ML062960368
| 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) | |
Text
I_ AmerGev Energy Company, LLC www.exelo::co!p corn An Exelon Company 200 Exelon 'jliay Keniiett Sq~mre, PA 19348 TS 6.9.1 .f.4 21 30-06-2041 5 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: nocW 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 COLR Oyster Creek 1 Rev. 2 Exeion Nuclear - Nuckar Fuels Cycte 21 Care Operating Limits Repart (COLR) - Oyster Creek Cycte 21 Gore Operating Limits Report (COLR) - Oyster Creek I io /lJ/h _11- Reviewed:
SQR 5ats Reactor Engineering
/.?&- JI NR Design Manager uam Paga t of ?&
Exeion Nuclear . Nuclear Fuels Cycle 21 Core Operating Limits Report (COLR) . Oyster Creek COLR Oyster Creek 1 Rev . 2 Table of Contents 1 . List of Tables .............................................................................................................................................
3 2 . References
................................................................................................................................................
4 3 . Terms and Definitions
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5 4 . General Information
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6 5 . Average Planar Linear Heat Generation Rate ..........................................................................................
7 6 . Minimum Critical Power Ratio
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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
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18 10 . Methodology
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18 Page 2 of 18 Exelon Nuclear . Nuclear Fuels Cycle 21 Core Operating Limits Report (COLR) . Oyster Creek COLR Oyster Creek 1 Rev . 2 1 . List of Tables Table 5-1 MAPLHGR for bundle: GE9B-PSOWB348-12GZ-8OU-145-T6
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7 Table 5-2 MAPLWGR for bundle: GEl1-P9HUB374-13GZ-lOOT-l45-T6-2559
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8 Table 5-3 MAPLHGR for bundle: GEll-P9HUB374-13GZ-?OOT-145-T6-2559
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8 Table 5-4 MAPLHGR for bundle: GEll-P9HUB369-12GZ-10OT-145-T6-2560
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9 Table 5-5 MAPLHGR for bundle: GEI 1-P9HUB369-12GZ-tOOT-145-T6-2560
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9 Table 56 MAPLHER for bundle: GE11-PQHUB363-12GZ-IOOT-145-T6-2817
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10 Table 5.7 MAPLHGR for bundle: GE1 1-P9HU8363-12GZ-100T-l45-^r6-2817
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10 Table 5-8 MAPLHGR for bundle:
GE11-PQHUB364-14GZ-100T-145-T6-2818
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11 Table 5-9 MAPLHGR for bundle:
GEl1-P9HUB364-14GZ-100T-145-T6-2818
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11 Table 5-10 MAPLHGR for bundle: GEll-P9DUB367-?
lGZ-lOOT-145-T6-2921
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12 Table 5-11 MAPLHGR for bundle: GEll-P9DUB367-1 lG2-1OOT-145-T6-2921
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"12 Table 5-12 MAPLHGR for bundle: GE11 -P9OU836l-14GZ-10OT-145-T6-2922
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13 Table 5-13 MAPLHGR for bundle: GElI-P9DUB361-14GZ-I00T-145-T6-2922
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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 6-3 GE93 K(f) Multiplier
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16 Table 6-4 GE11 K(f) Multiplier
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16 Table 8-1 OPTION tl Stability Protection Settings ......................................................................................
17 Page 3 of 18 Exelon Nuclear - Nuclear Fuels Cycle 21 Core Operating Limits Report (COLR) -Oyster Creek COLR Oyster Creek 1 Rev. 2 2. References
- 1. 2. 3. 4. 5. 6. 7. a. 9. 10. GNF Document, NEDE91152P, Reference 8, "General Electric Fuel Bundle Designs,"
April 2001. GNF Document, 0000-0056-41 17-SRLR, Revision 0, "Supplemental Reload Licensing Report for Oyster Creek Reload 21 Cycle 21 * September 2006. GNF Document, 0000-0056-41 17-FBIR, Revision 0, "Fuel Bundle Information Report for Oyster Creek Reload 21 Cycle 21 ," September 2006. Deleted. Deleted. GENE Letter, NSA02-247, "Oyster Creek APRM Flow-Biased Setpoint Margin Between Scram and Rod Block for Stability Option I1 Adjustment", January 2002. GPU Document, 'Technical Evaluation of EE9B Fuel for Oyster Creek", TOR 1132, March 1994. Passport EC 351249 (CAP 02004-251
- 1) EDMS Document, VM-PX-2469, Framatorne ANP Document, "POWERPLEX-Ill Core Monitoring Software Specification", EMF-2469(P)
Rev. 1. AMERGEN ENERGY COMPANY, LLC OYSTER CREEK GENERATJNG STAJION DOCKET NU. 50-21 9, License No. DPR-16 1 1. Exelon Document, C-l302-226-E620-447, Rev. 0, "Cycle 21 Core Loading Plan - Oyster Creek." Page 4 of 18 Exelon Nuclear - Nuclear Fuels Cycle 21 Core Operating Limits Report (COLR) - Oyster Creek COLR Oyster Creek 1 Rev. 2 3. Terms and Definitions APLHGR ARTS APFIM EOC BWROG Coastdown ELLLA EOC EOR GNF ICF ISOLATED K(f) LHGR LPRM MAPLHGR MCPR 00s Option A Option B TIP Average Planar Linear Heat Generation Rate APRM, Rod Btock Monitor, and Technical Specification (Improvement) Average Power Range Monitor Beginning of Cycle Boiling Water Reactor Owners Group Coastown occurs when full power is not achievable with ail rods out, maximum allowable core flow and feedwater temperature reduction, and equilibrium xenon Extended Load Line Limit Analysis End of Cycle End of Rated Conditions (kS cycle exposure at 100% power, 100% flow, all- rods-out, ail feedwater heaters in service and equilibrium xenon) Global Nuclear Fuel Increased Core Flow The recirculation loop suction, discharge and discharge bypass valves are in the closed position MCPR flow dependent multiplier flows less than rated) Linear Heat Generation Rate Local Power Range Monitor Maximum Average PIanar Linear Heat Generation Rate Minimum Critical Power Ratio Out of Service Option A refers to the Technical Specifications core average scram time speed that when applied results in a more restrictive MCPR limit Option B refers to a specific core average scram time speed that when met allows the use of a lower MCPR limit Traversing In Core Probe adjustment to the CPR limit when at core Page 5 of 78 Exelon Nuclear - Nuclear Fuels Cycle 21 Core Operating Limits Report (COLR) - Oyster Creek COLR Oyster Creek 1 Rev. 2 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 1 10.7% 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.
Page 6 of 18 Exelon Nuclear - Nuclear Fuels Cycle 21 Core Operating Limits Report (COLR) - Oyster Creek COLR Oyster Creek I Rev. 2 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 Cycle 21 Core Operating Limits Repot? (COLR) - Oyster Creek CQLR Oyster Creek I Rev, 2 I 1 22.0 9.03 27.6 8.44 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 38.6 1 8.24 49.6 8.20 ! 60.6 1 8.36 1 Table 5-3 MAPLHGR for bundle: GE1 l-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 Cycle 21 Core Operating Limits Report (COLR) - Oyster Creek COLR Oyster Creek 1 Rev. 2 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-f 00T-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 Cycle 21 Care Operating Limits Report (COLR) - Oyster Creek COLR Oyster Creek 1 Rev. 2 Table 5-6 MAPLHGR for bundle: GE11 -PBHUB363-12GZ-I OOT-145-T6-28l7 PPLX Lattices #3, #1 GNF Lattices #6783, M785 Table 5-7 MAPLHGR for bundie: GEl l-P9HUB363-12GZ-l OOT-l45-T&28l7 PPLX Lattlces #2, #& #9, #10 GNF Lattices M7S4, #6782, #6786, #6787 AvgmPlanar Exposure I MAPLHGR I 11.0 ! 9.73 ii 5.5 I 9.94 -- I 16.5 ! 9.43 I --.- !I 49.6 I 8.33 60.6 8-29 Page 10 of 18 Exelon Nuclear - Nuclear Fuels Cycle 21 Core Operating Limits Report (COLR) - Oyster Creek COLR Oyster Creek 1 Rev. 2 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 CMF Lattices #6789, #6782, #6"ll, a792 PPLX Lattices X6, #11 #l2, #4 Page 11 of 18 Exelon Nuclear - Nuclear Fuels Cycle 21 Core Operating Limits Report (COLR) -Oyster Creek COLR Oyster Creek 1 Rev. 2 Table 5-1 0 MAPLHCR for bundle: GE11 -P9DUB367-11 GZ-1 OOT-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, tt7 GNF lattices #7313, #7314, t7315, #7316 I 0.2 I 9.03 1 11.0 1 9.12 I I 16.5 9.10 22.0 9.03 U Y 60.6 i 8.11 71.7 8.15 Page 12 of 18 Exelon Nuclear - Nuclear Fuels Cycle 21 Core Operating Limits Report (COLR) - Oyster Creek COLR Oyster Creek 1 Rev. 2 fable 5-1 2 MAPLHGR for bundfct: CE1 1-PSDUB36l-14GZ-1 OOT-f45-T6-2922 PPtX Lattices #29, #19 GNF Lattices it7311 #7317 Table 5-13 MAPLHGR far bundle: GEl1-P9DUB361-14GZ-100T-145-T6~2922 GNF Lattices #7318, #7319, #7315, #7#7320 PPLx tMfGeS #20, #21, #2a, #% Page 13 of 18 Exelon Nuclear - Nuclear Fuels Cycle 21 Core Operating Limits Report (CQLR) - Oyster Creek COLR Oyster Creek 1 Rev. 2 Tabk 5-14 MAPLHGR Multiplier with One lSOLATED Loop Page 14 of t 8 Exelon Nuclear - Nuclear Fuels Cycle 21 Core Operating Limits Report (COLR) - Oyster Creek COLR Oyster Creek 1 Rev. 2 6. MlnCmum Critical Power Ratio The MCPR limits are discussed in Technical Specifications Section 3.1 O.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 6-2 limits 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 determined from 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 Recircuiation Loops in Service Page 15 of 18 Exelon Nuclear - Nuclear Fuels Cycle 21 Core Operating Limits Report (COLR) - Oyster Creek Tabk 6-3 GE9B K(f) Multlplier' il 1 .oo 1 120.0 1 50.0 l.18 40.0 1.22 Table 6-4 GE11 K(9 Multiplle?
It 12u.0 I 1.00 n K II 100.0 1-00 90.0 I 1 .# I 11 60.0 1 1.13 ' Tahle 6-3 incorporates a required ION flou correction muitiplier
bhie 6-4 does require a low Row correction multiplier COLR Oyster Creek 1 Rev. 2 Page 16 of I a Exelon Nuclear - Nuclear Fuels Cycle 21 Core Operating Limits Report (COLR) - Oyster Creek COLR Oyster Creek 1 Rev. 2 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 protection settings 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 protection settings 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) Page 17 of 18 Exeion Nuclear - Nuclear Fuels Cycle 21 Core Operating Limits Report (COLR) - Oyster Creek options'~J Five-loop Operation, Option A or 6 COLR Oyster Creek 1 Rev. 2 Standard I ELLLA 1 ICF' Yes 1 Yes I Yes Main Steam Line OOS4 I Yes I Yes Yes , TIP OUS5 i Yes 1 Yes f Yes 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). level is 40% per GESTAR.
1 Each operational mode may be coincident with caastdown operation.
The minimum coastdown power 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 II to Oyster Creek," April 2002. Page 18 OF 18