RBG-46792, Unit 1, Fifteenth Fuel Cycle Core Operating Limits Report (COLR)
| ML080700229 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 03/03/2008 |
| From: | Lorfing D Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RBG-46792 | |
| Download: ML080700229 (46) | |
Text
Entergy Operations, Inc.
Entergy River Bend Station 5485 U.S. Highway 61 N St. Francisville, LA 70775 Tel 225-381-4157 David N. Lorfing Manager, Licensing March 3, 2008 U.S. Nuclear Regulatory Commi ssion Attn: Document Control Desk Washington, DC 20555
Subject:
River Bend Station - Unit 1 Docket No. 50-458 License No. NPF-47 Fifteenth Fuel Cycie Core Operating Limits Report (COLR)
Dear Sir or Madam:
Enciosed is Revision 0 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 -Unit 1 DNL/bmb
)400(l
RBG-46 792 Page 2 of 2 cc: Mr. Elmo E. Collins, Jr.
U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Senior Resident Inspector P.O0. Box 1050 St. Francisville, LA 70775 U.S. Nuclear Regulatory Commission Attn: Mr. Jack Donohew Washington, DC 20555-000 1 Louisiana Department of Environmental Quality Office of Environmental Compliance Attn: Mr. Jeff Meyers Surveillance Division P.O0. Box 4312 Baton Rouge, LA 70821-4312
Core Operating Limits Report Cycle 15 Revision 0
Page 1 of 43 RBS CYCLE 15 COLR Revision 0 RIVER BEND STATION, CYCLE 15 CORE OPERATING LIMITS REPORT (COLR)
PREPARED BY: Phu Vo Date:
Responsible Engineer REVIEWED BY:
APPROVED BY:
Manager -
i~i4.4'L &
Nuclear Engineering b~ D ate: &1%g/Q~~
APPROVED BY: ateL~
Director, Engineering River Bend Nuclear Station APPROVED BY: Date: -/ 74ý
'6n~-site Safety Review Committee River Bend Nuclear Station
Page 2 of43 RBS CYCLE 15 COLR Revision 0 t TABLE OF CONTENTS INTRODUCTION AND
SUMMARY
.......................................................... 3 CONTROLRODS ................................................................................ 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..I 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...................................................................... 36
Page 3 of 43 RBS CYCLE 15 COLR Revision 0 INTRODUCTION AND
SUMMARY
This report provides Cycle 15 values for the following Technical Specifications:
- 1. AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) limuits,
- 2. MINIMUM CRITICAL POWER RATIO (MCPR) limits,
- 3. LINEAR HEAT GENERATION RATE (LHGR) limits,
- 4. FRACTION OF CORE BOILING BOUJNDARY (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 t'itled 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',
- 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 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 Appe ndix A shall be used.
The reload analyses were performed in accordance with AREVA methodology and its applicability to Cycle 15 was confirmed 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 of43 RBS CYCLE 15 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 29,641 MWd/MTU).
EOC - End of Cycle (Core Exposure 30,877 MWdJMTU).
EEOC - Extended cycle with Increased Core Flow (Core Exposure 31,191 MWdIMTU).
EFEOC - 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.
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.
Page 5 of43 RBS CYCLE 15 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. 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 6 of43 RBS CYCLE 15 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 4, 5, 6 and 7, respectively. Figure 27 is used in lieu of Figure 4 when the Reactor Recirculat ion 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 1 and are consistent with a Safety Limit MCPR from Technical Specification 2.0.
Page 7 of43 RBS CYCLE 15 COLR Revision 0 TECHNICAL SPECIFICATION 3.2.3 POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE (LHGR)
The limiting LHGR value for ATRIUM- 1 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 i'nFigures 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 of43 RBS CYCLE 15 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 afunction of reactor recirculationdrive 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)>ý TDESIGN (a ae)- 50' F, and rated equivalent at off-rated reactor conditions.
OR P! *30%
- b. Case 2 - Reduced Feedwater Heating Operation T, (at rated) < T IGIN (at rated) - 5Q0 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 43 RBS CYCLE 15 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 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) Ž!T~wIGN (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~wIG' (at rated) - 500 F, and rated equivalent at off-rated reactor conditions.
AND P >30%
Where: .T~w 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 of43 RBS CYCLE 15 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 11I 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 a function of reactor recirculationdrive 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:
T, (at rated)>ý TDESIGN (a ae)- 500 F, and rated equivalent at off-rated reactor conditions.
OR P! *30%
- b. Case 2 - Reduced Feedwater Heating Operation T, (at rated) < T ""' (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 43 RBS CYCLE 15 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 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)>ý TD'IGIN (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'IGIN (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 43 RBS CYCLE 15 COLR Revision 0 TECHNICAL REOUIREMENT 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 I - Normal Feedwater Heating Operation or Low Reactor Power:
T, (at rated)>ý T DESIG (at rated) - 500 F, and rated equivalent at off-rated reactor conditions.
OR P*!ý30%
- b. Case 2 - Reduced Feedwater Heating Operation T, (at rated) < T ""' (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 43 RBS CYCLE 15 COLR Revision 0 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 1 ElA Stability Power Uprate Evaluation."
ANALYTICAL METHODS DOCUMENTS (TS 5.6.5'):
- 1) XN-NF-8 1-58(P)(A) Revision 2 and Sup plements 1 and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.
- 2) XiN-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 (P)(A), RODEX2A (BWVNR) Fuel Rod Thermal-Mechanical Evaluation Model, Siemens Power Corporation, February 1998.
- 4) ANF-89-98(P)(A) Revision 1 and Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.
- 5) XN-NF 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 19(P)(A) Volume 4 Revision 1, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENG Methodology to BWR Reloads, Exxon Nuclear Company, June 1986.
- 7) EMF-2 158 (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) X-N-NF 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) X-N-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 1 Revision 1 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) X-N-NF-825(P)(A) Supplement 2, BWP./6 Generic Rod Withdrawal Error Analysis, MCPRp for Plant Operations within the Extended Operating Domain, Exxon Nuclear Company, October 1986.
Page 14 of43 RBS CYCLE 15 COLR Revision 0
- 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-1I997(P)(A) Revision 0, ANEW 10 Critical Power Correlation, Siemens Power Corporation, July 1998.
- 15) EMF-1I997(P) Supplement 1 (P)(A) Revision 0, ANEB-l10 Critical Power Correlation: High Local Peaking Results, Siemens Power Corporation, July 1998.
1-6) 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.
- 18) EMF-23 61 (P)(A), Revision 0 "EXEM BWR-2000 ECCS Evaluation Model," Framatome ANP Richland, Inc.
- 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, ATR1UMvUm-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 43 RBS CYCLE 15 COLR' Revision 0 Table 1. Aligned Drive Flow 101.209 A40 -31.028 - A'00+ 70. 181 - W WD =
70.181 - ( A100 _ A 40 Where:
= FCTR card input drive flow in percent rated,
= Aligned drive flow in percent rated, A40 = Low flow drive flow alignment setting, and A100 = High flow drive flow alignment setting.
Page 16 of 43 RBS CYCLE 15 COLR Revision 0 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 ý29 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 34.8B 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 KBOC Exposure (GWd/MTtJ) 2 26 26 26 23 35.0 35.5. 35.5 38.2 No. Per Fuel.Type Description Cycle Loaded Quarter core 22 .A1O-3996B-11G45 .12 .1 23 A1O-3981B-15GV75 12 5 25 A1O-3775B-9GV60 13 10 26 A1O-3747B-13GV70 13 40 29 A1O-3705B-13GV70 14 46 30 A10-3810B-14GV75 15 40:
31 A1O-3854B-12GV75 15 14
Page 17 of43 RBS CYCLE 15 COLR Revision 0 FIGURE 2. MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FOR ATRIUM-10 13 t~ 4 4 (0,12.5)-(515 ~r4.
12 -- 72 I.~ j 4..7 ...... ..
4 w ... .J....~....
w lo t4 z -M LU w Tt LU~~(7 7h4 3)4-I 4E _E-
.4. .. ..............
8 .......... ~ .
4444
.4~
4 5 .-
0 10 4 0 o7 73)
Average Planar Exposure (GWd/MTU)
Page 18 of43 RBS CYCLE 15 COLR Revision 0 FIGURE 3. LINEAR HEAT GENERATION RATE (LHGR) LIMIT VERSUS PELLET EXPOSURE FOR ATRIUM-10 14 4-j--
14 (0,13.4)t ~ (18.9,13.4) *;.~.j 13 ~ 13 1227 12 12 4- .z 4 ~
I 11 c 10 10 0
(U
- 4) -T-n 9 8,
_j 8
- 4 71'-4 7 .7 6
I1 5 5
0 10 20 30 40 50 60 70 Pellet Exposure (GWdIMTU)
Page 19 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 4. OPERATING LIMIT MCPR (MCPRF) VERSUS CORE FLOW FOR ATRIUM-10 FOR RECIRCULATION SYSTEM IN LOOP AUTO CONTROL, ALL EXPOSURES 1.50 1.40- ~ .. *rI:~1
_~~4 131i I444 I 11 .3 R F1 II .
1 1.15 1 1l L1 .j1 i 100. m1l .
0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow, %rated
Page 20 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 5. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE PO.WER FOR ATRIUM-10, EXPOSURE RANGE BOC TO EOC 2.3 2.2
~>50 Flow ~ r-**~~--
2.1 ............................
- 2.0 1.9
<=~ Fl 5D%
w .......
1.8 E
!D 1.7 7 - -
CL 0 1.6 (L
44- 1. 3 T~
1.5 4:9 -1.4~
1.4 1.3 I ~ 2
.. L4J -'4-~r-"-- ~ 9'~.
1.2
.. LL.L.)
12~4-F" f14~. 1 1.1 I- -4ii4 1.0 9 Q 0 10 20 30 40 50 60 70- 80 90 100 110 Power, % rated
Page 21 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 6. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIIJM-1O, EXPOSURE RANGE EOC TO EEOC 2.3 -~~t4i.
-J-21'
~t~t--4. rIi.. 17H ~~ t4 T 20~ 50%~o 196w 744 1- 4 ri 4
-.4f-i; 13 i 1I~~I~..1,)-.
, I'..~
ll.. I--.ý. I
+1 .-
0 1 20 30 40 0 0 7 80 90 10011 PoeJrae
Page 22 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 7. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIUM-10, EXPOSURE RANGE EEOC TO EEEOC 21 :T3-i 4- 71; L- tTT-#i-4+/- 4 L 4...
<50F ~ > 500/ Flow 17 ~
-'"-'F ~ 4- r-
<= 50% Flow .9 .;.....
JL- L-4-4.
E 16.3" ~ .T.iHL..,' . .
0ý - 7 Y .. .........
.-4. p ......... 14.
MIby 1314 T,.~---
v.4-.. V4
~+4 1 3112 L-,
4 T'
J t4II. ...... .-
+ - 'l4' ' -
1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 23 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 8. LHGR MULTIPLIER VERSUS CORE POWER FOR ALL ATRIUM-10, EXPOSURE RANGE BOC TO EEOC 1.10 1.00 0.90 0.
0 U-CD I
-J 0.80 0.70 0.60 0 10 20 30 40 50 60 .70 80 90 100 110 Power, % rated
I Page 24 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 9. LHGR MULTIPLIER VERSUS CORE POWER FOR ALL ATRIUM-1D, EXPOSURE RANGE EEOC TO EEEOC 1.10 ,
L. . I .1 4,. 1-.J .~ . . . . - L 1.00 3
.~ .. . . .. . ..... .. i 0~
0 LL (9
I
-J 1,0%Flow 17:4~T4
~ o II 1 4-. '.-....
0.80.
0.7 607'_j 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 25 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 10. LHGR. MULTIPLIER VERSUS CORE FLOW FOR ALL ATRIUM-10, ALL EXPOSURES 1.10-3 4
-1 1 1.00 1-V12 F.V UL~
LII 0819 4-1 f4 0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow, % rated
Page 26 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 11. MONITORED REGION BOUNDARY (CASE 1) 1200-----------------I------I-------------- r----------- I------------- ------------ ------ ----
W 60 MONITONE 0
S 50 -- ----------- --- ------ -------------- ----- --------------- ------
wu 0 40-0 ------- -------I --- - --- -------- --- ------ ------I- ------ --------- -
30 ----------------------------------------------------- 0------
0 10 20 30 40 50 60 70 80 90 100 110 ICORE FLOW (% rated)
Page 27 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 12. MONITORED REGION BOU~NDARY (CASE 2) 120 110 ------------- -------------
100 -------------
90 - -----------------
I------------
- -------- I-------------
I ------------
80 - ------------
------------- I ------------
- ----------- I ------------
70 -------------
- ------------ I ---
11------------
---------- ------------------------I --------
I-60 ------------
REGION w ----
50 0
0 40 ------------- ----------------------- ------- L------------------
30 ------------- :------
20 ------------------------------------- - ----- j--------
j-------------- I------------
I------------
10 ------------- -----------
I-------------
0 0 10 20 30 40 50 60 70 80 90 100 110 CORE FLOW(% rated)
Page 28 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 13. APRM FLOW BIASED SIMULATED THERMAL POWER
- HIGH SCRAM SETPOINTS AND RESTRICTED REGION BOUNDARY (TWO RECIRCULATION LOOP OPERATION - CASE 1) 120 100 90
--------- 0 I------- -------
ed 70 50 Boundary High Endpoint 0
40 j NS Non-Setup Scram RR Restricted Region 20 -
I IJ I I 10-0 0 10 20 30 40 50 60 70 Be3 90 100 110 120 ALIGNED DRIVE FLOW (%.rated)
Page 29 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 14. APRM FLOW BIASED SIMULATED THERMAL POWER
-HIGH SCRAM SETPOINTS AND RESTRICTED REGION BOUNDARY (SINGLE RECIRCULATION LOOP OPERATION - CASE 1) 120 110 1008
-..... ... .... . .. . Nominal Value .... L. .. . . .
Allowable Value 70 0 SLO Restricted Re~on
- a. *, Boundary High Endpoint --
... ~~~~~~~~
. ~ ..... ..... .Scram. Se. -----
w 50 -
0ý NS onSetup Scram 0.
0 40 -
____ RR Restricted Region 20
. . .. . .. . .. .. . . . .. . . . ... . . . . . .. . . . . I- ----
10 0I 0 10 20. 30 40 50 60 .70 80 go 100 110 120 ALIGNED DRIVE FLOW (%rated)
Page 30 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 15. APRM FLOW BIASED SIMULATED THERMAL POWER
- HIGH SCRAM SEIPOINTS AND RESTRICTED REGION BOUNDARY (TWO RECIRCULATION LOOP OPERATION - CASE 2) 120 ------------
- ------------------------------------- I-----------------------------
110++/- ------------------------------------------------I--------------------------------------- ------ ------------
100 + ----------- ------------ ------------------------ I --------------
90 + ---------- --------- -- ------------------------4-------- ------ --- --------r----------------------- T- - - - - - - - - -- - -- - - - - - - ------------
80 l -----------I-------------------------------------- --- -- ---- ----- --- ------------ ------------
- Nominal Value 70 - ---------- --------------------------------- -- ---- --- --- ---- ------------ - Allowable Value ------------
'U o TLO Restricted Region 60 - ---------- ------------ ------------ ---- -- II-- ------ -- - ---------II---------------
Boundary High Endpoint 0
50o ---------- ------------------ ---- --- --- ---- ---- ----------- ------------ S Setup Scram 0~
N Non-Setup 0 ----- ----- ------- ---- ---- ------------ ----------- ------------
40- RR Restricted Region ------------
NS - ------ - I-------------
RR 20 ------------ ------------------------- ----------- ------------ ----------- ------------ ------------
10 ------------ -----------, - -----------------
0 0 10 20 30 40 50 60 70 s0 90 100 110 120 ALIGNED DRIVE FLOW (%rated)
Page 31 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 16. APRM FLOW BIASED SIMULATED THERMAL POWER
- HIGH SCRAM SETPOINTS AND RESTRICTED REGION BOUNDARY (SINGLE RECIRCULATION LOOP OPERATION - CASE 2) 120 110 100 ---------- ------------
90 ---------- ------------
80 ---------- ------------
70 Nominal Valt eC ------------
0 60 Allowable Va lue 0 SLO Restricte d Region 0 50 Boundary Hig -hEndpoiitnt ------------
0 S Setup Scram 40 -----------------
N Non-Setup 30 ----
- ----- - ---------------- R R Restricted Re~gion RR 20 ---------- ----------- ------------
10 ---------- ------------------------
0 10 20 30 40 50 60 70 80 90 100 110 120 ALIGNED DRIVE FLOW (%rated)
Page 32 of 43 RBIS CYCLE 15 COLR Revision 0 FIGURE 17. APRM FLOW BIASED NEUTRON FLUX - HIGH ROD-BLOCK SETPOINTS (TWO RECIRCULATION LOOP OPERATION - CASE 1) 120 110-100 -
90 -
so-70
- Nominal Value 60- .. ......
.. ... . ... .. ... ... .. ... .. .- Allowable Value --- - - - - -r- - - - -
s Setup Rod-Block 0 50.
NS Non-Setup Rod-Block 40 30 20 .. .. . .. .. .. ... .. .. .. . . .. . . .. . . .. . . -- -- -- - -- - ---- ----
10 0 I 0 10 20 30 40 50 60 70 80 90 100 110 120 ALIGNED DRIVE FLOW (%.rated)
Page 33 of 43 RBS CYCLE 15 COLIR Revision 0 FIGURE 18. APRM FLOW BIASED NEUTRON FLUX - HIGH ROD-BLOCK SETPOINTS (SINGLE RECIRCULATION LOOP OPERATION - CASE 1) liiiM 110 ---------- ...................... ...........................I----------------------- T ----------7 ----------r ......................
10og........... .......... .......... .......... .......... ..................... ..................... -----------I ----------
go ----------- -------- ---------- ----------2----------- --------- ---- --- i ----------T..........T..........r ---------- r ..........
80- -----------L----------L -------
... .... .........I-----------
.....................I..........L---------- I..........
V 70- ---------------------- .... .... .. ... ................. ...... .....................
NominalValue w do. r .......... r..........
---- ------- ---------- AllowableValue 0
- a. S getup Rod-Block
'Ii 50- ----------------------------- ------ .......... ---------- ------ .......... ..........
0ý A NS Non-Setup Rod-Block 0,
40 ------- ---- -- --- ------- ---------- I----------- -----------r----------
S 30~ .................... ..... .................................................. ............ .......... --------
NS 20 ---------- .......... -------------------- ---------- ..........I----------- ---------- ---------- ---------- ---------- ----------
10 ........... ---------- ---------- .................................
T----------r ........... r ----------
0 0 10 20 30 40 50 50 70 80 90 100 110 120 ALIGNED DRIVE FLOW r/. rated)
Page 34 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 19. APRM FLOW BIASED NEUTRON FLUX - HIGH ROD-BLOCK SETPOINTS (TWO RECIRCULATION LOOP OPERATION - CASE 2) 120 - .
1100-------------------------------- ------------------- ------ -----
90 ------------- -------------- - - - - -- - - -- - - - -- --- -- - - - -- - --- - - - -- - - - - - -
- - Nominal Value 70 -- - - - - -- -- -- -- - - -- - - - - -- - - - - -
Allowable Value
- -: Set p Ro-Block wU 50-- - - -- - - - - - -- -- - - - - - - - -- -- -- -- - --. -- --
NS Non-Setup Rod-Block 0 0 10------20----- -- 50-- 0- 0--
--- 80-----
90----- 100--110 -120 ALIGNED---DRIVE--- FLO---raed
Page 35 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 20. APRM FLOW BIASED NEUTRON FLUX - HIGH ROD-BLOCK SETPOINTS (SINGLE RECIRCULATION LOOP OPERATION - CASE 2) 120 110 --- ---I----------------------- ------- --- -- -- - ---------- -----------
80 M~ N0SNnSetup Rod-Block 0U -----------
20 0
0 - - -- - - - -- - - - - - -k- - - - - - - - - - -- - - - -- - - - -- - - - - -- - - - --- - - - - - - - - -- -1 - -I--- - - - -
0 10 20 30 40 so 60 70 80 90 100 110 12 ALIGNED DRIVE FLOW (%rated)
Page 36 of 43 RBS CYCLE 15 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) (2)
- Reactor Recirculation System in Loop Manual control.
- End of Cycle Recirculation Pump Trip (EOC-RPT) Inoporable '
- Single-Loop Operation (SLO)
SPower 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 ioop auto and 10, 27 for ioop 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 ioop auto;' and 10, 27 for loop manual.
()The power dependent MCPRp for normal operation (Figures 5, 6.and 7) and equipment out of services (EOOS) described in (1) and (2) above 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).
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 43 RBS CYCLE 15 COLR Revision 0 FIGURE 21. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR-ATRIUM-10 BOUNDING FHOOS AND EOC-RPT INOPERABLE BOC TO MOC 2.3*
-2 1 7 ' f 2.2- -"4-2.11 -~~7r; ~ > 0%Flow ~.4+/-
T-2.0-1.9.
1.8. -T7A 4, 4-._
E 1.7.
CL T-1'-r-4--
1.6-rd-f A4+-+4F-4 * -4' 1.5-1.4.,
-1.4.
1.3- .4-12- -t '.T...-4. . -
- 1. 9 1.0 -
U I a I I I 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 38 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 22. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIUM-10 BOUNDING FHOOS AND EOC-RPT INOPERABLE MOC TO EEEOC 2.3 4--4j 4- J 44-~ ..
2.2 2.1 4. t-2.0 -j ~~ {~ ~ ~ ~ i : - .1.....*
1.9 4 il' 4 1.8 :ZEM~ 73/4+/-I 83____rr E
1.7 4-I 1.6 1.5 .......................
7............::~Y r=ttj .............
1.4 1 i' Z-. _ ZZ 4+ 4 1.3
~~
TP~~rT7~~
4
-~--~----~
121 4m4 i--.T 4-j .
P ~ ~ l S.-.
1.2 L t i 4 _
S~
1.1 1.0 0 10 20 30 40 50 60 70 80 90 10 110 Power, % rated
Page 39 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 23. LHGR MULTIPLIER VERSUS CORE POWER FOR ATRIUM-i10 BOUNDING FHOOS AND EOC-RPT INOPERABLE ALL EXPOSURES 1.10 1.00 0.90 0.
-j 0.80 0.70 0.60 0 10 20 30 40 50 60 -70 80 90 100 110 Power, % rated
Page 40 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 24. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIUM-10, PRESSURE REGULATOR OUT OF SERVICE (PROOS), BOC TO EEOC 2.3*
2.2- tL 2.17-2.1
< 50/1147 2.0-1.9.
~1 8 3~
1.8- at= :
-1.43 1.7-4 445 .1-0 1.6-T'-IT 7-t-7 3 ..
1.5. .4 4 z$g-i6 $+t- t 4 1.4 4 r ~m'-. L...f+...
1.3 4--H 1.2
-4 1.1 14 4 4
4 I 4.... - 1"Tý :~ 1 LA J4 .. ',
1.0 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 41 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 25. OPERATING LIMIT MCPR (MCPRp) VERSUS CORE POWER FOR ATRIUM-10 BOUNDING FHOOS, PROOS AND EOC-RPT INOPERABLE ALL EXPOSURES 2.3 2.2
~~4.....U -1 S50%Flow 2.1 2.0
<= 50%o Flow TT, 1.9 1.8
- ~ ~ T. I E
1.7 CA.
1.6 L L 1.5 L -1.63'-H.
1.4 1.3 t 4 ~ 4 IL.~.
1.2 1.1 1.0 11 of I I 0 9 9 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 42 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 26. LHGR.MULTIPLIER VERSUS CORE POWER FOR ALL ATRIUM-10 BOUNDING FHOOS, PROOS AND EOC-_RPT INOPERABLE ALL EXPOSURES
.1..
1.00 ~ "tttI4i~tttr1TT20
~ . 0.891 0.90 ~ T Q.
U-0r 0.80 ii4 0'77~
0.072 0 10 20 30 40 50 60 70 80 90 100 110 Power, % rated
Page 43 of 43 RBS CYCLE 15 COLR Revision 0 FIGURE 27. OPERATING LIMIT MCPR (MCPRF) VERSUS CORE FLOW FOR AT.RIUM-10 FOR RECIRCULATION SYSTEM IN LOOP MANUAL ALL EXPOSURES 1.5
~~4-1.4 J- 1~j ~
ILU J. 41 71, . 1.0
~4
- 1. -1vh 4r 4 - T+1r
.1, 1 -T ijI!ii418 0.9.4 0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow, % Rated