ML20094G876

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Core Operating Limits Rept
ML20094G876
Person / Time
Site: Cooper Entergy icon.png
Issue date: 11/09/1995
From:
NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20094G872 List:
References
NUDOCS 9511130242
Download: ML20094G876 (20)
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4 COOPER NUCLEAR STATION CORE OPERATING LIMITS REPORT 9511130242 951109 PDR ADOCK 05000298 11/09/95 P PDR

CORE OPERATING LIMITS REPORT LIST OF EFFECTIVE PAGES Page(s) Revision Date i through iv 4 11/09/95 1 through 14 4 11/09/95 1

-i- 11/09/95

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CORE OPERATING LIMITS REPORT E TABLE OF CONTENTS

- Li st o f Table s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iii i L i st o f Fi gures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i v 1.0 ' l.NT RO DU CTI ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 2.0 CO RE O P E RATING LI M ITS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 2.1 Rod Block Monitor Upscale Set Point . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 2.2 Averaue Planar Linear lleat Generation Limits . . . . . . . . . . . . . . . . . . . . . I 2.3 Linear IIeat Generation Rate Limit . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Minimum Critical Power Ratio Limits . . . . . . . . . . . . . . . . . . . . .... 2 2.4 3.0 RE F E R EN C E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 ii - 11/09/95

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CORE OPERATING LIMITS REPORT LIST OF TABLES Number Title Page 1 LilGR Limit 4 i

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CORE OPERATING LIMITS REPORT LIST OF FIGURES Number Title Page 1 Maximum Average Planar Linear IIeat Generation Rate 5 (MAPLliGR) versus Exposure with LPCI Modification and Bypass lloles Plugged,3.02% GE 8x8 NB Fuel 2 Maximum Average Planar Linear IIcat Generation Rate 6 (MAPLilGR) versus Exposure with LPCI Modification and i Bypass lloles Plugged,3.20% GE 8x8 NB Fuel 3 Maximum Average Planar Linear lleat Generation Rate 7 (MAPL 11GR) versus Exposure with LPCI Mod:fication and Bypass IIoles Plugged,3.48% w/l1GZ GE 8x8 NB Fuel 4 Maximum Average Planar Linear lleat Generation Rate 8 (MAPLIIGR) versus Exposure with LPCI Modification and Bypass lioles Plugged,3.48% w/12G7 GE 8x8 NB Fuel 5 Flow Dependent MAPL,liGR Factor (MAPFACr) 9 6 Power Dependent MAPLIIGR Factor (MAPFACp) 10 7 Power Dependent MCPR Limits, MCPRp and Kr 11 8 Flow Dependent MCPR Limits, MCPRr 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) i i

- iv - 11/09/95

1.0 INTRODUCTION

i 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 (APLHGR), Linear Heat Generation Rate (LilGR), and Minimum Critical Power Ratio (MCPR). If any of these limits are i exceeded, the action will be taken as dermed in the Technical Specifications. l 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. 1 i

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 Unseale 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 ilPSP 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 21.20. 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 Limits The limiting APLHGR value for the most limiting lattice (excluding natural uranium) 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 1 11/09/95 1

1 1

Figure 5, or the Power-Dependent MAPLIIGR Factor, MAPFACp from Figure 6.

APLilGR values were determined with the SAFFJREFLOOD LOCA methodology and are given in References 3 through 6, while the MAPFAC, and MAPFACp were i 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 APLIIGR (MAPLIIGR) value. Hence, these fuel bundles 4 have multiple MAPLHOR limiting values at a given planar exposure. The MAPLIIGR 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 MAPLilGR 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 Linear IIcat Generation Rate Limit 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 Li1GR; 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 (r), 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 (Kr) from Figure 7.

Technical Specification

Reference:

3.11.C 11/09/95 l

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

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3.0 REFERENCES

i i NEDE-24011-P-A-10, February 1991, General Electric Standard Application for Reactor 1.

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

i i

{ 2. Supplemental Reload Licensing Submittal for Cooper Nuclear Station Reload 16, Cycle 17, l

! 24A5187, Revision 1, November 1995.  :

I Letter No 262-95-182 from Ala Alzaben of General Electric to Gautam Sen of NPPD, for 3.

Cooper Nuclear Station Reload 16, Cycle 17, Lattice Dependent MAPLHGR, dated i September 15,1995.

I

. 4. NEDO-24N5, August 1977, Loss-of-Coolant Accident Analysis Report for Cooper Nuclear i i Power Station.
5. NEDE-24045P Supplement 1, December 1989, Loss-of-Coolant Accident Analysis Report

. for Cooper Nuclear Power Station.

6. NEDE-24045P Supplement 2, Loss-of-Coolant Accident Analysis Report for Cooper Nuclear 2

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.

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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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1 i

1 11/09/95

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

GE 8x8 NB (3.02%,

3.20%, and 3.48%) 14.4 1

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1 *

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CORE OPERATING LIMITS REPORT t i

Ficure 1

< l Maximum Average Planar Linear IIcat Generation Rate (MAPLIIGR) versus Exposure with LPCI Modification and Bypass lloles Plugged,3.02% GE 8x8 NB Fuel 16 14

/  %.

/ N

[s ii 10 3 w 5 N I '

N 6

N ,a 5

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

DATA COORDINATES (Reference 5)

Planar Ave. GWD/ST kW/Ft I 0.2 11.07 1.0 11.26 l 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 MAPLilGR 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

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

s w

^

g '

g 110F' N

g N

3

\

6

\ i2 5

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

DATA COORDINATES (Reference 5)

Planar Avg. GWD/SI 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 l 5.0 11.80  :

I 6.0 11.99 7.0 12.23 l

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 MAPLIIGR 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 l i

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I CORE OPERATING LIMITS REPORT Ficure 3 Maximum Average Planar Linear IIcat Generation Rate (MAPLiiGR) versus Exposure with LPCI Modification and Bypass lloles Plugged,3.48% w/l1GZ GE 8x8 NB Fuel 15 14 13 m' -,Q 11m-jV Q

, 10 l .

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N 1

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

DATA COORDINATES (Reference 6)

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 7.0 12.07 8.0 12.23 i 9.0 12.38 l 10.0 12.48 j 12.5 12.61 15.0 12.47 I I

20.0 11.79 25.0 11.05 35.0 9.69 45.0 7.86  ;

49.6 5.62 Note: When in single loop operation, a MAPLilGR factor of 0.75 is substituted for the LOCA analysis factors of 1.0 and 0.86 contained in the flow dependent MAPI HGR factor curves in Figure 5.

Cycle 17 11/09/95

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CORE OPERATING LIMITS REPORT 4
Ficure 4 Maximum Average Planar Linear lleat Generation Rate (MAPLIIGR) versus Exposure with LPCI Modification and Bypass lloles Plugged,3.48% w/12GZ GE 8x8 NB Fuel 15 I

14 1

9 13 l g # ' k l ], N m i g '* A i N I '

7 T

6 a S

0 10 20 30 40 50 60 PLANAR AVERAGE EXPOSURE (GWD/ST) 1' DATA COORDINATES (Reference 6)

Planar Ave. GWD/ST kW/Ft

! 0.0 10.89 O.2 10.94

! 1.0 11.05 l 2.0 11.19 j 3.0 11.34 4.0 11.49 l 5.0 11.64 i 6.0 11.50 7.0 11.97 8.0 12.14 9.0 12.31 i 10.0 12.49 j 12.5 12.52 15.0 12.23 20.0 11.53 l 25.0 10.86 35.0 9.60 45.0 7.75 49.0 5.83 1

i Note: When in single loop operation, a MAPLilGR 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 i in Figure 5.

, Cycle 17 11/09/95 4

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CORE OPERATING LIMITS REPORT

Figure 5 Flow Dependent MAPLHGR Factor (MAPFAC,)

4 (Reference 8, Section 5.4.4, Figure 5-9) l 1.0 -

l 1

- 0.9 -

& ___________ i.

6 yO

,,h+ f[\*

0.8 f

  1. 9*1 MAPLHGR(F) = MAPFACp+ MAPLHGRSTD 0 MAPLHGRSTD = STANDARD MAPLHGR LIMITS

. O I MAPFACp (F) = MINIMUM (1.0.p A g100 + Bp )

0.7 h WC= % RATED CORE FLOW g AND Ap Bp ARE FUEL TYPE DEPENDENT g CONSTANTS GIVEN BELOW.

O I GE FUELS

{3 0.6 UM CORE FLOW THROUGH GE11

(% RATED) Ap Bp 102.5 0.6784 0.4861 0.5 - 107.0 0.6758 0.4574 112.0 0.6807 0.4214 117.0 0.6886 0.3828 0.4 I I I I I I I 30 40 50 60 70 80 90 100 110 CORE FLOW (% RATED)

Cycle 17 11/09/95

CORE OPERATING LIMITS REPORT Figure 6 Power Dependent MAPLHGR Factor (MAPFAC,)

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

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u. 1.2 -

a.

1.0 -

0 I

E 0.8 -

0 I s50% CORE FLOW

$ f

( MAPLHGR, MAPFAC,eMAPLHGR sto 2 0.6 -- p MAPLHGR sto a STANDARD MAPLHGR UMITS h FOR 25%>P: NO THERMAL UMITS MONITORING REQUIRED 2 NO UMITS SPECIFIED Q roR 25% sP<30%

Z 0.4 -

80 + 0 005 (P-30%)

@ s > 50% CORE FLOW ,My,AC, o

Q*

MAPFAC, 0 50 + 0 005 (P 30%)

FOR>50% CORE FLOW FOR 30% s P:

O uAPrAC,-1.0 + 0 005224 (P.100%)

Q.

O i i i i e I i t 0 10 20 30 40 50 60 70 80 90 100 POVER (% RATED)

Cycle 17 11/09/95

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

I O

a

-4 2.60 2.40 -

8n OPERATING UMIT MCPR (P) = Kp* OPERATING LIMIT MCPR(100)

Q >50% FLOW ", FOR P<25%: NO THERMAL UMITS MONITORING REQUIRED m g eiv

~

g g NO UMITS SPECIFIED W O

! FOR 25%5Pc Pym: (%m=30%)

ON Kp = [K gyp + 0.026 (30% . P)]1 OLMCPR(100) $ Q aO KsYP

  • 183 FOR 5 50% CORE FLOW O ** T M' " M 2.00 i

a 227 FOR > 50% CORE FLOW

." mQ f  ! pop 3ag5p 4sg; go f

, Kp = 12S + 0 0134 (45% . P) m O nRy y d 7 5 50% FLOW".

FOR 45% SP< 60%:

Kp = 1.15 + 0 00067 (80% P) 7.

O D

[h So

  • 3

'A a

Z Q

FOR 60%5 P:

r 8, g a C y

4 g ,

T E <

) Kp = 1.0 + 0.00375 (100% - P)

  • - [vyac d H

e W

  • r5 m 3 1.40 - d6' C.
o. ~A m.,

5 O T

=j u h' O s & W e

v H

$ Q 1.20 2M O$

We 22 3.00 i i i i i i i 0 10 20 30 40 50 60 70 80 90 100 POWER (% RATED) o ,

k e

u

o; CORE OPERATING LIMITS REPORT Figure 8 Flow Dependent MCPR Limits (MCPRr)

(Reference 8, Section 5.4.3, Figure 5-8) 1.8 <-

FOR WC (% RATED CORE FLOW) <40% FOR We (% RATED CORE FLOW)240%

MCPR(F) = (Ap W C /100 + Bp ) . MCPR(F) = MAX (1.20

  • Ar %b /100+BF )

I'7 -

[1 + 0.0032 (40-WC)] 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 1.5 -

MAXIMUM FLOW RATE = 117.0%

C 112.0 %

E 107.0 % y b 102.5%

2 g,4 _

1.3 -

1.2 -

I I I I I I I I I 1.1 _

20 30 40 50 60 70 80 90 100 110 120 CORE FLOW (% RATED) a Cycle 17 11/09/95

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

{ 1.25 o

2 1.24

)

1.23 1.22 mummmmmum 1.21 1.20 l 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 EHFPl7 - 2205 mwd /MT l i

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l Cycle 17 11/09/95  !

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

1.30  :

1.29 1.28 1.27 1.26 1.25

[

o 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 Expc.;ure Range: EHFP - 2205 mwd /MT to EOC17 Cycle 17 14 I1/09/95

l LIST OF NRC COMMITMENTS l ATTACHMENT 3 l Correspondence No: NLS950186 The following table identifies those actions committed to by the District in this document. Any other actions discussed in the submittal represent intended or planned actions by the District. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Licensing Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.

COMMITTED DATE COMMITMENT OR OUTAGE None I

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l PROCEDURE NUMBER 0.42 l REVISION NUMBER 0.2 l PAGE 10 OF 16 l

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