ML20069G976

From kanterella
Jump to navigation Jump to search
Revised Cooper Nuclear Station Colr
ML20069G976
Person / Time
Site: Cooper Entergy icon.png
Issue date: 04/28/1994
From:
NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20069G967 List:
References
NSD940326, NUDOCS 9406100242
Download: ML20069G976 (26)
v • d • e


Text

.*

) y " Cooper Iluclear Station" "Attachnent to !!SD940326' CORE OPERATING LIMITS REPORT LIST OF EFFECTIVE PAGES Pace (s) Pevision Date i 3 04/28/94 ii and iii 2 03/26/93 iv 3 04/28/94 1 2 03/26/93 2 and 3 3 04/28/94 4 through 11 2 03/26/93 12 3 04/20/94 13 through 20 2 Os/26/93 21 and 22 3 04/28/94

- i -

04/28/94 9406100242 940525 PDR ADOCK 05000293 p PDR ,

l

.e \*** g l t .

J 1

I CORE OPERATING LIMITS REPORT i

TABLE OF CONTENTS Pace List of Tables . . . . . . . iii List of Figures . . . . . . . . . iv

1.0 INTRODUCTION

. . . . . . . 1 2.0 CORE OPERATING LIMITS . . . . . . . 1 2.1 Rod Block Monitor Unscale Setroint . . . . . 1 2.2 Average Planar Linear Heat Generation Limits . 1 2.3 Linear Heat Generation Pate Limits . . . 2 2.4 Minimum Critical Power Ratio Limits . . . . 2 1

3.0 REFERENCES

. . . . . . . . . . . 3 ,

t l

)

1

- ii -

03/26/93 i i

1

( ),

1 1

CORE OPERATING LIMITS REPORT LIST OF TABLES Number Title Page i

1 LHGR Limits for Cycle 16 4  ;

1

)

l 1

i a

s t

- lii -

03/26/93

.,. t. , j CORE OPERATING LIMITS REPORT LIST OF FIGURES Numbgr Title Page 1 Maximum Average Planar Linear Heat Generation Rate 5 (MAPLHGR) Versus Exposure with LPCI Modification and Bypass Holes Plugged, 3.02 percent GE8X8NB Fuel 2 Maximum Average Planar Linear Heat Generation Rate 6 .j' (MAPLHGR) Versus Exposure with LPCI Moilification and Bypass Holes Plugged, 3.20 percent GE8Z8NB Fuel 3 Maximum Average Planar Linear Heat Generation Rate 7 (KAPLHGR) Versus Exposure with LPCI Modification and Bypass Holes Plugged, GEli LUA Fuel 4 Maximum Average Planar Linear Heat Generation Rate 8 (MAPLHGR) Versus Exposure with LPCI Modification and Bypass Holes Plugged. BPBDRB283 Fuel 5 Maximum Average Planar Linear Heat Generation Rate 9 (MAPLHGR) Versus Exposure with LPCI Modification and Bypass Holes Plugged, 3.48 percent GE8X8NB Fuel with 11GZ 6 Maximum Average Planar Linear Heat Generation Rate 10 (MAPLHGR) Versus Exposure with LPCI Modification and ,

Bypass Holes Plugged, 3.48 percent GE8X8NB Fuel with 12GZ  !

7 Flow Dependent MAPLHGR Factor (MAPFACp) 11 f 8 Power Dependent MAPLHGR Factor (MAPFAC ) 12 f 9 Power Dependent MCPR Limits, MCPR, and Kn 13 10 Flow Dependent MCPR Limits, MCPRy 14

11. 12 Minimum Critical Power Ratio (MCPR) versus 7 GE8X8NB Fuel 15, 16 (various exposure ranges) ,

13, 14 Minimum Critical Power Ratio (MCPR) versus 7 Gell LUA 17, 18 Fuel (various exposure ranges) 15, 16 Minimum Critical Power Ratio (MCPR) versus 7 BP8DRB283, 19, 20 Fuel (various exposure ranges) 17 Minimum Critical Power Ratio (MCPR) versus 7 GE 8x8NB 21 Fuel with one Turbine Bypass Valve Unavailable 18 Minimum Critical Power Ratio (MCPR) versus 7 GE 11 LUA 22 Fuel with one Turbine Bypass Value Unavailable NOTE: The Term Lead Use Assembly (LUA) corresponds to the Term Lead Test i Assembly (LTA) discussed in Technical Specification 5.2.C.

- iv -

04/28/94

L *.

, j A

f

1.0 INTRODUCTION

'!his report provides the cycle-specific limits for operation of the Cooper Nuclear Station through Cycle 16. It includes the limits for the Rod Block Monitor Upscale Set Point, Average Planar Linear Heat Generation Rate (APLHGR), Linear Heat Generation Rate (LHGR), and ,

Minimum Critical Power Ratio (MCPR). If any of these limits are exceeded, the action will be taken as defined in the Technical Specifications.

These core operating limit values have been determined using the 1 NRC-approved methodologies given in Revision 10 to Reference 1 and are established such that all applicable limits of the plant safety ,

analysis are met.

2.0 CORE OPERATING LIMITS i

Cooper Nuclear Station shall be operated within the bounds of the below limits. The applicable Technical Specifications are referenced in each subsection.

2.1 Rod Block Monitor Unscale Setnoint  !

i Technical Specifications Table 3.2.C states that the Rod Block {

Monitor (RBM) upscale (Power Referenced) trip level setting is  ;

determined from the following: i

{

Lowest Rated MCPR Limit: LTSP ITSP HTSP ,

(LPSP s P < IPSP) (IPSP s P < HPSP) (HPSP s P) 2 1.20 s 117.0/125 s 111.2/125 s 107.4/125 2 1.25 s 120.0/125 s 115.2/125 s 110.2/125 l 2 1.30 s 123.0/125 s 118.0/125 s 113.2/125  !

t LPSP, IPSP, and HPSP are the power level setpoints listed on Table 3.2.C.

1 I

The lowest rated MCPR limit to be used with this table for Cycle 16 is 2 1.20. The trip level settings associated with this MCPR limit j have been generically calculated and verified to bound the Rod Withdrawal Error Analysis for Cycle 16 operation. ,

i Technical Specifici.tions

Reference:

3.2.C.

2.2 Averace Planar Linear Heat Generation Limits The limiting APLEGR value for the most limiting lattice (excluding. ,

natural uranium) for each fuel type as a function of Planar Average Exposure and core power and flow is calculated by taking the value from Figure 1, 2, 3, 4, 5, or 6, and multiplying it by the smaller  !

of the MAPLHGR Flow Factor, MAPFAC p from Figure 7, or the Power-Dependent MAPLHGR Factor, MAPFACp from Figure 8. On Figure 7, use the curve associated with a maximum core flow of 102.5 percent, which is the mechanical RRMG scoop tube limit specified in OPL-7.  ;

APLHGR values were determined with the SAFE /REFLOOD LOCA methodology 03/26/93

  • . t....

4 and are given in References 2 and 3, while the MAPFACp and MAPFAC p were determined in Reference 6.

The fuel types referred to'in Figures 1, 2, 5, and 6 consists of multiple combinations of enriched uranium and gadolinia called lattices with each having its own calculated maximum APLHGR (MAPLHGR) value. Hence, these fuel types have multiple MAPLHGR limiting values at a given planar exposure. The MAPLHGR values for these lattices, along with the axial location of each lattice in the bundle, are considered proprietary information by General Electric and are given in Reference 4 as a function of planar average exposure.

The MAPLHGR limits referred to above are for two recirculation loop operations. For single loop operation, the limiting APLHGR value is obtained as explained by the note at the bottom of Pages 5 through 10.

Technical Specification

Reference:

3.11.A.

2.3 Linear Heat Generation Rate Limits These limits are equivalent to the design LHGR, limiting power.

density, and maximum allowable LHGR referred to in the Technical Specifications. There are different LHGR limits for different fuel types. These limits are given in Table 1.

Technical Specification

References:

1.0.A.4 -

2.1.A.1.a 2.1.A.1.d 3.11.B-2.4 Minimum Critical Power Ratio Limits The operating limit MCPR (OLCPR) values, which are a function of core thermal power, core flow, fuel type, scram time (7), and fuel exposure are calculated as follows:

2.4.1 For core thermal power a 25 percent and < 30 percent of rated power, the OLMCPR is equal.,to the power dependent MCPR (MCPRp ) from Figure 8.

2.4.2 For core thermal power a 30 percent of rated power, the OLMCPR is the greater of either:

2.4.2.1 The. applicable flow dependent MCPR (MCPRp )

determined from Figure 10, or 2.4.2.2 The appropriate scram time (7) dependent MCPR at' rated power from Figures 11 through- 18, multiplied by the applicable power dependent MCPR multiplier (K p ) from Figure 9.

Technical Specification

Reference:

3.11.C 04/28/94-

3.0 REFERENCES

l

1. NEDE-24011-P-A-10, February 1991, General Electric Standard ,

Application for Reactor Fuel. (The approved revision at the time I the reload analyses were performed.)

'i

2. Supplemental Reload Licensing Submittal for Cooper Nuclear Station' j Reload 15, Cycle 16, 23A7199 Revision 0, February 1993. l 3, NEDO-24045, Loss-of-Coolant Accident Analysis Report for Cooper Nuclear Power Station.

i

4. NEDE-24045P Supplement 1, Loss-of-Coolant Accident Analysis Report- 5 for Cooper Nuclear Power Station.
5. Letter (with attachment), R. H. Buckholz (GE) to P. S. Check (NRC) '

dated September 5, 1980, Response to NRC Request for Information on ,

ODYN Computer Model.

6. NEDC-31892P, Revision 1, May 1991, Extended Load Line Limit and ARTS Improvement Program Analyses for Cooper Nuclear Station Cycle 14, i
7. Letter (with attachment), T. H. Black (GE) to Paul Ballinger (NPPD)  !

dated April 26, 1954, Revised Impact Evaluation of One Turbine ,

Bypass Valve out-of-service on MCPR for Cooper Nuclear Station.

(CNS), Cycle 1G.

l j

i i

i 04/28/94 l

y__.-_._._.-....-._._...-. --.-._.-____.--_.._.____._._..-m. .. ..__.-_ _ _,

f

. i ., - \ 4. . .

a

{

j CORE OPERATING LIMITS REPORT i

i

  • i, q~

t l

! Table 1 i

I'

'.! LHGR Limits for Cycle 16 I .

i 8

Fuel Type LHGR Limit (kW/Ft) '

4 BP8DRB283 13.4  !

]- .

' GE 8x0 NB (3.02%,'3.20%, and 3.48%) 14.4 j GE 11 LUA 14.4 i 3

,.- fi j.

) i 1

d a

i 4

l t

5  !

4 e

1

j. i.

.i I l 1

i '

f l f I

! I i, - i,

s. 6 i_ .e

! h i  !

'l I

D 3

i.

J l

I. .

l L

I-03/26/93

= _ . - . - . .-. . . . - - - . _ . - . . . . - . . - - . .- - . - ._ - -

... s .. .

CORE OPERATING LIMITS REPORT Fiqure 1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, 3.02% GE8X8NB Fuel 15 14 z,

r

" ~

E d5, 10 N

" N

!s e N '

e

\_ e s

0 10 20 30 40 50 60 PLANAR AVERAGE EXPOSURE (GWD/ST)

DATA COORDINATES GWD/ST kW/ft 0.2 11.07 1.0 11.26 2.0 11.49 3.0 11.73 4.0 11.90 6.0 12.23 7.0 12.41 8.0 12.61 9.0 12.80 10.0 12.93 12.5 12.93 15.0 12.69 20.0 12.02 25.0 11.35 45.0 7.12 50.6 5.92 51.3 5.80 Note: When in single loop operation, a MAPLHGR factor of 0.75 is substituted for the LOCA analysis factors of 1.0 and 0.86 contained in the flow dependent MAPLHGR factor curves in Figure 7.

Cycle 16 03/26/93

i

' f CORE OPERATING LIMITS REPORT Fiqure 2 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, 3.20% GE8X8NB Fuel 15 1

14 l

l 13

,, r x p it 10 8

  • N N 5
s a

, N  ;

O Nb 5

0 10 20 30 40 50 60 PLANAR AVERAGE EXPOSURE (GWO/ST)

DATA COORDINATES GWD/ST kW/ft 0.0 10.80 0.2 10.85 1.0 11.01 2.0 11.23 3.0 11.47 4.0 11.63 5.0 11.80 6.0 11.99 7.0 12.23 8.0 12.38 9.0 12.52 10.0 12.64 12.5 12.57 I

15.0 12.32 20.0 11.83 25.0 11.34 35.0 10.25 45.0 8.44 50.0 5.90 Noce: When in single loop operation, a MAPLHGR factor of 0.75 is substituted ,

for the LOCA analysis factors of 1.0 and 0.86 contained in the flow dependent I MAPLHGR factor curves in Figure 7.

Cycle 16 03/26/93

CORE OPERATING LXMITS REPORT Fiqure 3 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, GEli LUA Fuel j i

15 14 13 12 I

!] [ '~n

{ '

g N 9

5 s a N .,

7 -

6 5

0 10 20 30 40 50 60 70 4

PLANAR AVERAGE EXPOSURE (GWD/ST)

DATA COORDINATES GWD/ST kW/ft 0.2 11.3 20.0 11.3 25.0 11.1 30,0 10.6 35.0 10.1 40.0 9.7 45.0 9.0 50.0 8.0 55.0 7.2 61.5 6.6 Note: When in single loop operation, a MAPLHGR factor of 0.75 is substituted for the LOCA analysis factors of 1.0 and 0.86 contained in the flow dependent  !

MAPLHGR factor curves in Figure 7.

Cycle 16 03/26/93

,.. 6. . * , ,

i CORE OPERATING LIMITS REPORT i

F_igure 4 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, BP8DRB283 Fuel 15 14 13 12

~ x_ 1 m

-y-11 p

s' 6 to N ,g 5

  • 2

$ 8 7

6 5

O 10 20 30 40 50 60 PLANAR AVERAGE EXPOSURE (GWD/ST)

DATA COORDINATES GWD/ST kW/ft 0.2 11.2 1.0 11.2 i 5.0 11.8 10.0 12.0 15.0 12.1 20.0 11.8 ,

25.0 11.3 30.0 11.1 35.0 10.4 40.0 9.8 Note 'When in single loop operation, a MAPLHGR factor of 0.77 is substituted for the LOCA analysis f actors of 1.0 and 0.86 contained in the flow dependent MAPLHGR factor curves in Figure 7.

Cycle 16 03/26/93

s...

e l

CORE OPERATING LIMITS REPORT 1 l

Fiqure 5_

Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, 3.48% w/11GZ GE8X8NB Fuel 15 14 13

'2 5W 7

g it-x N a mw y a 7

e g

"o to 20 so 40 50 oo PLANAR AVERAGE EXPOSURE (GWD/ST)

DATA COORDINATES CWD/ST kW/ft 0.0 10.85 0.2 10.90 1.0 11.01 2.0 11.17 3.0 11.36 4.0 11.56 5.0 11.76 6.0 11.91 7.0 12.07 8.0 12.23 9.0 12.38 10.0 12.48 12.5 12.61 15.0 12.47 20.0 11.79 25.0 11.05 35.0 9.69 45.0 7.86 49.6 5.62 ote: When in single loop operation, a MAPLHGR factor of 0.75 is substituted for the LOCA analysis f actors of 1.0 and 0.86 contained in the flow dependent MAPLHGR factor curves in Figure 7.

Cycle 16 03/26/93

.. v... I l

CORE OPERATING LIMITS REPORT Figure 6 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, 3.48% w/12GZ GE8X8NB Fuel 15 14 13 r Y 11L.

x e

Y -

10 '

5 * 'N s a \

  • NU 5

0 10 20 30 40 50 60 PLANAR AVERAGE EXPOSURE (GWD/ST)

DATA COORDINATES l

GWD/ST kW/ft '

0.0 10.89 O.2 10.94 l 1.0 11.05 2.0 11.19 3.0 11.34 4.0 11.49 5.0 11.64 6.0 11.80 7.0 11.97 8.0 12.14 9.0 12.31 10.0 12.49 12.5 12.52 l 15.0 12.23 20.0 11.53 25.0 10.86 35.0 9.60 45.0 7.75 49.0 5.83 Note: When in single loop operation, a MAPLHGR factor of 0.75 is substituted for the LOCA analysis factors of 1.0 and 0.86 contained in the flow dependent MAPLHGR factor curves in Figure 7.

Cycle 16 03/26/93

... s....

CORE OPERATING LIMITS REPORT Ficure 7  ;

Flow Dependent MAPLHGR Factor  !

(MAPFAC) T j

r l

1.0 -

0.9 -

____________ 9" u

$ 0.8 0#e.0" +

g

/,s ,

y= MAPLHGRtri-MAPFACp MAPLHGR$TD f g - MAPLHoRsTo -STANDARD MAPLHGR UMITS j y MAPFACptF)= MINIMUM (1.0. ApWC8100 + Sp '

0.7 g" W C= % RATED CORE FLOW g

ANO Ar. Og ARE FUEL TYPE DEPENCENT ,

e CCNSTANTS GIVEN BELOW:

E GE FUELS c 0.8 THROUGH Gell- i

< MAXIMUM  !

2 CORE FLOW i

(% RATEDI As 85 l 102.5 0.8784 0.4861  ;

0.5 - 107.0 0.8758 0.4574 l 112.0 0.8807 0.4214  !

117.0 0.8886 0.3828  !

i 0.4 ,

f  ! I I f I I  !

30 AC 50 80 70 80 90 100 110 i

CORE FLOW (% AATEDI i

?

_03/26/93 i

1.2 -

T O O i C O (D  %

_a M M y 1.0 -

1 c O

< o T i T M

- G  %

I R o >

^ O. N 8 N 08 -

l 6*

e o

Yo T

a C

~

O N (t M h s60% COM FLOW O g Mart HGRp = MAPFACp-MAPtHGRsto f y g

y OS

  • MAPtHGR$iD = STANDARO MArtHGR tiMITS U E l FOR 25% > P. NO THERMAL ttMITS MOMTDRtNG REOUtRED NO tim 4TS SPECIFttD 5 I  %

si l FOR 26% sP< 30%:-

N M Q T l l > 60% COM FN MAPFACp.O 80 e 0 005 tr- 30%g ft i I FOR s 50% CORE FLOW O 8 1 I M l 1 MAPFACp-0 50

  • O 005 (P- 30%)

FOR> 60% CORE f LOW

~

'I I FOR 30% sP:

0 1 M APF ACp- t 0 + 0 005224 (P - 100%f i 1 8 8 0 I I

  • I I I I l I I O to 20 30 40 50 60 70 80 90 100 h

s POWER 1% R ATEDe PJ OC N

'O V

,.,w. ,, % ww w , . ..,,c..w.w.- e3+,w.... ,.,m.,, ,-,mwm ,wvs,e - ..-w-, -w,- m, ,-r -. ,-.e ...e-n, ,.-e --, , ,.s.,, ,.,,,-.e,.,s.,, ,, . - - -

.. s... .

i CORE OPERATING LIMITS REPORT i

Ficture 9 >

Power Dependent MCPR Limits (MCPR p and Kp) 8 5

I - o t o. a y5 e e= 8-2

? E v c c c. o j E _

=

m e _ 3 gg #

o o 1m g( :: 2- 8 oeo2 n e

g ..

as , ,

w s oo n e n

.mQ

-, e 5* E*

vu s#

o 8 n

o

, su >o on o o 8 - ~

o c Tar h= ..

- +

e ..

ma e e

o E~ stIm W "o oo a er - - -

U 2

  • g C.

go *

=m e

,A p,, p e

p e

j gg ev

> L ,,*p

-n a -

2  ;

.. m v v

- /

-s a. - 8 e. t L. _

o e M e I "# *

  • b E # 4 m # # *
  • "v e = m o e o E

'I y a. n n w e l e

o e

o e

o e

o e

o - o#

m -

i m m m a m e 1  :

o 4

b a

I

..____________ _____ _______________ g

_ g

g. ,

g C

$ o o

  • e M A _ o I I f f f I g o o o o o o o o e e n o e e n o_

n en n n .- _ _ =

%Ot >dSd %$l MOs %Ot td MOs tOOli W3W10 .4 (dm M3ndi11nW W3W C31Yu 03/26/93

,,- s ..

2 CORE OPERATING LIMITS REPORT 5 Ficure 10 7 t

Flow Dependent MCPR Limits ,

(MCPR) r  !

k i

1.8 f 4

FOR Wc (% RATED CCRE FLOWi<40% FOR We (% RATED CORE FLOW 1240%  ;

MCPRIFl (AcWcr100 + Bei MCPR(F)= MAX (1.20. ApWC'100 + 851 r 1.7 -

  • l1 + 0.0032 (40-WC il max FLOW AF BF 117.0 - 0.632 1.809 112.0 -0.602 1.747 1.6 -

107.0 - 0.586 1.697 102.5 - 0.571 1.655

~

- MAXIMUM FLOW RATE = 117.0%

112.0%

107.0% ,

h 102.5% i 2

1.4 g i

l 1.3 -

i 1.2 - ,

1.1

' ' '  ! I f f f f ,

20 30 40 50 60 70 30 30 100 110 120 CORE FLOW (% RATEDI 03/26/93 i I

,., 5....

CORE OPERATING LIMITS REPORT I

Fiqure 11 Minimum Critical Power Ratio (MCPR) versus Tau (based on tested measured i scram time as defined in Reference 5), GE8X8NB Fuel 1 1

1.30 -

1.29 1.28 1.27 1.2e g 1.25 S

s 1.24 1.23 1.22 1.21 1.20 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 TAU l

Exposure Ranges BOC16 to EHFP16 - 2205 mwd /MT i

l l

l Cycle 16 03/26/93 i

CORE OPERATING LIMITS REPORT Fiqure 12 Minimum Critical Power Ratio (MCPR) versus Tau (based on tested measured scram time as defined in Reference 5), GE8X8NB Fuel 1.30 1.29 i

1.28 1.27 1.26 g 1.25 S

3 >

~

1.24 1.23 1.22 1.21 1.20 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 TAU Exposure Ranger EHFP - 2205 mwd /MT to EOC16 P

Cycle 16 03/26/93

.. s..

CORE OPERATING LIMITS REPORT Figure 13 Minimum Critical Power Ratio (MCPR) versus Tau (based on tested mea:sured scram timo as defined in Referenco 5), GEli LUA Fuel 1.30 1.29 1.2a i 1.27 1.26 g 1.25 S

s 1.24 1.23 1.22 1

1.21 1.ao 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0,9 1 TAU l

Exposure Rango BOC16 to EHFP16 - 2205 mwd /MT i

cycle 16 03/26/93

.. % .=

CORE OPERATING LIMITS REPORT Fiqure 14 I

Minimum Critical Power Ratio (MCPR) versus Tau (based on tested measured BCram time as defined in Reference 5), Gell LUA Fuel 1.30 1.29 1.28 1.27 1.26

+

1,25 g

S 1.24 1.23 1.2'

/

t.21

/

1.20 0 0.1 0.2 0.3 0.4 0.5 0.C 0.7 0.8 0.9 1 TAU Exposure Ringer EHFP16 - 2205 mwd /MT to EOC16 i

Cycle 16 03/26/93

. , i CORE OPERATING LIMITS REPORT Fiqure 15 Minimum Critical Power Ratio (MCPR) versus Tau (based on tested measured ,

scram time as defined in Reference 5), DP8DRB283 Fuel 1.30 1.29 ,

1.28 1.27 1.26 g 1.25 S P s '

1.24 >

P b

1.23 1.22 P

1.21 l

r 1.20 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 TAU Exposure Ranger BOC16 to EHFP16 - 2205 mwd /MT i

1 P

Cycle 16 03/26/93 l l

I

s. ...

,.. . I 1

CORE OPERATING LIMITS REPORT Fiqure 16 l l.

Minimum Critical Power Ratio (MCPR) versus Tau (based of. tested measured scram time as defined in Reference 5), BPSDRB283 Fuel 1.30 .

1.2e 1.28 1.27 1.26 t

g 1.25 S

s 1.24 -

1.23 1.22 1.21 1.20 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 TAU Exposure Ranger EHFP16 - 2205 mwd /MT to EOC ,

[

Cycle 16 03/26/93 I

- s CORE OPERATING LIMITS REPORT Fioure 17 Minimum Critical Power Ratio (MCPR) versus Tau with one Turbine Bypass Valve Unavailable, (based on tested measured scram time as defined in Reference 5), GE8X8NB Fuel 1.30 129 128 127- v 128 e

$ 1.25 m

1.24 123 122 .-

121 120 00 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 09 1.0 TAU Exposure Range: BOC16 to EOC16 Cycle 16 04/28/94

,e * . .o

, CORE OPERATI!JG LIMITS REPORT Ficure 18 Minimum Critical Power Ratio (MCPR) versus Tau with one Turbine Bypass Valve Unavailable, (based on tested measured scram time as defined in Reference 5), Gell LUA Fuel 1.30 129 128 +

1.27 126 x

b 125 m

124 123 122 <

1.21 120 OO 0.1 02 0.3 04 0.5 0.6 0.7 0.8 0.9 1.0 TAU I

Erposure Range: BOC16 to EOC16 l

I Cycle 16 04/28/94

Retrieved from "https://kanterella.com/w/index.php?title=ML20069G976&oldid=2825602"