ML20138F562

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Revised Cooper Nuclear Station Colr
ML20138F562
Person / Time
Site: Cooper Entergy icon.png
Issue date: 04/25/1997
From:
NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20138F559 List:
References
NUDOCS 9705060004
Download: ML20138F562 (21)
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l COOPER NUCLEAR STATION CORE OPERATING LIMITS REPORT i  ;

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9705060004 970429 PDR ADOCK 05000298

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CORE OPERATING LIMITS REPORT LIST OF EFFECTIVE PAGES Page(s) Revision Date 1 6 04/25/97 il and ill 5 04/25/95 IV 6 04/25/97 1 and 2 5 04/25/97 3 6 04/25/97 4 through 10 5 04/25/97 11 through 15 6 04/25/97 Cycle 18 i 04/25/97

4 CORE OPERATING LIMITS REPORT TABLE OF CONTENTS List of Tables . . .............. .................. .. .......... .. . . . . . . . . , , iii List of Figures . . . . . . . . . . . . . . . . . . . . . .......... .. ..... .............,,,,,,,,,,ly

1.0 INTRODUCTION

. ............................ ..... .... ....,,, ,,, ,,,,,1 2.0 CORE OPERATING LIMITS . . . . . ...,, ............ . ...... .........,,.... 1 ,

l 2.1 Rod Block Monitor Unscale Set Point . . . . , , . . . . . . . , , , , , , , . . . . , . . . , , . . . , , , , 1 i 2.2 Ayeraae Planar Linear Heat Generation Limits . , , . . . , , , , . . . , , . . . , , . . . .. 1 2.3 Linear Heat Generation Rate Limit . . . . . . . . . . . . . . . . . . . . . . ..............2 2.4 Minimum Critical Power Ratio Limits . . . . . . . . , , , , . . . . . . . . . , , , . , . , , , , , . , , , 2 3.0 RE F E R E N C E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...........-........ 3 1

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l. CORE OPERATING LIMITS REPORT

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1 j LIST OF TABLES I 1

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.1 LHGR Umit 4 l i l

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. . 1 CORE OPERATING LIMITS REPORT LIST OF FIGURES Number Title Page 1 Maximum Average Planar Linear Heat 5 Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged,3.20 w/o with 10GZ GE8x8NB Fuel l

2 Maximum Average Planar Linear Heat 6 I

Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and  !

Bypass Holes Plugged,3.48w/o with .

11GZ GE8x8NB Fuel  !

I 3 Maximum Average Planar Unear Heat 7 J Generation Rate (MAPLHGR) versus  !

Exposure with LPCI Modification and  !

Bypass Holes Plugged,3.48 w/o with 12GZ GE8x8NB Fuel 4 Maximum Average Planar Linear Heat 8 Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged,3.50 w/o with 10GZ GE8x8NB Fuel 5 Flow Dependent MAPLHGR Factor (MAPFAC,) 9 6 Power Dependent MAPLHGR Factor (MAPFACp) 10 7 Power Dependent MCPR Limits, MCPR, and Kp 11 8 Flow Dependent MCPR Limits, MCPR, 12 9,10 Minimum Critical Power Ratio (MCPR) versus 13,14 Tau (based on tested measured scram time as defined in Reference 7), GE8x8NB Fuel (various exposure ranges) 11 Minimum Critical Power Ratio (MCPR) versus 15 Tau with One Turbine Bypass Valve Unavailable (based on tested measured scram time as defined in Reference 7), GE8x8NB Fuel 4

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i Cycle 18 iv 04/25/97 l

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1.0 INTRODUCTION

1 This report provides the cycle-specific limits for operation of the Cooper Nuclear Station through Cycle 18. 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 is exceeded, 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 plant safety analysis limits are met.

2.0 CORE OPERATING LIMITS Cooper Nuclear Station shall operate within the bounds of the below limits. The applicable .

Technical Specifications are referenced in each subsection. I 2.1 Rod Block Monitor Uoscale Set Point l Technical Specification Table 3.2.C states that the Rod Block Monitor (RBM) upscale ]

(power referenced) trip level setting is determined from the following: i i

Low Trip Intermediate Trip High Trip Lowest Rated Set Point Set Point Set Point MCPR Limit: (LTSP) (ITSP) (HTSP)

(LPSPsP51 PSP) (IPSPSPSHPSP) (HTSPSP) 1 1.20 s 117.0/125 5 111.2/125 5 107.4/125 1 1 1.25 s 120.0/125 5 115.2/125 1 110.2/125 t 1.30 s 123.0/125 5 118.0/125 5 113.2/125 LPSP, IPSP and HPSP are the Low Power Set Point, intermediate Power Set Point and High Power Set Point, respectively, as listed in Technical Specification Table 3.2.C.

The lowest rated MCPR limit to be used with this table for Cycle 18 is 11.20. The trip level settings associated with this MCPR limit have been generically calculated and verified to bound the Rod Withdrawal Error Analysis for Cycle 18 operation.

Technical Specifications

Reference:

3.2.C 2.2 Averaae Planar Linear Heat Generation Limits The most limiting lattice APLHGR value (excluding natural uranium) for each fuel bundle as a function of Planar Average Exposure, core power and core flowis calculated by multiplying the value from Figures 1,2,3 and 4 by the smaller of the MAPLHGR Flow Factor, MAPFAC, (Figure 5) or the Power-Dependent MAPLHGR Factor, MAPFACp, (Figure 6). APLHGR values determined with the SAFE /REFLOOD LOCA methodology are given in References 3 through 6 while MAPFAC, and MAPFAC, were determined in Reference 8.

The fuel bundles referred to in Figures 1,2,3 and 4 consist of multiple combinations of enriched uranium and gadolinia filled lattices 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 Cycle 18 4/25/97

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

information by General Electric and are given in Reference 3 as a function of planar l average exposure.

i i The MAPLHGR limits referred to above are for two recirculation loop operations. For i single loop operation, the limiting APLHGR value is obtained per Reference 6, as explained in the note at the bottom of Figures 1 through 4.

i Technical Specification

Reference:

3.11.A l e  !

2.3 Linear Heat Generation Rate Limit J

The limiting power density and maximum allowable Linear Heat Generation Rate (LHGR) i referred to in Technical Specification Sections 1.0.A.4 and 3.11.B is 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 i CNS Procedure 10.9, Control Rod Scram Time Evaluation; the OLMCPR values are as j follows:

4 4 2.4.1 For core thermal power 125 percent and < 30 percent of rated power, the OLMCPR is equal to the power dependent MCPR (MCPR,) from Figure 7.

I 2.4.2 For core thermal power 130 percent of rated power, the OLMCPR is the greater of either:

i l' 2.4.2.1 The applicable flow dependent MCPR (MCPR,) determined from Figure 8,or 2.4.2.2 The appropriate scram time (T) dependent MCPR at rated power from l Figures 9 and 10, multiplied by the applicable power dependent MCPR l multiplier (K,) from Figure 7.

Technical Specification

Reference:

3.11.C Cycle 18 4/25/97

3.0 REFERENCES

1. NEDE-24011-P-A-13, August 1996, General Electric Standard Application for Reactor Fuel.

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

2. Supplemental Reload Ucensing Report for Cooper Nuclear Station Reload 17, Cycle 18, 24A5399, Revision 0.

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3. Lattice Dependent MAPLHGR Report for Cooper Nuclear Station Reload 17, Cycle 18, 24A5399AA, Revision O.

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

S. NEDE-24045P Supplement 1, December 1989, Loss-of-Coolant Accident Analysis Report for l Cooper Nuclear Power Station. l

6. NEDE-24045P Supplement 2, Loss-of-Coolant Accident Analysis Report for Cooper Nuclear Power Station Reload 15, Cycle 16, March 1993. I
7. Letter (with attachment), R. H. Buckholz (GE) to P. S. Check (NRC) dated September 5,1980, i Response to NRC Request for information on ODYN Computer Model. i
8. NEDC-31892P, Revision 1, May 1991, Extended Load Line Umit and ARTS Improvement )

Program Analyses for Cooper Nuclear Station Cycle 14.

Cycle 18 4/25/97

_ . . _ . _ _ . . . _ . . _ . - . - . _ . _ _ _ . . _ . _ - - . . . _ . . . _ . . _ __.__.....__._-.....__...,_._____._m.

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CORE OPERATING LIMITS REPORT Table 1 l t

i LHGR Umit Fuel Type LHGR Limit (kW/ft) i GE 8x8 NB (3.20%, l 3.48% and 3.50%) 14,4 l

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CORE OPERATING LIMITS REPORT Figure 1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged,3.20 w/o with 10GZ GEBx8NB Fuel 15 14  ;

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5 0 10 20 30 40 50 PLANAR AVERAGE EXPOSURE (GWCWST)

DATA COORDINATES (Reference 3)

Planar Averaae Exoosure MAPLHGR (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 1 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 i 35.0 10.25 l 45.0 8.44 l 50.0 5.90 l NOTE
When in single loop operation, a MAPLHGR factor of 0.75 is substituted for the LOCA analysis i factors of 1.0 and 0.86 contained in the flow dependent MAPLHGR factor curves in Figure 5.

Cycle 18 4/25/97 N

l CORE OPERATING LIMITS REPORT l Figure 2 I

l Maximum Average Planar Linear Heat Generation Rate (M APLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged,3.48 w/o with 11GZ GEBx8NB Fuel i

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, PLANAR AVERAGE EXPOSURE (GWDfST)

DATA COORDINATES (Reference 3)

Planar Averaae Exoosure MAPLHGR l (GWD/ST) (kW/ft) I 0.0 10.85 l 0.2 10.90 1.0 11.01 2.0 11.17 1 3.0 11.36 l 4.0 11.56 5.0 11.76 l 6.0 11.91 1

7.0 12.07 ,

l 8.0 12.23 l 9.0 12.38 10.0 12.48 l 12.5 12.61 15.0 12.47 l

20.0 11.79 i 25.0 11.05 l 35.0 9.69 45.0 7.86 50.0 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 5.

Cycle 18 4/25/97 1

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s l CORE OPERATING LIMITS REPORT ,

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Figure 3 1

Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) I versus Exposure with LPCI Modification and Bypass Holes Plugged,3.48 w/o with 12GZ GE8x8NB Fuel i

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5 0 10 20 30 40 50 PLANAR AVERAGE EXPOSURE (GWDIST) 1 DATA COORDINATES (Reference 3)

Planar Averaae Exoosure MAPLHGR (GWD/ST) (kW/ft) 0.0 10.89 1 0.2 10.94 I 1.0 11.05 i 2.0 11.19 i 3.0 11.34 4.0 11.49 i 5.0 11.64 1 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 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 18 4/25/97

s CORE OPERATING LIMITS REPORT Figure 4 Maximum Average Planar Linear Heat Generation Rate (M APLHGig versus Exposure with LPCl Modification and Bypess Holes Plugged,3.50 w/o with 10GZ GEBx8MB Fuel ,

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p 5 I O 10 20 30 40 50 PLANAR AVERAGE EXPOSURE (GWDfST) f DATA COORDINATES (Reference 3)

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Plariar Averaae Exoosure MAPLHGR ,

(GWD/3T) (kW/ft) .

0.0 11.59 0.2 11.63 1.0 11.71 2.0 11.85 3.0 12.00 4.0 12.13 5.0 12.26 t 6.0 12.38  !

7.0 12.52 8.0 12.65 9.0 12.80 10.0 12.84 6 12.5 12.81 i 15.0 12.52 [

20.0 11.78 25.0 11.05 35.0 9.75 45.0 7.96 NOTE: When in single loop operation, a MAPLHGR factor of 0.75 is substituted for the LOCA analysis I factors of 1.0 and 0.86 contained in the flow dependent MAPLHGR factor curves in Figure 5.

1 Cycle 18 4/25/97

, CORE OPERATING LIMITS REPORT Fiaure 5 Flow Dependent MAPLHGR Factor 1

(MAPFACr)

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

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0.8 -

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MAPLHGR(F) = MAPFACp- MAPLHGRSTD MAPLHGRSTD = STANDARD MAPLHGR LIMITS )

I MAPFACp (F) = MINIMUM (1.0. A pCW /100 + Bp )

h WC= % RATED CORE FLOW g8 AND Ap By ARE FUEL TYPE DEPENDENT g CONSTANTS GIVEN BELOW:

O 5 0.6 GE FUELS MAXIMUM THROUGH GE11 CORE FLOW

(% 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

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

Cycle 18 4/25/97

CORE OPERATING l.lMITS REPORT Fiaute 6 Power Dependent MAPLHGR Factor (MAPFACp)

(Reference 8, Section 5.4.2, Figure 5-7) 1 O

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p l MAPU1GR am e STANDARD MAPLNGR UMITS h FOR 25%>P; NO THERMAL UMITS MOMTORING REQUIRED 2 NO UMITS SPECIFIED Q FOR 25% s P<30%

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Q. s > $0% CORE FLOW FOR s 50% CORE FLOW i

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O 10 20 30 40 50 60 70 80 90 100 POWER (% RATED) l Cycle 18 4/25/97

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  • OPERATING UMIT MCPR (P) = Kp* OPERATING UMIT MCPR(100)
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FOR P<25%: NO THERMAL LIMITS MONfTORfNG REQUIRED C v, NO UMITS SPECIFIED l m

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  • 183 FOR 5 50% CORE FLOW' 8 g O Ek e 2.27 FOR > 50% CORE FLOW @ T 2 00 a mO m  :

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550% FLOW l KP= 1.15 + 0 00867 (80% - P)

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l FOR80%5P: .*a O y i e Kp = 1.0 + 0.00375 (100% - P) -

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h Flow Dependent MCPR Limits t (MCPR,)

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

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  • l MAXIMUM FLOW RATE FOR We (% RATED CORE FLOW) t 40% i

. MCPR(F) = Max (1.20, A,We/100 + B,)

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117.0 -0.632 1.809 j 112.0 0.602 1.747 102. M

, 107.0 0.586 1.697 4' 102.5 -0.571 1.655 c 1.5

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O FOR We (% RATED CORE FLOW) < 40% ,

MCPR(F) = (A,Wc/100 + B,)

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I 1 20 30 40 50 60 70 80 90 100 110 120 CORE FLOW (% RATED) i n.

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l CORE OPERATING LIMITS REPORT l Fiaure 9 4

i Minimum Critical Power Ratio (MCPR) versus Tau (based on tested measured scram time as defined in Reference 7), GE 8x8 NB fuel i

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. Exposure range: BOC18 to EHFP18 - 2205 mwd /MT i

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Cycle 18 4/25/97 l

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

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1.21 1.2 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Tau i

Exposure range: EHFP18 - 2205 mwd /MT to EOC18 Cycle 18 4/25/97

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CORE OPERATING LIMITS REPORT Fiaure 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 i 1

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l 1.22 1.21 1.2 0 0.1 02 0,3 0.4 0.5 0.6 0.7 0.8 0.9 1 i Tau l Exposure range: BOC18 to EOC18 s

1 Cycle 18 4/25/97

l ATTACHMENT 3 LIST OF NRC COMMITMENTS l Correspondence No: NLS970072 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 4

f l PROCEDURE NUMBER 0.42 l REVISION NUMBER 4 l PAGE 8 v7 9 l

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