ML20086L333

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Rev 1 to Cooper Nuclear Station Core Operating Limits Rept
ML20086L333
Person / Time
Site: Cooper 
Issue date: 12/10/1991
From:
NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20086L330 List:
References
NUDOCS 9112160146
Download: ML20086L333 (27)
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Text

- _ - _ - _ _ - _ _ _ _ - _ _ _

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COOPER NUCl. EAR STATION CORE OPERATING LIMITS REPORT 1

9112160146 911210

)

PDR ADOCK 05000298 P

PDR

\\_

.s-C01'.E OPERATING LIMITS REPORT LIST OP EFFECTIVE PAGES

-Pare (s)

Revision Date 1-through iv 1

12/10/91

'l through 22 1

12/10/91' 4.

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CORE OPERATING LIMITS REPORT I6BLE OF CONTENTS UM List of Tables iii

List. of Figures.
  • r

.1. 0 - INTRODUCTION 1

1 2.0 CORE OPERATING LIMITS 2.1 Rod Block Monitor Unscale Setnoint 1

2.2 Average Planar Ling.ar Hect Generation Limits 1

l 2.3 Linear Hear Generacion Rate Limits 2

2.4 Minimum Critical Power Ratio Limits 2

3.0-REFERENCES 3-j 6

1

. 12/10/91

CORE OPERATING LIMITS REPORT LIST OF TABLES pumber Title Pace 1

1)lCR Limits for Cycle 15 4

i

-111-12/10/91

CORE OPERATING LIMITS REPORT

!asLoF EIGURPS thsher Ti_tle Ene 1

Maximum Average Planar Linear llear Generation Rate 5

(MAPulGR) Versus Exposure with LPCI Modification and Bypass lloles Plurred, 3.02 percent CE8X8NB Fuel.

2 Maximum Average Planar Linear lleat Generation Rate 6

(MAPulGR) Versus Exposure with LPCI Modification and Bypass lloles Plugged, 3.20 percent GE8X8NB Fuel.

3 Maximum Average Planar Linear lleat Generation Rate 7

(MAPUlGR) Versus Exposure with LPCI Modification and Bypass lloles Plugged, Gell LTA Fuel.

4 Maximum Average Planar Linear lleat Generation Rate 8

(MAPLilGR) Versus Exposure with LPCI Modification and Bypass lloles Plugged, BP8DRB265L and 1988 LTA Fuel.

5 Maximum Average Planar Linear lieat Generation Rate 9

(MAPUICR) Versus Exposure with LPCI Modification and Bypass lloles Plurred. hP8hRB283 Fuel.

6 Flow Dependent MAPLllGR Fac tor (MAPFACr) 10 7

Power Dependent MAPUICR Factor (MAPFAC,,)

11 8

Power Dependent MCPR Limits, MCPR, and Rp 12 9

Flow Dependent MCPR Limits, MCPR, 13 10-12 Minimum Critical Power Ratio (MCPR) versus T GE8X8NB 14-16 Fuel (various exposure ranges) 13-15 Minimum Critical Power Ratio (MCPR) Versus i Gell LTA 17-19 Fuel (various exposure ranges) 16-18 Minimum Critical Power Ratio (MCPR) versus 7 20-22 BPSDRB265L, BP8DRB283, and 1988 LTA Fuel (various exposure rances) e 12/10/91 l

. - - - ~ ~. - - -... - - -.. -

.7

}

1.0 INTRODUCT10t{

l This report provides the cycle specific limits for operation of the Cooper-

- Nuclear Station through Cycle 15.

It includes the limits for the Rod Block Monitor Upscale Set Point, Average Planar Linear lleat Generr. tion

- Rate (APulGR), Linear Heat Generation Rate __ (UlGR), 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 cera operating -limit values have been determined. using the

-NRC approved me;hodologies 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 Cooper Nuclear Station shall be operated within the bounda of the below limits.

The-applicable Technical Specifications.are referenced in each-

' subsection.

2.1

' Rod Block Monitor Unscalo Setnoint Technical Specifications Table 3.2.C states that the Rod Block

- Monito r. (RBM) upscale (Pont Referenced) trip igvel setting is i

determined from the following:

Lowest Rated

_MCPR Limi t:

__LTSP ITSP llTSP (LPSP $ P < IPSP) _ (IPSP $ P < HPSP)

(HPSP $ P) 2 1.20

$ 117.0/125 5 111.2/123

$ 107.4/125 2 1,25

$ 120.0/125 5 115.2/105 5 110.2/125 2 1.30

$ 123.0/125_

5 118,0/125

$ 11.~. 2/125

'LPSP. IPSP, and HPSP are the power level setpoints listed on

Table 3,2.C.

'The MCPR limit to be used with this table is determined by adding the aCPR value from the rod withdrawal error summary of Reference 2 and-adding it to the MCPR safety limit. The value for the MCPR in determining the RBM upscale trip level for Cycle 15 is 1.20.

-Technical Specifications

Reference:

3.2.C.

~

2.2 Averare Planar Linear Heat Generation Limits The limiting APUICR 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, or 5, and multiplying it by the smaller of L

the MAPUlGR Flow

Factor, MAPFAC, from Figure 6,.

or the Power-Dependent MAPulGR Factor, MAPFACp from Figure 7.

On Figure 6, use the curva associated.with a maximum core flow of 107 percent, L

which is the mechanical RRMG scoop tube limit specified in OPL-7.

APulGR values were determined with the SAFE /REFLOOD LOCA methodology 1

12/10/91 l

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

The fuel types referred to in Figures 1 and 2 consists of multiple combinations of enriched uranium and gadolinia called lattices with each having its own calculated maximum APUICR (MAPulGR) value.

llence, these fuel types have multiple MAPUICR limiting values at a given planar exposure. The MAPUICR values for these lattices, along with the axial location of each lattice in the bundle, are

.:onsidered proprietary information by General Electric and are given in Reference 4 as a function of planar average exposure.

The MAPUICR limits referred to above are for two recirculation loop operations. For single loop operation, the limiting APUlGR value is obtained by multiplying the values for two loop operation by the factor given at the bottom of each figure.

Technical Specification

Reference:

3.ll.A.

2.3 Linear Heat Generation Pate llmits These limits are equivalent to the design UICR, limiting power density, and maximum allowable UICR referred t.)

in the Technical Specifications. T1.ere are different UICR limits for dif ferent fuel types. These limits are given in Table 1.

Technical Specification

References:

1.0.A.4 2.1 4.1.a 2<l.A.l.d 3.11.B 2.4 Minimum Critical Power Patio 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 2 25 percent and < 30 percent of rated power, the OLMCPR is equal to the power dependent MCPR (MCPR ) from Figure 8, p

2.4.2 For core thermal power 2 30 percent of rated power, the OUICPR is the greater of either:

2.4.2.1 The applicable flow dependent MCPR (MCPR,)

determined from Figure 9, or 2.4.2.2 The appropriate scram time (7) dependent MCPR at rated power from Figures 10 through 18, multiplied by the applicable power dependent MCPR multiplier (K ) from Figure 8.

p Technical Specification

Reference:

3.ll.C 12/10/91

. LV

. 3.0; REFERENCES 1.

NEDE-240ll;P-A, General Electric Standard Application for-Reactor Fuel.

(The approved revfsion at the time the reload-analyses were performedi)

. 2. ;

Supplemental Reload Licensing Submittal for Cooper Nuclear Station Reload 14,. Cycle 15, 23A7117 Revision 0, July 1991, 3.

NEDO-24045, Loss-of Coolant Accident Analysis Report for Cooper Nuclear Power Station.

4 NEDE 24045P_ Supplement 1,: Revision-0, Loss-of-Coolant Accident

-Analysis Report for Cooper Nuclear Power-Station.

5.

Letter =(with attachment),:R. H, Buckholz-(CE) to Pe S. Check (NRC) dated September 5,1980, Response to NRC Request for Information on ODYN Computer Model.

6.

net';-31892P, Revision ~ 1, May 1991. Extended Load Line Limit and ARTS Improvement Program Analyses for Cooper Nuclear Station Cycle 14 f

.)

l i l-

' 12/10/91

CORE OPERATING LIMITS REPORTf Inble 1 11tGR Limits-for Cvele 14 F"el Tsoa 1]ICR Limit (kV/Ft)

BP8DRB265L 13.4 BPSDRB283 13.4 1988 LTA=

13.4 CE 8x8-NB (3.02% x 3.20%)

14.4 CE 11 LTA 14.4 i

i R

l-l..

I

~

4 12/10/91

m...

... - - - - - - -.. -.. _ ~

4 CORE OPERATING LIMITS REPORT

. figure 1 Maximum Average Planar Lincar lleat Generation Rate (MAPulGR) versus Exposure with LPCI Modification and Bypass 11 oles Plugged, 3.02% GE8X8NB Fuel is 14 u~

a

~"

\\

12 a.

a" h,

o p

11 g

i io x

o

\\

7 N

e g

i 3

i 9

t o-20 40 6o PL AN AR AVER AGE EXPOSURE IOWD/ST8 DATA COORDINATES CWD/ST Kv/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 l

-50.6 5.92 l:

51'3 5.80 L

-Note: MAPUlGR for single loop operation is obtained by multiplying the above by 0.75.

Cycle 15' l.

~

12/10/91 i

~.

... ~.... _

....~....c-,----_-.-__.

r.

6 CORE OPERATING LIMITS REPORT Eigure 2

' Maximum Average Planar Linear. Heat Generation Rate (MAPil1GR) versus Exposure with LPCI Modification and Bypass lloles Plugged, 3.20% CE8X8NB Fuel 15 14 13 -

_ a""'

<(

g,

[

h y',

t 11 s

5 N

'O K

g

\\

L 4'

0 N

7-

'N 6

5 oc to 40 co PL AN AR AVER AGE EXPOSURE tOWD/ST)

DATA COORDINATES GWD/ST Ew_f_f_t 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 15.0-12.32 20.0 11.83 25.0 11.34:

35.0 10.25 45.0

.8.44 50.0 5.90 Note: MAPulGR for single loop operation is cbtained by multiplying the abovo by'0,75.

Cycle 15

~ 12/10/91

d CORE OPERATING LIMITS REPORT Firure 3 Maximum Average Planar Linear lleat Generation Rate (MAPLilGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, Cell LTA Fuel j

15 14 13 12 i

n 1w
.2--

,..u n

g N,N Afew%

p...~..

-3 o

"t 7M--

b 5

-t 0

2o 40 60 PL AN AR AVER AGE EXIOSL%E IGWD/ST)

DATA COORDINATES GVD/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: MAPLHGR for single loop operation is obtained by multiplying the above by 0.75_

s Cycle 15 12/10/91

1

.. _ _,- -a - _ g l

j CORE OPERATING LIMITS REPORT Figure 4-

~

Maximurn Average Planar Linear Heat Generation Rate (MAPUICR) versus Exposure j

vith LPCI Modification and Bypass lloles Plugged, BP8DRB265L and 1988 LTA Fuel i

15 14 u

i 1

- ig

.m_.m n

sf 1

x NL to b

l o-3

- a 8

s ->

0.

20 40 60 PL AN AR AVER AGE EXPOSURE IQWD/ST)

DATA COORDINATES GWD/ST Kw/ft 0,2 11.6 1.0 11,6 5.0 12,1 10,0 l'2,1 15.0

-12.1 20.0

-11,9 25.0-11 3 L-30,0 10.7 35.0 10.2 4

.40,0

.9.6 MAPulGR-for singic lo' p operation is obtained by multiplying the above -

' Note:

o by 0.77.

Cycle 15

- 12/10/91

~

v

-e m r

+**e*

1-r-,

or c eww e-em-~a-

+,,-m---

-=

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N

'] 4 CORE 0"'

6. TING LIMITS REPORT F1ture 5 Maximum Average Planar Linear Heat Generation Rate (MAPUIGR) versus Exposure with LPCI Modification and Bypass lloles Plugged, BP8DRB283 Fuel 15 14 13 12

^ ^ " _ -

i 1 An 2~

}

N 10

- N' 9

0 7

6 5

o 2o 40 so PLAN AR AVE.R ACC EXPOSURE IQWtVST)

DATA COORDINATES

'GWD/ST Kw/ft 0.2 11.2 1.0 11.2-5.0 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 L.

Note: -MAPulGR for single loop operation is obtained by multiplying the above-

-by 0 77.

Cycle 15 12/10/91

a Figure 6 Flow Dependent AIAPLilGR Factor (SIAPFAC )

p 1.0 s

O.9 e

s.

0.8

=

MAPLHGRW) = MAPFACp MAPt.NG ASTO C

MAPU4GR g $TANDARD MAPu1GR UMIT3 M APcACpf) e MINIMUM (1.0. ApWed100 + Spl h

O' wC.% RA7ED CORE FLCW 3

AND Ac. Se ARE FUEL TYPE OEFENCENT E

CONSTANTS GNEN BELOW:

E GE FUEL.S j

0.s THROUGH Gell y,,yyy 2

CORE FLCW

(% RATED)

Ac Be

.102.5 0.678A Q.4861 0.5 107.0 0.S758 0.457A 112.0 0.6807 0.4214 117.0 0.6886 0.3825 g,4 9

I t

t I

t 30 A0 50 60 70 80 30 100 110 CORE FLCW (% RATED)

- 12/10/91

.......i - -

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f a

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h gg EE2

< 08

  • I2 " 3 7

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[

s 50% CORE FLOW MArtHGRp = MArf ACc M Af%GnSTD OCa 4

Uf -

2 MAPtHGRSTD - STAND ARD M Art HGR llWif S

.y 0.0 8'

i Fon 2ss >P: No TutnuAt ttuif s powifontwo ptoteo M

I t

No (suits setCtrtio E

8 M

{

8 g

j FOR 25% SP<30%:

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)

o g

g l

>50% ContFtOW y,py,cp,ggg,oogg,,,39g, 8

o4 FORs60% COpt f LOW i

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I MAMACc-0 50 + 0 00$ iP-30%I i

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I FOR>$0% Cont f LOW I

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g go, 3g g, p;.

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-1 uArgAcp. o,o oos224 te-100%

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y y

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en o

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a oY oc _E n

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o en -

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%0EttWOW idm W33dlDOW bd3W CHvW 12/10/91

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1 Figure 9 Flow Dependent MCPR Limits MCPRp e

i 1.8 FOR.Wc 1% RATED CORE FLCW1< 40%

- FCR We t% AATED CCAE FLCW)a40%

c.

MCP4(F). (AcWe#100

  • Ssl

' MCPR(Fl* MAX 81.20. AsWc 100

  • 858 1.7

'It

  • 0.0032 MO -W d C

M AX FLOW AF_

37 117.0

-0.632 1.803 112.0

- 0.602 1.747

-t 1.6 107.0

- 0.586 1.697 102.5

- 0.571 ' t.655

k 1.5 MAxtuuM FLOW RATE.117.0%

112.0%

ti --

107.0 %

--d 102.5%

=i..

1 1.3

_ 1.2 t

t

't I

f 8

8

.1.1

.20 30 40 50 60

-_ 70.

80 90-100.

110' 120'

- CCRC FLCW (% RATED 1 l'

5 12/10/91

.,=--e---

l a ~

]

r CORE OPERATING LIMITS REPORT Figure 10 Minimum Critical Power Ratio (MCPR) versus T (based on tested measured scram

time as defined. in Reference 5), CL8XSNB Fuel too ---

L29 1

128 127 L26 L25 -

L24 -

123 L22 L21 (20 0

0.2 0.4 0.6 0.0 1

TAU Exp_osure Range: B00 to EOC15

-2205 mwd /MT l

l l-I l-Cycle 15 1

l' l

. 12/10/91

CORE OPERATING LIMITS REPCU Firure 11 Minimum Critical Power Ratio (MCPR) versus T (based on tested measured scram ti:re as defined in Reference 5), GE8X8NB Fuel L30 129 L20 L27 120 -

125 L24 -4 j-123 -

l t22 1 I

J L21 L

3.-

e L2C r i

r-r--

i t

0 0.2 0.4 0.6 0.0 1

TAU Exposure Range: EOC15 - 2205 mwd /MT to EOC15 - 1102 mwd /MT Cycle l'

~15' 12/10/91

CORE OPERATING LIMITS REPORT Fir.ure 12 Minimum Critical Power Ratio (MCPR) versus v (based on tested measured scram time as defined in Reference 5),. CEaX8NB Fuel too

-l l

l L29 L28 r

127 L26 L25 124

-l 123 l

I 12

-t L21 L20

}-

0 0.2 0.4 06 0.8 1

TAU

' Exposure _ Range: EOC15 - 1102 mwd /MT to EOC15 I

l,

r Cyale 15 l

l

~

12/10/91

u.,_,

7 -

CORE OPERATINb LIMITS REPORT Tirure 13 Minimum Critical Power Ratio (MCPR) versus T (based on tested measured scram time as defined-in Reference 5), GEli LTA Fuct L30 L29 j

i 120 i

L27 -

126 l

L25 -

124

- - - +

+

L23 L22 -+--

r tyg

-f t-L2O 1:

}

r 0

0.2 0.4 0.6 0.8 1

TAU Exposure Range: EOC15 to EOC15 2205 mwd /MT Cycle 15

, 12/1d/91

--r w

~

4__,

CORE OPERATING LIMITS REPORT Fir.ure 14 Min.-

a Critical Power Ratio (MCPR) versus T (based on tested measured scram tino..s defined in Reference 5), Cell 1.TA Fuel L30 129 120 l

L27 t26

/

L25 -

n L24 -~

d r

/

4 L23 -

+ - - - - - - - - -

}

J u2 r

l

~-

t-L21 -

-4 L20 3 i

t 0

0.2 0,4 0.0 0.0 1

TAU Exposure Range: EOC15 - 2205 mwd /MT to EOC15 - 1102 mwd /MT

' Cycle 15 i

j 12/10/91 L

.e CORE OPF..MTING L1 HITS REPORT figura 15 Minimtuu Critical Power Ratio (MCPR) versus 7 (based on tested measured scrain i

time'as defined in Reference 5), CE1! LTA Fuel L30 L29 L28 I

127

/

\\

I 126 -

/

L25 -.-

, /

\\

g I

l.24 --

?

I

/

l t2a -

l L22

-4 l

L21 '-

p l

4; r

120 r r--+----~~---t--

0 0.2 0.4 0.6 0.8 1

l TAU l

l f.

Exposure Range: E0015 - 1102 mwd /MT to EOC15 l

l t

.I l

I i

Cycle 15 i

l L

f I 12/10/91 l

.J

CORE OPERATING LIMITS REPORT Firure 16 Minimum Critical Power Ratio (MCPR) versus T (based on tested measured scram

-time as defined in Reference 5), BP8DRB265L, BP8DRB283 and 1988 LTA Fuel 1.30 129 L28 L27 L26 L25 --

124 7

2 L23 -

1.22 t--

L21 L20

-t 1

O O.2 0.4 0.0 0.0 1

TAU Exposure Range: BOC15 to EOC15 - 2205 mwd /MT 1:

Il-l-

l Cycle 15 i

i i

l-

, 12/10/91

q~y_

~

.--i-.mi-CORE OPERATit1G LIMITS REPORT Figure 17 Minin:um Critical Power Ratio (MCPR) ve s7 (based on tested measured scram time as defined in Reference 5), BP8DRB

.5L, BP8DRB283 and 1988 LTA Fuel L30 tag 128 T

- ~ ~

127 4------

g20 7

__. ___7 l

125 ----f

-t-

+

---}--

124 --

} - --- ---

3 t:3

- __J l

l 1

g22 7

'._ _ _7_...__

l 1

b.-.___4___.

t;i I

i-- - yl i

l

--t 1

t0 0

0.2 0.4 0.6 0.0 1

t s.U Exposure Range: EOC15 - 2205 M'Jd/MT to EOC - 1102 trJd/MT I

s Cycle 15 12/10/91

6, CORE OPERATING LIMITS REPORT Finure 18 1

Minimum Critical Power Ratio (MCPR) versus f (based on tested mea-ured scram i

time as defined in Reference 5), BPSDRB265L, BP8DRB283 and 1988 LTA Fuel t30 y

)

129 --

128 127 ----

126 L25

-+ -

-_w l

-A i

[

L23 -

l I

i 1.22 121

-r--e--------

12 0 t

4 -- -

--n -

r - - -

0 0.2 0.4 00 0.0 1

TAU Exposure Range: EOC15 - 1102 FNd/MT to EOC15 Cycle 15 12/10/91

,

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