ML022980250

Core Operating Limits Report for Cycle 23

ML022980250
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	10/22/2002
From:	Balduzzi M Entergy Nuclear Operations, Entergy Nuclear Vermont Yankee
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BVY 02-84
Download: ML022980250 (29)

Text

"-

Entergy Entergy Nuclear Vermont Yankee, LLC Entergy Nuclear Operations, Inc.

185 Old Ferry Road Brattleboro, VT 05302-0500 October 22, 2002 BVY 02-84 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)

Core Operatinig Limits Report for Cycle 23 In accordance with Section 6.6.C of the Vermont Yankee Technical Specifications, enclosed is the Core Operating Limits Report (COLR) for Cycle 23. This report presents the cycle-specific operating limits for Cycle 23 of the Vermont Yankee Nuclear Power Station.

If you have any questions concerning this transmittal, please contact Mr. Jim DeVincentis at (802) 2584236.

Sincerely, Michael A. Balduzzi Vice President, Operations Enclosure cc:

USNRC Region 1 Administrator USNRC Resident Inspector-VYNPS USNRC Project Manager - VYNPS Vermont Department of Public Service

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SUMMARY

OF VERMONT YANKEE COMMITMENTS BVY NO.: 02-84 Core Operating Limits Report for Cycle 23 The following table identifies commitments made in this document by Vermont Yankee.

Any other actions discussed in the submittal represent intended or planned actions by Vermont Yankee. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Licensing Manager of any questions regarding this document or any associated commitments.

COMMITMENT COMMITTED DATE OR "OUTAGE" None N/A 1-

.4-VYAPF 0058.04 AP 0058 Rev. I Page I of I i

Vermont Yankee Nuclear Power Station Cycle 23 Core Operating Limits Report Revision 0 October 2002

Cycle 23 COLR Revision 0 October 2002 Prepared E-4 J-dacL.

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Reactor EngineerD'4=z 101,/4Z0O2 bate Date Approved 7'CCv N

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Reactor Engineering Superintendent Date Reviewed -

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Plant Operations Review Committd' Date Approved ztwl V,

"//Ioz General Manager, Plant Operations Date Approved Vice President, Operations ii Date I

Cycle 23 COLR Revision 0 October 2002 REVISION RECORD Revision Date Description 0

10/2002 Cycle 23 revision. Reviewed by PORC and approved by management.

iii Cycle 23

Cycle 23 COLR Revision 0 October 2002 ABSTRACT This report presents the cycle-specific operating limits for the operation of Cycle 23 of the Vermont Yankee Nuclear Power Station. The limits are the maximum average planar linear heat generation rate, maximum linear heat generation rate, minimum critical power ratio, and thermal-hydraulic stability exclusion region.

iv

Cycle 23 COLR Revision 0 October 2002 TABLE OF CONTENTS Page REVISION RECORD....................................................................................................................

i ABSTRACT.

iv LIST OF TABLES.......................................................................................

vi LIST OF FIGURES.......................................................................................................................

vii 1.0 INTRODU CTION...........................................................................................................

1 2.0 CORE OPERATIN G LIM ITS............................................................................................

2 2.1 Maximum Average Planar Linear Heat Generation Rate Limits.................................

2 2.2 M inim um Critical Power Ratio Lim its.......................................................................

2 2.3 M axim um Linear Heat Generation Rate Lim its..........................................................

4 2.4 Therm al-H ydraulic Stability Exclusion Region.........................................................

5 2.5 Power/Flow M ap......................................................................................................

7 3.0 REFEREN CES.....................................................................................................................

20 V

Cycle 23 COLR Revision 0 October 2002 LIST OF TABLES Title Table 2.1-1 Table 2.1-2 Table 2.1-3 Table 2.1-4 Table 2.1-5 Table 2.1-6 Table 2.1-7 Table 2.1-8 Table 2.2-1 Table 2.3-1 MAPLHGR Versus Average Planar Exposure for GE9B-P8DWB335-10GZ-80M-150-T Fuel Bundle No. 2017 MAPLHGR Versus Average Planar Exposure for GE13-P9HTB380-12GZ-100T-146-T Fuel Bundle No. 2278 MAPLHGR Versus Average Planar Exposure for GE13-P9HTB379-13GZ-100T-146-T Fuel Bundle No. 2279 MAPLHGR Versus Average Planar Exposure for GE13-P9DTB386-11G4.0/1G3.0-100T-146-T-2425 Fuel Bundle No. 2425 MAPLHGR Versus Average Planar Exposure for GE 13-P9DTB225-NOG-1OOT-146-T-2570 Fuel Bundle No. 2570 MAPLHGR Versus Average Planar Exposure for GE14-P1ODNAB394-7G5.0/6G4.0-10OT-150-T-2538 Fuel Bundle No. 2538 MAPLHGR Versus Average Planar Exposure for GE14-P1ODNAB394-8G5.0/6G4.0-1OOT-150-T-2589 Fuel Bundle No. 2589 MAPLHGR Versus Average Planar Exposure for GE14-P1ODNAB394-12G5.0-IOOT-150-T-2590 Fuel Bundle No. 2590 Cycle 23 MCPR Operating Limits (OLMCPR) and RBM Setpoints Maximum Allowable Linear Heat Generation Rate Limits vi Number Page 8

9 10 11 12 13 14 15 16 17

Cycle 23 COLR Revision 0 October 2002 LIST OF FIGURES Title Kf vs. Total Core Flow Limits of Power/Flow Operation vii Number 2.2-1 2.4-1 Eage 18 19

Cycle 23 COLR Revision 0 October 2002

1.0 INTRODUCTION

This report provides the cycle-specific limits for operation of the Vermont Yankee Nuclear Power Station in Cycle 23. It includes the limits for the maximum average planar linear heat generation rate, maximum 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.

This Core Operating Limits report for Cycle 23 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 1 through 3.

The methodologies are also listed in Technical Specification 6.6.C. The bases for these limits are in References 5 through 8 and 11 through 13.

1

Cycle 23 COLR Revision 0 October 2002 2.0 CORE OPERATING LIMITS The Cycle 23 operating limits have been defined using NRC-approved methodologies. Cycle 23 must be operated within the bounds of these limits and all others specified in the Technical Specifications.

2.1 Maximum Average Planar Linear Heat Generation Rate Limits (T.S. 3.1 1.A)

During steady-state power operation, the Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for each fuel type, as a function of the average planar exposure, shall not exceed the limiting values shown in Tables 2.1-1 through 2.1-8. 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 5 and 12). The source of these values is identified on each table.

The MAPLHGR values are usually the most limiting composite of the fuel thermal-mechanical design analysis MAPLHGRs and the Loss-of-Coolant Accident (LOCA) MAPLHGRs. The fuel thermal-mechanical design analysis, using the methods in Reference 1, demonstrates that all fuel rods in a lattice, operating at the bounding power history, meet the fuel design limits specified in Reference 1. The Vermont Yankee LOCA analysis, performed in conformance with the requirements of 10CFR50.46 and Appendix K demonstrates that the LOCA analysis MAPLHGR values are bounded at all exposure points by the thermal-mechanical design analysis MAPLHGR values.

The MAPLHGR actually varies axially, depending upon the specific combination of enriched uranium and gadolinia that comprises a fuel bundle cross section at a particular axial node. Each particular combination of enriched uranium and gadolinia is called a lattice type. Each lattice type has a set of MAPLHGR values that vary with fuel burnup. The process computer will verify that these lattice MAPLHGR limits are not violated. Tables 2.1-1 through 2.1-8 provide a limiting composite of MAPLHGR values for each fuel type, which envelope the lattice MAPLHGR values employed by the process computer. When hand calculations are required, these MAPLHGR values are used for all lattices in the bundle.

2.2 Minimum Critical Power Ratio Limits (T.S. 3.11.C)

During steady-state power operation, the Minimum Critical Power Ratio (MCPR) shall be equal to, or greater than the Operating Limit MCPR (OLMCPR), as calculated by the following method. 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.

2

Cycle 23 COLR Revision 0 October 2002 The OLMCPR shall be determined based upon all scram time surveillance data at position 36, generated thus far in the cycle (Ref. 13).

First,,rae shall be determined:

n E N,,r,

'ave :-

i=1 where:

n = number of scram time tests thus far this cycle, Ni= number of active rods measured in surveillance i, and

,= average scram time to position 36 dropout of all rods measured in surveillance i.

Second, TB shall be determined:

TB= y +1.65 nNj where:

pu = 0.830 = mean of the distribution for average scram insertion time to position 36 dropout used in the ODYN Option B analysis.

oy= 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.

Third, determine the OLMCPR, as follows:

If rave < TB, then OLMCPRopt, onB from Table 2.2.1 may be used.

If Tave > TB, then a new OLMCPR shall be calculated:

OLMCPRNe, = OLMCPROp,,o, B +.Ta -TB (OLMCPRoptio,,

A-OLMCPROpton B)

TA 1 TB 3

Cycle 23 COLR Revision 0 October 2002 where:

OLMCPRoptio 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.

OLMCPRoptio* B = Option B OLMCPR from Table 2.2.1 based on Option B analysis described in Reference 1.

-A = 1.096 seconds = Technical Specification 3.3.C.1.2 core average scram time to drop out of position 36.

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).

For core flows other than the rated condition, the MCPR limit shall be the appropriate value from Table 2.2-1 multiplied by Kf, where Kf is given in Figure 2.2-1 as a function of the Recirc MG Set Stop setting. Interpolation between Kf curves is allowable, provided the curve used is conservative to the Recirc MG Set Stop setting.

Also listed is the maximum RBM rod block setpoint to which the designated MCPR limits apply. This value determines the RBM rod block clamp setpoint.

These limits are only valid for the fuel types in Cycle 23.

2.3 Maximum Linear Heat Generation Rate Limits (T.S. 3.11.B)

During steady-state power operation, the Linear Heat Generation Rate (LHGR) of any rod in any fuel bundle at any axial location shall not exceed the maximum allowable LHGR limits in Table 2.3-1. This table only lists the limits for fuel types in Cycle 23.

4

Cycle 23 COLR Revision 0 October 2002 2.4 Thermal-Hydraulic Stability Exclusion Region (T.S. 3.6.J)

For Cycle 23, 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 (Reference 7). These power and flow limits are applicable for Cycle 23. 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.

The coordinates of the Exclusion Region are as follows:

The equation for the boundary is as follows:

P =PB[ýJiA2WB WA WB I

where, a core thermal power value on the Exclusion Region boundary (% of rated),

the core flow rate corresponding to power, P, on the Exclusion Region boundary (% of rated),

core thermal power at State Point A (% of rated),

core thermal power at State Point B (% of rated),

core flow rate at State Point A (% of rated),

core flow rate at State Point B (% of rated),

The range of validity of the fit is:30.6% <%Flow <50.3%

5 Point Power (%)

I Flow (%)

A 73.5 50.3 B

31.8 30.6 PA =

PB =

WA =

WB =

Cycle 23 COLR Revision 0 October 2002 The coordinates of the Buffer Region are as follows:

The generic equation used to generate the 5% buffer zone exclusion region boundary is:

~~ PD~j

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:29.6% <%Flow <55.3%.

6 Point Power (%)

I Flow (%)

C 77.6 55.3 D

26.8 29.6

Cycle 23 COLR Revision 0 October 2002 2.5 Power/Flow Map Power operation, with respect to Core Thermal Power/Total Core Flow combinations, is allowed within the boldly 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.

5% Buffer Region Boundary; The Buffer Region is determined by adjusting the endpoints of the 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%. Operational restrictions regarding the Exclusion and Buffer Regions are described in Section 2.4.

• High Flow Control Line; This line is defined by the path the plant would follow if a Dual Recirculation Pump Trip/Runback were to occur starting at the Extended Load Line Limit Analysis (ELLLA) Point, 100 %Power/87% Flow.

• Rated Power Line; This line provides an upper power limit assumed in transient analyses. The Rated Power line is equivalent to 1593 MW(th), or rated power for Vermont Yankee. The value is defined in the operating license and supplied in Technical Specifications.

0 107% Flow Line; This line represents the highest allowable analyzed core flow. The analysis in Reference 11 supports the maximum attainable core flow being approximately 107% of rated core flow.

• Minimum Power Line; This lines approximates the interlock that requires recirc pump speed to be at a minimum below 20% of feedwater flow. This interlock ensures NPSH requirements are met.

Additionally, up to approximately 20% Core Thermal Power, operation is allowed only at Minimum Pump Speed to ensure cavitation of Recirc Pumps and Jet Pumps does not occur.

7

Cycle 23 COLR Revision 0 October 2002 Table 2.1-1 MAPLHGR Versus Average Planar Exposure for GE9B-P8DWB335-1OGZ-80M-150-T Fuel Bundle No. 2017 MAPLHGR (kW/ft)

Average Planar Exposure (GWd/ST) 0.00 0.20 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 10.00 12.50 15.00 20.00 25.00 35.00 45.00 50.59 Two Loop Operation Single Loop Operationi 11.29 11.34 11.48 11.69 11.92 12.17 12.43 12.68 12.87 13.06 13.24 13.35 13.20 13.01 12.27 11.43 9.88 8.38 5.65 9.25 9.29 9.41 9.58 9.77 9.97 10.19 10.39 10.55 10.70 10.85 10.94 10.82 10.66 10.06 9.37 8.10 6.87 4.63 The process computer utilizes exposure dependent MAPLHGR limits for each lattice type as provided in Reference 8. When hand calculations of MAPLHGR are performed, the limits shall not exceed the limits provided in the table above for this fuel type (Ref. 1).

Technical Specification

References:

3.6.G. I a and 3.1.A.

1 MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.

8

Cycle 23 COLR Revision 0 October 2002 Table 2.1-2 MAPLHGR Versus Average Planar Exposure for GEl 3-P9HTB380-12GZ-IOOT-146-T Fuel Bundle No 2278 Average Planar Exposure (GWd/ST) 0.00 0.20 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 1000 12.50 15.00 17.50 20.00 25.00 30.00 35.00 40.00 45.00 50.00 55.00 57.58 MAPLHGR (kW/ft)

Two Loop Operation 10.64 10.71 10.85 11.04 11.23 11.43 11.64 11.82 11.96 12.12 12.27 12.44 12.57 12.24 11.90 11.54 10.82 10.12 9.43 8.76 8.10 7.44 6.77 6.42 Single Loop Operationi 8.72 8.78 8.89 9.05 9.20 9.37 9.54 9.69 9.80 9.93 10.06 10.20 10.30 10.03 9.75 9.46 8.87 8.29 7.73 7.18 6.64 6.10 5.55 5.26 The process computer utilizes exposure dependent MAPLHGR limits for each lattice type as provided in Reference 8. When hand calculations of MAPLHGR are performed, the limits shall not exceed the limits provided in the table above for this fuel type (Ref. 1).

Technical Specification

References:

3.6.G. la and 3.1.A.

1 MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.

9

Cycle 23 COLR Revision 0 October 2002 Table 2.1-3 MAPLHGR Versus Average Planar Exposure for GE13-P9HTB379-13GZ-l00T-146-T Fuel Bundle No. 2279 Average Planar Exposure (GWd/ST) 0.00 0.20 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 10.00 12.50 15.00 17.50 20.00 25.00 30.00 35.00 40.00 45.00 50.00 55.00 57.56 MAPLH-GR (kW/ft)

Two Loop Operation Single Loop Operationi 10.64 10.69 10.81 10.99 11.18 11.36 11.49 11.63 11.78 11.92 12.07 12.22 12.33 12.23 11.90 11.54 10.82 10.11 9.42 8.75 8.09 7.43 6.76 6.40 8.72 8.76 8.86 9.01 9.16 9.31 9.42 9.53 9.65 9.77 9.89 10.02 10.11 10.02 9.75 9.46 8.87 8.29 7.72 7.17 6.63 6.09 5.54 5.24 The process computer utilizes exposure dependent MAPLHGR limits for each lattice type as provided in Reference 8. When hand calculations of MAPLHGR are performed, the limits shall not exceed the limits provided in the table above for this fuel type (Ref. 1).

Technical Specification

References:

3.6.G. la and 3.11.A.

1 MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.

10

Cycle 23 COLR Revision 0 October 2002 Table 2.1-4 MAPLHGR Versus Average Planar Exposure for GE13-P9DTB386-11G4 011G3.0-IOOT-146-T-2425 Fuel Bundle No 2425 Average Planar Exposure (flWdlR~T' 0.00 0.20 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 10.00 12.50 15.00 17.50 20.00 25.00 30.00 35.00 40.00 45.00 50.00 55.00 57.58 MAPLHGR (kW/ft)

Two Loop Operation 10.87 10.94 11.09 11.29 11.50 11.68 11.87 12.06 12.26 12.41 12.55 12.66 12.59 12.28 11.95 11.62 10.92 10.22 9.54 8.87 8.20 7.52 6.84 6.47 Single Loop Operationi 8.91 8.97 9.09 9.25 9.43 9.57 9.73 9.88 10.05 10.17 10.29 10.38 10.32 10.06 9.79 9.52 8.95 8.38 7.82 7.27 6.72 6.16 5.60 5.30 The process computer utilizes exposure dependent MAPLHGR limits for each lattice type as provided in Reference 8. When hand calculations of MAPLHGR are performed, the limits shall not exceed the limits provided in the table above for this fuel type (Ref. 1).

Technical Specification

References:

3.6.G. 1 a and 3.11.A.

1 MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.

11 (GW ST)

Cycle 23 COLR Revision 0 October 2002 Table 2.1-5 MAPLHGR Versus Average Planar Exposure for GE13-P9DTB225-NOG-100T-146-T-2570 Fuel Bundle No. 2570 Average Planar Exposure (GWdIST) 0.00 0.20 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 10.00 12.50 15.00 17.50 20.00 25.00 30.00 35.00 40.00 45.00 50.00 55.00 56.78 MAPLHGR (kW/ft)

Two Loop Operation 12.95 12.91 12.88 12.88 12.91 12.94 12.99 13.05 13.10 13.10 13.10 13.10 13.10 13.03 12.75 12.45 11.56 1054 9.51 8.53 7.61 6.75 5.93 5.65 Single Loop Operation' 10.61 10.58 10.56 10.56 10.58 10.61 10.65 10.70 10.74 10.74 10.74 10.74 10.74 10.68 10.45 10.20 9.47 8.64 7.79 6.99 6.24 5.53 4.86 4.63 The process computer utilizes exposure dependent MAPLHGR limits for each lattice type as provided in Reference 8. When hand calculations of MAPLHGR are performed, the limits shall not exceed the limits provided in the table above for this fuel type (Ref. 1).

Technical Specification

References:

3.6 G. l a and 3.1.A.

1 MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.

12

Cycle 23 COLR Revision 0 October 2002 Table 2.1-6 MAPLHGR Versus Average Planar Exposure for GE14-P1ODNAB394-7G5.016G4.0-100T-150-T-2538 Fuel Bundle No 2538 Average Planar Exposure (GWd/ST) 0.00 0.20 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 17.00 20.00 25.00 30.00 35.00 40.00 45.00 50.00 55.00 57.13 MAPLHGR (kW/ft)

Two Loop Operation Single Loop Operation' 9.66 9.73 9.87 10.03 10.19 10.37 10.55 10.74 10.93 11.10 11.26 11.42 11.57 11.64 11.62 11.57 11.50 11.31 10.98 10.44 9.92 9.40 8.90 8.38 7.84 5.91 4.85 7.92 7.97 8.09 8.22 8.35 8.50 8.65 8.80 8.96 9.10 9.23 9.36 9.48 9.54 9.52 9.48 9.43 9.27 9.00 8.56 8.13 7.70 7.29 6.87 6.42 4.84 3.97 The process computer utilizes exposure dependent MAPLHGR limits for each lattice type as provided in Reference 8. When hand calculations of MAPLHGR are performed, the limits shall not exceed the limits provided in the table above for this fuel type (Ref. 1).

Technical Specification References" 3.6.G.la and 3.11.A.

1 MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.

13

Cycle 23 COLR Revision 0 October 2002 Table 2.1-7 MAPLHGR Versus Average Planar Exposure for GE14-P1ODNAB394-8G5.0/6G4 0-100T-150-T-2589 Fuel Bundle No 2589 Average Planar Exposure (GWdIST) 0.00 0.20 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 17.00 20.00 25.00 30.00 35.00 40.00 45.00 50.00 55.00 57.08 MAPLHGR (kW/ft)

Two Loop Operation 9.56 9.63 9.77 9.95 10.11 10.29 10.47 10.66 10.85 11.02 11.18 11.34 11.51 11.58 11.58 11.55 11.49 11.30 10.98 10.44 9.91 9.40 8.89 8.38 7.83 5.89 4.85 Single Loop Operationi 7.83 7.89 8.01 8.15 8.29 8.43 8.58 8.74 8.89 9.03 9.16 9.29 9.43 9.49 9.49 9.47 9.42 9.26 9.00 8.56 8.12 7.70 7.28 6.87 6.42 4.82 3.97 The process computer utilizes exposure dependent MAPLHGR limits for each lattice type as provided in Reference 8. When hand calculations of MAPLHGR are performed, the limits shall not exceed the limits provided in the table above for this fuel type (Ref. 1).

Technical Specification

References:

3.6.G.la and 3.1 1.A.

1 MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.

14

Cycle 23 COLR Revision 0 October 2002 Table 2.1-8 MAPLHGR Versus Average Planar Exposure for GE14-P1ODNAB394-12G5.0-100T-150-T-2590 Fuel Bundle No. 2590 Average Planar Exposure (GWd/ST) 0.00 0.20 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 17.00 20.00 25.00 30.00 35.00 40.00 45.00 50.00 55.00 57.14 MAPLHGR (kW/ft)

Two Loop Operation Single Loop Operationi 9.81 9.87 9.97 10.11 10.26 10.41 10.57 10.74 10.91 11.06 11.19 11.33 11.46 11.53 11.52 11.49 11.44 11.28 10.97 10.44 9.91 9.40 8.89 8.38 7.84 5.92 4.85 8.04 8.09 8.17 8.29 8.41 8.53 8.66 8.80 8.94 9.06 9.17 9.29 9.39 9.45 9.44 9.42 9.38 9.24 8.99 8.56 8.12 7.70 7.28 6.87 6.42 4.85 3.97 The process computer utilizes exposure dependent MAPLHGR limits for each lattice type as provided in Reference 8. When hand calculations of MAPLHGR are performed, the limits shall not exceed the limits provided in the table above for this fuel type (Ref. 1).

Technical Specification

References:

3.6.G. I a and 3.11.A.

1 MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.

15

Cycle 23 COLR Revision 0 October 2002 Table 2.2-1 Cycle 23 MCPR Operating Limits (OLMCPR) and RBM Setpoints MCPR Operating Limits (OLMCPR)

Option Cycle Exposure Two Loop Single Loop Range Operation 2 Operation Option A 0 to 10375 MWd/St 1.49 1.51 beyond 10375 MWd/St 1.61 1.63 Option B 0 to 10375 MWd/St 1.40 1.42 beyond 10375 MWd/St 1.44 1.46 Source:

References 6 and 7.

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.

RBM Setpoints 3 Maximum Value of "N" in RBM Setpoint Equation - 44.

Maximum Allowable RBM Rod Block setpoint - 110% power.

Source:

Reference 7.

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.

16

Cycle 23 COLR Revision 0 October 2002 Table 2.3-1 Maximum Allowable Linear Heat Generation Rate Limits Fuel Type GE9B-P8DWB335-10GZ-80M-150-T GEl 3-P9HTB380-12GZ-100T-146-T GEl 3-P9HTB 379-13GZ-100T-146-T GE13-P9DTB386-1 1G4.011G3.0-10OT-146-T-2425 GE 13-P9DTB225-NOG-LOOT-146-T-2570 GE14-P1ODNAB394-7G5.0/6G4.0-1OOT-150-T-2538 GE14-P1ODNAB394-8G5.016G4.0-1OOT-150-T-2589 GE14-P1ODNAB394-12G5.0-LOOT-150-T-2590 Maximum Allowable Linear Heat Generation Rate (kW/ft) 14.4 14.4 14.4 14.4 14.4 13.4 13.4 13.4 The process computer utilizes exposure dependent LHGR limits for each lattice type as provided in Reference 8.

Technical Specification

References:

2.1.A. 1 a, 2.1.B. 1, and 3.11.B.

17

Cycle 23 COLR Revision 0 October 2002 r

7 7

T I

I 1.4 1.3 12 1.1 1

09

\\

I 

1 ---.4

+

N 7

4 4

I N

t I

I t

r S.

4.

.6.

I a..

a.........L.a.4..

I 20 30 40 50 60 70 80 90 100 110 Total Core Flow (%) WT Figure 2.2-1 K1 vs Total Core Flow (Technical Specification Reference 3.1 I.C) 18 Equations for Kf curves:

Kf >= 1.0 Kf(WT>=40%) = A-0 441*(WT/100%)

Kf(WT<40%) =

Kf(WT>=40%)*(1.0+0.0032*(40-WT))

Stop Setting A

102.5%

1.3308 104.5%

1.3406 107.0%

1.3528 109.5%

1.3661 112.0%

1.3793 117.0%

1.4035 Value of A should be interpolated for Stop Settings other than those listed above.

4.-4 fI Manual Flow Control Scoop Tube Stop Settings Max Flow 102.5%

104.5%

107.0%

109.5%

112.0%

117.0%

S.

m I

f J

I i

Cycle 23 COLR Revision 0 October 2002 0

10 20 30 40 50 60 Total Core Flow (%)

70 80 90 100 110 Figure 2.4-1 Limits of Power/Flow Operation (Technical Specification Reference 3.6.J) 19 120 110 100 90 80 70 60 50 40 30 20 10 0

0

0.

I-0 0

Cycle 23 COLR Revision 0 October 2002

3.0 REFERENCES

1.

Report, General Electric Standard Application for Reactor Fuel (GESTARII),

NEDE-2401 1-P-A-14, GE Company Proprietary, June 2000.

2.

Report, General Electric Nuclear Energy, BWR Owners' Group Long-Term Stability Solutions Licensing Methodology, NEDO-31960, June 1991.

3.

Report, General Electric Nuclear Energy, BWR Owners' Group Long-Term Stability Solutions Licensing Methodology, NEDO-31960, Supplement 1, March 1992.

4.

Letter, USNRC to VYNPC, SER, August 9, 1995.

5.

Report, Vermont Yankee Nuclear Power Station SAFER/GESTR-LOCA Loss-of-Coolant Analysis, NEDC-32814P, March 1998.

6.

Report, Global Nuclear Fuels, Cycle Management Report for Vermont Yankee Nuclear Power Station Cycle 23, 0000-0007-9764-CMR, Rev. 0, October 2002.

7.

Report, Global Nuclear Fuels, Supplemental Reload Licensing Report for Vermont Yankee Nuclear Power Station Reload 22 Cycle 23, 0000-0006-1823-SRLR, Rev. 0, October 2002.

8.

Report, Global Nuclear Fuels, Lattice Dependent MAPLHGR Report for Vermont Yankee Nuclear Power Station Reload 22 Cycle 23, 0000-0006-1823-MAPL, Rev. 0, October 2002.

9.*

Report, BWR Owners' Group Long-Term Stability Solutions Licensing Methodology,"

NEDO-31960-A, November 1995.

10.*

Report, BWR Owners' Group Long-Term Stability Solutions Licensing Methodology,"

NEDO-31960-A, Supplement 1, November 1995.

11.

Report, Vermont Yankee Nuclear Power Station Increased Core Flow Analysis, NEDC 32791P, February 1999.

12.

Report, GE, Vermont Yankee ECCS-LOCA Evaluation for GE14 and GE13, GE-NE-0000-0000-9381-02P, September 2002

13.

Global Nuclear Fuels Letter WHV:2001-023, William H. Hetzel (GNF) to Dave Mannai (VYNPC), Vermont Yankee Option B Licensing Basis, November 9, 2001.

• References 9 and 10 are the generically approved documents for References 2 and 3, including the SER from Reference 4.

20