BVY 08-080, Core Operating Limits Report for Cycle 27
| ML083170484 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 11/07/2008 |
| From: | Michael Colomb Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BVY 08-080 | |
| Download: ML083170484 (30) | |
Text
Entergy Nuclear Operations, Inc.
Vermont Yankee P.O. Box 0250 320 Governor Hunt Road SEntergy Vernon, VT 05354 Tel 802 257 7711 November 7, 2008 BVY 08-080 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)
Core Operating Limits Report for Cycle 27 In accordance with Section 6.6.C of the Vermont Yankee Technical Specifications, enclosed is the Core Operating Limits Report for Cycle 27. This report presents the cycle-specific operating limits for Cycle 27 of the Vermont Yankee Nuclear Power Station.
Should you have any questions concerning this transmittal, please contact Mr. David J.
Mannai at (802) 451-3304.
Sincerely, Site Vice President Vermont Yankee Nuclear Power Station - Cycle 27 Vermont Yankee Core Operating Limits Report cc listing (next page) 96C)l
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BVY 08-080 Docket No. 50-271 Page 2 of 2 cc: Mr. Samuel J. Collins (w/o Attachment)
Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. James S. Kim, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8C2A Washington, DC 20555 USNRC Resident Inspector Entergy Nuclear Vermont Yankee, LLC 320 Governor Hunt Road Vernon, Vermont 05354 Mr. David O'Brien, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, Vermont 05620-2601
BVY 08-080 Docket No. 50-271 Attachment 1 Vermont Yankee Nuclear Power Station Core Operating Limits Report Cycle 27
Vermont Yankee Nuclear Power Station Cycle 27 Core Operating Limits Report Revision 0 October 2008 Prepared E N 11EAQ,.4 Ilmf&*t.- I/ ie,!3g IoS Responsible Engineer (Print/Sign) Date Reviewed React6r Engineer (Print/Sign) Date Approved Iflp Supervisor Reactor i- er (Print! ign) /ate Approved Approved
REVISION RECORD Cycle Revision Date Description 27 0 10/2008 Cycle 27 revision Cycle 27 COLR Vermont Yankee Nuclear Power Station Revision 0 Revision Record Page i of i
ABSTRACT This report presents Cycle 27 specific operating limits at current license thermal power (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.
Cycle 27 COLR Vermont Yankee Nuclear Power Station Revision 0 Abstract Page i of i
TABLE OF CONTENTS Page LIST O F TA BLES ........................................................................................................................ 1I........i LIST O F FIGU RES ............................................................................................................................ iii 1.0 IN TROD U CTION .................................................................................................................... 1 2.0 CO RE O PERATIN G LIM ITS ........................................................................................... 2 2.1 Average Planar Linear Heat Generation Rate Limits (APLHGR) ....................... 2 2.2 M inim um Critical Pow er Ratio (M CPR) Lim its .................................................. 2 2.3 Linear H eat G eneration Rate (LHG R) Lim its ....................................................... 4 2.4 Therm al-H ydraulic Stability Exclusion Region .................................................. 5 2.5 Pow er/Flow M ap.................................................................................................... 7 2.6 Single Loop O peration ........................................................................................... 7 2.7 Rod Block M onitoring ........................................................................................... 8 3.0 REFEREN CES ..................... ................................................................................................. 21 Cycle 27 COLR Vermont Yankee Nuclear Power Station Revision 0 Table :of Contents Page i of iii
TABLE OF CONTENTS (Continued)
LIST OF TABLES Number Title Pave Table 2.1-1 MAPLHGR Limits for GE 14-P 1ODNAB422-16GZ- 1 OT- I 50-T6-2862 Fuel B undle N o. 2862 ................................................................................ 9 Table 2.1-2 MAPLHGR Limits for GE 14-P 1ODNAB383-13G6.0-1OOT- 150-T6-2863 Fuel B undle N o. 2863 ................................................................................ 9 Table 2.1-3 MAPLHGR Limits for GE 14-P 1ODNAB383-14G6.0-LOOT- 150-T6-2864 Fuel Bundle No. 2864 .................................. 10 Table 2.1-4 MAPLHGR Limits for GE 14-P 1ODNAB383-17G6.0-1OOT- 150-T6-2865 Fuel B undle N o. 2865 .............................................................................. 10 Table 2.1-5 MAPLHGR Limits for GE 14-P 1ODNAB422-14GZ- 1 OT- 150-T6-2965 Fuel B undle No. 2965 ................................................................................... 11 Table 2.1-6 MAPLHGR Limits for GE14-PIODNAB388-15GZ- 1 OT-150-T6-2968 Fuel B undle No. 2968 ................................................................................... 1I Table 2.1-7 MAPLHGR Limits for GE14-P1ODNAB388-15GZ-1 GOT-150-T6-2969 Fuel B undle No. 2969 .............................................................................. 12 Table 2.1-8 MAPLHGR Limits for GNF2-P 1ODG2B387-15GZ- 100T2-150-T6-2977-LUA Fuel B undle N o. 2977 .............................................................................. 12 Table 2.1-9 MAPLHGR Limits for GE 14-P1ODNAB421-16GZ- 100T-I 50-T6-3084 Fuel B undle N o. 3084 .............................................................................. 13 Table 2.1-10 MAPLHGR Limits for GE14-P 1ODNAB420-16GZ- 100T-i 50-T6-3085 Fuel Bundle N o. 3085 ............................................................................. 13 Table 2.1-11 MAPLHGR Limits for GE 14-P 1ODNAB388-15G6.0-1GOT- 150-T6-3086 Fuel B undle N o. 3086 .............................................................................. 14 Cycle 27 COLR Vermont Yankee Nuclear Power Station Revision 0 Table of Contents Page ii of iii
TABLE OF CONTENTS (Continued)
Table 2.1-12 MAPLHGR Limits for GEI4-P1ODNAB388-16GZ-1 OOT-150-T6-3087 Fuel B undle N o. 3087 ............................................................................ 14 Table 2.2-1 Cycle 27 Rated MCPR Operating Limits (OLMCPR) ........................... 15 Table 2.2-2 RB M Setpo int ......................................................................................... . . 15 LIST OF FIGURES Number Title Page 2.2-1 Power Dependent K (P) / MCPR (P) Limits ........................... 16 2.2-2 Flow Dependent MCPR Operating Limit MCPR (F) .......................................... 17 2.3-1 Power Dependent LHGRFAC (P) Multiplier .......................... 18......
2.3-2 LHGR Flow Factor LHGRFAC (F) ..................................................................... 19 2.4-1 Lim its of Pow er/Flow O peration ............................................................................... 20 Cycle 27 COLR Vermont Yankee Nuclear Power Station Revision 0 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 27. 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 and dual loop operation are included in this report.
This Core Operating Limits Report for Cycle 27 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 by the NRC approved methodologies documented in General Electric Licensing Topical Report NEDE-2401 I-P-A, "General Electric Standard Application for Reactor Fuel," as amended and documented in the Core Operating Limits Report.
For Cycle 27 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 1.1 .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 27 operating limits have been defined using NRC-approved methodologies. Cycle 27 must be operated within the bounds of these limits and all others specified in the Technical Specifications.
2.1. Average Planar Linear Heat Generation Rate Limits (APLHGR) (T.S. 3.1 .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 10CFR50.46 (b) (1) and that the fuel design analysis criteria defined in References 3.1 and 3.3 will be met.
Tables 2.1-1 through 2.1-12 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 (References 3.6 and 3.9).
The power and flow dependent LHGR limits (LHGRFAC multipliers) in Figure 2.3-1 and 2.3-2 are sufficient to provide adequate protection for off-rated conditions for a LOCA. Therefore, the power and flow dependent MAPFAC multipliers are set to 1.
2.2. Minimum Critical Power Ratio (MCPR) Limits (T.S. 3.1 .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).
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).
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Determination of Tau:
- i. First, r,, shall be determined:
tYý Nj ri SIYL, - i where:
n = number of scram time tests thus far this cycle, Ni number of active rods measured in surveillance i, and ri= average scram time to position 36 dropout of all rods measured in surveillance i.
ii. Second, rB shall be determined:
r8 -p+l1.65 N where:
p = 0.830 = mean of the distribution for average scram insertion time to position 36 dropout used in the ODYN Option B analysis.
cr = 0.019 = standard deviation of the distribution for average scram insertion time to position 36 dropout used in the ODYN Option B analysis.
N, = number of active rods measured during the first surveillance test at BOC.
iii. Third, determine the OLMCPR, as follows:
If rove < rB, then OLMCPR,*io 0 ,, B from Table 2.2.1 may be used.
If rve> rB, then a new OLMCPR shall be calculated:
OLMCPR,, = OLMCPROp,,o. B + r,,,e - "r (OLMCPRopi,, - OLMCPRopto, )
"r I -- *B where:
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OLMCPRopti,0 1 A= Option A OLMCPR from Table 2.2.1 based on Option A analysis using full core scram times listed in Technical Specifications.
OLMCPRoptio 0 B= Option B OLMCPR from Table 2.2.1 based on Option B analysis described in Reference 3. 1.
Tj = 1.096 seconds = Technical Specification 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 limit, 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 1.1 .A. 1).
2.3. Linear Heat Generation Rate (LHGR) Limits (T.S. 3.11.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 (LHGRs1 d) 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 gadolinium concentration listed in Reference 3.7 are expected to operate near theLHGR 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 LHGRstd.
LHGR (P) = LHGRFAC (P) x LHGRltd The flow-dependent LHGR limit, LHGR (F), is the product of the LHGR flow dependent LHGR limit adjustment factor, LHGRFAC (F), shown in Figure 2.3-2 and the LHGR~td.
LHGR (F) = LHGRFAC (F) x LHGRstd 2.4. Thermal-Hydraulic Stability Exclusion Region (T.S. 3.6.J)
For Cycle 27, based on decay ratios at the most limiting point on the power/flow, the predominant 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 27. 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 ex(clusion region (Reference 3.6).
The coordinates of the Exclusion Region are as follows:
Point Power (%) Flow (%)
A 65.8 51.6 B 31.1 31.2 Cycle 27 COLR Vermont Yankee Nuclear Power Station Revision 0 Page 5 of 21
The equation for the boundary is as follows:
P= PBHJA AB+{A W PB 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),
PB = 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),
The range of validity of the fit is: 31.2% <%Flow <51.6%
The coordinates of the Buffer Region are as follows:
Point Power (%) Flow (%)
C 69.6 56.6 D 26.1 30.5 The generic equation used to generate the 5% buffer zone exclusion region boundary is:
2 rW-W D P=P ýcýW WD W C -W DJ 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),
The range of validity of the fit is: 30.5% <%Flow <56.6%.
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2.5. Power/Flow Map 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 line approximates the interlock that requires recirc pump speed to be at a minimum in terms of feedwater flow. This interlock ensures NPSH requirements for 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 plant safety 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 Loop 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%CTP), 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 Block 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 operational flexibility in the MELLLA region (TS 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 GE 14-P0ODNAB422-16GZ- 1OOT-1 50-T6-2862 Fuel Bundle No. 2862 MAPLHGR (kW/ft)
Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation' 0 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 2.1-2 MAPLHGR Limits for GE 14-P 10DNA383-13G6.0-10OT-I 50-T6-2863 Fuel Bundle No. 2863 MAPLHGR (kW/ft)
Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation' 0 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 3.1 l.A.
MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
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Table 2.1-3 MAPLHGR Limits for GE 14-P 1ODNAB388-17GZ- lOOT- 150-T6-2864 Fuel Bundle No. 2864 MAPLHGR (kW/ft)
Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation' 0 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. I a and 3.1 l.A.
MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
Table 2.1-4 MAPLHGR Limits for GE 14-P 1ODNAB383-17G6.0- lOOT- 150-T6-2865 Fuel Bundle No. 2865 MAPLHGR (kW/ft)
Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation' 0 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. I a and 3.1I.A.
MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
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Table 2 1-5 MAPLHGR Limits for GE 14-P IODNAB422-14GZ- 1OOT-150-T6-2965 Fuel Bundle No. 2965 MAPLHGR (kW/ft)
Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation' 0 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. I a and 3.11 .A.
MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
Table 2.1-6 MAPLHGR Limits for GE 14-PIODNAB388-15GZ-1 OOT-1 50-T6-2968 Fuel Bundle No. 2968 MAPLHGR (kW/ft)
Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation]
0 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. I a and 3.1 I.A.
MAPLHGR 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 GE 14-P 1ODNAB388-15GZ- 1OOT-I 50-T6-2969 Fuel Bundle No. 2969 MAPLHGR (kW/ft)
Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation' 0 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. Ia and 3.11 .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 GNF2-P1ODG2B387-15GZ- 100T2-150-T6-2977-LUA Fuel Bundle No. 2977 MAPLHGR (kW/ft)
Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operationi 0 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. Ia and 3.11 .A.
MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
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Table 2.1-9 MAPLHGR Limits for GE 14-PIODNAB421-16GZ-100T-1 50-T6-3084 Fuel Bundle No. 3084 MAPLHGR (kW/ft)
Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation' 0 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. Ia and 3.11 .A.
MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
Table 2.1-10 MAPLHGR Limits for GE 14-P 10DNAB420-16GZ- lOOT-1 50-T6-3085 Fuel Bundle No. 3085 MAPLHGR (kW/ft)
Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation' 0 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 3.1 l.A.
MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
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Table 2.1-11 MAPLHGR Limits for GE 14-P 1ODNAB388-15G6.0-1 00T2-150-T6-3086 Fuel Bundle No. 3086 MAPLHGR (kW/ft)
Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operationi 0 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. I a and 3.11 .A.
'MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
Table 2.1-12 MAPLHGR Limits for GE 14-P 1ODNAB388-16GZ- 100T2-150-T6-3087 Fuel Bundle No. 3087 MAPLHGR (kW/ft)
Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operationi 0 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. I a and 3.11 .A.
MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
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Table 2.2-1 Cycle 27 Rated MCPR Oieratina Limits (OLMCPR)
Cycle Exposure Two Loop Single Loo?
Option/Fuel Type Range Operation Operation Option A/GE 14 0 to 10,521 MWd/St 1.42 1.44 Beyond 10,521 MWd/St 1.56 1.58 Option A/GNF2 0 to 10,521 MWd/St 1.43 1.45 Beyond 10,521 MWd/St 1.52 1.54 Option B/GEl4 0 to 10,521 MWd/St 1.40 1.42 Beyond 10,521 MWd/St 1.40 1.42 Option B/GNF2 0 to 10,521 MWd/St 1.40 1.42 Beyond 10,521 MWd/St 1.42 1.44 Source: References 3.6.
1 The MCPR operating limit is increased by 0.02 for si.ngle loop operation.
2 The two loop MCPR operating limits bound ICF operation throughout the cycle.
Table 2.2-2 RBM Setpoint 3 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: Reference 3.8 Technical Specification
References:
Table 3.2.5.
3 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 3.1 1.C) 5.,00, -o--MCPR(P) for <25%P, >60%F 4.750 - - - - -
4.00..0 ------.
3.500 ----- -<25%P, MCPRP)- *60%F 2.750 ... I
..... .... ..... .... .... i i
.. L -L JL -K,_ I I I I I I , I I 1 1 * ! i t I i " i
- 0-3.0 - - - - I - -- 1 -- - I L I t I 1 . t I 3.250 --
3.500 ----- I I- L--- ---------- I ! I I I I i 3.000 - - - - - - -I - --....... L I_
50*___-_--
-- z:uu. .. o-2-_ .. L -... .J L.. -
I I
- I I i I I *II I I I 2.250 *--- ..... - k--...-
t I i II I I I A F 1'750-----------------------------. ------- r -r 1--
I II II I t 10 -' .. .. I . . . . * . . . . . "" . . ." . . . I. . . . . 1. . . . . . I. . . t. . . I- . . .T . .
I I I f . I t Fo 23.N P hra < Lmt eure 1.000 t :
20.0 25..0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0. 80.0 85.0 90.0 95.0 100.
Power (% Rated)
Operatinag Limit MCPR(P) = K(P) Opertig Limit MCPR(100)
For P < 23%, No Thermal Limits Re~quited P-Bypass = 25% Rated Power MCPR(P) fmits are based on a 1.07 SLMCPR MCPR(P) for <25%P. >60%F POWER LIMIT EQUATrONS 23-0 2.55 25.0 2.48 For 23.0% s P < 25.0%: MCPR(P) = 2.48 + 3.50E-02(25.0 - P)
MCPR(P) for 425.%P. 1OF POWER LIMIT 23.0 2.12 25-0 2.07 For 23.0% g P < 25.0%: MCPR(P) = 2.07 + 2.50E-02(25.0 - P)
K(P) for 225,_P POWER LIMIT 25.0 1.550 45.0 1.280 For 25.0% 5 P < 45.0%: K(P) = 1.280 + 1.35E-02(45.0 - P) 100.0 1.000 For 45.0% ! P' 100.0%: K(P) = 1.000 + 5.0@E-03(100.0 - P)
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Figure 2.2-2 Flow Dependent MCPR Operating Limit MCPR (F)
(Technical Specification Reference 3.11 .C) 1 800 I -aI 1.700 I Ii 1600 I, F,- - a I~ nu lw=195 1.500.
' !I I 1.400
'1300 I*I I F 1.200 1.10 1.10[
20.0 30-0 40.0 50.0 60,0 70.0 80.0 90.0 100.0 110.0 120C Row (% Rated)
MCPR(F) limits are based on a 1-07 SLMCPR Max Runout Flow = 109.5%
FLOW .LIMIT EQUATIONS 30.0 1.57 MCPR(F) = AtX(1.28, jA(F)'W(CyID + B(F)J) 77.5 1.28 A(F) = -0.802 109.5 1.28 B{F) = 1.747 Cycle 27 COLR Vermont Yankee Nuclear Power Station Revision 0 Page 17 of 21
Figure 2.3-1 Power Dependent LHGRFAC (P) Multiplier (Technical Specification Reference 3.11 .B)
F F I I F I I 1 F F 0.200 -- -- I I FI I - - I I * *F
- I I F I F I F F 0.100 TI F F F 2!25%P 104000.0 2 F 3 F ! F . 0 0 I 0 F0 FI0 7 I 1 I I F I i - P o we ( F a I F I FI F 0u00- ----- ----. F.......... .. ... - ------ -U..
... . , . . . .. , . ...... .......- .. L... . .. . ... ...
I F I F I r F I I I I i ! I i F 1 F I I 0500 u4 .,.. .- ,. ..
.... . I.. . L. -- -- - .. j.-...- , -- .. * . .,-. L ... . J . *.. .. ... L.. -... . - ..
F FI I1 I F F i F I F F F I F F F F F FoFoo F F F F -a-- LHGRFAC(P) for >25%P.>-,-
0.100 - -i F F F F F F LHGRF"i f Ž25 I F 20.0 25.0 30.0 35.0 40.0. 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 l00.1 Power (%Rated)
LHGR(P) = LHGRFAC(P) - LHGRstd For P < 23%. No Thermal Umits Requ-red P-Bypass = 25% Rated Power LHGRFACIP) for <25%P, >6O%F POWER ULMIT EQUATIONS 23.0 0.569 25.0 0.598 For 23.0% S P < 25.0%: LHGRFAC(P) = 0.580 + 8.50E-03(P - 25.0)
LHGRFACIP) for <25%P, !r.s%F POWER LUMIT EQUATIONS 23.0 0.598 25.0 0.808 For 273.0%9 P 4 25.0%: LHGRFAC(P) = 0.608 + 5.OOE-03(P - 25.0)
LHGRFAC(P) for .25%P POWER LUMIT FOUAIONS 25.0 0.808 100A 1.000 For 25.0% 9 P < 100.0%: LHGRFAC(P) = 1.000 + 5.23E-03(P - 100.0)
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Figure 2.3-2 LHGR Flow Factor LHGRFAC (F)
(Technical Specification Reference 3.11.B) 1.100 1.000 0.900 0.800 ........ * ... ~ .. ~....... , .. .......... .... ~. . ._. . ..-. - .t., .... ,4.......... .
0.700 . . . .... .F. . .... . . 1 . . . . .J . . . .. . . -. - . i
..a -...... - . . . ..... J, . . . . . . . .
-.- I Ma Mulo IOW IUiD2 U
0.600 0.500 5 . .. ... . .... ... . . . . . .. . . 1-. . .. .- ' -.. . .- .. .. . - -..
... .. . ........... L.. - -...... - .r ..... .. . . . . . .
F F F F i I F 0.400 F FF FI F F 0.300-F F....
F F FF F FI
.. F..
.. . . .F.. . . .. . . F . F... -- F- Fa Flo=F0. % . . .
0.200 0.100 0.000 20 .0 30.0 40.0 50.0 60.0 70-0 80.0 90.0 100.0 110.0 120.C Flow (%Rated)
LHGR(F) = LHGRFAC(F) - LHGRstd Max Runout Flow = 109.5%
FLOW LIMIT EQUATIONS 1
30.0 0.540 LHGRFAC(F) = MIN( 1.0. lA4F) W(C)100 + 8(F)])
82.6 1.000 A(F) = 0.874 109.5 1.000 B(F) = 0.278 Cycle 27 COLR Vermont Yankee Nuclear Power Station Revision 0 Page 19 of 21
Figure 2.4-1 Limits of Power/Flow Operation (Technical Specification Reference 3.6.J)
CYCLE 27 POWER/FLOW MAP 1101 90F 100 90
- 70
- 60 E 50 140 30 20 10 0 I .1.~.!., I 0 10 20 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)
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3.0 REFERENCES
3.1. Report, General Electric, General Electric Standard Application for Reactor Fuel (GESTAR II), NEDE-2401 l-P-A-16, October 2007 (Proprietary).
3.2. Report, GE, Vermont Yankee Nuclear Power Station APRM/RBM/Technical Specifications/Maximum Extended Load Line Limit Analysis (ARTS/MELLLA),
NEDC-33089P, March 2003 (Proprietary).
3.3. Report, GE, Entergy Nuclear Operation Incorporated Vermont Yankee Nuclear Power Station Extended Power Uprate - Task T0407 - ECCS-LOCA SAFER/GESTR, GE-NE-0000-0015-5477-01, September 2004 (Proprietary) 3.4. Report, GE, Vermont Yankee Nuclear Power Station Increased Core Flow Analysis, NEDC-32791P, February 1999 (Proprietary).
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 26 Cycle 27, 0000-0078-8270-SRLR, Rev. 0, September 2008.
3.7. Report, Global Nuclear Fuels, Fuel Bundle Information Report for Vermont Yankee Nuclear Power Station Reload 26 Cycle 27, 0000-0078-8270-FBIR, Rev. 0, September 2008 (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, Extended Power Uprate Amendment, March 2006.
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