ML110880106

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Core Operating Limits Report Cycle 31 Revision 1
ML110880106
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 03/21/2011
From: Wilson M
Dominion Energy Kewaunee
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
11-139
Download: ML110880106 (19)
v • d • e


Text

Dominion Energy Kewaunee, Inc.

N4Hy 42, Kewaunee, W1 54216 Dom inioni Web Address: www.dom.com MAR 2 12011 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Serial No.11-139 LIC/NW/RO Docket No.: 50-305 License No.: DPR-43 DOMINION ENERGY KEWAUNEE, INC.

KEWAUNEE POWER STATION CORE OPERATING LIMITS REPORT CYCLE 31 REVISION 1 Pursuant to Kewaunee Power Station (KPS) Technical Specification 5.6.3.d, enclosed is a copy of the Kewaunee Power Station Core Operating Limits Report Cycle 31, Revision 1.

If you have questions or require additional information, please feel free to contact Mr.

Jack Gadzala at 920-388-8604.

Very truly yours, Micha I J. Wilson Director Safety and Licensing Kewaunee Power Station Commitments made by this letter: NONE Enclosure

1. Kewaunee Power Station Core Operating Limits Report Cycle 31, Revision 1.

Serial No.11-139 Page 2 of 2 cc:

Regional Administrator, Region III U. S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 Mr. K. D. Feintuch 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

CORE OPERATING LIMITS REPORT Kewaunee Unit 1 Cycle 31 Revision 1 March 2011 I

COLR-KIC31, Revision 1 Page I.of 17 0

1

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Kewaunee Unit I Cycle 31 has been prepared in accordance with the requirements of Kewaunee Technical Specification 5.6.3.

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

COLR Section KPS Technical Description Specification 2.1 2.1.1 Reactor Core Safety Limit 2.2 3.1.1 Shutdown Margin 2.3 3.1.3 Moderator Temperature Coefficient (MTC) 2.4 3.1.5 Shutdown Bank Insertion Limits 2.5 3.1.6 Control Bank Insertion Limits 2.6 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

2.7 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F*u) 2.8 3.2.3 AXIAL FLUX DIFFERENCE (AFD) 2.9 3.3.1 Function 6 Reactor Protection System Instrumentation:

Overtemperature AT 2.10 3.3.1 Function 7 Reactor Protection System Instrumentation:

Overpower AT 2.11 3.4.1 RCS Pressure, Temperature and Flow Departure from Nucleate Boiling (DNB) Limits 2.12 3.9.1 Boron Concentration (Refueling Operations)

Figure 1 2.1 Reactor Core Safety Limits Curve (1772 MWt)

Figure 2 DELETED (Required Shutdown Margin)

Figure 3 DELETED (Hot Channel Factor Normalized Operating Envelope (K(Z)))

Figure 4 3.1.6 Control Bank Insertion Limits Figure 5 N(Z) Values (Top and Bottom 9% excluded)

Figure 6 DELETED (Penalty Factor, Fp, for FQ(Z))

Figure 7 3.2.3 AXIAL FLUX DIFFERENCE Envelope COLR-KIC3l, Revision 1 Page 2 of 17 1

2.0 OPERATING 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 5.6.3.

2.1 Reactor Core Safety Limits (TS 2.1.1)

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 Mar in (TS 3.1.1)

Shutdown Margin shall be Ž 1554 pcm.

2.3 Moderator Temperature Coefficient (ITC) (TS 3.1.3) 2.3.1 When the reactor is critical and *< 60% of RATED THERMAL POWER, the moderator temperature coefficient shall be _* 5.0 pcm/rF. When the reactor is > 60%

RATED THERMAL POWER, the moderator temperature coefficient shall be zero or negative.

a.

The BOC/ARO-MTC shall be _ 5.0 pcm/nF (upper limit), when *60% RTP, and ___

0.0 pcmnF when > 60% RTP.

b.

The EOC/ARO/RTP-MTC shall be less negative than or equal to -44.7 pcm!F (lower limit).

MTC surveillance limits are:

i)

The 300 ppn-dARO/RTP-MTC should be less negative than or equal to -39.1 pc/nilF. If MTC is more negative, then repeat measurement once per 14 EFPD during the remainder of the fiel cycle. Note this surveillance does not need to be repeated if criterion ii, listed below, is satisfied.

ii)

The 60 ppmIARO/RTP-MTC should be less negative than or equal to -43.6 pcm/°F.

COLR-K1C31, Revision I Page 3 of 17 1

2.4 Shutdown Bank Insertion Limits (TS 3.1.5)

The shutdown rods shall be fully withdrawn (224 steps) when the reactor is critical or approaching criticality.

2.5 Control Bank Insertion Limits (TS 3.1.6)

The control rod banks shall be limited in physical insertion as shown in COLR Figure 4.

2.6 Nuclear Heat Flux Hot Channel Factor (F& Z (TS 3.2.1) 2-6.1 FC(Z) Limits for Fuel F N

)

CFQ Q'(Z)

  • 1.03 *1.05

<-*K(Z) for P > 0.5

[422V+]

p F,()*103*N0' CFQ Q '(Z)

  • 1.03
  • 1:O5
  • K(Z) for P *_0.5

[422V+]

0.5 Where

P is the fraction of full power at which the core is operating K(Z) is 1.0 for all core heights Z

is the core height location for the FQ of interest CFQ equals 2.50 FQN (Z) is a measured FQ distribution obtained during the target flux determination 2.6.2 FQ(Z) Limits for Fuel FQ(Z)

  • 1.03
  • 1.05
  • N(Z)
  • K(Z)

[422V+]

P Where:

P is the fraction of full power at which the core is operating K(Z) is 1.0 for all core heights Z

is the core height location for the FQ of interest CFQ equals. 2.50 Fp is the penalty factor described in 2.6.3 N(Z) is a cycle-specific non-equilibrium multiplier on FQ (Z) to account for power distribution transients during normal operation, provided in Figure 5.

Fj(Z) is a measured FQ distribution obtained during the target flux determination The N(z) decks are generated for normal operation flux maps that are typically taken at fidl power, ARO. Additional N(z) decks may be generated, if necessary, consistent with the methodology described in Reference 1.

2.6.3 A penalty factor of 1.00 shall be used unless the Note criteria of TS SR 3.2.1.2 is met, at which time a penalty of 1.02 shall be used.

COLR-KIC31, Revision I Page 4 of 17 1

2.7 Nuclear Enithalpy Rise Hot Channel Factor (F~,)

(TS 3.2.2)

F N

  • 1.04*< CFDH * [1 + PFDH * (1 - P)]

[422V+]

Where:

P is the fraction of full power at which the core is operating CFDH equals 1.70 PFDH equals 0.3 2.8 AXIAL FLUX DIFFERENCE (AFD) (TS 3.2.3)

The AFD acceptable operation limits are provided in COLR Figure 7.

2.9 Overternperature AT Setpoint (TS 3.3.1 Function 6)

AT<ATo 4K

-K, *(T-T')* 1+vrts K *(pp'>f (AJ)

L 1 +it'fs AT0

=

hidicated AT at RATED THERMAL POWER, %

s Laplace transform operator, sec 1.

T Average temperature, OF T'

< 573.0 OF P

Pressurizer Pressure, psig P'

2235 psig Ki 1.195 K 2

Ž 0.015/"F K3

Ž 0.00072/psig "q

30 seconds

2 4 seconds f1(AIl)

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 RATED THERMAL POWER, such that (a) For qt - qb within -15, +6 %, f(A,)

= 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 THERMAL POWER.

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

COLR-K1C31, Revision I Page 5 of 17 1

2.10 Overpower AT Setpoint (TS 3.3.1 Function 7)

AT* ATo,*K 4 -

jKj5*-

31 *T-K6 *(T-fT')()1 ATo

=

Indicated AT at RATED THERMAL POWER, %

s Laplace transform operator, sec T

Average temperature, OF T'

_* 573.0 OF K4

< 1.095 K5

_ 0.0275/1F for increasing T

Ž 0 for decreasing T K6

Ž 0.00103/'F for T > T' OforT<T' T3 10 seconds f2(AI)

= 0for all Al 2.11 RCS Pressure, Temperature and Flow Departure from Nucleate Boiling (DNB) Limits (TS 3.4.1) 2.11.1 During steady state power operation, Tavg shall be < 576.7 OF for control board indication or

  • 576.5 OF for computer indication.

2.11.2 During steady state power operation, pressurizer pressure shall be Ž_ 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 Boron Concentration (Refueling Operations) (TS 3.9.1)

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

COLR-K1C31, Revision 1 Page 6 of 17 1

Figure 1 (TS 2.1.1)

Reactor Core Safety Limits Curve (1772 Mwt)

(Cores Containing 422V+ fuel) 665 LL 00 645 C_

C.

E Q) 625 0

0 60 0

M

(~585 565 0

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

COLR-KIC3l, Revision 1 Page 7 of'I 7 Z:>

I

Figure 2 Required Shutdown Margin vs. Boron Concentration DELETED Figure 3 Hot Channel Factor Normalized Operating Envelope (K(Z))

DELETED COLR-K1C31, Revision I Page8oM I

Figure 4 Control Bank Insertion Limits (TS 3.1.6)

C

-6 240 220 200 180 160 140 120 100 80 60 40 20 0

0 10 20 30 40 50 60 70 80 90 100 Percent of RATED THERMAL POWER Note: The Rod Bank Insertion Limits are based on a control bank tip-to-tip distance of 126 steps.

COLR-K IC3 I, Revision I Page 9 of 17 1

Figure 5 N(Z) Values NODE HEIGHT 0 to 1000 1000 to 3000 3000 to 5000 5000 to 7000 7000 to 9000 9000 to 11000 (FEET)

MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU AO = 2.3%

AO = 0.8%

AO = -1.0%

AO = -2.0%

AO = -2.4%

AO = -2.6%

Top 7

10.8 1.100 1.110 1.118 1.146 1.148 1.157 8

10.6 1.099 1.111 1.119 1.144 1.145 1.154 9

10.4 1.100 1.108 1.116 1.141 1.142 1.151 10 10.2 1.099 1.105 1.116 1.138 1.139 1.148 11 10.0 1.096 1.102 1.120 1.135 1.136 1.145 12 9.8 1.092 1.097 1.123 1.130 1.132 1.143 13 9.6 1.089 1.096 1.126 1.127 1.129 1.142 14 9.4 1.084 1.099 1.126 1.126 1.127 1.138 15 9.2 1.083 1.106 1.128 1.132 1.132 1.137 16 9.0 1.084 1.113

.1-136 1.144 1.143 1.140 17 8.8 1.089 1.119 1.147 1.157 1.157 1.148 18 8.6 1.095 1.125 1.153 1.166 1.165 1.159 19 8.4 1.102 1.128 1.157 1.171 1.170 1.170 20 8.2 1.108 1.131 1A160 1.175 1.175 1.175 21 8.0 1.112 1.132 1.160 1.177 1.179 1.179 22 7.8 1.117 1.131 1.160 1.178 1.184 1.184 23 7.6 1.120 1.129 1.158 1.178 1.188 1.188 24 7.4 1.122 1.127 1.157 1.178 1.190 1.190 25 7.2 1.124 1.125 1.156 1.176 1.192 1.192 26 7.0 1.124 1.124 1.152 1.173 1.192 1.192 27 6.8 1.123 1.122 1.139 1.168 1.188 1.188 28 6.6 1.120 1.120 1.123 1.161 1.181 1.181 29 6.4 1.118 1.118 1.114 1.157 1.178 1.178 30 6.2 1.115 1.115 1.112 1.154 1.174 1.174 31 6.0 1.113 1.112 1.108 1.149 1.168 1.168 32 5.8 1.109 1.109 1.106 1.141 1.159 1.159 33 5.6 1.102 1.102 1.102 1.130 1.148 1.147 34 5.4 1.099 1.099 1.099 1.121 1.134 1.134 35 5.2 1.102 1.102 1.095 1.114 1.119 1.121 36 5.0 1.107 1.107 1.092 1.111 1.110 1.111 37 4.8 1.111 1.111 1.088 1.110 1.109 1,105 38 4.6 1.120 1.119 1.091 1.107 1,107 1.106 39 4.4 1.131 1.129 1.100 1.101 1.101 1.111 40 4.2 1.136 1.134 1.107 1.100 1.094 1,114 41 4.0 1,136 1.134 1.110 1.105 1.091 1.114 42 3.8 1.137 1.135 1.114 1,108 1.093 1,112 43 3.6 1.143 1-141 1.119 1.110 1.101 1.110 44 3.4 1.153 1.150 1.123 1.111 1.107 1A109 45 3.2 1.167 1A163 1,129 1.113 1,113 1.110 46 3.0 1.181 1.176 1.135 1.117 1.118 1.115 47 2.8 1.195 1.189 1.144 1.122 1.122 1.120 48 2.6 1.208 1.201 1.153 1.123 1.123 1.121 COLR-KI C31, Revision 1 Page l0 of17 I

Figure 5 (continued)

N(Z) Values 1 NODE HEIGHT 0 to 1000 1000 to 3000 3000 to 5000 5000 to 7000 7000 to 9000 9000 to 11000 (FEET)

MWO/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 49 50 51 52 53 54 55 Bottom 2.4 2.2 2.0 1.8 1.6 1.4 1.2 1.222 1.240 1.251 1.256 1.260 1.268 1.275 1.214 1.230 1.241 1.245 1.249 1.257 1.263 1.164 1.179 1.188 1.191 1.195 1.202 1.207 1.126 1.135 1.142 1.143 1.145 1.150 1.154 1.126 1.135 1.142 1.143 1.145 1.150 1.154 1.124 1.134 1.141 1.143 1.145 1.150 1.155

1) Excludes top and bottom 9%

These decks were generated for normal operation flux maps that are typically taken at full power ARO. Additional N(z) decks may be generated, if necessary, consistent with the methodology described in Reference 1.

COLR-K1C31, Revision I Page I I of 17 1

Figure 5 (continued)

N(Z) Values 1 NODE HEIGHT 11000 to 13000 (FEET)

MWDIMTU AO = -2.7%

Top 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 10.8 10.6 10.4 10.2

.10.0 9.8 9.6 9.4 9.2 9.0 8.8 8.6 8.4 8.2 8.0 7.8 7.6 7.4 7.2 7.0 6.8 6.6 6.4 6.2 6.0 5.8 5.6 5.4 5.2 5.0 4.8 4.6 4.4 4.2 4.0 3.8 3.6 3.4 3.2 3.0 2.8 2.6 1.157 1.154 1.151 1.148 1.145 1.143 1.142 1.137 1.137 1.144 1.158 1.171 1.181 1.187 1.190 1.193 1.196 1.197 1.198 1.195 1.186 1.173 1.168 1.164 1.157 1.148 1.140 1.131 1.120 1.111 1.106 1.106 1.111 1.114 1.114 1.112 1.110 1.109 1.110 1.114 1.120 1.120 13000 MWD/MTU to EOR AO = -2.7%

1.158 1.155 1.153 1.151 1.150 1.148 1.146 1.140 1.139 1.145 1.158 1.171 1.181 1.187 1.190 1.193 1.195 1.196 1.198 1.197 1.192 1.184 1.181 1.177 1.172 1.162 1.151 1.137 1.121 1.108 1.102 1.097 1.090 1.085 1.084 1.084 1.087 1.091 1.099 1.108 1.117 1.120 COLR-KIC31, Revision I Page 12 of 17 1

Figure 5 (continued)

N(Z) Values 1 NODE HEIGHT 11000 to 13000 (FEET)

MWD/MTU 49 50 51 52 53 54 55 Bottom 2.4 2.2 2.0 1.8 1.6 1.4 1.2 1.125 1.138 1.149 1.152 1.155 1.159 1.163 13000 MWDIMTU to EOR 1.125 1.138 1.149 1.152 1.155 1.159 1.163

1) Excludes top and bottom 9%

These decks were generated for normal operation flux maps that are typically taken at full power ARO. Additional N(z) decks may be generated, if necessary, consistent with the methodology described in Reference 1.

COLR-KIC3 1, Revision I Page 13 of 17 1

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

DELETED COLR-K1 C31, Revision I Page 14 of 17 1

Figure 7 AXIAL FLUX DIFFERENCE Target Band (TS 3.2.3) 110

( 9.0, 100.0)

(6.0 100.0) 100 90 w

o 80

_J w

I 70 60 13._

50 40 I

Unacceptable Unacceptable Operation Operation Acceptable Operation

(-22.0, 50.0)

(20.0, 50.0)

-40

-30

-20

-10 0

10 20 AXIAL FLUX DIFFERENCE (% Delta-I) 30 40 COLR-KI C31, Revision 1 Page 15 of 17 1

3.0 REFERENCES

1. Topical Report DOM-NAF-5-A, Revision 0.2-A, "Application of Dominion Nuclear Core Design and Safety Analysis Methods to the Kewaunee Power Station (KPS),"

January 2011.

Methodology for:

TS 2.1.1 - Reactor Core Safety Limit; TS 3.1.1 - Shutdown Margin; TS 3.1.3 - Moderator Temperature Coefficient; TS 3.1.5 - Shutdown Bank Insertion Limits; TS 3.1.6 - Control Bank Insertion Limits; TS 3.2.1 - Heat Flux Hot Channel Factor (FQ (Z));

TS 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor (FAU);

TS 3.2.3 - AXIAL FLUX DIFFERENCE (AFD);

TS 3.4.1 - RCS Pressure, Temperature and Flow Departure from Nucleate Boiling (DNB) Limits; TS 3.9.1 -Boron Concentration (Refueling Operations)

2. Topical Report WPSRSEM-NP, Revision 3, "Kewaunee Nuclear Power Plant - Review for Kewaunee Reload Safety Evaluation Methods," September 10, 200 1.

Methodology for:

TS 3.1.1 - Shutdown Margin

3. WCAP-12945-P-A (Proprietary), "Westinghouse Code Qualification Document for Best-Estimate Loss-of-Coolant Accident Analysis," Volume I, Revision 2, and Volume II-V, Revision 1, March 1998.

Methodology for:

TS 3.2.1 - Heat Flux Hot Channel Factor (FQ(Z))

TS 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor (Ff,);

4. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985.

Methodology for:

TS 3.2.1 - Heat Flux Hot Channel Factor (FQ(Z))

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

Methodology for:

TS 3.2.1 - Heat Flux Hot Channel Factor (FQ(Z))

COLR-KIC3t, Revision I Page 16 of 17 1

6. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology,". July 1985.

Methodology for:

TS 2.1.1 - Reactor Core Safety Limit; TS 3.1.3 - Moderator Temperature Coefficient;

7. WCAP-8745-P-A, "Design Bases for the Thermal Overtemperature AT and Thermal Overpower AT trip functions," September 1986.

Methodology for:

TS 3.3.1 Function 6 - Overtemperature AT Setpoint; TS 3-3.1 Function 7 - Overpower AT Setpoint

8. WCAP-14449-P-A, Revision 1, "Application of Best Estimate Large-Break LOCA Methodology to Westinghouse PWRs with Upper Plenum Injection," October 1999.

Methodology for:

TS 3.2.1 - Heat Flux Hot Channel Factor (FQ (Z))

TS 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor (FA.);

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

Methodology for:

TS 3.2.1 - Heat Flux Hot Channel Factor (FQ (Z))

10. CENP-397-P-A, Revision 1, <Imnproved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology," May 2000.

Methodology for:

TS 3.3.1 Function 6 - Overtemperature AT Setpoint; TS 3.3.1 Function 7 - Overpower AT Setpoint COLR-KIC31, Revision 1 Page 17 of 17 1

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