ML071280307

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Core Operating Limits Report, COLR1 -18, Revision 0
ML071280307
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 05/01/2007
From: Schimmel M
Constellation Energy Group
To:
Document Control Desk, NRC/NRR/ADRO
References
COLR1-18, Rev 0
Download: ML071280307 (21)


Text

Constellation Energy Nine Mile Point Nuclear Station P.O. Box 63 Lycoming, NY 13093 May 1, 2007 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 ATTENTION:

SUBJECT:

Document Control Desk Nine Mile Point Nuclear Station Unit No. 1; Docket No. 50-220 Core Operating Limits Report, COLRI -18 Revision 0 Attached is a copy of the Core Operating Limits Report, COLR1-18 Revision 0, for Nine Mile Point Unit 1 (NMP 1). This report is being submitted pursuant to NMP1 Technical Specification 6.6.5.d.Should you have any questions regarding the information in this submittal, please contact M. H. Miller, Director Licensing, at (315) 349-5219.Very truly you Mark A. Schimmel Plant General Manager MAS/MHS/

Attachment:

(1) Core Operating Limits Report, COLRI-18 Revision 0 cc: S. J. Collins, NRC Regional Administrator, Region I L. M. Cline, NRC Senior Resident Inspector M. J. David, NRR Project Manager AD I ATTACHMENT (1)NINE MILE POINT UNIT 1 CORE OPERATING LIMITS REPORT COLRI-18 REVISION 0 Nine Mile Point Nuclear Station, LLC May 1, 2007 NINE' MILE POINT UNIT 1 CORE OPERATING LIMITS REPORT Document No.: COLRI-18 Revision 0 Controlled Document Copy For Latest Information Check CDS ORIGINAL Name Title Date Prepared by: Reviewed by: Independently Reviewed by: C. W. Lepine Fuel Engineer J---. L. Winklebleck Fuel Engineer W. J. arter Fuel Engineer-ýzc 101I d~J$~oo7 Approved by: M. A. Armenta Engineering Supervisor, Nuclear Fuels Services Approved by: J. N. Darweesh 313c,1v I-Supervisor, Reactor Engineering Approved by: , :, P. I. Wengloski

/-)V'*, *-General Supervisor, Nuclear Fuels Services This Controlled Document provides cycle specific core operating limits for use in conjunction with the Nine Mile Point Unit I Technical Specifications.

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

NINE MILE POINT UNIT 1 COLRI-18 Rev. 0 TERMS AND DEFINITIONS Average Planar Linear Heat Generation Rate (APLHGR)The Average Planar Linear Heat Generation Rate (APLHGR) shall be applicable to a specific planar height and is equal to the sum of the heat generation rate per unit length of fuel rod for all fuel rods in the specified bundle at the specified height, divided by the number of fuel rods in the fuel bundle at that height.BOC Beginning of Cycle Core Maximum Fraction of Limiting Power Density (CMFLPD)The .highest value'of the fraction of limiting power density which exists in the core.Critical Power Ratio (CPR)The ratio of critical power to the bundle power at the reactor condition of interest.EOC End of Cycle EOR End of Rated Conditions (i.e. cycle exposure at 100% power, 100% flow, all rods-out, all feedwater heaters in service and equilibrium xenon)Fraction of Limiting Power Density (FLPD)The linear heat generation rate (LHGR) existing at a given location divided by the specified LHGR limit for that bundle type.FRTP Fraction of Rated Thermal Power where Rated Thermal Power equals 1850 MW K~f)MCPR flow dependent multiplier Linear Heat Generation Rate (LHGR)The heat generation per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the fuel length.MAPLHGR Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio (MCPR)The minimum in-core critical power ratio.RSLD Reload Specific Lattice Data Document Page ii NINE MILE POINT UNIT 1 COLRI-18 Rev. 0 CORE OPERA TING LIMITS REPORT 1.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)1.1 Limits for Technical Specification 3.1.7.a During power operation, the APLHGR for each type of fuel as function of axial location and average planar exposure shall not exceed the limiting values shown in Table I a, I b, I c, and I d.1.2 Limits for Technical Specification 3.1.7.e During partial loop operation with four recirculation loops in operation, the APLHGR as a function of axial location and average planar exposure shall not exceed 98 percent of the limiting values shown in Table la, lb, Ic, and Id.During partial loop operation with three recirculation loops in operation, the APLHGR as a function of axial location and average planar exposure shall not exceed 98 percent of the limiting values shown in Table la, lb, lc, and 1d.Page .1 of 18 NINE MILE POINT UNIT 1 COLRI-18 Rev. 0 2.0 MINIMUM CRITICAL POWER RATIO (MCPR)2.1 Limits for Technical Specification 3.1.7.c During power operation, the operating MCPR shall be greater than or equal to the Operating Limit MCPR0l) from the appropriate(2)

Figure (2a thru 2d) with tau (or"T") defined as follows: T (Tave -TB) / (-CA -TB)where: TA = 0.868 seconds, control rod average scram insertion time limit to notch 39 n TB= .672+ 1.65 * [N 1 /E Ni ]1/2 *.016 i=1 n n Tare FN Y i -c i) /(EN i i=1 i=l n = number of surveillance tests performed in cycle Ni = number of active control rods measured in the ith surveillance test Ti = average scram time to notch 39 of all rods measured in the it surveillance test N 1 = total number of active rods measured in the first test at BOC For core flows other than rated the MCPR limit shall be the Operating Limit MCPR identified above times K(f) where K(f).is as shown in Figure 2e.Additional limits for operation between 45% and 90% RTP(') (4) are required for operations without a backup pressure regulator.

These limits are shown in Figure 2f.2.2 Limits for Technical Specification 3.1.7.e During 3 loop operation, the Operating Limit MCPR shall be increased by 0.02. No adjustment is needed during 4 loop operation.

NOTES: 1. Based on a 1.07 MCPR Safety Limit (SLCPR).2. If the feedwater pump configuration, as defined by Nuclear Engineering Report No. NER-1M-022, is such that a feedwater controller failure could result in maximum feedwater flow greater than that for two feedwater pumps (i.e., the shaft-driven pump plus one motor-driven pump), then the Operating Limit MCPR shall be as shown in Figures 2c or 2d, depending on exposure.3. Below 45% and above 90% RTP no additional limits are required for operation without a backup pressure regulator.

4. These limits are valid for 3, 4, and 5 loop operation. (Note that for the MCPR Limit for 70% < P< 90%, i.e.MCPR Limit = (Rated OLMCPR) /FRTP, the Rated OLMCPR is as determined by 2.1 and 2.2 above.)5. EOR on Figures 2a through 2d is the end of rated exposure as defined in the Cycle Management report.Page 2 of 18 NINE MILE POINT UNIT 1 COLR1-18 Rev. 0 3.0 LINEAR HEAT GENERATION RATE (LHGR)3.1 Limits for Technical Specification 3.1.7.b During power operation, the Linear Heat Generation Rate (LHGR) of any rod in any fuel assembly at any axial location shall not exceed the limiting values shown in RSLD-19, Revision 0, "Nine Mile Point Unit I Reload 19, Reload Specific Lattice Data". This document contains the LHGR limits for both U02 rods. (which contain no gadolinium) and the most limiting gadolinium-bearing rods. Other gadolinium-bearing rods have LHGR limits which lie between these two curves. Compliance with these limits will be monitored by the plant's 3D-Monicore computer.Additional limits for operation between 45% and 90% RTP(1) are required for operations without a backup pressure regulator.

These limits are shown in Figure 3.NOTE: (1) Below 45% and above 90% RTP no additional limits are required for operation without a backup pressure regulator.

Page 3 of 18 NINE MILE POINT UNIT 1 COLRl-18 Rev. 0 4.0 POWER/FLOW RELATIONSHIP DURING OPERATION 4.1 Limits for Technical Specification 3.1.7.d and e The power/flow relationship shall not exceed the limiting values shown in Figure 4.Page 4 of 18 NINE MILE POINT UNIT 1 COLR1-18 Rev. 0 6.0 SOURCE DOCUMENTS The Core Operating Limits contained in this report were obtained from the following documents:

CORE OPERATING LIMITS REFERENCE APLHGR Limits (Section 1.0)Table 1 and corresponding three and four loop multipliers Lattice Descriptions MCPR Limits (Section 2)0000-0053-5239-SRLR, Revision 1, March 2007, Supplemental Reload Licensing Report for Nine Mile Point Nuclear Station Unit 1, Reload 19 Cycle 18 RSLD- 19 Nine Mile Point Unit I Reload 19 Specific Lattice Data .0000-0053-5239-SRLR, Revision 1, March 2007, Supplemental Reload Licensing Report for Nine Mile Point Nuclear Station Unit 1, Reload 19 Cycle 18 0000-0053-5247-ER, Revision 1, March 2007, Engineering Report for Nine Mile Point Nuclear Station Unit 1,Reload 19 GE-NE-J1 1-03433-16-0 1-Ri, "Pressure Regulator Out of Service Calculations for Nine Mile Point Unit 1", January 2005 NMP1CMR Nine Mile Point Unit I Cycle 18 Cycle Management Report Pressure Regulator Out-of-Service Restriction EOR Definition LHGR Limits (Section 3)Pressure Regulator Out-of-Service Restriction 0000-0053-5247-ER, Revision 1, March 2007, Engineering Report for Nine Mile Point Nuclear Station Unit 1,Reload 19 GE-NE-Ji 1-03433-16-0 1-Ri, "Pressure Regulator Out of Service Calculations for Nine Mile Point Unit 1", January 2005 NMP1 Technical Specification Amendment 92, Figure 3.1.7.aa Power/Flow Relationship (Section 4)Page 6 of 18 NINE MILE POINT UNIT 1 COLR1 -18, Revision 0 Table la MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE(1) (2)Average Planar Exposure MAPLHGR Limits (kw/ft)GWd/ST Bundle Bundle Bundle Bundle GEll-C15 GE11-C16A GE11-C16B GEll-C17 0.00 8.82 9.93 9.93 9.81 0.20 8.82 9.93 9.93 9.81 1.00 8.89 9.89 9.90 9.78* 5.00 9.22 9.78 9.70 9.64 10.00 9.56 9.61 9.67 9.49 15.00 9.50 9.53 9.53 9.36 17.50 9.49 9.53 9.53 -20.00 9.44 9.08 9.08 8.87 25.00 8.76 8.83 8.83 8.55 30.00 8.32 8.63 8.63 -35.00 8.43.* 8.60 8.60 8.47 45.00 8.51 8.62 8.62 8.48.50.00 -8.65 8.65 --55.00 8.58 8.66 8.66 8.54 65.00 8.65 6.38 6.38 8.63 NOTE: (1) A "--" indicates that there is no entry for this box and the limit can be determined by linearly interpolating between the previous and next point in each column.MAPLHGRs are interpolated between exposure points for which explicit values are given.(2) These MAPLHGR are not lattice dependent, therefore the values shown also correspond to the limiting value for the most limiting lattice for use when hand calculations are required.Fuel Type GEl 1 -P9DUB362-13GZ-1 OOT-1 45-T6-3899 GEl 1 -P9DUB376-12GZ-1 OT-145-T6-2585 GEl 1-P9DUB376-12GZ-10OT-145-T6-2586 GEl 1 -P9DUB382-13GZ-1 OOT-145-T6-2831 ID GEl1-C15 GE11-C16A GE11-C16B GE11-C17 Page 7 of 18 NINE MILE POINT UNIT 1 COLR1-18, Revision 0 Table l b MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Bundle Type: GEl 1-P9DUB381-13GZ-1OOT-145-T6-2945 (GEl 1)Average Planar MAPLHGR Limits(1) (kw/ft)Exposure Lattice Lattice Lattice .Lattice Lattice Lattice Most GWd/ST 7433 7434 7435 7436 7437 7438 Limiting 0.00 9.91 9.91 9.87 9.87 9.87 9.87 9.87 0.20 9.91 9.91 9.87 9.87 9.87 9.87 9.87 1.00 9.87 9.87 9.86 9.86 9.86 9.86 9.86 5.00 9.72 9.72 9.76 9.76 9.76 9.76 9.72 10.00 9.67 9.67 9.63 9.63 9.63 9.63 9.63 15.00 9.51 9.51 9.52 9.52 9.52 9.52 9.51 20.00 9.47 9.47 9.48 9.48 9.48 9.48 9.47 25.00 8.77 8.77 8.74 8.74 8.74 8.74 8.74 35.00 8.45 8.45 8.54 8.54 8.54 8.54 8.45 45.00 8.53 8.53 8.53 8.53 8.53 8.53 8.53 55.00 8.57 8.57 8.57 8.57 8.57 8.57 8.57 65.00 8.64 8.64 8.64 8.64 8.64 8.64 8.64 (1) These MAPLHGR are lattice dependent.

The values shown in the Most Limiting Column correspond to the limiting value for the most limiting lattice for use when hand calculations are required.

Lattice desciptions are contained in the RSLD.Page 8 of 18 NINE MILE POINT UNIT 1 COLR1-18, Revision 0 Table 1c MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Bundle Type: GEl I -P9DUB381-14GZ-1 OOT-145-T6-2946 (GEl 1)Average Planar MAPLHGR Limits(1) (kw/ft)Exposure Lattice Lattice Lattice Lattice Lattice Lattice Most GWd/ST 7433 7439 7440 7441 7442 7443 Limiting 0.00 10.56 10.56 10.51 10.51 10.51 10.51 10.51 0.20 10.56 10.56 10.51 10.51 10.51 10.51 10.51 1.00 10.52 10.52 10.51 10.51 10.51 10.51 10.51 5.00 10.22 10.22 10.16 10.16 10.16 10.16 10.16 10.00 9.72 9.72 9.63 9.63 9.63 9.63 9.63 15.00 9.51 9.51 9.48 9.48 9.48 9.48 9.48 20.00 9.48 9.48 9.49 9.49 9.49 9.49 9.48 25.00 9.00 9.00 8.97 8.97 8.97 8.97 8.97 35.00 8.50 8.50 8.48 8.48 8.48 8.48 8.48 45.00 8.56 8.56 8.54 8.54 8.54 8.54 8.54 55.00 8.62 8.62 8.60 8.60 8.60 8.60 8.60 65.00 8.70 8.70 8.69 8.69 8.69 8.69 8.69 (1) These MAPLHGR are lattice dependent.

The values shown in the Most Limiting Column correspond to the limiting value for the most limiting lattice for use when hand calculations are required.

Lattice desciptions are contained jn the RSLD.Page 9 of 18 NINE MILE POINT UNIT 1 COLRI-18, Revision 0 Table 1d MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Bundle Type: GEl I-P9DUB380-13GZ-1OOT-145-T6-2948 (GEl 1)Average Planar MAPLHGR Limits(1) (kwlft)Exposure Lattice Lattice Lattice Lattice Lattice Lattice Most GWd/ST 7433 7449 7450 7451 7447 7448 Limiting 0.00 -10.02 10.02 10.00 10.00 10.00 10.00 10.00 0.20 10.02 10.02 10.00 10.00 10.00 10.00 10.00 1.00 9.99 9.99 9.97 9.97 9.97 9.97 9.97 5.00 9.86 9.86 9.80 9.80 9.80 9.80 9.80 10.00 9.68 9.68 9.61 9.61 9.61 9.61 9.61 15.00 9.52 9.52 9.53 9.53 9.53 9.53 9.52 20.00 9.67 9.67 9.70 9.70 9.70 9.70 9.67 25.00 8.85 8.85 8.84 8.84 8.84 8.84 8.84 35.00 8.51 8.51 8.51 8.51 8.51 8.51 8.51 45.00 8.53 8.53 8.55 8.55 8.55 8.55 8.53 55.00 8.57 8.57 8.59 8.59 8.59 8.59 8.57 65.00 8.66 8.66 8.65 8.65 8.65 8.65 8.65 (1) These MAPLHGR are lattice dependent.

The values shown in the Most Limiting Column correspond to the limiting value for the most limiting lattice for use when hand calculations are required.

Lattice desciptions are contained in the RSLD.Page 10 of 18 NINE MILE POINT UNIT 1 COLR1-18 Rev. 0 Figure 2a MCPR Operating Limits for Two Feedwater Pump Maximum Flow (1)(Beginning Of Cycle to EOR-201 0 MWd/ST)1.52 1.5 1.48 a--, 1.46 0 S1.44 E E 1.42 1.4 (1, 1.49)1.38 0 0.2 0.4 0.6 0.8 1 Tau (1) as defined by Nuclear Engineering Report No. NER-1 M-022 Page 11 of 18 NINE MILE POINT UNIT 1 COLR1-18 Rev. 0 Figure 2b MCPR Operating Limits for Two Feedwater Pump Maximum Flow (1)(EOR-2010 MWd/ST to End Of Cycle)1.54 1.52 1.5 C-CT n 6.4m I 1.48 0 a.1.46 ,E E 1.44 1.42 (1, 1.52)1.4 0 0.2 0.4 0.6 0.8 Tau 1 (1) as defined by Nuclear Engineering Report No. NER-1MV-022 Page 12 of 18 NINE MILE POINT UNIT 1 COLR 1-18 Rev. 0 1.58 1.56 1.54 a.2 E:3 E-U E Figure 2c MCPR Operating Limits for Greater Than Two Feedwater Pump Maximum Flow (1)(Beginning Of Cycle to EOR-2010 MWd/ST)(0, 1.45)(1,.1.56)1.52 1.5 1.48 1.46 1.44 0 0.2 0.4 0.6 0.8 1 Tau (1) as defined by Nuclear Engineering Report No. NER-1M-022 Page 13 of 18 NINE MILE POINT UNIT 1 COLR 1-18 Rev. 0 Figure 2d MCPR Operating Limits, for Greater Than Two Feedwater Pump Maximum Flow (1)(EOR-2010 MWd/ST to End Of Cycle)1.6 1.58 1.56 a.r 1.54 0 1.52 E E 1.5 1.48 1.46 (1, 1.59)0 0.2 0.4 0.6 0.8 1 Tau (1) as defined by Nuclear Engineering Report No. NER-1 M-022 Page 14 of 18 NINE MILE POINT UNIT 1 COLRI-18, Revision 0 Figure 2e NMP-1 K(f) Curve for MCPR 1.5 f-1.4 1.3.a..107% Scoop Tube Setting K(f) = 1.50 when 45% > Flow,-102.5% K(f) = MAX( 1.0, 1.33075 -0.441-107.0% K(f) = MAX( 1.0, 1.35280 -0.441-112.0% K(f) = MAX( 1.0, 1.37926 -0.441-117.0% K(f) = MAX( 1.0, 1.40352 -0.441-Automatic K(f) = MAX( 1.0, 1.441 -0.441 Otherwise

  • Flow / 100%)* Flow/ 100%)* Flow/ 100%)* Flow/ 100%)* Flow/ 100%)1.2 1.1 0.9 112% Scoop Tube Setting/, /102.5%Y Scoop Tube Setting: 0 20 40 60 Core Flow (% of Rated)80 100 120 Page 15 of 18 NINE MILE POINT UNIT 1 COLRI-18, Rev. 0 Figure 2f: MCPR Limits for Operation Between 45% and 90% RTP Without a Backup Pressure Regulator 2.3 2.2 2.1/I, MCPR Limit (P) =For 45% < P < 70% AND Core Flow < 75% Flow MCPR Limit (P) = [1.73+0.011(70%-P)]

OR For 45% < P < 70% AND Core Flow > 75% Flow MCPR Limit (P) = [1,79+0.013(70%-P)]

~1-For 70% P<90%: MCPR Limit = (Rated OLMCPR) / FRTP (see Note 4, Page 2)\j Operating MCPR shall be _> MCPR Limit Line E 2 4-+Ný-Core Flow > 75%/7/1.9 1.8 1.7 Core Flow < 75%45 50 55 60 65 70 Core Thermal Power (P) in units of % Rated Thermal Power (%RTP)Page 16 of 18 NINE MILE POINT UNIT I COLRI -18 Rev. 0 Figure 3: LHGR Limits for Operation Between 45% and 90% RTP Without a Backup Pressure Regulator 1.2 0.8 00 0.6-j 0.4 0.2 0 45 50 55 60 65 70 75 80 85 90 Core Thermal Power (P) in units of % Rated Thermal Power (%RTP)Page 17 of 18 NINE MILE POINT UNIT 1 COLRI-18, Revision 0 Fign-4 Unilirrj Poer/ Rcw Umn ILMRtJO imoam_ __mm _ _ __ _ _ _ _ _ _ _").4-"a-I-0 200 GOD Uniting Rbv"/ How~in PAu-QWRoN+M_________

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