ML20247G990
| ML20247G990 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 06/30/1989 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML20247G885 | List: |
| References | |
| NUDOCS 8905310132 | |
| Download: ML20247G990 (16) | |
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Vermont Yankee Cycle 14 Core Operating Limits Report Revision 0 June 1989 7503R Controlled Copy No. __
013 $4 DEl j 0033
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. DJECIAIMER OF RESPONSIBILITY This document was prepared by Yankee Atomic Electric Company
(" Yankee"). The use of information contained in this document by anyone other than Yankee, or the Organization for which this document was prepared under contract, is not authorized and, with respect to any unauthorized ung, neither.
Yankee nor its officers, directors, agents, or' employees assume any obligation, responsibility, or liability or make any warranty or representation as to the accuracy or completeness of the material contained in this document..
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ABSTRACT This report presents the cycle-specific operating limits for the operation of Cycle 14 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 the fuel cladding integrity safety limit.
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TABLE OF CONTENTS i f
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.e te ~ DISCLAIMER OF RESPONSIBILITY...................................... 11 ABSTRACT.......................................................... iii' q
. LIST OF TABLES........................................ v-p, ...........
l LIST OF FIGURES................................................... vi 1.0 IN TRODUCT I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2.0 CORE OPERATING LIMITS............................................ 2 2.1 Maximum Average Planar Linear Heat Generation Rate Limits.. 2 2.2 Maximum Linear Heat Generation Rate' Limits................. 2.
2.3 Minimum Critica1' Power Ratio Limits........................ 2
3.0 REFERENCES
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LIST OF TABLES Number Title Eage 2.1-1 MAPLHGR Versus Average Planar Exposure for 8DPB289 and P8DPB289 3 2.1-2 MAPLHGR Versus Average Planar Exposure for BP8DRB299 4 2.1-3 MAPLHGR Versus Average Planar Exposure for BD324B 5 2.1-4 MAPLHGR Versus Average Planar Exposure for BD326B 6 2.1-5 Significant Input Parameters to the Loss-of-Coolant Accident Analysis 7 2.3-1 MCPR Operating Limits for Cycle 14 8 i
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t LIST OF FIGURES Number Title Page 2.3-1 Kg Versus Percent of Core Flow Rate 9
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1.0 INTRODUCTION
This report provides the cycle-specific limits for operation of the Vermont Yankee Nuclear Power Station through Cycle 14. It includes the limits for the maximum average planar linear heat generation rate, maximum linear heat generation rate, and minimum critical power ratio. In this report, Cycle 14 will frequently be referred to as the Present Cycle. If any of these limits are exceeded, the action will be taken as defined in the Technical Specifications.
This report has been prepared in accordance with the requirements of Technical Specification 6.7.A.4. The core operating limits have been developed using the NRC-approved methodologies listed in References 1 through 14 and in Technical Specification 6.7.A.4. The bases for these limits are in References 15 and 16.
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, 2.0 CDRE OPERATING LIMITS 4
These Present Cycle operating limits have been defined using NRC-approved methodologies. The Present Cycle must be operated.within the bounds of thece limits and all others specified in the Technical
. Specifications.
2.1 Maximum Avetage Planar Linear Heat Generation Rate Limits
'During steady-state power operation, the Maximum Average Planar Linear Heat ' Generation Rate (MAPLHGR) for each fuel types in the Present Cycle as a function of the. average planar exposure shall not exceed the limiting values shown in Tables 2.1-1 through 2.1-4. 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 0.83. Table 2.1-5 lists the'significant plant input parameters to the loss-of-coolant accident analysis used in generating the MAPLHGR limits.
2.2 Maximum Linear Heat Generation Rate Limits During steady-state power operation, the Linear Heat Generation Rate (LHGR) of any rod in any fuel assembly at any axial location shall not exceed the peak LHGR limits in Table 2.1-5. There are different LHGR limits for different fuel types.
2.3 Minimum Critical Power Ratio Limits During steady-state power operation, the Minimum Critical Power Ratio (MCPR) operating value shall be equal to or greater than the limits in Table 2.3-1. For single recirculation loop operation, Lhe MCPR limits at rated flow are increased by 0.01. For core flows other than rated, the MCPR limit shall be the above value multiplied by Kg where Kg is given in Figure .2.3-1. These operating values were defined using the NRC-approved GEXL correlation and will assure that the Fuel Cladding Integrity Safety Limit (FCISL) is not violated. The FCISL is 1.04 (1.05 for Single Loop Operation) for the Present Cycle core loading.
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r TABLE 2.1-1 tMPJJiGR Versus Average Planar Exposure Plant: Vermont Yanken Fuel Type: 8DPB289 & P8DPB289 1
Average Planar MAPHLGR (kW/ft) i Exposure Two Loop
- Single Loop (mwd /t) Operation Operation 200.0 11.2 9.3 1,000.0 11.2 9.3 5,000.0 11.8 9.8 10,000.0 12.0 10.0 15,000.0 12.1 10.0 20,000.0 11.8 9.8 25,000.0 11.3 9.4 30,000.0 11.1 9.2 35,000.0 10.4 8.6 40,000.0 9.8 8.1 l Source: NED0-21697, August 1977 (revised)
Technical Specification
References:
3.6.G.la, 3.11.A. 3.11.D, 4.11.A and 4.11.B
- MAPLHGR for single loop operation is obtained by multiplying MAPLIIGR for two loop operation by 0.83.
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IABLE 2.1-2 MAPLHGR Versus Averagg E anar Exp.osure Plant: Vermont Yankee Fuel Type: BP8DRB299 Average Planar MAPHLGR (kW/ft)
Exposure Two Loop
- Single Loop (mwd /t) Operation Operation 200.0 10.7 8.8 1,000.0 10.8 8.9 5,000,0 11.4 9.4 10,000.0 12.2 10.1 15,000.0 12.3 10.2 20,000.0 12.2 10.1 25,000.0 11.7 9.7 35,000.0 10.6 8.8 41,900.0 9.4 7.8 Source: NED0-21697, August 1977 (revised) 1 Technical Specification
References:
3.6.G.la, 3.11.A, 3.11.D, 4.11.A, and 4.11.B
- MAPLEGR for single loop operation is obtained by multiplying MAFLHGR for two loop operation by 0.83.
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TABLE 2.1-3 '
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MAPLHGR Versus Average Planar Exposure Plant: Vermont Yankee Fuel Type: BD324B Average Planar MAPHLGR (kW/ft) for Two Loop Oneration Exposure Majority Shutdown . Power Peaking ' Natural (mwd /t) Lattice 'liargin Zone Zone Ends 200.0 11.76 11.24 11.71 11.50 1,000.0 11.90 11.42 11.83 11.30 2,000.0 12.05 11.61 11.96 11.28 3,000.0 12.21 11.85 12.15 11.33 5,000.0 12.51 12.17 12.40 11.47
'7,000.0 12.63 12.54 12.63 11.61 10,000.0 12.80 12.80 12.80 11.72 14,400.0 12.80 12.80 12.80 11.15 15,000.0 12.75 12.74 12.74 11.07 20,000.0 12.07 '12.05 12.06 10.29 25,000.0 11.41 11.39 11.40 9.50 35,000.0 10.14 10.12 10.12 7.93 43,360.0 8.80 8.73 8.74 4.66 50,000,0 6.08 5.99 6.02 -
Average Planar MAPHLGR (kW/ft) for Single Loop Operation
- Exposure. Majority Shutdown Power Peaking Natural (mwd /t) Lattice Margin Zone Zone Ends 200.0 9.76 9.32 9.71 9.54 1,000.0 9.87 9.47 9.81 9.37 2,000.0 10.00 9.63 9.92 9.36.
3,000.0' 10.13 9.83 10.08 9.40 5,000.0 10.38 10.10 10.29 9.52 7,000.0 10.48 10.40 10.48 9.63 10,000.0 10.62 10.62- 10.62 9.72 14,400.0 10.62 10.62 10.62' 9.25 15,000.0 10.58 10.57 10.57 9.18 20,000.0 10.01 10.00 10.00 8.54 25,000.0 9.47 9.45 9.46 7.88 35,000.0 8.41 8.39 8.39 6.58 43,360.0 7.30 7.24 7.25 3.86 50,000.0 5.04 4.97 4.99 -
Source: NEDO-21697, August 1977 (revised)
Technical Specification
References:
3.6.G.la, 3.11.A, 3.11.D 4.11.A, and 4.11.B
- MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.83.
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.Iable 2.1-4 MAPLHGR Versus Average Planar ExDDEura
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Plant: Vermoni_ Yankee Fuel Type: BD3263 .
J Average Planar MAPHLGR (kW/ft) for Two Loop Operation Exposure Majority Shutdown Power Peaking Natural (mwd /t) Lattice Margin Zone Zone __Enda_
200.0 11.80 11.35 11.76 11.50 1,000.0 11.86 11.42 11.79 11.30 2,000.0 11.97 11.56 11.88 11.28 3,000.0 12.10 11.74 11.99 11.33 5,000.0 12.48 12.16 12.33 11.47 7,000.0 12.69 12.66 12.69 11.61 10,000.0 12.90 12.90 12.90 11.72 14,400.0 12.90 -12.90 12.90 11.15 15,000.0 12.84 12.82 12.82 11.07 20,000.0 12.14 12.12 12.12 10.29 25,000.0 11.46 11.44 11.45 9.50 35,000.0 10.17 10.15 10.16 7.93 43,360.0 8.94 8.87 d.91 4.66 50,000.0 6.25 6.17 6.22 -
Average Planar MAPHLGR (kW/ft) for Singig_ Lapp _Dperation*
Exposure Majority Shutdown Power Peaking Natural (mwd /t) Lattice Margin Zone Zone. ... Enda_
200.0 9.79 9.42 9.76 9.54 1,000.0 9.84 9.47 9.78 9.37 2,000.0 9.93 9.59 9.86 9.36 3,000.0 10.04 9.74 9.95 9.40 5,000.0 10.35 10.09 10.23 9.52 7,000.0 10.53 10.50 10.53 9.63 10,000.0 10.70 10.70 10.70 9.72 14,400.0 10.70 10.70 10.70 9.25 15,000.0 10.65 10.64 10.64 9.18 20,000.0 10.07 10.05 10.05 8.54 25,000.0 9.51 9.49 9.50 7.88 35,000.0 8.44 8.42 8.43 6.58 43,360.0 7.42 7.36 7.39 3.86 50,000.0 5.18 5.12 5.16 -
Source: NED0-21697, August 1977 (revised)
Technical Specification
References:
3.6.G.la, 3.11.A, 3411.D, 4.11.A, and 4.11.B
- MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.83.
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,e 3 Table 2.1-5 Significant Input Parameters to the Loss-of-Coolant Accident Analysis Plant Parameters:
Core Thermal Power 1664 MWt, which corresponds to 105% of rated steam flow Vessel Steam Output 6.75 x 10 61bm/h, which corresponds to 105% of rated steam flow Vessel Steam Dome Pressure 1055 psia Recirculation Line Break Area for Large Breaks - Discharge 2.26 ft2 (DBA)
- Suction 4.14 ft2 Number of Drilled Bundles 368 Fuel Parameters:
Maximum Initial Allowable Design Minimum Fuel Linear Heat Axial Critical Bundle Generation Rate Peaking Power Fuel Type Geometry (kW/ft) Factor Ratie*
A. P8DFB289 8x8 13.4 1.4 1.2 B. BP8DRB299 8x8 13.4 1.4 1.2 C. BD324B 8 x 8EB 14.4 1.4 1.2 D. BD326B 8 x 8EB 14.4 1.4 1.2 Technical Specification
References:
2.1.A.la, 2.1.B.1, 3.1.B. 3.11.B. 3.11.D.
4.11.A, and 4.11.B
- To account for the 2% uncertainty in bundle power required by Appendix K, the SCAI calculation is performed with an MCIE of 1.18 (i.e., 1.2 divided by l 1.02) for a bundle with an initial MCIE of 1.20. '
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>+s- a Table 2.3-1 MCPR Operating Limits for Cycle 14 Value of "N" MCPR in RBM Average Control Rod Cycle Operating Equation (1) Scram Time Exoosure Range Limits (2&3)
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42% -Equal or better BOC to E00-2 GWD/T 1.26 than L.C.O. E00-2 GWD/T to E00-1 GWD/T 1.26
-3.3 C.1.1 EOC-1 GWD/T to EOC 1.27 Equal or better BOC to E00-2 GWD/T 1.26 than L.C.O. E00-2 GWD/T to E00-1 GWD/T 1.28 3.3 C.1.2 E00-1 GWD/T to E00 1.32' 41% Equal or better BOC to E00-2 GWD/T 1.22 than L.C.O. EOC-2 GWD/T to E00-1 GWD/T 1.22 3.3 C.1.1 E00-1 GWD/T to EOC 1.27 Equal or better BOC to E00-2 GWD/T 1.22 than L.C.0. EOC-2 GWD/T to E00-1 GWD/T 1.28 3.3 C.1.2 EOC-1 GWD/T to E00 1.32 40% Equal or better B00 to E00-2 GWD/T 1.22 than L.C.O. E00-2 GWD/T to E00-1 GWD/T 1.22 3.3 C.1.1 EOC-1 GWD/T to EOC 1.27 Equal or better BOC to E00-2 GWD/T 1.22 than L.C.O. E00-2 GWD/T to E00-1 GWD/T 1.28 3.3 0.1.2 E00-1 GWD/T to E00 1.32 NOTES:
(1) The Rod Block Monitor (RBM) trip setpoints are determined by the equation i shown in Table 3.2.5 of the Technical Specifications.
(2) The current analyses for MCPR Operating Limits do not include 7x7, 8x8, or 8x8R fuel types. On this basis, if any of these fuel types are to be reinserted, they will be evaluated in accordance with 10CFR50.59 to ensure that the above limits are bounding for these fuel types.
(3) MCPR Operating Limits are increased by 0.01 for single loop operation.
Technical Specification
References:
1.1.A.1, 3.2.E 3.3.B.6, 3.6.G.la, 3.11.C. 3.11.D 4.11.A 4.11.B, and 4.11.C I
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3.0 REFERENCES
- 1. Report, E. E. Pilat, " Methods for the Analysis of Boiling Water Reactors Lattice Physics," YAEC-1232, December 1980.
- 2. Report, D. M. VerPlanck, " Methods for the Analysis of Boiling Water Reactors Steady State Core Physics," YAEC-1238, March 1981.
- 3. Report, J. M. Holzer, " Methods for the Analysis of Boiling Water Reactors Transient Core Physics," YAEC-1239P, August 1981.
- 4. Report, S. P. Schultz and K. E. St. John, " Methods for the Analysis of 0xide Fuel Rod Steady-State Thermal Effects (FROSSTEY) Code /Model Description Manual," YAEC-1242P, April 1981.
- 5. Report, S. P. Schultz and K. E. St. John, " Methods for the Analysis of Oxide Fuel Rod Steady-State Thermal Effects (FROSSTEY): Code Qualifications and Applications," YAEC-1265P, June 1981.
- 6. Report, A. A. F. Ansari, 'Hethods for the Analysis of Boiling Water i Reactors: Steady-State Core Flow Distribution Code (FIBWR)," YAEC-1234, !
December 1980.
- 7. Report, A. A. F. Ansari and J. T. Cronin, " Methods for the Analysis of Boiling Water Reactors: A System Transient Analysis Model (RETRAN),"
YAEC-1233, April 1981.
- 8. Report, A. A. F. Ansari, K. J. Burns and D. K. Beller, " Methods f or the Analysis of Boiling Water Reactors: Transient Critical Power Ratio Analysis (RETRAN-TCPYA01)," YAEC-1299P, March 1982.
- 9. Report, "Less-of-Coolant Accident Analysis for Vermont Yankee Nuclear Power Station," NED0-21697, August 1977, as amended.
- 10. Report, " General Electric Standard Application for Reactor Fuel (CESTARII)," NEDE-24011-P-A-9, GE Company Proprietary, September 1988, as amended.
l
- 15. Report, " Vermont Yankee Nuclear Power Station Single Loop Operation,"
l NED0-30060, February 1983.
l 16. Report, " Vermont Yankee Cycle 14 Core Performance Analysis Report,"
YAEC-1706, October 1988.
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