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{{#Wiki_filter:Dominion Energy Kewaunee, Inc.mni N490 Highway 42, Kewaunee, WI 54216-9511 D APR 2 5 2008 Attn: Document Control Desk Serial No. 08-0179 U. S. Nuclear Regulatory Commission LIC/NW/RO Washington, DC 20555-0001 Docket No.: 50-305 License No.: DPR-43 DOMINION ENERGY KEWAUNEE, INC.KEWAUNEE POWER STATION CYCLE 29 CORE OPERATING LIMITS REPORTS Pursuant to Kewaunee Power Station (KPS) Technical Specification (TS) 6.9.a.4.D, enclosed are copies of the KPS Technical Requirements Manual (TRM) Section 2.1, Kewaunee Power Station Core Operating Limits Report (COLR), Cycle 29, Revision 0 and Revision 1.KPS TS 6.9.a.4.D states that the COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC. COLR Cycle 29, Revision 0 was approved but not issued. COLR Cycle 29, Revision 0 was not issued because COLR Cycle 29, Revision 1 was approved before the core was reloaded.If you have any questions or require additional information, please contact Mr. Gerald Riste at (920) 388-8424.Very truly yours, Mic 6l J. Wilson Dir ctor Safety and Licensing Kewaunee Power Station Commitments made by this letter: None  
{{#Wiki_filter:Dominion Energy Kewaunee, Inc.mni N490 Highway 42, Kewaunee, WI 54216-9511                           D APR 2 5 2008 Attn: Document Control Desk                                     Serial No. 08-0179 U. S. Nuclear Regulatory Commission                             LIC/NW/RO Washington, DC 20555-0001                                       Docket No.: 50-305 License No.: DPR-43 DOMINION ENERGY KEWAUNEE, INC.
KEWAUNEE POWER STATION CYCLE 29 CORE OPERATING LIMITS REPORTS Pursuant to Kewaunee Power Station (KPS) Technical Specification (TS) 6.9.a.4.D, enclosed are copies of the KPS Technical Requirements Manual (TRM) Section 2.1, Kewaunee Power Station Core Operating Limits Report (COLR), Cycle 29, Revision 0 and Revision 1.
KPS TS 6.9.a.4.D states that the COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC. COLR Cycle 29, Revision 0 was approved but not issued. COLR Cycle 29, Revision 0 was not issued because COLR Cycle 29, Revision 1 was approved before the core was reloaded.
If you have any questions or require additional information, please contact Mr. Gerald Riste at (920) 388-8424.
Very truly yours, Mic 6l J. Wilson Dir ctor Safety and Licensing Kewaunee Power Station Commitments made by this letter: None


==Enclosures:==
==Enclosures:==
: 1. TRM 2.1, Kewaunee Power Station Core Operating Limits Report (COLR), Cycle 29, Revision 0 2. TRM 2.1, Kewaunee Power Station Core Operating Limits Report (COLR), Cycle 29, Revision 1 P941-Serial No. 08-0179 Page 2 of 2 cc: Regional Administrator, Region III U.S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 Ms. M. H. Chernoff Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-H4A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Kewaunee Power Station Serial No. 08-0179 ENCLOSURE 1 TECHNICAL REQUIREMENTS MANUAL 2.1 KEWAUNEE POWER STATION CORE OPERATING LIMITS REPORT (COLR), CYCLE 29, REVISION 0 KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
: 1. TRM 2.1, Kewaunee Power Station Core Operating Limits Report (COLR), Cycle 29, Revision 0
TRM 2.1 Kewaunee Power Station CORE OPERATING LIMITS REPORT (COLR)CYCLE 29 REVISION 0 Approved Chairman Mtg.#Mtg.#
: 2. TRM 2.1, Kewaunee Power Station Core Operating Limits Report (COLR), Cycle 29, Revision 1 P941-
Table of Contents Section Title Page 1.0 CORE OPERATING LIMITS REPORT ........................................................................
 
1 2.0 OPERATING LIMITS ....................................................................................................
Serial No. 08-0179 Page 2 of 2 cc: Regional Administrator, Region III U.S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 Ms. M. H. Chernoff Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-H4A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Kewaunee Power Station
2 2.1 Reactor Core Safety Limits ....................................
 
2 2.2 Shutdown Margin (SDM) ......................................
Serial No. 08-0179 ENCLOSURE 1 TECHNICAL REQUIREMENTS MANUAL 2.1 KEWAUNEE POWER STATION CORE OPERATING LIMITS REPORT (COLR),
2 2.3 Moderator Temperature Coefficient  
CYCLE 29, REVISION 0 KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
.................................................................
 
2 2.4 Shutdown Bank Insertion Limit ..........................................................................
TRM 2.1 Kewaunee Power Station CORE OPERATING LIMITS REPORT (COLR)
2 2.5 Control Bank Insertion Limits ...............................................................................
CYCLE 29 REVISION 0 Approved Chairman         Mtg.#
2 2.6 Nuclear Heat Flux Hot Channel Limits (FQN(Z)) ................................................
Mtg.#
3 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FAHN) ............................
 
4 2.8 Axial Flux Difference (AFD) ...............................................................................
Table of Contents Section     Title                                                                                                           Page 1.0   CORE OPERATING LIMITS REPORT ........................................................................                   1 2.0   OPERATING LIMITS .................................................................................................... 2 2.1 Reactor Core Safety Limits                                 ....................................                     2 2.2 Shutdown Margin (SDM)                                 ......................................                       2 2.3 Moderator Temperature Coefficient .................................................................                 2 2.4 Shutdown Bank Insertion Limit ..........................................................................           2 2.5 Control Bank Insertion Limits ...............................................................................       2 2.6 Nuclear Heat Flux Hot Channel Limits (FQN(Z)) ................................................                     3 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FAHN)                                   ............................ 4 2.8 Axial Flux Difference (AFD) ...............................................................................         4 2.9 Overtemperature AT Setpoint ...........................................................................             5 2.10 Overpower AT Setpoint ....................................................................................         5 2.11 RCS Pressure, Temperature, and Flow Departure From ..................................                               6 Nucleate Boiling (DNB) Limits 2.12 Refueling Boron Concentration ........................................................................             6 i
4 2.9 Overtemperature AT Setpoint ...........................................................................
 
5 2.10 Overpower AT Setpoint ....................................................................................
List of Figures Figure         Title                                                                                                               Page
5 2.11 RCS Pressure, Temperature, and Flow Departure From ..................................
: 1. Reactor Core Safety Limits Curve (1772 MWt) ..............................................................                     7
6 Nucleate Boiling (DNB) Limits 2.12 Refueling Boron Concentration  
: 2. Required Shutdown Reactivity vs. Boron Concentration ..............................................                           8
........................................................................
: 3. Hot Channel Factor Normalized Operating Envelope (K(z)) ..........................................                             9
6 i List of Figures Figure Title Page 1. Reactor Core Safety Limits Curve (1772 MWt) ..............................................................
: 4. Control Bank Insertion Limits ......................................................................................         10
7 2. Required Shutdown Reactivity vs. Boron Concentration  
: 5. W(Z) Values (Top and Bottom 9% excluded) ............................................................                         11
..............................................
: 6. Penalty Factor, Fp (%), for FQEQ(Z)                               ...................................                       13
8 3. Hot Channel Factor Normalized Operating Envelope (K(z)) ..........................................
: 7. Axial Flux Difference ..................................................................................................... 14
9 4. Control Bank Insertion Limits ......................................................................................
 
10 5. W(Z) Values (Top and Bottom 9% excluded)  
List of Tables                   I Table                 Title                         Page
............................................................
: 1. NRC Approved Methodologies for COLR Parameters 15 iii
11 6. Penalty Factor, Fp (%), for FQEQ(Z) ...................................
 
13 7. Axial Flux Difference  
KEWAUNEE POWER STATION                                                     TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                              Revision 0 CORE OPERATING LIMITS REPORT CYdLE'29 1.0     CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Kewaunee Power Station (KPS) has been prepared in accordance with the requirements of Technical Specification (TS) 6.9.a.4.
.....................................................................................................
A cross-reference between the COLR sections and the KPS Technical Specifications affected by this report is given below:
14 List of Tables I Table Title Page 1. NRC Approved Methodologies for COLR Parameters 15 iii KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYdLE'29 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Kewaunee Power Station (KPS) has been prepared in accordance with the requirements of Technical Specification (TS) 6.9.a.4.A cross-reference between the COLR sections and the KPS Technical Specifications affected by this report is given below: COLR Section 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 2.10 2.11 2.12 Figure 1 Figure 2 Figure 3 Figure 4 Figure 5 Figure 6 Figure 7 KPS TS 2.1 3.10.a 3.1 .f.3 3.10.d.1 3.10.d.2 3.10.b.1.A 3.10.b.5 3.10.b.6 3.10.b.6.C.i 3.10.b.7 3.10.b.1.B 3.10.b.8 2.3.a.3.A 2.3.a.3.B 3.10.k 3.10.1 3.10.m.1 3.8.a.5 Description Reactor Core Safety Limits Shutdown Margin Moderator Temperature Coefficient Shutdown Bank Insertion Limit Control Bank Insertion Limits Heat Flux Hot Channel Factor (FQ(Z))Nuclear Enthalpy Rise Hot Channel Factor (FAHN)Axial Flux Difference (AFD)Overtemperature AT Setpoint Overpower AT Setpoint RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits Refueling Boron Concentration Reactor Core Safety Limits (1772 MWt)Required Shutdown Margin K(Z) Normalized Operating Envelope Control Bank Insertion Limits W(Z) Values (Top and Bottom 9% excluded)Penalty Factor, Fp, for FQEQ(Z)Axial Flux Difference Cycle 29 Page 1 of 19 Rev. 0 KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 2.0 Operatingq Limits The cycle-specific parameter limits forthe specifications listed in Section 1.0 are presented in the following subsections.
COLR             KPS        Description Section           TS 2.1               2.1      Reactor Core Safety Limits 2.2             3.10.a      Shutdown Margin 2.3            3.1 .f.3    Moderator Temperature Coefficient 2.4            3.10.d.1     Shutdown Bank Insertion Limit 2.5           3.10.d.2    Control Bank Insertion Limits 2.6          3.10.b.1.A   Heat Flux Hot Channel Factor (FQ(Z))
These limits have been developed using the NRC approved methodologies specified in Technical Specification 6.9.a.4.2.1 Reactor Core Safety Limits The combination of rated power level, coolant pressure, and coolant temperature shall not exceed the limits shown in COLR Figure 1 (1772 MWt). The safety limit is exceeded if the point defined by the combination of Reactor Coolant System average temperature and power level is at any time above the appropriate pressure line.2.2 Shutdown Marqin 2.2.1 When the reactor is subcritical prior to reactor startup, the SHUTDOWN margin shall be at least that shown in COLR Figure 2.2.3 Moderator Temperature Coefficient 2.3.1 When the reactor is critical and < 60% RATED POWER, the moderator temperature coefficient shall be < 5.0 pcm/&deg;F, except during LOW POWER PHYSICS TESTING. When the reactor is > 60% RATED POWER, the moderator temperature coefficient shall be zero or negative.2.3.2 The reactor:will have a moderator temperature coefficient no less negative, than -8 pcm/&deg;F for 95% of the cycle time at full power.2.4 Shutdown Bank Insertion Limit 2.4.1 The shutdown rods shall be fully withdrawn
3.10.b.5 3.10.b.6 3.10.b.6.C.i 3.10.b.7 2.7          3.10.b.1.B   Nuclear Enthalpy Rise Hot Channel Factor (FAHN) 2.8            3.10.b.8     Axial Flux Difference (AFD) 2.9            2.3.a.3.A   Overtemperature AT Setpoint 2.10          2.3.a.3.B   Overpower AT Setpoint 2.11            3.10.k     RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling 3.10.1     (DNB) Limits 3.10.m.1 2.12            3.8.a.5     Refueling Boron Concentration Figure  1                  Reactor Core Safety Limits (1772 MWt)
(_> 225 steps and __ 230 steps)when the reactor is critical or approaching criticality.
Figure 2                    Required Shutdown Margin Figure 3                    K(Z) Normalized Operating Envelope Figure 4                    Control Bank Insertion Limits Figure 5                    W(Z) Values (Top and Bottom 9% excluded)
2.5 Control Bank Insertion Limits 2.5.1 The control banks shall be limited in physical insertion; insertion limits are shown in COLR Figure 4.Cycle 29 Page 2 of 19 Rev. 0 KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT, CYCLE 29 2.6 Nuclear Heat Flux Hot Channel Factor (F 0 N(Z))2.6.1 F 0 N(Z) Limits for Fuel FQN(Z) x 1.03 x 1.05 < (2.50)/P x K(Z) for P > 0.5 [422 V+]FaN(Z) x 1.03 x 1.05 < (5.00) x K(Z) for P < 0.5 [422 V+]where: P is the fraction of full power at which the core is OPERATING K(Z) is the function given in Figure 3 Z is the core height location for the F 0 of interest 2.6.2 The measured F 0 EQ(Z) hot channel factors under equilibrium conditions shall satisfy the following relationship for the central axial 80% of the core for fuel: FQEQ(Z) x 1.03 x 1.05 x W(Z) x Fp _< (2.5)/ P x K(Z) [422 V +]where: P is the fraction of full power at which the core is OPERATING K(Z) is the function given in Figure 3 Z is the core height location for the FQ of interest Fp is the FQEQ(Z) penalty factor described in 2.6.3.W(Z) Is the function given in Figure 5 F EQ(Z) is a measured FQ distribution obtained during the target flux determination 2.6.3 The penalty factor of 1.0 shall be used for TS 3.10.b.6.A and TS 3.10.b.6.B.
Figure 6                    Penalty Factor, Fp, for FQEQ(Z)
Figure 7                    Axial Flux Difference Cycle 29                                    Page 1 of 19                                Rev. 0
 
KEWAUNEE POWER STATION                                                          TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                                  Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 2.0    Operatingq Limits The cycle-specific parameter limits forthe specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in Technical Specification 6.9.a.4.
2.1     Reactor Core Safety Limits The combination of rated power level, coolant pressure, and coolant temperature shall not exceed the limits shown in COLR Figure 1 (1772 MWt). The safety limit is exceeded ifthe point defined by the combination of Reactor Coolant System average temperature and power level is at any time above the appropriate pressure line.
2.2      Shutdown Marqin 2.2.1 When the reactor is subcritical prior to reactor startup, the SHUTDOWN margin shall be at least that shown in COLR Figure 2.
2.3      Moderator Temperature Coefficient 2.3.1 When the reactor is critical and < 60% RATED POWER, the moderator temperature coefficient shall be < 5.0 pcm/&deg;F, except during LOW POWER PHYSICS TESTING. When the reactor is > 60% RATED POWER, the moderator temperature coefficient shall be zero or negative.
2.3.2 The reactor:will have a moderator temperature coefficient no less negative, than -8 pcm/&deg;F for 95% of the cycle time at full power.
2.4     Shutdown Bank Insertion Limit 2.4.1 The shutdown rods shall be fully withdrawn (_> 225 steps and __ 230 steps) when the reactor is critical or approaching criticality.
2.5     Control Bank Insertion Limits 2.5.1 The control banks shall be limited in physical insertion; insertion limits are shown in COLR Figure 4.
Cycle 29                                   Page 2 of 19                                       Rev. 0
 
KEWAUNEE POWER STATION                                                     TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                               Revision 0 CORE OPERATING LIMITS REPORT, CYCLE 29 2.6   Nuclear Heat Flux Hot Channel Factor (F0 N(Z))
2.6.1 F0 N(Z) Limits for Fuel FQN(Z) x 1.03 x 1.05 < (2.50)/P x K(Z) for P > 0.5                 [422 V+]
FaN(Z) x 1.03 x 1.05 < (5.00) x K(Z) for P < 0.5                   [422 V+]
where:
P       is the fraction of full power at which the core is OPERATING K(Z)     is the function given in Figure 3 Z         is the core height location for the F0 of interest 2.6.2 The measured F0 EQ(Z) hot channel factors under equilibrium conditions shall satisfy the following relationship for the central axial 80% of the core for fuel:
FQEQ(Z) x 1.03 x 1.05 x W(Z) x Fp _<     (2.5)/ P x K(Z)               [422 V +]
where:
P       is the fraction of full power at which the core is OPERATING K(Z)     is the function given in Figure 3 Z       is the core height location for the FQ of interest Fp       is the FQEQ(Z) penalty factor described in 2.6.3.
W(Z)     Is the function given in Figure 5 F EQ(Z) is a measured FQ distribution obtained during the target flux determination 2.6.3 The penalty factor of 1.0 shall be used for TS 3.10.b.6.A and TS 3.10.b.6.B.
The penalty factor provided in Figure 6 shall be used for TS 3.10.b.6.C.i.
The penalty factor provided in Figure 6 shall be used for TS 3.10.b.6.C.i.
The penalty factor for all burnups outside the range of Figure 6 shall be 2%.Cycle 29 Page 3 of 19 Rev. 0 KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE
The penalty factor for all burnups outside the range of Figure 6 shall be 2%.
Cycle 29                                Page 3 of 19                                      Rev. 0
 
KEWAUNEE POWER STATION                                                      TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                                Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 2.7    Nuclear Enthalpy Rise Hot Channel Factor (FAHN) 2.7.1  FAHN Limits for Fuel FAHN x 1.04* 1.70 [1 + 0.3(1-P)]                                [422 V+]
where:
P    is the fraction of full power at which the core is OPERATING 2.8 Axial Flux Difference (AFD) 2.8.1  The Axial Flux Difference (AFD) acceptable operation limits are provided in Figure 7.
Cycle 29                                  Page 4 of 19                                    Rev. 0
 
KEWAUNEE POWER STATION                                                      TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                              Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 2.90 Overtemperature AT Setpoint Overtemperature
The penalty factor provided in Figure 6 shall be used for TS 3.10.b.6.C.i.
The penalty factor provided in Figure 6 shall be used for TS 3.10.b.6.C.i.
The penalty factor for all burnups outside the range of Figure 6 shall be 2%.Cycle 29 Page 3 of 18 Rev. 1 1 KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 1 CORE OPERATING LIMITS REPORT CYCLE 29 2.7 Nuclear Enthalpy Rise Hot Channel Factor Limits (FAHN 2.7.1 FAHN Limits for Fuel FAHN x 1.04_ 1.70 [1 + 0.3(1-P)]
The penalty factor for all burnups outside the range of Figure 6 shall be 2%.
[422 V+]where: P is the fraction of full power at which the core is OPERATING 2.8 Axial Flux Difference (AFD) Target Band 2.8.1 The Axial Flux Difference (AFD) acceptable operation limits are provided in Figure 7.Cycle 29 Page 4 of 18 Rev. 1 1 KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 1 CORE OPERATING LIMITS REPORT CYCLE 29 2.9 Overtemperature AT Setpoint Overtemperature AT setpoint parameter values: ATo = Indicated AT at RATED POWER, %T = Average temperature, OF T' _< 573.0 OF P = Pressurizer Pressure, psig P" = 2235 psig K, = 1.195 K2 = 0.015/&deg;F K3 = 0.00072/psig Tj = 30 seconds T2 = 4 seconds f(AI) = An even function of the indicated difference between top and bottom detectors of the power range nuclear ion chambers.
Cycle 29                                   Page 3 of 18                                     Rev. 1 1
Selected gains are based on measured instrument response during plant startup tests, where qt and qb are the percent power in the top and bottom halves of the core respectively, and qt + qb is total core power in percent of RATED POWER, such that (a) For qt -qb within -15, +6 %, f(Al) = 0 (b) For each percent that the magnitude of qt -qb exceeds +6 % the AT trip setpoint shall be automatically reduced by an equivalent of 1.51 % of RATED POWER.(c) For each percent that the magnitude of qt -qb exceed -15 % the AT trip setpoint shall be automatically reduced by an equivalent of 3.78% of RATED POWER.2.10 Overpower AT Setpoint Overpower AT setpoint parameter values: AT 0  = Indicated AT at RATED POWER, %T = Average temperature, OF T' 573.0 OF 1K4 < 1.095 K5 > 0.0275/&deg;F for increasing T; 0 for decreasing T K6 > 0.00103/&deg;F for T > T' ; 0 for T < T'3 = 10 seconds f(AI) 0 for all Al Cycle 29 Page 5 of 18 Rev. 1 1 KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision I CORE OPERATING LIMITS REPORT CYCLE 29 2.11 RCS Pressure, Temperature, and Flow Departure from Nucleate Boilingq (DNB) Limits 2.11.1 During steady state power operation, Tavg shall be < 576.7 0 F for control board indication or < 576.51F for computer indication.
 
2.11.2 During steady state power operation, Pressurizer Pressure shall be> 2217 psig for control board indication or > 2219 psig for computer indication 2.11.3 During steady state power operation, reactor coolant total flow rate shall be>_ 186,000 gpm.2.12 Refueling Boron Concentration 2.12.1 When there is fuel in the reactor, a minimum boron concentration of 2500 ppm and a shutdown margin of > 5% A k/k shall be maintained in the Reactor Coolant System during reactor vessel head removal or while loading and unloading fuel from the reactor.Cycle 29 Page 6 of 18 Rev. 1 1 KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 1 I Figure 1 Reactor Core Safety Limits Curve (1772 Mwt)(Cores Containing 422V&#xf7; fuel)hfi-h 645-0-62-(U 0.ME 8 4)25 I-* 2~425 psia I I I I Unacpeptable Operation 1 800 p4ia Acceptoble Operation--------------------4 565 0 20 40 60 80 100 120 Core Power (percent of 1772 MWt)Cycle 29 Page 7 of 18 Rev. 11 KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 1 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 2 Required Shutdown Reactivity vs. Boron Concentration 1700 1600 1542 1500 1400 1300 1200 1100 1 1000 9 00 80 U)700 C, 5O 900 Soo 3~ 00 200 100 0 0 200 400 600 800 1000 1200 1400 Full Power Equilibrium Boron Concentration (ppm)1600 1800 2000 Cycle 29 Page 8 of 18 Rev, .1 1 KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 1 Figure 3 Hot Channel Factor Normalized Operating Envelope (K(Z))I 1.2 1.1 1 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0 (0,1.0) (6,1.0)(12,1.0)0 1 2 3 4 5 6 7 Core Height (ft)8 9 10 11 12 Cycle 29 Page 9 of 18 Rev. 1 1 KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 1 I Figure 4 Control Bank Insertion Limits 240 220 200 180 C160140 (n* 120 100 C 0 0 80 60 40 20 0 0 10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power Fully withdrawn shall be the condition where control rods are at a position between the interval>_.225 and 5230 steps withdrawn.
KEWAUNEE POWER STATION                                                       TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                               Revision 1 CORE OPERATING LIMITS REPORT CYCLE 29 2.7 Nuclear Enthalpy Rise Hot Channel Factor Limits (FAHN 2.7.1   FAHN Limits for Fuel FAHN x 1.04*_ 1.70 [1 + 0.3(1-P)]                               [422 V+]
Note: The Rod Bank Insertion Limits are based on a control bank tip-to-tip distance of 126 steps.Cycle 29 Page 10 of 18 Rev. I KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 1 I Figure 5 -W(Z) Values (Top and Bottom 9% excluded)Height BU IMWd/MTU]tftJ 150 2000 6000 12000 17000 AO = 2.11%AO = -0.08%AO = -2.43% 1 AO = -2.99%AO= -3.07%[BOTTOM] 1 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 2 0.20 1.0000 1.0000 1.0000 1.0000 1.0000 3 j 0.40 1.0000 1.0000 1.0000 1.0000 1.0000 4 0.60 1.0000 1.0000 1.0000 1.0000 1.0000 5 0.80 1.0000 1.0000 1.0000 1.0000 1.0000 6 1.00 1.0000 1.0000 1.0000 1.0000 1.0000 7 1.20 1.3735 1.2862 1.2244 1.1994 1.1670 8 1.40 1.3580 1.2728 1.2133 1.1902 1.1591 9 1.60 1.3398 1.2573 1.2003 1.1797 1.1505 10 1.80 1.3194 1.2404 1.1860 1.1681 1.1414 11 2.00 1.2974 1.2248 1.1702 1.1556 1.1319 12 2.20 1.2742 1.2098 1.1545 1.1424 1.1222 13 2.40 1.2505 1.1938 1.1400 1.1291 1.1126 14 2.60 1.2267 1.1779 1.1264 1.1158 1.1032 15 2.80 1.2030 1.1617 1.1127 1.1020 1.0941 16 3.00 1.1816 1.1478 1.1019 1.0925 1.0858 17 3.20 1.1652 1.1394 1.0972 1.0892 1.0842 18 3.40 1.1561 1.1355 1.0970 1.0887 1.0908 19 3.60 1.1534 1.1313 1.0963 1.0880 1.0973 20 3.80 1.1506 1.1263 1.0955 1.0899 1.1036 21 4.00 1.1468 1.1226 1.0947 1.0928 1.1098 22 4.20 1.1428 1.1199 1.0936 1.0950 1.1154 23 4.40 1.1381 1.1166 1.0926 1.0970 1.1205 24 4.60 1.1330 1.1130 1.0921 1.0989 1.1249 25 4.80 1.1274 1.1087 1.0922 1.1018 1.1286 26 5.00 1.1212 1.1050 1.0922 1.1046 1.1314 27 5.20 1.1144 1.1018 1.0920 1.1067 1.1336 28 5.40 1.1072 1.0981 1.0923 1.1090 1.1346 29 5.60 1.0995 1.0940 1.0963 1.1132 1.1348 30 5.80 1.0912 1.0878 1.1012 1.1209 1.1392 31 6.00 1.0892 1.0899 1.1058 1.1312 1.1508 32 6.20 1.0942 1.0990 1.1124 1.1419 1.1649 33 6.40 1.1007 1.1065 1.1217 1.1512 1.1769 34 6.60 1.1061 1.1134 1.1304 1.1596 1.1879 35 6.80 1.1107 1.1195 1.1383 1.1668 1.1975 36 7.00 1.1146 1.1246 1.1449 1.1729 1.2056 37 7.20 1.1174 1.1289 1.1511 1.1787 1.2122 38 7.40 1.1194 1.1325 1.1573 1.1840 1.2170 39 7.60 1.1219 1.1363 1.1626 1.1877 1.2200 40 7.80 1.1235 1.1391 1.1667 1.1899 1.2210 41 8.00 1.1241 1.1408 1.1695 1.1906 1.2200 42 8.20 1.1237 1.1413 1.1710 1.1898 1.2169 43 8.40 1.1224 1.1408 1.1713 1.1873 1.2118 44 8.60 1.1202 1.1392 1.1702 1.1830 1.2063 45 8.80 1.1172 1.1378 1.1661 1.1792 1.2071 46 9.00 1.1216 1.1448 1.1679 1.1800 1.2075 47 9.20 1.1359 1.1638 1.1778 1.1845 1.2076 48 9.40 1.1485 1.1802 1.1899 1.1921 1.2129 49 9.60 1.1677 1.1966 1.2015 1.2098 1.2341 50 9.80 1.1854 1.2105 12114 1.2315 1.2562 51 10.00 1.2019 1.2299 1.2271 1.2525 1.2755 52 10.20 1.2142 1.2519 1.2446 1.2707 1.2939 53 10.40 1.2210 1.2690 1.2576 1.2896 1.3110 Cycle 29 Page 11 of 18 Rev. 11 KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 1 Figure 5 Cont'd (Top and Bottom 9% excluded)Height Iftl BU [MWd/MTUI 150 2000 1 6000 1 12000 17000 AO '=i2.11%/AO fi -0.08%AO-f-2.43%
where:
AO =-2.99%AO= -3.0l7%/54 10.60 1.2336 1.2877 1.2715 1.3049 1.3283 55 10.80 1.2480 1.3015 1.2779 1.3142 1.3430 56 11.00 1.0000 1.0000 1.0000 1.0000 1.0000 57 11.20 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.40 1.0000 1.0000 1.0000 1.0000 1.0000 59 11.60 1.0000 1.0000 1.0000 1.0000 1.0000 60 11.80 1.0000 1.0000 1.0000 1.0000 1.0000[TOP] 61 1 12.00 1.0000 1.0000 1.0000 1.0000 1.0000 Note: These W(Z)'s are based upon the previous cycle's RAOC Band of 1.0%, -9%, +8%, 0.5%,-27%, 28%. The current RAOC Band of 1.0%, -9%, +6%, 0.5%, -27%, 28% is less inclusive, thus, these W(Z)'s are conservative.
P   is the fraction of full power at which the core is OPERATING 2.8 Axial Flux Difference (AFD) Target Band 2.8.1 The Axial Flux Difference (AFD) acceptable operation limits are provided in Figure 7.
Cycle 29 Page 12 of 18 Rev. 1 1 KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision I I Figure 6 Penalty Factor, Fp (%), for FQN(Z)Cycle Burnup Penalty Factor (MWD/MTU)
Cycle 29                                 Page 4 of 18                                     Rev. 1 1
Fp (%)150 2.00 18,185 2.00 Note: Linear interpolation is adequate for intermediate cycle bumups.All cycle bumups outside the range of the table shall use a penalty factor, Fp, of 2.0%.Refer to TS 3.10.b.6.C.
 
Cycle 29 Page 13 of 18 Rev. 1 KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 1 Figure 7 Axial Flux Difference Envelope 110 100 I-(L 0 L a.0 4-C.(U 90 80 70 60 (-9.0, 100.0) (6.0, 100.0)(-27.0, 50.0) (28.0, 50.0)' I II I s'IIII IIII I' I "' I l 50 40-40 20 -10 0 10 20 30 40 Axial Flux Difference
KEWAUNEE POWER STATION                                                       TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                                 Revision 1 CORE OPERATING LIMITS REPORT CYCLE 29 2.9 Overtemperature AT Setpoint Overtemperature AT setpoint parameter values:
(% delta-I)Note: This figure represents the Relaxed Axial Offset Control (RAOC) band used in safety analyses.
ATo     =   Indicated AT at RATED POWER, %
It may be administratively tightened depending on in-core flux map results. Refer to Figure RD 11.4.1 of the Reactor Data Manual.I Cycle 29 Page 14 of 18 Rev. 1 KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUJAL TRM 2.1 Revision I I CORE OPERATING LIMITS REPORT CYCLE 29 Table I NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC Approved Methodology 2.1 Reactor Core Safety Limits 2.2 2.3 2.4 Shutdown Margin Moderator Temperature Coefficient Shutdown Bank Insertion Limits WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.I 2.5 Control Bank Insertion Limits Cycle 29 Page 15 of 18 Rev. 1 1 KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 1 JI Table I (cont)NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC ADDroved Methodoloav 2.6 Nuclear Heat Flux Hot Channel Limits (FQN(Z))WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset Control-FQ Surveillance Technical Specification," February 1994.WCAP-1 2945-P-A (Proprietary),"Westinghouse Code Qualification Document for Best-Estimate Loss-of-Coolant Accident Analysis," Volume I, Rev.2, and Volumes II-V, Rev.1, and WCAP-14747 (Non-Proprietary), March 1998.(FQ(Z)) WCAP-1 4449-P-A, "Application Of Best Estimate Large Break LOCA Methodology To Westinghouse PWRs With Upper Plenum Injection," Revision1, and WCAP-1 4450-NP- A, Rev.1 (Non-Proprietary), October 1999.WCAP-12610-P-A, "Vantage+
T       =   Average temperature, OF T'     _< 573.0 OF P       =   Pressurizer Pressure, psig P"     =   2235 psig K,     =   1.195 K2     =   0.015/&deg;F K3     =   0.00072/psig Tj     =   30 seconds T2     =   4 seconds f(AI)   =   An even function of the indicated difference between top and bottom detectors of the power range nuclear ion chambers. Selected gains are based on measured instrument response during plant startup tests, where qt and qb are the percent power in the top and bottom halves of the core respectively, and qt + qb is total core power in percent of RATED POWER, such that (a)     For qt - qb within -15, +6 %, f(Al) = 0 (b)     For each percent that the magnitude of qt - qb exceeds +6 % the AT trip setpoint shall be automatically reduced by an equivalent of 1.51 % of RATED POWER.
Fuel Assembly Reference Core Report," April 1995.WCAP-10054-P-AIWCAP-10081-NP-A,"Westinghouse Small Break ECCS Evaluation Using the NOTRUMP Code," August 1985.I Model NOTRUMP WCAP-10054-P-A/WCAP-10081-NP-A, Addendum 2, Revision 1, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the Code: Safety Injection into the Broken Loop and COSI Condensation Model," July 1997.Cycle 29 Page 16 of 18 Rev. 1 1 KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 1 I Table 1 (cont)NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC Approved Methodology 2.7 Nuclear Enthalpy Rise Hot Channel Factor Limits 2.8 Axial Flux Difference Target Band WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset (AFD) Control-F 0 Surveillance Technical Specification," February 1994.Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.WCAP-8745-P-A, "Design Bases For The Thermal Overpower AT and Thermal Overtemperature AT Trip Functions," September 1986.I I I 2.9 Reactor Protection System (RPS)Instrumentation-Overtemperature AT Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.CENP-397-P-A, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology," Rev. 1, May 2000.Cycle 29 Page 17 of 18 Rev. 1 KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 1 I Table I (cont)NRC Approved Methodolocies for COLR Parameters COLR Section Parameter NRC Approved Methodology I 2.10 Reactor Protection System (RPS)Instrumentation-Overpower AT WCAP-8745-P-A, "Design Bases For The Thermal Overpower AT and Thermal Overtemperature AT Trip Functions," September 1986.Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.CENP-397-P-A, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology," Rev. 1, May 2000.WCAP-1 1397-P-A, "Revised Thermal Design Procedure, "April 1989, for those events analyzed using RTDP Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 for those events not utilizing RTDP.WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.2.11 RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits 2.12 Refueling Boron Concentration Cycle 29 Page 18 of 18 Rev. 1}}
(c)     For each percent that the magnitude of qt - qb exceed -15 % the AT trip setpoint shall be automatically reduced by an equivalent of 3.78% of RATED POWER.
2.10 Overpower AT Setpoint Overpower AT setpoint parameter values:
AT0    =   Indicated AT at RATED POWER, %
T     =   Average temperature, OF T'         573.0 OF 1K4   <   1.095 K5   >   0.0275/&deg;F for increasing T; 0 for decreasing T K6   >   0.00103/&deg;F for T > T' ; 0 for T < T' 3   =   10 seconds f(AI)       0 for all Al Cycle 29                                 Page 5 of 18                                       Rev. 1 1
 
KEWAUNEE POWER STATION                                                   TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                             Revision I CORE OPERATING LIMITS REPORT CYCLE 29 2.11 RCS Pressure, Temperature, and Flow Departure from Nucleate Boilingq (DNB) Limits 2.11.1 During steady state power operation, Tavg shall be < 576.70 F for control board indication or < 576.51F for computer indication.
2.11.2 During steady state power operation, Pressurizer Pressure shall be
                  > 2217 psig for control board indication or > 2219 psig for computer indication 2.11.3 During steady state power operation, reactor coolant total flow rate shall be
                  >_186,000 gpm.
2.12 Refueling Boron Concentration 2.12.1 When there is fuel in the reactor, a minimum boron concentration of 2500 ppm and a shutdown margin of > 5% A k/k shall be maintained in the Reactor Coolant System during reactor vessel head removal or while loading and unloading fuel from the reactor.
Cycle 29                               Page 6 of 18                                     Rev. 1 1
 
KEWAUNEE POWER STATION                                                               TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                                       Revision 1          I CORE OPERATING LIMITS REPORT CYCLE 29 Figure 1 Reactor Core Safety Limits Curve (1772 Mwt)
(Cores Containing 422V&#xf7; fuel) hfi-h
* 2~425 psia                              I I      I            I  Unacpeptable Operation 645-0-
62-(U 1800 p4ia 0.
ME 4)25 8  4 I-Acceptoble Operation
                                - - -   - -   - - - - -           - - - - -   -   - - - -
565 0         20               40           60       80           100         120 Core Power (percent of 1772 MWt)
Cycle 29                                           Page 7 of 18                                   Rev. 11
 
KEWAUNEE POWER STATION                                                   TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                           Revision 1 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 2 Required Shutdown Reactivity vs. Boron Concentration 1700 1600 1542 1500 1400 1300 1200 1100 11000 U)
C,     900 80 Soo 700 5O 900 3~00 200 100 0
0 200 400   600       800       1000     1200     1400 1600  1800 2000 Full Power Equilibrium Boron Concentration (ppm)
Cycle 29                             Page 8 of 18                                 Rev,.1 1
 
KEWAUNEE POWER STATION                                             TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                     Revision 1 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 3 Hot Channel Factor Normalized Operating Envelope (K(Z))
I 1.2 1.1 (0,1.0)                (6,1.0) 1                                                            (12,1.0) 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0
0     1   2  3    4    5    6   7  8  9  10  11  12 Core Height (ft)
Cycle 29                             Page 9 of 18                               Rev. 1 1
 
KEWAUNEE POWER STATION                                                     TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                               Revision 1            I CORE OPERATING LIMITS REPORT CYCLE 29 Figure 4 Control Bank Insertion Limits 240 220 200 180 C
* 160
* 140 (n
120 100 C
0 0   80 60 40 20 0
0   10     20     30   40     50   60     70     80     90   100 Percent of Rated Thermal Power Fully withdrawn shall be the condition where control rods are at a position between the interval
>_.225 and *5230 steps withdrawn.
Note: The Rod Bank Insertion Limits are based on a control bank tip-to-tip distance of 126 steps.
Cycle 29                                 Page 10 of 18                                   Rev. I
 
KEWAUNEE POWER STATION                                                         TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                                 Revision 1            I CORE OPERATING LIMITS REPORT CYCLE 29 Figure 5 - W(Z) Values (Top and Bottom 9% excluded)
Height                           BU IMWd/MTU]
tftJ     150         2000         6000       12000         17000 AO = 2.11%   AO = -0.08% AO = -2.43% 1 AO = -2.99%   AO= -3.07%
[BOTTOM] 1   0.00     1.0000       1.0000       1.0000     1.0000         1.0000 2       0.20     1.0000       1.0000       1.0000     1.0000         1.0000 3     j 0.40     1.0000       1.0000       1.0000     1.0000         1.0000 4       0.60     1.0000       1.0000       1.0000     1.0000         1.0000 5       0.80     1.0000       1.0000       1.0000     1.0000         1.0000 6       1.00     1.0000       1.0000       1.0000     1.0000         1.0000 7       1.20     1.3735       1.2862       1.2244     1.1994         1.1670 8       1.40     1.3580         1.2728       1.2133       1.1902       1.1591 9       1.60   1.3398         1.2573       1.2003       1.1797       1.1505 10       1.80   1.3194         1.2404       1.1860       1.1681       1.1414 11       2.00     1.2974       1.2248       1.1702     1.1556         1.1319 12       2.20     1.2742         1.2098       1.1545       1.1424       1.1222 13       2.40     1.2505         1.1938       1.1400       1.1291       1.1126 14       2.60     1.2267         1.1779       1.1264       1.1158       1.1032 15       2.80     1.2030         1.1617       1.1127       1.1020       1.0941 16       3.00     1.1816         1.1478       1.1019       1.0925       1.0858 17       3.20     1.1652         1.1394       1.0972       1.0892       1.0842 18       3.40     1.1561         1.1355       1.0970       1.0887       1.0908 19       3.60     1.1534         1.1313       1.0963       1.0880       1.0973 20       3.80     1.1506         1.1263       1.0955       1.0899       1.1036 21       4.00     1.1468         1.1226       1.0947       1.0928       1.1098 22       4.20     1.1428         1.1199       1.0936       1.0950       1.1154 23       4.40     1.1381         1.1166       1.0926       1.0970       1.1205 24       4.60     1.1330         1.1130       1.0921       1.0989       1.1249 25       4.80     1.1274         1.1087       1.0922       1.1018       1.1286 26       5.00     1.1212         1.1050       1.0922       1.1046       1.1314 27       5.20     1.1144         1.1018       1.0920       1.1067       1.1336 28       5.40     1.1072         1.0981       1.0923       1.1090       1.1346 29       5.60   1.0995         1.0940       1.0963     1.1132         1.1348 30       5.80   1.0912         1.0878       1.1012       1.1209       1.1392 31       6.00     1.0892         1.0899       1.1058       1.1312       1.1508 32       6.20     1.0942         1.0990       1.1124       1.1419       1.1649 33       6.40     1.1007         1.1065       1.1217       1.1512       1.1769 34       6.60     1.1061         1.1134       1.1304       1.1596       1.1879 35       6.80     1.1107         1.1195       1.1383     1.1668         1.1975 36       7.00   1.1146         1.1246       1.1449     1.1729         1.2056 37       7.20   1.1174         1.1289       1.1511     1.1787         1.2122 38       7.40     1.1194         1.1325       1.1573       1.1840         1.2170 39       7.60     1.1219         1.1363       1.1626       1.1877         1.2200 40       7.80     1.1235       1.1391       1.1667     1.1899         1.2210 41       8.00   1.1241         1.1408       1.1695     1.1906         1.2200 42       8.20   1.1237         1.1413       1.1710     1.1898         1.2169 43       8.40   1.1224         1.1408       1.1713     1.1873         1.2118 44       8.60   1.1202         1.1392       1.1702     1.1830         1.2063 45       8.80   1.1172         1.1378       1.1661     1.1792         1.2071 46       9.00   1.1216         1.1448       1.1679     1.1800         1.2075 47       9.20   1.1359         1.1638       1.1778     1.1845         1.2076 48       9.40   1.1485         1.1802       1.1899     1.1921         1.2129 49       9.60   1.1677         1.1966       1.2015     1.2098         1.2341 50       9.80   1.1854         1.2105       12114       1.2315         1.2562 51       10.00     1.2019       1.2299       1.2271     1.2525         1.2755 52       10.20   1.2142         1.2519       1.2446     1.2707         1.2939 53       10.40   1.2210         1.2690       1.2576     1.2896         1.3110 Cycle 29                               Page 11 of 18                                         Rev. 11
 
KEWAUNEE POWER STATION                                                             TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                                       Revision 1 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 5 Cont'd (Top and Bottom 9% excluded)
Height                           BU [MWd/MTUI Iftl    150         2000     1     6000   1   12000         17000 AO'=i2.11%/   AO fi-0.08%   AO-f-2.43%   AO =-2.99%     AO= -3.0l7%/
54       10.60   1.2336       1.2877         1.2715       1.3049       1.3283 55       10.80   1.2480       1.3015         1.2779       1.3142       1.3430 56       11.00   1.0000       1.0000         1.0000       1.0000       1.0000 57       11.20   1.0000       1.0000         1.0000       1.0000       1.0000 58       11.40   1.0000       1.0000         1.0000       1.0000       1.0000 59       11.60   1.0000       1.0000         1.0000       1.0000       1.0000 60       11.80   1.0000       1.0000         1.0000       1.0000       1.0000
[TOP] 61 1 12.00   1.0000       1.0000         1.0000       1.0000       1.0000 Note: These W(Z)'s are based upon the previous cycle's RAOC Band of 1.0%, -9%, +8%, 0.5%,
      -27%, 28%. The current RAOC Band of 1.0%, -9%, +6%, 0.5%, -27%, 28% is less inclusive, thus, these W(Z)'s are conservative.
Cycle 29                                     Page 12 of 18                                           Rev. 1 1
 
KEWAUNEE POWER STATION                                                       TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                               Revision I            I CORE OPERATING LIMITS REPORT CYCLE 29 Figure 6 Penalty Factor, Fp (%), for FQN(Z)
Cycle Burnup       Penalty Factor (MWD/MTU)             Fp (%)
150               2.00 18,185               2.00 Note: Linear interpolation is adequate for intermediate cycle bumups.
All cycle bumups outside the range of the table shall use a penalty factor, Fp, of 2.0%.
Refer to TS 3.10.b.6.C.
Cycle 29                                   Page 13 of 18                                     Rev. 1
 
KEWAUNEE POWER STATION                                                         TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                                   Revision 1 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 7 Axial Flux Difference Envelope 110
(-9.0, 100.0)         (6.0, 100.0) 100 I-    90 (L
80 0
L
: a. 70 0
4-C.
(U 60 50
(-27.0, 50.0)                                             (28.0, 50.0) 40          I   II     I '    s'IIII   IIII         I'   I "'                 Il
                  -40     -30        -20           -10       0       10     20       30       40 Axial Flux Difference (% delta-I)
Note: This figure represents the Relaxed Axial Offset Control (RAOC) band used in safety analyses. It I may be administratively tightened depending on in-core flux map results. Refer to Figure RD 11.4.1 of the Reactor Data Manual.
Cycle 29                                   Page 14 of 18                                     Rev. 1
 
KEWAUNEE POWER STATION                                                 TRM 2.1 TECHNICAL REQUIREMENTS MANUJAL                                        Revision I               I CORE OPERATING LIMITS REPORT CYCLE 29 Table I NRC Approved Methodologies for COLR Parameters COLR Section         Parameter                     NRC Approved Methodology 2.1         Reactor Core Safety Limits           WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.
Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.
I 2.2            Shutdown Margin                    WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 2.3    Moderator Temperature Coefficient        WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.
2.4      Shutdown Bank Insertion Limits          WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.
Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.
2.5        Control Bank Insertion Limits          WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.
Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.
Cycle 29                               Page 15 of 18                                 Rev. 1       1
 
KEWAUNEE POWER STATION                                               TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                         Revision 1                JI CORE OPERATING LIMITS REPORT CYCLE 29 Table I (cont)
NRC Approved Methodologies for COLR Parameters COLR Section         Parameter                   NRC ADDroved Methodoloav 2.6       Nuclear Heat Flux Hot Channel         WCAP-10216-P-A, Revision 1A, "Relaxation Limits (FQN(Z))              of Constant Axial Offset Control-FQ Surveillance Technical Specification,"
February 1994.
WCAP-1 2945-P-A (Proprietary),               I "Westinghouse Code Qualification Document for Best-Estimate Loss-of-Coolant Accident Analysis," Volume I, Rev.2, and Volumes II-V, Rev.1, and WCAP-14747 (Non-Proprietary), March 1998.
(FQ(Z)) WCAP-1 4449-P-A, "Application Of Best Estimate Large Break LOCA Methodology To Westinghouse PWRs With Upper Plenum Injection," Revision1, and WCAP-1 4450-NP- A, Rev.1 (Non-Proprietary), October 1999.
WCAP-12610-P-A, "Vantage+ Fuel Assembly Reference Core Report," April 1995.
Model                    WCAP-10054-P-AIWCAP-10081-NP-A, "Westinghouse Small Break ECCS Evaluation Using the NOTRUMP Code,"
August 1985.
NOTRUMP                     WCAP-10054-P-A/WCAP-10081-NP-A, Addendum 2, Revision 1, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the Code: Safety Injection into the Broken Loop and COSI Condensation Model," July 1997.
Cycle 29                             Page 16 of 18                                   Rev. 1     1
 
KEWAUNEE POWER STATION                                                 TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                         Revision 1              I CORE OPERATING LIMITS REPORT CYCLE 29 Table 1 (cont)
NRC Approved Methodologies for COLR Parameters COLR Section           Parameter                   NRC Approved Methodology 2.7           Nuclear Enthalpy Rise             WCAP-9272-P-A, "Westinghouse Reload Hot Channel Factor Limits          Safety Evaluation Methodology," July 1985.
Kewaunee Nuclear Power Plant-Review for   I Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.
2.8    Axial Flux Difference Target Band          WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset (AFD) Control-F 0 I
Surveillance Technical Specification,"
February 1994.
Kewaunee Nuclear Power Plant-Review for   I Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.
2.9      Reactor Protection System (RPS)        WCAP-8745-P-A, "Design Bases For The Instrumentation-Overtemperature AT        Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"
September 1986.
Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.
CENP-397-P-A, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology,"
Rev. 1, May 2000.
Cycle 29                               Page 17 of 18                                 Rev. 1
 
KEWAUNEE POWER STATION                                                   TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                           Revision 1              I CORE OPERATING LIMITS REPORT CYCLE 29 Table I (cont)
NRC Approved Methodolocies for COLR Parameters COLR Section         Parameter                     NRC Approved Methodology I
2.10     Reactor Protection System (RPS)           WCAP-8745-P-A, "Design Bases For The Instrumentation-Overpower AT            Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"
September 1986.
Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.
CENP-397-P-A, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology,"
Rev. 1, May 2000.
2.11    RCS Pressure, Temperature, and            WCAP-1 1397-P-A, "Revised Thermal Design Flow Departure From Nucleate            Procedure, "April 1989, for those events Boiling (DNB) Limits              analyzed using RTDP Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 for those events not utilizing RTDP.
2.12      Refueling Boron Concentration            WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.
Cycle 29                               Page 18 of 18                                   Rev. 1}}

Revision as of 17:12, 14 November 2019

Cycle 29 Core Operating Limits Report, Revision 0 and Revision 1
ML081230658
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 04/25/2008
From: Wilson M
Dominion Energy Kewaunee
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
08-0179
Download: ML081230658 (49)
v • d • e


Text

Dominion Energy Kewaunee, Inc.mni N490 Highway 42, Kewaunee, WI 54216-9511 D APR 2 5 2008 Attn: Document Control Desk Serial No. 08-0179 U. S. Nuclear Regulatory Commission LIC/NW/RO Washington, DC 20555-0001 Docket No.: 50-305 License No.: DPR-43 DOMINION ENERGY KEWAUNEE, INC.

KEWAUNEE POWER STATION CYCLE 29 CORE OPERATING LIMITS REPORTS Pursuant to Kewaunee Power Station (KPS) Technical Specification (TS) 6.9.a.4.D, enclosed are copies of the KPS Technical Requirements Manual (TRM) Section 2.1, Kewaunee Power Station Core Operating Limits Report (COLR), Cycle 29, Revision 0 and Revision 1.

KPS TS 6.9.a.4.D states that the COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC. COLR Cycle 29, Revision 0 was approved but not issued. COLR Cycle 29, Revision 0 was not issued because COLR Cycle 29, Revision 1 was approved before the core was reloaded.

If you have any questions or require additional information, please contact Mr. Gerald Riste at (920) 388-8424.

Very truly yours, Mic 6l J. Wilson Dir ctor Safety and Licensing Kewaunee Power Station Commitments made by this letter: None

Enclosures:

1. TRM 2.1, Kewaunee Power Station Core Operating Limits Report (COLR), Cycle 29, Revision 0
2. TRM 2.1, Kewaunee Power Station Core Operating Limits Report (COLR), Cycle 29, Revision 1 P941-

Serial No. 08-0179 Page 2 of 2 cc: Regional Administrator, Region III U.S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 Ms. M. H. Chernoff Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-H4A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Kewaunee Power Station

Serial No. 08-0179 ENCLOSURE 1 TECHNICAL REQUIREMENTS MANUAL 2.1 KEWAUNEE POWER STATION CORE OPERATING LIMITS REPORT (COLR),

CYCLE 29, REVISION 0 KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.

TRM 2.1 Kewaunee Power Station CORE OPERATING LIMITS REPORT (COLR)

CYCLE 29 REVISION 0 Approved Chairman Mtg.#

Mtg.#

Table of Contents Section Title Page 1.0 CORE OPERATING LIMITS REPORT ........................................................................ 1 2.0 OPERATING LIMITS .................................................................................................... 2 2.1 Reactor Core Safety Limits .................................... 2 2.2 Shutdown Margin (SDM) ...................................... 2 2.3 Moderator Temperature Coefficient ................................................................. 2 2.4 Shutdown Bank Insertion Limit .......................................................................... 2 2.5 Control Bank Insertion Limits ............................................................................... 2 2.6 Nuclear Heat Flux Hot Channel Limits (FQN(Z)) ................................................ 3 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FAHN) ............................ 4 2.8 Axial Flux Difference (AFD) ............................................................................... 4 2.9 Overtemperature AT Setpoint ........................................................................... 5 2.10 Overpower AT Setpoint .................................................................................... 5 2.11 RCS Pressure, Temperature, and Flow Departure From .................................. 6 Nucleate Boiling (DNB) Limits 2.12 Refueling Boron Concentration ........................................................................ 6 i

List of Figures Figure Title Page

1. Reactor Core Safety Limits Curve (1772 MWt) .............................................................. 7
2. Required Shutdown Reactivity vs. Boron Concentration .............................................. 8
3. Hot Channel Factor Normalized Operating Envelope (K(z)) .......................................... 9
4. Control Bank Insertion Limits ...................................................................................... 10
5. W(Z) Values (Top and Bottom 9% excluded) ............................................................ 11
6. Penalty Factor, Fp (%), for FQEQ(Z) ................................... 13
7. Axial Flux Difference ..................................................................................................... 14

List of Tables I Table Title Page

1. NRC Approved Methodologies for COLR Parameters 15 iii

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYdLE'29 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Kewaunee Power Station (KPS) has been prepared in accordance with the requirements of Technical Specification (TS) 6.9.a.4.

A cross-reference between the COLR sections and the KPS Technical Specifications affected by this report is given below:

COLR KPS Description Section TS 2.1 2.1 Reactor Core Safety Limits 2.2 3.10.a Shutdown Margin 2.3 3.1 .f.3 Moderator Temperature Coefficient 2.4 3.10.d.1 Shutdown Bank Insertion Limit 2.5 3.10.d.2 Control Bank Insertion Limits 2.6 3.10.b.1.A Heat Flux Hot Channel Factor (FQ(Z))

3.10.b.5 3.10.b.6 3.10.b.6.C.i 3.10.b.7 2.7 3.10.b.1.B Nuclear Enthalpy Rise Hot Channel Factor (FAHN) 2.8 3.10.b.8 Axial Flux Difference (AFD) 2.9 2.3.a.3.A Overtemperature AT Setpoint 2.10 2.3.a.3.B Overpower AT Setpoint 2.11 3.10.k RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling 3.10.1 (DNB) Limits 3.10.m.1 2.12 3.8.a.5 Refueling Boron Concentration Figure 1 Reactor Core Safety Limits (1772 MWt)

Figure 2 Required Shutdown Margin Figure 3 K(Z) Normalized Operating Envelope Figure 4 Control Bank Insertion Limits Figure 5 W(Z) Values (Top and Bottom 9% excluded)

Figure 6 Penalty Factor, Fp, for FQEQ(Z)

Figure 7 Axial Flux Difference Cycle 29 Page 1 of 19 Rev. 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 2.0 Operatingq Limits The cycle-specific parameter limits forthe specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in Technical Specification 6.9.a.4.

2.1 Reactor Core Safety Limits The combination of rated power level, coolant pressure, and coolant temperature shall not exceed the limits shown in COLR Figure 1 (1772 MWt). The safety limit is exceeded ifthe point defined by the combination of Reactor Coolant System average temperature and power level is at any time above the appropriate pressure line.

2.2 Shutdown Marqin 2.2.1 When the reactor is subcritical prior to reactor startup, the SHUTDOWN margin shall be at least that shown in COLR Figure 2.

2.3 Moderator Temperature Coefficient 2.3.1 When the reactor is critical and < 60% RATED POWER, the moderator temperature coefficient shall be < 5.0 pcm/°F, except during LOW POWER PHYSICS TESTING. When the reactor is > 60% RATED POWER, the moderator temperature coefficient shall be zero or negative.

2.3.2 The reactor:will have a moderator temperature coefficient no less negative, than -8 pcm/°F for 95% of the cycle time at full power.

2.4 Shutdown Bank Insertion Limit 2.4.1 The shutdown rods shall be fully withdrawn (_> 225 steps and __ 230 steps) when the reactor is critical or approaching criticality.

2.5 Control Bank Insertion Limits 2.5.1 The control banks shall be limited in physical insertion; insertion limits are shown in COLR Figure 4.

Cycle 29 Page 2 of 19 Rev. 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT, CYCLE 29 2.6 Nuclear Heat Flux Hot Channel Factor (F0 N(Z))

2.6.1 F0 N(Z) Limits for Fuel FQN(Z) x 1.03 x 1.05 < (2.50)/P x K(Z) for P > 0.5 [422 V+]

FaN(Z) x 1.03 x 1.05 < (5.00) x K(Z) for P < 0.5 [422 V+]

where:

P is the fraction of full power at which the core is OPERATING K(Z) is the function given in Figure 3 Z is the core height location for the F0 of interest 2.6.2 The measured F0 EQ(Z) hot channel factors under equilibrium conditions shall satisfy the following relationship for the central axial 80% of the core for fuel:

FQEQ(Z) x 1.03 x 1.05 x W(Z) x Fp _< (2.5)/ P x K(Z) [422 V +]

where:

P is the fraction of full power at which the core is OPERATING K(Z) is the function given in Figure 3 Z is the core height location for the FQ of interest Fp is the FQEQ(Z) penalty factor described in 2.6.3.

W(Z) Is the function given in Figure 5 F EQ(Z) is a measured FQ distribution obtained during the target flux determination 2.6.3 The penalty factor of 1.0 shall be used for TS 3.10.b.6.A and TS 3.10.b.6.B.

The penalty factor provided in Figure 6 shall be used for TS 3.10.b.6.C.i.

The penalty factor for all burnups outside the range of Figure 6 shall be 2%.

Cycle 29 Page 3 of 19 Rev. 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FAHN) 2.7.1 FAHN Limits for Fuel FAHN x 1.04* 1.70 [1 + 0.3(1-P)] [422 V+]

where:

P is the fraction of full power at which the core is OPERATING 2.8 Axial Flux Difference (AFD) 2.8.1 The Axial Flux Difference (AFD) acceptable operation limits are provided in Figure 7.

Cycle 29 Page 4 of 19 Rev. 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 2.90 Overtemperature AT Setpoint Overtemperature AT setpoint parameter values:

AT0 = Indicated AT at RATED POWER, %

T = Average temperature, OF T7 < 573.0 OF P Pressurizer Pressure, psig p = 2235 psig K1 = 1.195 K2 = 0.015/°F K3 = 0.00072/psig t = 30 seconds 12 = 4 seconds f(AI) = An even function of the indicated difference between top and bottom detectors of the power range nuclear ion chambers. Selected gains are based on measured instrument response during plant startup tests, where qt and qb are the percent power in the top and bottom halves of the core respectively, and qt + qb is total core power in percent of RATED POWER, such that (a) For qt - qb within -15, +6 %, f(AI) = 0 (b) For each percent that the magnitude of qt - qb exceeds +6 % the AT trip setpoint shall be automatically reduced by an equivalent of 1.51 % of RATED POWER.

(c) For each percent that the magnitude of qt - qb exceed -15 % the AT trip setpoint shall be automatically reduced by an equivalent of 3.78% of RATED POWER.

2.10 Overpower AT Setpoint Overpower AT setpoint parameter values:

ATo = Indicated AT at RATED POWER, %

T = Average temperature, OF T' < 573.0 OF K4 < 1.095 K5 _ 0.0275/°F for increasing T; 0 for decreasing T K6 >-- 0.0O103/OF for T > T' ; 0for T < T'

,c = 10 seconds f(AI) = 0for allAl Cycle 29 Page 5 of 19 Rev. 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 2.11 RCS Pressure, Temperature, and Flow Departure from;Ndcleate Boiling (DNB) Limits 2.11.1 During steady state power operation, Tavg shall be < 576.70 F for control board indication or < 576.5 0 F for computer indication.

2.11.2 During steady state power operation, Pressurizer Pressure shall be

> 2217 psig for control board indication or > 2219 psig for computer indication 2.11.3 During steady state power operation, reactor coolant total flow rate shall be

> 186,000 gpm.

2.12 Refuelinq Boron Concentration 2.12.1 When there is fuel in the reactor, a minimum boron concentration of 2500 ppm and a shutdown margin of Ž5% A k/k shall be maintained in the Reactor Coolant System during reactor vessel head removal or while loading and unloading fuel from the reactor.

Cycle 29 Page 6 of 19 Rev. 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 1 Reactor Core Safety Limits Curve (1772 Mwt)

(Cores Containing 422V+ fuel) 665 IL 645 0)

L) 0.

Q M) 658 565 0 20 40 60 80 100 120 Core Power (percent of 1772 MWt)

Cycle 29 Page 7 of 19 Rev. 0

dI KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 2 Required Shutdown Reactivity vs. Boron Concentration 1700 1600 1542 - - - i- * -~- *- - - -

1500 1400 1300 r _________________

1200 1100

-E 1000 C.)

900 800

-o 3l 700 0*

600 500 400 300 200 100 0

0 200 400 600 800 1000 1200 1400 1600 1800 2000 Full Power Equilibrium Boron Concentration (ppm)

Cycle 29 Page 8 of 19 Rev. 0

i, KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 3 Hot Channel Factor Normalized Operating Envelope (K(z))

1.2 1.1 (0,1.0) (6,1.0) 1 (12,1.0) 0.9 0.8 0.7 N

0.6 0.5 0.4 0.3 0.2 0.1 0

0 1 2 3 4 5 6 7 8 9 10 11 12 Core Height (ft)

Cycle 29 Page 9 of 19 Rev. 0

KEWAUNEE POWER STATION TRM 2.1 TECH-NICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 4 Control Bank Insertion Limits 240 220 200 180 C

i160 I-CL S140 f5 120 100 0

60 40 20 0

0 10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power Fully withdrawn shall be the condition where control rods are at a position between the interval

>_225 and :230 steps withdrawn.

Note: The Rod Bank Insertion Limits are based on a control bank tip-to-tip distance of 126 steps.

Cycle 29 Page 10 of 19 Rev. 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 5 - W(Z) Values (Top and Bottom 9% excluded)

Height BU [MWd/MTU1

[ft] 150 2000 6I00 12000 17000 150 2000 6000 12000 17000 AO = 2.11% AO = -. 0908% AO = -2.43% AO - -2.99% AO= -3.07%

[BOTTOM] 1 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 2 0.20 1.0000 1.0000 1.0000 1.0000 1.0000 3 0.40 1.0000 1.0000 1.0000 1.0000 1.0000 4 0.60 1.0000 1.0000 1.0000 1.0000 1.0000 5 0.80 1.0000 1.0000 1.0000 1,0000 1.0000 6 1.00 1.0000 1.0000 1.0000 1,0000 1.0000 7 1.20 1.3735 1.2862 1.2244 1.1994 1.1670 8 1.40 1.3580 1.2728 1.2133 1.1902 1.1591 9 1.60 1.3398 1.2573 1.2003 1,1797 1.1505 10 1.80 1.3194 1.2404 1.1860 1,1681 1.1414 11 2.00 .1.2974 1.2248 1.1702 1.1556 1.1319 12 2.20 1.2742 1.2098 1.1545 1.1424 1.1222 13 2.40 1.2505 1.1938 1.1400 1.1291 1.1126 14 2.60 1.2267 1.1779 1.1264 1.1158 1.1032 15 2.80 1.2030 1.1617 1.1127 1.1020 1.0941 16 3.00 1.1816 1.1478 1.1019 1.0925 1.0858 17 3.20 1.1652 1.1394 1.0972 1.0892 1.0842 18 3.40 1.1561 1.1355 1.0970 1.0887 1.0908 19 3.60 1.1534 1.1313 1.0963 1.0880 1.0973 20 3.80 1.1506 1.1263 1.0955 1.0899 1.1036 21 4.00 1.1468. 1.1226 1.0947 1,0928 1.1098 22 4.20 1.1428 1.1199 1.0936 1,0950 1.1154 23 4.40 1.1381 1.1166 1.0926 1.0970 . 1.1205 24 4.60 1.1330 1.1130 1.0921 1.0989 .1.1249 25 4.80 1.1274 1.1087 1.0922 1,1018 1.1286 26 5.00 1.1212 1.1050 1.0922 1.1046 1.1314 27 5.20 1.1144 1.1018 1.0920 1.1067 1.1336 28 5.40 1.1072 1.0981 1.0923 1.1090 1.1346 29 5.60 1.0995 1.0940 1.0963. 1.1132 1.1348 30 5.80 1.0912 . 1.0878 1.1012 1.1209 1.1392 31 6.00 1.0892 1.0899 1.1058 1.1312 1.1508 32 6.20 1.0942 1.0990 1.1124 1.1419 1.1649 33 6.40 1.1007 1.1065 1.1217 1.1512 1.1769 34 6.60 1.1061 1.1134 1.1304 .1.1596 1.1879 35 6.80 1.1107 1.1195 1.1383 1.1668 1.1975 36 7.00 1.1146 1.1246 1.1449 1.1729 1.2056 37 7.20 1.1174 1.1289 1.1511 1.1787 1.2122 38 7.40 1.1194 1.1325 1,1573 1.1840 1.2170 39 7.60 1.1219 1.1363 1.1626 1.1877 1.2200 40 7.80 1.1235 1.1391 1.1667 1.1899 1.2210 41 8.00 1.1241 1.1408 1.1695 1.1906 1.2200 42 8.20 1.1237 1.1413 1.1710 1.1898 1.2169 43 8.40 1.1224 1.1408 1.1713 1.1873 1.2118 44 8.60 1.1202 1.1392 1.1702 1.1830 1.2063 45 8.80 1.1172 1.1378 1.1661 1.1792 .1.2071 46 9.00 1.1216 1.1448 1.1679 1.1800 1.2075 47 9.20 1.1359 1.1638 1.1778 1.1845 1.2076 48 9.40 1.1485 1.1802 1.1899 1.1921 1.2129 49 9.60 1.1677 1.1966 1.2015 1.2098 1.2341 50 9.80 1.1854 1.2105 1.2114 1.2315 1.2562 51 10.00 1.2019 1.2299 1.2271 1.2525 1.2755 52 10.20 1.2142 1.2519 1.2446 1.2707 1.2939 53 10.40 1.2210 1.2690 1.2576 1.2896 1.3110 Cycle 29 Page 11 of 19 Rev. 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 5 Cont'd (Top and Bottom 9% excluded)

Height BU [MWd/MTU

[ft] 150 2000 6000 1 12000 1 17000 AO = 2.11% AO = -0.08% AO = -2.43% AO - -2.99% AO= -3.070%

54 10.60 1.2336 1.2877 1.2715 1.3049 1.3283 55 10.80 1.2480 1.3015 1.2779 1.3142 1.3430 56 11.00 1.0000 1.0000 1.0000 1.0000 1:0000 57 11.20 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.40 1.0000 1.0000 1.0000 1.0000 1.0000 59 11.60 1.0000 1.0000 1.0000 1.0000 1.0000 60 11.80 1.0000 1.0000 1.0000 1.0000 1.0000

[TOP] 61 12.00 1.0000 1 .0000 1.0000 1.0000 1.0000 Note: These W(Z)'s are based upon the previous cycle's RAOC Band of 1.0%, -9%, +8%, 0.5%,

-27%, 28%. The current RAOC Band of 1.0%, -9%, +6%, 0.5%, -27%, 28% is less inclusive, thus, these W(Z)'s are conservative.

Cycle 29 Page 12 of 19 Rev. 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 i.'!ý Figure 6 Penalty Factor, Fp (%), for FQEQ(Z)

Cycle Burnup Penalty Factor (MWD/MTU) Fp (%)

150 2.00 18,185 2.00 Note: Linear interpolation is adequate for intermediate cycle burnups.

All cycle burnups outside the range of the table shall use a penalty factor, Fp, of 2.0%.

Refer to TS 3.10.b.6.C.

Cycle 29 Page 13 of 19 Rev. 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 7 Axial Flux Difference 110 100 C- 90 a.

0 80 0

0.

70 I-0 a,,-

60 50 40

-40 -30 -20 -10 0 10 20 30 40 Axial Flux Difference (% delta-I)

Note: This figure represents the Relaxed Axial Offset Control (RAOC) band used in safety analyses, it may be administratively tightened depending on in-core flux map results. Refer to Figure RD 11.4.1 of the Reactor Data Manual.

Cycle 29 Page 14 of 19 Rev. 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 Table 1 NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC ADoroved Methodoloav 2.1 Reactor Core Safety Limits WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21, 1979, report date September 29, 1978.

Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.

2.2 Shutdown Margin WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21, 1979, report date September 29, 1978.

2.3 Moderator Temperature Coefficient WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21, 1979, report date September 29, 1978.

2.4 Shutdown Bank Insertion Limit WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July .1985.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21, 1979, report date September 29, 1978.

Cycle 29 Page 15 of 19 Rev. 0

'~ 4:

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 Table I (cont)

NRC Approved Methodologies for COLIR Parameters COLR Section Parameter NRC Approved Methodology Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.

2.5 Control Bank Insertion Limits WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21, 1979, report date September 29, 1978.

Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.

2.6 Heat Flux Hot Channel Factor WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset Control-FQ Surveillance Technical Specification,"

February 1994.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21, 1979, report date September 29, 1978.

WCAP-1 2945-P-A (Proprietary),

"Westinghouse Code Qualification Document for Best-Estimate Loss-of-Coolant Accident Analysis," Volume I, Rev.2, and Volumes II-V, Rev.1, and WCAP-14747 (Non-Proprietary), March 1998.

Cycle 29 Page 16 of 19 Rev. 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 Table I (cont)

NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC Approved Methodology (FQ(Z)) WCAP-14449-P-A, "Application Of Best Estimate Large Break LOCA Methodology To Westinghouse PWRs With Upper Plenum Injection," Revision1, and WCAP-14450-NP- A, Rev.1 (Non-Proprietary), October 1999.

WCAP-12610-P-A, "Vantage+ Fuel Assembly Reference Core Report," April 1995.

Model WCAP-10054-P-A/WCAP-10081-NP-A, "Westinghouse Small Break ECCS Evaluation Using the NOTRUMP Code,",

August 1985.

NOTRUMP WCAP-10054-P-A/WCAP-10081-NP-A, Addendum 2, Revision 1, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the Code: Safety Injection into the Broken Loop and COSI Condensation Model," July 1997.

2.7 Nuclear Enthalpy Rise WCAP-9272-P-A, "Westinghouse Reload Hot Channel Factor (FNAH) Safety Evaluation Methodology," July 1985.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21, 1979, report date September 29, 1978.

Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.

Cycle 29 Page 17 of 19 Rev. 0

_KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 Table I (cont)

NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC Anproved Methodolociv 2.8 Axial Flux Difference WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset (AFD) Control-FQ Surveillance Technical Specification,"

February.1994.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21, 1979, report date September 29, 1978.

Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.

2.9 Reactor Protection System (RPS) WCAP-8745-P-A, "Design Bases For The Instrumentation-Overtemperature AT Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"

September 1986.

Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.

CENP-397-P-A, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology,"

Rev. 1, May 2000.

Cycle 29 Page 18 of 19 Rev. 0

ýý I.

>1*

KEWAUNEE POWER STATION TRM 2.1 TECHINICAIL REQUIREMENTS MANUAL Revision 0

-CORE OPERATING LIMITS REPORT CYCLE 29

- Table I (cont) t 1.

NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC Approved Methodology 2.10 Reactor Protection System (RPS) WCAP-8745-P-A, "Design Bases For The Instrumentation-Overpower AT Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"

September 1986.

Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.

CENP-397-P-A, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology,"

Rev. 1, May 2000.

2.11 RCS Pressure, Temperature, and WCAP-1 1397-P-A, "Revised Thermal Design Flow Departure From Nucleate Procedure, "April 1989, for those events (DNB) Limits analyzed using RTDP Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.

WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 for those events not utilizing RTDP.

2.12 Boron Concentration WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21, 1979, report date September 29, 1978.

Cycle 29 Page 19 of 19 Rev. 0

Serial No. 07-0241 ENCLOSURE 2 TECHNICAL REQUIREMENTS MANUAL 2.1 KEWAUNEE POWER STATION CORE OPERATING LIMITS REPORT (COLR),

CYCLE 29, REVISION 1 KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.

TRM 2.1 Kewaunee Power Station CORE OPERATING LIMITS REPORT (COLR)

CYCLE 29 REVISION 1 Approved -D/a- ?e2 -0 op- -,5 F C Chairman Date Mtg.#

Table of Contents Section Title Paqe 1.0 CORE OPERATING LIMITS REPORT ........................................................................ 1 2.0 OPERATING LIMITS ............................................. 2 2.1 Reactor Core Safety Limits ........................................................................... 2 2.2 Shutdown Margin ............................................................................................. 2 2.3 Moderator Temperature Coefficient (MTC) ....................................................... 2 2.4 Shutdown Bank Insertion Limits ........................................................................ 2 2.5 Control Bank Insertion Limits ............................................................................. 2 2.6 Nuclear Heat Flux Hot Channel Limits (FQN(Z)) ................................................ 3 2.7 Nuclear Enthalpy Rise Hot Channel Factor Limits (FAHN) ................................... 4 2.8 Axial Flux Difference (AFD) Target Band ........................... 4 2.9 Overtemperature AT Setpoint ........................................................................... 5 2.10 Overpower AT Setpoint ...................................................................................... 5 2.11 RCS Pressure, Temperature, and Flow Departure From .................................. 6 Nucleate Boiling (DNB) Limits 2.12 Refueling Boron Concentration ........................................................................ 6 i

List of Figures Figure Title Page

1. Reactor Core Safety Limits Curve (1772 MWt) ............................................................ 7
2. Required Shutdown Reactivity vs. Boron Concentration ............................................... 8
3. Hot Channel Factor Normalized Operating Envelope (K(z)) .......................................... 9
4. Control Bank Insertion Limits ........................................... 10
5. W(Z) Values (Top and Bottom 9% excluded) ............................................................. 11
6. Penalty Factor, Fp (%), for FQN(Z) ................................................................................ 13
7. Axial Flux Difference Envelope ..................................................................................... 14 ii

I List of Tables I Table Title Page

1. NRC Approved Methodologies for COLR Parameters 15 iii

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 1 CORE OPERATING LIMITS REPORT CYCLE 29 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Kewaunee Power Station (KPS) has been prepared in accordance with the requirements of Technical Specification (TS) 6.9.a.4.

A cross-reference between the COLR sections and the KPS Technical Specifications affected by this report is given below:

COLR KPS Description Section TS 2.1 2.1 Reactor Core Safety Limits 2.2 3.1O.a Shutdown Margin 2.3 3.1 .f.3 Moderator Temperature Coefficient (MTC) 2.4 3.10.d.1 Shutdown Bank Insertion Limits 2.5 3.10.d.2 Control Bank Insertion Limits 2.6 3.10.b.1 .A Heat Flux Hot Channel Factor Limits (FaN(Z))

3.10.b.5 3.10.b.6 3.10.b.6.C.i 3.10.b.7 2.7 3.10.b.1 .B Nuclear Enthalpy Rise Hot Channel Factor Limits (FAHN) 2.8 3.10.b.8 Axial Flux Difference (AFD) Target Band I 2.9 2.3.a.3.A Overtemperature AT Setpoint 2.10 2.3.a.3.1B Overpower AT Setpoint 2.11 3.1O.k RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling 3.10.1 (DNB) Limits 3.10.m.1 2.12 3.8.a.5 Refueling Boron Concentration Figure 1 Reactor Core Safety Limits (1772 MWt)

Figure 2 Required Shutdown Margin Figure 3 K(Z) Normalized Operating Envelope Figure 4 Control Bank Insertion Limits Figure 5 W(Z) Values (Top and Bottom 9% excluded)

Figure 6 Penalty Factor, Fp (%), for FQN(z)

Figure 7 Axial Flux Difference Envelope Cycle 29 Page 1 of 18 Rev. 1 1

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 1 CORE OPERATING LIMITS REPORT CYCLE 29 2.0 Operatinq Limits The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in Technical Specification 6.9.a.4.

2.1 Reactor Core Safety Limits The combination of rated power level, coolant pressure, and coolant temperature shall not exceed the limits shown in COLR Figure 1 (1772 MWt). The safety limit is exceeded ifthe point defined by the combination of Reactor Coolant System average temperature and power level is at any time above the appropriate pressure line.

2.2 Shutdown Margin 2.2.1 When the reactor is subcritical prior to reactor startup, the SHUTDOWN margin shall be at least that shown in COLR Figure 2.

2.3 Moderator Temperature Coefficient 2.3.1 When the reactor is critical and < 60% RATED POWER, the moderator temperature coefficient shall be *5.0 pcm/ 0 F, except during LOW POWER PHYSICS TESTING. When the reactor is > 60% RATED POWER, the moderator temperature coefficient shall be zero or negative.

2.3.2 The reactor will have a moderator temperature coefficient no less negative than -8 pcm/°F for 95% of the cycle time at full power.

2.4 Shutdown Bank Insertion Limit 2.4.1 The shutdown rods shall be fully withdrawn (>_225 steps and < 230 steps) when the reactor is critical or approaching criticality.

2.5 Control Bank Insertion Limits 2.5.1 The control banks shall be limited in physical insertion; insertion limits are shown in COLR Figure 4.

Cycle 29 Page 2 of 18 Rev. 1 1

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 1 CORE OPERATING LIMITS REPORT CYCLE 29 2.6 Nuclear Heat Flux Hot Channel Factor (F N(Z))

2.6.1 FQN(Z) Limits for Fuel F0 N(Z) X 1.03 x 1.05 < (2.50)/P x K(Z) for P > 0.5 [422 V+]

FaN(Z) x 1.03 x 1.05 < (5.00) x K(Z) for P 5 0.5 [422 V+]

where:

P is the fraction of full power at which the core is OPERATING K(Z) is the function given in Figure 3 Z is the core height location for the FQ of interest 2.6.2 The measured FQN(Z) hot channel factors under equilibrium conditions shall satisfy the following relationship for the central axial 80% of the core for fuel:

FQN(Z) x 1.03 x 1.05 x W(Z) x Fp _ (2.5)/ P x K(Z) [422 V +]

where:

P is the fraction of full power at which the core is OPERATING K(Z) is the function given in Figure 3 Z is the core height location for the FQ of interest Fp is the FQN(Z) penalty factor described in 2.6.3.

W(Z) Is the function given in Figure 5 FQN(Z) is a measured Fa distribution obtained during the target flux I determination 2.6.3 The penalty factor of 1.0 shall be used for TS 3.10.b.6.A and TS 3.10.b.6.B.

The penalty factor provided in Figure 6 shall be used for TS 3.10.b.6.C.i.

The penalty factor for all burnups outside the range of Figure 6 shall be 2%.

Cycle 29 Page 3 of 18 Rev. 1 1

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 1 CORE OPERATING LIMITS REPORT CYCLE 29 2.7 Nuclear Enthalpy Rise Hot Channel Factor Limits (FAHN 2.7.1 FAHN Limits for Fuel FAHN x 1.04*_ 1.70 [1 + 0.3(1-P)] [422 V+]

where:

P is the fraction of full power at which the core is OPERATING 2.8 Axial Flux Difference (AFD) Target Band 2.8.1 The Axial Flux Difference (AFD) acceptable operation limits are provided in Figure 7.

Cycle 29 Page 4 of 18 Rev. 1 1

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 1 CORE OPERATING LIMITS REPORT CYCLE 29 2.9 Overtemperature AT Setpoint Overtemperature AT setpoint parameter values:

ATo = Indicated AT at RATED POWER, %

T = Average temperature, OF T' _< 573.0 OF P = Pressurizer Pressure, psig P" = 2235 psig K, = 1.195 K2 = 0.015/°F K3 = 0.00072/psig Tj = 30 seconds T2 = 4 seconds f(AI) = An even function of the indicated difference between top and bottom detectors of the power range nuclear ion chambers. Selected gains are based on measured instrument response during plant startup tests, where qt and qb are the percent power in the top and bottom halves of the core respectively, and qt + qb is total core power in percent of RATED POWER, such that (a) For qt - qb within -15, +6 %, f(Al) = 0 (b) For each percent that the magnitude of qt - qb exceeds +6 % the AT trip setpoint shall be automatically reduced by an equivalent of 1.51 % of RATED POWER.

(c) For each percent that the magnitude of qt - qb exceed -15 % the AT trip setpoint shall be automatically reduced by an equivalent of 3.78% of RATED POWER.

2.10 Overpower AT Setpoint Overpower AT setpoint parameter values:

AT0 = Indicated AT at RATED POWER, %

T = Average temperature, OF T' 573.0 OF 1K4 < 1.095 K5 > 0.0275/°F for increasing T; 0 for decreasing T K6 > 0.00103/°F for T > T' ; 0 for T < T' 3 = 10 seconds f(AI) 0 for all Al Cycle 29 Page 5 of 18 Rev. 1 1

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision I CORE OPERATING LIMITS REPORT CYCLE 29 2.11 RCS Pressure, Temperature, and Flow Departure from Nucleate Boilingq (DNB) Limits 2.11.1 During steady state power operation, Tavg shall be < 576.70 F for control board indication or < 576.51F for computer indication.

2.11.2 During steady state power operation, Pressurizer Pressure shall be

> 2217 psig for control board indication or > 2219 psig for computer indication 2.11.3 During steady state power operation, reactor coolant total flow rate shall be

>_186,000 gpm.

2.12 Refueling Boron Concentration 2.12.1 When there is fuel in the reactor, a minimum boron concentration of 2500 ppm and a shutdown margin of > 5% A k/k shall be maintained in the Reactor Coolant System during reactor vessel head removal or while loading and unloading fuel from the reactor.

Cycle 29 Page 6 of 18 Rev. 1 1

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 1 I CORE OPERATING LIMITS REPORT CYCLE 29 Figure 1 Reactor Core Safety Limits Curve (1772 Mwt)

(Cores Containing 422V÷ fuel) hfi-h

  • 2~425 psia I I I I Unacpeptable Operation 645-0-

62-(U 1800 p4ia 0.

ME 4)25 8 4 I-Acceptoble Operation

- - - - - - - - - - - - - - - - - - - -

565 0 20 40 60 80 100 120 Core Power (percent of 1772 MWt)

Cycle 29 Page 7 of 18 Rev. 11

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 1 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 2 Required Shutdown Reactivity vs. Boron Concentration 1700 1600 1542 1500 1400 1300 1200 1100 11000 U)

C, 900 80 Soo 700 5O 900 3~00 200 100 0

0 200 400 600 800 1000 1200 1400 1600 1800 2000 Full Power Equilibrium Boron Concentration (ppm)

Cycle 29 Page 8 of 18 Rev,.1 1

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 1 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 3 Hot Channel Factor Normalized Operating Envelope (K(Z))

I 1.2 1.1 (0,1.0) (6,1.0) 1 (12,1.0) 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0

0 1 2 3 4 5 6 7 8 9 10 11 12 Core Height (ft)

Cycle 29 Page 9 of 18 Rev. 1 1

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 1 I CORE OPERATING LIMITS REPORT CYCLE 29 Figure 4 Control Bank Insertion Limits 240 220 200 180 C

  • 160
  • 140 (n

120 100 C

0 0 80 60 40 20 0

0 10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power Fully withdrawn shall be the condition where control rods are at a position between the interval

>_.225 and *5230 steps withdrawn.

Note: The Rod Bank Insertion Limits are based on a control bank tip-to-tip distance of 126 steps.

Cycle 29 Page 10 of 18 Rev. I

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 1 I CORE OPERATING LIMITS REPORT CYCLE 29 Figure 5 - W(Z) Values (Top and Bottom 9% excluded)

Height BU IMWd/MTU]

tftJ 150 2000 6000 12000 17000 AO = 2.11% AO = -0.08% AO = -2.43% 1 AO = -2.99% AO= -3.07%

[BOTTOM] 1 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 2 0.20 1.0000 1.0000 1.0000 1.0000 1.0000 3 j 0.40 1.0000 1.0000 1.0000 1.0000 1.0000 4 0.60 1.0000 1.0000 1.0000 1.0000 1.0000 5 0.80 1.0000 1.0000 1.0000 1.0000 1.0000 6 1.00 1.0000 1.0000 1.0000 1.0000 1.0000 7 1.20 1.3735 1.2862 1.2244 1.1994 1.1670 8 1.40 1.3580 1.2728 1.2133 1.1902 1.1591 9 1.60 1.3398 1.2573 1.2003 1.1797 1.1505 10 1.80 1.3194 1.2404 1.1860 1.1681 1.1414 11 2.00 1.2974 1.2248 1.1702 1.1556 1.1319 12 2.20 1.2742 1.2098 1.1545 1.1424 1.1222 13 2.40 1.2505 1.1938 1.1400 1.1291 1.1126 14 2.60 1.2267 1.1779 1.1264 1.1158 1.1032 15 2.80 1.2030 1.1617 1.1127 1.1020 1.0941 16 3.00 1.1816 1.1478 1.1019 1.0925 1.0858 17 3.20 1.1652 1.1394 1.0972 1.0892 1.0842 18 3.40 1.1561 1.1355 1.0970 1.0887 1.0908 19 3.60 1.1534 1.1313 1.0963 1.0880 1.0973 20 3.80 1.1506 1.1263 1.0955 1.0899 1.1036 21 4.00 1.1468 1.1226 1.0947 1.0928 1.1098 22 4.20 1.1428 1.1199 1.0936 1.0950 1.1154 23 4.40 1.1381 1.1166 1.0926 1.0970 1.1205 24 4.60 1.1330 1.1130 1.0921 1.0989 1.1249 25 4.80 1.1274 1.1087 1.0922 1.1018 1.1286 26 5.00 1.1212 1.1050 1.0922 1.1046 1.1314 27 5.20 1.1144 1.1018 1.0920 1.1067 1.1336 28 5.40 1.1072 1.0981 1.0923 1.1090 1.1346 29 5.60 1.0995 1.0940 1.0963 1.1132 1.1348 30 5.80 1.0912 1.0878 1.1012 1.1209 1.1392 31 6.00 1.0892 1.0899 1.1058 1.1312 1.1508 32 6.20 1.0942 1.0990 1.1124 1.1419 1.1649 33 6.40 1.1007 1.1065 1.1217 1.1512 1.1769 34 6.60 1.1061 1.1134 1.1304 1.1596 1.1879 35 6.80 1.1107 1.1195 1.1383 1.1668 1.1975 36 7.00 1.1146 1.1246 1.1449 1.1729 1.2056 37 7.20 1.1174 1.1289 1.1511 1.1787 1.2122 38 7.40 1.1194 1.1325 1.1573 1.1840 1.2170 39 7.60 1.1219 1.1363 1.1626 1.1877 1.2200 40 7.80 1.1235 1.1391 1.1667 1.1899 1.2210 41 8.00 1.1241 1.1408 1.1695 1.1906 1.2200 42 8.20 1.1237 1.1413 1.1710 1.1898 1.2169 43 8.40 1.1224 1.1408 1.1713 1.1873 1.2118 44 8.60 1.1202 1.1392 1.1702 1.1830 1.2063 45 8.80 1.1172 1.1378 1.1661 1.1792 1.2071 46 9.00 1.1216 1.1448 1.1679 1.1800 1.2075 47 9.20 1.1359 1.1638 1.1778 1.1845 1.2076 48 9.40 1.1485 1.1802 1.1899 1.1921 1.2129 49 9.60 1.1677 1.1966 1.2015 1.2098 1.2341 50 9.80 1.1854 1.2105 12114 1.2315 1.2562 51 10.00 1.2019 1.2299 1.2271 1.2525 1.2755 52 10.20 1.2142 1.2519 1.2446 1.2707 1.2939 53 10.40 1.2210 1.2690 1.2576 1.2896 1.3110 Cycle 29 Page 11 of 18 Rev. 11

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 1 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 5 Cont'd (Top and Bottom 9% excluded)

Height BU [MWd/MTUI Iftl 150 2000 1 6000 1 12000 17000 AO'=i2.11%/ AO fi-0.08% AO-f-2.43% AO =-2.99% AO= -3.0l7%/

54 10.60 1.2336 1.2877 1.2715 1.3049 1.3283 55 10.80 1.2480 1.3015 1.2779 1.3142 1.3430 56 11.00 1.0000 1.0000 1.0000 1.0000 1.0000 57 11.20 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.40 1.0000 1.0000 1.0000 1.0000 1.0000 59 11.60 1.0000 1.0000 1.0000 1.0000 1.0000 60 11.80 1.0000 1.0000 1.0000 1.0000 1.0000

[TOP] 61 1 12.00 1.0000 1.0000 1.0000 1.0000 1.0000 Note: These W(Z)'s are based upon the previous cycle's RAOC Band of 1.0%, -9%, +8%, 0.5%,

-27%, 28%. The current RAOC Band of 1.0%, -9%, +6%, 0.5%, -27%, 28% is less inclusive, thus, these W(Z)'s are conservative.

Cycle 29 Page 12 of 18 Rev. 1 1

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision I I CORE OPERATING LIMITS REPORT CYCLE 29 Figure 6 Penalty Factor, Fp (%), for FQN(Z)

Cycle Burnup Penalty Factor (MWD/MTU) Fp (%)

150 2.00 18,185 2.00 Note: Linear interpolation is adequate for intermediate cycle bumups.

All cycle bumups outside the range of the table shall use a penalty factor, Fp, of 2.0%.

Refer to TS 3.10.b.6.C.

Cycle 29 Page 13 of 18 Rev. 1

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 1 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 7 Axial Flux Difference Envelope 110

(-9.0, 100.0) (6.0, 100.0) 100 I- 90 (L

80 0

L

a. 70 0

4-C.

(U 60 50

(-27.0, 50.0) (28.0, 50.0) 40 I II I ' s'IIII IIII I' I "' Il

-40 -30 -20 -10 0 10 20 30 40 Axial Flux Difference (% delta-I)

Note: This figure represents the Relaxed Axial Offset Control (RAOC) band used in safety analyses. It I may be administratively tightened depending on in-core flux map results. Refer to Figure RD 11.4.1 of the Reactor Data Manual.

Cycle 29 Page 14 of 18 Rev. 1

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUJAL Revision I I CORE OPERATING LIMITS REPORT CYCLE 29 Table I NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC Approved Methodology 2.1 Reactor Core Safety Limits WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.

I 2.2 Shutdown Margin WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 2.3 Moderator Temperature Coefficient WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

2.4 Shutdown Bank Insertion Limits WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.

2.5 Control Bank Insertion Limits WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.

Cycle 29 Page 15 of 18 Rev. 1 1

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 1 JI CORE OPERATING LIMITS REPORT CYCLE 29 Table I (cont)

NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC ADDroved Methodoloav 2.6 Nuclear Heat Flux Hot Channel WCAP-10216-P-A, Revision 1A, "Relaxation Limits (FQN(Z)) of Constant Axial Offset Control-FQ Surveillance Technical Specification,"

February 1994.

WCAP-1 2945-P-A (Proprietary), I "Westinghouse Code Qualification Document for Best-Estimate Loss-of-Coolant Accident Analysis," Volume I, Rev.2, and Volumes II-V, Rev.1, and WCAP-14747 (Non-Proprietary), March 1998.

(FQ(Z)) WCAP-1 4449-P-A, "Application Of Best Estimate Large Break LOCA Methodology To Westinghouse PWRs With Upper Plenum Injection," Revision1, and WCAP-1 4450-NP- A, Rev.1 (Non-Proprietary), October 1999.

WCAP-12610-P-A, "Vantage+ Fuel Assembly Reference Core Report," April 1995.

Model WCAP-10054-P-AIWCAP-10081-NP-A, "Westinghouse Small Break ECCS Evaluation Using the NOTRUMP Code,"

August 1985.

NOTRUMP WCAP-10054-P-A/WCAP-10081-NP-A, Addendum 2, Revision 1, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the Code: Safety Injection into the Broken Loop and COSI Condensation Model," July 1997.

Cycle 29 Page 16 of 18 Rev. 1 1

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 1 I CORE OPERATING LIMITS REPORT CYCLE 29 Table 1 (cont)

NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC Approved Methodology 2.7 Nuclear Enthalpy Rise WCAP-9272-P-A, "Westinghouse Reload Hot Channel Factor Limits Safety Evaluation Methodology," July 1985.

Kewaunee Nuclear Power Plant-Review for I Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.

2.8 Axial Flux Difference Target Band WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset (AFD) Control-F 0 I

Surveillance Technical Specification,"

February 1994.

Kewaunee Nuclear Power Plant-Review for I Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.

2.9 Reactor Protection System (RPS) WCAP-8745-P-A, "Design Bases For The Instrumentation-Overtemperature AT Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"

September 1986.

Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.

CENP-397-P-A, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology,"

Rev. 1, May 2000.

Cycle 29 Page 17 of 18 Rev. 1

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 1 I CORE OPERATING LIMITS REPORT CYCLE 29 Table I (cont)

NRC Approved Methodolocies for COLR Parameters COLR Section Parameter NRC Approved Methodology I

2.10 Reactor Protection System (RPS) WCAP-8745-P-A, "Design Bases For The Instrumentation-Overpower AT Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"

September 1986.

Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.

CENP-397-P-A, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology,"

Rev. 1, May 2000.

2.11 RCS Pressure, Temperature, and WCAP-1 1397-P-A, "Revised Thermal Design Flow Departure From Nucleate Procedure, "April 1989, for those events Boiling (DNB) Limits analyzed using RTDP Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.

WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 for those events not utilizing RTDP.

2.12 Refueling Boron Concentration WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

Cycle 29 Page 18 of 18 Rev. 1

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