ML20036A461

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Rev 2 to Colr
ML20036A461
Person / Time
Site: Cooper Entergy icon.png
Issue date: 03/26/1993
From:
NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20036A460 List:
References
NSD930476, NUDOCS 9305110253
Download: ML20036A461 (24)


Text

-

Attachment to NSD930476 Cooper Nuclear Station NRC Docket No. 50-298 f, :

CORE OPERATING LIMITS REPORT LIST OF EFFECTIVE PAGES i

Page(s)

Revision Data i through iv 2

03/26/93 1 through 20 2

03/26/93 t

1 I

I

.i.

'03/26/93

~

9305110253 930503 PDR ADOCK 05000298 P'

PDR

..y CORE OPERATING LIMITS REPORT TABLE OF CONTENTS 1

Page List of Tables iii 5

i iv List of Figures i

1.0 INTRODUCTION

I 1

2.0 CORE OPERATING LIMITS.

1 2.1 Rod Block Monitor Unseale Setnoint 2.2 Averare Planar Linear Heat Generation Limits 1

2.3 Linear Heat Generation Rate Limits 2-2.4 Minimum Critical ~ Power Ratio Limits.

2 3

3.0 REFERENCES

f f

v h

i e

r P

..-11.

03/26/93 7

k.

-a i

- e CORE OPERATING LIMITS REPORT LIST OF TABLES t

1 Number Title Egge

}

1 UlGR Limits for Cycle 16 4

{

r

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. 03/26/93-l 1

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I CORE OPERATING LIMITS REPORT LTST OF FIGURES I

Number Title Pace l

l 1

Maximum Average Planar Linear Heat Generation Rate 5

l (MAPLHGR) Versus Exposure with LPCI Modification and Bypass Holes Plugged, 3.02 percent GE8X8NB Fuel 2

Maximum Average Planar Linear Heat Generation Rate _

6

' {

(MAPLHGR).Versus Exposure with LPCI Modification and

(

Bypass Holes Plugged, 3.20 percent GE8X8NB Fuel 3

Maximum Average Planar Linear Heat Generation Rate 7

(MAPLHCR) Versus Exposure with LPCl Modification and l

Bypass Holes Plugged, Gell LUA Fuel j

f 4

Maximum Average Planar Linear Heat Generation Rate 8

a (MAPLHGR) Versus Exposure with LPCI Modification.and

}

Bypass Holes Plugged, BP8DRB283 Fuel j

4 5

Maximum Average Planar Linear Heat Generation Rate 9

(MAPLEGR) Versus Exposure with LPCI Modification and Bypass Holes Plugged, 3.48 percent GE8X8NB Fuel with 11GZ

' t 6

Maximum Average Planar Linear Heat Generation Rate 10 l

(MAPLHCR) Versus Exposure with LPCI Modification and Bypass Holes Plugged, 3.48 percent GE8X8NB Fuel with 12GZ j

r 7

Flow Dependent MAPLEGR Factor (MAPFAC,)

11 l

)

8 Power Dependent MAPLEGR Factor (MAPFAC,)

12 l

9 Power Dependent MCPR Limits, MCPR, and K,-

13

^q 10 Flow Dependent MCPR-Limits, MCPR, 14 j

11, 12 Minimum Critical Power Ratio-(MCPR) versus 7-GE8X8NB Fuel 15, 16 (various exposure ranges) 1 13,.14 Minimum Critical Power' Ratio-(MCPR) versus f Gell UUA

.17,.18 Fuel (various exposure ranges)'

15, 16 Minimum Critical Power Ratio (MCPR) versus T BP8DRB283,

.19, 20 j

Fuel (various exposure ranges) r I

NOTE: The ' Term Lead Use Assembly. (LUA) corresponds to the Term ' Lead ' Test '

h Assembly (LTA) discussed in Technical-Specification 5.2.C.

t

- iv -

03/26/93 I

i t

t t

p p

T

i

1.0 INTRODUCTION

l This 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 l

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 Cooper Nuclear Station shall be operated within the bounds of the below limits.

The applicable Technical Specifications are referenced in each I

subsection.

2.1 Rod Block Monitor Unseale Setnoint Technical Specifications Table 3.2.C states that the Rod Block Monitor (RBM) upscale (Power Referenced) trip level setting is

.j determined from the following:

Lowest Rated MCPR Limit:

LTSP ITSP HTSP-(LPSP 5 P < IPSP)

(IPSP $ P < HPSP)

(HPSP S P) 2 1.20 5 117.0/125 5 111.2/125 s 107.4/125-2 1.25 5 120.0/125 5 115.2/125 5 110.2/125 2 1.30

$ 123.0/125 5 118.0/125 5 113.2/125 LPSP, IPSP, and HPSP are the power level. setpoints listed on Table 3.2.C.

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 have been generically calculated and verified to bound the. Rod Withdrawal Error Analysis for Cycle 16 operation.

Technical Specifications

Reference:

3.2.C.

2.2 Average Planar Linear Heat Generation Limits The limiting APMGR value for the mo'st limiting lattice l (excluding.

natural uranium) for each fuel type as a function of Planar Average

'l Exposure and core power and flow is calculated by taking the value j

.from Figure 1, 2, 3, 4, 5, or 6, and multiplying it by the smaller

'i of the-MAP M GR-Flow. Factor, MAPFACy from-Figure 7,

or the

.j Power-Dependent MAPMGR Factor, MAPFAC, 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 OPLi7.

APMGR values were determined with the SAFE /REFIDOD LOCA methodology j

1 03/26/93 1

t and are given in References 2 and 3, while the MAPFAC and MAPFAC y

p were determined in Reference 6.

i The fuel types referred to in Figures 1, 2, 5, and 6 consists of multiple combinations of enriched uranium and gadolinia called i

lattices with each having its own calculated maximum APMGR (MAPMGR) value.

Hence, these fuel types have multiple MAPLHGR limiting values at a given planar exposure. The MAPMGR 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 MAPMGR 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 i

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 I

2.1.A.l.a q

2.1.A.1.d j

3.11.B i

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 (r), and fuel i

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 i

(MCPR ) from Figure 8.

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

i 2.4.2.1 The applicable. flow dependent MCPR (MCPR )

y determined from Figure 10, or l

2.4.2.2 The appropriate scram time (7) dependent MCPR at rated power from Figures 11 through 16, multiplied by the applicable power dependent MCPR l

multiplier (Kp) from Figure 9.

4 Technical Specification

Reference:

3.11.C

! 03/26/93

[

s t

3.0 REFERENCES

1.

NEDE-24011-P-A-10, February

1991, General Electric Standard Application for Reactor Puel.

(The approved revision at the time the reload analyses were performed.)

2.

Supplemental Reload Licensing Submittal for Cooper Nuclear Station Reload 15, Cycle 16, 23A7199 Revision 0, February 1993.

3.

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

4 NEDE-24045P Supplement 1. Loss-of-Coolant Accident Analysis Report for Cooper Nuclear Power Station.

5.

Letter (with attachment), R. H. Buckholz (CE) to P. S. Check (NRC)

i 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 V

Improvement Program Analyses for Cooper Nuclear Station Cycle 14.

i i

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l i

.i I

e

.3-03/26/93

CORE OPERATING LIMITS REPORT Table 1 LHGR Limits for Cvele 16 Fuel Tvoe Il1GR Limit' (kW/Ft)

BP8DRB283 13.4 GE 8x8 NB (3.02%, 3.20%, and 3.48%)

14.4 CE 11 LUA 14.4

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h 5

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h l-e t 03/26/93 l

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 13 A

'*/

N 11-6 10 N

5 N

s a

o

_m

'o to

'20 30 40 50 so 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

~

CORE OPERATING LIMITS REPORT r

Fiqure 2 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, 3.20% GE8X8NB Fuel 15 14 13

,Y 1r g

' D~

N t

N-2 N

o N

s a

7 Y

'o 10 2o so 40 so so PLANAR AVERAGE EXPOSURE (GWD/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 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:

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

1

~

CORE OPERATING LIMITS REPORT Fiqure 3 Maximum Average. Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, Gell LUA Fuel 15 t

14 13 12 0

0 %

h 4

10 8

N

}

N s

e o

7 6

0 10 20 30 40 50 60 70 PLANAR AVERAGE EXPOSURE (GWD/ST) s DATA COORDIliATES GWD/ST kW/ft 0.2 11.3 i

20.0 11.3 25.0 11.1 30.0 10.6 I

35.0 10.1 40.0 9.7 45.0 9.0 50.0 8.0 i

55.0 7.2 i

61.5 6.6 l

1 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

CORE. OPERATING LIMITS REPORT Fiqure 4 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus-Exposure with LPCI Modification and Bypass Holes Plugged, BP8DRB283 Fuel 15 14 13 A

12

- m g

'N 6

10 33 8

I S

s Is e

7 i

6 0

to 20 30

' 40 50~

60 PLANAR AVERAGE EXPOSURE (GWD/ST)

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 Note:' When in single loop operation, a MAPLHGR factor of 0.77 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

CORE OPERATING LIMITS REPORT 1

Fiqure 5

?

Maxipum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure l

with LPCI Modification and Bypass Holes Plugged, 3.43% w/11GZ GE8X8NB Fuel I

f 15 I

l 14 13

'1 3-s i3m

?

3:

N i

N 1

5 i

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2 8

U\\

7

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10 20 30 40 50 60 PLANAR AVERAGE EXPOSURE (GWD/$T)

DATA COORDINATES GWD/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-i 35.0 9.69 45.0 7.86 49.6.

5.62 Notes - 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 a

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 l

l

+

14 L

13 Eb

, rA 12 1w-i X

8 5

N N-s a

x e

Q I

5 o

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

DATA COORDINATES GWD/ST kW/ft i

0.0 10.89 0.2 10.94 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 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-

.,-(.

<4

.-t CORE OPERATING LIMITS REPORT-i 3

l1

'Ficure'7 j

Flow' Dependent MAPLHGR Factor j

=(MAPFAC )

p 1

I

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l 1.0 i

1 e

i s

0.9

____________,,)"

s i

+,s.*:-

0.8 MAPLHGR(FleMAPFACp MAPLNGR$70 ~

j MAPLMGRSTD. STANDARD MAPLNGR UMITS L

. y MAPFACptF). MINIMUM (1.0. ApWe'100 + Sp)

O' WC.% RATED CORE FLOW g

AND Ar, Br ARE FUEL TYPE DEPENCENT ;

'f e.

CONSTANTS GIVEN BELOW:--

w.

E.

GE FUELS; 0.8 THROUGH Gell g

MAxiMuu -

2 CORE FLOW

(% RATEDI Ac Sc.

102.5-0.6784 0.4861

~ 0.5 107.0 '

O.6758 0.4574:

112.0 0.6807-0.4214-117.0-0.6886-0.3828-0.4 I

I I

1 8

I 30 40 50-60

'70 80

-90 100 110'-

CORE FLOW (% AATEDI :

l i

I T

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! 03/26/93~

't 1

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=

1.2 N

O w

O u e0 0

k C

h 4

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p.

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s sos core Flow r bU Q

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C O

P MArtHGRp MAPFACp MAPtHGRSID 10 3

N y

' t4 (D

Mart.HGRSTD STANDARD MAPtHGR tmeis 1

$ 06

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03 I

8 FOR 25% >P:NO THf RMAL 1IMITS MONITORWG REOLDatD H

2 E

I NO UMtiS SPECN16 D

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1 N

l FOR 26% sP< 30%;

d-l l

MAPTACp-O 60 e 0 005 IP-30%I N

>50% CN f LW f OR s 60% CORE 9 LOW O

t

- I' MAPFACp.O So e O 005 te-30%l y

8 7OR > 50% CORE f LOW p

02 g

. l FOR 30% se.

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- I-M APF ACp. t 0 + 0 005224 (P-800%I 1

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to 20 30' to 50 so 70 780 -

90 100 POWER 1% RAlf D)

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04

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w w w~1r r wer r--we-ewrtee---^-

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w sp 'e &

ty'v*--evM'3 w wmw git--^^

M-eq ^ W v 't yT-4-ev g1p-^1p1^*w4' e't1e'mtw d=~-W4g ei'e*'m'M

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1 CORE OPERATING LIMITS REPORT l

t Ficure 9 i

Power Dependent MCPR Lintits (MCPR, and K )

p r

[e R.

W5

'l t

C

.gI E

c, - c

-o c

e

_W g

, g : :g c rr 8 -

s a

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88 l2 2

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-3@=,

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=

U w

oo O,

O, o

a s

, g gg

- Y,g e b g

FA I

C n

n o

g l e

..=o 55 t

$ :=g go 1 ;; / i s i i

i s

2 2-g gg E g

-~

Z.

.j 2n c

.g,.

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.e E "

e, e

2 l g

g 5.5

.5 5

5 5-S-

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g i

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=_m._e

__m.

i a

g R

e,

=,

S

-g a

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f i

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j

=

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%0t>dsd %GE MOs

%0t td w0s 4001) w3w10.83 edMtW3rldtIY.M W3M C3ivu i

1 0 03/26/93.

.j f

a

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m

.t CORE OPERATING LIMITS REPORT Fiaure 10 i

Flow Dependent MCPR' Limits j

(MCPR )

p i,

-h 9

1.8 FOR We t% RATED CCRE FLOWi<40%

FOR We f% RATED CORE FLCWim 40% -

'r 1.7

  • l1 + 0.0032140-W 'l

.MCPR(F) MAX 11.20. ApW '100+ 8pl.

MCPR!Fl e tArWed100 + Bsl C

C MAX FLOW AF BF

.q

~

117.0

-0.632 1.809 112.0

- 0.602 : 1.747 1,6 107.0

. - 0.586 1.697 i!

102.5

~- 0.571 1.655

-l l-1.5 MAxlMUM FLOW RATE = 117.0%

E

' 112.0%

'E 107.0%.

D 102.5%

'?

3 1A

~

1.3 d

i

'.O 1.2 8

1 f

'f 8

I f

f f

_ g,3 20-30' 40 50' 60 70 80-

-90

'100 110 120--

'1) l i

CORE FLOW (% RATED 1 i

.i 1j r

r

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' lt -

03/26/93I

-i

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+

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c

CORE OPERATING LIMITS REPORT Fiqure 11 Minimum Critical Power Ratio (MCPR) versus Tau (based on tested measured scram time as defined in Reference 5), GE8X8NB Fuel 1.30 1.29 1.28 1.27 1.26 i

1.25 g

Ss 1.24 1.23 1.22 1.21 r

1.20 0

0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.0 1

TAU Exposure Range BOC16 to EHFP16 - 2205 mwd /MT i

. 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 j

1.30 1.29 l

l 1.28 1.27 r

i 1.20

?

1.25 g

S2 1.24 1.23 1.22 1.21 0

0.1 0.2 0.3 0.4 0.5 0.6 0.7.

0.8 0.9 -

1 TAU Exposure Range:

EHFP - 2205 mwd /MT to EOC16 Cycle 16 -

03/26/93

^

CORE OPERATING LIMITS REPORT Fiqure 13 Minimum Critical Power Ratio (MCPR) versus Tau (based on tested measured.

scram time as defined in Reference 5), Gell LUA Fuel i

1.30 I

1,29 1.28 1.27 1.26 t

1.25 g

S r

s 1.24 1.23 7

s 1.22 1.21 1.200 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.0 1

TAU Exposure Range:

BOC16 to EHFP16 - 2205 mwd /MT Cycle 16 03/26/93.

t CORE OPERATING LIMITS REPORT Fiqure 14 Minimum' Critical Power Ratio (MCPR) versus Tau (based on tested measured scram time as defined in Reference 5), Gell LUA Fuel 1.30 1.29 1.28 1.27 1.26 1.25 g

S2 1.24 1.23 1.22 1.21 0

0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 -

0.9 1

TAU Exposure Range:

EHFP16 - 2205 mwd /MT to EOC16

' Cycle 16 03/26/93

4 4

CORE OPERATING LIMITS REPORT-j t

Fiqure 15 Minimum Critical Power Ratio (MCPR) versus Tau (based on tested measured-scram time'as defined in Reference 5), BP8DRB283 Fuel

-i

- 1.30 1.29 1.28 t

1.27 1.26 1.25 g

S1 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 Ranges BOC16 to EHFP16 - 2205 mwd /MT j

P t

i Cycle 16 03/26/93

e CORE OPERATING LIMITS REPORT i

Fiqure 16 Minimum Critical Power Ratio (MCPR) versus Tau (based on tested measured scram time as defined in Reference 5), BP8DRB283. Fuel l

p 1.30 l

1.29 I

1.28 1.27 5

1.2e i

1.25 e

S 2

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 i

Exposure Ranges EHFP16 - 2205 mwd /MT to EOC

  • he-Cycle'16 03/26/93-M