ML062960368

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Issuance of the Oyster Creek Operating Limits Report for Cycle 21 (Document No. COLR Oyster Creek 1 Rev 2)
ML062960368
Person / Time
Site: Oyster Creek
Issue date: 10/23/2006
From: David Helker
AmerGen Energy Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2130-06-20415
Download: ML062960368 (19)
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AmerGev Energy Company, LLC www.exelo::co!p corn An Exelon Company 2 0 0 Exelon jliay Keniiett S q ~ m r e ,PA 19348 TS 6.9.1.f.4 2130-06-20415 October 23,2006 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Oyster Creek Generating Station Facility Operating License No. DPR-16 NRC: n o c W No. 50-319

Subject:

Issuance of the Oyster Creek Core Operating Limits Report For Cycle 21 (Document No. COLR Oyster Creek 1 Rev. 2)

Enclosed is a copy of the Core Operating Limits Report (COLR) for Oyster Creek Generating Station, Cycle 21 (Document No. COLR Oyster Creek 1 Rev. 2). This report incorporates the revised cycle specific parameters resulting from the new core configuration implemented during the Oyster Creek Generating Station refueling outage.

This COLR is being submitted to the NRC in accordance with Oyster Creek Generating Station Technical Specifications (TS) Section 6.9.1 .f.4.

If you have any questions, please contact Tom Loomis (610-765-5510).

Very truly yours, David P. Helker Manager - Licensing and Regulatory Affairs Enclosure cc: S . J. Collins, Regional Administrator, Region I , USNRC M. S. Ferdas, USNRC Senior Resident Inspector G. E. Miller, Project Manager, USNRC File No. 06033

Exeion Nuclear - Nuckar Fuels COLR Oyster Creek 1 Rev. 2 Cycte 21 Care Operating Limits Repart (COLR) Oyster Creek Cycte 21 Gore Operating Limits Report (COLR) Oyster Creek Reviewed: I io / l J / h

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SQR 5ats Reactor Engineering

?./&- J I N R Design Manager uam Paga t of ?&

Exeion Nuclear . Nuclear Fuels COLR Oyster Creek 1 Rev. 2 Cycle 21 Core Operating Limits Report (COLR). Oyster Creek Table of Contents 1 List of Tables ............................................................................................................................................. 3

2. References ................................................................................................................................................ 4
3. Terms and Definitions................................................................................................................................ 5
4. General Information................................................................................................................................... 6 5 . Average Planar Linear Heat Generation Rate .......................................................................................... 7 6 . Minimum Critical Power Ratio ................................................................................................................ 15 6.1 Manual Flow Controi MCPR Limits.................................................................................................. 15 6.2. Scram Time...................................................................................................................................... 15
7. Linear Heat Generation Rate ................................................................................................................. 17 8 Stability Protection Settings .................................................................................................................... 17
9. Modes of Operation ................................................................................................................................ 18 10 Methodology......................................................................................................................................... 18 Page 2 of 18

Exelon Nuclear .Nuclear Fuels COLR Oyster Creek 1 Rev. 2 Cycle 21 Core Operating Limits Report (COLR) . Oyster Creek 1 List of Tables Table 5-1 MAPLHGR for bundle: GE9B-PSOWB348-12GZ-8OU-145-T6..................................................... 7 Table 5-2 MAPLWGR for bundle: GEl1-P9HUB374-13GZ-lOOT-l45-T6-2559........................................... 8 Table 5-3 MAPLHGR for bundle: GEll-P9HUB374-13GZ-?OOT-145-T6-2559 ........................................... 8 Table 5-4 MAPLHGR for bundle: GEll-P9HUB369-12GZ-10OT-145-T6-2560 ........................................... 9 Table 5-5 MAPLHGR for bundle: GEI 1-P9HUB369-12GZ-tOOT-145-T6-2560........................................... 9 Table 5 6 MAPLHER for bundle: GE11-PQHUB363-12GZ-IOOT-145-T6-2817 ......................................... 10 Table 5.7 MAPLHGR for bundle: GE1 1-P9HU8363-12GZ-100T-l45-^r6-2817 ......................................... 10 Table 5-8 MAPLHGR for bundle: GE11-PQHUB364-14GZ-100T-145-T6-2818......................................... 11 Table 5-9 MAPLHGR for bundle: GEl1-P9HUB364-14GZ-100T-145-T6-2818......................................... 11 Table 5-10 MAPLHGR for bundle: GEll-P9DUB367-?lGZ-lOOT-145-T6-2921....................................... 12 Table 5-11 MAPLHGR for bundle: GEll-P9DUB367-1 lG2-1OOT-145-T6-2921...................................... "12 Table 5-12 MAPLHGR for bundle: GE11 -P9OU836l-14GZ-10OT-145-T6-2922 ....................................... 13 Table 5-13 MAPLHGR for bundle: GElI-P9DUB361-14GZ-I00T-145-T6-2922....................................... 13 Table 5-14 MAPLHGR Multiplier with One ISOLATED Loop...................................................................... 14 Table 6-1 MCPR Limit for Four or Five Recirculation Loops in Service...................................................... 15 Table 6-2 MCPR Limit for Three Recirculation Loops in Service ................................................................ 15 Table 6-3GE93 K(f) Multiplier .................................................................................................................... 16 Table 6-4 GE11 K(f) Multiplier..................................................................................................................... 16 Table 8-1 OPTION tl Stability Protection Settings ...................................................................................... 17 Page 3 of 18

Exelon Nuclear - Nuclear Fuels COLR Oyster Creek 1 Rev. 2 Cycle 21 Core Operating Limits Report (COLR) -Oyster Creek

2. References
1. GNF Document, NEDE91152P, Reference 8 , General Electric Fuel Bundle Designs, April 2001.
2. GNF Document, 0000-0056-4117-SRLR, Revision 0, Supplemental Reload Licensing Report for Oyster Creek Reload 21 Cycle 21* September 2006.
3. GNF Document, 0000-0056-4117-FBIR, Revision 0, Fuel Bundle Information Report for Oyster Creek Reload 21 Cycle 21, September 2006.
4. Deleted.
5. Deleted.
6. GENE Letter, NSA02-247, Oyster Creek APRM Flow-Biased Setpoint Margin Between Scram and Rod Block for Stability Option I1Adjustment, January 2002.
7. GPU Document, Technical Evaluation of EE9B Fuel for Oyster Creek, TOR 1132, March 1994.
a. Passport EC 351249 (CAP 02004-2511)
9. EDMS Document, VM-PX-2469, Framatorne ANP Document, POWERPLEX-Ill Core Monitoring Software Specification, EMF-2469(P) Rev. 1.
10. AMERGEN ENERGY COMPANY, LLC OYSTER CREEK GENERATJNG STAJION DOCKET NU. 50-219, License No. DPR-16 1 1. Exelon Document, C-l302-226-E620-447, Rev. 0, Cycle 21 Core Loading Plan - Oyster Creek.

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Exelon Nuclear Nuclear Fuels COLR Oyster Creek 1 Rev. 2 Cycle 21 Core Operating Limits Report (COLR) - Oyster Creek

3. Terms and Definitions APLHGR Average Planar Linear Heat Generation Rate ARTS APRM, Rod Btock Monitor, and Technical Specification (Improvement)

APFIM Average Power Range Monitor EOC Beginning of Cycle BWROG Boiling Water Reactor Owners Group Coastdown Coastown occurs when full power is not achievable with ail 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 (kS cycle exposure at 100% power, 100% flow, all-rods-out, ail 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 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 PIanar 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 Page 5 of 78

Exelon Nuclear Nuclear Fuels COLR Oyster Creek 1 Rev. 2 Cycle 21 Core Operating Limits Report (COLR) - Oyster Creek 4.General Information Oyster Creek is a non-ARTS plant. Therefore, there are no ARTS-based power or flow biased APLHEA, 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 6.1. Rated core flow is 61 Mlb/hr and operation up to 110.7% of rated is licensed for this cycle. Additionally, Oyster Creek utiiizes an ELLLA operating domain which ha5 expanded the power/flow map to allow for greater operational flexibility.

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Exelon Nuclear - Nuclear Fuels COLR Oyster Creek I Rev. 2 Cycle 21 Core Operating Limits Report (COLR) Oyster Creek

5. Average Planar Linear Heat Generation Rate The MAPLHGR limits are discussed in Technical Specifications Section 3.1 O.A. The MAPLHGR limits for the lattices in each fuel type as a function of average planar exposure are given in Tables 5-1 through 5-13 for operation with zero ISOLATED RECIRCULATION LOOPS (Reference 2 and Reference 11). For operation with one ISOLATED REClRCULATtON LOOP, muitipiy the limits in fables 5-1 through 5-13 by the ISOLATED Loop multiplier listed in Table 5-14 (Reference 2). Ali lattices are defined in Reference 11.

Table 5-1 MAPLHGR for bundle: GE98-P80WE3348-12GZ-80U-l4&T6 PPLX Lattice #18, #23,#24, #25, #26, #27 GNF Lattice #3792, #3791, #3790,#3789,#3118 1 0.2 I 10.88 H 1 27.6 1 9.86 1 Page 7 of 18

Exelon Nuclear - Nuclear Fuels CQLR Oyster Creek I Rev, 2 Cycle 21 Core Operating Limits Repot? (COLR) - Oyster Creek Table 5-2 MAPLHGR for bundle: GE11-PWU8374-t 3GZ-lOOT-145-Y6-2559 PPLX Lattice #36,#35, #33, it31 GNF Lattice t5542, #5540, #5544, #5545 t

I 22.0 27.6 1 1

9.03 8.44 I! 38.6 49.6 60.6 1 8.24 8.20 8.36 1 Table 5-3 MAPLHGR for bundle: GE1l-P9HUB374-13G2-100T-145-T6-2559 PPLX Lattices #32,#34 GNF iattlees #5541, #ti543 5.5 9.65 11.0 9.60 Page 8 of 18

Exelon Nuclear - Nuclear Fuels COLR Oyster Creek 1 Rev. 2 Cycle 21 Core Operating Limits Report (COLR) - Oyster Creek Table 5-4 MAPLHGR for bundle: GE11-P9HUB389-12EZ-lOOT-1&-T6-2560 PPLX Lattlces#43, #41, #45, #46 GNF Lattices #5547, #5540, #5544, #5549 Table 5-5 MAPLHGR for bundfe: EE1l-P9HU8369-12GZ-f00T-145-T6-2560 PPLX Lattices #42, #44 GNF Lattices#5546, #5548 38.6 8.33 49.6 8.31 Page 9 of 18

Exelon Nuclear - Nuclear Fuels COLR Oyster Creek 1 Rev. 2 Cycle 21 Care Operating Limits Report (COLR) Oyster Creek Table 5-6 MAPLHGR for bundle: GE11-PBHUB363-12GZ-IOOT-145-T6-28l7 PPLX Lattices #3, #1 GNF Lattices #6783, M785 Table 5-7 MAPLHGR for bundie: GEl l-P9HUB363-12GZ-lOOT-l45-T&28l7 PPLX Lattlces #2, #& #9, #10 GNF Lattices M7S4,#6782, #6786, #6787 I

Exposure MAPLHGR AvgmPlanar I

I 5.5 11.0 16.5 I

9.94 9.73 9.43 iI 49.6 I 8.33

!I 60.6 8-29 Page 10 of 18

Exelon Nuclear - Nuclear Fuels COLR Oyster Creek 1 Rev. 2 Cycle 21 Core Operating Limits Report (COLR)- Oyster Creek Table 5-8 MAPLHGR for bundie: GEll-P9liU8364-14GZ-l OOT-145-T6-2818 PPtX Lattices #7, #5 GNF Lattices f67788, C6790 Table 5-9 MAPLHGR far bundle: GEll-P9HU8364-19GZ-100T-145-T6-2818 PPLX LatticesX6, #11 #l2, #4 CMF Lattices #6789, #6782, #6ll, a792 Page 11 of 18

Exelon Nuclear - Nuclear Fuels COLR Oyster Creek 1 Rev. 2 Cycle 21 Core Operating Limits Report (COLR) -Oyster Creek Table 5-10 MAPLHCR for bundle: GE11-P9DUB367-11GZ-1OOT-145-T6-2921 PPLX Lattices #13, #28 GNF Lattices Jt7311, #7312 Table 5-1 1 MAPLHCR for bundle: GEl I-P9DUB36?-11 GZ-lOOT-t4~-T6-2921 PPLX Lattlces #14, #la, ale, t t 7 GNF lattices #7313, #7314, t7315, #7316 I

0.2 I 9.03 1 11.0 1 9.12 I 16.5 22.0 I 9.10 9.03 U Y 60.6 i 8.11 71.7 8.15 Page 12 of 18

Exelon Nuclear - Nuclear Fuels COLR Oyster Creek 1 Rev. 2 Cycle 21 Core Operating Limits Report (COLR) - Oyster Creek fable 5-12 MAPLHGR for bundfct:CE11-PSDUB36l-14GZ-1OOT-f45-T6-2922 PPtX Lattices #29, #19 GNF Lattices it7311 #7317 Table 5-13 MAPLHGR far bundle: GEl1-P9DUB361-14GZ-100T-145-T6~2922 PPLx t M f G e S #20, #21, #2a, #%

GNF Lattices #7318, #7319,#7315, #7#7320 Page 13 of 18

Exelon Nuclear - Nuclear Fuels COLR Oyster Creek 1 Rev. 2 Cycle 21 Core Operating Limits Report (CQLR) - Oyster Creek Tabk 5-14 MAPLHGR Multiplier with One lSOLATED Loop Page 14 of t 8

Exelon Nuclear - Nuclear Fuels COLR Oyster Creek 1 Rev. 2 Cycle 21 Core Operating Limits Report (COLR) - Oyster Creek

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

6.1. Manual Flow Control MCPR Limits The flow adjusted MCPR is determined by multiplying the appiicable rated condition MCPR limit shown in Table 6-1 or 6-2 by the applicable MCPR multiplier, K(f), given in Table 6-3 or Table 6-4. The MCPR values are documented in Reference 2 while the K(f) multipliers are documented in Reference 1. Table 6-1 and Table 6-2limits are independent of APRM status changes since Reference 2 analyzes the Rod Withdrawal Error (RWE) as unblocked. The appropriate K(ff value may be determined by linear interpolation. A low flow correction factor is applied to the K(f) value for GE9 fuel (Table 6-3). The low flow correction factor applied to K(f) was obtained from Reference 7. Per Reference 1, a low flow correction factor does not apply to GEl 1 fuel (Table 6-4).

6.2. Scram Time Core average scram insertion times are determined per Technicat Specifications 3.2.B.

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 6-1 or Table 6-2. If the core average scram insertion time does no?meet the Option B criteria, but has met Option A criteria, then the appropriate MCPR value may be determinedfrom a linear interpolation between the Option A and B limits with standard mathematical rounding to two decimal places.

Table 6-1 MCPR Limit for Four or Five Recirculation Loops in Service Table 6-2 MCPR Limit for Three RecircuiationLoops in Service Page 15 of 18

Exelon Nuclear - Nuclear Fuels COLR Oyster Creek 1 Rev. 2 Cycle 21 Core Operating Limits Report (COLR) Oyster Creek -

Tabk 6-3GE9B K(f) Multlplier' il 120.0 1 1 .oo 1 50.0 l.18 40.0 1.22 Table 6-4 GE11 K(9 Multiplle?

It K

12u.0 I 1.00 n II 100.0 90.0 I 1-00 1 .# I 11 60.0 1 1.13

' Tahle 6-3 incorporates a required ION flou correction muitiplier

bhie 6-4does require a low Row correction multiplier Page 16 of I a

Exelon Nuclear - Nuclear Fuels COLR Oyster Creek 1 Rev. 2 Cycle 21 Core Operating Limits Report (COLR) - Oyster Creek

7. Lineer Heat Generation Rate The LHER limits are discussed in Technical Specifications Section 3.10.8. The maximum LHGR shall not exceed the LHGR limits as specified in Reference 3. The maximum 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 GE11 fuel (Reference 3). The exposure dependent LHGR limits are contained in Reference 3 for both GEQB fuel and GE11 fuel.
8. Stability Protection Settings The stability protectionsettings are discussed in Technical Specifications 2.3. Oyster Creek utilizes the BWROG Option It solution in the licensing stability calculations for Oyster Creek. Table 8-1 provides the analytical limit equations for APRM based stability protectionsettings and related Control Rod Block settings to support Option It implementation (Reference 2 and Reference 6).

Table &I OPTION II Stability Protectfon Settings Technical Specification 2.3.A.1 Neutron Flux, Scram APRM -

For W s 27.5 x lo5 lb / hr:

S s (I ,433 x 10") W c 24.8 where:

S = setting in percent of rated power W = recirculation flow (Ib/hr)

I Technical Specification 2.3.8 Neutron Flux, Control Rod Block For W 5 27.5 x iQ6 lb / hr:

S 5 (1.433 x 10") W c 17.5 where:

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

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Exeion Nuclear - Nuclear Fuels COLR Oyster Creek 1 Rev. 2 Cycle 21 Core Operating Limits Report (COLR) - Oyster Creek options~J Standard I ELLLA 1 ICF Five-loop Operation, Option A or 6 Yes 1 Yes I Yes Main Steam Line OOS4 I Yes I Yes Yes

, TIP OUS5 i Yes 1 Yes f Yes 1

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 (Reference 2).

  • Operation up to 67.5 Mlbhr core flow is licensed for this cycle (Reference 2).

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

Reference 8 documents the Main Steam Line 00s condition.

Reference 9 documents the allowance of TIP machines 00s.

I a. Methodology

1. GNF Document, NEDC-31462P, Oyster Creek NGS SAFER/CORECOOUGESTR-LOCA Loss-of-Coolant Accident Analysis, August 1987.
2. GNF Document, NEDE-24011-P-A-15 and Supplement NEDE-24011-P-A-I 5-US, General Electric Standard Application for Reload Fuel, September 2005.
3. GNF Document, NEDC-33065P, Rev. 0,Application of Stability Long-Term Solution Option I I to Oyster Creek, April 2002.

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