ML20154Q337

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Rev 8 to Oyster Creek Cycle 17,COLR
ML20154Q337
Person / Time
Site: Oyster Creek
Issue date: 09/30/1998
From: Furia R
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20154Q324 List:
References
066, 066-R08, 66, 66-R8, NUDOCS 9810230213
Download: ML20154Q337 (11)
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Oyster Creek Cycle 17 Core Operating Limits Report Topical Report - 066 Rev. 8 l 1

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BA Number 335400 September 1998 Prepared by: R. V. Furia Approved:

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'ManageY Date Nuclear Fuels l

9810230213 981016 PDR ADOCK 05000219 P PDR ,.

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TR-066 Rev. 8 Page 2 of 11 TABLE OF CONTENTS Paae I n t r od u c ti o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 References..................................................................................................4 FIGUR71 GE98 348 Fuel MAFLHGR Limits.... .......... ......... . . ..................5 FIGU R E 2 G E93-338 Fuel MAPLHG R Limits.... .............. ......... . . .... ... . . .... .. . . . . . .. 6 FIGURE 3 GE88-338-12GZ Fuel MAPLHGR Limits....... ........................... .......... 7 FIGURE 4 GE8B-338-11 GZ Fuel MAPLHG R Limits........ ... ................ ............... 8 FI G U R E 5 M C P R Li m its. . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .9. . . . . . . .

F I G U R E 6 K, Fl ow Fa cto r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 0 FI G U R E 7 LLH G R Limit s. . . . . . . . . . .. . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1 l

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INTRODUCTION

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

modification also establishes reporting requirements and includes definitions supporting I the proposed changes. The COLR, including mid-cycle revisions, will be provided for '

each reload cycle.

This Core operating limits Report (COLR) has been prepared in accordance with the requirements of OC Technical Specification 6.9.1.f. The information in this report was reviewed and approved for use at Oyster Creek by means of the Cycle 17 Reload Information and Safety Analysis Report (TR-118 Rev. 0) dated September 1998. The Cycle 17 fuel / core operating limits were generated using the NRC approved codes and methodologies identified in References 1 through 8. l For each GE fuel design the APLHGR limits provided in the COLR for four-loop operation are calculated to be the same as the five-loop limits at all exposure levels

, provided the idle loop is unisolated. If the idle loop has both its suction and discharge l valves closed, the loop is isolated as defined in reference 6 and a 0.98 MAPHLGR l multiplier must be applied at all exposure levels. Requirements for operation with an idle loop are provided in Technical Specification 3.3.F.

, During power operation thermal margins should be maintained tvith the 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 prescribed I limits as specified in Technical Specification Section 3.10.

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TR-066 Rev. 8 '

Page 4 of 11

. REFERENCES

1. Letter from J. N. Donahew, Jr. (NRC) to P.B. Fiedler (GPUN) dated November i 14,1986, "P.eload Topical Report TR 020, Rev 0 (TAC 6039)."

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2. Letter from A. W. Dromerick (NRC) to P.B. Fiedler (GPUN) dated September 27, 1987, GPU Nuclear Corp. (GPUN) Topical Report TR 021, Revision 0, " Methods for the analysis of Boiling Water Reactors Steady State Physics."
3. Letter from A. W. Dromerick (NRC) to P.B. Fiedler (GPUN) dated March 21, 1988, GPU Nuclear Corp. (GPUN) Topical Report TR 033, Revision 0, " Methods for the Generation of Core Kinetics Data for RETRAN-02 (TAC No. 65138)."
4. Letter from 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 Code (TAC No. 66358)." ,

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6. " Oyster Creek NGS SAFER /CORECOOL/GETR-LOCA Loss-of-Coolant Accident Analysis," NEDE-31462P August 1987
7. " Reload Information and Safety Analysis Report for Oyster Creek Cycle 17 Reload", GPUN TR-118 Revision 0, dated September 1998
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."

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a TR-066 Rev. 8 ,

Page 5 of 11 FIGUP.E 1 GE92-P8DWB348-12GZ-80M-145-T -

P.iAPLHGR LIMITS MAPLHGR Limits for Four and Five Loop Operation Technical Specfication 3.10.A 12.00 DATA POINTS 1' 00 * '

LATTICES d Exposure PSZ DOM SDZ NATU g, ,

GWD/MT KW/FT KW/FT KW/FT KW/FT 10.00 j ,

0.22 10.89 10.23 9.81 10.76 1.10 10.97 10.32 9.92 10.59 ' ' * -

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3.31 11.14 10.61 10.28 10.62 ~

5.51 11.30 10.94 10.68 10.76 k '

8.82 11.26 11.26 11.13 10.93 5 800 11.02 11.21 11.21 11.15 11.21 11.15 10.99 10.76

[y 7.00 i 13.78 11.15 - ,

16.53 10.83 10.83 10.83 10.38 19.29 10.05 10.05 10.05 9.99 g gg 22.05 9.93 9.93 9.93 9.60 27.56 9.74 9.74 9.74 8.81 9.28 9.45 9.43 7.24 5 00 38.58 48.12 4.78 49.60 7.85 7.97 7.96 4.00 M49 5.88 0.00 10.00 20.00 30.00 40.00 50.00 60.00 56.62 5.87 Average Planar Exposure (GWD/MT) 56.87 5.67 l--+-psz -e-Dou -*-soz +NATU l

TR-066 Rev. 8 -

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Page 6 of.11 FIGURE 2 GE9B-P8DWB338-11GZ-80M-145-T MAPLHGR LIMITS Technical Specfication 3.10.A l MAPLHGR Limits for Four and Five Loop Operation DATA POINTS 12.00 LAlTICES ~ ~

Exposure PSZ DOM SDZ TWZ 11 00 1 GWD/MT KW/FT KW/FT KW/FT KW/FT i 0.22 10.87 10.30 9.95 10.87 10 00 s ,

1.10 10.96 10.40 10.05 10.96 3.31 11.19 10.77 10.45 11.19 h 9.00 5.51 11.41 11.23 10.94 11.41 h 6.61 11.38 11.38 11.18 11.38 Ea .00 - -

7.72 11.34 y +

8.82 11.31 11.31 11.31 g ,

11.02 11.25 11.25 11.25 11.25 3 ~

16.53 10.65 10.65 10.65 10.65 10.04 10.04 10.04 E00 ~ ~ ~

19.29 10.04 ,

22.05 9.94 9.94 9.94 9.94 i,.56 9.77 9.77 9.77 9.77 5.00 >

38.58 9.08 9.27 9.26 9.09 49.60 7.77 7.93 7.92 7.77 4.00 '

56.17 5.80 0.00 10.00 20.00 30.00 40.00 50.00 60.00 56.20 5.79 Average Planar Exposure (GWD/MT) 5.77

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Page 7 of 11 FIGURE 3 GE8B D8DOB338-12GZ-80M-4WR-145-T .

MAPLHGR LIP.11TS Technical Specification 3.10.A MAPLHGR Limits for Four and Five Loop Operation DATA POINTS 12.00 Expousre MAPLHGR (GWD/MT) (KW/FT) 33.0o 0.22 9.93 1.10 10.07 5.50 10.97 (

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11.00 16.50 11.50 10.90 E {O ^

22.00 9.70 27.50 9.60 l e 00 a.

33.00 9.60 '

38.50 9.40 44.00 8.63 a.00 "

50.00 7.85 7.00 0 00 10.00 20.00 30.00 40.00 50.00 Average Planar Exposure (GWDMT)

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FIGURE 4 G E8B-P8DO B338-11 GZ-80M-4WR-145-T .

MAPLHGR LIMITS -

Technical Specification 3.10.A MAPLHGR Limits for Four and Five Loop Operation 12.00 DATA POINTS Expousre MAPLHGR (GWD/MT) (KW/FT) 11.00 -

O.22 1.10 10.22 10.39

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5.50 11.18 ,g g 11.00 11.50 g , ,

16.50 10.90 g 22.00 9.70 5 s 27.50 9.60  % 8 00 ' '

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33.00 9.60 '

38.50 9.40 44.00 8.70 s ':0 50.00 7.95 7.00 0.00 10.00 20.00 30.00 40.00 50.00 Average Planar Exposure (GWDMT) w

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, FIGURE 5 MINIMUM CRITICAL POWER RATIO (MOPR)- Tech Spec 3.10.C 1

l APRM STATUS MCPR LIMIT

1. If any two (2) LPRM assemblies which are input to the APRM system and are separated in 1.52 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 bypassed (i.e., APRM channel or LPRM input bypassed or inoperable) j
2. If any LPRM input to the APRM system at the s,' 1.52 C, o D levelis failed or bypassed or any APRM channel is inoperable (or bypassed).
3. All B, C, and D LPRM inputs to the APRM 1.52 system are operation and no APRM channels are inoperable or by; tssed.

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DATA POINTS 1.3 -

FLOW Ke ,

0.3 1.28 O.4 1.22 1.2 0.5 1.17 i 0.6 1.13 0.7 1.09 g 3,3 ,

0.8 1.05 l .

0.9 1.00  !

1.0 1.00 3 i Flowmax = 117.0%

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h 0.8 t 0 0.2 0.4 0.6 0.8 1 1.2 )

Fraction of Core Flow  ;

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- NOTE: For Fraction of Core Flow (FCF) less than 0.40 the following adjustment factor must be applied to the curve: 1.0 + (0.32)(1.22)(0.40 -FCF)  !

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TR-066 Rev. 8 Page 11 of 11 FIGURE 7 LOCAL LINEAR HEAT GENERATION RATE (LLHGR) - Tech Spec 3.10.B FUEL TYPE LHGR Limit 1

-1. GE8x8NB s 13.4 kw/ft l

GE8x8EB i

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