ML023260227

Core Operating Limits Report, Revision 13

ML023260227
Person / Time
Site:	Oyster Creek
Issue date:	08/22/2002
From:	Degregorio R AmerGen Energy Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2130-02-20237, TAC MB6341
Download: ML023260227 (10)

Text

Amer-vr.

AmerGen Energy Company, LLC An Exelon/British Energy Company Oyster Creek US Route 9 South PO Box 388 Forked River, NJ 08731-0388 Technical Specification 6.9.1.f.4 Aug 22, 2002 2130-02-20237 67ct I United States Nuclear Regulatory Commission Document Control Desk Washington DC 20555 t

Subject:

Oyster Creek Generating Station Docket 50-219 Core Operating Limits Report, Revision 13 Enclosed with this cover letter is the approved Oyster Creek Generating Station Core Operating Limits Report, Revision 13. This report has been reviewed as required by the Technical Specifications If you should require any further information, please' contact Mr. John Rogers, of my staff, at 609.971.4893

(

very trmuy yours, Ron J. DeGregorio'ide Oyster Creek Generating Station RJD/JJR cc: Administrator, Region I NRC Senior Project Manager NRC Senior Resident Inspector

I AmerGen Oyster Creek Cycle 18 Core Operating Limits Report Topical Report - 066 Rev. 13 I BA Number 335400 July 2002 I Authors: R. V. Furia M. P. Hynes I

Approved:

Manager Date Nuclear Design - BWR Branch Approved:

D Nuclear Fuel Management

TR-066 Rev. 13 Page 2 of 9 TABLE OF CONTENTS Pacqe Introduction ................................................................................................... 3 References ...................................................................................................... 4 FIGURE 1 GE9B-348 Fuel MAPLHGR Limits .................................................... 5 FIGURE 2 GE9B-338 Fuel MAPLHGR Limits .................................................... 6 FIGURE 3 MCPR Limits .................................................................................... 7 FIGURE 4 Kf Flow Factor ..................................................................................... 8 FIGURE 5 LLHGR Limits ................................................................................. 9

TR-066 Rev. 13 Page 3 of 9 INTRODUCTION Generic Letter 88-16 provides guidance for Technical Specification Changes concerning cycle-specific limits. The generic letter provides a vehicle for the removal of cycle specific parameters from the Technical Specifications 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 the proposed changes. The COLR, including mid-cycle revisions, will be provided for each reload cycle.

This 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 18 Reload Information and Safety Analysis Report (TR-133, Revision 2) dated June 2002 (Reference 7). The Cycle 18 fuel/core operating limits were generated using the NRC-approved codes and methodologies identified in References 1 through 6.

For each GE fuel design, the APLHGR limits provided in the COLR for operation with less than five loops are calculated to be the same as the five-loop limits at all exposure levels provided a non-operating loop is not an ISOLATED RECIRCULATION LOOP. If a non-operating loop is ISOLATED, both the suction and discharge valves are in the closed position as defined in Reference 6, then a 0.98 MAPHLGR multiplier must be applied at all exposure levels. Only one ISOLATED non-operating loop is permitted.

Requirements for operation with recirculation loops out-of-service are provided in Technical Specification 3.3.F.2.

During power operation thermal margins should be maintained within the specified limits. If at any time during power operation it is determined by normal surveillance that the limiting value for APLHGR (Figures 1 and 2), LLHGR (Figure 5) or CPR (Figure 3) is being exceeded, action shall be initiated to restore operation to within the prescribed limits as specified in Technical Specification Section 3.10.

TR-066 Rev. 13 Page 4 of 9 REFERENCES

1. Letter from J. N. Donahew, Jr. (NRC) to P.B. Fiedler (GPUN) dated November 14, 1986, "Reload Topical Report TR 020, Rev 0 (TAC6039)."

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 045, Revision 0, "BWR-2 Transient Analysis Model using the RETRAN Code (TAC No. 66358)."

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

7. "Reload Information and Safety Analysis Report for Oyster Creek Cycle 18 Reload, GPUN TR-133 Revision 2, June 2002

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-24001 1-P-A-14 June 2000

10. 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."

TR-066 Rev. 13 Page 5 of 9 FIGURE 1 GE9B-P8DWB348-12GZ-80M-145-T MAPLHGR LIMITS MAPLHGR Limits for 3, 4, and 5 Loop Operation Technical Specfication 3.10.A 1200 DATA POINTS 1100 LATTICES Exposure PSZ DOM SDZ NATU KWIFT KW/FT KWIFT 1000 GWD/MT KW/FT 0.22 10.89 10.23 9.81 10.76 1.10 10.97 10.32 9.92 10.59 S9.00 3.31 11.14 10.61 10.28 10.62 U 5.51 11.30 10.94 10.68 10.76 8.82 11.26 11.26 11.13 10.93 Ce 800 11.02 11.21 11.21 11.21 10.99 a._ 7,0 13.78 11.15 11.15 11.15 10.76 *= 7.00 16.53 10.83 10.83 10.83 10.38 19.29 10.05 10.05 10.05 9.99 22.05 9.93 9.93 9.93 9.60 6.00 27.56 9.74 9.74 9.74 8.81 38.58 9.28 9.45 9.43 7.24 500 48.12 4.78 49.60 7.85 7.97 7.96 56.49 5.88 4.00 56.62 5.87 000 1000 2000 3000 4000 5000 6000 56.87 5.67 Average Planar Exposure (GWDIMT)

-PSZ -UM-DOM Ah-SDZ X-NAT7U

TR-066 Rev. 13 Page 6 of 9 FIGURE 2 GE9B-P8DWB338-11GZ-80M-145-T MAPLHGR LIMITS Technical Specfication 3.10.A MAPLHGR Limits for 3, 4, and 5 Loop Operation DATA POINTS LATTICES Exposure PSZ DOM SDZ TWZ 11.00 ------

GWD/MT KWIFT KW/FT KWIFT KW/FT 0.22 10.87 10.30 9.95 10.87 l0 o- . -- ,

1.10 10.96 10.40 10.05 10.96 3.31 11.19 10.77 10.45 11.19 5.51 11.41 11.23 10.94 11.41 6.61 11.38 11.38 11.18 11.38 *' 800 --- --- L. - L-. -- ---

-LL - -

7.72 11.34 8.82 11.31 11.31 11.31 11.02 11.25 11.25 11.25 11.25 4 7.00 --- - -

16.53 10.65 10.65 10.65 10.65 II '

19.29 10.04 10.04 10.04 10.04 6.00 ...... ------ ------ ..... ---- -

22.05 9.94 9.94 9.94 9.94 27.56 9.77 9.77 9.77 9.77 5 --

38.58 9.08 9.27 9.26 9.09 49.60 7.77 7.93 7.92 7.77 4.00 56.17 5.80 000 1000 2000 30.00 40.00 50.00 60.00 56.20 5.79 Average Planar Exposure (GWDIMT) 57.01 5.74 [-+l-PSZ -*DOM A---SDZ -- X--TWZ]

57.06 5.77

TR-066 Rev. 13 Page 7 of 9 FIGURE 3 MCPR MINIMUM CRITICAL POWER RATIO (MCPR) - Tech LIMIT Spec 3.10Q.C APRM STATUS

1. If any two (2) LPRM assemblies which are input 1.61 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 bypassed (i.e., APRM channel or LPRM input bypassed or inoperable) 1.61

2. If any LPRM input to the APRM system at the B, C, or D level is failed or bypassed or any APRM channel is inoperable (or bypassed).

1.61

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

TR-066 Rev. 13 Page 8 of 9 6' FIGURE 4 Technical Specification 3.10.C Kf Curve 1.40 DATA POINTS 1.30 FLOW Kf 0.3 1.28 1.20 0.4 1.22 0.5 1.17 0.6 1.13 1.10 0.7 1.09 0.8 1.05 0.9 1.00 1.00 1 1.00 1.2 1.00 0.90 Flowmax =117%

0.80 0 0.2 0.4 0.6 0.8 1 1.2 1.4 Fraction of Core Flow 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)

TR-066 Rev. 13 Page 9 of 9 FIGURE 5 LOCAL LINEAR HEAT GENERATION RATE (LLHGR) - Tech Spec 3.10.B FUEL TYPE LLHGR Limit GE8x8NB < 13.4 kw/ft