ML110660426

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Core Operating Limits Report Cycle 30 Revision 3
ML110660426
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 02/14/2011
From: Wilson M
Dominion Energy Kewaunee
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
11-001, LIC/NW/RO COLR-K1C30, Rev 3
Download: ML110660426 (19)
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Text

Dominion Energy Kewaunee, Inc.

0Dom inion N490 Hw 42, Kewaunee, WI 54216 Web Address: www.dom.com FEB 14 2011 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Serial No.11-001 LIC/NW/RO Docket No.: 50-305 License No.: DPR-43 DOMINION ENERGY KEWAUNEE, INC.

KEWAUNEE POWER STATION CORE OPERATING LIMITS REPORT CYCLE 30 REVISION 3 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 30, Revision 3.

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

Jack Gadzala at 920-388-8604.

Very truly yours, Mi.ael 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 30, Revision 3.

AcD00

Serial No.11-001 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

COLR-K1C30, Revision 3 CORE OPERATING LIMITS REPORT Kewaunee Cycle 30 Revision 3 COLR-K1C30, Revision 3 Page I of 17

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Kewaunee Unit I Cycle 30 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:

KPS Improved COLR Section 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))

Nuclear Enthalpy Rise Hot Channel Factor 2.7 3.2.2 (FN 2.8 3.2.3 Axial Flux Difference (AFD) 2.9 3.3.1 Function 6 Overtemperature AT Setpoint 2.10 3.3.1 Function 7 Overpower AT Setpoint RCS Pressure, Temperature and Flow 2.11 3.4.1 Departure from Nucleate Boiling (DNB)

Limits 2.12 3.9.1 Boron Concentration (Refueling Operations)

Reactor Core Safety Limits Curve (1772 Figure 1 2.1.1 M t MWt)

Figure 2 DELETED (Required Shutdown Margin)

DELETED (Hot Channel Factor Normalized Figure 3 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-KIC30, Revision 3 Page 2 of 17

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 Margin (TS 3.1.1)

Shutdown Margin shall be _1554 pcm.

2.3 Moderator Temperature Coefficient (MTC) (TS 3.1.3) 2.3.1 When the reactor is critical and _<60% of RATED POWER, the moderator temperature coefficient shall be *_5.0 pcm/3F. When the reactor is > 60% RATED POWER, the moderator temperature coefficient shall be zero or negative.

a.

The BOC/ARO-MTC shall be -*5.0 pem/0F (upper limit), when < 60% RTP, and

_*0.0 pcm/*F when _>60% RTP.

b.

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

c.

MTC surveillance limits are:

i)

The 300 ppm/ARO/RTP-MTC should be less negative than or equal to -39.3 pcmPF. If MTC is more negative, then repeat measurement once per 14 EFPD during the remainder of the fuel cycle. Note this surveillance does not need to be repeated if criterion ii, listed below, is satisfied.

ii)

The 60 ppm/ARO/RTP-MTC should be less negative than or equal to -43.6 pcm/0 F.

COLR-K1C30, Revision 3 Page 3 of 17

2.4 Shutdown Bank Insertion Limits (TS 3.1.5)

The shutdown rods shall be fully withdrawn ( 224 steps and <*230 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 (Fp(Z)) (TS 3.2.1) 2.6.1 FQc(Z) Limits for Fuel Fffj(Z)

  • 1.03
  • 1.0

< CFQ K(Z) for P > 0.5

[422V+]

QCFQ F(Z)

  • 1.0*3
  • 1.05
  • K(Z) forP V*<0.5

[422V+]

Q-

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 FQj (Z) is a measured FQ distribution obtained during the target flux determination 2.6.2 FQT(Z) Limits for Fuel Ff'(Z)

  • 1.03
  • 1.05
  • N(Z)
  • Fp L
  • K(Z)

[422V+]

Q-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 FQN(Z) to account for power distribution transients during normal operation, provided in Figure 5.

FQj (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 full 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 1.02 shall be used for TS SR 3.2.1.2.

COLR-K1C30, Revision 3 Page 4 of 17

2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNt) (TS 3.2.2)

FAN

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

[422 V+]

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 Overtemperature AT Setpoint (TS 3.3.1 Function 6)

AT<-AT *FK,-K 2 * (T-T')* ll+r 1

+ s + K3 (P-P')-

(AI AT* 2 I

I1+ 'r 2s +/-

ATO Indicated AT at RATED POWER, %

T

= Average temperature, OF T'

< 573.0 OF P

= Pressurizer Pressure, psig P'

= 2235 psig Ki

< 1.195 K2

=

0.015/-F K3

= 0.00072/psig Tj

>_t 30 seconds T2

  • 4 seconds f1(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 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 exceeds -15%, the AT trip setpoint shall be automatically reduced by an equivalent of 3.78% of RATED POWER.

COLR-K1C30, Revision 3 Page 5 of 17

2.10 Overpower AT Setpoint (TS 3.3.1 Function 7)

AT <AT0 *[K4 -K 5 *

'3s *T-K6*(T-T')-f2(AI)

AT0

= 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 K 6 0.00103/°F for T > T' 0 forT <T' T3 10 seconds f2(AI)

=

0 for 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 > 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 > 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-K1C30, Revision 3 Page 6 of 17

Figure 1 Reactor Core Safety Limits Curve (1772 Mwt)

(Cores Containing 422V+ fuel) 665 0

645 CL

) 625 I-0 605 0) 585 a,,

565 0

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

COLR-K1C30, Revision 3 Page 7 of 17

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

DELETED COLR-K1C30, Revision 3 Page 8 of 17

Figure 4 Control Bank Insertion Limits (TS 3.1.6) 240 220 200 180 160

.- 140 120

(.

100 80

-0 100 60 Fully w/d Position 229 steps I

I I.

(14.34%, 229)

(66.25%, 229)

BANK B (0.0%, 194)

(100.0%, 185)

/BANK C

BANK D (0.0 %, 68)

/

(23.8%, 0) 0 10.

20 30 40 5

0 7

0 9

0 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-KIC30, Revision 3 Page 9 of 17

Figure 5 N(Z) Values I I

Height I

Bumup (MWD/MTU)

N (ET 0 to 1000 1000 to 3000 3000 to 5000 5000 to 7000 7000 to 9000 9000 to 11000 Node __EET)

AO=0.50%

AO=-1.2%

AO=-2.4%

AO=-2.8%

AO=-2.6%

AO=-2.4%

Top 7

10.8 1.092 1.127 1.147 1.147 1.146 1.123 8

10.6 1.090 1.126 1.143 1.143 1.141 1.127 9

10.4 1.090 1.124 1.139 1.139 1.138 1.133 10 10.2 1.090 1.122 1.136 1.135 1.138 1.138 11 10.0 1.091 1.121 1.132 1.133 1.141 1.142 12 9.8 1.094 1.119 1.127 1.130 1.144 1.145 13 9.6 1.098 1.117 1.123 1.129 1.147 1.147 14 9.4 1.100 1.113 1.116 1.127 1.147 1.147 15 9.2 1.102 1.113 1.115 1.128 1.148 1.148 16 9.0 1.106 1.121 1.121 1.133 1.145 1.145 17 8.8 1.112 1.132 1.132 1.142 1.147 1.147 18 8.6 1.120 1.140 1.140 1.151 1.156 1.159 19 8.4 1.127 1.146 1.146 1.160 1.169 1.174 20 8.2 1.132 1.150 1.150 1.168 1.179 1.184 21 8.0 1.135 1.152 1.152 1.173 1.188 1.193 22 7.8 1.136 1.153 1.153 1.178 1.195 1.203 23 7.6 1.135 1.152 1.152 1.180 1.201 1.210 24 7.4 1.132 1.149 1.149 1.180 1.204 1.217 25 7.2 1.130 1.148 1.147 1.181 1.206 1.221 26 7.0 1.127 1.145 1.144 1.181 1.207 1.223 27 6.8 1.121 1.137 1.141 1.174 1.204 1.226 28 6.6 1.113 1.125 1.136 1.164 1.198 1.227 29 6.4 1.108 1.118 1.132 1.159 1.195 1.227 30 6.2 1.104 1.112 1.127 1.156 1.192 1.223 31 6.0 1.099 1.104 1.123 1.153 1.189 1.220 32 5.8 1.093 1.096 1.118 1.149 1.183 1.212 33 5.6 1.082 1.085 1.110 1.144 1.175 1.203 34 5.4 1.075 1.079 1.104 1.135 1.166 1.192 35 5.2 1.073 1.077 1.101 1.124 1.160 1.183 36 5.0 1.076 1.079 1.102 1.114 1.156 1.174 37 4.8 1.079 1.080 1.103 1.107 1.153 1.166 38 4.6 1.090 1.090 1.103 1.104 1.152 1.158 39 4.4 1.104 1.104 1.103 1.102 1.149 1.150 40 4.2 1.111 1.111 1.102 1.102 1.144 1.143 41 4.0 1.111 1.111 1.101 1.101 1.138 1.137 42 3.8 1.115 1.115 1.101 1.098 1.131 1.131 43 3.6 1.124 1.124 1.104 1.096 1.124 1.123 44 3.4 1.134 1.134 1.108 1.093 1.115 1.115 45 32 1.145 1.145 1.116 1.096 1.105 1.105 46 3.0 1.156 1.156 1.125 1.101 1.094 1.093 47 2.8 1.166 1.166 1.136 1.110 1.085 1.085 48 2.6 1.175 1.176 1.145 1.116 1.076 1.080 49 2.4 1.186 1.186 1.156 1.126 1.075 1.081 so 2.2 1.200 1.199 1.169 1.138 1.078 1.084 COLR-K1C30, Revision 3 Page 10 of 17

Figure 5 (continued)

N(Z) Values I Height Bumup (MWD/MTU) 0 to 1000 1000 to 3000 3000 to 5000 5000 to 7000 7000 to 9000 9000 to 11000 (FEET)

AO=0.50%

AO=-!.2%

AO = -2.4%

AO = -2.8%

AO = -2.6%

AO = -2.4%

51 2.0 1.210 1.207 1.178 1.146 1.082 1.088 52 1.8 1.214 1.211 1.181 1.149 1.082 1.088 53 1.6 1.218 1.214 1.185 1.151 1.084 1.089 54 1.4 1.225 1.221 1.191 1.157 1.086 1.091 55 1.2 1.232 1.226 1.197 1.162 1.088 1.094 Bottom

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-K1C30, Revision 3 Page I I of 17

Figure 5 (continued)

N(Z) Values 1 Height Bumup (MWD/MTU)

Node (EM 11000 to 13000 13000 to 15000 15000 to 17000 17000 to EOR I

AO = -2.2%

AO = -2.1%

AO = -2.2%

AO = -2.2%

Top 7

10.8 1.103 1.102 1.096 1.099 8

10.6 1.101 1.102 1.099 1.098 9

10.4 1.100 1.106 1.105 1.097 10 10.2 1.098 1.111 1.112 1.096 11 10.0 1.097 1.117 1.117 1.096 12 9.8 1.101 1.120 1.120 1.098 13 9.6 1.109 1.121 1.121 1.105 14 9.4 1.113 1.123 1.123 1.110 15 9.2 1.119 1.127 1.127 1.119 16 9.0 1.130 1.130 1.128 1.126 17 8.8 1.146 1.138 1.134 1.139 18 8.6 1.161 1.148 1.146 1.157 19 8.4 1.174 1.159 1.159 1.176 20 8.2 1.185 1.167 1.166 1.189

,21 8.0 1.194 1.175 1.175 1.200 22 7.8 1.203 1.182 1.187 1.212 23 7.6 1.210 1.187 1.199 1.221 24 7.4 1.217 1.190 1.208 1.228 25 7.2 1.221 1.192 1.215 1.232 26 7.0 1.223 1.194 1.218 1.234 27 6.8 1.226 1.197 1.225 1.237 28 6.6 1.227 1.203 1.232 1.241 29 6.4 1.227 1.208 1.235 1.243 30 6.2 1.223 1.211 1.233 1.241 31 6.0 1.219 1.213 1.233 1.241 32 5.8 1.213 1.210 1.229 1.237 33 5.6 1.209 1.210 1.225 1.233 34 5.4 1.204 1.205 1.217 1.224 35 5.2 1.198 1.199 1.206 1.212 36 5.0 1.190 1.191 1.199 1.205 37 4.8 1.182 1.182 1.198 1.203 38 4.6 1.170 1.170 1.191 1.194 39 4.4 1.156 1.156 1.177 1.178 40 4.2 1.144 1.144 1.167 1.167 41 4.0 1.136 1.136 1.162 1.161 42 3.8 1.129 1.129 1.155 1.155 43 3.6 1.122 1.122 1.146 1.146 44 3.4 1.113 1.113 1.134 1.134 45 3.2 1.103 1.105 1.121 1.121 46 3.0 1.090 1.095 1.105 1.105 47 2.8 1.083 1.090 1.096 1.096 48 2.6 1.081 1.086 1.092 1.092 49 2.4 1.085 1.088 1.095 1.095 50 2.2 1.088 1.092 1.097 1.097 COLR-KI C30, Revision 3 Page 12 of 17

Figure 5 (continued)

N(Z) Values 1 Height Bumup (MVVD/MTU) 11000 to 13000 13000 to 15000 15000 to 17000 17000 to EOR Node (FEET)

AO = -2.2%

AO = -2.1%

AO = -2.2%

AO = -2.2%

51 2.0 1.092 1.098 1.101 1.102 52 1.8 1.092 1.102 1.103 1.104 53 1.6 1.093 1.106 1.106 1.106 54 1.4 1.095 1.110 1.110 1.106 55 1.2 1.097 1.115 1.115 1.107 Bottom

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-K1C30, Revision 3 Page 13 of 17

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

DELETED COLR-KI C30, Revision 3 Page 14 of 17

Figure 7 Axial Flux Difference Target Band (T.S. 3.2.3) 110 100 90 0(. 80 aE I-70 a) 60 50 40

-40

-30

-20

-10 0

10 Axial Flux Difference (% Delta-I) 20 30 40 Note: This figure represents the Relaxed Power Distribution Control (RPDC) 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.

COLR-KIC30, Revision 3 Page 15 of 17

3.0 References

1. Topical Report DOM-NAF-5 Revision 0. 1-A, "Application of Dominion Nuclear Core Design and Safety Analysis Methods to the Kewaunee Power Station (KPS)," dated December, 2009.

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 (F~N);

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

Methodology for:

TS 3.1.1 - Shutdown Margin

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

Methodology for:

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

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

4. N. Lee, et al., "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," WCAP-10054-P-A, dated August 1985. (Westinghouse Proprietary)

Methodology for:

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

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

(Westinghouse Proprietary)

Methodology for:

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

COLR-K1C30, Revision 3 Page 16 of 17

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

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, dated September 1986. (Westinghouse Proprietary)

Methodology for:

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

8.

S. I. Dederer, et al., WCAP-14449-P-A, Application of Best Estimate Large-Break LOCA Methodology to Westinghouse POWs with Upper Plenum Injection, Revision 1, dated October 1999. (Westinghouse Proprietary)

Methodology for:

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

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

9. WCAP-126 10-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," dated April 1995. (Westinghouse Proprietary)

Methodology for:

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

10. CENP-397-P-A, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology," Revision 1, dated May 2000. (Proprietary)

Methodology for:

TS 3.3.1 Function 6 - Overtemperature AT Setpoint; TS 3.3.1 Function 7 - Overpower AT Setpoint COLR-K1C30, Revision 3 Page 17 of 17

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