ML061530472

Issuance of the Oyster Creek Core Operating Limits Report for Cycle 20, Revision 1

ML061530472
Person / Time
Site:	Oyster Creek
Issue date:	06/02/2006
From:	Cowan P AmerGen Energy Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2130-06-20344
Download: ML061530472 (17)

Text

TS 6.9.1.f.4 2 1 30-06-20344 June 2,2006 US. Nuclear Regulatory Commission Attention: Document Control Desk Washington DC 20555 Oyster Creek Generating Station Facility Operating License No. DPR-16 et NO. 50-319

Subject:

Issuance of the Oyster Creek Core Operating Limits Report For Cycle 20, Revision 1 Enclosed is a copy of the Core Operating Limits Report (COLR) for Oyster Creek Generating Station, Cycle 20, Revision 1. Revision 1 of this report incorporates updated Maximum Average Planar Linear Heat Generation Rate limits.

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 do not hesitate to contact us.

Very truly yours, Pamela B. Cowan Director - Licensing and Regulatory Affairs AmerGen Energy Company, LLC 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

Exelon Nuclear - Nuclear Fuels Oyster Creek 1 Cycle 20 COLR I

COLR Oyster Creek 1 Rev. 1 Oyster Creek 1 Cycle 20 Core Operating Limits Report (COLR) 1 I

Reviewed:

$/33/06 Date Reactor Engineering Approved:

5-

/4-06 Date Page 1 of 16

Exelon Nuclear - Nuclear Fuels Oyster Creek 1 Cycle 20 COLR I

COLR Oyster Creek 1 Rev. 1 Table of Contents

1. References...............................................................................................................................................

4

2. Terms and Definitions................................................................................................................................ 5

3. General Information...................................................................................................................................6

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

5. Minimum Critical Power Ratio................................................................................................................

13 5.1. Manual Flow Control MCPR Limits..................................................................................................

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

13

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

15 I

7. Stabtflty Protection Settings..........................................................................................

L......................... 15

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

16 9, Methodology........................................................................................................................................... 16 Page 2 of 16 I

Exelon Nuclear.

Nuclear Fuels Oyster Creek 1 Cycle 20 COLR COLR Oyster Creek 1 Rev. 1 I

I Li of Tables 7

Table 4-1 MAPLHGR for bundle: GE98-P8DWB348-12GZ-8OU-145-T6.....................................................

7 Table 4-2 MAPLHGR for bundie: GE9B-P8DWB338-1 lGZ-80U-145-T6..................................................... 8 Table 4-3 MAPLHGR for bundle: GEl l-P9HU8374-13GZ-lOOT-l45-T6-2559 8

Table 4-4 MAPLHGR for bundle: GE11 -P9HUB374-13GZ-lOOT-l45-T6-2559 9

Table 4-5 MAPLHGR for bundle: GE11 -P9HUB369-12GZ-lOOT-145-T6-2560...........................................

9 I,

Table 4-6 MAPLHGR for bundle: GEl 1 -P9HUB369-12GZ-lOOT-145-T6-2560 10 Table 4-7 MAPLHGR for bundle: GEll-P9HUB363-12GZ-100T-145-T6-2817

......................................... 10 Table 4-8 MAPLHGR for bundle: GEll-P9HUB363-12GZ-IOOT-145-T6-2817

......................................... 11

. Table 4-9 MAPLHGR for bundle: GEll-P9HUB364-14GZ-lOOT-145-T6-2818

......................................... 11 Table 4-10 MAPLHGR for bundle: GE1l-P9HUB364-14GZ-lOOT-145-T6-2818

....................................... 12 Table 4-1 1 MAPLHGR Multiplier with One ISOLATED Loop......................................................................

12 Tab1 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 GE9B K(f) Multiplier........................,...........................................................................................

14 I

6

?

Table 5-4 GE11 K(f) Multiplier.....................................................................................................................

14 Table 7-1 OPTION II Stability Protection Settings...................................................................................... 15 Page 3 of 16

I Exelon Nuclear - Nuclear Fuels Oyster Creek 1 Cycle 20 COLR COLR Oyster Creek 1 Rev. 1 1, References

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

2.

GNF Document, 0000-0029-31 51 -SRLR, Revision 1, Suppi~mental Reload Licensing Report for Oyster Creek Reload 20 Cycle 20, September 2004.

3.

GNF Document, 0000-OO29-3151-FBIR, Revision 0, Fuel Bundle Information Repwt for Oyster Creek Reload 20 Cycle 20, October 2004.

4. OPL3 Parameters for Oyster Creek Cycle 20 Transient Analysis, eDRF 00005026-5261, July 29,2004.

5.

Deleted.

I

6. GENE Document, NSA02-247, Oyster Creek APR M Ftow-Biased Setpoint Margin Between I

I t

Scram and Rod Block for Stability Option I1 Adjustment, January 2002.

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

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

9.

Framatome ANP Document, POWERPLEX-IJI Core Monitoring Software Specification, EMF-2469(P) Rev. 1.

NO. 50-21 9, Licqnse No. DPR-16

10. AMERGEN ENE;RGY COMPANY, LLC OYSTER CREEK GENERATING STATION DOCKET I Page 4 of I6

Exelon Nuclear -,Nuclear Fuels Oyster Creek 1 Cycle 20 COLR I

COLR Oyster Creek 1 Rev. 1 I

2. ems and Definitions T

APWGR ARTS Average Planar Linear Heat Generation Rate APRM Rod Block Monitor Technical Specification (Improvement)

APRM Average Power Range Monitor BOC Beginning of Cycle BWROG 1

I /

Boiling Water Reactor Owner's Group Coastdown Coastown occurs when full power is not achievable with alf rods out, maximum allowable core flow and feedwater temperature reduction, and equilibrium xenon ELLLA EOC End of Cycle Extended Load Line Limit Analysis EOR End of Rated Conditions (Le., cycle exposure at 100% power, 100% flow, all- '

rods-out, all feedwater heaters in service and equilibrium xenon)

GNF Gfobal Nuclear Fuel

',CF Increased Core Flow ISOLATED The recirculation loop suction, discharge and discharge bypass valves are in the closed position MCPR flow dependent multiplier (Le., adjustment to the CPR limit when at core flows less than rated)

K(f)

LWGR LPRM MAPLHGR MCPR 00s Option A Option B TIP Linear Heat Generation Rate Local Power Range Monitor Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio Out of Service Option A refers to the Technicai 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 Page 5 of 16

Exeion Nuclear - Nuclear Fuels Oyster Creek 1 Cycle 20 COLR I

COLR Oyster Creek 1 Rev. 1

3. General Information I

This revision is being performed to update MAPLHGR limits as a result of issue Report 487185.

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 Mfblhr and operation up to 110.7% 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, Page 6 of 16

I Exelon Nuclear - Nuclear Fuels Oyster Creek 1 Cycle 20 COLR COLR Oyster Creek 1 Rev. 1 1

4, 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 4-1 through 4-1 0 for operation with zero ISOLATED RECIRCULATION LOOPS (Reference 2). For I operation with one ISOLATED RECIRCULATION LOOP, multiply the limits in Tables 4-1 through 4-10 by the ISOLATED Loop multiplier listed in Tabie 4-1 1 (Reference 2).

Table 4-1 MAPLHGR for bundle: GE9B-P8DWB34&12GZ-80U-l45-T6 PPLX Lattice #18, #23, #24, #25, #26, #27 GNF Lattice #3792, #3791, #3790, #3789, #3118 I

5.5 11.30 f f

I 16.5 I

10.79 Page 7 of 16

I Exelon Nuclear - Nuclear Fuels Oyster Creek 1 Cycle 20 COLR COLR Oyster Creek 1 Rev. 1 I

Table 4-2 MAPLHGR for bundle: GE95P8DWB338-11 GZ-SOU-1 45-76 GNF Lattice #3734, #3788, #3787, w3786, #3785, #3118 I

' PPLX Lattice #17, #18, #19, #20,'#21, #22 I

Table I

I 13.8 11.11 n

16.5 10.68 19.3 I

9.96 c

71.7 I

9.67 I

4-3 MAPLHGR for bundle: GE11-PQHUB374-13GZ-1 PPLX Lattice #36, #35, #33, #31 GNF Lattice #5542, C5540, #5544, #554!5 I

I I

I I

I I

Page 8 of 16 I

I I,

I 1

I Exelon Nuclear - Nuclear Fuels Oyster Creek 1 Cycle 20 COLR COLR Oyster Creek 1 Rev. 1 J

Table 4-4 MAPLHGR for bundle: GE11-PQHUB374-1362-100T-145-T6-2559 PPLX Lattices #32, #34 GNF Lattices #5541, #5543 Table 4-5 MAPLHGR for bundle: GE11-P9HUB369-12GZ-100T-145-T62560 PPLX Lattices #43, #41, #45, #46 GNF Lattlces #5547, #5540, #5544, #5548 I '

i I

Page 9 of 16

I Exelon Nuclear - Nuclear Fuels Oyster Creek 1 Cycle 20 COLR COLR Oyster Creek 1 Rev. 1 Table ks MAPLHGR for bundle: GEl1-P9HU836812G2-1 OOT-14!5-T6-2560 GNF Lattices #5546, #5548 I

PPLX Lattices #42, #44' Table 4-7 W L H G R for bundle: GEll-P§HUB363-12GZ-l OOT-l45-T6-2817 P P U Lattices #3, #1 GNF Lattices #6783, #b785 I

Page 10 of 16

I Exelon Nuclear,- Nuclear Fuels Oyster Creek 1 Cycle 20 COLR I

COLR Oyster Creek 1 Rev. 1 Table 4-8 MAPLHGR for bundle: GEl l-P9HUB363-12GZ-l OOT-l&-T6-2817 PPLX Lattices #2, #8, #9, #lo GNF Lattices #6784, #6782, #6786, #6787 0.2 I

10.04 1.1 10.10 i

Table 4-9 MAPLHGR for bundle: GE1 l-P9HUB364-14GZ-j OOT-l45-T6-2818 PPLX Lattices #7, #5 GNF Lattices #6788, #6790 I

5.5 9.85 n

71.7 I

8.50 I

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Exelon Nuclear - Nuclear Fuels Oyster Creek 1 Cycle 20 COLR I

COLR Oyster Creek 1 Rev. 1 Table 4-10 MAPLHGR for bundle: GE1 l-P9HUB364-14GZ-100T-l4!%T6-2818 PPLX Lattices #8, #11, #12, #4 GNF Lattices #6789, #6782, #6791, M792 1

\\

i Table 4-1 1 MAPLHGR Muftiplier with One ISOLATED Loop Page 12 of 16

Exelon Nuclear - Nuclear Fuels Oyster Creek 1 Cycle 20 COLR I

COLR Oyster Creek 1 Rev. 1

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 Ktf) 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 GEl1 fuel (Table 5-4). The low flow correction factor applied to K(f) was obtained from Reference 7.

5.2. Scram Time I

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. If 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.

I Table 5-1 MCPR Limit for Four or Fke Recirculation Loops in Service I

Cycle Exposure I

Option BOC to EOR-2205 MWDfMT 2 EOR-2205 MWDlMT to EOC 1.47 1.51

~

Table 5-2 MCPR Limit for Three Recirculation Loops In Service I

I Page 13 of 16

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I Exelon Nuclear - Nuclear Fueis Oyster Creek 1 Cycle 20 COLR COLR Oyster Creek 1 Rev. 1 I

Table 5-3 GESB K(9 Multiplier'

\\

Flow

(% rated)

Table 5-4 GE11 K(f) Multlplie?

'low 1

K(f)

(% rated)

I Table 5-3 incorporates a required low flow correction multiplier

'Table 5-4 does ~JQ& require a low flow correction multiplier Page 14 of 16

I Exelon Nuclear - Nuclear Fuels Oyster Creek 1 Cycle 20 COLR COLR Oyster Creek 1 Rev. 1 I

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 maximum values at beginning of life are a function of fuel type; these values are 13.4 (kwlft) for GESB fuel (Reference 3) and 12.0 (kWlft) for GEl1 fuel (Reference 3). The exposure dependent LHGR limits are contained in Reference 3 for both GESB fuel and GE11 fuel.

7. Stability Protection Settings The stability protection settings are discussed in Technical Specifications 2.3. Oyster Creek utilizes the BWROG Option II 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 I I implementation (Reference 2 and Reference 6).

I I

I Table 7-1 OPTION II Stability Pratection Settings Technical Specification 2.3.A.1 Neutron Flux, Scram - APRM Fod W s 27.5 x loe lb I hr:

S 5 (1.433 x lo*) W + 24.8 I

where:

S = setting in percent of rated ppwer W = recirculation flow (lb/hr)

Technical Specification 2.3.B Neutron Flux, Control Rod Block For W 5 27.5 x 10' Ib / hr:

S S (1.433 x 10") W i 17.5 where:

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

Page 15 of 16 I

1 Exelon Nuclear - Nuclear Fuels Oyster Creek 1 Cycle 20 COLR I

Operating Region Options'*'

Standard I ELLLA lCV Five-loop Operation, Option A or B Yes 1

Yes

' Yes Four-loop Operation, Option A or B Yes Yes Yes Three-loop Operation, Option A or B Yes Yes Yes Main Steam Line 00s' Yes Yes Yes TIP 00s' Yes f

Yes Yes,

\\

I 8, bodes of Operation The allowed Modes of Operation are as described below:

I COLR Oyster Creek 1 Rev. 1 I

I

' 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 Mlblhr core flow is licensed for this cycle.

Each operational mode may be coincident with coastdown operatiw. The minimum coastdown power' Reference 8 documents the Main Steam Line 00s condition.

Reference 9 documents the allowance of TIP machines 00s.

3 level is 40Y0.

I

9. Methodology

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

2. GNF Document, NEDE-24011 -P-A-14 and Supplement NEDE-2401 l-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 I1 for Oyster Creek," April 2002.

Page 16 of 16