ML14126A724: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:}}
{{#Wiki_filter:a.EWExelon Generation April 24, 2014U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION:
 
==SUBJECT:==
Document Control DeskNine Mile Point Nuclear StationRenewed Facility Operating License No. NPF-69Unit No. 2; Docket No. 50-410Core Operating Limits ReportEnclosed is a copy of the Core Operating Limits Report, COLR2-15, Revision 0 for Nine Mile Point Unit2 (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. SwiftManager, Engineering ServicesPMS/MHS
 
==Enclosure:==
 
Nine Mile Point Unit 2 Core Operating Limits Reportcc: NRC Regional Administrator, Region INRC Project ManagerNRC Senior Resident Inspector AOD(
ENCLOSURE Nine Mile Point Unit 2Core Operating Limits ReportNine Mile Point Nuclear Station, LLCApril 24, 2014 NINE MILE POINT UNIT 2CORE OPERATING LIMITS REPORTCOLR2715Revision 0, Cycle 15Prepared by.NameMelisa KriekTitleFuels EngineerDateReviewed by:Approved by:Approved by:Approved by:Fuels EngineerSupervisor, Reactor EngineerJohn Darweessh 3/ /.Y//` V/ ISupervisor, FuelsiPhil WeyoskiGeneral Supervisor, FuelsThis controlled document provides cycle specific core operating limits for use in conjunction with theNine Mile Point Unit 2 Technical Specifications.
Document pages may only be changed through areissue of the entire document.
COLR2-15 NINE MILE POINT UNIT 2 Revision 0, Cycle 15CORE OPERATING LIMITS REPORTTABLE OF CONTENTSpage1.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 11.1 Limits for Technical Specification 3.2.1 12.0 MINIMUM CRITICAL POWER RATIO (OPTION B) 32.1 Limits for Technical Specification 3.2.2 32.2 Notes 43.0 LINEAR HEAT GENERATION RATE (LHGR) 123.1 Limits for Technical Specifications 3.2.3 124.0 AVERAGE POWER RANGE MONITOR SETPOINTS 174.1 Limits for Technical Specification Table 3.3.1.1-1 (OPRM Upscale) 175.0 CONTROL ROD BLOCK INSTRUMENTATION 185.1 Allowable Value for Technical Specification Table 3.3.2.1-1 1
 
==86.0 REFERENCES==
 
FOR TECHNICAL SPECIFICATIONS 1
 
==97.0 REFERENCES==
 
FOR TECHNICAL SPECIFICATION BASES 208.0 SOURCE DOCUMENTS 21Page i COLR2-15NINE MILE POINT UNIT 2CORE OPERATING LIMITS REPORTRevision 0,'Cycle 151.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)1.1 Limits for Technical Specification 3.2.1The APLHGR(s) for each fuel type as a function of Average Planar Exposure shall notexceed 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 COLR2-15NINE MILE POINT UNIT 2CORE OPERATING LIMITS REPORTRevision 0, Cycle 15Table 1MAPLHGR versus Average Planar ExposureAverage Planar Exposure MAPLHGR Limits(GWD/ST)
(KW/ft)0.00 12.8214.51 12.8219.13 12.8257.61 8.0063.50 5.00NOTES:1. APLHGR(s) are interpolated between exposure points for which explicit values are givenPage 2 of 21 COLR2-15NINE MILE POINT UNIT 2CORE OPERATING LIMITS REPORTRevision 0, Cycle 152.0 MINIMUM CRITICAL POWER RATIO (OPTION B).2.1 Limits for Technical Specification 3.2.2The Minimum Critical Power Ratio (MCPR) shall be greater than or equal to theOperating 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 2Minimum Critical Power RatioTwo Recirculation Loop Operation (TLO) Condition MCPR(P) = OLMCPR( 100) x K(P) P(bypass)
< P < 100%orMCPR(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%orMCPR(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 PowerPage 3 of 21 COLR2-15 NINE MILE POINT UNIT 2 Revision 0, C0 CORE OPERATING LIMITS REPORT2.2 Notes1. For Figures 2a and 2b tau (T) is defined as follows:*r ave -- 1"BA Bwhere:rA = 0.866 seconds, control rod average scram insertion time limit to notch 39 per Technical Specification 3.1.4.r, =O0672+i1.65 N1X(O.0 I6i=1n1=In = number of surveillance tests performed in cycleN, = number of active control rods measured in the it surveillance testz, = average scram time to notch 39 of all rods measured in the ihsurveillance testN 1 = total number of active rods measured in Specification 3.1.4.1IT 1.0 prior to performance of the initial scram time measurements for the cycle2. ARTS provides for power- and flow-dependent thermal limit adjustments and*multipliers, which allow for a more reliable administration of the MCPR thermallimit. 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 wereconverted to a K(P) consistent with the ARTS offrated limits. MCPR(F) isindependent of Scram Time Option and all EOOS.3. The Operating Limit MCPR values for TBVOOS and EOC-RPT Out ofService are higher (more limiting) than for the standard normal operation case, andare therefore specifically identified where appropriate (Figures 2a and 2b). TheOLMCPR values for all other analyzed EOOS transient events are bounded by theNormal Operation limits.4. EOR is the End of Rated exposure as defined in the Cycle Management Report.ycle 15Page 4 of 21 CO0-I 5NINE MILE PNT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYCLOFigure 2aOperating Limit MCPR(BOC to EOR-2816 MWd/ST)CLE.01.801.751.701.651.601.551.501.451.401.351.30(1,1.73)(1,1.63)(1,1.61)00.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9Tau1Page 5 of 21 C -15NINE MILE ONT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYCL950t(L7BEME.1.801.751.701.651.601.551.50Figure 2bOperating Limit MCPR(EOR-2816 MWd/ST to EOC)EOC-RPT INormal Operation (0,1.38)(1,1.63)(1,1.62)1.451.401.351.3000.1 0.20.3 0.4 0.5 0.60.7 0.8 0.91Ta uPage 6 of 21 C.2-15NINE MILEONT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYC*5Figure 2cMCPR(P) for <26%Power,
<75%FlowK(P) for >26% Powerfor Equipment In ServiceI-Wn.CL3.5003.2503.0002.7502.5002.2502.0001.7501.5001.2501.000(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 or2b) 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%--7&#xfd;&#xfd;&#xfd;1.336)-(60, 1.150)(55, 1.193)(85, 1.056)(100, 1.000)~ -.L4 + 4 ~.20 25 30 35 40 45 50 55 60Power (% Rate65 70 75 80 85 90 95 100Page 7 of 21 C*2-15NINE MILEONT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYC05Figure 2dMCPR(P) for <26%Power,
<75%FlowK(P) for >26% Powerfor Recirculation Pump Trip Out of Service1133.5003.2503.0002.7502.5002.2502.0001.7501.5001.250.1 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 or2b) 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_ /III 20 25 30 35 40 45 50 55 60 65Power (% Rated)1 1 I I70 75 80 85 90 95 100Page 8 of 21
.COO-15NINE MIiLE *T UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYCJ*Figure 2eMCPR(P) for <26%Power,
<75%FlowK(P) for >26% Powerfor Turbine Bypass Valve Out of Service3.5003.2503.0002.7502.5002.2502.000(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 or2b) 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 -j&#xfd; _C.,061.7501.5001.2501.000(55, 1.336)60, 1.150)(55, 1.193)(85, 1.056)(100, 1.000).--4 + 420 25 3035 40 45 50 55 60 65Power (% Rated)70 75 80 85 90 95 100Page 9 of 21 C.2-15NINE MILERNT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYC*5Figure 2fMCPR(P) for <26%Power,
<75%FlowK(P) for >26% Powerfor Operation without a Backup Pressure Regulator C.,Ve3.5003.2503.0002.7502.5002.2502.0001.7501.5001.2501.000*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)1.00020 25 30 35 40 45 5055 60 65 70 75 80 85 90 95 100Power (% Rated)Page 10 of 21
.2 -15NINE MILANT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CY05Figure 2gFlow-Dependent MCPR Limits1.801.701.601.50U.0~C.)1.401.301.201.102030 405060 70Flow (% Rated)80 90100110120Page 11 of 21 COLR2-15NINE MILE POINT UNIT 2CORE OPERATING LIMITS REPORTRevision 0, Cycle 153.0 LINEAR HEAT GENERATION RATE (LHGR)3.1 Limits for Technical Specification 3.2.3During power operation, the Linear.Heat Generation Rate (LHGR) in any fuel rod in anyfuel 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 rodsand Table D-4 for U02 rods containing Gadolinium inSource Document 8.10LHGRFAC(P)
= Applicable core power dependent multiplier from Figures3a, 3b, or 3cLHGRFAC(F)
= Applicable core flow dependent multiplier from Figure 3dLHGR(SLO)
= Applicable Single Loop Operation (SLO) PLHGR multiplier Table 3Linear Heat Generation RateTwo Recirculation Loop Operation (TLO) Condition LHGR = LHGR(100) x LHGRFAC(P) 23% < P < 100%orLHGR = LHGRFAC(F)
F > 30%Single Recirculation Loop Operation (SLO) Condition LHGR = LHGR(100) x LHGRFAC(P) 23% < P < 100%orLHGR = LHGR(100) x LHGRFAC(F)
F _ 30%orLHGR = LHGR(100) x LHGR(SLO)
SLONote: 1) LHGR(SLO)
= 0.782) ARTS provides for power- and flow-dependent thermal limit multipliers, which allow for a more reliableadministration 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 alsopresented in a manner more consistent with the ARTS offrated limits. LHGRFAC(F) is identical for allEOOS.Page 12 of 21 CW-15NINE MILEONT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYC95Figure 3aLHGRFAC(P) for < 26% Power, < 75% FlowLHGRFAC(P) for a 26% PowerIuipment In Service and Recirculation Pump Trip 01.0000.9000.8000.7000.6000.5000.400a.U-LI"-J0.3000.2000.1000.0002025 30 35 40 45 50 55 60 .65Power (% Rated)70 75 80 85 90 95 100Page 13 of 21 C.2-15NINE MILEINT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYC*5Figure 3bLHGRFAC(P) for < 26% Power, < 75% FlowLHGRFAC(P) for 2 26% Powerfor Turbine BvDass Valve Out of Service0-0U-,-J1.0000.9000.8000.7000.6000.5000.4000.3000.2000.1000.00020 25 30 35 40 45 50 55 60 65Power (% Rated)70 75 80 85 90 95 100Page 14 of 21 COW-15NINE MILEONT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYCL*5Figure 3cLHGRFAC(P) for < 26% Power, < 75% FlowLHGRFAC(P) for > 26% Powerfor Operation without a Backup Pressure Regulator (100, 1.000)1.0000.9000.8000.7000.600LLU-0.5000.4000.3000.2000.1000.00020 25 30 35 40 45 50 55 60 65Power (% Rated)70 75 80 85 90 95 100Page 15 of 21 C-15NINE MILE9INT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYC#5U-0"-J1.1001.0000.9000.8000.7000.6000.5000.4000.3000.2000.1000.000Figure 3dFlow-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%..&deg; ........2030405060 70Flow (% Rated)8090 100110120Page 16 of 21 COLR2-15 NINE MILE POINT UNIT 2 Revision 0, Cycle 15CORE OPERATING LIMITS REPORT4.0 AVERAGE POWER RANGE MONITOR SETPOINTS 4.1 Limits for Technical Specification Table 3.3.1.1-1 (OPRM Upscale)Allowable value < 1.14Page 17 of 21 COLR2-15NINE MILE POINT UNIT 2CORE OPERATING LIMITS REPORTRevision 0, Cycle 155.0 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 <1.701.701.701.40(e) MCPR <(h) Allowable Value:Low Power Range -UpscaleIntermediate Power Range -UpscaleHigh Power Range -Upscale(i) NTSP:Low Power Range -UpscaleIntermediate Power Range -UpscaleHigh Power Range -Upscale1.70124.6119.6114.6124.2119.2114.2NOTES:The RBM must be operable anytime the MCPR is less than the limits defined above for thegiven 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 15CORE 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 15CORE OPERATING LIMITS REPORT
 
==7.0 REFERENCES==
 
FOR TECHNICAL SPECIFICATION BASESBases Reference 3 (Section 2.1.1):General Electric Standard Application for Reactor Fuel (GESTAR II), NEDE 2401 I-P-A-20 andNEDE 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 PowerUprate (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 andNEDE 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 PowerUprate (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 andNEDE 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 andNEDE 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 PowerUprate (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 andNEDE 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 PowerUprate (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 15CORE OPERATING LIMITS REPORT8.0 SOURCE DOCUMENTS Section 1.0 -APLHGR Limits8.1. 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 Limits8.2. 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, February2007 (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, March2008.Section 3.0 -LHGR Limits8.6. 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 LimitAnalysis (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, February2007 (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 LimitAnalysis (ARTS/MELLLA),
NEDC-33286P, Rev. 0, March 2007.8.15. Instrument Limits Calculation Constellation Generation Group Nine Mile Point Nuclear Station Unit 2 Rod BlockMonitor (NUMAC ARTS-MELLA),
0000-0053-1006 NMP2 A-M-T506-RBM-Calc-2006, Rev. 1, March 2008 (Foundwithin NMP document NSSS 168805002).
Page 21 of 21}}

Revision as of 16:54, 1 July 2018

Nine Mile Point Nuclear Station - Core Operating Limits Report
ML14126A724
Person / Time
Site: Nine Mile Point Constellation icon.png
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, 2014U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION:

SUBJECT:

Document Control DeskNine Mile Point Nuclear StationRenewed Facility Operating License No. NPF-69Unit No. 2; Docket No. 50-410Core Operating Limits ReportEnclosed is a copy of the Core Operating Limits Report, COLR2-15, Revision 0 for Nine Mile Point Unit2 (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. SwiftManager, Engineering ServicesPMS/MHS

Enclosure:

Nine Mile Point Unit 2 Core Operating Limits Reportcc: NRC Regional Administrator, Region INRC Project ManagerNRC Senior Resident Inspector AOD(

ENCLOSURE Nine Mile Point Unit 2Core Operating Limits ReportNine Mile Point Nuclear Station, LLCApril 24, 2014 NINE MILE POINT UNIT 2CORE OPERATING LIMITS REPORTCOLR2715Revision 0, Cycle 15Prepared by.NameMelisa KriekTitleFuels EngineerDateReviewed by:Approved by:Approved by:Approved by:Fuels EngineerSupervisor, Reactor EngineerJohn Darweessh 3/ /.Y//` V/ ISupervisor, FuelsiPhil WeyoskiGeneral Supervisor, FuelsThis controlled document provides cycle specific core operating limits for use in conjunction with theNine Mile Point Unit 2 Technical Specifications.

Document pages may only be changed through areissue of the entire document.

COLR2-15 NINE MILE POINT UNIT 2 Revision 0, Cycle 15CORE OPERATING LIMITS REPORTTABLE OF CONTENTSpage1.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 11.1 Limits for Technical Specification 3.2.1 12.0 MINIMUM CRITICAL POWER RATIO (OPTION B) 32.1 Limits for Technical Specification 3.2.2 32.2 Notes 43.0 LINEAR HEAT GENERATION RATE (LHGR) 123.1 Limits for Technical Specifications 3.2.3 124.0 AVERAGE POWER RANGE MONITOR SETPOINTS 174.1 Limits for Technical Specification Table 3.3.1.1-1 (OPRM Upscale) 175.0 CONTROL ROD BLOCK INSTRUMENTATION 185.1 Allowable Value for Technical Specification Table 3.3.2.1-1 1

86.0 REFERENCES

FOR TECHNICAL SPECIFICATIONS 1

97.0 REFERENCES

FOR TECHNICAL SPECIFICATION BASES 208.0 SOURCE DOCUMENTS 21Page i COLR2-15NINE MILE POINT UNIT 2CORE OPERATING LIMITS REPORTRevision 0,'Cycle 151.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)1.1 Limits for Technical Specification 3.2.1The APLHGR(s) for each fuel type as a function of Average Planar Exposure shall notexceed 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 COLR2-15NINE MILE POINT UNIT 2CORE OPERATING LIMITS REPORTRevision 0, Cycle 15Table 1MAPLHGR versus Average Planar ExposureAverage Planar Exposure MAPLHGR Limits(GWD/ST)

(KW/ft)0.00 12.8214.51 12.8219.13 12.8257.61 8.0063.50 5.00NOTES:1. APLHGR(s) are interpolated between exposure points for which explicit values are givenPage 2 of 21 COLR2-15NINE MILE POINT UNIT 2CORE OPERATING LIMITS REPORTRevision 0, Cycle 152.0 MINIMUM CRITICAL POWER RATIO (OPTION B).2.1 Limits for Technical Specification 3.2.2The Minimum Critical Power Ratio (MCPR) shall be greater than or equal to theOperating 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 2Minimum Critical Power RatioTwo Recirculation Loop Operation (TLO) Condition MCPR(P) = OLMCPR( 100) x K(P) P(bypass)

< P < 100%orMCPR(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%orMCPR(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 PowerPage 3 of 21 COLR2-15 NINE MILE POINT UNIT 2 Revision 0, C0 CORE OPERATING LIMITS REPORT2.2 Notes1. For Figures 2a and 2b tau (T) is defined as follows:*r ave -- 1"BA Bwhere:rA = 0.866 seconds, control rod average scram insertion time limit to notch 39 per Technical Specification 3.1.4.r, =O0672+i1.65 N1X(O.0 I6i=1n1=In = number of surveillance tests performed in cycleN, = number of active control rods measured in the it surveillance testz, = average scram time to notch 39 of all rods measured in the ihsurveillance testN 1 = total number of active rods measured in Specification 3.1.4.1IT 1.0 prior to performance of the initial scram time measurements for the cycle2. ARTS provides for power- and flow-dependent thermal limit adjustments and*multipliers, which allow for a more reliable administration of the MCPR thermallimit. 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 wereconverted to a K(P) consistent with the ARTS offrated limits. MCPR(F) isindependent of Scram Time Option and all EOOS.3. The Operating Limit MCPR values for TBVOOS and EOC-RPT Out ofService are higher (more limiting) than for the standard normal operation case, andare therefore specifically identified where appropriate (Figures 2a and 2b). TheOLMCPR values for all other analyzed EOOS transient events are bounded by theNormal Operation limits.4. EOR is the End of Rated exposure as defined in the Cycle Management Report.ycle 15Page 4 of 21 CO0-I 5NINE MILE PNT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYCLOFigure 2aOperating Limit MCPR(BOC to EOR-2816 MWd/ST)CLE.01.801.751.701.651.601.551.501.451.401.351.30(1,1.73)(1,1.63)(1,1.61)00.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9Tau1Page 5 of 21 C -15NINE MILE ONT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYCL950t(L7BEME.1.801.751.701.651.601.551.50Figure 2bOperating Limit MCPR(EOR-2816 MWd/ST to EOC)EOC-RPT INormal Operation (0,1.38)(1,1.63)(1,1.62)1.451.401.351.3000.1 0.20.3 0.4 0.5 0.60.7 0.8 0.91Ta uPage 6 of 21 C.2-15NINE MILEONT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYC*5Figure 2cMCPR(P) for <26%Power,

<75%FlowK(P) for >26% Powerfor Equipment In ServiceI-Wn.CL3.5003.2503.0002.7502.5002.2502.0001.7501.5001.2501.000(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 or2b) 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)~ -.L4 + 4 ~.20 25 30 35 40 45 50 55 60Power (% Rate65 70 75 80 85 90 95 100Page 7 of 21 C*2-15NINE MILEONT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYC05Figure 2dMCPR(P) for <26%Power,

<75%FlowK(P) for >26% Powerfor Recirculation Pump Trip Out of Service1133.5003.2503.0002.7502.5002.2502.0001.7501.5001.250.1 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 or2b) 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_ /III 20 25 30 35 40 45 50 55 60 65Power (% Rated)1 1 I I70 75 80 85 90 95 100Page 8 of 21

.COO-15NINE MIiLE *T UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYCJ*Figure 2eMCPR(P) for <26%Power,

<75%FlowK(P) for >26% Powerfor Turbine Bypass Valve Out of Service3.5003.2503.0002.7502.5002.2502.000(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 or2b) 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.,061.7501.5001.2501.000(55, 1.336)60, 1.150)(55, 1.193)(85, 1.056)(100, 1.000).--4 + 420 25 3035 40 45 50 55 60 65Power (% Rated)70 75 80 85 90 95 100Page 9 of 21 C.2-15NINE MILERNT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYC*5Figure 2fMCPR(P) for <26%Power,

<75%FlowK(P) for >26% Powerfor Operation without a Backup Pressure Regulator C.,Ve3.5003.2503.0002.7502.5002.2502.0001.7501.5001.2501.000*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)1.00020 25 30 35 40 45 5055 60 65 70 75 80 85 90 95 100Power (% Rated)Page 10 of 21

.2 -15NINE MILANT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CY05Figure 2gFlow-Dependent MCPR Limits1.801.701.601.50U.0~C.)1.401.301.201.102030 405060 70Flow (% Rated)80 90100110120Page 11 of 21 COLR2-15NINE MILE POINT UNIT 2CORE OPERATING LIMITS REPORTRevision 0, Cycle 153.0 LINEAR HEAT GENERATION RATE (LHGR)3.1 Limits for Technical Specification 3.2.3During power operation, the Linear.Heat Generation Rate (LHGR) in any fuel rod in anyfuel 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 rodsand Table D-4 for U02 rods containing Gadolinium inSource Document 8.10LHGRFAC(P)

= Applicable core power dependent multiplier from Figures3a, 3b, or 3cLHGRFAC(F)

= Applicable core flow dependent multiplier from Figure 3dLHGR(SLO)

= Applicable Single Loop Operation (SLO) PLHGR multiplier Table 3Linear Heat Generation RateTwo Recirculation Loop Operation (TLO) Condition LHGR = LHGR(100) x LHGRFAC(P) 23% < P < 100%orLHGR = LHGRFAC(F)

F > 30%Single Recirculation Loop Operation (SLO) Condition LHGR = LHGR(100) x LHGRFAC(P) 23% < P < 100%orLHGR = LHGR(100) x LHGRFAC(F)

F _ 30%orLHGR = LHGR(100) x LHGR(SLO)

SLONote: 1) LHGR(SLO)

= 0.782) ARTS provides for power- and flow-dependent thermal limit multipliers, which allow for a more reliableadministration 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 alsopresented in a manner more consistent with the ARTS offrated limits. LHGRFAC(F) is identical for allEOOS.Page 12 of 21 CW-15NINE MILEONT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYC95Figure 3aLHGRFAC(P) for < 26% Power, < 75% FlowLHGRFAC(P) for a 26% PowerIuipment In Service and Recirculation Pump Trip 01.0000.9000.8000.7000.6000.5000.400a.U-LI"-J0.3000.2000.1000.0002025 30 35 40 45 50 55 60 .65Power (% Rated)70 75 80 85 90 95 100Page 13 of 21 C.2-15NINE MILEINT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYC*5Figure 3bLHGRFAC(P) for < 26% Power, < 75% FlowLHGRFAC(P) for 2 26% Powerfor Turbine BvDass Valve Out of Service0-0U-,-J1.0000.9000.8000.7000.6000.5000.4000.3000.2000.1000.00020 25 30 35 40 45 50 55 60 65Power (% Rated)70 75 80 85 90 95 100Page 14 of 21 COW-15NINE MILEONT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYCL*5Figure 3cLHGRFAC(P) for < 26% Power, < 75% FlowLHGRFAC(P) for > 26% Powerfor Operation without a Backup Pressure Regulator (100, 1.000)1.0000.9000.8000.7000.600LLU-0.5000.4000.3000.2000.1000.00020 25 30 35 40 45 50 55 60 65Power (% Rated)70 75 80 85 90 95 100Page 15 of 21 C-15NINE MILE9INT UNIT 2CORE OPERATING LIMITS REPORTREVISION 0, CYC#5U-0"-J1.1001.0000.9000.8000.7000.6000.5000.4000.3000.2000.1000.000Figure 3dFlow-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%..° ........2030405060 70Flow (% Rated)8090 100110120Page 16 of 21 COLR2-15 NINE MILE POINT UNIT 2 Revision 0, Cycle 15CORE OPERATING LIMITS REPORT4.0 AVERAGE POWER RANGE MONITOR SETPOINTS 4.1 Limits for Technical Specification Table 3.3.1.1-1 (OPRM Upscale)Allowable value < 1.14Page 17 of 21 COLR2-15NINE MILE POINT UNIT 2CORE OPERATING LIMITS REPORTRevision 0, Cycle 155.0 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 <1.701.701.701.40(e) MCPR <(h) Allowable Value:Low Power Range -UpscaleIntermediate Power Range -UpscaleHigh Power Range -Upscale(i) NTSP:Low Power Range -UpscaleIntermediate Power Range -UpscaleHigh Power Range -Upscale1.70124.6119.6114.6124.2119.2114.2NOTES:The RBM must be operable anytime the MCPR is less than the limits defined above for thegiven 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 15CORE 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 15CORE OPERATING LIMITS REPORT

7.0 REFERENCES

FOR TECHNICAL SPECIFICATION BASESBases Reference 3 (Section 2.1.1):General Electric Standard Application for Reactor Fuel (GESTAR II), NEDE 2401 I-P-A-20 andNEDE 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 PowerUprate (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 andNEDE 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 PowerUprate (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 andNEDE 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 andNEDE 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 PowerUprate (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 andNEDE 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 PowerUprate (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 15CORE OPERATING LIMITS REPORT8.0 SOURCE DOCUMENTS Section 1.0 -APLHGR Limits8.1. 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 Limits8.2. 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, February2007 (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, March2008.Section 3.0 -LHGR Limits8.6. 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 LimitAnalysis (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, February2007 (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 LimitAnalysis (ARTS/MELLLA),

NEDC-33286P, Rev. 0, March 2007.8.15. Instrument Limits Calculation Constellation Generation Group Nine Mile Point Nuclear Station Unit 2 Rod BlockMonitor (NUMAC ARTS-MELLA),

0000-0053-1006 NMP2 A-M-T506-RBM-Calc-2006, Rev. 1, March 2008 (Foundwithin NMP document NSSS 168805002).

Page 21 of 21