NL-20-0241, Cycle 30 Core Operating Limits Report Version 1.0
ML20070R213 | |
Person / Time | |
---|---|
Site: | Hatch ![]() |
Issue date: | 03/10/2020 |
From: | Gayheart C Southern Nuclear Operating Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
Shared Package | |
ML20071D265 | List: |
References | |
NL-20-0241 | |
Download: ML20070R213 (46) | |
Text
A Southern Nuclear Chery l A. Gayheart Regu latory Affairs Director
.1535 Co lonn ad~ P:.rl-.11a~
Birmingham. 1\L 3-:2-13
~05 992 53 16 tel
- 20. 992 7795 li1' to this letter contains Proprietary Information to be caga~ h\!afc?southcmco c-om withheld from public disclosure per 10 CFR 2.390. When separated from Enclosure 1 this transmittal document is decontrolled .
MAR 1 0 2020 Docket No.: 50-321 NL-20-0241 U. S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington , D. C. 20555-0001 Edwin I. Hatch Nuclear Plant - Unit 1 Cycle 30 Core Operating Limits Report Version 1.0 Ladies and Gentlemen :
In accordance with Technical Specification 5.6.5.d. , Southern Nuclear Operating Company (SNC) submits the enclosed Core Operating Limits Report (COLR) , for Edwin I. Hatch Nuclear Plant (HNP) Unit 1 Cycle 30, Version 1.0.
The enclosed documentation contains proprietary information as defined by 10 CFR 2.390.
Global Nuclear Fuel (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 SNC 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 provided in Enclosure 1 to this letter be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390 and 9.17. A non-proprietary version of the COLR is provided as Enclosure 2. This affidavit is also provided in Enclosure 1 to this letter and identifies that the designated information has been handled and classified as proprietary to GNF.
This letter contains no NRC commitments . If you have any questions, please contact Jamie Coleman at 205.992.6611 .
Respectfully submitted ,
ayheart Regulatory Affairs Director
U. S. Nuclear Regulatory Commission NL-20-0241 Page 2 CAG/TLE/scm
Enclosures:
- 1. Unit 1 Cycle 30 Core Operating Limits Report Version 1.0 PROPRIETARY INFORMATION and Global Nuclear Fuel - Americas Affidavit
- 2. Unit 1 Cycle 30 Core Operating Limits Report Version 1.0 NON-PROPRIETARY INFORMATION Cc: Regional Administrator, Region II NRR Project Manager - Hatch Senior Resident Inspector- Hatch RTYPE: CHA02.004
Edwin I. Hatch Nuclear Plant - Unit 1 Cycle 30 Core Operating Limits Report Version 1.0 Enclosure 2 Unit 1 Cycle 30 Core Operating Limits Report Version 1.0 NON-PROPRIETARY INFORMATION
Non-Proprietary Information SOUTHERN NUCLEAR OPERATING COMPANY EDWIN I. HATCH NUCLEAR PLANT Unit 1 Cycle 30 CORE OPERATING LIMITS REPORT Version 1
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 TABLE OF CONTENTS Section Title Page 1.0 Introduction 6 2.0 APLHGR Operating Limits 10 3.0 MCPR Operating Limits 12 4.0 LHGR Operating Limits 29 5.0 Operating Pressure Limits 39 6.0 References 43 2
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 TABLES Table No. Title Page 1-1 System Operability Requirements 7 1-2 Equipment Requirements 7 1-3 Equipment-Out-of-Service Limitations 8 1-4 Exposure Definitions 9 3-1 Cycle-Specific MCPR Safety Limit 14 3-2 Power-Dependent MCPRp Limit Operating Flexibility Options (for Core Power ~ 28% of Rated) 14 3-3 Power-Dependent Kp MCPR Limit Multiplier Flexibility Options (for Core Power > 28% of Rated) 14 3-4 Rated-Power OLMCPR Operating Flexibility Options 15 4-1 Rated-Power LHGR Limits versus Peak Pellet Exposure 30 4-2 Flow-Dependent LHGRFACF Limit Multiplier Operating Flexibility Options 31 4-3 Power-Dependent LHGRFACp Limit Multiplier Operating Flexibility Options 31 5-1 Pressure Dependent Operating Flexibility Options 42 5-2 MFLCPR and MFLPD Limits versus Operating Pressure Regions 42 3
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 FIGURES Figure No. Title Page 2-1 APLHGR Limits versus Average Planar Exposure 11 3-1 Flow-Dependent MCPR Limit (MCPRF) versus Core Flow 16 3-2A Power-Dependent MCPR Limit (MCPRp) versus Core Power 17 3-28 Power-Dependent MCPR Limit (MCPRp) versus Core Power (Main Turbine Bypass System Inoperable) 18 3-3A Power-Dependent MCPR Limit Multiplier (KP) versus Core Power 19 3-38 Power-Dependent MCPR Limit Multiplier (KP) versus Core Power (Main Turbine Pressure Regulator System in TLCO 3.3.13.c) 20 3-4A-1 Rated-Power TLO MCPR Limits versus Average SCRAM Time 21 3-4A-2 Rated-Power TLO MCPR Limits versus Average SCRAM Time (Main Turbine Bypass System Inoperable) 22 3-4A-3 Rated-Power TLO MCPR Limits versus Average SCRAM Time (EOC-RPT System Inoperable) 23 3-4A-4 Rated-Power TLO MCPR Limits versus Average SCRAM Time (Main Turbine Bypass System Inoperable &
EOC-RPT System Inoperable) 24 3-48-1 Rated-Power SLO MCPR Limits versus Average SCRAM Time 25 3-48-2 Rated-Power SLO MCPR Limits versus Average SCRAM Time (Main Turbine Bypass System Inoperable) 26 3-48-3 Rated-Power SLO MCPR Limits versus Average SCRAM Time (EOC-RPT System Inoperable) 27 4
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 Figure No . Title Page 3-48-4 Rated-Power SLO MCPR Limits versus Average SCRAM Time (Main Turbine Bypass System Inoperable &
EOC-RPT System Inoperable) 28 4-1A GNF2 Flow-Dependent LHGR Limit Multiplier (LHGRFACF) versus Core Flow 32 4-18 GNF2 Flow-Dependent LHGR Limit Multiplier (LHGRFACF) versus Core Flow (Main Turbine Bypass System Inoperable) 33 4-1C GNF3 Flow-Dependent LHGR Limit Multiplier (LHGRFACF) versus Core Flow 34 4-2A GNF2 Power-Dependent LHGR Limit Multiplier (LHGRFACp) versus Core Power 35 4-28 GNF3 Power-Dependent LHGR Limit Multiplier (LHGRFACp) versus Core Power 36 4-3A GNF2 Rated-Power LHGR Limit versus Peak Pellet Exposure 37 4-38 GNF3 Rated-Power LHGR Limit versus Peak Pellet Exposure 38 5-1 Licensed Regions of Operating Dome Pressure versus Core Power 41 5
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1
1.0 INTRODUCTION
The Core Operating Limits Report (COLR) for Plant Hatch Unit 1 Cycle 30 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 3) .
Results from the reload analyses for the fuel in Unit 1 Cycle 30 are documented in References 4 through 6.
GNF2 fuel limits in this report are applicable to ARMOR and IronClad Lead Test Assemblies (References 7 through 9).
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 This report also includes limits on the Maximum Fraction of Limiting Critical Power Ratio (MFLCPR) and Maximum Fraction of Limiting Power Density (MFLPD) thermal limit ratios, which may be used in conjunction with the standard core operating limits to allow operation with dome pressure down to 40 psi below nominal.
Related system operability requirements are defined in Table 1-1 . Equipment requirements which must be satisfied for the operating limits included in this report to remain applicable are defined in Table 1-2.
Operating limit flexibility options are provided for various equipment out-of-service conditions ,
dependent on the number of operating recirculation loops, operability of the main turbine bypass system, operability of the End-of-Cycle Recirculation Pump Trip (EOC-RPT) system, and status of the main turbine pressure regulator system. Additional operational limitations associated with use of combinations of equipment out-of-service limits are defined in Table 1-3.
Operating limits are presented in this report as a function of fuel type, core power, core flow, average scram time , and exposure. These limits are not a function of feedwater temperature.
Cycle exposure intervals used in the presentation of limits in this report are defined in Table 1-4.
Operating limits between tabulated values presented in this report are based on linear interpolation.
6
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 TABLE 1-1 System Operability Requirements System Operability Requirement Main Turbine Bypass System Operable At least two bypass valves must be operable (Technical Specification 3.7.7)
TABLE 1-2 Equipment Requirements Equipment Requirement The maximum achievable core flow on the highest Recirculation Flow Control System licensed rod line must be limited to less than 107% of rated core flow When operating at greater than 55% core thermal Turbine Power/Load Unbalance Trip Logic power, the turbine Power/Load Unbalance (PLU) trip logic must be functional The Oscillation Power Range Monitor (OPRM)
APRM System Period Based Detection Algorithm (PBDA) amplitude trip setpoint must be set equal to 1.15 7
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 TABLE 1-3 Equipment-Out-of-Service Limitations Equipment I Condition Limitation Single-Loop Operation (SLO)
- Core power must be ~ 2000 MWth
- Core flow must be :5 55% of rated Main Turbine Bypass System Inoperable OR Dome pressure must be within +/- 10 psi of nominal , as defined in Figure 5-1 Main Turbine Pressure Regulator System in TLCO 3.3.13.c 8
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 TABLE 1-4 Exposure Definitions Exposure Label Definition Cycle Exposure BOC Beginning of Cycle Exposure 0 MWd/ST MOC1 First Middle of Cycle Exposure EOR - 6000 MWd/ST Second Middle of Cycle MOC2 EOR - 3500 MWd/ST Exposure Projected exposure at end of rated power with all control rods EOR End of Rated Exposure out, rated core flow, and rated feedwater temperature EOC End of Cycle Exposure Exposure at cycle shutdown 9
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 2.0 APLHGR OPERATING LIMITS (Technical Specification 3.2.1)
For both two loop operation (TLO) and single loop operation (SLO) , the APLHGR operating limit for each six inch axial segment of each fuel assembly in the core is the applicable fuel-type-specific APLHGR limit defined in Figure 2-1 .
No flow dependent or power dependent APLHGR limit multipliers (MAPFACF or MAPFACp) are required . For SLO, no unique limit on MAPFACF or MAPFACp is required .
These limits apply to operation over the full range of licensed dome pressure regions shown in Figure 5-1 .
10
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 15 .00 Average Planar GNF2 APLHGR 14 .00 Exposure Limit 13 .00 ~ !!lit..
(GWd/ST) (kW/ft) 12 .00 1-0.00 13.78 ~~
17.15 13.78 11 .00 J GNF3 f
~~
60.78 6.87 10 .00 I 63 .50 5.50
~~
..lll: GNF2
- t
- ! I
'~
E 9 . 00
- J 0:::
Average GNF3 ~ 8 . 00
...J Planar APLHGR
~
D.
Exposure Limit
\
7 .00 (GWd/ST) (kW/ft) 6 . 00 0.00 9.07 14.36 13.78
\
5 . 00 21 .22 13.01 40 .82 10.75 4 . 00
- 0. 0 10.0 20.0 30.0 40 .0 50.0 60 .0 70.0 57 .60 8.00 63.50 6 .00 Average Planar Exposure (GWd/ST)
FIGURE 2-1 APLHGR Limits versus Average Planar Exposure 11
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 3.0 MCPR OPERATING LIMITS (Technical Specification 3.2.2)
The MCPR operating limit (OLMCPR) for each licensed equipment in or out of service operating flexibility combination is independent of fuel type, and is a function of core power, core flow, average scram time , and cycle exposure .
The cycle-specific MCPR safety limits (SLMCPRs) are specified in Table 3-1.
For both two loop operation (TLO) and single loop operation (SLO) , the OLMCPR is determined as follows :
- a. For 24% ~core power~ 28% , the greater of either:
- 1) The flow-dependent MCPR limit, MCPRF, as determined by Figure 3-1 ,
- 2) The power-dependent MCPR limit, MCPRp, as determined by Table 3-2.
- b. For core power> 28% , the greater of either:
- 1) MCPRF, as determined by Figure 3-1 ,
- 2) The product of the power-dependent MCPR limit multiplier (KP) , as determined by Table 3-3 , and the scram-time dependent rated-power OLMCPR, as determined by Table 3-4 .
These limits apply to operation with vessel dome pressure within +/- 10 psi of nominal pressure, as defined by the Region I pressure band shown in Figure 5-1 . With all equipment in service or with the EOC-RPT system inoperable, operation with vessel dome pressure down to 40 psi below nominal is licensed provided the additional restrictions identified in Section 5.0 are applied with the OLMCPR defined in this section .
12
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 In the 3-4A and 3-48 figures, Option A scram time rated-power OLMCPRs correspond to
, =1.0, where , 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 , = 0.0 . For scram times between Option A and Option B , the rated -power OLMCPR corresponds to , . If , has not been determined , Option A limits must be used .
The average scram time of the control rods , 't , is defined as:
't = 0, OR L ave -'t B
___::c..:....._---=.. , whichever is greater.
where: 't A = 1.08 sec (Technical Specification 3.1.4, Table 3.1.4-1 , scram time limit to notch 36) .
I 2
N,
't g = ~+1.6 5* cr
(J = 0.018 sec (standard deviation of J..l) .
N, = total number of active rods measured in Technical Specifications Surveillance Requirement 3.1.4.1.
n = number of surveillance tests performed to date in the cycle.
N i = number of active control rods measured in the i1h surveillance test.
11 I Ni 't i i=l
't ave = n I Ni i=l where: 'ti = average scram time to notch 36 of all rods in the i 1h surveillance test.
13
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 TABLE 3-1 Cycle-Specific MCPR Safety Limit TLO SLO 1.07 1.09 TABLE 3-2 Power-Dependent MCPRp Limit Operating Flexibility Options (for Core Power s 28% of Rated)
Equipment In/Out of Service Main Turbine Main Turbine Pressure Figure#
EOC-RPT S~stem B~ass S~stem Regulator S~stem 012erable 012erable Status Yes 3-2A Yes/No TLCO 3. 3.13.a, b, or c No 3-28 TABLE 3-3 Power-Dependent Kp MCPR Limit Multiplier Flexibility Options (for Core Power > 28% of Rated)
Equipment In/Out of Service Main Turbine Main Turbine Pressure Figure#
EOC-RPT S~stem B~12ass S~stem Regulator S~stem 012erable 012erable Status TLCO 3.3.13.a orb 3-3A Yes/No Yes/No TLCO 3.3.13 .c 3-38 14
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 TABLE 3-4 Rated-Power OLMCPR Operating Flexibility Options Figure#
Equipment In/Out of Service TLO SLO Equipment In Service 3-4A-1 3-4B-1 Main Turbine Bypass System Inoperable 3-4A-2 3-4B-2 EOC-RPT System Inoperable 3-4A-3 3-4B-3 Main Turbine Bypass EOC-RPT System AND 3-4A-4 3-4B-4 System Inoperable Inoperable Main Turbine Pressure Regulator System in TLCO 3.3.13.c 3-4A-1 3-4B-1 Main Turbine Bypass 3-4A-2 3-4B-2 System Inoperable EOC-RPT System 3-4A-3 3-4B-3 Main Turbine Pressure Inoperable Regulator System AND in TLCO 3.3.13.c Main Turbine Bypass System Inoperable AND 3-4A-4 3-4B-4 EOC-RPT System Inoperable 15
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 1.60 I TLO _]
1.50 ct a..
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~ 1.40
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E
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- 30. 0 40.0 50. 0 60. 0 70. 0 80 .0 90. 0 100 .0 110 .0 Core Flow (%of Rated)
Flow (%of Rated) MCPRF (TLO) 30.0 1.52 85.0 1.20 110.0 1.20 MCPRF(SLO) = MCPRF(TLO) + 0.03 FIGURE 3-1 Flow-Dependent MCPR Limit (MCPRF) versus Core Flow 16
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 2.80 I TLO I
2.70
~
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0 I Flow ~60%
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- 2. 30 24.0 28. 0 Core Power(%ofRated)
Flow (% of Rated) Power(% of Rated) MCPRp (TLO) 24 .0 2.40
- : 60.0
~ 28.0 2.35 24.0 2.35
< 60.0
~ 28.0 2.35 MCPRp(SLO) = MCPRp(TLO) + 0.03 FIGURE 3-2A Power-Dependent MCPR Limit (MCPRp) versus Core Power 17
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1
- 2. 80 I TLO I
I Flow~60%
I 2 .70
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Flow (%of Rated) Power (%of Rated) MCPRp (TLO) 24.0 2.71
- 60.0
~ 28.0 2.71 24.0 2.64
< 60.0
~ 28.0 2.45 MCPRp(SLO) = MCPRp(TLO) + 0.03 FIGURE 3-28 Power-Dependent MCPR Limit (MCPRp) versus Core Power (Main Turbine Bypass System Inoperable) 18
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 1.500 1.400
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28.0 30.0 40 .0 50.0 55.0 60 .0 70.0 80.0 90.0 100.0 Core Power(% of Rated)
Power(% of Rated) Kp (TLO/SLO)
> 28.0 1.413 45.0 1.285
- 55.0 1.285
> 55.0 1.150 60.0 1.150 85.0 1.070 100.0 1.000 FIGURE 3-3A Power-Dependent MCPR Limit Multiplier (KP) versus Core Power 19
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 1.500 1.400
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I 1.000 28 .0 30.0 40 .0 50.0 60.0 70.0 80.0 85.0 90.0 100.0 Core Power(% of Rated)
Power(% of Rated) Kp (TLO/SLO)
> 28.0 1.413 45.0 1.285 60.0 1.285
- 85.0 1.196
> 85.0 1.085 100.0 1.000 FIGURE 3-38 Power-Dependent MCPR Limit Multiplier (KP) versus Core Power (Main Turbine Pressure Regulator System in TLCO 3.3.13.c) 20
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 1.70 1.70 1.65 1.65 1.60 1.60 1.55 1.55
- t
- ;t:
.§ 1.50 1.50 E
- J
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1.40 1.40 1.35 1.35 1.30 1.30 0 .0 0.2 0.4 0.6 0.8 1.0 Rated OLMCPR(TLO)
Exposure Range
't = 0.0 't = 1.0 BOC - MOC1 1.31 1.44 MOC1- MOC2 1.32 1.46 MOC2- EOC 1.36 1.50 FIGURE 3-4A-1 Rated-Power TLO MCPR Limits versus Average SCRAM Time 21
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 1.70 1.70 1.65 1.65 1.60 1.60 1.55 1.55
.-::: ~
E 1.50 1.50 .§
- J -1 0::: 0:::
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1.40 1.40 1.35 1.35 1.30 1.30 00 0.2 0.4 0.6 0 .8 1.0 Rated OLMCPRnLo)
Exposure Range
't = 0.0 't = 1.0 BOC- MOC1 1.37 1.49 MOC1- MOC2 1.37 1.52 MOC2- EOC 1.40 1.56 FIGURE 3-4A-2 Rated-Power TLO MCPR Limits versus Average SCRAM Time (Main Turbine Bypass System Inoperable) 22
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 1.70 1.70 1.65 1-------1-----~-------t--------+--------1 1.65 MOC2- EOC 1.60 1.55 1.55
~ ~
E 1.50 1.50 E
- .J :.J
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c.. c..
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- !! 1.45 1.45 1.40 1.40 1.35 1.35 1.30 1.30 0 .0 0.2 0.4 0.6 0.8 1.0 Rated OLMCPR(TLOl Exposure Range
't = 0.0 't = 1.0 BOC- MOC1 1.32 1.51 MOC1- MOC2 1.38 1.57 MOC2- EOC 1.41 1.60 FIGURE 3-4A-3 Rated-Power TLO MCPR Limits versus Average SCRAM Time (EOC-RPT System Inoperable) 23
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 1.70 1.70 1 .65 1.65 1.60 1.60 1.55 1.55
.'t:: .'t::
E 1.50 1.50 E
- J :J 0:: 0::
a.. a..
(,) (,)
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- E 1.40 1.40 1.35 1. 35 1.30 1.30
- 0. 0 0.2 0 .4 0 .6 0 .8 1.0 Rated OLMCPRtTLo)
Exposure Range
't = 0.0 't = 1.0 BOC- MOC1 1.38 1.56 MOC1- MOC2 1.44 1.62 MOC2- EOC 1.47 1.65 FIGURE 3-4A-4 Rated-Power TLO MCPR Limits versus Average SCRAM Time (Main Turbine Bypass System Inoperable
& EOC-RPT System Inoperable) 24
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 1.70 1.70 1.65 1.65 1.60 1.60 1
1.55 MOC2-EOC 1.55 I MOC1 E 1.50 - MOC2 1.50 E
- .J :.J 0::
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(.) (.)
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-' BOC- MOC1 1.45 :iE
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1.40 1.40 1.35 1.35 1.30 1.30 0 .0 0.2 0.4 0.6 0 .8 1.0 Rated OLMCPR(sLO)
Exposure Range
't = 0.0 't = 1.0 BOC- MOC1 1.40 1.47 MOC1- MOC2 1.40 1.49 MOC2- EOC 1.40 1.53 FIGURE 3-48-1 Rated-Power SLO MCPR Limits versus Average SCRAM Time 25
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 1.70 1.70 1.65 1.65 1.60 1.60 1 .55 1.55 E 1.50 1.50 E
- .J :.J 0:: 0::
Q. Q.
(.) (.)
Exposure Range
't = 0.0 't = 1.0 BOC- MOC1 1.40 1.52 MOC1- MOC2 1.40 1.55 MOC2- EOC 1.43 1.59 FIGURE 3-48-2 Rated-Power SLO MCPR Limits versus Average SCRAM Time (Main Turbine Bypass System Inoperable) 26
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 1.70 1.70 1.65 1-- - - - - - + - - - - - - + - - - - - - - --1 MOC2 -EOC 1.65 1.60 1.55 1.55
~ ~
E 1.50 1.50 .§
- .:i ..J 0::: 0:::
a.. a..
u u
- lE 1.45 1.45 :lE 1.40 1.35 1--- - - - - - + - - - - - - + - - - - - - + - - - - - - - t - - - - ---t 1.35 1.30 1.30 0.0 0 .2 0.4 0.6 0 .8 1.0 Rated OLMCPR(sLO)
Exposure Range
't = 0.0 't = 1.0 SOC - MOC1 1.40 1.54 MOC1- MOC2 1.41 1.60 MOC2- EOC 1.44 1.63 FIGURE 3-48-3 Rated-Power SLO MCPR Limits versus Average SCRAM Time (EOC-RPT System Inoperable) 27
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 1.70 1.65 1.60 1.55 1.55 E 1.50 1.50 E
- .:i :.:i a::: a:::
0.. 0..
u u
- !: 1.45 1.45 ::!:
1.40 1.35 1.30 L------'--------L------'--------'-----____J 1.30 0 .0 0.2 0.4 0.6 0 .8 1.0 Rated OLMCPR(sLOl Exposure Range
't = 0.0 't = 1.0 BOC- MOC1 1.41 1.59 MOC1- MOC2 1.47 1.65 MOC2- EOC 1.50 1.68 FIGURE 3-48-4 Rated-Power SLO MCPR Limits versus Average SCRAM Time (Main Turbine Bypass System Inoperable
& EOC-RPT System Inoperable) 28
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 4.0 LHGR OPERATING LIMITS (Technical Specification 3.2.3)
The LHGR operating limit for each licensed equipment in or out of service operating flexibility combination is independent of average scram time, and is a function of fuel bundle type, fuel rod type, core power, core flow, and pellet exposure.
For both two loop operation (TLO) and single loop operation (SLO) , the LHGR operating 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 4-1 multiplied by the smaller of either:
- a. The flow-dependent LHGR limit multiplier, LHGRFACF, as determined by Table 4-2 ,
- b. The power-dependent LHGR limit multiplier, LHGRFACP , as determined by Table 4-3 .
Table 4-1 shows the exposure-dependent LHGR limits for all fuel types in the core, as a function of initial gadolinium concentration in a six inch segment of a fuel rod . Figures 4-3A and 4-38 show the LHGR limits for both U02 fuel segments and for fuel segments with the highest initial Gd (Gd203) concentrations.
These limits apply to operation with vessel dome pressure within +/- 10 psi of nominal pressure ,
as defined by the Region I pressure band shown in Figure 5-1. With all equipment in service or with the EOC-RPT system inoperable, operation with vessel dome pressure down to 40 psi below nominal is licensed provided the additional restrictions identified in Section 5.0 are applied with the LHGR operating limit defined in this section .
29
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 TABLE 4-1 Rated-Power LHGR Limits versus Peak Pellet Exposure
((
))
30
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 TABLE 4-2 Flow-Dependent LHGRFACF Limit Multiplier Operating Flexibility Options Equipment In/Out of Service Fuel Type Main Turbine EOC-RPT Main Turbine Figure#
B~eass S~stem S~stem Pressure Reg,ulator Oeerable Oeerable S~stem Status Yes 4-1A GNF2 Yes/No TLCO 3.3.13.a, b, or c No 4-1 B GNF3 Yes/No Yes/No TLCO 3.3.13.a, b, or c 4-1C TABLE 4-3 Power-Dependent LHGRFACp Limit Multiplier Operating Flexibility Options Equipment In/Out of Service Fuel Type Main Turbine EOC-RPT Main Turbine Figure#
B~eass S~stem S~stem Pressure Regulator Oeerable Oeerable S~stem Status GNF2 Yes/No Yes/No TLCO 3.3.13.a, b, or c 4-2A GNF3 Yes/No Yes/No TLCO 3.3.13.a, b, or c 4-28 31
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1
/
1.000
~
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- 30. 0 40. 0 50. 0 60 .0 70 .0 80.0 90.0 100 .0 110 .0 Core Flow (%of Rated)
Flow (%of Rated) LHGRFACF (TLO/SLO) 30.0 0.557 50.0 0.795 80.0 0.998 90.0 1.000 110.0 1.000 FIGURE 4-1A GNF2 Flow-Dependent LHGR Limit Multiplier (LHGRFACF) versus Core Flow 32
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1
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0 .400 3 0.0 4 0. 0 50.0 60.0 70.0 80.0 9 0. 0 100 .0 11 0 .0 Core Flow(% of Rated)
Flow (%of Rated) LHGRFACF (TLO/SLO) 30.0 0.527 50.0 0.625 60.0 0.792 90 .0 0.993 100.0 1.000 110.0 1.000 FIGURE 4-18 GNF2 Flow-Dependent LHGR Limit Multiplier (LHGRFACF) versus Core Flow (Main Turbine Bypass System Inoperable) 33
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 u::
(.)
1.000 0.900 v
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0.400 3 0.0 40 . 0 50.0 6 0 .0 70. 0 80. 0 9 0.0 100.0 11 0 .0 Core Flow (%of Rated)
Flow (%of Rated) LHGRFACF (TLO/SLO) 30.0 0.572 40.0 0.683 50.0 0.772 60.0 0.863 70.0 0.930 80.0 0.998 90.0 1.000 110.0 1.000 FIGURE 4-1C GNF3 Flow-Dependent LHGR Limit Multiplier (LHGRFACF) versus Core Flow 34
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 I
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Power LHGRFACp
(%of Rated) (TLO/SLO) 24.0 0.460 s 28.0 0.470
> 28.0 0.624 45.0 0.713 60.0 0.740 85.0 0.922 100.0 1.000 FIGURE 4-2A GNF2 Power-Dependent LHGR Limit Multiplier (LHGRFACp) versus Core Power 35
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 v
1.000
- ./
v 0.
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24 .0 28 .0 Core Power(%ofRated)
Power LHGRFACp
(%of Rated) (TLO/SLO) 24.0 0.415
- 28.0 0.445
> 28.0 0.583 45.0 0.713 100.0 1.000 FIGURE 4-28 GNF3 Power-Dependent LHGR Limit Multiplier (LHGRFACp) versus Core Power 36
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1
((
))
FIGURE 4-3A GNF2 Rated-Power LHGR Limit versus Peak Pellet Exposure 37
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1
((
))
FIGURE 4-38 GNF3 Rated-Power LHGR Limit versus Peak Pellet Exposure 38
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 5.0 OPERATING PRESSURE LIMITS The operating limits presented within this report require that reactor dome pressure be maintained within the licensed pressure bands defined by Figure 5-1 . For operation in each of these regions, the following pressure dependent restrictions apply:
- a. For Region I operation :
The core operating limits from Sections 2.0 through 4.0 are applicable.
- b. For Region II and Region Ill operation :
- 1) The core operating limits from Sections 2.0 through 4.0 are applicable
- 2) The MFLCPR and MFLPD thermal limit ratios must remain below the maximum values determined by Table 5-1.
These restrictions are independent of core power, core flow, cycle exposure, feedwater temperature , the number of operating recirculation loops, and average scram time .
39
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 The MFLCPR and MFLPD thermal limit ratios are defined in terms of the core operating limits defined in Section 3.0 and Section 4.0.
The MFLCPR thermal limit ratio is the most limiting (maximum) value of the Fraction of Limiting Critical Power Ratio (FLCPR) in the core . The FLCPR is defined for each fuel assembly in the core as:
MCPRLimit FLCPR =
Fuel Assembly Minimum Critical Power Ratio where: MCPRLimit = MCPR operating limit defined in Section 3.0 The MFLPD thermal limit ratio is the most limiting (maximum) value of the Fraction of Limiting Power Density (FLPD) in the core. The FLPD is defined for each six inch axial segment of each fuel rod in the core as:
Peak kW/ft power generated in a fuel rod segment FLPD =
LHGRLimit where: LHGRLimit = LHGR operating limit defined in Section 4.0 40
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 1080 I
I I I
I T.S. 3.4.10Limit I
I
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------- ------- __ I l ___
1058 1058 1Q~5---
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I Pnom*20 960
.......... ~
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940 Pnom-40 I lr 920
- 20. 0 I 30. 0 40. 0 50.0 60.0 70. 0 80.0 90. 0 100 .0 24.0 Core Power(%of Rated)
P = A + 0.30
- CP + 0.0048
- CP 2 Dome Pressure Curves Core Power A Nominal Dome Pressure (Pnom) 24 S CPS 100 967 Region I Upper Boundary (P nom+ 1o) 24 ::; CP::; 1 00 977 Region I Lower Boundary (P nom- 10 ) 24::; CP :5100 957 Regi on II Lower Boundary (Pnom- 20 ) 24::; CP :51 00 947 Regi on Ill Lower Boundary (Pnom- 40 ) 24::; CP :5100 927 CP =Percent of Rated Core Power P =Reactor Dome Pressure (psi g)
FIGURE 5-1 Licensed Regions of Operating Dome Pressure versus Core Power 41
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1 TABLE 5-1 Pressure Dependent Operating Flexibility Options Equipment In/Out of Service Main Turbine Main Turbine Table#
EOC-RPT S~stem Bl!Qass Sj!stem Pressure Regulator 0Qerable 0Qerable S~stem Status Yes Yes/No TLCO 3.3.13.a orb 5-2 No Yes/No TLCO 3.3.13.a or b Reduced-Pressure Flexibility Option Not Licensed Yes/No Yes/No TLCO 3.3.13 .c TABLE 5-2 MFLCPR and MFLPD Limits versus Operating Pressure Regions Max Allowable Thermal Limit Ratio Operating Pressure Region MFLCPR Limit MFLPD Limit I 1.000 1.000 II 0.977 0.940 Ill 0.954 0.830 42
Plant Hatch Core Operating Limits Report Unit 1 Cycle 30 Non-Proprietary Information Version 1
6.0 REFERENCES
- 1. Global Nuclear Fuel Document NEDE-24011-P-A-28, "General Electric Standard Application for Reactor Fuel (GESTAR //) ,"September 2019, and the US Supplement, NEDE-24011-P-A-28-US , September 2019 .
- 2. Global Nuclear Fuel Document NEDC-33270P, "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR //),"Revision 9, December 2017.
- 3. Global Nuclear Fuel Document NEDC-33879P, "GNF3 Generic Compliance with NEDE-24011-P-A (GESTAR //) ,"Revision 2, March 2018.
- 4. Southern Nuclear Operating Company Document NFD-H-19-342, "Hatch-1 Cycle 30 Reload Licensing Analysis Report," Version 1.0, December 2019.
- 5. Global Nuclear Fuel Document 004N8412, "Supplemental Reload Licensing Report for Hatch 1 Reload 29 Cycle 30," Revision 0, December 2019.
- 6. Global Nuclear Fuel Document 004N8413, "Fuel Bundle Information Report for Hatch 1 Reload 29 Cycle 30," Revision 0, November 2019.
- 7. Global Nuclear Fuel Document 004N4841, "Technical Evaluation to Support Introduction of Partially ARMOR Coated Lead Test Rods (LTRs) in Four (4) GNF2 Reload Assemblies at Hatch Nuclear Plant, Unit 1," Revision 0, November 2017.
- 8. Global Nuclear Fuel Document 004N5426 , "Technical Evaluation to Support Introduction of GNF FeCrAI (ATF) Unfueled Lead Test Rods (L TRs) in Four (4) GNF2 Reload Assemblies at Hatch Nuclear Plant, Unit 1," Revision 0, November 2017.
- 9. Global Nuclear Fuel Document 005N4842-RO, "Application of ARMOR and IronClad LTA Technical Evaluations to Hatch 1, Beyond Cycle 29 ," Revision 0, November 2019.
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