ML20091C174

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Rev 0 to Vermont Yankee Nuclear Power Station Cycle 16 Core Operating Limits Rept
ML20091C174
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 03/16/1992
From:
VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20091C171 List:
References
NUDOCS 9204030095
Download: ML20091C174 (18)
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I Vermont Yankee Nuclear Power Sta'.',1on Cycle 16 Core Operating Limits Report Revision 0 February 1992 Reviewed VA~?sSk #7k" d~ fM P1a W 0perations Date Review Committee Approved / N J ' [ /.2 Plant fiasiager Date Approved h-#M-#b' 3fl0 !92 -

Senior Vicf Preside ' ~ ' bate Operations itrolled Copy No.

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9204030095 920331 PDR ADOCK 05000271 P PDR

REVISION RECORD Cycl e Revision Date Descriotion 14 0 10/89 Initial printing, Reviewed by PORC and approved by management, 15 0 9/9C Cycle 15 revisions. Reviewed by PORC and approved by management.

15 1 11/91 Incorporate new HCPR limits to allow operation within the exposure window.

Reviewed by PORC and-approved by management.

h 16 0 3/92 Cycle 16 revisions. Reviewed by PORC and approved by management.

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ABSTRACT i

This report presents the cycle specific operating limits for-the operation of Cycle 16 of the Vermont Yankee Nuclear Power Station. The limits e are the maximum average planar linear heat generation rate, maximum linear heat generation rate, and minimum critical power ratio.

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TABLE 0F CONTENTS Page i REVISION RECORO-. . . . . ..... . . . . . . . . . . . . . . . . 11 ABSTRACT ............................. -lii LIST OF. TABLES

. . . -, . . . . . . . . . . .- . . . . . . .- . , . y LIST _0F FIGURES . . . . . . . . . . . . . . . . . . . . . . . . . . vi

1.0 INTRODUCTION

, . . . . .-. . . . . . . . . . . . . . . . . . . . . .. I 2.0- CORE OPERATING LIMITS . . . . . . . . . . . . . .-. . . . . . . 2 2 ,1 - Maximum Average Planar Linear Heat Generation Rate Lin>its . . 2 2.2 Minimum Crit'ical Power Ratic Limits . . . . . . . . . . . . . 3 '

2.3 Maximum Linear. Heat Generation Rate Limits . . . . . . . . . . 3

3.0 REFERENCES

. . . . . . . . . . . . . . . . . . . . . . . . . . . 11 4

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n LIST OF TABl.ES Number. Title Page Table 2.1-1 MAPLHGR Versus Average P_lanar. Exposure for BD324B Fuel .4

- Table 2.1-2 MAPLHGR Versus Average Planar Exposure for BD326B Fuel 5 Tabl e -2'.1 -3 MAPLHGR Versus Average Planar Exposure for BP80WB311-10GZ and ANF-IX-3.048 EGZ Fuel 6 i

Table 2.1 4 MAPLHGR Versus Average Planar Exposure for

-BP8DWB311 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 l

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o LIST OF FIGURES Number litle g i Figure 2.2-1 Kf Versus Percent of Rated Core Flow Rate 10 t

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. 1 1.0 1 NTRODtiCT10N '

This report provides the cycle specific limits for operation of _ the Vermont-Yankee Nuclear Power Station in Cycle 16. It includes the limits for the maximum everage planar linear heat generation rate, maximum linear. heat

, neneration 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 toen

~ developed using the NRC approved methodologies listed in References I through 16 and in Technical Specification 6.7. A.4. The bases for these limits are in References 11 and 12. and 17 through 20.

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2,0- CORE OPERATING LIMITS I

The Cycle ~16 operating limits have been defined using.NRC-approved methodol ogi es . The Cycle 16 must be operited within the bounds of these

-limits:and all others specified in the Technical Specifications.

2.1 Maximum Averace 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 16.

The ANF-IX bundle will be _ monitored as if it were a BP80WB311 10GZ bundle.

Therefore, the limits for the ANF IX bundle are the'same as the BP80WB311-10GZ bundle.

JThe MAPLHGR values are the most. limiting composite of the fuel l

mechanicalidesign analysis MAPLHGR and_the ECCS MAPLHGR, The fuel mechanical design analysis, using the methods. in Reference.12, demonstrates that all fuel rodsLin a_ lattice, operating at the bounding power history, meet the fuel

-design limits specified in Reference 12. The-LOCA analysis performed-in-accordance with 10CFR50, Appendix K, demonstrates that the MAPLHGR values

-comply with the ECCS limits specified in 10CFR50,46,

-The MAPLHGR actually varies _ axially, depending upon the specific

~

combination of enriched ~ uranium and gadolinia that ~ comprises a fuel bundle cross section at a p?rticular axial node. Each particular combination of l

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V 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 4 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-ifor 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 9845 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 2.21 multiplied by Kf ,

where K f 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 16, 2.3 Maximum Linear Heat Generation Rate limits

- Ouring 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. The ANF-IX bundle will be monitored asLif it were a 8P8DW8311-10GZ bundle. Therefore, the limits for the ANF-IX bundle-are the-same as the BP80WB311-10GZ bundle. This-table only

. lists theilimits for fuel = types in Cycle 16.

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- Ta bl e ? .1 1-HAPT.H(iR Versus' A'verage Planar Exposure for B03248 Fuel Plant:. Vermont Yankee fuel Type: ,@3248- ->

HAPLHGF, (kW/ft)

Avera9e Planer Exposurc (mwd /ST) Two loon Occration sinole toon Operation,

.200.0. 11.22 9.31 ,

3,000,0- 11.83 9.81 8,000,0 12.69 10.53 10,000,0 12.80 10,62 15,000.0 12.74 10.57 20,000.0 12.05 10.00 .

25,000,0 11.39 9.45-35,000.0 10.12 8,39 45,000.0 8.46 7.02 50,000.0 5.99 4.97 Source: NEDE 21697. Supplement 1, November 1987, Reference 11.

Technical Specification

References:

3.6.G la and 3.11.A.

t-l * ._MAPLHGR.for sing.le loop: operation-is obtained by multiplying MAPLHGR for two' loop operation by 0.83.

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Table 2.1 2 MAPlHGR Versus Average Planar Exposure for 803?6B Fuel Plant: Vermont ~ Yankee fuel Type: B0326B i

MAPLHGR (kW/ft)

Average Planar Exposure (mwd /ST) Two Loop Operation Sinole toon Ooeration,

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200,0 11.26 9,34 3,000.0 11.72 9.72 8,000.0 12 76 10.59 10,000.0 12.90 10.70

.15,000.0 12.82 10,64 20,000.01 12.12 10.05 25,000,0 11.44 9.49-35,000,0 10.15 8.42 l 45,000,0 8,63 7.16 50.000,0 6.17 5,12 Source:- - NEDE 21697 Supplement 1. November 1987,; Reference 11-.

. Technical Specification-

References:

3.6,G la and 3.11.A.

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

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l:: Table 2.1 3 MAPlHGR Versus Average Planar Exposure for BP80WB311 10G7

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and'ANF IX 3.048 EG2 Fuel Plant: Vermont Yankee fuel Type: BP80WB311 10GZ ANF-IX 3.048 EGZ MAPLHGR (kW/ft)

Avera9e Planar Exposure -

(mwd /ST) Two Loor. Oneration Sinale loop Operation,

200.0 11.00 9.13 6,000.0 11.92 9.89 7,000.0 12.11 10.05 l-l 8,000.0 12.34 10.24-10,000.0 12,83 10,64 12,500.0 13.00 10.79 20,000.0 12.24 10,15 25.000.0 11.55- 9.58 45,000.0 8.76 7.27 50,740.0-- 5.91 4.90

, , Source: NEDE 21697. Supplement 2. May 1990. Reference 11, and ANF-90-048.

Reference-19.

Technical Specification

References:

3.6.G.la and 3,11.A.

E MAPLHGR fer single loop operation is obtained by multiplying MAPLHGR for -

two loop' operation by 0.83.

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Table 2,1+4 j MAPLHGil Versus Average Planar Exposure for BP80WB311 11G7 Fuel Plant: Vermont Yankee Fuel. Type: BPB0VB 311 -11 GZ,-

HAPLHGR (kW/ft) 1

' Average Planar Exposure Two loon Operation Single toon Operation,  !

(mwd /ST) 200.0 11.00 9.13 6,000.0 11,92 9.89 >

7,000.0 12.11 10.05  ;

, 8,000.0 12.34 10.24 -

10,000.0 12.83- 10,64 12,500'.0 12.90 10.70

-15,000.0 ~12.81 10,63 35,000.0 10.24 8.49 D 45,000.0 8.76 7.27-50,740.0 5,91 4.90 Source: NEDE-21697 Supplement 2, May 1990. Reference 11.

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, L

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O Tabie 2,2_1

_ Minimum Critical Power Ratio boeratino limits u "CPR Operating Limits

-Value of 'N" Single

.in RBM- Average Control Cycle Exposure- Two Loop ' Loop Ecuation (Al l Range Operation Operation 2 Rod Scram Time _

42% Squal or better 0 to.9845 mwd /St 1.32 1.33 than L.C.0.

3.3 C.1.1 Equal'or-_better 0 to 9845 mwd /St 1,32 1.33 L than L.C.O.

3.3 C.1.2 41% Equal or better 0 to 9845 mwd /St 1.28 1.29 than L.C4 0.

3.3 C.1.1 Equal or better 0 to 9845 mwd /St' 1.28 1,29 than L.C.0.

3.3 C.1.2.

140% Equal or'better 0 to 9845 mwd /St 1.23 1.24 than L.C.0-.

3.3 C.1.1 l Equal or.better 0 to 8241 mwd /St 1.23 1.24 than L,C.O. 8241 to 9845 mwd /St - 1.24 1.25 3.3 C.1.2 _

Sources: ' Cycle 16 Core' Performance Analysis Report. YAEC-1844 Reference 18. and End-of Full-Power life Sensitivity Study-for the Revised BWR Licensino Methodolooy, YAEC-1822. Reference 20.

Technical Specification

References:

3.6.G.la and 3.11.C.

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

1 T2 MCPR Operating Limits are-increased by 0.01 for single-loop operation.

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Table 2,3 1 Maximum Allowable linear Heat Generation Rate limits Maximum Allowable Linear Fuel Tvoe Heat Generation Rate (kW/ft)

BD3248 14.4 B0326B 14.4 BP80WB311-10GZ 14.4 1

BP80WB311 11GZ 14.4 ANF IX-3.04B EGZ 14.4 )

i Source: NEDE 240ll-P A, Reference 12, and ANF-90 048. Reference 19. ,

Technical Specification-

References:

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

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f f f I?QUATIONS im Kf Curves:

Kf(WT>40%) = A.0. 4 41(WT/t 30 % )

.  ! l Kf(WT<40%) = l K f(WT > 4 0 % )'t l .0 + 0.0032( 4 0.WT))

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ws.,, 4o02.3 %) . i.3308 A(104.5 % ) = 1.3406 l l A(107 0%) = 1.3528 A(ll2.0%) = 1.3793 l l A(Il7.0%) = 1.4015 j,Q . . . .l. . - .. .. ... .. .........................

AUTOMA11C Ft.OW /'ONTROL j ,j ..- . . . . . . .. . ...

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M AWAL FLOW CON 1VOf.

Scoop. Tube Set. Point Calibration -

1- positioned soi) that: /

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. Flowmts = 102.5% .

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= 107.0% l l

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= 112.0 /

= 117.0%

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0.9 ~ mm..m. m.mmo m.mmm .mmm. .m.m." .mmmm "mm." .mimm 20 30 40 50 60 70 80 90 100 Core Flow (%)

Fioure 2.2-1 Kf Versus Percent of Rated Core Flow Rate (Technical Specification Reference 3.11.C)

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. . I 3,0 REFFRENCES

1. Report S. P. Schultz and K. E. .St, John, Methods for the Analysis of
0xide-Fuel Rod Steady State Thermal Effects (FROSSTEY) Code /Model DescriDtion Manual,.YAEC-1249P, April 1981.-  !

l

22. Report, S. P. Schultz and K. E. St. John, Methods for the Analysis of 0xide Fuel Rod Steady-State Thermal Effects (FROSSTEY): Code Qualifications and ADolications. YAEC-1765P, June 1981.

-q

3. Report' A. A. F. Ansari, Methods for the Analysis of Boiling Water Reactors: Steady-State Core flow Distribution Code-(FIBWR), YAEC 1234, December 1980.
4. Report, A. A. F. Ansari.and J. T. Cronin, Methods for the Analysis of Boilitio Water Reactors: A System Transient Analysis Model (RETRAN),

YAEC-1233, April 1981.

5. 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-lCPfA01), YAEL-1299P, March 1982.
6. Report. A. S. DiGiovine, et al., CASMO 3G validation, YAEC 1363*A, April 1988.

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

8. Report, R. A. Wochlke, et al . , MICBURN-3/CASMO-3/TABL ES-3/ SIMUL ATE-3 Benchmarking of Vermont Yankee Cveles 9 through 13. YAEC-1683-A, March.

1989.

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

L 10. Report V. Chandola, M. P. LeFrancois anc 1. D. Robichaud, ADDlication l of One-Dimensional Rinetics to Boiling Water-Reactor Transient Analysis Methqds, YAEC-1693 A, Revision 1, November 1989.

'11. Report, loss of-Coolant' Accident Analysis for Vermont Yankee Nuclear Power Station, NE00-21697, August 1977, as amended: NEDE-21697,

Supplement 1. November 1987; and NEDE-21697, Supplement 2, May 1990.

L12. Report, General Electric Standard ADD 11 cation for Reactor- Fuel (GESTARill', NEDE-24011-P-A-10. GE Company Proprietary - February 1991, as ll amended.

13. ' Letter, USNRC to VYNPC, SER. November 27, 1981.
14. ' Letter, USNRC to VYNPC, SER. NVY 82-157. September 15. 1982.

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-15. iLetter. USNRC to VYNPC,-SER.-NVY-85-205, September- 27, 1985,-

16. Letter, USNRC to VYNPC, SER, November'30, 1977.

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17. -Report. yermont Yankee Nuclear Pcwer Station-Sinole toon Operation. l NE00-30060 February 19d3. '
18. Report. H..A. Stronen, Vermont Yankee Cycle-16 Core Performance Analysis  ;

Report, YAEC+1844. February 1992. >-

19. Report.-M. E. Garrett, K. O, Hartley, and M. H. Smith, Vermont Yankee 9X9-IX Oualification Fuel Assembly Safety Analysis Report, ANF-90 048,

-May 1990.

20. Report, B. Y. Hubbard. .ct al . End of Full Power Life Sensitivity Study

'for the Revised BWR licensing Methodolocy, YAEC 1822, October 1991. -

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