RBG-46102, Unit 1, Twelfth Fuel Cycle Core Operating Limits Report (COLR)

Unit 1, Twelfth Fuel Cycle Core Operating Limits Report (COLR)

ML031080618
Person / Time
Site:	River Bend
Issue date:	04/14/2003
From:	King R Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RBF1-03-0066, RBG-46102
Download: ML031080618 (61)

Text

N Entergy Operations, Inc.

River Bend Station 5485 U S Highway 61 P 0 Box 220 St Francisville, LA 70775 tego Tel 225 336 6225 Fax 225 635 5068 Rick J. King Director Nuclear Safety Assurance April 14, 2003 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Subject:

River Bend Station - Unit 1 Docket No. 50-458 License No. NPF-47 Twelfth Fuel Cycle Core Operating Limits Report (COLR)

File Nos.: G9.5, G9.25.1.5 RBG-46102 RBF1-03-0066 Ladies and Gentlemen:

Enclosed is Revision 1 of the River Bend Station (RBS) Core Operation Limits Report (COLR) for the twelfth fuel cycle. This report is submitted in accordance with Technical Specification 5.6.5 of Appendix A of the Facility Operating License NPF-47. This COLR report will support operation from beginning of cycle 12 through 5200 MWd/MTU, approximately 6 months.

There are no commitments in this letter. For further information, contact Mr. B. M. Burmeister at (225) 381-4148.

Sincerely, RJK/BMB Enclosure

Twelfth Fuel Cycle Core Operating Limits Report (COLR)

RBG-46102 RBF1-03-0066 Page 2 of 2 cc: Mr. Michael Webb U. S. Nuclear Regulatory Commission M/S OWFN 07-Dl Washington, DC 20555 NRC Resident Inspector P. 0. Box 1050 St. Francisville, LA 70775 U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011

Core Operating Limits Report Cycle 12 Revision 0

Page 1 of 58 RBS CYCLE 12 COLR Revision 0 RIVER BEND STATION, CYCLE 12 CORE OPERATING LIMITS REPORT (COLR)

PREPARED BY: Date: _ _ 3 Responsible Engineer REVIEWED BY: ,/t O Date: _1710 3_

Review Engineer APPROVED BY: Date: /

gr NuclearEngineering APPROVED BY: Date: __7__ 3 Director, Engineering River Bend Nuclear Station APPROVED BY: Date: i/X+3

>-site SaYety Review Committee River Bend Nuclear Station

Page 2 of 58 RBS CYCLE 12 COLR Revision 0 TABLE OF CONTENTS INTRODUCTION AND

SUMMARY

............................................................. 3 CONTROL RODS .............................................................. 4 TECHNICAL SPECIFICATION 3.2.1 ............................................................. 5 TECHNICAL SPECIFICATION 3.2.2 ............................................................. 6 TECHNICAL SPECIFICATION 3.2.3 ............................................................. 7 TECHNICAL SPECIFICATION 3.2.4 .............................................................. 8 TECHNICAL SPECIFICATION 3.3.1.1 ............................................................. 9 TECHNICAL SPECIFICATION 3.3.1.3 ............................................................ 10 TECHNICAL REQUIREMENT 3.3.1.1 .............................................................. 1.1 TECHNICAL REQUIREMENT 3.3.2.1 ............................................................ 12 REFERENCES/ANALYTICAL METHODS DOCUMENTS .......................................... 13 TABLE 1. ALIGNED DRIVE FLOW ............................................................. 15 APPENDIX A - OPERATING LIMITS FOR EQUIPMENT OUT OF SERVICE OR LOOP MANUAL MODE ............................................................ 45

Page 3 of 58 RBS CYCLE 12 COLR Revision 0 INTRODUCTION AND

SUMMARY

This report provides Cycle 12 values for the following Technical Specifications:

I. AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) limits,

2. MINIMUM CRITICAL POWER RATIO (MCPR) limits,

3. LINEAR HEAT GENERATION RATE (LHGR) limits,

4. FRACTION OF CORE BOILING BOUNDARY (FCBB),

5. REACTOR PROTECTION SYSTEM (RPS) APRM Flow Biased Simulated Thermal Power - High Allowable Values,

6. REACTOR PROTECTION SYSTEM (RPS) APRM Flow Biased Simulated Thermal Power time constant.

7. PERIOD BASED DETECTION SYSTEM (PBDS) region boundaries.

Technical Specification section 5.6.5 requires these values be determined using NRC-approved methodology and are established such that all applicable limits of the plant safety analysis are met. The references for the pertinent methodology used by FRA-ANP are listed in the section titled Analytical Methods Documents.

This report also provides Cycle 12 values for the following Technical Requirements:

1. REACTOR PROTECTION SYSTEM (RPS) APRM Flow Biased Neutron Flux Power - High Allowable Values and Nominal Trip Setpoints ,

2. CONTROL ROD BLOCK INSTRUMENTATION APRM Flow Biased Neutron Flux High limits.

In some cases limits in the COLR differ from the limits in the core monitoring system.

This is sometimes due to limitations in the core monitoring system to model the actual limits, in which case the core monitoring limits may be more conservative than the COLR limit. In other cases the limits in the COLR are presented in less detail than in the core monitoring system. When these situations exist the core monitoring limits will be explained or be referenced by the COLR and will be made available to Operations.

The Cycle 12 COLR supports power operation with FHOOS, FFWTR, PROOS, SLO and Loop Manual Operation. In addition to the specific requirements listed in the Sections 3.2.1 to 3.2.4, the MCPRp and LHGRFAC-p limits as shown in Appendix A shall be used for the applicable modes of operation. For Loop Manual Operation, the MCPRf as shown in Appendix A shall be used. Figures 36 and 37 are applicable to FHOOS or PROOS but not for simultaneous FHOOS and PROOS.

The core operating limits in this report are applicable to a cycle exposure of up to 5200 MWDJMTU. The reload analyses were performed in accordance with FRA-ANP methodology and its applicability to Cycle 12 was confirmed by Reference 5.

'Note that for Figures 22 to 29, the Nominal Setpoints should be used for indicating the entry into a particular stability region as allowed and appropriate actions be taken prior to the entry

Page 4 of 58 RBS CYCLE 12 COLR Revision 0 CONTROL RODS The River Bend core utilizes both GE control rods and ABB CR-82M bottom entry cruciform control rods. These Control Rod designs are discussed in more detail in Reference 7.

DEFINITIONS BOC - Beginning of Cycle.

MOC - Middle of Cycle.

EOC - End of Cycle.

EEOC - Extended cycle with Increased Core Flow.

EEEOC - Extended cycle with Increased Core Flow and Final Feedwater Temperature Reduction.

FFWTR - Final Feedwater Temperature Reduction.

FHOOS - Feedwater Heater Out of Service.

PROOS - Pressure Regulator Out of Service.

SLO - Single Loop Operation.

FRA-ANP - Frarnatome ANP KAN - The designator for the once-burnt ATRIUM-1O assemblies.

Page 5 of 58 RBS CYCLE 12 COLR Revision 0 TECHNICAL SPECIFICATION 3.2.1 POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

The limiting APLHGR (sometimes referred to as Maximum APLHGR, or MAPLHGR) value for the most limiting lattice (excluding natural uranium) of each fuel type as a function of AVERAGE PLANAR EXPOSURE is given in Figures 2 through 5. Two sets of MAPLHGR are provided herein for ATRIUM-10 and GE-I l. The GE- Il set was determined with the SAFER/GESTR LOCA and GESTR-Mechanical methodology described in GESTAR-Il (Reference 1).

The ATRIUM- 10 set was determined with the FRA-ANP methodology (Reference 5). Core location by fuel type is provided in Figure 1 and is the reference core loading pattern in reference 5. These figures are used if alternate calculations are required. The limits of these figures shall be reduced to a value of 0.79 and 0.83 times the two recirculation loop operation limit when in single loop operation for GE-I1 and ATRIUM-10, respectively (Reference 5). Thermal power and core flow dependent multipliers are provided. The value of the exposure dependent limit is reduced by the value of the multiplier at a given offrated power or flow condition. The multipliers for single loop operation are shown in Appendix A.

The APLHGR limits for GE-I 1 in the core monitoring system are in more detail than the limits that appear in the COLR due to their proprietary nature. The core monitoring system has APLHGR limits for each lattice in a bundle rather than listing only the most limiting value for the entire bundle. References 4 and 5 list the core monitoring system limits.

Page 6 of 58 RBS CYCLE 12 COLR Revision 0 TECHNICAL SPECIFICATION 3.2.2 POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)

The MCPR limits for use in Technical Specification 3.2.2 for flow dependent MCPR (MCPRF) (Reference 5), power dependent MCPR (MCPRp) (Reference 5) are shown in Figures 10, 11, 12 and Figures 15, 16, 17, respectively. Figures 40, 41 and 42 are used in lieu of Figures 10, 11 and 12 when the Reactor Recirculation System is operating in Loop Manual Mode. The most limiting value from the applicable MCPRr and MCPR, figures is the operating limit.

These values were determined with FRA-ANP methodology as described in Reference 5 and are consistent with a Safety Limit MCPR from Technical Specification 2.0. At a power level greater than 40%, the power dependent MCPRp (Figures 15, 16 and 17) shall be increased by 0.02 for Single Loop Operation. At a power lower than 40%, the most limiting MCPRp value is the operating limit, and it shall be increased by 0.02 for Single Loop Operation.

Page 7 of 58 RBS CYCLE 12 COLR Revision 0 TECHNICAL SPECIFICATION 3.2.3 POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE (LHGR)

The limiting LHGR value for ATRIUM-10 and for the most limiting lattice of each GE- I I fuel type as a function of AVERAGE PLANAR EXPOSURE is given in Figures 6 through 9. Core location by fuel type is provided in Figure I and is the reference core loading pattern in reference 5. These figures are used if alternate calculations are required. The LHGR limits for GE-I I in the core monitoring system are in more detail than the limits that appear in the COLR due to proprietary nature (Reference 9). Thermal power and core flow dependent multipliers for ATRIUM-10 and GE-Il are provided in Figures 13 & 18 and Figures 14 & 19, respectively. The value of the exposure dependent limit is reduced by the value of the multiplier at a given offrated power or flow condition.

Page 8 of 58 RBS CYCLE 12 COLR Revision 0 TECHNICAL SPECIFICATION 3.2.4 POWER DISTRIBUTION LIMITS FRACTION OF CORE BOILING BOUNDARY (FCBB)

Restricted Region Boundary Vote: The boundary of the Restricted Region is established by analysis in terms of thermal power and core flow. The Restricted Region boundary is defined by the "non-setup" APRM Flow Biased Simulated Thermal Power - High Control Rod Block Setpoints. which are afunction of reactor recirculationdriveflow.

The Restricted Region boundaries as a function of aligned drive flow are given in Figures 22 through 25 in terms of aligned drive flow. The aligned drive flow is calculated from the input drive flow using the relationship given in Table 1.

Flow Biased Simulated Thermal Power - High Limits The APRM Flow Biased Simulated Thermal Power - High Scram setpoints as a function of aligned drive flow are given in Figures 22 through 25. The aligned drive flow is calculated from the input drive flow using the relationship given in Table 1.

a. Case I - Normal Feedwater Heating Operation or Low Reactor Power:

T, (at rated) TFSGN (at rated)- 50 F, and rated equivalent at off-rated reactor conditions.

OR P < 30%

b. Case 2 - Reduced Feedwater Heating Operation TFW (at rated) < TFw"" (at rated) - 50 F and rated equivalent at off-rated reactor conditions.

AND P>30%

Where: TFw is feedwater temperature in 'F, and P is reactor power in percent of rated.

Page 9 of 58 RBS CYCLE 12 COLR Revision 0 TECHNICAL SPECIFICATION 3.3.1.1 INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION AVERAGE POWER RANGE MONITORS APRM Flow Biased Simulated Thermal Power - High Limits The APRM Flow Biased Simulated Thermal Power - High scram setpoint Allowable Values are given in Figures 22 through 25 in terms of aligned drive flow. The aligned drive flow is calculated from the input drive flow using the relationship given in Table 1.

a. Case I - Normal Feedwater Heating Operation or Low Reactor Power:

TFW (at rated) ' TFs"' (at rated) - 500 F, and rated equivalent at off-rated reactor conditions.

OR P <30%

b. Case 2 - Reduced Feedwater Heating Operation TFw (at rated) < T DESIGN (at rated) - 50° F and rated equivalent at off-rated reactor conditions.

AND P>30%

Where: TFW is feedwater temperature in 'F, and P is reactor power in percent of rated.

APRM Simulated Thermal Power Time Constant The simulated thermal power time constant for use in Technical Specification Table 3.3.1.1-1, SR 3.3.1.1.14, is (Reference 6):

6 +/- 0.6 seconds.

The maximum simulated thermal power time constant for use in Technical Specification surveillance Table 3.3.1.1-1, SR 3.3.1.1.14 is:

6.6 seconds

Page 10 of 58 RBS CYCLE 12 COLR Revision 0 TECHNICAL SPECIFICATION 3.3.1.3 INSTRUMENTATION PERIOD BASED DETECTION SYSTEM (PBDS)

Monitored Region Boundary The Monitored Region Boundaries as a function of core flow are given in Figures 20 and 21.

Restricted Region Boundary Vote: The boundary of the Restricted Region is established by analysis in terms of thermal power and core flow. The Restricted Region boundary is defined by the "non-setup' APRM Flow Biased Simulated Thermal Power - High Control Rod Block Setpoints, which are a function ofreactorrecirculationdriveflow.

The Restricted Region boundaries as a function of aligned drive flow are given in Figures 22 through 25 in terms of aligned drive flow. The aligned drive flow is calculated from the input drive flow using the relationship given in Table 1.

a. Case I - Normal Feedwater Heating Operation or Low Reactor Power:

TFN; (at rated) > TFWs"' (at rated) - 500 F, and rated equivalent at off-rated reactor conditions.

OR P <30%

b. Case 2 - Reduced Feedwater Heating Operation TFW (at rated) < TFs"' (at rated) - 500 F, and rated equivalent at off-rated reactor conditions.

AND P>30%

Where: TFw is feedwater temperature in 'F, and P is reactor power in percent of rated.

Page 11 of 58 RBS CYCLE 12 COLR Revision 0 TECHNICAL REOUIREMENT 3.3.1.1 INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION AVERAGE POWER RANGE MONITORS APRM Flow Biased Simulated Thermal Power - High Limits The APRM Flow Biased Simulated Thermal Power - High scram setpoint Nominal Trip Setpoints are given in Figures 22 through 25 in terms of aligned drive flow. The aligned drive flow is calculated from the input drive flow using the relationship given in Table 1.

a. Case 1 - Normal Feedwater Heating Operation or Low Reactor Power:

TFW (at rated) ' TSGN(at rated)- 50 F, and rated equivalent at off-rated reactor conditions.

OR P <30%

b. Case 2 - Reduced Feedwater Heating Operation TFV (at rated) < TFs" (at rated) - 500 F, and rated equivalent at off-rated reactor conditions.

AND P>30%

Where: TFw is feedwater temperature in 'F, and P is reactor power in percent of rated.

Page 12 of 58 RBS CYCLE 12 COLR Revision 0 TECHNICAL REQUIREMENT 3.3.2.1 INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION AVERAGE POWER RANGE MONITORS APRM Flow Biased Neutron Flux - High Limits The APRM Flow Biased Neutron Flux - High rod block Allowable Values and Nominal Trip Setpoints are given in Figures 26 through 29 in terms of aligned drive flow. The aligned drive flow is calculated from the input drive flow using the relationship given in Table 1.

a. Case I - Normal Feedwater Heating Operation or Low Reactor Power:

TFW (at rated) 2 TFw's" (at rated) - 500 F, and rated equivalent at off-rated reactor conditions.

OR P <30%

b. Case 2 - Reduced Feedwater Heating Operation TF V (at rated) < TFw" (at rated) - 500 F.

and rated equivalent at off-rated reactor conditions.

AND P>30%

Where: TFw is feedwater temperature in 'F, and P is reactor power in percent of rated.

Page 13 of 58 RBS CYCLE 12 COLR Revision 0 REFERENCES

1) NEDE-2401 1-P-A-14 and US Supplement, "General Electric Standard Application for Reactor Fuel," June 2000.

2) Letter, J.S. Charnley (GE) to M.W. Hodges (NRC), Recommended MAPLHGR Technical Specifications for Multiple Lattice Fuel Designs, March 9,1987

3) 11 1-03660SRLR Rev. 2 Supplemental Reload Licensing Report for River Bend Station Reload 9 Cycle 10" November 2000.

4) J I11-03660MAPL, Revision I "Lattice Dependent MAPLHGR Report for River Bend Station Reload 9 Cycle 10" November 2000.

5) (a)EMF-2848, "River Bend Station Cycle 12 Reload Analysis." (b) Letter from Framatome-ANP to E0I, RBC-49962."

6) Letter, R.E. Kingston to G. W. Scronce. "Time Constant Values for Simulated Thermnal Power Monitor" GFP-1032 November 30, 1995.

7) RBS USAR Section 4.1

8) CEO 2003-00047, "River Bend Station Unit I EIA Stability Power Uprate Evalutaion."

9) RBC-48838, "Transmittal of River Bend Cycle 10 LHGR/MAPLHGR Relaxation Results."

ANALYTICAL METHODS DOCUMENTS (TS 5.6.5):

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

2) XN.NF-85-67(P)(A) Revision 1. Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel, Exxon Nuclear Company, September 1986.

3) EMF-85-74(P) Revision 0 Supplement I (P)(A) and Supplement 2 (PXA), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, Siemens Power Corporation, February 1998.

4) ANF-89-98(PXA) Revision I and Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.

5) XN-NF-80-19(PXA) Volume 1, Exxon Nuclear Methodology for Boiling Water Reactors -

Neutronic Methods for Design and Analysis, Exxon Nuclear Company, March 1983.

6) XN-NF-80-19(PXA) Vohume 4 Revision 1, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, Exxon Nuclear Company, June 1986.

7) EMF-2158 (PXA) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-41MICROBURN-B2, Siemens Power Corporation, October 1999.

8) XN-NF-80-19(P)(A) Volume 3 Revision 2, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limuts Methodology Sununary Description, Exxon Nuclear Company, January 1987.

9) XN-NF-84-l05(PXA) Volume I and Volume I Supplements I and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis, Exxon Nuclear Company, February 1987.

Page 14 of 58 RBS CYCLE 12 COLR Revision 0

10) ANF-524(PXA) Revision 2 and Supplements I and 2, ANF Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.

11) ANF-913(P)(A) Volume I Revision I and Volume I Supplements 2, 3 and 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation: August 1990.

12) XN-NF-825(P)(A) Supplement 2, BWR/6 Generic Rod Withdrawal Error Analysis, MCPRp for Plant Operations within the Extended Operatng Domain, Exxon Nuclear Company, October 1986.

13) ANF-1358(P)(A) Revision 1,The Loss of Feedwater Heating Transient in Boiling Water Reactors, Advanced Nuclear Fuels Corporation, September 1992.

14) EMF-1997(PXA) Revision 0, ANFB-10 Critical Power Correlation, Siemens Power Corporation, July 1998.

15) EMF-1997(P) Supplement I (P)(A) Revision 0, ANFB- 0 Critical Power Correlation: High Local Peaking Results, Siemens Power Corporation, July 1998.

16) EMF-2209(P)(A) Revision 1, SPCB Critical Power Correlation, Siemens Power Corporation, July 2000.

17) EMF-2245(P)(A) Revision 0, Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel, Siemens Power Corporation, August 2000.

18) \XN-NF-80-19(P)(A) Volumes 2, 2A, 2B, and 2C, Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECCS Evaluation Model, Exxon Nuclear Company, September 1982.

19) ANF-91-048(PXA), Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors EXEM BWR Evaluation Model, Advanced Nuclear Fuels Corporation, January 1993.

20) ANF-91-048(PXA) Supplements I and 2, BWR Jet Pump Model Revision for RELAX, Siemens Power Corporation, October 1997.

21) XN-CC-33(A) Revision I. HUXY: A Generalized Multirod Heatup Code with 10 CFR 50 Appendix K Heatup Option Users Manual, Exxon Nuclear Company, November 1975.

22) EMF.CC-074(PKA) Volume 4 Revision 0, BWR Stability Analysis: Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.

23) EMF-2292(P)(A) Revision 0, ATRIUMM9-10 Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.

24) NEDE-2401 I-P-A-14 and US Supplement, "General Electric Standard Application for Reactor Fuel," June 2000.

Page 15 of 58 RBS CYCLE 12 COLR Revision 0 Table 1. Aligned Drive Flow 101 209..&AO -31.028 -A' + 70.181 - Wa w:) =

70.181 - ( AlO0 - 440 Where:

W6 = FCTR card input drive flow in percent rated, WD = Aligned drive flow in percent rated, A40 = Low flow drive flow alignment setting, and A100 = High flow drive flow alignment setting.

Page 16 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 1. REFERENCE CORE LOADING PATTERN 29 31 33 35 37 39 41 43 45 47 49 51 53 55 28 19 21 23 20 23 20 23 20 23 24 23 23 14 is 32.7 17.2 0.0 18.7 0.0 18.9 0.0 18.3 0.0 0.0 0.0 0.0 32.8 26.0 26 21 23 21 23 24 23 21 23 21 23 19 23 21 14 17.0 0.0 14.3 0.0 0.0 0.0 18.5 0.0 18.7 0.0 32.5 0.0 19.3 35.7 24 23 21 19 21 19 20 23 21 23 24 23 22 14 14 0.0 14.3 32.6 13.6 33.8 17.9 0.0 17.5 0.0 0.0 0.0 0.0 33.5 35.2 22 20 23 21 23 21 23 21 23 20 22 24 22 14 is 18.6 0.0 13.5 0.0 18.4 0.0 15.9 0.0 17.5 0.0 0.0 0.0 31.1 28.2 20 23 24 19 21 23 21 19 21 19 is 23 21 14 0.0 0.0 33.7 18.0 0.0 17.6 33.6 14.9 33.6 32.2 0.0 18.5 32.6 18 20 23 20 23 21 22 19 22 is 22 24 21 is 16.9 0.0 17.5 0.0 17.4 0.0 30.5 0.0 31.9 0.0 0.0 18.1 26.9 16 23 21 23 21 19 19 22 21 22 14 22 14 14 0.0 18.4 0.0 15.7 33.4 31.1 0.0 17.4 0.0 36.0 0.0 34.9 31.6 14 20 23 21 23 21 22 21 22 19 21 is 14 17.8 0.0 17.5 0.0 14.8 0.0 17.3 0.0 33.6 16.0 30.1 33.9 12 23 21 23 20 19 15 22 19 19 15 14 0.0 18.2 0.0 17.5 33.2 31.8 0.0 33.5 32.9 30.5 32.4 10 24 23 24 22 is 22 14 21 is 14 0.0 0.0 0.0 0.0 32.0 0.0 35.9 15.9 30.4 35.8 8 23 19 23 24 23 24 22 15 14 0.0 32.4 0.0 0.0 0.0 0.0 0.0 30.2 33.7 6 23 23 22 22 21 21 14 14 0.0 0.0 0.0 0.0 17.7 18.1 32.6 34.2 4 14 21 14 14 14 15 15 Nuclear Fuel Type 32.8 18.9 32.6 31.1 31.8 26.4 30.4 BOC Exposure (GWd/MTU) 2 15 14 14 is 26.3 33.2 34.9 28.2 Fuel Type Description . Cycle Loaded 14 GEll 3.88B-13GZ-120T-146 9 15 GEll 4.00B-13GZ-120T-146 9 19 GEll 3.36B-12GZ-120T-146 10 20 ATRIUM-10 A10-3552B-12GV60 11 21 ATRIUM-10 A10-3899B-12GV60 11 22 ATRIUM-10 A10-3996B-11G45 12 23 ATRIUM-10 A10-3981B-15GV75 12 24 ATRIUM-10 A10-1997B-OGd 12

Page 17 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 2. MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FOR ATRIUM-10 13 13 1 ---. _________ - _________

12 12 I - - -- - .---- ---- - _____

r - --- ---- - -- ---- _____ --

11 11 LU r -. - - ------ - -.-- - ..-.--

I - - -- ------ --- - ----- - .--

z 10 10 LU 0

m z 9 9 8 8 LU 0

4 7 7

.2 6 6 5

h7r7 5 0 10 20 30 40 50 60 Average Planar Exposure (GWd/MT)

Page 18 of 58 RIBS CYCLE 12 COLR Revision 0 FIGURE 3. MAXIMMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE GElI1-P9SUB336-12GZ-120T-146-T 13 13 12 z

11 z

Lu 0 lo 10 Lu z 9 717i~

8 zz +/-- __

0.

17 Lu 7

6 5 5 0 10 20 30 40 50 60 AVERAGE PLANAR EXPOSURE (GWdIMT)

Page 19 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 4. MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FOR GEl1-P9SUB400-13GZ-120T-146-T 13 13 12 12 z

211 Nu 11 z

0 E 10 10 9

0 IL i 8

UJ

>7 ui7 7 6 6 5 5 0 10 20 30 40 50 60 AVERAGE PLANAR EXPOSURE (GWd/MT)

Page 20 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 5. MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FOR GE1 I-P9SUB388-13GZ-120T-146-T 13 13 12 11 10 10 I. - --

9 8

w - -. _

4.. - - - - - . - ._ _ _ _

7 71 -_ _ _ _ _ _ _ _ _ __6_ _ _ _ _ _

6 5

0 10 20 30 40 50 60 AVERAGE PLANAR EXPOSURE (GWd/MT)

Page 21 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 6. LINEAR HEAT GENERATION RATE (LHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE FOR ATRIUM-10 14 14 13 I

____Y__ - -- - -N

.. _ ___ ___=_ =- 13

N-- ---

7,i-i-,

12 I

i -: -

- - --- :I-

- L---_, - = -

12 I -- - .- - . - - 1-- - -

§ 11 11 F

0 Ig 10 I c 0 q 6*

-4.. ----- -

4.

t 10 0

c 0 9 0 8

-J 8

3 7 _ _ _

7 6 6 5 5 0 10 20 30 40 50 60 Average Planar Exposure (GWdIMT)

Page 22 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 7. LINEAR HEAT GENERATION RATE (LHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE GEI I-P9SUB400-13GZ-120T-146-T 15 15 14 14

_ 13 13 12 12 I-S Z' 12 W. 11 zl 10 10 I-CD =7 7 9

ZS 2<

U 8 1. I I 6 6 8

7 I - __

- zrz4 7 7

- -- a- - -

6 6 5 5 0 10 20 30 40 50 60 AVERAGE PLANAR EXPOSURE (GWd/MT)

Page 23 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 8. LINEAR HEAT GENERATION RATE (LHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE GE11-P9SUB336-12GZ-

- 120T-146-T 15 15 14 14 13 13: .-- - -

- 4[lik- -f=- -

WU 12 I 12 ZI-i 11 0

1o

~ H-. _ __7_ _

10 w

9 w

8

=w

-j:

7 6 6 5 5 0 10 20 30 40 50 60 AVERAGE PLANAR EXPOSURE (GWd/MT)

Page 24 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 9. LINEAR HEAT GENERATION RATE (LHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE GE1 1-PSUB388-13GZ-120T-146-T 15 15

7 14 14

-77

-7:7 7 13 13 L Z 9-12 12 z 11

-77 7. z 11 I-0 10 10 z

zA- 9 9 CD w

8 8 z 7 7 6 6 5 5 0 10 20 30 40 50 60 AVERAGE PLANAR EXPOSURE (GWdIMT)

Page 25 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 10. OPERATING LIMIT MCPR (MCPRF) VERSUS CORE FLOW FOR NON-KAN ATRIUM-10 FOR RECIRCULATION SYSTEM IN LOOP AUTO CONTROL, ALL EXPOSURES

.9- - n- -t - - i- Ad-- --

1.l*<-- I_-1, 1.4____

-.- ___ i.

i, = 1

. - S_. x I; :_

0 10 2) 30 40 0) 60 ;0 8) 90 1C0 110 123 cb PDV, %rctEd

Page 26 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 11. OPERATING LIMIT MCPR (MCPRF) VERSUS CORE FLOW FOR KAN ATRIUM-10 FOR RECIRCULATION SYSTEM IN LOOP AUTO CONTROL, ALL EXPOSURES

.s(J -

)! - - - - - _._._

1AC: I ----- C----- - - -- -- -- ---

1.E L, -

5! 1.3:

0~

I ------------- __, __

12:

Ii 1.10 I

i I I I .

I

--1. 11

- - I- .. . .I. , - - L-- - - - -

I m t

,.t I 4 4- 4 .4 4- I .5 I1 -

4-'

- I I

Liii YjIi I 0 10 2O 30 40 53 60 7 8 90 1W0 110 12D cbre FN, %rcki

Page 27 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 12. OPERATING LIMIT MCPR (MCPRF) VERSUS CORE FLOW FOR GE-1I1 FOR RECIRCULATION SYSTEM IN LOOP AUTO CONTROL, ALL EXPOSURES 1.60 1.50

._ 147 , _ -

I *, _- . . _-135s= -__

1.40 Nii E

ix 1.30 I - - -- -. _- -.- _

a.

01 1.20

__-- -. +/- _-'__ 1;15 I i0 L L __ i =-i_=_il 4-- i I\

KI1 I,. i I I Ii 1.' I Ah I

I - . . -.-- - - i, i . . I !+,ll  ! --

1.00 t~~ , I 0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow, % rated

Page 28 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 13. LHGR MULTIPLIER VERSUS CORE FLOW FOR ALL ATRIUM-10, ALL EXPOSURES 1.10 - - - - - . _= 1 1.00 100 1.00 - - - - -- - -

LL 0.9---0 90 toe. --

_e ' _ 1 __

07 0.80 - -7__ - - - - - --

i7o .. . ___ ___ __._ _.

0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow, % rated

Page 29 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 14. LHGR AND MAPLHGR MULTIPLIER VERSUS CORE FLOW FOR GE-il, ALL EXPOSURES 1.10 - - -

1.00 1.00 C - _ 3 0.90----1: - - '-- .- =- ' = -- - - --:-- t oIo - _ __ _ _- _- _- _ _ _- -

0.70 - - _- - - - - - - -

O D' __. __4 ___ _. - _ ._A I~ . _ ~ __ _I _. _

0.70 0.60 ,o6 h- -- - - - - - - -

= ~~~*

= I 0 10 20 30 40 50 60 70 80 90 100 110 120 Core Rtow, % rated

Page 30 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 15. OPERATING LIMIT MCPR (MCPRP) VERSUS CORE POWER FOR NON-KAN ATRIUM-10, EXPOSURE RANGE BOC TO BOC + 5200 MIWD/MTU 2..

2.3 -= [:r - =z -__ ...

2.2 - .216Z -Z 2 ~w1

-; -^. _ -_ .

o.E ~2.17  % a--x _ -___ __ ___ .. _ __ . __

20 IL= 2E - _ __ _ -

158 1471;*:: - 9__ r._

1-9., . -- __I f ,~: . _

1.3 1.2 1.0 t 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated

Page 31 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 16. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR KAN ATRIUM-10, EXPOSURE RANGE BOC TO BOC

+ 5200 MWD/MTU 2.3 2.19- _ . _

2.2 2.1 2.0

- - 1~88- ~-

1.9 I - - ---

1.8 L

. .- - -2 -- : _- -- _:___:_

14-.-- _  :=

-J!1.7

! -- ---- --. - - - - - ---- ~

---

2 0:

'L 1.6 - 53---- -- ----

1.5 1.4 1.3 1.2 1.1 I -- z 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated

Page 32 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 17. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR GE-il, EXPOSURE RANGE BOC TO BOC + 5200 MWD/MTU 2.1 2.0

. -_-5zhFow --- -_--...-. -- -- -_- .- -.

1.9 1.8

-- -1 -- -- -- --

1.7

• 19.437--

E

. 1.6 ol1.5

.4 1.3 1.2 1.1 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated

Page 33 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 18. LHGR MULTIPLIER VERSUS CORE POWER FOR ALL ATRIUM-10, EXPOSURE RANGE BOC TO BOC + 5200 MWDJMTU 1.10

. _, _-- ==_ ---- -- - -- 0--

1 .00--

I.. _. __ _-I- ___ . -_l 0.90:-- 8- - - - - - - -

_, aw_ ___50% _

0.80 0 77 ,.

--0.76----- = - ---

- 0.72-- - __7 ==- _- _-

!- -- =slyt = = =

0.70 I _ -

0.. 0 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated

Page 34 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 19. LHGR AND MAPLHGR MULTIPLIER VERSUS CORE POWER FOR GE-1l, ALL EXPOSURES (BOC TO BOC +

5200 MWD/MTU) 1.10 1.05 1.00 i

0.95 0.90 I 0.85 C.,

0.80 CD 0.75 x

-j 0.70 0.65 0.60 .

0.55 0.50 0.45 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated

Page 35 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 20. MONITORED REGION BOUNDARY (CASE 1) 120 *7 110 100-90 .0

~80

~70 WJ 60 2 50 w

W 40 0

030 20 10 0 10 20 30 40 50 60 70 80 90 100 110 CORE FLOW(% rated)

Page 36 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 21. MONITORED REGION BOUNDARY (CASE 2) 120 110 100 90

~80 0 70 uj 60 RGO Ce 40 0

C)30 20 10 0

0 10 20 30 40 50 60 70 80 90 100 110 CORE FLOW (% rated)

Page 37 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 22. APRM FLOW BIASED SIMULATED THERMAL POWER

- HIGH SCRAM SETPOINTS AND RESTRICTED REGION BOUNDARY (TWO RECIRCULATION LOOP OPERATION - CASE 1) 120 110 -

100 .

90.

I 70 * *

• ANowal~ Value 04 S.

60 ........... -1.... ..... .............. 0 TLO0RestrictedRegion

• • Boundary Egh dpoint 0 50 0.

NS Noti-Setup Scram 40 RR Restrcted Region 20 ..* . .. . . C... ... ..

..... ............-. -............... ..... S... .... .......... ..........

10 20 0 Is 20 30 40 50 60 70 so 90 100 110 120 ALIGNED DRIVE FLOW (Xrated)

Page 38 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 23. APRM FLOW BIASED SIMULATED THERMAL POWER

- HIGH SCRAM SETPOINTS AND RESTRICTED REGION BOUNDARY (SINGLE RECIRCULATION LOOP OPERATION - CASE 1) 120 110 , , . ..... S

.Im. ... .. . . ... . ....

g ....... ..... . . .... ......... 4.....

go .i~ ...... ...... / ... '.'... : .:.:

........... .............. ..... ommal Vim ~ ... ......

w @ I' S I @ , -Anowable VaIw

. ................ 1-t'./'1'"' '

2 ~ ~~, ~ * ~ t/ ' ' SL eo$Resckted Region .

60 . 1 f e. .. i , Bodna 9 Eno ... ..........

A D FLOW S S(%rSarte.

tu 50 ......... ... ... ........ ...... .......... ........... ...:

z / ie,!/ .NS N~on-Semp Scrarn O ' / j RR Resincted Region 30 . . .TR ..... ...... ........ ..... . ..... . ...... .. .. .. .... .....

2 ................... . . .... ........... ........ ................ .. .........

. ...... ...... ... ... ... .V . ... I . ... I. ......... T.. ........ r..... ........

a 2 .0 3. . .0 .0 7..0 Be . li 2

.%rtd ALGE DRV FLO

Page 39 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 24. APRM FLOW BIASED SIMULATED THERMAL POWER

- HIGH SCRAM SETPOINTS AND RESTRICTED REGION BOUNDARY (TWO RECIRCULATION LOOP OPERATION - CASE 2) 120 110 T 100 4.

• Wo 90 0 I - Nominal Value 70 4- - Allowable Value

° TLO Restricted Region Boundary High Endpoint R.,

0 l:o 4 S Setup Scram 0

N Non-Setup U 40 - RR Restricted Region r

10 -

20 -r 10 t oL _ V- V i 0 10 20 30 40 50 so 70 so 90 100 110 120 ALIGNED DRIVE FLOW (% rated)

Page 40 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 25. APRM FLOW BIASED SIMULATED THERMAL POWER

- HIGH SCRAM SETPOINTS AND RESTRICTED REGION BOUNDARY (SINGLE RECIRCULATION LOOP OPERATION - CASE 2) 120 110 100 90 us s 1 / // / P _ Allowable Value U 4 o: / // SLO Restricted Region

-/

jLgso/ / / / Boundary High Endpoint o // / S Setup Scram 20 20 10.

0 I II.IIII . I 0 10 20 30 40 so 60 70 80 90 100 110 120 ALIGNED DRIVE FLOW (%rated)

Page 41 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 26. APRM FLOW BIASED NEUTRON FLUX - HIGH ROD-BLOCK SETPOINTS (TWO RECIRCULATION LOOP OPERATION - CASE 1) 120.

110 ... . . . .. .. . . ... . .. . .. . . . . . . . . . . . .. . . . . . . . ...........

9 ... . . . .. . . . . . . ...

.J . . ... . . ......

.0. . . . . .. .. . . . .. . . . . . . .. . . . . . . . . . . . .

. . .NminalValue 90 ......... ......... .; . ;- .. --- . ... ..

¢-----------.-. J .beVa

-........ .............- ;---------;.---.i--.---

CLS Setup Rod lock 20 . r.......... ..........

/.,l ..... _..... .... ...... ...........'

NSi Non-Setup Rod-Block a Is 20 3 48 50 60 70 80 90 100 110 120 ALIGNED DRIVE FLOW (%rated)

Page 42 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 27. APRM FLOW BIASED NEUTRON FLUX - HIGH ROD-BLOCK SETPOINTS (SINGLE RECIRCULATION LOOP OPERATION - CASE 1) 120 p . . . - - .

110 100 ... .. . .. . ... . . ... ... . . . ... . . . .. . ... ... . . . .. . .. . ... . . . ... . . . .. . .. . .. . ..

........... ....... ...... I... ...... ...... ...... ........ ...............

90I 10 I.

d'4Im -Nominal Value w 60 . .... . . . . .. . . ..... eVafue 0

a. S Setup Rod-Block 50 0 NS Non-Setup Rod.lock U

40 . . . I. . .

30 t .

owbeau ............ T.......

20 . . . . _ . . .

10

• e _ . .... . . . . .

a I Is 21 30 40 50 60 70 s0 90 100 110 120 ALIGNED DRIVE FLOW (%rztd)

Page 43 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 28. APRM FLOW BIASED NEUTRON FLUX - HIGH ROD-BLOCK SETPOINTS (TWO RECIRCULATION LOOP OPERATION - CASE 2) 120 110 100 90

-8

• 70 w 60 a.0

.~

0 0

U 40 30 20 10 0

0 10 20 30 40 50 60 70 so 90 100 110 120 ALIGNED DRIVE FLOW (%rated)

Page 44 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 29. APRM FLOW BIASED NEUTRON FLUX - HIGH ROD-BLOCK SETPOINTS (SINGLE RECIRCULATION LOOP OPERATION - CASE 2) 120 110 100 90 70

-A/ / Allowabl Vau uL 60 3 Setup Rod-Bck 0

0.1 0

° 40 20 10 0 10 20 30 40 so 60 70 so 90 100 110 120 ALIGNED DRIVE FLOW (% rated)

Page 45 of 58 RBS CYCLE 12 COLR Revision 0 APPENDIX A OPERATING LIMITS FOR EQUIPMENT OUT OF SERVICE OR LOOP MANUAL MODE The operating limits listed in this appendix shall be used as indicated when operating in any of the following conditions:

- Feedwater Heater Out of Service (FHOOS)

- Pressure Regulator Out of Service (PROOS)

- Single-Loop Operation (SLO)

- Reactor Recirculation System in Loop Manual control.

Figures 36 and 37 are applicable to FHOOS or PROOS but not for FHOOS and PROOS since simultaneous FHOOS and PROOS was not analyzed. The core operating limits in this report are applicable to a cycle exposure of up to 5200 MWD/MTU.

Page 46 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 30. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR NON-KAN ATRIUM-10, EXPOSURE RANGE BOC TO BOC + 5200 MWD/MTU, FEEDWATER HEATER OUT OF SERVICE (FHOOS) 2.3 -- 1 - - - - -, =-, - -

2.2

_o~>5 _ __. - . _ _. - _

_ 2.12 ___ ___ _ __ .......-........

2.1 2.0 - ~.8 o- - . = - -_ _ ___ . _ . _

1.9 1.8 -

E

0. 1.7 0 1.6 1.5 1.4 1.3 1.2 1.1 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated

Page 47 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 31. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR KAN ATRIUM-10, EXPOSURE RANGE BOC TO BOC

+ 5200 MWD/MTU, FEEDWATER HEATER OUT OF SERVICE (FHOOS) 2.3 2.2 2.1 I -1 .I i

2.0 1.9 1.8 E

3CL 1.7

() 1.6 1.5 I

1.4 1.3 1.2 1.1 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power, %rated

Page 48 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 32. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR GEll, EXPOSURE RANGE BOC TO BOC + 5200 MWD/MTU, FEEDWATER HEATER OUT OF SERVICE (FHOOS) 2.1 2.0 1---- -- v I ., .__ .

1.9 1.8 t - w - rx - - - --

_- -1 _. 0- __

1.7 3 1.6 - - - - -. ...t -____

0.

o 1.5 1.4 1.3 1.2

, ~ ~ ~ __Pwr rated - _ ___

1.1 1.0

Page 49 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 33. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR NON-KAN ATRIUM-10, EXPOSURES RANGE BOC TO BOC + 5200 MWD/MTU, PRESSURE REGULATOR OUT OF SERVICE (PROOS) 2.3

.4 -_ -.- . ._ .

2.2 2.1 ,

1. _

. .2 '.12t

-- 2A1_

N-r. _21 50%._

[far-: __

=_ _r-: _.- -

Z.u ,t 1.9 - -= -_::__ - _ 1.__- - -- -_

1.8 -.  :--_ -- -__.____-=.

.E !_ -

_ . - .--- \

! ~~~~~- -i-- ---- - ---- ----

0.

L1.6

,~ : _ _ _ . 1

.3_ _ _--

1.5 1.4 1.3

..- i ____ - __ . __ __ l ,1.20 _,

4 0% I 1.'

- ._ ____'I [ _._ _I -I - I T- - I -- -

1 1

--!- - m : .-. i' I

I I I

+/-IE i I .,

- - EI E I[ z 1 .0 .__.__ _

0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated

RSCPage 50 of 58 RSCCLE 12 COLR Revision 0 FIGURE 34. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR KAN ATRIUM-10O, EXPOSURES RANGE BOC TO BOC + 5200 MWDJMTU, PRESSURE REGULATOR OUT OF SERVICE (PROOS) 1189 E t -- _

D 16.-7 --

1.15 - -- ~7 _ _

1.0 ~- _ _ _ _ _ _

0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated

Page 51 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 35. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR GEll, EXPOSURES RANGE BOC TO BOC + 5200 MWD/MTU, PRESSURE REGULATOR OUT OF SERVICE (PROOS) 2.1 - -- - -

I7 . 1 96R . - .- - __..

1.9.

1Pwer. %1atw_

~1.9

_1:.6:= _ _ - 16 _

cJ1.5 .. _______._=15__._

1.4 . . __ _ _- _ _

1.43: = _= ~ _ , __

1.2,_ ___o__

_ 20 30 40 _-- 60 70 _- 90 _ 1103-Power, % rated

Page 52 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 36. LHGR MULTIPLIER VERSUS CORE POWER FOR ALL ATRIUM-10, ALL EXPOSURES FHOOS OR PROOS 1.10 1.0-

.00O ---

- -l- -0 -- ____,x - - '- -100-----

i .- _. _. .- 0__-

0.90 L) 072-___ _ __ ___ ___=

-j 0.80 0.70 -

0.60 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated

Page 53 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 37. LHGR AND MAPLHGR MULTIPLIER VERSUS CORE POWER FOR GE-1i, ALL EXPOSURES FHOOS OR PROOS 1.10 - - - -

1.00 os,__ _ 1=__-I'___ _

0.90 - - - - - - -- - -

0.80 l 0. 0 - - - - t.=_ ._.'_

0.70 - - - -

• - -.- i - - - - -s7 _ _ - S._-s__

D___

0.60 0.70 .

0 5 0 2t,,',oa____=__

0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated

Page 54 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 38. LHGR MULTIPLIER VERSUS CORE POWER FOR ALL ATRIUM-10, ALL EXPOSURES SINGLE LOOP OPERATION (SLO) 1.10 1.00 0.90 0.

0

-. 1 0.80 0.70 0.60 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated

Page 55 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 39. LHGR AND MAPLHGR MULTIPLIER VERSUS CORE POWER FOR GE-il, ALL EXPOSURES SINGLE LOOP OPERATION (SLO) 1.10 -

1.05 -

____ .__._ _ 1I 00___ I00___ _

1 .00 - _ ____

0.90- I. - :- - - -- -. - - -

I.-- - _- _

0.80, _ .____;

0.65 f ~ i~z z r  :

0.50 0.45 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated:

Page 56 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 40. OPERATING LIMIT MCPR (MCPRF) VERSUS CORE FLOW FOR NON-KAN ATRIUM-10 FOR RECIRCULATION SYSTEM IN LOOP MANUAL, ALL EXPOSURES 1.5 1.4 i- .-- _ . . _ _ -

_ - .2 = __ ____ ._

1.3

_... __ ._ _ ___ __ - _._ - .-- . . _ =1 =

E 0.1 1.2 _. . _ _. . __=~1. 21 _._.__

CZ 1-- == = =2==_=

1.1 I -2 1.0 0.9 0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow, %Rated

Page 57 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 41. OPERATING LIMIT MCPR (MCPRF) VERSUS CORE FLOW FOR KAN ATRIUM-10 FOR RECIRCULATION SYSTEM IN LOOP MANUAL, ALL EXPOSURES 1.5 i-~~~ __,--- __

1.4 1.3 E

1.2 0.

u-1.1 1.0 0.9 0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow, % Rated

Page 58 of 58 RBS CYCLE 12 COLR Revision 0 FIGURE 42. OPERATING LIMIT MCPR (MCPRF) VERSUS CORE FLOW FOR GE-I 1 FOR RECIRCULATION SYSTEM IN LOOP MANUAL, ALL EXPOSURES 15 ;. . _ _

14. . __ _

. . _ __ A_ t _ _

13

__, __ _ ___ _ . _ ' __ ___ _ . 1_

!7 coo _ _ _ . _, ' _

t _. __ _ j . id __ . . __ _

E _ . _ . _ _ 1 !4_\ . A-. = - .

1.2

.2 ._. . . __ _. . . , _ = _. .

. .. . __ . _ _. _ l _-An_

. _ . ___. __ _ __ __ An_:. . .

_ . _ _ . _ _ _ _ _ _ , _ BY_ _ .

1.1

___ . _ ___ ' __e ' . . ' . .1. 8,. .

+ __

.__ __ __ _ l . __

__ __ > _ ' _ An__ __ _ .

. __ __ _ _ __ _ _ . _. _ _ . __ A_ _., . _ , _ . . ,_ .

1.0 . _, __

- L _-

__ __  : l A, __ }_ _ _ . _ , l _ __ , . . . __ ,

___ j., '. ____ ____ .. _ A.. _ __ __ ........................ _ _,_,

I___

. A--* 1- _ A-_ , . _ _ _ . . ' , i  : __. . .

A_

f _

09 _

0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow, % Rated