BVY 06-023, Revised Core Operating Limits Report for Cycle 25
| ML060750575 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 03/13/2006 |
| From: | Devincentis J Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BVY 06-023 | |
| Download: ML060750575 (27) | |
Text
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
Vermont Yankee
- EntegAy P.O. Box 0500 185 Old Ferry Road Brattleboro, Vr 05302-0500 Tel 802 257 5271 March 13, 2006 BVY 06-023 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)
Revised Core Operatine Limits Report for Cycle 25 In accordance with the Vermont Yankee Technical Specifications, section 6.6.C, please find enclosed the Core Operating Limits Report for Vermont Yankee Cycle 25, Revision 1, dated February 2006. This report presents the cycle-specific operating limits for the operation of Vermont Yankee Nuclear Power Station during Cycle 25.
If you have any questions concerning this transmittal, please contact me at (802) 258-4236.
Sincerely, for James M. DeVincentis Manager, Licensing Enclosure cc: USNRC Region I Administrator USNRC Resident Inspector - VYNPS USNRC Projxct Manager - VYNPS Vermont Department of Public Service ADO(1
R Vermont Yankee Nuclear Power Station Cycle 25 Core Operating Limits Report Revision 1 February 2006 Prepared RdctrEngineerOin Date Reviewed Reactor Engineer (rsi ign) Date Approved ~~vir 1 4 A14puj e n tRector En ering (Print/Sign) Date Reviewed 6 On-Site Saf Revi6w Committee (Print/Sigh)
I Approved General Manager, PltOjpations (Print/Sign) Date
REVISION RECORD Cycle Revision Date Description 25 . (I 10/2005 Cycle 25 revision.
25 I 02/2006 Implementation of Extended Power Uprate.
Cycle 25 COLR Vermont Yankee Nuclear Power Station Revision I Revision Record Page i of i
ABSTRACT This report presents Cycle 25 specific operating limits at current license thermal power I (1912 thermal megawatts)for the operation of the Vermont Yankee Nuclear Power Station as specified in Technical Specification 6.6.C. The limits included in the report are average planar linear heat generation rate, linear heat generation rate, minimum critical power ratio, and thermal-hydraulic stability exclusion region.
The requirement of Technical Specifications Table 3.2.5 pertaining to the rod block monitor (RBM) setpoint equation maximum value of N for single loop and dual loop operation are included in this report.
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TABLE OF CONTENTS PAge LIST OF TABLES ............. ii LIST OF FIGURES ............. iii
1.0 INTRODUCTION
.. I 2.0 CORE OPERATING LIMITS .................... 2-2.1 Average Planar Linear Heat Generation Rate Limits (APLHGR) .2 2.2 Minimum Critical Power Ratio (MCPR) Limits .2 2.3 Linear Heat Generation Rate (LHGR) Limits .4 2.4 Thermal-Hydraulic Stability Exclusion Region .5 2.5 Power/Flow Map .7 2.6 Single Loop Operation .7 2.7 Rod Blockc Monitoring.. 8 REFERENCES .. ......... 20 Cycle 25 COLR Vermont Yankee Nuclear Power Station Revision 1 Table of Contents Page i of iii
TABLE OF CONTENTS (Continued)
LIST OF TABLES Number Title Page Table 2.1-1 MAPLHGR Limits for GE 314-P I ODNAB426-1 6G6.0-1 OOT-1 50-T6-2682 Fuel Bundle No. 2682 .................................... 9 Table 2.1-2 MAPLHGR Limits for G3 14-P I ODNAB390-1 4GZ- I OOT- I 50-T6-2683 Fuel Bundle No. 2683 .................................... 9 Table 2.1-3 MAPLHGR Limits for G]l.14-P 1ODNAB388-1 7GZ-1 OOT-1 50-T6-2684 Fuel Bundle No. 2684 ............. 10 Table 2.1-4 MAPLHGR Limits for G],14-PI ODNAB422-1 6(3Z-IOOT-1 50-T6-2862 Fuel Bundle No. 2862 ............. 10 Table 2.1-5 MAPLHGR Limits for Gl314-P 1ODNAB383-13(J6.0-1 OOT-1 50-T6-2863 Fuel BundleNo. 2863 .............. 11 Table 2.1-6 MAPLHGR Limits for GE 14-P1 ODNAB388-1 7(GZ-1 OOT-I 50-T6-2864 Fuel Bundle No. 2864 .............. 11 Table 2.1-7 MAPLHGR Limits for GlE14-P1 ODNAB383-1 7(G6.0-1 OOT-1 50-T6-2865 Fuel Bundle No. 2865 .............. 12 Table 2.1-8 MAPLHGR Limits for GE 14-P I ODNAB394-7G5.0/6G4.0- 1OOT-I 50-T6-2566 Fuel Bundle No. 2566 .............. 12 Table 2.1-9 MAPLHGR Limits for GE314-P 1ODNAB394-8G5.0/6G4.0-1 OOT- 150-T6-2595 Fuel Bundle No. 2595 .............. 13 Table 2.1-10 MAPLHGR Limits for GEl14-P1 ODNAB394-12(G5.0-lOOT-1 50-T6-2596 Fuel Bundle No. 2596 .............. 13 Table 2.2-1 Cycle 25 Rated MCPR Operating Limits (OLMCPR) .............................. 14 Table 2.2-2 RBM Setpoint .................................... 14 Cycle 25 COLR Vermont Yankee Nuclear Power Station Revision 1 Table of Contents Page ii of iii
TABLE OF CONTENTS (Continued)
LIST OF FIGURES Number Title Page 2.2-1. Power Dependent K (P) / MCPR (P) Limits ................................... 15 2.2-2 Flow Dependent MCPR Operating Limit MCPR (F) ................................... 16 2.3-1 Power Dependent LHGRFAC (P) Multiplier ................................... 17 2.3-2 LHGR Flow Factor LHGRFAC (F).......................................................................18 2.4-1 Limits of Power/Flow Operation ................................... 19 Cycle 25 COLR Vermont Yankee Nuclear Power Station Revision 1 Table of Contents Page iii of iii
1.0 INTRODUCTION
This report provides the cycle-specific limits for operation of the Vermont Yankee Nuclear Power Station in Cycle 25. It includes the limits for the average planar linear heat generation rate, linear heat generation rate, minimum critical power ratio, and thermal-hydraulic stability exclusion region. If any of these limits are exceeded, action will be taken as defined in the Technical Specifications.
As specified in Technical Specifications Table 3.2.5, the rod block monitor (RBM) setpoint equation maximum value of N for single loop and dual loop operation are included in this report.
This Core Operating Limits report for Cycle 25 has been prepared in accordance with the requirements of Technical Specifications 6.6.C. The core operating limits have been developed using the NRC-approved methodologies listed in References 3.1 through 3.4. The methodologies are also listed in Technical Specification 6.6.C. The bases for these limits are in References 3.5 through 3.8.
As documented in the Vermont Yankee Extended Power Uprate (EPU) Safety Evaluation and resulting License Condition (Reference 3.10), when operating at thermal power greater than 1593 megawatts thermal, the safety limit minimum critical power ratio (SLMCPR) shall be established by adding 0.02 to the cycle-specific SLMCPR value calculated using the NRC approved methodologies documented in General Electric Licensing Topical Report NEDE-2401 1-P-A, "General Electric Standard Application for Reactor Fuel", as amended and documented in the Core Operating Limits Report.
In Cycle 25 at EPU conditions, the calculated SLMCPR was determined to be 1.05 (dual loop) and 1.07 (single loop) (Reference 3.6).
Therefore, the current SLMCPR documented in Technical Specification I.l.A (1.07 dual loop and 1.09 single loop) remain valid based on the above licensing condition.
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2.0 CORE OPERATING LIMITS The Cycle 25 operating limits have been defined using NRC-approved methodologies. Cycle 25 must be operated within the bounds of tlese limits and all others specified in the Technical Specifications.
2.1. Average Planar Linear Heat Generation Rate Limits (APLHGR) (T.S. 3.11 .A)
APLHGR. is applicable to a specific planar height and is equal to the sum of the linear heat generation rate (LHGR) for all of the fuel rods in the specific bundle at the specific height divided by the number of fuel rods in the fuel bundle at the height.
The maximum APLHGR (MAPLHGR) limit is a function of reactor power, core flow, fuel type, and average planar exposure. The cycle dependent limits are developed using NRC approved methodology described in References 3.1 and 3.3. The MAPLHGR limit ensures that the peak clad temperature during a LOCA will not exceed the limits as specified in I0CFR50.46 (b) (1) and that the fuel design analysis criteria defined in References 3.1 and 3.3 will be mnet.
Tables 2.1-1 through 2.1-10 provide a limiting composite of MAPLHGR values for each fuel type, which envelope the lattice MAPLHGR values employed by the process computer (Reference 3.6). When hand calculations are required, these MAPLHGR values are used for all lattices in the bundle.
For single recirculation loop operation, the limiting values shall be the values from these Tables listed under the heading "Single Loop Operation." These values are obtained by multiplying the values for two loop operation by 0.82 (Reference 3.6 and 3.9).
The poweT and flow dependent MAPLHGR limits (MAPFAC multipliers) are identical to the LHGR limits (LHGRFAC multipliers) in Figure 2.3-1 and 2.3-2 since the power and flow dependent LHGRFAC multiplier are sufficient to provide adequate protection for the off-rated conditions from an ECCS-LOCA. Therefore, a specific power and flow dependent MAPLHGR limit (M.APFAC multipler) is not required.
2.2. Minimum Critical Power Ratio (MCPR) Limits (T.S. 3.1 1.C)
MCPR is the smallest Critical Power Ratio (CPR) that exists in the core for each type of fuel and shall be equal to, or greater than the Operating Limit MCPR (OLMCPR), which is a function of Core Thermal Power, Core Flow, Fuel Type, and Scram Time (Tau).
The rated Operating Limit MCPR at steady-state rated power and increased core flow operating conditions is derived from the cycle specific fuel cladding integrity Safety Limit MCPR and the delta CPR, as determined from the most limiting transient event.
The rated OLMCPR will ensure that the Safety Limit MCPR is not exceeded during any abnormal operational occurrence (AOO) (Reference 3.6).
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The rated OLMCPR for two loop and single loop operation is documented in Table 2.2-1 and is dependent on scram time (Tau) surveillance data at position 36 (Reference 3.5).
Determination of Tau:
i First' age shall be determined:
EN, where:
n = number of scram time tests thus far this cycle, No = number of active rods measured in surveillance i, and
-= average scram time to position 36 dropout of all rods measured in surveillance i.
ii. Second, ix shall be determined:
rB 1/~r.65--; J where:
,= 0.830 = mean of the distribution for average scram insertion time to position 36 dropout used in the ODYN Option B analysis.
a= 0.019 = standard deviation of the distribution for average scram insertion time to position 36 dropout used in the ODYN Option B analysis.
N1 = number of active rods measured during the first surveillance test at BOC.
iii. Third, determine the OLMCPR, as follows:
If rave < rB, then OLMCPRo~ptitt from Table 2.2.1 may be used.
If z,, > ra, then a new OLMCPR shall be calculated:
OLMCPR^,, = OLMCPRo 0 + (- - ' (oikCPR,,;M. - OLMCPRO,.)
TA - r Cycle 25 COLR Vermont Yankee Nuclear Power Station Revision I Page 3 of 20
where:
OLMCPRoption A = Option A OLMCPR from Table 2.2.1 based on Option A analysis using full core scram times listed in Technical Specification 3.3.C.1.2.
OLMCP4opton B= Option B OLMCPR from Table 2.2.1 based on Option B analysis described in Reference 3.1.
A = 1.096 seconds = Technical Specification 3.3.C.1.2 core average scram time to drop-out of position 36.
The OLMCPR is the greater of the flow and power dependent MCPR operating limits, MCPR (F) and MCPR (P).
OLMCPR = MAX (MCPR (P), MCPR (F))
The flow dependent MCPR operating limits, MCPR (F) is provided in Figure 2.2-2.
For core thermal powers less than 25%, the power dependent MCPR operating limit, MCPR (P), is provided in Figure 2.2-1. For core thermal powers equal to or greater than 25%, MCPR (P) is the product of the rated OLMCPR presented in Table 2.2-1 and the K (P) factor presented in Figure 2.2-1.
Cycle exposure dependent limits are provided through the end of rated exposure point, which is expected to be the maximum exposure attainable at full power during ICF operation. Coastdown operation is allowable down to 40% rated CTP.
For single recirculation loop operation, the MCPR limits at rated flow shall be the values from Table 2.2-1 listed under the heading, "Single Loop Operation." The single loop values are obtained by adding 0.02 to the two loop operation values (TS l.l.A.1).
2.3. Linear Heat Generation Rate (LHGR) Limits (T.S. 3.1 I.B)
LHGR is the heat generation rate per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length. By maintaining the operating LHGR below the applicable LHGR limit, it is assured that all thermal-mechanical design basis and licensing limits for the fuel will be satisfied.
The maximum LHGR limit is a function of reactor power, core flow, fuel and rod type, and fuel rod nodal exposure. The limit is developed using NRC approved methodology described in Reference 3.1 to ensure the cladding will not exceed its yield stress and that the fuel thermal-mechanical design criteria will not be violated during any postulated transient events.
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During reactor power operation, the LHGR of any rod in any fuel bundle at any axial location shall not exceed the rated power and rated core flow limits (LHGRstd) for each fuel and rod type as a function of fuel rod nodal exposure listed in Reference 3.7.
The LHGR limits for the fuel pin axial locations with no gadolinium and maximum gadoliniwn concentration listed in Reference 3.7 are expected to operate near the LHGR limits.
There are also fuel pins with axial locations that have gadolinium concentrations that are less than the maximum concentration anywhere in the bundle. The LHGR limits for these axial locations range uniformly between the case of no gadolinium and the most limiting gadolinium concentration. _
For other than rated power and flow conditions (below 23% core thermal power thermal limit calculation is not required), the applicable limiting LHGR values for each fuel type is the smaller of the power and flow dependent LHGR limits multiplied by the applicable power and flow adjustment factor or the LHGR limit multiplied by 0.82 when in single loop operation.
LHGR limit = MIN (LHGR (P), LHGR (F)).
Power-dependent LHGR limit, LHGR (P), is the product of the LHGR power dependent LHGR limit adjustment factor, LHGRFAC (P), shown in Figure 2.3-1 and the LHGRSwd.
LHGR (P) = LHGRFAC (P) x LHGRSUd The flow-dependent LHGR limit, LHGR (F), is the product of the LHGR flow dependent LHGR limit adjustment factor, LIHGRFAC (F), shown in Figure 2.3-2 and the LHGRsMI.
LHGR (F) = LHGRFAC (F) x LHGRSwI 2.4. Thermal-Hydraulic Stability'Exclusion Region (T.S. 3.6.J)
For Cycle 25, based on decay ratios at the most limiting point on the power/flow, the predominate oscillation mode is core-wide. Normal plant operation is not allowed inside the bounds of the exclusion region defined in Figure 2.4-1. These power and flow limits are applicable for Cycle 25.. Operation inside of the exclusion region may result in a thermal-hydraulic oscillation. Intentional operation within the buffer region is not allowed unless the Stability Monitor is operable. Otherwise, the buffer region is considered part of the exclusion region (Reference 3.6).
The coordinates of the Exclusion Region are as follows:
1 Point Power ('o) Flow (%)
i 66.26 52.25 35.699 31.27 Cycle 25 COLR Vermont Yanlkee Nuclear Power Station Revision I Page 5 of 20
The equation for the boundary is as follows:
where, P = a core thermal power value on the Exclusion Region boundary (% of rated),
W = the core flow rate corresponding to power, P, on the Exclusion Region boundary (% of rated),
PA = core thermal power at State Point A (% of rated),
PF = core thermal power at State Point B (% of rated),
WA = core flow rate at State Point A (% of rated),
WB = core flow rate at State Point B (% of rated),
I The range of validity of the fit is: 31.27% <%Flow <52.25%
The coordinates of the Buffer Region are as follows:
Point Power (%) Flow (%)
C 70.10 57.25
- 1) 30.69 31.17 The generic equation used to generate the 5% buffer zone exclusion region boundary is:
P PD where, P = a core thermal power value on the Buffer Zone boundary (% of rated),
W = the core flow rate corresponding to power, P, on the 5% Buffer Zone boundary (% of rated),
Pc = core thermal power at State Point C (% of rated),
PD = core thermal power at State Point D (% of rated),
Wc = core flow rate at State Point C (% of rated),
WD = core flow rate at State Point D (% of rated),
I The range of validity of the fit is: 31.17% <%Flow <57.25%.
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2.5. Power/Flow Man Power operation, with respect to Core Thermal Power/Total Core Flow combinations, is allowed within the outlined area of Figure 2.4-1. This area is bounded by the following lines:
- Minimum Pump Speed Line; This line approximates operation at minimum pump speed. Plant start-up is performed with the recirculation pumps operating at approximately 20% speed. Reactor power level will approximately follow this line during the normal control rod withdrawal sequence.
- Minimum Power Line; This lines approximates the interlock that requires recirc pump speed to be at a minimum in terms of feedwater flow. This interlock ensures NPSH requirements jet pumps and recirculation pumps are met.
- Natural Circulation Line; The operating state the reactor follows along this line for the normal control rod withdrawal sequence in the absence of recirculation pump operation.
- Exclusion Region - The exclusion region is a power/flow region where an instability can occur. The boundary for the exclusion region is established through use of an analysis procedure which is demonstrated to be conservative relative to expected operating conditions.
- 5%, Buffer Region Boundary; The Buffer Region is determined by adjusting the endpoints of the Exclusion Region and increasing the flow on the highest rod line by 5% and decreasing power on the natural circulation line by 5%.
- Rated Power Line and MELLLA Boundary; These lines provide the upper power limit and operating domain assumed in transient analyses.
- ICF Boundary; This line represents the highest allowable analyzed core flow. The analysis in Reference 3.4 supports the maximum attainable core flow being 107%
of rated core flow.
2.6. Single Loon Operation SLO was not analyzed for operation in the MELLLA region. The power/flow operating condition for Single Loop Operation (SLO) is core power less than 1239 MWTh (64.80%C TP), core flow less than 26.35 M#/hr (54.9%) and maximum rod line less than 90%. (References 3.2 and 3.3)
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2.7. Rod Blockc Monitoring The Rod Block Monitor (RBM) control rod block functions are no longer credited in the Rod Withdrawal Error (RWE) Analysis and, as such, do not affect the MCPR Operating Limit. The RBM setpoints are based on providing operating flexibility in the MELLLA region (T.S. Bases 3.2). The rod block monitor (RBM) setpoint equation maximum value of N for single loop and dual loop operation are listed in Table 2.2-2.
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Table 2.1-1 MAPLHGR Limits for GE14-PIODNAB426-16G6.0-1OOT-150-T6-2682 Fuel Bundle No. 2682 MAPLHGR (kW/ft)
Average Planar Exposure (GWd'ST) Two Loop Operation Single Loop Operation' 0.00 12.82 10.51 19.12 12.82 10.51 57.61 8.00 6.56 63.50 5.00 4.10 Technical Specification
References:
3.6.G.la and 3.1 I.A.
MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
T'able 2.1-2 MAPLHGR Limits for GE14-P 1ODNAB390-14GZ-IOOT-150-T6-2683 Fuel Bundle No. 2683 MAPLHGR (kW/fi)
Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation' 0.00 12.82 10.51 19.12 12.82 10.51 57.61 8.00 6.56 .
63.50 5.00 4.10 Technical Specification
References:
3.6.G.la and 3.1 I.A.
l MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
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lable 2.1-3 MAPLHGR Limits for GE1 4-P 1ODNAB388-17GZ-1 OOT-1 50-T6-2684 Fuel Bundle No. 2684 MAPLHGR (kW/ft)
Average Planar Exposure (GWdIST) Two Loop Operation Single Loop Operation' 0.00 12.82 10.51 19.12 12.82 10.51 57.61 8.00 6.56 63.50 5.00 4.10 Technical Specification
References:
3.6.G.l a and 3.11 .A.
l MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
Table 2.1-4 MAPLFIGR Limits for GE14-P 1ODNAB422-16GZ-1 OOT-I 50-T6-2862 Fuel Bundle No. 2862 MAPLHGR (kW/ft)
Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation' 0.00 12.82 10.51 19.12 12.82 10.51 57.61 8.00 6.56 63.50 5.00. 4.10 Technical Specification
References:
3.6.G.la and 3.1 l.A.
XMAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
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1able 2.1-5 MAPLHGR Limits for GE14-PI ODNA383-13G6.0-lOOT-1 50-T6-2863 Fuel Bundle No. 2863 MAPLHGR (kW/ft)
Average Planar Exposure (GWd'ST) Two Loop Operation Single Loop Operation' 0.00 12.82 10.51 19.12 12.82 10.51 57.61 8.00 6.56 63.50 5.00 4.10 Technical Specification
References:
3.6.G.la anrd 3.1 l.A.
XMAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
Table 2.1-6 MAPLHGR Limits for GE14-F'IODNAB388-17GZ- lOOT-1 50-T6-2864 Fuel Bundle No. 2864 MAPLHGR (kW/ft)
Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation' 0.00 12.82 10.51 19.12 12.82 10.51 57.61 8.00 6.56 63.50 5.00 4.10 Technical Specification
References:
3.6.G.la and 3.1 l.A.
XMAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
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Table 2.1-7 MAPLHGR Limits for GE14-P 1ODNAB383-17G6.0-1OOT-150-T6-2865 Fuel Bundle No. 2865 MAPLHGR (kW/ft)
Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation' 0.00 12.82 10.51 19.12 12.82 10.51 57.61 8.00 6.56 63.50 5.00 4.10 Technical Specification
References:
3.6.G.la and 3.1 l.A.
MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
Table 2.1-8 MAPLHGR Limits for GE14-PI OI)NAB394-7GS.0/6G4.0- 1OOT-150-T6-2566 Fuel Bundle No. 2566 MAPLHGR (kW/ft)
Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation 0.00 12.82 10.51 19.12 12.82 10.51 57.61 8.00 6.56 63.50 5.00 4.10 Technical Specification
References:
3.6.G.la and 3.1 l.A.
1MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
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JTable 2.1-9 MAPLHGR. Limits for GEl 4-P10)NAB394-8G5.0/6G4.0-10OT-150-T6-2595 Fuel Bundle No. 2595 MAPLHGR (kW/ft)
Average Planar Exposure (GWdfST) Two Loop Operation Single Loop Operation' 0.00 12.82 .10.51 19.12 12.82 10.51 57.61 8.00 6.56 63.50 5.00 4.10 Technical Specification
References:
3.6.G.l a and 3.11.A.
l MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
Table 2.1-10 MAPLHGR Limits for GE14-P1ODNAB394-12G5.0-1OOT-150-T6-2596 Fuel Bundle No. 2596 MAPLHGR (kW/ft)
Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation' 0.00 12.82 10.51 19.12 12.82 10.51 57.61 8.00 6.56 63.50 5.00 4.10 Technical Specification
References:
3.6.G.la and 3.1 l.A.
1MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
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JTable 2.2-1 1 Cycle 25 Rated MCPR Operating Limits (OLMCPR) 3 I Cycle Exposure 5 Two Loop Single Loop Option Range Operation 2 Operation Oto 1770 MvIWd/St 1.47 1.49 Option A Beyond 11770 MWd/St 1.57 1.59 Option B4 BOC to EOC 1.40 1.42 Source: References 3.6.
1 The MCPR operating limit is increased by 0.02 for single loop operation.
2 -The two loop MCPR operating limits bound ICF operation throughout the cycle.
3 The OLMCPR is based on a SLDMCPR of 1.07 (1.05 calculated value + 0.02 adder).
4 The Rod Withdrawal Error event establishes the Option B OLMCPR limit from BOC to MOC and the Generator Load Reject with No Bypass event establishes the Option B OLMCPR limit from MOC to EOC.
5 MOC exposure is calculated as defined in Table 7-1 of Reference 3.6 using an EOR exposure 12870 Mwd/St from current revision of the Cycle Management Report.
Table 2.2-2 I RBM Setvoint 5 Dual Loop Operation Maximum Value of "N" in RBM Setpoint Equation - 62.
Single Loop Operation Maximum Value of "N" in RBM Setpoint Equation - 68.
Source: Reference3.8 Technical Specification
References:
Table 3.2.5.
6 The Rod Block Monitor (RBM) trip setpoints are determined by the equation shown in Table 3.2.5 of the Technical Specifications.
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Figure 2.2-1 Power Dependent K (P) / MCPR (P) Limits (Technical Specification Reference 3.11 .)
Power Dependent K (P) / MCPR (P) Lhadts 2.80 I
I I I I I I l TI Opting Oidt MCPR (P) a K(M)x OpcmlUgI Umit MCPR (100)
>i;0% Flow 2.4 FPor P c 23X: No Tbemal Umits Required For23% Pc25%,> 60%FMowm OMCPR (P) - 2.48 - 0.034 x (P - 25%)
2.410 - -- - - - - For23%5 P. 25%, 60% Fow OLMCPR (P) a 2.01- 0.026 x (P . 25%)
fP 25SS P < 45%: K (P)r* 1.55 - 0.0135 x (P - 25%)
< 60% Flow _Pa45%*S P c 100%: K (P) I 28 -0.009 x (P - 45%)
D0 - - ,. - -
. 2.C (I FMP;100%: K(F.I.00 g 2.00 I - &- I -...-.. 4.-. 4 4-4-4-4 4 4 .4 .4 S .
W IAN - .- -
1.60-- --
IAO - I- -0II II I II lAO---t 1.20- .- -_
1.00 20 25 30 35 40 45 50 55 e0 66 70 75 80 85 90 96 100 Power (% Raed)
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Fgure 2.2-2 Flow Dependent MC]?R Operating Limit MCPR (F)
(Technical Specification Reference 3.1 I.C)
Flow Dependent MCPR Operating Limit MCPR(F) 1.50 ___ _.
Maximml 109.5% Flow (Ra a1.40 1.30 1.20 1.10 __ __ _ _-
20 30 40 50 60 70 so 90 100 110 120 Core Flow (%Rated)
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Figure 2.3-1 Power Dependent LHGRFAC (P) Multiplier (Technical Specification Reference 3.1 1.B)
Power Dependent LHGRFAC(P) Mutplier 1.10 111
] I lv l l l l l 0 O:SO 101:I .eiSC 0.80 17>+/-O O.'
.^
I.1US>6 0% Flow Ut-GR (PJ = LHGRFAC (P)x LHGRstd Where LHGRstd = Rated LHGR limits For P < 23%: No Themal LUmits Required O. For 23% s P < 25%, >80% Flow:
LHGRFAC (P) - 0.586 + 0.0084 x (P-25%)
For 23% S P < 25%, s 60% Flow:
. 80% Flow
.5 LHGRFAC (P) = 1.0 + 0.00623 x (P.100%)
- 0. For25% s P c 100%
LH3RFAC (P)= 1.0 + 0.00623 x (P.100%)
For P 2 100%: LHGRFAC (P) a 1.0 0a.40 - - _
0.3 I _n 0.20 20 25 30 35 40 45 50 55 80 85 70 75 80 85 90 96 100 Powver (* Rated)
Cycle 25 COLR Vermont Yankee Nuclear Power Station Revision 1 Page 17 of 20
Fimure 2.3-2 LHGR Flow Factor LHGRFAC (F)
(Technical Specification Reference 3.1 I.B)
LHGR Flow Factor LHGRFAC (F) 1.20 1.10 ______________ _______
4 1M I
- .w
/
Maximum Flow aII 0.90
. I! - -
0 9 0.80 E
I I oo-0 3
0.60 = __:_==
LHGR (F) LHGRFAC (F) x LHGRstd LHGRstd a STANDARD LHGR UMITS 0.50 - - _
For W (%Rated Core Flow) > 30%
And Max Runout Flow 109.5%
UiGRFAC (F) a The Minimum of EITHER 1.0 0.40 _ OR (0.8737 x (W/I 00) + 0.279 W % Rated Core Flow
-M - .
20 30 40 50 SCI 70 sC 90 100 110 120 Core Flow (%Rated)
Cycle 25 COLR Vermont Yankee Nuclear Power Station Revision 1 Page 18 of 20
110r Ratd P6WS Un 100 -- '*- .
61 Smnar MS 0
70 -- -- -- ----- -- -Reg~n A -------.-
0 o I0 - -- -- - --
s o- - - - - - i -- - - - - - - - - -- 'jc 40 - ---- ---- .... ....
'10 0--- --- i ------ ---
3.0 REFERENCES
3.1. Report, General Electric, General Electric Standard Application for Reactor Fuel (GESTA ID. NEDE-2401 1-P-A-14, June 2000 (Proprietary).
3.2. Report, GE, Vermont Yankee Nuclear Power Station APRM/RBMiechnical Specificalions/Maximum Extended Load Line Limit Analysis (ARTS/MELLLA),
NEDC-33089P, March 2003 (Proprietary).
3.3. Report, GE, Entergv Nuclear Operation Incorporated Vermont Yankee Nuclear Power Station Extended Power Uprate - Task T0407 - ECCS-LOCA SAFERIGESTR, GE-NE-0000-001 5-5477-01, July 2003.
3.4. Report, Vermont Yankee Nuclear Power Station Increased Core Flow Analysis.
NEDC-32791P, February 1999.
3.5. Letter, Global Nuclear Fuels, William H. Hetzel (GNF) to Dave Mannai (VYNPC),
Vermont Yankee Option B Licensing Basis, WHV: 2001-023, November 9, 2001.
3.6. Report, Global Nuclear Fuels, Supplemental Reload Licensing Report for Vermont Yankee Nuclear Power Station Reload 24 Cycle 25 (with Extended Power Uprate),
0000-0035-6443-SRLR, Rev. 0, December 2005.
3.7. Report, Global Nuclear Fuels, Fuel Bundle Information Report for Vermnont Yankee Nuclear Power Station Reload 24 Cycle 25 0000-0035-6435-FBIR, Rev. 0, September 2005 (Proprietary).
3.8. VYDC 2003-015, ARTS/MELLLA Implementation.
3.9. Report, GE, Vermont Yankee Nuclear Power Station Single Loop Operation, NEDO-30060, February 1983.
3.10. Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc.
Docket No. 50-271 Vermont Yankee Nuclear Power Station Amendment to Facility Operating License Amendment No. 229 License No. DPR-28.
Cycle 25 COLR Vermont Yankee Nuclear Power Station Revision I Page 20 of 20