ML110810071

Core Operating Limits Report Cycle 31, Revision 0

ML110810071
Person / Time
Site:	Kewaunee
Issue date:	03/10/2011
From:	Wilson M Dominion Energy Kewaunee
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
11-116
Download: ML110810071 (17)

Text

Dominion Energy Kewaunee, Inc.

N490 Hwy 42, Kewaunee, WI 54216 iDominion Web Address: www.dom.com MAR 10 2011 ATTN: Document Control Desk Serial No.11-116 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 CORE OPERATING LIMITS REPORT CYCLE 31 REVISION 0 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 0.

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

Jack Gadzala at 920-388-8604.

Very truly yours, Mic el 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 0.

A-(:)C:) I

Serial No.11-116 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 I Cycle 31 Revision 0 February 2011 Page i of 15

1.0 IIqTRODUCTION This Core Operating Limits Report (COLR) for Kewaunee Unit 1 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:

KPS Technical Description 7ýý 2.1 Specification 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 (FNH) 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 Page 2-o9 15

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 Lirits (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 peni.

2.3 Moderator Temverature Coefficient (MTC) (TS 3.1.3) 2.3.1 When the reactor is critical and !5 60% of RATED THERMAL POWER, the moderator temperature coefficient shall be f5 5.0 pcm/°F. 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/0 F (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 XX pcmf°F (lower limit)-

MTC surveillance limits are:

i) The 300 ppmi/ARO/RTP-MTC should be less negative than or equal to XX pcmI0 F. 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 XX pcmI'F.

MTC EOC li-mits will be provided following shutdown of Cycle 30.

Page 3 of 15

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 cnticality.

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 0 Z) (TS 3.2.1) 2.6.1 F (Z) Limits for Fuel

( ) **1.03 F#Q(Z) . 3 1. s <CFQ

• 1.05 C

• K(Z)

P for P > 0.5 [422V+]

FfN Z 1 . 3 *1 0 < cFQ Q'(Z)

• 1.03

• 1.0:5 -~

• K(Z) forP _50.5 [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 FQj(Z) is a measured FQ distribution obtained during the target flux determination 2.6.2 F(T(Z) Limits for Fuel FP (Z)

• 1.03

• 1.05

• N(Z)

• Fp <!IfP

-- p

• K(Z) [422VF]

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.

FQ' (Z) is a measured FQ distribution obtained during the target flux determination The N(z) decks are generatedfor normal operationflux maps thaotaretypically taken atfidl power, ARO.

Additional N(z) decksmay be generated, f necessary, consistent with the methodology described in Reference 7.

Page 4. of !5

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.

2.7 Nuclear Enthalpy.Rise Hot Channel Factor LFp ) (TS 3.2.2)

FI!>

• 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 Setjoint (TS 3.3.1 Function 6)

-AT:ýATo* + K 3 *(P-P*)-f1 (M AT0 = Indicated AT at RATED THERMAL POWER, %

s = Laplace transform operator, sec-1 .

T = Average temperature, OF T') N 573.0 OF P = Pressurizer Pressure, psig P, > 2235 psig K,

• 1.195 K2 - 0.015/OF K3 Ž 0.00072/psig Tj Ž 30 seconds T2 4 seconds fl(AI) = An even fun-ction 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(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 THERMAL POWER.

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

Page 5 of 15

2.10 Overpower AT Setpoint (TS 3.3.1 Function 7)

AT* ATO* K4 -K 5

• T3s *T-K6 * (T- T') - f2 (AI)

ATo = Indicated AT at RATED THERMAL POWER, %

s = Laplace transform operator, sec-1.

T = Average temperature, OF T < 573.0 OF K4 - 1.095 K5 Ž> 0.0275/1F for increasing T

Ž 0 for decreasing T K6 Ž 0.00103/°F for T > T'

Ž0 forT<T'

"' Ž 10 seconds f2(AJ) 0 for all AI 2.11 RCS Pressure, Temperature and Flow Departure from Nucleate Boiling (D2NB) 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 'F for computer indication.

2.11.2 During steady state power operation, pressurizer pressure shall be Ž> 2217 psig for control board indication or Ž2219 psig for computer indication.

2.11.3 During steady state power operation, reactor coolant total flow rate shall be _Ž 186,000 gpm.

2.12 Boron Concentration (iRefueling 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.

Page 6 of 15

Figure 1 (TS 2.1.1)

Reactor Core Safety Limits Curve (1772 Mwt)

(Cores Containing 422V+ fuel) 665 i-0 645 E

• 625

' 605 0

.0 0

w 565 0 20 40 60 80 1100 120 Core Power (percent of 1772 MWt)

Page 7 of 15

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

Hot Channel Factor DELETED Page 8 o*i 15

Figuree4 Control Bank Insertion Limits (TS 3.1.6)

Fully W/D Position 224 Steps 240 220 200 180 160 140

-o 120

0. 100 Q

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.

Page 9 of 15

Figure 5 N(Z) Values 1 NODE HEIGHT 0 to 1000 1000 to 3000 3000 to 5000 5000 to 7000 7000 to 9000 9000 to XXXX0 XXXXX to EOC (FEET) MWD/MTU MWD/MTU IV1WD/MTU MWD/MTU MWD/MTU MWD/MTU MWDIMTU Top 6 11.0 7 10.8 8 10.6 9 10.4 10 10.2 11 10.0 12 9.8 13 9.6 14 9.4 15 9.2 16 9.0 17 8.8 The N(z) data will be provided 18 8.6 following shutdown of Cycle 30.

19 8.4 20 8.2 21 8.0 22 7.8 23 7.6 Cycle Specific N(Z) Data 24 7.4 25 7.2 26 7.0 27 6.8 28 6.6 29 6.4 30 6.2 31 6.0 32 5.8 33 5.6 34 5.4 35 5.2 3G 5.0 37 4.8 38 4.6 39 4.4 40 4.2 41 4.0 42 3.8 43 3.6 44 3.4 45 3.2 46 3.0 47 2.8 43 2.6 49 2.4 50 2.2 Page 10 of 15

Figure 5 (continued)

N(Z) Values' 0 to 1000 1000 to 3000 3000 to 5000 5000 to 7000 7000 to 900D 9000 to X)OO( XXXXX.to EOC NODE HEIGHT MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU (FEET) 51 2.0 52 1.8 53 1.6 54 1.4 55 1.2 56 1.0 Bottom

1) Excludes top and bottom 9%

ARO.

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

Page 11 of 15

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

DELETED Page 12 of 15

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

(-9.0, 100.0) (6.0, 100.0) 100 Unacceptable Unacceptable Operation Operation 90 3:z O 80 0L Acceptable Operation 70 LU U 6

'-- 70 50

(-22.0, 50.0) (20.0, 50.0) 40

-40 -30 -20 -10 0 "10 20 30 40 AXIAL FLUX DIFFERENCE (% Delta-I)

Page 13 of15

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

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

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, 2001.

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 H1-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 (FANM);

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 Chanmel 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 (F0 (Z))

Page 14 of 15

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 (FAN);

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, "Improved 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 Page 15 fo15