L-17-044, Core Operating Limits Report for Operating Cycle 17
| ML17081A005 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 03/21/2017 |
| From: | Hamilton D FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-17-044 | |
| Download: ML17081A005 (24) | |
Text
FENOC Perry Nuclear Power Plant PO Box 97 10 Center Road FirstEnergy Nuclear Operating Company Perry- Ohl° 44081 David B. Hamilton ' 440-280-5382 Vice President March 21, 2017 L-17-044 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 Core Operating Limits Report for Operating Cycle 17 Enclosed is Revision 26 of the Core Operating Limits Report for the Perry Nuclear Power Plant (PNPP). This revision is submitted to the Nuclear Regulatory Commission (NRC) in accordance with PNPP Technical Specification 5.6.5, "Core Operating Limits Report (COLR)." A summary of the revision is on page 23 of the COLR.
There are no regulatory commitments contained in this submittal. If there are any questions or additional information is required, please contact Mr. Thomas A. Lentz, Manager - Fleet Licensing, at (330) 315-6810.
David B. Hamilton
Enclosure:
Core Operating Limits Report for the Perry Nuclear Power Plant Unit 1 Cycle 17 (Reload 16), Revision 26 cc: NRC Region III Administrator NRC Resident Inspector NRC Project Manager
Procedure Number-PERRY NUCLEAR POWER PLANT PDB-F0001
Title:
Use Category Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision Page 26 1 of 23 CORE OPERATING LIMITS REPORT FOR THE PERRY NUCLEAR POWER PLANT UNIT 1 CYCLE 17 (RELOAD 16)
Functional Location (J11)
Plant Data Book Effective Date: 3-9-17 Preparer: Pat Curran / 3-1-17 Date Approver: Paul Bordlev / 3-2-17 Date
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-F0001
Title:
Use Category Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision. Page
, 26 2 of 23 TABLE OF CONTENTS
1.0 INTRODUCTION
3
2.0 REFERENCES
4 3.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (T.S. 3.2.1) 6 4.0 MINIMUM CRITICAL POWER RATIO (T.S. 3.2.2) 9 5.0 LINEAR HEAT GENERATION RATE (T.S. 3.2.3) 20 6.0 REACTOR PROTECTION SYSTEM INSTRUMENTATION (T.S. 3.3.1.1) 23 7.0 OSCILLATION POWER RANGE MONITOR (OPRM)
INSTRUMENTATION (T.S. 3.3.1.3) 23 8.0 SCOPE OF REVISION 23
Procedure Number PERRY NUCLEAR POWER PLANT PDB-F0001 Titie- Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision- Page 26 3 of 23
1.0 INTRODUCTION
This Core Operating Limits Report (COLR) for the Perry Nuclear Power Plant (PNPP) Unit 1 Cycle 17 is prepared in accordance with the requirements of PNPP Technical Specification Administrative Control 5.6.5.
The core operating limits presented herein were determined using NRC-approved methods (Obligation 1 and Obligation 2). The core operating limits for the Global Nuclear Fuel (GNF) fuel in PNPP Unit 1 for Cycle 17 are documented in Obligations 3, 4, 5, 14, 16, and 17 and summarized herein for the following PNPP Unit 1 Technical Specifications:
- 1. Average Planar Linear Heat Generation Rate (APLHGR) Limits for each fuel/lattice type, including the power and flow dependent MAPFAC multipliers with the single loop MAPLHGR reduction factor. (Technical Specification 3.2.1)
- 2. Minimum Critical Power Ratio Operating Limit including the power and flow dependent MCPR curves for Two Loop Operation and Single Loop Operation. (Technical Specification 3.2.2)
Additional power dependent MCPR curves for Two Loop Operation and Single Loop Operation are provided for operation with one pressure regulator out of service.
- 3. Linear Heat Generation Rate (LHGR) Limits for each fuel/lattice type, including the power and flow dependent LHGRFAC curves with the single loop LHGRFAC reduction factor. (Technical Specification 3.2.3)
- 4. The simulated thermal power time constant. (Technical Specification 3.3.1.1, SR 3.3.1.1.14)
- 5. Oscillation Power Range Monitor (OPRM) Instrumentation.
(Technical Specification 3.3.1.3)
The oscillation power range monitor setpoint methods have been changed to NEDE-33766P-A, GEH Simplified Stability Solution (GS3). The GS3 methods are a generic approach to establishing the OPRM period - based detection algorithm setpoints. This generic approach assumes feedwater temperature reductions are limited to 120°F anytime during the cycle.
Procedure Number.
PERRY NUCLEAR POWER PLANT PDB-F0001
Title:
Use Category.
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision Page.
26 4 of 23 Cycle 17 (Reload 16) core design was developed assuming feedwater temperature reductions of 100°F during the cycle and 170°F beyond the end of the normal fuel cycle. Plant operations will be limited to 100°F during the cycle to account for the assumptions of the core design and 120°F beyond the end of the normal fuel cycle to account for the GS3 limitation.
Calculation FM-075, Support for the Core Operating Limits Report, details the development of the various graphs contained within this COLR.
2.0 REFERENCES
2.1 Discretionary None 2.2 Obligations
- 1. General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A-23, September 2016; and the US Supplement, NEDE-24011-P-A-23-US, September 2016
- 2. Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications, Licensing Topical Report, NEDO-32465-A, August 1996
- 3. Supplemental Reload Licensing Report for Perry 1 Reload 16 Cycle 17, GNF Document 002N6979, Revision 0, December 2016
- 4. Fuel Bundle Information Report for Perry 1 Reload 16 Cycle 17, GNF Document 002N6980, Revision 0, December 2016
- 6. Technical Specification 2.1.1.2, Safety Limit MCPR, Amendment No. 165
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-F0001 Titie- Use Category Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision. Page 26 5 of 23
- 7. Technical Specification 3.2.1, Average Planar Linear Heat Generation Rate, Amendment No. 112
- 8. Technical Specification 3.2.2, Minimum Critical Power Ratio, Amendment No. 112
- 9. Technical Specification 3.2.3, Linear Heat Generation Rate, Amendment No. 112
- 10. Technical Specification 3.3.1.1, Reactor Protection System Instrumentation (SR 3.3.1.1.14), Amendment No. 115
- 11. Technical Specification 3.3.1.3, OPRM Instrumentation (SR 3.3.1.3.3), Amendment 138
- 12. Technical Specification 5.6.5, Core Operating Limits Report, Amendment No. 136
- 13. Neutron Monitoring System Design Specification, 22A3739, Revision 6
- 14. Calculation FM-075, Support for the Core Operating Limits Report, Revision 4
- 15. FTI-B0012, Single Loop Operation
- 16. Tables D-2 (UO2) and D-4 (U,GdO2) of GEM Compliance with Amendment 22 of NEDE-24011-P-A, (GESTAR II), NEDC-32868P, Revision 6, March 2016, MFN 16-015, March 24, 2016.
- 17. Tables B-1 (UO2) and B-2 (U,GdO2) of GNF2 Advantage Generic Compliance with NEDE-24011-P-A, (GESTAR II), NEDC-33270P, Revision 7, October 2016, MFN 16-073, October 12, 2016.
- 18. Condition Report 2015-06018 - Use of GNF Provided Proprietary Information
- 19. NEDE-33766P-A, Revision 1 March 2015, GEH Simplified Stability Solution (GS3)
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-F0001 Title , Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision Page-26 6 of 23 Commitments addressed in this document:
None 3.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (T.S. 3.2.1)
All AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) shall not exceed the result obtained from multiplying the applicable MAPLHGR limit, Figure 3.2.1-1a GE14 Fuel Type or Figure 3.2.1-1b GNF2 Fuel Type, by the smaller of either the flow dependent MAPLHGR factor (MAPFACf) or the power dependent MAPLHGR factor (MAPFACp).
MAPLHGR Limits and MAPFACf and MAPFACp are defined in Obligation 3.
For Two Loop Operation, MAPFACf and MAPFACp are set equal to 1.0.
For Single Loop Operation, MAPFACf and MAPFACp are set equal to 0.8.
The Single Loop Operation limits take effect when reset for single loop operation per LCO 3.4.1,"Recirculation Loops Operating". This is consistent with note "(b)" to Table 3.3.1.1-1 of the Technical Specifications.
Use FTI-B0012 Single Loop Operation to implement the revised MAPLHGR Limits.
Procedure Number '
PERRY NUCLEAR POWER PLANT PDB-F0001 Title Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision- Page 26 7 of 23 Figure 3.2.1-1 a MAPLHGR Versus Average Planar Exposure Fuel Type: GE14 16 14 12 N
PERMISSIBLE REGION OF U_ 10 OPERATION N
o O 6 iy V
^^GE14 EOCS MAPLHGR Limit MAPLHGR = 12.82 for Exposures <= 19.13 MAPLHGR -12.82 + (-0.12526) * (Exposure -19.13) for 19.13 < Exposures <= 57.61 MAPLHGR = 8.00 + (-0.50934) * (Exposure - 57.61) for 57.61 < Exposures <= 63.50 5 10 15 20 25 30 35 40 45 50 55 60 65 70 Average Planar Exposure (GWD/ST)
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-F0001
Title:
Use Category.
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision1 Page 26 8 of 23 Figure 3.2.1-1b MAPLHGR Versus Average Planar Exposure Fuel Type: GNF2 16 14 s
\
12
\
\
PERMISSK REGION (
\
10 OPERATIl o
\
I 8 CO 8
LU 6 \
-^GNF2 ECCS MAPLHGR LIMIT MAPLHGR = 13.78 for Exposures <= 17.15 MAPLHGR =13.78 + (-0.15838) * (Exposure -17.15) for 17.15 < Exposures <= 60.78 MAPLHGR = 6.87 + (-0.50368) * (Exposure - 60.78) for 60.78 < Exposures <= 63.50 5 10 15 20 25 30 35 40 45 50 55 60 65 70 Average Planar Exposure (GWD/ST)
Procedure Number PERRY NUCLEAR POWER PLANT PDB-F0001 Title. Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision- Page:
26 9 of 23 4.0 MINIMUM CRITICAL POWER RATIO (T.S. 3.2.2)
The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than the higher of the flow dependent MCPR (MCPRf) and the power dependent MCPR (MCPRp) limits.
MCPR Limits along with MCPRf and MCPRp are defined in Obligations 3.
The MCPR Safety Limit for Cycle 17 for Two Loop Operation is 1.10 and the MCPR Safety Limit for Single Loop Operation is 1.13 <TECHNICAL SPECIFICATIONS 2.1.1.2>. Normally, the change in Safety Limit from Two Loop Operations to Single Loop Operations is accomplished by increasing the Cycle 17 MCPRf and MCPRp limits by 03.
In order to bound the Cycle 17 GNF2 Single Loop Operating - Pump Seizure Event, the delta CPR between Two Loop Operating and Single Loop Operating OL-MCPR was increased from 0.03 to 0.04. For Cycle 17 Single Loop Operating MCRPf and MCPRp Limits were developed by adding 0.04 delta CPR. 3DMONICORE PANACEA Version 11 uses this approach to calculate Single Loop Operation Limits.
The Single Loop Operation limits take effect when reset for single loop operation per LCO 3.4.1,"Recirculation Loops Operating". This is consistent with note "(b)" to Table 3.3.1.1-1 of the Technical Specifications.
Use FTI-B0012 Single Loop Operation to implement the revised MCPR Limits.
For Cycle 17, the Operating Limit MCPR is a function of the fuel type and exposure. Middle of Cycle (MOC) exposure point is defined as End of Rated (EOR) exposure point minus the Cycle Delta Exposure. For Cycle 17, the EOR exposure is defined in the Cycle 17 Cycle Management Report. For Cycle 17, the Cycle Delta Exposure is set to 2832 MWd/ST.
Thus, MOC is equal to EOR - 2832 MWd/ST.
Procedure Number PERRY NUCLEAR POWER PLANT PDB-F0001
Title:
Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision. Page:
26 10 of 23 The End of Rated (EOR) is defined as the cycle exposure corresponding to all rods out, 100% power /100% flow, and normal feedwater temperature.
As such, the EOR is a projection based on various assumptions such as how the previous cycle operated, current cycle operations, core loading changes during the refueling outage, inoperable control rods, suppressed fuel defects, etc. The projected EOR exposure point may have to be updated during the cycle to ensure the appropriate MCPR limits applied.
The changes in the EOR value are documented in supplements or revisions to the Cycle Management Report.
Two Loop Operating Limit MCPR is defined as:
Two Loop GE14 GNF2 OL-MCPR BOC to < MOC 1.32 1.34
> MOC to EOC 1.35 1.40 Single Loop Operating Limit MCPR is defined as:
Single Loop GE14 GNF2 OL-MCPR BOC to < MOC 1.36 1.38
> MOC to EOC 1.39 1.44 The flow dependent MCPRf is independent of fuel type and exposure. The Single Loop Operating MCPRf value is defined as Two Loop Operating MCPRf + 0.04.
MCPRf is depicted in the following figures:
Figure 3.2.2-1, Flow Dependent MCPR (MCPRf) -Two Loop Operation FuelType:GE14/GNF2 Figure 3.2.2-2, Flow Dependent MCPR (MCPRf) - Single Loop Operation Fuel Type: GE14/GNF2 When equal to or above 38% RTP, the power dependent MCPRp is dependent on the fuel type, exposure, and the variable KP:
MCPRp = Operating Limit MCPR (fuel type and exposure)
- Kp.
Procedure Number PERRY NUCLEAR POWER PLANT PDB-F0001 Title Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision- Page.
26 11 of 23 When below 38% RTP, MCPRp is independent of fuel type and exposure.
The Single Loop Operating MCPRp value is defined as Two Loop Operating MCPRp + 0.04.
Additionally, MCPRp is dependent on equipment status. Separate MCPRp figures are provided for the condition where all equipment is in service and for the condition where one pressure regulator is out of service.
MCPRp is depicted in the following figures:
Figure 3.2.2-3, Power Dependent MCPR Limit (MCPRp) - Two Loop Operation Equipment in Service Fuel Type:GE14/GNF2 Figure 3.2.2-4, Power Dependent MCPR Limit (MCPRp) - Single Loop Operation
.Equipment in Service Fuel Type: GE14/GNF2 Figure 3.2.2-5, Power Dependent MCPR Limit (MCPRp) - Two Loop Operation
' Pressure Regulator Out of Service Fuel Type: GEM/GNF2 Figure 3.2.2-6, Power Dependent MCPR Limit (MCPRp) - Single Loop Operation Pressure Regulator Out of Service Fuel Type: GE14/GNF2 For Cycle 17 no change to MCPR limits is required for planned reduction of feedwater temperature to as low as 325.5°F. Final feedwater temperature may be reduced to 305.5°F after all control rods are withdrawn at the end of cycle if the OPRMs are OPERABLE.
Planned reduction of rated feedwater temperature from nominal rated feedwater temperature is not permitted during plant operation with the reactor recirculation system in Single Loop Operation.
Procedure Number.
PERRY NUCLEAR POWER PLANT PDB-F0001 Title. i Use Category Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision" Page 26 12 of 23 The 3DMONICORE Computer software will automatically shift between 2 LOOP ON and ONE LOOP ON modes of operation on transfer to Single Loop Operations. As such the Safety Limit change will occur automatically. The guidance in FTI-B0012 can be used to verify proper functioning of the 3DMONICORE System. If the 3DMONICORE System is not functioning properly, FTI-B0012 will implement administrative limits until such time as 3DMONICORE is properly calculating MCPR values.
The 3DMONICORE Computer software will automatically shift the Operating Limit MCPR based on the MOC exposure point.
The 3DMONICORE Software will not automatically shift to the Pressure Regulator Out of Service Thermal Limits. The 3DMONICORE databank will be manually changed using a software change request. Until such time as 3DMONICORE databank is updated for the Pressure Regulator Out of Service Thermal Limits, an MFLCPR Administrative Limit will be issued to Operations. Figure 3.2.2-7 can be used as a guide in establishing the MFLCPR Administrative Limit. The graph is the ratio of MCPRp -
Equipment In Service to MCPRp - Pressure Regulator Out Of Service.
Figure 3.2.2-7 Maximum Fraction Limiting Critical Power Ratio Limit (MFLCPR) With One Pressure Regulator Out Of Service
Procedure Number PERRY NUCLEAR POWER PLANT PDB-F0001 Title Use Category Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision. Page.
26 13 of 23 Figure 3.2.2-1 Flow Dependent MCPR (MCPRf) - Two Loop Operation Fuel Type: GE14/GNF2 1.8 1.7
\
k O
Q.
o Q.
O O
I" 4
\ N\
PERMISSIBLE REGION OF OPERATION Ql o
MCPRf = MAX [1.30, 1.65-0.00714 (F-30.0)1 1.4 1.3
\
\ K lOLMCPR = 1.30 l 13.
20 40 GO 80 100 120 CORE FLOW (% RATED)
Procedure Number PERRY NUCLEAR POWER PLANT PDB-F0001
Title:
Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision. Page 26 14 of 23 Figure 3.2.2-2 Flow Dependent MCPR (MCPRf) - Single Loop Operation Fuel Type: GE14/GNF2 1.8 1.7
\
\
0)
Q.
O Q.
O o
PERMISSIBLE REGION OF
\
1.5 HUB MCPRf = MAX [1.34, O) OPERATION 1.69 - 0.00714 (F-30)]
v Q_
O 1.4
\
1.3
\
P OLMCPR=1.34 l 1 ?
20 40 60 80 100 120 CORE FLOW (% RATED)
Procedure Number.
PERRY NUCLEAR POWER PLANT PDB-F0001 Title. Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision Page-26 15 of 23 Figure 3.2.2-3 Power Dependent MCPR Limit (MCPRp) - Two Loop Operation Equipment In Service Fuel Type: GE14/GNF2 2.4 2.3 2.60 PERMISSIBLE 2.2 REGION OF OPERATION 2.1 2.40 MCPRp = 2.61 - 0.02817 (P - 23.8)
For 23.8% <= P < 38%; Core Flow > 50%
2.0 MCPRp = 2.41 - 0.02042 (P - 23.8) O For 23.8% <= P < 38%; Core Flow <= 50%
1.9 2.20 1.8 1.7 2.00 1.6 1.5 1.80 1.4 MCPRp = Kp
>/=MOCtoEOC 1.35 1.40 1.2 Core Flow <= 105%
1.1 Kp = 1.576 - 0.00975 (P - 38) 38% <= P <= 50% 1.40 Kp = 1.190 - 0.00320 (P - 50) 50% < P <= 60%
Kp = 1.158 - 0.00328 (P - 60) 60% < P <= 66.7%
1.0 Kp >> 1.115 - 0.00251 (P - 66.7) 66.7% < P <= 85%
Kp = 1.069 - 0.00460 (P - 85) 85% < P <= 100%
0.9 1.20 0.00 20.00 40.00 60.00 80.00 100.00 CORE THERMAL POWER (% RATED)
Procedure Number PERRY NUCLEAR POWER PLANT PDB.F0001 Titie- Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision' Page 26 16 of 23 Figure 3.2.2-4 Power Dependent MCPR Limit (MCPRp) - Single Loop Operation Equipment In Service Fuel Type: GE14 /GNF2 2.4 2.3 2.60 PERMISSIBLE REGION OF 2.2 OPERATION 2.1 MCPRp = 2.65 - 0.02817 (P - 23.8)
For 23.8% <= P < 38%; Core Flow > 50%
MCPRp = 2.45 - 0.02042 (P - 23.8)
For 23.8% <= P < 38%; Core Flow <= 50%
MCPRp = Kp
>/= MOC to EOC 1.39 1.44 Core Flow <= 105%
Kp = 1.576 - 0.00975 (P - 38) 38% <= P <= 50%
1.40 Kp = 1.190 - 0.00320 (P - 50) 50% < P <= 60%
Kp = 1.158 - 0.00328 (P - 60) 60% < P <= 66.7%
Kp = 1.115 - 0.00251 (P - 67.7) 66.7% < P <= 85%
Kp = 1.069 - 0.00460 (P - 85) 85% < P <= 100%
1.20 0.00 20.00 40.00 60.00 80.00 100.00 CORE THERMAL POWER (% RATED)
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-F0001 Titie- Use Category.
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision Page-26 17 of 23 Figure 3.2.2-5 Power Dependent MCPR Limit (MCPRp) - Two Loop Operation Pressure Regulator Out Of Service Fuel Type: GE14 / GNF2 2.60 PERMISSIBLE REGION OF OPERATION MCPRp = 2.61 - 0.02817 (P - 23.8)
For 23.8% <= P < 38%; Core Flow > 50%
MCPRp = 2.41 - 0.02042 (P - 23.8)
For 23.8% <= P < 38%; Core Flow <= 50%
MCPRp = Kp
>/= MOC to EOC 1.35 Core Flow <= 105%
Kp = 1.576 - 0.00831 (P - 38) 38% <= P <= 80.0%
Kp = 1.100 - 0.00500 (P - 80) 80% < P <= 100%
1.40 1.0 0.9 1.20 0.00 20.00 40.00 60.00 80.00 100.00 CORE THERMAL POWER (% RATED)
Procedure Number PERRY NUCLEAR POWER PLANT PDB-F0001 Title Use Category Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision Page-26 18 of 23 Figure 3.2.2-6 Power Dependent MCPR Limit (MCPRp) - Single Loop Operation Pressure Regulator Out Of Service Fuel Type: GE14/GNF2 2.60 PERMISSIBLE REGION OF OPERATION MCPRp = 2.65 - 0.02817 (P - 23.8)
For 23.8% <= P < 38%; Core Flow > 50%
MCPRp = 2.45 - 0.02042 (P - 23.8)
For 23.8% <= P < 38%; Core Flow <= 50%
MCPRp = Kp
>/= MOC to EOC 1.39 1.44 Core Flow <= 105%
Kp = 1.576 - 0.00831 (P - 38) 38% <= P <= 80%
Kp = 1.100 - 0.00500 (P - 80) 80% < P <= 100%
1.1 1.40 1.0 0.9 1.20 0.00 20.00 40.00 60.00 80.00 100.00 CORE THERMAL POWER (% RATED)
Procedure Number PERRY NUCLEAR POWER PLANT PDB-F0001
Title:
Use Category Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision Page 26 19 of 23 Figure 3.2.2-7 Maximum Fraction Limiting Critical Power Ratio Limit (MFLCPR)
With One Pressure Regulator Out Of Service Fuel Type GE14/GNF2 (23.8, 1.00D) l_l(ss 1000) (100, 1 000) 1.00D (85, 0994 l SB (50, 0988) (80,0.983) /
0.975 0.950 (0
o o
0.925 o
LJ_
0.900 or Q_
O
_l
' l (80, 0881)
/
LL 0.875 (66 7, 0849) l 0J&50
/
/V f
0.825 367, 0 834) l PERMISSIBLE REGION OF GSO, 0 806) / OPERATION 0.800 20 25 30 Z& 40 45 50 55 60 65 70 75 80 85 90 95 100 CORE THERMAL POWER {% RATED)
Procedure Number-PERRY NUCLEAR POWER PLANT PDB-F0001
Title:
Use Category.
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision Page 26 20 of 23 5.0 LINEAR HEAT GENERATION RATE (T.S. 3.2.3)
All LINEAR HEAT GENERATION RATES (LHGRs) shall not exceed the result obtained from multiplying the applicable LHGR limit by the smaller of either the flow dependent LHGR factor (LHGRFACf), Figure 3.2.3-1, or the power dependent LHGR factor (LHGRFACp) Figure 3.2.3-2.
LHGR Limits and LHGRFACf and LHGRFACp are defined in Obligations 3, 4, 16, and 17.
LHGR Limits for the GE14 Uranium only fuel pins and Gadolinia bearing fuel pins are listed in:
- Tables D-2 (UO2) and D-4 (U,GdO2) of "GE14 Compliance with Amendment 22 of NEDE-24011-P-A, (GESTAR II), NEDC-32868P",
Revision 6, March 2016.
LHGR Limits for the GNF2 Uranium only fuel pins and Gadolinia bearing fuel pins are listed in:
- Tables B-1 (UO2) and B-2 (U,GdO2) of "GNF2 Advantage Generic Compliance with NEDE-24011-P-A, (GESTAR II), NEDC-33270P",
Revision 7, October 2016.
For both GE14 and GNF2 Gadolinia bearing fuel pins, the maximum Gadolinia content of a fuel pin is 7 wt-% Gd2O3.
For Two Loop Operation, LHGRFACf and LHGRFACp shall not exceed 1.0.
For Single Loop Operation, LHGRFACf and LHGRFACp shall not exceed 0.8.
The Single Loop Operation limits take effect when reset for single loop operation per LCO 3.4.1,"Recirculation Loops Operating". This is consistent with note "(b)" to Table 3.3.1.1-1 of the Technical Specifications.
Use FTI-B0012 Single Loop Operation to implement the revised MAPLHGR Limits.
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-F0001 Titie- Use Category Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision: Page 26 21 of 23 Figure 3.2.3-1 Flow Dependent LHGR Factor (LHGRFACf)
Fuel Type: GE14 / GNF2 Clamped at 0.80 During SLO
= 0.544 + 0.00310 (F - 30) => 30% and < 40% flow
= 0.575 + 0.02020 (F - 40} => 40% and < 50% flow
= 0.777 + 0.00850 (F - 50) => 50% and < 60% flow
= 0.862 + 0.00680 (F - 60) => 60% and < 80% flow
= 0.998 + 0.00667 (F 80) => 80% and < 80.3% flow
= 1.0 => 80.3% and <= 107% flow 40 60 80 100 120 CORE FLOW {% RATED)
Procedure Number PERRY NUCLEAR POWER PLANT PDB-F0001
Title:
Use Category Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision: Page:
26 22 of 23 Figure 3.2.3-2 Power Dependent LHGR Factor (LHGRFACP)
Fuel Type: GE14 / GNF2 1.0 LHGRFACp 0.604 + 0.00507 (P- 23.8) =>23.8% and <38% power 0.9 : 0.676 + 0.00408 (P- 38) =>38% and <5O% power 0.725 4 0.00550 (P- 50) =>50% and <100% power 38%<= P<=10Q%; Core Flow <=105%
23.8%<=P<38%; Core Flow <=50%
a.
O 2 0*4-o Clamped at 0.80 During SLO 0.7 0.6 -
LHGRFACp= 0.57 +0.00211 (P-23.8) 23.8%<=P<18%; Core Flow >50%
0.5 20 40 60 80 100 CORE THERMAL POWER (% RATED)
Procedure Number PERRY NUCLEAR POWER PLANT PDB-F0001
Title:
Use Category Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 17 (Reload 16) Revision: Page:
26 23 of 23 6.0 REACTOR PROTECTION SYSTEM INSTRUMENTATION (T.S. 3.3.1.1)
The simulated thermal power time constant shall be 6 +/-0.6 seconds (Obligation 13).
7.0 OSCILLATION POWER RANGE MONITOR (OPRM) INSTRUMENTATION (T.S. 3.3.1.3)
OPRM setpoints for operable OPRMs:
- 1. Confirmation Count Setpoint (NP = N2): 16
- 2. Amplitude Setpoint (Sp): 1.15 (Obligation 3) 8.0 SCOPE OF REVISION Rev. 26 - Incorporate Operating Limits for Cycle 17:
- 1. The cycle number was updated from Cycle 16 to Cycle 17 and the reload number was updated from Reload 15 to Reload 16 as appropriate. The figure names were updated for consistency.
Revision bars are not included (for this change only).
- 3. Exposure dependent Operating Limit MCPRs were developed for Cycle 17.
- 4. MCPRp / Kp curves and the Single Loop MCPRt Curve were updated for the Cycle 17 specific analysis.
- 5. Due to the proprietary nature of the LHGR Limits, the LHGR limits were removed from the COLR. In place of the LHGR Curves references were added to point to the applicable GEH document.
- 6. Updated the revision levels of GE Documents identified in References 16 and 17. There were no changes to the LHGR Limits contained within these documents.
Note: For Cycle 17, there are no changes to MAPLHGR Limits, MAPFACt, MAPFACp, Safety Limit MCPR values, Two Loop MCPRf, LHGR Limits, LHGRFACf, LHGRFACp, OPRM Setpoints, or the Simulated Thermal Power Time Constant.