ML092870375

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Cycle 30 Core Operating Limits Report
ML092870375
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 10/06/2009
From: Wilson M
Dominion Energy Kewaunee
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
09-600
Download: ML092870375 (20)
v • d • e


Text

Dominion Energy Kewaunee, Inc.

N490 Hwy 42, Kewaunee, WI 54216 -'Y D Web Address: www.dom.com OCT: 0 62009 ATTN: Document Control Desk Serial No.09-600 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 30 CORE OPERATING LIMITS REPORT Pursuant to Kewaunee Power Station (KPS) Technical Specification (TS) 6.9.a.4.D, enclosed is a copy of the KPS Technical Requirements Manual Section 2.1, Kewaunee Power Station Core Operating Limits Report Cycle 30, 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, Mich~el J. Wilson Director Safety and Licensing Kewaunee Power Station Commitments made by this letter: NONE Enclosure

1. KPS Technical Requirements Manual Section 2.1, Kewaunee Power Station Core Operating Limits Report Cycle 30, Revision 0.

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Serial No.09-600 Page 2 of 2 cc: Regional Administrator, Region III U. S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 Mr. P. S. Tam Sr. 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

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

CYCLE 30 REVISION 0 Approved AP C Chairman' ChairmanDfe Mg.

Table of Contents Section Title Page

1.0 INTRODUCTION

.......................................................................................................... 1 2.0 OPERATING LIM ITS .................................................................................................. 2 2.1 Reactor Core Safety Limits ......................................................................... 2 2.2 Shutdown Margin (SDM) ................................................................................. 2 2.3 Moderator Tem perature Coefficient ................................................................ 2 2.4 Shutdown Bank Insertion Limit ......................................................................... 2 2.5 Control Bank Insertion Lim its ........................................................................... 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 Overtem perature AT Setpoint ......................................................................... 4 2.10 Overpower AT Setpoint ...................................... 5 2.11 RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits .......................................................................... 5 2.12 Refueling Boron Concentration ...................................................................... 5

3.0 REFERENCES

........................................................................................................... 6

I List of Figures [ . . . . . -l - I Figure Title Page

1. Reactor Core Safety Limits Curve (1772 MWt) ............................................................. 8
2. Required Shutdown Reactivity vs. Boron Concentration ............................................. 9
3. Hot Channel Factor Normalized Operating Envelope (K(z)) ....................................... 10
4. Control Bank Insertion Limits ...................................................................................... 11
5. N(Z) Values (Top and Bottom 9% excluded) ............................................................ 12
6. Penalty Factor, Fp, for FQN(Z) .................................................................................. 14
7. Axial Flux Difference Target Band ............................................................................. 15 ii

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 30

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Kewaunee Unit 1 Cycle 30 has been prepared in accordance with the requirements of Kewaunee Technical Specification 6.9.a.4.

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 Reactor Core Safety Limit 2.2 3.10.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 3.10.b.5 (FQN(Z))

3.10.b.6.C.i 2.7 3.10.b.1.B Nuclear Enthalpy Rise Hot Channel Factor Limits (FAHlN) 2.8 3.10.b.8 Axial Flux Difference (AFD) Target Band 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 3.10.1 Departure from Nucleate Boiling (DNB) 3.10.m.1 Limits 2.12 3.8.a.5 Refueling Boron Concentration Figure 1 2.1 Reactor Core Safety Limits (1772 MWt)

Figure 2 3.10.a Required Shutdown Margin Figure 3 K(Z) Normalized Operating Envelope Figure 4 3.10.d.2 Control Bank Insertion Limits Figure 5 N(Z) Values (Top and Bottom 9% excluded)

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

Figure 7 3.10.b.8.A Axial Flux Difference Envelope Cycle 30 Page 1 of 15 Revision 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 30 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 6.9.a.4.

2.1 Reactor Core Safety Limits (TS 2.1.a)

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 3.10.a)

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 (TS 3.1 .f.3) 2.3.1 When the reactor is critical and < 60% of 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 pcrn/°F for 95% of the cycle time at full power.

2.4 Shutdown Bank Insertion Limits (TS 3.10.d. 1)

The shutdown rods shall be fully withdrawn (229 steps) when the reactor is critical or approaching criticality.

2.5 Control Bank Insertion Limits (TS 3.1O.d.2)

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

Cycle 30 Page 2 of 15 Revision 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 30 2.6 Nuclear Heat Flux Hot Channel Factor (FnN(Z)) (TS 3.10.b.l.A, 3.10.b.5, and 3.10.b.6.C.i) 2.6.1 FQN(Z) Limits for Fuel FQN (Z)* 1.03 *1.05*_< CFQ *K(Z)for P > 0.5 [422 V+]

P FQN (Z)* 1.03 *1.05*< CFQ

  • K(Z)forP *_0.5 [422 V+]

0.5 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 CFQ = 2.50 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)* 1.03 *1.05

  • N(Z)* F, <C _FQ
  • K(Z) [422 V+]

Pp 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 CFQ equals 2.50 Fp is the penalty factor described in 3.6.3 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.

FQN(Z) is a measured FQ distribution obtained during the target flux determination The N(z) decks are generatedfor normal operationflux maps that are typically taken atfull power, ARO. AdditionalN(z) decks may be generated,if necessary, consistent with the methodology described in Reference 1.

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 COLR Figure 6 shall be used for TS 3.10.b.6.C.i.

The penalty factor for all bumups outside the range of Figure 6 shall be 1.02.

Cycle 30 Page 3 of 15 Revision 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 30 2.7 Nuclear Enthalpy Rise Hot Channel Factor Limits (FAnN) (TS 3.1 O.b. 1.B)

F *"1.04*<CFDH*[1+ PFDH(1-P)] [422 V+]

Where:

P is the fraction of full power at which the core is OPERATING CFDH = 1.70 PFDH = 0.3 2.8 Axial Flux Difference (AFD) Target Band (TS 3.1O.b.8)

The Axial Flux Difference (AFD) acceptable operation limits are provided in COLR Figure 7.

2.9 Overtemperature AT Setpoint (TS 2.3.a.3.A)

AT < ATo *I -KX2 k *(r- r')*1 1+7rl_

+-C "g2S

+K 3 (P_ P') f-(A-[)

ATO = Indicated AT at RATED POWER, %

T = Average temperature, OF T' < 573.0 OF P = Pressurizer Pressure, psig P' = 2235 psig Ki <5 1.195 K2 = 0.015/ 0 F K3 = 0.00072/psig Tj > 30 seconds T2 5 4 seconds f1 (Al) = 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 %, fl(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.

Cycle 30 Page 4 of 15 Revision 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 30 2.10 Overpower AT Setpoint (TS 2.3.a.3.B)

A:AT0 K - K5

  • T3s1s*+ 1 T -K 6 *(T-T') -f 2 (AI)j 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 K6 >_ 0.00103/°F for T > T'

> 0 for T <T' T3 > 10 seconds f 2(AI) = 0 for all Al 2.11 RCS Pressure. Temperature and Flow Departure from Nucleate Boiling (DNB) Limits (TS 3.10.k, 3.10.1, and 3.1O.m.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 Refueling Boron Concentration (TS 3.8.a.5)

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.

Cycle 30 Page 5 of 15 Revision 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 30 3.0 References

1. Topical Report DOM-NAF-5-A, "Application of Dominion Nuclear Core Design and Safety Analysis Methods to the Kewaunee Power Station (KPS)," dated July, 2006.

Methodology for:

TS 2.1 - Reactor Core Safety Limits; TS 3.10.a - Shutdown Margin; TS 3.1. f. 3 - Moderator Temperature Coefficient; TS 3. 1O.d. 1 - Shutdown Bank Insertion Limits; TS 3. 10.d.2 - Control Bank Insertion Limits; TS 3.10.b. 1.A, 3.10.b.5, and 3.10.b.6.C.i - Heat Flux Hot Channel Factor Limits (FQN(Z));

TS 3.1O.b. 1.B Nuclear Enthalpy Rise Hot Channel Factor Limits (FAHN);

TS 3.10.b.8 - Axial Flux Difference (AFD) Target Band; TS 3.10.k, 3.10.1 and 3.10.m. 1 - RCS Pressure, Temperature and Flow Departure from Nucleate Boiling (DNB) Limits; TS 3.8.a.5 - Refueling Boron Concentration

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

Methodology for:

TS 3. 10.a - Shutdown Margin

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

Methodology for:

TS 3. 10.b. 1.A, 3. 10.b.5, and 3. 10.b.6.C.i - Heat Flux Hot Channel Factor Limits (FQN(Z))

TS 3. 10.b. 1.B Nuclear Enthalpy Rise Hot Channel Factor Limits (FAHN);

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

Methodology for:

TS 3.10.b.l.A, 3.10.b.5, and 3.10.b.6.C.i - Heat Flux Hot Channel Factor Limits (FQN(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.

Methodology for:

TS 3. 10.b. 1.A, 3. 10.b.5, and 3. 10.b.6.C.i - Heat Flux Hot Channel Factor Limits (FQN(Z))

Cycle 30 Page 6 of 15 Revision 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 30

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

(Westinghouse Proprietary)

Methodology for:

TS 2.1 - Reactor Core Safety Limits; TS 3.1 .f.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 2.3.a.3.A - Overtemperature AT Setpoint; TS 2.3.a.3.B - 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, Rev. 1, October 1999.

Methodology for:

TS 3. 10.b. 1 .A, 3. 10.b.5, and 3. 10.b.6.C.i - Heat Flux Hot Channel Factor Limits (FQN(Z))

TS 3.10.b. 1.B Nuclear Enthalpy Rise Hot Channel Factor Limits (FAHN);

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

(Westinghouse Proprietary)

Methodology for:

TS 3.10.b.l.A, 3.10.b.5, and 3.10.b.6.C.i - Heat Flux Hot Channel Factor Limits (FQN(Z))

10. CENP-397-P-A, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology," Rev. 1, May 2000.

Methodology for:

TS 2.3.a.3.A - Overtemperature AT Setpoint; TS 2.3.a.3.B - Overpower AT Setpoint Cycle 30 Page 7 of 15 Revision 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 30 Figure 1 Reactor Core Safety Limits Curve (1772 Mwt)

(Cores Containing 422V+ fuel)

(TS 2.1.a) 665 Unacceptable 64 Operation

- 645 a)a 0.

0 1862000 psia C.)

L- 625 0

5625 6052 06 8 02 Core Power (percent of 1772 MWt)

Cycle 30 Page 8 of 15 Revision 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 30 Figure 2 Required Shutdown Reactivity vs. Boron Concentration (TS 3.10.a) 1700 1600 1554 1500 1400 1300 1200 1100

> 1000 r 900

"* 800 2!

.5 700 600 500 400 300 200 100 0

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

Cycle 30 Page 9 of 15 Revision 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 30 Figure 3 Hot Channel Factor Normalized Operating Envelope (K(Z))

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

0.6 0.5 0.4 0.3 0.2 0.1 0

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

Cycle 30 Page 10 of 15 Revision 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 30 Figure 4 Control Bank Insertion Limits (TS 3.10.d.2)

Fully w/d Position 229 steps 240 S (14.34%, 229) /_ (66.25%, 229) 220 BANK B 200 (0.0%,194) (100.0%, 185) 180 160 e-

.* 140

____ BANK C w 120 0.

  • 100 BANK D (0.0%, 68) 60 40 20 (23.8%, 0) 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.

Cycle 30 Page 11 of 15 Revision 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 30 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 XXXXX XXXXX to EOC (FEET) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 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 18 8.6 19 8.4 The N(z) data will be provided 20 8.2 following shutdown of Cycle 29.

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 36 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 48 2.6 49 2.4 50 2.2 Cycle 30 Page 12 of 15 Revision 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 30 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 XXXXX XXXXX to EOC (FEET) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 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%

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

Cycle 30 Page 13 of 15 Revision 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 30 Figure 6 Penalty Factor, Fp, for FQN(Z)

Cycle Burnup Penalty Factor (MWD/MTU) Fp 150 1.02 18,700 1.02 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 1.02. Refer to TS 3.10.b.6.C.i.

Cycle 30 Page 14 of 15 Revision 0

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 30 Figure 7 Axial Flux Difference Target Band (3.10.b.8.A) 110

(-9.0, 100.0) (6.0, 100.0) 100 Unacceptable Unacceptable Operation Operation 90 0

0 E

L-(D Acceptable Operation (D70 z0 60 50

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

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

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.

Cycle 30 Page 15 of 15 Revision 0

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