NMP1L3525, Core Operating Limits Report
| ML23111A070 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/19/2023 |
| From: | Shultz B Constellation Energy Generation |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NMP1L3525 | |
| Download: ML23111A070 (1) | |
Text
NMP1L3525 April 19, 2023 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-001
Subject:
Nine Mile Point Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-63 NRC Docket No. 50-220 Core Operating Limits Report Technical Specification 6.6.5 Enclosed is a copy of the Core Operating Limits Report, Revision 6, for Nine Mile Point Unit 1 Cycle 26. This report is being submitted pursuant to NMP1 Technical Specification 6.6.5.d.
Should you have any questions regarding the information in this submittal, please contact Mr.
Eric Kelsey at (315) 349-7037.
Sincerely, C Digitally signed by Shultz, Shultz, Brandon K!\\Brandon K..
1,/.. Date: 2023.04.19 00:20:28 -04'00' Brandon K. Shultz Mgr. Site Regulatory Assurance, Nine Mile Point Nuclear Station Exelon Generation Company, LLC
Enclosure:
Core Operating Limits Report, Revision 6 for Nine Mile Point Unit 1, Cycle 26 cc:
NRC Regional Administrator, Region I NRC Project Manager NRC Senior Resident Inspector
Enclosure Core Operating Limits Report, Revision 6 for Nine Mile Point Unit 1, Cycle 26
Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 Prepared By:
Reviewed By:
Reviewed By:
Reviewed By:
Approved By:
Station Qualified Review By:
CORE OPERATING LIMITS REPORT FOR NINE MILE POINT NUCLEAR STATION UNIT 1 RELOAD 27 CYCLE 26 Mcclure, Kelly 2023.03.17 15:42:10 -04'00' K. McClure NF Cycle Manager d
~ rngitally signed by Eastmond, Eastmon, Anrjt~in ti. Date: 2023.03.17 15:26:37 -05'00' A Eastmond lndependept Reviewer
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/>-Bate: 2023.03.20 21 :18:08 -04'00' ll' E. Kelsey Reactor Engineering Reviewer Ahmed Rah a i~igit~lly signed by ~h':1ed, R~ha,t 1
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R. Ahmed Engineering Safety Analysis Reviewer Digitally signed by Mccoskey, Kristin Date: 2023.03.21 16:20:26 -05'00' K. Mccoskey Senior Manager - NF Cycle Management
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Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 Table of Contents Section Title Page 1.0 Terms and Definitions 5
2.0 General Information 6
3.0 MAPLHGR Limits 7
4.0 MCPR Limits 8
5.0 LHGR Limits 10 6.0 Limiting Power I Flow Line 11 7.0 Modes of Operation 12 8.0 Methodology 13 9.0 References 14 Page 2 of 14
Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 Revision Record of COLR Nine Mile Point 1 Cycle 26 Revisions Description Rev. Number - 6 Initial Issuance for Cycle 26 Page 3 of 14
Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure - GNF2 7
Table 3-2 MAPLHGR Multiplier for Three Recirculation Loop Operation 7
Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) 8 Table 4-2 MCPR Adder for Three Recirculation Loop Operation 9
Table 4-3 Power Dependent MCPR Limits and Multipliers, MCPRP and KP 9
Table 4-4 Flow Dependent Operating Limit MCPR Multiplier, KF 9
Table 4-5 Safety Limit Minimum Critical Power Ratio (SLMCPR) 9 Table 5-1 Linear Heat Generation Rate Limits - U02 Rods 10 Table 5-2 Linear Heat Generation Rate Limits - Gadolinia Rods 10 Table 5-3 Power Dependent LHGR Multiplier LHGRFACp for PROOS 10 Table 7-1 Modes of Operation 12 List of Figures Figure 6-1 Limiting Power/Flow Line 11 Page 4 of 14
Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 1.0 Terms and Definitions App. Condition 1 App. Condition 2 App. Condition 3 APRM ARTS ELLLA EOOS EOR LHGR LHGRFACF LHGRFACp MAPFACF MAPFACp MAPLHGR MCPR MCPRp MDFWP OLMCPR PROOS RTP SLMCPR TDFWP Application (App) Condition 1 is defined as operation with one TDFWP in seNice OR one MDFWP in seNice.
Application (App) Condition 2 is defined as operation with one TDFWP in seNice AND one MDFWP in seNice. This bounds TDFWP in seNice OR one MDFWP in seNice OR two MDFWPs in seNice.
Application (App) Condition 3 is defined as operation with one TDFWP in seNice AND two MDFWPs in seNice.
Average Power Range Monitor APRM, Rod Block Monitor, and Technical Specification Improvement Program Extended Load Line Limit Analysis Equipment Out of SeNice End of Rated. The cycle exposure at which reactor power is equal to rated thermal power with recirculation system flow equal to 100%, all control rods fully withdrawn, all feedwater heating in seNice and equilibrium Xenon.
Off-rated flow dependent OLMCPR multiplier Off-rated power dependent OLMCPR multiplier Linear Heat Generation Rate Off-rated LHGR flow dependent thermal limit multiplier Off-rated LHGR power dependent thermal limit multiplier Off-rated flow dependent MAPLHGR multiplier Off-rated power dependent MAPLHGR multiplier Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio Off-rated power dependent OLMCPR Motor Driven Feedwater Pump Operating Limit Minimum Critical Power Ratio Pressure Regulator Out of SeNice Rated Thermal Power Safety Limit Minimum Critical Power Ratio Turbine Driven Feedwater Pump Page 5 of 14
Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 2.0 General Information This report provides the following cycle-specific parameter limits for Nine Mile Point Nuclear Station Unit 1 Cycle 26:
Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
MAPLHGR three recirculation loop operation multiplier Safety Limit Minimum Critical Power Ratio (SLMCPR)
Operating Limit Minimum Critical Power Ratio (OLMCPR)
Three recirculation loop operation MCPR adjustment MCPR thermal limit adjustments and multipliers (MCPRP, KP, KF)
Linear Heat Generation Rate (LHGR)
LHGR thermal limit multipliers (LHGRFACp)
Limiting Power/ Flow Line This report is prepared in accordance with Technical Specification 6.6.5 of Reference 1 Appendix A.
Power and flow dependent limits are listed for various power and flow levels. Linear interpolation is to be used to find intermediate values unless otherwise specified. Nine Mile Point Unit 1 is a non-ARTS plant that utilizes ELLLA operating domain.
The data presented in this report is valid for all licensed operating domains on the operating map, including:
Extended Load Line Limit down to the minimum licensed core flow (i.e., 85% of rated) during full power operation, Rated core flow of 67.5 Mlb/hr, Each mode supports operation with up to 10°F reduction in feedwater temperature.
Further information on the cycle-specific analyses for Nine Mile Point Unit 1 Cycle 26 and the associated operating domains discussed above is available in Reference 2.
Note that GNF and Nine Mile Point Unit 1 have different cycle numbering schemes. Cycle 26 is referred to as Cycle 28 in all GNF documentation.
Page 6 of 14
Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report for Nine Mile Point 1 Cycle 26 3.0 MAPLHGR Limits 3.1 Technical Specification 3.1.7.a, 3.1.7.e, 6.6.5.a.1 3.2 Description Doc ID: COLR Nine Mile Point 1, Rev. 6 The MAPLHGR limits for each bundle type as a function of average planar exposure is given in Table 3-1. For reduced loop operation, a fuel type dependent multiplier is used, which is shown in Table 3-2. For operation with three recirculation loops, in service, multiply the values shown in Table 3-1 by the GNF2 value in Table 3-2. No additional multiplier is required for operation with four recirculation loops in service.
The MAPLHGR limits in Table 3-1 provide adequate protection for off-rated conditions; therefore, MAPFACp and MAPFACF are equal to 1.0 for all power and flow conditions (Reference 6 - Section 2). LHGRFACp and LHGRFACF are addressed in Section 5.0.
Table 3-1 MAPLHGR Versus Average Planar Exposure-GNF21:
(Reference 2 - Section 16.3)
Average Planar Exposure MAPLHGR Limit1 (GWD/ST}
(kW/ft) 0.00 9.85 13.61 9.85 16.33 9.50 25.40 9.50 29.94 9.00 41.10 9.00 57.15 6.96 Table 3-2 MAPLHGR Multiplier for Three Recirculation Loop Operation (Reference 2 - Section 16.3)
Fuel Type Three Loop Operation Multiplier GNF2 1.00 1 MAPLHGR limits are fuel lattice independent.
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Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 4.0 MCPR Limits 4.1 Technical Specification 3.1.7.c, 3.1.7.e, 6.6.5.a.2, 6.6.5.a.3 4.2 Description The OLMCPR is determined for a given power and flow condition by evaluating the power dependent MCPR and the flow dependent MCPR and selecting the greater of the two. Tables 4-1 and 4-2 originate in Reference 2 and are valid for all operating domains.
The current cycle has two mid-cycle MCPR breakpoints, as defined in Table 4-1. Note that PROOS has no effect on the base OLMCPRs in Table 4-1; however, there are PROOS KP multipliers in Table4-3.
For three loop recirculation, the adder presented in Table 4-2 must be applied to all limits in Table 4-1 and MCPRp in Table 4-3.
The power dependent MCPR limits are presented in Table 4-3 and are valid.for all GNF2 bundles. Equal to or below 45% rated thermal power, the MCPRP limits in Table 4-3 are applied directly, with the adder from Table 4-2 as required; above 45% power, the KP multiplier is applied to the OLMCPR from Table 4-1 (and as affected by Table 4-2). The appropriate MCPRP or KP value may be determined by linear interpolation for statepoints not explicitly listed.
The flow adjusted OLMCPR is determined by multiplying the applicable rated condition OLMCPR provided by Table 4-1 (and as affected by Table 4-2) by the applicable KF multiplier given in Table 4-4. The appropriate KF value may be determined by linear interpolation.
Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)
(Four/Five Recirculation Loop Operation)
(Reference 2 - Section 11)
Cycle Exposure Feedwater Pump SCRAM Time
?! 5500 MWd/ST ?! EOR - 2213 Combination2,3 Option4
< 5500 MWd/ST and< EOR-2213 MWd/ST MWd/ST App. Condition 1 B
1.45 1.46 1.54 A
1.55 1.56 1.64 App. Condition 2 B
1.47 1.48 1.56 A
1.57 1.58 1.66 App. Condition 3 B
1.50 1.51 1.59 A
1.60 1.61 1.69 2 OLMCPR values are independent of pressure regulator in-service or out-of service conditions.
3 The OLM CPR values are based on the safety limit minimum critical power ratio (SLM CPR) values in Table 4-5.
4 For tau (r) :S 0, use SCRAM Time Option B limits. For (r) ~ 1, use SCRAM Time Option A limits. When tau is between O and 1, use linear interpolation in accordance with site procedure to calculate OLMCPR (Reference 3).
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Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 EOOS Table 4-2 MCPR Adder for Three Recirculation Loop Operation (Reference 2-Footnote 10)
Three Recirculation Loop Operation Adder Table 4-3 0.03 Power Dependent MCPR Limits and Multipliers, MCPRP and KP (Reference 2 - Appendix D)
Core Core Thermal Power (% of Rated)
Flow 0
25
- 45
> 45 65
- 85
> 85 100 Combination
(% of Operating Limit Operating Limit MCPR Multiplier, Kp rated)
MCPR, MCPRP App. Condition 1 App. Condition 2 App. Condition 3 PROOS5
< 60 3.25 3.25 2.32 1.349 1.216 1.133
~ 60 3.27 3.27 2.75
< 60 3.25 3.25 2.32 1.349 1.216 1.133
~ 60 3.27 3.27 2.75
< 60 3.25 3.25 2.32 1.349 1.216 1.133
~ 60 3.27 3.27 2.75
< 60 3.25 3.25 2.32 1.553 1.336 1.198
~ 60 3.27 3.27 2.75 Table 4-4 Flow Dependent Operating Limit MCPR Multiplier, KF (Reference 2 - Appendix D)
Flow MCPR
(% rated)
Multiplier, KF6 0.0 1.500
- 45_0 1.500
> 45.0 1.132 75.0 1.000 102.5 1.000 Table 4-5 Safety Limit Minimum Critical Power Ratio (SLMCPR)
(Reference 2 - Section 11) 1.133 1.133 1.133 1.133 Exposure Range Four or Five Loop Value Three Loop Value
< 5500 MWd/ST 1.09 1.12
~ 5500 MWd/ST 1.10 1.12 5 Limits apply to PROOS coincident with any Application Condition.
1.000 1.000 1.000 1.000 6 Values are applicable up to a Maximum Runout Flow of 102.5% of rated. Values apply to operation in all Application Conditions with or without Pressure Regulator in-service.
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Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 5.0 LHGR Limits 5.1 Technical Specification 3.1.7.b, 6.6.5.a.4 5.2 Description The Linear Heat Generation Rate for all fuel bundles shall not exceed the LHGR limits presented in Tables 5-1 and 5-2. Linear interpolation should be used as* directed in Appendix B of Reference 4. Power adjusted LHGR limits are required for operation with PROOS at greater than or equal to 45% RTP. Below 45% RTP, no addition.al limits are required. These power dependent LHGR multipliers (LHGRFACp) are provided in Table 5-3 for Option B and Option A scram times (Reference 2). The power adjusted LHGR is determined by multiplying the applicable LHGR limit by the LHGR multiplier, LHGRFACp.
The LHGRFACp curves are independent of recirculation loop operability. The appropriate LHGRFACp values may be determined by linear interpolation. Flow dependent LHGR multipliers (LHGRFACF) are not required (Reference 2).
Table 5-1 Linear Heat Generation Rate Limits - UO2 Rods (Reference 4 and 7)
FuelT e
LHGR GNF2 See Table 8-3 of Reference 4 Table 5-2 Linear Heat Generation Rate Limits - Gadolinia Rods (Reference 4 and 7)
FuelT e
LHGR GNF2 See Table 8-4 of Reference 4 Table 5-3 Power Dependent LHGR Multiplier LHGRFACP for PROOS (Reference 2 - Appendix D)
Scram Time Option Core Thermal Power (% of rated) 0
< 45
- 2:45 65 85 Option A (i.e. r > O) 1.000 1.000 0.518 0.518 0.636 Option B 1.000 1.000 0.737 0.867 0.987 Page 10 of 14 100 1.000 1.000
Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 6.0 Limiting Power/Flow Line 6.1 Technical Specification 3.1.7.d, 3.1.7.e, 6.6.5.a.5 6.2 Description The Nine Mile Point Unit 1 limiting power/flow relationship is shown in Figure 6-1.
120 100 "O
Cl)
~
i:i:::
80 0
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J...,
Cl) 60 0
i:l..
~
E J...,
Cl)
..c:
40 E-<
Cl)
J...,
0 u 20 0
0 Figure 6-1 Limiting Power/Flow Line (References 5 and 8)
~ ~
(85, 100)
~
~
Power= 0.55* W+53 20 40 60 80 Core Flow= W (% of Rated)
Page 11 of 14 (100, 100) 100 120
Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 7.0 Modes of Operation The allowable modes of operation are found in Table 7-1. Operation up to 67.5 Mlb/hr core flow is licensed for this cycle (Reference 2). The minimum coastdown thermal power level is40% perT.S. 3.1.7.h (Reference 1).
All EOOS options allow for operation in either Option A or Option B.
Each mode supports operation with up to 10°F reduction in feedwater temperature.
Each mode may be coincident with coastdown operation.
PROOS, Three-I PROOS, Three-I Table 7M1 Modes of Operation (Reference 2)
Options
. Condition 1 ondition 2 Allowed Operating Region Yes Yes Yes*
Yes Yes Yes Yes7 Yes7 Yes7 Yes7 Yes7 Yes7 7 Per Ref. I Appendix A TS 3.1.7.e, during three-loop operation power is restricted to 90% ofrated.
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Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report for Nine Mile Point 1 Cycle 26 8.0 Methodology 8.1 Technical Specification 6.6.5.b.1 8.2 Description Doc ID: COLR Nine Mile Point 1, Rev. 6 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document:
- 1. "General Electric Standard Application for Reactor Fuel," Global Nuclear Fuel Document No. NEDE-24011-P-A-31, November 2020 and U.S. Supplement NEDE-24011-P-A US, November 2020.
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Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 9.0 References
- 1. "Nine Mile Point Nuclear Station, Unit 1 Renewed Facility Operating License", Docket No. 50-220, License No. DPR-63 (through Amendment 247).
- 2. "Supplemental Reload Licensing Report for Nine Mile Point Unit 1 Reload 27 Cycle 28", Global Nuclear Fuel Document No. 006N9233, Rev. 0, January 2023.
- 3. "Engineering Report for Nine Mile Point Nuclear Station Unit 1 Reload 19", Global Nuclear Fuel Document No. 0000-0053-5247-ER, Rev. 1, March 2007. 8
- 4. "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)," Global Nuclear Fuel Document No. NEDC-33270P, Rev. 11, August 2020.
- 5. "Limiting Relationship Between Core Power and Core Flow Rate (TAC 63532)," NRC Letter, Nine Mile Point 1 Technical Specification Amendment 92 to Facility Operating License No. DPR-63, March 24, 1987 (NRC Accession Number ML010990453).
- 6. "Nine Mile Point Nuclear Station Unit 1 TRACG-LOCA Loss-of-Coolant Accident Analysis for GNF2 Fuel", GEH Nuclear Energy Document No. 002N3714, Rev. 0, March 2017.
- 7. "Fuel Bundle Information Report for Nine Mile Point Unit 1 Reload 27 Cycle 28", Global Nuclear Fuel Document No. 006N9234, Rev. 0, January 2023.
- 8. "Nine Mile Point 1 Cycle 24 Limiting Load Line Analysis," Global Nuclear Fuel Lette~, Document No. 002N5662-R0, March 18, 2015.
8 The information referenced from this report (see COLR Section 4.2 footnote 4) is cycle independent.
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