ML021560411

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Core Operating Limits Report for Cycle 22B
ML021560411
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 06/03/2002
From: Sen G
Vermont Yankee
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BVY 02-40
Download: ML021560411 (26)
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Text

VERMONT YANKEE NUCLEAR POWER CORPORATION 185 OLD FERRY ROAD, PO BOX 7002, BRATFLEBORO, VT 05302-7002 (802) 257-5271 June 3, 2002 BVY 02-40 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 Operating Limits Report for Cycle 22B In accordance with Section 6.6.C of the Vermont Yankee Technical Specifications, enclosed is the Core Operating Limits Report (COLR) for Cycle 22B. This report presents the cycle-specific operating limits for Cycle 22B of the Vermont Yankee Nuclear Power Station.

If you have any questions concerning this transmittal, please contact Mr. Jeffrey T. Meyer at (802) 258-4105.

Sincerely, VERMONT YANKEE NUCLEAR POWER CORPORATION 4 liGautam Sen Licensing Manager Enclosure cc: USNRC Region I Administrator USNRC Resident Inspector- VYNPS USNRC Project Manager - VYNPS Vermont Department of Public Service

SUMMARY

OF VERMONT YANKEE COMMITMENTS BVY NO.: 02-40 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 ICOMMITTED DATE

___ ________ ___ ____ ___OR "OUTAGE" None N/A

+

+

i VYAPF 0058.04 AP 0058 Original Page 1 of 1

Vermont Yankee Nuclear Power Station Cycle 22B Core Operating Limits Report Revision 0 May 2002

Cycle 22B COLR Revision 0 May 2002 Prepared -~ V \Jor

&.2 Reactor Engineer Date Reviewed F--tI~cL k L 6 Reactor Engineer Date Approved AA R a/or Engineering Manager Date Reviewed 1mm, -:)4ea a-O f Ž c~

Plant Operations Review Committee Date Approved - -da Plant Manager Date Approved President o p n Vice President of Operations Date 7 "'m~2e, e&eYjlr ii

Cycle 22B COLR Revision 0 May 2002 REVISION RECORD Cycle Revision Date Description 22B 0 5/2002 Cycle 22B revision. Reviewed by PORC and approved by management.

iii

Cycle 22B COLR Revision 0 May 2002 ABSTRACT This report presents the cycle-specific operating limits for the operation of Cycle 22B 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 22B COLR Revision 0 May 2002 TABLE OF CONTENTS Page_

REVISION RECORD .................................................................................................. iii ABSTRACT .............................................................................................................................. iv LIST OF TABLES ....................................................................................................................... vi LIST OF FIGURES .................................................................................................................... vii

1.0 INTRODUCTION

............................................................................................................... 1 2.0 CORE OPERATING LIM ITS ............................................................................................. 2 2.1 Maximum Average Planar Linear Heat Generation Rate Limits.............................1 2 2.2 Minimum Critical Power Ratio Limits ................................ 2 2.3 M aximum Linear Heat Generation Rate Limits ........................................................... 3 2.4 Thermal-Hydraulic Stability Exclusion Region ........................................................... 4 2.5 Power/Flow M ap ........................................................................................................ 6

3.0 REFERENCES

.............................................................................................................. 17 v

Cycle 22B COLR Revision 0 May 2002 LIST OF TABLES Number Title Page Table 2.1-1 MAPLHGR Versus Average Planar Exposure for GE9B-BP8DWB354-12GZ-80U-150-T Fuel Bundle No. 2153 7 Table 2.1-2 MAPLHGR Versus Average Planar Exposure for GE13-P9HTB3380-12GZ-100T-146-T Fuel Bundle No. 2278 8 Table 2.1-3 MAPLHGR Versus Average Planar Exposure for GE13-P9HTB379-13GZ- 100T-146-T Fuel Bundle No. 2279 9 Table 2.1-4 MAPLHGR Versus Average Planar Exposure for GE13-P9HTB388-13GZ-100T-146-T Fuel Bundle No. 2365 10 Table 2.1-5 MAPLHGR Versus Average Planar Exposure for GE13-P9DTB386-11 G4.0/1G3.0-lOOT- 146-T-2425 Fuel Bundle No. 2425 11 Table 2.1-6 MAPLHGR Versus Average Planar Exposure for GEl 3-P9DTB225-NOG-1OOT-146-T-2570 Fuel Bundle No. 2570 12 Table 2.2-1 Cycle 22B MCPR Operating Limits 13 Table 2.3-1 Maximum Allowable Linear Heat Generation Rate Limits 14 vi

Cycle 22B COLR Revision 0 May 2002 LIST OF FIGURES Number Title Page 2.2-1 Kf vs. Total Flow Rate 15 2.4-1 Limits of Power/Flow Operation 16 vii

Cycle 22B COLR Revision 0 May 2002

1.0 INTRODUCTION

This report provides the cycle-specific limits for operation of the Vermont Yankee Nuclear Power Station in Cycle 22B. 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 22B 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.

I

Cycle 22B COLR Revision 0 May 2002 2.0 CORE OPERATING LIMITS The Cycle 22B operating limits have been defined using NRC-approved methodologies. Cycle 223 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. 3.11.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 2.1-7. 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 5). 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 bumup. The process computer will verify that these lattice MAPLHGR limits are not violated. Tables 2.1-1 through 2.1-7 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. 3.1I1.C)

During steady-state power operation, the Minimum Critical Power Ratio (MCPR) shall be equal to, or greater than, the limits shown in Table 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.

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Cycle 22B COLR Revision 0 May 2002 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 22B.

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 22B3.

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Cycle 22B COLR Revision 0 May 2002 2.4 Thermal-Hydraulic Stability Exclusion Region (T.S. 3.6j)

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 22B. 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:

Point Power (%) Flow (%)

A 73.5 50.3 B 31.8 30.6 The equation for the boundary is as follows:

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),

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:30.6% <%Flow <50.3%

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Cycle 22B COLR Revision 0 May 2002 The coordinates of the Buffer Region are as follows:

Point Power (%) Flow (%)

C 77.6 55.3 D 26.8 29.6 The generic equation used to generate the 5% buffer zone exclusion region boundary is:

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%.

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Cycle 22B COLR Revision 0 May 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.
  • 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.

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Cycle 22B COLR Revision 0 May 2002 Table 2.1-1 MAPLHGR Versus Average Planar Exposure for GE9B-BP8DWB354-12GZ-80U-150-T Fuel Bundle No. 2153 MAPLEOR (kWfft)

Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation' 0.00 10.96 8.98 0.20 11.04 9.05 1.00 11.18 9.16 2.00 11.40 9.34 3.00 11.63 9.53 4.00 11.81 9.68 5.00 12.01 9.84 6.00 12.14 9.95 7.00 12.26 10.05 8.00 12.37 10.14 9.00 12.46 10.21 10.00 12.52 10.26 12.50 12.40 10.16 15.00 12,10 9.92 20.00 11.40 9.34 25.00 10.72 8.79 35.00 9.44 7.74 45.00 7.24 5.93 48.20 5.67 4.64 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 MAPLI-GR for single loop operation is obtained by multiplying MAPLIIGR for two loop operation by 0.82.

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Cycle 22B COLR Revision 0 May 2002 Table 2.1-2 MAPLOIGR Versus Average Planar Exposure for GE13-P9HTB380-12GZ-100T-146-T Fuel Bundle No. 2278 MLAPLHGR (kW/ft)

Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation' 0.00 10.64 8.72 0.20 10.71 8.78 1.00 10.85 8.89 2.00 11.04 9.05 3.00 11.23 9.20 4.00 11.43 9.37 5.00 11.64 9.54 6.00 11.82 9.69 7.00 11.96 9.80 8.00 12.12 9.93 9.00 12.27 10.06 10.00 12.44 10.20 12.50 12.57 10.30 15.00 12.24 10.03 17.50 11.90 9.75 20.00 11.54 9.46 25.00 10.82 8.87 30.00 10.12 8.29 35.00 9.43 7.73 40.00 8.76 7.18 45.00 8.10 6.64 50.00 7.44 6.10 55.00 6.77 5.55 57.58 6.42 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. I a and 3.1 1.A.

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

8

Cycle 22B COLR Revision 0 May 2002 Table 2.1-3 MAPLHGR Versus Average Planar Exposure for GE 13-P9HTB379-13GZ- 100T- 146-T Fuel Bundle No. 2279 MAPLHGR (kW/ft)

Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation' 0.00 10.64 8.72 0.20 10.69 8.76 1.00 10.81 8.86 2.00 10.99 9.01 3.00 11.18 9.16 4.00 11.36 9.31 5.00 11.49 9.42 6.00 11.63 9.53 7.00 11.78 9.65 8.00 11.92 9.77 9.00 12.07 9.89 10.00 12.22 10.02 12.50 12.33 10.11 15.00 12.23 10.02 17.50 11.90 9.75 20.00 11.54 9.46 25.00 10.82 8.87 30.00 10.11 829 35.00 9.42 7.72 40.00 8.75 7.17 45.00 8.09 6.63 50.00 7.43 6.09 55.00 6.76 5.54 57.56 6.40 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 3.1 l.A.

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

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Cycle 22B COLR Revision 0 May 2002 Table 2.1-4 MAPLHGR Versus Average Planar Exposure for GE1 3-P9HTB388-13GZ-100T- 146-T Fuel Bundle No. 2365 MAPLHGR (kW/ft)

Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation' 0.00 10.85 8.89 0.20 10.93 8.96 1.00 11.06 9.06 2.00 11.25 9.22 3.00 11.45 9.38 4.00 11.63 9.53 5.00 11.78 9.65 6.00 11.92 9.77 7.00 12.06 9.88 8.00 12.2 10.00 9.00 12.32 10.10 10.00 12.44 10.20 12.50 12.42 10.18 15.00 12.22 10.02 17.50 11.95 9.79 20.00 11.64 9.54 25.00 10.93 8.96 30.00 10.23 8.38 35.00 9.55 7.83 40.00 8.87 7.27 45.00 8.21 6.73 50.00 7.54 6.18 55.00 6.86 5.62 57.86 6.46 5.29 The process computer utilizes exposure dependent MAPLHGR limits for each lattice type as provided in Reference 8. When hand calculations of MAPLHIGR 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 MAPLH-R for two loop operation by 0.82.

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Cycle 22B COLR Revision 0 May 2002 Table 2.1-5 MAPLHGR Versus Average Planar Exposure for GE 13-P9DTB386-1 1G4.0/1G3.0-1 0OT- 146-T-2425 Fuel Bundle No. 2425 MAPLHGR (kW/ft)

Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation' 0.00 10.87 8.91 0.20 10.94 8.97 1.00 11.09 9.09 2.00 11.29 9.25 3.00 11.5 9.43 4.00 11.68 9.57 5.00 11.87 9.73 6.00 12.06 9.88 7.00 12.26 10.05 8.00 12.41 10.17 9.00 12.55 10.29 10.00 12.66 10.38 12.50 12.59 10.32 15.00 12.28 10.06 17.50 11.95 9.79 20.00 11.62 9.52 25.00 10.92 8.95 30.00 10.22 8.38 35.00 9.54 7.82 40.00 8.87 7.27 45.00 8.2 6.72 50.00 7.52 6.16 55.00 6.84 5.60 57.58 6.47 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.la and 3,11.A.

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

1I

Cycle 22B COLR Revision 0 May 2002 Table 2.1-6 MAPLHGR Versus Average Planar Exposure for GE13-P9DTB225-NOG-100T-146-T-2570 Fuel Bundle No. 2570 MAPLHGR (kW/ft)

Average Planar Exposure (GWd/ST) Two Loop Operation Single Loop Operation1 0.00 12.95 10.61 0.20 12.91 10.58 1.00 12.88 10,56 2.00 12.88 10.56 3.00 12.91 10.58 4.00 12.94 10.61 5.00 12.99 10.65 6.00 13.05 10.7 7.00 13.10 10.74 8.00 13.10 10.74 9.00 13.10 10.74 10.00 13.10 10.74 12.50 13.10 10.74 15,00 13.03 10.68 17.50 12.75 10.45 20.00 12.45 10.20 25.00 11.56 9.47 30.00 10.54 8.64 35.00 9.51 7.79 40.00 8.53 6.99 45.00 7.61 6.24 50.00 6.75 5.53 55.00 5.93 4.86 56.78 5.65 4.63 The process computer utilizes exposure dependent MAPLHGR limits for each lattice type as provided in Reference 8. When hand calculations of MAPIHGR 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.

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Cycle 22B COLR Revision 0 May 2002 Table 2.2-1 Vermont Yankee Nuclear Power Station Cycle 22B MCPR Operating Limits Value of "N"in RBM Average Control Cycle Exposure Two Loop Single Loop Equation (A)1 Rod Scram Time Range Operation 3 Operation 44% Equal to or better 7806 to 9300 MWd/St 1.34 1.36 than L.C.O. beyond 9300 MWd/St 1.36 1.38 3.3.C.1.1 Equal to or better 7806 to 9300 MWd/St 1.37 1.39 than L.C.O. beyond 9300 MWd/St 1.46 1.48 3.3.C.1.2 Maximum Allowable RBM Rod Block setpoint - 110% power.

Source: References 6 and 7.

Technical Specification

References:

3.6.G. la and 3.11 .C.

1 The Rod Block Monitor (RBM) trip setpoints are determined by the equation shown in Table 3.2.5 of the Technical Specifications.

2 The MCPR operating limits should be increased by 0.02 for the single loop operation.

3 The two loop MCPR operating limits bound ICF operation throughout the cycle.

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Cycle 22B COLR Revision 0 May 2002 Table 2.3-1 Maximum Allowable Linear Heat Generation Rate Limits Maximum Allowable Linear Fuel Type Heat Generation Rate (kW/ft)

GE9B-BPSDWB354-12GZ-80U-150-T 14.4 GE13-P9HTB380-12GZ- 100T-146-T 14.4 GE13-P9HTB379-13GZ- 100T-146-T 14.4 GE13-P9HTB38S-I3GZ- 100T-146-T 14.4 GE13-P9DTB386-1 1G4.0/1G3.0-100T 14.4 146-T-2425 GE13-P9DTB225-NOG- 100T-146-T 14.4 2570 The process computer utilizes exposure dependent LHGR limits for each lattice type as provided in Reference 8.

Technical Specification

References:

2.1.A. la, 2.1.B.1, and 3.1 I.B.

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Cycle 22B COLR Revision 0 May 2002 1.4 F 1 T Equations for Kf curves:

Kf >= 1.0 Kf(WT>=40%) = A-0.441*(WT/100%)

Kf(WT<40%) =

1.3 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% 1.3659 112.0% 1.3793 1.2 117.0% 1.4035 Value of A should be interpolated for Stop Settings other than those listed above.

1.1 Manual Flow Control Scoop Tube Stop Settings Max Flow 102.5%

104.5%

107.0%

109.5%

11-0 fOL 117.0%

.. .. . .. . 1 . . ........ . .. . .. . -. .. .. ... . .

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 1.C) 15

Cycle 22B COLR Revision 0 May 2002 120 110 100 90 80

- 70 s

60 2

00 so 40 30 20 10 0 10 20 30 40 50 60 70 80 90 100 110 Total Core Flow (%)

Figure 2.4-1 Limits of Power/Flow Operation (Technical Specification Reference 3.6.3) 16

Cycle 22B COLR Revision 0 May 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, Cycle Management Report for Vermont Yankee Nuclear Power Station Cycle 22B, 0000-0004-2829-CMR, Rev. 0, May 2002.
7. Letter, Vermont Yankee Cycle 22B Option 1-D Stability Decay Ratio Analysis (ODYSY Based), NSA 02-308, May 20,2002
8. Report, Lattice Dependent MAPLHGR Report for Vermont Yankee Nuclear Power Station Reload 21B Cycle 22B, 0000-0003-901 1-MAPL, Rev. 0, May 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 3279 IP,February 1999.
  • References 9 and 10 are the generically approved documents for References 2 and 3, including the SER from Reference 4.

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