ML20196C424

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Rev 1 to Cooper Nuclear Station COLR Cycle 19
ML20196C424
Person / Time
Site: Cooper Entergy icon.png
Issue date: 11/20/1998
From:
NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20196C404 List:
References
NUDOCS 9812020049
Download: ML20196C424 (20)
v • d • e


Text

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2 COOPER NUCLEAR STATION CORE OPERATING LIMITS REPORT Cycle 19 Revision 1 4

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l, . . CORE OPERATING LIMITS REPORT Table ofContents ,

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b List of Figures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ii  ;

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t l Signature Page . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1  :

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i 1.0 In'roduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 l 2.0 Core Operating Limits . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2  !

I 2.1 Rod Block Monitor Upscale Set Point . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2  !

, 2.2 Average Planar Linear Heat Generation Limits . . . . . . . . . . . . . . . . . . . . . . . . 3 i 2.3 Linear heat Generation Rate Limit . . . . . . . . . . . . . . . . . . . . . . . . . . ........ 3 .

r T

Minimum Critical Power Ratio Limits. . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . 3-4 2.4 l 2.5 Power to Flow Map . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . 4 ,

! 3.0 References...................................................................... .....5 i t

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! Cycle 19, Revision 1 i l l

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CORE OPERATING LIMITS REPORT  ;

List ofFigures ,

i Number Title Py 1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) 6 [

versus Exposure with LPCI Modification and Bypass Holes Plugged, 3.50 w/o with 10GZ GE8x8NB Fuel  ;

i 2 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) 7 versus Exposure with LPCI Modification and Bypass Holes Plugged, 3.50 w/o with 10GZ1 GE8x8NB Fuel i 3 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) 8 versus Exposure with LPCI Modification and Bypass Holes Plugged 3.48 w/o with 1IGZ GE8x8NB Fuel 1 4~ Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) 9  !

versus Exposure with LPCI Modification and Bypass Holes Plugged  ;

3.48 w/o with 12GZ GE8x8NB Fuel l 5 Flow Dependent MAPLIIGR Factor (MAPFACr) 10 6 Power Dependent MAPLHGR Factor (MAPFACr) 11 7 Power Dependent MCPR Limits, MCPR, and Kr 12 8 Flow Dependent MCPR Limits, MCPRr 13 9,10 Minimum Critical Power Ratio (MCPR) versus Tau (based on tested 14,15 f measured scram time as defined in Reference 4), GE8x8NB Fuel i (various exposure ranges) 11 Minimum Critical Power Ratio (MCPR) versus Tau with One Turbine 16 l Bypass Valve Unavailable (based on tested measured scram time as  !

defined in Reference 4), GE8x8NB Fuel q 12 CNS Power / Flow Map 17 l

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Cycle 19, Revision 1 ii l

S'ignature Page Revision 1 l

Pre , - Ea k Lk.n Print

A GLAPsohdin M ~ ~ Sign /Dple / /

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Reviewer: M Print

/ b 1. MM Sign /Date

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RE Supervisor: / . e u.) i S

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Cycle 19, Revision 1 l 1

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1.0 INTRODUCTION

The Core Operating Limits Report provides the limits for operation of the Cooper

. Nuclear Station for Cycle 19. It includes the limits for the Rod Block Monitor i Upscale Set Point, Average Planar Linear Heat Generati6n Rate (APLHGR), and i Minimum Critical Power Ratio (MCPR.) If any of these limits is exceeded, action will be taken as defined in the Technical Specifications.

i  !

The core operating limit values have been detemiined using the NRC-approved I

{ methodologies given in References 1,2,10, and 11 and have been established

such that all applicable plant safety analysis limits are met.

2.0 CORE OPERATING LIMITS 1

Cooper Nuclear Station shall operate within the bounds of the below limits / values. The applicable Technical Specifications are referenced in each subsection. r 4

2.1 Rod Block Monitor Upscale Set Point j

1 The Technical Specifications reflect 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)

e (LPSPsPsIPSP) (IPSP<PsHPSP) (HPSP<P) l 21.20 si14.0/125 s108.5/125 s104.5/125 j 21.25 5117.0/125 5112.5/125 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 Analysis for Cycle 19 operation. ,

Technical Specification

Reference:

3.3.2.1 1

Cycle 19, Revision 1 l l

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2.2 Average 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 flow is calculated by multiplying the value fmm Figures 1,2,3, and 4 by the smaller of the MAPLHGR Flow Factor, MAPFACp (Figure

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

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

The calculated maximum APLHGR (MAPLHGR) limits in Figures 1, 2, 3, and 4 calculated maximum APLHGR (MAPLHGR) are conservative values bounding all fuel lattice types (excluding natural uranium) in a given fuel bundle design. MAPLHGR limits for each individual fuel lattice design in a bundle design, as a function of axial location and average planar exposure, are determined based on the approved methodology referenced in Technical Specification 5.6.5 and loaded in the process computer for use in core monitoring calculations. 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 Reference 3 as a function ofplanar 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, as can be found in Reference 5.

Technical Specification

Reference:

3.2.1 2.3 Linear Heat Generation Rate Limit The limiting power density and maximum allowable Linear Heat Generation Rate (LHGR) referred to in Technical Requirements Manual l Section T 3.2.1 is the design LHGR. The design LHGR for fuel type GE 8x8 NB is 14.4 kW/ft as found in Reference 12.

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 as follows:

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

Cycle 19, Revision 1 l

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For core thermal power 230 percent of rated power, the OLMCPR is the greater ofeither:

The applicable flow dependent MCPR (MCPRF) determined from Figure 8,or .

l The appropriate scram time (t) dependent MCPR at rated power from j Figures 9 and 10, multiplied by the applicable power dependent MCPR l multiplier (Kr) from Figure 7.

The appropriate scram time (t) dependent MCPR at rated power with One  !

Tmbine Bypass Valve Unavailable is shown in Figure 11. .

l The system response time for the Turbine Bypass System to be at 80% of  !

rated bypass flow is 0.3 seconds.

)

For single recirculation loop operation, the OLMCPR is 0.01 greater than the two recirculation loop operation OLMCPR.

i Technical Specification

References:

3.2.2,3.4.1 and 3.7.7 2.4 Power / Flow Map 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.  !

Technical Specification

Reference:

3.4.1 i

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' Cycle 19, Revision 1 l

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3.0 REFERENCES

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

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

2. NEDC-32687P, Revision 1, March 1997, Cooper Nuclear Station SAFER /GESTR-LOCA Loss-of-CoolantAccidentAnalysis.
3. Lattice Dependent MAPLHGR Reportfor Cooper Nuclear Station Reload 18 Cycle 19, J11-03354-10M, Revision 0.
4. Letter (with attachment), R.H. Buckholz (GE) to P.S. Check (NRC) dated September 5,1980, Response to NRC Requestfor Infonnation on ODYN Computer Model.
5. Supplemental Reload Licensing Reportfor Cooper Nuclear Station Reload 18, Cy cle 19, J11-03354-10, Revision 0.
6. GENE-A13-00395-01, Class I, November,1996, Application ofthe "Regroual Exclusion with Flow-Biased APRMNeutron Flux Scram " Stability Solution (Option I-D) to the Cooper Nuclear Station, Licensing TopicalReport.
7. Letter fron James R. Hall (NRC) to G. R. Horn (NPPD) dated September 23,1997, Appmvalof SAFER /GESTAR LOCA Analysisfor Cooper Nuclear Station (TAC NO. M98293.)
8. NEDC-31892P, Revision 1, May 1991, Extended Load Line Limit and ARTS Improvement Program Analysisfor Cooper NuclearStation, Cycle M.
9. NEDC 98-024, Revision 1, July 1998, APRM- RBMSetpoint Calculation. i
10. NEDO-31960.A and NEDO-31960-A Supplement 1, BWR Owner's Group Long-Term Stability Solutions Licensing Methodology.

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

Il. NEDE-23785-1-P-A. The GESTR-LOCA andSAFER Modelsfor the Evaluation ofthe Loss-of-Coolant Accident, Volume III, Revision 1, October 1984.  ;

12. Nuclear Design Reportfor Cooper Nuclear Station Reload,18, J11-03354-03, July 1998.

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i Cycle 19, Revision 1 l

CORE OPERATING LIMITS REPORT Figure 1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Pluggoda 3.50 w/o with 10GZ GE8x8NB Fuel l0<&%

10 C" 9

~ "

'h~w-58

%[$

3

'x 9 0 10 20 30 40 50 60 PLANAR AVERAGE EXPOSURE (GWD/ST)

DATA COORDINATES (Reference 3)

Planar Average Exposure 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 7.92 49.69 5.67 Cycle 19, Revision 1 l

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1 CORE OPERATING LIMITS REPORT Figure 2 Maximum Average Unear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged,3.50 w/o with 10GZ1 GE8x8NB Fuel 15 14

_ 13 - - _

g --- w y ,,,, .

l10 a.

<8 37 g

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6 5

  • 0 10 20 30 40 50 -

PLANAR AVERAGE EXPOSURE (GWDIST) i DATA COORDINATES (Reference 3)

Planar Average Exposure MAPLHGR *

(GWD/ST) (kW/ft) i I

0.0 11.59 0.2 11.63 1.0 11.71 2.0 11.84 3.0 11.99 4.0 12.14 ,

5.0 12.26 6.0 12.39 7.0 12.53

! 8.0 12.66 9.0 12.81  ;

10.0 12.85 l I 12.5 12.79 l 15.0 12.51 20.0 11.78  ;

25.0 11.05  !

I 35.0 9.74 45.0 7.96 49.61 5.66 l

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! Cycle 19, Revision 1 l l

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CORE OPERATING LIMITS REPORT Figure 3 J

Maximum Average Unear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI  ;

Modification and Bypass Holes Plugged,3.48 w/o with 11GZ GE8x8NS Fuel '

15 r

14  !

k s,

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/A,  %

O 1

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< =

I 7 i 6 '

5 0 10 20 30 40 50 PLANAR AVERAGE EXPOSURE (GWD/ST)

DATA COORDINATES (Reference 3)

Planar Average Exposure MAPLHGR (GWD/ST) (kW/ft) 0.0 10.85 0.2 10.00 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 35.0 9.70 45.0 7.86 49.56 5.62 Cycle 19, Revision 1 l

CORE OPERATING LIMITS REPORT Figure 4 Maximum Average Planar Linear Heat Goneration Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged,3.48 w/o with 12GZ OEBx8MB Fuel 15 14

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2 h 6 11 , 'A E 10 O

5s g N-N -

o- A 7

k65 \

4 0 10 20 30 40 50 PLANARAVERAGEEXPOSURE(GWDfST)

DATA COORDINATES (Reference 3)

Planar Average Exposure MAPLHGR (GWD/ST) (kW/ft) 0.( . 10.89 O!! 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 9.61 45.0 7.75 49.30 5.67 Cycle 19, Revision 1 l

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CORE OPERATING LIMITS REPORT Fiaure 5 -

Flow DependentMAPLHGR Factor (MAPFACr)

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

1 i, 1 1.0 - -

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0.9 -

e + $O

' h 0.8 - AA g.

y , #

+

MAPU1GR(F) = MAPFACp. MAPUiGRSTD n

g MAPulGRSTc = STANDARD MAPUiGR UMITS j $ MAPFACp (F) = MINIMUM (1.0. pC A W It00 + Bp) h WC= % RATED CORE FLOW g AND Ap Sp ARE FUELTYPE DEPENDENT g CONSTANTS GtVEN DELOW: , i O

5 g 0.6 GE FUELS THROUGH GEtt MAXIMUM

;h CORE FLOW

(% RATED) Ap Bp 102.5 0.6784 OA8G1 0.5 - 107.0 0.6758 0.4574 112.0 0.6807 OA214 117.0 0.688G 03828 ,

0.4 . I I I I I I I .

30 40 30. 60 . 70 -

, 80 90 100 110' -

e CORE FLOW (% RATED)

)

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j Cycle 19, Revision 1 . go . .. ,

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CORE OPERAllNG UMITS REPORT Fiaure 6 Power Dependent MAPLHGR Factor (MAPFAC,)

(Reference 8, Section 5.4.2, Figure 5-7) 4 O

O

u. 1.2 -

O.

v E 1.0 o

F-O k

E 0.8 -

O ,

3~ 550% CORE FLOW

n. /

% =swve,.auruam 0.6 -

sueuaan sinawtosueurmuomTs i F

.j sl ron m uo monnin.uesis soeroswa) neouns  !

$ No unavs specmco ronasu se< son:

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uJ > 50Y. CORE FLOW Amer $ =0A0 + 0.005 PM)

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  • 0.005 P 30%)

rof>50% CORE fuW

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0 10 -

20 30 40 50

  • 6d 70 80 90 100 >

POWER (% RATED) w Cycle 19. Revision 1 I

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2.40 -

d OPERATING UMIT MCPR (P) = Kp +0PERATI* - 1 UMIT MCPR(100) 8M e '

=. Z 550% FLOW " FOR P<2s%: NO THERMAL L!MITS MONITORING REQUfRED c, NO UMITS SPECIFIED e A ,A 2.20' W O g

FOR25%$Pe Pwm (%=30%) e O '

o' T M N Kp = [K gyp

  • 0.028 (30% . P)]I OLMCPR(100) 3 Q m ,

2 8 O 18 x'

Kay, = 1.83 FOR S 80% CORE PL0w'.

b ' 7 i

2.27 FOR > So% CORE FLOW 2.00 -

pon sessp< 4sg: .m 2 Ks = 1.28 + 0.0134 (48% .P) k d G

550% FLOW" A FOR 45% SP< 80%; h [qmm Z 0

Kp= 1.15 + am7 p.M a, 3 1.60 -

3g y ,

FOR 60%$P: ..A

" pO ^

]

3 Kp = 1.0 + a00378 (100%.P) -

7 wh 2 5  % [ m .

p 1.40 -

3 g b

D v

$ M 2 .

C 1.20 or s .

bg6 00 O 10 20 30 40 50 60 70 80 90 100 POV!ER (% RATED) ,

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_ . _ . . - . - - - - . _ _ _ _ _ . _ - _ _ _ . . _ . - - - - _ _ _ _ _ _ . - - -n- - - - _ _ -- - .w- e ~,c,, --e w ,cm

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

. . i I

F CORE OPERATING UMITS REPORT f

4 '

4 Fiaure 8 i

Flow Dependent MCPR Umits i (MCPR,)

(Reference 8, Section 5.4.3, Figure 5-8) i 33 max 3Muu noWRATE FOR We(% RATED CORE FIDW)t40%

MCPR(F) = Mm(1.20 A,Wer100 + Br) 1.7 - .

112.00% MAX FLOW aE _.BE_.

f 1.6 107.00% 117.0 ' 0.632

- 1A09 112A -0.002 1.747 IN 107.0 0.506 1.897 to2.s -05/1 1.ess -

6 (t- 1.5 -

I

{

o roR We(% RATED CORE FLOW) < 40%

MCPR(F) = (A,Wer 100 + 8,)

  • 2 1.4 - [1.0 +0.0032(40.Wc)] l i

I 1.3 - -

t

.* f 1.2 -  ;

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20 30 40 50 60 70 80 90 100 110 120  ;

CORE FLOW (% RATED) . 1

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I CORE OPERATING LIMITS REPORT Figure 9 Minimum Critical Power Ratio (MCPR) versus Tau (based on tested measured scram time as  ;

defined in Reference 4), GE 8x8 NB fuel

. l 1.3 -

1.29 .

1.28.

127.

1.26.

a:

$ 1.25.

m 1.24 .

1.23.

1.22.

1.21 .

1.2 '

0.6 '

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0 0.1 0.2 0.3 0.4 0.5 O.7 0.8 0.9 1 Tau Exposure range: BOC19 to EHFP19 - 2205 mwd /MT  !

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Cycle 19, Revision 1 - 14 l l

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i CORE OPERATING LIMITS REPORT Figure 10 Minimum Critical Power Ratio (MCPR) versus Tau (based on tested measured scram time as defined in Reference 4), GE 8x8 NB Fuel 6

1.32 I

1.31 1.3 . .l 1.29 .

1.28.  !

1.27.

x h 1.26.

1.25. /

1.24 .

1.23.

1.22.

I 1.21 .

1.2 j l

0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Tau Exposure range: EHFP19 -2205 mwd /MT to EOC19 ,

I Cycle 19, Revision 1 15 - l

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CORE OPERATING LIMITS REPORT I l

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 4), GE 8x8 NB Fuel 1.34 -

1.33.

1.32.

1.31 .

1.3 .

1.29 .

1.28.

a:

A 1.27.

1.26 .

1.25.

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 i

Exposure range: BOC19 to EOC19 Cycle 19, Revision 1 l i

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CORE OPERATING UMITS REPORT ,

F_ loure 12 140 APau Saam une 120 (toutoo) 100 - APRM Rod Block go. .

/ g Reediedliac 60 -

40 -

Mia puay, speed Neural 20- -

circulation 0

O 20 40 60 80 100 120 Core Flow (% ofrated)

.t W-w, ,( w-w,

p,p P[ i ,w,-w, Tw,-w.

(Pas'

-; Coo:dinates of Exclusion Region Bounda

~

' I wheri

, P'oint # Power (%) Flow (%)"

.4 ~

A 75 4

'l P = a cose el===I power value on the Exclusion Region boundary (% of rated), 43.8 W = the cose flow ratch.-4-- 'I=5 to power, P, on the Exclusion Region boundary B 36.3 30.0

(% efrated),

P4= core thermal power at State Point A (% of rated),

P. = core thenna! power at State Point B (% of rated),

'WA= core flow rate at State Point A (% of rated), .

Na = cose Gow rate at State Point B (% of rated),

Cycle 19, Revision i 17 l

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