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{{#Wiki_filter:a.EWExelon Generation April 24, | {{#Wiki_filter:a.EWExelon Generation April 24, 2014 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: | ||
==SUBJECT:== | ==SUBJECT:== | ||
Document Control | Document Control Desk Nine Mile Point Nuclear Station Renewed Facility Operating License No. NPF-69 Unit No. 2; Docket No. 50-410 Core Operating Limits Report Enclosed is a copy of the Core Operating Limits Report, COLR2-15, Revision 0 for Nine Mile Point Unit 2 (NMP2). 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 Everett P.Perkins, Director -Licensing, at (315) 349-5219.Very truly yours, Paul M. Swift Manager, Engineering Services PMS/MHS | ||
-Licensing, at (315) 349-5219. | |||
Very truly yours,Paul M. | |||
==Enclosure:== | ==Enclosure:== | ||
Nine Mile Point Unit 2 Core Operating Limits | Nine Mile Point Unit 2 Core Operating Limits Report cc: NRC Regional Administrator, Region I NRC Project Manager NRC Senior Resident Inspector AOD( | ||
ENCLOSURE Nine Mile Point Unit | ENCLOSURE Nine Mile Point Unit 2 Core Operating Limits Report Nine Mile Point Nuclear Station, LLC April 24, 2014 NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT COLR2715 Revision 0, Cycle 15 Prepared by.Name Melisa Kriek Title Fuels Engineer Date Reviewed by: Approved by: Approved by: Approved by: Fuels Engineer Supervisor, Reactor Engineer John Darweessh 3/ /.Y//` V/ I Supervisor, Fuels iPhil Weyoski General Supervisor, Fuels This controlled document provides cycle specific core operating limits for use in conjunction with the Nine Mile Point Unit 2 Technical Specifications. | ||
Document pages may only be changed through | Document pages may only be changed through a reissue of the entire document. | ||
COLR2-15 NINE MILE POINT UNIT 2 Revision 0, Cycle | COLR2-15 NINE MILE POINT UNIT 2 Revision 0, Cycle 15 CORE OPERATING LIMITS REPORT TABLE OF CONTENTS page 1.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 1 1.1 Limits for Technical Specification 3.2.1 1 2.0 MINIMUM CRITICAL POWER RATIO (OPTION B) 3 2.1 Limits for Technical Specification 3.2.2 3 2.2 Notes 4 3.0 LINEAR HEAT GENERATION RATE (LHGR) 12 3.1 Limits for Technical Specifications 3.2.3 12 4.0 AVERAGE POWER RANGE MONITOR SETPOINTS 17 4.1 Limits for Technical Specification Table 3.3.1.1-1 (OPRM Upscale) 17 5.0 CONTROL ROD BLOCK INSTRUMENTATION 18 5.1 Allowable Value for Technical Specification Table 3.3.2.1-1 18 | ||
== | ==6.0 REFERENCES== | ||
FOR TECHNICAL SPECIFICATIONS | FOR TECHNICAL SPECIFICATIONS 19 | ||
== | ==7.0 REFERENCES== | ||
FOR TECHNICAL SPECIFICATION BASES | FOR TECHNICAL SPECIFICATION BASES 20 8.0 SOURCE DOCUMENTS 21 Page i COLR2-15 NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT Revision 0,'Cycle 15 1.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)1.1 Limits for Technical Specification 3.2.1 The APLHGR(s) for each fuel type as a function of Average Planar Exposure shall not exceed the limits shown in Table 1.The limits of Table 1 shall be reduced to a value of 0.78 times the two recirculation loop operation limit when in single recirculation loop operation. | ||
Page 1 of 21 COLR2- | Page 1 of 21 COLR2-15 NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT Revision 0, Cycle 15 Table 1 MAPLHGR versus Average Planar Exposure Average Planar Exposure MAPLHGR Limits (GWD/ST) (KW/ft)0.00 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 5.00 NOTES: 1. APLHGR(s) are interpolated between exposure points for which explicit values are given Page 2 of 21 COLR2-15 NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT Revision 0, Cycle 15 2.0 MINIMUM CRITICAL POWER RATIO (OPTION B).2.1 Limits for Technical Specification 3.2.2 The Minimum Critical Power Ratio (MCPR) shall be greater than or equal to the Operating Limit MCPR (OLMCPR) for Two-Loop or Single-Loop Operation (Table 2).OLMCPR = maximum[MCPR(P), MCPR(F)]where, MCPR(P) = Applicable core power dependent MCPR (Fig. 2c, 2d, 2e, or 2f)MCPR(F) = Flow rate dependent MCPR (Fig. 2g)Table 2 Minimum Critical Power Ratio Two Recirculation Loop Operation (TLO) Condition MCPR(P) = OLMCPR( 100) x K(P) P(bypass) | ||
(KW/ft)0.00 12. | < P < 100%or MCPR(P) = MCPR(P) 23% < P < P(bypass)MCPR(F) = MCPR(F) F > 30%Single Recirculation Loop Operation (SLO) Condition MCPR(P) = 0.02 + OLMCPR( 100) x K(P) P(bypass) | ||
MCPR(F)]where, MCPR(P) = Applicable core power dependent MCPR (Fig. 2c, 2d, 2e, or 2f)MCPR(F) = Flow rate dependent MCPR (Fig. 2g)Table | < P < 100%or MCPR(P) = 0.02 + MCPR(P) 23% < P < P(bypass)MCPR(F) = 0.02 + MCPR(F) F 30%Note: 1) OLMCPR(100) | ||
< P < 100% | |||
MCPR(F) = MCPR(F) F > 30%Single Recirculation Loop Operation (SLO) Condition MCPR(P) = 0.02 + OLMCPR( 100) x K(P) P(bypass) | |||
< P < 100% | |||
MCPR(F) = 0.02 + MCPR(F) F 30%Note: 1) OLMCPR(100) | |||
-Applicable OLMCPR for rated core power and flow conditions (Figure 2a or 2b)2) K(P) = Applicable core power dependent OLMCPR multiplier (Figure 2c, 2d, 2e, or 2f)3) P(bypass) | -Applicable OLMCPR for rated core power and flow conditions (Figure 2a or 2b)2) K(P) = Applicable core power dependent OLMCPR multiplier (Figure 2c, 2d, 2e, or 2f)3) P(bypass) | ||
= 26% of Rated | = 26% of Rated Power Page 3 of 21 COLR2-15 NINE MILE POINT UNIT 2 Revision 0, C 0 CORE OPERATING LIMITS REPORT 2.2 Notes 1. For Figures 2a and 2b tau (T) is defined as follows:*r ave -- 1"B A B where: rA = 0.866 seconds, control rod average scram insertion time limit to notch 39 per Technical Specification 3.1.4.r, =O0672+i1.65 N 1 X(O.0 I6 i=1 n 1=I n = number of surveillance tests performed in cycle N, = number of active control rods measured in the it surveillance test z, = average scram time to notch 39 of all rods measured in the ihsurveillance test N 1 = total number of active rods measured in Specification 3.1.4.1I T 1.0 prior to performance of the initial scram time measurements for the cycle 2. ARTS provides for power- and flow-dependent thermal limit adjustments and*multipliers, which allow for a more reliable administration of the MCPR thermal limit. The MCPR(P) curves are independent of EOC-RPT and scram time option, but are determined for other EOOS. The MCPR(P) limits for PROOS were converted to a K(P) consistent with the ARTS offrated limits. MCPR(F) is independent of Scram Time Option and all EOOS.3. The Operating Limit MCPR values for TBVOOS and EOC-RPT Out of Service are higher (more limiting) than for the standard normal operation case, and are therefore specifically identified where appropriate (Figures 2a and 2b). The OLMCPR values for all other analyzed EOOS transient events are bounded by the Normal Operation limits.4. EOR is the End of Rated exposure as defined in the Cycle Management Report.ycle 15 Page 4 of 21 CO0-I 5 NINE MILE PNT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYCLO Figure 2a Operating Limit MCPR (BOC to EOR-2816 MWd/ST)CL E.0 1.80 1.75 1.70 1.65 1.60 1.55 1.50 1.45 1.40 1.35 1.30 (1,1.73)(1,1.63)(1,1.61)0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 Tau 1 Page 5 of 21 C -15 NINE MILE ONT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYCL95 0t (L 7B E M E.1.80 1.75 1.70 1.65 1.60 1.55 1.50 Figure 2b Operating Limit MCPR (EOR-2816 MWd/ST to EOC)EOC-RPT I Normal Operation (0,1.38)(1,1.63)(1,1.62)1.45 1.40 1.35 1.30 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Ta u Page 6 of 21 C.2-15 NINE MILEONT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYC*5 Figure 2c MCPR(P) for <26%Power, <75%Flow K(P) for >26% Power for Equipment In Service I-W n.CL 3.500 3.250 3.000 2.750 2.500 2.250 2.000 1.750 1.500 1.250 1.000 (23, 2.470)I ~ --A (26, 2.390)(26, 1.511)Im Ei-- MCPR(P) = 2.390 + 2.67E-02(26.0-P) for 23.0% ! P < 26.0%MCPR(P) = K(P)*(the appropriate MCPR limit from Figures 2a or 2b) for 26.0% < P < 100.0%-i-0 K(P) = 1.336 + 6.03E-03(55.0-P) for 26.0% 5 P < 55.0%K(P) = 1.150 + 8.60E-03(60.0-P) for 55.0% < P < 60.0%K(P) = 1.000 + 3.75E-03(1 00.0-P) for 60.0% ! P 5 100.0%--7ýýý1.336)-(60, 1.150)(55, 1.193)(85, 1.056)(100, 1.000)~ -.L 4 + 4 ~.20 25 30 35 40 45 50 55 60 Power (% Rate 65 70 75 80 85 90 95 100 Page 7 of 21 C*2-15 NINE MILEONT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYC05 Figure 2d MCPR(P) for <26%Power, <75%Flow K(P) for >26% Power for Recirculation Pump Trip Out of Service 113 3.500 3.250 3.000 2.750 2.500 2.250 2.000 1.750 1.500 1.250.1 n ) r)I F + + I I I-- MCPR(P) = 2.390 + 2.67E-02(26.0-P) for 23.0% 5 P < 26.0%MCPR(P) = K(P)*(the appropriate MCPR limit from Figures 2a or 2b) for 26.0% < P S 100.0%-K(P) = 1.336 + 6.03E-03(55.0-P) for 26.0% < P < 55.0%K(P) = 1. 150 + 8.60E-03(60.0-P) for 55.0% : P < 60.0%K(P) = 1.062 + 3.52E-03(85.0-P) for 60.0% < P < 85.0%K(P) = 1.000 + 4.13E-03(100.0-P) for 85.0% 5 P < 100.0%(23,(2.470) | ||
<75% | (26, 2.390)(26, 1.511)I F +(55, 1.336)(60, 1.150)(55, 1.193)(85, 1.062)(100, 1.000)--..-L_ /I I I 20 25 30 35 40 45 50 55 60 65 Power (% Rated)1 1 I I 70 75 80 85 90 95 100 Page 8 of 21 | ||
<75% | .COO-15 NINE MIiLE *T UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYCJ*Figure 2e MCPR(P) for <26%Power, <75%Flow K(P) for >26% Power for Turbine Bypass Valve Out of Service 3.500 3.250 3.000 2.750 2.500 2.250 2.000 (23, 3.270)MCPR(P) = 3.000 + 9.OOE-02(26.0-P) for 23.0% < P < 26.0%MCPR(P) = K(P)-(the appropriate MCPR limit from Figures 2a or 2b) for 26.0% : P < 100.0%(26, 3.000)-K(P) = 1.336 + 6.03E-03(55.0-P) for 26.0% < P < 55.0%K(P) = 1.150 + 8.60E-03(60.0-P) for 55.0% < P < 60.0%K(P) = 1.000 + 3.75E-03(100.0-P) for 60.0% < P < 100.0%(26, 1.511)_ I -jý _C., 06 1.750 1.500 1.250 1.000 (55, 1.336)60, 1.150)(55, 1.193)(85, 1.056)(100, 1.000).--4 + 4 20 25 30 35 40 45 50 55 60 65 Power (% Rated)70 75 80 85 90 95 100 Page 9 of 21 C.2-15 NINE MILERNT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYC*5 Figure 2f MCPR(P) for <26%Power, <75%Flow K(P) for >26% Power for Operation without a Backup Pressure Regulator C., Ve 3.500 3.250 3.000 2.750 2.500 2.250 2.000 1.750 1.500 1.250 1.000*MCPR(P) = 2.390 + 2.67E-02(26.0-P) for 23.0% s P < 26.0%MCPR(P) K(P)*(the appropriate MCPR limit from Figures 2a or 2b) j.for 26.0% < P <100.0%---___ K(P) = 1.122 + 6.08E-03(90.0-P) for 26.0% ! P < 90.0%K(P) = 1.000 + 3,80E-03(100.0-P) for 90.0% 5 P <100.0%(23, 2.470) -...(26, 2.390)(26, 1.511)(90, 1.122)_________ | ||
(26, 2.390)(26, 1.511)I F +(55, 1.336)(60, 1.150)(55, 1.193)(85, 1.062)(100, 1.000)--..-L_ / | |||
.COO- | |||
<75% | |||
<75% | |||
= 2.390 + 2.67E-02(26.0-P) for 23.0% s P < 26.0%MCPR(P) K(P)*(the appropriate MCPR limit from Figures 2a or 2b) j.for 26.0% < P <100.0%---___ K(P) = 1.122 + 6.08E-03(90.0-P) for 26.0% ! P < 90.0%K(P) = 1.000 + 3,80E-03(100.0-P) for 90.0% 5 P <100.0%(23, 2.470) -...(26, 2.390)(26, 1.511)(90, 1.122)_________ | |||
___ ____ ___ ____________ | ___ ____ ___ ____________ | ||
___ ____ 90, 1.08o(0, 1.000)1. | ___ ____ 90, 1.08o(0, 1.000)1.000 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)Page 10 of 21 | ||
.2 - | .2 -15 NINE MILANT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CY05 Figure 2g Flow-Dependent MCPR Limits 1.80 1.70 1.60 1.50 U.0~C.)1.40 1.30 1.20 1.10 20 30 40 50 60 70 Flow (% Rated)80 90 100 110 120 Page 11 of 21 COLR2-15 NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT Revision 0, Cycle 15 3.0 LINEAR HEAT GENERATION RATE (LHGR)3.1 Limits for Technical Specification 3.2.3 During power operation, the Linear.Heat Generation Rate (LHGR) in any fuel rod in any fuel assembly at any axial location shall not exceed the applicable LHGR limits for Two-Loop or Single-Loop Operation (Table 3).LHGR LHGR(100) x minimum[LHGRFAC(P), LHGRFAC(F), LHGR(SLO)] | ||
LHGRFAC(F), | |||
LHGR(SLO)] | |||
where, LHGR(100) | where, LHGR(100) | ||
= Applicable LHGR limit found in Table D-2 for U02 | = Applicable LHGR limit found in Table D-2 for U02 rods and Table D-4 for U02 rods containing Gadolinium in Source Document 8.10 LHGRFAC(P) | ||
= Applicable core power dependent multiplier from | = Applicable core power dependent multiplier from Figures 3a, 3b, or 3c LHGRFAC(F) | ||
= Applicable core flow dependent multiplier from Figure | = Applicable core flow dependent multiplier from Figure 3d LHGR(SLO) | ||
= Applicable Single Loop Operation (SLO) PLHGR multiplier Table | = Applicable Single Loop Operation (SLO) PLHGR multiplier Table 3 Linear Heat Generation Rate Two Recirculation Loop Operation (TLO) Condition LHGR = LHGR(100) x LHGRFAC(P) 23% < P < 100%or LHGR = LHGRFAC(F) | ||
F > 30%Single Recirculation Loop Operation (SLO) Condition LHGR = LHGR(100) x LHGRFAC(P) 23% < P < 100% | F > 30%Single Recirculation Loop Operation (SLO) Condition LHGR = LHGR(100) x LHGRFAC(P) 23% < P < 100%or LHGR = LHGR(100) x LHGRFAC(F) | ||
F _ 30% | F _ 30%or LHGR = LHGR(100) x LHGR(SLO) | ||
SLO Note: 1) LHGR(SLO) | |||
= 0. | = 0.78 2) ARTS provides for power- and flow-dependent thermal limit multipliers, which allow for a more reliable administration of the LHGR thermal limits. The LHGRFAC(P) curves are independent of recirculation pump trip operability, but are determined for other EOOS. The LHGRFAC (P) limits for PROOS are also presented in a manner more consistent with the ARTS offrated limits. LHGRFAC(F) is identical for all EOOS.Page 12 of 21 CW-15 NINE MILEONT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYC 9 5 Figure 3a LHGRFAC(P) for < 26% Power, < 75% Flow LHGRFAC(P) for a 26% Power Iuipment In Service and Recirculation Pump Trip 0 1.000 0.900 0.800 0.700 0.600 0.500 0.400 a.U-LI"-J 0.300 0.200 0.100 0.000 20 25 30 35 40 45 50 55 60 .65 Power (% Rated)70 75 80 85 90 95 100 Page 13 of 21 C.2-15 NINE MILEINT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYC*5 Figure 3b LHGRFAC(P) for < 26% Power, < 75% Flow LHGRFAC(P) for 2 26% Power for Turbine BvDass Valve Out of Service 0-0 U-,-J 1.000 0.900 0.800 0.700 0.600 0.500 0.400 0.300 0.200 0.100 0.000 20 25 30 35 40 45 50 55 60 65 Power (% Rated)70 75 80 85 90 95 100 Page 14 of 21 COW-15 NINE MILEONT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYCL*5 Figure 3c LHGRFAC(P) for < 26% Power, < 75% Flow LHGRFAC(P) for > 26% Power for Operation without a Backup Pressure Regulator (100, 1.000)1.000 0.900 0.800 0.700 0.600 LL U-0.500 0.400 0.300 0.200 0.100 0.000 20 25 30 35 40 45 50 55 60 65 Power (% Rated)70 75 80 85 90 95 100 Page 15 of 21 C-15 NINE MILE 9 INT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYC#5 U-0"-J 1.100 1.000 0.900 0.800 0.700 0.600 0.500 0.400 0.300 0.200 0.100 0.000 Figure 3d Flow-Dependent LHGR Multiplier LHGRFAC(F) | ||
(85,1.000) | (85,1.000) | ||
(112, 1.000)(30, 0.625)-LHGRFAC(F) | (112, 1.000)(30, 0.625)-LHGRFAC(F) | ||
= 1.000 + 6.82E-03(F-85.0) for 30.0% 5 F < 85.0%LHGRFAC(F) | = 1.000 + 6.82E-03(F-85.0) for 30.0% 5 F < 85.0%LHGRFAC(F) | ||
= 1.000 for 85.0%/ S F5 112.0%..° ........ | = 1.000 for 85.0%/ S F5 112.0%..° ........20 30 40 50 60 70 Flow (% Rated)80 90 100 110 120 Page 16 of 21 COLR2-15 NINE MILE POINT UNIT 2 Revision 0, Cycle 15 CORE OPERATING LIMITS REPORT 4.0 AVERAGE POWER RANGE MONITOR SETPOINTS 4.1 Limits for Technical Specification Table 3.3.1.1-1 (OPRM Upscale)Allowable value < 1.14 Page 17 of 21 COLR2-15 NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT Revision 0, Cycle 15 5.0 CONTROL ROD BLOCK INSTRUMENTATION 5.1 Footnote Values for Technical Specification Table 3.3.2.1-1 (a) MCPR <(b) MCPR <(c) MCPR <(d) MCPR <1.70 1.70 1.70 1.40 (e) MCPR <(h) Allowable Value: Low Power Range -Upscale Intermediate Power Range -Upscale High Power Range -Upscale (i) NTSP: Low Power Range -Upscale Intermediate Power Range -Upscale High Power Range -Upscale 1.70 124.6 119.6 114.6 124.2 119.2 114.2 NOTES: The RBM must be operable anytime the MCPR is less than the limits defined above for the given power range as defined in Technical Specification Table 3.3.2.1-1 Page 18 of 21 COLR2-15 NINE MILE POINT UNIT 2 Revision 0, Cycle 15 CORE OPERATING LIMITS REPORT | ||
==6.0 REFERENCES== | ==6.0 REFERENCES== | ||
FOR TECHNICAL SPECIFICATION 6.1 Technical Specification 5.6.5.b.1: | FOR TECHNICAL SPECIFICATION 6.1 Technical Specification 5.6.5.b.1: | ||
General Electric Standard Application for Reactor Fuel (GESTAR 1I), NEDE 24011-P-A-20 and NEDE 2401 1-P-A-20-US, December 2013.Page 19 of 21 COLR2-15 NINE MILE POINT UNIT 2 Revision 0, Cycle | General Electric Standard Application for Reactor Fuel (GESTAR 1I), NEDE 24011-P-A-20 and NEDE 2401 1-P-A-20-US, December 2013.Page 19 of 21 COLR2-15 NINE MILE POINT UNIT 2 Revision 0, Cycle 15 CORE OPERATING LIMITS REPORT | ||
==7.0 REFERENCES== | ==7.0 REFERENCES== | ||
FOR TECHNICAL SPECIFICATION | FOR TECHNICAL SPECIFICATION BASES Bases Reference 3 (Section 2.1.1): General Electric Standard Application for Reactor Fuel (GESTAR II), NEDE 2401 I-P-A-20 and NEDE 2401 1-P-A-20-US, December 2013.Bases Reference 4 (Section 2.1.1): Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt) | ||
/ MELLLA (99-105% | / MELLLA (99-105% Flow), 000N2528-SRLR, Rev. 1, January 2014.Bases Reference 7 (Section 3.1.1): General Electric Standard Application for Reactor Fuel (GESTAR I1), NEDE 2401 1-P-A-20 and NEDE 24011 -P-A-20-US, December 2013.Bases Reference I (Section 3.1.6): Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt) | ||
Flow), 000N2528-SRLR, Rev. 1, January 2014.Bases Reference 7 (Section 3.1.1):General Electric Standard Application for Reactor Fuel (GESTAR I1), NEDE 2401 1-P-A-20 | / MELLLA (99-105% Flow), 000N2528-SRLR, Rev. 1, January 2014.Bases Reference 1 (Section 3.2.1): General Electric Standard Application for Reactor Fuel (GESTAR 11), NEDE 2401 1-P-A-20 and NEDE 2401 I-P-A-20-US, December 2013.Bases Reference 2 (Section 3.2.2): General Electric Standard Application for Reactor Fuel (GESTAR 11). NEDE 2401 I-P-A-20 and NEDE 24011-P-A-20-US, December 2013.Bases Reference 3 (Section 3.2.2): Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt) | ||
/ MELLLA (99-105% | / MELLLA (99-105% Flow), 000N2528-SRLR, Rev. 1, January 2014.Bases Reference 1 (Section 3.2.3): General Electric Standard Application for Reactor Fuel (GESTAR 11), NEDE 2401 1-P-A-20 and NEDE 2401 1-P-A-20-US, December 2013.Bases Reference 2 (Section 3.2.3): Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt) | ||
Flow), 000N2528-SRLR, Rev. 1, January 2014.Bases Reference 1 (Section 3.2.1):General Electric Standard Application for Reactor Fuel (GESTAR 11), NEDE 2401 1-P-A-20 | / MELLLA (99-105% Flow), 000N2528-SRLR, Rev. 1, January 2014.Page 20 of 21 COLR2-15 NINE MILE POINT UNIT 2 Revision 0, Cycle 15 CORE OPERATING LIMITS REPORT 8.0 SOURCE DOCUMENTS Section 1.0 -APLHGR Limits 8.1. Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt) | ||
/ MELLLA (99-105% | /MELLLA (99-105% Flow), 000N2528-SRLR, Rev. 1, January 2014.Section 2.0 -MCPR Limits 8.2. Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt) | ||
Flow), 000N2528-SRLR, Rev. 1, January 2014.Bases Reference 1 (Section 3.2.3):General Electric Standard Application for Reactor Fuel (GESTAR 11), NEDE 2401 1-P-A-20 | /MELLLA (99-105% Flow), 000N2528-SRLR, Rev. 1, January 2014.8.3. Nine Mile Point Station Unit 2 -APRM/RBM/Technical Specifications/Maximum Extended Load Line Limit Analysis (ARTS/MELLLA), NEDC-33286P, Rev. 0, March 2007 (NER-2E-037). | ||
/ MELLLA (99-105% | 8.4. Nine Mile Point Nuclear Station Unit 2 ARTS/MELLLA, Task T0900, GE-NE-0000-0055-2373-RO, Rev. 0, February 2007 (NER-2E-037). | ||
Flow), 000N2528-SRLR, Rev. 1, January 2014.Page 20 of 21 COLR2-15 NINE MILE POINT UNIT 2 Revision 0, Cycle | 8.5. Engineering Report for Nine Mile Point Nuclear Station Unit 2, Reload 11, Cycle 12, 0000-0067-1271-ER, Rev 0, March 2008.Section 3.0 -LHGR Limits 8.6. Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt) | ||
/MELLLA (99-105% | /MELLLA (99-105% Flow), 000N2528-SRLR, Rev. 1, January 2014.8.7. Nine Mile Point Nuclear Station Unit 2 -APRM/RBM/Technical Specifications/Maximum Extended Load Line Limit Analysis (ARTS/MELLLA), NEDC-33286P, Rev. 0, March 2007.8.8. Nine Mile Point Nuclear Station Unit 2 ARTS/MELLLA, Task T0900, GE-NE-0000-0055-2373-RO, Rev. 0, February 2007 (NER-2E-037). | ||
Flow), 000N2528-SRLR, Rev. 1, January 2014.Section 2.0 -MCPR | 8.9. Fuel Bundle Information Report for Nine Mile Point 2 Reload 14 Cycle 15, 000N0123-FBIR-P, Rev. 0 December 2013.8.10. GE 14 Compliance with Amendment 22 of NEDE-2401 I-P-A (GESTAR 11), NEDC-32868P, Revision 5, May 2013, MFN 13-028, May 2013.Section 4.0 -APRM Setpoints 8.11. Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt) | ||
/MELLLA (99-105% | /MELLLA (99-105% Flow), 000N2528-SRLR, Rev. 1, January 2014.8.12. Design Specification Data Sheet 22A2843AM (NMPCNO NSSS161405000), Neutron Monitoring System.Section 5.0 -Control Rod Block Instrumentation 8.13. Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt) | ||
Flow), 000N2528-SRLR, Rev. 1, January 2014.8.3. Nine Mile Point Station Unit 2 -APRM/RBM/Technical Specifications/Maximum Extended Load Line Limit Analysis(ARTS/MELLLA), | /MELLLA (99-105% Flow), 000N2528-SRLR, Rev. I, January 2014.8.14. Nine Mile Point Nuclear Station Unit 2 -APRM/RBM/Technical Specifications/Maximum Extended Load Line Limit Analysis (ARTS/MELLLA), NEDC-33286P, Rev. 0, March 2007.8.15. Instrument Limits Calculation Constellation Generation Group Nine Mile Point Nuclear Station Unit 2 Rod Block Monitor (NUMAC ARTS-MELLA), 0000-0053-1006 NMP2 A-M-T506-RBM-Calc-2006, Rev. 1, March 2008 (Found within NMP document NSSS 168805002). | ||
NEDC-33286P, Rev. 0, March 2007 (NER-2E-037). | |||
8.4. Nine Mile Point Nuclear Station Unit 2 ARTS/MELLLA, Task T0900, GE-NE-0000-0055-2373-RO, Rev. 0, | |||
8.5. Engineering Report for Nine Mile Point Nuclear Station Unit 2, Reload 11, Cycle 12, 0000-0067-1271-ER, Rev 0, | |||
/MELLLA (99-105% | |||
Flow), 000N2528-SRLR, Rev. 1, January 2014.8.7. Nine Mile Point Nuclear Station Unit 2 -APRM/RBM/Technical Specifications/Maximum Extended Load Line | |||
NEDC-33286P, Rev. 0, March 2007.8.8. Nine Mile Point Nuclear Station Unit 2 ARTS/MELLLA, Task T0900, GE-NE-0000-0055-2373-RO, Rev. 0, | |||
8.9. Fuel Bundle Information Report for Nine Mile Point 2 Reload 14 Cycle 15, 000N0123-FBIR-P, Rev. 0 December 2013.8.10. GE 14 Compliance with Amendment 22 of NEDE-2401 I-P-A (GESTAR 11), NEDC-32868P, Revision 5, May 2013,MFN 13-028, May 2013.Section 4.0 -APRM Setpoints 8.11. Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt) | |||
/MELLLA (99-105% | |||
Flow), 000N2528-SRLR, Rev. 1, January 2014.8.12. Design Specification Data Sheet 22A2843AM (NMPCNO NSSS161405000), | |||
Neutron Monitoring System.Section 5.0 -Control Rod Block Instrumentation 8.13. Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt) | |||
/MELLLA (99-105% | |||
Flow), 000N2528-SRLR, Rev. I, January 2014.8.14. Nine Mile Point Nuclear Station Unit 2 -APRM/RBM/Technical Specifications/Maximum Extended Load Line | |||
NEDC-33286P, Rev. 0, March 2007.8.15. Instrument Limits Calculation Constellation Generation Group Nine Mile Point Nuclear Station Unit 2 Rod | |||
0000-0053-1006 NMP2 A-M-T506-RBM-Calc-2006, Rev. 1, March 2008 ( | |||
Page 21 of 21}} | Page 21 of 21}} | ||
Revision as of 17:15, 9 July 2018
| ML14126A724 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/24/2014 |
| From: | Swift P M Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML14126A724 (25) | |
Text
a.EWExelon Generation April 24, 2014 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION:
SUBJECT:
Document Control Desk Nine Mile Point Nuclear Station Renewed Facility Operating License No. NPF-69 Unit No. 2; Docket No. 50-410 Core Operating Limits Report Enclosed is a copy of the Core Operating Limits Report, COLR2-15, Revision 0 for Nine Mile Point Unit 2 (NMP2). 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 Everett P.Perkins, Director -Licensing, at (315) 349-5219.Very truly yours, Paul M. Swift Manager, Engineering Services PMS/MHS
Enclosure:
Nine Mile Point Unit 2 Core Operating Limits Report cc: NRC Regional Administrator, Region I NRC Project Manager NRC Senior Resident Inspector AOD(
ENCLOSURE Nine Mile Point Unit 2 Core Operating Limits Report Nine Mile Point Nuclear Station, LLC April 24, 2014 NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT COLR2715 Revision 0, Cycle 15 Prepared by.Name Melisa Kriek Title Fuels Engineer Date Reviewed by: Approved by: Approved by: Approved by: Fuels Engineer Supervisor, Reactor Engineer John Darweessh 3/ /.Y//` V/ I Supervisor, Fuels iPhil Weyoski General Supervisor, Fuels This controlled document provides cycle specific core operating limits for use in conjunction with the Nine Mile Point Unit 2 Technical Specifications.
Document pages may only be changed through a reissue of the entire document.
COLR2-15 NINE MILE POINT UNIT 2 Revision 0, Cycle 15 CORE OPERATING LIMITS REPORT TABLE OF CONTENTS page 1.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 1 1.1 Limits for Technical Specification 3.2.1 1 2.0 MINIMUM CRITICAL POWER RATIO (OPTION B) 3 2.1 Limits for Technical Specification 3.2.2 3 2.2 Notes 4 3.0 LINEAR HEAT GENERATION RATE (LHGR) 12 3.1 Limits for Technical Specifications 3.2.3 12 4.0 AVERAGE POWER RANGE MONITOR SETPOINTS 17 4.1 Limits for Technical Specification Table 3.3.1.1-1 (OPRM Upscale) 17 5.0 CONTROL ROD BLOCK INSTRUMENTATION 18 5.1 Allowable Value for Technical Specification Table 3.3.2.1-1 18
6.0 REFERENCES
FOR TECHNICAL SPECIFICATIONS 19
7.0 REFERENCES
FOR TECHNICAL SPECIFICATION BASES 20 8.0 SOURCE DOCUMENTS 21 Page i COLR2-15 NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT Revision 0,'Cycle 15 1.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)1.1 Limits for Technical Specification 3.2.1 The APLHGR(s) for each fuel type as a function of Average Planar Exposure shall not exceed the limits shown in Table 1.The limits of Table 1 shall be reduced to a value of 0.78 times the two recirculation loop operation limit when in single recirculation loop operation.
Page 1 of 21 COLR2-15 NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT Revision 0, Cycle 15 Table 1 MAPLHGR versus Average Planar Exposure Average Planar Exposure MAPLHGR Limits (GWD/ST) (KW/ft)0.00 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 5.00 NOTES: 1. APLHGR(s) are interpolated between exposure points for which explicit values are given Page 2 of 21 COLR2-15 NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT Revision 0, Cycle 15 2.0 MINIMUM CRITICAL POWER RATIO (OPTION B).2.1 Limits for Technical Specification 3.2.2 The Minimum Critical Power Ratio (MCPR) shall be greater than or equal to the Operating Limit MCPR (OLMCPR) for Two-Loop or Single-Loop Operation (Table 2).OLMCPR = maximum[MCPR(P), MCPR(F)]where, MCPR(P) = Applicable core power dependent MCPR (Fig. 2c, 2d, 2e, or 2f)MCPR(F) = Flow rate dependent MCPR (Fig. 2g)Table 2 Minimum Critical Power Ratio Two Recirculation Loop Operation (TLO) Condition MCPR(P) = OLMCPR( 100) x K(P) P(bypass)
< P < 100%or MCPR(P) = MCPR(P) 23% < P < P(bypass)MCPR(F) = MCPR(F) F > 30%Single Recirculation Loop Operation (SLO) Condition MCPR(P) = 0.02 + OLMCPR( 100) x K(P) P(bypass)
< P < 100%or MCPR(P) = 0.02 + MCPR(P) 23% < P < P(bypass)MCPR(F) = 0.02 + MCPR(F) F 30%Note: 1) OLMCPR(100)
-Applicable OLMCPR for rated core power and flow conditions (Figure 2a or 2b)2) K(P) = Applicable core power dependent OLMCPR multiplier (Figure 2c, 2d, 2e, or 2f)3) P(bypass)
= 26% of Rated Power Page 3 of 21 COLR2-15 NINE MILE POINT UNIT 2 Revision 0, C 0 CORE OPERATING LIMITS REPORT 2.2 Notes 1. For Figures 2a and 2b tau (T) is defined as follows:*r ave -- 1"B A B where: rA = 0.866 seconds, control rod average scram insertion time limit to notch 39 per Technical Specification 3.1.4.r, =O0672+i1.65 N 1 X(O.0 I6 i=1 n 1=I n = number of surveillance tests performed in cycle N, = number of active control rods measured in the it surveillance test z, = average scram time to notch 39 of all rods measured in the ihsurveillance test N 1 = total number of active rods measured in Specification 3.1.4.1I T 1.0 prior to performance of the initial scram time measurements for the cycle 2. ARTS provides for power- and flow-dependent thermal limit adjustments and*multipliers, which allow for a more reliable administration of the MCPR thermal limit. The MCPR(P) curves are independent of EOC-RPT and scram time option, but are determined for other EOOS. The MCPR(P) limits for PROOS were converted to a K(P) consistent with the ARTS offrated limits. MCPR(F) is independent of Scram Time Option and all EOOS.3. The Operating Limit MCPR values for TBVOOS and EOC-RPT Out of Service are higher (more limiting) than for the standard normal operation case, and are therefore specifically identified where appropriate (Figures 2a and 2b). The OLMCPR values for all other analyzed EOOS transient events are bounded by the Normal Operation limits.4. EOR is the End of Rated exposure as defined in the Cycle Management Report.ycle 15 Page 4 of 21 CO0-I 5 NINE MILE PNT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYCLO Figure 2a Operating Limit MCPR (BOC to EOR-2816 MWd/ST)CL E.0 1.80 1.75 1.70 1.65 1.60 1.55 1.50 1.45 1.40 1.35 1.30 (1,1.73)(1,1.63)(1,1.61)0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 Tau 1 Page 5 of 21 C -15 NINE MILE ONT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYCL95 0t (L 7B E M E.1.80 1.75 1.70 1.65 1.60 1.55 1.50 Figure 2b Operating Limit MCPR (EOR-2816 MWd/ST to EOC)EOC-RPT I Normal Operation (0,1.38)(1,1.63)(1,1.62)1.45 1.40 1.35 1.30 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Ta u Page 6 of 21 C.2-15 NINE MILEONT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYC*5 Figure 2c MCPR(P) for <26%Power, <75%Flow K(P) for >26% Power for Equipment In Service I-W n.CL 3.500 3.250 3.000 2.750 2.500 2.250 2.000 1.750 1.500 1.250 1.000 (23, 2.470)I ~ --A (26, 2.390)(26, 1.511)Im Ei-- MCPR(P) = 2.390 + 2.67E-02(26.0-P) for 23.0% ! P < 26.0%MCPR(P) = K(P)*(the appropriate MCPR limit from Figures 2a or 2b) for 26.0% < P < 100.0%-i-0 K(P) = 1.336 + 6.03E-03(55.0-P) for 26.0% 5 P < 55.0%K(P) = 1.150 + 8.60E-03(60.0-P) for 55.0% < P < 60.0%K(P) = 1.000 + 3.75E-03(1 00.0-P) for 60.0% ! P 5 100.0%--7ýýý1.336)-(60, 1.150)(55, 1.193)(85, 1.056)(100, 1.000)~ -.L 4 + 4 ~.20 25 30 35 40 45 50 55 60 Power (% Rate 65 70 75 80 85 90 95 100 Page 7 of 21 C*2-15 NINE MILEONT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYC05 Figure 2d MCPR(P) for <26%Power, <75%Flow K(P) for >26% Power for Recirculation Pump Trip Out of Service 113 3.500 3.250 3.000 2.750 2.500 2.250 2.000 1.750 1.500 1.250.1 n ) r)I F + + I I I-- MCPR(P) = 2.390 + 2.67E-02(26.0-P) for 23.0% 5 P < 26.0%MCPR(P) = K(P)*(the appropriate MCPR limit from Figures 2a or 2b) for 26.0% < P S 100.0%-K(P) = 1.336 + 6.03E-03(55.0-P) for 26.0% < P < 55.0%K(P) = 1. 150 + 8.60E-03(60.0-P) for 55.0% : P < 60.0%K(P) = 1.062 + 3.52E-03(85.0-P) for 60.0% < P < 85.0%K(P) = 1.000 + 4.13E-03(100.0-P) for 85.0% 5 P < 100.0%(23,(2.470)
(26, 2.390)(26, 1.511)I F +(55, 1.336)(60, 1.150)(55, 1.193)(85, 1.062)(100, 1.000)--..-L_ /I I I 20 25 30 35 40 45 50 55 60 65 Power (% Rated)1 1 I I 70 75 80 85 90 95 100 Page 8 of 21
.COO-15 NINE MIiLE *T UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYCJ*Figure 2e MCPR(P) for <26%Power, <75%Flow K(P) for >26% Power for Turbine Bypass Valve Out of Service 3.500 3.250 3.000 2.750 2.500 2.250 2.000 (23, 3.270)MCPR(P) = 3.000 + 9.OOE-02(26.0-P) for 23.0% < P < 26.0%MCPR(P) = K(P)-(the appropriate MCPR limit from Figures 2a or 2b) for 26.0% : P < 100.0%(26, 3.000)-K(P) = 1.336 + 6.03E-03(55.0-P) for 26.0% < P < 55.0%K(P) = 1.150 + 8.60E-03(60.0-P) for 55.0% < P < 60.0%K(P) = 1.000 + 3.75E-03(100.0-P) for 60.0% < P < 100.0%(26, 1.511)_ I -jý _C., 06 1.750 1.500 1.250 1.000 (55, 1.336)60, 1.150)(55, 1.193)(85, 1.056)(100, 1.000).--4 + 4 20 25 30 35 40 45 50 55 60 65 Power (% Rated)70 75 80 85 90 95 100 Page 9 of 21 C.2-15 NINE MILERNT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYC*5 Figure 2f MCPR(P) for <26%Power, <75%Flow K(P) for >26% Power for Operation without a Backup Pressure Regulator C., Ve 3.500 3.250 3.000 2.750 2.500 2.250 2.000 1.750 1.500 1.250 1.000*MCPR(P) = 2.390 + 2.67E-02(26.0-P) for 23.0% s P < 26.0%MCPR(P) K(P)*(the appropriate MCPR limit from Figures 2a or 2b) j.for 26.0% < P <100.0%---___ K(P) = 1.122 + 6.08E-03(90.0-P) for 26.0% ! P < 90.0%K(P) = 1.000 + 3,80E-03(100.0-P) for 90.0% 5 P <100.0%(23, 2.470) -...(26, 2.390)(26, 1.511)(90, 1.122)_________
___ ____ ___ ____________
___ ____ 90, 1.08o(0, 1.000)1.000 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)Page 10 of 21
.2 -15 NINE MILANT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CY05 Figure 2g Flow-Dependent MCPR Limits 1.80 1.70 1.60 1.50 U.0~C.)1.40 1.30 1.20 1.10 20 30 40 50 60 70 Flow (% Rated)80 90 100 110 120 Page 11 of 21 COLR2-15 NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT Revision 0, Cycle 15 3.0 LINEAR HEAT GENERATION RATE (LHGR)3.1 Limits for Technical Specification 3.2.3 During power operation, the Linear.Heat Generation Rate (LHGR) in any fuel rod in any fuel assembly at any axial location shall not exceed the applicable LHGR limits for Two-Loop or Single-Loop Operation (Table 3).LHGR LHGR(100) x minimum[LHGRFAC(P), LHGRFAC(F), LHGR(SLO)]
where, LHGR(100)
= Applicable LHGR limit found in Table D-2 for U02 rods and Table D-4 for U02 rods containing Gadolinium in Source Document 8.10 LHGRFAC(P)
= Applicable core power dependent multiplier from Figures 3a, 3b, or 3c LHGRFAC(F)
= Applicable core flow dependent multiplier from Figure 3d LHGR(SLO)
= Applicable Single Loop Operation (SLO) PLHGR multiplier Table 3 Linear Heat Generation Rate Two Recirculation Loop Operation (TLO) Condition LHGR = LHGR(100) x LHGRFAC(P) 23% < P < 100%or LHGR = LHGRFAC(F)
F > 30%Single Recirculation Loop Operation (SLO) Condition LHGR = LHGR(100) x LHGRFAC(P) 23% < P < 100%or LHGR = LHGR(100) x LHGRFAC(F)
F _ 30%or LHGR = LHGR(100) x LHGR(SLO)
= 0.78 2) ARTS provides for power- and flow-dependent thermal limit multipliers, which allow for a more reliable administration of the LHGR thermal limits. The LHGRFAC(P) curves are independent of recirculation pump trip operability, but are determined for other EOOS. The LHGRFAC (P) limits for PROOS are also presented in a manner more consistent with the ARTS offrated limits. LHGRFAC(F) is identical for all EOOS.Page 12 of 21 CW-15 NINE MILEONT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYC 9 5 Figure 3a LHGRFAC(P) for < 26% Power, < 75% Flow LHGRFAC(P) for a 26% Power Iuipment In Service and Recirculation Pump Trip 0 1.000 0.900 0.800 0.700 0.600 0.500 0.400 a.U-LI"-J 0.300 0.200 0.100 0.000 20 25 30 35 40 45 50 55 60 .65 Power (% Rated)70 75 80 85 90 95 100 Page 13 of 21 C.2-15 NINE MILEINT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYC*5 Figure 3b LHGRFAC(P) for < 26% Power, < 75% Flow LHGRFAC(P) for 2 26% Power for Turbine BvDass Valve Out of Service 0-0 U-,-J 1.000 0.900 0.800 0.700 0.600 0.500 0.400 0.300 0.200 0.100 0.000 20 25 30 35 40 45 50 55 60 65 Power (% Rated)70 75 80 85 90 95 100 Page 14 of 21 COW-15 NINE MILEONT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYCL*5 Figure 3c LHGRFAC(P) for < 26% Power, < 75% Flow LHGRFAC(P) for > 26% Power for Operation without a Backup Pressure Regulator (100, 1.000)1.000 0.900 0.800 0.700 0.600 LL U-0.500 0.400 0.300 0.200 0.100 0.000 20 25 30 35 40 45 50 55 60 65 Power (% Rated)70 75 80 85 90 95 100 Page 15 of 21 C-15 NINE MILE 9 INT UNIT 2 CORE OPERATING LIMITS REPORT REVISION 0, CYC#5 U-0"-J 1.100 1.000 0.900 0.800 0.700 0.600 0.500 0.400 0.300 0.200 0.100 0.000 Figure 3d Flow-Dependent LHGR Multiplier LHGRFAC(F)
(85,1.000)
(112, 1.000)(30, 0.625)-LHGRFAC(F)
= 1.000 + 6.82E-03(F-85.0) for 30.0% 5 F < 85.0%LHGRFAC(F)
= 1.000 for 85.0%/ S F5 112.0%..° ........20 30 40 50 60 70 Flow (% Rated)80 90 100 110 120 Page 16 of 21 COLR2-15 NINE MILE POINT UNIT 2 Revision 0, Cycle 15 CORE OPERATING LIMITS REPORT 4.0 AVERAGE POWER RANGE MONITOR SETPOINTS 4.1 Limits for Technical Specification Table 3.3.1.1-1 (OPRM Upscale)Allowable value < 1.14 Page 17 of 21 COLR2-15 NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT Revision 0, Cycle 15 5.0 CONTROL ROD BLOCK INSTRUMENTATION 5.1 Footnote Values for Technical Specification Table 3.3.2.1-1 (a) MCPR <(b) MCPR <(c) MCPR <(d) MCPR <1.70 1.70 1.70 1.40 (e) MCPR <(h) Allowable Value: Low Power Range -Upscale Intermediate Power Range -Upscale High Power Range -Upscale (i) NTSP: Low Power Range -Upscale Intermediate Power Range -Upscale High Power Range -Upscale 1.70 124.6 119.6 114.6 124.2 119.2 114.2 NOTES: The RBM must be operable anytime the MCPR is less than the limits defined above for the given power range as defined in Technical Specification Table 3.3.2.1-1 Page 18 of 21 COLR2-15 NINE MILE POINT UNIT 2 Revision 0, Cycle 15 CORE OPERATING LIMITS REPORT
6.0 REFERENCES
FOR TECHNICAL SPECIFICATION 6.1 Technical Specification 5.6.5.b.1:
General Electric Standard Application for Reactor Fuel (GESTAR 1I), NEDE 24011-P-A-20 and NEDE 2401 1-P-A-20-US, December 2013.Page 19 of 21 COLR2-15 NINE MILE POINT UNIT 2 Revision 0, Cycle 15 CORE OPERATING LIMITS REPORT
7.0 REFERENCES
FOR TECHNICAL SPECIFICATION BASES Bases Reference 3 (Section 2.1.1): General Electric Standard Application for Reactor Fuel (GESTAR II), NEDE 2401 I-P-A-20 and NEDE 2401 1-P-A-20-US, December 2013.Bases Reference 4 (Section 2.1.1): Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt)
/ MELLLA (99-105% Flow), 000N2528-SRLR, Rev. 1, January 2014.Bases Reference 7 (Section 3.1.1): General Electric Standard Application for Reactor Fuel (GESTAR I1), NEDE 2401 1-P-A-20 and NEDE 24011 -P-A-20-US, December 2013.Bases Reference I (Section 3.1.6): Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt)
/ MELLLA (99-105% Flow), 000N2528-SRLR, Rev. 1, January 2014.Bases Reference 1 (Section 3.2.1): General Electric Standard Application for Reactor Fuel (GESTAR 11), NEDE 2401 1-P-A-20 and NEDE 2401 I-P-A-20-US, December 2013.Bases Reference 2 (Section 3.2.2): General Electric Standard Application for Reactor Fuel (GESTAR 11). NEDE 2401 I-P-A-20 and NEDE 24011-P-A-20-US, December 2013.Bases Reference 3 (Section 3.2.2): Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt)
/ MELLLA (99-105% Flow), 000N2528-SRLR, Rev. 1, January 2014.Bases Reference 1 (Section 3.2.3): General Electric Standard Application for Reactor Fuel (GESTAR 11), NEDE 2401 1-P-A-20 and NEDE 2401 1-P-A-20-US, December 2013.Bases Reference 2 (Section 3.2.3): Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt)
/ MELLLA (99-105% Flow), 000N2528-SRLR, Rev. 1, January 2014.Page 20 of 21 COLR2-15 NINE MILE POINT UNIT 2 Revision 0, Cycle 15 CORE OPERATING LIMITS REPORT 8.0 SOURCE DOCUMENTS Section 1.0 -APLHGR Limits 8.1. Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt)
/MELLLA (99-105% Flow), 000N2528-SRLR, Rev. 1, January 2014.Section 2.0 -MCPR Limits 8.2. Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt)
/MELLLA (99-105% Flow), 000N2528-SRLR, Rev. 1, January 2014.8.3. Nine Mile Point Station Unit 2 -APRM/RBM/Technical Specifications/Maximum Extended Load Line Limit Analysis (ARTS/MELLLA), NEDC-33286P, Rev. 0, March 2007 (NER-2E-037).
8.4. Nine Mile Point Nuclear Station Unit 2 ARTS/MELLLA, Task T0900, GE-NE-0000-0055-2373-RO, Rev. 0, February 2007 (NER-2E-037).
8.5. Engineering Report for Nine Mile Point Nuclear Station Unit 2, Reload 11, Cycle 12, 0000-0067-1271-ER, Rev 0, March 2008.Section 3.0 -LHGR Limits 8.6. Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt)
/MELLLA (99-105% Flow), 000N2528-SRLR, Rev. 1, January 2014.8.7. Nine Mile Point Nuclear Station Unit 2 -APRM/RBM/Technical Specifications/Maximum Extended Load Line Limit Analysis (ARTS/MELLLA), NEDC-33286P, Rev. 0, March 2007.8.8. Nine Mile Point Nuclear Station Unit 2 ARTS/MELLLA, Task T0900, GE-NE-0000-0055-2373-RO, Rev. 0, February 2007 (NER-2E-037).
8.9. Fuel Bundle Information Report for Nine Mile Point 2 Reload 14 Cycle 15, 000N0123-FBIR-P, Rev. 0 December 2013.8.10. GE 14 Compliance with Amendment 22 of NEDE-2401 I-P-A (GESTAR 11), NEDC-32868P, Revision 5, May 2013, MFN 13-028, May 2013.Section 4.0 -APRM Setpoints 8.11. Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt)
/MELLLA (99-105% Flow), 000N2528-SRLR, Rev. 1, January 2014.8.12. Design Specification Data Sheet 22A2843AM (NMPCNO NSSS161405000), Neutron Monitoring System.Section 5.0 -Control Rod Block Instrumentation 8.13. Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988MWt)
/MELLLA (99-105% Flow), 000N2528-SRLR, Rev. I, January 2014.8.14. Nine Mile Point Nuclear Station Unit 2 -APRM/RBM/Technical Specifications/Maximum Extended Load Line Limit Analysis (ARTS/MELLLA), NEDC-33286P, Rev. 0, March 2007.8.15. Instrument Limits Calculation Constellation Generation Group Nine Mile Point Nuclear Station Unit 2 Rod Block Monitor (NUMAC ARTS-MELLA), 0000-0053-1006 NMP2 A-M-T506-RBM-Calc-2006, Rev. 1, March 2008 (Found within NMP document NSSS 168805002).
Page 21 of 21