ML19332G192

Rev 0 to Vermont Yankee Nuclear Power Station Cycle 14 Core Operating Limits Rept.

ML19332G192
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Site:	Vermont Yankee
Issue date:	10/02/1989
From:	VERMONT YANKEE NUCLEAR POWER CORP.
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ML19332G180	List: ML19332G179 ML19332G192
References
NUDOCS 8912200295
Download: ML19332G192 (18)

Text

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Vermont Yankee Nuclear-Power Station '

Cycle 14 Core Operating Limits Report Revision 0 l

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September 1989 Reviewed [ /A* A M '9 2MTV

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Plant Operations Date Review Committee l

Approved u 9/d/8?

flant Manager " Da'te f

Approved h [d Vice PresidenFand Dalel Manager of Operations Controlled Copy No.

8912200295 891M2 PDR ADDCK 05000271

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,. L REVISION RECORD. T

Revislon

Date Deserlption O' Initial printing. Reviewed by PORC and approved by. management. i i

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L* AREIRACT t

, r This_ report presents the cycle-specific operating limits for the l-( operation cf Cycle 14 of the Vermont Yankee Nuclear Power Station. The limits are the maximum average planar linear heat <neration rate, maximum linear I

heat generation rate, and minimum critical power rativ.

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• TABLE OF CONTENTS Page A

REVISION REC 0RD................................................... ii ABSTRACT.......................................................... iii LIST OF TABLES.................................................... v LIST OF FIGURES................................................... vi 1

1.0 INTRODUCTION

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

3.0 REFERENCES

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• LIST OF TABLFR e

( Number Title gg 2.1-1 MAPLHGR Versus Average Planar Exposure for F8DFB259 4 2.1-2 MAPLHGR Versus Average Planar Exposure for BP8DRB299 $

2.1-3 MAPLHGR Versus Average Planar Exposure for BD324B 6 2.1-4 MAPLHGR Versus Average Planar Exposure for BD326B 7 2.2-1 MCPR Operating Limits for Cycle 14 8 ,

2. 3-1 Maximum Allowable LHGR Limits for Cycle 14 9 h

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I LIST OF FICURES p-If = E M AI Tit 1e Paae

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2.2-1 10 K{ Versus Fcreent of Core Flow Rate F

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1.0 INTRODUCTION

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( 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 9, 10, and 15 through 18.

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2.0 CORE OPERATING LIMITS ,

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%< These Present Cycle operating limits have been defined using NRC-approved methodologies. The Present Cycle 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 Limita 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 the Present Cycle.

The fuel types, referred to in Tables 2.1-3 and 2.1-4, contain an 1 enriched middle portion with short natural uranium ends at both the top and bottom of the assembly. The latter are called " Natural Ends" in the tables.

I The enriched middle portion of the assembly is broken down into three distinct lattices which have the same enrichment distribution, but dif fer by number and weight percent of gadolinium pins. These are called zones. There is a " Power l Peaking Zone" near the bottom of the lattice. This is designed with a higher weight percent gadolinium to control the peaking of the predominantly bottom peaked power shapes typical of BWRs. The " Shutdown Margin Zone" is near the top of each assembly. It contains additional, part-length, gadolinium pins to control the flux peak near the top of the resctor when the reactor is in the 1

i cold shutdown condition. The remainder of the assembly is called the l

j " Majority Lattice."

l l 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. For single recirculation loop operation, the MCPR limits at rated flow shall be 8062R

I the values from the Table listed under the heading, " Single Loop Operation."

2he 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 g where gK 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 the Present Cycle.

The EOFPL in Table 2.2-1 is the projected end-of-full-power life exposure for the present cycle provided in the licensing analysis described in Reference 16. This value of 9,480 mwd /ST cycle average exposure will be used in the implementation of the exposure dependent MCPR limits regardless of subsequent, more accurate predictions of EOFPL. Justification for this interpretation is the sensitivity study described in Reference 18. The differences between the licensing analysis EOFPL and the actual plant EOFPL can affect the validity of the MCPR limits. However, the MCPR limits will be  :

valid if the actual EOFPL exposure falls within an exposure window defined as 8,880 to 9,480 mwd /ST. The MCPR limits are also valid during ceastdown.

2.3 MaximunLlingar llent Ceng.rAlf on Rate Limits k

During steady-state power operation, the Linear Heat Generation Rate (LHG9) of any rod in any fuel bundle at any axial location shall not exceed

.the maximum allowable LHGR limits in Table 2.3-1. There are different LHGR limits for different fuel types. These limits are only valid for the fuel types in the Present Cycle.

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l TABLE 2.1-1 g MAPLHCR Versus Average Planar Exoosure s

Plantt Vermont Yankee Tuel Type P8DPB289 Average Planar MAPHLGR (LW/ft) i Exposure Two Loop Single Loop (mwd /ST) Operation Ooeration* t 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 t

40,000.0 9.8 8.1 i Sourcet NEDO-21697 August 1977 (revised) Reference 9.

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

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

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- TABLE 2.1-2 g- NAPLHGR Versus Average Planar Exposure

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plant: Vermont Yankee Fuel Typet IP8DRB299 Average Planar MAPHLCR (kW/ft)

Exposure Two Loop Single Loop (mwd /ST) Operation Operation

• 200.0 10.7 8.8 ,,

i 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 l 35,000.0 10.6 8.8 4 41,900.0 9.4 7.8 t

Source: NEDO-21697, August 1977 (revised), Reference 9. .

Technical Specification Referencest 3.6.G.la and 3.11.A.

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• MAPLHGR for single loop operatir.1 is obtained by multiplying MAPLHGR for two loop operation by 0.83.

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' TARLE 2.2-1 MCPR Operatine Limits

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t V;1ue of "N" MCPR Operating Limits l Average Control Cycle Two-Loop Single-Loop in RBM Enuation (1) EDd Beram Time Edp_gaure kanne Operation Operation (2)

Equal or better BOC to EOFPL-2 CWD/T 1.26 1.27 42%

1.26 1.27 than L.C.O. EOFPL-2 CWD/T to EOFPL-1 GWD/T 1.27 3.3 C.1.1 EOFPL-1 OWD/T to EOFPL 1.26 B00 to EOFPL-2 GWD/T 1.26 1.27 '

Equal or better EOFPL-2 CWD/T to EOFPL-1 GWD/T 1.27 1.28 than L.C.O. 1.31 1.32 3.3.C.1.2 EOFPL-1 GWD/T to EOFPL 1.22 1.23 41% Equal or better BOC to EOFPL-2 GWD/T 1.23 than L.C.O. EOFPL-2 GWD/T to EOFPL-1 GWD/T 1.22  :

EOFPL-1 GWD/T to EQFPL 1.26 1.27 3.3 C.1.1 BOC to EOFPL-2 GWD/T 1.22 1.23 Equal or better 1.27 1.28 than L.C.0. E0FPL-2 GWD/T to EOFPL-1 GWD/T 1.31 1.32 3.3 C.1.2- EOFPL-1 GWD/T to EOFPL 1.22 1.23 5 40% Equal or better B00 to EOFPL-2 GWD/T 1.23 than L.C.O. EOFPL-2 GWD/T to EOFPL-1 GWD/T 1.22 EOFPL-1 gWD/T to EOFPL 1.26 1.27 3.3 C.1.1 1.22 1.23 Equal or better BOC to EOFPL-2 GWD/T 1.28 than L.C.O. EOFPL-2 GWD/T to E0FPL-1 GWD/T 1.27 1.31 1.32 3.3 C.1.2 E0fPL-1 CWD/T to EOFPL (s arce: Revision to Cycle 14 Core Performance Analysis Report, YAEC-1706, Reference 17.

7;chnical Specification

References:

3.6.G.la and 3.11.0.

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

(2) MCPR Operating Limits are increased by 0.01 for single loop operation.

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TABLE 2.1-3 MAPLilCR Versus Average Planar ExpDA.uIt Plant: Vermont Yankee Fuel Type BD324B Average Planar MAPHLCR (kW/f t) f or Two Loop Operation Exposure Majority Shutdown Power Peaking Natural Bargin Zone Zone Enda (mwd /ST) lattice- i 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 Sinnie Loop Operation *

< F.xposure Majority Shutdown Power Peaking Natural Zone Ends k (mwd /ST) Lt.ttice. Marrin Zong 9.76 9.32 9.71 9.54 200.0 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 l 6.58 35,000.0 8.41 8.39 8.39 43,360.0 7.30 7.24 7.25 3.86 50,000.0 5.04 4.97 4.99 -

1 l Source: NEDO-21697, August 1977 (revised), Reference 9.

Technical Specification

References:

3.6.G.la and 3.11.A.

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

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TABLE 2.1-4 e MAPLEGE_yntus Average Planar ExpRiutt k '

Plantt Yumoallankte Tuel Typet AD110 l

Average Planar MAPHLCR (kW/ft) for Two Loop Operation '

Exposure Majority Shutdown Power Peaking Natural (mwd /ST) 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 8.91 4.66 50,000.0 6.25 6.17 6.22 -

Average Planar MAPHLCR (kW/ft) for Single Loop Operation

• Exposure Majority Shutdown Power Peaking Natural y Zone Ends 4 (mwd /ST) Lallist_ MarsitLlong 9.79 9.42 9.76 9.54 200.0 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 10.53 10.50 10.53 9.63 7,000.0 10,000.0 10.70 10.70 10.70 9.72 10.70 10.70 10.70 9.25 14,400.0 10.65 10.64 10.64 9.18 15,000.0 8.54 20,000.0 10.07 10.05 10.05 9.51 9.49 9.50 7.88 25,000.0 6.58 35,000.0 8.44 8.42 8.43 7.42 7.36 7.39 3.86 43,360.0 50,000.0 5.18 5.12 5.16 -

Sourcet NEDO-21697, August 1977 (revised), Reference 9.

Technical Specification Referencest 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 1

'i-('i ,. Maximum Allowable __IllGR Limits

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Linear Heat  ;

Generation Rate Entl Typs _

(kW/ft)

P8DFB289 13.4 BP8DRB299 13.4 BD324B 14.4 BD326B 14.4 Source: NEDE-24011-P-A, Reference 10.

Technical Specification

References:

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

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i FlGURE 22-1 K Versus Percent Of Core Flow Rote i

TeEhnical Specification Reference 3.11.C

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positioned such that I'lowmax = 10/15,<. ' _.s - .

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= 107.0 % - -

= 112.0 % - -

= 117.0Te _ ___ _ ___

0.9 . .

20 30 40 50 60 70 80 90 10 0 CORE FLOW %

. 3.0 ILEFERENCES

1. Report, E. E. Pilat, 'Hethods for the Analysis of Boiling Water Reactors J Lattice Physics," YAEC-1232, December 1980.

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2. Report, D. M. VerPlanck, 'Wethods 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 Oxide Fuel Rod Steady-State Thermal Effects (FROSSTEY) Code /Model '

Description Manual," YAEC-1249P, April 1981.

5. Report, S. P. Schultz and K. E. St. John, "Metheds 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, " Methods for the Analysis of Boiling Water Reactorst Steady-State Core Flow Listribution Code (FIBWR)," YAEC-1234 December 1980.

7. Report, A. A. F. Ansari and J. T. Cronin, " Methods for the Analysis of Boiling Water Reactorst A System Transient Analysis Model (RETRAN),"

YAEC-1233, April 1981.

8. Report. A. A. T. Ansari, K. J. Burns and D. K. Beller, " Methods for the

, g Analysis of Boiling Water Reactorst Transient Critical Power Ratio

, ( Analysis (RETRAN-TCPYA01)," YAEC-1299P, March 1982.

l 9. Report, " Loss-of-Coolant Accident Analysis for Vermont Yankee Nuclear Power Station," NEDO-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 i amended.

l 11. Letter, USNRC to VYNPC, SER, November 27, 1981.

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

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

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

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15. Report, " Vermont Yankee Nuclear Power Station Single Loop Operation,"

NEDO-30060. February 1983.

16. Report, " Vermont Yankee Cycle 14 Core Performance Analysis Report."

YAEC-1706, October 1988.

17, Memo, M. A. Sironen to S. R. Miller, " Revised VY Cycle 14 Core i -

Performance Analysis Report," NED 89-42 March 10,1989.

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.' 18. Report, " Sensitivity Study of Vermont Yankee Methods to Projected End-of-Tull-Power Life," YAEC-1460, February 1985.

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