ML060550403

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Issuance of the Core Operating Limits Report for Clinton Power Station, Unit 1, Cycle 11
ML060550403
Person / Time
Site: Clinton Constellation icon.png
Issue date: 02/23/2006
From: Bement R
AmerGen Energy Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
U-603759
Download: ML060550403 (17)
v • d • e


Text

U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 JLP/bIf Attachment CC: Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-46.1

Subject:

Issuance of the Core Operating Limits Report for Clinton Power Station, Unit 1, Cycle 11 In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)," Item d., AmerGen Energy Company (AmerGen), LLC is submitting the COLR for Clinton Power Station, Unit 1, Cycle 11. Should you have any questions concerning this report, please contact Mr. Bill Iliff, Regulatory Assurance Manager, at (217) 937-2800. Robert S. libment Site Vice President Clinton Power Stati trator - NRC Region III Senior Resident Inspector - Clinton Power Station 10CFR5&36 LIE03759 February 23, 2006 Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 Page 1 of 16 Rev. 2 CLI C1 1 Core Operating Limits Report CORE OPERATING LIMITS REPORT FOR CLINTON POWER STATION UNIT 1 CYCLE 11 004 , 'A I L ~tei - -

Exelon Nuclear - Nuclear Fuels DOG ID: COLR Clinton 1 CL1 C1 1 Core Operating Limits Report Page 2 of 16 Rev. 2 Tahlp of Cnntants Page 1.0 Terms and Definitions 4 2.0 General information 5 3.0 MAPLHGR Limits 6 4.0 MCPR Limits 7 5.0 Linear Heat Generation Rate Limits 11 6.0 Reactor Protection System (RPS) Instrumentation 14 7.0 Stability Protection Setpoints 14 8.0 Modes of Operation 15 9.0 Methodology 15 10.0 References 16 Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I CL1 C1 1 Core Operating Limits Report Page 3 of 16 Rev. 2 Table 3-1 MAPLHGR for all GE14C Fuel Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier Table 4-1 Operating Limit Minimum Critical Power Ratio Power Dependent MCPR Limit Adjustments and Mult Table 4-3 Flow Dependent MCPR Limits MCPR(F) Single Loop Oper Table 5-1 Linear Heat Generation Rate Limits for U02 Rods PR(P) 9 10 10 11 Table 5-2 Linear Heat Generation Rate Limits for Gad Rods 12 Table 5-3 Power Dependent LHGR Multiplier LHGRFAC(P) 12 Table 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F) 12 Table 5-5 LHGR Single Loop Operation (SLO) Reduction Factor 13 Table 5-6 Power Dependent LHGR Multiplier LHGRFAC(P)

Table 4-2 Table 14 Table 5-7 Flow Dependent LHGR Multipl (Loss of 'FULL' Feedwater Hea 11st of Tables (SLO) Flow Dependent MCPR Limits MCPR(F) (Loss of 'FULL' Feedwater Heating) 13 LHGRFAC(F)

Page 13 Table 7-1 OPRM PBDA Trip Setpoints 14 Table 8-1 Modes of Operation 15 Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I CL1 C1 1 Core Operating Limits Report Page 4 of 16 Rev. 2 1.0 Terms and Definitions Base Case A case analyzed with two (2) Safety-Relief Valves Out-of-Service (OOS), one (1) ADS valve OOS, and up to a 50'F feedwater temperature reduction (FWTR includes feedwater heater OOS or final feedwater temperature reduction) at any point in the cycle operation in Dual Loop mode (Reference 3). Coastdown The reactor condition where thermal power gradually decreases due to fuel depletion while the following conditions are met: 1) all operable control rods are fully withdrawn and 2) all cycle extension techniques have been exhausted including FFWTR and ICF. DLO Dual Reactor Rec rculation Loop Operation FFWTR Final Feedwater Temperature Reduction FWHOOS Feedwater Heaters Out of Service ICF Increased Core Flow LHGR Linear Heat Generation Rate LHGRFAC(F)

LHGR thermal limit flow dependent adjustments and multipliers LHGRFAC(P)

LHGR thermal limit power dependent adjustments and multipliers MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(P) MCPR thermal limit power dependent adjustments and multipliers MCPR(F) MCPR thermal limit flow dependent adjustments and multipliers OLMCPR Operating Limit Minimum Critical Power Ratio SLMCPR Safety Limit Minimum Critical Power Ratio SLCO Single Reactor Recirculation Loop Operation Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CL1 C1 1 Core Operating Limits Report Page 5 of 16 Rev. 2 2.0 General Information This report is prepared in accordance with Technical Specification 5.6.5 of Reference

1. Power and flow dependent limits are listed for various power and flow levels. Linear interpolation is to be used to find intermediate values. The data presented in this report including: Extended Load fine Limit down to 99% of rated core flow during full power operation increased Core Flow (ICF) up to 107% of rated core flow Final Feedwater Temperature Reduction (FFWTR) up to 50oF during cycle extension operation Feedwater Heater Out of Service (FWHOOS) up to 50cF feedwater temperature reduction at any time during the cycle prior to cycle extension. alid for all li operating domains on the operating map, Exelon Nuclear - Nuclear Fuels CL1 C1 1 Core Operating Limits Report 3.0 MAIPLHGR Limits 3.1 Technical Specific I Linear interpola Sections 3.2.1 and 3.4.1. 3,2 Description

Reference:

Table 3-1 is used to determine the maximum average planar linear heat generation rate (MAPLHGR) limit for each fuel type. Limits listed in Table 3-1 are for dual reactor recirculation loop operation (DI-0). For single reactor recirculation loop opera must be multiplied by a SLO MAPLHGR multipi ier for GE14 fuel is 0.76 (Reference 3). Table 3-1 MAPLHGR for all GE14C Fuel (Reference 3 and 13) Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference

3) ints not listed in Table 3-t. Page 6 DOC ID , COLIR Clinton I Page 6 of 16 Rev. 2 , the MAPLHGR limits given in Table 3-1 er provided in Table 3-2. The SLO MAPLHGR Fuel MAPLHGR Type SLO Multiplier GE14C 1 0.76 Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I CL1 C1 1 Core Operating Limits Report Page 7 of 16 Rev. 2 TO PACPR Limits 4.1 Technical Sped 4,2 Description , 112 and 3.4.1

Reference:

The various MCPR limits are described below, 4.2.1 Manual Flow Control MCPR Limits The Operating Limit MCPR (OLMCPR) is determined from either section 4.2.1.1 or 4.2.1.2, whichever is greater at any given power and flow condition, 4.2.1.1 Power-Depandent M CPR For operation less than or equal to 33,3% core thermal power, the OLIVICPR as a function of core thermal power is shown in Table 4-2. For operation at greater than 33.3% core thermal power, the OLMCPR as a function of core thermal power is determined by multiplying the applicable rated condition OLIVICPR limit shown in Table 4-1 by the applicable MCPR multiplier K(P) given in Table 4-2. 4.2.1.2 Flow-Dependent MCPR Tables 4-3 through 04 give the MCPR(F) as a function of flow based on the applicable plant condition, The limits for dual loop operation are listed in Tables 4-3. The limits for single loop operation are listed in Tables 4-4. The MCPR(F) determined from these tables is the flow dependent OLMCPR. 4.2.2 Automatic Flow Control MCPR Limits Automatic Flow Control MCPR Lim vided.

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CL1 C1 I Core Operating Limits Report Page 8 of 16 Rev. 2 4.2.3 AW Option A and Option B refer to use of scram speeds for establishing MCPR operating A and-Qp1jDn3 Option A scram speed is the BWR/6 Technical Specification scram speed. The Technical Specification scram speeds must be met to utilize the Option A MCPR limits, Reload analyses performed by GNF for Cycle 11 Option A MCPR limits utilized a 20% core average insertion time of 0.516 seconds (Reference 15). 14 Me the MCPR limits for the Option B scram speed, the cycle average scram insertion time for 20% insertion must satisfy equation 2 in Reference 5 Section 4. If the cycle average scram insertion time does not meet the Option B criteria, the appropr MCPR value may be determined from a linear interpolation between the Option A and B limits as specified by equation 4 in Reference 5 Section 4. Won Flaw Control valve a114 affi= Cycle 11 was analyzed with a maximum core flow runout of 109%; therefore the recirculation flow control valve must be set to maintain core flow less than 109% (92.105 Mlb/hr) for all runout events (Reference 14).

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I CL1 C1 1 Core Operating Limits Report Page 9 of 16 Rev. 2 Notes for Table 4-2: Operat EOOS Combbati Base Case Base Case ETO 1. Values are interpolated between relevant power levels. 2. Allowable EOOS conditions are listed in Section 8. le 4-1 MR Minimum Critical Power Ratio Tattle 4-2 Power Dependent MCPR Limit Adjustments and Multipliers MCPR(P) (Reference 7 and 11) (Reference

3) !on B I nosures Ooti L all 1 1.28 130 1 1.31 133 Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I CL1 CI 1 Core Operating Limits Report Page 10 of 16 Rev. 2 Flow Dependent MCPR Limits MCPR(F) 1 (Reference 7 and 11) Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) (Reference 7 and 11) Table 4-3 Table 4-4 erpolation should be used for points not listed in Table 4-3. 2 Linear interpolation should be used for points not listed in Table 4-4. Page 1 0 Core Flow (16 rated) MCPR(F) 0 t8755 25 11954 9318 120 109 120 DOC ID: COLR Clinton 1 CL1 CI 1 Core Operating Limits Report Page 11 of 16 Rev. 2 Exelon Nuclear - Nuclear Fuels 5.0 Linear Heat Generation Rate Limits 5.1 Technical Specification Referenne: Section 3.2.3 and 3.4.1. 52 Description
eat generation rate (LHGR) limit is the product of the exposure dependent LHGR able 5-1 for U02 fuel rods and Tables 5-2 for Gadolinia fuel rods) and the minimum of: the power dependent LHGR Factor, LHGRFAC(P), the flow dependent LHGR Factor, LHGRFAC(F), or the single loop operation (SLO) multiplication factor if applicable. The LHGRFAC(P) is determined from Table 5-3. The LHGRFAC(F) is determined from Table 5-4. The SLO multiplication factor can be found in Table 5-5. Tables 5-1 and 5-2 are the LHGR limit as a function of peak pellet exposure. The Gadolinia fuel rod limits in Tables 12 are the most limiting Gadolinia fuel rods. The most limiting values are provided here as a convenience and do not imply that all the Gadolinia fuel rods must satisfy the listed values. For Loss of 'FULL' Feedwater Heating {+/-10 'F of design NORMAL temperature), LHGRFAC(P) is determined from Table 5-6 and LHGRFAC(F) is determined from Table 5-7. Concurrent operation with SLO and reduced feedwater heating has not been evaluated and thus not a valid operating mode. (Reference 3, 7, 8, 9 and 10) Table 5-1 Linear Heat Generation Rate Limits for U02 Rods (Reference 4 and 12) I Linear interpolation should be used for points not listed in Table 5-Y The values listed in Table 5-1 are limiting for all bundle types. Page 11 Peak Pellet LHGR Exposure ~ Limit A2Wd/ST (kWIft) 0.00 13AO 1411 1140 5161 820 6150 510 Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CL1 C1 1 Core Operating Limits Report Page 12 of 16 Rev. 2 1 2 3 Table 92 Linear Heat Generation Rate Limits for Gad hods (Reference 4 and 12) Table 5-3 Power Dependent LHGR Multiplier LHGRFA (Reference 7 and 11) Flow Dependent LHGR Multiplier t.HGRFAC(F}

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Linear interpolation should be used for points not listed in Table 5-2. The values lived in Table 02 are limiting for all bundle types. Linear interpolation should be used for points not listed in Table 5-3. Linear interpolation should be used for points not listed in Table 5-4. Table 6-4 Page 1 2 Core Thermal Power- (!/;,-Rated)

EOOS Combination Core Flow >33.3 100 FAG(P) s 50 0.634 0.634 0,689 0----- F- Base case > 50 0.572 0.572 2.600 .0-9 1 1.000 .11 I- -5Q 1 0.634 - 0.634 0.689 Base Case SLO > 50 0. 572 17U72 0.600 0.689 1 1.000 Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CLIC11 Core Operating Limits Report Page 13 of 16 Rev. 2 1 2 LHGR Single Loop Operation (SLO) Reduction Factor (Reference

3) Fuel Type Table 5-5 GE14C _I 0.76 Table 5-6 Power Dependent LHGR Multiplier LHGRFAC(P) (Loss of `FULL' Feedwater Heating (Reference 7, 8, 9, 10 and 11) Table 5-7 Flow Dependent LHGR Multiplier LHGRFAC(F) (Loss of 'FULL' Feedwater Heating) (Reference 7, 8, 9, 10 and 11) Linear interpolation should be used for points not listed in Table 5-6. Linear interpolation should be used for points not listed in Table 5-7. Page 13 LHGR SLO Multi olier Core Flow (% rated) LHGRFAC(F) 0.00 0.438 25.00 0.606 30.00 0.639 82.18 0.99 107.00 0.99 Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CL1 C11 Core Operating Limits Report Page 14 of 16 Ran 2 The Clinton I Cycle 11 OPRM Period Based Detection Algorithm (PBDA) Trip Setpoints for the OPRM System for use in Technical Specification 3.3.1.3 are found in Table 7-1. These values are based on the cycle specific analysis documented in Reference
3. the OLMCPR value and/or ARTS-based power dependent MCPR limits should be evaluated Any c for potential impact on the OPRM PBDA Trip Setpoints. The OPRM PBDA Trip Setpoints are applicable when the associated Technical Specification JS Table 3.3.1.3} is implemented. Table 7-1 OPRIVI PBDA Trip Setpoints (Reference
3) PBDA Trip Amplitude Corresponding Maximum -Confirmation Count Trip Setting W 15 6.0 Reactor Protection System (RPS) Instrumentation 6.1 Technical Specification Beferencp-Section 3.3.1.1 6.2 The Average Power Range Monitor (APRM) simulated thermal power time constant, shall be between 5.4 seconds and 6.6 seconds (Reference 15). 7.0 Stability Protecti points Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CL1 G11 Core Operating Limits Report Page 15 of 16 Rev. 2 8.0 Modes Of Operation The Allowed Modes of Operation with combinations of Equipment Out-of-Service (EOOS) are as described below: 9.0 Methodology Table 8-1 Modes of Operation (Reference
3) Notes: 1. A single Main Steam Isolation Valve (MSIV) may be taken OOS (shut) under any one OOS Option so long as core thermal power is maintained X75% of 3473 MWt (Reference 3). 2. Pressure Regulator Out-Of-Service (PRODS} was evaluated for thermal limits only in dual loop mode with up to 50'F feedwater temperature reduction at any point in the cycle (Reference 3). PRODS has nW been evaluated for Balance of Plant operation, 3. The maximum ICF flow utilized in licensing analysis is 107.0% (Reference 3). 4Concurrent operation with SLO and toss of `FULL' Feedwater Heating {+/-10°F of design NORMAL temperature) or FWTR has not been evaluated and thus not a valid operating mode. (Reference 3, 7, 8, 9 and 10) The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document: 1. "General Electric Standard Application for Reactor Fuel", NEDE-24011-P-A-14, June 2000 and U.S. Supplement NEDE-2401 1 -P-A-1 4-US, June 2000.

Exelon Nuclear CL1C11 Core Operating Limits Report IWO References oats Technical Specifications for Clinton Power Station Unit 1, Docket No. 50-461, License No. NPF-62, Core Operating Limits Report (COLR). General Electric Standard Application for Reactor Fuel (GESTAR 11) and US supplement, NEDE-2401 I -P-A-1 4, June 2000. Document 0000-0038-3490SRLR Revision 1, "Supplemental Reload Licensing Report for Clinton Power Station Unit I Reload 10 Cycle 11", January 2006, Document 0000-0000-0038-3490FBIR Revision 0, "Fuel Bundle Information Report for Clinton Power Station Unit 1 Reload 10 Cycle 11", December 2005 Document GE-NE-0000-0000-7456-01 P, "Option B Scram Times For Clinton Power Station", February 2002 NEDC-32694P-A, "Power Dist August 1999. 7. GE-NE-0000-0042-4570-RO, "Clinton Off rated Analyses Below the PLU Power Level," September 2005. 8. Calculation GENE-0000-0030-8309, "Clinton Assessment of Feedwater Riser Flow Deviation," Rev. 0. 9. EC 355034 RO, "Feedwater Riser Flow Deviation Assessment" 10, EC 354185 RO, "Uncertainty in Feedwater Temperature for Two Loop and Single Loop Operation" 11. GE-NE-0000-0026-1857-RO, " Evaluation of Operation With Equipment Out-Of-Service for the Clinton Power Station", May 7, 2004 12. Document 0000-0000-001 6-5277FBIR Revision 0, "Fuel Bundle information Report for Clinton Power Station Unit 1 Reload 9 Cycle 10", December 2003 13. Document 000-0016-5277SRLR Revision 1, "Supplemental Reload Licensing Report For Clinton Power Station Unit 1 Reload 9 Cycle 10" 14. TODI NF0500144 Rev ion Uncertainties for Safety Limit MCPR Evaluations," 0, "Clinton Unit 1 Cycle 11 FRED Form Exelon Approval" 15. TODI CPS-05-011 Revision 0, "Clinton: Cycle-11, OPI-3 Customer Proposed Values", August 2005 DOC ID: COLR Clinton 1 Page 16 of 16 Rev. 2

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