RBG-46568, Thirteenth Fuel Cycle Core Operating Limits Report
| ML061390033 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 05/11/2006 |
| From: | Lorfing D Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| G9.25.1.5, G9.5, RBF1-06-0079, RBG-46568 | |
| Download: ML061390033 (50) | |
Text
Entergy Operations, Inc.
River Bend Station 5485 U.S. Highway 61 N St. Francisville, LA 70775 Tel 225 381 4157 vm~tw Fax 225 635 5068 dlorfin~entergy.com David N. Lorfing Manager-Licensing May 11, 2006 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 Thirteenth Fuel Cycle Core Operating Limits Report (COLR)
File Nos.:
G9.5, G9.25.1.5 RBG-46568 RBF1-06-0079 Ladies and Gentlemen:
Enclosed is Revision 0 of the River Bend Station (RBS) Core Operation Limits Report (COLR) for the fourteenth 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 through the end of the fuel cycle.
There are no commitments in this letter. For further information, contact Mr. B. M. Burmeister at (225) 381-4148.
Sincerely, D. N. Lorfing J()
Manager - Site Lc'bising DNL/BMB Enclosure X0\\2~c
Fourteenth Fuel Cycle Core Operating Limits Report (COLR)
RBG-46568 RBF1-06-0079 Page 2 of 2 cc:
U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Resident Inspector PO Box 1050 St. Francisville, LA 70775 Mr. Bhalchandra Vaidya, Project Manager U.S. Nuclear Regulatory Commission MS O-7D1A 11555 Rockville Pike Rockville, MD 20852-2738
Core Operating Limits Report Cycle 14 Revision 0
Page I of 47 RBS CYCLE 14 COLR Revision 0 RIVER BEND STATION, CYCLE 14 CORE OPERATING LIMITS REPORT (COLR)
PREPARED BY:
REVIEWED BY:
APPROVED BY:
APPROVED BY:
APPROVED BY:
_~ c_-Date:
Responsible Engineer 1h I)
Date:
Review Engineer er Ue"Al 017?
@ C Date:
Ad Manager - Nuclear Engineering n
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Date:
/iirecdor, Engineering River Bend Nuclear Station dg~z 3,.r Z,o,;S
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fin-site'afety Review Committee River Bend Nuclear Station 0 -
Page 2 of 47 RBS CYCLE 14 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............................................................. 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 LOOP MANUAL MODE..............................................................
38
Page 3 of 47 RBS CYCLE 14 COLR Revision 0 INTRODUCTION AND
SUMMARY
This report provides Cycle 14 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 FANP are listed in the section titled Analytical Methods Documents.
This report also provides Cycle 14 values for the following Technical Requirements:
- 1. REACTOR PROTECTION SYSTEM (RPS) APRM Flow Biased Neutron Flux Power - High Allowable Values and Nominal Trip Setpoints1,
- 2. CONTROL ROD BLOCK INSTRUMENTATION APRM Flow Biased Neutron Flux High limits.
The Cycle 14 COLR supports power operation with FHOOS, FFWTR, PROOS, SLO, EOC-RPT INOPERABLE 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 MCPR-f as shown in Appendix A shall be used.
The reload analyses were performed in accordance with FANP methodology and its applicability to Cycle 14 was confirmed by Reference 1.
'Note that for Figures 15 to 22, 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 47 RBS CYCLE 14 COLR Revision 0 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 29,460 MWd/MTU).
EOC - End of Cycle (Core Exposure 31,364 MWd/MTU).
EEOC - Extended cycle with Increased Core Flow (Core Exposure 31,610 MWd/MTU).
EEEOC - Extended cycle with Increased Core Flow and Final Feedwater Temperature Reduction (Core Exposure 32,203 MWd/MTU).
FFWTR - Final Feedwater Temperature Reduction.
FHOOS - Feedwater Heater Out of Service.
PROOS - Pressure Regulator Out of Service.
SLO - Single Loop Operation.
FANP - Framatome ANP EOC-RPT - End of Cycle Recirculation Pump Trip KAN - The designator for the reconstituted ATRIUM-1I assemblies.
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 14 power operation.
Page 5 of 47 RBS CYCLE 14 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) as a function of AVERAGE PLANAR EXPOSURE is given in Figure 2 and Figure 3. The ATRIUM-10 APLHGR is divided into two subsets:
the reconstituted ATRIUM-10 (marked by the designator KAN FUEL as listed in Figure 3), and the ATRIUM-10 (Figure 2). They were determined with the FANP methodology (Reference 1). Core location by fuel type is provided in Figure 1 and is the reference core loading pattern in reference 1. The limits of these figures shall be reduced to a value of 0.83 times the two recirculation loop operation limit when in single loop operation (Reference 1). 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.
Page 6of47 RBS CYCLE 14 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) and power dependent MCPR (MCPRp) (Reference 1) are shown in Figure 5 and Figures 7 to 10, respectively. Figure 29 is used in lieu of Figure 5 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 FANP methodology as described in Reference 1 and are consistent with a Safety Limit MCPR from Technical Specification 2.0.
At a power level greater than 40%, the power dependent MCPRp (Figure 10) 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 47 RBS CYCLE 14 COLR Revision 0 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 4. 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 11 & 12 and Figure 6, 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 47 RBS CYCLE 14 COLR Revision 0 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 a function of reactor recirculation drive flow.
The Restricted Region boundaries as a function of aligned drive flow are given in Figures 15 through 18 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 15 through 18. 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:
Tw (at rated) 2 TSwI (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;FW (at rated) - 500 F, and rated equivalent at off-rated reactor conditions.
AND P>30%
Where:
TFw is feedwater temperature in OF, and P is reactor power in percent of rated.
Page 9 of 47 RBS CYCLE 14 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 15 through 18 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) 2 TFSWG (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) < TFwG (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 47 RBS CYCLE 14 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 13 and 14.
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" APAM Flow Biased Simulated Thermal Power - High Control Rod Block Setpoints, which are afiunction of reactor recirculation drive flow.
The Restricted Region boundaries as a function of aligned drive flow are given in Figures 15 through 18 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:
T,, (at rated) 2 TFWIG (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) <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 11 of 47 RBS CYCLE 14 COLR Revision 0 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 15 through 18 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) 2 TwIGN(at rated) - 50 0 F and rated equivalent at off-rated reactor conditions.
OR P<30%
- b. Case 2 - Reduced Feedwater Heating Operation T, (at rated) < TFWG (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 12 of 47 RBS CYCLE.14 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 19 through 22 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) 2 TDEIUGN (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) < TFWG (at rated) - 500 F, and rated equivalent at off-rated reactor conditions.
AND P>30%
Where:
TFw is feedwater temperature in OF, and P is reactor power in percent of rated.
Page 13 of 47 RBS CYCLE 14 COLR Revision 0 REFERENCES I)
[a] EMF-3270 Revision 0, "River Bend Station Cycle 14 Reload Analysis." [b] RJD:06:062, "River Bend Cycle 14 Loading Pattern Changes Due to Three Failed Fuel Assemblies."
- 2)
Letter, R.E. Kingston to G. W. Scronce, "Time Constant Values for Simulated Thermal Power Monitor" GFP-1032 November 30, 1995.
- 3)
- 4)
CEO 2003-00047, "River Bend Station Unit 1 EIA Stability Power Uprate Evaluation."
- 5)
RBC-48838, "Transmittal of River Bend Cycle 10 LHGR/MAPLHGR Relaxation Results."
- 6)
EMF-3266(P) Revision 0, Mechanical Design Report for River Bend Unit 1 Reload RBE1-14 ATRIUM-10 Fuel Assemblies, Framatome ANP, November, 2005.
ANALYTICAL METHODS DOCUMENTS (TS 5.6.5):
I)
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, Exxon Nuclear Methodology for Boiling Water Reactors -
Neutronic Methods for Design and Analysis, Exxon Nuclear Company, March 1983.
- 6)
XN-NF-80-19(PXA) 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(PXA) 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 Thermnal-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 1 Revision 1 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, BWRI6 Generic Rod Withdrawal Error Analysis, MCPRp for Plant Operations within the Extended Operating Domain, Exxon Nuclear Company, October 1986.
Page 14 of 47 RBS CYCLE 14 COLR Revision 0
- 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(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, November 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.
- 18)
XN-NF-80-1 9(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(P)(A), Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors EXEM BWR Evaluation Model, Advanced Nuclear Fuels Corporation, January 1993.
- 20)
ANF-91-048(P)(A) Supplements 1 and 2, BWR Jet Pump Model Revision for RELAX, Siemens Power Corporation, October 1997.
- 21)
XN-CC-33(A) Revision 1, 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(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, ATRIUM-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 47 RBS CYCLE 14 COLR Revision 0 Table 1. Aligned Drive Flow WD =
Where:
WD WD A40 A100 101.209* -31.028
- '°° + 70.181
- W 70.181 -
( A10 0 _ A4 0
)
= FCTR card input drive flow in percent rated,
= Aligned drive flow in percent rated,
= Low flow drive flow alignment setting, and
= High flow drive flow alignment setting.
Page 16 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 1. REFERENCE CORE LOADING PATTERN 29 i1 A3
_3 37 39 4I 43 45 Al?
9 51 53 55 2S 22 22 23 2 9 2
C 29 6
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'.0 13.1 23:7 34.g 26 22 2Ž 6
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- 29) 2S 23 3J.4 32.2 1$.9 0.0 14.9 32.6 t6.2 0.0 14.0
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- 2) 26 2.3 26
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- 21.
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Page 17 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 2. MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FOR ATRIUM-10 13 12 z0 I.-
<9
'Uz 1 w
w<79
)
3 13 12 11 10 9
8 7
6 5
3 6
5 0
10 20 30 40 50 60 70 Average Planar Exposure (GWd/MT)
Page 18 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 3. MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FOR ATRIUM-10 (KAN FUEL) 13 0
F z
I.-
'Uz aU.
2
'U 12 11 10 9
8 7
6 13
_ -12
_11 10 9
8 7
6 5
70 5
0 10 20 30 40 50 60 Average Planar Exposure (GWd/MT)
Page 19 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 4. LINEAR HEAT GENERATION RATE (LHGR) LIMIT VERSUS PELLET EXPOSURE FOR ATRIUM-10 14 14 13' I
13 12 1
'1T 11 0
09 l
T3 I I rS I !X r.iTL 7
7 6 -
6 5
I I
5 0
10 20 30 40 50 60 70 Pellet Exposure (GWd/MT)
Page 20 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 5. OPERATING LIMIT MCPR (MCPRF) VERSUS CORE FLOW FOR ATRIUM-10 FOR RECIRCULATION SYSTEM IN LOOP AUTO CONTROL, ALL EXPOSURES ll~ llllIl 1
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Page 21 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 6. LHGR MULTIPLIER VERSUS CORE FLOW FOR ALL ATRIUM-10, ALL EXPOSURES 1.10 1.00 U-.w 0.90 I
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I j I
I I-I I
I I..
I.
I..
I I I.
I I.
I.
I I i.
I ; I.
I I I I.
I I I I.
I.
I .
I.
I I I.
I...
I I I 0.70
.1.
1 1
1 1
1 1
1 1
1 I
I 0
10 20 30 40 50 60 70 80 90 Core Flow, % rated 1
100 110 120
Page 22 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 7. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIUM-10, EXPOSURE RANGE BOC TO MOC 2.3 2.2 2.1 2.0 1.9 E
0l.
0 1.8 1.7 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 23 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 8. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIUM-10, EXPOSURE RANGE MOC TO EOC 2.3 1 I
2.2 2.1 2.0 1.9 1.8 E
i 1.7 0.Q g 1.6 1.5 1.4
.1.)
1.3 1.2 1.1 1.:
1.0 I
I I
-I 0
10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 24 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 9. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIUM-10, EXPOSURE RANGE EOC TO EEOC 2.3 I
I 2.2 2.1 2.0 1.9 1.8 ft::
BE
> 1.6 1.5 1.4 1.3 1.2 1.1 1.0 t
l I
I I
0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 25 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 10. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIUM-10, EXPOSURE RANGE EEOC TO EEEOC 2.3 2.2 2.1 2.0 1.9 1.8 E
-i 1.7 CL IL1.6 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 26 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 11. LHGR MULTIPLIER VERSUS CORE POWER FOR ALL ATRIUM-10, EXPOSURE RANGE BOC TO EEOC 1.10 1.00 I
...I......_..1._.1.I _.I......1.I I 1.-
0.90 a-0 LL i I
.I I E Iir.
!III
.I I...
I ITII u1IuI IiIi III I
I 0.80 0.70 0.60 1 1 1 1 1 1 1 I I I I A 1 1 1 1 1 1 1 1 1 H I I I I I I 1 1 W111H I HT II Jill I
I M
I IIH 11111 II W
11
!III T
I I H II I
11 11 I1 11 1 1 1
1 m
I 0
10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 27 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 12. LHGR MULTIPLIER VERSUS CORE POWER FOR ALL ATRIUM-10, EXPOSURE RANGE EEOC TO EEEOC 1.10 I.
F..
k I
I1 I I I! iII I I
I i
1.00 CD U-
-.1 0.90 0.80 I
IIC 0.70 0.60 0
10 20 30 40 50 60 70 80 Power, % rated 90 100 110
Page 28 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 13. MONITORED REGION BOUNDARY (CASE 1) 120 110 100 90 n 80 S
70 L
60 0
CL 50 o 40 30 20 10 0
0 10 20 30 40 so 60 70 CORE FLOW(% rated) 80 90 100 110
Page 29 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 14. MONITORED REGION BOUNDARY (CASE 2) 120 110 100 90 1
80
'E ae0 70 70:
LU 60 0
C 50 Lu
° 40 30 20 10 0
s z _ ------
w ------~-4~~----
-- ------------ I--4------
.----------- 4----------- q----~-~-- ~
-~~-~~i~~~~~~n~---~---
~------ ---------- ----------
~-- -----
!REGIO
- ~~
-L-1----------------------
a--------_
---t--- -- s---------
--- -- --- -- ---- ~---
L------------ ; i ;- - -- - -- - -- - -- -
--- --- --- ' ---- F-J-
-- ---- -- I--- ---- ---- -- I---.-- -- ------- -- F-
--- --- t---- -- ------ ~~
~
0 10 20 30 40 50 60 70 CORE FLOW(% rated) 80 90 100 110
Page 30 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 15. APRM FLOW BIASED SIMULATED THERMAL POWER
- HIGH SCRAM SETPOINTS AND RESTRICTED REGION BOUNDARY (TWO RECIRCULATION LOOP OPERATION - CASE 1)
A-I w
0 0U
,0...
T....
-I.
70.
'owable Vae
- 11.
0 TLO RestrictedReon Boundary IHigh Eadpoint 100.
S SetupScram fs 1
l_
NS Non-Setp Scram RR Restrictedkegon 20...
he 7.,
8
.S 8
S 60..........,,---q----2-!-- ---- --------- o10 snkdRo
.....................T.........T.....................------
50 8./
Z 8
8 e
=......
/
/
- N NnSepcn 4S 8*
6~----*
F-<¢-
...........^l--.sss.
8/
f 8
RRetcdto U
10 20 30 40 50 60 70 ALIGNED DRIVE FLOW (% rated) so 90 100 110 120
Page 31 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 16. APRM FLOW BIASED SIMULATED THERMAL POWER
- HIGH SCRAM SETPOINTS AND RESTRICTED REGION BOUNDARY (SINGLE RECIRCULATION LOOP OPERATION - CASE 1)
I 0a-0U 120 100 go 70 60 50 30 -
20-10 -
4......
a a
a #.
r
,-,-a a
a
-U a
a/X a
a S
a a
.a a
a'w'_r--------s----
5:
- /
a I
f n
l V
NS NnS4,cam a
a a
a
- j.
i--
i nl a
Se........
~Allowable Value, a 0 SLO Restricted Region
.j-BoHIdy~Endpoint.. '
.S Setup Scrm NS Non-Setup Scram
.RR Restricted Region:
a a
a
.a:
.a a
.a a4 a
a a
a a
S
a.
.a
.a a
a.
.a
.a
.a.
.a a
a.
.1 p
I I
a le 20 30 40 s0 60 70 ALIGNED DRIVE FLOW CA rated) so 90 I
I 190 110 120
Page 32 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 17. APRM FLOW BIASED SIMULATED THERMAL POWER
- HIGH SCRAM SETPOINTS AND RESTRICTED REGION BOUNDARY (TWO RECIRCULATION LOOP OPERATION - CASE 2) 120 -~ ~
~
r-------------.
110o ----------- '------------f-----------J--
----F----
i--------------
F 100-__
j
_ g i
90-I!
- t r'T1 Nominal Value 70 _---
Allowable Value 0 TLO Restricted Region u_ 6 - ---------- 1------------f-----
-/----/-,--- -/---/
-,.°Rsne eo Boundary High Endpoint I~ 0
,]s 7%IL;/7, S
Setup Scram.....
O
- //
/
/N Non-Setup.
00 40 RR Reqtrirted Re'ion 0
1C 20 30 40 50 60 70 80 90 100 110 120 ALIGNED DRIVE FLOW (% rated)
Page 33 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 18. APRM FLOW BIASED SIMULATED THERMAL POWER
- HIGH SCRAM SETPOINTS AND RESTRICTED REGION BOUNDARY (SINGLE RECIRCULATION LOOP OPERATION - CASE 2) 120 120-100
'----------_-L--
I-------
70 N om inal V alue Allowable Value o
SLO Restricted Region Uj Boundary High Endpoint o
S Setup Scram 7 0
-t-I---------------- -
I------------Vlu N
Non-Setup 3 0
! --- 4------ --------
Stu 30 yK*
,.R.R Restricted Region.
0 10 20 so 40 so so 70 so 20 ion 110 120 ALIGNED DRIVE FLOW (% rated)
Page 34 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 19. APRM FLOW BIASED NEUTRON FLUX - HIGH ROD-BLOCK SETPOINTS (TWO. RECIRCULATION LOOP OPERATION - CASE 1) 120 110 100 90 goI 170 0
w70 0
Lw50 40 10 40 20 10 0
I L
a a
a a
a Nominal Value
.-. I.
AlloWable Value S
Setup Rod-Block NS Non-Setup Rod-Block
~
.i-
~
~
i----...---------Y-----------
i------. -...........
i---
...... -i----------
U 10 20 30 40 50 60 70 ALIGNED DRIVE FLOW % rated) 80 100 11tO 120
Page 35 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 20. APRM FLOW BIASED NEUTRON FLUX - HIGH ROD-BLOCK SETIPOINTS (SINGLE RECIRCULATION LOOP OPERATION - CASE 1)
N 0!
w UJ U
110 S
S S
S S
S S
S
- 0.
0......
S NominalValue s................
y
......;.......AoWable Value S
Setup Rod-Block 4 0 30..........
2 0............ L----------
Alwal l
/
/
i S
NnSetup Ro d-Block.
i
/*/
i NS Nnepo Sli
,i 40
.I aI I.I 10 v
1
- l
- t 1
I I
A 10 20 30 40 50 60 70 80 ALIGNED DRIVE FLOW (% nted) 90 100 110 120
Page 36 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 21. APRM FLOW BIASED NEUTRON FLUX - HIGH ROD-
. BLOCK SETPOINTS (TWO RECIRCULATION LOOP OPERATION - CASE 2) 120 110 100 90 80 0
go-70 JIl 60 0
IL s 0
U 40 30 20 10 0
------------ ------~----,------
j---------
.~ ~ ~ 9
~~~~~--
~-
Z
/
/
/
/
Allbwable Value t--------_7i *;/_____
S Setup Rod-Block ;..
/
XNS Non-Setup Rod-Block
_--_----_-- 4-----------t- -Z-,!--e.;----------'---- -------n----- -------r----- ----------~--- ----t------~-- ---r-------- -------------------
-- - - - - -I- - -- - -
tf--------~---'-I----------- ------------ --r--------- -- ------ ------------
F
~--
~i~~~~~~
0 10 20 30 40 50 60 70 ALIGNED DRIVE FLOW (% rated) so 90 100 110 120
Page 37 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 22. APRM FLOW BIASED NEUTRON FLUX - HIGH ROD-BLOCK SETPOINTS (SINGLE RECIRCULATION LOOP OPERATION - CASE 2)
I I
I 0A
'U Ce 0U 20 110 _ -
-Nominal Value Allowable Value 60 -- - - --- -- - - - - - -- - - - - - - -- ----
S Setup Rod-Block-NS Non-Setup Rod-Block so - -- - - - - -- - -- - - -- - - - - -
I- - - -----
I---------~~~~~--~~~--
30
'-------------t------------
I--------- ------------
Jo
-1 50 20 4 -
r
~
4 0
10 20 30 40 50 60 70 ALIGNED DRIVE FLOW (% rated) o0 90 100 110 120
Page 38 of 47 RBS CYCLE 14 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)Y')
Pressure Regulator Out of Service (PROOS) (2)
Single-Loop Operation (SLO)
Reactor Recirculation System in Loop Manual control.
End of Cycle Recirculation Pump Trip (EOC-RPT) Inoporable' 3 )
')At a power level greater than 40%, the power dependent MCPRp (Figure 23) shall be increased by 0.02 for concurrent SLO and FHOOS. At a power lower than 40%, the most limiting MCPRp value is the operating limit, and it shall be increased by 0.02 for SLO and FHOOS.
(2)At a power level greater than 40%, the power dependent MCPRp (Figures 25 and 26) shall be increased by 0.02 for concurrent SLO and PROOS. At a power lower than 40%, the most limiting MCPRp value is the operating limit, and it shall be increased by 0.02 for SLO and PROOS.
3)At a power level greater than 40%, the power dependent MCPRp (Figure 30) shall be increased by 0.02 for concurrent SLO / EOC-RPT INOPERABLE, or concurrent SLO / EOC-RPT INOPERABLE / FHOOS. At a power lower than 40%, the most limiting MCPRp value is the operating limit, and it shall be increased by 0.02. At a power lower than 40%, the most limiting LHGRFACPp (Figure 31) at high core flow conditions is the operating limit for SLO.
2.3 2.2 2.1 Page 39 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 23. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIUM-10, FEEDWATER HEATER OUT OF SERVICE (FHOOS), BOC TO EEEOC I 1 1 i!
I i S I ti 11_ --
I I ii+
TTTI ~~~lI fib~ b S t = IiII 2.0 1.9 1.8 E:i 1.7 0.Q V 1.6 1.5 1.4 1.3 1.2 1.1 1.0 II I
+ A---
I I
I 0
10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 40 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 24. LHGR MULTIPLIER VERSUS CORE POWER FOR ALL ATRIUM-10, ALL EXPOSURES, FHOOS 1.10 1.00 OD--
L/I T I
Hill T11-0.8 0.-
n(A W.Wv I
I I
I l
I 0
10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 41 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 25. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIUM-i10, PRESSURE REGULATOR OUT OF SERVICE (PROOS), BOC TO EEOC 2.3-2.2 -'
I 2.1 -
.1 2.0
'1.9 1.8
.4-E
- D1.5 a-1.4 1.3 I f I
1.2 1.1 I
1.0
,I I
I 0
10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 42 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 26. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIUM-10, PRESSURE REGULATOR OUT OF SERVICE (PROOS), EEOC TO EEEOC 2.3 I
iii 2.2o l
i !., S :. !,. i l l., ; ! * ;.
I I
I 2.1 2.0 1.9 1.8 E:i 1.7 0.
1.6 1.5 1.4 I
1.31 1.2-1.1 f
1.0 0
10
.20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 43 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 27. LHGR MULTIPLIER VERSUS CORE POWER FOR ALL ATRIUM-10, ALL EXPOSURES, PROOS 1.10 1.00 0.
Ur-CD x=
-J 0.90 0.80 M1111H TI1Ill H ill H I I-I I II I I
I '0.91' Mill I11 Mill I
I Fill Hill I I-IL 0.70 0.60 0
10 20 30 40 50 60 70 80 90 Power, % rated 100 110
Page 44 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 28. LHGR MULTIPLIER VERSUS CORE POWER FOR ALL ATRIUM-10, ALL EXPOSURES SINGLE LOOP OPERATION (SLO) 1.10 1.00 II I
I ~ ~ ~.
I.
I. I I. F I
I I.
!. I I I I.
I I -
! I I ' i I I I I -
I I I 0.90 C.)
I
-j 0.80 E.
, I.
'S.
i.'
I I'.
1-
!!l'l!!!!l!.
l ! ! l -!
I' i II II!!II!
II I
I !!! I
.I..I : I.
.II
!I !II I ! I.I.!
!I I
! I
! I
! I 0..7a ! -
! I I I I
I
. I!
I I
i I
I I -
I
' I !
I I41 0.70 IIIEIIITETT TEl:
IIIIIIl:lI:
,I:.:iI.rtIIuIII:u IITIIEIIITEII
- ,r:ITrT c;u:c.I:
TE*!.I.ITE:::
ITTITE I
i []TJ i N 1! f 1 l 1T ! h]
i I 11 0.60 I I
T 1
-T 0
10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 45 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 29. OPERATING LIMIT MCPR (MCPRF) VERSUS CORE FLOW FOR ATRIUM-10 FOR RECIRCULATION SYSTEM IN LOOP MANUAL, ALL EXPOSURES 1.51 lEl llli l~;llhll ll lllll
~lii~
I I. -.
. I..
I.
-!I 1
1 1 :
II
- 1 i; c
r
-c-i-'
.i m_
'I i ii.
1.4
.:-1 II..
Il IE El
[I I I I
I II_.
. I
.II I I I
I E l
I II I
I I...
.I I
- I i
1.3 E
cL
- Ea-C.
II Tl '1-I ifl I I I 1.15 ITA THI 1.2 1.1..
1-11-I I..
I I
I I
I I I
I..
1 1
1 1
1
. I I I . - I I.....
-11.
I. -.
. I - I.__
II -
I. I. II....
I.. III.. I. i III.. III...
I -
III I. III I---. -
_11-11..
I..
I-1.0 0.9 0
10 20 30 40 50 60 70 80 90 100 110 120 Core Flow, % Rated
Page 46 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 30. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIUM-10, ALL EXPOSURES, EOC-RPT INOPERABLE, OR CONCURRENT EOC-RPT INOPERABLE I FHOOS 2.3 2.2 -
I I
I II IIH I +.
11 lo l _IISA 2.1 2.0 1.9 1.8 4.-
E ZI 1.7 I
1.6 1.5
-1.4 I
1.4 1.3 1.2 1.1 1.0 0
10 20 30 40 50 60 Power, % rated 70 80 90 100 110
Page 47 of 47 RBS CYCLE 14 COLR Revision 0 FIGURE 31. LHGR MULTIPLIER VERSUS CORE POWER FOR ALL ATRIUM-10, ALL EXPOSURES, EOC-RPT INOPERABLE, OR CONCURRENT FHOOS / EOC-RPT INOPERABLE 1.10 1.00 C)
I 0.90 0.80 1.00-U I 50 1 I A ' 1 1 I I I I i I I I I I 0J7(
0.77 F
LI I I 1
0.70 1 ; i i 1 1 : : ; 1 ; i 1 1 : : i HH! I:;;:!;;
I 1 : 1 ; 1 : I 1 : ; i 1 i : : ;
1 I !I I
II.
I IL I
-I 1
I II I I.~II 0.60 0
10 20 30 40 50 60 Power, % rated 80 90 100 110 70