ML20115E362
| ML20115E362 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/21/2020 |
| From: | Shultz B Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NMP2L 2728 | |
| Download: ML20115E362 (24) | |
Text
,i&BYW Exelon Generation NMP2L 2728 April 21, 2020 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-001
Subject:
Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 NRC Docket No. 50-410 Core Operating Limits Report Technical Specification 5.6.5 Enclosed is a copy of the Core Operating Limits Report, Revision 5, for Nine Mile Point Unit 2, Cycle 18. This report is being submitted pursuant to NMP2 Technical Specification 5.6.5.d.
Should you have any questions regarding the information in this submittal, please contact Mr.
John Darweesh at (315) 349-7444.
Sincerely, Brandon K. Shultz Regulatory Assurance Manager, Nine Mile Point Nuclear Station Exelon Generation Company, LLC BKS/DJW
Enclosure:
Core Operating Limits Report, Revision 5, for Nine Mile Point Unit 2, Cycle 18 cc:
NRC Regional Administrator, Region I NRC Project Manager NRC Senior Resident Inspector
Enclosure Core Operating Limits Report, Revision 5 For Nine Mile Point Unit 2, Cycle 18
Exelon Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 5 CORE OPERA TING LIMITS REPORT FOR NINE MILE POINT UNIT 2 CYCLE 18 (This is a complete re-write; no revision bars are used)
Prepared By:
Ferheen Qureshi Preparer, Nuclear Fuels Reviewed By:
~
Megan.0oerzbacher Independent Reviewer, Nuclear Fuels Reviewed By:
Date:
3/1212020 Date: _31_1_21,_20_20 __
Date: 03/12/2020 Independent Reviewer, Engineering Safety Analysis Reviewed By:
Eric A. Kelsey Reviewer, Reactor Approved By: /hM- }1£~
Kristin C. McCoey Senior Manager, Nuclear Fuels SQRBy:
Page 1 of 22 Date: 3/ 1.2/:J(.),,2,D Date: 3/13/2020 Date: 3113/.;;ioJ.o
Exelon Generation - Nuclear Fuels Core Operating Limits Report Section Summary of Revisions List of Tables 1.0 Terms and Definitions 2.0 General Information 3.0 MAPLHGR Limits 4.0 MCPR Limits 5.0 LHGR Limits Table of Contents 6.0 Rod Block Monitor Setpoints 7.0 Turbine Bypass Valve Parameters 8.0 Modes of Operation 9.0 Stability Protection 10.0 Power Flow Operating Map 11.0 Methodology 12.0 References Appendix A Page 2 of 22 Document ID: COLR Nine Mile Point 2, Rev. 5 Page Number 3
4 5
7 8
9 13 15 16 17 18 19 19 20 21
Exelon Generation - Nuclear Fuels Core Operating Limits Report Revision Revision 5 Document ID: COLR Nine Mile Point 2, Rev. 5 Summary of Revisions Description New Issue for Cycle 18 Page 3 of 22
Exelon Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 5 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure 8
Table 3-2 MAPLHGR SLO Multiplier 8
Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) 10 Table 4-2 Power Dependent MCPR Limits (MCPRP) and Multipliers (KP) 11 Table 4-3 Flow Dependent MCPR Limits (MCPRF) for DLO 11 Table 4-4 Flow Dependent MCPR Limits (MCPRF) for SLO 11 Table 4-5 Cycle Specific SLMCPR (MCPR99.9%)
12 Table 5-1 LHGR Limits for U02 Fuel Rods 13 Table 5-2 LHGR Limits for Gadolinia Rods 13 Table 5-3 Power Dependent LHGR Multipliers (LHGRFACp) 14 Table 5-4 Flow Dependent LHGR Multipliers (LHGRFACF) 14 Table 6-1 Rod Block Monitor Setpoints 15 Table 6-2 ARTS RWE Validated MCPR Values 15 Table 7-1 Turbine Bypass Valve Response Time 16 Table 8-1 Modes of Operation 17 Table 8-2 EOOS Conditions Included under BASE Option 17 Table 9-1 BSP Endpoints for Normal Feedwater Temperature 18 Table 9-2 Automated BSP Setpoints 18 Page 4 of 22
Exelon Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 5 1.0 Terms and Definitions ADSOOS APLHGR APRM ARTS BSP COLR DLO ECCS EIS EOOS EOR EPU GEH GNF HFCL HTSP ICF INOP ITSP KP LCO LHGR LHGRFACF LHGRFACP LOCA LTSP MAPFACF MAPFACP MAPLHGR MCPR MCPR99.9%
MCPRF MCPRP MELLLA Automatic Depressurization System Out of Service Average Planar Linear Heat Generation Rate Average Power Range Monitor APRM and RBM Technical Specification Analysis Backup Stability Protection Core Operating Limits Report Dual Loop Operation Emergency Core Cooling System Equipment in Service Equipment Out of Service End of Rated. The cycle exposure at which reactor power is equal to 100% rated (3988 MWth), recirculation flow equal to 100% rated (108.5 Mlb/hr), and all control blades are fully withdrawn with equilibrium xenon.
Extended Power Uprate General Electric-Hitachi Global Nuclear Fuel High Flow Control Line High Trip Set Point (regarding RSM)
Increased Core Flow Inoperable Intermediate Trip Set Point (regarding RSM)
Off-rated power dependent OLMCPR multiplier Limiting Condition for Operation Linear Heat Generation Rate Off-rated flow dependent LHGR multiplier Off-rated power dependent LHGR multiplier Loss of Coolant Accident Low Trip Set Point (regarding RBM)
Off-rated flow dependent MAPLHGR multiplier Off-rated power dependent MAPLHGR multiplier Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio Limiting MCPR value such that 99.9 percent of the fuel in the core is not susceptible to boiling transition. Also known as the cycle-specific SLMCPR.
Off-rated flow dependent OLMCPR Off-rated power dependent OLMCPR Maximum Extended Load Line Limit Analysis Page 5 of 22
Exelon Generation - Nuclear Fuels Core Operating Limits Report MELLLA+
MSIVOOS NCL NRC OLMCPR OPRM PROOS RBM RDF RPTOOS RTP RWE SLMCPR SLO SRVOOS TBV TBVOOS TCV TCVOOS TS TSV TSVOOS Document ID: COLR Nine Mile Point 2, Rev. 5 Maximum Extended Load Line Limit Analysis Plus Main Steam Isolation Valve Out of Service Natural Circulation Line Nuclear Regulatory Commission Operating Limit MCPR Oscillation Power Range Monitor Pressure Regulator Out of Service Rod Block Monitor Recirculation Drive Flow Recirculation Pump Trip Out of Service; also known as EOC-RPT Rated Thermal Power (3988 MW1)
Rod Withdrawal Error Safety Limit MCPR Single Loop Operation Safety Relief Valve Out of Service Turbine Bypass Valve Turbine Bypass Valve Out of Service. TBVOOS supports 3 of 5 TBVs slow open and 2 of 5 TBVs do not slow open (stuck closed)
Turbine Control Valve Turbine Control Valve Out of Service Technical Specification Turbine Stop Valve Turbine Stop Valve Out of Service Page 6 of 22
Exelon Generation - Nuclear Fuels Core Operating Limits Report 2.0 General Information Document ID: COLR Nine Mile Point 2, Rev. 5 This report is prepared in accordance with Technical Specification (TS) 5.6.5 of Reference 1. Power and flow dependent limits are listed for various power and flow levels. Linear interpolation is to be used for intermediate values.
This report provides the values of the power distribution limits, control rod withdraw block instrumentation, and stability protection setpoints for Nine Mile Point Unit 2 Cycle 18.
This report provides the following cycle-specific parameter limits for Nine Mile Point Unit 2 Cycle 18 (Reload 17):
Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
Single Loop Operation (SLO) MAPLHGR multipliers Operating Limit Minimum Critical Power Ratio (OLMCPR)
ARTS MCPR thermal limit adjustments and multipliers Single Loop Operation (SLO) MCPR adjustment Linear Heat Generation Rate (LHGR)
ARTS LHGR thermal limit multipliers Single Loop Operation (SLO) LHGR multipliers Rod Block Monitor (RBM) Nominal Trip Setpoints, Allowable Values and MCPR Limits Turbine Bypass Valve (TBV) parameters Backup Stability Protection (BSP) parameters Cycle-specific SLMCPRs (MCPR99.9%)
The BASE thermal limit values shown in tables are for normal, equipment-in-service (EIS) two loop operation. Analysis also supports Increased Core Flow (ICF) for operational flexibility. Additional equipment out of service (EOOS) applicability can be found in Section 8.0, Modes of Operation.
The data presented in this report is valid for all licensed operating domains on the operating map, including (Reference 2):
Maximum Extended Load Line Limit Analysis Plus (MELLLA+) to a minimum core flow of 85% of rated.
ICF up to 105% rated (rated core flow is 108.5 Mlb/hr).
Extended Power Uprate (EPU) to 3988 MWth.
Coastdown operation down to 40% Rated Thermal Power (RTP)
Page 7 of 22
Exelon Generation - Nuclear Fuels Core Operating Limits Report 3.0 MAPLHGR Limits Document ID: COLR Nine Mile Point 2, Rev. 5 Technical Specification Sections 3.2.1, 3.4.1 The MAPLHGR limits obtained from the ECCS analysis are provided in Table 3-1. The limiting MAPLHGR value for the most limiting lattice of each fuel type as a function of exposure is given. For SLO, a multiplier is used as shown in Table 3-2.
The power and flow dependent LHGR multipliers are sufficient to provide adequate protection for the off-rated conditions from an ECCS-LOCA analysis perspective and there is no need for MAPLHGR multipliers, in addition to off-rated LHGR multipliers per Reference 2 - Section 16.
Table 3-1 MAPLHGR Versus Average Planar Exposure All Fuel Types (Reference 2 - Table 7)
Averaae Planar Exposure [GWD/ST]
MAPLHGR Limit [KW/ft]
0.00 17.15 60.78 63.50 Table 3-2 MAPLHGR SLO Multiplier All Fuel Types (Reference 2 - Table 8) 13.78 13.78 6.87 5.50 Fuel Type I
SLO Multiplier GNF2 0.78 Page 8 of 22
Exelon Generation - Nuclear Fuels Core Operating Limits Report 4.0 MCPR Limits Technical Specification Sections 3.2.2, 3.3.4.1, 3.4.1, 3. 7.5 Document ID: COLR Nine Mile Point 2, Rev. 5 OLMCPR values listed in Table 4-1 cover all conditions listed in Section 8.0, Modes of Operation.
Additional EOOS information can be found in Section 8.0. ARTS provides for power and flow dependent thermal limits adjustments, which allow for a more reliable administration of the MCPR thermal limit. Per TS 3.2.2, all MCPR's shall be verified in accordance with limits specified in this section.
Control rod scram time verification is also required per TS 3.1.4, Control Rod Scram Times. The applicable MCPR thermal limit set shall be determined with Tau (r), a measure of scram time performance throughout the cycle based on the cumulative plant scram time test results. The calculation of Tau shall be performed in accordance with site procedures.
ARTS power and flow dependent thermal limits have been confirmed for the following modes of operation: Base, Turbine Bypass Valves Out-Of-Service (TBVOOS), Recirculation Pump Trip Out-Of-Service (RPTOOS) and Pressure Regulator Out-Of-Service (PROOS).
The cycle-specific SLMCPRs, known as MCPR99.9%, can be found in Table 4-5 for dual loop and single loop operating conditions. The values in Table 4-5 or conservative values were used to calculate the MCPR limits and off-rated limits in this section.
Page 9 of 22
Exelon Generation - Nuclear Fuels Core Operating Limits Report Table 4-1 Document ID: COLR Nine Mile Point 2, Rev. 5 Operating Limit Minimum Critical Power Ratio (OLMCPR)
All Fuel Types (Reference 2 - Section 11)
EOOS Combination SCRAM Time Cycle Exposure Option1
<EOR-3414 MWD/ST
- EOR-3414 MWD/ST BASE A
1.62 1.69 B
1.46 1.49 BASE SLO A
1.65 1.72 B
1.49 1.52 TBVOOS A
1.75 1.75 B
1.78 1.78 B
1.55 1.55 RPTOOS A
1.68 1.73 B
1.46 1.49 RPTOOS SLO A
1.71 1.76 B
1.49 1.52 PROOS A
1.62 1.69 B
1.46 1.49 1 For tau (r) = 0, use SCRAM Time Option 8 limits. For (r) = 1, use SCRAM Time Option A limits. When tau does not equal O or 1, use linear interpolation in accordance with site proced1.Jre to calculate OLMCPR.
Page 10 of 22
Exelon Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 5 Table 4-2 Power Dependent MCPR Limits (MCPRP) and Multipliers (KP)
All Fuel Types (Reference 2 -Appendix D)
Core Thermal Power [% of rated]
EOOS Combination Core Flow 0
23 S26
>26 55 60 85 100
[% of rated]
Operating Limit Operating Limit MCPR Multiplier (KP)
BASE BASE SLO TBVOOS TBVOOS SLO RPTOOS RPTOOS SLO PROOS MCPRP
.::75 1:.,,**','
l*t :..
<75 2.65 2.65 2.57 1.218 1.180
.::75
<75 2.68 2.68 2.60 1.218 1.180
.::75 1.218 1.180
<75 3.51 3.51 3.22
.::75 1.218 1.180
<75 3.54 3.54 3.25
.::75
<75 2.65 2.65 2.57 1.218 1.180
.::75
<75 2.68 2.68 2.60 1.218 1.180
.::75 r
<75 2.65 2.65 2.57 1.218 1.180 Table 4-3 Flow Dependent MCPR Limits (MCPRF) for DLO All Fuel Types (Reference 2 - Appendix D)
Flow [% rated]
MCPRF Limit 0.0 2.01 30.0 1.78 94.2 1.29 112.0 1.29 Table 4-4 Flow Dependent MCPR Limits (MCPRF) for SLO All Fuel Types (Reference 2 - Appendix D)
Flow [% rated]
MCPRF Limit 0.0 2.04 30.0 1.81 94.2 1.32 112.0 1.32 Page 11 of 22 1.150 1.056 1.000 1.150 1.056 1.000 1.150 1.056 1.000 1.150 1.056 1.000 1.150 1.056 1.000 1.150 1.056 1.000 1.172 1.056 1.000
Exelon Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 5 Table 4-5 Cycle Specific SLMCPR (MCPR99.9%)
(Reference 2 - Section 11)
Flow Mode MCPR99.9%
DLO 1.14 SLO 1.14 Page 12 of 22
Exelon Generation - Nuclear Fuels Core Operating Limits Report 5.0 LHGR Limits Document ID: COLR Nine Mile Point 2, Rev. 5 Technical Specification Section 3.2.3 The LHGR limit is the product of the exposure dependent LHGR limit and the minimum of the LHGRFACp or the LHGRFACF.
The off-rated limits assumed in the ECCS-LOCA analyses are confirmed to be consistent with the cycle-specific off-rated LHGR multipliers calculated for MELLLA+ operation. The off-rated LHGR multipliers provide adequate protection for MELLLA+ operation (Reference 2).
Table 5-1 LHGR Limits for U02 Fuel Rods Reference 3, Reference 5, Reference 11 GNF2 See Reference 5 Table 5-2 LHGR Limits for Gadolinia Rods Reference 3, Reference 5, Reference 11 GNF2 See Reference 5 Page 13 of 22
Exelon Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 5 Table 5-3 Power Dependent LHGR Multipliers (LHGRFACp)
All Fuels Types (Reference 2 -Appendix D)
EOOS Core Flow[%
Core Thermal Power [% of rated Combination BASE BASE SLO TBVOOS TBVOOS SLO RPTOOS RPTOOS SLO PROOS EOOS Condition DLO SLO of rated]
0 23 S26
>26 55
.::75 0.613 0.720
<75 0.495 0.495 0.502
.::75
, '"'\\
0.613 0.720
<75 0.495 0.495 0.502
.::75
<75 0.475 0.475 0.502 0.613 0.720
.::75
~
<75 0.475 0.475 0.502 0.613 0.720
.::75
<75 0.495 0.495 0.502 0.613 0.720
.::75
'.* 0.613 0.720
<75 0.495 0.495 0.502
.::75 0.613 0.720
<75 0.495 0.495 0.502 Table 5-4 Flow Dependent LHGR Multipliers (LHGRFACF)
All Fuel Types and Modes of Operation (Reference 2 - Appendix D)
Core Flow % of rated 0
30 40 52.7 0.241 0.580 0.693
- '*' *,,.,),'.. : '
0.241 0.580 0.693 0.780 Page 14 of 22 60 0.791 0.791 0.791 0.791 0.791 0.791 0.740 85 1.000 0.780 85 100 0.922 1.000 0.922 1.000 0.922 1.000 0.922 1.000 0.922 1.000 0.922 1.000 0.831 1.000 112 1.000 0.780
Exelon Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 5 6.0 Rod Block Monitor Setpoints Technical Specification Section 3.3.2.1 Per Technical Specifications 3.3.2.1, the RBM instrumentation channels will be operable with the allowable values set to the values shown in Table 6-1. The values given in Table 6-1 are unfiltered; these unfiltered values are applicable as the time filter constant is set to zero. (Reference 7 - Table 58). The RBM operability requirements have been evaluated and shown to be sufficient to ensure that the cycle specific SLMCPR and cladding 1% plastic strain criteria will not be exceeded in the event of a Rod Withdrawal Error.
The ARTS RWE analysis validated the MCPR values in Table 6-2 below for use in Cycle 18. The RWE MCPR values have been analyzed at discrete setpoint values and unblocked (continuous withdrawal) conditions.
Table 6-1 Rod Block Monitor Setpoints2 (Reference 2 - Section 10, Reference 8 - Section 3 Power Level Allowable Value Nominal Trip Setpoint Analytical Limit LTSP 121.6%
121.2%
124.0%
ITSP 116.6%
116.2%
119.0%
HTSP 111.6%
111.2%
114.0%
Table 6-2 ARTS RWE Validated MCPR Values (Reference 2 - Section 10)
Power Level [% Rated]
<90%
~1.81
~90%
~1.49 2 See Reference 8 for filtered values.
Page 15 of 22
Exelon Generation - Nuclear Fuels Core Operating Limits Report 7.0 Turbine Bypass Valve Parameters Technical Specification Section 3.7.5 Document ID: COLR Nine Mile Point 2, Rev. 5 Per Technical Specification LCO 3.7.5, whenever the reactor power is at or above 23% RTP the main turbine bypass system shall be operable or the plant must operate with the TBVOOS penalties.
The definition of operable is given in Table 7-1 below.
Table 7-1 Turbine Bypass Valve Response Time
{Reference 9 - Section 1.6)
Event Response Time [sec]
Maximum delay time before start of bypass valve opening following initial turbine inlet 0.15 valve movement Maximum time after initial turbine inlet valve movement for bypass valve position to 0.30 reach 80% of full flow (includes the above delay time)
Page 16 of 22
Exelon Generation - Nuclear Fuels Core Operating Limits Report 8.0 Modes of Operation Document ID: COLR Nine Mile Point 2, Rev. 5 The following conditions are supported by the Cycle 18 licensing analysis; operation in a condition (or conditions) is controlled by station procedures. If a combination of options is not listed, it is not supported. Table 8-1 provides allowed modes of operation with thermal limit sets in the COLR. Table 8-2 provides allowed modes of operation that do not contain explicit thermal limit sets but are included in the BASE option. Note that per TS LCO 3.4.1, SLO in the MELLLA or MELLLA+ domains is prohibited.
Table 8-1 Modes of Operation (Reference 2, Reference 10, Reference 12)
Options3 Allowed Operating Region BASE Yes BASE SLO Yes TBVOOS7 Yes TBVOOS SL07 Yes RPTOOS Yes RPTOOS SLO Yes PROOS Yes Table 8-2 EOOS Conditions Included under BASE Option (Reference 2, Reference 13)
EOOS Condition4 SRVOOS ADSOOS MS1VOOS5 TCV/TSVOOS6* 7 3 The EOOS Options listed apply to both Option A and Option B 4 Base includes 2 SRVOOS, 1 MSIVOOS (limited to 75% power), 1 TCVfrSVOOS (limited to 85% power), and 1 ADSOOS.
5 1 MSIVOOS limited to 75% rated thermal power 6 1 Tcvrrsvoos limited to 85% rated thermal power.
7 TCV/TSVOOS not analyzed concurrent with TBVOOS Page 17 of 22
Exelon Generation - Nuclear Fuels Core Operating Limits Report 9.0 Stability Protection Technical Specification Section 3.3.1.1 Document ID: COLR Nine Mile Point 2, Rev. 5 The OPRM Amplitude Discriminator Setpoint (SAo) is 1.10 (Reference 2 - Section 15.1). Results have been validated with rated feedwater temperature.:: 420.5°F as described by Reference 2. Per TS 5.6.5.a.4, the Backup Stability Protection (BSP) regions and values are as shown below in Tables 9-1 and 9-2. The manual BSP region boundary endpoints are connected using the Generic Shape Function. A graphical representation of the BSP regions can be found in Reference 2 - Figure 1.
Table 9-1 BSP Endpoints for Normal Feedwater Temperature8*9 Reference 2 - Table 3)
Endpoint Power Flow Definition
[% of rated]
[% of rated]
A1 69.1 43.6 Scram Region Boundary, HFCL B1 39.7 29.5 Scram Region Boundary, NCL A2 64.5 50.0 Controlled Entry Region Boundary, HFCL 82 27.5 28.9 Controlled Entry Region Boundary, NCL A3 100.0 88.3 BSP Boundary Intercept, HFCL 83 68.7 55.0 Table 9-2 Automated BSP Setpoints10 (Reference 2 - Table 4)
Parameter Symbol Slope of Automated BSP APRM flow-biased mTRJP trip linear seoment Automated BSP APRM flow-biased trip setpoint power intercept. Constant Power PssP-TRJP Line for Trip from zero Drive Flow to Flow Breakpoint value.
Automated BSP APRM flow-biased trip setpoint drive flow intercept. Constant Flow WssP-TRJP Line for Trip.
Flow Breakpoint value WssP-BREAK 8 Bounding for both DLO and SLO BSP Boundary Intercept, MELLLA Boundary Value 1.26 39.7% RTP 36.9% RDF 19.2% RDF 9 Station may elect to place additional administrative margin on the endpoints provided in Table 9-1 10 Applicable to both DLO and SLO Page 18 of 22
Exelon Generation - Nuclear Fuels Core Operating Limits Report 10.0 Power Flow Operating Map See Appendix A for a Power Flow Map (Reference 6).
11.0 Methodology Document ID: COLR Nine Mile Point 2, Rev. 5 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the Nuclear Regulatory Commission, particularly those described in the following documents:
- 1.
"General Electric Standard Application for Reactor Fuel (GEST AR II) (Supplement for United States)", NEDE-24011-P-A-29-US, October 2019.
Page 19 of 22
Exelon Generation - Nuclear Fuels Core Operating Limits Report 12.0 References Document ID: COLR Nine Mile Point 2, Rev. 5
- 1. "Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License", Exelon Document, Docket No. 50-410, Renewed License No. NPF-69.
- 2. "Supplemental Reload Licensing Report for Nine Mile Point Unit 2 Reload 17 Cycle 18", Global Nuclear Fuel Document, No. 004N8624, Revision 0, January 2020.
- 3. "Fuel Bundle Information Report for Nine Mile Point Unit 2 Reload 17 Cycle 18", GNF Document, No. 004N8625, Revision 0, January 2020.
- 4. "Nine Mile Point Unit 2 Revised TMOL Application Evaluation" Global Nuclear Fuel Document, No 005N5463, Revision 0, January 2020.
- 5.
"Revised GNF2 Thermal Mechanical Operating Limits for Nine Mile Point Unit 2" Global Nuclear Fuel Document, No 005N5546, Revision 1, January 2020.
- 6. "Safety Analysis Report for Nine Mile Point Unit 2 Maximum Extended Load Line Limit Analysis Plus", GEH Document, No. NEDC-33576P, Revision 0, October 2013.
- 7. "Revise 22A2843AM", Engineering Change Notice for NSSS161405000 "Design Spec Data Sheet, Neutron Monitoring System", Exelon Document, No. 007242, Revision 1, April 2008.
- 8. "Instrumentation Limits Calculation Constellation Generation Group Nine Mile Point Nuclear Station Unit 2 Rod Block Monitor (NUMAC ARTS-MELLLA)", GEH Document, No. 0000-0053-1006 NMP2 A-M-T506-RBM-Calc-2006, Revision 1, March 2008.
- 9. "Final resolved OPL-3 parameters for NMP2 C18", Exelon Document, ENSAF ID No.
ES1900009, Revision 0, September 2019.
- 10. "Nine Mile Point 2 GNF2 NFI T0900 Coincident Equipment Out-of-Service (EOOS) Report",
GEH Document, No. 003N2077-RO Revision 0, February 2016.Searchable in FCMS as 003N2077.
- 11. "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GEST AR II)", GNF Document, No. NEDC-33270P, Revision 9, December 2017.
- 12. "GNF2 Fuel Design Cycle-Independent Analyses for Exelon Nine Mile Point Nuclear Station Unit 2", GEH Document, No. 003N2003 Revision 5, August 2019.
004N0521-RO, September 2017.
- 14. "Removal of Generic ARTS Rated RWE DCPR for Limerick Units 1 and 2, Nine Mile Point Unit 2, and Peach Bottom Units 2 and 3," General Electric Hitachi Nuclear Energy Document No.
005N2836-RO, Revision 0, July 2019.
Page 20 of 22
Exelon Generation - Nuclear Fuels Core Operating Limits Report Appendix A Page 21 of 22 Document ID: COLR Nine Mile Point 2, Rev. 5
Exelon Generation - Nuclear Fuels Core Operating Limits Report 0
10 20 Ill 110 100 tlO to
- t.. I..
- l.
i 40 JG 20 10 10 c... n-oa-k, JO 40 50 70 NILLLA*...._
Ld lffllc,-,s,...
/Bo.KVilbllhl.
J so 70 C-flew~)
Document ID: COLR Nine Mile Point 2, Rev. 5 too llO l:IO IJO
,soo
,...1111, 4000 JWllllt
)SOO ICf JGIIO =
- J C 1'901 lCIIIO l i 1500 1000 soo 0
'° 100 110 n*
Power/Flow Operating Map for MELLLA+ in Dual Loop Operation (Reference 6)
Page 22 of 22