ML20237E777

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Revised COLR Cycle 18 for Cooper Nuclear Station
ML20237E777
Person / Time
Site: Cooper Entergy icon.png
Issue date: 08/20/1998
From: Black T, Lewis J, Moncil J
NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20237E737 List:
References
NUDOCS 9809010167
Download: ML20237E777 (21)
v • d • e


Text

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COOPER NUCLEAR STATION l

l CORE OPERATING LIMITS REPORT Cycle 18-l 9809010167 980820 PDR ADOCK 05000298  !

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Revision 7

,- .- CORE OPERATING LIMITS REPORT List of Effective Pages j

Pace (s) Revision Date i 7 08/05/98 ii 7 08/05/98 iii 6 08/05/98 1 0 08/05/98 2-4 6 08/05/98 5 7 08/05/98 l

6-9 6 08/05/98  !

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10-13 5 04/25/97 {

14-15 7 08/05/98 i

16 6 04/25/97 17 0 08/05/98 I

Cycle 18 i 08/05/98

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Revision 7

.- .- CORE OPERATING LIMITS REPORT Table of Contents List of Figures . . ... . .. . . . . . . . iii 1.0 Introduction . .... . .. . ,... .. . .. . . . 2 2.0 Core Operating Limits . . . . . . . . . . ., .... . .. . .2 2.1 Rod Block Monitor Upscale Set Point . . . . . . 2 2.2 Average Planar Linear Heat Generation Limits . . . . . . . . . . . . . . , ...3 2.3 Minimum Critical Power Ratio Limits. . ... .. . .3 2.4 Power to Flow Map . . . . . . . . . . . . . . ... ... .. . 4 3.0 References . . . ., .. . . . .. .. . . ..... ... 5 1

l 9

Cycle 18 il 08/05/98 l l

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l R; vision 6 CORE OPERATING LIMITS REPORT I

List of Figures Number Title '

Pace i Maximum Average Planar Linear lleat Generation Rate (MAPLHGR) 6 versus Exposure with LPCI Modification and Bypass Holes Plugged, 3.2 w/o with 10GZ GF8x8ND Fuel 2 Maximum Average Planar Linear lleat Generation Rate (MAPLilGR) 7 versus Exposure with LPCI Modification and Bypass lloles Plugged, i 3.48 w/o with llGZ GE8x8NB Fuel l 3 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) 8 I versus Exposure with LPCI Modification and Bypass Holes Plugged 3.48 w/o with 12GZ GE8x8NB Fuel 4 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) 9 i versus Exposure with LPCI Modification and Bypass Holes Plugged

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3.50 w/o with 10GZ GE8x8NB Fuel '

5 Flow Dependent MAPLHGR Factor (MAPFACr) 10 6 Power Dependent MAPLHGR Factor (MAPFACp) 11 7 Power Dependent MCPR Limits, MCPRp and Kp 12 8 Flow Dependent MCPR Limits, MCPRr 13 9,10 Minimum Critical Power Ratio (MCPR) versus Tau (based on tested 14,15 measured scram time as defined in Reference 8), GE8x8NB Fuel (various exposure ranges) 11 Minimum Critical Power Ratio (MCPR) versus Tau with One Turbine 16 Bypass Valve Unavailable (based on tested measured scram time as defined in Reference 8), GE8x8NB Fuel 12 CNS Power / Flow Map 17 1

1 Cycle 18 iii 08/05/98 I l

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Cycle 18 1- 08/05/98

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1.0 INTRODUCTION

I . .

The Core Operating Limits Report provides the limits per cycle for operation of the Cooper Nuclear Station through Cycle 18. It includes the limits for the Rod l Block Monitor Upscale Set Point, Average Planar Linear Heat Generation Rate (APLHOR), and Minimum Critical Power Ratio (MCPR.) If any of these limits is exceeded, action will be taken as defined in the Improved Technical Specifications.

l The core operating limit values have been determined using the NRC-approved methodologies given in References 1,2,10, and 11 and have been established such that all applicable plant safety analysis limits are met.

i 2.0 CORE OPERATING LIMITS Cooper Nuclear Station shall operate within the bounds of the below limits / values. The applicable Improved Technical Specifications are referenced in each subsection.

2.1 Rod Block Monitor Unscale Set Point The Improved Technical Specifications reficct a reference to Allowable Values for the Rod Block Monitor (RBM) upscale (power referenced) trip level setting, found in Reference 9, are as follows:

Lowest Rated Low Trip Set Intermed Trip Set High Trip Set MCPR Limit Point (LTSP) Point (ITSP) Point (HTSP_)

(LPSPsPslPSP) (IPSPsPsHPSP) (HPSPsP) 21.20 s114.0/125 s108.5/125 s104.5/125 21.25 s117.0/125 s112.5/125 s107.5/125 21.30 s120.0/125 s115.0/125 s110.5/125 LPSP, IPSP, and HPSP are the Low Power Set Point, Intermediate Power Set Point, and High Power Set Point, respectively.

The trip level settings associated with this MCPR limit have been generically calculated and verified to bound the Rod Withdrawal Error l Analysis for Cycle 18 operation. ,

l improved Technical Specification

Reference:

3.3.2.1 l l Cycle 18 Revision 6 -2 08/05/98

( ,

2.2 Averane Planar Linear IIcat Generation Limits The most limiting lattice APLHGR value (excluding natural uranium) for each fuel bundle as a function of Planar Average Exposure, core power, l and core flow is calculated by multiplying the value from Figures 1,2,3, and 4 by the smaller of the MAPLHGR Flow Factor, MAPFACr (Figure

5) or the Power-Dependent MAPLHGR Factor, MAPFACr, (Figure 6).

APLHGR values determined with the SAFER /GESTR-LOCA methodology are given in References 2,3, and 5 while M APFACr and MAPFACp were detennined in Reference 8.

The fuel bundles referred to in Figures 1,2,3, and 4 consist of multiple combinations of enriched uranium and gadolinium 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 MAPLHOR 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 3 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 multiplied by 0.77 for GE8x8 NB fuel. l Improved Technical Specification

Reference:

3.2.1 l 2.3 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 as follows:

For core thermal power 2 25 percent and <30 percent of rated power, the OLMCPR is the power dependent MCPR (MCPRp) from Figure 7.

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

Cycle 18 Revision 6 -3 08/05/98

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The applicable flow dependent MCPR (MCPRr) determined from Figure 8,or The appropriate scram time (t) dependent MCPR at rated power from Figures 9 and 10, multiplied by the applicable power dependent MCPR .

, multiplier (Kp) from Figure 7. I

(

Improved Technical Specification

References:

3.2.2 and 3.7.7 l 12.4 Power / Flow Man l

The power / flow map defining the Stability Exclusion Region can be found as Figure 12.' References 5 and 6 reflect the documents describing the

. current Cooper Nuclear Station power / flow map.

Improved Technical Specification

Reference:

3.4.1 l l

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l Cycle 18 Revision 6 4 08/05/98

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3.0 REFERENCES

I. NEDE-240l l-Y-A-13-US, August 1990, General Elearic Standard Applicationfor Reactor Fuel.

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

2. NEDC-32687P, Revision l, March l997, Cooper Nuclear Station SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis.
3. Lattice Dependent AIAPLilGR Reportfor Cooper Nuclear Station Reload 17, Cycle 18, 24A5399AA, Revision 0.
4. Letter (with attachment), R.H. Buckholz (GE) to P.S. Check (NRC) dated September 5,1980, Response to NRC Requestfor Information on ODYN Computer Afodel. l l
5. Supplemental ReloadLicensing Reportfor Cooper Nuclear Station Reload 17, Cycle 18, 24A5399, Revision 2,
6. GENE-A I3-00395-01, Class I, November,1996, Application ofthe " Regional Exclusion with Flow-Biased APRhiNeutron Flux Scram " Stability Solution (Option I-D) to the Cooper Nuclear Station, Licensing Topical Report.
7. Letter from James R. Hall (NRC) to G. R. Horn (NPPD) dated September 23,1997, Approval of SAFER /GESTAR LOCA Analysisfor Cooper Nuclear Station (TACNO. A198293.)
8. NEDC-31892P, Revision 1, May 199 l, Extended Load Line Limit and ARTSImprovement Program Analysisfor Cooper Nuclear Station, Cycle 14.
9. NEDC 98-024, Revision 1, July 1998, APRAI- RBAISetpoint Calculation.
10. NEDO-31960-A and NEDO-31960-A Supplement 1. BWR Owner's Group Long-Term Stability Solutions Licensing Afethodology.

(The approved revision at the time the reload analysis is performed.)

11. NEDE-23785-1-P-A, The GESTR-LOCA andSAFER Sfodelsfor the Evaluation ofthe Loss-of-Coolant Accident, Volume 111, Revision 1, October 1984.

Cycle 18 Revision 7 08/05/98 l

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 GE8x8NB Fuel 15 _. .._ __ ___

14 _ _1_..._. ._,.. . . - _ . _ . _

E 13 - _ _ - - . . _ . . . _ _ _

3 12 _ #.._. g . _ . _ _ _ _ . . . . _

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. g *' p 5

i 8

6 5 5

0 10 20 30 40 50 PLANAR AVERAGE EXPOSURE (GWIVST)

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 6.0 11.99 7.0 12.23 ,

8.0 12.38 I 9.0 12.52 l 10.0 12.64 j 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 I

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CORE OPERATING LIMITS REPORT Figure 2 Maximum Average Planar Linear Heat Generation Rate (M APLHGR) versus Exposure with LPCl Modification and Bypass Holes Plugged,3.48 w/o with 11GZ GEBx8PE Fuel 15 __. . . - _ .. -_. __.._.- ._ _ _ _ _ _

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0 10 20 30 40 50 PLANAR AVERAGE EXPOSURE (GWEVST)

DATA COORDINATES (Reference 3)

Planar Averaae Exoosure MAPLHGR (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 1 8.0 12.23 9.0 12.38 10.0 12.48 12.5 12.61 15.0 12.47 20.0 11.79

l. 25.0 11.05 1

35.0 9.69 ,

45.0 7.86 50.0 5.83 Cycle 18 Revision 6 08/05/98 j:

CORE OPERATING LIMITS REPORT Figure 3 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCl Modification and Bypass Holes Plugged,3.48 w/o with 12GZ GE8x8NB Fuel 15 - . _ _ . - - _ _ , . _ . . .

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5 1 0 10 20 30 40 50 PLANAR AVERAGE EXPOSURE (GWDfST)

DATA COORDINATES (Reference 3)

Planar Averaae Exoosure MAPLHGR (GWD/ST) (kW/ft) 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 l

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Cycle 18 Revision 6 l

CORE OPERATING LIMITS REPORT Figure 4 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged,3.50 w/o with 10GZ GE8x8NB Fuel 15 __ _ _ . _ _ . _ _ - -

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0 10 20 30 40 50 PLANAR AVERAGE EXPOSURE (GWtyST)

DATA COORDINATES (Reference 3)

Planar Averace Exoosure MAPLHGR (GWD/ST) (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 6.0 12.38 7.0 12.52 8.0 12.65 9.0 12.80 10.0 12.84 12.5 12.81 15.0 12.52 20.0 11.78 25.0 11.05 35.0 9.75 ,

45.0 7.96 Cycle 18 Revision 6 08/05/98

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CORE OPERATING LIMITS REPORT Fiaure 5 Flow Dependent MAPLHGR Factor

, (MAPFACr) l 1 (Reference 8, Section 5.4.4, Figure 5-9) {

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\q l* MAPLHGR(F) = MAPFACp. MAPLHGRSTD MAPLHGRSTD = STANDARD MAPLHGR LIMITS I MAPFACp (F) = MINIMUM (1.0. A pCW /100 + Bp) h WC= % RATED CORE FLOW g AND Ap Bp ARE FUELT(PE DEPENDENT 1 g CONSTANTS GIVEN BELOW: j O

GE FUELS 5 0.6 THROUGH GE11 a WI UM h CORE FLOW Ap Bp )

(% RATED) 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 ,

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

Cycle 18 Revision 5 04/25/97

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CORE OPERATING LIMITS REPORT >

Fiaure 6 Power Dependent MAPLHGR Factor (MAPFAC,)

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

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-I s50% CORE FLOW Y l MAPLHGR, a MAPFAC,* MAPuiGR em 0.3 -- ,,,,- MAPLHGRsm STANDARD MAPLHGR UMITS I"

FOR 25%>P: NO THERAkAL UMITS MONITORING REQUIRED 2 NO UMITS SPEOFIED O -

FOR 25% 5P<30%:

Z 0.4 -

W MAPFAC, =0.60 + 0.005 (P 30%)

O. # > 50% CORE FLOW FOR 5 60% CORE FLOW W

O e MAPFAC, 0.50 + 0.005 (P-30%)

FOR*50% CORE FLOW i

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

l . Cycle 18 Revision 5 04/25/97 ,

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a CORE OPERATING LIMITS REPORT

,. ,. Fiaure 8 Flow Dependent MCPR Limits (MCPR,)

(Reference 8, Section 5.4.3, Figure 5-8) 1.8 MAXIMUM FLOW RATE FOR We (% RATED CORE FLOW)140%

g MCPR(F) = Max (1.20, A,We/100 + Br) 112 00% MAX FLOW AF 1 1.6 _ 107.00 % -117.0 -0.632 1.809 112.0 -0.602 - 1.747 102.M 107.0 4 586 1.697 102.5 -0.571 1.655

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

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

  • 2 1.4 - 0 0 +0.0032(40-Wc)]

1.3 -

. 1.2 -

1.1 . . . . . . . . .

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

Cycle 18 Revision 5 04/25/97 ,

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CORE OPERATING LIMITS REPORT

.- .- Fiaure 9 Minimum Cotical Power Ratio (MCPR) versus Tau (based on tested measured scram time as defined in Reference 4), GE 8x8 NB fuel 1.3 1.29 __.

7 1.28 1.27 1.26 a:

h 1.25 t lE 1.24 1.23 1.22 _ . . _ _ . _ . _ _ _ _

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 Exposure range: BOC18 to EHFP18 - 2205 mwd /MT Cycle 18 Revision 7 08/05/98 i

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l CORE OPERATING LIMITS REPORT I

.' . Fiaure 10 )

Minimum Critical Power Ratio (MCPR) versus Tau (based on tested measured scram time as defined in Reference 4), GE 8x8 NB Fuel i

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1.3 i

i 1.29 . -.

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l' 1.2 O 0.1 02 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 l

Tau Exposure range: EHFP18 - 2205 mwd /MT to EOC18 Cycle 18 Revision 7

-15 08/05/98

CORE OPERATING LIMITS REPORT

Eigure 11 Minimum Critical Power Ratio (MCPR) versus Tau with One Turbine Bypass Valve Unavailable (based on tested measured scram time as defined in Reference 4), GE 8x8 NB Fuel 1.3 i

1.29 - . _ _ _ _

1.28 _ _ _ ._

l 1.27 1.26 I

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1.23 1.22 .. - - - - - . _ _~

1.21 _ _ . . _ _ _ l I

1 1.2 ,

1 0 0.1 0.2 0.3 0.4 05 0.6 0.7 0.8 0.9 1 Tau

! I Exposure range: BOC18 to EOC18 l Cycle 18 Revision 6 04/25/97

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< = s CORE OPERATING LIMITS REPORT Fiaure 12 140 APRM Scram Line

, (108/100) 100 APRM Rod Block 80- -

[

N Rated rod line 60 40 Min pump, speed Natural 20 cuculation ,

i o_ i i i i 0 20 40 60 80 100 120 Core Flow (% ofrated)

I W-W, f W-W, '

2 W.-W, (W,-We p,p P[

tPas Coortlinates of Exclusion Region Boundary Point # Power (%) Flow (%)

P = a core thermal power value on the Exclusion Region boundary (% of rated), A 75.4 43.8 W = the core flow rate corresponding to power, P, on the Exclusion Region boundary B 36.3 30.0

(% of rated),

Pa = core thermal power at State Point A (% of rated),

Po = core thermal power at State Point B (% of rated),

Wa = core flow rate at State Point A (% of rated).

W e= core flow rate at State Point B (% of rated),

Cycle 18 Revision 0 08/05/98 1

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