ML023080105

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Core Operating Limits Report for Dresden Unit 3 Cycle 18
ML023080105
Person / Time
Site: Dresden Constellation icon.png
Issue date: 10/22/2002
From: Hovey R
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RHLTR: #02-0075
Download: ML023080105 (20)
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Text

Exelkns.

Exelon Generation wwwexeloncorpcorn NucleaT Dresden Generating Station 6500 North Dresden Road Morms, IL60450-9765 Tel 815-942-2920 October 22, 2002 RHLTR: #02-0075 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington D.C. 20555-0001 Dresden Nuclear Power Station, Unit 3 Facility Operating License No. DPR-25 NRC Docket No. 50-249

Subject:

Core Operating Limits Report for Unit 3 Cycle 18 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for the upcoming operating cycle (D3C1 8) in accordance with Technical Specification (TS) Section 5.6.5, "CORE OPERATING LIMITS REPORT (COLR)." The analytical methods used to determine the operating limits were NRC approved. The COLR is enclosed as an attachment to this letter Should you have any questions concerning this letter, please contact Mr. J. Hansen at (815) 416-2800.

Respectfully, R.J. Hovey L

Site Vice President Dresden Nuclear Power Station

Attachment:

Core Operating Limits Report, Dresden Station Unit 3 Cycle 18, Revision 0 cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - Dresden Nuclear Power Station Aoo)

Core Operating Limits Report for Dresden Unit 3 Cycle 18 Revision 0

Issuance of Changes Summary Affected Affected Summary of Changes Revision Date Section Pages I I All All Original Issue (Cycle 18) 0 10102 Dresden Unit 3 Cycle 18 ii Revision 0

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. M inim um 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 W ithdrawal Block Instrum entation ................................................. 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. M ethodology (5.6.5) .............................................................................................. 6-1 Dresden Unit 3 Cycle 18 iii Revision 0

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 NFM0200041 Sequence 02, April 24, 2002.
13. Letter from Russell Lindquist (GNF) to Jim Nevling (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.

Dresden Unit 3 Cycle 18 iv Revision 0

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 I 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-SPCIOOT-9WR-144-T6-2450 ATRM9-P9DATB360-12GZ-SPCIOOT-9WR-144-T6-2451 ATRM9-P9DATB378-13GZ-SPCIOOT-9WR-144-T6-2464 ATRM9-P9DATB378-1 1GZ-SPC100T-9WR-144-T6-2465 (Bundles2447, 2448, 2449, 2450,2451, 2464, 2465, bundle types 16, 17, 18, 19, 20, 1 and 2)

(Reference 3 Section 16 and Reference 13)

Planar Average Exposure MAPLHGR (GWd/MTU) (kWIft) 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 GE14-PIODNAB408-16GZ-10OT-145-T6-2554 GE14-PIODNAB411-4G7.0/9G6.0-10OT-145-T6-2553 (Bundles 2553 and 2554, bundle types 3 and 4)

(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 0

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 18 Option A MCPR limits utilized a 20%

core average insertion time of 0.900 seconds (Reference 7 Page 6).

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 Page 6). 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 Dresden Unit 3 Cycle 18 2-1 Revision 0

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 0

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

Cycle Exposure EOOS Combination Fuel Type <13,800 >13,800 MWd/MT MWdlMT GE14 1.53 1.65 Base Case ATRIUM-9B 1.52 1.61 Base Case SLO GE14 1.54 1.66 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 GE1I4 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 0

Table 2-2 MCPR Option B Based Operating Limits (Reference 3 Appendix G, Reference 14 and Reference 9 page 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 1A8 TCV Slow Closure ATRIUM-gB 1.41 1.44 GE14 1.47 1.49 TCV Slow Closure SLO ATRIUM-gB 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 0

Table 2-3 MCPRp for GE and SPC Fuel (Reference 3 Appendix G)

Core Thermal Power (% of rated)

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

(% of rated)

Ooeratina Limit MCPR Operating Limit MCPR Multiplier, Kp

<*60 3.16 2.58 2.27 Base Case 1.32 1.28 1.15 11.00

> 60 3.77 2.99 2.56

  • 60 3.17 2.59 2.28 ~1.00 Base Case SLO 1.32 1.28 1.15

> 60 3.78 3.00 2.57

  • 60 5.55 3.77 2.82 TBPOOS 1.37 1.28 1.15 1.00

> 60 6.79 4.62 3.45

< 60 5.56 3.78 2.83 ~1.00 TBPOOS SLO 1.37 1.28 1.15

> 60 6.80 4.63 3.46

  • 60 5.55 3.77 2.82 TCV Slow Closure 1.64 1.45 1.26 1.11 1.00

> 60 6.79 4.62 3.45

  • 60 5.56 3.78 2.83 TCV Slow Closure SLO 1.64 1.45 1.26 1.11 1.00

> 60 6.80 4.63 3.46 PLUOOS

  • 60 555 3.77 282 1.64 1.45 1.26 1.11 1.00

> 60 6.79 4.62 3.45

  • 60 5.56 3.78 2.83 PLU>OS SLO

_____________ > 60 6 80 4 63 3.46 ____ 1.64 1.45 1.26 1.11 1.00 560 3.16 2.58 2.27 TCV Stuck Closed + + 1.32 1 1.28 1 1.15 1.00

> 60 3.77 2.99 2.56 TCV Stuck Closed SLO 1*60!56 3.17 2.5912.281I 1 1.32 1 28 1.15 1.00

>.60 1 3.7 3.00 2.57 1 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 0

Table 2-4 MCPRF limits for all fuel types and all operating conditions except TCV Stuck Closed (Reference 9 Page 8)

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 Page 8)

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 Mlb/hr.
  • 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 0

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, or 3-3 and the minimum of either the power dependent LHGR Factor, LHGRFACp, or the flow dependent LHGR Factor, LHGRFACF. 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.

Table 3-1 LHGR Limits for Bundle Types GE14-P10DNAB408-16GZ-100T-145-T6-2554 (Bundle 2554, bundle type 4)

(Reference 4 Page 6)

Nodal Exposure LHGR Limit (GWd/MT) (kWlft) 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-PIODNAB411-4G7.0/9G6.0-1OOT-145-T6-2553 (Bundle 2553, bundle type 3)

(Reference 4 Page 6)

Nodal Exposure LHGR Limit (GWdlMT) (kW/ft) 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 0

Table 3-3 LHGR Limits 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-SPCI OOT-9WR-144-T6-2450 ATRM9-P9DATB360-12GZ-SPC1 OOT-9WR-144-T6-2451 ATRM9-P9DATB378-13GZ-SPC1 OOT-9WR-144-T6-2464 ATRM9-P9DATB378-1 1GZ-SPC1 OOT-9WR-144-T6-2465 (Bundles 2447,2448, 2449, 2450,2451, 2464, 2465, bundle types 16, 17, 18, 19, 20, 1 and 2)

(Reference 8 Figure 2.1)

Nodal Exposure LHGR Limit (GWdiMT) (kWlft) 0.00 14.40 15.00 14.40 64.30 7.90 Dresden Unit 3 Cycle 18 3-2 Revision 0

Table 3-4 LHGRFACp for all fuel types (Reference 3 Appendix G)

Core Thermal Power (% of rated)

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

(% of rated)

L 4-

  • 60 0..86 1.00 Base Case > 60 0.50 0.56 0.59

< 60 0.86 1.00 Base Case SLO > 60 0.50 0.56 0.59 0.68

< 60 0.22 0.48

  • 1.00 TBPOOS 0.39 0.54

> 60 0.33 0.42

<*60 0.22 0.48 TBPOOS SLO 0.39 0.54 1.00

> 60 0.33 0.42 S~1.00

< 60 0.22 0.48 TCV Slow Closure 0.39

> 60 0.33 0.42

< 60 0.22 0.48 TCV Slow Closure SLO 0.39 0.54 0.73 0.78 1.00

> 60 0.33 0.42 S~1.00 PLUOS 60 .22 0.39 0.48 0.54 0.73 0.78

> 60 0.33 0.42 1

> 60

  • 60 0.33 0.39 0.42 0.8 1.0oo TCV Stuck Closed TCV Stuck Closed SLO 560

> 60 0.50 0.50 0.56 0.56 0.59 0.59 0.68 0.68 o1.00o 0.8

> 60 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.

Dresden Unit 3 Cycle 18 3-3 Revision 0

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 LHGRFAC 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.
  • LFI-GRFACF multipliers are applicable to all fuel types used in cycle 18.

0 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.

Dresden Unit 3 Cycle 18 3-4 Revision 0

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 Page 11):

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 0

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:

I....-OPERATING REGION-...---

Equipment Out of Service Options1'23 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, Option A or B Yes Yes Yes TCV Slow Closure SLO, 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, Option A or B Yes Yes Yes TCV Stuck Closed SLO, Option A or B Yes Yes Yes 1 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 1201F 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.

Dresden Unit 3 Cycle 18 5-1 Revision 0

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 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, OExxon 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 1 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 I 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 I Extended Burnup Qualification of ENC 9x9 BWR Fuel," May 1988.
13. ANF-89-14(P)(A) Revision 1 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 I 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 0

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 Revisioh 14, "General Electric Standard Application for Reactor Fuel (GESTAR)," June 2000.
20. NEDC-32981P Revision 0, "GEXL96 Correlation for ATRIUM-9B Fuel", September 2000.
21. ANF-1125(P)(A), Supplement 1 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.

Dresden Unit 3 Cycle 18 6-2 Revision 0

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