HNP-03-075, Cycle 12 Core Operating Limits Report

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Cycle 12 Core Operating Limits Report
ML031900078
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 07/01/2003
From: Caves J
Progress Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-03-075
Download: ML031900078 (17)
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Text

Progress Energy SERIAL: HNP-03-075 JUL 0 1 2003 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50400/LICENSE NO. NPF-63 CYCLE 12 CORE OPERATING LIMITS REPORT Ladies and Gentlemen:

In accordance with Technical Specifications CTS) 6.9.1.6.4, Progress Energy Carolinas, Inc.

hereby submits the Harris Nuclear Plant (HNP) Cycle 12 Core Operating Limits Report (COLR).

This COLR revision incorporates: (1) changes necessary as a result of Cycle 12 core changes, and (2) changes required to update the COLR methodology references as a result of License Amendment 114. provides a summary of the COLR changes. Attachment 2 contains a copy of the Cycle 12 COLR.

Please refer any questions regarding this submittal to myself at (919) 362-3137.

Sincerely, John Supervisor Licensing / Regulatory Programs Harris Nuclear Plant RTG/rtg Attachments:

1. Summary of Cycle 12 COLR Changes
2. Copy of the Cycle 12 COLR c:

NRC Senior Resident Inspector Mr. C. P. Patel, NRC Project Manager Mr. L. A. Reyes, NRC Regional Administrator Progress Energy Carlinas, Inc.

Harris Nuclear Plant P.O. Box 165 New Hill, NC 27562 to SERIAL: HNP-03-075 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-4001LICENSE NO. NPF-63 CYCLE 12 CORE OPERATING LIMITS REPORT

SUMMARY

OF CYCLE 12 COLR REVISIONS Section Title 1.0 2.2 2.3 2.4 2.6 2.7 2.8 3.0.2 3.0.3 3.0.9 3.0.10 3.0.11 Description of Change Revised title throughout Attachment 9 from Cycle 11 to Cycle 12 Revised from Cycle 11 to Cycle 12 Item 2: Change -42.7 pcnV/F to -42.6 pcmPF Changed fully withdrawn rod position from 231 to 225 Changed fully withdrawn rod position from 231 to 225 Placed items in outline format and added the words "The FQ(Z) Limit as referenced in TS 3.2.2 is:" to item 1

  • re-outlined items a., b. and c.,
  • moved previous item c. to under new Item 2.,
  • deleted words "for SPC fuel" from item b.,
  • changed new Item 2 value from 20520 MWD/MTU to 20936 MWD/MTU Deleted words "for SPC fuel" from items b. and c.

Changed boron concentration from 2202 to 2261 Changed "April" to "May" at end of first paragraph Added ", September 1983" to end of first paragraph Added ", February 1994" to end of first paragraph Added ", March 1994" to end of first paragraph Revised first paragraph to add dates for the 2 documents listed Reason for Change (see Notes) 1 1

1 1

1 1

1 1

2 2

2 2

2 Al-i of 2 to SERIAL: HNP-03-075 3.0.13 Added methodology EMF-2328 (A) 2 (New) 3.0.14 Created new Mechanical Methodologies section with 2

(New) methodologies from page 73 section 3.0.6.

Moved items between pages 73 and 74 to accommodate changes. Added ", and Letter, R. A. Copeland (SPC) to R. C.

Jones (USNRC), RAC: 050: 91, dated May 13, 1992" to fifth paragraph Figure 1 Changed Figure 1 to reflect the new Cycle 12 information 1

Figure 2 Changed Figure 2 to reflect the new rod park position of 225 1

steps for Cycle 12 Figure 4 Changed Figure 4 to reflect the new Cycle 12 information 1

Figure 5 Changed Figure 5 to reflect the V(Z) curve for Cycle 12 1

operation up to 16000 MWD/MTU Figure 6 Changed Figure 6 to reflect the V(Z) curve for Cycle 12 1

operation for burnups from 16000 MWDIMTrU through 20936 MWDIMTU Notes:

1. Revised for Cycle 12 operation.
2. Revised per License Amendment 114 concerning COLR methodology references.

A1-2of2 to SERIAL: HNP-03-075 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 CYCLE 12 CORE OPERATING LIMITS REPORT to HNP Procedure PLP-106.

"Technical Specification Equipment List Program and Core Operating Limits Report." Rev. 32 Page A2-1 of 14 Sheet 1 of 13 Harris Unit 1 Cycle 12 Core Operating Limits Report -

Rev. 0 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report COLR) for Shearon Harris Unit 1 Cycle 12 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 -

FQ(Z) 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor -

Fx 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 Temperature Coefficient (Specification 3/4.1.1.3)

1.

The Moderator Temperature Coefficient MTC) limits are:

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

+5.0 pm/*F for power levels up to 70% RTP with a linear ramp to 0 pcm/OF at 100% RTP.

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

-50 pcm/ 0 F.

PLP-106 Rev. 32 Page 70 of 85 Sheet 2 of 13 Harris Unit 1 Cycle 12 Core Operating Limits Report -

Rev. 0 2.2 Moderator Temperature Coefficient (Specification 3/4.1.1.3) (continued)

2.

The TC Surveillance limit is:

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

-42.6 pcm/0 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 225 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 225 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 -

FQ(Z) (Specification 3/4.2.2)

1.

The F(Z) Limit as referenced in TS 3.2.2 is:

Fo(Z)

FTP

  • K(Z)/P for P > 0.5 Fo(Z)

F

  • K(Z)/0.5 for P

0.5 where

a.

P = THERMAL POWER/RATED THERMAL POWER

b.

FQRTP 2.41

c.

K(Z) = the normalized F(Z) as a function of core height, as specified in Figure 4.

2.

V(Z) Curves versus core height for PDC-3 Operation, as used in T.S.

4.2.2, are specified in Figures 5 and 6. The first V(Z) curve (Figure 5) is valid for Cycle 12 burnups from 0 up to but not including 16000 MWD/MTU.

The second V(Z) curve (Figure 6) is valid for Cycle 12 burnups greater than or equal to 16000 WD/MTU to a maximum cycle energy of 20936 MWD/MTU.

PLP-106 Rev. 32 Page 71 of 85 Sheet 3 of 13 Harris Unit 1 Cycle 12 Core Operating Limits Report -

Rev. 0 2.7 Nuclear Enthalpy Rise Hot Channel Factor -

F (Specification 3/4.2.3)

FH FOP * (1 + PFm * (1 -

P))

where:

a. P = THERMAL POWER/RATED THERMAL POWER
b.

FrP

= Fm Limit at RATED THERMAL POWER = 1.66

c.

PF

= Power Factor Multiplier for F

= 0.35 F

= Enthalpy rise hot channel factor obtained by using the movable incore detectors to obtain a power distribution map, with the measured value of the nuclear enthalpy rise hot channel factor (Fwr) increased by an allowance of 4%

to account for measurement uncertainty.

2.8 Boron Concentration for Refueling Operations Specification 3/4.9.1.a)

Through the end of Cycle 12, the boron concentration required to maintain Keft less than or equal to.95 is equal to 2261 ppm.

Boron concentration must be maintained greater than or equal to 2261 ppm during refueling operations.

3.0 METHODOLOGY REFERENCES

1.

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).

2.

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, May 1992.

(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).

3.

XN-NF-82-21(A), Revision 1, Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations,' Exxon Nuclear Company, Richland, WA 99352, September 1983.

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

PLP-106 Rev. 32 Page 72 of 85 Sheet 4 of 13 Harris Unit 1 Cycle 12 Core Operating Limits Report - Rev. 0 3.0 METHODOLOGY REFERENCES (continued)

4.

XN-75-32(A), Supplements 1, 2, 3, and 4,

'Computational Procedure for Evaluating Fuel Rod Bowing,' Exxon 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).

5.

EMF-84-093(A), Revision 1, Steamline Break Methodology for PWRs,"

Siemens Power Corporation, February 1999.

(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).

6.

EMF-2087(A), Revision 0, SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications,' Siemens Power Corporation, June 1999.

(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).

7.

XN-NF-78-44(A), 'A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors,* Exxon Nuclear Company, Richland, WA 99352, October 1983.

(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).

8.

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,' Advanced Nuclear Fuels Corporation, Richland, WA 99352, October 1990.

(Methodology for Specification 3.2.1 -

Axial Flux Difference, and 3.2.2 -

Heat Flux Hot Channel Factor).

9.

EMF-92-081(A), and Supplement 1, Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors,' Siemens Power Corporation, Richland, WA 99352, February 1994.

(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).

10.

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, March 1994.

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

11.

XN-NF-82-49(A), Revision 1, April 1989 and XN-NF-82-49(P), Revision 1, Supplement 1, December 1994, 'Exxon Nuclear Company Evaluation Model EXEM PWR Small Break Model,' 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).

PLP-106 Rev. 32 Page 73 of 85 Sheet 5 of 13 Harris Unit 1 Cycle 12 Core Operating Limits Report -

Rev. 0 3.0 METHODOLOGY REFERENCES (continued)

12.

EMF-96-029(A),

Volumes 1 and 2, Reactor Analysis Systems for PWRs, Volume 1 - Methodology Description, Volume 2 - Benchmarking Results,'

Siemens Power Corporation, January 1997.

(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).

13.

EMF-2328 (A), Revision 0, PWR Small Break LOCA Evaluation Model, S-RELAPS Based,' Siemens Power Corporation, March 2001 (Methodology for Specification 3.2.1 -

Axial Flux Difference, and 3.2.2 - Heat Flux Hot Channel Factor), and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

14.

Mechanical Design Methodologies XN-NF-81-58(A), Revision 2 and Supplements 1 and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model,' Exxon Nuclear Company, March 1984.

ANF-81-58(A), Revision 2 and Supplements 3 and 4, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model,' Advanced Nuclear Fuels Corporation, June 1990.

XN-NF-82-06(A), Revision 1 and Supplements 2, 4, and 5, Qualification of Exxon Nuclear Fuel for Extended Burnup (PWR),' Exxon Nuclear Company, October 1986.

ANF-88-133(A), and Supplement 1, 'Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 GWd/MTU,5 Advanced Nuclear Fuels Corporation, December 1991.

XN-NF-85-92(A),

Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, November 1986, and letter, R. A. Copeland (SPC) to R. C. Jones (USNRC),

RAC: 050: 91, dated May 13, 1992.

EMF-92-116(A), Revision 0, 'Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation, February 1999.

(Methodologies 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. 3 2 Page 74 of 85 Sheet 6 of 13 Harris Unit 1 Cycle 12 Core Operating Limits Report -

Rev. 0 4.0 OTHER REQUIREMENTS 4.1 Movable Incore Detection System

1.

Operability: The Movable Incore Detection System shall be OPERABLE with:

R

a.

At least 38 detector thimbles at the 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),

b.

A minimum of 38 detector thimbles for the remainder of the operating cycle,

c.

A minimum of two detector thimbles per core quadrant, and

d.

Sufficient movable detectors, drive, and readout equipment to map these thimbles.

2.

Applicability: 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 and FQ(Z)

3.

Surveillance Requirements: 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 F and F(Z)

4.

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 F(Z) or FH, 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. 32 Page 75 of 85 Sheet 7 of 13 Harris Unit 1 Cycle 12 Core Operating Limits Report - Rev. 0 4.0 OTHER REQUIREMENTS (continued)

R

5.

Evaluation Requirements 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:

a.

How an inadvertent loading of a fuel assembly into an improper location will be detected,

b.

How the validity of the tilt estimates will be ensured,

c.

How adequate core coverage will be maintained,

d.

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 factor, radial peaking factor and quadrant power tilt factor meet Technical Specification limits, and

e.

How the Movable Incore Detection System will be restored to full (or nearly full) service before the beginning of each cycle.

PLP-106 Rev. 32 Page 76 of 85 Sheet 8 of 13 Harris Unit 1 Cycle 12 Core Operating Limits Report -

Rev. 0 Figure 1 Shutdown argin Versus RCS Boron Concentration Modes 3, 4, and 5/Drained Applicable to Mode 4, with or without RCPs in operation a4m 70W 0003 E~00 IOP MD

--- I

_E-UOE

) 50,' 00e 00 lOW a

0 400 800 12 o0 2000 2400 RequIred RCS Boron Concentration pm) 200 PLP-106 Rev. 32 Page 77 of 85 Sheet 9 of 13 Harris Unit 1 Cycle 12 Core Operating Limits Report - Rev. 0 Figure 2 Rod Group Insertion Limits Versus Thermal Power (Three-Loop Operation) 240 220 200 180 E 140 120 lo0g o0 XEso Zt

-2 La 0o (10,85 m

i~~~~~~~

I_

_T_ _

- Ba k

_ ____ -vr---

._.w

/ : w

's _ w

_~~~-.0

^ _ _

40 20 p

0 10 20 30 40 60 0

70 0

Power X (Flly withdrawn elO be 225 tepa)

Note:

Control Banks A and rB mst be wNhdrawn from the core prior to power operation so IW0 PLP-106 Rev. 32 Page 78 of 85 Sheet 10 of 13 Harris Unit 1 Cycle 12 Core Operating Limits Report -

Rev. 0 Figure 3 Axial Flux Difference TA-its as a Function of Rated Thermal Power 120 110 100 90 t

o j70 P

60 o

0 L30 20 10 la

~~~~~~~~~~~.

UlYC:CEPT8BIE

  • /

.. L L

-50

-40

-30

-20

-10 0

10 20 30 40 AXIAL FLUX DFFERENCE (

DELTA-1)

(DEVLATION ROM TARGET AD)

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. 3 2 Page 79 of 85 Sheet 11 of 13 Harris Unit 1 Cycle 12 Core Operating Limits Report -

Rev. 0 Figure K(Z) - Local Axial Penalty Function for FQ(Z)

L-OA-Us----X

0.

Li3 0

1 2

a 4

a 6

7 Core HeIght (Feet) a 10 11 12 PLP-106 Rev. 32 Page 80 of 85 Sheet 12 of 13 Harris Unit 1 Cycle 12 Core Operating Limits Report -

Rev. 0 Figure 5 V(Z) Versus Core Height 1.25 1225 1.2 1.175 1.15

% 1.125 1.1 1.075 d~t1111111 t

.2.1ttI 22-L

-..ii~i

+/-L.. 1.t. J-~ILL

-i¶i?~T::I-t~t-itttI7:Li

i t I

Heigft

  • 0.000 1.000
  • 0.200 1.000
  • 0.400 1.000
  • 0.600 1.000
  • 0.800 1.000
  • 1.000 1000
  • 1.200 100
  • 1.400 1.000
  • 1.600 1.000 1300 1.183 2M0 1.175 2.200 1.167 2.400 1.159 2.600 1.152 2J00 1.144 3.000 1.136 3.200 1.128 3.400 1.120 3W600 1.118 3300 1.120 4.000 1.122 4.200 1.124 4.400 1.125 4.600 1.127 4S00 1.130 5.000 1.134 5.200 1.139 5.400 1.144 5.600 1.154 5.800 1.162 6.000 1.168 6.200 1.172 6.400 1.174 6.600 1.175 6.00 1.174 7.000 1.172 7200 1.171 7.400 1.169 7.600 1.166 7300 1.161 6n0 1.154 8.200 1.147 6400 1.141 8.600 1.135 800 1.125 900 1.116 9.200 1.111 9.400 1.110 9.600 1.113 9.800 1.115 10.000 1.116 10.200 1.116 10.40 1.000 10.600 1.000 10.800 1.000 11.000 1.000 11200 1.000 11.400 1.000 11.600 1.000 11100 1.000 12.000 1.000 102S O

1 2

3 4

5 6

7 a

Core Height (Feet)

S 10 11 12

(Figure 5) is valid for Cycle 12 burnups from 0 up to but not including 16000 WD/MTU.

PLP-106 Rev. 32 Page 81 of 85 Sheet 13 of 13 Harris Unit 1 Cycle 12 Core Operating Limits Report -

Rev. 0 Figure 6 V(Z) Versus Core Height 1.3 1m7 1.25 1.22S 1.2 1.175 P

1.15 1.125 1.1

-I T

t [ -

ILl: ;EEEEEITEEEIBFI: I Ft

-I--- ii-



xliii

>X B

B A

A zz:zzz.zz....

Height Leen V

  • 0.000 1.000
  • 0200 1.000 0.400 1.000
  • 0.600 1.000
  • 0.800 1.000
  • 1.000 1.000
  • 1.200 1.000 1.400 1.000
  • 1.600 1.000 1300 1.196 2.000 1.186 2.200 1.176 2.400 1.165 2.600 1.153 2800 1.141 3.000 1.132 3.200 1.126 3.400 1.122 3.600 1.128 3.800 1.136 4.000 1.143 4.200 1.149 4.400 1.155 4.600 1.161 4.800 1.169 5.000 1.176 5.200 1.185 5.400 1.198 5.600 1.208

,8.00 1.215 6.OW 1.220 6.200 1.223 6.400 1.224 6.600 1.222 6.800 1.218 7.000 1213 7.200 1.207 7A00 1.203 7.600 1.200 700 1.196 8.000 1.189 8.200 1.180 8.400 1.171 8.600 1.160 8.800 1.148 9.000 1.134 0.200 1.120 9.400 1.114 9.600 1.133 9.800 1.153 10.000 1.174 10.200 1.195 10.400 1.000

  • 10.600 1.000 10.800 1.000
  • 11.000 1.000 11.200 1.000
  • 11.400 1.000
  • 11.600 1.000
  • 11.800 1.000

'12.000 1.000 l.OS tIJ 1.

0 1

2 3

4 5

6 7

a 0

Core Height (Feet) 10 11 12 Top and bottom 15% excluded as per Technical Specification 4.2.2.2.

(Figure 6) Is valid for Cycle 12 bumups greater than or equal to 16000 MWDIMTU to a maximum cycle energy of 20936 MWD/MTU.

PLP-106 Rev 32 Page 82 of 85

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