ML20082N580

Cycle 18 COLR, Rev 0

ML20082N580
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	04/17/1995
From:	VERMONT YANKEE NUCLEAR POWER CORP.
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ML20082N570	List: ML20082N567 ML20082N580 ML20082N592
References
NUDOCS 9504250300
Download: ML20082N580 (19)

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I' Vermont Yankee Nuclear Power Station l l Cycle 18 Core Operating Limits Report l Revision 0 April 1995 Reviewed 9 M 8 / Y A!9[

Plant Operations 'Da te Review Committee Approved M d//n);Ff P1 anager [/g D'a tE Approved Ak A '

M!/7!il Vice Presidelit bate' Operations Controlled Copy No.

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9504250300 950429 i PDR ADOCK 05000271  !

P . _ . , . PDR ,

e ao REVISION RECORD l

Cycle Revision, Date Description i

14 .0 10/89 Initial printing. Reviewed by PORC and ,

approved by management.

15 0 9/90 Cycle 15 revisions. Reviewed by PORC and )

approved by management. I 15 1 11/91 Incorporate new MCPR limits to allow  ;

operation within the exposure window, j Reviewed by PORC and approved by management.

J 16 0 3/92 Cycle 16 revisions. Reviewed by PORC and approved by management. j 17 0 7/93 Cycle 17 revisions. Reviewed by PORC and approved by management.

18 0 4/95 Cycle 18 revisions. Reviewed by PORC and approved by management.

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ABSTRACT' This report presents the cycle-specific operating limits for the operation of Cycle 18 of the Vermont Yankee Nuclear Power Station. The limits are the maximum average planar linear heat generation-rate, maximum linear heat generation rate, and minimum critical power ratio.

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l TABLE OF CONTENTS l m i Page REVISION RECORD . ......................... ii ABSTRACT ............................. iii LIST OF TABLES .......................... v LIST OF FIGURES . . . . . . . . . . . . . . . . . . . . . . . . . . vi

1.0 INTRODUCTION

........................... 1 2.0 CORE OPERATING LIMITS . . . . . . . . . . . . . . . . . . . . . . . 2 2.1 Maximum Average Planar Linear Heat Generation Rate Limits . . 2 2.2 Minimum Critical Power Ratio Limits . . . . . . . . . . . . . 3 2.3 Maximum Linear Heat Generation Rate Limits ......... 3

3.0 REFERENCES

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i LIST OF TABLES Number Title Page Table 2.1-1 MAPLHGR Versus Average Planar Exposure for BP8DWB311-10GZ Fuel 4 Table 2.1-2 MAPLHGR Versus Average Planar Exposure for BP8DWB311-11GZ Fuel 5 Table 2.1-3 MAPLHGR Versus Average Planar Exposure for BP8DWB335-10GZ Fuel 6 Table 2.1-4 MAPLHGR Versus Average Planar Exposure for BP8DWB335-11GZ Fuel 7 Table 2.2-1 Minimum Critical Power Ratio Operating Limits 8 Table 2.3-1 Maximum Allowable Linear Heat Generation Rate Limits 9 b

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'f 4 LIST OF FIGURES Number Title Page Figure 2.2-1 Kf Versus Percent of Rated Core Flow Rate 10 1

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1.0 INTRODUCTION

This report provides the cycle-specific limits for operation of the Vermont Yankee Nuclear Power Station in Cycle 18. It includes the limits for the maximum average planar linear heat generation rate, maximum linear heat generation rate, and minimum critical power ratio. If any of these limits are exceeded, 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 29 and in Technical Specification 6.7.A.4. The bases for these limits are in References 12, 17, and 30 through 32.

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2.0 CORE OPERATING LIMITS The Cycle 18 operating limits have been defined using NRC-approved methodologies. Cycle 18 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 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 2.1-4. 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. The source of these values is identified on ,

each table. These tables only list the limits for fuel types in Cycle 18.

The MAPLHGR values are usually the most limiting composite of the fuel mechanical design analysis MAPLHGRs and the Loss-of-Coolant Accident (LOCA)

MAPLHGRs. The fuel mechanical design analysis, usirg the methods in Reference 12, demonstrates that all fuel rods in a lattice, operating at the bounding power history, meet the fuel design limits specified in Reference 12. The Vermont Yankee LOCA analysis, performed in accordance with 10CFR50, Appendix K, demonstrates that the LOCA analysis MAPLHGR values are bounded at all exposure points by the 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 l

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I will verify that these lattice MAPLHGR limits are not violated. Tables 2.1-1 )

through 2.1-4 provide a limiting composite of MAPLHGR vblues for each fuel l 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 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.

The MCPR limits are also valid during coastdown beyond 10644 mwd /St.

For single recirculation loop operation, the MCPR limits at rated flow shall be the values from the Table listed under the heading, " Single Loop Operation." The single loop values are obtained by adding 0.01 to the two loop operation values. For core flows other than the rated condition, the MCPR limit shall be the appropriate value from Table 2.2-1 multiplied by K f, where Kr is given in Figure 2.2-1 as a function of the flow control method in use. These limits are only valid for the fuel types in Cycle 18, 2.3 Maximum Linear Heat Generation Rate limits 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 18.

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L Table 2.1-1 i MAPLHGR Versus Averace Planar Exposure for BP80WB311-10GZ Fuel Plant: Vermont Yankee Fuel Type: BP80WB311-10GZ MAPLHGR (kW/ft)

Average Planar Exposure (mwd /ST) Two Loop Operation Sinole Loop Operation.

0.0 10.93 9.07 200.00 11.00 9.13 1,000.00 11.13 9.24 2,000.00 11.32 9.40 ,.

3,000.00 11.52 9.56 4.000.00 11.64 9.66 5.000.00 11.77 9.77 6,000.00 11.92 9.89 7,000.00 12.11 10.05 8,000.00 12.34 10.24 9,000.00 12.59 10.45 10,000.00 12.83 10.65 ,

12,500.00 13.00 10.79 15,000.00 12.81 10.63 20,000.00 12.24 10.16 25,000.00 11.55 9.59 35,000.00 10.24 8.50 45,000.00 8.76 7.27 51,299.00 5.87 4.87 Source: Vermont Yankee Cycle 18 Core Performance Analysis Report, YAEC-1908, Reference 31 and Vermont Yankee Nuclear Power Station Sinole looo Operation, NED0-30060, Reference 30.

Technical Specification

References:

3.6.G.la and 3.11.A.

• MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.83.

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Table 2.1-2 MAPLHGR Versus Avtrage Planar Exposure for BP80WB311-11GZ Fuel Plant: Vermont Yankee Fuel Type: BP80WB311-11GZ MAPLHGR (kW/ft)

Average Planar Exposure (mwd /ST)

Two Loop Operation Single Loop Operation, 0.00 10.93 9.07 200.00 11.00 9.13 1.000.00 11.13 9.24 2,000.00 11.32 9.40 3.000.00 11.52 9.56 4,000.00 11.64 9.66 ,

5,000.00 11.77 9.77 6,000.00 11.92 9.89 7,000.00 12.11 10.05 8,000.00 12.34 10.24 9,000.00 12.59 10.45

, 1Q,000.00 12.83 10.65 12,500.00 13.00 10.79 15,000.00 12.81 10.63 20,000.00 12.24 10.16 25.000.00 11.55 9.59

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35,000.00 10.24 8.50 45,000.00 8.76 7.27 51,466.00 5.83 4.84 Source: Vermont Yankee Cycle 18 Core Performance A.nal_ysis Report, YAEC-1908 Reference 31 and Vermont Yankee Nuclear Power Station Sinole Loop Operation, NE00-30060, Reference 30. ,

Technical Specification

References:

3.6.G.la and 3.11.A.

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• MAPLHGR for single loop operation is obtained by multipiying MAPLHGR for two loop operation by 0.83.

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Table 2.1-3 MAPLHGR Versus Average Planar Exposure for BP80WB335-10GZ Fuel Plant: Vermont Yankee Fuel Type: BP80WB335-10GZ MAPlHGR (kW/ft)

Average Planar Exposure (mwd /ST) Two Loop Operatt.g Single Loop Operation, 0.00 11.29 9.37 200.00 11.34 9.41 1,000.00 11.48 9.53 2,000.00 11.69 9.70 3,000.00 11.92 9.89 4,000.00 12.17 10.10 5,000.0C 12.43 10.32 6,000.00 12.68 10.52 7,000.00 12.87 10.68 8,000.00 13.06 10.84 9,000.00. 13.24 10.99 10,000.00 13.35 11.08 12,500.00 13.20 10.96 20,000.00 12.27 10.80 25,000.00 11.43 9.49 35,000.00 9.88 8.20 45,000.00 8.38 6.96 50,593.00 5.65 4.69 Source: Vermont Yankee Cycle 18 Core Performance Analysis Report, YAEC-1908, Reference 31 and Vermont Yankee Nuclear Power Station Single Loop Operation, NE00-30060 Reference 30.

Technical Specification

References:

3.6.G.la and 3.11.A.

• MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.83.

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Table 2.1-4 MAPLHGR Versus Averaoe Planar Exposure for BP80WB335-11GZ Fuel Plant: Vermont Yankee fuel Type: BP80WB335-11GZ MAPLHGR (kW/ft) '

Average Planar Exposure (mwd /ST) Two Loop Opera; ion Single Loop Operation.

0.00 11.28 9.36 200.00 11.33 9.40 1,000.00 11.43 9.49 2,000.00 11.60 9.63 3,000.00 11.80 9.79 4,000.00 12.04 9.99 5,000.00 12.30 10.21 6,000.00 12.53 10.40 7,000.00 12.73 10.57 8,000.00 12.94 10.74 9,000.00 13.13 10.90 >

10,000.00 13.29 11.03 i

12,500.00 13.20 10.96 15,000.00 12.99 10.78 20,000.00 12.27 10.02 j 25,000.00 11.43 9.49 35,000.00 9.88 8.20 45,000.00 8.38 6.96 50,593.00 5.65 4.69 Source: Vermont Yankee Cycle 18 Core Performance Analysis Report, YAEC-1908, Reference 31 and Vermont Yankee Nuclear Power Station Sinole loop Operation NED0-30060, Reference 30.

Technical Specification

References:

3.6.G.la and 3.11.A.

MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for  ;

two loop operation by 0.83.

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., Table 2.2-1 Minimum Critical Power Ratio Operating Limits MCPR Operating Limits Value of "N" Single J in RBM Average Control Cycle Exposure Two Loop Loop Eauction (A)I Rod Scram Time Range Operation Operation 2 42% Equal to or

- .5.0.to4000 mwd /St 1.39 1.40 better than 4000 to 5500 mwd /St. 1.35 1.36.

L.C.0. 5500 to 10644 mwd /St 1.33 1.34 3.3.C.1.1 Equal to or 0.0 to 4000 mwd /St 1.39 1.40 better than 4000 to 5500 mwd /St 1.35 1.36 L.C.O. 5500 to 9035 mwd /St 1.33 1.34 3.3.C.1.2 9035 to 10644 mwd /St 1.34 1.35 ,

l 41% Equal to or 0.0 to 4000 mwd /St 1.39 1.40 i better than 4000 to 5500 mwd /St 1.35 1.36 L.C.0. 5500 to 6500 mwd /St 1.29 1.30 3.3.C.I.1 6500 to 9035 mwd /St 1.27 1.28 9035 to 10644 mwd /St 1.32 1.33 l Equal to or 0.0 to 4000 mwd /St 1.39 1.40 better than 4000 to 5500 mwd /St 1.35 1.36 L.C.0. 5500 to 6500 mwd /St 1.29 1.30 3.3.C.I.2 6500 to 8035 mwd /St 1.27 1.28 l 8035 to 9035 mwd /St 1.30 1.31 9035 to 10644 mwd /St 1.34 1.35 140% Equal to or 0.0 to 4000 mwd /St 1.39 1.40 better than 4000 to 5500 mwd /St 1.35 1.36 L.C.O. 5500 to 6500 mwd /St 1.29 1.30 3.3.C.1.1 6500.to 8035 mwd /St 1.25 1.26 8035 to 9035 mwd /St 1.27 1.28 9035 to 10644 mwd /St 1.32 1.33 Equal to or 0.0 to 4000 mwd /St 1.39 1.40 better than 4000 to 5500 mwd /St 1.35 1.36 L.C.O. 5500 to 6500 mwd /St- 1.29 1.30 3.3.C.1.2 6500 to 8035 mwd /St 1.25 1.26 8035 to 9035 mwd /St 1.30 1.31 9035 to 10644 mwd /St 1.34 -1.35 Sources: Vermont Yankee Cycle 18 Core Performance Analysis Report, YAEC-1908, Reference 31; End of-Full-Power-life Sensitivity Study for the Revised BWR Licensino Methodology, YAEC-1822 Reference 32; and Vermont Yankee Nuclear Power Station Sinole Loop Operation, NE00-30060 Reference 30.

Technical Specification

References:

3.6.G.la and 3.11.C.

l 1 The Rod Block Monitor (RBM) trip setpoints are determined by the equation shown in-Table 3.2.5 of the Technical Specifications.1-2 MCPR Operating Limits are increased by 0.01 for single loop operation.

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Table 2.3-1  !

. 'l Maximum Allowable Linear-Heat Generation Rate Limits l t

Maximum Allowable ~ Linear ,

Fuel TYDe Heat Generation Rate (kW/ft)  ;

BP80WB311-10GZ 14.4 l BP8DWB311-11GZ 14.4- >

BP80WB335-10GZ 14.4 BP80WB335-11GZ 14.4 4 i

' Source: NEDE-24011-P-A, Reference 21. I Technical Specification.

References:

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

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k~

Kf 1.4 . . .

EQUATIONS for Kf Curves:

- . . . Kf ;t 1.0 Kf(WT>40%) = A.0.441(WT/1005)  ;

= .

Kf(WTc40%) =  :

j,$ __.....* .. .........*......

Kf(WT>40%)*(I.0+0.0032(40.WT)) -

Where A(102.5%) = 1.3308 A(104.5 %) = 1.3406 A(107.0%) = 1.3528

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A(112.0%) = 1.3793

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A(117.0%) = 1.4035 .j-j,2 $

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.....*.. . ... ..... ..l............l............<

. . . AU10MA11C PLOW CONTROL

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. . . . . .. . . . . . . . . . . . . . . . . ... ... ... ........ ..... ,l

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• I MANUAL RDW CONTROL  ;

jl_ Scoop. Tube Set-Point Calibration .- .. . ... .. .....  ;

positioned such that: -

• Flowmax = 102.5%/ * * * '

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=107.0%

= 104.5%/ * . .

=  !!2.0%/

= 117.0% .

0.9 ~ ......... ......... ......... ......... ......... ......... ......... .........

20 30 40 50 60 70 80 90 100

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Core Flow (%) (WT) .

Fiqure 2.2-1 ,

L Versus Percent of Rated Core Flow Rate (Technical Specification Reference 3.11.C) 'l t

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3.0 REFERENCES

1. Report A. A. F. Ansari, Methods for the Analysis of Boiling Water Reactors: Steady-State Core Flow Distribution Code (FIBWR), YAEC-1234, December 1980,

2. 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. .

3. Report, A. A. F. Ansari, K. J. Burns and D. K. Beller, Methods for the Analysis of Boiling Water Reactors: Transient Critical Power Ratio Analysis (RETRAN-TCPYA01), YAEC-1299P, March 1982.

4. Report, A. S. DiGiovine, et al., CASMO-3G Validation,, YAEC-1363-A, April 1988.

5. Report, A. S. DiGiovine, J. P. Gorski, and M. A. Tremblay, SIMULATE-3 Validation and Verification YAEC-1659-A, September 1988.

6. Report, R. A. Woehlke, et al., MICBURN-3/CASM0-3/ TABLES-3/ SIMULATE-3 Benchmarking of Vermont Yankee Cycles 9 through 13 YAEC-1683-A, March 1989. , , ,

7. Report, J. T. Cronin, Method for Generation of One-Dimensional Kinetics Data for RETRAN-02, YAEC-1694-A, June 1989.

8. Report, V. Chandola, M. .P. LeFrancois and J. D. Robichaud, Application of One-Dimensional Kinetics to Boiling Water Reactor Transient Analysis Methods, YAEC-1693-A, Revision 1, November 1989.

9. Report, RELAPSYA. A Computer Program for Light-Water Reactor System Thermal-Hydraulic Analysis, YAEC-1300P-A, Revision 0, October 1982:

Revision 1. July 1993.

10. Report, Vermont Yankee BWR Loss-of-Coolant Accident Licensing Analysis Method. YAEC-1547P-A, July 1993.

11. Letter from R. W. Capstick (VYNPC) to USNRC, HUXY Computer Code ,

1 Information for the Vermont Yankee BWR LOCA Licensing Analysis Method, FVY 87-63, dated June 4, 1987.

12. Letter from R. W. Capstick (VYNPC) to USNRC, Vermont Yankee LOCA Analysis Method FROSSTEY Fuel Performance Code (FROSSTEY-2), FVY 87-116, dated December 16, 1987. ,

13. Letter from R. W. Capstick (VYNPC) to USNRC, Response to NRC Recuest for Additional Information on the FROSSTEY-2 Fuel Performance Code, BVY 89-65, dated July 14, 1989.

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14. Letter from R. W. Capstick (VYNPC) to USNRC, Supplemental Information on the FROSSTEY-2 Fuel Performance Code, BVY 89-74, dated August 4, 1989.

15. Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, Responses to Reauest for Additional Information on FROSSTEY-2 Fuel Performance Code, BVY 90-045, dated April 19, 1990.

16. Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, Supplemental information to VYNPC April 19. 1990 Response Regarding FROSSTEY-2 Fuel Performance Code, BVY 90-054, dated May 10, 1990.

17. Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, Responses to Reauest for Additional Information on FROSSTEY-2 Fuel Performance Code, BVY 91-024, dated March 6, 1991.

18. Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, LOCA-Related Responses to Open Issues on FROSSTEY-2 Fuel Performance Code, BVY 92-39, dated March 27, 1992.

19. Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, FROSSTEY-2 Fuel Performance Code - Vermont Yankee Response to Remaining Concerns, BVY 92-54, dated May 15, 1992.

20. Report, L. Schor, et al . , Vermont Yankee loss-of-Coolant Accident Analysis, YAEC-1772, June 1993.

21. Report, General Electric Standard Application for Reactor Fuel (GESTARTI), NEDE-24011-P-A-10, GE Company Proprietary February 1991, as amended.

22. Letter, USNRC to VYNPC, SER, November 27, 1981.

23. Letter, USNRC to VYNPC, SER, NVY 82-157, September 15, 1982.

24. Letter, USNRC to VYNPC, SER, NVY 85-205, September 27, 1985.

25. Letter, USNRC to VYNPC, SER, November 30, 1977.

26. Letter, USNRC to VYNPC, SER, NVY 87-136, August 25, 1987.

27. Letter, USNRC to VYNPC, SER NVY 91-26, February 27, 1991.

28. Letter, USNRC to VYNPC, SER, NVY 92-192, October 21, 1992.

29. Letter USNRC to VYNPC, SER, NVY 92-178, September 24, 1992.

30. Report, Vermont Yankee Nuclear Power Station Sinole Loop Operation.

NE00-30060 February 1983.

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'31. Report, M. : A. Stronen,' Vermont' Yankee Cycle 18 Core Performance Analysis Report, YAEC-1908, Jariuary 1995.

32. Report, B. Y. Hubbard, et al., End-of-Full-Power-life Sensitivity Study for the Revised BWR licensing Methodology, YAEC-1822, October 1991.

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