View source for NL-15-0520, Edwin I. Hatch, Unit 2 - VSP-SNC-GEN-15-002, Cycle 23 Core Operating Limits Report, Version 2, Non-Proprietary, Enclosure 6

{{Adams
| number = ML15078A232
| issue date = 03/13/2015
| title = Edwin I. Hatch, Unit 2 - VSP-SNC-GEN-15-002, Cycle 23 Core Operating Limits Report, Version 2, Non-Proprietary, Enclosure 6
| author name = Pierce C R
| author affiliation = Southern Co, Southern Nuclear Operating Co, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000321, 05000366
| license number = 
| contact person = 
| case reference number = NL-15-0520
| document report number = VSP-SNC-GEN-15-002
| package number = ML15078A228
| document type = Fuel Cycle Reload Report
| page count = 45
}}

=Text=
{{#Wiki_filter:Edwin I. Hatch Nuclear Plant Unit 1 Cycle 27 Core Operating Limits Report Version 2 Unit 2 Cycle 23 Core Operating Limits Report Version 2 Unit 2 Cycle 24 Core Operating Limits Report Version 1 Information Letter of NSF Lead Test Assemblies Enclosure 6 HNP Unit 2 Cycle 23 Version 2 Core Operating Limits Report NON-PROPRIETARY INFORMATION ENCLOSURE 5 VSP-SNC-GEN-15-002 Edwin I. Hatch Nuclear Plant Unit 2 Cycle 23 Core Operating Limits Report, Version 2 Non-Proprietary Information INFORMATION NOTICE This is a non-proprietary version of Enclosure 4 of VSP-SNC-GEN-15-002, which has the proprietary information removed. Portions of the document that have been removed are indicated by white space inside open and closed bracket as shown here [[ I].
SOUTHERN NUCLEAR OPERATING COMPANY EDWIN I. HATCH NUCLEAR PLANT Unit 2 Cycle 23 CORE OPERATING LIMITS REPORT Version 2 Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201 Non-Proprietary Information Non-Proprietary Information Edwin I. Hatch Nuclear Plant Unit 2 Cycle 23 Core Operating Limits Report TABLE OF CONTENTS Section Title Page 1.0 Introduction 1 2.0 APLHGR Limits 3 3.0 MCPR Operating Limits 6 4.0 LHGR Limits 24 5.0 PBDA Amplitude Setpoint 32 6.0 References 33 Version 2 Plant Hatch Core Operating Unit 2 Cycle 23 Non-Proprietary Information Limits Report TABLES Table No. Title Page 1-1 Main Turbine Bypass System Operability 1 1-2 Equipment-Out-of-Service Limitations 2 3-1 Exposure Definitions 8 3-2 MCPR Operating Flexibility Options 8 4-1 LHGR Operating Flexibility Options 25 4-2 LHGR Limit versus Peak Pellet Exposure 25 5-1 OPRM Setpoint 32 ii Version 2 Plant Hatch Core Operating Unit 2 Cycle 23 Non-Proprietary Information Limits Report FIGURES Figure No. Title Page 2-1 Flow-Dependent APLHGR Multiplier 4 (MAPFACF) versus Core Flow 2-2 APLHGR Limit versus Average Planar 5 Exposure 3-1A Power-Dependent MCPR Limit (MCPRp) 10 versus Core Power from 24% to 48% of Rated Core Power 3-1 B Power-Dependent MCPR Limit (MCPRp) 11 versus Core Power from 24% to 48% of Rated Core Power (Main Turbine Bypass System Inoperable) 3-2 Flow-Dependent MCPR Limit (MCPRF) 12 versus Core Flow 3-3A Power-Dependent MCPR Multiplier (Kp) 13 versus Core Power 3-3B Power-Dependent MCPR Multiplier (Kp) 14 versus Core Power (EOC-RPT System Out of Service and Main Turbine Bypass System Inoperable Simultaneously) 3-3C Power-Dependent MCPR Multiplier (Kp) 15 versus Core Power (Main Turbine Pressure Regulator System in TLCO 3.3.13.c)3-4A-1 GE14C MCPR Limits versus Average 16 Scram Time (BOC to MOCI)3-4A-2 GNF2 LTA MCPR Limits versus Average 17 Scram Time (BOC to MOCI)3-4A-3 GE14C MCPR Limits versus Average 18 Scram Time (High Pressure Heaters Out of Service) (BOC to MOCI)iii Version 2 Plant Hatch Core Operating Unit 2 Cycle 23 Non-Proprietary Information Limits Report Figure No. Title Pae 3-4A-4 GNF2 LTA MCPR Limits versus Average 19 Scram Time (High Pressure Heaters Out of Service) (BOC to MOCI)3-4B-1 GE14C MCPR Limits versus Average 20 Scram Time (MOCI to MOC2)3-4B-2 GNF2 LTA MCPR Limits versus Average 21 Scram Time (MOCI to MOC2)3-4C-1 GE14C MCPR Limits versus Average 22 Scram Time (MOC2 to EOC)3-4C-2 GNF2 LTA MCPR Limits versus Average 23 Scram Time (MOC2 to EOC)4-1 Flow-Dependent LHGR Multiplier 26 (LHGRFACF) versus Core Flow 4-2A Power-Dependent LHGR Multiplier 27 (LHGRFACp) versus Core Power (Main Turbine Bypass System Operable or Inoperable) 4-2B Power-Dependent LHGR Multiplier 28 (LHGRFACp) versus Core Power (Main Turbine Bypass System Operable or Inoperable and Main Turbine Pressure Regulator System in TLCO 3.3.13.c)4-2C Power-Dependent LHGR Multiplier 29 (LHGRFACp) versus Core Power (Main Turbine Bypass System Operable or Inoperable and High Pressure Heaters Out of Service)iv Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information Figure No.Title 4-3A 4-3B GE14C LHGR versus Peak Pellet Exposure GNF2 LTA LHGR versus Peak Pellet Exposure 30 31 V Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information

==1.0 INTRODUCTION==

The Core Operating Limits Report (COLR) for Plant Hatch Unit 2 Cycle 23 is prepared in accordance with the requirements of Technical Specification 5.6.5. The core operating limits presented herein were developed using NRC-approved methods (References 1 through 6). Results from the reload analyses for the fuel in Unit 2 Cycle 23 are documented in References 3 through 5.The following core operating limits are included in this report: a. Average Planar Linear Heat Generation Rate (APLHGR) -Technical Specification 3.2.1 b. Minimum Critical Power Ratio (MCPR) -Technical Specification 3.2.2 c. Linear Heat Generation Rate (LHGR) -Technical Specification 3.2.3 Also included in this report is the maximum allowable scram setpoint for the Period Based Detection Algorithm (PBDA) in the Oscillation Power Range Monitor (OPRM).Based upon the reload analysis for this cycle, the following operability requirement is defined for Unit 2 operation.
TABLE 1-1 Main Turbine Bypass System Operability System Operability Requirement Main Turbine Bypass System Operable At least two bypass valves must be (Technical Specification 3.7.7) operable 1 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information From a fuel thermal limits perspective, the following limitations are placed on Unit 2 operation.
TABLE 1-2 Equipment-Out-of-Service Limitations Equipment 
/ Condition Limitation EOC-RPT Out of Service and Main Turbine Option B scram speeds must be Bypass System Inoperable simultaneously met (in place) at CTP > 48% RTP Main Turbine Pressure Regulator System in Option B scram speeds must be TLCO 3.3.13.c met (in place) at CTP > 48% RTP e CTP must be 5 2000 MWth Single-Loop Operation (SLO) , Core Flow must be -- 56% of Rated High Pressure Feedwater Heaters Out of Service No Core Operating Limits available and Main Turbine Pressure Regulator System in (Technical Specifications RAS TLCO 3.3.13.c simultaneously 3.2.2. and 3.2.3 must be entered)NOTE: The power distribution limits in this report apply to plant operation with all equipment in service, unless otherwise specified.
2 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information 2.0 APLHGR LIMITS (Technical Specification 3.2.1)The APLHGR limit for each six inch axial segment of each fuel assembly in the core is the applicable APLHGR limit taken from Figure 2-2 multiplied by the flow-dependent multiplier, MAPFACF, from Figure 2-1.3 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information 1.0 A.0.0.9 o 0.87-D 0.8 C, I-- 0.6 0.0.a.o u. 0.5 0.4 6 t TLO TLO +*1.1.Li~fl T___________________________
L _______________________
__________________________
__________________________
61 30 40 50 61 60 70 Core Flow (% of Rated)80 90 100 110 Operating Conditions F SLO / TLO MAPFACF 30 _< F < 61 TLO 0.86 61 < F TLO 1.00 30 < F SLO 0.80 F = Percent of Rated Core Flow FIGURE 2-1 Flow-Dependent APLHGR Multiplier (MAPFACF) versus Core Flow 4 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information Average Planar Exposure (GWd/st)0.00 14.51 19.13 57.61 63.50 APLHGR Limit (kW/ft)12.82 12.82 12.82 8.00 5.00 14.0 13.0 12.0 11.0 10.0.E 90 9.0 8.0 7.0 6.0 5.0 4.0 1&#xfd;61 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 Average Planar Exposure (GWd/ST)65.0 70.0 FIGURE 2-2 APLHGR Limit versus Average Planar Exposure 5 Version 2 Plant Hatch Core Operating Unit 2 Cycle 23 Non-Proprietary Information Limits Report 3.0 MCPR OPERATING LIMITS (Technical Specification 3.2.2)The MCPR operating limits (OLMCPR) for each fuel type are a function of core power, core flow, average scram time, number of operating recirculation loops, EOC-RPT system status, operability of the main turbine bypass system, status of the high pressure feedwater heaters, the status of the main turbine pressure regulator system, and cycle exposure.
Cycle exposures are defined in Table 3-1.With both recirculation pumps in operation (TLO), the OLMCPRs are determined as follows: a. For 24% _< power < 48%, the power-dependent MCPR limit, MCPRp, as determined by Table 3-2.b. For power _> 48%, the OLMCPRs are the greater of either: 1) The flow-dependent MCPR limit, MCPRF, from Figure 3-2, or 2) The product of the power-dependent multiplier, Kp, and the rated-power OLMCPRs, as determined by Table 3-2.As shown on the figures for absolute MCPR, the OLMCPR with only one recirculation pump in operation (SLO) is equal to the two loop (TLO) OLMCPR plus 0.02.These limits apply to all modes of operation with feedwater temperature reduction, as well as operation with normal feedwater temperatures.
In the 3-4A, 3-4B, and 3-4C figures, Option A scram time OLMCPRs correspond to c = 1.0, where T is determined from scram time measurements performed in accordance with Technical Specifications Surveillance Requirements 3.1.4.1 and 3.1.4.2. Option B values correspond to r = 0.0. For scram times between Option A and Option B, the rated-power OLMCPR corresponds to c. If t has not been determined, Option A limits must be used.6 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information The average scram time of the control rods, r, is defined as: Tave -TB= 0, or , whichever is greater.TA -TB where: TA = 1.08 sec (Technical Specification 3.1.4, Table 3.1.4-1, scram time limit to notch 36).1/2 TB + +1.65 -o'*Ni=where: p = 0.822 sec (mean scram time used in the transient analysis).
a = 0.018 sec (standard deviation of lt).17 Yl-- Niz, T;ave -1=]i=1 where: n Ni Ni N,= number of surveillance tests performed to date in the cycle.= number of active control rods measured in the ith surveillance test.= average scram time to notch 36 of all rods in the ith surveillance test.= total number of active rods measured in Technical Specifications Surveillance Requirement 3.1.4.1.7 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information TABLE 3-1 Exposure Definitions Exposure Label Cycle Exposure Definition BOC Beginning of Cycle 0 MWd/st Exposure MOC1 First Middle of Cycle EOR -7566 MWd/st Exposure MOC2 Second Middle of Cycle EOR -1566 MWd/st Exposure Projected end of rated power with all control rods out at EOR End of Rated Exposure rated core flow and rated feedwater temperature EOC End of Cycle Exposure Exposure at cycle shutdown TABLE 3-2 MCPR Operating Flexibility Options Rated-power OLMCPRs High Pressure Cycle Exposure Feedwater Heaters GE14C GNF2 LTAs In Service BOC to MOC1 Yes Figure 3-4A-1 Figure 3-4A-2 BOC to MOC1 No Figure 3-4A-3 Figure 3-4A-4 MOC1 to MOC2 Yes/No Figure 3-4B-1 Figure 3-4B-2 MOC2 to EOC Yes/No Figure 3-4C-1 Figure 3-4C-2 8 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information TABLE 3-2 (continued)
MCPRP from _ 24% to < 48% Power Main Turbine Bypass System Operable*
Figure 3-1A Main Turbine Bypass System Inoperable Figure 3-1B Kp for Power > 48% of Rated EOC-RPT System In Main Turbine Main Turbine Service Bypass System Pressure Regulator Operable*
System Status Yes Yes TLCO 3.3.13.a or b Figure 3-3A No Yes TLCO 3.3.13.a or b Figure 3-3A Yes No TLCO 3.3.13.a or b Figure 3-3A No No TLCO 3.3.13.a or b Figure 3-3B**Yes/No Yes/No TLCO 3.3.13.c Figure 3-3C*** At least two bypass valves must be operable** Option B scram speeds must be met (in place) at CTP > 48% RTP 9 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information 3.0 2.8 U 2.6 a 2.4 U 2.2 C.)a)0.2.0 0 1.8 1.6 24 27 28 30 33 36 39 42 45 Core Power(% of Rated)48 MCPRp(TLO) 
= A + B*P MCPRp(SLO) 
= MCPRp(TLO) 
+ 0.02 F P A B F5 <60 24< P < 28 4.1620 -0.06735 F > 60 24< P < 28 4.1015 -0.04752 F5 <60 28< P < 48 2.1005 -0.00630 F>60 28< P < 48 2.5093 -0.01077 P = Percent of Rated Core Power F = Percent of Rated Core Flow FIGURE 3-1A Power-Dependent MCPR Limit (MCPRp) versus Core Power from 24% to 48% of Rated Core Power 10 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information 4.0 3.8 3.6 a- 3.4 S3.2_j W* 3.0 0.0 2.82.6 1 2.4 5 2.2 a.2.0 1.8 1.6 24 27 28 30 33 36 39 42 45 48 Core Power(% of Rated)MCPRp(TLO) 
= A + B*P MCPRp(SLO) 
= MCPRp(TLO) 
+ 0.02 F P A B F5 <60 24_ P < 28 4.3996 -0.07070 F > 60 24_ P < 28 6.6484 -0.11780 F5 -60 28 P< 48 2.1005 -0.00630 F>60 28_ P < 48 2.5093 -0.01077 P = Percent of Rated Core Power F = Percent of Rated Core Flow FIGURE 3-1B Power-Dependent MCPR Limit (MCPRp) versus Core Power from 24% to 48% of Rated Core Power (Main Turbine Bypass System Inoperable) 11 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information 1.6 1.5[L C.)E 1.4 , 1.3 0.a, 0 L1.1.2 1.1 30 40 50 60 70 80 90 Core Flow (% of Rated)100 110 MCPRF(TLO) 
= A + B*F MCPRF(SLO) 
= MCPRF(TLO) 
+ 0.02 Flow A B 30 <&#xfd; F <&#xfd; 71.574 1.713 -0.00591 71.574 < F 1.290 0.00000 F = Percent of Rated Core Flow FIGURE 3-2 Flow-Dependent MCPR Limit (MCPRF) versus Core Flow 12 Version 2 Plant Hatch Unit 2 Cycle 23 Non-Proprietary Information Core Operating Limits Report 1.3 I.3 12 0.C.CL 0 0.o 1.1 0 0 0.1.0 48 52 56 60 64 68 72 76 80 84 88 92 96 100 Core Power(% of Rated)Kp = A + B*P P A -B 48< P < 60 1.6702 -0.00867 60 5 P 1.3750 -0.00375 P = Percent of Rated Core Power FIGURE 3-3A Power-Dependent MCPR Multiplier (Kp) versus Core Power 13 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information 1.3 1.2 2 L.V 0)a)0 C? 1.1 1.0 48 52 56 60 64 68 72 76 80 84 88 92 96 100 Core Power (% of Rated)K-- A + B*P P A B 8 48 P < 60 1.6702 -0.00867 60 < P < 90 1.3308 -0.00301 90 < P 1.5961 -0.00596 P = Percent of Rated Core Power FIGURE 3-3B Power-Dependent MCPR Multiplier (Kp) versus Core Power (EOC-RPT System Out of Service and Main Turbine Bypass System Inoperable Simultaneously) 14 Version 2 Plant Hatch Unit 2 Cycle 23 Non-Proprietary Information Core Operating Limits Report 1.5 1.4 L 21.3 a-C.4)al)a1)'0 a)0 a.1.1 1.0 48 52 56 60 64 68 72 76 80 84 88 92 96 100 Core Power(% of Rated)Kp = A + B*P P A B 48:< P < 70 1.6268 -0.00451 70 P 2.0367 -0.01037 P = Percent of Rated Core Power FIGURE 3-3C Power-Dependent MCPR Multiplier (Kp) versus Core Power (Main Turbine Pressure Regulator System in TLCO 3.3.13.c)15 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information 1.52.)E.0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 Tau OLMCPR(sLO) 
= OLMCPR(TLO) 
+ 0.02 Operating Conditions OLMCPR(TLO)
Main Turbine EOC-RPT Bypass System t = 0.0 ' = 1.0 In Service Operable 1.29 1.29 Out of Service Operable 1.30 1.41 In Service Inoperable 1.35 1.35 Out of Service Inoperable 1.35 1.45 FIGURE 3-4A-1 GE14C MCPR Limits versus Average Scram Time (BOC to MOCI)16 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information 1.46 1.44 1.42 1.40 1.38 Ix 1.36 0.(.3 1.34 1.32 1.30 1.28 1.26 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 Tau OLMCPR(SLO) 
= OLMCPR(TLO) 
+ 0.02 Operating Conditions OLMCPR(TLO)
Main Turbine EOC-RPT Bypass System r = 0.0 ' = 1.0 In Service Operable 1.29 1.31 Out of Service Operable 1.31 1.41 In Service Inoperable 1.35 1.35 Out of Service Inoperable 1.35 1.45 FIGURE 3-4A-2 GNF2 LTA MCPR Limits versus Average Scram Time (BOC to MOC1)17 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information 1.52 1.50 1.48 1.46 1.44 1.42 1.40 0.U 1.38 1.36 1.34 1.32 1.30 1.28 1.26 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 Tau OLMCPR(SLO) 
= OLMCPR(TLO) 
+ 0.02 Operating Conditions OLMCPR(TLO)
Main Turbine EOC-RPT Bypass System r = 0.0 ' = 1.0 In Service Operable 1.31 1.31 Out of Service Operable 1.31 1.41 In Service Inoperable 1.35 1.35 Out of Service Inoperable 1.35 1.45 FIGURE 3-4A-3 GE14C MCPR Limits versus Average Scram Time (High Pressure Heaters Out of Service)(BOC to MOC1)18 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information 0.E.0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 Tau OLMCPR(SLO) 
= OLMCPR(TLO) 
+ 0.02 Operating Conditions OLMCPR(TLO)
Main Turbine EOC-RPT Bypass System r = 0.0 -1.0 In Service Operable 1.31 1.31 Out of Service Operable 1.31 1.41 In Service Inoperable 1.35 1.35 Out of Service Inoperable 1.35 1.45 FIGURE 3-4A-4 GNF2 LTA MCPR Limits versus Average Scram Time (High Pressure Heaters Out of Service)(BOC to MOC1)19 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information 1.56 1.54 1.52 1.50 1.48 E 1.46 0.o 1.44 1.42 1.40 1.38 1.36 1.34 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 Tau OLMCPR(sLO) 
= OLMCPR(TLO) 
+ 0.02 Operating Conditions OLMCPR(TLO)
Main Turbine EOC-RPT Bypass System = 0.0 = 1.0 In Service Operable 1.36 1.39 Out of Service Operable 1.40 1.51 In Service Inoperable 1.39 1.42 Out of Service Inoperable 1.43 1.54 FIGURE 3-4B-1 GE14C MCPR Limits versus Average Scram Time (MOC1 to MOC2)20 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information 1.56 1.1.52 1.50 1.48 1.46 1.44 1.42 1.40 Tau OLMCPR(sLO) 
= OLMCPR(TLO) 
+ 0.02 Operating Conditions OLMCPR(TLO)
Main Turbine EOC-RPT Bypass System r = 0.0 _ --- 1.0 In Service Operable 1.41 1.46 Out of Service Operable 1.43 1.53 In Service Inoperable 1.43 1.48 Out of Service Inoperable 1.45 1.55 FIGURE 3-4B-2 GNF2 LTA MCPR Limits versus Average Scram Time (MOC1 to MOC2)21 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information a._C.)1.68 1.66 1.64 1.62 1.60 1.58 1.56 1.54 1.52 1.50 1.48 1.46 1.44 1.42 1.40 1.38 1.36 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 Tau OLMCPR(sLo) 
= OLMCPR(TLO) 
+ 0.02 Operating Conditions OLMCPR(TLO)
Main Turbine EOC-RPT Bypass System ' = 0.0 C = 1.0 In Service Operable 1.39 1.42 Out of Service Operable 1.46 1.63 In Service Inoperable 1.42 1.45 Out of Service Inoperable 1.48 1.65 FIGURE 3-4C-1 GE14C MCPR Limits versus Average Scram Time (MOC2.to EOC)22 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information 1.64 1.62 1.60 1.58 1.56 1.54 U)E 1.52 1.50 1.48 1.46 1.44 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 Tau OLMCPR(sLo) 
= OLMCPR(TLO) 
+ 0.02 Operating Conditions OLMCPR(TLO)
Main Turbine EOC-RPT Bypass System = 0.0 T= 1.0 In Service Operable 1.46 1.51 Out of Service Operable 1.50 1.60 In Service Inoperable 1.49 1.54 Out of Service Inoperable 1.53 1.63 FIGURE 3-4C-2 GNF2 LTA MCPR Limits versus Average Scram Time (MOC2 to EOC)23 Version 2 Plant Hatch Core Operating Unit 2 Cycle 23 Non-Proprietary Information Limits Report 4.0 LHGR LIMITS (Technical Specification 3.2.3)The LHGR limit for each six inch axial segment of each fuel rod in the core is the applicable rated-power, rated-flow LHGR limit taken from Table 4-2 multiplied by the smaller of either: a. The flow-dependent multiplier, LHGRFACF, from Figure 4-1, or b. The power-dependent multiplier, LHGRFACp, as determined by Table 4-1.Table 4-2 shows the exposure-dependent LHGR limits for all fuel types in the core, including the U0 2 rods which contain no gadolinium.
The LHGR limit is based on initial Gd content in a six inch segment of a fuel rod and the maximum initial Gd content anywhere in the same rod. The second column in Table 4-2 shows the segment Gd concentration and the third column shows the maximum Gd concentration for that rod.For exposures between the values shown in Table 4-2, the LHGR limit is based on linear interpolation.
For illustration purposes, Figures 4-3A and 4-3B show the LHGR limits for U0 2 rods and the most limiting Gd rods for each fuel type.24 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information TABLE 4-1 LHGR Operating Flexibility Options LHGRFACp Main Turbine Pressure Regulator High Pressure System Status Feedwater Heaters TLCO 3.3.13.a or b In Service Figure 4-2A TLCO 3.3.13.c In Service Figure 4-2B*TCLO 3.3.13.a or b Out of Service Figure 4-2C* Option B scram speeds must be met (in place) at CTP > 48% RTP TABLE 4-2 LHGR Limit versus Peak Pellet Exposure LHGR LHGR LHGR LHGR Six Inch Rod limit at limit at Exp. at limit at Exp. at limit at Exp. at Fuel Segment Max. BOL Knee I Knee I Knee 2 Knee 2 EOL EOL Type Gd (w/o) Gd (wlo) (kWlft) (kWlft) (GWdlst) (kWlft) (GWdlst) (kWift) (GWdlst)0.00 0.00 13.400 13.400 14.515 8.000 57.607 5.000 63.504 0.00 4.00 13.100 13.100 14.190 7.821 56.317 4.888 62.082 0.00 6.00 13.100 13.100 14.190 7.821 56.317 4.888 62.082 4.00 4.00 12.800 12.800 12.510 7.642 55.928 4.776 61.869 5.00 5.00 12.521 12.521 12.389 7.475 55.443 4.672 61.335 5.00 6.00 12.400 12.400 12.247 7.403 54.884 4.627 60.718 GE14 5.00 7.00 12.300 12.300 12.132 7.343 54.424 4.590 60.212 6.00 6.00 12.255 12.255 12.276 7.316 54.999 4.572 60.845 6.00 7.00 12.100 12.100 12.095 7.224 54.275 4.515 60.047 6.00 8.00 12.100 12.100 12.095 7.224 54.275 4.515 60.047 7.00 7.00 12.000 12.000 12.174 7.164 54.589 4.478 60.394 7.00 8.00 11.900 11.900 12.055 7.104 54.117 4.440 59.873 8.00 8.00 11.755 11.755 12.079 7.018 54.215 4.386 59.981 GNF2 LTAs BOL = Beginning of Life (zero exposure)EOL = End of Life (maximum licensed pellet exposure)25 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information 1.0 A 0.9*. 0.8 07 0 0.6_o 0.6 LL 0.5 0.4 30 40 50 60 70 80 90 Core Flow (% of Rated)100 110 LHGRFACF = A + B*F Operating Conditions Values of Variables F SLO / TLO A B 30 _ F < 50.70 SLO / TLO 0.4574 0.006758 50.70 _ F < 80.29 TLO 0.4574 0.006758 50.70 _ F SLO 0.8000 0.000000 80.29 _ F TLO 1.0000 0.000000 F = Percent of Rated Core Flow FIGURE 4-1 Flow-Dependent LHGR Multiplier (LHGRFACF) versus Core Flow 26 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information 1.1 0a 1.0 x 0.9 (.3= 0.8-J v 0.7 r CL 0.0.8 CL 0 0.5 0.4 24 28 32 36 40 44 48 52 56 60 64 68 72 76 80 84 88 92 96 100 Core Power(% of Rated)LHGRFACP = A + B*P Operating Conditions Values of Variables P F A B 24< P < 28 F > 60 0.17924 0.009670 24_ P < 28 F 5 60 0.10366 0.016741 28 ! P < 48 All 0.52261 0.003617 48 _ P All 0.47760 0.005224 P = Percent of Rated Core Power F = Percent of Rated Core Flow FIGURE 4-2A Power-Dependent LHGR Multiplier (LHGRFACp) versus Core Power (Main Turbine Bypass System Operable or Inoperable) 27 Version 2 Plant Hatch Unit 2 Cycle 23 Non-Proprietary Information Core Operating Limits Report 1.1 3. 1.0 0.9 2* 0.8"r-J 0.7 0.6 0 0.0.5 0.4 24 28 32 36 40 44 48 52 56 60 64 68 72 76 80 84 88 92 96 100 Core Power(% of Rated)LHGRFACP = A + B*P Operating Conditions Values of Variables P F A B 24_ P < 28 F > 60 0.17924 0.009670 24!< P < 28 F 60 0.10366 0.016741 28 _ P < 70 All 0.52261 0.003617 70 _ P All 0.25270 0.007473 P = Percent of Rated Core Power F = Percent of Rated Core Flow FIGURE 4-2B Power-Dependent LHGR Multiplier (LHGRFACp) versus Core Power (Main Turbine Bypass System Operable or Inoperable and Main Turbine Pressure Regulator System in TLCO 3.3.13.c)28 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information 1.1 1.0.)U-o 0.9-r-0.8 S0.7 CL a.0.6 0.0.0.5 0.4< 60% Core Flow----I>Core Flow/I-/2 4 28 32 36 40 44 48 52 56 60 64 68 72 76 80 84 88 92 96 100 Core Power (% of Rated)LHGRFACP = A + B*P Operating Conditions Values of Variables P F A B 24!_ P < 28 F > 60 0.17924 0.009670 24< P < 28 F < 60 0.10366 0.016741 28< P < 48 All 0.52261 0.003617 48 < P < 60.04 All 0.47760 0.005224 60.04 < P < 86.06 All' 0.79100 0.000000 86.06 < P All -0.49800 0.014980 P = Percent of Rated Core Power F = Percent of Rated Core Flow FIGURE 4-2C Power-Dependent LHGR Multiplier (LHGRFACp) versus Core Power (Main Turbine Bypass System Operable or Inoperable and High Pressure Heaters Out of Service)29 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information Limiting Gd Rods Peak Pellet Exposure LHGR (GWd/st) (kW/ft)0.000 11.755 12.079 11.755 54.215 7.018 59.981 4.386 i ,o I 8.0 700 4.0----------------------
0.0 5.0 10.0 15.0 20.0 250 30.0 35.0 40.(Peak Pellet Exposure (GWd FIGURE 4-3A GE14C LHGR versus Peak Pellet Exposure 45.0 50.0 55.0 00.0 55.030 Version 2 Plant Hatch Unit 2 Cycle 23 Non-Proprietary Information Core Operating Limits Report U02 Rods Peak Pellet Exposure (GWd/st) LHGR (kW/ft)Limitin Gd Rods Peak Pellet Exposure (GWd/st) LHGR (kW/ft)[[~-]]11 FIGURE 4-3B GNF2 LTA LHGR versus Peak Pellet Exposure 31 Version 2 Plant Hatch Unit 2 Cycle 23 Core Operating Limits Report Non-Proprietary Information 5.0 PBDA AMPLITUDE SETPOINT The amplitude trip setpoint in the Period Based Detection Algorithm in the OPRM system shall not exceed the value reported in the Table below. This applies to instruments 2C51K615 A, B, C, and D.TABLE 5-1 OPRM Setpoint I OLMCPR OPRM Setpoint I-1.29 1.12 32 Version 2 Plant Hatch Core Operating Unit 2 Cycle 23 Non-Proprietary Information Limits Report 

==6.0 REFERENCES==
: 1. "General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A-19, May 2012, and the US Supplement, NEDE-2401 1-P-A-19-US, May 2012.2. GNF letter MEF-SNC-GEN-12-117, "Hatch 2 Reload 22 Cycle 23 Supplemental Reload Licensing Report and Fuel Bundle Information Report," M. Fitzpatrick to S.Hoxie-Key, December 7, 2012.3. Global Nuclear Fuel document 0000-0145-7166-SRLR, "Supplemental Reload Licensing Report for Edwin I. Hatch Nuclear Power Plant Unit 2, Reload 22 Cycle 23," Revision 0, December 2012.4. Global Nuclear Fuel document 0000-0145-7166-FBIR-P, "Fuel Bundle Information Report for Edwin I. Hatch Nuclear Power Plant Unit 2, Reload 22 Cycle 23," Revision 0, December 2012.5. SNC Nuclear Fuel Document NF-13-005, "Hatch-2 Cycle 23 Reload Licensing Analysis Report," Version 2, December 2014.6. GNF Design Basis Document DB-0012.05, "Fuel-Rod Thermal-Mechanical Performance Limits for GE14 and GNF2," Revision 4, April 2014.33 Version 2 Edwin I. Hatch Nuclear Plant Unit 1 Cycle 27 Core Operating Limits Report Version 2 Unit 2 Cycle 23 Core Operating Limits Report Version 2 Unit 2 Cycle 24 Core Operating Limits Report Version 1 Information Letter of NSF Lead Test Assemblies Enclosure 7 Global Nuclear Fuel -Americas Affidavit for Enclosure 8
Global Nuclear Fuel -Americas AFFIDAVIT I, Lukas Trosman, state as follows: (1) I am Engineering Manager, Reload Design and Analysis, Global Nuclear Fuel -Americas, LLC ("GNF-A"), and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in Enclosure 1 of GNF's letter, VSP-SNC-HVI-15-013, Vickie S. Perry to Susan Hoxie-Key (Southern Nuclear Operating Company), entitled "Edwin I. Hatch Nuclear Plant Unit 2 Cycle 24 Core Operating Limits Report (COLR)," February 24, 2015. GNF proprietary information in Enclosure I, which is entitled "Edwin I. Hatch Nuclear Plant Unit 2 Cycle 24 Core Operating Limits Report," is identified by a dotted underline inside double square brackets. 
[[Thntence s an exam.p.le...
A "[[" marking at the beginning of a table, figure, or paragraph closed with a "]]" marking at the end of the table, figure or paragraph is used to indicate that the entire content between the double brackets is proprietary.
In each case, the superscript notation (13 refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.
(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GNF-A relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for "trade secrets" (Exemption 4). The material for which exemption from disclosure is here sought also qualify under the narrower definition of "trade secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission.
975F2d871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704F2d1280 (DC Cir. 1983).(4) Some examples of categories of information which fit into the definition of proprietary information are: a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GNF-A's competitors without license from GNF-A constitutes a competitive economic advantage over other companies;
: b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;VSP-SNC-HVI-15-013 Enclosure I Affidavit Page I of 3 
: c. Information which reveals aspects of past, present, or future GNF-A customer-funded development plans and programs, resulting in potential products to GNF-A;d. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. above.(5) To address 10 CFR 2.390 (b) (4), the information sought to be withheld is being submitted to NRC in confidence.
The information is of a sort customarily held in confidence by GNF-A, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GNF-A, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence.
Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6) and (7)following.
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or subject to the terms under which it was licensed to GNF-A.(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation.
Disclosures outside GNF-A are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.
(8) The information identified in paragraph (2) is classified as proprietary because it contains details of GNF-A's fuel design and licensing methodology.
The development of the methods used in these analyses, along with the testing, development and approval of the supporting methodology was achieved at a significant cost to GNF-A or its licensor.VSP-SNC-HVI-15-013 Enclosure I Affidavit Page 2 of 3 (9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GNF-A's competitive position and foreclose or reduce the availability of profit-making opportunities.
The information is part of GNF-A's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost. The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.The research, development, engineering, analytical, and NRC review costs comprise a substantial investment of time and money by GNF-A.The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.
GNF-A's competitive advantage will be lost if its competitors are able to use the results of the GNF-A experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to GNF-A would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GNF-A of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.I declare under penalty of perjury that the foregoing affidavit is true and correct.Executed on this 2 4 th day of February 2015.Lukas Trosman Engineering Manager, Reload Design and Analysis Global Nuclear Fuel -Americas, LLC VSP-SNC-HVI-15-013 Enclosure I Affidavit Page 3 of 3}}