ML18016A707

Rev 0 to Harris Unit 1 Cycle 9 Colr.

ML18016A707
Person / Time
Site:	Harris
Issue date:	11/03/1998
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18016A706	List: ML18016A705 ML18016A707
References
NUDOCS 9811100368
Download: ML18016A707 (13)

Text

Attachment 9 Sheet 1 of 12 Harris Unit 1 Cycle 9 Core Operating Limits Report - Rev. 0 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Shearon Harris Unit 1 Cycle 9 has been prepared in accordance with the requirements of Technical Specification 6.9.1.6.

The Technical Specifications affected by this report are listed below:

3/4.1.1.2 SHUTDOWN MARGIN - Modes 3, 4, and 5 3/4.1.1.3 Moderator Temperature Coefficient 3/4.1.3.5 Shutdown Rod Insertion Limit 3/4.1.3.6 Control Rod Insertion Limits 3/4.2.1 Axial Flux Difference 3/4.2.2 Heat Flux Hot Channel Factor - Fo(Z) 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor - Fzg 3/4.9.1.a Boron Concentration During Refueling Operations 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 NRC-approved methodologies specified in Technical Specification 6.9.1.6 and given in Section 3.0.

2.1 SHUTDOWN MARGIN - Modes 3, 4 and 5 (Specification 3/4.1.1.2)

The SHUTDOWN MARGIN versus RCS boron concentration - Modes 3, 4, and 5 is specified in Figure 1.

2.2 Moderator Tem erature Coefficient (Specification 3/4.1.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

The Positive MTC Limit (ARO/HZP) shall be less positive than

+5.0 pcm/OF for power levels up to 70't RTP with a linear ramp to 0 pcm/OF at 100% RTP.

The Negative MTC Limit (ARO/RTP) shall be less negative than

-45 pcm/ F.

98iii00368 98ii03 l PDR ADGCK 05000400 P P DR+

PLP-106 Rev.. 19 Page 70 of ()4

Attachment 9 Sheet 2 of 12 Harris Unit 1 Cycle 9 Core Operating Limits Report - Rev. 0 2.2 Moderator Tem erature Coefficient (Specification 3/4.1.1.3) (continued)

2. The MTC Surveillance limit is:

The 300 ppm/ARO/RTP-MTC should be less negative than or equal to

-37.8 pcm/~F.

where: ARO stands for All Rods Out HZP stands for Hot Zero THERMAL POWER RTP stands for RATED THERMAL POWER 2 .3 Shutdown Rod Insertion Limit (Specification 3/4 .1 .3 .5)

Fully withdrawn for all shutdown rods shall be 222 steps.

2.4 Control Rod Insertion Limit (Specification 3/4.1.3.6)

The control rod banks shall be limited in physical insertion as specified in Figure 2. Fully withdrawn for all control rods shall be 222 steps.

2.5 Axial Flux Difference (Specification 3/4.2.1)

The AXIAL FLUX DIFFERENCE (AFD) target band is specified in Figure 3.

2.6 Heat Flux Hot Channel Factor - Fo(Z) (Specification 3/4.2.2)

Fq(Z) S Fo"

• K(Z)/P for P > 0.5 Fo(Z) S F<>"

• K(Z)/0.5 for P 5 0.5 where: P = THERMAL POWER/RATED THERMAL POWER Fo~~ = 2.45 for LOPAR fuel Fq"~ = 2.52 for SPC fuel K(Z) is specified in Figure 4.

V(Z) Curve for PDC-3 Operation is specified in Figure 5. The V(Z) curve is sufficient to determine the PDC-3 V(Z) versus core height for Cycle 9 burnups through the end of full power reactivity plus a coastdown for a maximum cycle energy of 489 EFPDs.

PLP-106 Rev. 19 Page 71 of 84

Attachment 9 Sheet 3 of 12 Harris Unit 1 Cycle 9 Core Operating Limits Report - Rev. 0 2.7 Nuclear Enthal Rise Hot Channel Factor - Fm (Specification 3/4.2.3)

Fag S Fag " (1 + PFag * (1 - P))

where: P = THERMAL POWER/RATED THERMAL POWER

a. F~" = 1.62 for LOPAR fuel

b. Fm" = 1.73 for SPC fuel PF~ = 0.3 for LOPAR fuel

d. PF~ = 0.35 for SPC fuel 2.8 Boron Concentration for Refuelin 0 erations (Specification 3/4.9.1.a)

Through the end of Cycle 9, the boron concentration required to maintain K,ff less than or equal to .95 is equal to 2217 ppm. Boron concentration must be maintained greater than or equal to 2217 ppm during refueling operations.

3.0 METHODOLOGY REFERENCES XN-75-27(A), and Supplements 1, 2, 3, 4, and 5, "Exxon Nuclear Neutronics Design Methods for Pressurized Water Reactors, Exxon Nuclear Company, Richland, WA 99352.

(Methodology for Specification 3.1.1.2 - SHUTDOWN MARGIN - Modes 3, 4, and 5, 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor, and 3.9.1 Boron Concentration).

ANF-89-151(A), and Correspondence, ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events, Advanced Nuclear Fuels Corporation, Richland, WA 99352.

(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient. 3.1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

XN-NF-82-21(A), Revision 1, Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations,'xxon Nuclear Company, Richland, WA 99352.

(Methodology for Specification 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor) .

PLP-106 Rev. 19 Page 72 of 84

Attachment 9 Sheet 4 of 12 Harris Unit 1 Cycle 9 Core Operating Limits Report Rev. 0 3.0 METHODOLOGY REFERENCES (continued)

XN-75-32(A), Supplements 1, 2, 3, and 4, Computational Procedure for Evaluating Fuel Rod Bowing,'xxon Nuclear Company, Richland, WA 99352.

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

XN-NF-84-93(A), and Supplement 1, "Steamline Break Methodology for PWRs, Nuclear Company, Richland, WA 99352. 'xxon (Methodology for Specification 3.1.1.3 Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

EXEM PWR Large Break LOCA Evaluation Model as defined by XN-NF-82-20(A), Revision 1 and Supplements 1, 2, 3, and 4, Exxon Nuclear Company Evaluation Model EXEM/PWR ECCS Model Updates, Exxon Nuclear Company, Richland, WA 99352.

XN-NF-82-07(A), Revision 1, Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model, Exxon Nuclear 'Company, Richland, WA 99352.

XN-NF-81-58(A), Revision 2 and Supplements 1, 2, 3, and 4, RODEX2 Fuel Rod Thermal Response Evaluation Model,'xxon Nuclear Company, Richland, WA 99352.

XN-NF-85-16(A), Volume 1 and Supplements 1, 2, and 3, Volume 2, Revision 1 and Supplement 1, PWR 17x17 Fuel Cooling Test Program, Exxon Nuclear Company, Richland, WA 99352.

XN-NF-85-105(A), and Supplement 1, 'Scaling of FCTF Based Reflood Heat Transfer Correlation for Other Bundle Designs," Exxon Nuclear Company, Richland, WA 99352.

(Methodology for Specification 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor) .

XN-NF-78-44(A), A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors,'xxon Nuclear Company, Richland, WA 99352.

(Methodology for Specification 3.1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, and 3.2.2 - Heat Flux Hot Channel Factor).

PLP-106 Rev. 19 Page 73 of 84

Attachment 9 Sheet 5 of 12 Harris Unit 1 Cycle 9 Core Operating Limits Report Rev. 0 3.0 METHODOLOGY REFERENCES (continued)

ANF-88-054(A), PDC-3: Advanced Nuclear Fuels Corporation Power Distribution Control for Pressurized Water Reactors and Application of PDC-3 to H. B. Robinson Unit 2,'dvanced Nuclear Fuels Corporation, Richland, WA 99352.

(Methodology for Specification 3.2.1 - Axial Flux Difference, and 3.2.2 - Heat Flux Hot Channel Factor) .

WCAP-9272-P-A, 'WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY,'uly 1985 (W Proprietary) .

(Methodology for Specification 3.1.1.2 - SHUTDOWN MARGIN - Modes 3, 4, and 5, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Ri,se Hot Channel Factor).

10. WCAP-10266-P-A, Rev. 2, The 1981 Version of the WESTINGHOUSE ECCS EVALUATION MODEL USING THE BASH CODE, March 1987 (W Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor)

11. WCAP-11837-P-A, "EXTENSION OF METHODOLOGY FOR CALCULATING TRANSZTION CORE DNBR PENALTIES,anuary 1990 (W Proprietary).

(Methodology for Specification 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

12. EMF-92-081(A), and Supplement 1, 'Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors, Siemens Power Corporation, Richland, WA 99352.

(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor) .

13. EMF-92-153(A), and Supplement 1, 'HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel, Siemens Nuclear Power Corporation, Richland, WA 99352.

(Methodology for Specification 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor) .

XN-NF-82-49(A), Revision 1, and XN-NF-82-49(P), Revision 1, Supplement 1, Exxon Nuclear Company Evaluation Model EXEM PWR Small Break Model, Nuclear Company, Richland, WA 99352. 'xxon (Methodology for Specification 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

PLP-106 Rev. 19 Page 74 of 84

Attachment 9 Sheet 6 of 12 Harris Unit I Cycle 9 Core Operating Limits Report Rev. 0 4.0 OTHER RE UIREMENTS 4.1 Movable Incore Detection S stem

l. ~oerabilit: The Movable lncore Detection system shall be opERABLE with:

All the following at beginning of cycle (where the beginning of cycle is defined in this instance as a flux map determination that the core is loaded consistent with design):

i. At least 45 detector thimbles (90% of the total number),

ii. Either J-10 or L-14 locations, and iii. Either N-S, H-6, or J-7 locations A minimum of 38 detector thimbles for the remainder of the operating cycle,

c. A minimum of two detector thimbles per core quadrant, and Suf ficient movable detectors, drive, and readout equipment to map these thimbles.

A licabilit  : When the Movable Incore Detection System is used for:

a. Recalibration of the Excore Neutron Flux Detection System, or

b. Monitoring the QUADRANT POWER TILT RATIO, or

c. Measurement of Fm and Fq(Z)

Surveillance Re irements: The Movable Incore Detection System shall be demonstrated OPERABLE, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to use, by irradiating each detector used and determining the acceptability of its voltage curve when required for:

a. Recalibration of the Excore Neutron Flux Detection System, or

b. Monitoring the QUADRANT POWER TILT RATIO, or

c. Measurement of Fw and Fa(Z)

Bases The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the core. The OPERABILITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.

For the purpose of measuring Fo(Z) or Fm, a full incore flux map is used.

Quarter-core flux maps, as defined in WCAP-8648, June 1976, may be used in recalibration of the Excore Neutron Flux Detection System, and full incore flux maps or symmetric incore thimbles may be used for monitoring QUADRANT POWER TILT RATIO when one Power Range channel is inoperable.

PLP-106 Rev. 19 Page 75 of 84

Attachment 9 Sheet 7 of 12 Harris Unit 1 Cycle 9 Core Operating Limits Report - Rev. 0 4.0 OTHER RE UIREMENTS (continued)

Evaluation Re irements In order to change the requirements concerning the number and location of operable detectors, the NRC staff deems that a rigorous evaluation and justification is required. The following is a list of elements that must be part of a 50.59 determination and available for audit if the licensee wishes to change the requirements:

How an inadvertent loading of a fuel assembly into an improper location will be detected, How the validity of the tilt estimates will be ensured, How adequate core coverage will be maintained, How the measurement uncertainties will be assured and why the added uncertainties are adequate to guarantee that measured nuclear heat flux hot channel factor, nuclear enthalpy rise hot channel'actor, radial peaking factor and quadrant power factor meet Technical Specification limits, and tilt How the Movable Incore Detection System will be restored to full (or nearly full) service before the beginning of each cycle.

PLP-106 Rev. 19 Page 76 of 84

Attachment 9 Sheet 8 of 12 Harris Unit 1 Cycle 9 Core Operating Limits Report - Rev. 0 Figure 1 Shutdown Margin Versus RCS Boron Concentration Modes 3, 4, and 5/Drained

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PLP-106 Rev. 19 Page 77 of 84

Attachment 9 Sheet 9 of 12 Harris Unit 1 Cycle 9 Core Operating Limits Report - Rev. 0 Figure 2 Rod Group 1nsertion Limits Versus"Thermal Power (Three-Loop Operation) 240 (0.505,222) 220 (1,222) 200 BANK C ('I,186) 180 C

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60 40 20 (0,000) 0 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 FRACTION OF RATED THERMAL POWER (Fully withdrawn shall be 222 steps)

Note: Control Banks A and B must be withdrawn from the core prior to power operation.

PLP-106 Rev. 19 Page 78 of 84

Attachment 9 Sheet 10 of 12 Harris Unit 1 Cycle 9 Core Operating Limits Report - Rev. 0 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power 120

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Note: At power levels less than HFP, the deviation is applied to the target AFD appropriate to that power level. The target AFD varies linearly between the HFP target and zero at zero power.

PLP-106 Rev. 19 Page 79 of 84

Attachment 9 Sheet 11 of 12 Harris Unit 1 Cycle 9 Core Operating Limits Report Rev. 0 Figure 4 K(Z) - Local Axial Penalty Function for FQ(Z) 1.2

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PLP-106 Rev. 19 Page 80 of 84

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