ML043220636

Core Operating Limits Report for Oyster Creek Cycle 20, Revision 0

ML043220636
Person / Time
Site:	Oyster Creek
Issue date:	11/17/2004
From:	Gallagher M AmerGen Energy Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2130-04-20265
Download: ML043220636 (17)

Text

Technical Specification 6.9.1 .f.4 2 130-04-20265 November 17.2004 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Oyster Creek Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219

Subject:

Core Operating Limits Report for Oyster Creek Cycle 20, Revision 0 Enclosed with this cover letter is the approved Oyster Creek Generating Station, Core Operating Limits Report for Oyster Creek Cycle 20, Revision 0. The report has been reviewed as required by the Oyster Creek Technical Specifications.

If any additional information is needed, please contact Dave Robillard at (610) 765-5952.

Very truly yours, M. P. Gallagher Director - Licensing & Regulatory Affairs AmerGen Energy Company, LLC

Enclosure:

Core Operating Limits Report for Oyster Creek Cycle 20, Revision 0 cc: S. J. Collins, USNRC, Administrator, Region 1 P. S.Tam, USNRC, Senior Project Manager, Oyster Creek R. J. Summers, USNRC, Senior Resident Inspector, Oyster Creek File No. 04005

0yste;Creek Core Operating Limits Report Page I Cycle 20 Rev. 0 Core Operating Limits Report for Oyster Creek Cycle 20 Revision 0 I

Reviewed:

Reactor Engineering

Oyster Creek Core Operating Limits Report Page 2 Cycle 20 Rev. 0 Table of Contents 1 . References ................................................................................................................................................ 4

2. Terms and Definitions

3. General Information ................................................................

4. Average Planar Linear Heat Generation Rate ................................................................ 7

5. Minimum Critical Power Ratio ............. ................................................................................ 13 5.1 . Manual Flow Control MCPR Limits ........................................................

5.2. Scram Time ........................................ ................................................................. 13

6. Linear Heat Generation Rate .. ...................................................... ..................... 15

7. Stability Protection Settings ................................... ................................................................ 15

8. Modes of Operation ...................................... 16

9. Methodology ......................... ............................ ........................................... 16

Oyster Creek Core Operating Limits Report Page 3 Cycle 20 Rev. 0 List of Tables Table 4-1 MAPLHGR for bundle: GE9B-P8DWB348-12GZ-80U-I 45-T6 ....................... ................... 7 Table 4-2 MAPLHGR for bundle: GE9B-P8DWB338-11GZ-80U-I45-T6 ......................................

Table 4-3 MAPLHGR for bundle: GEll-P9HUB374-13GZ-1OOT-145-T6-2559 .............................

Table 4-4 MAPLHGR for bundle: G E l l -P9HUB374-13GZ-I00T-145-T6-2559 ..................

Table 4-5 MAPLHGR for bundle: G E l l -P9HUB369-12GZ-lOOT-l45-T6-2560 ..

Table 4-6 MAPLHGR for bundle: GEI I -P9HUB369-12GZ-lOOT-145-T6-2560 ......................................... lo Table 4-7 MAPLHGR for bundle: G E l l -P9HUB363-12GZ-lOOT-145-T6-2817. ....................... 10 Table 4-8 MAPLHGR for bundle: GE1 1-P9HUB363-12GZ-lOOT-145-T6-2817......................................... 11 Table 4-9 MAPLHGR for bundle: GE11-P9HUB364-14GZ-lOOT-l45-T6-2818 ......... ........................ 11 Table 4-10 MAPLHGR for bundle: GE11-P9HUB364-14GZ-lOOT-145-T6-2818 ....................................... 12 Table 4-1 1 MAPLHGR Multiplier with One ISOLATED Loop .... ........... 12 Table 5-1 MCPR Limit for Four or Five Recirculation Loops in Service ...................................................... 13 Table 5-2 MCPR Limit for Three Recirculation Loops in Service ................................................................ 13 Table 5-3 GEgB K(f) Multiplier .................................................................................................................... 14 Table 5-4 GEI 1 K(f) Multiplier ..................................................................................................................... 14 Table 7-1 OPTION I1 Stability Protection Settings ...................................................................................... 15

Oyster Creek Core Operating Limits Report Page 4 Cycle 20 Rev. 0

1. References

1. GNF Document, NEDE-31152P, Revision 8, General Electric Fuel Bundle Design, April 2001.

2. GNF Document, OOOO-0029-3151-SRLR, Revision 1, Supplemental Reload Licensing Report for Oyster Creek Reload 20 Cycle 20, September 2004.

3. GNF Document, 0000-0029-3151 -FBIR, Revision 0, Fuel Bundle Information Report for Oyster Creek Reload 20 Cycle 20, October 2004.

4. OPL3 Parameters for Oyster Creek Cycle 20 Transient Analysis, eDRF 0000-0026-5261, July 29, 2004.

5. Design Record File 20620.

6 . GENE Document, NSA02-247, Oyster Creek APRM Flow-Biased Setpoint Margin Between Scram and Rod Block for Stability Option I1 Adjustment, January 2002.

7 . GPU Document, Technical Evaluation of GE9B Fuel for Oyster Creek, TDR 1132, March 1994.

8. Passport EC 351429 (CAP 02004-251 1 )

9. Framatome ANP Document, POWERPLEX-Ill Core Monitoring Software Specification, EMF-2469jP) Rev. 1.

Oyster Creek Core Operating Limits Report Page 5 Cycle 20 Rev. 0

2. Terms and Definitions APLHGR Average Planar Linear Heat Generation Rate ARTS A P R M Rod Block Monitor Technical Specification (Improvement)

APRM Average Power Range Monitor BOC Beginning of Cycle BWROG Boiling Water Reactor Owners Group Coastdown Coastown occurs when full power is not achievable with all rods out, maximum allowable core flow and feedwater temperature reduction, and equilibrium xenon ELLLA Extended Load Line Limit Analysis EOC End of Cycle EOR End of Rated Conditions (i.e., cycle exposure at 100% power, 100% flow, all-rods-out, all feedwater heaters in service and equilibrium xenon)

GNF Global Nuclear Fuel ICF Increased Core Flow ISOLATED The recirculation loop suction, discharge and discharge bypass valves are in the closed position K(f) MCPR flow dependent multiplier (i.e., adjustment to the CPR limit when at core flows less than rated)

LHGR Linear Heat Generation Rate LPRM Local Power Range Monitor MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio 00s Out of Service Option A Option A refers to the Technical Specifications core average scram time speed that when applied results in a more restrictive MCPR limit Option B Option B refers to a specific core average scram time speed that when met allows the use of a lower MCPR limit TIP Traversing In Core Probe

Oyster Creek Core Operating Limits Report Page 6 Cycle 20 Rev. 0

3. General information Oyster Creek is a non-ARTS plant. Therefore, there are no ARTS-based power or flow biased APLHGR, LHGR or CPR operating limits. There are, however, Oyster Creek specific flow biased CPR operating limits for operation at less than rated flow. The flow-biased limits are discussed in Section 5.1. Rated core flow is 61 Mlb/hr and operation up to 1 10.7% of rated is licensed for this cycle. Additionally, Oyster Creek utilizes an ELLLA operating domain which has expanded the powerlflow map to allow for greater operational flexibility.

Oyster Creek Core Operating Limits Report Page 7 Cycle 20 Rev. 0

4. Average Planar Linear Heat Generation Rate The MAPLHGR limits are discussed in Technical Specifications Section 3.1O.A. The MAPLHGR limits for the lattices in each fuel type as a function of average planar exposure are given in Tables 4-1 through 4-10 for operation with zero ISOLATED RECIRCULATION LOOPS (Reference 2 and 5). For operation with one ISOLATED RECIRCULATION LOOP, multiply the limits in Tables 4-1 through 4-10 by the ISOLATED Loop multiplier listed in Table 4-1 1 (Reference 2).

Table 4-1 MAPLHGR for bundle: GE9B-P8DWB348-12GZ-8OU-l45-T6 PPLX Lattice #18,#23,#24,#25, #26,#27 GNF Lattice #3792,#3791,3790,#3789,#3118 0.00 f 0.88 0.20 10.88 1.10 10.98 5.50 11.30 8.80 11.28 11 .oo 11.19 13.80 11.11 16.50 10.79 19.30 22.00 27.60 38.60 9.39 ir 49.60 I 9.45 I 1 60.60 71.70 9.37

Oyster Creek Core Operating Limits Report Page 8 Cycle 20 Rev. 0 Table 4-2 MAPLHGR for bundle: GE9B-P8DWB338-11GZ-80U-145-T6 PPLX Lattice #17, #18, #19, #20, #21, #22 GNF Lattice #3734, #3788,3787, #3786, #3785, #3118 0.00 10.93 0.20 10.93 1.10 11.03 5.50 1I .37 8.80 11.29 11 .oo 11.11 k16.50 13.80 1 11.11 10.68 27.60 9.60 38.60 9.39 49.60 9.43 71.70 9.44 Table 4-3 MAPLHGR for bundle: GE11-PSHU8374-13GZ-100T-145-T6-2559 PPLX Lattice #36,#35, #33, #31 GNF Lattice #5542, #5540, #5544, #5545 0.00 9.64 0.20 9.64 1.10 9.75 5.50 9.65 11 .oo 9.49 16.50 9.47 22.00 9.03 27.60 8.28 38.60 8.04 8.04 49.60 7.99 60.60 8.15 71.70 8.19

Oyster Creek Core Operating Limits Report Page 9 Cycle 20 Rev. 0 Table 4-4MAPLHGR for bundle: GE1 l-P9HUB374-13GZ-lOOT-145-T6-2559 PPLX Lattices #32,#34 GNF Lattices #5541,#5543 0.20 9.83 1 1.10 5.50 7 1.oo 9.65 9.60 16.50 9.44 22.00 9.04 27.60 8.24 38.60 8.02 49.60 7.98 60.60 8.1 4 71.70 8.19 Table 4-5MAPLHGR for bundle: G E l l-P9HUB369-12GZ-lOOT-145-T6-2560 PPLX Lattices #43,#41,#45,#46 GNF Lattices #5547,#5540,#5544,#5549 71.70 8.32

Oyster Creek Core Operating Limits Report Page 10 Cycle 20 Rev. 0 Table 4-6 MAPLHGR for bundle: GE1l-PQHUB369-12GZ-100T-145-T6-2560 PPLX Lattices #42,#44 GNF Lattices #5546, #5548 Table 4-7 MAPLHGR for bundle: GE1l-P9HUB363-12GZ-lOOT-145-T6-2817 PPLX Lattices #3, #1 GNF Lattices #6783, #6785

Oyster Creek Core Operating Limits Report Page 11 Cycle 20 Rev. 0 Table 4-8MAPLHGR for bundle: GEll-P9HUB363-12GZ-10OT-145-T6-2817 PPLX Lattices #2, #8, #9, #I0 GNF Lattices #6784,#6782,#6786,#6787 Avg. Planar I

11.oo 9.73 16.50 9.43 22.00 9.08 27.60 8.29 38.60 8.15 49.60 8.13 60.60 8.09 71.70 8.36 Table 4-9 MAPLHGR for bundle: GE1l-P9HUB364-14GZ-lOOT-145-T6-2818 PPLX Lattices #7, #5 GNF Lattices #6788,#6790 0.00 9.96 0.20 9.96 1.10 9.97 11 .oo 16.50 1ir-- 22.00 I 9.03 II I I 27.60 38.60 49.60 60.60

j!

8.10 71.70 8.29

Oyster Creek Core Operating Limits Report Page 12 Cycle 20 Rev. 0 Table 4-1 0 MAPLHGR for bundle: GEll-P9HUB364-14GZ-lOOT-145-T6-2818 PPLX Lattices #6, #11, #12, #4 GNF Lattices #6789,#6782,#6791,#6792 0.00 9.93 0.20 9.93 1.10 9.91 5.50 9.85 I 1.oo 9.62 16.50 9.61 22.00 9.04 27.60 8.26 38.60 8.10 49.60 8.08 60.60 8.25 71.70 8.31 Table 4-1 1 MAPLHGR Multiplier with One ISOLATED Loop I/ Fuel Type

/Isolated Loop/j Multiplier GE11 0.98

Oyster Creek Core Operating Limits Report Page 13 Cycle 20 Rev. 0

5. Minimum Critical Power Ratio The MCPR limits are discussed in Technical Specifications Section 3.1 O.C.

5.1. Manual Flow Control MCPR Limits The flow adjusted MCPR is determined by multiplying the applicable rated condition MCPR limit shown in Table 5-1 or 5-2 by the applicable MCPR multiplier, K(f), given in Table 5-3 or Table 5-4. The MCPR values are documented in Reference 2 while the K(f) multipliers are documented in Reference 1. The appropriate K(f) value may be determined by linear interpolation. A low flow correction factor is applied to the K(f) value for GE9 fuel (Table 5-3). The low flow correction factor does not apply to GEI 1 fuel (Table 5-4). The low flow correction factor applied to K(f) was obtained from Reference 7.

5.2. Scram Time Core average scram insertion times are determined per Technical Specifications 3.2.

Based on the results of the scram time surveillance testing and calculation of the core average insertion time, a MCPR limit is chosen from Table 5-1 or Table 5-2. I f the core average scram insertion time does not meet the Option B criteria, but has met Option A criteria, then the appropriate MCPR value may be determined from a linear interpolation between the Option A and B limits with standard mathematical rounding to two decimal places.

Table 5-1 MCPR Limit for Four or Five Recirculation Loops in Service Cycle Exposure Option BOC to EOR-2205 MWD/MT 2 EOR-2205 MWD/MT to EOC A 1.47 1.51 B I .36 1.40 1

Table 5-2 MCPR Limit for Three Recirculation Loops in Service Cycle Exposure Option BOC to EOR-2205 MWD/MT 2 EOR-2205 MWDlMT to EOC A 1.49 1.53 B 1.38 1.42

Oyster Creek Core Operating Limits Report Page 14 Cycle 20 Rev. 0 Table 5-3 GESB K(f) Multiplier' 100.0 70.0 1.09 1 50.0 40.0 30.0 1.22 1.33 Table 5-4 G E l l K(f) Multiplier' 120.0

~~~ 100.0 90.0

Oyster Creek Core Operating Limits Report Page 15 Cycle 20 Rev. 0

6. Linear Heat Generation Rate The LHGR limits are discussed in Technical Specifications Section 3.10.B. The maximum LHGR shall not exceed the LHGR limits as specified in Reference 3. The maximurn values at beginning of life are a function of fuel type; these values are 13.4 (kW/ft) for GESB fuel (Reference 3) and 12.0 (kW/ft) for GEl 1 fuel (Reference 3). The exposure dependent LHGR limits are contained in Reference 3 for both GESB fuel and GEI 1 fuel.

7. Stability Protection Settings The stability protection settings are discussed in Technical Specifications 2.3. Oyster Creek utilizes the BWROG Option I1 solution in the licensing stability calculations for Oyster Creek. Table 7-1 provides the analytical limit equations for APRM based stability protection settings and related Control Rod Block settings to support Option II implementation (Reference 2 and Reference 6).

Table 7-1 OPTION li Stability Protection Settings Technical Specification 2.3.A.1 Neutron Flux, Scram - APRM For W 2 27.5 x I Ob 16 / hr:

S I (1.433 x 1O.b) W + 24.8 where:

S = setting in percent of rated power W = recirculation flow (Ib/hr) rechnical Specification 2.3.B Neutron Flux, Control Rod Block For W 5 27.5 x 10" Ib / hr:

s 5 (1.433 x 1o-6)w + 17.5 where:

S = setting in percent of rated power W = recirculation flow (Ibihr)

Oyster Creek Core Operating Limits Report Page 16 Cycle 20 Rev. 0

8. Modes of Operation The allowed Modes of Operation are as described below:

Each operational mode may be combined with up to a 100°F reduction in feedwater temperature (Final Feedwater Temperature Reduction or Feedwater Heaters 00s)at any point in the cycle.

Operation up to 67.5 Mlb/hr core flow is licensed for this cycle.

3 Each operational mode may be coincident with coastdown operation. The minimum coastdown power level is 40%.

Reference 8 documents the Main Steam Line 00s condition.

Reference 9 documents the allowance of TIP machines 00s.

9. Methodology

1. GNF Document, NEDE-31462P, Oyster Creek NGS SAFER/CORECOOUGESTR-LOCA Loss-of-Coolant Accident Analysis, August 1987.

2. GNF Document, NEDE-24011-P-A-14 and Supplement NEDE-24011 -P-A-14-US, General Electric Standard Application for Reload Fuel, June 2000.

3. GNF Document, NEDC-33065P, Rev. 0, Application of Stability Long-Term Solution Option l i for Oyster Creek, April 2002.