ML20134H179
| ML20134H179 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 06/30/1996 |
| From: | Kingston R, Reda R GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20134H145 | List: |
| References | |
| 24A5188, 24A5188-R02, 24A5188-R2, NUDOCS 9611130560 | |
| Download: ML20134H179 (86) | |
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GE Nuclear Energy l
24A5188 Revision 2 ClassI June 1996 24A5188, Rev. 2 Supplemental Reload Licensing Report for River Bend Station l
Reload 6 Cycle 7 l
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Approved Approved R. E.
R. J. Reda, Manager R. E. Kingston Fuel and Facility Licensing Fuel Project Manager l
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i 9611130560 961105 l
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RIVER BEND 24A5188 Reload 6 __ Rev.2 Important Notice Regarding Contents of This Report Please Read Carefully This report was prepared by General Electric Company (GE) solely for Entergy Opera-tionc, Inc. (EOI) for EOl's use with the U. S. Nuclear Regulatory Commission (USNRC) for amending EOl's operating license of the River Bend Station. The information con-tained in this report is believed by GE to be an accurate and true representation of the facts known, obtained or provided to GE at the time this report was prepared.
The only undertakings of GE respecting information in this document are contained in the contract between EOl and GE for fuel bundle fabrication and related services for Riv-er Bend Station and nothing contained in this document shall be construed as changing said contract. The use of this information, except as defined by said contracts, by anyone other than EOl for any purpose other than that for which it is' intended, is not authorized; and with respect to any unauthorized use, neither GE nor any of the contributors to this -
document makes any representation or warranty (expressed or implied), as to the com-pleteness, accuracy or usefulness of the information contained in this document or that such use of such information may not infdoge privately owned rights; nor do they assume i any responsibility for liability or damage of any kind which may result from such use of !
such information.
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RIVER BEND 24A5188 Reload 6 Rev.2 1
Acknowledgement l I
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l The engineering and reload licensing analyses, which form the technical basis of this Supplemental Reload Licensing Repon, were performed by D. R Stier. 'Ihis Revision to the Supplernental Reload Licensing Repon was prepared by W. E. Russell. This document has been verified by A. E Alzaben.
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RIVER BEND 24A5188 Reload 6 Rev.2
- The basis for this report is General Electric Standard Applicationfor Reactor Fuel. NEDE-24011-P-A-10, February 1991; and the U.S. Supplement, NEDE-24011-P-A-10-US, March 1991.
- 1. Plant-unique items Appendix A: Analysis Conditions l
' Appendix B: Alternate Analysis for Feedwater Temperature Reduction Appendix C: Basis for Analysis of Loss-of-Feedwater Heate: Event Appendix D: Basis for Analysis of Core-Wide and Overpressurization Transients -
Appendix E: Basis for Analysis of Loss-of-Coolant Accident Appendix F: Basis for Analysis of Standby Liquid Control System Shutdown Capability Appendix G: Plant Operation Above the Rated Load Line Up to Rated Power Appendix H: Off Rated MCPRp and MCPRf Curves
- 2. Reload Fuel Bundles Cycle Fuel Type Loaded Number Irradiated:
GE8B-P8SQB 333-10GZ-120M-4WR-150-T (GE8x8EB) 4 8 G E8 B-P8SQB 334-10GZ-120M-4WR-150-T (G E8 x 8EB) 5 1%
GE8B-P8SQB 334-10GZ2-120M-4WR-150-T (GE8x8EB) 6 132 GE8B-P8SQB334-1 I GZ-120M-4WR-150-T (GE8x8EB) 6 56 Ncm G E l l-P9S UB 353-10GZ-120T-146-T (GE l l) 7 128.
G E l 1 -P95UB 354-13GZ-120T-146-T (gel 1 ) 7 64 G E l l-P9S UB 354-14GZ-120T-146-T (GE l l ) 7 40
' Total 624 l
- 3. Reference Core Loading Pattern l ' Nominal previous cycle core average exposure at end of cycle: 26043 mwd /MT l ( 23626 mwd /ST)
Minimun previous cycle core average exposure at end of cycle 25259 mwd /MT from cold shutdown considerations: ( 22915 mwd /ST)
Assumed reload cycle core average exposure at beginning of 13188 mwd /MT l
cycle: ( 11964 mwd /ST)
- Assumed reload cycle core average exposure at end of cycle
- 26250 mwd /MT
( 23814 mwd /ST)
Reference core loading pattern: Figure 1 r
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l RIVER BEND 24A5188 Reload 6 Rev.2
- 4. Calculated Core Effective Multiplication and Control System Worth - No Voids,20 C Beginning of Cycle, kenecove l Uncontrolled 1.118 !
I Fully controlled 0.953 Strongest control rod out 0.981 R. Maximum increase in cold core reactivity with ;
exposure into cycle, Ak 0.003 )
l i 5. Standby Liquid Control System Shutdown Capability 6 Appendix F) i Boron Shutdown Margin (Ak)
(ppm) (20'C, Xenon Free) 660 0.021
- 6. Reload Unique GETAB Anticipated Operational Occurrences (AOO) Analysis l Initial Condition Parameters Exposure: BOC7 to EOC7100%P/100%F Peaking Factors l Fuel Bundle Bundle Initial Design Local - Radial Axial R-Factor Power Flow MCPR (MWt) (1000 lb/hr) '
l gel 1 1.45 1.39 1.36 1.035 6.307 112.4 1.27 GE8x8EB 1.20 1.51 1.40 1.051 6.821 109.7 1.17 l Exposure: BOC7 to EEOC7 WITH ICF 100%P/107%F Peaking Factors l
Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (Mwt) (1000 lb/hr) gel 1 1.45 1.40 1.38 1.035 6.333 120.9 1.27 GE8x8EB 1.20 1.51 1.40 1.051 6.826 118.3 1.18
! Exposure: BOC7 to EEEOC7 WITH ICF AND FFWTR 100%P/107%F 320 Deg. F Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial , R-Factor Power Flow MCPR (MWt) (1000 lb/hr)
Gell 1.45 1.46 1.37 1.035 6.612 119.6 1.25 GE8x8EB 1.20 1.55 1.40 1.051 7.016 116.9 1.18 l Page 5 1
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RIVER BENV 24A5188 Reload 6 Rev.2 1
1 Exposure: BOC7 to EOC7 FWTR 100%P/100%F 320 Deg.F Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow {
MCPR i
( M W t) (10001%r)
GEIi 1.45 1.46 1.34 1.035 6.581 111.1 1.25 f GE8x8EB 1.20 1.55 1.40 1.051 6.990 108.4 1.17 l Exposure: BOC7 to EOC7 - HALING 100%P/100%F Peaking Factors l
Fuel Bundle Bundle Initial - I Design Local Radial Axial R-Factor Power Flow MCPR I (MWt) (10001%r) gel 1 1.45 1.50 1.16 1.035 6.768 108.0 1.25 GE8x8EB 1.20 1.56 1.40 1.051 7.079 108.0 1.12 j Exposure: BOC7 to EEOC7 WITH ICF- HALING 100%P/107%F Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR I (MWt) (1000 IMr) gel 1 1.45 1.50 1.18 1.035 6.778 116.5 1.26 GE8x8EB 1.20 1.57 1.40 1.051 7.123 116.3 1.13 Exposure: BOC7 to EEEOC7 WITH ICF AND FFWTR - HALING 100%P/107%F 320 Deg.F Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (1000 IMr)
Gell 1.45 1.55 1.23 1.035 6.993 115.4 1.25 GE8x8EB 1.20 1.61 1.40 1.051 7.273 115.1 1.14 Exposure: BOC7 to EOC7 WITH FFWTR - HALING-100%P/100%F 320 Deg. F l Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (1000 IMr) gel 1 1.45 1.54 1.21 1.035 6.947 107.1 1.24 GE8x8EB 1.20 1.60 1.40 1.051 7.245 106 7 1.12 Page 6
RIVER BEND 24A5188 Reload 6 Rev.2 Exposure: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100% P/100%F l Pealdng Factors
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Fuel Bundle Bundle initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (1000 IMr) i Gell 1.45 1.56 1.41 1.035 7.056 105.0 1.24 l GE8x8EB 1.20 1.60 1.40 1.051 7.261 106.9 1.09 l Exposure: BOC7 to EOC7-3693 mwd /MT (3350 MWa/ST) 100% P/107% F
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Peaking Factors l
Fuel Bundle Bundle Initial Design l
Local Radial Axial R-Factor Power Flow MCPR i (MWt) (1000 IMr)
Gell 1.45 1.57 1.39 1.035 7.093 113.0 1.26 GE8x8EB 1.20 1.61 1.40 1.051 7.301 115.1 1.10 Exposure: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100%P/107% F 320 Deg. F -
Peaking Factors Fuel Bundle Bundle Initial l Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (1000 IMr) gel 1 1.45 1.66 1,42 1.035 7.489 110.0 1.22 GE8x8EB 1.20 1.66 1.40 1.051 7.513 111.1 1.09 Exposure: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100%P/100%F 320 Deg. F Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR i
(MWt) (1000 IMr) gel 1 1.45 1.65 1.44 1.035 7.449 102.1 1.20 GE8x8EB 1.20 1.66 1.40 1.051 7.500 102.9 1.08 l
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l RIVER BEND 24A5188 Reload 6 Rev.2
! 7. Selected Margin Improvement Options Recirculation pump trip: Yes Rod withdrawal limiter: Yes Thermal power monitor: Yes Improved scram time: No Measured scram time: No Exposure dependent limits: Yes '
l Exposure points analyzed: 2
- 8. Operating Flexibility Options Single-loop operation: Yes Load line limit: No (See Appendix G)
Extended load line limit: No i
Maximum extended load line limit: No Increased core flow throughout cycle: Yes l Flow point analyzed: 107.0 %
increased core flow at EOC: Yes l
l Feedwater temperature reduction throughout cycle: Yes Temperature reduction: 100.0 F Final feedwater temperature reduction: Yes ARTS Program: . No Maximum extended operating domain: No i Moisture separator reheater OOS: No Turbine bypass system OOS: No Safety / relief valves OOS: No (See Appendix D)
ADS OOS: No EOC RIT OOS: No Main steam isolation valves OOS: No Feedwater Heater OOS Yes l Page 8 i
RIVER BEND 24A5188 Reload 6 Rev. 2 1
- 9. Core-wide AOO Analysis Results Methods used: GEMINI; GEXL-PLUS Exposure ange: BOC7 to EOC7 1007eP/1007eF Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.
(7eNBR) (7eNBR)
FW Controller Failure 291 113 0.18 0.09 2 Load Reject w/o Bypass 386 114 0.20 0.10 3 l
Turbine Trip w/o Bypass 336 112 0.18 0.08 4 Press. Regulator Failure 144 104 0.09 0.04 5 I Exposure range: BOC7 to EEOC7 EEOC WITH ICF 1007eP/1077eF Uncorrected ACPR l Event Flux Q/A Gell GE8x8EB Fig.
(%NBR) (%NBR)
FW Controller Failure 329 115 0.18 0.10 6 Load Reject w/o Bypass 429 116 0.20 0.12 7 Turbine Trip w/o Bypasa 381 113 0.19 0.10 8 Press. Regulator Failure 144 105 0.09 0.04 9 Exposure range: BOC7 to EEEOC7 WITH ICF AND FFWTR 100%P/107%F 320 Deg. F.
Uncorrected ACPR 1
Event Flux Q/A Gell GE8x8EB Fig.
(%NBR) (57eNBR)
FW Controller Failure 311 118 0.18 0.11 10 Load Reject w/o Bypass 381 115 0.18 0.10 11 Turbine Trip w/o Bypass 335 112 0.16 0.08 12 Press. Regulator Failure 146 105 0.10 0.05 13 Exposure range: BOC7 to EOC7 - 100%P/100%F 320 Deg. F Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.
(%NBR) (%NBR)
FW Controller Failure 289 116 0.18 0.10 14 Load Reject w/o Bypass 361 114 0.18 0.09 15 Turbine Trip w/o Bypass 314 111 0.16 0.07 16 Press. Regulator Failure 144 105 0.10 0.04 17 Page 9
RIVER BEND 24A5188 l
Reload 6 Rev. 2 l
l Exposure range: BOC7 to EOC7 - HALING 100%P/100%F l
Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig. l
(%NBR) (%NBR) !
FW Controller Failure 198 107 0.16 0.04 18 Load Reject w/o Bypass 267 108 0.18 0.05 19 Turbine Trip w/o Bypass 231 105 0.16 0.03 20 l Press. Regulator Faih:re 142 103 0.07 0.03 21 1
Exposure range: BOC7 to EEOC7 WITH ICF - HALING 100%P/107%F l Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.
(%NBR) (%NBR)
FW Controller Failure 229 109 0.17 0.05 22 !
Load Reject w/o Bypass 313 110 0.19 0.07 23 Turbine Trip w/o Bypass 266 107 0.17 0.05 24 Press. Regulator Failure 143 104 0.07 0.03 25 Exposure range: BOC7 to EEEOC7 WITH ICF AND FFWTR - HALING 100%P/107%F !
Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.
(%NBR) (%NBR) -
FW Controller Failure 234 112 0.18 0.07 26 Load Reject w/o Bypass 310 110 0.18 0.07 27 Turbine Trip w/o Bypass 256 107 0.16 0.04 28 Press. Regulator Failure 144 104 0.09 0.03 29 !
Exposure range: BOC7 to EOC7 - HALING-100% P/100% F 320 Deg. F Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig. '
(%NBR) (%NBR)
FW Controller Failure 205 110 0.17 0.05 30 l Load Reject w/o Bypass 274 108 0.17 0.05 31 Turbine Trip w/o Bypass 228 105 0.15 0.03 32 l Press. Regulator Failure 144 104 0.08 0.03 33 i
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i RIVER BEND 24A5188 Reload 6 Rev.2 Exposure range: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100%P/100%F Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.
(%NBR) (%NBR)
FW Controller Failure 153 .04 0.14 0.03 34 Load Reject w/o Bypass 204 104 0.17 0.02 35 Turbine Trip w/o Bypass 184 102 0.15 0.00 36 Press. Regulator Failure 143 103 0.% 0.03 37 Exposure range: BOC7 to EOC7-3693 mwd /MT (3350 mwd /St) 100%P/107%F Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.
(%NBR) (%NBR)
FW Controller Failure 174 105 0.16 0.03 38 Load Reject w/o Bypass 234 106 0.19 0.03 39 Turbine Trip w/o Bypass 205 103 0.17 0.01 40 Press. Regulator Failure 143 103 0.% 0.03 41 Exposure range: HOC 7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100%P/107%F 320 Deg. F Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.
(%NBR) (%NBR)
FW Controller Failure 144 108 0.14 0.06 42 Load Reject w/o Bypass 196 104 0.15 0.01 43 Turbine Trip w/o Bypass 168 101 0.13 0.00 44 Press. Regulator Failure 144 104 0.% 0.03 45 Exposure range: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100% P/100% F 320 Deg. F Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.
(%NBR) (%NBR)
FW Controller Failure 129 108 0.13 0.05 46 Load Reject w/o Bypass 173 102 0.13 0.01 47 Turbine Trip w/o Bypass 150 100 0.11 0.00 48 Press. Regulator Failure 144 103 0.06 0.03 49 i
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I RIVER BEND 24A5188 i Reload 6 Rev.2 l
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- 10. Local Rod Withduwal Error (With Limiting Instrument Failure) AOO Summary The generic bounding BWR/6 rod withdrawal error analysis described in NEDE-240ll-P-A-US is not ap-plied. - A cycle-specific rod withdrawal analysis found the AMCPR to be 0.13 based upon a one foot with-drawal, and is not bounded by the generic RWE analysis reported in the referenced report.
- 11. Cycle MCPR Valuest In agreement with commitments to the NRC (letter from M, A. Smith to the Document Control Desk,10CFR Part 21 Reportable Condition Safety Limit MCPR Evaluation, May 24,19%) a cycle-specific Safety Limit ;
MCPR calculation was performed, and has been reported in both the Safety Limit MCPR and the Operating !
l Limit MCPR shown below. This cycle specific SLMCPR was determined using the analysis basis docu- !
mented in GESTAR with the following exceptions:
- 1. The actual core loading was analyzed.
- 2. The actual bundle parameters (e.g., local peaking) were used.
- 3. The full cycle exposure range was analyzed.
l Safety limit: 1.10 ~
Single loop operation safety limit: 1.12 l i I
l Non-pressurization events:
l Exposure range: BOC7 to EOC7 Gell GE8x8EB l Rod Withdrawal Error 1.23 1.23 l Loss of Feedwater Heating 1.21 1.21 ;
Fuel Loading Error- Rotated 1.20 1.25 Fuel Loading Error- Mislocated 1.25 1.25 Pressurization events:2 l Exposure range: BOC7 to EOC7100%P/100F Exposure point: EOC7 Gell GE8x8EB l FW Controller Failure 1.29 1.20 Load Reject w/o Bypass 1.31 1.21 Turbine Trip w/o Bypass 1.30 1.19 Press. Regulator Failure 1.20 1.15 1 Deleted.
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RIVER BEND 24A5188 i Reload 6 o Rev. 2 i
I Exposure range: BOC7 to EEOC7 WITH ICF 100%P/107%F l Exposure point: EEOC7 l
l Gell l GE8x8EB FW Controller Failure 1.30 1.21 ~i Load Reject w/o Bypass 1.32 1.22 Turbine Trip w/o Bypass 1.30 1.20 Press. Regulator Failure 1.20 1.15 Exposure range: BOC7 to EEEOC WITH ICF AND FFWTR 100%P/107%F 320 Deg. F 1
Exposure point: EEEOC7 Gell GE8x8EB FW Controller Failure 1.30 1.22 Load Reject w/o Bypass 1.29 1.21 Turbine Trip w/o Bypass 1.28 1.19 Press. Regulator Failure 1.22 1.16 Exposure range: BOC7 to EOC7100%P/100%F 320 Deg. F Exposure point: EOC7 Gell GE8x8EB FW Controller Failure 1.29 1.21 Load Reject w/o Bypass 1.29 1.20 Turbine Trip w/o Bypass 1.28 1.18 Press. Regulator Failure 1.21 1.15 Exposure range: BOC7 to EOC7 - HALING 100%P/100%F Exposure point: EOC7 Gell GE8x8EB FW Controller Failure 1.27 1.15 Load Reject w/o Bypass 1.30 1.16 Turbine Trip w/o Bypass 1.28 1.14 l Press. Regulator Failure 1.18 1.14 l
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RIVER BEND - 24A5188 Reload 6 P.ev. 2
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Exposure range: BOC7 to EEOC7 WITH ICF - HALING 100%P/107%F Exposure point: EOC7 Gell GE8x8EB PN Controller Failure 1.28 1.16 i Load Reject w/o Bypass 1.31 1.17 Turbine Trip w/o Bypass 1.29 1.15 )
Press. Regulator Failure 1.18 1.14
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Exposure range: BOC7 to EEEOC7 WITH ICF AND FFWTR - HALING 100%P/107%F Exposure point: EEEOC7 GE11 GE8x8EB l FW Controller Failure 1.29 1.18 Load Reject w/o Bypass 1.30 1.17 Turbine Trip w/o Bypass 1.28 1.15 Press. Regulator Failure 1.21 1.14 Exposun range: BOC7 to EOC7 FFWTR -HALING-100%P/100%F Exposure point: EOC7 Gell GE8x8EB FW Controller Failure 1.28 1.16 Load Reject w/o Bypass 1.28 1.16 Turbine Trip w/o Bypass 1.26 1.13 Press. Regulator Failure 1.20 1.14 Exposure range: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100%P/100% F l Exposure point: EOC7-3693 mwd /MT (3350 mwd /ST) l Gell GE8x8EB l FW Controller Failure 1.22 nc*
Load Reject w/o Bypass 1.26 nc 1
Turbine Trip w/o Bypass 1.24 nc '
4 Press. Regulator Failure 1.18 nc '
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- nc = not calculated Exposure range: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100%P/107%F '
i Exposure point: EOC7-3693 mwd /MT (3350 mwd /ST)
Gell GE8x8EB FW Controller Failure 1.24 nc i
Load Reject w/o Bypass 1.28 nc Turbine Trip w/o Bypass 1.26 nc Press. Regulator Failure 1.18 ne l
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! RIVER BEND 24A5188 i Reload 6 l
Rev.J l
Exposure range: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100% P/107%F 320 Deg.F.
Exposure point: EOC7-3693 mwd /MT (3350 mwd /ST)
Gell GE8x8EB FW Controller Failure 1.23 nc Load Reject w/o Bypass 1.24 nc Turbine Trip w/o Bypass 1.22 nc Press. Regulator Failu. 1.18 nc Exposure range: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100%P/100% F 320 Deg. F.
Exposure point: EOC7-3693 mwd /MT (3350 mwd /ST)
Gell GE8x8EB FW Controller Failure 1.21 nc Load Reject w/o Bypass 1.22 nc
'lbrbine Trip w/o Bypass 1.19 nc Press. Regulator Failure 1.18 nc
- 12. Overpressurization Analysis Summary Psi Pv Plant Event (psig) (,asig) Response MSIV Closure (Flux Scram) 1282 1311 Figure 50
- 13. Loading Error Results3 Variable water gap misoriented bundle analysis: Yes4 Misoriented Fuel Bundle ACPR G E 8 B -P8 S Q B 334- 10GZ2- 120M-4 W R- 150-T 0.15 gel 1-P9SUB353-10GZ-120T-146-T 0.10 Mislocated bundle analysis: Yes ACPR 0.15 l
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RIVER BEND 24A5188 Reload 6 Rev. 2
- 14. Control Rod Drop Analysis Results River Bend Station 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-US.
- 15. Stability Analysis Results GE SIL-380 recommendations have been included in the River Bend Station operating procedures and Tech-nical Specifications; therefore, the stability analysis is not required. NRC approval for deletion of a cycle-specific stability analysis is documented in Amendment 8 to NEDE-240ll-P-A-US. River Bend Station recognizes the issuance of NRC Bulletin No. 88-07, Supplement 1, Power Oscillations in Boiling Water -
Reactors (BWRs), and will comply with the recommendations contained therein.
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- 16. Loss-of-Coolant Accident Results LOCA method used: SAFE /REFLOOD The following table lists the least limiting and most limiting MAPLHGRs for the new fuel: The core-wide metal water reaction is <0.23%. The peak clad temperature is 5 2189'F at all exposures; the local oxidation (fraction) is 5 0.060. The MAPLHGR multiplier for single-loop operation is 0.84 for all fuels in the core.
- 3. see tener, J. F. Klapproth (GE) to R. C. Jones, Jr (NRC). Rotated Bundle Evaluation. July 20.1992. Tius letter identines that the rotauon of C-lamce fuel designs nuy result en a signancant CPR change.
4 includes a 0 02 penalty due to vanable water gap R-factor uncertainty.
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i RIVER BEND 24A5188 i Reload 6 Rev.2 l
- 16. Loss-of-Coolant Accident Results (cont)5 Bundle Type: gel 1-P9SUB354-14GZ-120T-146-T
{
Average Planar Exposure MAPLHGR(kW/ft)
(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 11.23 11.65 0.20 0.22 11.29 11.69 1.00 1.10 11.40 11.77 2.00 2.20 11.55 11.88 3.00 3.31 11.70 11.99 l
4.00 4.4 l 11.85 12.09 5.00 5.51 12.00 12.20 6.00 6.6I I2.16 12.25 7.00 7.72 12.30 12.31 8.00 8.82 12.36 12.36 9.00 9.92 12.48 12.48 10.00 11.02 12.59 12.59 12.50 13.78 12.65 12.71 15.00 16.53 12.40 12.55 l 17.50 19.29 12.10 12.14 20.00 22.05 11.73 11.79 l 25.00 27.56 10.96 11.19 30.00 33.07 10.24 10.51 35.00 38.58 9.55 9.78 l 40.00 44.09 8.92 9.26 45.00 49.60 8.32 8.62 50.00 55.12 7.74 7.95 55.00 60.63 7.11 7.22 58.77 64.78 6.65 6.71 59.14 65.19 -
6.67 59.19 65.25 -
6.66 i 5. For format explananon. see letter J. S. Charnley (GE) to M. W. Hodges (NRC). Recornmended MAPLHGR Technical Specificanons for Mul.
tiple laruce Fuel Designs, March 9.1987. Most Limitmg and least Linuung tefer to the lowest and highest lirnats respecovely. of any ennched lattice in the bundle.
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! RIVER BEND 24A5188 l Reload 6 Rev. 2 i
- 16. Loss-of-Coolant Accident Results (cont)6 Bundle Type: Gell-P9SUB354-13GZ-120T-146-T Average Planar Exposure MAPLHGR(kW/ft)
(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 11.39 11.65 0.20 0.22 11.44 11.69 1.00 1.10 11.53 11.77 2.00 2.20 11.65 11.88 3.00 3.31 11.77 11.99 4.00 4.41 11.89 12.09 5.00 5.51 12.02 12.20 6.00 6.61 12.15 12.25 7.00 7.72 12.27 12.31 8.00 8.82 12.36 12.36 9.00 9.92 12.48 12.48 10.00 11.02 12.59 12.59 12.50 13.78 12.64 12.71 15.00 16.53 12.40 12.55 17.50 19.29 12.09 12.14 20.00 22.05 11.74 11.79 25.00 27.56 10.97 11.19 30.00 33.07 10.25 10.51 35.00 38.58 9.57 9.78 40.00 44.09 8.93 9.04 45.00 49.60 8.23 8.35 50.00 55.12 7.54 7.76 55.00 60.63 6.85 7.09 58.40 64.37 6.35 6.61 58.52 64.51 -
6.59 59.19 65.25 -
6.50 59.21 65.26 -
6.49
- 6 For format eaplananon, see tener J. S. Charnley (GE) to M. W. Hodges (NRC). Recommended MAPLHGR Technical Specificanons for Mul-l tiple Laruce Fuel Designs. March 9.1987. Most Linuting and Least Linuung refer to the lowest and highest limits, respecovely, of any ennched latuce in the bundle.
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! RIVER BEND 24A5188 l
Reload 6 Rev.2 i
- 16. Loss-of-Coolant Accident Results (cont)7 Bundle Type: Gell-P9SUB353-10GZ-120T-146-T I
Average Planar Exposure MAPLHGR(kW/ft)
(GWd/ST) (GWd/MT) Most Limiting Least Limiting .
0.00 0.00 11.65 12.00 0.20 0.22 11.69 12.03 1.00 1.10 11.77 12.09 2.00 2.20 11.88 12.17 3.00 3.31 11.99 12.26 4.00 4.41 12.10 12.35 5.00 5.51 12.22 12.44 6.00 6.61 12.34 12.53 7.00 7.72 12.46 12.63 8.00 8.82 12.56 12.71 9.00 9.92 12.64 12.76 10.00 11.02 12.72 12.81 12.50 13.78 12.69 12.77 15.00 16.53 12.41 12.55 17.50 19.29 12.10 12.15 20.00 22.05 11.75 11.79 25.00 27.56 10.98 11.19 30.00 33.07 10.25 10.59 35.00 38.58 9.58 9.93 40.00 44.09 8.95 9.26 45.00 49.60 8.35 8.63 50.00 55.12 7.76 7.96 55.00 60.63 7.16 7.23 58.86 64.88 6.63 6.65 59.19 65.25 -
6.60 59.25 65.31 -
6.58 i 7. For fonnat eaplananon. see letter J. S. Charnley (GE) to M. W. Hodges (NRC). Recommended MAPLHGR Technical Specificanons for Mul-tiple Laruce Fuel Designs. March 9.1987. Most Linuting and Least Linuung refer to the lowest and highest linuts. respecovely, of any ennched lattice in the bundle.
Page 19
~ - - _ _ _ . _ _ _ _ _ _ . _ _ _ - _ _ . _ _ _ . _ _ . . _ . _ . _ . . _ . . . . . _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ . . _ _ _ . . _ _ .
RIVER BEND Reload 6 24A5188 l Rev. 2 I
' 5'
[D[D(D 0[D[D[D(D
- mMMMMMMMo mMMMMMMMMMo mMMMMMMMMMMMo
- -MMMMMMMMMMMMM lLo M M M M M M M M M M M M M o
!;:EM M M M M M M M M M M M ME
- E M M M M M M M M M M M M M E l
- E M M M M M M M M M M M M M E
- -"MMMMMMMMMMMMM" ,
ll-MMMMMMMMMMMMM !
ll "MMMMMMMMMMM" .
"MMMMMMMMM" 2
"MMMMMMM5 (D(D(DIDIDIDIDID '
1 3 5 7 9 il IIIIIIl l '
131317 lt Il 33 35 37 30 3133 as 37 3e di 43 43 47 as 5183 SS Fuel Type A =GE88-P8SQB 333-10GL 120M-4 WR-150-T (Cycle 4) E=GE88-P8SQB 334-10GL 120M-4WR-l %T (Cycle 5)
B= Gell-P95UB354-14GL12E-146-T (Cycle 7) F=GE8B-P8SQB334-10GZ2-120M-4WR-150-T (Cycle 6)
C= Gell-P95UB354-13GL120T-146-T (Cycle 7) G=GE88-P85QB 334-I I GL 120M-4WR-150-T (Cycle 6)
D= Gell-P95UB353-10GL12(TT-146-T (Cycle 7) l Figure 1 Reference Core Loading Pattern l
Page 20 l ._ _ , _. _ _ _ . __ _ _
i
RIVER BEND 24A5188 Reload 6 Rev.2 1
I Neutron Flux ; Vessel Press Rise (psi)
- - - - Ave Surface Heat Flux - - - - Safety Valve Flow !
150 0 - --- Core inlet Flow 125.0 - --- Relief Valve Flow
- - - Core inlet Subcoohng - - - Bypass Valve Flow
_J l j
-=""-------a '.
g 100.0 g 75.0 lii '\ "ii E \ C ;
'Y '\ Y
~
.\
50.0 -
'.\
25.0 -
l
. .I .
I l l
' 1 00 - 25.0 ' ' '
00 20.0 0.0 20.0 Time (sec) Time (sec) ;
l Level (inch-REF-SEP-SKRT) ! Void Reactivity
- - - - Vesset Steam Flow - - - - - Doppler Reactivity 150.0 - --- Turbine Steam Flow 1.0 - --- Scram Reactivity !
--- Feedwater Flow --- Total Reactivity G
m ,
l!! ,'
t 100 0 - --- - \ 8 o 0.0 --.-..........-.3
$ l' '
g t .
/
$ l,
'o I j g -
l' : 0 -
t '
lP .# l I. .n 50.0 -
.:' e', um -1.0 -
l " ' E l' . ' , , f. . . . .
l' i', -
l' ' ',
00 l P' i
-2.0 '
O.0 20.0 0.0 20.0 Time (sec) Time (sec) j Figure 2 Plant Response to FW Controller Failure (BOC7 to EOC7 STANDARD) I l
l l
f Page 21 l
1
RIVER BEND 24A5188 Reload 6 Rev.2 Neutron Flux Vessel Press Rise (psi)
- - - Ave Surface Heat Flux - - - - Safety Valve Flow 150 0 -
- Core inlet Flow 300 0 - --- Relief Valve Flow
--- Bypass Valve Flow g."
- 100 0 $ 200.0 3
.T ~.%. 3
' ~
E E
'.\-s' 3R ~ $ '
~~~
50.0 - ** 100.0
. 1 0.0 O.0 I /~~ ,- - --......,'~~
OO 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Level (inch-REF-SEP-SKRT) Void R vlty
- - - - - Vessel Steam Flow - - - - Doppler eacti 1 200 0 - --- Turtune Steam Flow 1.0 - -
Scram R
--- Feedwater Flow -
Total Rea vity g
7 E
- 8
- g 100 0 y, ,~~
0.0 .,
g ',
~
N' . ?, .
g o \i
' '.',. ~'........
l ', '+ O \
8 l. ,',' ' . ,,' ' , ,
g I
0.0 L '---* - -a - - - - ------
$>1.0 en - -
.' a>
.' .. a E 4
\.
-100.0 1 -
- 2.0 ) I -
00 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 3 Plant Response to Load Reject w/o Bypass (BOC7 to EOC7 STANDARD)
Page 22 j
RIVER BEND 24A5188 Reload 6 Rev. 2 L
Neutron Flux Vessel Press Rise (psi)
-
- Ave Surface Heat Flux - - - - Safety Valve Flow 150.0 -
Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow '
s,'
- g 100.0 k 200.0 -
E E
Ns. ,N E E
g -
., , g -
. ~
., ~ _ .
~.
50 0 - **
. , 100.0 -
t
~ ' / ,---- --..... ,,~~'
0.0 O.0 # - ' I O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Level (inch-REF-SEP-SKRT) Void R ctivity
- - - Vessel Steam Flow - - - - Doppler eactivi 200.0 - --- Turtune Steam Flow 1.0 -
- Scram R
--- Feedwater Flow Total Reactivity g
JG c ,
v 100 0 '"- 0.0
~
o .-
Tl, g
[ .
.#.s E o
N\ t *..*
s
's.**.
Y ,
l ', , l ', l .
\
\
\'
O0 Er-s. - *. ,,- - - - - - - - - - -
-fru -1.0 -
(
, . o E '
h.A
\
-100.0 ' I '
- 2.0 \ 'I O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 4 Plant Response to 'Ibrbine Trip w/o Bypass (BOC7 to EOC7 STANDARD)
Page 23
RIVER BEND 24A5188 Reload 6 Rev.2 Neutron Flux Vessel Press Rise (psi)
- - - - - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - --- Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow
. -N 100.0 7 , A 200.0 -
w ,
s a C * \ C
, s
$ '. ~s
/ ~
. 's 50 0 -
s*%, *
., 100.0 -
' I 0.0 O.0 0.0 5.0 10.0 0.0 5.0 10.0 Time (sec) Time (sec)
Level (incMEF-SEP-SKRT) Voedhvity
- - - - Vessel Steam Flow - - - - - Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 J
Scram Reactivity
- - - Feedwater Flow j n
Total Reactivity .**, .***,... ;
- t .
i a *
.- 1 g 100.0 - l 0.0 g ,-
p.%,N.
3 N. .#,f- \
I C \'. o \ ;
g . \', O *
,..... ~~- ...- ......
g
\~ *
.g
- e ;
, 2 00 - % -----------
TI m -1.0 -
\'
g e
C 1 I,
\
l
- 100.0 ' l '
- 2.0 ' ' '
O.0 5.0 10.0 0.0 5.0 10.0 Time (sec) Time (sec)
Figure 5 Plant Response to Press. Regulator Failure (BOC7 to EOC7 STANDARD)
Page 24
RIVER BEND 24A5188 Reload _{i Rev.2 Neutron Flux 4 Vessel Press Rise (psi)
- - - - - Ave Surface Heat Flux '
- - - - - Safety Valve Flow 1!O.0 -
--- Core inlet Flow 125.0 - --- Relief Valve Flow
- -- Core inlet Subcooling --- Bypass Valve Flow
~
r
(
- - - - - - - - - _ - - - ~)
- -~ -'
100.0 --
]' ,4 g 75.0 E '\ E E ', \ C g -
.\ g
'.\
N 50 0 -
25.0 -
l
~~~
i I I
0.0 - 25.0 ' I 00 20.0 0.0 20.0 Time (sec) Time (sec)
Level (inch-REF-SEP-SKRT) Void Reactivity
- - - Vessel Steam Flow - - - - - Doppler Reactivity 150.0 - --- Turbine Steam Flow 1.0 - --- Scram Reactivity I y
- - - Feedwater Flow - - - Total Reactivity .
' S _ ,
. . . . . m [ ,'
E <
-- \ g , /
g 1000 , g 0.0 --
! 8 Yl e
k(. ?
1 50.0 - I.ll\
' i' 1
- g-1.0 -
I. ', ", ,' l', . , . m
- l. . ' , ' ,
llll' -
llll l'.
0.0 l'. '
- 2.0 ' I l' O.0 20.0 0.0 20.0 Time (sec) Time (sec)
Figure 6 Plant Response to FW Controlle'r Failure (BOC7 to EEOC7 WITH ICF)
Page 25
RIVER BEND 24A5188 Reload 6 Rev.2 4
el 2
IJoutron Flux Vessel Press Rise (psi)
- - - Ave Surface Heat Flux - - - - - Safety Valve Flow 150 0 -
- Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow
\- .
_/
100.0 M ,s- -) %
a
, 200.0 -
m C
's m
'. C
~. ,~~~ ~ ,~ ~ ~ f 50.0 -
. 100.0 -
4 0.0 O.0 'I
/~ ,--- ' --.....,~~~~~'
O.0 3.0 6.0 0.0 30 6.0 1
Eme (Sec) mme (Sec) i l
Level (inct>-REF-SEP-SKRT) Void Re vity
- - - - - Vessel Steam Flow - - - - - Doppler eacti '
200.0 - --- Turtune Steam Flow 1.0 - -
Scram R
--- Feedwater Flow ,
Total Reactivity j g
- 2 8
C 7 100.0 p. , - - - - , g 0.0 ,
\: .-
2 g *,
o e
O ). ..
- t; l ,'
. - ........ y
. s
$m -1.0 00 L -.'*'----
.~,.,
E e
),
1
\
- 100.0 ' ' '
- 2.0
\
O.0 3.0 6.0 0.0 3.0 6.0 j mme (sec) mme (Sec)
Figure 7 Plant Response to Load Reject w/o Bypass (BOC7 to EEOC7 WITH ICF)
Page 26 l
J
RIVER BEND 24A5188 Reload 6 Rev. 2 Neutron Flux Vessel Press Rise (psi)
- - - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 -
- -- Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow a
_ \-. ',
E 100.0 . 200.0 -
w
"@7v,s s -
E w
E g -
, s's,' C g -
I ., ,
- 1 50.0 -
. 100.0 -
l l
' ' l '
O.0 O.0 '# '
O.0 30 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Level (irw&REF-SEP-SKRT) Void R ctivity Vessel Steam Flow - - - - - Doppler eacti 200.0 - --- Turbine Steam Flow 1,0 - -
Scram R vity Feedwater Fbw Total Reactivity t*,, .. -
, . l 2c
\
v 100 0 0.0 .
e a C i.
~ -- . .
" r.
E I. -
, o '
,- ,'.. O
- 1 . : .. .. . .-
....... 3
\g.
%l .- := t 0.0 h. . '
N. -1.0 E
k.
\
I '
-100.0 ' *
- 2.0 '
O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 8 Plant Response to 'Ibrbine Trip w/o Bypass (BOC7 to EEOC7 WITil ICF)
I I
Page 27
l -;
,I j\lIj11l};l l i l llliIlI!ll g Cag $ C%3 RR 1 1 2 eI F 0 0 0 0 0 0 0
5 1
0 1
5 lV o
g i
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- g .
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- - - 6 r -
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E 9
\~
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N CAN t : - euee y ov e _
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r m -
ea- f t
s Fe ux cl n
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e 5 0
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s e - -
l o- e
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g - . .
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a t 0 1
. 1 .
o r 0 0
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a xg1f 0Oe{ecs w@
3 1
$ CE32 _
i - - 3 l 0 0 0 2
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0 0 1
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e 0 '
- 0 .
~
(
B g.- - -
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C 1 1
\ \
7 t
l\l\
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- I o ' * '
TSDV
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', a ap r d p i f s l
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err T sV VaVP eU
~
i -
a eR ar C c l m .
ae e - av l ve v e t l 7 e 5 vticavi e5 - e s s
( 0 I
iic yt vtiy t
( 0 k eF l F W s y ti vi s
- lFoloi sR I
e c
y t
e c
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p a - s g
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- )
i I
- 2 2 C 8
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)
RA e5
.v81
'. 28 1 . 1 0 0 0 0 Il ilil11l1 lI,i\!<
RIVER BEND 24A5188 Reload 6 Rev.2 l
Ney Veasel Press Rise (psi) p Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 W-- Core inlet Flow 125.0 - --- Relief Valve Flow
- -- Core inlet Subcooling --- Bypass Valve Flow j
100.0 -
7* , . . .- - = -
e 75.0 -
. ,s .
C . N C
$ '. \ $ ~
50 0 -
25.0 -
{ ~~~ ~
-l -
_l....
l 00 I
- 25.0 I '
O.0 9.0 18.0 0.0 9.0 18.0 1 Time (sec) Time (sec) I 1'
Level (inch-REF-SEP-SKRT) Void Reactivity
- - - - Vessel Steam Flow - - - - - Doppler Reactivity 150 0 - --- Turbine Steam Flow 1.0 - --- Scram Reactivity
)
- - - Feedwater Flow - - - Total Reactivity g
n 3C ,.
\ W >
, l ,
g 1m.0 g a0 i
w ___ ---
,.\ e
- - . . . . . . . . . . . . g. , / .
- C l' . g l '
l, h: .
. 2 50 0 -
N-1.0 I..' '
e,
- e l ' l ', , , '. ., '. , C
~
~
l, 1; l 'l.' . * = \
- 1. . . .
t.'
I l 00 ' '
- 2.0 I '
O.0 9.0 18 0 0.0 9.0 18.0 Time (sec) Time (sec) :
1 Figure 10 Plant Response to FW Controller Failure (BOC7 to EEEOC7 WITH ICF AND 1 FFWTR)
Page 29
RIVER BEND 24A5188 Reload 6 Rev.2 1
Neutron Flux Vessel Press Rise (psi)
- - - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - -
-- Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow
-)\*1 ',
g 100.0 ,' i fg -
e C
Y. s N E.200.0 f
~s~
., ~~
C 50.0 -
.., 100.0 -
\
j
_ _ _ . - - - - _ . ~ _ l
' l l 0.0 O.0 # -'------ '-------
0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Level (inch-REF-SEP-SKRT) Void R vity
- - - - - Vessel Steam Flow - - - - - Doppler 'ty 200.0 - --- Turbene Steam Flow 1.0 -
-- Scram R vity
--- Feedwater Flow
- Total ReactMty '
g ms
,.=_
2c . -
e ,-
C o 100.0 0.0 .
e .
s% .-
h i* , ,
--.-. .' P
e t: l. /, .,
.., ,. 3 1
0.0 -. , ' .- - - - 1.0 -
' C
),
I
\ l
-100.0 '
- 2.0 ' '
l 0.0 3.0 6.0 0.0 3.0 6.0 l Time (sec) Time (sec) ;
Figure 11. Plant Response to Load Reject w/o Bypass (BOC7 to EEEOC7 WITH ICF AND FFWTR) l l
l l
1 I
Page 30 1
RIVER BEND 24A5188 1
Reload 6 Rev.2 I i
1 i
Neutron Flux Vessel Press Rise (psi) !
- - - Ave Surface Heat Flux - - - - Safety Valve Flow 150.0 -
- -- Core inlet Flow 300.0 - --- Relief Valve Flow )
--- Bypass Valve Flow 1
\
g 100.0 ,e' j, g ,
y 200.0 -
r E .,,,_N h N C '. E
., s'- $
. -- 1 i
50.0 -
. 100.0 -
~
\
0.0
' / '------- ------- i 0.0 '
l 0.0 3.( 6.0 0.0 30 i
. 6.0 Time (sec) Eme (sec)
Level (inch-REF-SEP-SKRT) oid Re vity
-- - - Vessel Steam Flow - - - Doppler o vity 200.0 - --- Turbine Steam Flow 1.0 -
-- Scram Re 'vity Feedwater Flow -
Total Reactivity
. O - ,.***
m
- E .
v 100.0 @ \ .
g 0.0
. 5' } .
- g Ql, ,. ,'-'"-- "'p ,,
,o 4 ,.
, o . \
.. , y
.. .... 5 l' .' '
ttti -1.0 00 ,.*r-'-r,------ ---- -
. o
',.,a g
f
'Y.
I
\
-100.0 ' '
- 2.0 ' '
l 0.0 3.0 6.0 0.0 3.0 6.0 t
Time (sec) Time (sec) i Figure 12 Plant Response to 'Ibrbine Trip w/o Bypass (BOC7 to EEEOC7 WITH ICF AND FFWTR)
Page 31 l
i i
RIVER BEND 24A5188 Relo-d 6 Rev. 2 Neutron Flux Vessel Press Rise (psi)
- - - - - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - --- Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow
,,,, _ """ N g 100.0
',% s g 200.0 E '
N E C '. N s E
, 's $
I
. 's '%
50.0 -
'- 100.0 -
I .
0.0 O.0 # I C 5.0 10.0 0.0 5.0 - 10.0 Time (sec) Time (sec)
Level (incMEF-SEP-SKRT) I VoidNactivity
- - - - - Vessel Steam Flow ---
- Doppler Reactivity 200 0 - --- Turbine Steam Flow 1.0 - --
Scram Reactivity *,.. -
- - - Feedwater Flow --
Total Reactivity g .
- m .-
E '
V 100 0 2
{0.0 -
( ,'
7-L N'.
% . -Y./. g o
O
\
4 e
\. ~ >.
g
- .. ................. y \ ,
00
\. .-
g \
- - - - - - - - - - - - m -1.0 -
)
e 1 \.
1
\.
-100.0 - ' - l' '
- 2.0 O.0 5.0 10.0 0.0 5.0 10.0 Time (sec) Time (sec)
Figure 13 Plant Response to Press. Regulator Failure (BOC7 to EEEOC7 WITH ICF AND FFWTR)
Page 32
RIVER BEND 24A5188 Reload 6 Rev.2 I
N[utron Flux Vessel Press Rise (psi) d Ave Surface Heat Flux f i
- - - - - Safety Valve Flow I 150.0 - --- Core inlet Flow 125.0 - --- Rehof Valve Flow
- - - Core Inlet Subcooling - - - Bypass Valve Flow l ,
i i
g 100.0 m
4: ~ ~ ~ ~ ~O~hk '.
75.0 -
E 't 5 C ' ,\ C i
j
~
cA ', N 8 '
l
'. s 1
50.0 -
25.0 - "' 1 1
-l -
(_1....
0.0 I '
I
- 25.0 '
O.0 9.0 18.0 0.0 9.0 18.0 Time (sec) Time (sec) i Level (inch-REF-SEP-SKRT) Void Reactivity
- - - - - Vessel Steam Flow - - - - - Doppler Reactivity 150.0 -- --- Turtrine Steam Flow 1.0 - --- Scram Reactivity
- - - Feedwater Flow )
--- Total Reactivity Q
i i
j
- . . . . m .
\ "C . o' e, 100.0
@ 0.0 - -
-- ~= .- : , , , . .=. . e 3
--h i y _ _ ._ ---
m.
C l' , O I
- - O -
{,
1' ;\
3
. l', ,, \ -
s: 5 50.0 -
l,. ' . , . . N-1.0 e
l',',.,,*., E l,
l' l.l.
- i, \
j, .
O.0
- 2.0 ' '
0.0 9.0 18.0 0.0 9.0 18.0 Time (sec) Time (sec) l l Figure 14 Plant Response to FW Controller Failure (BOC7 to EOC7
- FWTR-100%P/100F)
Page 33
RIVER BEND 24A5188 Relord 6 Rev.2 Neutron Flux Vessel Press Rise (psi)
- - - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 300.0
- --- Relief Valve Flow
--- Core inlet Flow
--- Bypass Valve Flow 100.0 -
200 3m
[
u %c.,%~~
30 m
,N
' E ,
f -
f -
50.0 -
100.0 -
' /
0.0 O.0 ' -I--- ---'-------
0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Level (inch-REF-SEP-SKRT) oed R ~v ity
- - - - Vessel Steam Flow - - - - - Doppler e 200 0 - --- Turbine Steam Flow 1.0 -
-- Scram R vity
--- Feedwater Flow -
Total Reactivity i n .-
_ S .
'\ '.
e \ .. ,,.
2 s t 100.0 -
8 0.0
\ .-
{
g l,
.s,----.
,. .- 4.},...
\
vo (. .' a
. ' . .. O - \
. .. . y 3
0.0 L._.l_q'.-_-_ h -
-__ g _i.0 e
e 4
' I
-1000 '
- 2.0 I '
0,0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 15 Plant Response to Load Reject w/o Bypass (BOC7 to EOC7 FWTR-100%P/100%F)
Page 34
RIVER BEND 24A5188 Reload 6 Rev.2 Neutron Flux Vessel Press Rise (psi)
- - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 -
- -- Core inlet Flow 300.0 - --- Relief Velve Flow
--- Bypass Valve Flow s ,' '. I g 100.0 \ ', p 200.0 -
e
'S m svN 2 E %* ce t
,%s C l
'.. ~
f -
l
~~~ .
50.0 -
100.0 - l i
0.0
. / ,
0.0 '
0.0 3.0 6.0 0.0 3.0 6.0
)
Time (sec) Time (sec) j l
l 1
i Level (inch-REF-SEP-SKRT) /oid Re etivity
- - - - Vessel Steam Flow {
- - - - - Doppler a ty 200 0 - --- Turtune Steam Flow 1.0 -
-- Scram R vity
--- Feedwater Flow - Total Reactivity -
g .\ )
\
sc . .-
l g '
t 100.0 g 0.0
$ 7 - --- . .- E c 1 .. .N- o \
,.' U \
.'=
o'. i.. ' ,., -
..- ... 3 .
0.0 . r-- r - - - - - - - ---
en -1.0 -
e
',. e (V
I' I
-100.0 '
- 2.0 l '
O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 16 Plant Response to 'Ibrbine Trip w/o Bypass (BOC7 to EOC7 FWTR 100%P/100%F)
Page 35
RIVER BEND 24A5188 Reload 6 Rev.2 Neutron Flux Vessel Press Rise (psi)
- - - - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - --- Cor* Inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow 100.0 M's !
., 200.0 -
4
- N M C '. N s E
$ ~
's %
s 8 j
- N
%s' l 50 0 -
'., -% 100.0 -
j_____________.
0.0 O.0 ' '
O.0 5.0 10.0 0.0 5.0 10.0 Time (sec) Time (sec) i Level (inct>-REF-SEP-SKRT) VoidNactivity
- - - - Vessel Steam Flow -- - Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 - --
Scram Reactivity
- - - Feedwater Flow --
Total Reactivity ,.
Q' w . ,.
,. ~*
m .-
E ,
v 100.0 .g ,' ,'
{0.0 f
g,,
\---"----.
N. -'f', E o
\
\ '
- . \', O .
g
\' ' y N .-
- . ................. 5 \
0.0 - '--- ----------
5m -1.0 -
i, gi x \
1.
\
l
-100.0 I '
- 2.0 \ ' '
O0 5.0 10.0 0.0 5.0 10.0 Time (sec) Time (sec)
Figure 17 Plant Response to Press. Regulator Failure (BOC7 to EOC7 FWTR 100%p/100F)
Page 36
RIVER BEND 24A5188 Reload 6 Rev. 2
(
i Neutron Flux Vessel Press Rise (psi) \
Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - ---
Coro inlet Flow 125.0 - --- Relief Valve Flow
- - - Core inlet Subcooling --- Bypass Valve Flow
~
(
---*-w' g 100 0 -----------[ '
g 75.0 E
l E }\.
E
[
'. y
', \
50.0 -
25.0 -
j
~~~
.J .
-- _I_ i l
00 I
- 25.0 ' I l
00 20.0 0.0 20.0 -
l Time (sec) Time (sec)
Level (inch-REF-SEP-SKRT) Void Reactivity ;
i ----
Vessel Steam Flow - - - - - Doppler Reactivity 150.0 - --- Turbine Steam Flow 1.0 - --- Scram Reactivity ' }
Feedwater Flow --- Total Reactivity Q
. . . . . m , ,
-\
E l V 100 0 -- ---
0.0 -
s --........---..-...b ea g >
C O 1, g -
t 0 -
)
l'
- k \
l d. 3 1, 1
50.0 -
l* = 0-1.0 e
b . . ,~ . .
C l '.\,,
1l
, . . . .. ' , i i . ' * ,
< l
- l. .. ..,, I,
! 1.' '. i l-00 - 2.0 -
0.0 20.0 0.0 20.0 Time (sec) Time (sec)
Figure 18 Plant Response to FW Controller Failure (BOC7 to EOC7 STANDARD-HALING) i P
l l Page 37
- RIVER BEND 24A5188 Reload 6 Rev.2 i
i i
Neutron Flux Vessel Press Rise (psi) 1
- - - Ave Surface Heat Flux - - - - - Safety Va!ve Flow l 150.0 -
- -- Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow ,
'00'O /u\' 200 0 ~
4 W -
C 3R ., 3R
., --~~~
50 0 -
100.0 -
1 i
' I '
-- ..... ~~~~'
0.0 O.0 '# - ' '
O.0 3.0 6.0 0.0 3.0 6.0 l l
Time (sec) T'aw (sec) ;
Level (inch-REF-SEP-SKRT) Void R 'vity
- - - - - Vessel Steam Flow -- Doppler eacti i 200 0 --- Turbine Steam Flow 1.0 -
- Scram R vity
--- Feedwater Flow Total Reacuvity ;
n
. t* . ... ~~.. .
m ..
y '
@ i
- V 100.0 w. c '
y g 0.0 .
l .'
~'---. ~.. -
- l. ,
g l', , ,'. . . o . N at .',... ' ~
- l. : '. '
. .... ... g. \
00 L W,-*- -r,- -
$m -1.0 -
\
\
c g.
. \
)
-100.0 ' - '
- 2.0 -
0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 19 Plant Response to Load Reject w/o Bypass (BOC7 to EOC7 STANDARD-HALING)
Page 38
RIVER BEND 24A5188 Reload 6 Rev.2 Neutron Flux Vessel Press Rise (psi)
Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - -- -- Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow p 100.0 '
200.0 -
E e *
'% E E ' M' E
,N~, C
, ~~ ,' - 8 -
50.0 -
. 100.0 -
0.0 '
4 l ' ' '* -
....~~~~~~'
0.0 ' '
O.0 i 6.0 0.0 3.0 6.0 Eme (sec) Time (sec)
Level (incMEF-SEP-SKRT) Void Re Mty
- - - - - Vessel Stearn Flow -- - Doppler 200 0 - --- Turbine Steam Flow 1.0 -
Scram R vity
- - - Feedwater Flow -
Total Reactivity g .-
. w .
h ,..** .
s . . ..
g .. -
C e 100.0 y. .%--. 0.0 ,
- o S . ___ . -
m I. .
g '. o \ 1
- l. '
. .' . O ' \
R:. '.
. . ' . . ' ~ . . . . .... y 1 . \
.l fm - 1.0 h\
00 h. . , .- - - - - - - - - - - - -
\1
~'
x
~
\\\,'(
i00.0 . i -
-2.0 \ \- I -
00 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 20 Plant Response to 'Ibrbine Trip w/o Bypass (BOC7 to EOC7 STANDARD-HALING)
Page 39
I RIVER BEND 24A5188 Reload 6 Rev. 2 I
l Neutron Flux Vessel Press Rise (psi)
- - - - - Ave Surface Heat Flux - - - - Safety Valve Flow 150.0 - --- Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow
/% j j \
g 100.0 , o 200.0 -
Ns l w '. i l l e , c l 4 '.,
! e N s' 8 "
l
?
1 ~
50.0 - ,'- i 100.0 -
1
' 1
.,, . 1
' I l 0.0 O.0 ' l'*-- --'-
s
! 0.0 5.0 10.0 0.0 5.0 10.0 l Time (sec) Time (sec) - t l
l I
Levei(inch-REF-SEP-SKRT)
- - - - Vessel Steam Flow 200.0 - --- Turbine Steam Flow
- - - fDoppler Voiddactivity Reactivity 1.0 - -
Scram Reactivity
- - - Feedwater Flow - - - Total Reactivity ,..
n 11 . ,. .. -
t t ac .-
l e
{0.0 q,,,,,_,,'
g 100.0 g, *p _
q s'. . ,,N. .
E \\,
c \'.
g gV 4 . \- .
k
\'. b I .
s.
,. ---.......... 3 \ ,
0.0 - - ------------
tcc -1.0 - i 1 e \
l [ l l .
- 1{
- l. \'
?
\
! -100.0 I '
- 2.0 I I '
l 0.0 5.0 10.0 0.0 5.0 10.0 Time (sec) Time (sec) 1 Figure 21 Plant Response to Press. Regulator Failure (BOC7 to EOC7 STANDARD-HALING)
Page 40 l
l
l RIVER BEND 24A5188 l Reloed 6 Rev.2 I l
i Neutron Flux
- - - - Ave Surface Heat Flux Vessel Press Rise (psi)
- - - - - Safety Valve Flow
\
- 50.0 - --- Core inlet Flow 125.0 - --- Relief Valve Flow
- - - Core inlet Subcooling --- Bypass Valve Flow
.____'_______.__l y j
100.0
, f, 75.0 -
C
= .s [
e
- \
'\ $ '
l
',\ s 50.0 -
', 25.0 -
l- ~ ~
. J -- - .
1 I -
1 0.0 I
- 25.0 ' I 0.0 20.0 0.0 20.0 Time (sec) Time (sec) i Level (incMEF-SEP-SKRT) Void Reactivity l
- - - - Vessel Steam Flow - - - - - Doppler Reactivity '
150.0 - --- Turbine Steam Flow 1.0 - --- Scram Reactivity
- - - Feedwater Flow l
--- Total Reactivity <
Q
. . . . . m ,
2 *
-- \ @ 0.0 i
- e. 100.0 p. 8. .
E E e
g l' o 0 n.'
t -
1 k \
\C, ,*{ :'. 3 k 50 0 -
=
0 -1.0 -
I E l t, P'}",l. .
p.,
1: ,.'
(; .'
O.0 - 2.0 - I 0.0 20.0 0.0 20.0 Time (sec) Time (sec)
Figure 22 Plant Response to FW Controller Failure (BOC7 to EEOC7 WITH ICF -
HALING)
Page 41
RIVER BEND 24A5188 Reload 6 Rev.2 Neutron Flux Vessel Press Rise (psi)
- - Ave Surface Heat Flux - - - - Safety Valve Flow 150.0 -
--- Core injet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow
_ /us. ,
100.0 lDY,\ 200.0 - - - -
m .
m 39
., s __ ' % gt -
%s'~
50.0 -
100.0 -
I 0.0 O.0 '# "'
I --.....'
O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Level (inch-REF-SEP-SKRT) VoM Re etivity
- - - - - Vessel Steam Flow -
Doppler e 200.0 - --- Turt>ine Steam Flow 1.0 -
Scram R ctivity
- - - Feedwater Flow Total Reactivity
. 6 . ,} *,,. .
~~
sc .
C
- E '*
- r. - --- . 8.
- 0 '. .,
- 2 E
s .,.. ...- ;
l '. .. N
- [; ; '.
l , ' ' , , ' . . * '. ..
o y
\ '
l
... .... l 0.0 ,* ,, ---------
$m -1.0 -
\
g
',,,,, e l' l
- 1 g i
\ ').\
-100.0 ' I '
- 2.0 \ l I '
O0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 23 Plant Response to Load Reject w/o Bypass (BOC7 to EEOC7 WITH ICF-HALING)
Page 42
RIVER BEND 24A5188 Reload 6 Rev.2 Neutron Flux Vessel Press Rise (psi)
- Ave Surface Heat Flux - - - Safety Valve Flow 150.0 - .- -- Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow o
_./ \ .
g 100.0 ,.
\'d,\ 200.0 -
E . N- E E . N c
- R
%'s , g -
., ~~
50.0 -
. 100.0 -
' / '
'"I. --.....,'
00 O.0 ' '
O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
I Level (inci>-REF-SEP-SKRT) Void Re 'vity
Vessel Steam Flow -- - Doppler ea ty 200.0 - --- Turbine Steam Flow 1.0 -
Scram Reactivity Feedwater Flow Total Reactivity
. E /\ ,,...
g ..
c e '
t 100.0 y. k 0.0 ,
~~ , ,
g ;, -. ..
E s ',' -
c g. l' s 3
- 1: ,',, l ',- , ' ' . ,' ' . . .
p
\.
. :. \ 1
= \
0.0 L;. m., _1._ __ _ _ _ . _ _ _ _ _ _ _ g -1.0 -
,, e \ ,i c I
'.,, ~
\
t.
\
l I
-100.0 ' *
- 2.0 I '
O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 24 Plant Response to 'Ibrbine Trip w/o Bypass (BOC7 to EEOC7 WITH ICF -
HALING)
Page 43
I RIVER BEND' 24A5188 Reload 6 Rev.2 l
I i
i Neutron Flux Vessel Press Rise (psi)
- - - - - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - --- Core inlet Flow 300.0 h --- Relief Valve Flow
--- Bypass Valve Flow !
. l
/~' %
- \
l
- \ 200.0 g 100.0 ,
E
- s E C '. \ Z
$ ~
s N
'. s N
%s%
50.0 -
. 100.0 -
' I 0.0 O.0 ' '------'-
0.0 5.0 10.0 0.0 5.0 10.0 Time (sec) Time (sec)
Level (inch-REF-SEP-SKRT) VoidNactivity
- - - - - Vessel Steam Flow - - - - f - Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 -
Scram Reactivity
--- Feedwater Flow - - Total Reactivity
~~~.
2c ..
8 .-
3 1000 c- s . ~. g. a0 .
q t ~~.. .
e 3.
1 (,.#
- g \'. o 8 ~ N- O .
N', , y \ '
- s. , -
--.......... y g 0.0 - - ------------
T>
co - 1.0 -
\
@ \ ;
E \
. . \
\'
\
I
-100.0 ' '
-2.0 I' I '
OO S.0 10.0 0.0 5.0 10.0 Time (sec) Time (sec)
Figure 25 Plant Response to Press. Regulator Failure (BOC7 to EEOC7 WITH ICF -
HALING) i 1
Page 44
1 RIVER BEND 24A5188 Reload 6 Rev.2 l
l
{
Nep Vessel Press Rise (psi)
\
- - j- Ave Surface Heat Flux - - - - - Safety Valve Flow l 150.0 W-- 125.0 Core Irdet Flow - --- Relief Valve Flow !
- -- Core inlet Subcooling --- Bypass Valve Flow l
~~~~"~~~
g 100.0 $ 75.0 -
E I W
C g -
'.s \ \
C g -
'. 1 50.0 -
25.0 - ' ' ~ ~ ~ I I
..l
_._ L_J.....
0.0 ' I
- 25.0 '
O.0 9.0 18.0 0.0 9.0 19.0 Time (sec) Time (sec)
Level (inch-REF-SEP-SKRT) Void Reactivity
- - - - - Vessel Steam Flow - - - - - Doppler Reactivity 9 150.0 - --- Turbine Steam Flow 1.0 - --- Scram Reactivity
--- Feedwater Flow --- Total Reactivity ) -
e . ,. .
3C 1 g 100.0 q
@ 0.0 -
W.% -=,= - , .'
s g\ .
- n.
- C l' . O
$ ' O ~ \.I la \ x l',.,', \ s l 5m -1.0 l
50 0 -
- l. , . .. -
. e l ' ,' ', ' ' . , ' ' . , - E
. l,.'
j..
I: ' :.' .
0.0 ' J" " '
- 2.0 ' ' '
O.0 90 18.0 0.0 9.0 18.0 Time (sec) Time (sec)
Figure 26 Plant Response to FW Controller Failure (BOC7 to EEEOC7 WITH ICF AND FFWTR HALING)
~
Page 45
RIVER BEND 24A5188 Reload 6 Rev.2 Neutron Flux Vessel Press Rise (psi)
- - - Ave Surface Heat Flux - - - - Safety Valve Flow 150.0 -
- Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow
\
-/ V ,
- ' i g 100.0 , 4 200.0 -
1 w
x ' ?^w w
a N
,'--~
l
'--~~. \
50.0 -
100.0 -
l
' /
00 O.0 ' I --- - ---
0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec) i l
i Level (irMEF-SEP-SKRT) Void Re vity ;
- - - - - Vessel Steam Flow - - - - Doppler e vity 200.0 - --- Turbine Steam Flow 1.0 -
Scram Re ctivity
--- Feedwater Flow Total Reactivity G
y?
g '
v 100 0 c ,
0.0 *,-
E --------.
g
, , g U -
3.\
[.. ,.
d
.. ..- ... g, 0.0 ------
m -1.0 -
e g
C .
.. \
\.
-100.0 I '
- 2.0 \hA I '
00 3.0 6.0 0.0 3.0 60 Time (sec) Time (sec)
Figure 27 Plant Response to Load Reject w/o Bypass (BOC7 to EEEOC7 WITH ICF AND FFWTR HALING)
Page 46
RIVER BEND 24A5188 Reload 6 Rev.2 Neutron Flux Vessel Press Rise (psi)
Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - .- --
Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow 5
i
/ (. ,
, / g 200.0 g 100.0 ,
s C
' w a E
~
N-s' $ -
50.0 -
100.0 -
1 l
0.0 O.0 '
O0 3.0 6.0 0.0 3.0 - 6.0 Eme (sec) Time (sec) ;
1 Level (inch-REF-SEP-SKRT) Void Re etivity Vessel Steam Flow - - - Doppler vity 200 0 - --- Turbine Steam Flow 1.0 -
Scram Reactivity Feedwater Flow Total Reactivity g
2? ,.
C '
u 100.0 -
0.0 .. -
s c cl. ~ ~. .- a x4,-
g ii 8 i*. .. ,'. *
\l
~... ..- ...
0.0 , , r- - ------ m -1.0 -
\(
.. e m ) .t y
\'
I I
-100.0 '
- 2.0 I '
O.0 3.0 6.0 0.0 3.0 6.0
- Eme (sec) Time (sec) l Figure 28 Plant Response to 'Ibrbine Trip w/o Bypass (BOC7 to EEEOC7 WITH ICF AND FFWTR HALING) l i Page 47
, llll ! :
F $ gyg g C%5-g i
1
- RR eI 1 2 u 0 0 0 0 0 5 1
0 1
5 lV -
o r 0 0 0 0 0 0 aE e 0 0 0 0 0 0 0 2
O.
0 -
~
v - -
O.
0 -
0 dR 9 - - 6 B Y
t -
- - - E P
l
\
- - N a
n \ -
D t s .~ ~ -- -
R - -
. FTVL '
N CAN e -
. euee er sv ov e s ,
disb e
~ .\
r e u p wne \ e t
.'N (l i Sr o T -
a el i n Sc N nur on n
s i - -
t eSt t eh T l ef aF i
r t e m - e a - m Feclux e 5 - Fa mR e5 s
om l
t I . l E o wH
( 0 o s - .
wFlFo -F (
s 0
% e a
P e -
l o e N w wS
. t r c .
E c F e
)
, P
)
s ul s . - '
x s
. S '
. . K s -
FR ' - . R .
)
T .
Fe -
Wgul Ta - . . .
Ro t Hr F 1
0 - . 1 0
Aa Li 0 0 I u l
C@eg;;y Ooe { @cm 2..2 g CE5n .
Nr 2 1
0 1 0
1 2 0
3 0
0 0
) (e G O. 0 0 0 0 0 0 0 0 0 0 0 B 0 .
~ .
- 0 .
O -
C g --
7 \
g , -
t o \
l;\
\y, f lli E
I I
E -
TSDV ocooi 'I yBRSVeae E ',
t al rap d p aet ef s l
i s
O '. RmpeN err l
sfy e sV l
C iT
- c a eRc a T VaVP av ar l
7 m t aet mi v e l
v e e e 5 i vti c avi cti e5 l
s eF F s W
I
(
s 0
I ti y i vtiy t
y i v (
s 0
I Fol oi ow l
l Rs T e c
y t
e we P - c w g
a H )
) (
p s
i I )
e .
4 C -
, 2 8 F '
4 A .
RA e5 N -
.v81 D *
- 28 1 , 1 0 0 0 0
.i l .I
RIVER BEND 24A5188 Reload 6 Rev.2*
l N on Flux d Ave Surface Heat Flux Vessel Press Rise (psi)
- - - - - Safety Valve Flow
\
150.0 - --- Core inlet Flow 125.0 - --- Relief Valve Flow
- -- Core inlet Subcooling --- Bypass Valve Flow ,
. l l
~ '
I 100.0 e 4 W ~~~~~ - '
75 .0 -
?m hw ?
C I e
.N C
$ '. N $
~
50.0 -
25.0 - F~~
l ;
-l -
_J....
I
. 0.0 '
- 25.0 ' I '
O.0 9.0 18.0 0.0 9.0 18.0 Time (sec) Time (sec)
Level (inch-REF-SEP-SKRT) Void Reactivity
- - - - - Vessel Steam Flow - - - - - Doppler Reactivity f 150 0 - --- Turbine Steam Flow 1.0 - --- Scram Reactivity i
--- Feedwater Flow --- Total Reactivity I G
v . ,
1 ,-
. @ l g 100.0 g g 0.0 - --
T s r_- i . ,q ,- 2, m - ---
n\ E C o \
l'; . *
$ l ,\
\'
y ll ,. \ s l 50.0 -
e .
Qm -1.0 -
\
i::.' '. : . *. ,' '. ,
l .*
(
l . i ,
i 0.0 I 'I' # .. d \ l I'
- 2.0 OO 9.0 18.0 0.0 9.0 18.0 Time (sec) Time (sec) l 1
Figure 30 Plant Response to FW Controller Failure (BOC7 to EOC7 WITH FFWTR HALING-100%P/100%F) l Page 49
RIVER BEND 24A5188 Reload 6 Rev.2 Neutron Flux Vessel Press Rise (psi)
- - - Ave Surface Heat Flux - - - - Safety Valve Flow 150.0 -
- Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow
/ \,b -
n 100.0 e 200.0 -
,.,x y 5 f x W -N s E N C ~
~
W
- ~
'~~-. l 50.0 -
100.0 -
. .. i i
I l
0.0 l I --- l O.0 --- --
0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Level (inch-REF-SEP-SKRT) Void Re 'vity
- - - - - Vessel Steam Flow - -- Doppler sa ty 200.0 - --- Turbine Steam Flow 1.0 -
Scram R 'vity
--- Feedwater Flow Total Reactivity -
i g , ,\
.. ~ ~ '
m 2e \ .-
,- l e 100.0 '
{0.0 y w - -- ,
~~~~~~~p
~
C l ', ~N-N*
- r' l.
y
\
m . '-
.~,
.- . . . . . ....... .g \\
00 l'. l '
iica -1.0 -
l' e \
e x \'g
-100.0 2 ' I
- 2.0 O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 31 Plant Response to Load Reject w/o Bypass (BOC7 to EOC7 WITH FFWTR HALING-100%P/100%F) l l Page 50
iJ RIVER BEND 24A5188 Reload 6 Rev.2 Neutron Flux Vessel Press Rise (psi)
- - - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - -- -- Core Inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow 1
5 j d
g 100.0 )'{ '. 200 0 -
'l C
3 Mb C 3
-w 1 gt -
s'N 3R 1
50.0 -
. 100.0 - I r-----~~------
/
i 00 0.0 ' '
l 0.0 30 6,0 0.0 3.0 6.0 ;
Time (sec) Time (sec) !
Level (inch-REF-SEP-SKRT) Void Re c*vity Vessel Steam Flow - -- Doppler e 'ty j 200 0 - --- Turtune Steam Flow 1.0 -
Scram R ~v ity Feedwater Flow Total Reactivity g ~~
- . A .. ...
g +\ ...
c s e .-
t 100.0 -
o 0.0 .
y r-- --- . g- ,. -
E ---
- i.
i',
g s3 at l ', /, ,-
\
3 \.
0.0 , r- - ------
m -1.0 -
- s. e \ \
E t.
\f l-
-100.0 ' ' ' I '
- 2.0 ' '
i 00 3.0 6.0 0.0 3.0 6.0
! Time (sec) Time (sec)
Figure 32 Plant Response to 1brbine Trip w/o Bypass (BOC7 to EOC7 WITH FFWTR HALING-100%P/100%F) l l
l Page 51 i
RIVER BEND 24A5188 Reload 6 Rev. 2 Neutron Flux Vessel Press Rise (psi)
- - - - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - --- Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow
\
~~ N v 100.0 -r ( l 3 200.0 o , s
- 4 -
N E C '. N s C i $
- i
%s' s, N l
j 50.0 -
'-- 100.0 - '
' I 00 O.0 ' ' '
O.O 5.0 10.0 0.0 5.0 10.0 Time (sec) Time (sec)
Level (inch-REF-SEP-SKRT)
- - - - - Vessel Steam Flow - - - fDoppler VoidNactivity Reactivity l
I 200.0 - --- Turbine Steam Flow 1.0 - -
Scram Reactivity
--- Feedwater Flow ~~.
- - TotalReactivity ,..
. t" .
$C
.~ i g ,-
u 100 0 -
g 0.0 g..
2 7 . s -- ..,-
,%.- Y g
@ L
\', O o \ h 8 \- y
\
'.\..
g y \
0.0 - - - - - - - - - - - - - m -1.0 -
C e \t \
l
. l .
\
\
I
-100.0 '
- 2.0 I' I '
O.0 5.0 10.0 0.0 5.0 10.0 Time (sec) Time (sec)
Figure 33 Plant Response to Press. Regulator Failure (BOC7 to EOC7 WITH FFWTR HALING-100%P/100%F)
Page 52
~. __
1 RIVER BEND 24A5188 i Reload 6 Rev.2 1 l
l 1
I i
Neutron Flux 7 Vessel Press Rise (psi) f
- - - - - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - --- Core inlet Flow 125.0 - --- Relief Valve Flow i l
- -- Core inlet Subcooling --- Bypass Valve Flow '
. \
100.0 " " " A --~ -
g 75.0
% '.\ %
C .\ C
$ ~
'. Y
~
N 50.0 -
25.0 -
l ~ ~ ~~
0.0 l
- 25.0 ' I 0.0 20.0 0.0 20.0 Time (sec) Time (sec) l Level (inch-REF-SEP-SKRT) Void Reactivity Y
- - - - - Vessel Steam Flow - - - - - Doppler Reactivity l 150.0 - --- Turbine Steam Flow 1.0 - --- Scram Reactivity
- - - Feedwater Flow - - - Total Reactivity '
~
l
. t .
g ,..- l g <
ts 100.0 -- ---
o 0.0 --
o V' cL 7.,,*/
E E C o l l' O 1 l' ,' ' D [.
t *, 5 i !
50 0 -
' l. ,
O-1.0 -
g I. ' [' ' l', . . . . E l' P . ,' '
}
II.; .',
^
, 1, ll .. ' l'i
' ' IN 0.0 '
- 2.0 '
0.0 20.0 0.0 20.0 Time (sec) Time (sec)
Figure 34 Plant Response to FW Controller Failure (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) STANDARD) i I
l l
Page 53
RIVER BEND 24A5188 Reload 6 Rev.2 l
Neutron Flux Vessel Press Rise (psi)
Ave Surface Heat Flux - - - - - Safety Valve Flow
! 150.0 - -- --
Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow l
l i 3 100.0 ',.('.
k 3
200.0 -
lii / w*\ > s e
Y
. s e
. .,~'~~ Y
~
50.0 -
'. 100.0 -
l
' I -- ..... -
0.0 O.0 i .-r . -
l 0.0 30 6.0 0.0 3.0 6.0 l Time (sec) Time (sec) l
- I Level (inch-REF-SEP-SKRT) Void Re Vessel Sap clow -
- Doppler Reactivity 200 0 - --- Turbine Steam Flow 1.0 -
-- Scram Reactmty l Feedwater Flow -- Total Reactmty .
g =,,... -
... ~,..-
g .
c <\
e .
\
t C
- e 100.0, ;
'-- ' g 0.0
.,j i
$ Ij,',
. .- g x *.
o \,
l ,
, , ' \l
.2 %
k .- - ,
g 1 r
0.0
'.,',u--
E l$ -1.0 e
\,
\
I
_.' \
\.
I l -100.0 '
- 2.0 ' I r
t 00 3.0 6.0 0.0 3.0 6.0 l Time (sec) Time (sec) 1 i
i Figure 35 Plant Response to Load Reject w/o Bypass (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) STANDARD)
! i Page 54
l RIVER BEND 24A5188 Reload 6 Rev.2 A
9 Neutron Flux Vessel Press Rise (psi)
Ave Surface Heat Flux - - - - - Safety Valve Flow 150 0 - --<-- Core inlet Flow 300.0 - --- Relief Valve Flow
- - - Bypass Valve Flow n
1000 /d
'. !, i' -
3= ]m200.0 e A N. w % . e
- ~) ,
' ~~_,~ ~~
t -
50.0 -
. ., 100.0 -
nn, ,
n_n
.I .u.....--
0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Level (inch-REF-SEP-SKRT)
Vessel Steam Flow Void RM
- - - - - Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 -
-- Scram Reactivity Feedwater Flow -- Total Reactivity G
3c o
l .
C j ~
t 100 0 ;-.- . % ,
2m ~~- .
0.0 3,.
,. ~ )
. s C
- l. .
O
\ >
I, *, i
- >. O +
l ,.
1 N.
.. .... .-- y
- g . \g r l O.0 h, - - - - - - , . . - k;p -1.0 - \'
': \g 1
\\1,
-100.0 I
- 2.0
\\I I '
i 00 3.d 6.0 0.0 3.0 6.0 Time (sec) Time (sec) l l
l l Figure 36 Plant Response to 'Ibrbine ' Rip w/o Bypass (BOC7 to EOC7-3693 mwd /MT '
(3350 mwd /ST) STANDARD) 1 l
Page 55
RIVER BEND 24A5188 Reload 6 Rev.2 -
l l
l Neutron Flux Vessel Press Rise (psi)
- - - - - Ave Surface Heat Flux - - - - - Safety Valve Flow
- 150 0 - --- Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow g 100.0
<~ " . ,s'~h g 200.0 1
\
s E
',- ' s, a
- N E
s s g -
s 1
- %~ 1 50.0 -
100.0 -
l i
~. .. .
)
0.0
' l I
= 0.0 0.0 5.0 10.0 0.0 5.0 -10.0
)
Time (sec) Tirt e (sec)
I Level (inch-REF-SEP-SKRT) Void Reactivity
- - - - Vessel Steam Flow ---
- Doppler Reactivity 200 0 - --- Turbine Steam Flow 1.0 - - - Scram Reactivity
--- Feedwater Flow - - Total Reactivity ,..
g - .
m .
C .
e
- C g 1000 g, g 0.0 ..,,,' ' i s 9. -,,,,N- ."_
E g \', )
O N - \' O -
\
\ b \'y f s, , .
............... j g 00 - U I
- ------------- cc -1.0 -
i e \
" \
\ ,
\
\
- 100.0 I '
- 2.0 ' ' '
O.0 5.0 10.0 0.0 5.') 10.0 Time (sec) Time (sec)
I Figure 37 Plant Response to Press. Regulator Failure (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) STANDARD) l l
Page 56
! i
RIVER BEND 24A5188 Reload 6 Rev. 2 Neutron Flux Vessel Press Rise (psi)
- - - - - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - --- Core inlet Flow 125.0 - --- Relief Valve Flow
- -- Core inlet Subcoohng l --- Bypass Valve Flow
_p.O -
_. J
- -'- ~~~~~
j 100 0 - -
o a 75 30 3m s
- \ ce C ', g C Y
',\ \
~
. s 50.0 ' ~~~
, 25.0 -
l
.)
~
i l I
00 - 25.0 ' I 0.0 20.0 0.0 20.0 Time (sec) Time (sec)
- Level (inch-REF-SEP-SKRT)
- - - - Vessel Steam Flow Void Reactivity
- - - - - Doppler Reactivity fY NO - --- Turbine Steam Flow 1.0 - --- Scram Reactivity
--- Feedwater Flow --- Total Reactivity 3
g ,.
g .
t 100.0 c)
- - --- -\ {0.0 - ----. r.:- w-n.m ,
l' i W b-E C O g .
[ O .
l #', Y [
50.0 -
[f.\,4s ca -1.0 -
\.
g 1, d l." ',,'. . $ j I, ' . ., .<
l.
l' .':. . ll I'. .*'
.- t 00 '
- 2.0 ' I I' O.0 20.0 0.0 20.0 Time (sec) Time (sec)
Figure 38 Plant Response to FW Controller Failure (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) WITH ICF)
Page 57
RIVER BEND 24A5188 Reload 6 Rev.2 Neutron Flux Vessel Press Rise (psi)
- - - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - -- -- Core inlet Flow 300.0 - --- Relief Valve Flow Bypass Valve Flow
-/ s ; .
100.0 ,
/7\ 200.0 -
c e g -
's ' N . , g -
., ~~
50 0 -
100.0
~~..,
nn 0.0
,_n l ..u.. -
3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec) i Levol(inch-REF-SEP-SKRT) # Void ReaNty
- - - - Vessel Steam Flow -
- Doppler Reactivity .
200.0 - --- Turtune Steam Flow 1.0 -
-- Scram Reachvity
- - - Feedwater Flow -- Total Reactivity j G . ..
l f.
c ,
.. ,_.... 1 e 100 0 -. '
g ; ,, -. .'
0.0 f.,
{
E l C '. o I l ,.
- O g .
...... g.
- \
\\ l '
c 0.0 d. ,. '.., -------- 8-1.0 -
gI
\.
'... E il '
.. . \1 1 l-
-100.0 ' ' '
- 2.0 l(I ' I '
O.0 3.0 6.0 0.0 3.0 6.0 i
Time (sec) Time (sec)
Figure 39 Plant Response to Load Reject w/o Bypass (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) WITH ICF)
Page 58
RNER BEND 24AS188 Reload 6 Rev.2
!I Neutron Flux Vessel Press Rise (psi)
Ave Rurface Heat Flux * - - - - Safety Valve Flow 150.0 - --.-- Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow n
100.0
/
E E
'.,' M'w s N
', E E
200'0 -
E
. 's , C
~
Y 50.0 -
. . 100.0 -
0.0
/ '-------'~-----
O.0 00 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Level (inch-REF-SEP-SKRT) I Void ReaMty Vessel Steam Flow ---
- Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 -
-- Scram Reactivity Feedwater Flow -- Total Reactivity -
G 2 ..
c .
C
- u 100 0 p. . o 0.0 '
s .
. . . _ _ _ . - g
,,t e .
- , o i .
'. O
- 1< l ,. , '.
. .' 's .
- -. .* .. .- h- \y 3
0.0 D*.- h -
e
- - - - - - - - - - h-1.0 e
(
1 \;
.,. \.
-100.0 I '
- 2.0 I '
O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec) i i
i Figure 40 Plant Response to Thrbine Trip w/o Bypass (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) WITH ICF) t l
I l Page 59 l
RIVER BEND 24A5188 Reload 6 Rev.2 Neutron Flux Vessel Press Rise (psi)
- - - - - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - --- Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow
_ ./ \
g 100.0 .,
g 200.0 w
C
. s N s
, s E
~
s's' %s / ~
50.0 -
. 100.0 -
0.0
, I ' '
0.0 O.0 5.0 10.0 0.0 5.0 10.0 Time (sec) Time (sec)
Level (inch-REF-SEP-SKRT) Void Reactivity
- - - - - Vessel Steam Flow ---
- Doppler Reat tivity 200.0 - --- Turbine Steam Flow 1.0 - - - Scram Reactivity -
--- Feedwater Flow - - Total Reactivity .. -**
g w . ,. ..
$c ..
7 im0 7 L-- --
g" g s . . .'
W . N - '.~. E l c N. o
$ ~ N. O .
\.
\, ,
. ................ 3 y \'s 0.0 - ------------- U l m -1.0 -
e i
[ )
)
1 ,
I
\
_100.0 - I -
- 2.0 \ ' '
OO 5.0 10.0 0.0 5.0 10.0 Time (sec) Time (sec)
Figure 41 Plant Response to Press. Regulator Failure (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) WITH ICF)
Page 60
RIVER BEND 24A5188 Reload 6 Rev.2
/ I NepTlux Vessel Press Rise (psi)
\
y Ave Surface Heat Flux - - - - - Safety Valve Flow l 150.0 - Core inlet Flow 125.0 - --- Relief Valve Flow
- -- Core inlet Subcooling l --- Bypass Valve Flow
_I \
- ~~
100.0 k 75 0 -
. '\
E .s N, .
~
. [ !
8 l '. \ $
1 50.0 - '
25.0 - F -" ~ l I
( J....-
I :
l l
0.0 I '
-25.0 '
l 00 9.0 18.0 0.0 9.0 - 18.0 1 Time (sec) Time (sec) i Level (inch-REF-SEP-SKRT) Void Reactivity k
- - - - Vessel Steam Flow - - - - - Doppler Reactivity 150.0 -
--- Turbine Steam Flow 1.0 - --- Scram Reactivity
--- Feedwater Flow --- Total Reactivity G
m .
E e _. ,*a'
~ Af' g 100 0 -
'g --W - .- "--E-l--j,1 g _- ---
{ 0.0 1, ,/
E 1.\ E i, l' . 8 !
$ ~
l,.
g
~
II .
'.{\ E I.
50.0 -
i U. -1.0 \
- 1. ',
e, e
g
- l. ' . * . . ' . , , [ I,
, l l .' ', . . ' ' l ll l :l '.' I, l ' .' I 0.0 ' I '
- 2.0 I ' I.'
O.0 9.0 18.0 0.0 9.0 18.0 Time (sec) Time (sec)
Figure 42 Plant Response to FW Controller Failure (BOC7 to EOC7-3693 mwd /MT
'(3350 mwd /ST) FWHOOS with ICF)
Page 61
ll
! t!I'
- E%@u $ C%g RR F 1 1 2 1 eI g
i 0 0 0 0
0 0
0 0 5
0 0
0 1
5 lV o
u 0 0 0 0 0 0 0 0 0 0 aE r 0 . 1 <
0 dR e . , ' - - 0 -
. - 6 B
,'- ,
- A. ::r 4 *,,- , l E
3 --
'l - % N f
}
P l
- ,r' - -
D a '
~ - -
n '
- a
- FTVL t
,W euee ov e R ,' et sv dns e r
er e u e w n e (l Sr t
p s
T ,. % a et ni t
eSt Sc T ,'
% inur o l
ef n
o i m
r t eh t aF n Fa mR e a - mi - ~ Fec ul
( s e 3 I
,. . om l
E e3 ! . ol wH x
3e 3t
(
s e
0 w Fl F F ol wS o-(
s e
0 ,
N e a
t 5o )
c - w E c F 0 L .
P
) '
ul s x Moa -
S Wd K
R dR
)
T .
/e Sj -
s
)Tect -
Fw W/ 6 -
- 6
~
o 0 0 H B Oy Cesbj>
a 8EGoCga - G
- C%p Op - -
1 0
2 3 Sass 0 0 2 1 0
0 0
1 0
0 0 0 0
0 0
0 0
0 0
0 w 0 . - .
0 i (B
~
t h
O g \pf. . ( -
I CC Il\
\ ,
. \ - / -- -
F 7 II I -
,\ ,
. -- \
) t o
- -- - / -- -
TSDV E ,
o t cooi / yBRSV eae O .
al rap d , p i f s l
aet e s C #, RmpeR l
. sfy el 7 T ,
err a ea T ._
sV VaVP av e ar c aeti eRc i . l 3 mi e 3 icav" t
vt m .
l v
vl e e ss e3
~r.
6 I i ici t t ,
eF
( 0 .
y tvtiy 0 F 9 s . y ii v (
s . Fol oiR l
ow wes l
3 e c - y t
e w P c -
g a M ) -
)
(
p s
i e
6 W
d
)
2 2 /
- - 4 M .
_ RA e5 T .
.v 81 28 6 '
6 .
0 0
! I l 1jj l Ill1{ !l.ii
RIVER BEND 24A5188 Reload 6 Rev.2 Neutron Flux Vessel Press Rise (psi)
- f - - - Ave Surface Heat Flux - - - - - Safety VaNo Flow 150.0 - -
-- Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow
~
._ /\
g 100.0 , ,1/g 200.0 -
' \ s E C ,N E
$ ~
%,' ~
$ ~ N 50.0 -
100.0 -
7 __-
,00 " ~
- e -- = 0.0 I ' '
OO 3.0 6.0 0.0 3.0 6.0 Eme (sec) Time (sec) l
/\ '
Level (inch-REF-SEP-SKRT) / oid V Reactivity '
- - - - - Vessel Steam Flow - - - - Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 -
-- Scram Reactivity
--- Feedwater Flow -- Total Reactivity g
.. - l m
z g
t 100.0 T - ---- --
g 0.0
. E x I. .
o \
- i'. l '.'- O ~
.. y .
. . .- ... g z g
\
I,. .
U 00 . , . , .-- y'---- -------
\;
g-1.0 -
g I,' .'
E 1
. \
l*
~ \
00 30 6.0 0.0 30 6.0 Eme (sec) Time (sec) l l
Figure 44 Plant Response to 'Ibrbine 'IYip v!o Bypass (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) FWHOOS with ICF) i Page 63 i
i' RIVER BEW 34A5188 Reload 6 Rev.2 i
1 I
i I
1 Neutron Flux Vessel Press Rise (psi) !
- - - - - Ave Surface Heat Flux - - - Safety Valve Flow I 150.0 - --- Core inlet Flow 300.0 - --- Relief Valve Flow l
--- Bypass Valve Flow
_ ./
g 100.0
~
'., \ 200.0 -
s C
's N w
C
$ ~
s N
$ ~
%'s 50 0 -
i ~. '
100.0 -
' i
., ' l 0.0 I I 0.0 '
O0 5.0 10.0 0.0 5.0 10.0 Time (sec) Time (sec)
I Level (inch-REF-SEP-SKRT) Void Reactivity
- - - - - Vessel Steam Flow - - - - - Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 - - - Scram Reactivity
- - - Feedwater Flow - - TotalReactivity * '
- g ws . ,.= .. **
vs
- E ~
v 100.0 -
I ,
ae --
- 8. 0.0 %. . , ..*
7
~ y\~ '
._ . ~~. E \ J
- 0 \ .
N.
~
2- \ 'l A.
-.............. ;g g 0.0 -
N -1.0 - I e \ .
\
\
\
t
- 100.0 ' ' '
t I
- 2.0 '
O.0 5.0 10.0 0.0 5.0 10.0 Time (sec) Time (sec)
Figure 45 Plant Response to Press. Regulator Failure (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) FWHOOS with ICF)
Page 64
~
RIVER BEND 24A5188 Reload 6 Rev. 2 p N[ron Flux Vessel Press Rise (psi)
- - - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - --- Core inlet Flow 125.0 - --- Relief Valve Flow
- - - Core Inlet Subcooling --- Bypass Valve Flow g .
- g. . . . . . - - - - - ~A _
o %3 m C .A C
~
8 [ '. N $ ~
50.0 - '
25.0 - F -~ ~
l g -); ....
I 0.0 - 25.0 I 0.0 9.0 18.0 0.0 9.0 18.0 '
Time (sec) Time (sec) ra v Level (inctwAEF-SEP-SKRT) Void Reactivity IV
- - - - - Vessel Stearn Flow - - - - - Doppler Reactivity 150.0 - --- Turbine Steam Flow 1.0 - --- Scram Reactivity
--- Feedwater Flow - - - Total Reactivity G
3c ,.
\ .
k 2F '
g 0.0 , e7,ff,g, g 100 0 - --
. . .--y, ,,,
y _- ---
7 E l. i C
8 -
l', i d ~
]'
- 1. \ 3 l' .i,.\
s a 1 50 0 -
- g. ' , , *
- 1.0 -
g l : . ,' ,\'. ,' '. ,- [
);
. l', , . . \\
I ,' ' .":,
I li ' . ' . I,j 0.0 I ' ' I L
-20 '
0.0 9.0 18.0 0.0 9.0 18.0 Time (sec) Time (sec)
Figure 46 Plant Response to FW Controller Failure (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) FWTR-100%P/100%F) l Page 65
RIVER BEND 24A5188 Reload 6 Rev.2 Neutron Flux Vessel Press Rise (psi)
-b - - - Ave Surface Heat Flux -----
Safety Valve Flow 150.0 - ---- Core inlet Flow 300.0 - ---
Relief Valve Flow
--- Bypass Valve Flow 100.0 i '-
' ' 200 .0 -
h MN.? w *~ m e e p '
'., g -
~~
50.0 -
., 100.0 -
~.
00 O.0 I '
O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
O Level (inch-REF-SEP-SKRT) Void Rea ty Vessel Steam Flow -
- Doppler Reactivity 200.0 - --- Turtune Steam Flow 1.0 -
-- Scram Reactivity Feedwater Flow -- Total Reactivity G
ac n . ...
m e e ,
C '
v.100 0 _.__' ' 8. 0.0 -
p ',
. .- g t ,
o
( ,.
n ',
U \
., ,. ,. y \
0.0 ----,4----
- a------ cc -1.0 -
, .a , ' . * ,' e \
E g'
. . \
\
\.
-100 0 I '
- 2.0 ' '
O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 47 Plant Response to Load Reject w/o Bypass (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) FWTR-100%P/100c/cF)
Page 66
RIVER BEND Reload 6 24A5188 Rev.2 Neutron Flux Vessel Press Rise (psi)
- - - - - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 -
Core inlet Flow 300.0 - --- Relief Valve Flow f --- Bypass Valve Flow l
E 100.0 /.n
..h e 200.0
,s\s s o E W C. '.,s\ C N
~~,' ~~_
f 50 0 -
. 100.0 -
1 ~
1 0.0 O.0 I I '
O0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Level (inch-REF-SEP-SKRT) Void ReaYty
- - - - - Vessel Steam Flow - - - - - Doppler Reactivity 200.0 - --- Turtune Steam Flow 1.0 -
-- Scram Reactivity
- - - Feedwater Flow -- Total Reactivity w .
,\
sc ,
I v 100 0 g ..-
~..-
g 0.0 -,.
$ C - ---- -- . ,_____.- E C l. ,
o
- A'-
l,
..- ... E'
.a
~\ \ll 1 i 00 ',.- -!---- ------ - 1.0 -
.:. .' C \
\
1.
-100 0 O.0 I '
- 2.0 \\'
I '
3.0 60 0.0 3.0 6.0 l
Time (sec) Time (sec)
Figure 48 Plant Response to 'Ibrbine Trip w/o Bypass (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) FWTR-100%P/100%F)
Page 67
RIVER BEND
' Reload 6 24A5188 Rev. 2 Neutron Flux Vessel Press Rise (psi)
- - - - - Ave Surface Heat Flux - - - - Safety Valve Flow 150.0 - --- Core inlet Flow 300.0 - --- Relief Valve Flow
--- Bypass Valve Flow 100.0 <"'. \ -
g 200.0 g '., N g C * \
, s C
$ '. ', ~s Y
'% s
., N-50.0 -
. '- 100.0 -
00 O.0 '
O.0 5.0 10.0 0.0 5.0 10.0 Time (sec) Time (sec)
Leve8'Ach-REF-SEP-SKRT) Vod Reactivity
'.'.ssel Steam Flow ---
Doppler Reactivity 200 0 - -- - Turbine Steam Flow 1.0 - - - Scram Reactivity
Feedwater Flow - - . Total Reactivity ,.
~
g w . ,e,,.
m ,-
e .-
l e '
t 100.0 -
0.0 ,'
, _ , _ , g..,
'~'m_ _. / " l
. v,
\' ,
o .
1/
y
\g \.
.- ................ s; .
s..s- tco -1.0 0.0 -
- I
@ \ ;
C '
g .
\
\
l I
- 100.0 '
- 2.0 ' I ! '
O.0 5.0 10.0 0.0 5.0 10.0 Time (sec) Time (sec) '
Figure 49 Plant Response to Press. Regulator Failure (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) FWTR-100%P/100%F)
Page 68
RIVER BEND 24A5188 Reload 6 Rev.2 utron Flux Vessel Presc Rise (psi)
A urface Heat Fiux - - - - Safety Valve Flow 150 0 - ---. Cor inlet Flow 300.0 - --- Relief Valve Flow l --- Bypass Valve Flow
~
's
~
~'
/4 %
100.0 -
s 200.0 -
a 's a E Ts Z g - '
,' w g -
., s~~,,
50.0 -
' , , 100.0 -
ja ..
0.0 ' I O.0 i
0.0 4.0 8.0 0.0 4.0 8.0 i Time (sec) Time (sec) j a
Level (inch-REF-SEP-SKRT) Void R ~v ity
- - - - Vessel Steam Flow - - - - - Dop r Reactivi 200 0 - --- Turt)ine Steam Flow 1.0 - - - - Sc Reactivity
- - - Feedwater Flow ---
Reactivity
- G, , .*
ts 100.0 -- e w . #
C 0 .0
.\i ,'
~-
j2 ', N N. ,~ b ',\ . ,-
co ,s -
E \ .
1 ,
y
..,,, g '\, ..
\
x k 0.0 - N* . ' \
,,- _N---------< $co -1.0 - \\g\
G E \
. \
\.
\
-100.0 ' ' '
-2.0 O.0 4.0 8.0 0.0 4.0 8.0 Time (sec) Time (sec)
~
Figure 50 Plant Response to MSIV Closure (Flux Scram)
Page 69
RIVER BEND 24A5188 Reload 6 Rev.2 Appendix A l Analysis Conditions l
l To reflect actual plant parameters accurately, the values shown in Table A-1 were used this cycle.
)
Table A-1 i STANDARD Parameter Analysis Value Thermal power, MWt 2894.0 Core flow, Mlb/hr 84.5 Reactor pressure, psia 1055.0 Inlet enthalpy. BTU /lb 527.9 Non-fuel power fraction 0.039 Steam flow analysis, Mib/hr 12.46 Dome pressure, psig 1025.0 I Turbine pressure, psig 985.9 No. of Dual Mode S/R Valves 9 Relief mode lowest setpoint, psig i133.0 l Safety mode lowest setpoint, psig 1200.0 EEOC WITH ICF Parameter Analysis Value Thermal power, MWt 2894.0 Core flow, Mlb/hr 90.4 Reactor pressure, psia 1056.4 Inlet enthalpy, BTU /lb 529.3 l
Non-fuel power fraction 0.039 Steam flow analysis, Mlb/hr 12.45 !
Dome pressure, psig 1025.0 Turbine pressure, psig 985.9 No. of Dual Mode S/R Valves 9 Relicf mode lowest setpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0 Page 70
RIVER BEND 24A5188 Relord 6 Rev. 2 Appendix A Analysis Conditions (continued)
EEEOC WITH ICF AND FFWTR Parameter Analysis Value Themial power, MWt 2894.0 Core flow, Mlb/hr 90.4 Reactor pressure, psia 1055.1 Inlet enthalpy, BTU /lb 519.0 Non-fuel power fraction 0.039 Steam flow analysis, Mib/hr 11.00 Dome pressure, psig 1025.0 Turbine pressure, psig 994.7 -
No. of Dual Mode S/R Valves 9 Relief mode lowest setpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0 FWTR-100%P/100%F Parameter Analysis Value Thermal power MWt 2894.0 Core flow, Mlb/hr 84.5 Reactor pressure, psia 1053.9 Inlet enthalpy, BTU /lb 516.8 Non-fuel power fraction 0.039 Steam flow analysis, Mlb/hr 11.00 Dome pressure, psig 1025.0 Turbine pressure, psig 994.7 No. of Dual Mode S/R Valves 9 Relief mode lowest setpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0 Page 71
RIVER BEND 24A5188 Reload 6 Rev.2 Appendix A Analysis Conditions (continued)
STANDARD-HALING Parameter Analysis Value Thermal power, MWt 2894.0 Core flow, Mlb/hr 84.5 Reactor pressure, psia 1055.0 Inlet enthalpy, BTU /lb 527.9 Non-fuel power fractica 0.039 Steam flow analysis, Mlb/hr 12.46 j
Dome pressure, psig 1025.0 Turbine pressure, psig 985.9 No. of Dual Mode S/R Valves 9 Relief mode lowest setpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0 EEOC WITH ICF- HALING Parameter Analysis Value Thermal power, MWt 2894.0 Core flow, Mlb/hr 90.4 Reactor pressure, psia 1056.4 Inlet enthalpy, BTU /lb 529.3 Non-fuel power fraction 0.039 Steam flow analysis, Mlb/hr 12.45 Dome pressure, psig 1025.0 Turbine pressure, psig 985.9 No. of Dual Mode S/R Valves 9 Relief mode !owest setpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0 Page 72 i
i RIVER BEND 24A5188 Reload 6 Rev.2 Appendix A Analysis Conditions l (continued) l EEEOC WITH ICF AND FFWTR HALING Parameter Analysis Value Thermal power, MWt 2894.0 Core flow, Mlb/hr 90.4 Reactor pressure, psia 1055.1 Inlet enthalpy, BTU /lb 519.0 Non-fuel power fraction 0.039 Steam flow analysis, Mlb/hr 11.00 Dome pressure, psig 1025.0 Turbine pressure, psig 994.7 No. of Dual Mode S/R Valves 9 Relief mode lowest setpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0 EOC WITH FFWTR HALING-100%P/100%F Parameter Analysis Value Thermal power, MWt 2894.0 Core flow, Mib/hr 84.5 Reactor pressure, psia 1053.9 Inlet enthalpy, BTU /lb 516.8 Non-fuel power fraction 0.039 Steam flow analysis, Mlb/hr i1.00 Dome pressure, psig 1025.0 Turbine pressure, psig 994.7 No. of Dual Mode S/R Valves 9 Relief mode lowest setpoint, psig i133.0 Safety mode lowest setpoint, psig 1200.0 Page 73
RIVER BEND 24A5188 Reload 6 Rev.2 Appendix A Analysis Conditions (continued) 1 STANDARD-MOC Parameter Analysis Value Thermal power, MWt 2894.0 Core flow, Mlb/hr 84.5 Reactor pressure, psia 1055.0 Inlet enthalpy, BTU /lb 527.9 Non-fuel power fraction 0.039 Steam flow analysis, Mlb/hr 12.46 Dome pressure, psig 1025.0 I Turbine pressure, psig 985.9 No. of Dual Mode S/R Valves 9 Relief mode lowest setpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0 MOC WITH ICF Parameter Analysis Value Thermal power, MWt 2894.0 Core flow, Mlb/hr 90.4 Reactor pressure, psia 1056.4 Inlet enthalpy, BTU /lb 529.3 Non-fuel power fraction 0.039 Steam flow analysis, Mlb/hr 12.45 Dome pressure, psig 1025.0 Turbine pressure, psig 985.9 No. of Dual Mode S/R Valves 9 Relief mode lowest setpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0
~
Page 74
l RIVER BENT 24A5188 !
Reload 6 Rev.2 l I
Appendix A Analysis Conditions l
(continued)
MOC-FWHOOS with ICF Parameter Analysis Value Thermal power, MWt 2894.0 Core flow, Mlb/hr 90.4 Reactor pressure, psia 1055.1 Inlet enthalpy, BTU /lb 519.0 Non-fuel power fraction 0.039 Steam flow analysis, Mlb/hr 11.00 Dome pressure, psig 1025.0 Turbine pressure, psig 904.7 No. of Dual Mode S/R Valves 9 Relief mode lowest setpoint, psig 1133.0 !
Safety mode lowest setpoint, psig 1200.0 MOC-FWTR 100%P/100%F Parameter Analysis Value Thermal power, MWt 2894.0 Core flow, Mlb/hr -
84.5 Reactor pressure, psia 1053.9 Inlet enthalpy, BTU /lb 516.8 Non-fuel power fraction 0.039 Steam flow analysis, Mlb/hr 11.00 Dome pressure, psig 1025.0 Turbine pressure, psig 994.7 No. of Dual Mode S/R Valves 9 Relief mode lowest setpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0 Page 75
RIVER BEND l 24A5188 t Reload 6 Rev.2 l
1 Appendix B l Alternate Analysis for Feedwater Temperature Reduction To provide for improved operating flexibility and cycle extension for Cycle 7, expanded operating domain r_nalyses were performed for Increased Core Flow (ICF) at 107% rated and intermittent use of Final Feedwater Temperature Reduction (FFWTR) to a temperature (at full power) of 320 degrees F. The analyses for cycle extension with ICF were performed at EEOC78 exposure point using appropriate thermal hydraulic condi-tions. The analyses for cycle extension with ICF and FFWTR was performed at EEEOC79 exposure point achieved with ICF and FFWTR using the appropriate thermal hydraulic conditions. Contained in this license submittal are results of all analyses evaluated for this licensing activity. The transient MCPR values for all analyses are given in Section i1. The analyses for ICF and FFWTR bound the intermittent concurrent use of FFWTR from BOC to EEEOC operation with ICF and FFWTR.
l The Final Feedwater Temperature Reduction (FFWTR) extension flexibility option cannot be exercised until the GE Nuclear Service organization has completed their work and evaluation.
1
- 8. EEOC7 identifies the rated power operation eaposure point ariainable using ICF only. For Cycle 7 the core average exposure for EEOC7 is 26.476 mwd /Mll).
- 9. EEEOC7 idennfies the rated power operation exposure point attainable. using ICF and FTWTR. For Cycle 7 the core average exposure for EEEOC7 is 27.133 mwd /MTU Page 76
1 RIVER BEND 24A5188 Reload 6 Rev. 2 l
l 1
Appendix C '
Basis for Analysis of Loss-of-Feedwater Heater Event The loss-of-feedwater heating event was analyzed at 102% rated power using the BWR Simulator Code (Reference B-1). The use of this code is permitted in GESTAR II (Reference B-2). The transient plots, neutton flux and heat flux values normally reported in Section 9 are not an output of the BWR Simulator Code; therefore, these items are not included in this document.
l
References:
I B-1. Steady-State Nuclear Methods NEDE-30130-P-A, and NEDO-30130-A, April 1985. j B-2. General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A (latest approved version).
i
)
l l
Page 77
)
RIVER BEND 24A5188 Reload 6 Rev.2
- Appendix D Basis for Analysis of Core-Wide and Overpressurization Transients The Core-Wide and Overpressurization Transients were analyzed with four valves out of sixteen operable in relief mode and five valves out of sixteen operable in safety mode. The seven inoperable S/RV's are appli-
' cable only to the Vessel Overpressure ASME Code Compliance upset condition and fuel thermal performance criteria. The analyses performed reflect the River Bend Station Technical Specifications, which permit operation with 4 valves in relief mode and 5 valves in safety (spring) mode.
J In addition , the core-wide pressurization transients and overpressurization transients were evaluated with
' new opening setpoints on the S/RV's. The GE Nuclear Services analysis is still not complete and these set i points cannot be implemented until such time as their evaluation has been completed. I l
l l
1 4
Page 78
RIVER BEND 24A5188 Reload 6 Rev.2 Appendix E Basis for Analysis of Loss-of-Coolant Accident i
1 j
i The gel 1 MAPLHGR's for Cycle 7 have been generated assuming a MCPR of 21.28 and a diesel startup time of 10 seconds, which is the same as the FS Ak basis. By having generated the gel l MAPLHGR's with the above assumptions the potentially lower OLMCPR MOC points reported in this submittal are not applicable until further analyses are performed or SAFER /GESTR is implemented.
1 l
l l
1 l
i
~
Page 79
RIVER BEND 24A5188 Relood 6 Rev.2 Appendix F Basis for Analysis of Standby Liquid Control System Shutdown Capability The minimum required boron shutdown margin is dependent on the fuel design type and the calculational method. The minimum required boron shutdown margin represents the biases and uncertainties needed to assure subcriticality. This is a GE recommended value and may be less restrictive than the River Bend specific technical specifications requirement for the liquid boron shutdown margin, in which case the technical speci-fication value shall be used. For the analysis reported in this Supplemental Reload Licensing Submittal fuel specific borated libraries were generated using lattice physics methods at 160 deg. C and 724 ppm boron.
A boron concentration of 724 ppm boron at 160 deg. C is equivalent to 660 ppm boron at 20 deg. C resulting from the change in water density and inventory. The margin requirements to satisfy for this method with Gell in the core is 1.4%
l l
Page 80
RIVER BEND Reload 6 24A5188 Rev. 2 Appendix G Plant Operation Above the Rated Load Line Up to Rated Power For River Bend Station, Reload 6/ Cycle 7 analyses have been performed in addition to the standard reload analyses to support operation in the extended operation region. The consequences of the AOO's have been evaluated to determine if operating limits reported in Section 11 are bounding for operation in the extended operating range. The analyses were performed at 1007e power and 91% flow with both normal feedwater temperature and reduced feedwater temperature. The results of the calculations are reported below and are bounded by the OLMCPR operating limits for exposure ranges BOC7 to EEOC7 and BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) reported in Section 11.
Exposure range: BOC7 to EOC71009eP/91 */eF Exposure point: EOC7 Gell GE8x8EB !
FW Controller Failure 1.28 nc* l Load Reject w/o Bypass 1.30 nc Turbine Trip w/o Bypass 1.28 ne l Press. Regulator Failure 1.20 nc Exposure range: BOC7 to EOC71007 P/91 r/eF 320 Deg. F Exposure point: EOC7 i
Gell GE8x8EB I FW Controller Failure 1.28 nc Load Reject w/o Bypass 1.28 nc 1
Turbine Trip w/o Bypass 1.27 nc !
Press. Regulator Failure 1.21 ne l
- RC a not Calcu lated Page 81
, RIVER BEND 24A5188 Reload 6 Rev.2 l
l Appendix G (continued) l l
Plant Operation Above the Rated Load Line Up to Rated Power l
l Exposure range: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100%P91% F E.xposure point: EOC7-3693 mwd /MT (3350 mwd /ST)
GEi1 GE8x8EB FW Controller Failure 1.21 nc*
, Load Reject w/o Bypass 1.23 nc Torbine Trip w/o Bypass 1.22 nc
, Press. Regulator Failure 1.17 nc Exposure range: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100%PSl%F 320 Deg.F.
Exposure point: EOC7-3693 mwd /MT (3350 mwd /ST)
- Gell GE8x8EB N Controller Failure 1.19 nc 4
' Load Reject w/o Bypass 1.20 nc Turbine Trip w/o Bypass 1.18 nc Press. Regulator Failure 1.17 nc ,
l
- nc = not calculated I
Page 82
-.. . . - - _ . - . ._ . _ - . - _ - . _ ~ . - . - . - - . _ . . - . . - - - . . - . . . . . . .
l l RIVER BEM 24A5188 l Reload 6 Rev.2 l
Append!x H Off Rated MCPRp and MCPRf Curves l
BOC to EOC-3350 MWD /ST ,
1.8 (30.0.1.735)
_ l I
1.6 -
(40.0.1.608) 1.5 -
E '
b 2
1.4 -
13 -
GE11 (84.92,1.28) =
'. ......... GE8 (89.03,1.25) 1.2 ' ' ' ' l ' ' ' I ' ' ' ' ' ' ' I ' I '
OO 10.0 20.0 30.0 40.0 o0.0 60.0 70.0 80.0 90.0 100.0 110.0 Core Flow (W), % of Rated Core Flow l
j_
Figure 51 Operating Limit MCPR (MCPRf) Versus Core Flow (BOC to EOC-3350 MWD /ST)
Page 83
RIVER BEND 24A5188 Reload 6 Rev.2 i
i i
Appendix H (Continued) i Off Rated MCPRp and MCPRf Curves l
BOC to EOC-3350 MWD /ST
} 1.8 i
} (40.0,1.758) l 1.7 -
i j 1.6 -
(40.0.1.614)
I 4 i
- 1.5 -
l q (70.0.1.491) -
E -
O 2 .
1.4 -
(70.0.1.357) .
i-1.3 - GE11 g (89.47,1.28) .
' . G.E8 (97.06,1.25) 6 I 1.2 . I . f . f , f , I . I , I f .
0.0 10 0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 Thermal Power, % of Rated Thermal Power Figure 52 Operating Limit MCPR (MCPRp) Versus Core Power (BOC to EOC-3350 MWD /ST)
Page 84
. - . . .- - -- .. . . . - . . . . . . . - - . _ -._ . - . _ . - ~ - - . .
. RIVER BEND 24A5188
] Reload 6 Rev.2 l Appendix H (Continued) i Off Rated MCPRp and MCPRf Curves d
l 1
EOC-3350 MWD /ST to EEOC i d
1.8 (30.0.1.735) ,
1.7 -
i
~
(40.0,1.608) 1.5 -
2 Q. -
O !
2 1.4 -
L GE11 1.3 -
(79.44,1.32) *.
', GE8 (89.03,1.25)
' ' ' I '
1.2 ' ' I I ' l ' I ' ' l ' I '
OO 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 Core Flow (W), % of Rated Core Flow Figure 53 Operating Limit MCPR (MCPRf) Versus Core Flow (EOC-3350 MWD /ST to EEOC)
Page 85
RIVER BEND 24A5188 Reload 6 Rev.2 i
4
?
Appendix H (Continued)
Off Rated MCPRp and MCPRf Curves 4 1 i \
! (
! EOC-3350 MWD /ST to EEOC l ,
1.8
- (40.0,1.758) ,
1.7 -
I t
b (40.0,1.614)
I i -
l 1.5 -
(70.0,1.491)
E -
0 2
1.4 -
(70.0,1.357) 1.3 -
(79.36,1.32) ' . , ,
'., GE8 (97.06,1.25) 1.2 ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' '
O.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 Thermal Power, % of Rated Thermal Power Figure 54 Operating Limit MCPR (MCPRp) Versus Core Power (EOC-3350 MWD /ST to EEOC)
I Page 86 i