at least 1 % (in AT span) for each 1 % thatFQC(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<1.0RRH=1.67 whenP<0.8 P = THERMAL POWER / RATED THERMAL POWERRRH = Thermal power reduction required to compensate for each1% that FAH(X,Y) exceeds its limit.2.6.3 TRH = 0.0334 when 0.8 < P < 1.0TRH = 0.0167 when P < 0.8P = THERMAL POWER / RATED THERMAL POWERTRH = Reduction in Overtemperature Delta T K1 setpoint required tocompensate for each 1% that FAH(X,Y) exceeds its limit.SEQUOYAH-UNIT 1Pae6o16RvsnI Page 6 of 16Revision 1
COLR FOR SEQUOYAH UNIT 1 CYCLE 212.6.4 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 ITS 3.2.2 Required Action A.4 reduces the Overtemperature Delta Tsetpoint (K1 term in Table 3.3.1-1) by > TRH multiplied by the FAH minmargin.*2.6.6 ITS 3.2.2 Required Action B.1 reduces the Overtemperature Delta Tsetpoint (K1 term in Table 3.3.1-1) by >- TRH multiplied by the f1(Al)min margin.2.7 AXIAL FLUX DIFFERENCE
-AFD (TS 3.2.3)2.7.1 The AFD limits are specified in Figure 3SEQUOYAH-UNIT 1Pae7o16RvsnI Page 7 of 16Revision 1
COLR FOR SEQUOYAH UNIT 1 CYCLE 212.8 Reactor Trip System Instrumentation (TS *3.3.1)2.8.1 Trip Reset Term [f1(Al)] for Overtemperature Delta-T Trip*The following parameters are required to specify the power level-dependent f1(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 RATEDTHERMAL POWER at which the trip setpoint isnot reduced by the axial power distribution.
2.8.1.2 QTPL = +5%where QTPL = the maximum positive Al setpoint at RATEDTHERMAL POWER at which the trip setpoint isnot 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 RATEDTHERMAL 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 RATEDTHERMAL POWER (QTPL).SEQUOYAH-UNIT 1 ae8o 6RvsoPage 8 of 16Revision 1
COLR FOR SEQUOYAH UNIT 1 CYCLE 212.8.2 Trip Reset Term [f2(AI)] for Overpower Delta-T TripThe 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 RATEDTHERMAL *POWER at which the trip setpoint isnot reduced by the axial power distribution.
2.8.2.2 QPPL = +25%where QPPL = the maximum positive Al setpoint at RATEDTHERMAL POWER at which the trip setpoint isnot reduced by the axial power distribution.
2.8.2.3 QPNS = 1.70%where QPNS = the percent reduction in Overpower Delta-T tripsetpoint for each percent that the magnitude of Alexceeds its negative limit at RATED THERMALPOWER (QPNL).2.8.2.4 QPPS = 1.70%where QPPS = the percent reduction in Overpower Delta-T tripsetpoint 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 z 2080 ppm.SEQUOYAH-UNIT 1 ae9o 6RvsoPage 9 of 16Revision 1
COLR FOR SEQUOYAH UNIT 1 CYCLE 21Table 1COLR Methodology Topical Reports1. 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 AnalysisMethodology 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
[f1(AI), f2(AI) limits],3.1.5-Shutdown Bank Insertion Limits, 3.1.6-Control Bank Insertion Limits, 3.2.1-Heat F~lux 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-Hleat 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])1 1. BAW-10159P-A, "BWCMV Correlation of Critical Heat Fluxin Mixing Vane Grid FuelAssemblies,"
August .1990.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-Reactor Trip System Instrumentation
[f1(AI) limits])12. BAW-10231P-A, Revision 1, "COPERNIC Fuel Rod Design Computer Code," January2004.(Methodology for TS 3.3.1-Reactor Trip System Instrumentation
[f2(AI) limits])-
SEQUOYAH-UNIT 1 ae1 f16RvsoPage 10 of 16Revision 1
COLR FOR SEQUOYAH UNIT 1 CYCLE 21Table 2Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation (TS 3.2.2)AXlAL(X,Y)
ELEVATION (ft) MAP(X,Y,Z) 1 1.81282 1.81253 1.8122.4 1.81195 1.81151.1 6 1.81097 1.81068 1.81049 1.809810 1.809211 1.75991 2.06712 2.06643 2.06564 2.06495 2.06421.2 6 2.06367 2.06248 2.06159 2.045710 1.949211 -1.85891 2.34332 2.34193 2.34124 2.33975 2.33891.3 6 2.33817 2.33578 2.31309 2.188610 2.0643______11 1.9439AXIAL(X,Y)
ELEVATION (ft) MAP(X,Y,Z) 1 2.59692 2.53803 2.48274 2.44115 2.43151.4 6 2.48007 2.53568 2.44479 2.355510 2.173811 2.02381 2.67232 2.60613 2.54174 2.49135 2.48011.5 6 2.53807 2.62738 2.53119 2.444710 2.277211 2.09751 2.73082 2.66053 2.59474 2.53715 2.52341.6 6 2.59067 2.70778 2.61179 2.524010 2.375811 2.1662SEQUOYAH-UNIT 1 ae1 f16RvsoPage 11 of 16Revision 1
TableFO 2EU A Uont in CYCEd 2Table 2 (continued)
AXIAL(X,Y)
ELEVATION(ft)
MAP(X,Y,Z) 1 2.76642 2.70833 2.63804 2.57915 2.56391.7 6 2.63597 2.77958 2.68709 " 2.579810 2.472611 2.23041 2.79632 2.74663 2.67754 2.61725 2.60101.8 6 2.68027 2.84568 2.75529 2.664810 2.565511 2.29311 2.82352 2.77393 2.71254 2.65235 2.63281.9 6 2.72007 2.90658 2.81939 2.728810 2.6384______11 2.3482AXIAL(X,Y)
ELEVATION (if) MAP(X,Y,Z) 1 2.43392 2.40603 2.38564 2.34235 2.3114>1.9 6 2.60067 2.50038 2.40049 2.298910 2.148311 .1.96301 2.50572 2.47543 2.44494 2.35915 2.42052.1 6 2.76437 2.64748 2.53609 2.440010 2.327711 2.05491 2.53802 2.52163 2.46194 2.42945 2.42902.3 6 2.82227 2.73348 2.62349 2.518610 2.4215_____11 2.1250SEQUOYAH-UNIT I1ae1 f16RvsoPage 12 of 16Revision 1
TableFO 2EU A UcnItin CYCEd 2Table 2 (continued)
AXIAL(X,Y)
ELEVATION (ft) MAP(X,Y,Z) 1 2.64402 2.51603 2.50454 2.44885 2.58032.5 6 2.94817 2.85448 2.72869 2.645010 2.552711 2.17311 2.55542 2.55293 2.51974 2.43755 2.56432.7 6 2.98397 2.88378 2.79399 2.704010 2.599711 2.19951 2.42232 2.56533 2.50754 2.39555 2.72952.9 6 3.09217 3.00708 2.88969 2.805810 2.6974_____11 2.2039AXIAL(X,Y)
ELEVATION (ft) MAP(X,Y,Z) 1 2.24482 2.55353 2.46784 2.32295 2.89133.1 6 3.15157 3.01818 2.96999 2.894110 2.781911 2.18661 2.02282 2.51723 2.40074 2.21955 3.04963.3 6 3.22267 3.14468 3.03509 2.968810 2.853311 2.14731 1.75632 2.45663 2.30624 2.08545 3.20453.5 6 3.29297 3.26278 3.08469 3.0299* 10 2.9117_____11 2.0862SEQUOYAH-UNIT 1 Pg 3o 6RvsoPage 13 of 16Revision 1
COLR FOR SEQUOYAH UNIT 1 CYCLE 21231220 (FuI~y Withdn~wn Regior~ (575~225) p --'Inn I0-Cl)rm0
/ ABANK D82040020 __ _ _ _ _40(Fully Inserted) 0.20.40.60_8IFraction of RATED THERMAL POWERFIGURE 1Rod 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 areat a position within the interval of 225 and <231 steps withdrawn, inclusive.
Fully withdrawn shall be the position as defined belowCycle Burnup (MWd/mtU)
>0Steps Withdrawn
-> 225 to < 231This 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 levelmust be reduced by 1 .3% in power, and the rod insertion limit lines must be increased by 3 steps withdrawn untilthe LEFM is returned to operation.
SEQUOYAH-UNIT 1 ae1 f16RvsoPage 14 of 16Revision 1
COLR FOR SEQUOYAH UNIT 1 CYCLE 211.21.00.80.60.40.20.0Eeaio K Iz)( )0.00 10006,25 1000\ IIiIElvaio K!z0246-Core Height (Feet)81012FIGURE 2K(Z) -Normalized FQ(X,Y,Z) as a Function of Core Height(TS 3.2.1)SEQUOYAH-UNIT 1Page 15 of 16 RvsoRevision 1
COLR FOR SEQUOYAH UNIT 1 CYCLE 21a.000.'II-a'UII-01201101009080706050403020100III I I(710) UnaccieptableI_
--hOpe rationI-_ -. I_S I I 1COLR FOR SEQUOYAH UNIT 1 CYCLE 21I q]IILIII' ! i '-50-40 20 -10 0 10 20 30Flux Difference (Al) %FIGURE 3AXIAL FLUX DIFFERENCE Limits As AFunction of RATED THERMAL POWERFor Burnup Range 0 EFPD to EOL(TS 3.2.3)4050This 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 levelmust be reduced by 1.3% in power, and the AFD limit lines must be made more restrictive by 1% in AFD untilthe LEFM is returned to operation.
SEQUOYAH-UNIT 1 Pg 6o 6RvsoPage 16 of 16Revision 1
ENCLOSURE 3SEQUOYAH UNIT 2 CYCLE 20CORE OPERATING LIMITS REPORT REVISION 1
QA RecordQA RcordL36 151009 803SEQUOYAH UNIT 2 CYCLE 20CORE OPERATING LIMITS REPORTREVISION IOctober 2015Prepared by:Christine A. Setter, PWR Fuel Engineering DateVerified by:/
P,5R Fuel Engineering DatO! eReviewed by:K PWR Fuel Engineering Manager DateBrandon S. Catalanotto, Reactor Engineering Manager Date/ /Approved by:PORC Chairman DatePlant Manager 'DateRevision
.._1Pages affected AllReason for Revision:
Update for Improved Technical Specifications (ITS) Implementation SEQUOYAH-UNJT 2Pae1o17Rvsn1 Page 1 of 17Revision 1
COLR FOR SEQUOYAH UNIT 2 CYCLE 201.0 CORE OPERATING LIMITS REPORTThis CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit 2 Cycle 20has 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 COLRSection Technical Specification COLR Parameter Section Page3.1.1 SHUTDOWN MARGIN (SDM) SDM 2.1 3BOL MTC Limit 2.2.1 4313 Moderator Temperature EOL MTC Limit 2.2.2 4Coefficient (MTC) 300Oppm Surveillance Limit 2.2.3 460 ppm Surveillance Limit 2.2.4 43.1.4 Rod Group Alignment Limits SDM 2.1.3 3Shutdown Bank Insertion Limits 2.3 43.1.5 Shutdown Bank Insertion LimitsSD214 3CotoS anDnetinLmt 2..4 53.1.6rCntrolnBnkIInsetionnLiitsiSs 2.14 33.1.8 PHYSICS TESTS Exceptions
-SDM 2.1.6 3MODE 2FTP 2.5.1 6K(Z) 2.5.2 6NSLOPEAFD 2.5.3 6321 Heat Flux Hot ChanneiFactor PSLOPEAFD 2.5.4 6(F0(X,Y,Z))
NSLOPEf2(AI) 2.5.5 6PSLOPEf2(AI) 2.5.6 6FQ(X,Y,Z)
Appropriate Factor 2.5.7 6___________________ITS LCO 3.2.1 Required Action A.3 2.5.8 6MAP(X,Y,Z) 2.6.1 6RRH 2.6.2 6322 Nuclear Enthalpy Rise Hot TRH 2.6.3 6Channel Factor (FAH(X,Y))
FAH(X,Y)
Appropriate Factor 2.6.4 7ITS 3.2.2 Required Action A.4 2.6.5 7ITS 3.2.2 Required Action B.1 2.6.6 7323 AXIAL FLUX DIFFERENCE AOLmt .(AFD) _ _ _ _ _ _ _ _ _ _ _331 Reactor Trip System (RTS) QTNL, QTPL, QTNS, and QTPS 2.8.1 8Instrumentation QPNL, QPPL, QPNS, and QPPS 2.8.2 93.9.1 Boron Concentration Refueling Boron Concentration 2.9 9CORE OPERATING LlMITS Aayia ehd5.6.3 REOT(OR nltclMtos2.0 3SEQUOYAH-UNIT 2Pae2o17Risn1 Page 2 of 17Revision 1
COLR FoR SEQUOYAH UNIT 2 CYCLE 202.0 OPERATING LIMITSThe cycle-specific parameter limits for the TS listed in section 1 .0 are presented inthe following subsections.
These limits have been developed using the NRCapproved methodologies specified in TS 5.6.3. The versions of the topical reportswhich 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 LifeEOL stands for End of Cycle LifeRTP stands for RATED THERMAL POWER2.1 SHUTDOWN MARGIN -SOM (TS 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8)2.1.1 For TS 3.1.1, SOM shall be >_1.6 %Ak/kin MODE 2 with keff < 1.0, MODE 3 and MODE 42.1.2 For TS 3.1.1, SDM shall be >_1.0 %Ak/kin MODE 5.2.1.3 For TS 3.1.4, SDM shall be >1.6 %Ak/kin MODE 1 and MODE 2.2.1.4 For TS 3.1.5, SDM shall be >_1.6 %Ak/kin MODE 1 and MODE 2.2.1.5 For TS 3.1.6, SDM shall be >__1.6 %Ak/kin MODE 1 and MODE 2 with keff> 1.0.2.1.6 For TS 3.1.8, SDM shall, be >_.1.6 %Ak/kin MODE 2.SEQUOYAH-UNIT 2Pae3o17RvsnI Page 3 of 17.Revision 1
COLR FOR SEQUOYAH UNIT 2 CYCLE 202.2Moderator Temperature Coefficient
-MTC (TS 3.1.3)2.2.1 The BOL MTC limit is:less positive than2.2.2 The EOL MTC limit is:less negative than or equal to2.2.3 The 300 ppm Surveillance limit is:less negative than or equal to2.2.4 The 60 ppm Surveillance limit is:less negative than or equal to-0.16 x10-5 Ak/k/&deg;F.-4.50 x 1 0A Ak/k/&deg;F.-3.75 x 1 04 Ak/k/&deg;F.-4.20 x10A Ak/k/&deg;F.2.3Shutdown Bank Insertion Limits (TS 3.1.5)2.3.1 Each shutdown bank shall be withdrawn to a position as definedbelow:SEQUOYAH-UNIT 2Pae4o17RvsnI
* Page 4 of 17Revision 1
COLR FOR SEQUOYAH UNIT 2 CYCLE 202.4Control Bank Insertion Limits (TS 3.1.6)2.4.1 The control banks Shall be limited in physical insertion as shown inFigure 1.2.4.2 Each control bank shall be considered fully withdrawn from the coreat>__225 steps.2.4.3 The control banks shall be operated in sequence by withdrawal ofBank A, Bank B, Bank C, and Bank 0. The control banks shall besequenced in reverse order upon insertion.
2.4.4 Each control bank not fully withdrawn from the core shall be operatedwith the following overlap as a function of full out position.
Full Out Position Bank Overlap Bank Difference (ts) (steps) (steps)225 9712226 9812227 99 128__________
228 100 128229 101 128230 102 128231 103 "128SEQUOYAH-UNIT 2Pae5o17RvsnI Page 5 of 17Revision 1
COLR FOR SEQUOYAH UNIT 2 CYCLE 202.5 Heat Flux Hot Channel Factor- FQ(X,Y,Z)
(TS 3.2.1)RTP2.5.1 FQ = 2.622.5.2 K(Z) is provided in Figure 22.5.3 NsLoPEAFD
= 1.442.5.4 PSLOPEAFD
= 1.76-2.5.5 NSLOPEf2(/I) = 1.482.5.6 PSLOPEf2(AI) = 2.98M2.5.7 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:
0 to 3312 MWd/mtU, use 2.0%For cycle burnups:
> 3312 to 3864 MWd/mtU, use 2.12%For cycle* burnups:
> 386,4 MWd/mtU, use 2.0%2.5.8 ITS LCO 3.2.1 Required Action A.3 reduces the Overpower Delta TTrip setpoints (value of K4) at least 1% (in AT span) for each 1% thatFQC(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 Tables 2a and 2b.2.6.2 RRH = 3.34 when 0.8 < P_ 1.0RRHIl.67 whenP<0.8 P = THERMAL POWER / RATED THERMAL POWERRRH = Thermal power reduction required to compensate for each*1% that FAH(X,Y) exceeds its limit.2.6.3 TRH = 0.0334 when 0.8 < P < 1.0TRH = 0.01 67 when P < 0.8P = THERMAL POWER I RATED THERMAL POWERTRH = Reduction in Overtemperature Delta T K1 setpoint required tocompensate for each 1 % that FAH(X,Y) exceeds its limit.SEQUOYAH-UNIT 2 Pg f1Page 6 of 17Revision 1
COLR FOR SEQUOYAH UNIT 2 CYCLE 202.6.4 The appropriate factor for increase in FAHM (X,Y) for compliance withSR 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 Tsetpoint (K1 term in Table 3.3.1-1) by > TRH multiplied by the FAN minmargin.2.6.6 ITS 3.2.2 Required Action 8.1 reduces the Overtemperature Delta Tsetpoint (K1 term in Table 3.3.1-1) by > TRH multiplied by the f1 (Al)min margin.2.7 AXIAL FLUX DIFFERENCE
-AFD (TS 3.2.3)2.7.1 The AFD limits are specified in Figure 3SEQUOYAH-UNIT 2Pae7o17RvsnI Page 7 of 17Revision 1
COLR FOR SEQUOYAH UNIT 2 CYCLE 202.8 Reactor Trip System Instrumentation (TS 3.3.1)2.8.1 Trip Reset Term [f1(AI)] for Overtemperature Delta-T TripThe following parameters are required to specify the power level-dependent f1(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 RATEDTHERMAL POWER at which the trip setpoint isnot reduced by the axial power distribution.
2.8.1.2 QTPL = +5%where QTPL = the maximum positive AlI setpoint at RATEDTHERMAL POWER at which the trip setpoint isnot 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 RATEDTHERMAL 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 RATEDTHERMAL POWER (QTPL).SEQUOYAH-UNIT 2Pae8o17Rvsn1 Page 8 of 17Revision 1
COLR FOR SEQUOYAH UNIT 2 CYCLE 202.8.2 Trip Reset Term [fz(AI)]
for Overpower Delta-T TripThe 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 RATEDTHERMAL POWER at which the trip setpoint isnot reduced by the axial power distribution.
2.8.2.2 QPPL = +25%where QPPL = the maximum positive Al setpoint at RATEDTHERMAL POWER at which the trip setpoint isnot reduced by the axial power distribution.
2.8.2.3 QPNS = 1.70%where QPNS = the percent reduction in Overpower Delta-Ttrip setpoint for each percent that themagnitude of Al exceeds its negative limit atRATED THERMAL POWER (QPNL).2.8.2.4 QPPS = 1.70%where QPPS = the percent reduction in Overpower Delta-Ttrip setpoint for each percent that themagnitude of Al exceeds its positive limit atRATED THERMAL POWER (QPPL).2.9 Boron Concentration (TS 3.9.1)2.9.1 The refueling boron concentration shall be > 2000 ppm.SEQUOYAH-UNIT 2Pae9o17Rvsn1 Page 9 of 17Revision 1
COLR FOR SEQUOYAH UNIT 2 CYCLE 20Table 1COLR Methodology Topical Reports1. BAW-1 0180-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 AnalysisMethodology 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-1 0227P-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(Al) limits])11. BAW-1 01 59P-A, "BWCMV Correlation of Critical Heat Flux in Mixing Vane Grid FuelAssemblies,"
August 1990.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-Reactor Trip System Instrumentation
[f1(AI) limits])12. BAW-10231 P-A, Revision
.1, "COPERNIC Fuel Rod Design Computer Code," January2004.(Methodology for TS 3.3.1-Reactor Trip System Instrumentation
[f2(Al) limits])SEQUOYAH-UNIT 2 Pg 0o 7RvsoPage 10 of 17Revision 1
CQLR FOR SEQUOYAH UNIT 2 CYCLE 20Table 2aMaximum Allowable Peaking Limits MAP(X,Y,Z) for Operation Advanced W17 HTPTMFuel (TS 3.2.2)AXIAL(X,Y)
ELEVATION (ft) MAP(X,Y,Z) 1 1.81282 1.81253 1.81224 1.81195 1.81151.1 6 1.81097 1.81068 1.81049 1.809810 1.8092______11 1.75991 2.06712 2.06643 2.06564 2.06495 2.06421.2 6 2.06367 2.06248 2.06159 2.045710 1.9492_____11 1.85891 2.34332 2.34193 2.34124 2.33975 2.33891.3 6 2.3381-7 2.33578 2.31309 2.188610 2.0643______11 1.9439AXIAL(X,Y)
ELEVATION (ft) MAP(X,Y,Z) 1 2.59692 2.53803 2.48274 2.44115 2.43151.4 6 2.48007 2.53568 2.44479 2.355510 2.173811 2.02381 2.67232 2.60613 2.54174 2.49135 2.48011.5 6 2.53807 2.62738 2.53119 2.444710 2.277211 2.09751 2.73082 2.66053. 2.59474 2.53715 2.52341.6 6 2.59067 2.70778 2.61179 2.524010 2.3758_ _ _ _ _11 2.1662SEQUOYAH-UNIT 2Pae1of7eisnI Page 11 of 17Revision 1
CO ablFO 2OaH UcnIti2n YCed 20Table 2a (continued)
AXIAL(X,Y)
ELEVATION (ft) MAP(X,Y,Z) 1 ,2.76642 2.70833 2.63804 2.57915 2.56391.7 6 2.6359,7 2.77958 2.68709 2.579810 2.472611 2.23041 2.79632 2.74663 2.67754 2.61725 2.60101.8 6 2.68027 2.84568 2.75529 2.664810 2.565511 2.29311 2.82352 2.77393 2.71254 2.65235 2.63281.9 6 2.72007 2.90658 2.81939 2.728810 2.6384_____11 2.3482AXlAL(X,Y)
ELEVATION (ft) MAP(X,Y,Z) 1 2.43392 2.40603 2.38564 2.34235 2.3114>1.9 6 2.60067 2.50038 2.40049 2.298910 2.1483_____11 1.96301 2.50572 2.47543 2.44494 2.35915 2.42052.1 6 2.76437 2.64748 2.53609 2.440010 2.3277_____11 2.05491 2.53802 2.52163 2.46194 2.42945 2.42902.3 6 2.82227 2.73348 2.62349 2.518610 2.4215_____11 2.1250SEQUOYAH-UNIT 2Pae1of7Page 12 of 17Revision 1
TableFO 2OaH UcnIti2nCYLEd 2Table 2a (continued)
AXIAL(X,Y)
ELEVATION (ft) MAP(X,Y,Z) 1 2.64402 2.5160' 3 2.50454 2.44885 2.58032.5. 6 2.94817 2.85448 2.72869 2.645010 2.5527_____11 2.17311 2.55542 2.55293 2.51974 2.43755 2.56432.7 6 2.98397 2.88378 2.79399 2.704010 .2.599711 2.19951 2.42232 2.56533 2.50754 2.39555 2.72952.9 6 3.09217 3.00708 2.88969 2.805810 2.6974_____11 2.2039AXIAL(X,Y)
ELEVATION (ft) MAP(X,Y,Z) 1 2.24482 2.55353 2.46784 2.32295 2.89133.1 6 3.15157 3.01818 2.96999 2.894110 2.781911 2.18661 2.02282 2.51723 2.40074 2.21955 3.04963.3 6 3.22267 3.14468 3.03509 2.968810 2.853311 2.14731. 1.75632 2.45663 2.30624 2.08545 3.20453.5 6 3.29297 3.26278 3.08469 .3.029910. 2.9117_____11 2.0862SEQUOYAH-UNIT 2 Pg 3f7RvsoPage 13 of 17Revision 1
COLR FOR SEQUOYAH UNIT 2 CYCLE 20Table 2bMaximum Allowable Peaking Limits MAP(X,Y,Z) for Operation Mark-BW Fuel (TS 3.2.2)AXIAL(X,Y)
ELEVATION (ft) MAP(X,Y,Z) 2 1.93434 1.93001.1 6 1.92348 1.911510 1.88942 2.16634 2.15581.2 6 2.14108 2.1153'10 2,05822 *2.40234 2.38251.3 6 2.35998 2.3100_______10 2.17602 2.64534 2.61361.4 6 2.56108 2.419910 2.27872 2.71894 2.81811.5 6 2.67358 2.528010 2.37492 2.77204 2.92191.7 6 2.86418 2.706410 2.5539AXIAL(X,Y)
ELEVATION (ft) MAP(X,Y,Z) 2 2.81434 2.98561.9 6 3.00738 2.850910 2.70482 2.44054 2.4405>1.9 6 2.73768 2.590610 2.34562 2.58814 2.58812.2 6 2.98998 2.780010 2.53672 2.61114 2.61112.6 6 3.29478 3.205510 2.80492 2.91424 2.914236 4.02168 3.652710 3.17112 2.96184 2.96183.5 6 4.23518 3.745210 3.3214SEQUOYAH-UNIT 2 Pg 4o 7RvsoPage 14 of 17Revision 1
COLR FOR SEQUOYAH UNIT 2 CYCLE 20r- /~- BA K C/* 140& (u120 8w100 _______BANK 0DZ8040 /20,0 {.09,o) ________
________
_______ _______0 0.2 0.A 0.6 0_8(Fully Inserted)
Fraction of RATED THERMAL POWERFIGURE 1Rod 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 areat a position within the interval of >225 and <231 steps withdrawn, inclusive.
Fully withdrawn shall be the position as defined below,Cycle Burnup (MWd/mtU)
Steps Withdrawn 0  225 to -231This figure is valid for operation at a RATED THERMAL POWER of 3455 MWth when the LEFM is in operation.
If the LEEM becomes inoperable, then prior to the next NIS calibration, the maximum allowable power levelmust 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 Pg 5o 7RvsoPage 15 of 17Revision 1
COLR FOR SEQUOYAH UNIT 2 CYCLE 201.21.00.80.60.40.20.0I 2 2 II 2 I I-2 I I II I I2 I4-----22 2 2I 2 2 I2 2Elevation K(z)(ft)0.000 1.00006.285 1.0000 -~----------
2 7.995 1.0000 2 2 22 9.705 1.0000 2 2 212.000 1.0000 2 2-2 2 I2 2 2 22 2 2 2I. 2 2 22 I I 2 II I I0246Core Height (Feet)1012FIGURE 2K(Z) -Normalized FQ(X,Y,Z) as a Function of Core Height(TS 3.2.1 )SEQUOYAH-UNIT 2 Pg 6o 7RvsoPage 16 of 17Revision 1
COLR FOR SEQUOYAH UNIT 2 CYCLE 20I-1-S1*6='U1201101009080706050403020100I I II---K- ---LU accept be_/--tperatD-7 -n---I----/ .--&deg;PecirainI
* -- I--/ t- --- I(-4b,5o)
I IIII I I-- -V- -- -K-I [-.II i I _-- -- i28,o -I 2-----1--K* l--I-II.v-50 30 10 0 10Flux Difference (hl) %20 30 4050FIGURE 3AXIAL FLUX DIFFERENCE Limits As AFunction 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 levelmust be reduced by 1.3% in power, and the AFD limit lines must be made more restrictive by 1% in AFO untilthe LEFM is returned to operation.
SEQUOYAH-UNIT 2 Pg 7o 7RvsoPage 17 of 17Revision 1}}

Latest revision as of 07:24, 5 February 2020

Cycle 21 and Unit 2 Cycle 20 Core Operating Limits Reports, Revision No. 1
ML15328A052
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 11/16/2015
From: John Carlin
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML15328A052 (38)
v • d • e


Text

Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 November 16, 2015 10 CFR 50.4 ATTN: Document Controi Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328

Subject:

Sequoyah Unit I Cycle 21, and Unit 2 Cycle 20 Core Operating Limits Reports, Revision No. 1

References:

1. Letter from NRC to TVA, "Sequoyah Nuclear Plant, Units 1 and 2

- Issuance of Amendments for the Conversion to the Improved Technical Specifications with Beyond Scope Issues (TAC Nos.

MF3128 and MF3129)," dated September 30, 20015 (ML15238B460)

In accordance with Sequoyah Nuclear Plant (SQN) Units 1 and 2 Technical Specifications (TSs) 5.6.3.d, enclosed is the Unit 1 Cycle 21 Core Operating Limits Report (COLR), Revision 1, and Unit 2 Cycle 20OCOLR, Revision 1. In accordance with TSs 5.6.3.d, the COLRs are required to be provided to the Nuclear Regulatory Commission (NRC) within 30 days of issuance for each reload cycle. Sequoyah Units 1 and 2 were issued license amendment Nos. 334 and 327, respectively for improved standard TSs (Reference 1). These license amendments resulted in the revisions to each of the COLRs as discussed in Enclosure 1. The revised COLRs became effective on October 21, 2016.

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.

Soso

U.S. Nuclear Regulatory Commission Page 2 November 16, 2015 Sequoyah Nuclear Plant Enclosures

1. Units 1 and 2 Core Operating Limits Report Changes
2. Sequoyah Unit I Cycle 21 Core Operating Limits Report, Revision 1
3. Sequoyah Unit 2 Cycle 20 Core Operating Limits Report, Revision 1 ZTK: DVG Enclosures cc (Enclosures):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - SQN

ENCLOSURE1I SEQUOYAH UNITS 1 AND 2 CORE OPERATING LIMITS REPORT CHANGES The following describes the changes made to each Units' Core Operating Limits Report (COLR), as result of the NRC review and approval of License Amendment Request for the conversion of the Sequoyah Technical Specification (TS) to Improved Standard Technical Specification, NUREG-1 431, Revision 4.

1. Acronyms for All Rods Out (ARO) and Hot Zero THERMAL POWER (HZP) were removed from the COLRs.
2. In Section 1.0, a table was added to assist user of the COLRs.
3. Section 2.0 was updated to align the new TSs Reporting Requirements Section, 5.6.3, "Core Operating Limits Report".
4. In Section 2.1 the Cycle-Specific Parameter Limits were relocated from the TSs to the COLRs. These parameters involve the Shutdown Margin requirements with references to the associated Limiting Condition for Operation (LCO).
5. 60 ppm Moderator Temperature Coefficient limits were added in "Section 2.2 consistent with the NOTE in TSs LCO 3.1.3, "Moderator Temperature Coefficient," Surveillance Requirement 3.1.3.2.
6. Control Bank Insertion Limits requirement were added in Section 2.4 as necessary for TSs LCO 3.1.6, "Control Bank Insertion Limits," Surveillance Requirements.
7. Section 2.5 was revised to add information relocated from previous TSs for consistency with approved TSs LCO 3.2.1, "Heat Flux Hot Channel Factor (Fq(X, Y, Z))".
8. Section 2.6 was revised to add information relocated from previous TSs for consistency with approved TSs LCO 3.2.2, 'Nuclear Enthalpy Rise Hot Channel Factor F&H(X, Y)".
9. Power Distribution Limits coefficient definitions, such as BQNOM and BHDES, were eliminated as these are defined in the TS Bases.
10. The boron concentration limit for TSs LCO 3.9.1, 'Boron Concentration," were added to the COLRs consistent with the approved TVA License Amendment Request.

ENCLOSURE 2 SEQUOYAH UNIT 1 CYCLE 21 CORE OPERATING LIMITS REPORT REVISION 1

QA Record QARcordL36 151009 802 SEQUOYAH UNIT 1 CYCLE 21 CORE OPERATING LIMITS REPORT REVISION 1 October 2015 Prepared by:

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

John E. Strange, P R Fuel Engineering Reviewed by:

Date Kathl&*i',A unningham, PW Fuengneig ManagerL Date radnS. Catalanotto, Reactor Engineering Manager Approved by:

/ '&,/S Date Revision Pages affected All Reason for Revision: *Update for Improved Technical Specifications ('ITS) Implementation SEQUOYAH-UNIT 1Pae1o16Rvsn1 Page 1 of 16 Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 1.0 CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit I 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 3.3 Moderator Temperature EOL MTC Limit "2.2.2 4 313 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 Shutdown Bank Insertion Limits 2.3 4 3.1.5 Shutdown Bank Insertion LimitsSD2.4 3 CotoS BnDnsrinMiit 2.14 5 3.1.6rConrolnBanknnsertion imitstSD 2.1. 3 3.1.8 PHYSICS TESTS Exceptions- SDM 2.1.6 3 MODE 2 -___________ __

FQ 2.5.1 6 K(Z) 2.5.2 6 NSLOPEAFD 2.5.3 6 321 Heat Flux Hot Channel Factor PSLOPEAFD 2.5.4 6 321 (F0 (X,Y,Z)) NSLOPEf 2 (Al) 2.5.5 6 PSLOPEf 2 (AI) 2.5.6 6 FQ(X,YZ) Appropriate Factor 2.5.7 6 ITS 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 TRH2.3 6 3.2.2263 Channel Factor (FAH(XY)) FAH(X,Y) Appropriate Factor 6 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 3.2.3 AXIAL FLUX DIFFERENCE AFD Limits 2.7 7 (AFD)___

3.3.1 Reactor Trip System (RTS) QTNL, QTPL, QTNS, 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 CORE REOT(OR OPERATING LIMITS Aayia ehd nltclMtos2.0 3 SEQUOYAH-UNIT 1Pae2o16Rvsn1Page 2 of 16 Revision 1

COLR FOR SEQUOYAH UNIT 1 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 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 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 %Alk/

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 ae3o Page 6Rvso 3 of 16 Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 2.2 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.2.1 The BOL MTC limit is: ,*

less positive than -0.05 x10-5 Ak/k/ 0 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 -3.74 x 10-4 Ak/k/°F.

2.2.4 The 60 ppm Surveillance limit is:

less negative than or equal to -4.15 xl10 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 1 ae4o page 6Rvso 4 of 16 Revision 1

COLR FOR SEQUOYAH UNIT 1 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 1 ae 5 off16Rvso Page 16 Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 2.5 Heat Flux Hot Channel Factor - FQ(X,Y,Z) (TS 3.2.1) 2.5.1 FQRT- 2.62 2.5.2 K(Z) is provided in Figure 2 2.5.3 NSLOPEAFD = 1.21 2.5.4 PSLOPEAFD = 1.55 2.5.5 NSLOPEf2 (AI) = 1.48 2.5.6 PSLOPEf 2(AI) = 2.00 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 cycle burn ups, use 2.0%

2.5.8 ITS LCO 3.2.1 Required Action A.3 reduces the Overpower Delta T Trip setpoints (value of K< 4) at least 1% (in AT span) 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 whenP<0.8 P = THERMAL POWER / RATED THERMAL POWER RRH = Thermal power reduction required to compensate for each 1% that FAH(X,Y) exceeds its limit.

2.6.3 TRH = 0.0334 when 0.8 < P < 1.0 TRH = 0.0167 when P < 0.8 P = THERMAL POWER / RATED THERMAL POWER TRH = Reduction in Overtemperature Delta T K1 setpoint required to compensate for each 1% that FAH(X,Y) exceeds its limit.

SEQUOYAH-UNIT 1Pae6o16RvsnIPage 6 of 16 Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 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 ITS 3.2.2 Required Action A.4 reduces the Overtemperature Delta T setpoint (K1 term in Table 3.3.1-1) by > TRH multiplied by the FAH min margin.

  • 2.6.6 ITS 3.2.2 Required Action B.1 reduces the Overtemperature Delta T setpoint (K1 term in Table 3.3.1-1) by >-TRH multiplied by the f1(Al) min margin.

2.7 AXIAL FLUX DIFFERENCE - AFD (TS 3.2.3) 2.7.1 The AFD limits are specified in Figure 3 SEQUOYAH-UNIT 1Pae7o16RvsnIPage 7 of 16 Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 2.8 Reactor Trip System Instrumentation (TS *3.3.1) 2.8.1 Trip Reset Term [f1(Al)] for Overtemperature Delta-T Trip

  • The following parameters are required to specify the power level-dependent f1(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 ae8o Page 8 of 166Rvso Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 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 z 2080 ppm.

SEQUOYAH-UNIT 1 ae9o Page 9 of 166Rvso Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 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 [f1 (AI), f2(AI) limits],

3.1.5-Shutdown Bank Insertion Limits, 3.1.6-Control Bank Insertion Limits, 3.2.1-Heat F~lux 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-Hleat 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])

1 1. BAW-10159P-A, "BWCMV Correlation of Critical Heat Fluxin 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(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 ae110 off16Rvso Page 16 Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 Table 2 Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation (TS 3.2.2)

AXlAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) 1 1.8128 1 2.5969 2 1.8125 2 2.5380 3 1.8122. 3 2.4827 4 1.8119 4 2.4411 5 1.8115 5 2.4315 1.1 6 1.8109 1.4 6 2.4800 7 1.8106 7 2.5356 8 1.8104 8 2.4447 9 1.8098 9 2.3555 10 1.8092 10 2.1738 11 1.7599 11 2.0238 1 2.0671 1 2.6723 2 2.0664 2 2.6061 3 2.0656 3 2.5417 4 2.0649 4 2.4913 5 2.0642 5 2.4801 1.2 6 2.0636 1.5 6 2.5380 7 2.0624 7 2.6273 8 2.0615 8 2.5311 9 2.0457 9 2.4447 10 1.9492 10 2.2772 11 - 1.8589 11 2.0975 1 2.3433 1 2.7308 2 2.3419 2 2.6605 3 2.3412 3 2.5947 4 2.3397 4 2.5371 5 2.3389 5 2.5234 1.3 6 2.3381 1.6 6 2.5906 7 2.3357 7 2.7077 8 2.3130 8 2.6117 9 2.1886 9 2.5240 10 2.0643 10 2.3758

______11 1.9439 11 2.1662 SEQUOYAH-UNIT 1 ae111 off16Rvso Page 16 Revision 1

Uont in CYCEd2 2EUA TableFO Table 2 (continued)

AXIAL(X,Y) ELEVATION(ft) MAP(X,Y,Z) AXIAL(X,Y) ELEVATION (if) MAP(X,Y,Z) 1 2.7664 1 2.4339 2 2.7083 2 2.4060 3 2.6380 3 2.3856 4 2.5791 4 2.3423 5 2.5639 5 2.3114 1.7 6 2.6359 >1.9 6 2.6006 7 2.7795 7 2.5003 8 2.6870 8 2.4004 9 " 2.5798 9 2.2989 10 2.4726 10 2.1483 11 2.2304 11 . 1.9630 1 2.7963 1 2.5057 2 2.7466 2 2.4754 3 2.6775 3 2.4449 4 2.6172 4 2.3591 5 2.6010 5 2.4205 1.8 6 2.6802 2.1 6 2.7643 7 2.8456 7 2.6474 8 2.7552 8 2.5360 9 2.6648 9 2.4400 10 2.5655 10 2.3277 11 2.2931 11 2.0549 1 2.8235 1 2.5380 2 2.7739 2 2.5216 3 2.7125 3 2.4619 4 2.6523 4 2.4294 5 2.6328 5 2.4290 1.9 6 2.7200 2.3 6 2.8222 7 2.9065 7 2.7334 8 2.8193 8 2.6234 9 2.7288 9 2.5186 10 2.6384 10 2.4215

______11 2.3482 _____11 2.1250 SEQUOYAH-UNIT I1ae1 Page 12 off16Rvso 16 Revision 1

2 2EUA UcnItinCYCEd TableFO Table 2 (continued)

AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) 1 2.6440 1 2.2448 2 2.5160 2 2.5535 3 2.5045 3 2.4678 4 2.4488 4 2.3229 5 2.5803 5 2.8913 2.5 6 2.9481 3.1 6 3.1515 7 2.8544 7 3.0181 8 2.7286 8 2.9699 9 2.6450 9 2.8941 10 2.5527 10 2.7819 11 2.1731 11 2.1866 1 2.5554 1 2.0228 2 2.5529 2 2.5172 3 2.5197 3 2.4007 4 2.4375 4 2.2195 5 2.5643 5 3.0496 2.7 6 2.9839 3.3 6 3.2226 7 2.8837 7 3.1446 8 2.7939 8 3.0350 9 2.7040 9 2.9688 10 2.5997 10 2.8533 11 2.1995 11 2.1473 1 2.4223 1 1.7563 2 2.5653 2 2.4566 3 2.5075 3 2.3062 4 2.3955 4 2.0854 5 2.7295 5 3.2045 2.9 6 3.0921 3.5 6 3.2929 7 3.0070 7 3.2627 8 2.8896 8 3.0846 9 2.8058 9 3.0299 10 2.6974

  • 10 2.9117

_____11 2.2039 _____11 2.0862 SEQUOYAH-UNIT 1 Pg 13 Page 3oof 16 6Rvso Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 231

{Fu]* %%%hdr'a*.* RegiGn)* (.575*225}

220 p Regior~

(FuI~y Withdn~wn - (575~225)

'Inn I 14160/'*B 0-

/ ABANK D Cl) 820 rm 0

400 20 __ _ _ _ _

40 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 Ž225 and <231 steps withdrawn, inclusive.

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

>0 ->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 1 ae114 off16Rvso Page 16 Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 1.2 1.0 Eeaio K Iz) 0.8

( )

0.00 1000 6,25 1000 0.6

\ I 0.4 I i

I Elvaio K!z 0.2 0.0 0 2 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 1 Rvso

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 120 COLR FOR SEQUOYAH UNIT 1 CYCLE 21 I II I I 110 100 (710) UnaccieptableI_

90

- - hOpe rationI a.

0 80 0

0.

70 - _ -. I_

'I 60 I-a'U 50 II-0 40 30

]

I q L I

20 I I S I I1 10 I I 0 '  ! i '

-50 -40 -30 -20 -10 0 10 20 30 40 50 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% in power, and the AFD limit lines must be made more restrictive by 1% in AFD until the LEFM is returned to operation.

SEQUOYAH-UNIT 1 Pg 166oof 16 Page 6Rvso Revision 1

ENCLOSURE 3 SEQUOYAH UNIT 2 CYCLE 20 CORE OPERATING LIMITS REPORT REVISION 1

QA Record QARcordL36 151009 803 SEQUOYAH UNIT 2 CYCLE 20 CORE OPERATING LIMITS REPORT REVISION I October 2015 Prepared by:

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

Jol*E.Strange., P,5R* Fuel Engineering / DatO!e Reviewed by:

K *he1A.Cnigam, PWR Fuel Engineering Manager Date Brandon S. Catalanotto, Reactor Engineering Manager Date/

/

Approved by:

PORC Chairman Date Plant Manager 'Date Revision .. _1 Pages affected All Reason for Revision: Update for Improved Technical Specifications (ITS) Implementation SEQUOYAH-UNJT 2Pae1o17Rvsn1 Page 1 of 17 Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 1.0 CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit 2 Cycle 20 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 4 313 Moderator Temperature EOL MTC Limit 2.2.2 4 Coefficient (MTC) 300Oppm 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 Shutdown Bank Insertion Limits 2.3 4 3.1.5 Shutdown Bank Insertion LimitsSD214 3 CotoS anDnetinLmt 2..4 5 3.1.6rCntrolnBnkIInsetionnLiitsiSs 2.14 3 3.1.8 PHYSICS TESTS Exceptions - SDM 2.1.6 3 MODE 2 FTP 2.5.1 6 K(Z) 2.5.2 6 NSLOPEAFD 2.5.3 6 321 Heat Flux Hot ChanneiFactor PSLOPEAFD 2.5.4 6 (F0 (X,Y,Z)) NSLOPEf 2 (AI) 2.5.5 6 PSLOPEf 2 (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,Y,Z) 2.6.1 6 RRH 2.6.2 6 322 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) _ _ _ _ _ _ _ _ _ _ _

331 Reactor Trip System (RTS) QTNL, QTPL, QTNS, 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 CORE REOT(OR OPERATING LlMITS Aayia nltclMtos2.0 ehd 3 SEQUOYAH-UNIT 2Pae2o17Risn1 Page 2 of 17 Revision 1

COLR FoR SEQUOYAH UNIT 2 CYCLE 20 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 - SOM (TS 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8) 2.1.1 For TS 3.1.1, SOM 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 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 For TS 3.1.8, SDM shall, be >_.1.6 %Ak/k in MODE 2.

SEQUOYAH-UNIT 2Pae3o17RvsnIPage 3 of 17 .Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 2.2 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.2.1 The BOL MTC limit is:

less positive than -0.16 x10-5 Ak/k/°F.

2.2.2 The EOL MTC limit is:

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

2.2.3 The 300 ppm Surveillance limit is:

less negative than or equal to -3.75 x 104 Ak/k/°F.

2.2.4 The 60 ppm Surveillance limit is:

less negative than or equal to -4.20 x10A 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:

SEQUOYAH-UNIT 2Pae4o17RvsnI*Page 4 of 17 Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 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 0. 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 Bank Overlap Bank Difference (ts) (steps) (steps) 225 9712 226 9812 227 99 128__________

228 100 128 229 101 128 230 102 128 231 103 "128 SEQUOYAH-UNIT 2Pae5o17RvsnIPage 5 of 17 Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 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 = 1.44 2.5.4 PSLOPEAFD = 1.76-2.5.5 NSLOPEf 2(/I) = 1.48 2.5.6 PSLOPEf 2(AI) = 2.98 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: 0 to 3312 MWd/mtU, use 2.0%

For cycle burnups: > 3312 to 3864 MWd/mtU, use 2.12%

For cycle* burnups: > 386,4 MWd/mtU, 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 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 Tables 2a and 2b.

2.6.2 RRH = 3.34 when 0.8 < P_* 1.0 RRHIl.67 whenP<0.8 P = THERMAL POWER / RATED THERMAL POWER RRH = Thermal power reduction required to compensate for each

  • 1% that FAH(X,Y) exceeds its limit.

2.6.3 TRH = 0.0334 when 0.8 < P < 1.0 TRH = 0.01 67 when P < 0.8 P = THERMAL POWER I RATED THERMAL POWER TRH = Reduction in Overtemperature Delta T K1 setpoint required to compensate for each 1% that FAH(X,Y) exceeds its limit.

SEQUOYAH-UNIT 2 Pg Page 6 off117 Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 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 ITS 3.2.2 Required Action A.4 reduces the overtemperature Delta T setpoint (K1 term in Table 3.3.1-1) by > TRH multiplied by the FAN min margin.

2.6.6 ITS 3.2.2 Required Action 8.1 reduces the Overtemperature Delta T setpoint (K1 term in Table 3.3.1-1) by > TRH multiplied by the f1 (Al) min margin.

2.7 AXIAL FLUX DIFFERENCE - AFD (TS 3.2.3) 2.7.1 The AFD limits are specified in Figure 3 SEQUOYAH-UNIT 2Pae7o17RvsnI Page 7 of 17 Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 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 f1(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 AlI 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 2Pae8o17Rvsn1Page 8 of 17 Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 2.8.2 Trip Reset Term [fz(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 > 2000 ppm.

SEQUOYAH-UNIT 2Pae9o17Rvsn1 Revision 1 Page 9 of 17

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 Table 1 COLR Methodology Topical Reports

1. BAW-1 0180-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-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-1 0227P-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(Al) 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(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(Al) limits])

SEQUOYAH-UNIT 2 Pg Page 100oof 17 7Rvso Revision 1

CQLR FOR SEQUOYAH UNIT 2 CYCLE 20 Table 2a Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation Advanced W17 HTP TM Fuel (TS 3.2.2)

AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) 1 1.8128 1 2.5969 2 1.8125 2 2.5380 3 1.8122 3 2.4827 4 1.8119 4 2.4411 5 1.8115 5 2.4315 1.1 6 1.8109 1.4 6 2.4800 7 1.8106 7 2.5356 8 1.8104 8 2.4447 9 1.8098 9 2.3555 10 1.8092 10 2.1738

______11 1.7599 11 2.0238 1 2.0671 1 2.6723 2 2.0664 2 2.6061 3 2.0656 3 2.5417 4 2.0649 4 2.4913 5 2.0642 5 2.4801 1.2 6 2.0636 1.5 6 2.5380 7 2.0624 7 2.6273 8 2.0615 8 2.5311 9 2.0457 9 2.4447 10 1.9492 10 2.2772

_____11 1.8589 11 2.0975 1 2.3433 1 2.7308 2 2.3419 2 2.6605 3 2.3412 3. 2.5947 4 2.3397 4 2.5371 5 2.3389 5 2.5234 1.3 6 2.3381 1.6 6 2.5906

-7 2.3357 7 2.7077 8 2.3130 8 2.6117 9 2.1886 9 2.5240 10 2.0643 10 2.3758

______11 1.9439 __ __ _11 2.1662 SEQUOYAH-UNIT 2Pae1of7eisnI Page 11 of 17 Revision 1

YCed 20 CO ablFO2OaH UcnIti2n Table 2a (continued)

AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) AXlAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) 1 ,2.7664 1 2.4339 2 2.7083 2 2.4060 3 2.6380 3 2.3856 4 2.5791 4 2.3423 5 2.5639 5 2.3114 1.7 6 2.6359, >1.9 6 2.6006 7 2.7795 7 2.5003 8 2.6870 8 2.4004 9 2.5798 9 2.2989 10 2.4726 10 2.1483 11 2.2304 _____11 1.9630 1 2.7963 1 2.5057 2 2.7466 2 2.4754 3 2.6775 3 2.4449 4 2.6172 4 2.3591 5 2.6010 5 2.4205 1.8 6 2.6802 2.1 6 2.7643 7 2.8456 7 2.6474 8 2.7552 8 2.5360 9 2.6648 9 2.4400 10 2.5655 10 2.3277 11 2.2931 _____11 2.0549 1 2.8235 1 2.5380 2 2.7739 2 2.5216 3 2.7125 3 2.4619 4 2.6523 4 2.4294 5 2.6328 5 2.4290 1.9 6 2.7200 2.3 6 2.8222 7 2.9065 7 2.7334 8 2.8193 8 2.6234 9 2.7288 9 2.5186 10 2.6384 10 2.4215

_____11 2.3482 _____11 2.1250 SEQUOYAH-UNIT 2Pae1of7 Revision 1 Page 12 of 17

2 2OaH UcnIti2nCYLEd TableFO Table 2a (continued)

AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) 1 2.6440 1 2.2448 2 2.5160 2 2.5535

' 3 2.5045 3 2.4678 4 2.4488 4 2.3229 5 2.5803 5 2.8913 2.5. 6 2.9481 3.1 6 3.1515 7 2.8544 7 3.0181 8 2.7286 8 2.9699 9 2.6450 9 2.8941 10 2.5527 10 2.7819

_____11 2.1731 11 2.1866 1 2.5554 1 2.0228 2 2.5529 2 2.5172 3 2.5197 3 2.4007 4 2.4375 4 2.2195 5 2.5643 5 3.0496 2.7 6 2.9839 3.3 6 3.2226 7 2.8837 7 3.1446 8 2.7939 8 3.0350 9 2.7040 9 2.9688 10 .2.5997 10 2.8533 11 2.1995 11 2.1473 1 2.4223 1. 1.7563 2 2.5653 2 2.4566 3 2.5075 3 2.3062 4 2.3955 4 2.0854 5 2.7295 5 3.2045 2.9 6 3.0921 3.5 6 3.2929 7 3.0070 7 3.2627 8 2.8896 8 3.0846 9 2.8058 9 .3.0299 10 2.6974 10. 2.9117

_____11 2.2039 _____11 2.0862 SEQUOYAH-UNIT 2 Pg Page 133f7Rvso of 17 Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 Table 2b Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation Mark-BW Fuel (TS 3.2.2)

AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) 2 1.9343 2 2.8143 4 1.9300 4 2.9856 1.1 6 1.9234 1.9 6 3.0073 8 1.9115 8 2.8509 10 1.8894 10 2.7048 2 2.1663 2 2.4405 4 2.1558 4 2.4405 1.2 6 2.1410 >1.9 6 2.7376 8 2.1153 8 2.5906

'10 2,0582 10 2.3456 2 *2.4023 2 2.5881 4 2.3825 4 2.5881 1.3 6 2.3599 2.2 6 2.9899 8 2.3100 8 2.7800

_______10 2.1760 10 2.5367 2 2.6453 2 2.6111 4 2.6136 4 2.6111 1.4 6 2.5610 2.6 6 3.2947 8 2.4199 8 3.2055 10 2.2787 10 2.8049 2 2.7189 2 2.9142 4 2.8181 4 2.9142 1.5 6 2.6735 36 4.0216 8 2.5280 8 3.6527 10 2.3749 10 3.1711 2 2.7720 2 2.9618 4 2.9219 4 2.9618 1.7 6 2.8641 3.5 6 4.2351 8 2.7064 8 3.7452 10 2.5539 10 3.3214 SEQUOYAH-UNIT 2 Pg 144oof 17 Page 7Rvso Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 r- /~- BA K C/

  • 140

& (u1208 w100 _______

-* BANK 0D Z80 40 /

20, 0 {.09,o) ________ ________ _______ _______

0 0.2 0.A 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, inclusive.

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

Ž0 Ž 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 LEEM 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 Pg Page 155oof 17 7Rvso Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 1.2 I 2 2 I I 2 I I

- 2 1.0 I I I I I I 2 I 0.8 4-----2 2 2 2 I 2 2 I 2 2 0.6 Elevation K(z)

(ft) 0.000 1.0000 0.4 6.285 1.0000 -~----------

2 7.995 1.0000 2 2 2 2 9.705 1.0000 2 2 2 12.000 1.0000 2 2 0.2 - 2 2 I 2 2 2 2 2 2 2 2 I. 2 2 2 2 I I 2 I I I I 0.0 0 2 4 6 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 166oof 17 Pg 7Rvso Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 120 110 100

--- K-I I II

- - - L I --

II

-V---

I I

K-I

[-.

Uaccept be_/

90 - -tperatD- 7 -n-I-

80 - -I----/. -- °PecirainI II i I _

70

-- -- i28,o -

60 * -- I--/t- --- I 1-S1 50

  • 6=

'U

(-4b,5o) I I 40 30 I2 20

--- 1--K 10

  • l--

I -I 0v I.

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

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% in power, and the AFD limit lines must be made more restrictive by 1% in AFO until the LEFM is returned to operation.

SEQUOYAH-UNIT 2 Pg Page 17 7oof 17 7Rvso Revision 1

Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 November 16, 2015 10 CFR 50.4 ATTN: Document Controi Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328

Subject:

Sequoyah Unit I Cycle 21, and Unit 2 Cycle 20 Core Operating Limits Reports, Revision No. 1

References:

1. Letter from NRC to TVA, "Sequoyah Nuclear Plant, Units 1 and 2

- Issuance of Amendments for the Conversion to the Improved Technical Specifications with Beyond Scope Issues (TAC Nos.

MF3128 and MF3129)," dated September 30, 20015 (ML15238B460)

In accordance with Sequoyah Nuclear Plant (SQN) Units 1 and 2 Technical Specifications (TSs) 5.6.3.d, enclosed is the Unit 1 Cycle 21 Core Operating Limits Report (COLR), Revision 1, and Unit 2 Cycle 20OCOLR, Revision 1. In accordance with TSs 5.6.3.d, the COLRs are required to be provided to the Nuclear Regulatory Commission (NRC) within 30 days of issuance for each reload cycle. Sequoyah Units 1 and 2 were issued license amendment Nos. 334 and 327, respectively for improved standard TSs (Reference 1). These license amendments resulted in the revisions to each of the COLRs as discussed in Enclosure 1. The revised COLRs became effective on October 21, 2016.

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.

Soso

U.S. Nuclear Regulatory Commission Page 2 November 16, 2015 Sequoyah Nuclear Plant Enclosures

1. Units 1 and 2 Core Operating Limits Report Changes
2. Sequoyah Unit I Cycle 21 Core Operating Limits Report, Revision 1
3. Sequoyah Unit 2 Cycle 20 Core Operating Limits Report, Revision 1 ZTK: DVG Enclosures cc (Enclosures):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - SQN

ENCLOSURE1I SEQUOYAH UNITS 1 AND 2 CORE OPERATING LIMITS REPORT CHANGES The following describes the changes made to each Units' Core Operating Limits Report (COLR), as result of the NRC review and approval of License Amendment Request for the conversion of the Sequoyah Technical Specification (TS) to Improved Standard Technical Specification, NUREG-1 431, Revision 4.

1. Acronyms for All Rods Out (ARO) and Hot Zero THERMAL POWER (HZP) were removed from the COLRs.
2. In Section 1.0, a table was added to assist user of the COLRs.
3. Section 2.0 was updated to align the new TSs Reporting Requirements Section, 5.6.3, "Core Operating Limits Report".
4. In Section 2.1 the Cycle-Specific Parameter Limits were relocated from the TSs to the COLRs. These parameters involve the Shutdown Margin requirements with references to the associated Limiting Condition for Operation (LCO).
5. 60 ppm Moderator Temperature Coefficient limits were added in "Section 2.2 consistent with the NOTE in TSs LCO 3.1.3, "Moderator Temperature Coefficient," Surveillance Requirement 3.1.3.2.
6. Control Bank Insertion Limits requirement were added in Section 2.4 as necessary for TSs LCO 3.1.6, "Control Bank Insertion Limits," Surveillance Requirements.
7. Section 2.5 was revised to add information relocated from previous TSs for consistency with approved TSs LCO 3.2.1, "Heat Flux Hot Channel Factor (Fq(X, Y, Z))".
8. Section 2.6 was revised to add information relocated from previous TSs for consistency with approved TSs LCO 3.2.2, 'Nuclear Enthalpy Rise Hot Channel Factor F&H(X, Y)".
9. Power Distribution Limits coefficient definitions, such as BQNOM and BHDES, were eliminated as these are defined in the TS Bases.
10. The boron concentration limit for TSs LCO 3.9.1, 'Boron Concentration," were added to the COLRs consistent with the approved TVA License Amendment Request.

ENCLOSURE 2 SEQUOYAH UNIT 1 CYCLE 21 CORE OPERATING LIMITS REPORT REVISION 1

QA Record QARcordL36 151009 802 SEQUOYAH UNIT 1 CYCLE 21 CORE OPERATING LIMITS REPORT REVISION 1 October 2015 Prepared by:

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

John E. Strange, P R Fuel Engineering Reviewed by:

Date Kathl&*i',A unningham, PW Fuengneig ManagerL Date radnS. Catalanotto, Reactor Engineering Manager Approved by:

/ '&,/S Date Revision Pages affected All Reason for Revision: *Update for Improved Technical Specifications ('ITS) Implementation SEQUOYAH-UNIT 1Pae1o16Rvsn1 Page 1 of 16 Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 1.0 CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit I 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 3.3 Moderator Temperature EOL MTC Limit "2.2.2 4 313 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 Shutdown Bank Insertion Limits 2.3 4 3.1.5 Shutdown Bank Insertion LimitsSD2.4 3 CotoS BnDnsrinMiit 2.14 5 3.1.6rConrolnBanknnsertion imitstSD 2.1. 3 3.1.8 PHYSICS TESTS Exceptions- SDM 2.1.6 3 MODE 2 -___________ __

FQ 2.5.1 6 K(Z) 2.5.2 6 NSLOPEAFD 2.5.3 6 321 Heat Flux Hot Channel Factor PSLOPEAFD 2.5.4 6 321 (F0 (X,Y,Z)) NSLOPEf 2 (Al) 2.5.5 6 PSLOPEf 2 (AI) 2.5.6 6 FQ(X,YZ) Appropriate Factor 2.5.7 6 ITS 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 TRH2.3 6 3.2.2263 Channel Factor (FAH(XY)) FAH(X,Y) Appropriate Factor 6 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 3.2.3 AXIAL FLUX DIFFERENCE AFD Limits 2.7 7 (AFD)___

3.3.1 Reactor Trip System (RTS) QTNL, QTPL, QTNS, 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 CORE REOT(OR OPERATING LIMITS Aayia ehd nltclMtos2.0 3 SEQUOYAH-UNIT 1Pae2o16Rvsn1Page 2 of 16 Revision 1

COLR FOR SEQUOYAH UNIT 1 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 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 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 %Alk/

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 ae3o Page 6Rvso 3 of 16 Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 2.2 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.2.1 The BOL MTC limit is: ,*

less positive than -0.05 x10-5 Ak/k/ 0 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 -3.74 x 10-4 Ak/k/°F.

2.2.4 The 60 ppm Surveillance limit is:

less negative than or equal to -4.15 xl10 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 1 ae4o page 6Rvso 4 of 16 Revision 1

COLR FOR SEQUOYAH UNIT 1 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 1 ae 5 off16Rvso Page 16 Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 2.5 Heat Flux Hot Channel Factor - FQ(X,Y,Z) (TS 3.2.1) 2.5.1 FQRT- 2.62 2.5.2 K(Z) is provided in Figure 2 2.5.3 NSLOPEAFD = 1.21 2.5.4 PSLOPEAFD = 1.55 2.5.5 NSLOPEf2 (AI) = 1.48 2.5.6 PSLOPEf 2(AI) = 2.00 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 cycle burn ups, use 2.0%

2.5.8 ITS LCO 3.2.1 Required Action A.3 reduces the Overpower Delta T Trip setpoints (value of K< 4) at least 1% (in AT span) 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 whenP<0.8 P = THERMAL POWER / RATED THERMAL POWER RRH = Thermal power reduction required to compensate for each 1% that FAH(X,Y) exceeds its limit.

2.6.3 TRH = 0.0334 when 0.8 < P < 1.0 TRH = 0.0167 when P < 0.8 P = THERMAL POWER / RATED THERMAL POWER TRH = Reduction in Overtemperature Delta T K1 setpoint required to compensate for each 1% that FAH(X,Y) exceeds its limit.

SEQUOYAH-UNIT 1Pae6o16RvsnIPage 6 of 16 Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 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 ITS 3.2.2 Required Action A.4 reduces the Overtemperature Delta T setpoint (K1 term in Table 3.3.1-1) by > TRH multiplied by the FAH min margin.

  • 2.6.6 ITS 3.2.2 Required Action B.1 reduces the Overtemperature Delta T setpoint (K1 term in Table 3.3.1-1) by >-TRH multiplied by the f1(Al) min margin.

2.7 AXIAL FLUX DIFFERENCE - AFD (TS 3.2.3) 2.7.1 The AFD limits are specified in Figure 3 SEQUOYAH-UNIT 1Pae7o16RvsnIPage 7 of 16 Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 2.8 Reactor Trip System Instrumentation (TS *3.3.1) 2.8.1 Trip Reset Term [f1(Al)] for Overtemperature Delta-T Trip

  • The following parameters are required to specify the power level-dependent f1(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 ae8o Page 8 of 166Rvso Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 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 z 2080 ppm.

SEQUOYAH-UNIT 1 ae9o Page 9 of 166Rvso Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 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 [f1 (AI), f2(AI) limits],

3.1.5-Shutdown Bank Insertion Limits, 3.1.6-Control Bank Insertion Limits, 3.2.1-Heat F~lux 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-Hleat 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])

1 1. BAW-10159P-A, "BWCMV Correlation of Critical Heat Fluxin 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(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 ae110 off16Rvso Page 16 Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 Table 2 Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation (TS 3.2.2)

AXlAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) 1 1.8128 1 2.5969 2 1.8125 2 2.5380 3 1.8122. 3 2.4827 4 1.8119 4 2.4411 5 1.8115 5 2.4315 1.1 6 1.8109 1.4 6 2.4800 7 1.8106 7 2.5356 8 1.8104 8 2.4447 9 1.8098 9 2.3555 10 1.8092 10 2.1738 11 1.7599 11 2.0238 1 2.0671 1 2.6723 2 2.0664 2 2.6061 3 2.0656 3 2.5417 4 2.0649 4 2.4913 5 2.0642 5 2.4801 1.2 6 2.0636 1.5 6 2.5380 7 2.0624 7 2.6273 8 2.0615 8 2.5311 9 2.0457 9 2.4447 10 1.9492 10 2.2772 11 - 1.8589 11 2.0975 1 2.3433 1 2.7308 2 2.3419 2 2.6605 3 2.3412 3 2.5947 4 2.3397 4 2.5371 5 2.3389 5 2.5234 1.3 6 2.3381 1.6 6 2.5906 7 2.3357 7 2.7077 8 2.3130 8 2.6117 9 2.1886 9 2.5240 10 2.0643 10 2.3758

______11 1.9439 11 2.1662 SEQUOYAH-UNIT 1 ae111 off16Rvso Page 16 Revision 1

Uont in CYCEd2 2EUA TableFO Table 2 (continued)

AXIAL(X,Y) ELEVATION(ft) MAP(X,Y,Z) AXIAL(X,Y) ELEVATION (if) MAP(X,Y,Z) 1 2.7664 1 2.4339 2 2.7083 2 2.4060 3 2.6380 3 2.3856 4 2.5791 4 2.3423 5 2.5639 5 2.3114 1.7 6 2.6359 >1.9 6 2.6006 7 2.7795 7 2.5003 8 2.6870 8 2.4004 9 " 2.5798 9 2.2989 10 2.4726 10 2.1483 11 2.2304 11 . 1.9630 1 2.7963 1 2.5057 2 2.7466 2 2.4754 3 2.6775 3 2.4449 4 2.6172 4 2.3591 5 2.6010 5 2.4205 1.8 6 2.6802 2.1 6 2.7643 7 2.8456 7 2.6474 8 2.7552 8 2.5360 9 2.6648 9 2.4400 10 2.5655 10 2.3277 11 2.2931 11 2.0549 1 2.8235 1 2.5380 2 2.7739 2 2.5216 3 2.7125 3 2.4619 4 2.6523 4 2.4294 5 2.6328 5 2.4290 1.9 6 2.7200 2.3 6 2.8222 7 2.9065 7 2.7334 8 2.8193 8 2.6234 9 2.7288 9 2.5186 10 2.6384 10 2.4215

______11 2.3482 _____11 2.1250 SEQUOYAH-UNIT I1ae1 Page 12 off16Rvso 16 Revision 1

2 2EUA UcnItinCYCEd TableFO Table 2 (continued)

AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) 1 2.6440 1 2.2448 2 2.5160 2 2.5535 3 2.5045 3 2.4678 4 2.4488 4 2.3229 5 2.5803 5 2.8913 2.5 6 2.9481 3.1 6 3.1515 7 2.8544 7 3.0181 8 2.7286 8 2.9699 9 2.6450 9 2.8941 10 2.5527 10 2.7819 11 2.1731 11 2.1866 1 2.5554 1 2.0228 2 2.5529 2 2.5172 3 2.5197 3 2.4007 4 2.4375 4 2.2195 5 2.5643 5 3.0496 2.7 6 2.9839 3.3 6 3.2226 7 2.8837 7 3.1446 8 2.7939 8 3.0350 9 2.7040 9 2.9688 10 2.5997 10 2.8533 11 2.1995 11 2.1473 1 2.4223 1 1.7563 2 2.5653 2 2.4566 3 2.5075 3 2.3062 4 2.3955 4 2.0854 5 2.7295 5 3.2045 2.9 6 3.0921 3.5 6 3.2929 7 3.0070 7 3.2627 8 2.8896 8 3.0846 9 2.8058 9 3.0299 10 2.6974

  • 10 2.9117

_____11 2.2039 _____11 2.0862 SEQUOYAH-UNIT 1 Pg 13 Page 3oof 16 6Rvso Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 231

{Fu]* %%%hdr'a*.* RegiGn)* (.575*225}

220 p Regior~

(FuI~y Withdn~wn - (575~225)

'Inn I 14160/'*B 0-

/ ABANK D Cl) 820 rm 0

400 20 __ _ _ _ _

40 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 Ž225 and <231 steps withdrawn, inclusive.

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

>0 ->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 1 ae114 off16Rvso Page 16 Revision 1

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 1.2 1.0 Eeaio K Iz) 0.8

( )

0.00 1000 6,25 1000 0.6

\ I 0.4 I i

I Elvaio K!z 0.2 0.0 0 2 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 1 Rvso

COLR FOR SEQUOYAH UNIT 1 CYCLE 21 120 COLR FOR SEQUOYAH UNIT 1 CYCLE 21 I II I I 110 100 (710) UnaccieptableI_

90

- - hOpe rationI a.

0 80 0

0.

70 - _ -. I_

'I 60 I-a'U 50 II-0 40 30

]

I q L I

20 I I S I I1 10 I I 0 '  ! i '

-50 -40 -30 -20 -10 0 10 20 30 40 50 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% in power, and the AFD limit lines must be made more restrictive by 1% in AFD until the LEFM is returned to operation.

SEQUOYAH-UNIT 1 Pg 166oof 16 Page 6Rvso Revision 1

ENCLOSURE 3 SEQUOYAH UNIT 2 CYCLE 20 CORE OPERATING LIMITS REPORT REVISION 1

QA Record QARcordL36 151009 803 SEQUOYAH UNIT 2 CYCLE 20 CORE OPERATING LIMITS REPORT REVISION I October 2015 Prepared by:

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

Jol*E.Strange., P,5R* Fuel Engineering / DatO!e Reviewed by:

K *he1A.Cnigam, PWR Fuel Engineering Manager Date Brandon S. Catalanotto, Reactor Engineering Manager Date/

/

Approved by:

PORC Chairman Date Plant Manager 'Date Revision .. _1 Pages affected All Reason for Revision: Update for Improved Technical Specifications (ITS) Implementation SEQUOYAH-UNJT 2Pae1o17Rvsn1 Page 1 of 17 Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 1.0 CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit 2 Cycle 20 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 4 313 Moderator Temperature EOL MTC Limit 2.2.2 4 Coefficient (MTC) 300Oppm 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 Shutdown Bank Insertion Limits 2.3 4 3.1.5 Shutdown Bank Insertion LimitsSD214 3 CotoS anDnetinLmt 2..4 5 3.1.6rCntrolnBnkIInsetionnLiitsiSs 2.14 3 3.1.8 PHYSICS TESTS Exceptions - SDM 2.1.6 3 MODE 2 FTP 2.5.1 6 K(Z) 2.5.2 6 NSLOPEAFD 2.5.3 6 321 Heat Flux Hot ChanneiFactor PSLOPEAFD 2.5.4 6 (F0 (X,Y,Z)) NSLOPEf 2 (AI) 2.5.5 6 PSLOPEf 2 (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,Y,Z) 2.6.1 6 RRH 2.6.2 6 322 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) _ _ _ _ _ _ _ _ _ _ _

331 Reactor Trip System (RTS) QTNL, QTPL, QTNS, 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 CORE REOT(OR OPERATING LlMITS Aayia nltclMtos2.0 ehd 3 SEQUOYAH-UNIT 2Pae2o17Risn1 Page 2 of 17 Revision 1

COLR FoR SEQUOYAH UNIT 2 CYCLE 20 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 - SOM (TS 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8) 2.1.1 For TS 3.1.1, SOM 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 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 For TS 3.1.8, SDM shall, be >_.1.6 %Ak/k in MODE 2.

SEQUOYAH-UNIT 2Pae3o17RvsnIPage 3 of 17 .Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 2.2 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.2.1 The BOL MTC limit is:

less positive than -0.16 x10-5 Ak/k/°F.

2.2.2 The EOL MTC limit is:

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

2.2.3 The 300 ppm Surveillance limit is:

less negative than or equal to -3.75 x 104 Ak/k/°F.

2.2.4 The 60 ppm Surveillance limit is:

less negative than or equal to -4.20 x10A 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:

SEQUOYAH-UNIT 2Pae4o17RvsnI*Page 4 of 17 Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 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 0. 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 Bank Overlap Bank Difference (ts) (steps) (steps) 225 9712 226 9812 227 99 128__________

228 100 128 229 101 128 230 102 128 231 103 "128 SEQUOYAH-UNIT 2Pae5o17RvsnIPage 5 of 17 Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 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 = 1.44 2.5.4 PSLOPEAFD = 1.76-2.5.5 NSLOPEf 2(/I) = 1.48 2.5.6 PSLOPEf 2(AI) = 2.98 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: 0 to 3312 MWd/mtU, use 2.0%

For cycle burnups: > 3312 to 3864 MWd/mtU, use 2.12%

For cycle* burnups: > 386,4 MWd/mtU, 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 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 Tables 2a and 2b.

2.6.2 RRH = 3.34 when 0.8 < P_* 1.0 RRHIl.67 whenP<0.8 P = THERMAL POWER / RATED THERMAL POWER RRH = Thermal power reduction required to compensate for each

  • 1% that FAH(X,Y) exceeds its limit.

2.6.3 TRH = 0.0334 when 0.8 < P < 1.0 TRH = 0.01 67 when P < 0.8 P = THERMAL POWER I RATED THERMAL POWER TRH = Reduction in Overtemperature Delta T K1 setpoint required to compensate for each 1% that FAH(X,Y) exceeds its limit.

SEQUOYAH-UNIT 2 Pg Page 6 off117 Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 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 ITS 3.2.2 Required Action A.4 reduces the overtemperature Delta T setpoint (K1 term in Table 3.3.1-1) by > TRH multiplied by the FAN min margin.

2.6.6 ITS 3.2.2 Required Action 8.1 reduces the Overtemperature Delta T setpoint (K1 term in Table 3.3.1-1) by > TRH multiplied by the f1 (Al) min margin.

2.7 AXIAL FLUX DIFFERENCE - AFD (TS 3.2.3) 2.7.1 The AFD limits are specified in Figure 3 SEQUOYAH-UNIT 2Pae7o17RvsnI Page 7 of 17 Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 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 f1(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 AlI 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 2Pae8o17Rvsn1Page 8 of 17 Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 2.8.2 Trip Reset Term [fz(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 > 2000 ppm.

SEQUOYAH-UNIT 2Pae9o17Rvsn1 Revision 1 Page 9 of 17

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 Table 1 COLR Methodology Topical Reports

1. BAW-1 0180-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-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-1 0227P-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(Al) 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(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(Al) limits])

SEQUOYAH-UNIT 2 Pg Page 100oof 17 7Rvso Revision 1

CQLR FOR SEQUOYAH UNIT 2 CYCLE 20 Table 2a Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation Advanced W17 HTP TM Fuel (TS 3.2.2)

AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) 1 1.8128 1 2.5969 2 1.8125 2 2.5380 3 1.8122 3 2.4827 4 1.8119 4 2.4411 5 1.8115 5 2.4315 1.1 6 1.8109 1.4 6 2.4800 7 1.8106 7 2.5356 8 1.8104 8 2.4447 9 1.8098 9 2.3555 10 1.8092 10 2.1738

______11 1.7599 11 2.0238 1 2.0671 1 2.6723 2 2.0664 2 2.6061 3 2.0656 3 2.5417 4 2.0649 4 2.4913 5 2.0642 5 2.4801 1.2 6 2.0636 1.5 6 2.5380 7 2.0624 7 2.6273 8 2.0615 8 2.5311 9 2.0457 9 2.4447 10 1.9492 10 2.2772

_____11 1.8589 11 2.0975 1 2.3433 1 2.7308 2 2.3419 2 2.6605 3 2.3412 3. 2.5947 4 2.3397 4 2.5371 5 2.3389 5 2.5234 1.3 6 2.3381 1.6 6 2.5906

-7 2.3357 7 2.7077 8 2.3130 8 2.6117 9 2.1886 9 2.5240 10 2.0643 10 2.3758

______11 1.9439 __ __ _11 2.1662 SEQUOYAH-UNIT 2Pae1of7eisnI Page 11 of 17 Revision 1

YCed 20 CO ablFO2OaH UcnIti2n Table 2a (continued)

AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) AXlAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) 1 ,2.7664 1 2.4339 2 2.7083 2 2.4060 3 2.6380 3 2.3856 4 2.5791 4 2.3423 5 2.5639 5 2.3114 1.7 6 2.6359, >1.9 6 2.6006 7 2.7795 7 2.5003 8 2.6870 8 2.4004 9 2.5798 9 2.2989 10 2.4726 10 2.1483 11 2.2304 _____11 1.9630 1 2.7963 1 2.5057 2 2.7466 2 2.4754 3 2.6775 3 2.4449 4 2.6172 4 2.3591 5 2.6010 5 2.4205 1.8 6 2.6802 2.1 6 2.7643 7 2.8456 7 2.6474 8 2.7552 8 2.5360 9 2.6648 9 2.4400 10 2.5655 10 2.3277 11 2.2931 _____11 2.0549 1 2.8235 1 2.5380 2 2.7739 2 2.5216 3 2.7125 3 2.4619 4 2.6523 4 2.4294 5 2.6328 5 2.4290 1.9 6 2.7200 2.3 6 2.8222 7 2.9065 7 2.7334 8 2.8193 8 2.6234 9 2.7288 9 2.5186 10 2.6384 10 2.4215

_____11 2.3482 _____11 2.1250 SEQUOYAH-UNIT 2Pae1of7 Revision 1 Page 12 of 17

2 2OaH UcnIti2nCYLEd TableFO Table 2a (continued)

AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) 1 2.6440 1 2.2448 2 2.5160 2 2.5535

' 3 2.5045 3 2.4678 4 2.4488 4 2.3229 5 2.5803 5 2.8913 2.5. 6 2.9481 3.1 6 3.1515 7 2.8544 7 3.0181 8 2.7286 8 2.9699 9 2.6450 9 2.8941 10 2.5527 10 2.7819

_____11 2.1731 11 2.1866 1 2.5554 1 2.0228 2 2.5529 2 2.5172 3 2.5197 3 2.4007 4 2.4375 4 2.2195 5 2.5643 5 3.0496 2.7 6 2.9839 3.3 6 3.2226 7 2.8837 7 3.1446 8 2.7939 8 3.0350 9 2.7040 9 2.9688 10 .2.5997 10 2.8533 11 2.1995 11 2.1473 1 2.4223 1. 1.7563 2 2.5653 2 2.4566 3 2.5075 3 2.3062 4 2.3955 4 2.0854 5 2.7295 5 3.2045 2.9 6 3.0921 3.5 6 3.2929 7 3.0070 7 3.2627 8 2.8896 8 3.0846 9 2.8058 9 .3.0299 10 2.6974 10. 2.9117

_____11 2.2039 _____11 2.0862 SEQUOYAH-UNIT 2 Pg Page 133f7Rvso of 17 Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 Table 2b Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation Mark-BW Fuel (TS 3.2.2)

AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) 2 1.9343 2 2.8143 4 1.9300 4 2.9856 1.1 6 1.9234 1.9 6 3.0073 8 1.9115 8 2.8509 10 1.8894 10 2.7048 2 2.1663 2 2.4405 4 2.1558 4 2.4405 1.2 6 2.1410 >1.9 6 2.7376 8 2.1153 8 2.5906

'10 2,0582 10 2.3456 2 *2.4023 2 2.5881 4 2.3825 4 2.5881 1.3 6 2.3599 2.2 6 2.9899 8 2.3100 8 2.7800

_______10 2.1760 10 2.5367 2 2.6453 2 2.6111 4 2.6136 4 2.6111 1.4 6 2.5610 2.6 6 3.2947 8 2.4199 8 3.2055 10 2.2787 10 2.8049 2 2.7189 2 2.9142 4 2.8181 4 2.9142 1.5 6 2.6735 36 4.0216 8 2.5280 8 3.6527 10 2.3749 10 3.1711 2 2.7720 2 2.9618 4 2.9219 4 2.9618 1.7 6 2.8641 3.5 6 4.2351 8 2.7064 8 3.7452 10 2.5539 10 3.3214 SEQUOYAH-UNIT 2 Pg 144oof 17 Page 7Rvso Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 r- /~- BA K C/

  • 140

& (u1208 w100 _______

-* BANK 0D Z80 40 /

20, 0 {.09,o) ________ ________ _______ _______

0 0.2 0.A 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, inclusive.

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

Ž0 Ž 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 LEEM 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 Pg Page 155oof 17 7Rvso Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 1.2 I 2 2 I I 2 I I

- 2 1.0 I I I I I I 2 I 0.8 4-----2 2 2 2 I 2 2 I 2 2 0.6 Elevation K(z)

(ft) 0.000 1.0000 0.4 6.285 1.0000 -~----------

2 7.995 1.0000 2 2 2 2 9.705 1.0000 2 2 2 12.000 1.0000 2 2 0.2 - 2 2 I 2 2 2 2 2 2 2 2 I. 2 2 2 2 I I 2 I I I I 0.0 0 2 4 6 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 166oof 17 Pg 7Rvso Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 120 110 100

--- K-I I II

- - - L I --

II

-V---

I I

K-I

[-.

Uaccept be_/

90 - -tperatD- 7 -n-I-

80 - -I----/. -- °PecirainI II i I _

70

-- -- i28,o -

60 * -- I--/t- --- I 1-S1 50

  • 6=

'U

(-4b,5o) I I 40 30 I2 20

--- 1--K 10

  • l--

I -I 0v I.

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

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% in power, and the AFD limit lines must be made more restrictive by 1% in AFO until the LEFM is returned to operation.

SEQUOYAH-UNIT 2 Pg Page 17 7oof 17 7Rvso Revision 1

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