ML20134F738

Rev 7 to Topical Rept - 066, Oyster Creek Cycle 16 Colr

ML20134F738
Person / Time
Site:	Oyster Creek
Issue date:	09/17/1996
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20134F734	List: ML20134F731 ML20134F738
References
066, 066-R07, 335400, 66, 66-R7, NUDOCS 9611070207
Download: ML20134F738 (11)

Text

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l. Oyster Creek Cycle 16 i I i

j Core Operating Limits Report i

}- Topical Report - 066 Rev. 7 1

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BA Number 335400 September 1996 Prepared:

• 4!i7!4h Engineer Date l "uclear Fuels Approved:

• _ 9'/ 7"f4 Manager ' Date Nuclear Fuels l

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9611070207 961031 PDR ADOCK 05000219 P PM

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TABLE OF COFFEWIS

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1 j Introduction ........ ...............

h 4 ............................. 3 a

l References . ........... . . . ........................................ 4

, Figure 1 GE9B-348 Fuel MAPLHGR Limits ............................ . 5 4

Figure 2 GE9B-338 Fuel MAPLHGR Limits .. . . . . . . . . . . . . . . . . ......... 6 1 *  ;

Figure 3 GE8B-338-12GZ Fuel MAPLHGR Limits .........................

/ 7 i Figure 4 GE8B-338-11GZ Fuel MAPLHGR Limits ..................... ... 8 Figure 5 MCPR Limits .......... ......................

. . ... .. . 9 Figu r e 6 K f Fl ow Fa ct or . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 d

. Figure 7 LLHGR Limits .......

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TR-066 {

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. 1 1

. . INTRODUCTION l l 1 i

Generic Letter 88-16 provides guidance for Technical Specification Changes concerning cycle-specific limits. The generic letter provides a 1 vehicle for the removal of cycle specific parameters from the Technical l Specification and the maintenance of these values within a Core

! Operating Limits Report (COLR). The Technical. Specification l modification also establishes reporting requirements and includes definitions supporting the proposed changes. The COLR, including mid-cycle revisions, will be provided for each reload cycle.

l This Core operating limits Report (COLR) has been prepared in accordance j with the requirements of OC Technical Specification 6.9.1.f. The information in this report was reviewed and approved for use at Oyster l Creek by means of the Cycle 16 Reload Information and Safety Analysis

Report (TR-109 Rev. 0) dated September 1996. The Cycle 16 fuel / core j operacing limits were generated using the NRC approved codes and i methedologies identified in References 1 through S.

4 For each GE fuel design the APLHGR limits provided in the COLR for four-

loop operation are calculated to be he same as the five-loop limits at aAl exposure levels prov4aed the idla loop is unisolated. If the idle loop have both its succion and discharge valves closed the loop is

} isolated as defined in reference 6 and a 0.98 MAPHLGR multiplier must be

applied at all exposure levels. Requirements for operation with'an idle loop are provided in Technical Specification 3.3.F.

.E During power operation thermal margins should be maintained with the l specified limits. If at any time during power operation it is determined by normal surveillance that the limiting value for APLHGR (Figures 1-4), LLHGR (Figure 7) or CPR (Figures 5 and 6) is being exceeded, action shall be initiated to restore operation to within the proscribed limits as specified in Technical Specification Section 3.10.

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I TR-066 R0v. 7 1 Page 4 of 11 I REFERENCES

1. Letter from J. N. Donahow, Jr. (NRC) to P.B. Fiedler (GPUN) dated ,

November 14, 1986, " Reload Topical Report TR 020, Rev 0 I (TAC 6039) ,

l

2. Letter from A. W. Dromerick (NRC) to P.B. Fiedler (GPUN) dated l September 27, 1987, GPU Nuclear Corp. (GPUN) Topical Report TR I 021, Revision 0, " Methods for the analysis of Boiling Water Reactors Steady State Physics.

3. Letter from A. W. ')romerick (NRC) to P.B. Fiedler (GPUN) dated March 21, 1988, GP' Nuclear Corp. (GPUN) Topical Report TR 033, Revision 0, "Meth. .' for the Generation of Core Kinetics Data for RETRAN-02 (TAC No. 65138). "

4. Letter frcm A. W. Dromerick (NRC) to P.B. Fiedler (GPUN) dated March 21, 1988, GPU Nuclear Corp. (GPUN) Topical Report TR 040, Revision 0, " Steady State and Quasi-Steady State Methods for Analyzing Accidents and Transients (TAC No. 65139) . "

5. Letter from A. W. Dromerick (NRC) to E.E. Fitzpatrick (GPUN) dated October 12, 1988, GPU Nuclear Corp. (GPUN) Topical Report TR 040, Revision 0, "BWR-2 Transient Analysis Model using the RETRAN Cods; (TAC No . 6 6 3 5 8 ) . ' '

6. " Oyster Creek NGS SAFER /CORECOOL/GETR~LOCA Loss-of-Coolant Accident Analysis, ' NEDE-31462P August 1987 j

7. " Reload Information a'ad Safety Analysis Report for Oyster Creek Cycle 16 Reload, GPUN N-109 Revision 0, dated September 1996

8. Letter form A. W. Dromerick (NRC) to E. E. Fitzpatrick (GPUN) dated October 31, 1988 " Issuance of Amendment No. 129 (TAC No.

67743).

9. " General Electric Standard Application for Reload Fuel, ' NEDE-240011-P-A-13 dated August 1996

10. Letter WHO: 91-002, W.H. Hetzel (GE) to R.V. Furia (GPUN) dated January 14, 1991, " Oyster Creek Reload 12 MAPLHGR Calculation. "

11. Letter WHO: 94-036, W.H. Hetzel (GE) to R.V. Furia (GPUN) dated July 29, 1994, "MAPLHGR Report for Oyster Creek Reload Fuel Bundles . "

FIGURE 1 .'

GE9B-P8DWB348-12GZ-80M-145-T FUEL -

MAXIMUM ALLOWABLE AVERAGE PLANAR LINEAR HEAT GENERATION RATE D

Li_

(FOUR AND FIVE LOOP OPERATION)

\

g 1m? _

iiiip ii i si i i iiiiiiip 'I' - EXPOSURE Lattice Lattice Lattice Lottice SG s-

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(GWD/MT)

(PSZ) (DOM) (SDZ) N AT-U 10.76 1 1 1 ,, 'I

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0.22 1.10 10.89 10.97 10.23 10.32 9.81 9.92 10.59 O / I

\l i I I 3.31 11.14 10.61 10.28 10.62 I / Ni  ; i i 5.51 11.30 10.94 10.68 10.76 J 1O V- b '

8.82 11.26 11.26 11.13 10.93 1 7 I I I 11.02 11.21 11.21 11.21 10.99 1 I\ l I I 13.78 11.15 11.15 11.15 10.76

\ '

i--: 16.53 10.83 10.83 10.83 10.38 4_f 9~-~- 2 i

\_ t -

19.29 10.05 10.05 10.05 9.99 b" -

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\rl I I

22.05 9.93 9.93 9.93 9.60 O_ _- 1 I x I I 27.56 9.74 9.74 9.74 8.81 38.58 9.28 9.45 9.43 7.24 g__ _ __ 4 _ _ _ i _ _ __ p_ y _ 4 _ 48.12 4.78 LJ -

O - I I I I h

49.60 7.85 7.97 7. 9 E.

<C  : I I I i 1 -

56.49 5.88 E 7----r--i-- r-- --i - -: 56.62 5.87

56.S7 5.67 i i  ;  ;  ; i

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4 iii,iiiiiiiiiiiiiiiii w e 0 10 20 30 40 50 60 2 WEF AGE. PLANAR EXPOSURE (GWD/'MT)  :

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FIGURE 2 GE9B-P8DWB338-11 GZ-80M-145-T FUEL .

~

MAXIMUM ALLOWABLE AVERAGE PLANAR LINEAR HEAT GENERATION RATE

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(FOUR AND FIVE LOOP OPERATION) 3 12 -

' ' ' ' ' ' 'I' ''''''''"'' - EXPOSURE Lottice Lattice Lattice Lottice M -

1 I I I I (GWD/MT) (PSZ) (DOM) (SDZ) (TWZ) v - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . -

o'11-C -// I I

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---l---b 1

?:20 3.31 jgg; 11.19 j0 jg 10.77 1g gg 10.45 jggf 11.19 I

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[  ;  ;  ;  ; i  : 5.51 11.41 11.23 10.94 11.41

-' - 6.61 11.38 11.38 11.18 11.38 10--" - 2-- -'-2--'--- 7.72 11.34 i I I i 8.82 11.31 11.31 11.31 h

i i e' i i  : 11.02 11.25 11.25 11.25 11.25 16.53 10.65 10.65 10.65 10.65 5 g_-___1 O_

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19.29 22.05 10.04 9.94 10.04 9.94

,0.04 9.94 10.04 9.94 i i i l l 27.56 9.77 9.77 9.77 9.77 La 38.58 9.08 9.27 9.26 9.09 O I I I I I -

49.60 7.77 7.93 7.92 7.77

<C O_ l i I i 56.17 5.80 1 -

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- 56.20 5.79 LLJ - -

57.01 5.74

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57.06 5.77

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5 ,i Iiiiiliiiij.iiiliiiili<ii m " Pn 0 10 20 30 40 50 60 a AVERAGE PLANAR EXPOSURE (GWD/MT) r

FIGURE 3 Tech Spec 3.10.A GE-P8DOB338-12GZ FUEL MAXIMUM ALLOWABLE AVERAGE PLANAR LINEAR HEAT GENERATION RATE DATA POINTS P

b-(FOUR AND FIVE LOOP OPERATION)

EXPOSURE MAPLHGR (GWD/MT) (KW/FT) p 12 ~ , i i i i iiiiiii i. iiiii,,

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M l i I I 0.22 9.93

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, , , j 1.10 10.07 O g]__ _ _ _ _ __ L _ _ __L_____L_____L______ 5.50 10.97 J -

, [ 11.00 11.50 1 I I I 16.50 10.90 f1C.-----

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i 22.00 27.50 9.70 9.60 I ' ' '

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33.00 9.60 g _

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< g_______L_____L_____L_____L______ 38.50 9AO

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LJ 44.00 8.63 1 I I I *s 1 I i I N -

50.00 7.85

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, , i i ut i i i i i iiiiiii iiiii i i i i ~ g 0 10 20 30 40 50 2 AVERAGE PLANAP EXPOSURE (GWD/MT)  :

t - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - _ - - - _ - - - - - - _ _ - _ - _ _ - _ _ _ - _ _ -- -_ _ _

FIGURE 4 Tech Spec '3.10.A GE-P8DOB338-11 GZ FUEL .

MAXIMUM ALLOWABLE AVERAGE PLANAR LINEAR HEAT GENERATION RATE DATA POINTS P

b-(FOUR AND FIVE LOOP OPERATION)

EXPOSURE MAPLHGR p 12 - i , i i i iiiiiiiiiii i i i,,,,

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(GWD/MT) (KW/FT)

M 1 I I I 0.22 10.22 1 I i g

1.10 10.39 g3]_ ______L__

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5.50 11.18 l l , l  : 11.00 11.50 1 I I I 16.50 10.90 22.00 9.70 f 10 - ------h----- -----h-----h----- 2'I.50 9.60 CL 1 I t

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33.00 9.60 I I i 0 _. _

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'---- '---- ,'---- ,' - - - - - 38.50 9.40

, , , , [ 44.00 8.70 4 50.00 7.95 N

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l i i i l i i i i j i i i i @ g 0 10 20 30 40 50 a AVERAGE PLANAR EXPOSURE (GWD/MT) =

e TR-066 Rev. 7 Page 9 of 11

. Figure 5

)

l MINIMUM CRITICAL POWER RATIO (MCPR) - Tech Soec 3.10.C l

l APRM STATUS MCPR LIMIT l

1. If any two (2) LPRM assemblies which are 1.53 input to the APRM system and are separated in distance by less than three (3) times the control rod pitch contain a combination of three (3) out of four (4) detector located in either the A and B or C and D levels which are failed.or I

, bypassed (i.e., APRM channel or LPRM

. input bypassed or inoperable)  !

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2. If any LPRM input to the APRM system at 1.53

. the B, C, or D level is failed or i bypassed or any APRM channel is inoperable (or bypassed).

3. All B, C, and D LPRM inputs to the APRM 1.53 system are operating and no APRM l channels are inoperable or bypassed.

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FIGURE 7 Tech Spec 3.10.C MOW AC~O R, 4 .

O q i i i i i i i i i i i i i i i DATA POINTS FLOWMAX (5)

O _ _

FLOW 117

,- O.3 1.28 0.4 1.22 O 0.5 1.17 W

kO 0.6 1.13 0.7 1.09 g" MANUAL FLOW CONTROL y SCOOP TUBE POSITION 0.8 1.05

• LIMITED SUCH THAT FLOWMAX = 117.0 s 0.9 1.00 O 1.0 1.00

=

0 -

NOTE: For Froction of Core Flow (FCF) less than 0.40 the following odjustment factor must be applied to the K, curve:

1.0 + (0.32)(1.22)(0.40 - FCF) yyg O  %

@ l ' I I I i l i I i I 3 I i 8$

O 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 R .

FRACTION CORE FLOW 2

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

1,

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• Figure 7 LOCAL LINEAR HEAT GENERATION RATE (LLHGR) - Tech spec 3.10.8 FUEL TYPE LHGR Limit 1

1. GE8x8NB s 13.4 kw/ft '

GE8x8EB l

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