U-603759, Issuance of the Core Operating Limits Report for Clinton Power Station, Unit 1, Cycle 11

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Issuance of the Core Operating Limits Report for Clinton Power Station, Unit 1, Cycle 11
ML060660386
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: ML060660386 (17)
v • d • e


Text

AmerClo An Exelol Company Clinton Power Station R. R. 3, Box 228 Clinton, IL 61727 10CFR50.36 U-603759 February 23, 2006 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461

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 lliff, Regulatory Assurance Manager, at (217) 937-2800.

Respectfully, Robert S. ement Site Vice President Clinton Power Station JLP/bIf Attachment cc: Regional Administrator- NRC Region IlIl NRC Senior Resident Inspector - Clinton Power Station

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Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CLIC1I Core Operating Limits Report Page 1 of 16 Rev. 2 CORE OPERATING LIMITS REPORT FOR CLINTON POWER STATION UNIT 1 CYCLE 11 Prepared 83y. Date: //1H06 GMpepp Rubnaecio Reviewed By: ' I Date: ' u144 Wiliam P. Ganwn Appraovd By: Date:

/ JwmJ. Tut RevieAer By: V 4.. , C Date: 4/* L Page 1

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CLI C11 Core Operating Limits Report Page 2 of 16 Rev.2 C

Tal! of nten 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 Page 2

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CL1C11 Core Operating Limits Report Page 3 of 16 Rev. 2 s10 of T Ehks Page Table 3-1 MAPLHGR for all GE1 4C Fuel 6 Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier 6 Table 4-1 Operating Li-nit Minimum Critical Power Ratio 9 Table 4-2 Power Dependent MCPR Limit Adjustments and Multipliers MCPR(P) 9 Table 4-3 Flow Dependent MCPR Limits MCPR(F) 10 Table 4-4 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) 10 Table 5-1 Linear Heat Generation Rate Limits for U02 Rods 11 Table 5-2 Linear Heat Generation Rate Limits for Gad Rods 12 Table 5-3 Power Dependent LHGR Multiplier LH3RFAC(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)

(Loss of 'FULL' Feedwater Heating) 13 Table 5-7 Flow Dependent LHGR Multiplier LHGRFAC(F)

(Loss of 'FULL' Feedwater Heating) 13 Table 7-1 OPRM PBDA Trip Setpoints 14 Table 8-1 Modes of Operation 15 Page 3

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CL1 C11 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 500 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 Recirculation 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 SLO Single Reactor Recirculation Loop Operation Page 4

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CL1 C11 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 is valid for all licensed operating domains on the operating map, including:

  • Maximum Extended Load Line 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 5OoF during cycle extension operation

. Feedwater Heater Out of Service (FWHOOS) up to 50OF feedwater temperature reduction at any time during the cycle prior to cycle extension.

Page 5

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CL1 Cl1 Core Operating Limits Report Page 6 of 16 Rev. 2 3.0 MAPLHGR Limits 3.1 Technical Specification

Reference:

Sections 3.2.1 and 3.4.1.

3.2

Description:

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 (DLO).

For single reactor recirculation loop operation (SLO), the MAPLHGR limits given in Table 3-1 must be multiplied by a SLO MAPLHGR multiplier provided in Table 3-2. The SLO MAPLHGR multiplier for GE14 fuel is 0.76 (Reference 3).

Table 3-1 MAPLHGR for all GE14C FuelI (Reference 3 and 13)

Avg. Planar MAPLHGR Exposure Limit l(GWd/SD_ (kW/ft) 0.00 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 5.00 Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference 3)

Fu l MAPLHGR Fuel JSLOJ T Multiplier !

l GE14 C 0.76 I

Linear interpolation should be used for points not listed in Table 3-1.

Page 6

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CLiC11 Core Operating Limits Report Page 7 of 16 Rev.2 4.0 MCPR Limits 4.1 Technical Specification

Reference:

Sections 3..2.2 and 3.4.1 4.2

Description:

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-Dependent MCPR For operation less than or equal to 33.3% core thermal power, the OLMCPR 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 OLMCPR limit shown in Table 4-1 by the applicable MCPR multiplier K(P) given inTable 4-2.

4.2.1.2 Flow-Dependent MCPR Tables 4-3 through 4-4 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 Limits are not provided.

Page 7

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CL C1l1 Core Operating Limits Report Page 8 of 16 Rev. 2 4.2.3 Avon A and Option B Option A and Option B refer to use of scram speeds for establishing MCPR operating limits.

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).

To utilize 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 appropriate 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.

4.2.4 ftacirculation Flow Control V ilve Settings 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).

Page 8

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CL1 C1I Core Operating Limits Report Page 9 of 16 Rev. 2 Table 4-1 Operating Limit Minimum Critical Power Ratio (Reference 3)

Option B Option A EOOS Combination All exposures All exposures Base Case 1.28 1.30 Base Case SLO 1.31 1.33 Table 4-2 Power Dependent MCPR Limit Adjustments and Multipliers MCPR(P)

(Reference 7 and 11)

EOO Core Flow ,l Core Thermal Power (%/6l Combination (% of I11 21.6 s3i-3 >33.3 l 43 <70 >70 100 Rated) MCPR(PL _-l K(P)

  • 50 2.20 2.20 1.97 Base Case . * . 1.351 1.313 1.212 1.15 1.00

> 50 2.46 2.46 2.17 l

  • 50 2.23 2.23 2.00 Base Case SLO 1.351 1.313 1.212 1.15 1.00

> 50 2.49 2.49 2.20_

Notes for Table 4-2:

1. Values are interpolated between relevant power levels.
2. Allowable EOOS conditions are listed in Section 8.

Page 9

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CL1 Cl1 Core Operating Limits Report Page 10 of 16 Rev.2 Table 4-3 Flow Dependent MCPR Limits MCPR(F) 1 (Reference 7 and 11)

Core Flow

(% rated) 1 MCPR(F) j_____ ___j 0 1.8755 25 1.6954 93.78 1.20 109 1.20 _

Table 4-4 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) 2 (Reference 7 and 11)

(raD)w MCPR(F) 0 1.9055 25 1.7254 93.78 1.23 109 1.23 1Linear interpolation should be used for points not listed in Table 4-3.

Linear interpolation should be used for points not listed in Table 4-4.

Page 10

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CLlCll Core Operating Limits Report Page 11 of 16 Rev. 2 5.0 Linear Heat Generation Rate Limits 5.1 Technical Apecification Reference Section 3.2.3 and 3.4.1.

5.2 Description-The linear heat generation rate (LHGR) limit is the product of the exposure dependent LHGR limit (from Table 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) isdetermined 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 5-2 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 OF 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)

Peak Pellet LHGR Exposure Limit (GWd/';T) (kW/ft) 0.00 13.40 14.51 13.40 57.61 8.00 63.50) 5.00 1

Linear interpolation should be used for points not listed in Table 5-1. The values listed in Table 5-1 are limiting for all bundle types.

Page 11

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CL1 C11 Core Operating Limits Report Page 12 of 16 Rev. 2 Table 5-2 Linear Heat Generation Rate Limits for Gad Rods 1 (Reference 4 and 12)

Peak Pellet LHGR Exposure Limit

__L(GWd/qT) ( kW/ft) Ii 0.00 11.76 12.03 11.76 54.21 7.02 59.98 4.39 Table 5-3 Power Dependent Ll-GR Multiplier LHGRFAC(P) 2 (Reference 7 and 11)

Core Core Thermal Power (% Rated)

EOOS Combination Flow (%) 0 1 21.6 1 < 33.3 1 >33.3 1 100 Flow

_% LHGRFAC(I)

Base Case!

  • 50 0.634 0.634 0.689 068 .0

> 50 0.572 0.572 0.600 0.689 1.000 Base Case SLO

  • 50 0.634 0.634 0.689 0.689 1.000 I____________ > 50 0.572 I0.572 0 .600 0681.0 Table 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F) 3 (Reference 7 and 11)

Corlw lLHGRFAC(F)

(%rated) j_______

0.00 0.443 25.00 0.612 30.00 0.646 82.18 1.00 107.00 1.00 1 Linear interpolation should be used for points not listed inTable 5-2. The values listed inTable 5-2 are limiting for all bundle types.

2 near interpolation should be used for points not listed inTable 5-3.

Linear interpolation should be used for points not listed inTable 5-4.

Page 12

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CL1 C11 Core Operatin, Limits Report Page 13 of 16 Rev. 2 Table 5-5 LHGR Single Loop Operation (SLO) Reduction Factor (Reference 3)

Fuel LHG Type SLiOe IGE14C 0.76 Table 5-6 Power Dependent LHGR Multiplier LHGRFAC(P)

(Loss of 'FULL' Feedwater Heating)'

(Reference 7, 8, 9, 10 and 11)

Como Core Thermal Power (% Rated) lCombination Core Flow 0t 21.6 1 < 33.3 1l> 33.3 100

___._ _ LHGRFAC(P)l Base Case *50 l 0.627 0.627 0.682 0.682 0.99

> 50 0.566 0.566 0.594 Base Case SLO Table 5-7 Flow Dependent LHGR Multiplier LHGRFAC(F)

(Loss of 'FU LL' Feedwater Heating) 2 (Reference 7, 8, 9, 10 and 11) oraeFlw l LHGRFAC(F) 0.00 0.438 25.00 0.606 30.00 0.639 82.18 0.99 107.00 0.99 1 Linear interpolation should be used for points not listed in Table 5-6.

2 Linear interpolation should be used for points not listed in Table 5-7.

Page 13

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CL1 C11 Core Operating Limits Report Page 14 of 16 Rev. 2 6.0 Reactor Protection System (RPS) Instrumentation 6.1 Technical Soecification Reference Section 3.3.1.1 6.2 Description 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 Protection Setpoints The Clinton 1 Cycle 11 OPRM Period Based Detection Algorithm (PBDA) Trip Setpoints for the OPRM System for use in Technibal Specification 3.3.1.3 are found in Table 7-1. These values are based on the cycle specific analysis documented in Reference 3.

Any change to the OLMCPR value and/or ARTS-based power dependent MCPR limits should be evaluated for potential impact on the OPRM PBDA Trip Setpoints.

The OPRM PBDA Trip Setpoints are applicable when the associated Technical Specification (TS Table 3.3.1.3) is implemented.

Table 7-1 OPRM PE;DA Trip Setpoints (Reference 3)

PBDA Trip Amplitude Corresponding Maximum

______TripAmplitude Confirmation Count Trip Setting 1.13 .15 Page 14

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CL1 C11 Core Operating Limits Report Page 15 of 16 Rev. 2 8.0 Modes Of Operation The Allowed Modes of C'peration with combinations of Equipment Out-of-Service (EOOS) are as described below:

Table 8-1 Modes of Operation (Reference 3)

Oneratin Reion EOOS Options12 Standard MELLLA ICF3 FWTR 4 Coastdown Base Case, Option A Yes Yes Yes Yes Yes Base Case SLO4, Option A Yes No No No Yes Base Case, Option B Yes Yes Yes Yes Yes Base Case SLO4 , Option B I Yes I No No No Yes Notes:

1. A single Main Steam Isolation Valve (MSIV) may be taken 0OS (shut) under any one OOS Option so long as core thermal power is maintained <75% of 3473 MWt (Reference 3).
2. Pressure Regulator Out-Of-Service (PROOS) was evaluated for thermal limits only in dual loop mode with up to 500 F feedwater temperature reduction at any point in the cycle (Reference 3). PROOS has nni been evaluated for Balance of Plant operation.
3. The maximum ICF flow utilized in licensing analysis is 107.0% (Reference 3).
4. Concurrent operation with SLO and Loss of 'FULL' Feedwater Heating (t100 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) 9.0 Methodology 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-2401 1-P-A-14, June 2000 and U.S. Supplement NEDE-2401 1-P-A-14-US, June 2000.

Page 15

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 CL1 C11 Core Operating Limits Report Page 16 of 16 Rev. 2 10.0 References

1. Technical Specifications for Clinton Power Station Unit 1, Docket No. 50-461, License No. NPF-62, Core Operating Limits Report (COLR).
2. General Electric Standard Application for Reactor Fuel (GESTAR II) and US supplement, NEDE-24011 -P-A-14, June 2000.
3. Document 0000-0038-3490SRLR Revision 1, "Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload 10 Cycle 11 ", January 2006.
4. Document 0000-0000-0038-3490FBIR Revision 0, "Fuel Bundle Information Report for Clinton Power Station Unit 1 Reload 10 Cycle 11", December 2005
5. Document GE-NE-0000-0000-7456-01 P, "Option B Scram Times For Clinton Power Station", February 2002
6. NEDC-32694P-A, "Power Distribution Uncertainties for Safety Limit MCPR Evaluations,"

August 1999.

7. GE-NE-0000-0042-4570-RO, "Clinton Offrated 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 0000-0000-0016-5277FBIR 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 Revision 0, "Clinton Unit 1 Cycle 11 FRED Form Exelon Approval"
15. TODI CPS-05-011 Revision 0, "Clinton: Cycle-11, OPL3 Customer Proposed Values",

August 2005 Page 16

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