ML20112G524

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Revised Cooper Nuclear Station Colr
ML20112G524
Person / Time
Site: Cooper Entergy icon.png
Issue date: 06/07/1996
From:
NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20112G518 List:
References
NUDOCS 9606120062
Download: ML20112G524 (20)
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COOPER NUCLSH C (ATION CORE OPERATING LIMITS REPORT 9606120062 960607 PDR ADOCK 05000298 P

PDR 06/07/96

e e

CORE OPERATING LIMITS REPORT LIST OF EFFECTIVE PAGES Pagg[s)_,_.

Revision Date _

i 5

06/07/96 ii and iii 4.

I1/09/95 iv 5

06/07/96 1 and 2 4

11/09/95 1

3 5

06/07/96 4 through 12 4

11/09/95 13 through 15 5

06/07/96 l

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I-CORE OPERATING LIMITS REPORT i

TABLE OF CONTENTS List o f Table s................................................................ iii i

l List o f Figu re s.............................................................. iv l

l 1.0 INTR O D UCTION.................................................... 1

(

2.0 CORE OPERATING LIMITS.......................................

......I 2.1 Rod Block Monitor Unscale Set Point........................... 1 l

i 2.2 Average Planar I inear Heat Generation Limits................... 1 i

2.3 Linear Heat Generation Rate Limit............................. 2 l

2.4 '

Minimum Critical Power Ratio Limits.......................... 2 3.0 RE FE RE NC ES............. -........................................... 3 I

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CORE OPERATING LIMITS REPORT LIST OF TABLES

._ Number

__ Title Page_

1 LHGR Limit 4

)

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CORE OPERATING LIMITS REPORT LIS_ OF FIGURES T

Pag [

Number Title 1

Maximum Average Planar Linear Heat Generation Rate 5

(MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged,3.02% GE 8x8 NB Fuel 2

Maximum Average Planar Linear Heat Generation Rate 6

(MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged,3.20% GE 8x8 NB Fuel 3

Maximum Average Planar Linear Heat Generation Rate 7

(MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged,3.48% w/l1GZ GE 8x8 NB Fuel 4

Maximum Average Planar Linear Heat Generation Rate 8

(MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged,3.48% w/12GZ GE 8x8 NB Fuel 5

Flow Dependent MAPLHGR Factor (MAPFACp) 9 6

Power Dependent MAPLHGR Factor (MAPFAC )

10 p

7 Power Dependent MCPR Limits, MCPR and Kp 11 p

8 Flow Dependent MCPR Limits, MCPR, 12 9,10 Minimum Critical Power Ratio (MCPR) versus Tau 13,14 (based on tested measured scram time as defined in Reference 7),

GE 8x8 NB Fuel (various exposure ranges) 11 Minimum Critical Power Ratio (MCPR) versus Tau with One 15 Turbine Bypass Valve Unavailable (based on tested measured scrun time as defined in Reference 7), GE 8x8 NB Fuel i

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1.0 INTRODUCTION

This report provides the cycle-specific limits for operation of the Cooper Nuclear Station through Cycle 17. It includes the limits for the Rod Block Monitor Upscale Set Point, Average Planar Linear Heat Generation Rate (APLHOR), 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 NRC-approved methodologies given in References 1 and 4, 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 subsection.

2.1 Rod Block Monitor Unscale Set Point

. Technical Specification Table 3.2.C states that the Rod Block Monitor (RBM) upscale (Power Referenced) trip level setting is determined from the following:

Low Trip Intermediate Trip High Trip Lowest Rated Set Point Set Point Set Point 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 2 1.30 s 123.0/125 s 118.0/125 s 113.2/125 LPSP, IPSP, and HPSP are the Low Power Set Point, Intermediate Power Set Point, and High Power Set Point respectively, as listed on Technical Specification Table 3.2.C.

The lowest rated MCPR limit to be used with this table for Cycle 17 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 17 operation.

l Technical Specifications

Reference:

3.2.C.

2.2 Average Planar Linear Heat Generation I imits i

The limiting APLHGR value for the most limiting lattice (excluding natural uranium) i for each fuel bundle as a function of Planar Average Exposure and core power and flow is calculated by taking the value from Figures 1,2,3, or 4, and multiplying it by the smaller of the MAPLHGR Flow Factor, MAPFACr from Figure 5, or the 11/09/95 l

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Power-Dependent MAPLHGR Factor, MAPFAC from Figure 6. APLHGR values p

were determined with the SAFE /REFLOOD LOCA methodology and are given in References 3 through 6, while the MAPFAC, and MAPFAC, were determined in Reference 8.

The fuel bundles referred to in Figures 1, 2, 3, and 4 consists of multiple combinations of enriched uranium and gadolinia filled lattices with each having its own calculated maximum APLHGR (MAPLHGR) value. Hence, these fuel bundles 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 References 5 and 6 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 Figures 1 through 4 per Reference 6.

Technical Specification

Reference:

3.11.A 2.3 I incar Heat Generation Rate I imit The limiting power density and maximum allowable Linear Heat Generation Rate (LHGR) referred to in the Technical Specification Sections 1.0.A.4 and 3.11.B are the design LHGR; this design LHGR value is given in Table 1.

2.4 Minimum Critical Power Ratio Limits The operating limit MCPR (OLMCPR) values are a function of core thermal power, core flow, fuel bundle, scram time (t), and fuel exposure. The scram time (T) is determined from CNS Procedure 10.9, Control Rod Scram Time Evaluation; the OLMCPR values are provided 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 (MCPRp) from Figure 7 2.4.2 For core thermal power 2 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 8, or 2.4.2.2 The appropriate scram time (t) dependent MCPR at rated power from Figures 9 and 10, multiplied by the applicable power dependent MCPR multiplier (K ) from Figure 7.

p Technical Specification

Reference:

3.11.C 11/09/95

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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 the reload analyses were performed.)

l 2.

Supplemental Reload Licensing Submittal for Cooper Nuclear Station Reload 16, Cycle 17, t

24A5187, Revision 3, June 1996.

3.

letter No. 262-95-182 from Ala Alzaben of General Electric to Gautam Sen of NPPD, for Cooper Nuclear Station Reload 16, Cycle 17, Lattice Dependent MAPLHGR, dated l

September 15,1995.

l 4.

NEDO-24045, August 1977, Loss-of-Coolant Accident Analysis Report for Cooper Nuclear Power Station.

5.

NEDE-24045P Supplement 1, December 1989, Loss-of-Coolant Accident Analysis Report l

for Cooper Nuclear Power Station.

6.

NEDE-24045P S., sement 2, Loss-of-Coolant Accident Analysis Report for Cooper Nuclear Power Station Reload 15, Cycle 16, March 1993.

7.

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.

8.

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

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CORE OPERATING LIMITS REPORT Table 1 LHGR Limit Fuel Type LHGR Limit (kW/Ft)

GE 8x8 NB (3.02%,

3.20%, and 3.48%)

14.4 11/09/95

CORE OPERATING LIMITS REPORT Figure 1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged,3.02% GE 8x8 NB Fuel 15 14

'N.

[

11.-

h g

10 N

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

DATA COORDINATES (Reference 5)

Planar Avg. 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 M APLHGR factor curves in Figure 5.

Cycle 17 11/09/95

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CORE OPERATING LIMITS REPORT Figure 2 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged,3.20% GE 8x8 NB Fuel 15 14 13

_.. _. ~

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N N

3

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u 5

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

DATA COORDINATES (Reference 5)

Planar Avg. 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 l

6.0 11.99 7.0 12.23 8.0 12.38 i

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 5.

Cycle 17 11/09/95 1

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l CORE OPERATING LIMITS REPORT Figure 3 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged,3.48% w/l1GZ GE 8x8 NB Fuel 15 14 13 m

ar- - x E

1

g I'

N x

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\\

5 0

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

DATA COORDINATES (Reference 61 Planar Avg. 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 l

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 i

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 5, 4

Cycle 17 11/09/95 i

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CORE OPERA *11NG LIMITS REPORT Figure 4 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged,3.48% w/12GZ GE 8x8 NB Fuel 16 14 13 JN

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

DATA COORDINATES (Refere_ m.6)

Planar Avg. GWD/ST kW/Ft 0.0 10.89 0.2 10.94 1.0 11.05 2.0 11.19 l

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 l

20.0 11.53 25.0 10.86 35.0 9.60 45.0 7.75

]

49.0 5.83 i

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 l

in Figure 5.

4 Cycle 17 11/09/95

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CORE OPERATING LIMITS REPORT Fieure 5 Flow Dependent MAPLHGR Factor (MAPFAC,)

(Reference 8, Section 5.4.4, Figure 5-9)

I 1.0 0.9 A

3

.-----------4 6

  1. jot-0.8 olo MAPLHGR(F) = MAPFACp-MAPLHGRSTD g

MAPLHGRSTD = STANDARD MAPLHGR LIMITS MAPFACp (F) = MINIMUM (1.0. A W /100 + B )

pC p

h W = % RATED CORE FLOW C

g AND Ap Bp ARE FUELTYPE DEPENDENT CONSTANTS GIVEN BELOW:

g 4

0 i,

5 Gti FUELS 0.6 THROUGH GE11 MAXIMUM 1

3 CORE FLOW

(% RATED)

Ap Bp 1

102.5 0.6784 0.4861 i

0.5 107.0 0.6758 0.4574

]

112.0 0.6807 0.4214 117.0 0.6886 0.3828 0.4 I

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30 40 50 60 70 80 90 100 110 CORE FLOW (% RATED)

Cycle 17 11/09/95

l l-l CORE OPERATING LIMITS REPORT Figure 6 Power Dependent MAPLHGR Factor

)

(MAPFAC,)

l Reference 8, Section 5.4.2, Figure 5-7) l l

1.2 g

1<

2 c,

Eo 1.0

~

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[0 0.8 3

g, s50% CORE FLOW h

b 0.6 --

3,,,

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-. -Fw, -n uAptnGR,,,. STANDARD MAPLHGR UMITS FOR 25%>P: No THERMAL UMITS MONITORING REQUIRED NO UMITS SPECIFIED Z

Lu Q.

FOR 25% sPm Lu 0.4 9

  1. > 50% CORE FLOW MAPFAC, =0 60 + 0.0005 (PM) l g

FOR 550% CORE FLOW MAPFAC, = 0.50 + 0.005 (P 30%)

FOR>50% COREFLOW FOR 30% $ P:

MAPFAC, = 1.0 + 0.005224 (P 100%)

j 0

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0 10 20 30 40 50 60 70 80 90 100 POWER (% RATED) i 1

.i 4

Cycle 17 10 I1/09/95

f OM g

4 2.60 2.40 f

OPERATING UMIT MCPR (P) - Kp ' OPERATING UMIT MCPR(100) 8Q q

5 50% FLOW "

FOR P<25% NO THERMAL UMITS MONITORING REQUIRED Q

m gy NO UMITS SPECIFIED W

Q 2.20 FOR 25%sP< Ppass:(bass =30%)

[

oN Kp = [Kgyp + 0.026 (30% - P)]/ OLMCPR(100)

Q Q

]

ao K8YP = 1.83 FOR 5 50% CGRE FLOW Q

x u.

8 227 FOR > 50% CORE FLOW aC g

2.00 FOR 30%s P< 45%

Kp = 1.28 + 0.0134 (45% - P)

O m

E A

2

[D E

O FOR 45%sP< 60%

U-

~

s 50% FLOW" 1.60 Kp = 1.15 + 0.00067 (60% - P)

D C0

  • O

[

p

{g q

rOR 60%s P:

,a n

g T

Kp-1.0 + 0.00375 (100% - P)

T x

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b l

m r.n p

1.40 l

6 C.

W g

g m

p o

w m

a v.

O W

H v

g g g i.20 2

SE i

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f 1.00 O

10 20 30 40 50 60 70 80 90 100 POWER (% RATED) o&

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CORE OPERATING LIMITS REPORT Figure 8 Flow Dependent MCPR Limits l

(MCPR )r l

(Reference 8, Section 5.4.3, Figure 5-8) 1.8 FOR Wc (% RATED CORE FLOW) <40%

FOR We (% RATED CORE FLOW)240%

1.7 MCPR(F) = (ApWc /100 + Bp)

MCPR(F) = MAX (1.20 Ap We /100+Bp)

[1 > 0.0032 (40-Wc)}

MAX FLOW AF BF l

117.0

-0.632 1.809 112.0

-0.602 1.747 1'6 107.0

-0.586 1.697 j

102.5

-0.571 1.655 1.5 MAXIMUM FLOW RATE = 117.0%

C 112.0 %

l E

107.0 %

l

/ 102.5 %

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1.3 1.2 I

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1.1 20 30 40 50 60 70 80 90 100 110 120 CORE FLOW (% RATED) l

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CORE OPERATING LIMITS REPORT Figure 9 Minimum Critical Power Ratio (MCPR) versus Tau (based on tested measured scram time as defined in Reference 7), GE 8x8 NB Fuel 1.30 1.29 1.28 1.27 1.26 l

[

1.25 o2 1.24 1.23 -

unummmmmm-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

l TAU l

l Exposure Range: BOC17 to EHFPl7 - 2205 mwd /MT J

Cycle 17 06/07/96 1

CORE OPERATING LIMITS REPORT Ficure 10 Minimum Critical Power Ratio (MCPR) versus Tau (based on tested measured scram time as defined in Reference 7), GE 8x8 NB Fuel 1.30 i

1.29 1.28 1.27 1.26 1.25 03 1'24

/

l 1.23 l

1.22 1.21 l

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 Range: EHFPl7 - 2205 mwd /MT to EOC17 4

?

Cycle 17 06/07/96

CORE OPERATING LIMITS REPORT Figure 11 Minimum Critical Power Ratio (MCPR) versus Tau with One Turbine Bypass Valve Unavailable (based on tested measured scram time as defined in Reference 7), GE 8x8 NB Fuel 1.30 1.29 1.28 1.27 1.26

[

1.25 p

s 1.24 y

1.23 1.22 M 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 Range: BOC17 to EOC17 Cycle 17

-15 06/07/96

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