ML25316A005
| ML25316A005 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 11/12/2025 |
| From: | Public Service Enterprise Group |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML25316A003 | List: |
| References | |
| LR-N25-0090, TS 5.6.3 | |
| Download: ML25316A005 (1) | |
Text
LR-N25-0090
CORE OPERATING LIMITS REPORT FOR Hope Creek Generating Station Unit 1 RELOAD 26, CYCLE 27 Prepared By:
(SAP#80136400/1520-0010)
Benjamin A. Troxell Reviewed By:
(SAP#80136400/1520-0020)
Nathan C. Langlitz Approved By:
(SAP#80136400/1520-0030)
Eric S. Scott Date: 10/17/25 Date: 10/17/25 Date: 10/18/25 LR-N25-0090 1
Table of Contents 1.0 Terms and Definitions 4
2.0 References 5
3.0 General Information 6
4.0 Precautions and Limitations 7
5.0 Technical Specifications that Reference the COLR 8
5.1 Average Planar Linear Heat Generation Rate 9
5.2 Minimum Critical Power Ratio 10 5.3 Linear Heat Generation Rate 15 5.4 OPRM Setpoints 17 5.5 Rod Block Monitor 17 Appendix A Method of Core Average Scram Speed Calculation 18 Appendix B Exposure-Dependent Linear Heat Generation Rate Limits 20 Appendix C Backup Stability Protection 23 Appendix D MCPR99.9% Value 26 LR-N25-0090 2
List of Tables TABLE 5.1-1 APLHGR Data for GNF2 9
TABLE 5.2-1 MCPR Operating Limits Cycle Exposure 9,452 MWd/MTU ( 8,575 MWd/STU) 11 TABLE 5.2-2 MCPR Operating Limits Cycle Exposure > 9,452 MWd/MTU (> 8,575 MWd/STU) and
< 11,646 MWd/MTU(< 10,565 MWd/STU) 12 TABLE 5.2-3 MCPR Operating Limits Cycle Exposure 11,646 MWd/MTU ( 10,565 MWd/STU) 13 TABLE 5.2-4 Power Dependent MCPR Multiplier (Kp) Data 14 TABLE 5.2-5 Flow Dependent MCPR Limit (MCPRf) 14 TABLE 5.3-1 Power Dependent Linear Heat Generation Rate Multiplier (LHGRFACp) 16 TABLE 5.3-2 Flow Dependent Linear Heat Generation Rate Multiplier (LHGRFACf) 16 TABLE 5.5.2-1 Control Rod Block Instrumentation Function 1, Rod Block Monitor, Trip Setpoints and Allowable Values 17 TABLE B-1 GNF2 LHGR Limits - UO2 Fuel Rods 22 TABLE B-2 GNF2 LHGR Limits - Gadolinia Bearing Rods 22 TABLE C-1 BSP Region Intercepts (Operation Prior to FFWTR) 24 TABLE C-2 BSP Region Intercepts (Required for FFWTR) 24 TABLE C-3 ABSP Region Setpoints 25 TABLE D-1 MCPR99.9% Value 27 LR-N25-0090 3
1.0 Terms and Definitions ABSP Automated Backup Stability Protection APLHGR Average Planar Linear Heat Generation Rate ARTS APRM and RBM Technical Specification Analysis BSP Backup Stability Protection COLR Core Operating Limits Report DSS-CD Detect and Suppress Solution - Confirmation Density ECCS Emergency Core Cooling Systems EOC End-of-Cycle EOC-RPT End-of-Cycle Recirculation Pump Trip FFWTR Final Feedwater Temperature Reduction FWHOOS Feedwater Heater(s) Out of Service GNF Global Nuclear Fuel LCO Limiting Condition for Operation LHGR Linear Heat Generation Rate LHGRFACf ARTS LHGR thermal limit flow dependent adjustments and multipliers LHGRFACp ARTS LHGR thermal limit power dependent adjustments and multipliers MCPR Minimum Critical Power Ratio MCPR99.9%
Cycle-specific MCPR that ensures at least 99.9% of fuel rods are not susceptible to boiling transition MCPRf ARTS MCPR flow dependent thermal limit MCPRp ARTS MCPR power dependent thermal limit which is the product of the rated thermal power MCPR limit and a power dependent multiplier, Kp OPRM Oscillation Power Range Monitor PROOS Pressure Regulator Out of Service (i.e. One of three pressure control channels failed or out of service)
RBM Rod Block Monitor RDF Recirculation Drive Flow RTP Rated Thermal Power SAD Amplitude Discriminator Setpoint SLO Single Recirculation Loop Operation TCV Turbine Control Valve TSV Turbine Stop Valve TSV/TCVOOS TSV/TCV Out of Service, refers to operation with one TSV or one TCV Out of Service TLO Two Recirculation Loop Operation LR-N25-0090 4
2.0 References Methodology References
- 1. General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A-32, and the U.S.
Supplement NEDE-24011-P-A-32-US, August 2024.
User References
- 2. GE Hitachi Boiling Water Reactor Detect and Suppress Solution - Confirmation Density, NEDC-33075P-A, Revision 8, November 2013.
- 3. Renewed Facility Operating License No. NPF-57, PSEG Nuclear LLC, Hope Creek Generating Station, Docket No. 50-354.
- 4. Applicability of GE Methods to Expanded Operating Domains, NEDC-33173P-A, Revision 5, August 2019.
- 5. Supplemental Reload Licensing Report for Hope Creek Reload 26 Cycle 27, Global Nuclear Fuel Document No. 008N4873, Revision 0, August 2025.
- 6. Fuel Bundle Information Report for Hope Creek Reload 26 Cycle 27, Global Nuclear Fuel Document No. 008N4874, Revision 0, August 2025.
- 7. Option B Licensing Basis & Cycle-Independent Transient Evaluation for Implementation of the Technical Specification Improvement Program (TSIP) Scram Speed, GE Hitachi Nuclear Energy Document No. 0000-0119-7785-R0, Revision 0, October 2010.
- 8. SRLR Bases Confirmation with Control Rods Inserted at End of Cycle for Hope Creek (KT1), Global Nuclear Fuel Document No. 002N4856, Revision 0, February 18, 2015.
- 9. GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II), NEDC-33270P, Revision 11, August 2020.
- 10. Hope Creek SRLR Bases Confirmation for Control Rods Inserted at the End of Cycle, Global Nuclear Fuel Letter 005N3138, Revision 0, May 31, 2019.
LR-N25-0090 5
3.0 General Information This revision of the Core Operating Limits Report provides the core operating limits for Hope Creek Generating Station Unit 1 Cycle 27 operation. This report provides information relative to OPRM setpoints, backup stability protection regions, RBM setpoints, single recirculation loop operation, and core average scram speed. The power distribution limits presented here correspond to the core thermal limits for Average Planar Linear Heat Generation Rate (APLHGR), Minimum Critical Power Ratio (MCPR),
and Linear Heat Generation Rate (LHGR). The MCPR99.9% values determined for the generation of the MCPR power distribution limits are provided in Appendix D. Finally, this report provides references to the most recent revision of the implemented approved methodology.
These operating limit values have been determined using NRC approved methods contained in GESTAR-II (Reference 1).
These operating limit values also include limitations where required by the NRC Safety Evaluation Report for Hope Creek License Amendment Number 174, Extended Power Uprate (Reference 3) for the use of GE Licensing Topical Report NEDC-33173P, Applicability of GE Methods to Expanded Operating Domains (Reference 4).
The following sections contain operating limit values applicable for the GNF2 fuel design in use for Cycle
- 27.
The method of calculating core average scram speed,, is provided in Option B Licensing Basis & Cycle-Independent Transient Evaluation for Implementation of the Technical Specification Improvement Program (TSIP) Scram Speed (Reference 7).
These operating limits are established such that all applicable fuel thermal-mechanical, core thermal-hydraulic, ECCS, and nuclear limits such as shutdown margin, and transient and accident analysis limits are met.
Various sections of the Hope Creek Technical Specifications reference this COLR. Those sections are listed in Section 5 of this document. Hope Creek Technical Specification 5.6.3 also requires that this report, including any mid-cycle revisions, shall be provided upon issuance to the NRC.
LR-N25-0090 6
4.0 Precautions and Limitations This document is specific to Hope Creek Generating Station Unit 1 Cycle 27 and shall not be applicable to any other core or cycle design. Revision 25 of the COLR is applicable for Cycle 27 operating from the date of issuance through the end of cycle including consideration of reduced feedwater temperatures for FWHOOS or FFWTR, and a power coastdown to a core thermal power that shall not go below 40%
rated core thermal power. End of full power capability is reached when 100% rated power can no longer be maintained by increasing core flow (up to 105% of rated core flow), at allowable feedwater temperatures, in the all-rods-out configuration. The term all-rods-out excludes control rods that have been inserted to suppress fuel leakers, address cell friction performance, or other circumstances that would require control rod insertion such as, but not limited to, meeting Technical Specification Operability requirements. Inserted rods may be removed at any point of the cycle, including after the end of full power capability (References 8 and 10). Operation beyond the end of full power capability is defined as power coastdown operation which includes an operating assumption that vessel dome pressure will decrease during the power coastdown period as steam flow decreases (maintaining constant vessel dome pressure during the power coastdown period was not generically considered by GESTAR-II for determining the operating limit LCO values described above).
FWHOOS was evaluated for a final feedwater temperature reduction of up to 60°F from the design rated thermal power final feedwater temperature of 433.5°F (433.5°F - 60°F = 373.5°F). Therefore, Cycle 27 FWHOOS operation is limited to feedwater system configurations that result in a final feedwater temperature greater than or equal to 373.5°F at rated thermal power. FWHOOS operation and the associated limitations may be implemented any time during the operating cycle prior to cycle extension utilizing FFWTR.
FFWTR was evaluated for a final feedwater temperature reduction of up to 102°F from the design rated thermal power final feedwater temperature of 433.5°F (433.5°F - 102°F = 331.5°F). Therefore, Cycle 27 FFWTR operation is limited to feedwater system configurations that result in a final feedwater temperature greater than or equal to 331.5°F at rated thermal power which is compliant with Renewed Facility Operating License No. NPF-57 License Condition 2.C.(11): The facility shall not be operated with a rated thermal power feedwater temperature less than 331.5°F for the purpose of extending the normal fuel cycle. FFWTR operation and the associated limitations shall only be implemented for the purposes of cycle extension after rated thermal power cannot be maintained at 100% rated total core flow in the all-rods-out configuration.
The off-rated power and flow dependent limits support operation with one TSV/TCVOOS at power levels 86% RTP in all operating conditions. Therefore, Cycle 27 operation with one TSV/TCVOOS is restricted to power levels no greater than 86% RTP.
LR-N25-0090 7
5.0 Technical Specifications that Reference the COLR The following Hope Creek Technical Specifications reference this COLR:
Technical Specification Title 3.2.1 Average Planar Linear Heat Generation Rate (APLHGR) 3.2.2 Minimum Critical Power Ratio (MCPR) 3.2.3 Linear Heat Generation Rate (LHGR) 3.3.1.1 Reactor Protection System (RPS) Instrumentation 3.3.2.1 Control Rod Block Instrumentation 3.3.4.1 End-of-Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation 3.4.1 Recirculation Loops Operating 5.6.3 Reporting Requirements, Core Operating Limits Report LR-N25-0090 8
5.1 Average Planar Linear Heat Generation Rate Technical Specification 3.2.1 All AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) shall be less than or equal to the limits specified in Table 5.1-1 for two recirculation loop operation (TLO).
In accordance with LCO 3.4.1.a, with one recirculation loop in operation, reduce the APLHGR limits to the values specified in Table 5.1-1 for single recirculation loop operation (SLO).
Linear interpolation shall be used to determine APLHGR limits as a function of exposure for intermediate values in Table 5.1-1.
TABLE 5.1-1 APLHGR Data for GNF2 Average Planar Exposure APLHGR Limit (kW/ft)
MWd/MTU MWd/STU TLO SLO 0.00 0.00 13.78 12.40 18910 17150 13.78 12.40 67000 60780 6.87 6.18 70000 63503 5.50 4.95 LR-N25-0090 9
5.2 Minimum Critical Power Ratio Technical Specification 3.2.2 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than the MCPR limit computed from the following steps:
- 1. Determine as defined in Appendix A.
NOTE The SLO operating condition MCPR values in Tables 5.2-1, 5.2-2, 5.2-3, and 5.2-5 implement the limiting SLO adder to meet the requirements of Technical Specification 3.4.1.b.
- 2. Linearly interpolate a rated MCPR limit as a function of from the MCPR value at =0 and MCPR value at =1 as specified in Table 5.2-1, Table 5.2-2, and Table 5.2-3 for the appropriate condition.
- 3. When thermal power is 24% rated core thermal power, determine a power dependent MCPR adjustment (Kp) value by linearly interpolating a Kp value as a function of core rated thermal power from Table 5.2-4. Multiply the rated MCPR value obtained from Step 2 by the Kp value to determine the power dependent MCPR limit (MCPRp).
When core thermal power is < 24% rated thermal power, no thermal limits are required.
- 4. For the flow dependent MCPR adjustment, determine the appropriate flow dependent MCPR limit (MCPRf) by linearly interpolating between the MCPRf values as a function of rated core flow using the information in Table 5.2-5.
- 5. Choose the most limiting (highest value) of the power and flow dependent MCPR limits determined in Steps 3 and 4 as the value for the MCPR limit for the Limiting Condition for Operation.
Note that the MCPR limit is a function of core average scram speed (), cycle exposure, core thermal power, total core flow, EOC-RPT operability, Pressure Regulator operability, the number of reactor coolant recirculation loops in operation, and main turbine bypass operability.
EOC-RPT system operability is defined by Hope Creek Technical Specification 3.3.4.1.
Reactor coolant recirculation loop operation is defined by Hope Creek Technical Specification 3.4.1.
Main Turbine Bypass operability is defined by Hope Creek Technical Specification 3.7.6.
LR-N25-0090 10
TABLE 5.2-1 MCPR Operating Limits Cycle Exposure 9,452 MWd/MTU ( 8,575 MWd/STU)
Main Turbine Bypass Operable Operating Condition Scram Speed Option GNF2 TLO EOC-RPT Operable
+
Pressure Regulator In-Service A
1.41 B
1.38 EOC-RPT Inoperable
+
Pressure Regulator In-Service A
1.41 B
+
Pressure Regulator Out-of-Service A
1.41 B
1.38 EOC-RPT Inoperable
+
Pressure Regulator Out-of-Service A
1.41 B
+
Pressure Regulator In-Service A
1.45 B
1.42 EOC-RPT Inoperable
+
Pressure Regulator In-Service A
1.45 B
+
Pressure Regulator Out-of-Service A
1.45 B
1.42 EOC-RPT Inoperable
+
Pressure Regulator Out-of-Service A
1.45 B
1.42 Scram Speed Option A =1, Scram Speed Option B =0 TLO = Two Recirculation Loop Operation SLO = Single Recirculation Loop Operation LR-N25-0090 11
TABLE 5.2-2 MCPR Operating Limits Cycle Exposure > 9,452 MWd/MTU (> 8,575 MWd/STU) and < 11,646 MWd/MTU(< 10,565 MWd/STU)
Main Turbine Bypass Operable Operating Condition Scram Speed Option GNF2 TLO EOC-RPT Operable
+
Pressure Regulator In-Service A
1.41 B
1.34 EOC-RPT Inoperable
+
Pressure Regulator In-Service A
1.41 B
+
Pressure Regulator Out-of-Service A
1.41 B
1.34 EOC-RPT Inoperable
+
Pressure Regulator Out-of-Service A
1.41 B
+
Pressure Regulator In-Service A
1.45 B
1.38 EOC-RPT Inoperable
+
Pressure Regulator In-Service A
1.45 B
+
Pressure Regulator Out-of-Service A
1.45 B
1.38 EOC-RPT Inoperable
+
Pressure Regulator Out-of-Service A
1.45 B
1.39 Scram Speed Option A =1, Scram Speed Option B =0 TLO = Two Recirculation Loop Operation SLO = Single Recirculation Loop Operation LR-N25-0090 12
TABLE 5.2-3 MCPR Operating Limits Cycle Exposure 11,646 MWd/MTU ( 10,565 MWd/STU)
Main Turbine Bypass Operable Operating Condition Scram Speed Option GNF2 TLO EOC-RPT Operable
+
Pressure Regulator In-Service A
1.42 B
1.35 EOC-RPT Inoperable
+
Pressure Regulator In-Service A
1.42 B
+
Pressure Regulator Out-of-Service A
1.42 B
1.35 EOC-RPT Inoperable
+
Pressure Regulator Out-of-Service A
1.42 B
+
Pressure Regulator In-Service A
1.46 B
1.39 EOC-RPT Inoperable
+
Pressure Regulator In-Service A
1.46 B
+
Pressure Regulator Out-of-Service A
1.46 B
1.39 EOC-RPT Inoperable
+
Pressure Regulator Out-of-Service A
1.46 B
1.40 Scram Speed Option A =1, Scram Speed Option B =0 TLO = Two Recirculation Loop Operation SLO = Single Recirculation Loop Operation LR-N25-0090 13
TABLE 5.2-4 Power Dependent MCPR Multiplier (Kp) Data Operating Condition Core Thermal Power (% of Rated) 24 45 55 60 85
>85 100 MCPR Multiplier Kp Pressure Regulator In-Service 1.193 1.193 1.150 1.150 1.000 Pressure Regulator Out-of-Service 1.806 1.806 1.456 1.439 1.231 1.056 1.000 Kp is linearly interpolated between core thermal power entries.
Kp is not affected by recirculation loop or EOC-RPT operability.
TABLE 5.2-5 Flow Dependent MCPR Limit (MCPRf)
Operating Condition Core Flow (% of Rated) 30 60 92.9 105 MCPR Limit TLO 1.58 1.20 1.20 SLO 1.62 1.44 MCPRf is linearly interpolated between core flow entries.
MCPRf is not affected by EOC-RPT or pressure regulator operability.
TLO = Two Recirculation Loop Operation SLO = Single Recirculation Loop Operation LR-N25-0090 14
5.3 Linear Heat Generation Rate Technical Specification 3.2.3 The LINEAR HEAT GENERATION RATE (LHGR) shall not exceed the limit computed from the following steps:
NOTE The steps performed in 1 through 6 below should be repeated for both UO2 and gadolinia bearing fuel rods in each bundle type.
- 1. Determine the exposure dependent LHGR limit using linear interpolation between the table values in Appendix B.
NOTE For two recirculation loop operation (TLO) utilize steps 1, 2, 3, and 6 to determine the LHGR limits.
In accordance with LCO 3.4.1.c, with one recirculation loop in operation, utilize steps 1, 4, 5, and 6 to determine the LHGR limits for single recirculation loop operation (SLO).
- 2. For the power dependent LHGR adjustment for TLO, determine a LHGRFACp value by linearly interpolating a LHGRFACp value as a function of rated core thermal power from the TLO entries in Table 5.3-1. Multiply the LHGR values obtained from Step 1 by the LHGRFACp value to determine the power dependent LHGR limit.
- 3. For the flow dependent LHGR adjustment for TLO, determine a LHGRFACf value by linearly interpolating a LHGRFACf value as a function of rated core flow from the TLO entries in Table 5.3-2. Multiply the LHGR values obtained from Step 1 by the LHGRFACf value to determine the flow dependent LHGR limit.
- 4. For the power dependent LHGR adjustment for SLO, determine a LHGRFACp value by linearly interpolating a LHGRFACp value as a function of rated core thermal power from the SLO entries in Table 5.3-1. Multiply the LHGR values obtained from Step 1 by the LHGRFACp value to determine the power dependent LHGR limit.
- 5. For the flow dependent LHGR adjustment for SLO, determine a LHGRFACf value by linearly interpolating a LHGRFACf value as a function of rated core flow from the SLO entries in Table 5.3-2. Multiply the LHGR values obtained from Step 1 by the LHGRFACf value to determine the flow dependent LHGR limit.
- 6. Choose the most limiting (lowest value) of the power and flow dependent LHGR limits determined in Steps 2 and 3 (TLO) or 4 and 5 (SLO) as the value for the LHGR limit for the Limiting Condition for Operation.
LR-N25-0090 15
TABLE 5.3-1 Power Dependent Linear Heat Generation Rate Multiplier (LHGRFACp)
Operating Condition Core Thermal Power (% of Rated) 24 30 45 55 59.89 60 85
>85 100 LHGRFACp Multiplier TLO Pressure Regulator In-Service 1.000 1.000 1.000 1.000 1.000 Pressure Regulator Out-of-Service 0.675 0.703 0.795 0.853 0.868 0.968 1.000 1.000 SLO Pressure Regulator In-Service 1.000 1.000 1.000 Pressure Regulator Out-of-Service 0.675 0.703 0.795 0.853 0.868 LHGRFACp is linearly interpolated between core thermal power entries.
LHGRFACp is not affected by EOC-RPT operability.
TLO = Two Recirculation Loop Operation SLO = Single Recirculation Loop Operation TABLE 5.3-2 Flow Dependent Linear Heat Generation Rate Multiplier (LHGRFACf)
Operating Condition Core Flow (% of Rated) 30 50 60 82.2 105 LHGRFACf Multiplier TLO 0.500 0.782 1.000 1.000 SLO 0.500 0.782 0.850 LHGRFACf is linearly interpolated between core flow entries.
LHGRFACf is not affected by EOC-RPT or pressure regulator operability.
TLO = Two Recirculation Loop Operation SLO = Single Recirculation Loop Operation LR-N25-0090 16
5.4 OPRM Setpoints 5.4.1 Technical Requirements Manual, Table 16.3.3.1.1-1, Function 2.f, OPRM Upscale A DSS-CD evaluation was completed for Hope Creek Cycle 27 in accordance with the licensing methodology described in Reference 2. The DSS-CD evaluation confirms that the DSS-CD solution is applicable to Hope Creek Cycle 27 and confirms SAD = 1.10 for Hope Creek Cycle 27 operation.
The SAD = 1.10 is applicable under all operating conditions within the OPRM Armed Region.
5.5 Rod Block Monitor 5.5.1 Technical Specification Table 3.3.2.1-1 Control Rod Block Instrumentation, Function 1, Rod Block Monitor, Applicable Modes Or Other Specified Conditions With THERMAL POWER 30% RTP and THERMAL POWER < 90 % RTP and MCPR < 1.75 Or, With THERMAL POWER 90% RTP and MCPR < 1.44 5.5.2 Technical Specification Table 3.3.2.1-1, Control Rod Block Instrumentation, Function 1, Rod Block Monitor TABLE 5.5.2-1 Control Rod Block Instrumentation Function 1, Rod Block Monitor, Trip Setpoints and Allowable Values Function Trip Setpoint*
Allowable Value*
1.a Low Power Range - Upscale (Applicability: RTP 30% but < 63%)
123.0 123.4 1.b Intermediate Power Range - Upscale (Applicability: RTP 63% but < 83%)
118.2 118.6 1.c High Power Range - Upscale (Applicability: RTP 83%)
113.2 113.6 1.e Downscale (Applicability: RTP 30%)
5 N/A
- % RBM Reference Level LR-N25-0090 17
Appendix A: Method of Core Average Scram Speed Calculation LR-N25-0090 18
Method of Core Average Scram Speed,, Calculation is defined as
(
)
B A
B ave
=
where:
(
)
016
.0 65
.1 672
.0 2
/
1 1
1
+
=
=
n i
i B
N N
=
=
=
n i
i n
i i
i ave N
N 1
1
A= 0.86 seconds, control rod scram insertion time limit to notch 39 per Technical Specification 3.1.4, Table 3.1.4-1, n = number of surveillance tests performed to date in cycle, Ni = number of active control rods measured in the ith surveillance test, i = average scram time to notch 39 of all rods measured in the ith surveillance test, and N1 = total number of active rods measured in Technical Specification SR 3.1.4.1 or SR 3.1.4.4.
If B
ave
, set = 0 to apply Option B OLMCPR.
shall be 1.0 ( = 1.0) prior to performance of the initial scram time measurements for the cycle in accordance with Technical Specification 3.1.4 Surveillance Requirements.
LR-N25-0090 19
Appendix B: Exposure-Dependent Linear Heat Generation Rate Limits LR-N25-0090 20
Exposure-Dependent Linear Heat Generation Rate Limits The LHGR limits for all fuel and rod types are considered proprietary information of the vendor. Tables B-1 and B-2 contain exposure-dependent LHGR limits. The tables are presented as a pair since the LHGR limits are presented at separate peak pellet exposures for UO2 and gadolinia bearing fuel rods. The gadolinia fuel rod limits provided contain the gadolinia LHGR limit for possible gadolinium concentrations occurring in GNF2 fuel bundles.
LR-N25-0090 21
Tables B-1 and B-2 contain limits (Reference 9) applicable to the GNF2 bundle types in use at Hope Creek Unit 1.
TABLE B-1: GNF2 LHGR Limits - UO2 Fuel Rods
((
))
TABLE B-2: GNF2 LHGR Limits - Gadolinia Bearing Rods
((
))
LR-N25-0090 22
Appendix C: Backup Stability Protection LR-N25-0090 23
Backup Stability Protection Region Intercepts Table C-1 values reflect the cycle-specific BSP region intercepts determined for Cycle 27 considering nominal feedwater temperature operation and FWHOOS (Reference 5).
Table C-2 provides BSP region intercepts for Cycle 27 for the implementation of FFWTR operation (Reference 5).
TABLE C-1: BSP Region Intercepts (Operation Prior to FFWTR)
Region Boundary Intercept
% Power
% Flow Region 1 High Flow Control Line 62.9 46.9 Region 1 Natural Circulation Line 43.5 35.2 Region 2 High Flow Control Line 70.5 56.6 Region 2 Natural Circulation Line 31.7 36.3 TABLE C-2: BSP Region Intercepts (Required for FFWTR)
Region Boundary Intercept
% Power
% Flow Region 1 High Flow Control Line 72.3 58.9 Region 1 Natural Circulation Line 41.5 35.4 Region 2 High Flow Control Line 75.2 62.6 Region 2 Natural Circulation Line 31.7 36.3 Region 1 = BSP Scram Region Region 2 = BSP Controlled Entry Region LR-N25-0090 24
Automated Backup Stability Protection (ABSP) Region Setpoints Table C-3 values reflect the cycle-specific adjusted Simulated Thermal Power - Upscale trip setpoints for implementation of the ABSP region (Reference 5).
The ABSP region is conservatively constructed to encompass BSP Region 1 and generates an immediate automatic reactor scram upon entry. The ABSP region provided is applicable for Nominal, FWHOOS, and FFWTR conditions.
TABLE C-3: ABSP Region Setpoints Parameter Setpoint Slope for Trip (mTRIP) 0.79 (% RTP / % RDF)
Constant Power Line for Trip (PBSP-TRIP) 42.6 (% RTP)
Constant Flow Line for Trip (WBSP-TRIP) 37.8 (% RDF)
Flow Breakpoint (WBSP-BREAK) 16.2 (% RDF)
LR-N25-0090 25
Appendix D: MCPR99.9% Value LR-N25-0090 26
MCPR99.9% Value Table D-1 contains the MCPR99.9% values developed for the determination of the Hope Creek Cycle 27 Technical Specification 3.2.2 MCPR Operating Limits (Reference 5), generated in accordance with Section 5.2. The MCPR99.9% value is dependent on the number of reactor coolant recirculation loops in operation.
TABLE D-1: MCPR99.9% Value Operating Condition MCPR99.9% Value TLO 1.10 SLO 1.12 TLO = Two Recirculation Loop Operation SLO = Single Recirculation Loop Operation LR-N25-0090 27