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{{#Wiki_filter:._ ._ | {{#Wiki_filter:._ ._ | ||
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Vermont Yankee Nuclear-Power Station ' | Vermont Yankee Nuclear-Power Station ' | ||
Cycle 14 Core Operating Limits Report Revision 0 l | |||
l | |||
l t-ig _ | l t-ig _ | ||
t f | t f | ||
September 1989 Reviewed [ /A* A M '9 2MTV | September 1989 Reviewed [ /A* A M '9 2MTV | ||
/ | / | ||
Plant Operations Date | Plant Operations Date Review Committee l | ||
Review Committee l | |||
Approved u 9/d/8? | Approved u 9/d/8? | ||
flant Manager " Da'te f | flant Manager " Da'te f | ||
Approved h [d Vice PresidenFand Dalel Manager of Operations Controlled Copy No. | Approved h [d Vice PresidenFand Dalel Manager of Operations Controlled Copy No. | ||
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: 3. - R&L . _ . | : 3. - R&L . _ . | ||
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,,. .. ., 3 | ,,. .. ., 3 | ||
, c.; *. . , . | , c.; *. . , . | ||
.T' | .T' | ||
,. L | ,. L REVISION RECORD. T | ||
; Revislon :Date Deserlption O' Initial printing. Reviewed by PORC and approved by. management. i i | |||
REVISION RECORD. T | |||
; Revislon :Date Deserlption | |||
O' Initial printing. Reviewed by PORC and approved by. management. i i | |||
i{ | i{ | ||
' t b | ' t b | ||
l k | l k | ||
k | k | ||
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k1 i | k1 i | ||
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(; I 8062R | (; I 8062R k | ||
4 l- | |||
l- | |||
-e - - - - - - - | -e - - - - - - - | ||
t < | t < | ||
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 | |||
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. | heat generation rate, and minimum critical power rativ. | ||
h. | h. | ||
l' a | l' a | ||
Line 121: | Line 68: | ||
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!it | !it t | ||
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Line 132: | Line 77: | ||
i | i | ||
* TABLE OF CONTENTS Page A | |||
REVISION REC 0RD................................................... ii ABSTRACT.......................................................... iii LIST OF TABLES.................................................... v LIST OF FIGURES................................................... vi 1 | |||
* TABLE OF CONTENTS | |||
Page | |||
==1.0 INTRODUCTION== | ==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 | |||
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 | |||
==3.0 REFERENCES== | ==3.0 REFERENCES== | ||
....................................................... 11 1-i s | ....................................................... 11 1-i s | ||
( 8062R | ( 8062R | ||
r : | |||
r : | * LIST OF TABLFR e | ||
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 $ | ( 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 | 2.1-3 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 | |||
: 2. 3-1 Maximum Allowable LHGR Limits for Cycle 14 9 | r s | ||
l-i | |||
(- -v. | (- -v. | ||
8062R 1 | 8062R 1 | ||
L i.. . | L i.. . | ||
I'' LIST OF FICURES p-If = E M AI Tit 1e Paae | |||
I'' LIST OF FICURES | |||
p-If = E M AI Tit 1e Paae | |||
: f. ( | : f. ( | ||
2.2-1 10 K{ Versus Fcreent of Core Flow Rate F | 2.2-1 10 K{ Versus Fcreent of Core Flow Rate F | ||
4 | 4 | ||
'A | 'A | ||
( | ( | ||
l | l | ||
~ | ~ | ||
8062R | 8062R i | ||
i | |||
==1.0 INTRODUCTION== | ==1.0 INTRODUCTION== | ||
1 | 1 | ||
( This report provides the cycle-specific limits for operation of the Vermont Yankee Nuclear Power Station through Cycle 14. It includes the limits | ( 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. | |||
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. | |||
l-l l | l-l l | ||
1 I 8062R | 1 I 8062R l' | ||
l' | |||
__ - _ __ .__ ___ _____ __ _ _J | __ - _ __ .__ ___ _____ __ _ _J | ||
2.0 CORE OPERATING LIMITS , | 2.0 CORE OPERATING LIMITS , | ||
s | s | ||
%< These Present Cycle operating limits have been defined using NRC-approved methodologies. The Present Cycle must be operated within the ; | %< 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. | bounds of these limits and all others specified in the Technical Specifications. | ||
2.1 Maximum Average Planar Linear Heat Generation Rate Limita | 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 , | ||
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. | 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. | |||
The fuel types, referred to in Tables 2.1-3 and 2.1-4, contain an | 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 | ||
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 | i cold shutdown condition. The remainder of the assembly is called the l | ||
j " Majority Lattice." | j " Majority Lattice." | ||
l l 2.2 Minimum Critical Power Ratio Limits | l l 2.2 Minimum Critical Power Ratio Limits During ' steady-state power operation, the Minimum Critical Power Ratio | ||
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 | . (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." | 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 | 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 ) | ( 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. | 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 | 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 : | ||
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. | 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 | 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. | .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. | ||
8062R | 8062R | ||
. ]- , | . ]- , | ||
l | l TABLE 2.1-1 g MAPLHCR Versus Average Planar Exoosure s | ||
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 ,. | 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 , | 1,000.0 11.2 9.3 5,000.0 11.8 9.8 , | ||
10,000.0 12.0 10.0 ' | 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 ' | 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 | [ 35,000.0 10.4 8.6 t | ||
Line 303: | Line 153: | ||
* MAPLRGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.83. | * MAPLRGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.83. | ||
i 1 | i 1 | ||
l l | l l | ||
( 8062R | ( 8062R | ||
-4 1 | -4 1 | ||
L .. - __ | L .. - __ | ||
, e | , e | ||
- TABLE 2.1-2 g- NAPLHGR Versus Average Planar Exposure | |||
- TABLE 2.1-2 | |||
g- NAPLHGR Versus Average Planar Exposure | |||
~\ | ~\ | ||
plant: Vermont Yankee Fuel Typet IP8DRB299 Average Planar MAPHLCR (kW/ft) | plant: Vermont Yankee Fuel Typet IP8DRB299 Average Planar MAPHLCR (kW/ft) | ||
Exposure Two Loop Single Loop (mwd /ST) Operation Operation | Exposure Two Loop Single Loop (mwd /ST) Operation Operation | ||
* 200.0 10.7 8.8 ,, | * 200.0 10.7 8.8 ,, | ||
i | i 1,000.0 10.8 8.9 , | ||
1,000.0 10.8 8.9 , | |||
5,000.0 11.4 9.4 $ | 5,000.0 11.4 9.4 $ | ||
10,000.0 12.2 10.1 | 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 | ||
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. . | Source: NEDO-21697, August 1977 (revised), Reference 9. . | ||
Technical Specification Referencest 3.6.G.la and 3.11.A. | Technical Specification Referencest 3.6.G.la and 3.11.A. | ||
Line 343: | Line 172: | ||
* MAPLHGR for single loop operatir.1 is obtained by multiplying MAPLHGR for two loop operation by 0.83. | * MAPLHGR for single loop operatir.1 is obtained by multiplying MAPLHGR for two loop operation by 0.83. | ||
8062R | 8062R | ||
~ | ~ | ||
' TARLE 2.2-1 MCPR Operatine Limits | ' TARLE 2.2-1 MCPR Operatine Limits | ||
( | ( | ||
Line 365: | Line 189: | ||
8062R | 8062R | ||
. . l! | . . l! | ||
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 - | |||
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 | 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 - | . 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 * | 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 | < 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 - | ||
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. | 1 l Source: NEDO-21697, August 1977 (revised), Reference 9. | ||
Technical Specification | Technical Specification | ||
Line 393: | Line 205: | ||
8062R l | 8062R l | ||
TABLE 2.1-4 e MAPLEGE_yntus Average Planar ExpRiutt k ' | TABLE 2.1-4 e MAPLEGE_yntus Average Planar ExpRiutt k ' | ||
Plantt Yumoallankte Tuel Typet AD110 l | Plantt Yumoallankte Tuel Typet AD110 l | ||
Average Planar MAPHLCR (kW/ft) for Two Loop Operation ' | Average Planar MAPHLCR (kW/ft) for Two Loop Operation ' | ||
Exposure Majority Shutdown Power Peaking Natural (mwd /ST) Lattice. Margin Zone Zone _ Enda_ | 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 | 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 - | ||
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 | 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 - | * 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 - | ||
Line 414: | Line 218: | ||
8062R | 8062R | ||
_j. | _j. | ||
\ | \ | ||
\; - | \; - | ||
' TABLE 2.):1 1 | ' TABLE 2.):1 1 | ||
'i- | 'i-('i ,. Maximum Allowable __IllGR Limits | ||
('i ,. Maximum Allowable __IllGR Limits | |||
( , | ( , | ||
e Maximum Allowable ; | e Maximum Allowable ; | ||
Line 431: | Line 228: | ||
Generation Rate Entl Typs _ | Generation Rate Entl Typs _ | ||
(kW/ft) | (kW/ft) | ||
P8DFB289 13.4 | P8DFB289 13.4 BP8DRB299 13.4 BD324B 14.4 BD326B 14.4 Source: NEDE-24011-P-A, Reference 10. | ||
BP8DRB299 13.4 BD324B 14.4 BD326B 14.4 | |||
Source: NEDE-24011-P-A, Reference 10. | |||
Technical Specification | Technical Specification | ||
==References:== | ==References:== | ||
2.1.A.la, 2.1.B.1, and 3.11.B ] | 2.1.A.la, 2.1.B.1, and 3.11.B ] | ||
l l | l l | ||
l | l | ||
Line 447: | Line 238: | ||
8062R | 8062R | ||
p- - - | p- - - | ||
: m. ,c , | : m. ,c , | ||
4 | 4 t | ||
i FlGURE 22-1 K Versus Percent Of Core Flow Rote i | |||
t | |||
i FlGURE 22-1 | |||
K Versus Percent Of Core Flow Rote i | |||
TeEhnical Specification Reference 3.11.C | TeEhnical Specification Reference 3.11.C | ||
, 1.4 , | , 1.4 , | ||
e | e | ||
\. | \. | ||
x ' 1 3 | x ' 1 3 | ||
Line 474: | Line 250: | ||
1.3 ,s N m T u | 1.3 ,s N m T u | ||
''N x , | ''N x , | ||
: s. sm I s t | : s. sm I s t | ||
s_'sm | s_'sm | ||
* s ' | |||
s ' | |||
s.'s . | s.'s . | ||
m N | m N 4 | ||
4 | |||
-\ | -\ | ||
s 'N.'s 1.2 _ m x , | |||
s 'N.'s | |||
1.2 _ m x , | |||
s x' -s | s x' -s | ||
, N;*::: s. s. N -xN x s s AUTOMATIC FLOW CONTROL y u. | , N;*::: s. s. N -xN x s s AUTOMATIC FLOW CONTROL y u. | ||
Line 495: | Line 264: | ||
-s's; s:s: s '~ -x s s | -s's; s:s: s '~ -x s s | ||
: x. /. | : x. /. | ||
s %Js s '-s s 's m s | s %Js s '-s s 's m s | ||
'%i% s 's ''s 's " | '%i% s 's ''s 's " | ||
s_ af s;ss x x -w f 11 NNA * * '' | s_ af s;ss x x -w f 11 NNA * * '' | ||
'scs 's s ;s s m | 'scs 's s ;s s m s ' | ||
s ' | |||
s s sJw ' | s s sJw ' | ||
s 's. 'sm | s 's. 'sm s 's s N s 's 's sm ' | ||
s.' 's,'sm u m | |||
s 's s N s 's 's | |||
sm ' | |||
s.' 's,'sm u | |||
m | |||
3s 'sm scsm s E A. | 3s 'sm scsm s E A. | ||
s zs s. | s zs s. | ||
%-sA v_ | %-sA v_ | ||
s.x x | s.x x | ||
/ s | / s | ||
- MANUAL. FI OW CONTROL /.- e ' rsA - | - MANUAL. FI OW CONTROL /.- e ' rsA - | ||
Line 528: | Line 281: | ||
- :7 v's. | - :7 v's. | ||
_f x's. 's | _f x's. 's | ||
's s | 's s | ||
: d. coop-Tube Set-Po.int Calibrat.i '- - . - | : d. coop-Tube Set-Po.int Calibrat.i '- - . - | ||
--- - s.m's s_ | |||
--- - s.m's | x s | ||
x x ' - | |||
s_ | |||
x | |||
x ' - | |||
1'0 - - = 25 ; e-- 5 -<-, -' | 1'0 - - = 25 ; e-- 5 -<-, -' | ||
positioned such that I'lowmax = 10/15,<. ' _.s - . | positioned such that I'lowmax = 10/15,<. ' _.s - . | ||
, e . _ a | , e . _ a | ||
= 107.0 % - - | = 107.0 % - - | ||
: = 112.0 % - - | : = 112.0 % - - | ||
= 117.0Te _ ___ _ ___ | = 117.0Te _ ___ _ ___ | ||
0.9 . . | 0.9 . . | ||
20 30 40 50 60 70 80 90 10 0 CORE FLOW % | 20 30 40 50 60 70 80 90 10 0 CORE FLOW % | ||
. 3.0 ILEFERENCES | . 3.0 ILEFERENCES | ||
: 1. Report, E. E. Pilat, 'Hethods for the Analysis of Boiling Water Reactors J Lattice Physics," YAEC-1232, December 1980. | : 1. Report, E. E. Pilat, 'Hethods for the Analysis of Boiling Water Reactors J Lattice Physics," YAEC-1232, December 1980. | ||
l | l | ||
: 2. Report, D. M. VerPlanck, 'Wethods for the Analysis of Boiling Water Reactors Steady State Core Physics," YAEC-1238, March 1981. | : 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. | : 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 ' | : 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. | 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. | : 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. | : 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)," | : 7. Report, A. A. F. Ansari and J. T. Cronin, " Methods for the Analysis of Boiling Water Reactorst A System Transient Analysis Model (RETRAN)," | ||
Line 583: | Line 309: | ||
, g Analysis of Boiling Water Reactorst Transient Critical Power Ratio | , g Analysis of Boiling Water Reactorst Transient Critical Power Ratio | ||
, ( Analysis (RETRAN-TCPYA01)," YAEC-1299P, March 1982. | , ( 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. | 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. | : 10. Report, " General Electric Standard Application for Reactor Fuel (CESTARII)," NEDE-24011-P-A-9, GE Company Proprietary, September 1988, as i amended. | ||
Line 597: | Line 322: | ||
YAEC-1706, October 1988. | YAEC-1706, October 1988. | ||
17, Memo, M. A. Sironen to S. R. Miller, " Revised VY Cycle 14 Core i - | 17, Memo, M. A. Sironen to S. R. Miller, " Revised VY Cycle 14 Core i - | ||
Performance Analysis Report," NED 89-42 March 10,1989. | Performance Analysis Report," NED 89-42 March 10,1989. | ||
8062R l - | 8062R l - | ||
.. 4 e , | |||
.. 4 | |||
e , | |||
0 | 0 | ||
.' 18. Report, " Sensitivity Study of Vermont Yankee Methods to Projected End-of-Tull-Power Life," YAEC-1460, February 1985. | .' 18. Report, " Sensitivity Study of Vermont Yankee Methods to Projected End-of-Tull-Power Life," YAEC-1460, February 1985. | ||
1 i | 1 i | ||
's | 's |
Latest revision as of 12:01, 18 February 2020
ML19332G192 | |
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Site: | Vermont Yankee ![]() |
Issue date: | 10/02/1989 |
From: | VERMONT YANKEE NUCLEAR POWER CORP. |
To: | |
Shared Package | |
ML19332G180 | List: |
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Download: ML19332G192 (18) | |
Text
._ ._
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_a i
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
/
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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.T'
,. 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
....................................................... 11 1-i s
( 8062R
r :
- 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
r s
l-i
(- -v.
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L i.. .
I LIST OF FICURES p-If = E M AI Tit 1e Paae
- f. (
2.2-1 10 K{ Versus Fcreent of Core Flow Rate F
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1.0 INTRODUCTION
1
( 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.
l-l l
1 I 8062R l'
__ - _ __ .__ ___ _____ __ _ _J
2.0 CORE OPERATING LIMITS ,
s
%< 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..
1
- MAPLRGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.83.
i 1
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- TABLE 2.1-2 g- NAPLHGR Versus Average Planar Exposure
~\
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.
B
- 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
(
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.
l
- MAPLEGR for single loop operation is obtained by multiplying MAPLHGR for two loop operation by 0.83.
(,
8062R l
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.
. loop operation by 0.83.
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\; -
' TABLE 2.):1 1
'i-('i ,. Maximum Allowable __IllGR Limits
( ,
e Maximum Allowable ;
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 ]
l l
l
(
8062R
p- - -
- m. ,c ,
4 t
i FlGURE 22-1 K Versus Percent Of Core Flow Rote i
TeEhnical Specification Reference 3.11.C
, 1.4 ,
e
\.
x ' 1 3
s i N '
1.3 ,s N m T u
N x ,
- s. sm I s t
s_'sm
- s '
s.'s .
m N 4
-\
s 'N.'s 1.2 _ m x ,
s x' -s
, N;*::: s. s. N -xN x s s AUTOMATIC FLOW CONTROL y u.
w s:s's. s -s.
a' x ,
'sc x s._ s
-s's; s:s: s '~ -x s s
- x. /.
s %Js s '-s s 's m s
'%i% s 's s 's "
s_ af s;ss x x -w f 11 NNA * *
'scs 's s ;s s m s '
s s sJw '
s 's. 'sm s 's s N s 's 's sm '
s.' 's,'sm u m
3s 'sm scsm s E A.
s zs s.
%-sA v_
s.x x
/ s
- MANUAL. FI OW CONTROL /.- e ' rsA -
e '
s 's.
- :7 v's.
_f x's. 's
's s
- d. coop-Tube Set-Po.int Calibrat.i '- - . -
--- - s.m's s_
x s
x x ' -
1'0 - - = 25 ; e-- 5 -<-, -'
positioned such that I'lowmax = 10/15,<. ' _.s - .
, e . _ a
= 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.
l
- 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.
I
l
- 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.
8062R l -
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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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