ML20205P824
| ML20205P824 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 02/28/1999 |
| From: | Duda E VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML20205P822 | List: |
| References | |
| NUDOCS 9904200393 | |
| Download: ML20205P824 (20) | |
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1 Vermont Yankee Nuclear Power Station Cycle 20 Core Operating Limits Report l Revision 2 l February 1999
-W 9904200393 990413 PDR ADOCK 05000271 P PDR ,
Cycle 20 COLR Revision 2 February 1999 Preparer 2,//2 W l Reactor Engineer ' Dat'e Reviewed Ar Thu9ed pede/ecen :2.[/7/ff
{ Reactor Engineer bat 5 -
Approved d7[ff Reactorbfineering Manager Date Reviewed W /G M M 99-d/d J/3/97 Plant Operations Review Comdrfttee bate Approved WY M' 3/3k9 gf Date Plant 6. ML, @
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Approved Mi il l le IP' 3 4 6 l DiMtor $tions Date I
Cycle 20 COLR Revision 2 l February 1999 REVISION RECORD l
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Cvele Revision Date Description 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.
15 1 11/91 Incorporate new MCPR limits to allow operation within l
the exposure window. Reviewed by PORC and approved by management.
16 0 3/92 Cycle 16 revisions. Reviewcd by PORC and approved by management.
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.
j 18 1 8/95 Incorporate new MAPLHGR limits to account for Loss l of Stator Cooling Event. Reviewed by PORC and approved by management.
18 2 8/95 Incorporate the thermal-hydraulic stability exclusion 1 region. Reviewed by PORC and approved by management.
18 3 11/95 Revise the thermal-hydraulic stability exclusion region to more accurately represent the exclusion region boundary equation. Revise the MCPR limits to allow SRV and SV setpoint tolerance relaxation. Reviewed j by PORC and approved by management. '
19 0 10/96 Cycle 19 revisions. Reviewed by PORC and approved by management.
20 0 5/98 Cycle 20 revisions. Reviewed by PORC and approved by management.
20 1 5/98 Revise the thermal-hydraulic stability exclusion region.
Reviewed by PORC and approved by managenient.
20 2 2/99 Revise LOSC transient analys' .o eliminate MAPLHGR penalties required for 20 fuel assemblies iii
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l Cycle 20 COL.R
, Aevision 2 l'ebruary 1999 ABSTRACT This report presents the cycle-specific opewting limits for the operation of Cycle 20 of the Vermont Yankee Nuclear Power Statien. 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.
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Cycle 20 COLR Revision 2 February 1999 TABLE OF CONTENTS Pace REVI S I ON REC ORD .. . . .... . . ... ... .... .. . . . . .. .. ... . ... . . .. .. .... ................................................. ... iii ABSTRACT....................................................................... . . . . . . . . . . . . . . . . . . . . . .. iv L I S T O F TAB L E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
L I ST O F F I G URE S . . . . . . . . . . . . . . . . . . . . . . . . . . . l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . vii 1.0 INT RO D U CTI O N . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 2.0 CORE O PERATING 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 Heat Generation Rate Limits..... ... . ... .... .. .. .. ...... .. . ....... .... . 3 2.4 Thermal-Hydraulic Stability Exclusion Region... .... .... ... .. . .......... . .. ............ 3 3.0 RE F E RENC ES . . . . . .. . .. .. ... . .. . . . . .. . ... .. . .. ... ............................................................14 .
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Cycle 20 COLR Revision 2 February 1999 LIST OF TABLES Number Title Page Table 2.1-1 MAPLHGR Versus Average Planar Exposure for BP8DWB335-10GZ Fuel Bundle No. 2017 -
5 Table 2.1-2 MAPLHGR Versus Average Planar Exposure for BP8DWB335-1IGZ Fuel Bundle No. 2018 6 l Table 2.1-3 MAPLHGR Versus Average Planar Exposure for BP8DWB354-12GZ Fuel Bundle No. 2153 7 I
Table 2.1-4 MAPLHGR Versus Average Planar Exposure for P9HTB380-12GZ Fuel Bundle No. 2278 8 1
Table 2.1-5 MAPLHGR Versus Average Planar Exposure for P9HTB379-13GZ Fuel l Bundle No. 2279 9 i Table 2.2-1 Vermont Yankee Nuclear Power Station Cycle 20 MCPR Operating Limits 10 Table 2.3-1 Maximum Allowable Linear Heat Generation Rate Limits 11 I
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l Cycle 20 COLR Revision 2 February 1999 LIST OF FIGURES Number Title Pace 2.2-1 Kr Versus Percent of Rated Core Flow Rate 12 2.4-1 Limits of Power / Flow Operation
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Cycle 20 COLR
. Revision 2 February 1999
1.0 INTRODUCTION
This report provides the cycle-specific limits for operation of the Vermont l Yankee Nuclear Power Station in Cycle 20. It includes the limits for the maximum
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average planar linear heat generation rate, maximum linear heat generation rate, j 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 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 3. The methodologies are also listed in Technical Specification 6.7.A.4. The bases for these limits are in References 5 through 8.
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l Cycle 20 COLR
. Revision 2 February 1999 2.0 CORE OPERATING LIMITS l
The Cycle 20 operating limits have been defined using NRC-approved methodologies. Cycle 20 must be operated 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 valnes shown in Tables 2.1-1 through 2.1-5. Due to very conservative assumptions in the original Cycle 20 LOSC transient analysis,20 1 BP8DWB354-12GZ fuel bundles were required to have a MAPLHGR penalty. The LOSC transient analysis has been re-performed, resulting in the elimination of the MAPLHGR penalty for these 20 bundles. All BP8DWB354-12GZ bundles will now have the same required MAPLHGR limits. 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. These tables only list the limits for fuel types in Cycle 20.
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 i LOCA analysis, performed in conformance with the requirements of 10CFR50.46 and l Appendix K demonstrates that the LOCA analysis MAPLHGR values are bounded at all l exposure points by the thermal-mechanical design analysis MAPLHGR values. l 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 will verify that these lattice MAPLHGR limits are not violated. Tables 2.1-1 through 2.1-5 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 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 10175 mwd /St (Reference 6) which is the expected end of full power life exposure.
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Cycle 20 COLR
. Revision 2 February 1999 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 I loop values are obtained by adding 0.02 to the two loop operation values (Reference 7). !
For core flows other than the rated condition, the MCPR limit shall be the appropriate value from Table 2.2-1 multiplied by Kr, where Kris 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
- 20. l 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 20.
2.4 Thermal-Hydraulic Stability Exclusion Region 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 20. 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 74.9 49.8 B 30.7 25.4 The equation for the boundary is as follows:
W-W 'W-WB r 3- B, P 2 WA -WB W -WB, pB=pB -d. p
.A r B>
where, P= a core thermal power value on the Exclusion Region boundary (% of rated),
W= 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),
Pa = core thermal power at State Point B (% of rated),
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Cycle 20 COLR Revision 2 )
February 1999 l
W=
A core flow rate at State Point A (% of rated),
Wu= core flow rate at State Point B (% of rated),
The range of validity of the fit is: 25.4% s% Flow $49.8%
The coordinates of the Buffer Region are as follows:
Point Power (%) Flow (%)
C 78.2 54.8 D 25.7 24.3 The generic equation used to generate the 5% buffer zone exclusion region boundary is:
'W-WD
- W-W m- D,
<P C 2 WC -WD WC -W
. D.
PD=PD p
<D>
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),
Po = core thermal power at State Point D (% of rated),
We= core flow rate at State Point C (% of rated),
Wo= core flow rate at State Point D (% of rated),
The range of validity of the fit is: 24.3% 5% Flow 554.8%. l 1
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l Cycle 20 COLR Revision 2 February 1999 Table 2.1-1 MAPLHGR Versus Average Planar Exposure for BP8DWB335-10GZ Fuel Bundle No. 2017 j Plant: Vermont Yankee Fuel Type: P8DWB335-10GZ l MAPLHGR(kW/ft)
Average Planar Exposure (mwd /ST) Two Loop Operation Single Loop Operation' O.00 . I1.29 9.25 200.00 11.34 9.29 1,000.00 11.48 9.41 2,000.00 11.69 9.58 3,000.00 11.92 9.77 4,000.00 12.17 9.97 5,000.00 12.43 10.19 6,000.00 12.68 10.39 l 7,000.00 12.87 10.55 8,000.00 13.06 10.70 9,000.00 13.24 10.85 10,000.00 13.35 10.94 12,500.00 13.20 10.82 15,000.00 13.01 10.66 20,000.00 12.27 10.06 25,000.00 11.43 9.37 35,000.00 9.88 8.10 45,000.00 8.38 6.87 50,590.00 5.65 4.63 Source: NEDC-32814P, Report, Vermont Yankee Nuclear Power Station SAFER /GESTR-LOCA m Loss-of-Coolant Analysis. Reference 5. 24A5416AA, Revision 0, GE Report, Lattice Dependent MAPLHGR Report for Vermont Yankee Nuclear Power Station Reload 19 Cvele 20. Reference 8.
Technical Specification
References:
3.6.G.la and 3.ll.A.
1 MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
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Cycle 20 COLR Revision 2 February 1999 Tab!e 2.1-2 MAPLHOR Versus Averace Planar Exposure for BP8DWB335-1IGZ Fuel Bundle No. 2018 Plant: Vermont Yankee Fuel Type: P8DWB335-l lGZ MAPLHGR (kW/ft)
Average Planar Exposure (mwd /ST) Two Loop Operation Single Loop Operation' O.00 ,
11.28 9.24 200.00 11.33 9.29 1,000.00 11.43 9.37 2,000.00 11.60 9.51 3,000.00 11.80 9.67 4,000.00 12.04 9.87 5,000.00 12.30 10.08 6,000.00 12.53 10.27 7,000.00 12.73 10.43 8,000.00 12.94 10.61 9,000.00 13.I3 10.76 10,000.00 13.29 10 89 12,500.00 13.20 10.82 15,000.00 12.99 10.65 20,000.00 12.27 10.06 25,000.00 11.43 9.37 35,000.00 9.88 8.10 45,000.00 8.38 6.87 50,590.00 5.65 4.63 Source: NEDC-32814P, Report, Vermont Yankee Nuclear Power Station SAFER /GESTR-LOCA.
Loss-of-Coolant Analvsis. Reference 5. 24AS416AA, Revision 0, GE Report, L.attice Dependent MAPLHGR Reoort for Vermont Yankee Nuclear Power Station Reload 19 Cvele 20. Reference 8.
Technical Specification
References:
3.6.G.1a and 3.11.A.
I MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
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Cycle 20 COLR Revision 2 February 1999 l Table 2.1-3 MAPLHGR Versus /.s pec Pbnar Exposure for BP8DWB354-12GZ Fuel 6undle No. 2153 Plant: Vermont Yankee Fuel Type: PSDWB354-12GZ MAPLHGR(kW/ft)
Average Planar Exposure (mwd /ST) Two Loop Operation Single Loop Operation' O.00 , 10.96 8.98 200.00 11.04 9.05 1,000.00 11.I8 9. I6 2,000.00 11.40 9.34 3,000.00 11.63 9.53 4,000.00 11.81 9.68 5,000.00 12.01 9.84 6,000.00 12.14 9.95 7,000.00 12.26 10.05 8,000.00 12.37 10.14 9,000.00 12.46 10.21 10,000.00 12.52 10.26 12,500.00 12.40 10.16 15,000.00 12.10 9.92 20,000.00 11.40 9.34 25,000.00 10.72 8.79 35,000.00 9.44 7.74 45,000.00 7.24 5.93 48,200.00 5.67 4.65 Source: NEDC-32814P, Report, Vermont Yankee Nuclear Power Station SAFER /GESTR-LOCA.
Loss-of-Coolant Analysis. Reference 5. 24A5416AA, Revision 0, GE Report, Lattice Denendent MAPLHGR Report for Vermont Yankee Nuclear Power Station Reload 19 Cycle 20. Reference 8.
Technical Specification
References:
3.6.G.la and 3.ll.A.
1 MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.82.
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Cycle 20 COLR Revision 2 February 1999 l Table 2.1-4 j MAPLHGR Versus Average Planar Exposure for P9HTB380-12GZ Fuel l Bundle No. 2278 l Plant: Verrnont Yar,kee Fuel Type: P9HTB380-12G7.
l MAPLHGR(kW/ft) .
Average Planar Exposure l (mwd /ST) Two Loop Operation Single Loop Operation' O.00 10.64 8.72 200.00 10.71 8.78 1,000.00 10.85 8.89 )
l 2,000.00 11.04 9.05 l l 3,000.00 11.23 9.20 4,000.00 11.43 9.37 5,000.00 11.64 9.54 6,000.00 11.82 9.69 7,000.00 11.96 9.80 8,000.00 12.12 9.93 9,000.00 12.27 10.06 10,000.00 12.44 10.20 12,500.00 12.57 10.30 15,000.00 12.24 10.03 17,500.00 11.90 9.75 j 20,000.00 11.54 9.46 25,000.00 10.82 8.87 30,000.00 10.12 8.29 35,000.00 9.43 7.73 40,000.00 8.76 7.I8 45,000.00 8.10 6.64 50,000.00 7.44 6.10 55,000.00 6.77 5.55 57,480.00 6.43 5.27 57,580.00 6.42 5.26 Source: NEDC-32814P, Report, Vermont Yankee Nuclear Power Station SAFER /GESTR-LOCA.
Loss-of-Coolant Analysis. Reference 5. 24A5416AA, Revision 0, GE Report, Lattice Dependent MAPLHGR Report for Vermont Yankee Nuclear Power Station Reload 19 Cycle 20. Reference 8.
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 20 COLR Revision 2 February 1999 Table 2.1-5 MAPLHGR Versus Averace Planar Exposure for P9HTB379-13GZ Fuel Bundle No. 2279 Plant: Vermont Yankee Fuel Type: P9HTB379-13GZ Average Planar Exposure (mwd /ST) Two Loop Operation Single Loop Operation'
)
0.00 -
10.64 8.72 200.00 10.69 8.76 1,000.00 10.81 8.86 2,000.00 10.99 9.01 3,000.00 11.I8 9.I6 4,000.00 11.36 9.31 !
5,000.00 11.49 9.42 i 6,000.00 11.63 9.53 l
7,000.00 11,78 9.65 8,000.00 11.92 9.77 9,000.00 12.07 9.89 10,000.00 12.22 10.02 12,500.00 12.33 10.I i 15,000.00 12.23 10.02 l 17,500.00 11.90 9.75 l 20,000.00 11.54 9.46 l 25,000.00 10.82 8.87 30,000.00 10.I1 8.29 l 35,000.00 9.42 7.72 l 40,000.00 8.75 7.17 45,000.00 8.09 6.63 50,000.00 7.43 6.09 55,000.00 6.76 5.54 57,500.00 , 6.42 5.26 57,560.00 6.40 5.24 l Source: NEDC-32814P, Report, Vermont Yankee Nuclear Power Station SAFER /GESTR-LOCA.
Loss-of-Coolant Analysis. Reference 5. 24A5416AA, Revision 0, GE Report, Lattice i Dependent MAPLHGR Report for Vermont Yankee Nuclear Power Station Reload 19 Cycle 20. Reference 8. l l
Technical Specification
References:
3.6.G.la and 3.ll.A. {
l MAPLHGR for single loop operation is obtained by multiplying MAPLHGR for two loop '
operation by 0.82.
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Cycle 20 COLR Revision 2 February 1999 Table 2.2-1 Vermont Yankee Nuclear Power Station Cycle 20 MCPR Operatine Limits Value of"N" in RBM Average Control Cycle Exposure Two Loop Single Loop Eauation (AV Rod Scram Time Rance Operation Operation 42 % Equal to or better 0.0 to 8175 mwd /St 1.33 1.35 i than L.C.O. 8175 to 9175 mwd /St 1.34 1.36 l 3.3.C. l .1 9175 to 10175 mwd /St 3 1.37 1.39 Equal to or better 0.0 to 8175 mwd /St 1.37 1.39 i than L.C.O. 8175 to 9175 mwd /St 1.38 1.40 l 3.3.C. I .2 9175 to 10175 mwd /St3 1.47 1.49 l 1
Source: Report, Cycle Management Report for Vermont Yankee Nuclear Power Station Cycle 20. J11-03297 CMR, Rev. 0, April 1998, Reference 6. Report, General Electric Nuclear Energy, Sucolemental Reload Licensine Report for Vermont Yankee Nuclear Power Station Reload 19/Cvele 20. 24AS416, Rev.
l 3, January 1999, Reference 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 l 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 MCPR values are also valid for coastdown beyond 10175 mwd /ST.
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Cycle 20 COLR Revision 2 February 1999 Table 2.3 1 Maximum Allowable Linear Heat Generation Rate Limits Maximum Allowable Linear Fuel Tvoe Heat Generation Rate (kW/ft)
BP8DWB335-10GZ 14.4 BP8DWB335-11GZ . 14.4 BP8DWB354-12GZ 14.4 P9HTB380-12GZ 14.4 P9HTB379-13GZ 14.4 Source: NEDE-24011-P-A, Reference 1.
t Technical Specification
References:
2.1.A.1a,2.1.B.1, and 3.11.B.
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. Revision 2
! February 1999 l
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' Cycle 20 COLR Revision 2 February 1999
3.0 REFERENCES
- 1. Report, General Electric Standard Apolication for Reactor Fuel (GESTARIIL NEDE-24011-P-A-13, GE Company Proprietary, August 1996, as amended.
- 2. Report, General Electric Nuclear Energy, BWR Owners' Group Lone-Term Stability Solutions Licensine Methodolouv, NEDO-31960, June 1991.
1
- 3. Report, General Electric Nuclear Energy, BWR Owners' Group Lone-Term Stability Solations Licensine 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, Cvele Management Reoort for Vermont Yankee Nuclear Power Station Cycle 20. Jl1-03297 CMR, Rev. O, April 1998.
- 7. Report, General Electric Nuclear Energy, Sucolemental Reload Licensine Reoort for Verment Yankee Nuclear Power Station Reload 19/ Cycle 20, l 24A5416, Rev. 3, January 1999.
- 8. Report, Lattice Dependent MAPLHOR Report for Vermont Yankee Nuclear Power Station Reload 19. Cycle 20,24A5416AA, Rev. O, March 1998.
9.* Report, BWR Owners' Grouc Lone-Term Stability Solutions Licensine Methodoloav," NEDO-31960-A, November 1995. 10.* Report, BWR Owners' Grouo Lone-Term Stability Solutions Licensine Methodology," NEDO-31960-A, Supplement 1, November 1995.
- References 9 and 10 are the generically approved documents for References 2 and 3, including the SER from Reference 4.
14 _}}