ML033230191

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Attachments C and D - Core Operating Limits Report for Dresden Unit 2 Cycle 19 Revision 0 and Unit 3 Cycle 18 Revision 1, Non-Proprietary Version
ML033230191
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 11/07/2003
From:
Exelon Generation Co, Exelon Nuclear
To:
Office of Nuclear Reactor Regulation
References
RHLTR: #03-0073
Download: ML033230191 (43)
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Text

Attachment C Core Operating Limits Report for Dresden Unit 2 Cycle 19 Revision 0 Non-Proprietary Version

(( 11 Core Operating Limits Report for Dresden Unit 2 Cycle 19 Revision 0

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Issuance of Changes Summary

. Affectod S . Afeed Summary of Changes Revision Date AlSection Pages I a All All IOriginal Issue (Cycle 19) 0 10103 I

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frrlden Unit 2 Ccle 19 ii Revision 0

Table of Contents References.......................................................................................................................... iv

1. Average Planar Linear Heat Generation Rate (3.2.1, 3.4.1) . . . 1-1 1.1 Technical Specification Reference ............................................................ 1-1 1.2 Description ............................................................ 1-1
2. Minimum Critical Power Ratio (3.2.2, 3.4.1, 3.7.7) . ............................ 2-1 2.1 Technical Specification Reference ............................................................ 2-1 2.2 Description ............  ; 2-1
3. Linear Heat Generation Rate (3.2.3) ............................................................ 3-1 3.1 Technical Specification Reference ...............................  ; ............... 3-1 3.2 Description ............  ; 3-1
4. Control Rod Withdrawal Block Instrumentation (3.3.2.1) .*----------- 4-1 4.1 Technical Specification Reference .4-1 4.2 Description .4-1
5. Allowed Modes of Operation (B 3.2.2, B 3.2.3) .................................... 5-1
6. Methodology (5.6.5) ...................................  : 6-1

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Dresden Unit 2 Cycle 19 iii Revision 0

References

1. Exelon Generation Company, LLC Docket No. 50-237, Dresden Nuclear Power Station,

-Unit 2 Facility Operating License, License No. DPR-19.

2. Letter from D. M. Crutchfield to All Power Reactor Licensees and Applicants, Generic Letter 88-16; Concerning the Removal of Cycle-Specific Parameter Limits from Tech Specs, October 3, 1988.
3. 'Supplemental Reload Licensing Report for Dresden Unit 2 Reload 18 Cycle 19", 0000-0016-1235-SRLR, Revision 0, September 2003.
4. 'MICROBURN Steady State LHGR Limit Curve Generation for GE-14 Fuel (D2C18)",

BNDD:01-008, May 30, 2001.

5. "DRESDEN 2 and 3 QUAD CITIES I and 2 Equipment Out-Of-Service and Legacy Fuel Transient Analysis", GE-NE-J 11-03912-00-01-R2, TODI NFM01 00091 Sequence 02, September 2003.
6. "Instrument Setpoint Calculation Nuclear Instrumentation Rod Block Monitor Dresden 2 &

3", GE DRF C51-00217-01, December 15, 1999.

7. "OPL-3 Parameters for Dresden Unit 2 Cycle 19 Transient Analysis", TODI NF0300049 Sequence 00, June 20, 2003.
8. "Fuel Mechanical Design Report Exposure Extension for ATRIUM-9B Fuel Assemblies at Dresden, Quad Cities, and LaSalle Units", EMF-2563(P) Revision 1, TODI NFMO100107 Sequence 0, August 2001.
9. "Dresden Unit 2 Cycle 17 Reload Analysis", NDIT NFM9900187, Sequence 01, EMF-2275 Revision 1, November 1999.
10. 'Determination of Generic MCPRF Limits", BNDG:02-001, May 17, 2002.
11. General Electric Standard Application for Reactor Fuel (GESTAR II) and US supplement, NEDE-24011-P-A-14, June 2000.
12. Letter from Carlos de la Hoz to Doug Wise and Alex Misak, "Approval of GE Evaluation of MSIV out of Service for Dresden and Quad Cities", NFM-MW:02-0274, dated August 2, 2002.
13. Dresden Unit 2 Cycle 19 FRED Form", TODI NFM0300038 Revision 2, August 8, 2003.
14. 'ICA Stability Evaluation for Dresden Unit 2 C19", GE-NE-0000-0020-4496-Rl, October 2003.
15. "Single Loop Operation (SLO) LHGR Limits", TGO:03-008, May 30, 2003.
16. "SAFER/GESTR - LOCA Loss-of-Coolant Accident Analysis for Dresden Nuclear Station 2 and 3 and Quad Cities Nuclear Station Units 1 and 2", NEDC-32990P, Revision 2, September 2003., TODI 0100086, Sequence 02, October 2003.
17. Letter from Carlos de la Hoz to Doug Wise and Alex Misak, "Approval of GE Evaluation of Dresden and Quad Cities Pressure Regulator Out of Service Analysis," NF-MW:02-0413, October 22, 2002.

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Dresden .Unit 2 Cycle 19 iv Revision 0

18. Letter from F. R. Lindquist to A. Giancatarino, Dresden Unit 2 Cycle 18 Safety Limit MCPR Change," FRL03DR2-003, February 21, 2003.
19. Letter from R. Lindquist to J. Neviing, TSD NFM-MW-Bl 15 D2C1 8 CBH Impact from Withdrawing 1OB Rods", FRL03DR2-001 1, dated January 9, 2003.
20. "D2C19 Core Operating Limits Report Creation", BNDD:03-021, October 14,2003.
21. D2C19 Fuel Type based LHGR Limits for Fresh Fuel" (D2C19), BNDD:03-022 Rev. 0, October 9, 2003.
22. Letter from R. Lindquist to J. NevIing, 'Dresden and Quad Cities Equipment Out of Service (EoOS) Interpretation Letter", FRL02EX-01 1, dated September 6, 2002.
23. Letter from Candice Chou to Alex Misak and Doug Wise, 'Dresden and Quad Cities Operation with one TSV OOS", NF-MW:03-069, July 28, 2003.
24. Letter from Carlos de la Hoz to Doug Wise and Alex Misak, Approval of GE evaluation of Dresden and Quad Cities Extended Final Feedwater Temperature Reduction," NF-MW:02-0081, August 27, 2002.

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1. Average Planar Linear Heat Generation Rate 1.1 Technical Specification

Reference:

Sections 3.2.1 and 3.4.1.

1.2

Description:

Tables 1-1 and 1-2 are used to determine the maximum average planar linear heat generation rate (MAPLHGR) limit for each fuel type. Limits listed in Tables 1-1 and 1-2 are for Dual Reactor Recirculation Loop Operation.

For Single Reactor Recirculation Loop Operation (SLO), the MAPLHGR limits given in Tables 1-1 and 1-2 must be multiplied by a SLO MAPLHGR multiplier. The SLO MAPLHGR multiplier for SPC fuel is 0.84 (Reference 3 Section 16). The SLO MAPLHGR multiplier for GEI4 fuel is 0.77 (Reference 3 Section 16).

Table 1-1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for all ATRIUM-9B Fuel ATRM9-P9HATB371-13GZ-SPC100T-9WR-144-T6-3912 ATRM9-P9HATB371 -13GZ-SPC100T-9WR-144-T6-3914 (Bundles 3912 and 3914 - bundle types 6 and 7)

(Reference 3 Section 16)

Planar Average Exposure MAPLHGR (GWd/MTU) (kW/ft) 0.00 13.52 17.25 13.52 44.09 10.73 70.00 7.84 Table 1-2 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for all GE14 Fuel GE1 4-P1 OHNAB408-16GZ-1 OOT-1 45-T6-2483 GE1 4-P1 OHNAB411 -4G7.0/9G6.0-1 OOT-145-T6-2484 GE14-P1 ODNAB418-16GZ-1 OOT-145-T6-2646 GE14-Pl ODNAB389-18GZ-1OOT-145-T6-2650 (Bundles 2483, 2484, 2646 and 2650, bundle types 16,17,19, 20, 28, 29, 31, 32, 38, 39, 41, 42 and 47)

(Reference 3 Section 16)

Planar Average Exposure MAPLHGR (GWd/MTU) (kW/ft) 0.00 11.68 16.00 11.68 55.12 8.02 63.50 6.97 70.00 4.36 1:]

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Dresden Unit 2 Cycle 19 1-1 Revision

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2. Minimum Critical Power Ratio 2.1 Technical Specification

Reference:

Sections 3.2.2, 3.4.1 and 3.7.7.

2.2

Description:

The various MCPR limits are described below.

2.2.1 Manual Flow Control MCPR Limits The Operating Limit MCPR (OLMCPR) is determined from either section 2.2.1.1 or 2.2.1.2, whichever is greater at any given power and flow condition.

2.2.1.1 Power-Dependent MCPR For operation at less than 38.5% core thermal power, the OLMCPR as a function of core thermal power is shown in Table 2-3. For operation at greater than 38.5% core thermal power, the OLMCPR as a function of core thermal power is determined by multiplying the applicable EOOS condition limit shown in Table 2-1 or 2-2 by the applicable MCPR multiplier Kp given in Table 2-3. For operation at exactly 38.5% core thermal power, the OLMCPR as a function of core thermal power is the higher of either of the two aforementioned methods evaluated at exactly 38.5% core thermal power.

2.2.1.2 Flow-Dependent MCPR Tables 2-4 and 2-5 provide the MCPRF limit as a function of flow.

The MCPRF limit determined from these. tables is the flow dependent OLMCPR.

2.2.2 Automatic Flow Control MCPR Limits Automatic Flow Control MCPR Limits are not provided.

2.2.3 Option A and Option B Option A and Option B refer to scram speeds.

Option A scram speed is the Improved Technical Specification scram speed. The core average scram speed insertion time for 20% insertion must be less than or equal to the Technical Specification Scram Speed to utilize Option A MCPR limits. Reload analyses performed by Global Nuclear Fuel (GNF) for cycle 19 Option A MCPR limits utilized a 20% core average insertion time of 0.900 seconds (Reference 7).

To utilize the MCPR limits for the Option B scram speed, the core average scram insertion time for 20% insertion must be less than or equal to 0.694 seconds (Reference 7). If the core average scram insertion time does not meet the Option B criteria, but is within the Option A criteria, the appropriate MCPR value may be determined from a linear interpolation

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Dresden Unit 2 Cycle 19 2-1 Revision 0

between the Option A and B limits with standard mathematical rounding to two decimal places. When performing a linear interpolation to determine MCPR limits, ensure that the time used for Option A is 0.900 seconds, which is the 20% insertion time utilized by GNF in the reload analysis.

.2.2.4 . Recirculation Pump Motor Generator Settings Cycle 19 was analyzed with a maximum core flow runout of 110%;

therefore the Recirculation Pump Motor Generator scoop tube mechanical and electrical stops must be set to maintain core flow less than 110%

(107.8 Mlb/hr) for all runout events (Reference 13 Section 15). This value is consistent with the analyses of Reference 5.

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Dresden Unit 2 Cycle 19 2-2 Revision 0

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Table 2-1 MCPR Option A Based Operating Limits

-(Reference 3 Cycle Exposure EOOS Combination Fuel Type <EOR' - 1385 > EOR' - 1385

_________ MWdIMT MWd/MT GE14 1.58 1.68 Base Case ATRIUM-98 1.54 1.64 GE14 1.59 1.69 Base Case SLO ATRIUM-9B 1.55 1.65 GE14 1.75 1.77 TBPOOS ATRIUM-9B 1.69 1.71 GE14 1.76 1.78 TBPOOS SLO ATRIUM-98 1.70 1.72 GE14 1.60 .1.68 TCV Slow Closure ATRIUM-9B 1.54 1.64 GE14 1.61 1.69 TCV Slow Closure SLO ATRIUM-9B 1.55 1.65 GE14 1.64 1.68 PLUOS ATRIUM-9B 1.59 1.64 GE14 1.65 1.69 PLUOOS SLO ATRIUM-9B 1.60 1.65 GE14 1.58 1.68 TCV Stuck Closed ATRIUM-98 1.54 1.64 GE14 1.59 1.69 TCV Stuck Closed SLO ATRIUM.9B 1.55 1.65

1. EOR refers to the end of rated power (i.e., 100% power/1 00% flow operation with all rods out)

GE14 fuel is fuel types 16,17, 19, 20, 28, 29, 31, 32, 38. 39,41, 42, and 47 ATRIUM-9B fuel Is fuel types 6 and 7

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Dresden Unit 2 Cycle 19 2-3 Revision 0

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Table 2-2 MCPR Option B Based Operating Limits (Reference 3 Cycle Exposure EOOS Combination Fuel Type <EOR' -1385 2 EOR' -1385

._______________ ._________ MWd/MT MWdlMT GE14 1.47 1.51 Base Case ATRIUM-9B 1.45 1.47 GE14 1.48 1.52 Base Case SLO ATRIUM-9B 1.46 1.48 GE14 1.58 1.60 TBPOOS ATRIUM-9B 1.52 1.54 GE14 1.59 1.61 TBPOOS SLO ATRIUM-9B - 1.53 1.55 GE14 1.47 1.51 TCV Slow Closure ATRIUM-9B 1.A5 1.A7 GE14 1.48 1.52 TCV Slow Closure SLO ATRIUM-9B 1.46 1.48 GE14 1.47 1.51 PLUOS ATRIUM-9B 1.45 1.47 GE14 1A8 1.52 PLUMOS SLO ATRIUM-9B. 1.46 1.48 GE14 1.47 1.51 TCV Stuck Closed ATRIUM-9B 1.45 1.47 GE14 . 1.48 1.52 TCV Stuck Closed SLO ATRIUM-9B- 1.46 1.48

1. EOR refers to the end of rated power (i.e., 100% power/100% flow operation with all rods out)

GE14 fuel Is fuel types 16,17, 19,20, 28, 29, 31, 32, 38, 39, 41, 42, and 47 ATRIUM-9B fuel Is fuel types 6 and 7

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Dresden Unit 2 Cycle 19 2-4 Revision 0

(( )) I Table 2-3 MCPRp for GE and SPC Fuel (Reference 5 and 18) -

p p Core Thermal Power (% of rated)

Core Flow EOOS Combination (%of rated) 0 1 25 I 38.5 38.5 1 45 1 60 1 70 l 70 I 100 Operating Limit MCPR Operating Limit Base Case S60 3.19 2.61 2.29 1.32 1.28 1.15 ' 1.00

> 60 3.81 3.01 2.59 s C60 3.20 2.62 2.30 132 1.28 1.15 Base Case SLO > 60 3.82 3.02 2.60 1.00 TBPOOS _ _60 5.60 3.81 2.84 1.37 1.28 1.15 1.00

>60 6.85 4.66 3.48 S60 5.61 3.82 2.85 TBPOOS SLO __ 1.37 1.28 1.15 1.00

>60 6.86 4.67 3.49 TCV Slow Closure S 60 5.60 3.81 2.84 1.64 1.45 1.26 1.11 , 1.00

> 60 6.85 4.66 3.48 TCV Slow Closure SLO 60 5.61 3.82 2.854 1.45 1.26 1.11 1.00

> 60 6.86 4.67 3.49 PLUSOS. 60 5.60 3.81 2.84 1.64 1.45 1.26 1.11 1.00

> 60 6.85 4.66 3.48 PLUOS SLO 560 5.61 3.82 2.85 1.64 1.45 1.26 1.11 1.00

> 60 6.86 4.67 3.49 S60 3.19 2.61 2.29 TCV Stuck Closed I -- + -- ________

.1.32 1.28 1.15 1.00

>60 3.1 3.01 2.59 TCV Stuck Closed SO 60 3.20 2.62 2.30 1.32 1.28 1.15 1.00' I_ _ > 60 3.82 . 3.02 2.60 I Notes for Table 2-3:

  • Values are interpolated between relevant power levels.
  • For thermal limit monitoring at greater than 100% core thermal power, the 100% core thermal power multiplier, Kp, should be applied.
  • Allowable EOOS conditions are listed in Section 5.
  • MCRPp limits are independent of scram speed.

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Table 2-4 MCPRF limits for all fuel'types and all operating conditions except TCV Stuck Closed (Reference 10)

Flow % rated) MCPRF 110.0 1.22 100.0 1.22 0.0 1.86 Notes for Tables 2-4:

  • Values are interpolated between relevant flow values.
  • Rated flow is 98 Mlb/hr.
  • MCRPF limit is independent of scram speed.
  • This table is not applicable to TCV Stuck Closed operating conditions.

Table 2-5 MCPRF limits for all fuel types with a TCV Stuck Closed (Reference 10)

Flow (% rated) l MCPRF 110.0 1.27 108.9 1.27 0.0 1.97 Notes for Tables 2-5:

Values are interpolated between relevant flow values.

Rated flow is 98 Mlb/hr.

. MCRPF limit is independent of scram speed.

  • This table is only applicable to TCV Stuck Closed operating conditions.

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3. Linear Heat Generation Rate 3.1 Technical Specification

Reference:

Section 3.2.3.

3.2

Description:

The linear heat generation rate (LHGR) limit is the product of the LHGR Limit from Tables 3-1, 3-2, 3-3, 3-4, 3-5, or 3-6 and the minimum of either the power dependent LHGR Factor, LHGRFACp, the flow dependent LHGR Factor, LHGRFACF or the single loop operation (SLO) multiplication factor. The applicable power dependent LHGR Factor (LHGRFACp) is determined from Table 3-7. The applicable flow dependent LHGR Factor (LHGRFACF) is determined from Tables 3-8 and 3-9. The SLO multiplication factor can be found in Table 3-10.

Table 3-1 LHGR Limits for all ATRIUM-9B Fuel ATRM9-P9HATB371 -13GZ-SPC1 OOT-9WR-1 44-T6-3912 ATRM9-P9HATB371-13GZ-SPC100T-9WR-144-T6-3914 (Bundles 3912 and 3914 - bundle types 6, and 7)

(Reference 8)

Nodal Exposure LHGR Limit (GWdIMT) (kWlft) 0.00 14.40 15.00 14.40 64.30 7.90 Table 3-2 LHGR Limits for Bundle Types 16, 28, and 29 GE14-Pl OHNAB411-4G7.019G6.0-1OOT-145-T6-2484 (Bundle 2484, bundle types 16, 28, and 29)

(Reference 4)

Nodal Exposure LHGR Limit (GWdIMT) (kWlft)

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Table 3-3 LHGR Limits for Bundle Types 17, 31, and 32 GE1 4-P1 OHNAB408-16GZ-1 OOT-145-T6-2483 (Bundle 2483, bundle types 17, 31, and 32)

(Reference 4) -

Nodal Exposure LHGR Limit (GWd/MT) (kW/ft)

II _______________________________

_ _ _ _ _ _ _ ~~~~ ~ ~ ~ ~~~~~~~~~~I _

11 Table 3-4 LHGR Limits for Bundle Types 19, 38 and 39 GE14-PI ODNAB418-16GZ-10OT-145-T6-2646 (Bundles 2646, bundle types 19, 38, and 39)

(Reference 21)

Nodal Exposure LHGR Limit (GWd/MT) (kWlft)

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Table 3-5 LHGR Limits for Bundle Types 20, 41, and 42 GE14-PI ODNAB389-1 8GZ-1 OT-145-T6-2650 (Bundles 2650, bundle types 20,41, and 42)

(Reference 21)

Nodal Exposure LHGR Limit (GWdIMT) (kWlft)

Table 3-6 LHGR Limits for Bundle Type 47 GE14-Pi OHNAB408-16GZ-1 OOT-145-T6-2483 (Bundle 2483, bundle types 47)

(Reference 4 nd 19)

Nodal Exposure LHGR Limit (GWd/MT) (kW/ft)

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Table 3-7 LHGRFACP for all fuel types Y p (Reference 5)

Core Thermal Power (% of rated)

Core Flow EOOS Combination 0 1 25 - 38.5 38.5 [ 70 70 1 80 {. 100

(%of rated)

LHGRF l 5 60 Base Case 0.50 0.56 0.59 0.68 1.00

> 60 60 Base Case SIC > 60 0.50 0.56 0.59 0.68 1.00

  • 60 0.22 0.48 TBPOOS >60 0.33 0.39 0.42 0.54 1.00

> 60 0.2332 0.48 TBPOOS SL 03 >0 0.39 0.2 0.54 1.00 560 0.22 0.48:

TCV Slow Closure 0.39 0.54 1.00

>60 0.33 0.42 TCV Slow Closure SLO

  • 60 0.22 0.39 0.48 0.54 0.73 0.78 1.00

>60 0.33 0. 0.42 0.54 0.73 0.76 1.00 PLUOOS >~~60 0.22 0.39 -0.42 0.54 0.73 0.78

  • 60 0.22 0.48 PWOOS SLO 0.39 0.54 . 1.00

>60 0.33 0.42 TCV Stuck Closed > 60 0.50 0.56 0.59 0.68 0.86 1.00 TCV Stuck Closed SLO > 60 0.50 0.56 0.59 0.68 0.86 1.00 Notes for Table 3-7:

  • Values are interpolated between relevant power levels.
  • For thermal limit monitoring at greater than 100% core thermal power, the 100% core thermal power LHGRFACp multiplier should be applied.
  • Allowable EOOS conditions are listed in Section 5.
  • LHGRFACp multiplier is independent of scram speed.
  • The LHGR multiplier for any core poweriflow condition is the limiting of the LHGRFACp, LHGRFACF, and SLO Multiplier (if applicable)

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Table 3-8 LHGRFACF multipliers (Reference 5)

Flow ( rated) LHGRFACF 110 1.00 100 1.00 80 1.00 50 0.77 40 0.64 30 0.55 0 0.28 Table 3-9 LHGRFACF multipliers for Turbine Control Valve Stuck Closed (Reference 5)

Flow ( rated) LHGRFACF 110 1.00 100 1.00 98.3 1.00 80 0.86 50 0.63 40 0.50 30 0.41 0 0.14 Notes for Tables 3-8 and 3-9:

  • Values are interpolated between relevant flow values.

. 98 Mlb/hr is rated flow.

  • For thermal limit monitoring above 100% rated core flow, utilize the 100% rated core flow LHGRFACF multiplier.
  • LHGRFACF multipliers are applicable to all fuel types.
  • Table 3-8 is valid for all operating conditions for all EOOS scenarios except TCV stuck closed.
  • Table 3-9 is valid for all operating conditions with a TCV stuck closed.

LHGRFACF multipliers are independent of scram speed.

The LHGR multiplier for any core power/flow condition is the limiting of the LHGRFACp, LHGRFACF, and SLO Multiplier (if applicable).

Table 3-10 LHGR SLO Multipliers for All Fuel Types (Reference 3, 15 and 16)

Fuel Product Line SLO LHGR Multiplier ATRIUM-9B1 0.84 GE-14 0.77 Note for Table 3-10:

The LHGR multiplier for any core power/flow condition is the limiting of the LHGRFACp, LHGRFACF, and SLO Multiplier (if applicable).

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. .4. Control Rod Withdrawal Block Instrumentation 4.1 Technical Specification

Reference:

Table 3.3.2.1-1 4.2

Description:

The Rod Block Monitor Upscale Instrumentation Setpoints are determined from the relationships shown below (Reference 6):

ROD BLOCK MONITOR UPSCALE TRIP FUNCTION ALLOWABLE VALUE

- Two Recirculation Loop Operation 0.65 Wd + 55%

Single Recirculation Loop 0.65 Wd + 51%

Operation 0__65_ ______ _____

The setpoint may be lower/higher and will still comply with the Rod Withdrawal Event (RWE) Analysis because RWE is analyzed unblocked.

Wd - percent of drive flow required to produce a rated core flow of 98 Mlb/hr.

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5. Allowed Modes of Operation (B 3.2.2, B 3.2.3)

The Allowed Modes of Operation with combinations of Equipment Out-of-Service are as described below:

OPERATING REGION-Equipment Out of Service Options 23- 7 Standard MELLLA Coastdown 4 Base Case, Option A or B Yes Yes Yes Base Case SLO, Option A or B Yes Yes Yes TBPOOS, Option A or B Yes Yes -Yes TBPOOS SLO, Option A or B Yes Yes Yes TCV Slow Closure5, Option A or B Yes Yes Yes TCV Slow Closure SLO5 , Option A or B Yes Yes Yes PLUOOS, Option A or B Yes Yes Yes PLUOOS SLO, Option A or B Yes Yes Yes TCV Stuck Closed 6 , Option A or B Yes Yes Yes TCV Stuck Closed SLO6 , Option A or B Yes Yes Yes

' Each OOS Option may be combined with up to 18 TIP channels OOS (provided the requirements for utilizing SUBTIP methodology are met) with all TIPS available at startup from a refuel outage, a 120 0F reduction in feedwater temperature throughout the cycle (Final Feedwater Temperature Reduction was analyzed for the entire cycle, which is subject to restriction in Reference 24), and up to 50% of the LPRMs OOS with an LPRM calibration frequency of 2500 Effective Full Power Hours (EFPH) (2000 EFPH +25%).

2 Additionally, a single MSIV may be taken OOS (shut) under any and all OOS Options, so long as core thermal power is maintained <75% of 2957 MWt (Reference 12).

3 All OOS Options support 1 Turbine Bypass Valve OOS, if the OPL-3 (Reference 7) assumed opening profile for the Turbine Bypass system is met. If the OPL-3 opening profile is not met, or if more than one Turbine Bypass Valve is OOS, utilize the TBPOOS condition.

4 Coastdown operation is defined as any cycle exposure beyond the full power, all rods out condition with plant power slowly lowering to a lesser value while core flow is held constant (Reference 11 Section 4.3.1.2.8). Up to a 15% overpower is analyzed per Reference 5.

5 For operation with a pressure regulator out-of-service (PROOS), the TCV Slow Closure limits should be applied (Reference 17) and the operational notes from Reference 17 reviewed. PROOS and TCV Slow Closure is not an analyzed out-of-service combination.

6 Operation with one TSV OOS is allowed as evaluated in Reference 23. Combination of one TCV OOS and one TSV OOS is not allowed.

7The cycle specific stability analysis may impose restrictions on the Power-to-flow map andlor restrict the applicable temperature for feedwater temperature reduction (FWTR).

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6. Methodology (5.6.5)

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 documents:

1. ANF-1 125 (P)(A) and Supplements 1 and 2, Critical Power Correlation - ANFB," April 1990.
2. ANF-524 (P)(A) Revision 2 and Supplements 1 and 2, ANF Critical Power Methodology for Boiling Water Reactors," November 1990.
3. XN-NF-79-71 (P)(A) Revision 2 and Supplements 1, 2 & 3, Exxon Nuclear Plant Transient Methodology for Boiling Water Reactors," March 1986.
4. XN-NF-80-19 (P)(A) Volume I Supplements I and 2, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis," March 1993.
5. XN-NF-80-19 (P)(A) Volume I Supplement 3, Supplement 3 Appendix F, and Supplement 4, Exxon Nuclear Methodology for Boiling Water Reactors," November 1990.
6. XN-NF-80-19 (P)(A) Volumes 2, 2A, 2B and 2C, Exxon Nuclear Methodology for Boiling Water Reactors:

EXEM BWR ECCS Evaluation Model," September 1982.

7. XN-NF-80-19 (P)(A) Volume 3 Revision 2, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description," January 1987.
8. XN-NF-80-1 9 (P)(A) Volume 4 Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors:

Application of the ENC Methodology to BWR Reloads," June 1986.

9. XN-NF-85-67 (P)(A) Revision 1, Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," September 1986.
10. ANF-913 (P)(A) Volume 1 Revision 1, and Volume 1 Supplements 2, 3, 4, "COTRANSA2: A Computer Program for Boiling Water Reactor Transients Analysis," August 1990.

II. XN-NF-82 (P)(A) Revision 1 and Supplements 2, 4 and 5, Qualification of Exxon Nuclear Fuel for Extended Burnup," October 1986.

12. XN-NF-82 (P)(A) Supplement 1 Revision 2, "Qualification of Exxon Nuclear Fuel for Extended Burnup Supplement 1 Extended Burnup Qualification of ENC 9x9 BWR Fuel," May 1988.
13. ANF-89-14(P)(A) Revision I and Supplements I & 2, Advanced Nuclear Fuels Corporation Generic Mechanical Design for Advanced Nuclear Fuels Corporation 9X9 - IX and 9x9 - 9X BWR Reload Fuel,"

October 1991.

14. ANF-89-14(P), "Advanced Nuclear Fuels Corporation Generic Mechanical Design for Advanced Nuclear Fuels Corporation 9X9 - IX and 9x9 - 9X BWR Reload Fuel," May 1989.
15. ANF-89-98 (P)(A), "Generic Mechanical Design Criteria for BWR Fuel Designs," Revision 1 and Revision 1 Supplement 1, May 1995.
16. ANF-91-048 (P)(A), Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors EXEM BWR ECCS Evaluation Model," January 1993.
17. Commonwealth Edison Company Topical Report NFSR-0091, "Benchmark of CASMO/MICROBURN BWR Nuclear Design Methods," Revision 0 and Supplements on Neutronics Licensing Analysis

[l))

Dresden Unit 2 Cycle 19 6-1 Revision 0

(())

(Supplement 1) and La Salle County Unit 2 benchmarking (Supplement 2), December 1991, March 1992, and May 1992, respectively.

18. EMF-85-74 (P) Revision 0 and Supplement 1(P)(A) and Supplement 2(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," February 1998.
19. NEDE-24011-P-A-14 Revision 14, General Electric Standard Application for Reactor Fuel (GESTAR),"

June 2000.

20. NEDC-32981P Revision 0, t GEXL96 Correlation for ATRIUM-9B Fuel", September 2000.
21. ANF-1125(P)(A), Supplement I Appendix E, ANFB Critical Power Correlation Determination of ATRIUM-9B Additive Constant uncertainties," September 1998.
22. ANF-91-048(P)(A), Supplements I and 2, BWR Jet Pump Model Revision for RELAX," October-1997.

[ 6]

Dresden Unit 2 Cycle 19 6-2 Revision 0

Attachment D Core Operating Limits Report for Dresden Unit 3 Cycle 18 Revision 1

Core Operating Limits Report for Dresden Unit 3 Cycle 18 Revision 1

Issuance of Changes Summary Affected Affected Summary of Changes Revision Date Section Pages All All Original Issue (Cycle 18) 0 10/02 References, ii, iv, v, 1-1, Incorporate CBH reference, clarify fuel types being 1 9/03 1, 3, and 5 3-1, 3-2, impacted, incorporate revised LHGR limits for fuel type 3-3, 3-4 and 33, include the LHGR SLO multiplier, and include 5-1 applicable PROOS reference and note in Section 5.

Dresden Unit 3 Cycle 18 ii Revision 1

Table of Contents References...... IV

1. Average Planar Linear Heat Generation Rate .1-1 1.1 Technical Specification Reference .1-1 1.2 Description .1-1
2. Minimum Critical Power Ratio .2-1 2.1 Technical Specification Reference .2-1 2.2 Description .2-1
3. Linear Heat Generation Rate .3-1 3.1 Technical Specification Reference .3-1 3.2 Description .3-1
4. Control Rod Withdrawal Block Instrumentation .4-1 4.1 Technical Specification Reference .4-1 4.2 Description .4-1
5. Allowed Modes of Operation (B 3.2.2, B 3.2.3) .5-1
6. Methodology (5.6.5) .............. ........................... 66-1 Dresden Unit 3 Cycle 18 i Revision

References

1. Exelon Generation Company, LLC Docket No. 50-249, Dresden Nuclear Power Station, Unit 3 Facility Operating License, License No. DPR-25.
2. Letter from D. M. Crutchfield to All Power Reactor Licensees and Applicants, Generic Letter 88-16; Concerning the Removal of Cycle-Specific Parameter Limits from Tech Specs, October 3, 1988.
3. 'Supplemental Reload Licensing Report for DRESDEN UNIT 3 Reload 17 Cycle 18", 0000-0006-9848-SRLR, Revision 1, August 2002.
4. "Determination of D3C18 MICROBURN GE14 LHGR Limits", BNDD:02-001, Revision 1, June 18, 2002.
5. "DRESDEN 2 and 3 QUAD CITIES 1 and 2 Equipment Out-Of-Service and Legacy Fuel Transient Analysis", GE-NE-J 11-03912-00-01-RI, TODI NFMO100091 Sequence 01, November 2001.
6. Instrument Setpoint Calculation Nuclear Instrumentation Rod Block Monitor Dresden 2 &

3", GE DRF C51-00217-01, December 15,1999.

7. "OPL-3 Parameters for Dresden Unit 3 Cycle 18 Transient Analysis", TODI NF2002-9994, April 5, 2002.
8. "Fuel Mechanical Design Report Exposure Extension for ATRIUM-9B Fuel Assemblies at Dresden, Quad Cities, and LaSalle Units", EMF-2563(P) Revision 1, TODI NFMO100107 Sequence 0, August 2001.
9. "Determination of Generic MCPRF Limits", BNDG:02-001, May 17,2002.
10. General Electric Standard Application for Reactor Fuel (GESTAR II) and US supplement, NEDE-24011-P-A-14, June 2000.
11. Letter from Carlos de la Hoz to Doug Wise and Alex Misak, "Approval of GE Evaluation of MSIV out of Service for Dresden and Quad Cities", NFM-MW:02-0274, dated August 2, 2002.
12. 'Dresden Unit 3 Cycle 18 FRED Form Revision 2", TODI NFMO200041 Sequence 02, April 24, 2002.
13. Letter from Russell Lindquist (GNF) to Jim Neviing (Exelon), NFM-MW-B088 D3C18 Licensing Applicability Review", FRL02DR3-007, dated August 26, 2002.
14. Letter from Anthony Giancatarino (Nuclear Fuels) to Doug Wise (Dresden), Determination of Dresden Unit 3 Cycle 18 Middle of cycle Exposure Point", NF-MW:02-0383, dated September 27, 2002.
15. "Dresden Unit 3 Cycle 18 CBH Impact for GE-14 Fuel in 10C Control Cells",

TODI NF0300035, Revision 1, dated May 2, 2003.

Dresden Unit 3 Cycle 18 iv Revision 1

16. Single Loop Operation (SLO) LHGR Limits", TGO:03-008, May 30, 2003.
17. "SAFERIGESTR - LOCA Loss-of-Coolant Accident Analysis for Dresden Nuclear Station 2 and 3 and Quad Cities Nuclear Station Units I and 2", NEDC-32990P, Revision 1, September 2001.
18. 'Approval of GE Evaluation of Dresden and Quad Cities Pressure Regulator Out of Service Analysis", NF-MW:02-0413, October 22, 2002.

Dresden Unit 3 Cycle 18 v Revision 1

1. Average Planar Linear Heat Generation Rate 1.1 Technical Specification

Reference:

Sections 3.2.1 and 3.4.1.

1.2

Description:

Tables 1-1 and 1-2 are used to determine the maximum average planar linear heat generation rate (MAPLHGR) limit for each fuel type. Limits listed in Tables 1-1 and 1-2 are for Dual Reactor Recirculation Loop Operation.

For Single Reactor Recirculation Loop Operation (SLO), the MAPLHGR limits given in Tables 1-1 and 1-2 must be multiplied by a SLO MAPLHGR multiplier.

The SLO MAPLHGR multiplier for SPC fuel is 0.84 (Reference 3 Section 16). The SLO MAPLHGR multiplier for GE14 fuel is 0.77 (Reference 3 Section 16).

Table 1-1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for SPC ATRIUM-9B Fuel ATRM9-P9DATB326-1 1GZ-SPC80M-9WR-144-T6-2447 ATRM9-P9DATB326-1 1GZ-SPC80M-9WR-144-T6-2448 ATRM9-P9DATB339-6GZ-SPC80M-9WR-144-T6-2449 ATRM9-P9DATB362-12GZ-SPC100T-9WR-144-T6-2450 ATRM9-P9DATB360-12GZ-SPC100T-9WR-144-T6-2451 ATRM9-P9DATB378-13GZ-SPCIOOT-9WR-144-T6-2464 ATRM9-P9DATB378-1 IGZ-SPC100T-9WR-144-T6-2465 (Bundles 2447, 2448, 2449, 2450, 2451, 2464, 2465, bundle types 16, 17, 18, 19, 49, 20, 1, 31, 2 and 32)

(Reference 3 Section 16 and Reference 13)

Planar Average Exposure MAPLHGR (GWd/MTU) (kWlft) 0.00 13.52 17.25 13.52 70.00 7.84 Table 1-2 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for GE14 Fuel GE 14-Pl ODNAB408-16GZ-1 OOT-1 45-T6-2554 GE1 4-P1 ODNAB411-4G7.0/9G6.0-1 00T-145-T6-2553 (Bundles 2553 and 2554, bundle types 3, 33, 4 and 34)

(Reference 3 Section 16)

Planar Average Exposure MAPLHGR (GWd/MTU) (kWlft) 0.00 11.68 16.00 11.68 55.12 8.01 63.50 6.97 70.00 4.36 Dresden Unit 3 Cycle 18 1-1 Revision 1

2. Minimum Critical Power Ratio 2.1 Technical Specification

Reference:

Sections 3.2.2, 3.4.1 and 3.7.7.

2.2

Description:

The various MCPR limits are described below.

2.2.1 Manual Flow Control MCPR Limits The Operating Limit MCPR (OLMCPR) is determined from either section 2.2.1.1 or 2.2.1.2, whichever is greater at any given power and flow condition.

2.2.1.1 Power-Dependent MCPR For operation at less than 38.5% core thermal power, the OLMCPR as a function of core thermal power is shown in Table 2-3. For operation at greater than 38.5% core thermal power, the OLMCPR as a function of core thermal power is determined by multiplying the applicable EOOS condition limit shown in Table 2-1 or 2-2 by the applicable MCPR multiplier Kp given in Table 2-3. For operation at exactly 38.5% core thermal power, the OLMCPR as a function of core thermal power is the higher of either of the two aforementioned methods evaluated at exactly 38.5% core thermal power.

2.2.1.2 Flow-Dependent MCPR Tables 2-4 and 2-5 provide the MCPRF limit as a function of flow.

The MCPRF limit determined from these tables is the flow dependent OLMCPR.

2.2.2 Automatic Flow Control MCPR Limits Automatic Flow Control MCPR Limits are not provided.

Dresden Unit 3 Cycle 18 2-1 Revision I

2.2.3 Option A and Option B Option A and Option B refer to scram speeds.

Option A scram speed is the Improved Technical Specification scram speed. The core average scram speed insertion time for 20% insertion must be less than or equal to the Technical Specification Scram Speed to utilize Option A MCPR limits. Reload analyses performed by Global Nuclear Fuel (GNF) for cycle 18 Option A MCPR limits utilized a 20%

core average insertion time of 0.900 seconds (Reference 7).

To utilize the MCPR limits for the Option B scram speed, the core average scram insertion time for 20% insertion must be less than or equal to 0.694 seconds (Reference 7). If the core average scram insertion time does not meet the Option B criteria, but is within the Option A criteria, 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. When performing a linear interpolation to determine MCPR limits, ensure that the time used for Option A is 0.900 seconds, which is the 20% insertion time utilized by GNF in the reload analysis.

2.2.4 Recirculation Pump Motor Generator Settings Cycle 18 was analyzed with a maximum core flow runout of 110%;

therefore the Recirculation Pump Motor Generator scoop tube mechanical and electrical stops must be set to maintain core flow less than 110% (107.8 Mlb/hr) for all runout events (Reference 12 Section 15). This value is consistent with the analyses of Reference 5.

Dresden Unit 3 Cycle 18 2-2 Revision 1

Table 2-1 MCPR Option A Based Operating Limits (Reference 3 Appendix G and Reference 14)

Cycle Exposure EOOS Combination Fuel Type <13,800 213,800 MWd/MT MWd/MT GE14 1.53 1.65 Base Case ATRIUM-9B 1.52 1.61

- GE14 1.54 1.66 Base Case SLO ATRIUM-9B 1.53 1.62 GE14 1.73 1.75 TBPOOS ATRIUM-9B 1.67 1.69 GE14 1.74 1.76 TBPOOS SLO ATRIUM-9B 1.68 1.70 GE14 1.63 1.65 TCV Slow Closure ATRIUM-9B 1.58 1.61 GE14 1.64 1.66 TCV Slow Closure SLO ATRIUM-9B 1.59 1.62 GE14 1.68 1.68 PLUOOS ATRIUM-9B 1.63 1.63 GE14 1.69 1.69 PLUOOS SLO ATRIUM-9B 1.64 1.64 GE14 1.53 1.65 TCV Stuck Closed ATRIUM-9B 1.52 1.61 GE14 1.54 1.66 TCV Stuck Closed SLO ATRIUM-9B 1.53 1.62 Dresden Unit 3 Cycle 18 2-3 Revision

Table 2-2 MCPR Option B Based Operating Limits (Reference 3 Appendix G, Reference 14 and Reference 9)

Cycle Exposure EOOS Combination Fuel Type <13,800 >13,800 MWd/MT MWd/MT GE14 1.42 1.48 Base Case .

ATRIUM-9B 1.41 1.44 GE14 1.43 1.49 Base Case SLO ATRIUM-9B 1.42 1.45 GE14 1.56 1.58 TBPOOS ATRIUM-9B 1.50 1.52 GE14 1.57 1.59 TBPOOS SLO ATRIUM-9B 1.51 1.53 GE14 1.46 1.48 TCV Slow Closure ATRIUM-9B 1.41 1.44 GE14 1.47 1.49 TCV Slow Closure SLO ATRIUM-9B 1.42 1.45 GE14 1.51 1.51 PLUOOS ATRIUM-9B 1.46 1.46 GE14 1.52 1.52 PLUOOS SLO ATRIUM-9B 1.47 1.47 GE14 1.43 1.48 TCV Stuck Closed ATRIUM-9B 1.43 1.44 GE14 1.44 1.49 TCV Stuck Closed SLO ATRIUM-9B 1.44 1.45 Dresden Unit 3 Cycle 18 2-4 Revision 1

Table 2-3 MCPRp for GE and SPC Fuel (Reference 3 Appendix GI Core Thermal Power (% of rated)

Core Flow EOOS Combination 0 1 25 1 38.5 1 38.5 1 45 1 60 1 70 1 70 1 100

(%of rated)

Operating Limit MCPR Operating Limit MCPR Multiplier, Kp Base Case *60 3.16 2.58 2.27 1.32 1.28 1.15 1.00

> 60 3.77 2.99 2.56 Base Case SLO *60 3.17 2.59 2.28 1.32 1.28 1.15 1.00

> 60 3.78 3.00 2.57 TBPQOS

  • 60 5.55 3.77 2.82 1.37 1.28 1.15 1.00

> 60 6.79 4.62 3.45

  • 60 5.56 3.78 2.83 TBPOOS SLO _._ _ _ _.__ 1.37 1.28 1.15 1.00

> 60 6.80 4.63 3.46 TCV Slow Closure *60 5.55 3.77 2.82 1.64 1.45 1.26 1.11 1.00

> 60 6.79 4.62 3.45 TCV Slow Closure SLO

  • 60 5.56 3.78 2.83 1.64 1.45 1.26 1.11 1.00

> 60 6.80 4.63 3.46 1.64 PLUOS *60 5.55 3.77 2.82 1.64 1.45 1.26 1.11 1.00

> 60 6.79 4.62 3.45 PLUOOS SLO *60 .5.56 3.78 2.83 1.64 1.45 1.26 1.11 1.00

> 60 6.80 4.63 3.46

  • 60 3.16 2.58 2.27 TCV Stuck Closed .. ~ _ 1.32 1.28 0 1.15 1.00

>60 3.77 2.99 2.56 TCV Stuck Closed SLO j1__ *60

> 60 3.17 3.78 j 2.59 3.00 2.28 2.57 1.32 1.28 I

1.15 1.00.

Notes for Table 2-3:

  • Values are interpolated between relevant power levels.
  • For thermal limit monitoring at greater than 100% core thermal power, the 100% core thermal power multiplier, Kp, should be applied.
  • Allowable EOOS conditions are listed in Section 5.
  • MCRPp limits are independent of scram speed.

Dresden Unit 3 Cycle 18 2-5 Revision

Table 2-4 MCPRF limits for all fuel types and all operating conditions except TCV Stuck Closed (Reference 9)

Flow % rated) MCPRF 110.0 1.22 100.0 1.22 0.0 1.86 Notes for Tables 2-4:

- Values are interpolated between relevant flow values.

  • Rated flow is 98 Mlb/hr.
  • MCRPF limit is independent of scram speed.
  • This table is not applicable to TCV Stuck Closed operating conditions.

Table 2-5 MCPRF limits for all fuel types with a TCV Stuck Closed (Reference 9)

Flow (% rated) MCPRF 110.0 1.27 108.9 1.27 0.0 1.97 Notes for Tables 2-5:

  • Values are interpolated between relevant flow values.
  • Rated flow is 98 Mlblhr.
  • MCRPF limit is independent of scram speed.
  • This table is only applicable to TCV Stuck Closed operating conditions.

Dresden Unit 3 Cycle 18 2-6 Revision 1

3. Linear Heat Generation Rate 3.1 Technical Specification

Reference:

Section 3.2.3.

3.2

Description:

The linear heat generation rate (LHGR) limit is the product of the LHGR Limit from Tables 3-1, 3-2, 3-2a, or 3-3 and the minimum of either the power dependent LHGR Factor, LHGRFACp, the flow dependent LHGR Factor, LHGRFACF or the single loop operation (SLO) multiplication factor. The applicable power dependent LHGR Factor (LHGRFACp) is determined from Table 3-4. The applicable flow dependent LHGR Factor (LHGRFACF) is determined from Tables 3-5 and 3-6. The SLO multiplication factor can be found in Table 3-7. I Table 3-1 LHGR Limits for Bundle Types GE1 4-P1 ODNAB408-16GZ-1 OOT-1 45-T6-2554 (Bundle 2554, bundle types 4 and 34)

(Reference 4)

Nodal Exposure LHGR Limit (GWd/MT) (kW/ft) 0.00 13.20 10.00 13.20 13.22 12.90 14.33 12.45 18.73 11.74 27.50 10.40 55.11 7.70 63.61 4.48 Table 3-2 LHGR Limits for Bundle Types GE14-Pl ODNAB411 -4G7.0/9G6.0-1 OOT-145-T6-2553 (Bundle 2553, bundle type 3)

(Reference 4)

Nodal Exposure LHGR Limit (GWdIMT) (kWlft) 0.00 13.40 12.50 13.40 14.33 12.90 22.04 11.90 44.09 9.00 55.00 7.95 58.10 7.20 63.02 5.00 Dresden Unit 3 Cycle 18 3-1 Revision 1

Table 3-2a LHGR Limits for Bundle Types GE14-P1 ODNAB411-4G7.019G6.0-1 OOT-1 45-T6-2553 Applicable from 4060 MWD/MTU to End of Cycle (EOC)

(Bundle 2553, bundle type 33)

(Reference 4 and Reference 15)

Nodal Exposure LHGR Limit (GWd/MT) (kWlft) 0.00 13.06 12.50 13.06 14.33 12.57 22.04 11.60 44.09 8.77 55.00 7.75 58.10 7.02 63.02 4.87 Table 3-3 LHGR Limits for SPC ATRIUM-9B Fuel ATRM9-P9DATB326-1 1GZ-SPC80M-9WR-1 44-T6-2447 ATRM9-P9DATB326-1 GZ-SPC80M-9WR-144-T6-2448 ATRM9-P9DATB339-6GZ-SPC8OM-9WR-144-T6-2449 ATRM9-P9DATB362-12GZ-SPC1 OOT-9WR-144-T6-2450 ATRM9-P9DATB360-12GZ-SPC1 OOT-9WR-144-T6-2451 ATRM9-P9DATB378-13GZ-SPC1 OOT-9WR-1 44-T6-2464 ATRM9-P9DATB378-1 GZ-SPC1 OOT-9WR-144-T6-2465 (Bundles 2447, 2448, 2449, 2450, 2451, 2464, 2465, bundle types 16, 17, 18, 19, 49, 20, 1, 31, 2 and 32)

(Reference 8 Figure 2.1)

Nodal Exposure LHGR Limit (GWd/MT) (kW/ft) 0.00 14.40 15.00 14.40 64.30 7.90 Dresden Unit 3 Cycle 18 3-2 Revision

Table 3-4 LHGRFACp for all fuel types (Reference 3 Appendix GI Core Thermal Power (% of rated)

Core Flow EOOS Combination 0 1 25 1 38.5 1 38.5 1 70 1 70 1 80 I 100

(%of rated)

LHGRFACp multiplier

  • 60 Base Case > 60 0.50 0.56 0.59 0.68 1.00
  • 560 Base Case SLO > 60 0.50 0.56 0.59 0.68 1.00
  • 60 0.22 0 0.48 TBPOOS 0.39 0.54 1.00

> 60 0.22 0.48 TBPOOS SLO 6022 0.39 0.8 0.54 1.00

> 60 0.33 __ _ _ _ 0.42 _ _ _ _ _

  • 60 0.22 0.48 TCV Slow Closure 0.39 0.54 1.00

>60 0.33 0.42 TCV Slow Closure SLO > 60 0.22 0.39 0.48 0.54 0.73 0.78 1.00 PLUOOS

  • 60 0.22 0.39 0.48 0.54 0.73 0.78 1.00

> 60 0.33 __ _ _ _ 0.42 __ _ _ _ _ _ _ _ _ _ _ _ _ _

560 0.22 0.48 PLUOOS SLO 0.39 0.54 1.00

> 60 0.33 0.42

  • 601 TCV Stuck Closed > 60 0.50 0.56 0.59 0.68 1.00 Ccd60 TCV Stuck Closed SLO > 60 0.50 0.56 0.59 0.68 1.00 Notes for Table 3-4:
  • Values are interpolated between relevant power levels.
  • For thermal limit monitoring at greater than 100% core thermal power, the 100% core thermal power LHGRFACp multiplier should be applied.
  • Allowable EOOS conditions are listed in Section 5.
  • LHGRFACp multiplier is independent of scram speed.
  • The LHGR multiplier for any core power/flow condition is the limiting of the LHGRFACp, LHGRFACF, and SLO Multiplier (if applicable)

Dresden Unit 3 Cycle 18 3-3 Revision 1

Table 3-5 LHGRFACF multipliers (Reference 5 Figure 3-3)

Flow (% rated) LHGRFACF 0 0.28 30 0.55 40 0.64 50 0.77 80 1.00 100 1.00 110 1.00 Table 3-6 LHGRFACF multipliers for Turbine Control Valve Stuck Closed (Reference 5 Table 2-17)

Flow (% rated) LHGRFACF 0 0.14 30 0.41 40 0.50 50 0.63 80 0.86 98.3 1.00 100 1.00 110 1.00 Notes for Tables 3-5 and 3-6:

  • Values are interpolated between relevant flow values.
  • 98 Mlb/hr is rated flow.
  • LHGRFACF multipliers are applicable to all fuel types used in cycle 18.
  • Table 3-5 is valid for all operating conditions for all EOOS scenarios except TCV stuck closed.
  • Table 3-6 is valid for all operating conditions with a TCV stuck closed.
  • LHGRFACF multipliers are independent of scram speed.
  • The LHGR multiplier for any core power/flow condition is the limiting of the LHGRFACp, LHGRFACF, and SLO Multiplier (if applicable).

Table 3-7 LHGR SLO Multipliers for All Fuel Types (Reference 16 and 17)

Fuel Product Line SLO LHGR Multiplier ATRIUM-9B1 0.84 GE-14 0.77 Note for Table 3-7:

  • The LHGR multiplier for any core power/flow condition is the limiting of the LHGRFACp, LHGRFACF, and SLO Multiplier (if applicable).

Dresden Unit 3 Cycle 18 3-4 Revision

4. Control Rod Withdrawal Block Instrumentation 4.1 Technical Specification

Reference:

Table 3.3.2.1-1 4.2

Description:

The Rod Block Monitor Upscale Instrumentation Setpoints are determined from the relationships shown below (Reference 6):

ROD BLOCK MONITOR UPSCALE TRIP FUNCTION ALLOWABLE VALUE Two Recirculation Loop 0.65 Wd + 55%

Operation -

Single Recirculation Loop 0.65 Wd + 51%

Operation__ _ _ _ _ _ _ _ _ _

The setpoint may be lower/higher and will still comply with the Rod Withdrawal Event (RWE) Analysis because RWE is analyzed unblocked.

Wd - percent of drive flow required to produce a rated core flow of 98 Mlb/hr.

Dresden Unit 3 Cycle 18 4-1 Revision 1

5. Allowed Modes of Operation (B 3.2.2, B 3.2.3)

The Allowed Modes of Operation with combinations of Equipment Out-of-Service are as described below:

OPERATING REGION-----

Equipment Out of Service Options"23 Standard MELLLA Coastdown 4 Base Case, Option A or B Yes Yes Yes Base Case SLO, Option A or B Yes Yes Yes TBPOOS, Option A or B Yes Yes Yes TBPOOS SLO, Option A or B Yes Yes Yes TCV Slow Closure 5 , Option A or B Yes Yes Yes I TCV Slow Closure 5L05 , Option A or B Yes Yes Yes I PLUOS, Option A or B Yes Yes Yes PLUOOS SLO, Option A or B Yes Yes Yes TCV Stuck Closed, Option A or B Yes Yes Yes TCV Stuck Closed SLO, Option A or B Yes Yes Yes

' Each OOS Option may be combined with up to 18 TIP channels OOS (provided the requirements for utilizing SUBTIP methodology are met) with all TIPS available at startup from a refuel outage, a 120 0F reduction in feedwater temperature throughout the cycle (Final Feedwater Temperature Reduction was analyzed for the entire cycle), and up to 50% of the LPRMs OOS with an LPRM calibration frequency of 2500 Effective Full Power Hours (EFPH) (2000 EFPH +25%).

2 Additionally, a single MSIV may be taken OOS (shut) under any and all OOS Options, so long as core thermal power is maintained <75% of 2957 MWt (Reference 11).

3 All OOS Options support 1 Turbine Bypass Valve OOS, if the OPL-3 assumed opening profile for the Turbine Bypass system is met. If the OPL-3 opening profile is not met, or if more than one Turbine Bypass Valve is OOS, utilize the TBPOOS condition.

4 Coastdown operation is defined as any cycle exposure beyond the full power, all rods out condition with plant power slowly lowering to a lesser value while core flow is held constant (Reference 10 Section 4.3.1.2.8). Up to a 15% overpower is analyzed per Reference 5.

5 For operation with a pressure regulator out-of-service (PROOS), the TCV Slow Closure limits should be applied (Reference 18) and the operational notes from Reference 18 reviewed. PROOS and TCV Slow Closure is not an analyzed out-of-service combination Dresden Unit 3 Cycle 18 5-1 Revision 1

6. Methodology (5.6.5)

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 documents:

1. ANF-1125 (P)(A) and Supplements I and 2, "Critical Power Correlation - ANFB," April 1990.
2. ANF-524 (P)(A) Revision 2 and Supplements I and 2, ANF Critical Power Methodology for Boiling Water Reactors," November 1990.
3. XN-NF-79-71 (P)(A) Revision 2 and Supplements 1, 2 & 3, "Exxon Nuclear Plant Transient Methodology for Boiling Water Reactors," March 1986.
4. XN-NF-80-19 (P)(A) Volume 1 Supplements I and 2, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis," March 1993.
5. XN-NF-80-19 (P)(A) Volume I Supplement 3, Supplement 3 Appendix F, and Supplement 4, Exxon Nuclear Methodology for Boiling Water Reactors," November 1990.
6. XN-NF-80-19 (P)(A) Volumes 2, 2A, 2B and 2C, Exxon Nuclear Methodology for Boiling Water Reactors:

EXEM BWR ECCS Evaluation Model," September 1982.

7. XN-NF-80-19 (P)(A) Volume 3 Revision 2, "Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description," January 1987.
8. XN-NF-80-19 (P)(A) Volume 4 Revision 1, 'Exxon Nuclear Methodology for Boiling Water Reactors:

Application of the ENC Methodology to BWR Reloads," June 1986.

9. XN-NF-85-67 (P)(A) Revision 1, Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," September 1986.
10. ANF-913 (P)(A) Volume 1 Revision 1, and Volume 1 Supplements 2, 3, 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transients Analysis," August 1990.
11. XN-NF-82 (P)(A) Revision 1 and Supplements 2, 4 and 5, Qualification of Exxon Nuclear Fuel for Extended Burnup," October 1986.
12. XN-NF-82 (P)(A) Supplement 1 Revision 2, "Qualification of Exxon Nuclear Fuel for Extended Burnup Supplement 1 Extended Burnup Qualification of ENC 9x9 BWR Fuel," May 1988.
13. ANF-89-14(P)(A) Revision 1 and Supplements 1 & 2, "Advanced Nuclear Fuels Corporation Generic Mechanical Design for Advanced Nuclear Fuels Corporation 9X9 - IX and 9x9 - 9X BWR Reload Fuel,"

October 1991.

14. ANF-89-14(P), "Advanced Nuclear Fuels Corporation Generic Mechanical Design for Advanced Nuclear Fuels Corporation 9X9 - IX and 9x9 - 9X BWR Reload Fuel," May 1989.
15. ANF-89-98 (P)(A), "Generic Mechanical Design Criteria for BWR Fuel Designs," Revision 1 and Revision 1 Supplement 1, May 1995.
16. ANF-91-048 (P)(A), Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors EXEM BWR ECCS Evaluation Model," January 1993.
17. Commonwealth Edison Company Topical Report NFSR-0091, Benchmark of CASMO/MICROBURN BWR Nuclear Design Methods," Revision 0 and Supplements on Neutronics Licensing Analysis (Supplement 1) and La Salle County Unit 2 benchmarking (Supplement 2), December 1991, March 1992, and May 1992, respectively.

Dresden Unit 3 Cycle 18 6-1 Revision I

18. EMF-85-74 (P) Revision 0 and Supplement 1(P)(A) and Supplement 2(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," February 1998.
19. NEDE-24011-P-A-14 Revision 14, General Electric Standard Application for Reactor Fuel (GESTAR),"

June 2000.

20. NEDC-32981 P Revision 0, GEXL96 Correlation for ATRIUM-9B Fuel", September 2000.
21. ANF-1125(P)(A), Supplement I Appendix E, ANFB Critical Power Correlation Determination of ATRIUM-9B Additive Constant uncertainties," September 1998.
22. ANF-91-048(P)(A), Supplements 1 and 2, 'BWR Jet Pump Model Revision for RELAX," October 1997.

Dresden Unit 3 Cycle 18 6-2 Revision 1

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