ML23311A357
| ML23311A357 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 11/07/2023 |
| From: | Borgen T Northern States Power Company, Minnesota, Xcel Energy |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| L-Pl-23-030 | |
| Download: ML23311A357 (1) | |
Text
fl Xcel Energy 1717 Wa ko n a de Drive We lc h, MN 55089
November 7, 2023 L-Pl-23-030 TS 5.6.5.d
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Prairie Island Nuclear Generating Plant, Unit 2 Docket No. 50-306 Renewed Facility Operating License No. DPR-60
Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP)
Unit 2. Cycle 33. Revision 0
Pursuant to the requirements of Technical Specification 5.6.5.d, Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM "),
hereby submits the COLR for the PINGP Unit 2, Cycle 33, Revision 0. The COLR provides the cycle-specific values of the limits established using NRC approved methodologies such that the applicable limits of the plant safety analysis are me t.
If you have any questions about this submittal, please contact Carrie Seipp, Senior Regulatory Engineer, at 612-330-5576.
Summary of Commitments
This letter makes no new commitments and no revisions to existing commitments.
~$~_,--/~ G Timothy P. Borgen Plant Manager, Prairie Island Nuclear Gene rating Plant Northern States Power Company - Minnesota
Enclosure
cc: Administrator, Region Ill, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC State of Minnesota ENCLOSURE
PRAIRIE I SLAND NUCLEAR GENERATING P LANT CORE OPERATING LIMITS R EPORT UNIT 2 - CYCLE 3 3 REVISION 0
35 pages follow PRAIRIE ISLAND NUCLEAR GENERATING PLANT
Core Operating Limits Report
Record of Revision
Unit Cycle Revision Approval No. Date Remarks
2 13 0 3/22/90 Original Unit 2 Core Operating Limits Report, distributed with Technical Specification Revision 92.
1 14 0 3/22/90 Original Unit 1 Core Operating Limits Report, distributed with Technical Specification Revision 92.
1 7/27/90 Incorporated expanded V(z) curves.
2 9/27/90 Clarified rod insertion limit curve applicability.
3 2/11/91 Incorporated revised FQ of 2.45 as a result of NRC approval of Westinghouse Topical Report WCAP-10924-P-A, Volume 1, Addendum 4, October 1990.
2 14 0 - Not used.
1 9/27/90 Updated to Unit 2 Cycle 14, incorporated expanded V(z) curves and clarified rod insertion limit curve applicability.
2 2/11/91 Incorporated revised FQ of 2.45 as a result of NRC approval of Westinghouse Topical Report WCAP-10924-P-A, Volume 1, Addendum 4, October 1990.
1 15 0 6/25/91 Updated to Unit 1 Cycle 15.
2 15 0 3/9/92 Updated to Unit 2 Cycle 15 and clarified labeling of Figure 4. Clarified the actions to be taken if the nuclear enthalpy rise hot channel factor exceeds the Technical Specification limit.
1 16 0 12/28/92 Updated to Unit 1 Cycle 16, removed V(z) curves and replaced them with list of bounding V(z) values for three ranges of exposures.
2 16 0 12/8/93 Updated to Unit 2 Cycle 16. Removed the multiple V(z) curves and replaced them with a single figure with bounding V(z) curves for four ranges of exposures. Incorporated additional discussion related to V(z) and K(z).
Page 1 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT
Core Operating Limits Report
Record of Revision
Unit Cycle Revision Approval No. Date Remarks
2 16 1 11/3/94 The table containing the bounding V(z) values and Figure 2 updated to incorporate revised bounding V(z) values for the exposure range of 14-21.5 GWD/MTU. Figures 3 through 6 re-formatted.
1 17 0 6/17/94 Updated to Unit 1 Cycle 17. Removed the list of bounding V(z) values and replaced it with multiple V(z) curves. Incorporated additional discussion related to V(z) and K(z).
2 17 0 6/2/95 Updated to Unit 2 Cycle 17. Incorporated Table 1 and expanded Figure 2 with updated bounding V(z) values.
1 18 0 2/7/96 Updated to Unit 1 Cycle 18. Incorporated revised FH limitf.77.Iorporated Table 1 and updated Figureithevised boundi(z) vues.
2 0 27/ Uotycl18. ised FHlimo
- 77. Updated Table 1gur 2a itrised boundi(z)ues.
Ir Figures 2f and 2git ti ng V(z)ues.
1 0 25/ Uotycl19. Tabl gur 2a t ithis bounding V(z)ues.
2 0 12/17/ Uotycl19. Tabl gur 2a t itrised boundi V(z) vues. D Figur,f 2g.
1 0 13/ Uotycl20. Tabl gur 2a t ithis bounding V(z)ues.
1 Technicpecificion Amt:
Re shutdownargin (SDM)rts fromhpecsporattiDM rrts for-6 fromised ysis trlilion ent.
Page 2 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT
Core Operating Limits Report
Record of Revision
Unit Cycle Revision Approval No. Date Remarks
2 20 0 5/31/00 Updated to Unit 2 Cycle 20. Updated Table 1 and Figures 2a through 2d with revised bounding V(z) values. Added new Table 2 and Figures 2e, 2f and 2g with additional bounding V(z) values.
Added references to Tables 1 and 2 and to Figures 2e, 2f and 2g to discussion of heat flux hot channel factor limits. Added discussion clarifying applicability of axial flux difference limits when using Tables 1 and 2 and Figures 2a through 2g. Added discussion of two tier V(z) curve presented in Table 2 and Figure 2g.
1 8/4/00 Technical Specification Amendment 142:
Relocate shutdown margin (SDM) requirements from Tech Specs and incorporate additional SDM requirements for Modes 3-6 from revised analysis of Uncontrolled Dilution event.
1 20 2 9/1/00 Revised to change axial flux difference target band.
1 21 0 1/31/01 Updated to support refueling activities associated with Unit 1 Cycle 21. Revision 0 of the Unit 1 Cycle 21 COLR had to be issued prior to confirming the applicability of the LOCA analysis.
Therefore, Revision 0 of the Unit 1 Cycle 21 COLR does not contain all of the operating limits necessary to support operation of Unit 1 Cycle 21.
1 21 1 2/19/01 Updated to Unit 1 Cycle 21. Updated Tables 1 and 2 and Figures 2a through 2f with revised bounding V(z) values.
1 21 2 10/02/02 Revised to support License Amendment 158 changes, including revision of all references to TS, revision of FQ symbols, addition of Table 4, ITC limits, DNB limits and refueling boron concentrations.
2 21 0 2/06/02 Updated to Unit 2 Cycle 21.
Page 3 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT
Core Operating Limits Report
Record of Revision
Unit Cycle Revision Approval No. Date Remarks
2 211 10/02/02 Revised to support License Amendment 149 changes, including revision of all references to TS, revision of FQ symbols, addition of Table 4, ITC limits, DNB limits and refueling boron concentrations. Also revised to include an additional V(z) curve to give greater FQ margin between 13.0 and 16.0 GWd/MTU.
1 22 0 11/25/02 Updated to Unit 1 Cycle 22. Updated Tables 1 and 2 and Figures 2a through 2f with revised bounding V(z) values. Incorporated new Figure 2g with additional bounding V(z) values.
Updated Table 3 with revised minimum shutdown margin limits. Deleted and revised text to eliminate duplication with the Technical Specifications and the Bases.
2 22 0 9/19/03 Updated to Unit 2 Cycle 22. Updated Tables 1 and 2. A reduced number of exposure ranges were calculated in Table 1, therefore new Figures 2a through 2e with revised bounding V(z) values replaced Figures 2a through 2f. New Figure 2f replaced Figure 2g for the 2 tier band bounding V(z) values. Updated Table 3 with revised minimum shutdown margin limits. Deleted and revised text to eliminate duplication with the Technical Specifications and the Bases.
1 22 1 7/6/04 Revision to incorporate Westinghouse Safety Analysis Transition per LA 162/153. Revision 1 contains transitional values for the OP/OT T Trip setpoints that will be used while the physical changes are implemented.
2 22 1 7/6/04 Revision to incorporate Westinghouse Safety Analysis transition per LA 162/153. Revision 1 contains transitional values for the OP/OT T Trip setpoints that will be used while the physical changes are implemented.
2 22 2 7/12/04 Revised Fq limit from 2.4 to 2.5. Removed OP and OT delta-T setpoints based on NMC methodology and replaced with Westinghouse developed setpoints.
Page 4 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT
Core Operating Limits Report
Record of Revision
Unit Cycle Revision Approval No. Date Remarks
1 22 2 7/16/04 Revised Fq limit form 2.4 to 2.5. Removed OP and OT delta-T setpoints based on NMC methodology and replaced with Westinghouse developed setpoints.
1 23 0 10/20/04 Updated to Unit 1 Cycle 23.
2 23 0 - Not used due to core redesign.
2 23 1 5/19/05 Updated to Unit 2 Cycle 23 and to support redesign of Unit 2 Cycle 23 core.
1 23 1 7/11/05 Revised ITC upper limit from < 0 pcm/°F for power levels > 70% RTP to less than a line that slopes linearly from 0 pcm/F at 70% RTP to -2.9 pcm/F at 100% RTP. Revised the title of Figure 3 to reference T.S. 3.1.4 Condition B and revised the title of Figure 4 to reference T.S. 3.1.4 Condition A. Added references 24 and 25 to include the 50.59 screenings written to issue revision 1.
1 24 0 5/10/06 Updated to Unit 1 Cycle 24.
1 24 1 8/7/06 Updated Table 3 to reflect the correct Fqw(z) penalty factors.
2 24 0 11/26/06 Updated to Unit 2 Cycle 24 Modes 5 and 6.
2 24 1 12/6/06 Updated to Unit 2 Cycle 24 for Modes 1-6.
2 24 2 9/4/07 Revised to support LA-179/169. Revised reference 24 to include the revision number (revision 0) and the correct date of the report (January 2005). Revised references 6a, 6b, 6c, and 8 to say Deleted. These references referred to the old LBLOCA methodology and model.
1 24 2 2/11/08 Updated Table 1 to reflect correct Shutdown Margin Requirements and added Figures 6A through 6H.
Page 5 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT
Core Operating Limits Report
Record of Revision
Unit Cycle Revision Approval No. Date Remarks
2 24 3 2/11/08 Updated Table 1 to reflect correct Shutdown Margin Requirements and added Figures 6A through 6H.
1 25 0 2/24/08 Updated to Unit 1 Cycle 25
1 25 1 5/28/08 Updated Table 2 to reflect the correct W(z) at a burnup of 150 MWd/MTU and a core height of 6.20 feet
2 25 0 9/26/08 Updated for Unit 2 Cycle 25
1 26 0 9/24/09 Updated for Unit 1 Cycle 26
2 26 0 5/3/10 Updated for Unit 2 Cycle 26
2 26 1 5/17/10 Updated to include part power W(z) factors
1 26 1 9/2/10 Updated for second set of W(z) factors
2 26 2 9/30/10 Updated for Measurement Uncertainty Recapture power uprate to 1677 MWth and for a second set of W(z) factors
1 26 2 9/30/10 Updated for Measurement Uncertainty Recapture power uprate to 1677 MWth
1 26 3 12/17/10 Updated SDM in Table 1 for Mode 2 to say 1.9.
1 27 0 5/5/11 Updated for Unit 1 Cycle 27
1 27 1 6/2/11 Updated for Unit 1 Cycle 27 Modes 1 through 6
2 27 0 3/28/12 Updated for Unit 2 Cycle 27
1 28 0 11/29/12 Updated for Unit 1 Cycle 28
Page 6 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT
Core Operating Limits Report
Record of Revision
Unit Cycle Revision Approval No. Date Remarks
2 28 0 11/23/13 Updated for Unit 2 Cycle 28
1 29 0 10/23/14 Updated for Unit 1 Cycle 29
2 29 0 Updated for Unit 2 Cycle 29 11/05/15
1 30 0 10/25/16 Updated for Unit 1 Cycle 30
2 30 0 10/24/17 Updated for Unit 2 Cycle 30
1 31 0 09/06/18 Updated for Unit 1 Cycle 31
2 31 0 10/14/19 Updated for Unit 2 Cycle 31
2 31 1 09/14/20 Updated to revise Table 2 and Table 3 due to Flexible Power Operation
1 32 0 09/21/20 Updated for Unit 1 Cycle 32
2 32 0 10/11/21 Updated for Unit 2 Cycle 32
2 32 1 10/25/21 Updated to clarify p ower value used in calculation of FQW(Z)
1 33 0 10/13/22 Updated for Unit 1 Cycle 33
2 33 0 10/26/23 Updated for Unit 2 Cycle 33
Page 7 of 7 Core Operating Limits Report Unit 2, Cycle 33 Revision 0 PRAIRIE ISLAND NUCLEAR GENERATING PLANT
CORE OPERATING LIMITS REPORT
UNIT 2-CYCLE 33
REVISION 0
Note: This report is not part of the Technical Specifications
This report is referenced in the Technical Specifications
APPROVAL:
LDC#: 604000000901
Page 1 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0
PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT 2-CYCLE 33 REVISION 0
This report provides the values of the limits for Unit 2 Cycle 33 as required by Technical Specification 5.6.5. These values have been established using NRC approved methodology and are established such that all applicable limits of the plant safety analysis are met. The Technical Specifications affected by this report are listed below:
- 1. 2.1.1 Reactor Core Safety L imits
- 2. 3.1.1 Shutdown MarginRequirements
- 3. 3.1.3 Isothermal Temperature Coefficient (ITC)
- 4. 3.1.5 Shutdown Bank Insertion Limits
- 5. 3.1.6 Control Bank Insertion Limits
- 6. 3.1.8 Physics Tests Exceptions - MODE 2
- 7. 3.2.1 Heat Flux Hot Channel Factor (FQ(z))
- 8. 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( )F
- 9. 3.2.3 Axial Flux Difference (AFD)
- 10. 3.3.1 Reactor Trip System (RTS) Instrumentation Overtemperature T and Overpower T Parameter Values for Technical Specification Table 3.3.1-1 (Note 1 and Note 2)
- 12. 3.9.1 Refueling Boron Concentration
- 1. 2.1.1 Reactor Core Safety Limits
Reactor Core Safety Limits are shown in Figure 1.
Reference Technical Specification 2.1.1.
- 2. 3.1.1 Shutdown Margin Requirements
Minimum Shutdown Margin requirements are shown in Table 1.
Reference Technical Specification 3.1.1.
Page 2 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0
- 3. 3.1.3 Isothermal Temperature Coefficient (ITC)
ITC Upper limit:
- a. < 5 pcm/ °F for power levels < 70% RTP; and
- b. a line which slopes linearly from
ITC Lower limit:
- a. - 43.15 pcm/°F
Reference Technical Specification 3.1.3.
- 4. 3.1.5 Shutdown Bank Insertion Limits
The shutdown rods shall be fully withdrawn.
Reference Technical Specification 3.1.5.
- 5. 3.1.6 Control Bank Insertion Limits
The control rod banks shall be limited in physical insertio n as shown in Figures 2, 3, and4.
The control rod banks withdrawal sequence shall be Bank A, Bank B, Bank C, and finally Bank D.
The control rod banks shall be withdrawn maintaining 128 step tip-to-tip distance.
Reference Technical Specification 3.1.6.
- 6. 3.1.8 Physics Tests Exceptions - MODE 2
Minimum Shutdown Margin requirements during physics testing are shown in Table 1.
Reference Technical Specification 3.1.8.
Page 3 of 28
Core Operating Limits Report Unit 2, Cycle 33 Revision 0
- 7. 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))
The Heat Flux Hot Channel Factor shall be within the following limits:
() ()
> 0.5
(
) 0.5 () 0.5
() = [()] [()] () 1.0815 for P > 0.5
() = [()] [()] () 1.0815 for P 0.5 0.5
[()] is the measured planar radial peaking factor.
P is the ratio of thermal power at the time of surveillance to rated thermal power.
CFQ = 2.50
K(Z) is a constant value = 1.0 at all elevations.
The T (Z) values are provided in Tables 2and 4.
The T (Z) values in Table 2 are applicable to Figure 5 which represents RAOC Operation Space #1 (ROS1).
The T(Z) values in Table 4 are applicable to Figure 6, which represents RAOC Operating Space #2 (ROS2). Through Table 6, Table 4is also associated with F igures 7 and 8.
The Rj Penalty Factors associated with Figure 5 and Table 2 (ROS1) are provided in Table 3.
The Rj Penalty Factors associated with Figure 6 and Table 4 (ROS2) are provided in Table 5.Through Table 6, Table 5 is a lso associated with Figures 7 and 8.
The AXY(Z) factors adjust the surveillance to the reference conditions assumed in generating the T(z) factors. AXY(Z) may be assumed to equal 1.0 or may be determined for specific surveillance conditions using the approved methods listed in TS 5.6.5.
Page 4 of 28
Core Operating Limits Report Unit 2, Cycle 33 Revision 0 Either ROS1 or ROS2 may be implemented at any time during Cycle 33
If ROS1 is implemented and entering LCO 3.2.1 Condition B for FWQ(Z) not within limits, EITHER take Action B.1.1 by implementing ROS2, OR take Action B.2.1 by using Table 6 to determine required THERMAL POWER and AFD limits based on Required FWQ(Z) margin improvement available in ROS1.
If ROS2 is implemented and entering LCO 3.2.1 Condition B for FWQ(Z) not within limits, take Action B.2.1 by using Table 6 to determine required THERMAL POWER and AFD limits based on Required FWQ(Z) margin improvement available in ROS2.
Reference Technical Specification 3.2.1.
- 8. 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FHN)
The Nuclear Enthalpy Rise Hot Channel Factor shall be within the following limits:
FH 1.77 x [1 + 0.3(1-P)]
where: P is the fraction of RATED THERMAL POWER at which the core is operating.
Reference Technical Specification 3.2.2.
- 9. 3.2.3 Axial Flux Difference (AFD)
The indicated axial flux difference shall be maintained within the allowed operational space defined by either Figure 5, if ROS1 is implemented, or Figure 6 if ROS2 is implemented.If implementing TS 3.2.1 Required Action B.2.1, the AFD shall be maintained within the allowed space defined by Figure 7 or 8, as determined by Table 6 and the condition that led to the required action.
Reference Technical Specification 3.2.3.
- 10. 3.3.1 Reactor Trip System (RTS) Instrumentation
Overtemperature T and Overpower T Parameter Values for Technical Specification Table 3.3.1-1(Note 1 and Note 2) :
Page 5 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0
Overtemperature T Setpoint
Overtemperature T setpoint parameter values:
T0=== IniateatATED=MAL=PO,= =
T=== Ave=tpur=F =
T=== °F=
P=== Prsurizerrsursig=
P=== 2235=psig=
K 1= =
K 2 = 0.014 /°F K 3 = 0.00100 /psi 1=== e =
2=== 4=se =
I)=== Auntion=ofniate fferee=betweent=
etorsfhe=powge=nueon=hbers.==Setns=
are=base=on=measenstreesei=platartests whe t=a b=areereern=then=bott=hals=of=
thre=rptily,=an=°t=+=°b=isot=ore=powntf=
RATED=THMAL=PO,uhhat =
(a) For qt - q b within -13, +8 % f( I) = 0 (b) For each percent that the magnitude of qt - qb exceeds +8%
the T trip setpoint shall be automatically reduced by an equivalent of 1.73 % of RATED THERMAL POWER.
(c) For each percent that the magnitude of qt - qb exceeds -13 %
the T trip setpoint shall be automatically reduced by an equivalent of 3.846 % of RATED THERMAL POWER.
Overpower T Setpoint Overpower T setpoint parameter values:
T0=== IniateatATED=MALO,= =
T=== Ave=tpur=F =
T=== °F=
K 4= = =
K 5=== 0.0275/°Freasing=T;=ereasi=
K 6=== °F=for=T=>=;=for=T==T=
3=== 10=se =
=
Rehnipeifiation=3. =
=
Page 6 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0
Limits
The DNB Limits are:
Pressurizer pressure limit = 2190psia RCS average temperature limit = 564°F RCS total flow rate limit = 178,000 gpm
Reference Technical Specification 3.4.1.
- 12. 3.9.1 Refueling Boron Concentration.
The boron concentration of the reactor coolant system and the refueling cavity shall be sufficient to ensure that the more restrictive of the following conditions is met:
a) Keff 0.95 b) 2000 ppm c) The Shutdown Margin specified in Table 1
Reference Technical Specification 3.9.1.
Page 7 of 28
Core Operating Limits Report Unit 2, Cycle 33 Revision 0
REFERENCES (NRC Approved Methodologies for COLR Parameters)
- 1. NSPNAD-8101-A, Qualification of Reactor Physics Methods for Application to Prairie Island, Revision 2, October 2000.
- 2. NSPNAD-8102-PA, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units, Revision 7, July 1999.
- 3. NSPNAD-97002-PA, Northern States Power Companys Steam Line Break Methodology, Revision 1, October 2000.
- 4. WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, July, 1985.
5.a WCAP-10054-P-A, Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code, August, 1985.
5.b WCAP-10054-P-A, Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code, Addendum 2 Revision 1, July 1997.
- 6. WCAP-16045-P-A Addendum 1-A, Qualification of the NEXUS Nuclear Data Methodology, August 2007.
- 7. WCAP-10924-P-A, Volume 1, Revision 1, and Volume 2, Revision 2, Westinghouse Large Break LOCA Best Estimate Methodology, September 2005.
- 8. XN-NF 57- (A), XN-NF 57, Supplement 1 (A), Exxon Nuclear Power Distribution Control for Pressurized Water Reactors Phase II, May 1981.
- 9. WCAP-13677-P-A, 10 CFR 50.46 Evaluation Model Report: W -COBRA/TRAC 2-Loop Upper Plenum Injection Model Update to Support ZIRLO ' Cladding Options, February 1994.
- 10. NSPNAD-93003-A, Prairie Island Units 1 and 2 Transient Power Distribution Methodology, Revision 0, April 1993.
- 11. NAD-PI-003, Prairie Island Nuclear Power Plant Required Shutdown Margin During P hysics Tests, Revision 0, January 2001.
- 12. NAD-PI-004, Prairie Island Nuclear Power Plant F WQ(Z) Penalty With Increasing [FCQ(Z) / K(Z)]
Trend, Revision 0, January 2001.
- 13. WCAP-10216-P-A, Revision 1A, Relaxation of Constant Axial Offset Control/ F Q Surveillance Technical Specification, February 1994.
ZIRLO' is a registered trademark of Westinghouse Electric Company LLC, its Affiliates and/or its Subsidiaries in the United States of America and may be registered in other countries throughout the world.
All rights reserved. Unauthorized use is strictly prohibited.
Page 8 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0
- 14. WCAP-8745-P-A, Design Bases for the Thermal Overpower T and Thermal Overtemperature T Trip Functions, September 1986.
- 15. WCAP-11397-P-A, Revised Thermal Design Procedure, April 1989.
- 16. WCAP-14483-A, Generic Methodology for Expanded Core Operat ing Limits Report, January 1999.
- 17. WCAP-7588 Rev. 1-A, An Evaluation of the Rod Ejection Accident in Westinghouse Pressurized Water Reactors Using Spatial Kinetics Methods, January 1975.
- 18. WCAP-7908-A, FACTRAN - A FORTRAN IV Code for Thermal Transients in a UO2 Fuel Rod, December 1989.
- 19. WCAP-7907-P-A, LOFTRAN Code Description, April 1984.
- 20. WCAP-7979-P-A, TWINKLE - A Multidimensional Neutron Kinetics Computer Code, January 1975.
- 21. WCAP-10965-P-A, ANC: A Westinghouse Advanced Nodal Computer Code, September 1986.
- 22. WCAP-11394-P-A, Methodology for the Analysis of the Dropped Ro d Event, January 1990.
- 23. WCAP-16045-P-A, Qualification of the Two-Dimensional Transport Code PARAGON, August 2004.
- 24. WCAP-12910 Rev. 1-A, Pressurizer Safety Valve Set Pressure Shift, May 1993.
- 25. WCAP-14565-P-A, VIPRE -01 Modeling and Qualification for Pressurized Water Reactor Non -
LOCA Thermal-Hydraulic Safety Analysis, October 1999.
- 26. WCAP-14882-P-A, RETRAN- 02 Modeling and Qualification for Westinghouse Pressurized Water Reactor Non-LOCA Safety Analyses, April 1999.
- 27. WCAP-16009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment Of Uncertainty Method (ASTRUM)," Revision 0, January 2005.
- 28. Caldon, Inc. Engineering Report-80P, Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM ' System, Revision 0, March 1997.
- 29. Caldon, Inc. Engineering Report-157P, Supplement to Topical Report ER -80P: Basis for a Power Uprate With the LEFM ' Check or CheckPlus ' System, Revision 5, October 2001.
- 30. WCAP-12610- P-A, VANTAGE+ Fuel Assembly Reference Core Report, April 1995.
Page 9 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0
- 31. WCAP-12610- P-A and CENPD-404-P-A, Addendum 1-A, Optimized ZIRLO', July 2006.
- 32. Design Equivalent Change EC 601000004483Rev.0 2R3 3Core Reload
- 33. WCAP-17661-P-A, Improved RAOC and CAOC FQ Surveillance Technical Specifications, February 2019.
Optimized ZIRLO' is a trademark of Westinghouse Electric Company LLC, its Affiliates and/or its Subsidiaries in the United States of America and may be registered in other countries throughout the world.
All rights reserved. Unauthorized use is strictly prohibited.
Page 10 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0 Table 1
Minimum Required Shutdown Margin, %
Number of Charging Pumps Running**
Mode 1*
0-1 Pump 2 Pumps 3 Pumps 0 - 24500 MWd/MTU - - -
Mode 2*
0-1 Pump 2 Pumps 3 Pumps 0 - 24500 MWd/MTU 1.7 1.7 1.7
Physics Testing in Mode 2 0-1 Pump 2 Pumps 3 Pumps 0 - 24500 MWd/MTU 0.5 0.5 0.5 T 520°F (Most Reactive Rod Out)
Mode 3 ave 0-1p 2 3
- 2 MTU 2.0 2.0 2.0 350°F T < 520°F (Most Reactive Rod Out)
Mode 3 a
0-1p 2 3 0 MWTIMTU 2.0 2.0 2.0 3000 MWd/MTU 2.0 2.0 2.0 6000 MWd/MTU 2.0 2.0 2.0 11000 MWd/MTU 2.0 2.0 2.0 16000 MWd/MTU 2.0 2.0 2.0 24500 MWd/MTU 2.0 2.0 2.0 Operational Mode Definitions, as per TS Table 1.1-1.
- For Mode 1 and Mode 2 with Keff 1.0, the minimum shutdown margin requirements are provided by the Rod Insertion Limits.
- Charging pump(s) in service only pertains to steady state operations. It does not include
transitory operations. For example, operations such as starting a second charging pump in order to secure the operating pump would fall under the one pump in service column.
E} W>]v -]v -}o]}v v µ-vµ ]oo} X -}oion is not allowed.
Page 11 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0 Table 1, Continued
Minimum Required Shutdown Margin, %
Number of Charging Pumps Running**
Mode 4 200°F < Tave < 350°F (Most Reactive Rod Out)
0-1p 2 3 0IMTU 2.0 3.5 5.5 3000 MWd/MTU 2.0 4.0 6.0 6000 MWd/MTU 2.0 3.5 6.0 11000 MWd/MTU 2.0 3.5 5.5 16000 MWd/MTU 2.0 3.0 5.0 24500 MWd/MTU 2.0 2.0 2.5
Number of Charging Pumps Running**
Mode 5 68°F Ta 200°F (Most Reactive Rod Out)
0-1p 2 3 0 MWTIMTU*** 2.0 4.0 6.5 3000 MWd/MTU 2.0 4.0 6.5 6000 MWd/MTU 2.0 4.0 6.5 11000 MWd/MTU 2.0 4.0 6.0 16000 MWd/MTU 2.0 3.5 5.5 24500 MWd/MTU 2.0 2.0 3.5 Operational Mode Definitions, as per TS Table 1.1-1.
- Charging pump(s) in service only pertains to steady state operations. It does not include transitory operations. For example, operations such as starting a second charging pump in order to secure the operating pump would fall under the one pump in service column.
- These values are also applicable for the Unit 2 Cycle 32 end of cycle.
Note: Linear interpolation between burnup steps is allowed. Extrapolation is not allowed.
Page 12 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0 Table 1, Continued
Minimum Required Shutdown Margin, %
Number of Charging Pumps Running**
Mode 6 68°F Tave < 200°F (ARI)
0-1p 2 3 0 MWTIMTU*** 5.129 5.129 6.5 3000 MWd/MTU 5.129 5.129 6.5 6000 MWd/MTU 5.129 5.129 6.5 11000 MWd/MTU 5.129 5.129 6.0 16000 MWd/MTU 5.129 5.129 5.5 24500 MWd/MTU 5.129 5.129 5.129
Mode 6 68°F Ta < 200°F (ARO)
0-1p 2 3 0 MWTIMTU*** 5.129 5.129 8.0 3000 MWd/MTU 5.129 5.5 8.0 6000 MWd/MTU 5.129 5.5 8.0 11000 MWd/MTU 5.129 5.129 8.0 16000 MWd/MTU 5.129 5.129 7.0 24500 MWd/MTU 5.129 5.129 5.5
- Charging pump(s) in service only pertains to steady state operations. It does not include
transitory operations. For example, operations such as starting a second charging pump in order to secure the operating pump would fall under the one pump in service column.
ŽŽŽdZ oµ - o}o] o (}-Z hv]2 Ç o 32 v }( Ç o X
E} W>]v -]v -}o]}v v µ-vµ ]oo} X -}o]}v]v}oo} X
Page 13 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0 Table 2: T (z) Factors associated with Figure 5 (ROS1)
(Top 10% and Bottom 8% excluded)*
Height BU [MWd/MTU]
[ft] 150 1500 2000 2500 3500 4000 4500 6500 7000 7500
[BOTTOM] 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1
2 0.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 3 0.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 4 0.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 5 0.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6 1.00 1.1604 1.1259 1.1133 1.0900 1.0763 1.0728 1.0719 1.0870 1.0865 1.0900 7 1.20 1.1871 1.1618 1.1517 1.1305 1.1207 1.1188 1.1193 1.1396 1.1398 1.1444 8 1.40 1.2039 1.1869 1.1789 1.1597 1.1529 1.1522 1.1536 1.1766 1.1769 1.1819 9 1.60 1.2219 1.2122 1.2062 1.1887 1.1844 1.1846 1.1868 1.2113 1.2114 1.2165 10 1.80 1.2212 1.2181 1.2137 1.1983 1.1964 1.1974 1.2001 1.2253 1.2252 1.2304 11 2.00 1.1811 1.1837 1.1811 1.1682 1.1685 1.1704 1.1736 1.1988 1.1986 1.2036 12 2.20 1.1380 1.1458 1.1446 1.1341 1.1363 1.1424 1.1459 1.1669 1.1665 1.1713 13 2.40 1.1614 1.1731 1.1728 1.1657 1.1696 1.1725 1.1763 1.1962 1.1951 1.1995 14 2.60 1.2023 1.2178 1.2180 1.2160 1.2208 1.2239 1.2276 1.2409 1.2387 1.2426 15 2.80 1.2139 1.2302 1.2309 1.2356 1.2408 1.2440 1.2476 1.2539 1.2514 1.2550 16 3.00 1.2037 1.2192 1.2208 1.2299 1.2360 1.2393 1.2428 1.2451 1.2426 1.2459 17 3.20 1.1982 1.2155 1.2180 1.2263 1.2334 1.2365 1.2398 1.2429 1.2400 1.2424 18 3.40 1.2019 1.2214 1.2235 1.2311 1.2383 1.2410 1.2440 1.2459 1.2425 1.2450 19 3.60 1.2122 1.2358 1.2383 1.2456 1.2516 1.2540 1.2564 1.2554 1.2516 1.2524 20 3.80 1.2256 1.2518 1.2551 1.2623 1.2689 1.2712 1.2730 1.2681 1.2638 1.2638 21 4.00 1.2191 1.2473 1.2512 1.2583 1.2651 1.2674 1.2690 1.2630 1.2585 1.2576 22 4.20 1.1777 1.2071 1.2116 1.2184 1.2258 1.2281 1.2297 1.2238 1.2194 1.2182 23 4.40 1.1391 1.1686 1.1738 1.1803 1.1881 1.1905 1.1920 1.1861 1.1819 1.1821 24 4.60 1.1697 1.1992 1.2048 1.2110 1.2188 1.2209 1.2219 1.2142 1.2112 1.2111 25 4.80 1.2168 1.2461 1.2520 1.2578 1.2656 1.2672 1.2678 1.2589 1.2563 1.2555 26 5.00 1.2320 1.2610 1.2675 1.2729 1.2802 1.2816 1.2820 1.2744 1.2710 1.2700 27 5.20 1.2229 1.2525 1.2593 1.2643 1.2713 1.2726 1.2723 1.2665 1.2619 1.2603 28 5.40 1.2171 1.2482 1.2547 1.2592 1.2666 1.2677 1.2659 1.2600 1.2551 1.2517 29 5.60 1.2213 1.2529 1.2595 1.2637 1.2710 1.2721 1.2695 1.2619 1.2572 1.2531 30 5.80 1.2337 1.2653 1.2722 1.2757 1.2831 1.2840 1.2810 1.2725 1.2668 1.2626 31 6.00 1.2495 1.2808 1.2877 1.2918 1.2983 1.2991 1.2960 1.2874 1.2807 1.2749 32 6.20 1.2440 1.2755 1.2826 1.2874 1.2922 1.2929 1.2897 1.2821 1.2755 1.2688 33 6.40 1.2032 1.2369 1.2440 1.2475 1.2518 1.2510 1.2483 1.2426 1.2372 1.2332 34 6.61 1.1676 1.2053 1.2124 1.2151 1.2203 1.2127 1.2104 1.2066 1.2069 1.2032 35 6.81 1.2028 1.2400 1.2471 1.2493 1.2543 1.2445 1.2420 1.2385 1.2388 1.2349 36 7.01 1.2524 1.2916 1.2988 1.3003 1.3050 1.2921 1.2894 1.2858 1.2867 1.2826 37 7.21 1.2688 1.3093 1.3164 1.3175 1.3220 1.3070 1.3043 1.3017 1.3029 1.2989 38 7.41 1.2600 1.3002 1.3071 1.3078 1.3125 1.2964 1.2941 1.2933 1.2951 1.2915 39 7.61 1.2529 1.2900 1.2968 1.2972 1.3019 1.2871 1.2852 1.2866 1.2889 1.2859 40 7.81 1.2545 1.2880 1.2945 1.2945 1.2992 1.2866 1.2851 1.2876 1.2906 1.2879 41 8.01 1.2628 1.2916 1.2979 1.2974 1.3020 1.2919 1.2906 1.2945 1.2981 1.2957 42 8.21 1.2717 1.2954 1.3014 1.3003 1.3047 1.2974 1.2967 1.3029 1.3061 1.3054 43 8.41 1.2579 1.2753 1.2809 1.2796 1.2839 1.2808 1.2811 1.2897 1.2916 1.2938 44 8.61 1.2091 1.2207 1.2258 1.2247 1.2290 1.2306 1.2313 1.2421 1.2440 1.2471 45 8.81 1.1654 1.1750 1.1800 1.1783 1.1831 1.1847 1.1858 1.1986 1.2037 1.2046 46 9.01 1.1976 1.2050 1.2078 1.2068 1.2111 1.2123 1.2132 1.2240 1.2304 1.2306 47 9.21 1.2453 1.2506 1.2505 1.2510 1.2550 1.2560 1.2568 1.2675 1.2743 1.2746 48 9.41 1.2586 1.2614 1.2598 1.2608 1.2646 1.2655 1.2664 1.2783 1.2857 1.2861 49 9.61 1.2447 1.2454 1.2455 1.2440 1.2478 1.2486 1.2497 1.2643 1.2718 1.2726 50 9.81 1.2305 1.2295 1.2325 1.2276 1.2309 1.2316 1.2329 1.2510 1.2582 1.2594 51 10.01 1.2261 1.2210 1.2234 1.2181 1.2204 1.2208 1.2219 1.2404 1.2482 1.2495 52 10.21 1.2267 1.2192 1.2196 1.2139 1.2155 1.2154 1.2162 1.2337 1.2416 1.2429 53 10.41 1.2225 1.2092 1.2092 1.2009 1.2012 1.2004 1.2009 1.2178 1.2256 1.2266 54 10.61 1.1887 1.1695 1.1657 1.1591 1.1578 1.1564 1.1565 1.1702 1.1779 1.1788 55 10.81 1.1149 1.0900 1.0755 1.0778 1.0754 1.0737 1.0737 1.0776 1.0850 1.0861 56 11.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 57 11.21 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.41 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 11.61 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 60 11.81 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
[TOP] 61 12.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
- Linear extrapolation based on a line between 20,500 MWD/MTU and 22,000 MWD/MTU is adequate for addressing burnups beyond 22,000 MWD/MTU.
Page 14 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0 Table 2( cont.): T(z) Factors associated with Figure 5 (ROS1)
(Top 10% and Bottom 8% excluded)*
Height BU [MWd/MTU]
[ft] 10000 10500 11000 12000 12500 14500 18500 19000 20500 22000
[BOTTOM] 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1
2 0.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 3 0.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 4 0.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 5 0.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6 1.00 1.1095 1.1117 1.1177 1.1340 1.1394 1.1935 1.2414 1.2493 1.2500 1.2750 7 1.20 1.1680 1.1708 1.1774 1.1946 1.2000 1.2522 1.2914 1.2982 1.2953 1.3170 8 1.40 1.2062 1.2091 1.2155 1.2316 1.2360 1.2823 1.3099 1.3154 1.3090 1.3268 9 1.60 1.2402 1.2429 1.2488 1.2629 1.2661 1.3052 1.3219 1.3261 1.3168 1.3309 10 1.80 1.2530 1.2554 1.2606 1.2727 1.2748 1.3072 1.3156 1.3188 1.3079 1.3191 11 2.00 1.2250 1.2273 1.2319 1.2419 1.2432 1.2699 1.2737 1.2762 1.2655 1.2746 12 2.20 1.1908 1.1929 1.1967 1.2043 1.2046 1.2256 1.2258 1.2279 1.2180 1.2254 13 2.40 1.2158 1.2172 1.2197 1.2239 1.2226 1.2360 1.2299 1.2313 1.2209 1.2260 14 2.60 1.2553 1.2559 1.2570 1.2571 1.2539 1.2599 1.2477 1.2485 1.2378 1.2404 15 2.80 1.2648 1.2649 1.2649 1.2628 1.2584 1.2580 1.2420 1.2424 1.2318 1.2333 16 3.00 1.2533 1.2530 1.2523 1.2489 1.2434 1.2378 1.2206 1.2200 1.2111 1.2084 17 3.20 1.2476 1.2464 1.2449 1.2386 1.2318 1.2214 1.2047 1.2021 1.1978 1.1871 18 3.40 1.2478 1.2459 1.2436 1.2338 1.2260 1.2111 1.1948 1.1910 1.1900 1.1833 19 3.60 1.2540 1.2513 1.2483 1.2352 1.2265 1.2105 1.1935 1.1910 1.1892 1.1843 20 3.80 1.2643 1.2609 1.2571 1.2405 1.2311 1.2118 1.1920 1.1948 1.1924 1.1889 21 4.00 1.2570 1.2531 1.2490 1.2309 1.2213 1.1997 1.1845 1.1842 1.1835 1.1823 22 4.20 1.2175 1.2137 1.2096 1.1917 1.1824 1.1607 1.1494 1.1493 1.1504 1.1519 23 4.40 1.1796 1.1758 1.1720 1.1558 1.1470 1.1235 1.1159 1.1159 1.1187 1.1228 24 4.60 1.2043 1.1999 1.1953 1.1791 1.1695 1.1423 1.1323 1.1322 1.1356 1.1412 25 4.80 1.2440 1.2393 1.2338 1.2166 1.2060 1.1740 1.1614 1.1607 1.1639 1.1708 26 5.00 1.2552 1.2511 1.2451 1.2274 1.2163 1.1836 1.1687 1.1685 1.1712 1.1791 27 5.20 1.2447 1.2404 1.2344 1.2174 1.2064 1.1753 1.1587 1.1601 1.1617 1.1698 28 5.40 1.2361 1.2307 1.2248 1.2088 1.1982 1.1668 1.1495 1.1523 1.1522 1.1598 29 5.60 1.2359 1.2306 1.2249 1.2085 1.1982 1.1666 1.1485 1.1512 1.1503 1.1559 30 5.80 1.2448 1.2387 1.2331 1.2174 1.2054 1.1731 1.1581 1.1586 1.1587 1.1602 31 6.00 1.2584 1.2506 1.2449 1.2307 1.2176 1.1863 1.1735 1.1723 1.1737 1.1744 32 6.20 1.2527 1.2458 1.2382 1.2259 1.2149 1.1864 1.1735 1.1726 1.1760 1.1789 33 6.40 1.2157 1.2124 1.2019 1.1927 1.1850 1.1589 1.1487 1.1478 1.1563 1.1585 34 6.61 1.1828 1.1840 1.1709 1.1665 1.1602 1.1365 1.1282 1.1279 1.1403 1.1421 35 6.81 1.2149 1.2143 1.2008 1.1961 1.1899 1.1687 1.1559 1.1573 1.1704 1.1707 36 7.01 1.2603 1.2590 1.2508 1.2405 1.2363 1.2164 1.1977 1.1990 1.2124 1.2109 37 7.21 1.2764 1.2775 1.2746 1.2609 1.2582 1.2390 1.2176 1.2182 1.2312 1.2284 38 7.41 1.2717 1.2759 1.2742 1.2613 1.2593 1.2411 1.2196 1.2199 1.2313 1.2275 39 7.61 1.2693 1.2739 1.2730 1.2599 1.2591 1.2425 1.2203 1.2202 1.2303 1.2256 40 7.81 1.2736 1.2784 1.2781 1.2651 1.2653 1.2500 1.2269 1.2262 1.2344 1.2285 41 8.01 1.2856 1.2895 1.2899 1.2768 1.2781 1.2641 1.2396 1.2383 1.2439 1.2359 42 8.21 1.2977 1.3003 1.3015 1.2884 1.2908 1.2783 1.2527 1.2507 1.2535 1.2435 43 8.41 1.2881 1.2893 1.2913 1.2789 1.2825 1.2728 1.2478 1.2454 1.2453 1.2344 44 8.61 1.2450 1.2448 1.2478 1.2368 1.2419 1.2366 1.2156 1.2129 1.2108 1.2018 45 8.81 1.2062 1.2044 1.2082 1.1987 1.2052 1.2044 1.1904 1.1876 1.1821 1.1781 46 9.01 1.2326 1.2308 1.2353 1.2254 1.2332 1.2367 1.2181 1.2189 1.2054 1.2024 47 9.21 1.2683 1.2753 1.2803 1.2719 1.2814 1.2843 1.2567 1.2595 1.2463 1.2403 48 9.41 1.2767 1.2884 1.2942 1.2896 1.3004 1.3026 1.2732 1.2775 1.2644 1.2535 49 9.61 1.2665 1.2779 1.2843 1.2825 1.2945 1.2997 1.2710 1.2773 1.2625 1.2528 50 9.81 1.2553 1.2672 1.2744 1.2714 1.2845 1.2967 1.2668 1.2746 1.2621 1.2560 51 10.01 1.2459 1.2571 1.2649 1.2591 1.2724 1.2942 1.2693 1.2784 1.2693 1.2634 52 10.21 1.2398 1.2517 1.2599 1.2532 1.2672 1.2932 1.2746 1.2812 1.2819 1.2735 53 10.41 1.2238 1.2368 1.2449 1.2383 1.2532 1.2843 1.2759 1.2769 1.2888 1.2772 54 10.61 1.1778 1.1889 1.1979 1.1928 1.2073 1.2429 1.2512 1.2495 1.2688 1.2574 55 10.81 1.0924 1.0988 1.1064 1.1079 1.1170 1.1550 1.1832 1.1841 1.2069 1.2012 56 11.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 57 11.21 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.41 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 11.61 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 60 11.81 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
[TOP] 61 12.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
- Linear extrapolation based on a line between 20,500 MWD/MTU and 22,000 MWD/MTU is adequate for addressing burnups beyond 22,000 MWD/MTU.
Page 15 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0
Table 3: RJ Margin Decrease Factors associated with Figure 5 (ROS1) and Table 2
Cycle RJ Cycle RJ Cycle RJ Burnup Penalty Burnup Penalty Burnup Penalty (MWD/MTU) Multiplier (MWD/MTU) Multiplier (MWD/MTU) Multiplier 150 1.042 7174 1.001 14198 1.003 321 1.038 7345 1.001 14370 1.003 493 1.035 7517 1.000 14541 1.003 664 1.030 7688 1.000 14712 1.002 835 1.026 7859 1.000 14884 1.002 1007 1.022 8031 1.000 15055 1.002 1178 1.018 8202 1.000 15226 1.001 1349 1.015 8373 1.001 15398 1.001 1521 1.013 8545 1.002 15569 1.000 1692 1.017 8716 1.003 15740 1.000 1863 1.017 8887 1.008 15912 1.000 2035 1.015 9059 1.009 16083 1.000 2206 1.014 9230 1.009 16254 1.000 2377 1.014 9401 1.010 16426 1.000 2548 1.012 9573 1.009 16597 1.000 2720 1.010 9744 1.008 16768 1.001 2891 1.008 9915 1.007 16939 1.001 3062 1.002 10087 1.006 17111 1.001 3234 1.000 10258 1.004 17282 1.001 3405 1.000 10429 1.003 17453 1.002 3576 1.000 10601 1.002 17625 1.002 3748 1.000 10772 1.000 17796 1.001 3919 1.005 10943 1.000 17967 1.001 4090 1.007 11115 1.000 18139 1.001 4262 1.007 11286 1.000 18310 1.001 4433 1.007 11457 1.001 18481 1.001 4604 1.008 11629 1.002 18653 1.001 4776 1.008 11800 1.001 18824 1.000 4947 1.009 11971 1.000 18995 1.000 5118 1.010 12142 1.004 19167 1.000 5290 1.010 12314 1.006 19338 1.000 5461 1.012 12485 1.007 19509 1.000 5632 1.012 12656 1.006 19681 1.000 5804 1.011 12828 1.006 19852 1.000 5975 1.010 12999 1.006 20023 1.000 6146 1.009 13170 1.007 20195 1.000 6318 1.008 13342 1.009 20366 1.000 6489 1.006 13513 1.003 20537 1.002 6660 1.005 13684 1.003 20709 1.003 6832 1.003 13856 1.003 7003 1.001 14027 1.003 Values may be interpolated to the surveillance cycle burnup. The Rj factor value for the last burnup step shall be used for all burnups greater than the last burnup step.
Page 16 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0 Table 4 : T(z) Factors associated with Figures 6, 7 and 8 (ROS2)
(Top 10% and Bottom 8% excluded)*
Height BU [MWd/MTU]
[ft] 150 1500 2000 2500 3500 4000 4500 6500 7000 7500
[BOTTOM] 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1
2 0.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 3 0.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 4 0.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 5 0.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6 1.00 1.1200 1.0865 1.0744 1.0717 1.0592 1.0560 1.0554 1.0488 1.0480 1.0513 7 1.20 1.1464 1.1218 1.1121 1.1118 1.1031 1.1015 1.1023 1.1002 1.1000 1.1043 8 1.40 1.1634 1.1468 1.1391 1.1408 1.1350 1.1347 1.1364 1.1367 1.1366 1.1412 9 1.60 1.1817 1.1722 1.1663 1.1697 1.1664 1.1669 1.1694 1.1711 1.1708 1.1756 10 1.80 1.1821 1.1788 1.1746 1.1794 1.1784 1.1798 1.1827 1.1857 1.1852 1.1900 11 2.00 1.1444 1.1468 1.1442 1.1501 1.1513 1.1534 1.1569 1.1611 1.1606 1.1653 12 2.20 1.1039 1.1112 1.1101 1.1170 1.1200 1.1228 1.1265 1.1315 1.1307 1.1352 13 2.40 1.1280 1.1391 1.1388 1.1464 1.1504 1.1534 1.1571 1.1613 1.1599 1.1639 14 2.60 1.1687 1.1837 1.1839 1.1923 1.1969 1.1999 1.2034 1.2059 1.2033 1.2071 15 2.80 1.1834 1.1981 1.1991 1.2069 1.2121 1.2152 1.2186 1.2208 1.2245 1.2214 16 3.00 1.1774 1.1906 1.1922 1.1996 1.2068 1.2101 1.2134 1.2148 1.2262 1.2152 17 3.20 1.1723 1.1887 1.1904 1.1992 1.2062 1.2096 1.2128 1.2139 1.2240 1.2136 18 3.40 1.1776 1.1953 1.1973 1.2055 1.2123 1.2157 1.2188 1.2183 1.2289 1.2171 19 3.60 1.1894 1.2103 1.2129 1.2210 1.2266 1.2293 1.2316 1.2299 1.2392 1.2283 20 3.80 1.2041 1.2272 1.2303 1.2390 1.2439 1.2461 1.2477 1.2448 1.2516 1.2427 21 4.00 1.2001 1.2242 1.2283 1.2366 1.2417 1.2439 1.2454 1.2422 1.2442 1.2399 22 4.20 1.1635 1.1865 1.1926 1.1992 1.2047 1.2070 1.2084 1.2069 1.2043 1.2048 23 4.40 1.1287 1.1523 1.1622 1.1638 1.1743 1.1765 1.1748 1.1741 1.1747 1.1721 24 4.60 1.1614 1.1861 1.1936 1.1975 1.2052 1.2071 1.2081 1.2062 1.2037 1.2036 25 4.80 1.2101 1.2366 1.2442 1.2479 1.2549 1.2565 1.2571 1.2538 1.2510 1.2503 26 5.00 1.2291 1.2570 1.2638 1.2682 1.2743 1.2757 1.2755 1.2717 1.2685 1.2675 27 5.20 1.2233 1.2526 1.2587 1.2638 1.2699 1.2711 1.2698 1.2658 1.2616 1.2599 28 5.40 1.2171 1.2482 1.2547 1.2592 1.2666 1.2677 1.2651 1.2600 1.2551 1.2517 29 5.60 1.2213 1.2529 1.2595 1.2637 1.2710 1.2721 1.2693 1.2619 1.2572 1.2531 30 5.80 1.2337 1.2654 1.2722 1.2759 1.2831 1.2840 1.2810 1.2725 1.2671 1.2626 31 6.00 1.2495 1.2808 1.2877 1.2910 1.2983 1.2991 1.2959 1.2874 1.2796 1.2749 32 6.20 1.2440 1.2755 1.2826 1.2856 1.2922 1.2929 1.2897 1.2821 1.2734 1.2688 33 6.40 1.2031 1.2368 1.2439 1.2468 1.2517 1.2510 1.2483 1.2426 1.2372 1.2331 34 6.61 1.1675 1.2051 1.2123 1.2149 1.2201 1.2127 1.2103 1.2066 1.2068 1.2031 35 6.81 1.2026 1.2397 1.2469 1.2490 1.2541 1.2443 1.2418 1.2384 1.2386 1.2348 36 7.01 1.2521 1.2913 1.2985 1.3000 1.3046 1.2918 1.2891 1.2855 1.2864 1.2823 37 7.21 1.2687 1.3090 1.3158 1.3171 1.3217 1.3069 1.3042 1.3016 1.3028 1.2988 38 7.41 1.2591 1.2997 1.3055 1.3074 1.3120 1.2955 1.2933 1.2924 1.2942 1.2907 39 7.61 1.2488 1.2896 1.2934 1.2967 1.3015 1.2833 1.2814 1.2823 1.2847 1.2816 40 7.81 1.2466 1.2875 1.2885 1.2940 1.2987 1.2781 1.2772 1.2797 1.2826 1.2798 41 8.01 1.2504 1.2911 1.2906 1.2969 1.3014 1.2802 1.2797 1.2825 1.2859 1.2835 42 8.21 1.2544 1.2950 1.2919 1.2998 1.3042 1.2857 1.2860 1.2849 1.2888 1.2866 43 8.41 1.2360 1.2747 1.2693 1.2789 1.2833 1.2709 1.2712 1.2661 1.2705 1.2690 44 8.61 1.1844 1.2179 1.2100 1.2216 1.2261 1.2202 1.2209 1.2160 1.2211 1.2207 45 8.81 1.1393 1.1661 1.1557 1.1691 1.1738 1.1742 1.1753 1.1711 1.1768 1.1768 46 9.01 1.1676 1.1867 1.1790 1.1923 1.1942 1.1963 1.1973 1.1945 1.1999 1.2000 47 9.21 1.2122 1.2188 1.2203 1.2272 1.2241 1.2272 1.2282 1.2351 1.2414 1.2416 48 9.41 1.2230 1.2248 1.2304 1.2325 1.2290 1.2319 1.2329 1.2443 1.2516 1.2519 49 9.61 1.2090 1.2116 1.2166 1.2156 1.2157 1.2177 1.2189 1.2298 1.2371 1.2378 50 9.81 1.1966 1.1969 1.2020 1.1979 1.1989 1.2014 1.2026 1.2161 1.2232 1.2242 51 10.01 1.1908 1.1872 1.1920 1.1874 1.1868 1.1895 1.1907 1.2051 1.2128 1.2139 52 10.21 1.1915 1.1836 1.1852 1.1790 1.1802 1.1808 1.1815 1.1980 1.2057 1.2068 53 10.41 1.1866 1.1742 1.1733 1.1679 1.1670 1.1657 1.1664 1.1823 1.1897 1.1905 54 10.61 1.1510 1.1323 1.1311 1.1252 1.1205 1.1199 1.1193 1.1350 1.1430 1.1437 55 10.81 1.0756 1.0481 1.0466 1.0364 1.0314 1.0325 1.0301 1.0457 1.0526 1.0536 56 11.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 57 11.21 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.41 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 11.61 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 60 11.81 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
[TOP] 61 12.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
- Linear extrapolation based on a line between 20,500 MWD/MTU and 22,000 MWD/MTU is adequate for addressing burnups beyond 22,000 MWD/MTU.
Page 17 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0 Table 4 (cont.): T(z) Factors associated with Figures 6, 7 and 8 (ROS2)
(Top 10% and Bottom 8% excluded)*
Height BU [MWd/MTU]
[ft] 10000 10500 11000 12000 12500 14500 18500 19000 20500 22000
[BOTTOM] 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1
2 0.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 3 0.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 4 0.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 5 0.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6 1.00 1.0775 1.0712 1.0767 1.0911 1.1133 1.1458 1.1877 1.1948 1.2193 1.2229 7 1.20 1.1347 1.1288 1.1349 1.1501 1.1729 1.2030 1.2363 1.2424 1.2639 1.2642 8 1.40 1.1725 1.1665 1.1723 1.1865 1.2088 1.2328 1.2551 1.2598 1.2777 1.2748 9 1.60 1.2062 1.2000 1.2053 1.2176 1.2389 1.2559 1.2676 1.2712 1.2858 1.2801 10 1.80 1.2195 1.2132 1.2178 1.2282 1.2482 1.2590 1.2630 1.2656 1.2777 1.2703 11 2.00 1.1932 1.1872 1.1913 1.1998 1.2183 1.2245 1.2242 1.2262 1.2370 1.2294 12 2.20 1.1610 1.1552 1.1585 1.1648 1.1816 1.1832 1.1798 1.1814 1.1912 1.1839 13 2.40 1.1865 1.1802 1.1823 1.1852 1.2003 1.1948 1.1854 1.1864 1.1948 1.1867 14 2.60 1.2261 1.2191 1.2198 1.2188 1.2324 1.2193 1.2042 1.2046 1.2120 1.2030 15 2.80 1.2371 1.2301 1.2298 1.2266 1.2377 1.2198 1.2015 1.2015 1.2073 1.1982 16 3.00 1.2281 1.2213 1.2203 1.2159 1.2240 1.2030 1.1839 1.1838 1.1869 1.1802 17 3.20 1.2240 1.2168 1.2150 1.2077 1.2143 1.1891 1.1709 1.1707 1.1703 1.1699 18 3.40 1.2260 1.2193 1.2168 1.2059 1.2119 1.1812 1.1653 1.1652 1.1594 1.1650 19 3.60 1.2359 1.2294 1.2261 1.2101 1.2171 1.1829 1.1680 1.1679 1.1596 1.1662 20 3.80 1.2496 1.2431 1.2392 1.2187 1.2263 1.1881 1.1733 1.1731 1.1655 1.1689 21 4.00 1.2446 1.2384 1.2341 1.2125 1.2185 1.1796 1.1650 1.1645 1.1593 1.1592 22 4.20 1.2079 1.2025 1.1984 1.1778 1.1820 1.1470 1.1324 1.1322 1.1295 1.1284 23 4.40 1.1726 1.1680 1.1641 1.1457 1.1470 1.1156 1.1014 1.1037 1.1010 1.1016 24 4.60 1.1994 1.1948 1.1902 1.1716 1.1695 1.1375 1.1217 1.1244 1.1202 1.1214 25 4.80 1.2411 1.2364 1.2309 1.2115 1.2060 1.1725 1.1544 1.1569 1.1508 1.1522 26 5.00 1.2543 1.2501 1.2442 1.2253 1.2163 1.1837 1.1649 1.1675 1.1607 1.1626 27 5.20 1.2448 1.2405 1.2346 1.2173 1.2064 1.1753 1.1574 1.1602 1.1539 1.1569 28 5.40 1.2361 1.2307 1.2248 1.2088 1.1982 1.1668 1.1495 1.1523 1.1476 1.1512 29 5.60 1.2359 1.2306 1.2249 1.2085 1.1982 1.1666 1.1485 1.1512 1.1493 1.1511 30 5.80 1.2446 1.2383 1.2329 1.2174 1.2054 1.1731 1.1578 1.1582 1.1582 1.1593 31 6.00 1.2577 1.2503 1.2441 1.2307 1.2175 1.1863 1.1726 1.1713 1.1703 1.1715 32 6.20 1.2515 1.2459 1.2369 1.2259 1.2149 1.1863 1.1720 1.1710 1.1676 1.1703 33 6.40 1.2141 1.2124 1.2002 1.1926 1.1850 1.1589 1.1467 1.1457 1.1409 1.1478 34 6.61 1.1807 1.1840 1.1686 1.1665 1.1601 1.1364 1.1256 1.1253 1.1194 1.1289 35 6.81 1.2123 1.2142 1.1986 1.1961 1.1900 1.1651 1.1527 1.1541 1.1455 1.1547 36 7.01 1.2571 1.2594 1.2418 1.2398 1.2338 1.2067 1.1941 1.1954 1.1837 1.1920 37 7.21 1.2728 1.2757 1.2599 1.2565 1.2511 1.2239 1.2126 1.2131 1.2001 1.2079 38 7.41 1.2653 1.2691 1.2573 1.2513 1.2473 1.2217 1.2120 1.2123 1.1992 1.2066 39 7.61 1.2573 1.2614 1.2533 1.2461 1.2429 1.2192 1.2107 1.2106 1.1973 1.2043 40 7.81 1.2571 1.2608 1.2558 1.2510 1.2455 1.2247 1.2149 1.2142 1.2007 1.2071 41 8.01 1.2650 1.2648 1.2639 1.2617 1.2547 1.2368 1.2250 1.2237 1.2097 1.2143 42 8.21 1.2745 1.2712 1.2723 1.2730 1.2650 1.2490 1.2355 1.2335 1.2192 1.2223 43 8.41 1.2626 1.2579 1.2596 1.2637 1.2547 1.2421 1.2278 1.2253 1.2115 1.2137 44 8.61 1.2179 1.2118 1.2144 1.2226 1.2129 1.2053 1.1935 1.1908 1.1789 1.1800 45 8.81 1.1775 1.1698 1.1733 1.1856 1.1750 1.1724 1.1659 1.1634 1.1555 1.1506 46 9.01 1.2040 1.1924 1.1965 1.2105 1.1997 1.2013 1.1917 1.1885 1.1808 1.1706 47 9.21 1.2416 1.2342 1.2394 1.2430 1.2457 1.2451 1.2303 1.2263 1.2142 1.2079 48 9.41 1.2522 1.2482 1.2543 1.2524 1.2636 1.2628 1.2438 1.2393 1.2280 1.2237 49 9.61 1.2403 1.2382 1.2450 1.2454 1.2567 1.2589 1.2380 1.2334 1.2288 1.2208 50 9.81 1.2254 1.2244 1.2318 1.2335 1.2463 1.2522 1.2338 1.2299 1.2308 1.2199 51 10.01 1.2184 1.2109 1.2183 1.2202 1.2340 1.2485 1.2345 1.2332 1.2371 1.2272 52 10.21 1.2115 1.2043 1.2119 1.2122 1.2261 1.2476 1.2353 1.2403 1.2458 1.2406 53 10.41 1.1981 1.1892 1.1970 1.1970 1.2109 1.2363 1.2337 1.2420 1.2474 1.2492 54 10.61 1.1554 1.1426 1.1505 1.1511 1.1658 1.1965 1.2095 1.2173 1.2254 1.2329 55 10.81 1.0656 1.0570 1.0646 1.0647 1.0804 1.1173 1.1442 1.1515 1.1668 1.1771 56 11.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 57 11.21 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.41 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 11.61 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 60 11.81 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
[TOP] 61 12.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
- Linear extrapolation based on a line between 20,500 MWD/MTU and 22,000 MWD/MTU is adequate for addressing burnups beyond 22,000 MWD/MTU.
Page 18 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0 Table 5: RJ Margin Decrease Factors associated with Figures 6, 7, and 8 (ROS2) and Table 4
Cycle RJ Cycle RJ Cycle RJ Burnup Penalty Burnup Penalty Burnup Penalty (MWD/MTU) Multiplier (MWD/MTU) Multiplier (MWD/MTU) Multiplier 150 1.042 7174 1.000 14198 1.000 321 1.038 7345 1.000 14370 1.000 493 1.034 7517 1.000 14541 1.000 664 1.030 7688 1.000 14712 1.000 835 1.026 7859 1.000 14884 1.000 1007 1.021 8031 1.000 15055 1.000 1178 1.018 8202 1.000 15226 1.000 1349 1.015 8373 1.000 15398 1.000 1521 1.013 8545 1.000 15569 1.000 1692 1.017 8716 1.000 15740 1.000 1863 1.017 8887 1.007 15912 1.000 2035 1.016 9059 1.007 16083 1.000 2206 1.014 9230 1.007 16254 1.000 2377 1.014 9401 1.007 16426 1.000 2548 1.012 9573 1.007 16597 1.000 2720 1.010 9744 1.006 16768 1.000 2891 1.008 9915 1.005 16939 1.000 3062 1.002 10087 1.004 17111 1.000 3234 1.000 10258 1.000 17282 1.000 3405 1.000 10429 1.000 17453 1.000 3576 1.000 10601 1.000 17625 1.000 3748 1.000 10772 1.000 17796 1.000 3919 1.005 10943 1.000 17967 1.001 4090 1.007 11115 1.001 18139 1.001 4262 1.007 11286 1.001 18310 1.002 4433 1.007 11457 1.003 18481 1.004 4604 1.008 11629 1.003 18653 1.004 4776 1.008 11800 1.004 18824 1.004 4947 1.009 11971 1.005 18995 1.004 5118 1.010 12142 1.006 19167 1.004 5290 1.010 12314 1.008 19338 1.004 5461 1.012 12485 1.007 19509 1.003 5632 1.012 12656 1.004 19681 1.003 5804 1.011 12828 1.002 19852 1.000 5975 1.010 12999 1.001 20023 1.000 6146 1.009 13170 1.000 20195 1.000 6318 1.008 13342 1.000 20366 1.000 6489 1.006 13513 1.000 20537 1.000 6660 1.005 13684 1.000 20709 1.000 6832 1.002 13856 1.000 7003 1.001 14027 1.000 Values may be interpolated to the surveillance cycle burnup. The Rj factor value for the last burnup step shall be used for all burnups greater than the last burnup step.
Page 19 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0
Table 6: Required THERMAL POWER Limits and AFD Reductions*
Required THERMAL RAOC Operating Required FQW(z) Margin POWER Limit
Space Improvement (%) (%RTP) Reference AFD Figure
ROS1
(Figure 5) > 0 < 50 N/A
2.9 95 Use Figure 7 ROS2
> 2.9 and 5.6 90 Use Figure 8 (Figure 6)
> 5.6 < 50 N/A
Page 20 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0 Figure 1
Reactor Core Safety Limits
680
2425 psia 660 2250 psia Unacceptable
640
1850 psia
620
600 Acceptable
580
560
540 0 0.2 0.4 0.6 0.8 1 1.2 1.4 Fraction of 1677 MWt Rated Thermal Pow er
Page 21 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0 Figure 2 Rod Insertion Limit, 128 Step Tip-to-Tip
B ank B 200
150
B ank C
100
B ank D
50
0 0 20 40 60 80 100 Powe r Le v e l, % of Rate d T he rmal Powe r Bank Positions Given By:
- Bank D = (150 / 63) * (P -100) + 185
- Bank C = (150 / 63) * (P -100) + 185 + 128
- Bank B = (150 / 63) * (P -100) + 185 + 128 + 128
NOTE: The top of the active fuel height corresponds to 224steps.
Page 22 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0 Figure 3 Rod Insertion Limit, 128 Step Tip-to-Tip, One Bottomed Rod (Technical Specification 3.1.4, Condition B)
224
200
Bank C
150
Operation Forbidden in this Region
100
Bank D 50
0 0 20 40 60 80 100
Power Level, % of Rated Thermal Power
Bank Positions Given By:
- Bank D = (150 / 63) * (P -90) + 224
- Bank C = (150 / 63) * (P -90) + 224+ 128
NOTE: The top of the active fuel height corresponds to 224steps.
Page 23 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0
Figure 4 Rod Insertion Limit, 128 Step Tip -to-Tip, One Inoperable Rod (Technical Specification 3.1.4, Condition A) 224
200
Bank C
150
Operation Forbidden in Bank D this Region 100
50
0 0 20 40 60 80 100
Power Level, % of Rated Thermal Power
Bank Positions Given By:
- Bank D = (150 / 63) * (P -70) + 224
- Bank C = (150 / 63) * (P -70) + 224+ 128
NOTE: The top of the active fuel height corresponds to 224steps.
Page 24 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0
Figure 5 Flux Difference Operating Envelope associated with ROS1(Tables 2 and 3)
110
-9 8 100 Unacceptable Unacceptable
90
Acceptable 80
70
60
50
-22 21
40
30
20
10
0
-25 -20 -15 -10 -5 0 5 10 15 20 25 I %
Page 25 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0 Figure 6 Flux Difference Operating Envelope associated with ROS2 (Tables 4 and 5) 110
-7 6 100 Unacceptable Unacceptable
90
Acceptable 80
70
60
50 -20 19
40
30
20
10
0
-25 -20 -15 -10 -5 0 5 10 15 20 25 I %
Page 26 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0
Figure 7 Flux Difference Operating Envelope associated with ROS2 95% THERMAL POWER Required Action (Tables 4, 5, and 6) 110
100 Unacceptable -7, 95 6, 95Unacceptable
90
Acceptable 80
70
60
50
-18.7 17.7
40
30
20
10
0
-25 -20 -15 -10 -5 0 5 10 15 20 25 I %
Page 27 of 28 Core Operating Limits Report Unit 2, Cycle 33 Revision 0
Figure 8 Flux Difference Operating Envelope associated with ROS2 90% THERMAL POWER Required Action (Tables 4, 5 and 6) 110
100 Unacceptable Unacceptable
-7, 90 6, 90 90
Acceptable 80
70
60
50
-17.4 16.4
40
30
20
10
0
-25 -20 -15 -10 -5 0 5 10 15 20 25 I %
Page 28 of 28