ML040090150
| ML040090150 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 10/31/2003 |
| From: | Global Nuclear Fuel |
| To: | NRC/NRR/DLPM/LPD3 |
| Banerjee, M, NRR/DLPM/LPD III-2, 415-227 | |
| References | |
| 000-0006-9848-SRLR Rev. 2 | |
| Download: ML040090150 (77) | |
Text
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 2 Important Notice Regarding Contents of This Report Please Read Carefully This report was prepared by Global Nuclear Fuel - Americas, LLC (GNF) solely for Exelon Nuclear. The information contained in this report is believed by GNF to be an accurate and true representation of the facts known, obtained or provided to GNF at the time this report was prepared.
The only undertakings of GNF respecting information in this document are contained in the contract between Exelon Nuclear and GNF for Fuel Bundle Fabrication and Related Services for the Dresden Unit 3 and nothing contained in this document shall be construed as changing said contract. The use of this information except as defined by said contract, or for any purpose other than that for which it is intended, is not authorized; and with respect to any such unauthorized use, neither GNF nor any of the contributors to this document makes any representation or warranty (expressed or implied) as to the completeness, accuracy or usefulness of the information contained in this document or that such use of such information may not infringe privately owned rights; nor do they assume any responsibility for liability or damage of any kind which may result from such use of such information.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 3 Acknowledgement The engineering and reload licensing analyses, which form the technical basis of this Supplemental Reload Licensing Report, were performed by GNF Fuel Engineering Services (GNFFES) and GENE Nuclear and Safety Analysis (GENE N&SA) personnel. The Supplemental Reload Licensing Report was prepared by H. Zhang. This document has been verified by G.I. Maldonado.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 4 The basis for this report is General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A-14, June 2000; and the U.S. Supplement, NEDE-24011-P-A-14-US, June 2000.
- 1.
Plant-unique Items Appendix A: Analysis Conditions Appendix B: Decrease in Core Coolant Temperature Events Appendix C: Operating Flexibility Options Appendix D: Extended Power Uprate (EPU)
Appendix E: Decay Ratio Calculations Appendix F: Legacy Fuel Licensing Applicability Appendix G: COLR Inputs
- 2. Reload Fuel Bundles Cycle Fuel Type Loaded Number Irradiated:
ANF9X9-2-P9DANB313-7G3.5-SPC80M-145-T6-2453 14 6
ANF9X9-2-P9DANB313-11GZ-SPC80M-145-T6-2452 14 18 ATRM9-P9DATB362-12GZ-SPC100T-9WR-144-T6-2450 16 160 ATRM9-P9DATB360-12GZ-SPC100T-9WR-144-T6-2451 16 16 ATRM9-P9DATB378-13GZ-SPC100T-9WR-144-T6-2464 17 112 ATRM9-P9DATB378-11GZ-SPC100T-9WR-144-T6-2465 17 128 New:
GE14-P10DNAB408-16GZ-100T-145-T6-2554 (GE14C) 18 136 GE14-P10DNAB411-4G7.0/9G6.0-100T-145-T6-2553 (GE14C) 18 148 Total 724
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 5
- 3.
Reference Core Loading Pattern Nominal previous cycle core average exposure at end of cycle:
30784 MWd/MT
( 27927 MWd/ST)
Minimum previous cycle core average exposure at end of cycle from cold shutdown considerations:
30284 MWd/MT
( 27473 MWd/ST)
Assumed reload cycle core average exposure at beginning of cycle:
15102 MWd/MT
( 13700 MWd/ST)
Assumed reload cycle core average exposure at end of cycle:
31428 MWd/MT
( 28511 MWd/ST)
Reference core loading pattern:
Figure 1
- 4.
Calculated Core Effective Multiplication and Control System Worth - No Voids, 20°C Beginning of Cycle, keffective Uncontrolled 1.105 Fully controlled 0.950 Strongest control rod out 0.989 R, Maximum increase in cold core reactivity with exposure into cycle, k 0.001
- 5. Standby Liquid Control System Shutdown Capability Boron (ppm)
(at 20°C)
Shutdown Margin (k)
(at 160°C, Xenon Free) 600 0.021
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 6
- 6.
Reload Unique GETAB Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters1 Exposure: BOC18 to EOR2-1663 MWd/MT ICF-HBB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.55 1.64 1.040 6.173 118.3 1.39 ATRM9 1.20 1.39 1.64 1.050 5.511 123.6 1.39 Exposure: EOR-1663 MWd/MT to EOC183 ICF-HBB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.48 1.77 1.040 5.912 121.0 1.41 ATRM9 1.20 1.39 1.77 1.050 5.543 124.0 1.36 Exposure: BOC18 to EOR-1663 MWd/MT ICF-FFWTR-HBB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.60 1.62 1.040 6.376 116.6 1.40 ATRM9 1.20 1.44 1.62 1.050 5.692 121.8 1.39 Exposure: EOR-1663 MWd/MT to EEOC184 ICF-FFWTR-HBB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.55 1.78 1.040 6.178 119.5 1.40 ATRM9 1.20 1.42 1.78 1.050 5.633 123.2 1.38 1 Note that FANP 9x9-2 fuel in DRESDEN 3 Reload 17 is bounded by FANP ATRIUM-9B fuel.
2 EOR is the end of rated exposure obtained at 100% power and 100% flow conditions.
3 EOC is the exposure obtained with increased core flow only.
4 EEOC is the exposure obtained with increased core flow and with up to 120oF feedwater temperature reduction.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 7 Exposure: EOR-1663 MWd/MT to EOC18 MELLLA-HBB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.49 1.71 1.040 5.951 105.3 1.37 ATRM9 1.20 1.40 1.71 1.050 5.542 107.7 1.34 Exposure: BOC18 to EOC18 ICF_TBPOOS-HBB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.42 1.77 1.040 5.665 122.5 1.47 ATRM9 1.20 1.35 1.77 1.050 5.352 125.4 1.41 Exposure: BOC18 to EEOC18 ICF-FFWTR_TBPOOS-HBB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.48 1.78 1.040 5.904 121.2 1.47 ATRM9 1.20 1.39 1.78 1.050 5.524 124.0 1.41 Exposure: BOC18 to EOC18 MELLLA_TBPOOS-HBB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.45 1.71 1.040 5.758 106.4 1.42 ATRM9 1.20 1.35 1.71 1.050 5.346 109.0 1.40 Exposure: BOC18 to EOC18 ICF_TCVSC-HBB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.49 1.77 1.040 5.936 120.8 1.40 ATRM9 1.20 1.40 1.77 1.050 5.551 124.0 1.36
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 8 Exposure: BOC18 to EOC18 MELLLA_TCVSC-HBB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.48 1.71 1.040 5.902 105.6 1.38 ATRM9 1.20 1.40 1.71 1.050 5.545 107.7 1.34 Exposure: BOC18 to EOC18 ICF_PLUOOS-HBB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.45 1.77 1.040 5.762 121.9 1.45 ATRM9 1.20 1.36 1.77 1.050 5.396 125.1 1.40 Exposure: BOC18 to EOC18 MELLLA_PLUOOS-HBB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.45 1.71 1.040 5.781 106.3 1.42 ATRM9 1.20 1.37 1.71 1.050 5.449 108.3 1.37 Exposure: BOC18 to EOC18 ICF-UDB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.64 1.28 1.040 6.522 113.7 1.41 ATRM9 1.20 1.49 1.28 1.050 5.907 119.5 1.37
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 9 Exposure: BOC18 to EEOC18 ICF-FFWTR-UDB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.69 1.27 1.040 6.714 112.0 1.42 ATRM9 1.20 1.52 1.27 1.050 6.025 118.0 1.38 Exposure: EOR-1663 MWd/MT to EOC18 MELLLA-UDB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.60 1.23 1.040 6.376 99.4 1.40 ATRM9 1.20 1.50 1.23 1.050 5.944 103.2 1.33 Exposure: BOC18 to EOC18 ICF_TBPOOS-UDB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.59 1.28 1.040 6.329 114.9 1.46 ATRM9 1.20 1.45 1.28 1.050 5.752 120.7 1.41 Exposure: BOC18 to EEOC18 ICF-FFWTR_TBPOOS-UDB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.65 1.27 1.040 6.550 113.1 1.46 ATRM9 1.20 1.50 1.27 1.050 5.926 118.8 1.41 Exposure: BOC18 to EOC18 MELLLA_TBPOOS-UDB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.55 1.23 1.040 6.183 100.6 1.45 ATRM9 1.20 1.44 1.23 1.050 5.721 104.8 1.39
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 10 Exposure: BOC18 to EOC18 ICF_TCVSC-UDB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.65 1.28 1.040 6.588 113.3 1.40 ATRM9 1.20 1.54 1.28 1.050 6.125 117.9 1.32 Exposure: BOC18 to EOC18 MELLLA_TCVSC-UDB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.64 1.23 1.040 6.510 98.6 1.37 ATRM9 1.20 1.53 1.23 1.050 6.060 102.4 1.30 Exposure: BOC18 to EOC18 ICF_PLUOOS-UDB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.62 1.28 1.040 6.438 114.2 1.44 ATRM9 1.20 1.50 1.28 1.050 5.947 119.2 1.36 Exposure: BOC18 to EOC18 MELLLA_PLUOOS-UDB Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GE14C 1.45 1.58 1.23 1.040 6.292 99.9 1.43 ATRM9 1.20 1.49 1.23 1.050 5.891 103.6 1.34
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 11
- 7. Selected Margin Improvement Options Recirculation pump trip:
No Rod withdrawal limiter:
No Thermal power monitor:
No Improved scram time:
Yes (ODYN Option B)
Measured scram time:
No Exposure dependent limits:
Yes Exposure points analyzed:
2
- 8.
Operating Flexibility Options Single-loop operation:
Yes Load line limit:
No Extended load line limit:
No Maximum extended load line limit:
Yes Increased core flow throughout cycle:
Yes Flow point analyzed:
108.0 %
Feedwater temperature reduction throughout cycle:
Yes Temperature reduction:5 120.0°F Final feedwater temperature reduction:
Yes ARTS Program (power and flow dependent limits):
Yes Maximum extended operating domain:
Yes Moisture separator reheater OOS:
No Turbine bypass system OOS:
Yes Safety/relief valves OOS:
Yes (1 valve OOS)
ADS OOS:
No Main steam isolation valves OOS:
Yes 5 See Appendix C.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 12 Turbine control valve slow closure:
Yes Turbine control valve stuck closed:
Yes Power load unbalance OOS:
Yes
- 9. Core-wide AOO Analysis Results Methods used: GEMINI; GEXL-PLUS Exposure range: BOC18 to EOR-1663 MWd/MT ICF-HBB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
FW Controller Failure 593 137 0.29 0.29 2
Load Reject w/o Bypass 572 130 0.28 0.25 3
Turbine Trip w/o Bypass 566 129 0.27 0.25 4
Exposure range: EOR-1663 MWd/MT to EOC18 ICF-HBB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
FW Controller Failure 547 134 0.28 0.28 5
Load Reject w/o Bypass 526 128 0.31 0.26 6
Turbine Trip w/o Bypass 523 127 0.29 0.25 7
Exposure range: BOC18 to EOR-1663 MWd/MT ICF-FFWTR-HBB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
FW Controller Failure 568 139 0.30 0.29 8
Exposure range: EOR-1663 MWd/MT to EEOC18 ICF-FFWTR-HBB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
FW Controller Failure 506 136 0.29 0.28 9
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 13 Exposure range: EOR-1663 MWd/MT to EOC18 MELLLA-HBB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
FW Controller Failure 533 134 0.26 0.27 10 Load Reject w/o Bypass 520 128 0.27 0.24 11 Turbine Trip w/o Bypass 517 127 0.26 0.24 12 Exposure range: BOC18 to EOC18 ICF_TBPOOS-HBB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
FW Controller Failure 586 137 0.37 0.31 13 Exposure range: BOC18 to EEOC18 ICF-FFWTR_TBPOOS-HBB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
FW Controller Failure 521 137 0.37 0.31 14 Exposure range: BOC18 to EOC18 MELLLA_TBPOOS-HBB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
FW Controller Failure 579 136 0.32 0.29 15 Exposure range: BOC18 to EOC18 ICF_TCVSC-HBB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
Load Reject w/o Bypass 328 120 0.30 0.26 16 Exposure range: BOC18 to EOC18 MELLLA_TCVSC-HBB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
Load Reject w/o Bypass 327 120 0.28 0.24 17
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 14 Exposure range: BOC18 to EOC18 ICF_PLUOOS-HBB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
Load Reject w/o Bypass 374 127 0.35 0.30 18 Exposure range: BOC18 to EOC18 MELLLA_PLUOOS-HBB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
Load Reject w/o Bypass 367 127 0.31 0.26 19 Exposure range: BOC18 to EOC18 ICF-UDB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
FW Controller Failure 482 131 0.31 0.27 20 Load Reject w/o Bypass 488 126 0.30 0.25 21 Turbine Trip w/o Bypass 491 125 0.30 0.25 22 Exposure range: BOC18 to EEOC18 ICF-FFWTR-UDB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
FW Controller Failure 457 134 0.32 0.28 23 Exposure range: EOR-1663 MWd/MT to EOC18 MELLLA-UDB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
FW Controller Failure 411 127 0.29 0.24 24 Load Reject w/o Bypass 422 123 0.30 0.23 25 Turbine Trip w/o Bypass 414 122 0.30 0.23 26
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 15 Exposure range: BOC18 to EOC18 ICF_TBPOOS-UDB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
FW Controller Failure 552 135 0.36 0.31 27 Exposure range: BOC18 to EEOC18 ICF-FFWTR_TBPOOS-UDB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
FW Controller Failure 482 136 0.36 0.31 28 Exposure range: BOC18 to EOC18 MELLLA_TBPOOS-UDB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
FW Controller Failure 481 132 0.36 0.29 29 Exposure range: BOC18 to EOC18 ICF_TCVSC-UDB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
Load Reject w/o Bypass 362 123 0.29 0.22 30 Exposure range: BOC18 to EOC18 MELLLA_TCVSC-UDB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
Load Reject w/o Bypass 356 123 0.27 0.20 31 Exposure range: BOC18 to EOC18 ICF_PLUOOS-UDB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
Load Reject w/o Bypass 341 126 0.33 0.26 32
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 16 Exposure range: BOC18 to EOC18 MELLLA_PLUOOS-UDB Uncorrected CPR Event Flux
(%NBR)
Q/A
(%NBR)
GE14C ATRM9 Fig.
Load Reject w/o Bypass 307 123 0.32 0.24 33
- 10. Local Rod Withdrawal Error (With Limiting Instrument Failure) AOO Summary Rod Block CPR GE14C ATRM9 Unblocked 0.24 0.24 See Figure 36 for Limiting Rod Pattern.
- 11. Cycle MCPR Values 6 Safety limit:
1.10 Single loop operation safety limit:
1.11 Non-pressurization events:
All Fuel Types Fuel Loading Error (Misoriented) 1.267 Control Rod Withdrawal Error (Unblocked) 1.34 Loss of Feedwater Heating (See Appendix B) 1.29 6 For single-loop operation, the MCPR operating limit is 0.01 greater than the two-loop value.
7 Based on GE14 results reported in Section 13.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 17 Pressurization events: 8 Exposure range: BOC18 to EOR-1663 MWd/MT ICF-HBB Exposure point: EOR-1663 MWd/MT Option A Option B GE14C ATRM9 GE14C ATRM9 FW Controller Failure 1.51 1.52 1.40 1.41 Load Reject w/o Bypass 1.51 1.48 1.40 1.37 Turbine Trip w/o Bypass 1.50 1.48 1.39 1.37 Exposure range: EOR-1663 MWd/MT to EOC18 ICF-HBB Exposure point: EOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 FW Controller Failure 1.61 1.61 1.44 1.44 Load Reject w/o Bypass 1.63 1.59 1.46 1.42 Turbine Trip w/o Bypass 1.62 1.57 1.45 1.40 Exposure range: BOC18 to EOR-1663 MWd/MT ICF-FFWTR-HBB Exposure point: EOR-1663 MWd/MT Option A Option B GE14C ATRM9 GE14C ATRM9 FW Controller Failure 1.53 1.52 1.42 1.41 Exposure range: EOR-1663 MWd/MT to EEOC18 ICF-FFWTR-HBB Exposure point: EEOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 FW Controller Failure 1.62 1.61 1.45 1.44 8 ECCS MCPR value is 1.27 for GE14C and 1.35 for ATRM9.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 18 Exposure range: EOR-1663 MWd/MT to EOC18 MELLLA-HBB Exposure point: EOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 FW Controller Failure 1.59 1.59 1.42 1.42 Load Reject w/o Bypass 1.59 1.56 1.42 1.39 Turbine Trip w/o Bypass 1.58 1.56 1.41 1.39 Exposure range: BOC18 to EOC18 ICF_TBPOOS-HBB Exposure point: EOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 FW Controller Failure 1.70 1.64 1.53 1.47 Exposure range: BOC18 to EEOC18 ICF-FFWTR_TBPOOS-HBB Exposure point: EEOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 FW Controller Failure 1.70 1.64 1.53 1.47 Exposure range: BOC18 to EOC18 MELLLA_TBPOOS-HBB Exposure point: EOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 FW Controller Failure 1.65 1.62 1.48 1.45 Exposure range: BOC18 to EOC18 ICF_TCVSC-HBB Exposure point: EOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 Load Reject w/o Bypass 1.63 1.58 1.46 1.41 Exposure range: BOC18 to EOC18 MELLLA_TCVSC-HBB Exposure point: EOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 Load Reject w/o Bypass 1.61 1.56 1.44 1.39
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 19 Exposure range: BOC18 to EOC18 ICF_PLUOOS-HBB Exposure point: EOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 Load Reject w/o Bypass 1.68 1.63 1.51 1.46 Exposure range: BOC18 to EOC18 MELLLA_PLUOOS-HBB Exposure point: EOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 Load Reject w/o Bypass 1.64 1.59 1.47 1.42 Exposure range: BOC18 to EOC18 ICF-UDB Exposure point: EOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 FW Controller Failure 1.64 1.60 1.47 1.43 Load Reject w/o Bypass 1.63 1.58 1.46 1.41 Turbine Trip w/o Bypass 1.63 1.57 1.46 1.40 Exposure range: BOC18 to EEOC18 ICF-FFWTR-UDB Exposure point: EEOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 FW Controller Failure 1.65 1.61 1.48 1.44 Exposure range: EOR-1663 MWd/MT to EOC18 MELLLA-UDB Exposure point: EOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 FW Controller Failure 1.62 1.56 1.45 1.39 Load Reject w/o Bypass 1.63 1.55 1.46 1.38 Turbine Trip w/o Bypass 1.62 1.55 1.45 1.38
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 20 Exposure range: BOC18 to EOC18 ICF_TBPOOS-UDB Exposure point: EOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 FW Controller Failure 1.69 1.64 1.52 1.47 Exposure range: BOC18 to EEOC18 ICF-FFWTR_TBPOOS-UDB Exposure point: EEOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 FW Controller Failure 1.69 1.64 1.52 1.47 Exposure range: BOC18 to EOC18 MELLLA_TBPOOS-UDB Exposure point: EOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 FW Controller Failure 1.69 1.61 1.52 1.44 Exposure range: BOC18 to EOC18 ICF_TCVSC-UDB Exposure point: EOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 Load Reject w/o Bypass 1.62 1.54 1.45 1.37 Exposure range: BOC18 to EOC18 MELLLA_TCVSC-UDB Exposure point: EOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 Load Reject w/o Bypass 1.59 1.52 1.42 1.35 Exposure range: BOC18 to EOC18 ICF_PLUOOS-UDB Exposure point: EOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 Load Reject w/o Bypass 1.66 1.58 1.49 1.41
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 21 Exposure range: BOC18 to EOC18 MELLLA_PLUOOS-UDB Exposure point: EOC18 Option A Option B GE14C ATRM9 GE14C ATRM9 Load Reject w/o Bypass 1.65 1.56 1.48 1.39
- 12. Overpressurization Analysis Summary Event PDome (psig)
Pv (psig)
Psl (psig)
Plant
Response
ICF-HBB MSIV Closure (Flux Scram)
(0 SRV OOS) 1336.4 1362.2 1332.8 Figure 34 MEL-HBB MSIV Closure (Flux Scram)
(0 SRV OOS) 1338.6 1361.2 1334.9 Figure 35
- 13. Loading Error Results Variable water gap misoriented bundle analysis: Yes 9 Misoriented Fuel Bundle CPR GE14-P10DNAB411-4G7.0/9G6.0-100T-145-T6-2553 (GE14C) 0.05 GE14-P10DNAB408-16GZ-100T-145-T6-2554 (GE14C) 0.16 ATRM9-P9DATB362-12GZ-SPC100T-9WR-144-T6-2450 0.27 ATRM9-P9DATB360-12GZ-SPC100T-9WR-144-T6-2451 0.29 ATRM9-P9DATB378-13GZ-SPC100T-9WR-144-T6-2464 0.13 ATRM9-P9DATB378-11GZ-SPC100T-9WR-144-T6-2465 0.13
- 14. Control Rod Drop Analysis Results This is a banked position withdrawal sequence plant, therefore, the control rod drop accident analysis is not required. NRC approval is documented in NEDE-24011-P-A-14-US.
If a rod sequence that eliminates some of the standard BPWS banked positions of 04, 08, and 12 (e.g. fast shutdown sequence) is to be used during the cycle, a cycle specific control rod drop accident analysis will be performed.
9 Includes a 0.02 penalty due to variable water gap R-factor uncertainty.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 22
- 15. Stability Analysis Results GE SIL-380 recommendations and BWROG Interim Corrective Actions (BWROG-94079) have been included in the Dresden 3 Cycle 18 operating procedures. Regions of restricted operation defined in to NRC Bulletin No. 88-07, Supplement 1, Power Oscillations in Boiling Water Reactors (BWRs) and expanded in BWROG-94079, are applicable to Dresden 3 Cycle 18 operation.
These provide the stability licensing bases for Dresden 3 Cycle 18. The validation of Interim Corrective Action regions can be found in Appendix E.
- 16. Loss-of-Coolant Accident Results LOCA method used: SAFER/GESTR-LOCA The SAFER/GESTR-LOCA analysis is documented in NEDC-32990P, Revision 1, SAFER/GESTR-LOCA Loss-of Coolant Accident for Dresden Nuclear Station 2 and 3 and Quad Cities Nuclear Station Units 1 and 2, September 2001. This analysis yielded the Licensing Basis Peak Cladding Temperatures (PCT) of 2110°F for GE14C and 2060°F for ATRIUM-9B fuels. The maximum local oxidation is <6%
and the core-wide metal water reaction is <0.1%. The initial operating MCPRs are 1.27 for GE14C and 1.35 for ATRIUM-9B fuels. The multipliers on PLHGR and MAPLHGR at SLO conditions are 0.77 for GE14C and 0.84 for ATRIUM-9B fuels. The multipliers on PLHGR and MAPLHGR to permit operation with one ADS valve out-of-service (ADSOOS) are 0.75 for both GE14C and ATRIUM-9B. When the plant is operated with both SLO and ADSOOS at the same time, the lower of the SLO and ADSOOS multipliers (0.75) should be applied to the PLHGR and MAPLHGR for both fuel types. This reduction will provide adequate protection for both conditions.
All reported ECCS-LOCA 10CFR50.46 errors have been addressed in the GE14C and ATRIUM-9B ECCS-LOCA analyses. No additional adjustment to the licensing PCT for GE14C and ATRIUM-9B is required.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 23
- 16. Loss-of-Coolant Accident Results (cont.)
The ECCS MAPLHGR operating limits for each of the fuel bundle types available for Dresden Unit 3 Cycle 18 core are presented in the following tables:
Bundle Type: GE14-P10DNAB411-4G7.0/9G6.0-100T-145-T6-2553 Average Planar Exposure MAPLHGR (GWd/ST)
(GWd/MT)
(kW/ft) 0.00 0.00 11.68 14.51 16.00 11.68 50.00 55.12 8.01 57.61 63.50 6.97 63.50 70.00 4.36 Bundle Type: GE14-P10DNAB408-16GZ-100T-145-T6-2554 Average Planar Exposure MAPLHGR (GWd/ST)
(GWd/MT)
(kW/ft) 0.00 0.00 11.68 14.51 16.00 11.68 50.00 55.12 8.01 57.61 63.50 6.97 63.50 70.00 4.36 Bundle Type: ATRM9-P9DATB378-13GZ-SPC100T-9WR-144-T6-2464 Average Planar Exposure MAPLHGR (GWd/ST)
(GWd/MT)
(kW/ft) 0.00 0.00 13.52 15.65 17.25 13.52 63.50 70.00 7.84 Bundle Type: ATRM9-P9DATB378-11GZ-SPC100T-9WR-144-T6-2465 Average Planar Exposure MAPLHGR (GWd/ST)
(GWd/MT)
(kW/ft) 0.00 0.00 13.52 15.65 17.25 13.52 63.50 70.00 7.84
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 24
- 16.
Loss-of-Coolant Accident Results (cont.)
Bundle Type: ATRM9-P9DATB362-12GZ-SPC100T-9WR-144-T6-2450 Average Planar Exposure MAPLHGR (GWd/ST)
(GWd/MT)
(kW/ft) 0.00 0.00 13.52 15.65 17.25 13.52 63.50 70.00 7.84 Bundle Type: ATRM9-P9DATB360-12GZ-SPC100T-9WR-144-T6-2451 Average Planar Exposure MAPLHGR (GWd/ST)
(GWd/MT)
(kW/ft) 0.00 0.00 13.52 15.65 17.25 13.52 63.50 70.00 7.84 Bundle Type: ANF9X9-2-P9DANB313-11GZ-SPC80M-145-T6-2452 Average Planar Exposure MAPLHGR (GWd/ST)
(GWd/MT)
(kW/ft) 0.00 0.00 13.52 15.65 17.25 13.52 63.50 70.00 7.84 Bundle Type: ANF9X9-2-P9DANB313-7G3.5-SPC80M-145-T6-2453 Average Planar Exposure MAPLHGR (GWd/ST)
(GWd/MT)
(kW/ft) 0.00 0.00 13.52 15.65 17.25 13.52 63.50 70.00 7.84
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 25 60 G
G G
G G
G G
G G
G 58 E
G G
B A
A A
A B
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E 56 G
G F
A A
B B
B G
G B
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A A
G F
G 54 F
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C C
C C
C C
C C
C C
A B
A G
F 52 G
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A C
C G
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D D
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B C
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C A
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B D
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A A
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D D
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D D
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G C
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B D
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D D
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G 32 G
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D D
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D D
D G
C B
C A
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B A
G 26 G
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C A
D B
D G
D B
C A
D B
B D
A C
B D
G D
B D
A C
B B
G 24 G
G B
C C
C B
D D
D B
G C
D H
H D
C G
B D
D D
B C
C C
B G
E 22 G
G A
C G
C G
A B
D B
B B
D B
B D
B B
B D
B A
G C
G C
A G
G 20 F
A A
C G
D D
D G
D D
D G
D D
G D
D D
G D
D D
G C
A A
F 18 F
B C
C B
D G
D B
D G
C A
A C
G D
B D
G D
B C
C B
G 16 G
A A
C D
G D
D A
D D
B D
D B
D D
A D
D G
D C
A A
G 14 G
G A
B C
D B
D G
B B
C H
H C
B B
G D
B D
C B
A G
G 12 F
G A
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C G
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D A
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A D
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G C
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2 G
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G 1
3 5
7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 57 59 49 51 53 55 Fuel Type A=ATRM9-P9DATB378-13GZ-SPC100T-9WR-144-T6-2464 (Cycle 17)
B=ATRM9-P9DATB378-11GZ-SPC100T-9WR-144-T6-2465 (Cycle 17)
C=GE14-P10DNAB411-4G7.0/9G6.0-100T-145-T6-2553 (Cycle 18)
D=GE14-P10DNAB408-16GZ-100T-145-T6-2554 (Cycle 18)
E=ANF9X9-2-P9DANB313-7G3.5-SPC80M-145-T6-2453 (Cycle 14)
F=ANF9X9-2-P9DANB313-11GZ-SPC80M-145-T6-2452 (Cycle 14)
G=ATRM9-P9DATB362-12GZ-SPC100T-9WR-144-T6-2450 (Cycle 16)
H=ATRM9-P9DATB360-12GZ-SPC100T-9WR-144-T6-2451 (Cycle 16)
Figure 1 Reference Core Loading Pattern
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 26
-25.0 25.0 75.0 125.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow 0.0 50.0 100.0 150.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 5.0 10.0 15.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Core Inlet Subcooling Figure 2 Plant Response to FW Controller Failure (BOC18 to EOR-1663 MWd/MT ICF-HBB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 27 0.0 100.0 200.0 300.0 0.0 3.0 6.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-100.0 0.0 100.0 200.0 0.0 3.0 6.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 3.0 6.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 3.0 6.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Figure 3 Plant Response to Load Reject w/o Bypass (BOC18 to EOR-1663 MWd/MT ICF-HBB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 28 0.0 100.0 200.0 300.0 0.0 3.0 6.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-100.0 0.0 100.0 200.0 0.0 3.0 6.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 3.0 6.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 3.0 6.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Figure 4 Plant Response to Turbine Trip w/o Bypass (BOC18 to EOR-1663 MWd/MT ICF-HBB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 29
-25.0 25.0 75.0 125.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow 0.0 50.0 100.0 150.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 5.0 10.0 15.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Core Inlet Subcooling Figure 5 Plant Response to FW Controller Failure (EOR-1663 MWd/MT to EOC18 ICF-HBB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 30 0.0 100.0 200.0 300.0 0.0 3.0 6.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-100.0 0.0 100.0 200.0 0.0 3.0 6.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 3.0 6.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 3.0 6.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Figure 6 Plant Response to Load Reject w/o Bypass (EOR-1663 MWd/MT to EOC18 ICF-HBB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 31 0.0 100.0 200.0 300.0 0.0 3.0 6.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-100.0 0.0 100.0 200.0 0.0 3.0 6.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 3.0 6.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 3.0 6.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Figure 7 Plant Response to Turbine Trip w/o Bypass (EOR-1663 MWd/MT to EOC18 ICF-HBB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 32
-25.0 25.0 75.0 125.0 0.0 5.0 10.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow 0.0 50.0 100.0 150.0 0.0 5.0 10.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 5.0 10.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 5.0 10.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Core Inlet Subcooling Figure 8 Plant Response to FW Controller Failure (BOC18 to EOR-1663 MWd/MT ICF-FFWTR-HBB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 33
-25.0 25.0 75.0 125.0 0.0 5.0 10.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow 0.0 50.0 100.0 150.0 0.0 5.0 10.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 5.0 10.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 5.0 10.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Core Inlet Subcooling Figure 9 Plant Response to FW Controller Failure (EOR-1663 MWd/MT to EEOC18 ICF-FFWTR-HBB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 34
-25.0 25.0 75.0 125.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow 0.0 50.0 100.0 150.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 5.0 10.0 15.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Core Inlet Subcooling Figure 10 Plant Response to FW Controller Failure (EOR-1663 MWd/MT to EOC18 MELLLA-HBB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 35 0.0 100.0 200.0 300.0 0.0 3.0 6.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-100.0 0.0 100.0 200.0 0.0 3.0 6.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 3.0 6.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 3.0 6.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Figure 11 Plant Response to Load Reject w/o Bypass (EOR-1663 MWd/MT to EOC18 MELLLA-HBB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 36 0.0 100.0 200.0 300.0 0.0 3.0 6.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-100.0 0.0 100.0 200.0 0.0 3.0 6.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 3.0 6.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 3.0 6.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Figure 12 Plant Response to Turbine Trip w/o Bypass (EOR-1663 MWd/MT to EOC18 MELLLA-HBB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 37
-25.0 25.0 75.0 125.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow 0.0 50.0 100.0 150.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 5.0 10.0 15.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Core Inlet Subcooling Figure 13 Plant Response to FW Controller Failure (BOC18 to EOC18 ICF_TBPOOS-HBB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 38
-25.0 25.0 75.0 125.0 0.0 5.0 10.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow 0.0 50.0 100.0 150.0 0.0 5.0 10.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 5.0 10.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 5.0 10.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Core Inlet Subcooling Figure 14 Plant Response to FW Controller Failure (BOC18 to EEOC18 ICF-FFWTR_TBPOOS-HBB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 39
-25.0 25.0 75.0 125.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow 0.0 50.0 100.0 150.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 5.0 10.0 15.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Core Inlet Subcooling Figure 15 Plant Response to FW Controller Failure (BOC18 to EOC18 MELLLA_TBPOOS-HBB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 40 0.0 100.0 200.0 300.0 0.0 3.0 6.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-100.0 0.0 100.0 200.0 0.0 3.0 6.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 3.0 6.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 3.0 6.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Figure 16 Plant Response to Load Reject w/o Bypass (BOC18 to EOC18 ICF_TCVSC-HBB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 41 0.0 100.0 200.0 300.0 0.0 3.0 6.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-100.0 0.0 100.0 200.0 0.0 3.0 6.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 3.0 6.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 3.0 6.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Figure 17 Plant Response to Load Reject w/o Bypass (BOC18 to EOC18 MELLLA_TCVSC-HBB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 42 0.0 100.0 200.0 300.0 0.0 2.5 5.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-100.0 0.0 100.0 200.0 0.0 2.5 5.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 2.5 5.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 2.5 5.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Figure 18 Plant Response to Load Reject w/o Bypass (BOC18 to EOC18 ICF_PLUOOS-HBB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 43 0.0 100.0 200.0 300.0 0.0 2.5 5.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-100.0 0.0 100.0 200.0 0.0 2.5 5.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 2.5 5.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 2.5 5.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Figure 19 Plant Response to Load Reject w/o Bypass (BOC18 to EOC18 MELLLA_PLUOOS-HBB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 44
-25.0 25.0 75.0 125.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow 0.0 50.0 100.0 150.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 5.0 10.0 15.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Core Inlet Subcooling Figure 20 Plant Response to FW Controller Failure (BOC18 to EOC18 ICF-UDB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 45 0.0 100.0 200.0 300.0 0.0 3.0 6.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-100.0 0.0 100.0 200.0 0.0 3.0 6.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 3.0 6.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 3.0 6.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Figure 21 Plant Response to Load Reject w/o Bypass (BOC18 to EOC18 ICF-UDB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 46 0.0 100.0 200.0 300.0 0.0 3.0 6.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-100.0 0.0 100.0 200.0 0.0 3.0 6.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 3.0 6.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 3.0 6.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Figure 22 Plant Response to Turbine Trip w/o Bypass (BOC18 to EOC18 ICF-UDB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 47
-25.0 25.0 75.0 125.0 0.0 5.0 10.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow 0.0 50.0 100.0 150.0 0.0 5.0 10.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 5.0 10.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 5.0 10.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Core Inlet Subcooling Figure 23 Plant Response to FW Controller Failure (BOC18 to EEOC18 ICF-FFWTR-UDB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 48
-25.0 25.0 75.0 125.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow 0.0 50.0 100.0 150.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 5.0 10.0 15.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Core Inlet Subcooling Figure 24 Plant Response to FW Controller Failure (EOR-1663 MWd/MT to EOC18 MELLLA-UDB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 49 0.0 100.0 200.0 300.0 0.0 3.0 6.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-100.0 0.0 100.0 200.0 0.0 3.0 6.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 3.0 6.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 3.0 6.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Figure 25 Plant Response to Load Reject w/o Bypass (EOR-1663 MWd/MT to EOC18 MELLLA-UDB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 50 0.0 100.0 200.0 300.0 0.0 3.0 6.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-100.0 0.0 100.0 200.0 0.0 3.0 6.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 3.0 6.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 3.0 6.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Figure 26 Plant Response to Turbine Trip w/o Bypass (EOR-1663 MWd/MT to EOC18 MELLLA-UDB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 51
-25.0 25.0 75.0 125.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow 0.0 50.0 100.0 150.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 5.0 10.0 15.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Core Inlet Subcooling Figure 27 Plant Response to FW Controller Failure (BOC18 to EOC18 ICF_TBPOOS-UDB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 52
-25.0 25.0 75.0 125.0 0.0 5.0 10.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow 0.0 50.0 100.0 150.0 0.0 5.0 10.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 5.0 10.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 5.0 10.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Core Inlet Subcooling Figure 28 Plant Response to FW Controller Failure (BOC18 to EEOC18 ICF-FFWTR_TBPOOS-UDB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 53
-25.0 25.0 75.0 125.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow 0.0 50.0 100.0 150.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 5.0 10.0 15.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 5.0 10.0 15.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Core Inlet Subcooling Figure 29 Plant Response to FW Controller Failure (BOC18 to EOC18 MELLLA_TBPOOS-UDB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 54 0.0 100.0 200.0 300.0 0.0 3.0 6.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-100.0 0.0 100.0 200.0 0.0 3.0 6.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 3.0 6.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 3.0 6.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Figure 30 Plant Response to Load Reject w/o Bypass (BOC18 to EOC18 ICF_TCVSC-UDB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 55 0.0 100.0 200.0 300.0 0.0 3.0 6.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-100.0 0.0 100.0 200.0 0.0 3.0 6.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 3.0 6.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 3.0 6.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Figure 31 Plant Response to Load Reject w/o Bypass (BOC18 to EOC18 MELLLA_TCVSC-UDB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 56 0.0 100.0 200.0 300.0 0.0 2.5 5.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-100.0 0.0 100.0 200.0 0.0 2.5 5.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 2.5 5.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 2.5 5.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Figure 32 Plant Response to Load Reject w/o Bypass (BOC18 to EOC18 ICF_PLUOOS-UDB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 57 0.0 100.0 200.0 300.0 0.0 2.5 5.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-100.0 0.0 100.0 200.0 0.0 2.5 5.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 2.5 5.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 2.5 5.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Figure 33 Plant Response to Load Reject w/o Bypass (BOC18 to EOC18 MELLLA_PLUOOS-UDB)
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% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-100.0 0.0 100.0 200.0 0.0 4.0 8.0 Time (sec)
% Rated Level(inch-REF-SEP-SKRT)
Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 4.0 8.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 0.0 4.0 8.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Figure 34 Plant Response to MSIV Closure (Flux Scram, ICF-HBB)
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 59 Figure 35 Plant Response to MSIV Closure (Flux Scram, MEL-HBB)
-25.0 25.0 75.0 125.0 175.0 225.0 275.0 325.0 375.0 0.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 Time (sec)
% Rated Vessel Press Rise (psi)
Safety Valve Flow Relief Valve Flow Bypass Valve Flow
-50.0
-25.0 0.0 25.0 50.0 75.0 100.0 125.0 150.0 175.0 200.0 0.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 Time (sec)
% Rated Level - Inch above Sep Skirt Vessel Steam Flow Turbine Steam Flow Feedwater Flow
-2.0
-1.0 0.0 1.0 0.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 Time (sec)
Reactivity Components ($)
Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 200.0 250.0 0.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 Time (sec)
% Rated Neutron Flux Ave Surface Heat Flux Core Inlet Flow Core Inlet Subcooling
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 60 2 6 10 14 18 22 26 30 34 38 42 46 50 54 58 59 55 51 0
0 0
47 43 0
0 0
30 0
39 0
35 0
0 0
0 0
0 31 27 0
0 0
0 0
0 0
23 19 0
0 0
0 0
15 11 0
0 0
7 3
Notes: 1. Number indicates number of notches withdrawn out of 48. Blank is a fully withdrawn rod.
- 2. Error rod is (34,39).
Figure 36 Rod Withdrawal Error Limiting Rod Pattern
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 61 Appendix A Analysis Conditions To reflect actual plant parameters accurately, the values shown in Table A-1 were used this cycle. 10 Table A-1 Analysis Value ICF Analysis Value MELLLA Analysis Value ICF & FFWTR Thermal power, MWt 2957.0 2957.0 2957.0 Core flow, Mlb/hr 105.8 93.4 105.8 Reactor pressure, psia 1036.6 1034.1 1008.4 Inlet enthalpy, BTU/lb 523.6 520.3 511.1 Non-fuel power fraction 0.036 0.036 0.036 Steam flow, Mlb/hr 11.73 11.71 10.26 Dome pressure, psig 1005.0 1005.0 978.2 Turbine pressure, psig 924.1 924.4 915.2 No. of Dual Mode S/R Valves 0
0 0
No. of Relief Valves 4
4 4
No. of Single Spring Safety Valves 8
8 8
Relief mode lowest setpoint, psig 1112.0 1112.0 1112.0 Safety mode lowest setpoint, psig 1147.0 1147.0 1147.0 Feedwater temperature, F 355.6 355.6 235.6 10 These conditions are also applicable for all the equipment out of service options presented in Sections 6, 9 and 11.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 62 Appendix B Decrease in Core Coolant Temperature Events The Dresden 3 Cycle 18 Loss of Feedwater Heating (LFWH) analysis was evaluated per the applicable GE internal technical design procedure at 100% rated power and 145oF feedwater temperature reduction using the BWR simulator code. The use of this code is permitted by GESTAR II. The transient plots, neutron flux and heat flux values normally reported are not an output of the BWR simulator code; therefore, those items are not included in this document. The OLMCPR results are included in Section 11 for non-pressurization events.
The conclusion from the analysis is that the resulting operating limit minimum critical power ratio (OLMCPR) is 1.29 and is reported in Section 11.
In addition, the Inadvertent HPCI start-up event was shown to be bounded by the LFWH event in accordance with Determination of Limiting Cold Water Event, NEDC-32538P-A.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 63 Appendix C Operating Flexibility Options The options depicted in Sections 7 and 8 are defined in the EOOS report (Reference C-1). The 15 psi pressure band (from normal FWT) is accounted for in Reference C-1 (the EOOS analysis report).
The basis for application of 120°F Final Feedwater Temperature Reduction is contained in Reference C-2.
The results of the validation analysis required by Reference C-1 Appendix A are as follows:
Results For MCPR(P) Verification Power/Flow Transient Option B OLMCPR (GE14C/ATRM9)
Required K(p)
(GE14C/ATRM9)
K(p)
Limit (Ref. C-1) 38.5/108 FWCF 1.66/1.71 1.19/1.22 1.32 60/108 TCV slow closure 4S0F 2.00/1.92 1.43/1.37 1.45 60/42 TCV slow closure 4S0F 2.03/1.73 1.45/1.23 1.45 Results For LHGRFAC(P) Verification Power/Flow Transient TOP (GE14C/
ATRM9)
MOP (GE14C/
ATRM9)
Required LHGRFAC(P)
(GE14C/
ATRM9)
LHGRFAC(P)
Limit (Ref. C-1) 38.5/108 FWCF 45.78 / 45.78 47.44 / 49.72 0.801 / 0.764 0.68 60/108 TCV 4S0F 50.25 / 54.31 54.82 / 63.59 0.693 / 0.598*
0.67 60/42 TCV 4S0F 25.18 / 29.77 30.50 / 35.97 1.000 / 1.000 0.67
- Since these values are bounded by the values in Table 2-15 of Reference C-1, (0.610/0.517), the LHGRFAC limit of 0.67 applies.
Results For LHGRFAC(F) Verification Flow Transient TOP (GE14C/
ATRM9)
MOP (GE14C/
ATRM9)
Required LHGRFAC(F)
(GE14C/
ATRM9)
LHGRFAC(F)
Limit (Ref. C-1) 40%
Slow Flow Runout 86.62 / 86.62 87.87 / 87.87 0.6377 / 0.6377 0.64
- The ATRM9 TOP/MOP results are reported the same as that of GE14C since they have been demonstrated to be bounded by GE14C.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 64 Reference C-3 documents the MSIVOOS evaluation for both units of Dresden and Quad Cities. This evaluation considered AOOs, Overpressure, ATWS, LOCA, Containment, Main Steam Line Piping and the operational aspects of operating with 1 MSIV closed (1 MSIV OOS). These evaluations document the acceptability of MSIV OOS operation at or below 75% power.
References:
C-1. Dresden 2 and 3 Quad Cities 1 and 2 Equipment Out-of-Service and Legacy Fuel Transient Analysis, GE-NE-J11-03912-00-01-R1, November 2001.
C-2. Dresden and Quad Cities Evaluation of Extended Final Feedwater Temperature Reduction, GE-NE-A13-00487-00-01P, Revision 1, August 2002.
C-3. Evaluation of Limiting Events with One Main Steam Line Out-of-Service for Dresden, Units 2 and 3 and Quad Cities Units 1 and 2, GE-Nuclear Energy, Letter NSA 02-350, July 2002.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 65 Appendix D Extended Power Uprate (EPU)
To provide Dresden Unit 3 with operating improvements, analyses were performed to increase the rated power from 2527 MWth to 2957 MWth.
Operation with power uprated to 2957 MWth was justified for Dresden Unit 3 in Reference D-1.
Reference:
D-1. Safety Analysis Report for Dresden 2 & 3 Extended Power Uprate, NEDC-32962P, December 2000.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 66 Appendix E Decay Ratio Calculations This appendix summarizes the results of the ODYSY decay ratio calculations for seven power/flow points for Dresden 3 Cycle 18. The purpose of these calculations is to assess the effectiveness of the stability Interim Corrective Action (ICA) regions in preventing reactor instability, and to provide a cycle-to-cycle comparison of relative changes in stability performance. The seven analyzed power/flow state points are as follows:
- 1. Natural Circulation Line (NCL) at the 67.9% LPU load line,
- 2. NCL at the 84.9% LPU load line,
- 3. Two pump minimum pump speed line at the 67.9% Licensed Power Uprate (LPU) load
- line,
- 4. 50% core flow on the MELLLA upper boundary,
- 5. 40% core flow on the MELLLA upper boundary,
- 6. 45% core flow on the 91.7% LPU load line, and
- 7. 45% core flow on the MELLLA upper boundary.
The NRC-approved PANAC11/ODYSY05 (P11/O5) methodology (Reference E.1) is used in this evaluation. The decay ratios are calculated for Dresden 3 C18 based on the Reference Loading Pattern and customer-supplied information, including the power/flow map. Haling depletions are used in all cases except for the three Point 7 rodded exposure cases. Rated power/minimum flow Haling depletion is used for the High Flow Control Line (HFCL) cases while rated power/rated flow Haling depletion is used for the NCL cases. The decay ratios must meet the ODYSY stability criteria. The ODYSY criterion is essentially a 0.8 core decay ratio (DR).
Table E.1 below summarizes the case results for the NCL and HFCL cases. Table E.2 lists the exposure-dependent results for the Haling exposure points used in the scoping out the worst core decay ratios.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 67 Table E.1. P11/O5 Case Results for C18 (EPU)
Case
% Rated Power
% Rated Core Flow Core DR Channel DR (GE14C)
Channel DR (ATRM9)
NCL 35.8 (point 2) 23 1.149 0.442 0.389 28.1 (point 1) 22 0.839 0.323 0.284 23.9 (point 8) 20.6 0.538 0.288 0.264 HFCL 58.0 (point 5) 40.0 0.707 0.309 0.272 66.154 (point 4) 50.0 0.538 0.268 0.047 55.2 (point 6) 45.0 0.525 0.279 0.008 35.9 (point 3) 36.0 0.383 0.015 62.106 (point 7) 45.0 0.598 0.284 0.268 62.106 (point 7, BOC) 45.0 0.232 0.289 0.322 62.106 (point 7, MOC) 45.0 0.258 0.304 0.305 62.106 (point 7, EOC) 45.0 0.688 0.295 0.279 Table E.2. Exposure-Dependent Results for Haling Cases NCL (3623)
HFL (5840)
Exposure (MWD/ST)
Calculated Core DR Channel DR Calculated Core DR Channel DR 15540 1.149 0.442 0.707 0.309 14540 1.125 0.462 0.681 0.313 13540 1.098 0.492 0.671 0.315 12540 1.058 0.502 0.650 0.319 For the HFCL cases, the EOC case is the most limiting. For the NCL cases, the EOC case is the most limiting. Hence, these exposure state points will be used as the bases for finding the decay ratios. Figure E.1 plots the decay ratio results against the ODYSY stability criteria. It is concluded that the existing Interim Corrective Action (ICA) stability regions are sufficient for D3C18 operation because the core decay ratios are all less than 0.8, except on the natural circulation line. An additional point (point 8) shows that at the ICA lowest boundary, the core decay ratio is less than 0.80. It is recommended that for a two-pump trip to natural circulation at load line higher than 59.5% LPU, the operators should exit the Controlled Entry region immediately.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 68
Reference:
E.1. NEDC-32992P-A, Licensing Topical Report, ODYSY Application for Stability Licensing Calculations, July 2001.
0 0.2 0.4 0.6 0.8 1
1.2 0
0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1
Channel Decay Ratio Core Decay Ratio ODYSY Stability Criteria Point 2 Point 1 Point 5 Point 4 Point 6 Point 3 Point 7, BOC Point 7 Point 7, MOC Point 7, EOC Point 8 Figure E.1. Calculated Decay Ratios versus the ODYSY Stability Criteria
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 69 Appendix F Legacy Fuel Licensing Applicability Thermal hydraulic and GEXL evaluations were performed to demonstrate the acceptability of the GE14 fuel compatibility with the Exelon legacy fuel (ANF ATRIUM-9B). The results of these evaluations support the conclusion that GE14 fuel and the legacy fuel can be safely and acceptably operated together at Dresden Unit 3 Cycle 18. These evaluations are described in References F-1 and F-2.
References:
F-1. GE14 Thermal Hydraulic Compatibility with Commonwealth Edison Legacy Fuel, Revision 1, September 2000 (DRF # J11-03723-06).
F-2. GEXL96 Correlation for ATRIUM-9B Fuel, NEDC-32981P, Revision 0, September 2000.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 70 Appendix G COLR INPUTS MCPR Option A Based Operating Limits Dresden-3 Cycle 18 Cycle Exposure EOOS Combination Fuel Type
<15,000 MWd/MT 15,000 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
- TBPOOS cases include a +0.03 penalty for operation below analysis basis dome pressure per page 24 of Reference G-1.
+These cases also include a +0.02 penalty for TBPOOS during coastdown per page 22 of Reference G-1.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 71 MCPR Option B Based Operating Limits Dresden-3 Cycle 18 Cycle Exposure EOOS Combination Fuel Type
<15,000 MWd/MT 15,000 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 1.42 1.48 TCV Stuck Closed ATRIUM-9B 1.41 1.44 GE14 1.43 1.49 TCV Stuck Closed SLO ATRIUM-9B 1.42 1.45
- TBPOOS cases include +0.03 penalty for operation below analysis basis dome pressure per page 24 of Reference G-1.
+These cases also include a +0.02 penalty for TBPOOS during coastdown per page 22 of Reference G-1.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 72 MCPR(P) / K(P) for GE and SPC Fuel Core Thermal Power (% of rated) 0 25 38.5 38.5 45 60 70 70 100 EOOS Combination Core Flow
(% of rated)
Operating Limit MCPR Operating Limit MCPR Multiplier, KP 60 3.16 2.58 2.27 Base Case (Option A or Option B)1
> 60 3.77 2.99 2.56 1.32 1.28 1.15 N/A N/A 1.00 60 3.17 2.59 2.28 Base Case SLO (Option A or Option B)2
> 60 3.78 3.00 2.57 1.32 1.28 1.15 N/A N/A 1.00 60 5.55 3.77 2.82 TBPOOS (Option A or Option B)3
> 60 6.79 4.62 3.45 1.37 1.28 1.15 N/A N/A 1.00 60 5.56 3.78 2.83 TBPOOS SLO (Option A or Option B)4
> 60 6.80 4.63 3.46 1.37 1.28 1.15 N/A N/A 1.00 60 5.55 3.77 2.82 TCV Slow Closure (Option A or Option B)5
> 60 6.79 4.62 3.45 1.64 N/A 1.45 1.26 1.11 1.00 60 5.56 3.78 2.83 TCV Slow Closure SLO (Option A or Option B)6
> 60 6.80 4.63 3.46 1.64 N/A 1.45 1.26 1.11 1.00 60 5.55 3.77 2.82 PLUOOS (Option A or Option B)7
> 60 6.79 4.62 3.45 1.64 N/A 1.45 1.26 1.11 1.00 60 5.56 3.78 2.83 PLUOOS SLO (Option A or Option B)8
> 60 6.80 4.63 3.46 1.64 N/A 1.45 1.26 1.11 1.00 60 3.16 2.58 2.27 TCV Stuck Closed (Option A or Option B)9
> 60 3.77 2.99 2.56 1.32 1.28 1.15 N/A N/A 1.00 60 3.17 2.59 2.28 TCV Stuck Closed SLO (Option A or Option B)10
> 60 3.78 3.00 2.57 1.32 1.28 1.15 N/A N/A 1.00 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 Reference 1, Section 2.1.
For single-loop operation, the MCPR operating limit is 0.01 greater than the two-loop value.
N/A indicates data intentionally omitted at the request of the customer since it is redundant and can be obtained by the core monitoring system.
1 MCPR(P)/ K(P) based on Reference G-1, Figure 2-1.
2 MCPR(P) Based on Reference G-1, Figure 2-1 with SLO scaling defined in Section 2.3.9 of Reference 1. SLO K(P) is the same as TLO K(P).
3 MCPR(P) / K(P) based on Reference G-1, Figure 2-3.
4 MCPR(P) Based on Reference G-1, Figure 2-3 with SLO scaling defined in Section 2.3.9 of Reference 1. SLO K(P) is the same as TLO K(P).
5 MCPR(P) / K(P) based on Reference G-1, Figure 2-5.
6 MCPR(P) Based on Reference G-1, Figure 2-5 with SLO scaling defined in Section 2.3.9 of Reference 1. SLO K(P) is the same as TLO K(P).
7 MCPR(P) / K(P) based on Reference G-1, Figure 2-5.
8 MCPR(P) Based on Reference G-1, Figure 2-5 with SLO scaling defined in Section 2.3.9 of Reference 1. SLO K(P) is the same as TLO K(P).
9 MCPR(P) / K(P) based on Reference G-1, Figure 2-1.
10 MCPR(P) Based on Reference G-1, Figure 2-1 with SLO scaling defined in Section 2.3.9 of Reference 1. SLO K(P) is the same as TLO K(P).
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 73 MCPR(F) limits for GE and SPC Fuel are to be determined by Exelon.
LHGR limits are to be determined by Exelon.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 74 LHGRFAC(P) for GE and SPC Fuel Core Thermal Power (% of rated) 0 25 38.5 38.5 70 70 80 100 EOOS Combination Core Flow
(% of rated)
LHGRFAC(P) multiplier 60 Base Case1
> 60 0.50 0.56 0.59 0.68 N/A N/A 0.86 1.00 60 Base Case SLO2
> 60 0.50 0.56 0.59 0.68 N/A N/A 0.86 1.00 60 0.22 0.48 TBP OOS3
> 60 0.33 0.39 0.42 0.54 N/A N/A N/A 1.00 60 0.22 0.48 TBP OOS SLO4
> 60 0.33 0.39 0.42 0.54 N/A N/A N/A 1.00 60 0.22 0.48 TCV Slow Closure5
> 60 0.33 0.39 0.42 0.54 0.73 0.78 N/A 1.00 60 0.22 0.48 TCV Slow Closure SLO6
> 60 0.33 0.39 0.42 0.54 0.73 0.78 N/A 1.00 60 0.22 0.48 PLUOOS7
> 60 0.33 0.39 0.42 0.54 0.73 0.78 N/A 1.00 60 0.22 0.48 PLUOOS SLO8
> 60 0.33 0.39 0.42 0.54 0.73 0.78 N/A 1.00 60 TCV Stuck Closed1
> 60 0.50 0.56 0.59 0.68 N/A N/A 0.86 1.00 60 TCV Stuck Closed SLO2
> 60 0.50 0.56 0.59 0.68 N/A N/A 0.86 1.00 Values are interpolated between relevant power levels.
For thermal limit monitoring at greater than 100% core thermal power, the 100% core thermal power LHGRFAC(P) should be applied.
Allowable EOOS conditions are listed in Reference G.1, Section 2.1.
N/A indicates data intentionally omitted at the request of Exelon since it is redundant and can be obtained by the core monitoring system.
1 LHGRFAC(P) based on Reference G-1, Figure 2-2.
2 LHGRFAC(P) based on Reference G-1, Figure 2-2 (no change from Two Loop Operation).
3 LHGRFAC(P) based on Reference G-1, Figure 2-4.
4 LHGRFAC(P) based on Reference G-1, Figure 2-4 (no change from Two Loop Operation).
5 LHGRFAC(P) based on Reference G-1, Figure 2-6.
6 LHGRFAC(P) based on Reference G-1, Figure 2-6 (no change from Two Loop Operation).
7 LHGRFAC(P) based on Reference G-1, Figure 2-6.
8 LHGRFAC(P) based on Reference G-1, Figure 2-6 (no change from Two Loop Operation).
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 75 LHGRFAC(F) multipliers1 Flow (% rated)
LHGRFAC(F) 30 0.55 40 0.64 50 0.77 80 1.00 100 1.00 110 1.00 LHGRFAC(F) multipliers for Turbine Control Valve Stuck Closed2 Flow (% rated)
LHGRFAC(F) 30 0.41 40 0.50 50 0.63 80 0.86 98.3 1.00 100 1.00 110 1.00 1 Reference G-1, Figure 3-3.
2 Reference G-1, Table 2-17.
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 76 Allowed Modes of Operation The Allowed Modes of Operation with combinations of Equipment Out-of-Service are as described below:
OPERATING REGION---------
Equipment Out of Service Options Standard MELLLA Coastdown ICF Base Case, Option A Yes Yes Yes No Base Case SLO, Option A Yes Yes Yes No TBPOOS, Option A Yes Yes Yes No TBPOOS SLO, Option A Yes Yes Yes No TCV Slow Closure, Option A Yes Yes Yes No TCV Slow Closure SLO, Option A Yes Yes Yes No PLUOOS, Option A Yes Yes Yes No PLUOOS SLO, Option A Yes Yes Yes No TCV Stuck Closed, Option A Yes Yes Yes No TCV Stuck Closed SLO, Option A Yes Yes Yes No Base Case, Option B Yes Yes Yes No Base Case SLO, Option B Yes Yes Yes No TBPOOS, Option B Yes Yes Yes No TBPOOS SLO, Option B Yes Yes Yes No TCV Slow Closure, Option B Yes Yes Yes No TCV Slow Closure SLO, Option B Yes Yes Yes No PLUOOS, Option B Yes Yes Yes No PLUOOS SLO, Option B Yes Yes Yes No TCV Stuck Closed, Option B Yes Yes Yes No TCV Stuck Closed SLO, Option B Yes Yes Yes No
DRESDEN 3 0000-0006-9848-SRLR Reload 17 Rev. 2 Page 77
Reference:
G-1. Dresden 2 and 3 Quad Cities 1 and 2 Equipment Out-of-Service and Legacy Fuel Transient Analysis, GE-NE-J11-03912-00-01-R1, Revision 1, November 2001.