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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.
{{#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.
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.
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.
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: 2. TRM 2.1, Kewaunee Power Station Core Operating Limits Report (COLR), Cycle 29, Revision 1 P941-
: 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 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),
Serial No. 08-0179 ENCLOSURE 1 TECHNICAL REQUIREMENTS MANUAL 2.1 KEWAUNEE POWER STATION CORE OPERATING LIMITS REPORT (COLR),
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TRM 2.1 Kewaunee Power Station CORE OPERATING LIMITS REPORT (COLR)
TRM 2.1 Kewaunee Power Station CORE OPERATING LIMITS REPORT (COLR)
CYCLE 29 REVISION 0 Approved Chairman         Mtg.#
CYCLE 29 REVISION 0 Approved Chairman Mtg.#
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
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
List of Figures Figure Title Page
: 1. Reactor Core Safety Limits Curve (1772 MWt) ..............................................................                     7
: 1.
: 2. Required Shutdown Reactivity vs. Boron Concentration ..............................................                           8
Reactor Core Safety Limits Curve (1772 MWt)..............................................................
: 3. Hot Channel Factor Normalized Operating Envelope (K(z)) ..........................................                             9
7
: 4. Control Bank Insertion Limits ......................................................................................         10
: 2.
: 5. W(Z) Values (Top and Bottom 9% excluded) ............................................................                         11
Required Shutdown Reactivity vs. Boron Concentration..............................................
: 6. Penalty Factor, Fp (%), for FQEQ(Z)                               ...................................                        13
8
: 7. Axial Flux Difference ..................................................................................................... 14
: 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
List of Tables I
: 1. NRC Approved Methodologies for COLR Parameters 15 iii
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.
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:
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))
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))
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)
Nuclear Enthalpy Rise Hot Channel Factor (FAHN)
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)
Axial Flux Difference (AFD)
Figure 6                    Penalty Factor, Fp, for FQEQ(Z)
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)
Figure 7                    Axial Flux Difference Cycle 29                                     Page 1 of 19                                 Rev. 0
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. These limits have been developed using the NRC approved methodologies specified in Technical Specification 6.9.a.4.
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.
2.1 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.
2.2 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 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.
2.3.2 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.
2.4 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.
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.
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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))
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+]
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
FaN(Z) x 1.03 x 1.05 < (5.00) x K(Z) for P < 0.5                   [422 V+]
[422 V+]
FaN(Z) x 1.03 x 1.05 < (5.00) x K(Z) for P < 0.5
[422 V+]
where:
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:
P is the fraction of full power at which the core is OPERATING K(Z) is the function given in Figure 3 Z
FQEQ(Z) x 1.03 x 1.05 x W(Z) x Fp _<     (2.5)/ P x K(Z)               [422 V +]
is the core height location for the F0 of interest 2.6.2 The measured F0EQ(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:
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.
P is the fraction of full power at which the core is OPERATING K(Z) is the function given in Figure 3 Z
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.
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%.
The penalty factor for all burnups outside the range of Figure 6 shall be 2%.
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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+]
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 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:
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.
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.
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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:
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, %
AT0  
T     =   Average temperature, OF T7     <  573.0 OF P         Pressurizer Pressure, psig p     =   2235 psig K1     =   1.195 K2     =   0.015/&deg;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.
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/&deg;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:
2.10 Overpower AT Setpoint Overpower AT setpoint parameter values:
ATo   =   Indicated AT at RATED POWER, %
ATo  
T     =   Average temperature, OF T'   <    573.0 OF K4   <    1.095 K5     _  0.0275/&deg;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
Indicated AT at RATED POWER, %
T  
=
Average temperature, OF T'
573.0 OF K4 1.095 K5 0.0275/&deg;F for increasing T; 0 for decreasing T K6  
>-- 0.0O103/OF for T > T' ; 0 for 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.
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 < 576.70F for control board indication or < 576.5 0F for computer indication.
2.11.2 During steady state power operation, Pressurizer Pressure shall be
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
> 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.
> 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 &#x17d;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.
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 &#x17d;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.
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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)
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 0 Figure 1 Reactor Core Safety Limits Curve (1772 Mwt)
(Cores Containing 422V+ fuel) 665 IL 645 0)
(Cores Containing 422V+ fuel) 665 IL 645 0)
L) 0.
L) 0.Q M) 658 565 0
Q M) 658 565 0 20       40         60       80       100       120 Core Power (percent of 1772 MWt)
20 40 60 80 100 Core Power (percent of 1772 MWt) 120 Cycle 29 Page 7 of 19 Rev. 0
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-        * -~-                  *-      -    -      -
dI KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 0 Figure 2 Required Shutdown Reactivity vs. Boron Concentration
1500 1400 1300 r                                      _________________
-E C.)
1200 1100
-o 3l 0*
    -E 1000 C.)
1700 1600 1542 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0
900 800
i -
  -o 3l    700 0*
* -~-
600 500 400 300 200 100 0
r 0
0 200   400   600       800       1000       1200     1400 1600    1800 2000 Full Power Equilibrium Boron Concentration (ppm)
200 400 600 800 1000 1200 1400 Full Power Equilibrium Boron Concentration (ppm) 1600 1800 2000 Cycle 29 Page 8 of 19 Rev. 0
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))
i, KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 0 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
N 1.2 1.1 1
0.6 0.5 0.4 0.3 0.2 0.1 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)
(0,1.0)
Cycle 29                             Page 9 of 19                                 Rev. 0
(6,1.0)
(12,1.0) 0 1
2 3
4 5
6 7
8 9
10 Core Height (ft) 11 12 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
KEWAUNEE POWER STATION TECH-NICAL REQUIREMENTS MANUAL TRM 2.1 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
i160 CL I-S140 f5 120 100 0
60 40 20 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
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.
>_225 and :230 steps withdrawn.
Note: The Rod Bank Insertion Limits are based on a control bank tip-to-tip distance of 126 steps.
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
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)
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 5 - W(Z) Values (Top and Bottom 9% excluded)
Height                             BU [MWd/MTU1
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%
[ft]
[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
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)
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 0 Figure 5 Cont'd (Top and Bottom 9% excluded)
Height                         BU [MWd/MTU
Height
[ft]    150         2000         6000   1   12000     1   17000 AO = 2.11%   AO = -0.08%   AO = -2.43%   AO - -2.99%   AO= -3.070%
[ft]
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
BU [MWd/MTU 150 2000 6000 1
[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%,
12000 1
      -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.
17000 AO = 2.11%
Cycle 29                                   Page 12 of 19                                           Rev. 0
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.'!&#xfd; Figure 6 Penalty Factor, Fp (%), for FQEQ(Z)
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 i.'! &#xfd; Figure 6 Penalty Factor, Fp (%), for FQEQ(Z)
Cycle Burnup Penalty Factor (MWD/MTU)             Fp (%)
Cycle Burnup Penalty Factor (MWD/MTU)
150               2.00 18,185             2.00 Note: Linear interpolation is adequate for intermediate cycle burnups.
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%.
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.
Refer to TS 3.10.b.6.C.
Cycle 29                                   Page 13 of 19                                   Rev. 0
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.
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 7 Axial Flux Difference 110 100 C-0a.
0 80 0
00.
0.
I-0 a,,-
70 I-0 a,,-
90 80 70 60 50 40
60 50 40
-40  
                -40     -30     -20     -10       0       10       20       30       40 Axial Flux Difference (% delta-I)
-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.
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
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.
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 0 Table 1 NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC ADoroved Methodoloav 2.1 Reactor Core Safety Limits 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.
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.
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.
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.
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.
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.
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.
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
2.3 Moderator Temperature Coefficient 2.4 Shutdown Bank Insertion Limit 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)
4:
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.
KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 Table I (cont)
2.5       Control Bank Insertion Limits         WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.
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.
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.
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,"
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.
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.
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),
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.
"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
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)
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 0 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.
NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC Approved Methodology Model NOTRUMP (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.
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,",
WCAP-10054-P-A/WCAP-10081-NP-A, "Westinghouse Small Break ECCS Evaluation Using the NOTRUMP Code,",
August 1985.
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.
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.
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.
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.
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
2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNAH)
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)
_KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 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,"
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.
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.
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.
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,"
WCAP-8745-P-A, "Design Bases For The Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"
September 1986.
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.
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,"
CENP-397-P-A, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology,"
Rev. 1, May 2000.
Rev. 1, May 2000.
Cycle 29                             Page 18 of 19                                 Rev. 0
Cycle 29 Page 18 of 19 Rev. 0


                                        &#xfd;&#xfd; I.
&#xfd;&#xfd; I.
                                                            >1*
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KEWAUNEE POWER STATION                                                 TRM 2.1 TECHINICAIL REQUIREMENTS MANUAL                                        Revision 0
KEWAUNEE POWER STATION TECHINICAIL REQUIREMENTS MANUAL TRM 2.1 Revision 0
-CORE OPERATING LIMITS REPORT CYCLE 29
-CORE OPERATING LIMITS REPORT CYCLE 29
                                        - Table I (cont)           t 1.
-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,"
NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC Approved Methodology 2.10 Reactor Protection System (RPS)
Instrumentation-Overpower AT 2.11 RCS Pressure, Temperature, and Flow Departure From Nucleate (DNB) Limits WCAP-8745-P-A, "Design Bases For The Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"
September 1986.
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.
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,"
CENP-397-P-A, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology,"
Rev. 1, May 2000.
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-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 for those events not utilizing RTDP.
2.12          Boron Concentration              WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.
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.
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
2.12 Boron Concentration 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),
Serial No. 07-0241 ENCLOSURE 2 TECHNICAL REQUIREMENTS MANUAL 2.1 KEWAUNEE POWER STATION CORE OPERATING LIMITS REPORT (COLR),
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TRM 2.1 Kewaunee Power Station CORE OPERATING LIMITS REPORT (COLR)
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.#
CYCLE 29 REVISION 1 Approved F
C Chairman
-D/a- ?e2 -0 Date op-  
-,5 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
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
List of Figures Figure Title Page
: 1. Reactor Core Safety Limits Curve (1772 MWt) ............................................................               7
: 1.
: 2. Required Shutdown Reactivity vs. Boron Concentration ...............................................                   8
Reactor Core Safety Limits Curve (1772 MWt)............................................................
: 3. Hot Channel Factor Normalized Operating Envelope (K(z)) ..........................................                     9
7
: 4. Control Bank Insertion Limits ...........................................                                             10
: 2.
: 5. W(Z) Values (Top and Bottom 9% excluded) .............................................................                 11
Required Shutdown Reactivity vs. Boron Concentration...............................................
: 6. Penalty Factor, Fp (%), for FQN(Z) ................................................................................ 13
8
: 7. Axial Flux Difference Envelope ..................................................................................... 14 ii
: 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
I List of Tables I
: 1. NRC Approved Methodologies for COLR Parameters 15 iii
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.
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 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:
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))
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 3.1O.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.3.1B 3.1O.k 3.10.1 3.10.m.1 3.8.a.5 Description Reactor Core Safety Limits Shutdown Margin Moderator Temperature Coefficient (MTC)
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)
Shutdown Bank Insertion Limits Control Bank Insertion Limits Heat Flux Hot Channel Factor Limits (FaN(Z))
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)
Nuclear Enthalpy Rise Hot Channel Factor Limits (FAHN)
Figure  6                  Penalty Factor, Fp (%), for FQN(z)
Axial Flux Difference (AFD) Target Band 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)
Figure  7                  Axial Flux Difference Envelope Cycle 29                                     Page 1 of 18                                 Rev. 1 1
Required Shutdown Margin K(Z) Normalized Operating Envelope Control Bank Insertion Limits W(Z) Values (Top and Bottom 9% excluded)
Penalty Factor, Fp (%), for FQN(z)
Axial Flux Difference Envelope I
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.
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.
2.1 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 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.
2.2 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 Moderator Temperature Coefficient 2.3.1 When the reactor is critical and < 60% RATED POWER, the moderator temperature coefficient shall be *5.0 pcm/0F, 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.
2.3.2 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.
2.4 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.
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
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))
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+]
2.6.1 FQN(Z) Limits for Fuel F0N(Z) X 1.03 x 1.05 < (2.50)/P x K(Z) for P > 0.5
FaN(Z) x 1.03 x 1.05 < (5.00) x K(Z) for P 5 0.5                   [422 V+]
[422 V+]
FaN(Z) x 1.03 x 1.05 < (5.00) x K(Z) for P 5 0.5
[422 V+]
where:
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:
P is the fraction of full power at which the core is OPERATING K(Z) is the function given in Figure 3 Z
FQN(Z) x 1.03 x 1.05 x W(Z) x Fp _ (2.5)/ P x K(Z)                     [422 V +]
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:
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.
P is the fraction of full power at which the core is OPERATING K(Z) is the function given in Figure 3 Z
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.
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 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%.
The penalty factor for all burnups outside the range of Figure 6 shall be 2%.
Cycle 29                                   Page 3 of 18                                     Rev. 1 1
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+]
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:
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.
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
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:
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, %
ATo  
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.
=
(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.
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. 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:
2.10 Overpower AT Setpoint Overpower AT setpoint parameter values:
AT0   =   Indicated AT at RATED POWER, %
AT0  
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
=
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.
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 < 576.70F for control board indication or < 576.51F for computer indication.
2.11.2 During steady state power operation, Pressurizer Pressure shall be
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
> 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.
>_ 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.
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
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)
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 1 I
(Cores Containing 422V&#xf7; fuel) hfi-h
Figure 1 Reactor Core Safety Limits Curve (1772 Mwt)
* 2~425 psia                              I I      I            I  Unacpeptable Operation 645-0-
(Cores Containing 422V&#xf7; fuel) hfi-h 645-0-
62-(U 1800 p4ia 0.
62-(U 0.
ME 4)25 8  4 I-Acceptoble Operation
ME 8 4)25 I-2~425 psia I
                                - -  -  -  -    -  - - -  -          - - - - -  -  - -  - -
I I
565 0         20               40           60       80           100         120 Core Power (percent of 1772 MWt)
I Unacpeptable Operation 1 800 p4ia Acceptoble Operation 4
Cycle 29                                           Page 7 of 18                                   Rev. 11
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)
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,
C,     900 80 Soo 700 5O 900 3~00 200 100 0
5O 900 Soo 3~
0 200 400   600       800       1000     1200     1400 1600  1800 2000 Full Power Equilibrium Boron Concentration (ppm)
00 200 100 0
Cycle 29                             Page 8 of 18                                 Rev,.1 1
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                                             TRM 2.1 TECHNICAL REQUIREMENTS MANUAL                                     Revision 1 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 3 Hot Channel Factor Normalized Operating Envelope (K(Z))
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 (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
I 1.2 1.1 1
0     1   2 3   4   5     6   7 8  9  10  11  12 Core Height (ft)
0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0
Cycle 29                             Page 9 of 18                               Rev. 1 1
(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                                                     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
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 1 I
* 160
Figure 4 Control Bank Insertion Limits 240 220 200 180 C
* 140 (n
160 140 (n
120 100 C
120 100 C0 0
0 0    80 60 40 20 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
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.
>_.225 and *5230 steps withdrawn.
Note: The Rod Bank Insertion Limits are based on a control bank tip-to-tip distance of 126 steps.
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
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)
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 1 I
Height                           BU IMWd/MTU]
Figure 5 - W(Z) Values (Top and Bottom 9% excluded)
tftJ     150         2000         6000       12000         17000 AO = 2.11%   AO = -0.08% AO = -2.43% 1 AO = -2.99%   AO= -3.07%
Height BU IMWd/MTU]
[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
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)
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                           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%/
Height Iftl BU [MWd/MTUI 150 2000 1
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
6000 1
[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%,
12000 17000 AO '=i2.11%/
      -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.
AO fi -0.08%
Cycle 29                                     Page 12 of 18                                           Rev. 1 1
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)
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision I I
Cycle Burnup       Penalty Factor (MWD/MTU)             Fp (%)
Figure 6 Penalty Factor, Fp (%), for FQN(Z)
150               2.00 18,185               2.00 Note: Linear interpolation is adequate for intermediate cycle bumups.
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%.
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.
Refer to TS 3.10.b.6.C.
Cycle 29                                   Page 13 of 18                                     Rev. 1
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
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
(-9.0, 100.0)         (6.0, 100.0) 100 I-    90 (L
L a.
80 0
0 4-C.
L
(U 90 80 70 60
: a. 70 0
(-9.0, 100.0)
4-C.
(6.0, 100.0)
(U 60 50
(-27.0, 50.0)
(-27.0, 50.0)                                             (28.0, 50.0) 40          I   II     I '    s'IIII   IIII         I'   I "'                Il
(28.0, 50.0)
                  -40     -30       -20           -10       0       10     20       30       40 Axial Flux Difference (% delta-I)
I II 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.
s'IIII IIII I'
Cycle 29                                   Page 14 of 18                                     Rev. 1
I I l 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.
I 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 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.
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.
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 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.
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.
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.
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.
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
I 2.5 Control Bank Insertion Limits 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)
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         WCAP-10216-P-A, Revision 1A, "Relaxation Limits (FQN(Z))              of Constant Axial Offset Control-FQ Surveillance Technical Specification,"
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.
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.
WCAP-1 2945-P-A (Proprietary),
(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.
"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.
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,"
WCAP-10054-P-AIWCAP-10081-NP-A, "Westinghouse Small Break ECCS Evaluation Using the NOTRUMP Code,"
August 1985.
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.
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
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)
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 1 I
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.
Table 1 (cont)
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.
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.
2.8    Axial Flux Difference Target Band          WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset (AFD) Control-F 0 I
Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.
Surveillance Technical Specification,"
WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset (AFD) Control-F0 Surveillance Technical Specification,"
February 1994.
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.
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,"
WCAP-8745-P-A, "Design Bases For The Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"
September 1986.
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.
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,"
CENP-397-P-A, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology,"
Rev. 1, May 2000.
Rev. 1, May 2000.
Cycle 29                               Page 17 of 18                                 Rev. 1
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)
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 1 I
NRC Approved Methodolocies for COLR Parameters COLR Section         Parameter                     NRC Approved Methodology I
Table I (cont)
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,"
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.
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.
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,"
CENP-397-P-A, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology,"
Rev. 1, May 2000.
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-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 for those events not utilizing RTDP.
2.12      Refueling Boron Concentration            WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.
Cycle 29                               Page 18 of 18                                   Rev. 1}}
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}}

Latest revision as of 16:56, 14 January 2025

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 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. 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/°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 F0EQ(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 TECHNICAL REQUIREMENTS MANUAL TRM 2.1 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' ; 0 for 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 < 576.70F for control board indication or < 576.5 0F 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 TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 0 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 Core Power (percent of 1772 MWt) 120 Cycle 29 Page 7 of 19 Rev. 0

dI KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 0 Figure 2 Required Shutdown Reactivity vs. Boron Concentration

-E C.)

-o 3l 0*

1700 1600 1542 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0

i -

  • -~-

r 0

200 400 600 800 1000 1200 1400 Full Power Equilibrium Boron Concentration (ppm) 1600 1800 2000 Cycle 29 Page 8 of 19 Rev. 0

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

N 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

8 9

10 Core Height (ft) 11 12 Cycle 29 Page 9 of 19 Rev. 0

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

i160 CL I-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 TECHNICAL REQUIREMENTS MANUAL TRM 2.1 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 TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 0 Figure 5 Cont'd (Top and Bottom 9% excluded)

Height

[ft]

BU [MWd/MTU 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 TECHNICAL REQUIREMENTS MANUAL TRM 2.1 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 TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 7 Axial Flux Difference 110 100 C-0a.

00.

I-0 a,,-

90 80 70 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 TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 0 Table 1 NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC ADoroved Methodoloav 2.1 Reactor Core Safety Limits 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.

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 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-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.

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 2.4 Shutdown Bank Insertion Limit 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 TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 0 Table I (cont)

NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC Approved Methodology Model NOTRUMP (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.

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

August 1985.

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.

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.

2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNAH)

Cycle 29 Page 17 of 19 Rev. 0

_KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 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.

WCAP-8745-P-A, "Design Bases For The Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"

September 1986.

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 18 of 19 Rev. 0

ýý I.

>1*

KEWAUNEE POWER STATION TECHINICAIL REQUIREMENTS MANUAL TRM 2.1 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)

Instrumentation-Overpower AT 2.11 RCS Pressure, Temperature, and Flow Departure From Nucleate (DNB) Limits 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.

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.

2.12 Boron Concentration 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 F

C Chairman

-D/a- ?e2 -0 Date op-

-,5 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 TECHNICAL REQUIREMENTS MANUAL TRM 2.1 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 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 3.1O.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.3.1B 3.1O.k 3.10.1 3.10.m.1 3.8.a.5 Description Reactor Core Safety Limits Shutdown Margin Moderator Temperature Coefficient (MTC)

Shutdown Bank Insertion Limits Control Bank Insertion Limits Heat Flux Hot Channel Factor Limits (FaN(Z))

Nuclear Enthalpy Rise Hot Channel Factor Limits (FAHN)

Axial Flux Difference (AFD) Target Band 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 FQN(z)

Axial Flux Difference Envelope I

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 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 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/0F, 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 F0N(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 < 576.70F 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÷ 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 C

160 140 (n

120 100 C0 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 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%

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 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)

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

-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.

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+ 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-F0 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

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