ML18176A052
| ML18176A052 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/22/2018 |
| From: | Emily Larson Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GNR0-2018/00031 | |
| Download: ML18176A052 (23) | |
Text
- -=~ Entergy Entergy Operations, Inc.
P.O. Box756
-Port Gibson, Mississippi 39150 Eric A. Larson Site Vice President Grand Gulf Nuclear Station Tel: 601-437-7500 GNR0-2018/00031 June 22, 2018 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Core Operating Limits Report Cycle 22 Grand Gulf Nuclear Station, Unit 1 No. 50-416 License No. NPF~29
Dear Sir or Madam:
Entergy Operations Inc. is submitting a revised Core Operating Limits Report (COLR) for Grand Gulf Nuclear Station (GGNS) as required by GGNS Technical Specification (TS) 5.6.5.d. The revised COLR is for Cycle 22 operation. The analytical methods used to determine the Cycle 22
-Core Operating Limits were previously approved by the Nuclear Regulatory Commission and are listed in GGNS TS 5.6.5.
This letter contains no new commitments. Should you have any questions or require additional information, please contact Douglas Neve at 601-437-2103.
Sincerely,
£('~
Eric A. Larson
- Site Vice -President Grand Gulf Nuclear Station EAL/tdf
Attachment:
Core Operating Limits Report cc: (See Next Page)
GNR0-2018/00031 Page 2 of 2
- cc: NRC Senior Resident. Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 U.S. Nuclear Regulatory Commission ;* .. *.
- ' ) -~~~;~~
ATTN: Ms. Je_nnifer Bridges 1600 East Lamar Boulevard Arlington, TX 76011-4511
Attachment to G N R0-2018/00031 Core Operating Limits Report
ll'i l l 1
!iii m m 1 1 1 COLR Page 1 LBDCR 18051
CORE OPERATING LIMITS REPORT REASON FOR REVISION This rev1s1on provides the Cycle 22 core operating limits. These limits are based on a core power of 4408 MWt.
TABLE OF CONTENTS 1.0 PURPOSE 3 2.0 SCOPE 3
3.0 REFERENCES
4-6 3.1 Background References 4 3.2 Current Cycle References 4 3.3 Methodology References 5 4.0 DEFINITIONS 7 5.0 GENERAL REQUIREMENTS 8-10 5.1 Averaqe Planar Linear Heat Generation Rates 8 5.2 Minimum Critical Power Ratio 8 5.3 Linear Heat Generation Rate 9 5.4 Stability 9
- 5. 5 Applicability 9 5 .* . 5 Limitations and Conditions 10 Table 1 OPRM Upscale CDA Amplitude Discriminator 10 Setpoint Table 2 BSP Endpoints for Normal Feedwater Temperature 10 Table 3 BSP Endpoints for Reduced Feedwater 11 Temperature Table 4 ABSP Setpoints for the Scram Region 11 Table-.5 I,
Margin to Thermal Overpower and Mechanical 11 Overpower Limits Figure(s) 1 APLHGR Operating Limits 12 Figure(s) 2 MCPR Operating Limits 13-16 Figure(s) 3 LHGR Operating Limits 16-18 Figure 4 Backup Stability Protection Regi~n Boundaries 19 for Normal Feedwater Temperature Figure 5 Backup Stability Protection Region Boundaries 20 for Reduced Feedwater Temperature COLR Page 2 LBDCR 18051
CORE OPERATING LIMITS REPORT 1.0 PURPOSE On October 4, 1988, the NRC issued Generic Letter 88-16 [3.1.1] encouraging licensees to remove cycle-specific parameter limits from Technical Specifications and to place these limits in a formal report to be prepared by the licensee. As long as the parameter limits were developed with NRC-approved methodologies, the letter indicated that this would remove unnecessary burdens on licensee and NRC resources.
On October 29, 1992, Entergy Operations submitted a Proposed Amendment to the Grand Gulf Operating License requesting changes to the GGNS Technical Specifications ~o remove certain reactor physics parameter limits that change each fuel cycle
[3.1.2]. This amendment committed to placing these operating limits in a separate Core Operating Limits Report (COLR) which is defined in Technical Specifications.
This PCOL was approved by the NRC by SER dated January 21, 1993 [3.1.3].
The-COLR is controlled as a License Basis Document and revised accordingly for each fuel cycle or remaining portion of a fuel cycle. Any revisions to the COLR must be submitted to the NRC for information as required by Tech Spec 5.6.5 and tracked by Licensing Commitment 29132. This COLR reporti the Cycle 22 core operating and stability setpoint confirmation and regions.
2.0 SCOPE As defined in Technical Speci fi cation 1.1, the COLR is the GGNS document that provides the core operating limits for the current fuel cycle. This document is prepared in accordance with Technical Speci fi cation 5. 6. 5 for each reload cycle using NRC-approved analytical methods.
- The Cycle 22 core operating and stability limits included in this report are:
- the Average Planar Linear Heat Generation Rate (APLHGR),
- the Linear Heat Generation~Rate (LHGR) limit, and
- the DSS-CD stability setpoint confirmation and regions.
CORE OPERATING LIMITS REPORT
3.0 REFERENCES
This section contains the background, cycl e-speci fi c, and methodology references used in the safety analysis of Grand Gulf Cycle 22.
3.1 Background References 3 .1.1 MAEC.i:-88/0313, Generic Letter 88-16, "Removal of Cycl e-Speci fi c Parameter Limits from Technical Specifications", October 4, 1988.
3.1.2 GNR0-92-00093, Proposed Amendment to Grand Gulf Operating License, PCOL-92/07, dated October 29, 1992.
3.1.3 GNRI-93-0008, Amendment 106 to Grand Gulf Operating License, January 21, 1993.
3 .1. 4 GEXI 2000-00116, K. V. Walters to J . B. Lee, "Technical -Speci fi cation and COLR References for Grand Gulf Nuclear Station and River Bend Station,"
1 November 3, 2000.
3.2 Current Cycle References 3.2.1 ECH-NE-18-00022 Revision 0, Supplemental Reload Licensing Report for Grand Gulf Nuclear Station Reload 21 Cycle 22, dated May 2018.
3.2.2 ECH-NE-10-00021 Revision~' GNF2 Fuel Design Cycle-Independent Analyses for Entergy Grand Gulf Nuclear Station, dated November ?013.
3.2.3 ECH-NE-18-00023 Revision 0, Fuel Bundle Information Report for Grand Gulf Nuclear Station Reload 21 Cycle 22, dated May 2018.
3.2.4 NEDC-32910P, Revision 1, Grand Gulf Nuclear Station SAFER/GESTR-LOCA Accident Analysis With Relaxed ECCS Parameters, dated October 1999.
I 3.2.5 GGNS-NE-10-00022 Revision o; Grand Gulf Nuclear Station MELLLA+ Task T0407, ECCS-LOCA Performance, dated September 2012.
3.2.6 GGNS-SA-09-00002 Revision 1, Grand Gulf Nuclear Station GNF2 ECCS-LOCA Evaluation, dated December 2009.
3.2.7 NEDC-33173P-A, Rev.4, Application of GE Methods to Expanded Operating Domains, dated -November 2012 3.2.8 NEDC-33006P-A, Rev.3, GE BWR Maximum Extended Load Line Limit Analysis Plus, dated June2009 3.2.9 ECH~NE-18-00029, Revision 0, GGNS Cycle 22 GESTAR Assessment, dated May 2018.
3.2.10 ECH-NE-14-00014 Revision 2, GGNS RF19 Bundle Reconstitution Report -
Bundle GEQ830, dated April' 2015.
3.2.11 KGO-ENO~JBl-18-053, Grand Gulf Cycle 22 GEQ830 RECON Applicability Letter, dated May 2018.
3.2.12 GEH-GGNS-AEP-632, GGNS MELLLA+ Final DSS-CD Settings Report, dated October 23, 2013.
CORE OPERATING LIMITS REPORT 3.3 Methodology References The Technical Specifications (TS) supported by each methodology reference are provided in brackets ({ }).
3.3.1 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 {TS 3.2.1, TS 3.2.2, TS 3:2.3}.
3.3.2 XN-NF-85-67(P)(A) Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, September 1986
{TS 3.2.3}.
3.3.3 EMF-85-74(P) Revision O Supplement 1 (P)(A) and Supplement 2 (P)(A),
RODEX2A (BWR) Fuel Rod Thermal-Methanical Evaluation Model, Siemens Power Corporation," February 1998 {TS 3.2.3}.
3.3.4 ANF-89-98(P)(A) Revision 1 and Supplement 1, ~Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995 {TS 3.2.3}.
3.3.5 Deleted 3.3.6 XN-NF-80-19(P)(A) Volume 1 and Supplements 1 and 2, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and_
Analysis, Exxon Nuclear Company," March 1983 {TS 3.2.1, TS.3.2.2, TS 3.2.3}.
3.3~7 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 {TS 3.2.1, TS 3.2.2, TS 3.2.3}.
3.3.8 EMF-2158(P)(A) Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-MICROBURN-B2, Siemens Power Corporation," October 1999 {TS 3.2.2, TS 3.2.3} .
3.3.9 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 {TS 3.2.2}.
3.3.10 XN-NF-84-105(P)(A), Volume 1 and Supplements 1 and 2, "XCOBRA-T: A Computer Code for BWR Transient- Thermal Hydraulic Core Analysis," Exxon Nuclear Company, February 1987 {TS 3.2.2}.
3.3.11 ANF-524(P)(A) Revision 2 and Supplements 1 and 2, "ANF Critical Power Methodology for Boiling Water Reactors," Advanced .Nuclear Fuels
' 3.3.12 Corporation, November 1990 {TS 3.2.2}.
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 {TS 3.2.2}.
3.3.13 XN-NF-825(P)(A) Supplement 2, "BWR/6 Generic Rod Withdrawal Error Analysis, MCPRp for Plant Operation Within the Extended Operating Domain," Exxon Nuclear Company, October 1986 {TS 3.2.2}.
3.3.14 ANF-1358(P)(A) Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005 {TS 3.2.2}.
CORE OPERATING LIMITS REPORT 3.3 Methodology References (continued) 3.3.15 EMF-1997(.P)(A) Revision 0, "ANFB-10 Critical Power Correlation," Siemens Power Corporation, July 1998 {TS 3.2.2}.
3.3.16 EMF-1997(P), Supplement l(P)(A), Revision 0, "ANFB-10 Critical Power Correlation: High Local Peaking Results, Siemens Power Corporation," July 1998 {TS 3.2.2}.
3.3.17 EMF-2209(P)(A) Revision 2, "SPCB Critical Power Correlation, Siemens Power Corporation," September 2003 {TS 3.2.2}.
3.3.18 EMF-2245(P)(A) Revision 0, "Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel," Siemens Power Corporation, August 2000 {TS 3.2.2}.
3.3.19 EMF-2361 (P)(A) Revision 0, "EXEM BWR-2000 ECCS Evaluation Model,"
Framatome ANP Richland, Inc., May 2001 {TS 3.2.1}.
3.3.20 Deleted 3.3.21 Deleted 3.3.22 NEDC-33383P, Revision 1, "GEXL97 Correlation Applicable to ATRIUM-10 Fuel," June, 2008 {TS 3.2.2}.
3.3.23 EMF-2292(P)(A) Revision 0, "ATRIUM-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation," September 2000 {TS 3.2.1}.
3.3.24 Deleted 3.3.25~*:( NEDE-24011-P-A, General Electric Standard Appli-cation for Reactor Fuel (GESTAR-II) {TS 3.2.1, TS 3.2.2, TS 3.2.3}.
3.3.26* NED0-33075P-A, Revision 8, Licensing Topical Report, Boiling Water Reactor Detect and Suppress Solution - Confirmation Density, November 2013 {TS 3.2.2, 3.3.1.1}
3.3.27* NED0-33612-A, Revision 0, Safety Analysis Report for GGNS Maximum Extended Load Line Limit Analysis Plus, September 2013 {TS 3.2.2,
- 3. 3 .1.1}
3.3.28* GGNS-NE~l0-00076 Revision O (GEH 0000-012101122-RO), GGNS EPU Option B Scram Times, dated September 2010. {TS 3.2.2}
- Note: These references are applicable when GE fuel is in the reactor.
CORE OPERATING LIMITS REPORT 4.0 DEFINITIONS 4.1 Average Planar Linear Heat Generation Rate (APLHGR) - the APLHGR shall be
~pplicable to a specific planar height and is equal to the sum of the linear heat generation rates for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the specified height.
4.2 , Average Planar Exposure - the Average Planar Exposure shall be applicable to a specific planar height and is equal to the sum of the exposure of all the fuel rods .in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the specified height.
4.3 Critical Power Ratio (CPR) - the ratio of that power in the assembly, which is calculated by ~pplication of the fuel vendor's appropriate boiling correlation, to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating.
4.4 Core Operating Limits Report (COLR) - The Grand Gulf Nuclear Station specific document that provides core operating limits for the current reload cycle in accordance with Technical Specification 5.6.5.
4.5 Linear Heat Generation Rate (LHGR) - the LHGR shall be the heat generation per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.
4.6 Minimum Critical Power Ratio (MCPR) - the MCPR shall be the smallest CPR which exists in the core. _
4.7 MCPR Safety Limit - the minimum-value of the CPR at which the fuel could be operated with the expected number of rods in boiling transition not exceeding 0.1% of the fuel rods in the core.
4.8 Oscillation Power Range Monitor (OPRM) - Provides automatic detection and suppression of reactor core thermal-hydraulic instabilities through monitoring neutron flux changes.
4.9 Backup Stability Protection (BSP) Scram Region - The area of the core power and flow operating domain where the reactor is susceptible to reactor instabilities under conditions exceeding the licensing basis of the current reactor system. An immediate manual scram is required upon entry.
4.10 Backup Stability Protection (BSP) Controlled Entry Region - The area of the core power and flow operating domain where the reactor is susceptible to reactor instabilities. Compliance with at least one alternate stabilfry control is required upon entry.
4.11 Automated Backup Stability Protection (ABSP) Scram Region - An automated reactor scram region that bounds the BSP Scram Region and is initiated by the APRM flow-biased scram setpoint upon entry.
4.12 End of Rated (EOR) - The Cycle exposure corresponding to all rods out, 100%
power, 100% flow, and normal feedwater temperature [3.2.1].
4.13 Middle of Cycle (MOC) - The Cycle 22 MOC Core Average Exposure (CAE) is separated into two segments; MOCl is EOR-5,062 MWd/ST, MOC2 is EOR-2,812 MWd/ST [3.2.1]. .
4.14 End of Cycle (EOC) - The Cycle 22 EOC CAE is 30,375 MWd/ST [3.2.1].
4.15 Maximum Extended Load Line Limit Analysis Plus (MELLLA+) - The GGNS MELLLA+
operating domain is depicted in Figure 4.
4.16 Maximum Number of OPRM Cells Along an Instability Symmetry Axis CM l - An OPRM configuration constant representing maximum number of OPRM cefis along an instability symmetry axis. It *is used to calculate the number of unresponsive OPRM cells. Per [3.2.12] the GGNS specific value is five (M.v = 5).
CORE OPERATIN~ LIMITS REPORT 5.0 GENERAL REQUIREMENTS 5.1 Average Planar Linear Heat Generation Rates Consistent with Technical Specification 3.2.1, all APLHGRs shall not exceed the exposure-d~pendent limits reported in Figure 1-1 [3.2.1].
5.2 Minimum Critical Power Ratio Consistent with Technical Specification 3.2.2, the MCPR shall be equal to or greater than the limits reported in Figure(s) 2 as functions of power, flow, exposure, and scram speed. [3*.2.1, 3.2.2, 3.3.28]. For operation at powers ~35.4%,
the power-dependent MCPR shall be determined based on scram time surveillance data as follows. [3.3.28]
- 1) If the average scram time (rAVE) satisfies the following:
r AVE ~ r B '
then the power dependent MCPR shall be equal to or greater than the Option B limits reported in Figure(s) 2 as a function of exposure.
- 2) If the average scram time rAvE >r 8 and r :::;0.2, then the power-dependent MCPR shall be equal to or greater than the Tau 0.2 limits reported in Figure(s) 2 as a function of exposure,
- 3) If the average scram time then the power-dependent MCPR shall be equal to or greater than the Option A limits reported in Figure(s) 2 as a function of exposure.
In the above equations:
rAVE = average scram time to the 20% insertion position as calculated by equation 1 of Reference 3.3.28, rH adjusted analysis mean scram time for 20% insertion as calculated by equation 3 of Reference 3.3.28 and where
'A the technical specification limit on core average scram time to the 20 percent insertion position (0.503 seconds).
CORE OPERATING LIMITS REPORT The limits determined above support operation with Turbine Bypass Valves Out of Service as descri.bed in Technical Specification 3.7.7. Additional MCPR operating limits are provided to support operation with EOC-RPT inoperable as described i-n Technical Specification 3.3.4.1.
5.3 Linear Heat Generation Rate Consistent with Technical Specification 3.2.3, the LHGRs for any GNF2 fuel rod at any axial location shall not exceed the nodal exposure-dependent limits reported in Reference 3.2.3 multiplied by the smalJer of either 1 the power-dependent or flow-dependent LHGR factors reported in Figures 3-1 and 3-2, respectively [3.2.1]. The limits determined above support operation with Turbine Bypass Valves Out of Service as described in Technical Specification 3.7.7.
- 5. 4 Stabil i ty The OPRM Upscale Confirmation Density Algorithm (CDA) Amplitude Discriminator setpoint is reported in Table 1.
The Backup Stability Protectioh (BSP) regions boundaries are reported in Figures 4 and 5 [3.2.1]. BSP measures support operation with the OPRM upscale trip function inoperable as desc~ibed in Technical Specification 3.3.1.1 Condition J. The endpoints for *the BSP region boundaries are provided for normal (NFWT) and reduced (RFWT) feedwater temperature operations in Tables 2 and 3, respectively. Figures 4 and 5
'depict the BSP region boundaries for NFWT and RFWT operations. Note that Figures 4 and 5 also depict the MELLLA+ and MELLLA domains, consistent with feedwater temperature operating limitations.
The ABSP APRM Simulated Thermal Power (STP) setpoints associated with the ABSP Scram Region are provided in Table 4. The ABSP setpoints are applicable to TLO and SLO, and to both normal and reduced feedwater temperature operations.
The BSP Boundary and Manual BSP region boundaries for normal feedwater temperature operations are valid for reductions in normal feedwater temperature as much as (and including) -10.0 °F.
5.5 Applicability The following core operatin~ limits are applicable for operation in the Maximum Extended Operating Domain (MEOD), with Feedwater Heaters Out of Service (FHOOS),
Turbine Bypass Out of Service (TBVOOS), and EOC-RPT inoperable. For operation with EOC-RPT inoperable, the alternate MCPR limits described in Section 5.2 above must be implemented. For single-loop operation (SLO), the following additional requirements must be satisfied.
- 1. THE APLHGRs shall not exceed the exposure-dependent limits determined in accordance with Section 5.1 reduced by a 0.83 SLO multiplier. [3.2.1].
- 2. THE LHGRs shall not exceed the smaller of the nodal exposure-dependent limits determined in accordance with Section 5.3 above or the nodal exposure-dependent limits reported in Reference 3.2.3 reduced by a 0.83 SLO multiplier [3.2.1].
3~ The MCPR shall be equal to or greater than the limits determined in accordance with Section 5.2 above increased by 0.00 to account for the difference between the two-loop and single-loop MCPR safety limits for the allowable range of single-loop operation [3.2.1].
I CORE OPERATING LIMITS REPORT Note that th~ above described limits are applicable to all bundles in the core; however, a re-inserted bundle (GEQ830 - reconstituted in RF19) requires a multiplier to account for uncertainties in its predicted neutronic response during operation. After re-constitution, the vendor documented analyses to determine its performance in C22 [3.2.10, 3.2.11]; which concluded that a 10% setdown was required for the TLs of GEQ830 (MFLCPR, MFLPD, MAPRAT) . This addi t.i ona 1 factor has been incorporated into the C21 core monitoring system.
5.6 Limitations and Conditions As required' by Limitation and Condition 9.10/9.11 of licensing topical report NEDC-33173P-A [3.2.7], the limiting Thermal and Mechanical Overpower results are reported in Table 5. The results are summarized as a percent margin to both of these limits. The results are confirmed to meet the required 10% margin to the design limits [3.2.1].
As required by Limitation and Condition 12.10.b of licensing topical report NEDC-33006P-A [3.2.8], the off-rated limits assumed in the ECCS-LOCA analyses are confirmed to be consistent with the off-rated LHGR multipliers provided Figures 3-1 and 3-2. These off-rated LHGR multipliers provide adequate protection for MELLLA+
operation.
As required by Limitation and Condition 12.5.c of licensing topical report NEDC-33006P-A [3.2.8], the plant specific power/flow map specifying the GGNS licensed MELLLA+ operating domain is included as Figure 4.
As required by Limitation and Condition 12.5.b of licensing topical report NEDC-33006P-A [3.2.8], operation with Feedwater Heaters Out of Service (FWHOOS) is prohibited while in the MELLLA+ operating domain [3.2.1]. In addition, as required by Limitation and Condition 12.5.a of licensing topical report NEDC-33006P-A
[3.2.8], and described in GGNS TS 3.4.1 LCO, SLO is prohibited in the MELLLA+
operating domain [3.2.1].Therefore, operations with RFWT and/or SLO must adhere to the operating domain.shown in Figure 5.
Table 1 OPRM Upscale CDA Amplitude Discri'minator Setpoint Amplitude Discriminator Trip 1.10 Table 2 BSP Endpoints for Normal Feedwater Temperature Endpoint Power(%) Flow(%) Definition Al 72.3 44.2 Scram Region Boundary, HFCL Bl 35.1 25.3 Scram Region Boundary, NCL A2 67.3 50.0 Controlled Entry Region Boundary, HFCL 82 26.4 24.4 Controlled Entry Region Boundary, NCL A3 100.0 85.4 BSP Boundary Intercept, HFCL 83 82.6 69.3 BSP Boundary Intercept, MELLLA Line COLR Page 10 LBDCR 18051
CORE OPERATING LIMITS REPORT Table 3 BSP Endpoin~s for Reduced Feedwater Temperature Endpoint Power(%) Flow(%) Definition Al' 62.9 44.6 Scram Region Boundary, HFCL Bl' 29.4 24.7 Scram Region Boundary, NCL A2' 67.3 50.0 Controlled Entry Region Boundary, HFCL 82' -26.4 24A Controlled Entry Region Boundary, NCL Table 4 ABSP Setpoints for the Scram Region Parameter Symbol Value Slope of ABSP APRM fl ow-biased trip linear segment m,nTn
- Constant Power Line for Trip from zero Drive Flow to pBSP-TRIP Flow Breakpoint.
ABSP APRM flow-biased trip setpoint drive flow 39. 0% RDF2 intercept. Constant Flow Line for Trip. WBSP-TRIP Flow Breakpoint value 6.4% RDF2 WBSP-BREAK
- 1. RTP - Rated Thermal Power 2. RDF - Rec1rculat1on Drive Flow Table 5 Margin to Thermal Overpower and Mechanical Overpower Limits Criteria GNF2 Thermal Overpower Margin 57.6%
Mechanical Overpower Margin 58.5%
CORE OPERATING LIMITS REPORT 0.00, 13.78 17.52, 13.78 14 13 12 11
=
3:
10 0::: 9
(!)
- c
..J
- a. 8
<(
~
7 6
5 4
0 10 20 30 40 50 60 70 Average Planar Exposure (GWd/ST)
Figure 1-1 Maximum Average Planar Linear Heat Generation Rate Note: Actual Limits described in Sections 5.1 and 5.5 COLR Page 12 LBDCR 18051
CORE OPERATING LIMITS REPORT 2.5 2.4 2.3 2.2 2.1 2.0
'ii: 35.4,2.00 35.4, 2.00 ct 1.9 a.
0 1.8 40, 1.69
- i 50, 1.68 35.4, 1.69 40, 1.67 Tau= 0.2 1.7 35.4, 1.67 1.6 35.4, 1.66 40, 1.66 1.5 100, 1.45 1.4 ..
Per Section 5.5, bundle GEQ830 uses these limits w/10% setdown 100, 1.35 1.3 100, 1.32 1.2 0 10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)
Figure 2-1 Cycle 22 Power-Dependent MCPR Limits BOC to MOC1 2.5 21.8,2.41 2.4 > 50% Core Flow 2.3 2.2 2.1
.::. 50% Core Flow 2.0 35.4, 2.00
'ii: 1.9 ct a.
0 1.8
- i 1.7 * -
1.6 50, 1.62 1.5 100, 1.48 70, 1.53 1 .4 100, 1.38 Per Section 5.5, bundle GEQ830 uses these limits w/10% setdown 1.3 * -
1.2 0 10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)
Figure 2-2 Cycle 22 Power-Dependent MCPR Limits BOC to MOC1 with EOC-RPT Inoperable COLR Page 13 LBDCR 18051
CORE OPERATING LIMITS REPORT 2.s T 2.4 t 21.8, 2.41
> 50% Core Flow 21.8,2.29 35.4, 2.22 2.1 It*
35.4, 2.05 2.0 a: 1
[ 1.91 0 1.8 50, 1.80
- !E 1.7 35.4, 1.66 1.4 tt 1.6 -i-1.5 100, 1.49 100, 1.39 1.3 1.2 f Per Section 5.5, bundle GEQ830 uses these limits w/10% setdown Option B
+,~_._--;1--~~-t----'~-+-~-'---t~-'-~+---'-~-t-~...._-+~-'-~t---'-~-+-----'~-I 100, 1.36 0 10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)
Figure 2-3 Cycle 22 Power-Dependent .MCPR Limits MOC1 to MOC2 2.5 21.8. 2.41 2.4 2.3 2.2 35.4,2.22 2.1 2.0
~ 50% Core Flow ,;;;,2_05 35.4, 2.05 a: 1.9 Option A ci'
- a. 40, 1.80 50, 1.80 35.4, 1.80 0 1.8
- !E 1.7 35.4, 1.69 ll"'-----
1.6 35.4, 1.66 100, 1.52 1.5 1.4 100, 1.42 1.3 Per Section 5.5, bundle GEQ830 uses these limits w/10% setdown 1.2 ~---'-~-+-~~-+~~~t---'-~t*~~~.--~~~---j~-'-~-+--~-~....._~~~
0 10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)
Figure 2-4 Cycle 22 Power-Dependent MCPR Limits MOC1 to MOC2 with EOC-RPT Inoperable COLR Page 14 LBDCR 18051
CORE OPERATING LIMITS REPORT 2.5 21.8, 2.41 2.4 / > 50% Core Flow 2.3 21.8, 2.29 35.4,2.22 2.2 -
2.1 ~ 50% Core Flow /
35.4, 2.05 35.4,2.05 2.0 a: Option A
~ 1.9
- a. 35.4, 1.82 0 1.8 a
1.7 1.6 35.4, 1.70 35.4, 1.67 40, 1.67 1.5 100, 1.51 1.4 - . 100, 1.43 Per Section 5.5, bundle GEQ830 uses these limits w/10% setdown Option B 100, 1.41 1.3 1.2 0 10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)
Figure 2-5 Cycle 22 Power-Dependent MCPR Limits MOC2to EOC 2.5 2.4 2.3 -
2.2 35.4, 2.22 2.1
.::: 50% Core Flow 35.4,2.05 2.0 35.4, 2.05 a: 1.9
~ 40, 1.82
- a. 35.4, 1.82 0 1.8 a
35.4, 1.10 r-4_0"*'*1_*7_0_ _ _ __
1.7 35.4, 1.67 1.6 40, 1.67 100, 1.54 1.5 1.4 Per Section 5.5, bundle GEQ830 uses these limits w/10% setdown Option B 1.3 1.2 0 10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)
Figure 2-6 Cycle 22 Power-Dependent MCPR Limits MOC2 to EOC with EOC-RPT.lnoperable COLR Page 15 LBDCR 18051
CORE OPERATING LIMITS REPORT 1.40
- 20. 1.38 30, 1.38 1.35 s0::
0.. 1.30 0
- E 90, 1.27 105, 1.27 1.25 Per Section 5.5, bundle GEQ830 uses these limits w/10% setdown
/
1.20 . --** *--*-*******-****-*+*************** ***-**********+*-*********'**-**-******-t-***-****-*****-**********t****************'*****--****-* ;---****..**-*....-**********: --****************************+**-****-*-******************-;---***************************+***************' *******--**-t**-*-*-* * *-*********,
0 10 20 30 40 50 60 70 80 90 100 110 Core Flow{% Rated)
Figure 2-7 Cycle 22 Flow-Dependent MCPR Limits 1.05 35.4, 1.00 100,1.00 1.00 0.95 *
- 0.90 ..
0.
0 35.4,0.865 if0:: 0.85 ~ 50% Core Flow c,
- i 0.80 * .
21.8,0.766 0.75 Per Section 5.5, bundle GEQ830 uses these limits w/10% setdown 0.70 - 35.4, 0.701 21.8, 0.671 > 50% Core Flow 0 10 20 30 40 50 60 70 80 90
- 100 110 Power (% Rated)
Figure 3-1a Cycle 22 Power-Dependent LHGR Factor BOC-MOC1 Note: These factors to be applied to the exposure-dependent limits as descibed in. Section 5.3 COLR Page 16 LBDCR 18051
CORE OPERATING LIMITS REPORT 1.05 35A, 1.00 100, 1.00 1.00 0.95
-Q. 0.90 0
if 0:::
0.85 ~ 50% Core Flow 35.4, 0.851
(!)
- r:
...I 0.80 21.8, 0.759 0.75 Per Section 5.5, bundle GEQ830 uses these limits w/10% setdown 0.70 35.4, 0.692 21.8, 0.671
> 50% Core Flow 0.65 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
, Figure 3-1b Cycle 22 Power-Dependent LHGR Factor MOC1-MOC2 Note: These factors to be applied to the exposure-dependent limits as descibed in Section 5.3 1.05.
35.4, 1.00 100, 1.00
. 1.00 0.95
-Q. 0.90
- u.o 0.85 ~ 50% Core Flow 35.4, 0.851 0
- ::
(!)
- r:
....1 0.80 21.8, 0.759 0.75
- Per Section 5.5, bundle GEQ830 uses these limits w/10% setdown 0.70 35.4, 0.692
. 21.8, 0.671 > 50% Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
Figure 3-1c Cycle 22 Power-Dependent LHGR Factor MOC2-EOC Note: These factors to be applied to the exposure-dependent limits as descibed in Section 5.3 COLR Page 17 LBDCR 18051
CORE OPERATING LIMITS REPORT 1.05 71.4, 1.00 105, 1.00 1.00
- 0.95 0.90 s
~ 0.85 LL:
D:!
<!> 0.80
- c
..J 0.75 0.70 -
Per Section 5.5, bundle GEQ830 uses these limits w/10% setdown 0.65
- 20, 0.652 30, 0.652 0.60 +-~--~~--~ -t--~--~--~ -+-~--~'--- --'--+--~-- ~-
0 10 20 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)
Figure 3-2 Cycle 22 Flow-Dependent LHGR Factor Note: These factors to be applied to the exposure-dependent limits as descibed in Section 5.3 COLR Page 18 LBDCR 18051
CORE OPERATING LIMITS REPORT CORE FLOW (% rated) 0 10 20 30 40 50 60 70 80 90 100 110 110 I j
I i . 1, I
i - - - - t--------
1 100
i ***--- ...... ! ****---1--,........--__..._ _ _ _ _ __
90
- 1
! MELLLA+ Boundary 80
- -10
.....Q)ns
.._ 60
-ffi --:
50 ;
Scram Region 1
~--------------}------*----*~---
- I ; I OPR~Armed R~gion *** -!-** ------!---
!-+--+-:-----~~.~~
~ *********!**********************i*************-********j*****--
0 ***- ******r***********--****-*1**********-*
a.. 40 w
0:::
0 30
(.)
20 Note:
10 SLO is prohibited in MELLLA+ region I l 1 I 0
0 10' 20 30 40 50 60 70 80 90 100 110 120 .-- 130 CORE FLOW (MLB/HR)
Figure 4 Backup Stability Protection Region Boundaries for Normal Feedwater Temperature (NFWT)
CORE OPERATING LIMITS REPORT CORE FLOW {% rated) 0 10 20 30 40 50 60 70 80 90 100 110 110
---:-----+---- :- - I i
4--------* ----****,**-****
l !
.i----- **-*
i I,******-- --******-t--******
I I
- - . ----'i *...
100 (105'fo,10 }
90
--1-* --:------- 1-- -----1----- ......_lm__,p,....l_em--.-en_te_d.....,B....-S_P_B-.-o_u_n.....,da,....ry__.
- ; --+
80 i ! !
~70 Q) res,
,_ 60
---+-------- MELLLABoundary ---+---------~A+-** - ------+---------1----------+----__y------ -----:---- *r--**-1****--
'#. l i 11
- .***;---****** *------**r***----- ****----:******- OPRM Armed Region J
.... ( .... ...
- -----*+*****---
---t-- - -+-- ---
t---+~-+-~-.-~+---if---+~""'t.---t-~-ff--1'!r---t-~-t-~~!~-1-~~!>---,-~-.i----. : !
~----!----******.;.*--****-! i
---i---___ i ____L ____ ---: _
20 10
...... i----- ------;--*-* -*- --- -* --- -- .. ---* *j***** ----+-**** .*-**t ** .****-i****-* ..... i........ *-*-+***** -*-* i--*- ____J _____ ***-* *l*-**-*
__ j____ I
- ;--- - -4 I
--- -- 1 - -- t- -..............-- ------- - -
i -----------------* ______ ---! ---
0 0 10 20 30 40 50 60 70 80 90 100 110 120 130 CORE FLOW (MLB/HR)
Figure 5 Backup Stability Protection Region Boundaries for Reduced Feedwater Temperature (RFWT)