RBG-46938, Fifteenth Fuel Cycle Core Operating Limits Report (COLR)
| ML092230340 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 08/03/2009 |
| From: | Lorfing D Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RBG-46938 | |
| Download: ML092230340 (47) | |
Text
Entergy Operations, Inc.
Entergy River Bend Station 5485 U.S. Highway 61 N St. Francisville, LA 70775 Thi00SS031 A197 David N. Lorfing Manager, Licensing August 3, 2009 RBG-46938 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 Fifteenth Fuel Cycle Core Operating Limits Report (COLR)
Dear Sir or Madam:
Enclosed is Revision 1 of the River Bend Station (RBS) Core Operation Limits Report (COLR) for the fifteenth fuel cycle. This report is submitted in accordance with Technical Specification, 5.6.5 of Appendix A of the Facility Operating License NPF-47.
There are no commitments in this letter. For further information, contact Mr. B. M. Burmeister at (225) 381-4148.
Sincerely, Manager, Licensing River Bend Station -
DNL/bmb ADO(
k]g~
RBG-46792 Page 2 of 2-cc: Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector P. 0. Box 1050 St. Francisville, LA 70775 U. S. Nuclear Regulatory Commission Attn: Mr, Alan B. Wang MS 0-7 D1 Washington, DC 20555-0001 Mr. Jeffrey P. Meyers Louisiana Department of Environmental Quality Office of Environmental Compliance Attn. OEC - ERSD P. O. Box 4312 Baton Rouge, LA 70821-4312
Core Operating Limits Report Cycle 15 Revision 1
Page 1 of 44 RBS CYCLE 15 COLR Revision 1 RIVER BEND STATION, CYCLE 15 CORE OPERATING LIMITS REPORT (COLR)
PREPARED BY: Thomas W. Oliphant* Date:
Responsible Engineer REVIEWED BY: Phu V. Vo* Date:
Review Engineer APPROVED BY: Frederick H. Smith* Date:
Manager - Nuclear Engineering APPROVED BY: Dennis P Wiles* Date:
Director, Engineering River Bend Nuclear Station APPROVED BY: N/A Date:
On-site Safety Review Committee River Bend Nuclear Station
- Signatures and dates are documented in EC 15765
Page 2 of 44 RBS CYCLE 15 COLR Revision 1 TABLE OF CONTENTS INTRODUCTION AND
SUMMARY
....................................... 3 C O NTR O L RO D S ................................................................................................. 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 ............................. ................................. 11 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 LO OP M AN UAL MO D E ...................................................................................... .36
Page 3 of 44 RBS CYCLE 15 COLR Revision 1 INTRODUCTION AND
SUMMARY
This report provides Cycle 15 values for the following Technical Specifications:
- 1. 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 AREVA are listed in the section titled Analytical Methods Documents.
This report also provides Cycle 15 values for the following Technical Requirements:
- 1. REACTOR PROTECTION SYSTEM (RPS) APRM Flow Biased Neutron Flux Power - High Allowable Values and Nominal Trip Setpoints l,
- 2. CONTROL ROD BLOCK INSTRUMENTATION APRM Flow Biased Neutron Flux High limits.
The Cycle 15 COLR supports power operation with FHOOS, FFWTR, PROOS, SLO, EOC-RPT, and TBOOS INOPERABLE and Loop Manual Operation. In addition to the specific requirements listed in the Sections 3.2.1 to 3.2.4, the APLHGR, MCPRp and LHGR-p limits as shown in Appendix A shall be used for the applicable modes of operation. For Loop Manual Operation, the MCPR-f as shown in Appendix A shall be used.
The reload analyses were performed in accordance with AREVA methodology and its applicability to Cycle 15 was confinned by Reference 1.
Note that for Figures 13 to 20, 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 44 RBS CYCLE 15 COLR Revision 1 CONTROL RODS The River Bend core utilizes the GE design control rods, non GE design CR-82M and CR-82M-1 bottom entry cruciform control rods. These Control Rod designs are discussed in more detail in Reference 3.
DEFINITIONS MOC - Middle of Cycle (Core Exposure 29,641 MWd/MTU).
EOC - End of Cycle (Core Exposure 30,877 MWd/MTU).
EEOC - Extended cycle with Increased Core Flow (Core Exposure 31,191 MWd/MTU).
EEEOC - Extended cycle with Increased Core Flow and Final Feedwater Temperature Reduction (Core Exposure 31,712 MWd/MTU).
FFWTR - Final Feedwater Temperature Reduction.
FHOOS - Feedwater Heater Out of Service.
PROOS - Pressure Regulator Out of Service.
SLO - Single Loop Operation.
TBOOS -Turbine Bypass Out of Service AREVA - AREVA NP Inc.
EOC-RPT - End of Cycle Recirculation Pump Trip REFERENCE CORE LOADING PATTERN - The Core Loading Pattern Used for Reload Licensing Analysis.
REVISION HISTORY Revision 0 is to provide the thermal limits for Cycle 15 power operation.
Revision I iniplements thermal limits changes f*r LAR 07-09, Rev. 0, "Main Turbine Bypass System Out-Of-Service"
Page 5 of 44 RBS CYCLE 15 COLR Revision 1 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) as a function of AVERAGE PLANAR EXPOSURE is given in Figure 2. They were determined with the AREVA methodology (Reference 1).
Core location by fuel type is provided in Figure 1 and is the reference core loading pattern in Reference 1.
Page 6of 44 RBS CYCLE 15 COLR Revision 1 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) and power dependent MCPR (MCPRp) (Reference 1) are shown in Figure 4, 5, 6 and 7, respectively. Figure 27 is used in lieu of Figure 4 when the Reactor Recirculation System is operating in Loop Manual Mode. The most limiting value from the applicable MCPRf and MCPRp figures is the operating limit. These values were determined with AREVA methodology as described in Reference I and are consistent with a Safety Limit MCPR from Technical Specification 2.0.
Page 7 of 44 RBS CYCLE 15 COLR Revision 1 TECHNICAL SPECIFICATION 3.2.3 POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE (LHGR)
The limiting LHGR value for ATRIUM- 10 as a function of PELLET EXPOSURE is given in Figure 3. Core location by-fuel type is provided in Figure 1 and is the reference core loading pattern in reference 1. Thermal power and core flow dependent multipliers for ATRIUM- 10 are provided in Figures 8, 9 and Figure 10, 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 44 RBS CYCLE 15 COLR Revision 1 TECHNICAL SPECIFICATION 3.2.4 POWER DISTRIBUTION LIMITS FRACTION OF CORE BOILING BOUNDARY (FCBB)
Restricted Region Boundary Note: 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 reactorrecirculationdrive flow.
The Restricted Region boundaries as a function of aligned drive flow are given in Figures 13 through 16 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 13 through 16. 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:
T, (at rated) > T"SI"N (at rated) - 500 F and rated equivalent at off-rated reactor conditions.
OR P < 30%
- b. Case 2 - Reduced Feedwater Heating Operation T, (at rated) < T"SIGN (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 9 of 44 RBS CYCLE 15 COLR Revision 1 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 13 through 16 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:
T, (at rated) >_Ts"'GN (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) < TwSIGN (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.
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 2):
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 44 RBS CYCLE 15 COLR Revision 1 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 11 and 12.
Restricted Region Boundary Note: 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 afinction of reactorrecirculationdrive flow.
The Restricted Region boundaries as a function of aligned drive flow are given in Figures 13 through 16 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) > T"Sl"N (at rated) - 500 F, and rated equivalent at off-rated reactor conditions.
OR P < 30%
- b. Case 2 - Reduced Feedwater Heating Operation T, (at rated) < T"S'GN (at rated) - 500 F, and rated equivalent at off-rated reactor conditions.
AND P> 30%
Where: TEW is feedwater temperature in 'F, and P is reactor power in percent of rated.
Page 11 of 44 RBS CYCLE 15 COLR Revision 1 TECHNICAL REQUIREMENT 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 13 through 16 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) _>TwSIGN (at rated) - 500 F, and rated equivalent at off-rated reactor conditions.
OR P_< 30%
- b. Case 2 - Reduced Feedwater Heating Operation FW (at rated) < T"s"' (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 44 RBS CYCLE 15 COLR Revision 1 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 17 through 20 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) > TDS"N"(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"s"'w (at rated) - 50' F, and rated equivalent at off-rated reactor conditions.
AND P > 30%
Where: T1~w is feedwater temperature in 'F, and P is reactor power in percent of rated.
Page 13 of 44 RBS CYCLE 15 COLR Revision 1 REFERENCES
- 1) (a) RBS Cycle 15 Reload Analysis Report, ANP-2653 Revision 1, December 2007, and (b)
AREVA Letter, FAB08-2069, "Transmittal of River Bend Cycle 15 Final Core Loading Report, Revision 1," February 4, 2008.
- 2) Letter, R.E. Kingston to G. W. Scronce, "Time Constant Values for Simulated Thermal Power Monitor" GFP-1032 November 30, 1995.
- 4) CEO 2003-00047, "River Bend Station Unit I E1A Stability Power Uprate Evaluation."
ANALYTICAL METHODS DOCUMENTS (TS 5.6.5):
- 1) XN-NF-81-58(P)(A) Revision 2 and Supplements 1 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 1 (P)(A) and Supplement 2 (P)(A), RODEX2A (BWR)
Fuel Rod Thermal-Mechanical Evaluation Model, Siemens Power Corporation, February 1998.
- 4) ANF-89-98(P)(A) Revision I and Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.
- 5) XN-NF-80-19(P)(A) Volume 1 Supplements 1 and 2, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis, Exxon Nuclear Company, March 1983.
- 6) XN-NF-80-19(P)(A) Volume 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 (P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-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 Limits Methodology Summary Description, Exxon Nuclear Company, January 1987.
- 9) XN-NF-84-105(P)(A) Volume 1 and Volume 1 Supplements 1 and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis, Exxon Nuclear Company, February 1987.
- 10) ANF-524(P)(A) Revision 2 and Supplements 1 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 1 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 Operating Domain, Exxon Nuclear Company, October 1986.
Page 14 of 44 RBS CYCLE 15 COLR Revision 1
- 13) ANF-1358(P)(A) Revision 3, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Advanced Nuclear Fuels Corporation, September 2005.
- 14) EMF-1997(P)(A) Revision 0, ANFB-10 Critical Power Correlation, Siemens Power Corporation, July 1998.
- 15) EMF-1997(P) Supplement 1 (P)(A) Revision 0, ANFB-10 Critical Power Correlation: High Local Peaking Results, Siemens Power Corporation, July 1998.
- 16) EMF-2209(P)(A) Revision 2, SPCB Critical Power Correlation, Siemens Power Corporation, September 2003.
- 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.
- 19) Deleted.
- 20) Deleted.
- 21) Deleted.
- 22) EMF-CC-074(P)(A) 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, ATRIUMTM- 10 Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.
- 24) NEDE-2401 1-P-A and US Supplement, "General Electric Standard Application for Reactor Fuel."
Page 15 of 44 RBS CYCLE 15 COLR Revision 1 Table 1. Aligned Drive Flow 101.209. A4 -31.028
- A'O° + 70.181
- W WD =
70.181 -( - o Where:
FCTR card input drive flow in percent rated, WD Aligned drive flow in percent rated, 40 A Low flow drive flow alignment setting, and A100 High flow drive flow alignment setting.
Page 16 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 1. REFERENCE CORE LOADING PATTERN 29 31 33 35 37 39 41 43 45 47 49 51 53 55 28 25 30 29 26 29 30 29 30 29 30 29 31 25 26 27.8 0.0 15.2 28.6 20.4 0.0 21.1 0.0 18.9 0.0 18.5 0.0 29.4 34.6 26 30 26 30 29 30 26 30 26 30 26 30 29 26 26 0.0 32.5 0.0 14.6 0.0 33.1 0.0 34.2 0.0 34.7 0.0 18.6 33.2 35.5 24 29 30 29 30 26 30 29 30 29 30 29 29 26 25 15.0 0.0 17.0 0.0 33.6 0.0 18.8 0.0 17.4 0.0 18.0 19.8 34.3 36.1 22 26 29 30 29 30' 29 30 29 30 29 30 29 26 23 28.6 14.8 0.0 16.8 0.0 20.6 0.0 15.8 0.0 16.3 0.0 18.7 34.5 38.4 20 29 30 26 30 25 30 26 31 26 30 29 29 26 20.1 0.0 34.4 0.0 27.9 0.0 30.4 0.0 34.3 0.0 18.5 19.1 35.4 18 30 26 30 29 30 29 31 29 31 29 30 25 26 0.0 33.0 0.0 20.5 0.0 19.0 0.0 17.0 0.0 19.6 0.0 28.9 35.6 16 29 30 29 30 26 31 26 31 26 31 29 26 23 20.6 0.0 18.9 0.0 30.2 0.0 34.1 0.0 35.0 0.0 20.0 33.2 39.0 14 30 26 30 29 31 29 31 29 31 29 26 26 0.0 33.4 0.0 16.2 0.0 17.1 0.0 17.8 0.0 19.7 34.2 35.5 12 29 30 29 30 26 31 26 31 25 26 23 18.7 0.0 17.8 0.0 34.6 0.0 34.9 0.0 29.3 35.0 39.9 10 30 26 30 29 30 29 31 29 26 23 0.0 34.7 0.0 16.6 0.0 20.1 0.0 19.2 34.8 39.7 8 29 30 29 30 29 30 29 26 25 18.6 0.0 17.8 0.0 18.7 0.0 20.4 35.0 37.0 6 31 29 29 29 29 25 26 25 0.0 18.9 19.3 18.7 19.2 29.3 34.0 36.2 4 26 26 26 26 26 25 22 Nuclear Fuel Type 33.0 32.6 34.7 33.3 34.1 37.0 37.9 BOC Exposure (GWd/MTU) 2 26 26 26 23 35.0 35.5 35.5 38.2 No. Per Fuel Type Description Cycle Loaded Quarter core 22 A10-3996B-11G45 12 1 23 A10-3981B-15GV75 12 5 25 A10-3775B-9GV60 13 10 26 A10-3747B-13GV70 13 40 29 A10-3705B-13GV70 14 46 30 A10-3810B-14GV75 15 40 31 A10-3854B-12GV75 15 14
Page 17 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 2. MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FOR ATRIUM-10 13 (0, 12.5) (15, 12.5)-
-.. I ~tz4z 174~ 4194
.4,
.- A- -41ý 4-1 -xS w
I--
z 0
11 A
T S
! V -=i P7 zuLJ 0 10 I- t iNI w
z 9.
~E1K K 4
a.
z 4
S.
uJ
,_1 H
LI.
0l w
F (67, 7.3) 0 7- (2 .1>:~
I t F-F 6-L 4 1 V- -H-T F
5 4 6 0 10 20 30 40 50 60 70 Average Planar Exposure (GWd/MTU)
Page 18 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 3. LINEAR HEAT GENERATION RATE (LHGR) LIMIT VERSUS PELLET EXPOSURE FOR ATRIUM-10 14 14
( '"(18.9, 13.4) '
13 -+13 12 12 10 } 2 K> 10
.....---. -,,. -.-- -4 =
c,) 9 9 I =: ". q:7...
4 747 7j< I <.i,+
65 0 10 20 30 40 50 60 70 Pellet Exposure (GWd/MTU)
Page 19 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 4. OPERATING LIMIT MCPR (MCPRF) VERSUS CORE FLOW FOR ATRIUM-10 FOR RECIRCULATION SYSTEM IN LOOP AUTO CONTROL, ALL EXPOSURES 1.50 I-! I
-j4 1.11.0 p1.33 z,41 i Ii ~~1-T
- I
__1.20 .r~ r~
,L . ....
1200 --
110111T17 f.T [,iq i ----1 --- --- - -- F 1.00 i 0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow, % rated
Page 20 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 5. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIUM-10, EXPOSURE RANGE BOC TO EOC 2.3 2.2-
> 50% Flow 2.1 - 2,13 L 1.1:,+i . t f J -j L 2.0-
<= 50%Fow 1.96 1.9-4-
1,83 1.8-
... 1,*.....*
- i- -r* ,,*, ,*
E 444 1 1.7-(a.
41T%'* @ <'" " "/...... ..... *"*"*
n 1.6-
.÷ +4*t..........
1.5- - IL .....
. L. 4 IiJL,.
L t t,
,s...
........... ....... ,K i, , , .. ÷l-r y 4:,1 1...................
,2 1.4-1.3- 1*119 1.2-1.1 1.0 *W W 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 21 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 6. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIUM-10, EXPOSURE RANGE EOC TO EEOC 2.3-2.2- 2 .17 2.1 21 2.0 1.9.
1.8-E 1.7-iD -- 44 C0 1.64 1.5-1.4- -44 4 .*l*
1.3-1.2-1.1 1.0. I I I 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 22 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 7. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIUM-10, EXPOSURE RANGE EEOC TO EEEOC 2.3-t:
2.2-217 > 5 0% FlovN 2.1 2.0-
<= 50o%Flow S1.96 1,5 1.9. Li.. L. -
1,83* '1 44.
1.8- 7 ý'INM1 -4 E 1::
E T 2i 1.7- .. . 8 0L 1.6- I
-I 1.5- ............
I.. ~&tI ~ W T 1.4-1.3-1.31 1.2-
......... , *
- J... ..
1.1 I 1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 23 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 8. LHGR MULTIPLIER VERSUS CORE POWER FOR ALL ATRIUM-10, EXPOSURE RANGE BOC TO EEOC 1.10 1.00 0.90 0.
0
(.9
-I-
.- 1 0.80 0.70 0.60 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 24 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 9. L0GR MULTIPLIER VERSUS CORE POWER FOR ALL ATRIUM-10, EXPOSURE RANGE EEOC TO EEEOC i.10-1.00 100 0909 A+
0~ {1 ~Ii 0
LL (9
I
-j 0.60 <=> 50% Flow 0.60 r*r' 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 25 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 10. LHGR MULTIPLIER VERSUS CORE FLOW FOR ALL ATRIUM-10, ALL EXPOSURES 1.10 t f 1.00 U
u-n 0.90
(.9 T-0.80 0.70 0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow, % rated
Page 26 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 11. MONITORED REGION BOUNDARY (CASE 1) 120 110 ----------
100 ..........
90 --------------------------
I-
~80 8
70 LLI 60 0
0- 50 w
0 40 30 20 -----------------
10 ..........
0 0 10 20 30 40 50 60 70 80 90 100 110 CORE FLOW(% rated)
Page 27 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 12. MONITORED REGION BOUNDARY (CASE 2) 120 110 100 90 "0 80
'70 Wu 60 0
- a. 50 0
o 40 30 20 10 0
0 10 20 30 40 50 60 70 80 90 100 110 CORE FLOW(% rated)
Page 28 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 13. APRM FLOW BIASED SIMULATED THERMAL POWER
- HIGH SCRAM SETPOINTS AND RESTRICTED REGION BOUNDARY (TWO RECIRCULATION LOOP OPERATION - CASE 1) 120 100 . .. . . . . . . .. .. . . . . . . .. . . ..... .. . ... . . . . . .. . . ... . ........ ... . ..
10 ------ - Nomina Value -- ------ -----
/---------------- --------- 4-- 0 h _71itd~go
-- Normial Value 70 -------------.-------------------------- ------ --------
0lowable Value LLJ60 ---------- --- -- ---------- . ......... -- 0
.. . .. ------- TLO Restricted Region ............
O0. Boundary High Endpoint 50* --- -- *-- . ---. -*- ---.... . .....................
ii... -- --- -Io -----------.. ~*p o* ...
0 Si 4Uo------ -- - ---- . . . . . . . . ............ .
. . . . . . . . . . . . . . . . . I. -............
100............................... ............... ........... ----......................................................................
20---- ---
10 ---------
--- ---- -- --- ------ --- --- --- --- --- --- ------- --- ------ --- ------- --- --- --- --- --- --- ---r - --- ---
o '
0 10 20 30 40 50 60 70 80 90 100 110 120 ALIGNED DRIVE FLOW (%rated)
Page 29 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 14. APRM FLOW BIASED SIMULATED THERMAL POWER
- HIGH SCRAM SETPOINTS AND RESTRICTED REGION BOUNDARY (SINGLE RECIRCULATION LOOP OPERATION - CASE 1) 120 110 -
- 100 -
90
?80 V
. - I~---.. ...... .*...........
I - Alowable Nomind alyVValue al e n p .... ..........
6 70-o SLO Restricted Region 60 ........---------- - - ---- -------------- - - - - Boundary H4ghBndpoint ........
0 / S Setup Scram 0.
50 NS Non-Setup Scram 0U
. ... .... RR Restricted Region 40 30 20 10 0 It I ' I ' I I' ' I I ' I I 0 10 20 30 40 50 60 70 80 §0 100 110 120 ALIGNED DRIVE FLOW (%rated)
Page 30 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 15. APRM FLOW BIASED SIMULATED THERMAL POWER
- HIGH SCRAM SETPOINTS AND RESTRICTED REGION BOUNDARY (TWO RECIRCULATION LOOP OPERATION - CASE 2) 120 110 100 -----------------
90 -----------------
80 ------------------
Nominal Value 70 Allowable Value -----------------
Wu 60 TLO Restricted Region -----------------
Boundary High Endpoint 0
Setup Scram
. 50 -----------------
Non-Setup 0
L) 40 Restricted Region - -- -- --------
30 -----------------
20 -----------------
10 0
0 10 20 30 40 50 60 70 80 90 100 110 120 ALIGNED DRIVE FLOW (% rated)
Page 31 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 16. APRM FLOW BIASED SIMULATED THERMAL POWER
- HIGH SCRAM SETPOINTS AND RESTRICTED REGION BOUNDARY (SINGLE RECIRCULATION LOOP OPERATION - CASE 2) 120 110 -1 ---------------- ..................
100 1 90 I 80 +
70 -- ---
N om inal V alue --- --------
LU
- Allowable Value 60 1 3t.
uIJ 0 *0 SLO Restricted Region 50 T
- Boundary High Endpoint ------------
0 0 40 1 *S- Setup Scram N Non-Setup 30 RR Restricted Region.........
20 10 J 10 20 30 40 50 60 70 80 90 100 110 120 ALIGNED DRIVE FLOW (% rated)
Page 32,of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 17. APRM FLOW BIASED NEUTRON FLUX - HIGH ROD-BLOCK SETPOINTS (TWO RECIRCULATION LOOP OPERATION - CASE 1) 12'0 11 10
'0 9
0 - .----- .----------------- -
8 7
0 0Nominal Value 6
!S Setup Rod-Block 0 5
///' j NS Non-Setup Rod-Block U 4 40 -..-- --- ---. . -- -.--..
3 2
30 0 10 20 30 40 50 60 70 80 90 100 110 120 ALIGNED DRIVE FLOW (, rated)
Page 33 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 18. APRM FLOW BIASED NEUTRON FLUX - HIGH ROD-BLOCK SETPOINTS (SINGLE RECIRCULATION LOOP OPERATION - CASE 1) 120 110 100 90 80 70
-.. Nominal Value
'U 60 ........... ........... ......... ... .... ... ................ Allowable Value ...... .......... -------
S Setup Red-Block 50 NS Non-Setup Rod-Block 40 30 20 I -- --- - ---- -- -
10 0I 0 10 20 30 40 50 60 70 80 90 100 110 120 ALIGNED DRIVE FLOW r rated)
Page 34 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 19. APRM FLOW BIASED NEUTRON FLUX - HIGH ROD-BLOCK SETPOINTS (TWO RECIRCULATION LOOP OPERATION - CASE 2) 120 110 100 90 80
- 70 LI 60 0
0a Lu50 0 3O
(. 40 30 20 10 0
0 10 20 30 40 50 60 70 80 90 100 110 120 ALIGNED DRIVE FLOW (% rated)
Page 35 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 20. APRM FLOW BIASED NEUTRON FLUX - HIGH ROD-BLOCK SETPOINTS (SINGLE RECIRCULATION LOOP OPERATION - CASE 2) 120
- 110 -..-
100 90 80 _ _ _
cc- Nominal Value 6O
~ 70-- - Allowable Value 0 --- -------- -------- -------- _1- -------- -Rod-Block NS Non-Setup------
eu R d Boc --------- ---------
0
- 0 10 20 20 10 -----..............
20--------------
-0 - 40.................. 50 ---
0 70 90 80---.................. 100--------------
120--------------
110--------------
130...............................................................................................
0 10 20 30 40 50 60 70 80 90 100 110 120 ALIGNED DRIVE FLOW (% rated)
Page 36 of 44 RBS CYCLE 15 COLR Revision 1 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)o'
- Pressure Regulator Out of Service (PROOS) (2)
- Reactor Recirculation System in Loop Manual control.
- End of Cycle Recirculation Pump Trip (EOC-RPT) Inoperable m
- Single-Loop Operation (SLO) (3)
- Turbine Bypass Out of Service (TBOOS)*4 o Power dependent MCPR and LHGR limits are presented in Figures 21, 22 and 23. Flow dependent LHGR and MCPR limits are presented in Figures 10, 4 for loop auto and 10, 27 for loop manual.
(2) Power dependent MCPR and LHGR limits are presented in Figures 24, 25, and 26. Flow dependent LHGR and MCPR limits are presented in Figures 10, 4 for loop auto, and 10, 27 for loop manual.
(3) The power dependent MCPRp for normal operation (Figures 5, 6 and 7) and equipment out of services (EOOS) described in (1), (2), and (4) shall .be increased by 0.02 for SLO. The limits of APLHGR (Figure 2) shall be reduced to a value of 0.95 times the two recirculation loop operation limit when in single loop operation (Reference 1).
(4) Power and Flow dependent MCPR and LHGR limits are presented in Figures 21, 22, 23, 25, 26, 28 for loop auto, and 27 for loop manual.
Note: Power dependent MCPR and LHGR limits for an operating mode at EEEOC exposure point may be used to bound all cycle exposures
Page 37 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 21. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIUM-10 BOUNDING FHOOS, TBOOS AND EOC-RPT INOPERABLE BOC TO MOC 2.3-
.I '- I 2.17 I*"I"-"T 2.2- 1-2.1 . >50% Flow 2.0 .
<= 50% Flow 1.9- 22
.... i i t .................I
....................i -I] + ...................
1.8 E
U 1.7 1 n 1.6-1.5-1.4-1.3- 1 L4 1.2- F~~-; ii L 1.1 1.0 i , F i .. . . . .. .i i¸ i iy * * * ... . i
- i 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated
9 Page 38 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 22. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIUM-10 BOUNDING FHOOS, TBOOS AND EOC-RPT INOPERABLE MOC TO EEEOC 2.3-7A 2.2-4-i-'.- 4 -
2.1 > 5 2.0O
<= 50% Flow 7~fF42iKI.'
1.9*
1,83 1.8-E 0... 1.7-13_ 41.4 C- 1.6-11.5 1-4 1.5- 1.33 ii:
1-.-
4 I 1.4- .r -.
+F 1.3-114
.24 1.2-I-.4--..I. I+
4 ii K I 1.1 'I t j
444*
4-4.44 44
.4-4--.
{-I-. 4.
1.0. W W
- I I 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 39 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 23. LHGR MULTIPLIER VERSUS CORE POWER FOR ATRIUM-10 BOUNDING FHOOS, TBOOS AND EOC-RPT INOPERABLE ALL EXPOSURES 1.10 1.00 0.90 CL LL (D
0.80 0.70 0.60 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 40 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 24. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIUM-10, PRESSURE REGULATOR OUT OF SERVICE (PROOS), BOC TO EEOC 2.3-
$ 4 4-a "2.17 2.2-2.1 - 2.13 2.0- I <= 50%s Flw9 1.9-aa .a.T *.:*,*
1.8- 183 E
qj 1.7-
.45 D.
n 1.6-C-)
1.3a at a 1.5- .... ,,.a a*
-Ii 1.4- 4 I-4-
1.3- -1 I.
.' -I4 1.2-1.1 a, - 11 - '
1.0 0 10 20 30 40 50 60 70 80 90 r 100 110 Power, % rated.
Page 41 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 25. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIUM-10 BOUNDING FHOOS, PROOS, TBOOS AND EOC-RPT INOPERABLE ALL EXPOSURES 2.3 2.17 2.2-
> 50% Flow 2.1 2.133
<= 50%
2.0 / 1.96 72 l wJ 1.9. -I'....
-VA 2.~1jA E-712
.4 ii i-i; 24411 +
1.8- -4631,63
- E 1.7-n- r'T2 n1.6- 1,3 9 44==
1.5- I. *-- .-.. i,- 3' .....-...
1.4-1.3- 2-'
1.2-1.1 1.0 1 9 1 1 1 1 1 1 1 1 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 42 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 26. LHGR MULTIPLIER VERSUS CORE POWER FOR ALL ATRIUM-10 BOUNDING FHOOS, PROOS, TBOOS AND EOC-RPT INOPERABLE ALL EXPOSURES 1.10 1.00 0.90 c-0 u-0.80 0.70 I
I 0.60 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 43 of 44 RBS CYCLE 15 COLR Revision 1 FIGURE 27. OPERATING LIMIT MCPR (MCPRF) VERSUS CORE FLOW FOR ATRIUM-10 FOR RECIRCULATION SYSTEM IN LOOP MANUAL ALL EXPOSURES 1.5
... 'tI ,
- I i !
1.3-
-1iTurbine Bypass Out-of-Servicel2' 6
.1.24 1 - ... 1... 1 0.9....1~ T (rbine In Bypass +-],i l 4~'~ ~ i l~ 11.08I 1.0 ![ i 0 ..... 9i t t- -- . . ..
0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow, % Rated
Page 44 of 44 RBS CYCLE 15 COLR Revision I FIGURE 28. OPERATING LIMIT MCPR (MCPRF) VERSUS CORE FLOW FOR ATRIUM-10 FOR RECIRCULATION SYSTEM IN LOOP AUTO CONTROL, TBOOS, ALL EXPOSURES 1.50 141j 1.30 1.26
~. 1. 18
- 1.2 0 .,
- i,*:** ,,,;****.....** ,
1.00 .a... a.
1.10 i 1.00- . .
0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow, %rated