NL-11-0665, Cycle 22 Core Operating Limits Report, Version 1

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Cycle 22 Core Operating Limits Report, Version 1
ML111380420
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 05/17/2011
From: Ajluni M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML111380419 List:
References
NL-11-0665 MEF-SNC-HV1-11-037
Download: ML111380420 (43)
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Proprietary Information Mark J. Ajluni, Southern Nuclear Withhold Under 10 CFR 2.390 Nuclear Licensing Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 T 81 Fax SOUTHERN'\'

May COMPANY Docket Nos.: NL-11-0665

u. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant Unit 2 Cycle 22 Core Operating Limits Report, Version 1 Ladies and Gentlemen:

In accordance with Technical Specification 5.6.5.d, Southern Nuclear Operating Company submits the enclosed Core Operating Limits Report for Edwin I. Hatch Nuclear Plant Unit 2 Cycle 22 Version 1. The Attachment to this letter contains the following: Vendor transmittal letter Vendor Enclosure 1 -Edwin I. Hatch Nuclear Plant Unit 2 Cycle 22 Operating Limits Report -Vendor Enclosure 2 -Edwin I. Hatch Nuclear Plant Unit 2 Cycle 22 Operating Limits Report -Vendor Enclosure 3 -Vendor Affidavit Proprietary Statement:

The enclosed documentation contains proprietary information as defined by 10 CFR 2.390. GNF, as the owner of the proprietary information, has executed the enclosed affidavit, which identifies that the enclosed proprietary information has been handled and classified as proprietary, is customarily held in confidence, and has been withheld from public disclosure.

The proprietary information was provided to Edwin I. Hatch Nuclear Plant Unit 2 in a GNF transmittal that is referenced by the affidavit.

The proprietary information has been faithfully reproduced in the enclosed documentation such that the affidavit remains applicable.

GNF hereby requests that the enclosed proprietary information be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390 and 9.17. A non-proprietary version of the documentation also is provided.

This letter contains no NRC commitments.

If you have any questions, please contact Jack Stringfellow at (205) 992-7037.

Enclosures transmitted herewith contains SUNSL When separated enclosure, this transmittal document is U. S. Nuclear Regulatory Commission NL*11-0665 Page 2 Respectfully submitted, M. J. Ajluni Nuclear Licensing Director MJAlDWM/lac

Attachment:

Edwin I. Hatch Nuclear Plant Unit 2 Cycle 22 Core Operating Limits Report, Version 1 Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. D. R. Madison, Vice President

-Hatch Ms. P. M. Marino, Vice President

-Engineering RTYPE: CHA02.004 U. S. Nuclear Regulatory Mr. V. M. McCree, Regional Mr. P. G. Boyle, NRR Project Mr. E. D. Morris, Senior Resident Inspector

-Enclosures transmitted herewith contains SUNS!. When separated from enclosure, this transmittal document is decontrolled.

SOUTHERN NUCLEAR OPERATING EDWIN I. HATCH NUCLEAR Unit 2 Cycle CORE OPERATING LIMITS Version Southern Nuclear Operating Post Office Box Birmingham, Alabama GNF Proprietary Information ENCLOSURE 2 MEF-SNC-HVI-II-037 Edwin 1. Hatch Nuclear Plant Unit 2 Cycle Core Operating Limits N on-Proprietary INFORMATION This is a non-proprietary version of Enclosure 1 of MEF-SNC-HVI-ll-037, 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 [[ ]].

SOUTHERN NUCLEAR OPERATING EDWIN I. HATCH NUCLEAR Unit 2 Cycle CORE OPERATING LIMITS Version Southern Nuclear Operating Post Office Box Birmingham, Alabama Non-Proprietary Information Non-Proprietary Information Edwin I. Hatch Nuclear Unit 2 Cycle 22 Core Operating Limits TABLE OF CONTENTS Section Title Page 1.0 Introduction 2.0 APLHGR Limits 3.0 MCPR Operating Limits 4.0 LHGR Limits 5.0 PBOA Amplitude Setpoint 6.0 References Version Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits TABLES Table No. Title Page 1-1 Main Turbine Bypass System Operability 1-2 Equipment-Out-of-Service Limitations 3-1 MCPR Operating Flexibility Options 4-1 LHGR Operating Flexibility Options 4-2 LHGR Limit versus Peak Pellet Exposure 5-1 OPRM Setpoint ii Version Plant Hatch Core Operating Unit 2 Cycle 22 Non-Proprietary Information Limits Report FIGURES Figure No. Page 4 Flow-Dependent APLHGR Multiplier (MAPFAC F) versus Core Flow APLHGR Limit versus Average Planar 5 Exposure Power-Dependent MCPR Limit (MCPR p) 9 versus Core Power from 24% to 48% of Rated Core Power Power-Dependent MCPR Limit (MCPR p) 10 versus Core Power from 24% to 48% of Rated Core Power (Main Turbine Bypass System Inoperable) Flow-Dependent MCPR Limit (MCPR F) 11 versus Core Flow Power-Dependent MCPR Multiplier (Kp) 12 versus Core Power Power-Dependent MCPR Multiplier (Kp) 13 versus Core Power (EOC-RPT System Out of Service and Main Turbine Bypass System Inoperable Simultaneously) Power-Dependent MCPR Multiplier (Kp) 14 versus Core Power (Main Turbine Pressure Regulator System in TLCO 3.3. 13.c) GE14C MCPR Limits versus Average 15 Scram Time (BOC to EOR-4647 MWd/st) GNF2 L TA MCPR Limits versus Average 16 Scram Time (BOC to EOR-4647 MWd/st) GE14C MCPR Limits versus Average 17 Scram Time (EOR-4647 MWd/st to 3147 MWd/st) iii Version 1 Plant Hatch Unit 2 Cycle 22 Non-Proprietary Information Core Operating Limits Report Figure No. Title Page 3-48-2 GNF2 LTA MCPR Limits versus Average Scram Time (EOR-4647 MWd/st to 3147 MWdlst) 18 3-4C-1 GE14C MCPR Limits versus Average Scram Time (EOR-3147 MWd/st to EOC) 19 3-4C-2 GNF2 LTA MCPR Limits versus Average Scram Time (EOR-3147 MWdlst to EOC) 20 4-1 Flow-Dependent LHGR Multiplier (LHGRFAC F) versus Core Flow 23 4-2A Power-Dependent LHGR Multiplier (LHGRFAC p) versus Core Power 24 4-28 Power-Dependent LHGR Multiplier (LHGRFACp ) versus Core Power (Main Turbine Pressure Regulator System in TLCO 3.3. 13.c) 25 4-2C Power-Dependent LHGR Multiplier (LHGRFAC p) versus Core Power (High Pressure Heaters Out of Service) 26 4-3A GE14C LHGR versus Peak Pellet Exposure 27 4-38 GNF2 LTA LHGR versus Peak Pellet Exposure 28 iv Version 1 Plant Hatch Core Operating Unit 2 Cycle 22 Non-Proprietary Information Limits Report

1.0 INTRODUCTION

The Core Operating Limits Report (COLR) for Plant Hatch Unit 2 Cycle 22 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 22 are documented in References 3 through 5. The following core operating limits are included in this report: Average Planar Linear Heat Generation Rate (APLHGR) -Technical Specification 3.2.1 Minimum Critical Power Ratio (MCPR) -Technical Specification 3.2.2 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 Main Turbine Bypass System Operability Requirement Main Turbine Bypass System Operable At least two bypass valves must be (Technical Specification 3.7.7) operable Version 1 Plant Hatch Core Operating Unit 2 Cycle 22 Non-Proprietary Information Limits Report From a fuel thermal limits perspective, the following limitations are placed on Unit 2 operation.

TABLE 1-2 Equipment-Out-of-Service Limitations Equipment I 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

  • CTP must be s 2000 MWth Single-Loop Operation (SLO)
  • Core Flow must be s 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 1 Plant Hatch Core Operating Unit 2 Cycle 22 Non-Proprietary Information Limits Report 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 multiplied by the multiplier, MAPFAC F , from Figure 3 Version 1 Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits 1.0 I I TLO II I I<t I II. Il. 0.9 TLO -.. 0.86 *9 1 15. :2 0.8 :::I II SLO I {3 :3: 0.7 <t 1: GI -g 0.6 GI C I I II o u:: I I I I I I I 0.4 61 30 40 50 60 70 80 90 100 110 Core Flow ("to of Rated) Operating F SLO/TLO MAPFAC30 < F < 61 ILO 61 < F TLO 30::;; F SLO F = Percent of Rated Core Flow FIGURE Flow-Dependent APLHGR Multiplier (MAPFAC F) versus Core Version 1 Plant Hatch Unit 2 Cycle 22 Planar APLHGR Exposure Limit (GWd/st) (kW/ft) 0.00 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 5.00 Core Operating Non-Proprietary Information Limits Report 14.0 13,0 12,0 11,0 n g s:: 10,0 ::!!:..-'5 '" '" ::::i 9.0 IX: :s CI '" '" , 8,0 7,0 \ \5,0 R 4,0 5.0 10,0 15.0 20,0 25,0 30,0 35.0 40.0 45.0 SO.O 55.0 60,0 65,0 70,0 Average Planar Exposure (GWd/ST) FIGURE 2-2 APLHGR Limit versus Average Planar Exposure Version 1 Plant Hatch Core Operating Unit 2 Cycle 22 Non-Proprietary Information Limits Report 3.0 MCPR OPERATING LIMITS (Technical Specification 3.2.2) The MCPR operating limits (OLMCPR) 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. and the status of the main turbine pressure regulator system. With both recirculation pumps in operation (TLO). the OLMCPRs are determined as follows: For 24% ::;; power < 48%. the power-dependent MCPR limit, MCPR p , as determined by Table 3-1. For power 48%, the OLMCPRs are the greater of either: 1) The flow-dependent MCPR limit, MCPR F* from Figure 3-2, or The product of the power-dependent multiplier.

K p* and the rated-power OLMCPRs, as determined by Table 3-1. 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 1:" = 1.0, where 1:" 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 1:" 0.0. For scram times between Option A and Option B. the rated-power OLMCPR corresponds to 1:". If 1:" has not been determined, Option A limits must be used. Version 1 Plant Hatch Core Operating Unit 2 Cycle 22 Non-Proprietary Information Limits Report The average scram time of the control rods, 't, is defined as: 't ave -'tB 't = 0, , whichever is greater. where: 'tA = 1.08 sec (Technical Specification 3.1.4, Table 3.1.4-1, scram time limit to notch 36). 'tB = 11 + 1.65

  • a
  • LNi ;=! J.1 = 0.822 sec (mean scram time used in the transient analysis).

a = 0.018 sec (standard deviation of 11)' n LN;li ;=1'tave = n LN; ;=1 n = number of surveillance tests performed to date in the cycle. N; = number of active control rods measured in the ith surveillance test. 'tl = average scram time to notch 36 of all rods in the ith surveillance test. N1 = total number of active rods measured in Technical SpeCifications Surveillance Requirement 3.1.4.1. Version 1 Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits TABLE 3-1 MCPR Operating Flexibility Options Rated Power OLMCPRs GE14C BOC to EOR -4647 Figure 3-4A-1 EOR -4647 to EOR -3147 Figure 3-4B-1 EOR -3147 to EOC Figure 3-4C-1 MCPR p from 2: 24% to < 48% Power Main Turbine Bypass System Main Turbine Bypass System Kp for Power 2: 48% of Rated EOC-RPT In Main Bypass .. Main Pressure System TLCO 3.3.13.a or TLCO 3.3.13.a or TLCO 3.3.13.a or TLCO 3.3.13.a or TLCO GNF2 Figure Figure Figure Figure Figure 3-1 Figure Figure Figure Figure Figure EOR = End of rated conditions (100% power, 100% flow, ARO, with nominal feedwater temperature)

  • At least two bypass valves must be operable ** Option B scram speeds must be met (in place) at CTP ;:: 48% RTP 8 Version 1 3.0 Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits 2.8 l>60% FIOWIa: 0:: \a.. o '\ 2.6 ... '\*e :J g: 2.4 o ::Ii: \ 1: GI \" N \ \ L-g 2.2 GI Q. ; 2.0 o a.. \ 1.8 L--J :!:: 60% 1.6 27 28 24 30 33 36 39 42 45 Core Power (% of Rated) MCPRp(TLO)

=A + MCPRp(SLO)

= MCPRp(TLO)

+ F P A F s 60 24:-:; P < 28 4.1620 F > 60 24:-:; P < 28 4.1015 F s 60 28:-:; P < 48 2.1005 F > 60 28 P < 48 2.5093 P =Percent of Rated Core F =Percent of Rated Core FIGURE 3-1A Power-Dependent MCPR Limit (MCPR p) versus Core Power from 24% to 48% of Rated Core Power 9 Version 1 48 Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information limits 4.0 I I I 3.8 I I I -.3,6.. 0:: f; 3,4 :!. 3.2 :J g: 3.0 o :IE 1:! 2.8 CII "CI 5i 2.6 a. 2.4.:. CII 2.2 , "'" I.... I I ": I I I I I I I I I I I N I I I> 60% Flow I \ \ \ \ \ \ a. I I 2.0 t t 1.8 I 160% Flow" ... I 1.6 24 27 28 30 33 36 39 42 45 48 Core Power (0/. of Rated) MCPRP(TLO)

=A + B*P MCPRp(SLO)

=MCPRp(TLO)

+ 0.02 F P A B F!> 60 24:::; P <: 28 4.3996 -0.07070 F > 60 24:::; P <: 28 6.6484 -0.11780 F!> 60 28 S; P <: 48 2.1005 -0,00630 F> 60 28 S; 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 (MCPR p) versus Core Power from 24% to 48% of Rated Core Power (Main Turbine Bypass System Inoperable) 10 Version 1 Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits 1.6 I I'U: 1.5 I Maximum Flow 107% 0::: '"" a. I o -'E '" I I:J1.4 0::: " a. o I I 'E 4J "C J ai 1.3 Q '" .2 u.. 1.2 1.1 30 40 50 60 70 80 90 100 110 Core Flow (% of Rated) MCPRF(TLO)

=A + MCPRF(SLO)

=MCPRF(TLO)

+ Flow A 30 :s; F :s; 68.190 1.713 68.190 < F 1.310 F = Percent of Rated Core FIGURE Flow-Dependent MCPR Limit (MCPR F) versus Core 11 Version 1 Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits 1.3 '" " " '" '" too... to 48 52 56 60 64 68 72 76 80 84 92 Core Power (% of Kp =A + 8*P P A 48 < P < 60 1.6702 60:'>P 1.3750 P = Percent of Rated Core Power FIGURE 3-3A Power-Dependent MCPR Multiplier (Kp) versus Core Power 12 Version 1 100 Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits 1,3 " '"

'"

-..... " 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 48::;; P < 60 1.6702 60::;; P < 90 1.3308 90< P 1.5961 P = Percent of Rated Core FIGURE 3-3B Power-Dependent MCPR Multiplier (Kp) versus Core (EOC-RPT System Out of Service and Main Bypass System Inoperable 13 Version 1

--Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits 1.5 II> 1.4 r---... r--.... --......! :; --......

=!51.3 It:: " " Q. o :::E C II> -C c

'" '" II> C .!. II> 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 48 P < 70 1.6268 70 P 2.0367 P = Percent of Rated Core FIGURE 3-3C Power-Dependent MCPR Multiplier (Kp) versus Core Power (Main Turbine Pressure Regulator System in TLCO 3.3. 13.c) 14 Version 1

Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits 1.52 1.50 ---EOC-RPT Out of Service 1.46 --Turbine Bypass System Inoperable

.!! 1.42 *s 1.40 I EOC-RPT Out of Service I ---------1.38 -----1.36 U -----Turbine BypassI I I System Inoperable I V-----I I I EOC-RPT In Service and Turbine Bypass System Operable I 1.28 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 Main EOC-RPT Bypass System 't =0.0 't = In Service Operable 1.31 Out of Service Operable 1.33 In Service Inoperable 1.31 Out of Service Inoperable 1.37 FIGURE 3-4A-1 GE14C MCPR Limits versus Average Scram Time (SOC to EOR -4647 MWd/st) Version 1

---I Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits 1.52 1.50 ---1.48 EOC-RPT Out of Service Plus Turbine System --------------1 flO 1.42 I EOC-RPT Out of Service----::::i 140 g: U -------:;;; 1.38 ---I Turbine Bypass )'Stem Inoperable 1.36 ---1.34 1.32 I EOC-RPT In Service and Turbine Bypass System Operable I 1.30 1.28 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 Main EOC-RPT Bypass System t=O.O 't = In Service Operable 1.31 Out of Service Operable 1.35 In Service Inoperable 1.32 Out of Service Inoperable 1.39 FIGURE 3-4A-2 GNF2 L TA MCPR Limits versus Average Scram Time (SOC to EaR -4647 MWd/st) Version 1

Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits 1.56 1.54 1.52 EOC*RPT Out of Turbine System Inoperable

L---r---1A6 :t:::-I EOC*RPT Out of Service ,:11.44 1.42 E -----------Q. li 1.40 I Turbine Bypass I System Inoperable I 1.36 1.34 1.32 I EOC*RPT In Service and Turbine Bypass System Operable I 1.30 1.28 0.1 0.2 0.3 OA 0.5 0.6 0.7 0.8 0.9 Tau OLMCPR(SLO)

=OLMCPR(TLO)

+ 0.02 Operating Conditions Main EOC*RPT Bypass System t =0.0 1'= In Service Operable 1.31 Out of Service Operable 1.38 Inoperable 1.35 Out of Servi Inoperable 1.41 In c ........ FIGURE 3-46*1 GE14C MCPR Limits versus Average Scram Time (EOR -4647 MWd/st to EOR -3147 MWd/st) Version 1

Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits 1.56 1.54 EOC.RPT Out of ServicePlus Turbine System Inoperable 1.48 -1.46 ---I EOC-RPT Out of Service :§ --------.! 1.44 1.42 D.. U Turbine Bypass :::e 1.40 System Inoperable i""" I 1.38 1.36 I EOC-RPT In Service and Turbine Bypass System Operable I i"""" 1.34 1.32 1.30 1,28 0.1 0,2 0.3 0.4 0.5 0.6 0.7 0,8 O,g Tau OLMCPR(SlO)

= OLMCPR(TlO)

+ 0.02 Operating Conditions Main EOC-RPT Bypass System 't =0.0 't =In Service Operable 1.35 Out of Service Operable 1.40 In Service Inoperable 1.39 Out of Service Inoperable 1.44 FIGURE 3-4B-2 GNF2 LTA MCPR Limits versus Average Scram Time (EOR -4647 MWd/st to EOR -3147 MWd/st) Version 1 Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits 1.68 ,----,------,----,----,-----,----r----,.----,------,r---_ +----t----+---t----f----+---f-----f----+----.,f__--

!

EOC*RPT Out of___ ____ +---+_--_+_--1 Plus Turbine Bypass _____

___ 1.54 ___

...............

EOC*RPT Out of Service

+---+---+--

--+I-"""--:::;;I,.....::---I::-"""""OI::-----:....-+-li 1.52 ____+---+-

!i 1.50 _____ _____ _I Turbine Bypass 11__--+---+----1 1.46 I System Inoperable I 1.44 1.42 1.40 I EOC*RPT In Service and Turbine Bypass System Operable 1.38 -I-----I----4----4-----l-----I---_>--

__4--__-I-__---l__---I 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 Main EOC-RPT Bypass System 't =0.0 't = In Service Operable 1.40 Out of Service Operable 1.45 In Service Inoperable 1.42 Out of Service Inoperable 1.48 FIGURE 3-4C-1 GE14C MCPR Limits versus Average Scram Time (EOR -3147 MWdlst to EOC) Version 1

Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits 1.68 1.66 1.64 EOC-RPT Out of Turbine Bypass System Inoperable -------------1.58 1.56 I EOC-RPT Out of Service E --I a. ---I Turbine BypassSystem Inoperable

E 1.52 ---1.50 1.48 1A6 I EOC-RPT In Service and Turbine Bypass System Operable -1A4 1.42 1AO o 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 Main EOC-RPT Bypass System 1: =0.0 1: =In Service Operable Out of Service Operable 1.4 In Service Inoperable 1.48 Out of Service Inoperable 1.53 1.1=+= 1.50 FIGURE 3-4C-2 GNF2 L TA MCPR Limits versus Average Scram Time (EOR -3147 MWd/st to EOC) Version 1 Plant Hatch Core Operating Unit 2 Cycle 22 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, LHGRFAC F , from Figure 4-1, or b. The power-dependent multiplier, LHGRFAC p , 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 secona 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 4-38 show the LHGR limits for U0 2 rods and the most limiting Gd rods for each fuel type. 21 Version 1 Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits TABLE 4-1 LHGR Operating Flexibility Options LHGRFAC p Main Turbine Pressure Regulator System Status High Pressure Feedwater Heaters TlCO 3.3.13.a or b In Service Figure 4-2A TlCO 3.3.13.c In Service Figure 4-28* 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 Fuel Type GE14 Six Inch Segment Gd (w/o) 0.00 0.00 0.00 4.00 5.00 5.00 5.00 6.00 6.00 7.00 Rod Max. Gd (w/o) 0.00 4.00 6.00 4.00 5.00 6.00 7.00 6.00 7.00 7.00 lHGR limit at BOl (kW/ft) 13.400 13.100 13.100 12.800 12.521 12.400 12.300 12.255 12.100 12.000 lHGR limit at Knee 1 (kW/ft) 13.400 13.100 13.100 12.800 12.521 12.400 12.300 12.255 12.100 12.000 Exp. at Knee 1 {GWd/st} 14.515 14.190 14.190 12.510 12.389 12.247 12.132 12.276 12.095 12.174 lHGR limit at Knee 2 (kW/ft) 8.000 7.821 7.821 7.642 7.475 7.403 7.343 7.316 7.224 7.164 Exp. at Knee 2 (GWd/st) 57.607 56.317 56.317 55.928 55.443 54.884 54.424 54.999 54.275 54.589 lHGR limit at EOl (kW/ft) 5.000 4.888 4.888 4.776 4.672 4.627 4.590 4.572 4.515 4.478 Exp. at EOl (GWd/st) 63.504 62.082 62.082 61.869 61.335 60.718 60.212 60.845 60.047 60.394 GNF2 lTAs [[ BOL = Beginning of Life (zero exposure)

]] EOL = End of Life (maximum licensed pellet exposure) 22 Version 1 Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits 1.0 V II! 0.9 (!) I TLO/SLO I "Y:z:: /::... Q) 0.8 :::I :& vV D:: ./ r------,0.7 / SLO...J C Q) 06 Q) Q o ii: 0.5 MAXFLOW= 107% 0.4 30 40 50 60 70 80 90 100 110 Core Flow (% of Rated) LHGRFAC F =A + B*F Operating Conditions Values of F SLO I TLO A SLO/TLO 0.4574 50.70 F < 80.29 TLO 0.4574 0.006758 50.70 F SLO 0.8000 0.000000 80.29 F TLO 1.0000 F = Percent of Rated Core FIGURE 4-1 Flow-Dependent LHGR Multiplier (LHGRFAC F) versus Core Flow 23 Version 1

--Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits 1.1 ..,.".. V ,; 60% Core Flow I / ".... >60% Core Flow 0.5 lJ 0.4 M a @ << LHGRFAC p = A + B*P Operating Conditions P F 24 < P < 28 F > 60 24 < P < 28 F 28:s: P < 48 All 48:s:P All P -Percent of Rated Core Power F =Percent of Rated Core Flow M

  • n Core Power (% of Rated) Values of Variables A B 0.17924 0.009670 0.10366 0.016741 0.52261 0.003617 0.47760 0.005224 FIGURE4-2A ro W M *
  • 100 Power-Dependent LHGR Multiplier (LHGRFAC p) versus Core Power 24 Version 1

Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits 1.1 J 1.0 V C) J::::!. 0.9 .. 'a. / ... a! .// 0.8 I S 60% Core Flow I --' C) J: V...J 1: 0.7 a! 'C C a! Co 2l 0.6 V a! &. 0.5 / A> 60% Core Flow I ) 0.4 M W M n ro M M % 100 Core Power (% of Rated) LHGRFAC p = 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 Pressure Regulator System in TLCO 3.3. 13. c) 25 Version 1 1.0 Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits 1.1 .. (J 't1. ,/ II:: /0.9 ...J Q) '5. .. / /E 0.8 S 60% Core Flow :::I ",.::& ::t: t3 V / 07 --Q) I: C. Q) 0.6 .:. Q) /;:: o Il. A>60% Core Flow I 0.5 / V 0.4 3 % *

  • M M n ffl M M % 100 Core Power (% of Rated) LHGRFAC p =A + B*P Operating Conditions Values of Variables P F A 24::; P < 28 F > 60 0.17924 24::; P < 28 F ::;60 0.10366 28 < P < ,n All 0.52261 48 < P < 60.04 All 0.47760 0.005224 60.04 ::;; P < 86.06 All 0.79100 86.06::; P All -0.49800 P = Percent of Rated Core F =Percent of Rated Core FIGURE 4-2C Power-Dependent LHGR Multiplier (LHGRFAC p) versus Core Power (High Pressure Heaters Out of Service) 26 Version 1 Plant Hatch Core Unit 2 Cycle 22 Non-Proprietary Information Limits 14.0 U02 Rods 13.0 Peak 12.0 Exposure LHGR (GWd/st) (kW/ft) " U02Rods 0.000 13.400 11.0 " 14.515 13.400 "'-57.607 8.000 10.0 63.504 5.000 '" " 3: :!. 9.0 I GdRods I 0:: C)Limiting Gd Rods J: Peak ... 8.0 , Exposure LHGR 7.0 (GWd/st) 0.000 12.000 1\ 12.174 12.000 6.0 54.589 7.164 60.394 4.478 5.0 j 4.0 0.0 liO 10.0 15.0 20.0 25.0 D.O 35.0 40.0 450 500 55.0 60.0 65.0 Peak Pellet Exposure (GWd/st) FIGURE4-3A GE14C LHGR versus Peak Pellet Exposure 27 Version 1 Plant Hatch Unit 2 Cycle 22 Non-Proprietary Information Core Operating Limits Report [( U02 Rods Peak Pellet Exposure LHGR (GWd/st) (kW/ft) [[ ]] Limiting Gd Rods Peak Pellet Exposure LHGR (GWd/st) (kW/ft) II ]] ]] FIGURE 4-38 GNF2 LTA LHGR versus Peak Pellet Exposure 28 Version 1 Plant Hatch Core Operating Unit 2 Cycle 22 Non-Proprietary Information Limits Report 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 OLMCPR 1.31 29 Version 1 Plant Hatch Core Operating Unit 2 Cycle 22 Non-Proprietary Information Limits Report

6.0 REFERENCES

"General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A-17, September 2010, and the US Supplement, NEDE-24011-P-A-17-US, September 2010. GNF letter MEF-SNC-HV1-10-055, "Hatch 2 Reload 21 Cycle 22 Supplemental Reload Licensing Report and Fuel Bundle Information Report," M. Fitzpatrick to S. Hoxie-Key, December 17, 2010. Global Nuclear Fuel document 0000-0116-1536-SRLR, "Supplemental Reload Licensing Report for Edwin I. Hatch Nuclear Power Plant Unit 2, Reload 21 Cycle 22," Revision 0, December 2010. Global Nuclear Fuel document 0000-0116-1536-FBIR-P, "Fuel Bundle Information Report for Edwin I. Hatch Nuclear Power Plant Unit 2, Reload 21 Cycle 22," Revision 0, December 2010. SNC Nuclear Fuel document NF-11-020 "Hatch-2 Cycle 22 Reload Licensing Analysis Report," Version 1, February 2011. GNF Document DB-0012.03, "Fuel-Rod Thermal-Mechanical Performance Limits for GE14C," Rev. 2, September 2006. Version 1 ENCLOSURE 3 MEF-SNC-HVl-l1-037 Edwin 1. Hatch Nuclear Plant Unit 2 Cycle Core Operating Limits Global Nuclear Fuel-I, Russell E. Stachowski, state as follows: I am Chief Consulting Engineer, Nuclear Physics, Global Nuclear Fuel-Americas, LLC ("GNF-A"), and have been delegated the function of reviewing the infonnation described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding. The infonnation sought to be withheld is contained in Enclosure 1 of GNF's letter, MEF-SNC-HVI-II-037, Michael E. Fitzpatrick to Susan Hoxie-Key (Southern Nuclear Operating Company), entitled "Edwin 1. Hatch Nuclear Plant Unit 2 Cycle 22 Core Operating Limits Report (COLR)," March 17, 2011. GNF proprietary infonnation in Enclosure I, which is entitled "Edwin 1. Hatch Nuclear Plant Unit 2 Cycle 22 Core Operating Limits Report," is identified by a dotted underline inside double square brackets.

..

..

..?:]] 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 {J} refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary detennination. In making this application for withholding of proprietary infonnation of which it is the owner or licensee, GNF -A relies upon the exemption from disclosure set forth in the Freedom of Infonnation 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 tenns 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, 704F2dl280 (DC Cir. 1983). Some examples of categories of infonnation which fit into the definition of proprietary infonnation are: Infonnation 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; Infonnation 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; Affidavit Page 1 of 3 Information which reveals aspects of past, present, or future GNF-A funded development plans and programs, resulting in potential products to GNF-A; 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. 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. 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. Access to such documents within GNF-A is limited on a "need to know" basis. 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. The information identified in paragraph (2) is classified as proprietary because it contains details ofGNF-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.

Affidavit Page 2 of 3 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 and the matters stated therein are true and correct to the best of my knowledge, information, and belief. Executed on this 17th day of March 2011. Russell E. Stachowski Chief Consulting Engineer, Nuclear Physics Global Nuclear Fuel-Americas, LLC Affidavit Page 3 of 3

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