Text

Rev 0 to J1103150SRLR, Supplemental Reload Licensing Rept for Rbs,Reload 7,Cycle 8
	ML20212A729
Person / Time
Site:	River Bend
Issue date:	07/31/1997
From:	Reda R, Tuttle J; GENERAL ELECTRIC CO.
To:	;
Shared Package
ML20212A720	List: ML20212A722; ML20212A729; ML20212A736; ML20212A740; RBG-44252, Forwards Rev 0 to RBS Cycle 8 COLR & Rev 2 to RBS Cycle 7 COLR, Submitted IAW TS 5.6.5 of App a of Fol.General Electric Supplemental Reload Licensing Repts,Also Encl;
References
	J1103150SRLR, J1103150SRLR-R, J1103150SRLR-R00, NUDOCS 9710240217
	Download: ML20212A729 (121)
	v • d • e

.

GE Nuclear Energy J1103150SRLR Revision 0 Class !

July 1997 i

a J1103150SRLR, Rev. 0 Supplemental Reload Licensing Report i

for

}

River Bend Station l

Reload 7 Cycle 8 i

0

/

1A Approved Y'

Approved

/ - [e.<.t<

R.J.Reda, Manager J. L. Tuttle Fuel and Facility Licensing Fuel Project Manager t

4 9710240217 971017 DR ADOCK 050004 8

(IVER 3END Jl103150SRLR Reload 1 Nev. 0 Important Notice Regarding Contents of This Report Please Read CareMly This report was prepared by General Electric Company (GE) solely for Entergy Opera-tions, Inc. (EOI) for EOl's use with the U. S. Nuclear Regulatory Commission (USNRC) for amending EOl's operating license of the River Bond 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 Bond 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 infringe privately owned rights; nor do they assume any rc%nsibility for liability or damage of any kind which may result from such use of such Imunnation.

4 Page 2

)

{ER 5END J1103150g Acknowledgement I

ne engineering and reload licensing analyses, which form the technical basis of this Supplemental Reload Licensing Report, were performed by W.E. Russell. The Supplemental Reload Licensing Report was pre-pared by W.E. Russell, nis document has been verified by E.W.Gibbs.

Page 3

UVER BEND Jil03160SRLR teload 7 Reyu0 The basis for this seport is General Electric Standard Applicationfor Reactor Furl, NEDE-24011 ~P-A-13, August 1996; and the U.S. Supplement, NEDE-240ll-P-A-13-US, August 1996, 1.

Plant-unique llems Appendix A: Analysis Conditions Appendix B: Altemate Analysis for Feedwater Temperature Reduction Appendix C: Basis for Analysis of Loss-of-Feedwater lleater Event Appendix D: Basis for Analysis of Core Wide and Overpressurization Transients Appendix E: Basis for Analysis of Standby Liquid Control System Shutdown Capability Appendix F: Off Rated MCPR and LllGR Multiplier Curves Appendix G: River Bend Cycle 8 Rated OLMCPR Summary 2.

Reload Fuel Bundles Cycle Fuel Type Loaded Number Irrmmtei G E8 B-P85Q B 334-1007.2-120M-4 WR-150-T (G E8 x 8 EB )

6 124 GE8 B-P8SQB 334-i l GZ-120M-4 WR-150-T (GE8 x 8 EB) 6 56 G E l 1 -P9S U B 354-14 GZ-120T-146-T (G E l 1 )

7 40 G E l l-P95 UB 354-130Z-120T-146-T (G E l 1 )

7 64 l

G E l l-P9S UB 353-10GZ-120T-146-T (G E l 1 )

7 128 Nas G E l l-P9S UB 360-120Z-120T-146-T (G E l 1 )

S 64 l

GE l l-P9S UB 386-120Z-120T-146-T (G E l l )

8 148 Total 624 l

3.

Reference Core Loading Pattern Nominal previous cycle core average exposure at end of cycle:

27645 mwd /MT

( 25079 mwd /ST)

Minimum previous cyc!c core average exposure at end of cycle 27141 mwd /MT from cold shutdown considerations:

( 24622 mwd /ST)

Assumed reload cycle core average exposore at beginning of 15013 mwd /MT cycle:

( 13619 mwd /ST)

Assumed reload cycle core average exposure at end of cycle:

28593 mwd /MT

( 25939 mwd /ST)

Reference core loading pattern:

Figure i Page 4

AN5o 3" 3 Ta 4.

Calculated Cost Effective Multiplication and Control System Worth - No Volds,20'C Beginning of Cycle, kennuo Uncontrolled 1.118 Fully controlled 0.953 Strongest control rod out 0.987 R. Maximum increase in cold core reactivity with exposure into cycle. Ak 0.000 5.

Standby L.lquid Control System Shutdown Capability Boron Shutdown Margin (Ak)

(ppm)

(20*C, Xenon Free) 660 0.0260 6.

Reload Unique GETAB Anticipated Operational Occurrences (ADO) Analysis Inlllal Condition Parameters Exposure: HOC 8 to EOC8 HBB Peaking Factors

~

Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt)

(1000 IMr)

GEli 1.45 1.37 1.35 1.035 6.212 Ii1.9 1.31 GE8x8EB 1.20 1.46 1.40 1.051 6.603 111.4 1.21 Exposures BOC8 to EOC8 FWHOOS - HBB Peaking Factors Fuel Bundle Bundle Initial Design I m al Radial Axial R-Factor Power Flow MCPR (MWt)

(1000 lMr) gel 1 1.45 1.43 1.35 1.035 6.460 110.8 1,29 GE8x8EB l'.20 1.50 1.40 1.051 6.765 110.3 1.21 Exposure BOC8 to EOC8 ICF - HBD Peaking Factors Fuel Bundle Bundle initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt)

(1000 IMr)

Gell 1.45 1.37 1.36 1.035 6.215 120.6 1.32 GE8x8EB 1.20 1.45 1.40 1.051 6.594 120.3 1.23 Page5

I (IVER BEND J1103150SRLR

<eload 7 Rev.0 Exposure: ROC 8 to EOC8 ICF & FWTR -IIHH Peaking Factors Fuel Bundle Hundle initial Design Local Radial Axlal R-Factor Power Flow MCPR (MWt)

(1000 lMr)

Gell 1.45 1.44 1.36 1.035 6.503 119.1 1.29 GE8x5EB 1.20 1.50 1.40 1.051 6.805 118.9 1.22 Exposure: BOC8 to EOC8 MELLL-HBB i

Peaking Factors Fuel Bundle Hundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt)

(1000 lMr)

Gell 1.45 1.34 1.31 1.035 6.078 82.5 1.25 2

GE8x8EB 1.20 1.42 1.40 1.051 6.448 81.8 1.15 Exposure: HOC 8 to EOC8 MELLL & FWHOOS - HHB Peaking Factors Fuel Bundle Bundle initial Design Local Radial Axlal R-Factor Power Flow MCPR (MWt)

(10001%r)

]

gel 1 1.45 1.37 1.33 1.035 6.165 82.5 1.26 GE8x8EB 1.20 1.44 1.40 1.051 6.516 81.4 1.18 Exposure: HOC 8 to EOC8 HALING Peaking Factors Fuel Bundle Hundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWI)

(10001%r)

GEli 1.45 1,49 1.20 1.035 6.736 107.2 1.27 GE8x8EB l.20 1,53 1.40 1.051 6.928 109.3 1.15 Exposurt: BOC8 to EOC8 FWHOOS - HALING Peaking Factoss Fuel Bundle Bundle initial Design Local Radial Axlal R-Factor Power Flow MCPR (MWt)

(10001%r) gel 1 1.45 1.52 1.23 1.035 6.869 106.6 1.27 GE8x8EB 1.20 1,53 1.40 1.051 6.922 109.3 1.18 Page 6 4

(IVER BEND J1103150SRLR teload 7 Rev.0 Exposure: BOC8 to EOC8 ICF-HALING Peaking Factors Fuel Bundle Bundle initial Design Local Radial Axlai R-Factor Power Flow MCPR

( M W t)

(1000 lMr)

Gell 1.45 1.49 1.20 1.035 6.741 115.7 1.29 GE8x8EB 1.20 1.53 1.40 1.051 6.924 118.0 1.17 Exposure: HOC 8 to EOC8 ICF & F%TR HALING Peaking Factors Fuel Bundle Bundle initial Design Local Radial Axlal R-Factor Power Flow MCPR (MWt)

(1000 IMr) gel 1 1.45 1.52 1.24 1.035 6.858 115.2 1.29 GE8x8EB 1.20 1.56 1.40 1.051 7.076 117.0 1.17 Exposure: BOC8 to EOC8 MELLL-HALING Peaking Factors Fuel Bundle Bundle initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt)

(1000 IMr) gel 1 1.45 131 1.25 1.035 6.356 80.3 1.23 GE8x8EB 1.20 1.45 1.40 1.051 6.555 81.2 1.13 Exposure: HOC'8 to EOC8 MELLL & FWHOOS - HALING Peaking Factors Fuel Bundle Bundle inliial Design Local Radial Atlal R-Factor Power Flow MCPR

( M W t)

(1000 IMr) gel 1 1.45 1.44 1.22 1.035 6.506 79.6 1.23 GE8x8EB 1.20 1.45 1.40 1.051 6.548 81.2 1.17 Exposure: BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) HBB Peaking Factors Fuel Bundle Bundle lattial Design Local Radial Axial R-Factor Power Flow MCPR (MWt)

(1000 IMr)

GEli 1.45 1.47 1.33 1.035 6.659 107.8 1.27 GE8x8EB 1.20 1.52 1.40 1.051 6.872 109.6 1.16 Page 7

UVER BEND J1103150SRLR

<eload 7 Rev. 9 Exposure: BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) FWHOOS - HBB 1

Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt)

(1000 IMr) gel 1 1.45 1.53 1.39 1.035

6.901 106.1 1.26 GE8x8EB 1.20 1.56 1.40 1.051 7.073 108.2 1.16 i

Exposure: HOC 8 to EOC8-2006 mwd /MT (1820 mwd /ST) ICF - HBB Peaking Factors Fuel Bundle Bundle initial Design Local Radial Axlai R-Factor Power Flow MCPR (MWt)

(10001%r)

Gell 1.45 1.49 1.34 1.035 6.731 115.6 1.28 GE8x8EB 1.20 i.52 1.40 1.051 6.906 118.2 1.17 Exposure: BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) ICF & FWTR -HBB Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt)

(1000 IMr)

GEli 1.45 1.55 1.40 1.035 7.009 113.8 1.26 GEEx8EB 1.20 1.58 1.40 1.051 7.129 116.6 1.16 Exposure: BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) MELLL - HBB Peaking Factors Fuel Bundle Bundle initial Design Local Radial Axlal R-Factor Power Flow MCPR (MWt)

(1000 IMr) gel 1 1.45 1.40 1.29 1.035 6.321 80.7 1.22 GE8x8EB 1.20 1.41 1.40 1.051 6.534 81.3 1.14 Exposure: BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) MELLL & FWHOOS - HBB Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axlal R-Factor Power Flow MCPR (MWt)

(10001%r)

Gell 1.45 1.45 1.33 1.035 6.539 79.3 1.22 GE8x8EB 1.20 1.45 1.40 1.051 6.542 81.2 1.17 Page 8 i

UVER BEND JI103150SRLR teload 7 Rev, 0 7.

Selected Margin Improvement Options Recirculation pump trip:

Yes Rod withdrawallimiter:

Yes Thermal power monitor:

Yes Improved scram time:

No 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:

107.0 %

Increased core flow at EOC:

Yes Feedwater temperature reduction throughout cycle:

Yes-Temperature reduction:

100.0'F Final feedwater temperature reduction:

Yes ARTS Program:

No Maximum extended operating domain:

Yes Moisture separator reheater OOS:

No Tbrbine bypass system OOS:

No Safety / relief valves 005:

Yes(See Appendix D)

ADS OOS:

No EOC RPT OOS:

No Main steam isolation valves OOS:

No Feedwater Heater OOS:

Yes s

Page 9

' lVER BEND J1103150SRLR l

teload 7 Rev.0 9.

Cort-wide ADO Analysis Results Methods used: GEMIN!; GEXL-PLUS Exposure range BOC8 to EOC8 IIHH Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NHR)

(%NBR)

FW Controller Failure 277 112 0.15 0.07 2

Load Reject w/o Bypass 364 114 0.17 0.08 3

hrbine Trip w/o Bypass 326 110 0.16 0.06 4

Press. Regulator Failure 149 105 0.09 0.05 5

Exposure range HOC 8 to EOC8 FWHOOS-IIBB Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NHR)

(%NBR)

FW Controller Failure 270 115 0.16 0.09 6

Load Reject w/o Bypass 340 113 0.16 0.07 7

hrbine Trip w/o Bypass 296 110 0.14 0.05 8

Press. Regulator Failure 157 107 0.10 0.05 9

Exposure range HOC 8 to EOC8 ICF-IIHB Uncorrected ACPR Event Flux Q/A Gell GE8x8EH Fig.

(%NBR)

(%NHR)

FW Controller Failure -

319 114 0.16 0.08 10 Load I" ject w/o Bypass 412 116 0.19 0.10 11 hrbine Trip w/o Bypass 381 113 0.16 0.07 12 Press. Regulator Failure 150 106 0.09 0.05 13 Exposure range BOC8 to EOC8 ICF & FWTR-lIBH Uncorrected ACPR Event Flux Q/A Gell GE8x8EH Fig.

(%NBR)

FW Controller Failure 285 117 0.16 0.09 14 Load Reject w/o Bypass 3*7 114 0.16 0.08 15 hrbine Trip w/o Bypass 315 111 0.14 0.06 16 IYess. Regulator Failure 158 107 0.11 0.%

17 Page 10

g p END J1103150g Exposure ranger BOC8 to EOC8 MELLL-HBB Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR)

FW controller Failure 166 104 0.10 0.03 18 Load Reject w/o Bypass 213 104 0.12 0.03 19 hrbine Trip w/o Bypass 183 101 0.10 0.01 20 Press. Regulator Failure 144 104 0.07 0.03 21 Exposure range HOC 8 to EOC8 MELLL & FWHOOS - HBB Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR)

FW CoNroller Failure 205 109 0.12 0.05 22 Load Reject w/o Bypass 251 108 0.13 0.04 23 hrbine Trip w/o Bypass 217 104 0.11 0.02 24 Press. Regulator Failure 155 105 0.09 0.04 25 Exposurt range BOC8 to EOC8 HALING Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR)

(%NDR)

FW Controller Failurc 162 104 0.12 0.03 26 Load Reject w/o Bypass 217 105 0.14 0.02 27 hrbine Trip w/o Bypass 189 102 0.13 0.00 28 Press. Regulator Failure 145 104 0.07 0.03 29 Exposure ranger BOC8 to EOC8 FWHOOS - HALING Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR)

FW Controller Failure 173 108 0.14 0.06 30 Load Reject w/o Bypass 233 106 0.14 0.02 31 hrbine Trip w/o Bypass 192 102 0.12 0.00 32 Press. Regulator Failure 154 105 0.10 0.03 33 l

Page 11

IIVERJ1END Jl103150SRLR teload 7 Rev, 0 Exposure ranger BOC8 to EOC8 ICF-HALING Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR)

(%NilR)

~

FW Controller Failure 191 106 0.13 0.04 34 Load Reject w/o Bypass 259 107 0.16 0.04 35 Turbine Trip w/o Bypass 224 104 0.14 0.02 36 Prvss. Regulator Failure 146 104 0.08 0.03 37 Exposure range BOC8 to EOC8 ICF & FWTR IIALING Uncorrected ACPR Event Flex Q/A Gell GE8x8EB Fig.

(%NBR)

('TrNBR)

IM Controller Failure 197 109 0.13 0.06 38 Load Reject w/o Bypass 263 108 0.15 0.04 39 Turbine Trip w/o Dypass 216 104 0.13 0.01 40 Press. Regulator Failure 154 105 0.11 0.04 41 Exposure range: BOC8 to EOC8 MELLL-HALING Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR)

FW Controller Failure 109 104 0.09 0.03 42 Load Reject w/o Bypass 142 100 0.10 0.00 43 hrbine Trip w/o Bypass 120 100 0.08 0.00 44 Press. Regulator Failure 144 103 0.06 0.02 45 Exposure range: HOC 8 to EOC3 MELLL & FWHOOS - HALING Uncorrected ACPR Event Flux Q/A Gell GE8x8Eli Fig.

(%NBR)

FW Controller Failure 117 106 0.10 0.04 46 Load Reject w/o Bypass 151 100 0.09 0.00 47 hrbine Trip w/o Bypass 126 100 0.08 0.00 48 Press. Regulator Failure 152 104 0.09 0.02 49 Page 12

(IVER BEND J1103150SRLR teload 7 Rev.O Exposure ranger BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) HBB Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR)

FW Controller Failure 183 IN 0.11 0.03 50 Load Reject w/o Bypass 268 106 0.14 0.03 51 l

hrbine Trip w/o Bypass 213 103 0.11 0.00 52 Press. Regulator Failure 146 IN 0.%

0.03 53 l

Exposure range BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) FWHOOS - HBB Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR)

FW Controller Failure 172 108 0.12 0.06 54 Load Reject w/o Bypass 243 106 0.13 0.02 55 brbine Trip w/o Bypass 191 102 0.10 0.00 56 Press. Regulator Failure 154 105 0.07 0.03 57 Exposure ranges BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) ICF - HBB Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR)

FW Controller Failure 202 106 0.12 0.04 58 Load Reject w/o Bypass 298 108 0.15 0.N 59 hrbine Trip w/o Bypass 238 104 0.13 0.01 60 Press. Regulator Failure 147 104 0.%

0.03 61 Exposure range BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) ICF & FWTR 'Id8 Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR)

FW Controller Failure 184 109 0.13 0.06 62 Load Reject w/o Bypass 257 107 0.13 0.03 63 hrbine Trip w/o Bypass 205 103 0.11 0.00 64 Press. Regulator Failure 154 105 0.08 0.04 65 Page 13

UVER BEND J1103150SRLR teload 7 Rev,O Exposure range BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) MELLL - HBB Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR)

FW Controller Failure 130 104 0.08 0.03 66 Load Reject w/o Bypass 170 101 0.09 0.00 67 Turbine Trip w/o Bypass 144 100 0.07 0.00 68 Press, Regulator Failure 144 104 0.%

0.03 69 Exposure e.ge BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) MELLL & FWHOOS - HBB Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR)

FW Controller Failure 127 106 0.09 0.04 70 Load Reject w/o Bypass 165 100 0.09 0.00 71 hrbine Trip w/o Bypass 134 100 0.07 0.00 72 Press. Regulator Failure 152 104 0.07 0.02 73

10. Local Rod Withdrawal Error (With Limiting Instrument Failure) ADO Summary The generic bounding BWR/6 rod withdrawal error analysis described in NFDE-240ll-P-A-US is applied,,

A cycle specific rod withdrawal analysis was found to be 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. Smit:.to the Document Control Desk.10CFR Part 21, Reportable Condition, Safety Limit MCPR Evaluation, May 24,19%) a cycle-speciCnc Sniety Limit MCP." alcuLition was performed, and has been reported in both the Safety Limit MCPR and the Operating 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.

l

3) The full cycle exposure range was analyzed, I. For single-kop operation, the MCPR operating linut is 0 01 greater than the two-loop talue.

l l

l Page 14

(IVER BEND J1103150SRLR (eload 7 Rev.0 Safety limit:

1.13 Single loop operation safety limit:

1.14 Non-attuurlaation eventst Exposure Ranger BOC8 to EOC8 Gell GE8x8EB Fuel Loading Error (Mislocated) 1.28 1.28 Fuel Loading Error (Rotated) 1.26 Rod Withdrawal Error 1.25 1.25 Loss of Feedwater Heating 1.26 1.26 Pressurization events:

Exposure ranger BOC8 to EOC8 HBB Exposure point: EOC8 Option A l

Gell GE8x8EB FW Controller Failure 1.30 1.21 Load Reject w/o Bypass 1.32 1.22 lbrbine Trip w/o Bypass 1.30 1.20 Press. Regulator Failure 1.23 1.18 Exposure range: BOC8 to EOC8 FWHOOS - HBB Exp.sure point: EOC8 Option A Gell GE8x8EB FW Controller Failure 1.30 1.23 Load Reject w/o Bypass 1,30 1.21 lbrbine Trip w/o Bypass 1.28 1.19 Press. Regulator Failure 1.25 1.19 Page 15

(IVER BEND J1103150SRLR teload 7 Rev.O Exposure ranger BOC8 to EOC8 ICF-HBB Exposure point EOC8 Option A Gell GE8s8EB FW Controller F'ailure 1.31 1.22 Load Reject w/o Bypass 1.33 1.24 hrbine Trip w/o Bypass 1.31 1.21 Press. Regulator Failure 1.24 1.19 Exposurt ranger BOC8 to EOC8 ICF & FWTR -HBB Exposure point EOC8 Option A Gell GE8x8EB

~

FW Controller Failure 1.31 1.24 Load Reject w/o Bypass 1.30 1.22 hrbine Trip w/o Bypass 1.28 1.19 Press. Regulator Failure

. 26 1.20 Exposure ran8e BOC8 to EOC8 MELLL-HBB Exposure point: EOC8 Option A Gell GE8x8EB FW Controller Failure 1.25 1.17 Load Reject w/o Bypass 1.26 1.16 hrbine Trip w/o Bypass 1.24 1.15 Press. Regulator Failure 1.21 1.17 Exposure range: BOC8 to EOC8 MELLL & FWHOOS - HBB l

Exposure point: EOC8 Option A Gell GE8x8EB FW Controller Failure 1.27 1.19

. cad Reject w/o Bypass 1.27 1.18 hrbine Trip w/o Bypass 1.25 1.16

~

Press. Regulator Failure 1.24 1.18 Page 16

UVER END J1103150kRLR (eload ev. 0 Expecure range: HOC 8 to EOC8 HALING Exposure point EOC8 Option A Gell GE8x8EH

~

IM Controller Failure 1.26 1.17 Load Reject w/o Bypass 1.29 1.16 hrbine Trip w/o Bypass 1.27 1.14 Press. R'egulator Failure 1.21 1.17 Exposure range BOC8 to EOC8 FWHOOS - HALING Exposure point: EOC8 Option A Gell GE8x8EB IM Controller Failure 1.28 1.20 Load Reject w/o Bypass 1.28 1.16 hrbine Trip w/o Bypass 1.26 1.14 Press. Regulator Failure 1.24 1.17 Exposure range: HOC 8 to EOC8 ICF - HALING Exposure point: EOC8 Option A Gell GE8x8EB FW Controller Failure 1.28 1.16 Load Reject w/o Bypass 1.30 1.17 hrbine Trip w/o Bypass 1.29 1.15 Iwss Regulator Failure 1.22 1.17 Exposure range HOC 8 to EOC8 ICF & FWTR HALING Exposure point: EOC8 Option A Gell GE8x8EB FW Controller Failure 1.30 1.20 Load Reject w/o Bypass 1.30 1.17 hrbine Trip w/o Bypass

.28 1.15 Press. Regulator Failure 1.25 1.18 Pag: 17

(IVER BEND J1103150SRLR teload 7 Rev.0 Exposum renset BOC8 to EOC8 MELLL - HALING l

Exposun point: EOC8 Option A a

Gell GE8x8EB FW Controller Failure 1.23 1.17 Load Reject w/o Bypass 1.24 1.14 Turbine Trip w/o Bypass 1.23 1.14 Press. Regulator Failure 1.20 1.16 Exposure renset BOC8 to EOC8 MELLL & FWHOOS - HALING Expcsure point EOC8 Option A Gell GE8x8EB FW Controller Failure 1.24 1.18 Load Reject w/o Bypass 1.24 1.14 hrbine Trip w/o Bypass 1.22 1.14

~

.i Press. Regulator Failure 1.23 1.16 Exposure renset BOC8 to EOCS-2006 mwd /MT (1820 mwd /ST) HBB Exposure point: EOC8-2006 mwd /MT (1820 mwd /ST)

Option A Gell GE8x8EB FW Controller Failure 1.23 Load Reject w/o Bypass 1.26 I

hrbine Trip w/o Bypass 1.23 Press. Regulator Failure 1.20 Exposure renset BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) FWHOOS - HBB Exposure point: EOC8-2006 mwd /MT (1820 mwd /ST)

Option A Gell GE8x8EB

~

FW Controller Failure 1.24

"*e

^

~

Load Reject w/o Bypass 1.24

~

Turbine Trip w/o Bypass 1 22 Press. Regulator Failure 1.22 Page la

RIVER BEND J1103150SRLR Jhload 7 Rev. O Exposure range BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) ICF - IIBB ExAure point: EOC8-2006 mwd /MT (1820 mwd /ST)

Option A Gell GE8x8EH FW boaller FaIfule 1.24 Load Re;c wh Bypriss 1.27 Wrbine Trip w/o flypass ~

1.24 Press. Regulator IUhtto 1.21

--a-Exposure ran8e BOCH to EdC8-2006 mwd /MT (1820 mwd /ST) ICF & FWTR -11HH Exposure point EOC8 2006 mwd /MT(1820 mwd /ST)

Option A Gell GE8x8EH FW Cor. troller Failure 1.25 Load Reject wEBypass 1.25 hrbine Trip w/o Bypass 1.22 Press. Regulator Failure 1.23 Exposure ranger BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) MELLL - HHB Exposure point EOC8-2006 mwd /MT (1820 mwd /ST)

Option A Gell GE8x8EH FW Controller Failure 1.22 1.17 Load Reject wlo Bypass 1.23 1.14 Tbrbine Trip w/o Bypass 1.22 1.14 Press. Regulator Fellure 1.20 1.16 Exposure range BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) MELLL & FWHOOS - HBB Exposure point: EOC8-20% mwd /MT (1820 mwd /ST)

Option A Gell GE8x8EB l

FW Controller Failure 1.21

~

l Load Reject w/o Bypass 1.20 hrbine Trip w/o Bypass 1.18

u*

l Press. Regulator Failure 1.22 l

I i

Page 19

(IVER BEND J1103150SRLR teload 7 Rev.0

12. Overpressurization Analysis Summary Psi Pv Plant Event (psig)

(psig)

Response

MSIV Closure (Flux Scram) 1274 1305 Figure 74

13. Loading Error Results Variable water gap misoriented bundle analysis: Yes2 Misoriental Fuel Bundle ACPR GE l 1 -P95UB 386-120Z-120T-146-T (GE l l) 0.12 G E l l-P9S UB 360-120Z-120T-146-T (GE l l )

0.09 Mislocated Bundle Analysis: Yes Mislocated Bundle ACPR 0.15

14. Control Rod Drop Analysis Results River Bend Station is a barked position withdrawal r.equence 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-?-A-US. River Bend Station reepgnizes the issuance of NRC Bulletin No. 88-07, Supplement 1. Power Oscilletuns in Boiling Water Reactors (BWRs), and will comply with the recommendations contained therein.

River Bend has submitted for review to the NRC the Enhaned Option I-A stability solution for use in Cycle

8. Upon NRC approval, River Bend Cycle 8 willlicensed in accordance with NEDO-32339-A Revision 1, Licensing Topical Report Reactor Stability lxng-Term Solution: Enhanced Option I-A. Reference GENE-A13-00367--46, Revision 1, River Bend Cycle 7 Reactc.r Stability long-Term Solution Enhanced Option I-A Stability Region Boundary Generation tmd Validation documents the enhanced Option I-A (El A) stability region boundaries for River Bend Cycle 7 and the analysis associated with the generation and -

validation, Flow Mapping Application Input and Flow Mapping Application Output based on the above ref-crence is the responsibility of EOI. RVM confirms best-estimate code boundary validation stability criteria in accordance with NEDO-33229-A Revision 1. Section 8.3.3 (Optional IVM Adjusted Region Boundary validation). 'Ihe River Bend Cycle 8 Option I-A stability decay ratios can be found in Figure 75.

16. Lou-et-Coolant Accident Results LOCA method used: SAFER /GESTR-LOCA The LOCA analyris results for all fuel types loaded in the current cycle are presented in Section 5 and Section 6 of Ru.ar Bend Station SAFER /GESTR-LOCA loss-of-Coolant Accident Analysis, NEDC-32640P, Junc

2. Indudes a 0 02 genalty due to vanable warer gap R-factor uneenamty.

Page 20

(IVER B31ND Jil03150SRLR (eload 7 Rev.0 1997. 'Ihese analyses yielded a licensing basis peak clad temperature (PCT) of 1300.0'F, a peak local oxida-tion fraction of <0.1%, and a core-wide metal-water reaction of <0.05%. The SLO analysis resulted in a MAPLHOR multiplier of 0.79 for Gell and 0.87 for GE8x8EB *The following table. lists the least limiting and most limiting MAPLHORs for all the Cycle 8 fuel:

16. Loss-of-Coolant Accident Results (cont)3 Bundle Type: gel 1-P95UB386-120Z-120'l-146-T i

Average Planar Exposure MAPLHGR(kW/ft)

(GWd/ST)

(GWd/MT)

Most Limiting Least Limiting 0.00 0.00 11.%

11.34 0.20 0.22 11.15 11.39 1.00 1.10 11.25 11.46

-2.00 2.20 Il.36 11.54 3.00 3.31 11,48 11.63 4.00 4.41 11.59 11.71 5.00 5.51 11.70 11.80 6.00 6.61 11.78 11.89 7.00 7.72 11.87 11.98 8.00 8.82 11.95 12.07 9.00 9.92 12.04 12.17 10.00 11.02 12.12 12.27 12.50 13.78 12.%

12.26 15.00 16.53 I1.82 11.99 17.50 19.29 Il.53 11.o6 20.00 22.05 11.22 11.34

~

25.00 27.56 10.61 10.71 30.00 33.07 10.01 10.09 35.00 38.58 9.41 9.49 40.00 44.09 8.80 8.89

~

45.00 49.60 8.17 8.28 50.00 55.12 7.51 7.63 55.00 60.63 6.82 6.95 56.67 62.46 6.58 6.72 56.69 62.49 6.71 57.15 63.00 6.65 57.22 63.07 6.64

3. For format explananon, see letter i S Chamley (GE) to M. W. Hodges (NRC), Reconymtaded MAplMGR Technical Spec @canoarfor Mulnple lamce fuel Desigru. March 9.1987. Most Linuung and 1.4ast Limitsng tefer to the lowest and highest linets respecovely, of any ennched latuce in the bundle.

Page 21 1

~

(IVER BEND J1103130SRLR teload ?

Rev.0

16. Loss-of-Coolant Accident Results (con 03 Bundle Type: gel 1-P9SUB386-120Z-120T-146-T Average Planar Esposure i

MAPLHGR(kW/ft)

(GWd/ST)

(GWd/MT)

Most Limiting Least Limiting 0.00 0.00 l1.06 11.34 0.20 0.22 11.15 11.39 1.00 1.10 11.25 11.46 2.00 2.20 11.36 11.54 3.00 3.31 11.48 11.63 4.00 4.41 11.59 11.71 5.00 5.5I i1.70 11.80 6.00 6.61 11.78 11.89 7.00 7.72 11.87 11.98 8.00 8.82 Il.95 12.07 9.00 9.92 12.04 12.17 10.00 l1.02 12.12 12.27 12.50 13.78 12.%

12.26 15.00 16.53 11.82 11.99 17.50 19.29 11.53 11.66 20.00 22.05 11.22 11.34 25.00 27.56 10.61 10.71 30.00 33.07 10.01 10.09 35.00 38.58 9.41 9.49 40.00 44.09 8.80 8.89 45.00 49.60 8.17 8.28 50.00 55.12 7.51 7.63 55.00 60.63 6.82

- 6.95 56.67 62.46 6.58 6.72 56.69 62.49 6.71 57.15 63.00 6.65 57.22 63.07 6.64 3.- For fortnet explanation. see ktier 1 S. Charnley (GE) to M. W. Hodges (NRC). Recommended MArulGR TechnicalSpec$carionsfor Mainple latrice Fuel Designs. March 9.1987. Most Linuting and Least Linuung rtfer to the lowest and highest linuts, respecuvely, of any eviched laruce in the bundle.

Page 21 m

llVER BEND J11031.50SRLR (eload 7

_,_ Rev. O i

16. Loss-of-Coolant Accident Results(contY Bundle Type: Gell-P9Sl!B360-120Zel20T-146-T Average Planer Exposure MAPLHGR(kW/ft)

(GWd/ST)

(GWd/MT)

Most Limiting Least Limiting 0.00 0.00 11.08 11.45 0.20 0.22 11.16 11.48 1.00.

1.10 11.27 11.56 2.00 2.20 11.41 11.66 3.00 3.31 11.55 11.77 4.00 4.41 11.69 11.'87 5.00 5.51 11.84 11.97 6.00 6.61 11.98 12.07

~

7.00 7.72 12.13 12.18 8.00 8.82 12.26 12.30 9.00 9.92 12.36 12.41 10,00 11.02 12.46 12.55 12.50 13.78 12.45 12.58 15.00 16.53 12.10 12.19 17.50 19,29 11.70 11.89 20.00 22.05 11.32 11.54 25.00 27.56 10.57 10.82 30.00 33.07 9.86 10.09 35.00 38.58-9.20 9.38 40.00 44.09 8.58 8.68 45.00 49.60 7.98 7.99 50.00 55.12 7.29 7.40

~

55.00 60.63 6.61 6.77 56.68 62.48 6.37 6.55 56.73 62.54 6.54 57.28 63.14 6.47 57.29 63.15 6.46-

4. For format captananen, see letter 1 S Charnley (GE) to M. W. Hodges (NRC), Recommended MAPulGR Tecanical Spervicarwar for Mufnple tornce het Desitas. March 9.1987. Most unuting and Least Linuung tefer to the lowest and lughest linuts. respeenvely, of any ennched lamce in the bundle.

Page 22

(IVER BEND Ji103150SRLR teload 7 Rev. O

16. Loss-of-Coolant Accident Results (cont)5 Bundle Type: Gell-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

)

4.00 4.41 11.85 12.10 5.00 5.51 12.00 12.22 6.00 6.61 12.16 12.34 7.00 7.72 12.30 12.46 8.00 8.82 12.40 12.59 9.00 9.92 12.51 12.72 10.00 11.02 12.62 12.84 12.50 13.78 12.65 12.82 15.00 16.53 12.40 12.55 17.50 19.29 12.10 12.14 20.00 22.05 I1.73 11.79 25.00 27.56 10.%

11.19 30.00 33.07 10.24 10.59

- 35.00 38.58 9.55 9.93

~

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 C6

5. For formas explananon, see lener J. S. Charnley (CE) to M. W. Hodges (NRC). Reconwded MAPUlGR TecWral Specylcationsfor Mulnple 14 nce fuel Desgas. March 9.1987. Most Linuting and Last Linuting refer to the lowest and highest lirruts. tespecovely, of any ennched lattice in the bundle.

Page 23

RIVER BEND Jil03150SRLR Reload 7.

Rev.0 4

16. Loss-of-Coolant Accident Results (cont)6 Bundle Type: Gell-P95UB354-130Z-120T-146-T

\\

Average Planar Exposun MAPLHGR(kW/ft)

(GWd/ST)

(GWd/MT)

Most Limiting Least Limiting O.00 0.00 11.39 11.65 4

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 3.3 s 11.77 11.99 4.00 4.41 11.89 12,10 5.00 5.51 12.02 12.22 6.00 6.61 12.15 12.34 7.00 7.72 12.27 12.46 8.00 8.82 12.39 12.59 9.00 9.92 12.50 12.72 10.00 11.02 12.62 12.84 12.50 13.78 12.54 12.82 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 10.54 35.00 38.58 9.57 9.79 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 J

6. For format esplanation, see letter J. 5 Charnley (GE) to M. W. Hodges (NRC) Raremmended MAPLNGR Technical Sper$catioufor Malaple lordce fuelDesirw. March 9,1987. Most Limitmg and last Linutug tefer to the lowest and highest Ismits respecovely, of any enriched lamce in the bundle.

Page 24

tlVER BEND J1103150SRLR teload 7 Rev.0

16. Loss-of-Coolant Accident Results (cont)7 Bundle Type: Gell-P9SUB353-10GZ-120T-14c T Average Planar Exposure MAPLHGR(kW#t)

(GWd/ST)

I (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 12.72 9.00 9.92 1M 12.82 10.00 11.02 12.',2 12.91 12.50 13.78 12.69 12.82 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.I9

~

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 1

55.00 60.63 7 16 7.23 58.86 64.88' 6.6.'

6.71 59.19 65.25 6.67 59.25 65.31 6.66

1. For format esplanation. see lener J. S. Charnley (GE) to M. W. Hodges (NRC). Recommended MAPLHGR Technical 5pec$carions for

- MulJple terrace Feel Designs, March 9.1987. Most Urruting and Least Uruting refer to the lowest and highest Imuts, respecovely, of any enriched latace in the bundle.

Page 25

RIVER BEND J1103150SRLR Reload 7 Rev.O i

16. Loss-of-Coolant Accident Results (cont)s Bundle Type: GE8B-P8SQB334-100Z2-120M.4WR-150-T Average Planar Exposure MAPLHGR(kW/ft)

(GWd/ST)

(GWd/MT)

Most Limiting Least Limiting 0.00 0.00 11.36 11.88 i

0.20 0.22 11.42 11.91 1

l 1.00 1.10 11.54 12.00 2.00 2.20 11.71 12.13 l

3.00 3.31 11.89 12.28 I

4.00 4.41 12.08 12.43

~

5.00 5.51 12.28 12.60 6.00 6.61 12.48 12.76 7.00 7.72 12.69 12.94 8.00 8.87 12.91 13.1I l

9.00 9.92 13.13 13.29 10.00 11.02 13.34 13.48 l

12.50 13.78 13.57 13.63 l

15.00 16.53 13.30 13.31 l

20.00 22.05 12.63 12.64 25.00 27.56 11.95 11 %

35.00 38.58 10.46 80.52 45.00 4960 9.08 9.21 l

l 50.00 55.12 6.95 7.03 i

L l

a l

i

8. For format esplananon, see letter L S. Charnley (GEHo M. W. Ilodges (NRC). Recommended MAPulGR Technical Spec <ficationsfor Mulaple femce fuel Designs. March 9.1987. Most Limiting and Least Linuting refer to the lowest and lughest limits, respecovely, of any ennched lamce in the bundle.

l Page 26 I

I

(IVER BEND -

J1103150SRLR teload 7 Rev 0

16. Loss-of-Coolant Accident Results (cont)'

Bundle Type: GE8B-P8SQB334-1IGZ-120M-4WR-150-T Average Planar Exposure MAPLHGR(kW/ft)

(GWd/ST)

(GWd/MT)

Most Limiting Least Limiting 0.00 0.00 10.86 11,24 0.20 0.22 10.93 11.30 1.00 1.10 11.09 11.44 2.00 2.20 11.30 11.63 3.00 3.3I i1.53 11.83 4.00 4.4I i1,76 12.05

-5.00 5.51 12.01 12.27 6.00 6.61 12.27 12.50 7.00 7.72 12.53 12.74 8.00 8.82 12.81 12.98 9.00 9.92 13.09 13.22 10.00 11.02

.I3.36 13.46 12.50 13.78 13.58 13.61 15.00 16.53 13.29 13.31 20.00 22.05 12.63 12.63 25.00 27.56 11.95 11,%

35.00 38.58 10.46 10.52 45.00 49.60 9.08 9.20 50.00 55.12 6.95 7.02 4

S

9. For format explannuon. see lettet J. S. Chamley (GE) to M. W. Hodges (NRC), Recommended MAPUlGR TechnicalSpec$catwnsfor Mulaple lattice FaeI Desigar. March 9,1987. Most Unuting and Least Ununng refer to the lowest and highest linuts, respectively. of any ennched latuce in the bundle.

Page 27 i

l

'UVER BEND J1103150SRLR (cload 7 Rev.0 e

se omooooom mMMMMMMMo eMMMMMMMMMo oHMMMMMMMMMMo

L M M M M M M M M M M M M M lLo H M M M M M M M M M M M M o

sHMMMMMMMMMMME8

s M M M M M M M M M M M M M 8

sMMMMMMMMMMMMM8

-*HMMMMMMMMMMMM5

MEMMMMMMMMMMM ll

MMMMMMMMMMM*

MMMMMMMMM5 MEMMMMMS 2

ooooooom l 11IIIII 1 5 5 7 e il la 15 17 19 21 23 25 2r to 31 as as 37 at 91 43 15 47 to 51 58 55 Fuel Type 4

A= Gell-P95UB386-12GZ-120T-14T (Cycle 8)

E= Gell-P9SUB353-10GZ-120T-14T (Cycle 7)

B= Gell-P9SUB360-12GZ-120T-14T (Cycle 8)

F=G E88-P8SQ B 334-10GZ2-120M-4WR-150-T (Cycle 6)

C= Gell-P9SUB354-14GZ-12&T-14T (Cycle 7)

G=GE88-P8SQB334-! ! GZ-120M-4 WR-150-T (Cycle 6)

D= Gell-P95UB354-13GZ-120T-14T (Cycle 7)

Figure 1 Reference Core Loading Pattern 6

Page 28 l

UVER BEND J1103150SRLR leload 7 Rev.0 Neutron Flux Vessel Press Rios (pol)

Ave Surface Heat Flux

* *

Safety Valve Flow 150.0

--- Core inlet Flow 125.0 - --- Rehet Valve Flow

- - -- Core Irdet Subcooling

--- Bypass Valve Flow

./.

100 0 u-- - 1 l

75.0 2

'?

e Y

's,\\

.\\

50.0

',\\\\

25.0

{ ~~ ~"" '"

i g.

_l......

0.0

- 25 0 O.0 20.0 0.0 20.0 Time (sec)

Time (sec)

Level (Inch-REF-SEP-SKRT)

Void Reactivity

.... - Vessel Stearn Flow

- - Doppler ReactMty

--- Turt>ine Steam Flow 1.0 - --- Scram Reactivtty k

150.0

--- Foodwater Flow

- - - Total ReactMty

~

G

~

i 100.0

[

0.0

-....,.......,4.

E

).

y t.\\

t

[ f. '.

I

1 6

50.0 E f' '.

- 1.0

(,'..",,'...

I( ' '..

p,..

U" 0.0

-2.0 0.0 20.0 0.0 20.0 Time (sec)

Time (sec)

Figure 2 Plant Response to FW Controller Failure (BOC8 to EOC8 HBB)

Page 29

LIVER BEND -

J1103150SRLR teload 7 Rev.O Neutron Flux Vessel Press Rese (psi)

Ave Surface Heat Flux

Safety Valve Flow 150.0

- -- Core inlet Flow 300 0 - --- Rehet Valve Flow

--- Bypass Valve Flow g,

h.100.0 200.0 E

'%n-u % ' -.

E E

3R gt 60.0 100.0 I '~

a.. -

n_,

0.0 3.0 60 0.0 3.0 60 Eme(SGC)

ErTM(SeC)

Level (IrMEF-SEP-SKRT)

Void eartMty Vessel Steam Flow Reactivtty

--- Turtune Steam Flow 1.0 200.0 Scram eactMty

--- Feedwater Flow Total R g

Je i-i f{ ~ ('... *

3 T

~~ - -

a o

3 e

\\

ae p

k *,' M *- - -

p 0.0

- t.0

)

a, '

g p

ss '

i' a

- 2.0 I

-100.0 O.0 3.0 6.0 0.0 3.0 60 Eme (SOC)

Eme (SOC)

Figure 3 Plant Response to Load Reject w/o Bypass (BOC8 to EOC8 HBB)

Page 30

IIVER BEND J1103150SRLR leload 7 P.ev. 0 Neutron Flux Vessel Press Rise (psi)

Ave Surface Heat Flux Safety Valve Flow 150.0

--- Core trWet Flow 300.0

--- Relief Valve Flow

--- Bypass Vstve Flow A o,

~

~>

_~~

~~.

50.0 100.0

,1 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec)

Time (sec)

Level (incMEF-SEP-SKRT) fVoid vity

- - - - Vessel Steam Flow r ReactMty 200.0

--- Turtnne Steam Flow 1.0 Scram

--- Feedwater Flow Total R

- ~~

~

100.0 0.0 T --

~

s,... -

i, i,

l ',

\\1 e

);

l,,

\\,

g, 0.0

- i.0

)

i.---

-iOO.0 t

- 2.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec)

Time (sec)

Figure 4 Plant Response to 'Ibrbine 'IYip w/o Bypass (BOC8 to EOC8 HBB)

Page 31

'IIVER BEND Jil03150SRLR teload 7 Rev.0 Neutron Flux Vessel Press Rise (psi)

* * - Ave Surface Heat Flux Safety VaNo Flow 150.0

-- Core Irdet Flow 300 0

--- Relief Valve Flow

--- Bypass Valve Flow 100 0 200.0 2

N 2

N., 's,, %

e sN 50.0 100.0 g-~~~~~-------.

'I 0.0 O.0 O.0 5.0 10.0 0.0 5.0 10.0 Time (sec)

Time (sec)

I Level (inch-REF-SEP-SKRT)

V ReactMty

/

..... Vessel Steam Flow rR 200.0 - ---- Turbine Steam Flow 1.0 Scr Total vity

--- Feedwater Flow Q

w g 100.0 p.%

0.0 g

s' i, a

t E

\\'.

i g

\\-

g

\\'.

g M. -1.0

)

0.0 C

-\\

t

~

l l

1 l

-100.0

-2.0 0.0 5.0 10.0 00 5.0 10.0 Time (sec)

Time (sec)

Figure 5 Plant Response to Press. Regulator Failure (BOC8 to EOC8 HBB)

Page 32

UVER BEND J1103150SRLR

.teload 7 Rev,0

[utron 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 E'

100.0 a i

75.0 i

l%

a e

Y

~

',\\

\\

Y s

50.0 25.0 F~~'

l 4

L.....

I 0.0

- 25.0 O.0 9.5 19.0 00 9.5 19.0 Time (sec)

Time (sec)

Level (IncNREF-SEP-SKRT)

Void Reactivity

- - - Vessel Steam Flow

- * * - Doppler Reactivtty 150.0 - --- Turtnne Steam Flow 1.0 - --- Scrarn Reactivity

)

--- Feedwater Flow

--- Total Reactivitf 8,

s n

g 100.0 k

mlp 0.0 Wh, y l, \\

fl-

\\

i, \\

1 g

I,.

T\\

k f

k -10 l

50.0 l, '

lo i::',:,,""'-

I......

.ei.

t. 0 3 I

I I *,

'l 0.0

- 2.0 O.0 9.5 19.0 0.0 9.5 19.0 Time (sec)

Time (sec)

Figure 6 Plant Response to FW Controller Failure (BOC8 to EOC8 FWHOOS - HBB)

J Page 33

UVER BEND J1103150SRLR teload 7 Rev.O 4

Neutron Flux -

Vessel Press Rsse (pel)

- - - Ave Surface Heat Flux Safety Valve Flow 150.0

-- Core inlet Flow 300.0 - --- Relief Valve Flow

--- Bypass Valve Flow sl ',

g 100.0

,\\, '.

g200.0 1h S_

~

~'

3e g

50.0 100.0

/

0.0 0.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec)

Time (sec) l Level (inch-REF-SEP-SKRT)

Vold vtty

..... Vesset Steam Flow Reactivity 200.0 - --- TurtWne Steam Flow 1.0 Scram earevtty

--- Feedwater Flow Total

.,)I 7 100.0 0.0 v,.

3

---.s------

e l ',

i ne c.

V_

{

E -i.0

\\li

.. '~.. ~...

0.0 e

cc 9k I

- 2.0

-100.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec)

Time (sec)

Figure 7 Plant Response to Load Reject w/o Bypass (BOC8 to EOC8 FWHOOS - HBB)

Page 34

UVER BEND' J1103150SRLR Teload 7 Rev.0

- Neutron Flux Vessel Press Rise (psi)

Ave Surface Heat Flux Safety Vafve Flow 150.0

--- Core Inlet Flow 300.0 - --- Rehef Valve Flow

--- Bypass Valve Flow s,

100.0

\\

200.0

'\\

e

%, s li E

C gt

,w,*~s gt

'~~~_,

50.0 100.0 0.0 O.0 O.0 3.0 6.0 0.0 3.0 6.0 Eme (sec)

Time (sec)

Level (inch-REF-SEP-SKRT)

Void ty

- - - Vessel Steam Flow Reactivity 200.0 - --- TurtWne Steam Flow 1.0

-- Scram eactMty

--- Feedwater Flow Total R 1vt e.

2 3 100.0 l 0.0 a

r~

%, N -

s',

~...

\\

l.

g i

g 4

O

)

.i

\\p 0.0

.0 e

-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 (BOC8 to EOC8 FWHOOS - HBB)

Page 35

i UVERDEND J1103150SRLR teload 7 Rev, 0 Neutron Flux Vessel Press Rise (psi)

Ave Surface Heat Flux Safety Valve Flow 150.0

-- Core IrWet Flow 300.0 - --- Rehof Valve Flow

- - - Bypeas Valve Flow 100.0

\\

200 1

.N 30 a

a 8

's 8

s' s.

s%-

100.0 50.0 e--------,

0.0 O.0 O.0 5.0 10.0 0.0 5.0 10.0 mme (sec) mme (sec) 6.... xh-REF-SEP-SKRT)

I V Reactrvtty

- - - - Vessel Steam Flow t

vtty 200.0 - --- TurtWne Steam Flow 1.0

- Sc m

--- Foodwater Flow

- To

'vity n

8 f@

4 g 100.0 0.0 c..._

i.

g( \\,

w t

o m

\\'s.

\\ '\\

.y 1

i h-1.0 0.0 2

i

\\

1, 4

\\

I i\\

I

-100.0

- 2.0 0.0 5.0 10.0 0.0 5.0 10.0 mme (SOC) mme (SeC)

Figure 9 Plant Response to Press. Regulator Failure (BOC8 to EOC8 FWHOOS - HBB)

Page 36

RIVER BEND J1103150SRLR Reload 7 -

Rev.O i

i Neutron Flux

\\

Vessel Press Rise (psi)

Ave Surface Heat Flux Safety Valve Flow t50 0 - ---

Core inlet Flow 125.0

--- Relief Valve Flow i

Core inlet Subcooling

--- Bypass Valve Flow

-ed

,p.

al',

100.0

'~~~~~~}

75.0 e

E

\\

d

', g

\\

'. \\,

i 50.0

' ~ ~ "

21.0 l

A.

bl......

0.0 I

- 25.0 0.0 20.0 00 20.0 4

Eme(Sec)

Eme (SOC) 4 Level (inch-DEF-SEP-SKRT)

Void Reactivrty Vessel Steam Flow Doppler ReactMty 150.0 - ---

Turt>ine Steam Flow 1.0

--- Scram Reecevtty Feedwater Flow

- - - Total Reecevtty E

lf

{\\

100.0 0.0

.,,,,,,,q,',,'

-,v.,.

I E

e d

[

. p,,,.

1 50.0

- 1.0

[' ';,\\',.....

ti::.:

6 l

[M' i

O.0

- 2.0 0.0 20.0 0.0 20.0 Eme(sec)

Eme(sec)

Figure 10 Plant Response to FW Controller Failure (BOC8 to EOC8 ICF - HBB)

Page 37

.~.

IIVER BEND J1103150SRLR teload'1 Rev,0 Neutron Flux Vessel Press Rise (psi)

Ave Surface Heat Flux Saiety Valve Flow 150.0

-- Core inlet Flow 300.0 - --- Rehof Valve Flow

--- Bypass Valve Flow

\\-

T, ', \\

100.0

,' p, v 200.0

.,s S

's j

~~~s~~~

g g

50.0 100.0

/-

a 0.0 3.0 6.0 0.0 34 6.0 Time (sec)

Eme(sec)

Level (inch-REF-SEP-SKRT)

Void vity

- VesselSteamFlow Reactivtty 200.0

--- Turtnne Steam Flow 1.0 Scram eactivity Feedwater Flow Total R g

,\\

\\

,,e g 100.0 p, 0.0 v,..*,

a y

j,

\\.

e O

\\

'g Ii 1,p e

We z'

e O.0 k b

M-1.0 1

.e e

e

-100.0

\\

- 2.0 00 3.0 6.0 0.0 3.0 6.0 Eme (sec)

Time (sec)

Figun 11 Plant Response to Load Reject w/o Bypass (BOC8 to EOC8 ICF - HBB)

Page 38

.UVER BEND J1103150SRLR

.Leload 7 Rev.0 Neutron Flux Vessel Press Rise (psi)

Ave Suriace Heat Flux

-

Safety Valve Flow 150.0

- -- Core inlet Flow 300.0 - ---

Relief Valve Flow Bypass VEive Flow a

y '* 0f/\\[

s ~.'

y***

's"s h

g s

g 50.0 100.0

.,/......... -

n_n n_n 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec)

Time (sec) t me a 1.evel(inctv-REF-SEP-SKRT)

Void activtty

- - + Vessel Steam Flow Reactivity 200.0

--- Turtnne Steam Flow 1.0 Scram vety Feedwater Flow Total R g

,\\

\\

w t

\\

31*.0 r

~.

OS i,

s,.,....

31.

i.

\\1 g

1 2-g,

E y

1.r. ; - t,

0.0 g -10 t

ir l'

9.

j q

-100.0

-2.0 I

0.0 3.0 6.0 0.0 3.0 6.0 Time (sec)

Time (sec)

Figure 12 Plant Response to 'Ihrbine Trip w/o Bypass (BOC8 to EOC8 ICF - HBB)

Page 39

RIVER BEND Jl103150SRLR Reload 7 Rev.O Neutron Rux 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 1000 g 200.0 s

s%

S s*%s 33!

~,'

~.

50.0 100.0 7-- *v~.....

.1

,_o 0.0.

5.0 10.0 0,0 6.0 10.0 Time (sec)

Time (sec) r I

Level (inch-REF-SEP-SKRT)

V ' Reactivity Vessel Steam Flow R

200.0 - ---

Turbine Steam Flow 1.0 - --

vtty Feedwater Flow Total vety G

~

g 100.0 p. % ' N.

\\', * *,.

0.0 g

g L

g

\\s

\\

C i

\\

) t

\\',

k

}

0.0 g -1.0 g1 e

Il

~

\\'

I

\\

I I'

I

_ jrA.o

- 2.0 0.0 5.0 10.0 0.0 5.0 10.0 Time (sec)

Time (sec) rigure 13 Plant Response to Press. Regulator Failure (BOC8 to EOC8 ICF - HBB)

Page 40

RIVER BEND J1103150SRLR Reload 7 Rev.O r

NojamnTiux Vessel Press Rise (psi) y-Ave Surface Heat Flux

- - * - Safety Valve Flow 150.0 W--

Core Irdet Flow 125 0 - --- Relief Valve Flow

- -- Core Irdet Subcool6ng

--- Bypass Valve Flow 100.0 75.0

=

k

'. N k

e

', s e

N 50.0 25.0 l

P~~

H.

l......

0.0 I

~

- 25.0 O0 9.5 19.0 0.0 9.5 19.0 Eme (SOC)

Eme (SOC)

Level (inch-REF-SEP-SKRT)

Void ReactMty Vessel Steam Flow

- - - Doppler Reecavity

--- Turbine Steam Flow 1.0 - --- Scram ReactMty k

150.0

--- Feedwater Flow

--- Total Reecevtty G

g 100.0 0.0 w :.-- Q -, 7 i,

\\' **

I

s E

l.

\\.

g ll, i I

l b

l So.o l, ".'

, - 1,0 ll.. ' ',.,,,,,

f E

I.......

l......

..e.

g....

t I*' o '.

-2.0 I

'I 0.0 O.0 9.5 19.0 0.0 9.5 19.0 Eme (Sec)

Eme(Sec)

Figure 14 Plant Response to FW Controller Failure (BOC8 to EOC8 ICF & FMTR -HBB) 4 4

9 Page 41

RIVER BEND J1103150SRLR Reload 7 Rev,0 Neutron Flux Vessel Press Rise (pel)

Ave Surface Heat Flux.

- - Safety Velve Flow 150 0

-- Core inlet Flow 300.0

--- Relief Valve Flow

--- Bypass Valve Flow

) \\*

Q,,s')g 200.0 100.0

.u E

E

~

50.0 100.0

/

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 Ve.aol Steam Flow Dor Reactivity 200.0 - --- Turbine Steam Flow 1.0 Scram eactivi

--- Feoowater Flow Total R g

2 g 100.0 0.0 g,

4 v.,.. -

~.

\\

a I

I.

U

~

r i

[

j

~..-...

] i.0 i

0.0

! l, l

?:

\\

~

\\

l

-100.0

-2.0 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 (BOC8 to EOC8 ICF & FWTR

-HBB)

Page 42

(IVER BEND

- J1103150SRLR teload 7 Rev.O Neutron Flux Vessel Press Rise (psi)

-(

Ave Surface Heat Flux Safety Valve Flow 150.0

- Core irdet Flow 300.0 - --- Reisef Va' e Flow

--- Bypass Valve Flow

)

/

j.100.0

,'pg g200.0 e

s e

.N-.,,~~

3h!

50.0 100.0

/

0.0 i

0.0 O.0 3.0 6.0 0.0 3.0 6.0 Time (soc)

Time (sec) l Level (inch-REF-SEP-SKRT)

Void

'vity

..... Vessel Steam Flow Reactivity 200.0

--- TurtWne Stearn Fkw 1.0 Scram

--- Feedwater Flow Total R

, '\\

e.

s'.\\....',.

p 100.0 0.0 r-k

].

,N---

\\,i g

1

\\

\\.

o.0,-.,,.- a,r - - - - -

- 1.0 g{

Il 1

-100.0

-2.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec)

Time (sec)

Figure 16 Plant Response to ibrbine Trip w/o Bypass (BOC8 to EOC8 ICF & FWTR

-HBB)

Page 43

RIVER BEND Jl103150SRLR Esload 7 Rev.0 Neutron Flux Vessel Press Rise (psi)

Ave Surface Heat Flux

- *

Safety Valve Flow 150.0

-- Core trWet Flow 300.0 - --- Relief Valve Flow

--- Bypass Valve Flow

'\\

~~

\\

100.0 p 200.0 K

h-

%s h

^

%s N s's s-

. 50.0 100.0 r- - - ~ - - - - - - - - - -.

0.0 O.0 I

0.0 5.0 10.0 0.0 5.0 10.0 Time (sec)

Time (sec)

Level (inch-REF-SEP-SKRT)

Vo 1

- - - - Vossel Steam Flow Doggier R

'vnty 200.0 - --- Turbine Steam Flow 1.0 - - - Sc vity

-T eactMty

--- Foodwater Flow g

g 100.0 10.0 e'

g 'i g-- % ' %.

A g,...

h

\\',

\\

g

. \\'

l 0.0 1.0 g,

E

\\

l

\\'I I

I

-100.0

- 2.0 O.0 5.0 10.0 0.0 5.0 10.0 Time (sec)

Time (sec)

Figure 17 Plant Response to Press. Regulator Failum (BOC8 to EOC8 ICF & FWTR

-HBB)

Page 44

UVER BEND J1103150SRLR teload 7 Rev, 0 Neutron Flux Vessel Press Rose (psi)

- Ave Surface Heat Flux Safety Valve Flow

CoprAear ',

125 0 - --- Rehof Valve Flow 150.0

\\

_. p Core Inlet Subcoohng

--- Bypass Valve Flow 100.0 75.0 a

f,.,

e, N

50 0

',g 25.0 l

' " ~ ~ ~

.s b.'.... '.

i 0.0 I

l

- 25.0 0.0 20.0 0,0 20.0 Time (sec)

Time (sec)

Lovel(inch-REF-SEP-SKRT)

Void ReactMty Vessel Steam Flow

- Doppler ReactMty

(

150.0

--- Turtnne Steam Flow 1.0 - --- Scram ReactMty j

--- Feedwater Flow

--- Total ReactMty i,'

e 1\\

g 100.0 0.0

,r........-f,, '

E

\\

e td t'

i r'

f t

N-1.0 l

50.0

/

l',., 't ;;,iY'/...

2 I

l e:::

I b

,6 0.0

-2.0 00 20 0 0.0 20.0 Time (sec)

Time (sec)

Figure 18 Plant Response to FW Controller Failure (BOC8 to EOC8 MELLL - HBB)

Page 45

'UVER BEND Jl103150SRLR-(cload 7 Rev 0 NeJtron Flux Vessel Press Rise (psi)

Ave Surface Heat Flux

- -

SafetyValve Flow 150.0

- -- Core Irdet Flow 300.0

--- Relief Valve Flow

--- bypass Valve Flow MO 2M0

% t/

~

\\ v',,

e ~, w -

~

o 50.0 100.0 l~ ~.........''*

0.0 00 0.0 3.0 6.0 0.0 3.0 6.C Time (sec) -

B.ve(sec)

Level (inch-PEF-SEP-SKRT)

Void vity

..... Vessel Steam Flow -

er Reactivity

--- Turtune Steam Flow 1.0 200 0 e

Reactivity

- - - Feedwater Flow Total vtty g

w t

4 4

y 100.0 r.s, 00

.),...-

,~

S l

s

- \\

1'

i

\\'

}

\\

0.0

,7-----

- 1.0 g*{

\\

)

. 's g.

\\\\

I I

- 100.0 '

I

=

-20 0.0 3.0 6.0 3.0 6.0 Time (sec)

Time (sec)

Figure 19 Plant Response to Load Reject w/o Bypass (BOC8 to EOC8 MELLL-HBB)

Page 46

..~

UVER DEND J1103150SRLR -

teload 7 Rev.0 1

Nsutron Fluv Vessel Press Rise (psi)

Ave Surface Hea; Flux Safety Valve Flow 150.0 - --

-- Core trWet Flow 300.0 Relief VaNa Flow Bypass Valve Flow o 100.0 o 200.0 e

9 E

cf

~js^

m%.

t 7,'. '. - -

50.0 100.0

,l n_n no 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec)

Time (sec)

"rddheactMty Level (inch-REF-SEP-SKRT)

- - - Vessel Steam Flow r ReactMty 200.0 - --- Turtnne Steam Flow 1.0 Scr Reactvity

--- Feedwater Flow Total g

l 10.0

['

7 100.0 ml. _, ^ - - - -.

..{,..-

s l

s c

i.

[,',

.'N, *,.

~ i p

\\i 1; ;

\\

3 j -i.0 g

Q _-_y___-

0.o l,..

e i'\\,

\\

1! -

-100.0

-2.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec)

Time (sec)

Figure 20 Plant Response to 1brbine Trip w/o Bypass (BOC8 to EOC8 MELLL - HBB)

Page 47

.~ _

UVER BEND J1103150SRLR (eload 7 Rev, 0 Neutron Flux Vessel Press Rise (psi)

Ave Surface Heat Flux

* *

Safety Velve Flow

-150.0 - --- Core Itdet Flow 300 0 - --- Relief Velve Flow

-- - Bypass Velve Flow g 100.0 g 200.0 a

a C

E g\\

"~

g g

ds.N%

' ~ ~.,

50.0 100.0

(

0 0.0 O.0 O.0 5.0 10.0 0.0 5.0 10.0 Time (sec)

Time (sec) 1 Level (inch-REF-SEP-SKRT)

VMi ReactMty

..... Vessel Steam Flow

- - - Dog rR 200.0 - --- Turtnne Steam Finw 1.0 Sc R

--- Feedwater Flow T

ty G

~~

7 g 100.0 r % ~~...

\\\\

0.0 g.,,.*

n s

x

\\

\\ \\-

g

\\-

p(j

\\',

k

,a 0.0

\\~~

M-1.0 e

\\\\

c il l'

I

\\

I I

-100.0

- 2.0

- 0,0 5.0 10.0 0.0 5.0 1r.0 Time (sec)

Time (sec)

Figure 21 Plar.t Response to Press. Regulator Failure (BOC8 to EOC8 MELLL - HBB)

Page 48

RIVER BEND Jl10315CSRLR Reload 7 Rev.0 Neutron Flux Vessel Press Rise (psi) f

- - - Ave Surface Heat Flux Safety Valve Flow T

150.0 - --- Core inlet Flow 125 0 - --- Rollef Valve Flow

- -- core weiSubcoonn9

-- - sypen vwve Fio.

****~~'

100.0 7 75.0

_._-.-----------l T

E s

g g

1,5 50.0 25.0 T~~~

l-rl-2.....

0.0 I

- 25.0 O.0 9.5 19.0 0.0 9.5 19.0 Time (sec)

Time (sec)

Level (inch-REF-SEP-SKRT)

Void ReactMty f

- - - - Vessel Steam Flow

- - - - Doppler Reactivtty A

150.0 - --- Turtnne Steam Flow 1.0 - --- Scram Reactivity

--- Feedwater Flow

--- Total ReactMty

^

l

~

\\

w g 100.0 0.0 i

g

,. \\

- <s........, \\'i g

l',.

I i,:,;\\

f i

50.0

. t a N-1.0 i:...^ : t.,,.

e

\\; ' ', 'e i.

I l,, i, ' '

l p' '

\\

e 0.0 I

I

- 2.0 0.0 9.5 19.0 0.0 9.5 19.0 Time (sec)

Time (sec)

Figure 22 Plant Response to FW Controller Failum (BOC8 to EOC8 MELLL &

FWHOOS - HBB)

Page 49

j UVER BEND J1103150SRLR Reload 7 Rev.0 Neutron Flux Vessel Press Rise (pol)

- - Ave Surface Heat Flux

- - - Safety Valve Flow 150.0

-- Core inlet Flow 300 0

--- Relief Valve Flow

-- - Bypass Valve Flow q,I N, 100.0 200.0 7

7 a

p x

~b p%

'.g 5

7'~-

103.0 50.0

,/

.L.........

o.o o.o 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec)

Time (sec)

Level (inch-REF-SEP-SKRT)

'vity

..... Vessel Steam Flow r Reactivity 200.0 - --- Turbine Steam Flow 1.0 Reactrvtty

--- Feedwater Flow Total vtty a

,t

\\

y 100.0 0.0 s'j,...<

.,i

.s,~-

e

\\.

t'

\\1

[

\\

L. -,..'

31.0 g

0.0 e

C l,

'i

-100.0

- 2.0 O.0 3.0 6.0 0.0 3.0 6.0 Time (sec)

Time (sec)

Figure 23 Plant Response to Load Reject w/o Bypass (BOC8 to EOC8 MELLL &

FWHOOS - HBB)

Page 50

(IVER BEND J1103150SRLR leload 7 Rev.O Neutron Flux Vessel Press Rise (pel)

Ave Surface Heat Flux

- - SafetyVaNo Flow 150.0

- -- Core inlet Flow 300 0 - --- Relief Valve Flow

--- Bypass Valve Flow l

100.0

, ' ' 'i 200.0

's a

e

',% a,. v.'.

e e

% ~ 7 '" ~ ~ ~

SOA 100.0

~

/-

i i...........

o.o no 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec)

Time (sec)

Level (inct>-REF.-SEP-SKRT) oid

- - - Vessel Steam Flow r Reactivity 200.0 - --- Turbine Steam Flow 1.0

- Sc Reactivity

--- Feedwater Flow Total vt

- . 2 -

t*

i g 100.0 0.0 2,,J,..**

T[, '-

~. %.-

\\

,\\

n

\\

g e

i'

\\

i f

\\

~.*

0.0 m -; m -a - - - - - - -

- 1.0 l1 m

i

'i'.'

~

li

\\

.s

\\

-100.0

- 2.0 O.0 3.C 6.0 0.0 3.0 6.0 Time (sec)

Time (sec)

Figure 24 Plant Response to Thrbine Trip w/o Bypass (BOC8 to EOC8 MELLL &

FWHOOS - HBB)

Page 51

UVER BEND J1103150SRLR (eload 7 Rev.0 Neutron Flux Vessel Proes Rise (pol)

- Ave Surface Heat Flux -

Safety Valve Flow 150 0

-- Core In'ot Flow 300.0 - --- Relief Valve Flow

--- Bypass Valve Flow J

100.0

'. ~

200.0 2

e p

q.

g s

s 50.0

' N, 100.0 f.______,

0.0 O.0 0.0 5.0 10.0 0.0 50 10.0 Time (sec)

Time (sec)

Level (inch-REF-SEP-SKRT)

Vdd Reactivtty

..... v.ee.i steam now

-Do r

tv 200.0.- --- Tm Sie.m now 1.0 - - - Sc wy

-T

--- Feedwater Flow g

f g.100.0

/',.

00 s\\...-

V ' ~~ -..

\\

e

\\'.

\\.

~ \\.

g

\\\\

o.o N'

] -1.0 I'

g

=

i.

\\

I<

\\.

-100.0 f

- 2.0 O.0 -

5.0 10.0 0.0 5.0 10.0

- Time (sec)

Time (sec)

Figure 25 Plant Response to Press. Regulator Failum (BOC8 to EOC8 MELLL &

FWHOOS - HBB)

Page 52

RIVER BEND J1103150SRLR Reload 7 Rev.O o

Neutron Flux j

h Vessel Press Rise (psi)

Ave Surface He.at Flux i

- Safety Valve Flow 150.0 - --- Core inlet Flow 125 0 - --- Relief Valve Flow

- -- Core Irdet Subcoohng

--- Bypass Valve Flow 100.0

--"-"-----1

(

g 75.0 2

)\\

w l

m Y

\\

s

', \\

50.0 g

25.0 l

" ~ "" '

0.0 I

1

- 25.0 0.0 20.0 0.0 20.0 Time (sec)

Eme (sec)

Level (inch-REF-SEP-SKRT)

Void ReactMty

{f

- - Vessel Steam Flow

- - - - Doppler Reactivity I

150.0 - --- Turtune Steam Flow 1.0 - --- Scram ReactMty

--- Feedwater Flow

--- Total ReactMty a

\\l..

E9

\\

. p 100 0 0.0 o

w t'

e

(

l g

p

\\.

i h

l i

50.0 E,;,

j-1.0 t .,"

C

$'l:.., k......

L t

I I. !'

I 0.0 I

- 2.0 0.0 20.0 0.0 20.0 Time (sec)

Time (sec)

Figure 26 Plant Response to FW Controller Failure (BOC8 to EOC8 HALING)

{

Page 53

RIVER BEND J1103150SRLR Reload 7 -

Rev, 0 Neutron Flux Vessei Press Rise (pel)-

Ave Suriace Heat Flux Safety Valve Flow 150.0 Core irdet Flow 300.0 - --- Relief Valve Flow

--- Bypass Valve Flow I',M.

200.0 100.0 3

, /v\\y 3

5 s

E

\\~s~'

C Y

Y

~~_

50.0 100.0 c, ol

.,I

..i.........

i o,

0.0 3.0 6.0 0.0 3.0 6.0 Time (sec)

Time (sec)

Level (inch-REF-SEP-SKRT)

Void Vessel Steam Flow ReactMty 200.0 - ---

Turtaine Steam Flow 1.0 Scram eactMty Feedwater Flow Total R g

/

p 100.0, -.._

,,...,..~

0.0 y

.~.-

\\,' '.

~

\\,

I

- 0.0

= = - - - - - - - - - -

m -1.0

\\\\

...r--

e s s*

T

\\s e

11 1)

\\'

-100.0 t

i\\'

- 2.0 O.O.

3,0 6.0 0.0 3.0 6.0 Time (sec)

Time (sec)

Figure 27 Plant Response to Load Reject w/o Bypass (BOC8 to EOC8 HALING) i Page 54

(IVER BEND Jil03150SRLR teload 7 Rev, 0 Il Neutron Flux Voteel Press Ree (pel)

Ave Surface Heat Flus Safety Valve Flow 150 0 Core irdet Flow 300 0

--- Relef Valve Flow

--- Byp*.no Valve Flow o

100.0

/ h--),y 200'0 m

.,vs g ~. ' *"" %

~~.

60.0 100.0

,/

i

.i...............

_,.o o,

0.0 3.0 6.0 00 30 60 Time (sec)

Time (sec)

^ #

Level (WEF-SEP-SKRT)

Void 4

Veeeel Steam Flow

+D Roncevity Turtnne Steam Flow 1.0

- Scram esce 200.0 Feoow.ier rio.

- - Toisi g

f,

,f.\\

] 100 0

$q 00

)......

m.%,~.

l\\i l

~

g.

J.t.0 L,. g _.,. _ _

0.0 3

c:

\\ 'i I

\\\\

a

\\'

I I

-100 0

- 2.0 O.0 3.0 6.0 0.0 3.0 60 Time (soc)

Time (sec)

Figure 28 Plant Response to 'Ibrbine 'IYip w/o Bypass (BOC8 to EOC8 HALING)

Page 55

)

g g END J1103150g Pseutron Flum Veteel Prees Rite (pel)

* * *

Ave Surface Hott Flus

* * *

Selety Vehm Flow 160 0

--- Core trWet Flow 300 0

--- Re46ef Velve Flow

--- Sypees Velve Flow 100 0 200 0 N

\\ s s

A s

s*%

50.0 100.0 j------~~-----,

0.0 00

,f 1.....

0.0 5.0 10 0 00

$G 10.0

.Eme(tec)

Eme(Sec)

Level (inch 4tEF-SEP-8KMT)

Volt Reecevity

* *

VesselSteam Flow

Dop vtty 200.0

--- TurtWne Steam Flow 1.0

- Sc vtty

--- Feedwater Flow

- Total ReactMiy g

100.0 0.0 y--. %

. #

p._

g,,,,*,,*

t l\\.

e

\\' '.

\\

l

\\*

d.

e g

0.0 1.0 g

C.

l l

I i

l l

I I

-100.0

- 2.0 O.0 5.0 10.0 0.0 60 10.0 mme (sec)

Vme (sec)

Figure 29 Plant Response to Press. Regulator Failure (BOC8 to EOC8 HALING)

Page 56

(IVER BEND jl103150SRLR teload 7 Rev, O l

dron Flux

- Vessel Press Mise (pol)

Ave Surface Heat Flux

* *.

Safety VaNo Flow 160 0

--- Core inlet Flow 125 0

--- Releef Valve Flow

- -- Core Irdet Subcooiing

--- Bypass Valve Flow

u*******~~'~ II I.0 s

10 100 a-76 f

'N

. *N 1

+

60.0 26.0 r--

l

-l. -

-.L.....

0.0 I

-26.0 O.0 9.6 19.0 0.0 96 19 0 Time (sec)

Time (sec)

Level (inch-REF-SEP-SKRT)

Vo6d Reecevity

..... Vessel Steam Flow Doppler Reecevtty 160.0

--- Turbine Steam Flow 1.0 - --- Scram ReactMty

--- Foodwater Flow

--- Total ReactMty 3

j 100.0 00

- WTmQli,,

g ll ) s

\\

~

l. \\

l'

' i, \\'., *

\\

60.0

), 'a

- 1.0 l

,,, I '.. '.

i'i

,,,i.

g.

M"i

\\

'n 0.0

- 2.0 0.0 96

'90 0.0 9.6 19.0 Time (sec)

Time (sec)

Figure 30 Plant Response to FW Controller Failure (BOC8 to EOC8 FWHOOS -

HALING)

Page 57

(IVER HEND Jil03150SRLR (eload 7 Rev, 0 Neutron Flum Vessel Press Rise (psi)

Ave Surface Heat Flun

* * *

Safety Vidve Flow 160 0

-- Core inlet Flow 300 0

--- Relief Valve Flow

- - - Bypass Valve Flow r

I 100 0 200 0 F,s

.N s ~ ~ ~~,,,, ' ~

i

~.

f

~~~.

60 0 100 0 00 O.0 I

0.0 30 60 00 3.0 60 Time (sec)

Vme (sec)

Level (inch-REF-SEP-SKRT)

' Void vity

..... Vessel Steam Flow Hoec#vity 200.0 - --- Turbine Steam Flow 1.0 Scram eacti

- - - Feedwater Flow Total R g

a 100.0 0.0

,f g'l..

.~.-

s 8

\\ I I

i 00 -

g 11

\\,

I

\\

'I'

-100.0

- 2.0 O.0 30 60 0.0 3.0 60 Emo(sec)

Time (sec)

Figure 31 Plant Response to Load Reject w/o Bypass (BOC8 to EOC8 FWHOOS -

HALING)

Page 58 J

__._,__..________m____._..-

g PEND Jil03150g I

Neutron Flux Vessel Press Rise (pol)

Ave Surface Heat Flux

*

Safety Valve Flow 160 0 - -- -- Core inlet Flow 300 0

--- R,64f Valve Flow

--- Bypene Valve Flow h

10 100 200.0

,/v\\

%s%~'

s'-

~~_,

50.0 100.0

, +..*.

c------------

I 0.0 O.0 0.0 30 60 00 3.0 60 Eme(84C)

Eme(soc) i Level (inch-ALF-SEP-SKRT)

Void

+ +

Vessel Steam Fk,n Reecevity

--- Turbine Steam Flow 1.0 Scram onett 200.0

--- roeow ier now

- - Total n g

A

f.,I

] 100 0 y,

0.0

- ( j i

\\

j%

\\,

,,4 '...

] -i.0 Oc -,- ;- -.: - h

(

.,')

G

\\,

h

\\\\

),

Ii'

-100.0

~ 2.0 - -

O.0 30 6.0 0.0 30 6.0 Eme(Sec)

Emo(soc)

Figure 32 Plant Response to 'harbine Trip w/o Bypass (HOC 8 to EOC8 FWHOOS -

HALING)

Page 59

g p END J1103150g Neutron Flu Vessel Press Roe (psi)

* * *

Ave Surface Heal Flux

* * *

Safety VnNe Flow 150 0

-- Core truet Flow 300 0 - --- Relief Valve Flow

--- Bypass VaNo Flow

'7 \\

100.0 200.0

. N~N s

ens g % *-

50.0 100.0

(---- - -

0.0 OO I

0.0 5.0 10.0 0.0 5.0 10 0 Time (sec)

Time (sec)

Voll Reacti Level (inch-REF4EP-6KRT)

* *

Vessel Sloam Flow

* * *

Dog r

vety

--- Turbine Steam Flow 1.0 200.0

- Sc very

- TotalReactivity

--- Foodwater Flow n8

] 100.0 q-

. s, __.

00

-}*

\\*{

v.

g-1,0 1, \\

0.0

\\---

I

\\,

l 1 Il

\\.

-100.0

-20 0.0 5.0 10.0 00 5.0 10.0 Time (sec)

Time (sec)

Figure 33 Plant Response to Press. Regulator Failure (BOC8 to EOC8 FWHOOS -

HALING)

Page 60

4 (IVER BEND J1103150 RLR teload 7 ev, O l

Vessel Press Rise (psi)

Neutron Flus

* * *

i-9 Surface Heat Flus b

Salvty Valve Flow 1

a - * * *

--- Je truet Fivw its 0 160 0

--- Relief Valv1 Flow

- -- Coro inlet Subcooling

- - - Bypass Valve Flow 1

j.

, ~.

.:. _ _ _.- _ - -. -. _ _ _ i i

y 100.0 15.0 l

\\

d g

'. s g

\\

,,\\

25 0 60.0 g" ~ ~ ~

H.

2_l......

00

- 25.0 00 20.0 0.0 20.0 Eme(soc)

Eme(soc)

Level (inch-REF-SEP-SKRT)

Void ReactMty

. * * *

Voteel Steam Flow

* * *

Doppler ReactMty i

150 o

--- Turbine Steam Flow 1.0

--- Scram Reactivity

--- Foodwater Flow

--- Total ReactMty w

i g\\

too.o o.0

-.... e.

.. v..., l '.

['

i-l F

t C,, h 6

60.o

- 1.0 cg....

l g

0.0

-20 I'

00 20.0 0.0 20.0 Eme(sec)

Emo (sec)

Figure 34 Plant Response to FW Controller Failure (BOC8 to EOC8 ICF - HALING)

Page 61

gigEND Jil03150 g Wutron Flux Ve6 eel Press Rese (pol)

*

Ave Surface Heat Flus

+ *

Safety VaNo Flow 160.0

- -- Core inlet Flow 300 0

RebelValve Flow

- - - Bypass Velve Flow

[ \\,

100.0

,'.s 7. \\

200 0 e%

% s%

~~~

e 60.0 100.0

~.......

.,/ - ~~ ~ - -..s........

n_,

o_,

0.0 30 60 00 3.0 60 Emo (SOC)

Emt (soc)

Level (inch-REF-SEP-8KRT)

Void

- +

Vessel Steam Flow

- Doppie Res iivtty 200.0

--- Turbine Steam Flow 1.0 Scram

--- Feedwater Flow Total G

A

\\l'r,k,....,.*,...

1 1000 7._

~.

0.0

\\

1 n

i'.

l.

N,.

e

- 1.0 I,

00 4 - +.,- -

g

\\g'\\

I

\\'

-100.0

- 2.0 I

0.0 3.0 6.0 0.0 3.0 60 Vme(soc)

Vme(See)

Figure 35 Plant Response to Load Reject w/o Bypass (BOC8 to EOC8 ICF-HALING)

Page 62

(IVER.3END J1103150cRLD teloadi Rey,"(}

l Neutron Rus Veteel Prees Ree (poi)

Ave Surface Heat Fluz

* * *

Safety VaNo Flow 150.0 core iniet now 300 0

--- Rouetv ive riow

--- erp es vaive now f/ \\

103.0

'e PCC 0 N

~ ~ ~ ~ ~

50 0 100.0

/

'l'-**"*****-"-

^

0.0 00 0.0 30 6.0 00 3.0 60 Time (soc)

Time (sec)

Level (inch-REF-SEP-SKRT)

Vo6d vety Veesel Steam Flow Reactvity 200 0 Turbine Steam Flow 1.0 Scram Feedwater Flow

- - Total R R

f E

j 100.0 y..

,,,, ~. _.

g00 p,....,,,*

i h

l' ei

\\

}.,

\\

'.. ~~.......

\\

0.0

-.r.---

1.0 j

s gs d,.

\\t

'.c

\\\\\\s a

-100.0 I

~ 2,0 O0 30 6.0 0.0 30 60 Time (sec)

Time (soc)

Figure 36 Plant Response to 'Ibrbine Trip w/o Bypass (BOC8 to EOC8 ICF-HALING)

Page 63

llVER,3END Jil03150gRLR te ond ev. 0 Neutron Flum Vestel Prete Rise (pal)

* *

Ave Surface Heat Flus Safety Valve Flow

- - a 160 0

--- Core irdet F6ow 300 0 Releef Vaive Flow Bypass Valve Flow

" Ns 100.0 N

200 0

\\s s

N 100 0

$0.0 i

ao

.s

...i......

0.0 60 10 0 00 6.0 10 0 Time (sec)

Time (soc)

I Level (inch-REF-SEP-SKRT)

Void ReactMty

* *. Veneel Steam Flow

. Dop r

vity 200,0

--- TurtWne Steam Flow 1.0

- Sc eactMty

--- Foodwater Flow

- TotalReactivtty

.100.0 N.,'

00 g.

7. %, ~~~..

.s*p.

\\ p-Y'.

g 4

\\'

g l

l

\\i de g

00

- 1.0 c:

\\'

4 I

I,

\\

I I'

-100.0

~20 0.0 5.0 10.0 0.0 5.0 10 0 Time (sec)

Time (sec)

Figure 37 Plant Response to Press. Regulator Failure (BOC8 to EOC8 ICF-HALING)

Page 64

(IVER BEND J1103150SRLR teload 7.

key. O f

7 Ngupon' Flus Vessel Prete Rise (p61) y Ave Surince Host Flus

* * *

Safety Velve Flow

+.

160.0 --$*~~

Core inlet Flow 125 0

--- Rohet Verve Flow

- -- Co*e inlet Subcoo66ng

- - ~ Bypese Velve Flow

~~~W...-.~~

g\\

,, n n

'.\\

E

\\

0l Y

', \\

Y s

60 0 26.0 f* "" ~ -

l

4. -

1.....

I I

00

-80 O.0 9.6 19.0 0.0 96 19 0 Time (sec)

Time (sec)

I Level (inch-REF-SEP-SKRT)

Void ReactMty

..... Vessel Steam Flow Doppler Reeevytty 0

--- Turb6ne Steam Flow 1.0

.160.0

--- Scram ReactMty

)

- - - Foodwater Flow

- - - Total ReactMty E

r.

100.0 0.0

- - hW M*g,

-- g l'. \\

'6 I' e

\\

kt

',!\\

?

60.0 g, 'i...

, - 1.0 g

1,,,','.e'..'

'+e.

j.

l. ' '

D'i!

\\

'h 0.0

~ 2.0 O.0 9.6 19.0 0.0 9.6 19 0 Time (sec)

Time (sec)

Figure 38 Plant Response to FW Controller Failure (BOC8 to EOC8 ICF & FWTR HALING)

Page 65

LIVER BEND J1103150SRLR teload 7 Rev.O Neutron Flua Vessel Pro 64 R6te (pol)

Ave Surfoce Host Flum

+

Safety Valve Flow 150.0 Coro inlet Flow 300 0

--- Relief Valve Flow

- - - Bypote Valve Flow V

i 100.0

.,*( g % -. N 200.0

,4 N

100.0 60 0 00

~

00 O.0 3.0 60 00 3.0 6.0 Eme (60C)

Vme(60C)

Level (inch-REF-SEP-SKRT)

Vold R

'vtty Vessel Steam Flow Dopp6o Reactivtty furtNne Steam Flow 1.0 200 0 Scram eactivi

- --~

--- Foodwater Flow Total R W

..+ ***'

l.

,. **,,e**,,

} 100.0 r

~.~.

,,+

00 ei

\\j I ',

\\

l%

m,---*-

- 1.0 y

00 g

E V.

i, i

\\\\

-100.0

- 2.0 O0 3.0 6.0 00 3.0 6.0 Eme(Sec)

Eme(Sec)

Figure 39 Plant Response to Load Reject w/o Bypass (BOC8 to EOC8 ICF & FWTR HALING)

Page 66

_ _ _ _. _ _. - _ _ - _ - - - ~ - _ _ _ _ _ -. _ - -

(IVER BEND J1103150SRLR (eload 7 Rev.O Neutron Flus Vessel Press Rise (psi)

Ave Surisco Heat Flux Safety Valve Flow 150 0

-- Coee inlet Flow 300.0

--- Relief Valve Flow

--- Bypase Valve Flow

/'s '

ts 100 0

,- Mg 200.0 g

N E

N.,,

N bl 60 0 100 0 o -

0.0 O0 00 3.0 6.0 0.0 3.0 60 Time (sec)

Time (sec)

Level (tre.REF-SEP-SKRT)

Void cuvity Vessel S'eam Flow Doppio Reecevity 200.0

--- Turtune Steam Flow 1.0 Scram escu

- - - Foodwater Flow Total g

~

1

] 100.0 0.0

~ (+

7,..

il

\\

5

~,, r. ~, w ~ ~ -

_1.0

,(

0.0

.z cc 1.

l(

\\\\

\\.

II '

-100.0

- 2.0 0.0 3.0 6.0 00 3.0 60 Time (sec)

Time (sec)

Figure 40 Plant Response to 'Ibrbir.e Trip w/o Bypass (BOC8 to EOC8 ICF & FWTR HALING)

Page 67 l

i

.~

'tIVER BEND J1103150SRLR teload7 Rev.0 teeutron Flux Vessel Press Rise (pal)

Ave Surface Hoot Flux

- Se'ety VaNo Flow 150.0

-- Core Wet Flow 300 0

--- Rehof Valve Flow

--- Bypass Valve Flow

, *~ ' N 100 0 S

200 0

'.g N

N g%~

g Y

's, s

Y

~

's 50.0 100.0 l

0.0 O.0 I

O.0 5.0 10.0 0.0 5.0 10.0 Dme (sec)

Emo (sec)

Level (inch-REF-SEP-SKRT)

..... Vessel Stoem Flow vtty 200.0 - --- Turbine Steam Flow 1.0

- Scr vety

--- Fadwater Flow

- TotalReactivity G

100.0 0.0 g

~.s,_

hg '.

e X,

- \\(

I 1

,\\ - ~,

- 1.0 I

0.0

~

~~----

I.

\\

l.

I 100.0 2.0 O.0 5.0 10.0 0.0 5.0 10.0 Vme (sec)

Emo(see)

Figum 41 Plant Response to Press. Regulator Failum (BOC8 to EOC8 ICF & FWTR HALING)

Page 68

(IVER HEND J1103150SRLR teload 7 Rev.0

)

l i

Neutron Flus Vessel Press R4e (pol)

Ave Surface Heat Flux, ]

Safety VaNo Flow

--- Cofre154cw * "

125 0 150 0 Rel4f Ve8ve Flow

_, = Core treet Subcooling Bypate Valve Flow 100 0

' '~

~

~~'~~,

75 0 S,

g..

\\N

'\\

$0.0

"~'

25.0

' k' l

rl-s I......

I 0.0

~ 25.0 0.0 20.0 0.0 20.0 Time (seC)

Time (sec)

Level (inch-REF-SEP-SKRT)

Void Reecevity Vessel Steam Flow Doppler Reactivity aa *

150.0 - --- Turb6ne Steam Flow 1.0

--- Scram Reactivity

- -- Foodwater Flow Total Redetivity n

to 4

E 1\\

g; l

t 100.0 0.0

. -. -. +..

....g ;,.

$\\

h" 1

e Y

ll\\

~

\\

P'

I i

I'

- 1.0 50.0 I

(,..e.ei h,,. q.'

l

\\

l'

('.i

(

E '..

l El,'

O.0

- 2.0 t u_

0.0 20.0 0.0 20.0 1

L Time (sec)

Thne (sec) l Figure 42 Plant Response to FW Controller Failure (BOC8 to EOC8 MELLL - HALING) d I

(

Page 69 r

(IVER BEND J1103150SRLR teload 7 Rev.0 Neutron Flus Vessel Press Rise (pol)

Ave Surface Heat Fkts

Safety VeW Flow 150.0

--- Core inlet Flow 300 'J

--- Relief Valve Flow

--- Bypase Valve Flow i

100.0

- 200 0

]

E

"" g\\a^ % k'o,' ".T Y

' *., ~ ~ ' '

100.0 60.0

/~ ~

- I....'**

0.0 00 O.0 30 6.0 0.0 30 60 Time (s**$

Time (soc)

Level (6nch-REF-SEP-SKRT)

Y Void Vessel Steam Flow

< Reecevity 200 0

--- Turtune Steam Flow 1.0

-- Scram oncevtty

--- Feoow.ier Fiow

- - Total a

'.... ~.....

})

i 100 0 0.0 r.

I'

\\

l ',

a

\\

I.

g s.

1.0

\\\\

0.0

,-.-r,'---

,e s.

4t'

e

{\\*

4 I('

i I

-100.0

-2.0 O.0 3.0 6.0 0.0 3.0 60 Time (sec)

Time (sec)

Figure 43 Plant Response to Load Reject w/o Bypass (BOC8 to EOC8 MELLL'-

HALING)

Page 70

m.

(IVER BEND J1103150SRLR igload 7 Rev 0 Neutron Flux Vessel Press Rise (psi)

* * *

Ave Surface Heat Flux

- * *

Safety Valve Flow 150 0 - - ~ ~ Core Wet Flow 300 0

--- Reef Valve Flow

--- Bypass Valve Flow

~

RfA :x %

7 vt 50 0

~~

100 0 l

_.s........

00 nn 0.0 3.0 6.0 0.0 3.0 6.0 Eme(SeC)

Eme ($OC)

Level (inch-REF-SEP-SKMT)

Void vtty Vessel Steam Flow r Reecevity

--- Turb6ne Steam Flow 1.0 200.0

- - Screm eacevity

- - - Feoo ter Fio.

- - Toi.:

~

a

.g 0.0 g 1w.0 m.

2 i'

/ g i

\\ l'j i,

j ., /,

y-

\\

k'-fp-l

- 1.0 0.0 l.','

ct

)\\

\\

t ')

~.

\\

I

-100.0

- 2.0 O0 3.0 6.0 0.0 3.0 6.0 Eme (sec)

Vme (sec)

Figure 44 Plant Response to 'Ibrbine Trip w/o Bypass (BOC8 to EOC8 MELLL -

HALING)

Page 71

- ~ _. -

(IVER BEND J1103150SRL teload 7 Rev.

Neutron Fkaa Vessel Prese Rise (pol)

Ave surtece seat Fius

..... severy vwve raw 150 0

--- Coro irdet Flow 300 0

--- Relief Veno Flow

--- 9ypees Velve Flow 100 0 200.0 8

,s 8

N

.s

. s.N

'.,%s%

60 0 100.0 o.,

i n oi _.

.i

..i.......

0.0 6.0 10 0 00 50 10.0 Time (scc)

TL?e (se:)

4 t

Leveylnch-REF-SEP-SKRT)

Voh Reecevtty

..... Vessel Steam Flow r

- -- Turtnne Steam Flow 1.0 200.0 Sc

~ ~ ~ Feedwater F.tw g

]g,.... *.

100 0 0.0 p.%,%

p.

\\t N.

y'.\\',

\\\\

8 t.

\\

in g

$Y

- 1.0

\\

0,0

(

).

l I 't t

i i

_300.0

-2.0 0.0 5.0 to0 0.0 6.0 10.0 Time (sec)

Time (sec)

Figure 45 Plant Response to Press, Regulator Failure (BOC8 to EOC8 MELLL -

HALING)

Page 72

~

ggpEND J1103150g m,oe nu.

ve e m... R,.e

.o

*

Ave Surface Heat Flux

*

Safety Valve Flow 150 0 - --- Core INet Flow 125 0

--- Relief Valve Flow

- -- Core (Net Subcooling

- * - Bypass Valve Flow 1

100.0 m M

- - - - ~***

75.0

/

g q,h g

g

,s.)

50 0 25 0 I-

-a.....

0.0 I

I

- 25.0 00 9.5 19.0 0.0 9.5 19 0 Time (sec)

Time (sec) i Level (6nch-REF-SEP-SKRT)

Void ReactMty Vessel Steam Flow

*

Dropler ReactMty 150 0

--- Turtune Steam Flow 1.0

--- Scram ReactMty

--- Feedv.atef Flow

--- Total ReactMty G

100 0 0.0

-,, v. r. 7, ;; -a e

g',

j g

l,'

i l

I. ' \\

l I' ". \\..'

\\.

50.0 1

- 1.0 I:

i',

I

i. ::,s l.,

T.. "

i.

g....

i lll ll 1,

0.0

- 2.0 O.0 9.5 19.0 00 9.5 19.0 Time (sec)

Time (sec)

J Figure 46 Plant Response to' FW Controller Failure (BOC8 to EOC8 MELLL &

FWHOOS - HALING)

Page 73

i UVER BEND J1103150SRLR (eload 7 Rev,0 4

Neutron Flux Voss31 Press Ree (psi)

Ave Suriace Hott Flus

Safety VaNo Flow 160.0

- Core inlet Flow 300 0

--- Relief Valve Flow

--- Bypass VaNo Flow J

100 0 200.0

~\\ y K

's.

-q

%e

' ' ' ).] '..'

60.0 100.0 0.0 00 00 30 6.0 00 3.0 60 Time (sec)

Time (sec) i Level (inch-REF-SEP-SKRT)

Vo6d eactMty Veteel Steam Flow r ReactMty

+

=

Tu$ine Steam Flow 1.0 200 0 Scram eacti Foodwater Flow

- - Total R g

~

a l

100.0

}g 00

~

\\'

[ *,,~ ~ '..-

\\

t; l ',

j-s 0.0

,," 1'r.- - - -

- 1.0 g,1

',, e,'

C g

\\i 1 'I I

I I

I

-100.0

-2.0 O.0 3.0 60 0.0 3.0 6.0 Time (sec)

Time (sec)

Figure 47 Plant Response to Load Reject w/o Bypass (BOC8 to EOC8 MELLL &

FWHOOS - HALING) 9 Page 74

-.. - =

tlVER BEND J1103150SRLR teload 7 Rev. 0 Neutron Flum Vessel Press Rise (psi)

* *

Ave Suriace Heat Flux

Safety Valve Flow i

150.0 -- --- Core inlet Flow 300 0

--- Rehof Valve Flow

Bypass Valve Flow 100.0 200.0 N

g% v.,

g g

%a

>. s,

'**.. ~~'~~~

100.0 60_0 c

00 O.0 O.0 30 60 0.0 3.0 6.0 Time (sec)

Time (sec)

I Levoi(inch REF-SEP-SKRT)

Void. seWvity

* *

Vessel Steam Flow Doppi e Reactivity

--- Turtnne Steam Flow 1.0 200.0

-- Scram

--- Foodwater Flow

- - Total R i

g l.\\

100.0 0.0 7 '. '. **

,~.-

g

}

Ii g

'..*'s..

{

0.0

- f- - 8 ;8 - - - -- -

- 1.0

\\

\\'

g\\

\\

I 100 0

- 2.0 O.0 3.0 6.0 00 30 6.0 Time (sec)

Time (sec)

Figure 48 Plant Res, wse to 'Ibrbine Trip w/o Bypass (BOC8 to EOC8 MELLL &

FWHOOS - HALING)

Page 75

(IVER BEND J1103150SRLR (eload 7.

Rev, O Neutron Flux Vessel Press Rise (psi)

Ave Surface Heat Flut Safety Valve Flow 150.0 Core irdet Flow 200.0

--- Rehof Valve Flow

--- Bypass Valve Flow 100.0 200.0 4

~

g g

?,*

60.0 100.0

%,~~.

(------.

00 0.0 O.0 5.0 10.0 0.0 6.0 10.0 Time (sec)

Time (sec)

Level (lnch-REF-SEP-SKRT)

V Reacti j

+ Vessel Steam Flow r

vtty 200.0 - --- Turtnne Steam Flow 1.0

- Se eactivity

- - - roodwater Flow

-T

'vtty G

4 t

} 100.0 y ~.~.

0.0 T.

y*

y

'n

~ "-

f -1.0 I*

0.0 E

).

\\\\i l l

\\ '! '

I 100.o t

- 2.0 0.0 5.0 10.0 0.0 6.0 10.0 Time (sec)

Time (sec)

Figure 49 Plant Response to Press. Regulator Failure (BOC8 to EOC8 MELLL &

FWH00S - HALING)

Page 76

tiVER BEND J1103150SRLR teload~1 Rev.0 Neutron Flux h

Vessel Press Rise (psi)

)

Ave Surface Host Flux

* *

Safety Valve Flow 160 0

--- Coro inlet Flow 125 0 - --- Rehof Valve Flow

- -- Core inlet Subcoohng

--- Bypass Valve Flow

~ ~ ~ ~ ~

100.0

-'-^~--~~-~~l l ',

75 0

,\\

d

'. N

\\

',',N, 50.0 25 0 I

"~

i e,

M.

'_f......

00

-a0 00 20 0 0.0 20.0 Eme(Sec)

Eme(Sec) l Leve4(inch-REF-SEP-eKRT)

Vold Reecovity Vessel Steam Flow

* * *

Doppler Reactivity 150.0

--- Turbine Steam Flow 1.0 - --- Scrcm Reactivtty

--- Feedwater Flow

- - - Total Reactivity c.

e i

\\

h

~~~

o' y 100.0

()

g0.0

-,,., =....,,,,, /j, /

t.

II b.

l t;\\

i.

P' i

50.0 cl,::f'bf....

- 1.0 I

2

+ i.

0.0

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Eme (sec)

Figure 50 Plant Response to FW Controller Failure (BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) HBB)

Page 77

VER BEND J1103150SRLR load 7 Rev.0 1

Neutron Flux Vessel Press Rise (psi) 1 Ave Surface Heat Flux Safety Valve Flow 150 0 Core irget Fiow 300.0

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Figure 51 Plant Response to Locd Reject w/o Bypass (BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST)IIBB) l l

Page 78 l

l

, - - - ~

~

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-- Vessel Press Rise (psi)

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Figure 52 Plant Response to 'Ibrbine ' hip w/o Bypass (BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) HBB)

Page 79 LsY

(IVER BEND J1103150SRLR (eload 7 l(evJ Neverm Flux Vessel Press Rise (psi)

* * *

Ave Surface Heat Flux

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=

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Figure 53 Plant Response to Press. Regulator Failure (EOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) HHB)

Page 80

(IVER BEND J1103150 SRI R teload 7 Rev 0

[1ron Flum Vessel Press Rise (psi)

Ave Surface Heat Flux Safety Vatve Flow 160 0

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Figure 54 Plant Response to FW Controller Failure (BOC8 to EOC8-4006 mwd /MT (1820 mwd /ST) FWHOOS - HBB)

Page 81

. - = -

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LIVERDEND J1103150SRLR teload 7 Rev,0 Neutron Flux Vessel Press Rise (psi)

Ave Surtece Heat Flux

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Time (sec) l Figure 55 Plant Response to Load Reject w/o Bypass (BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) FWHOOS - HBB)

Page 82 I

i RIVER BEND J1103150SRLR Reload 7 RgyJ 1

Neutron Flux Vessel Press Rise (psi)

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Figure 56 Plant Response to 'Ibrbine 'IYip w/o Bypass (BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) FWHOOS - HBB)

Page 83

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Figure 58 Plant Response to FW Controller Failure (BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST)ICF-HBB)

Page 85

~

(IVER BEND Jl103150SRLR teload 7 -

Rev,0 Neutrori Flux Vessel Press Rise (psi)

-

Ave Surface Heat Flux Safety Vane Flow 150.0 Core inlet Flow 300.0 - --- Relief VaNo Flow

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Figure 59 Plant Response to Load Reject w/o Bypass (BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST)ICF-HBB)

Page 86

A

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Figure 61 Plant Response to Press. Reeulator Failure (BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST)ICF-HBB)

Page 88

UVERJEND J1103150SRLR teload i Rev, 0 Ngupch'FIlu Vessel Press Fese (psi)

A

- -' ~~7 ve Surface Heat Rux

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Level (inch REF-SEP-SKRT)

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Figure 62 Plant Response to FW Controller Failure (BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST)ICF & FWTR -HBB)

Page 89

RIVER BEND J1103150SRLR Reload 7 Rev.O Neutron Flux Vessel Press Rise (psi)

-

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Figure 63 Plant Response to Load Reject w/o Bypass (BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST)ICF & FWTR -HBB)

Page 90

I RIVER)/END J1103150SRLR Reload Rev.0 Neutron Flux Vessel Press Rise (psi)

I Ave Surface Heat Flux

- Safety Valve Flow 150.0 - -- -- Core inlet Flow 300.0 - --- Rehof Valve Flow

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Figure 64 Plant Response to 'Ibrbine Trip w/o Bypass (BOC8 to EOC8.-2006 mwd /MT (1820 mwd /ST)ICF & FWTR -HBB)

Page 91

UVER BEND J1103150SRLR (eload 7 Rev.0 Neutron Flux Vessel Press Rise (psi)

* * *

Ave Surface Heat Flux

Safety Valve Flow 150.0

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s

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.. Vessel Steam Flow

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Figure 65 Plant Response to Press. Regulator Failure (BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST)ICF & FWTR -HBB)

Page 92

-, _ _.. =.

~_

RIVER BEND J1103150SRLR R. eload 7 Rev.O Neutron Flux Vessel Press Rise (psi)

- - Ave Surface Heat Flux

--- CopreRow-* '.J Safety Valve Flow 150 0 125 0

--- Rehof Valve Flow

-- core wet Subcoonna

--- sype s v tv. Fiow i

100.0 75.0 e,

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Figure 66 Plant Response to FW Controller Failure (BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) MELLL-HBB)

Page 93

RIVER BEND J1103150SRLR Reload 7 Rev.0 Neutron Flux Vessel Press Rise (psi)

- * - Ave Surface Heat Flux Safety Valve Flow 150.0

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Figure 67 Plant Response to Load Reject w/o Bypass (BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) MELLL-HBB)

Page 94

RIVER BEND J1103150SRLR Reload 7 Rev.0 Neutron Flux Vessel Press Rise (psi)

~~

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Figure 68 Plant Response to 'Ibrbine 'IYip w/o Bypass (BOC8 to EOCS-2006 mwd /MT (1820 mwd /ST) MELLL-HBB) i Page 95

UVER BEND J1103150SRLR teload 7 Rev.0 Neutron Flux Wssel Press Rise (psi)

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- 1.0 g.

l\\

a l.l' g

-100.0 I

I

- 2.0 O.0 5.0 10.0 0.0 5.0 10.0 Time (sec)

Time (sec)

Figure 69 Plant Response to Press. Regulator Failure (BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) MELLL - HBB)

Page 96

UVERpEND Jl103150SRLR (eload Rev.O j

i w

4 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 Subco Jing

--- Bypass Valve FL>w

~~''~

3 100.0 7

75.0 3

g

-..---------------g,.

p tg sN j

- 50.0

\\

25.0 f~~'

l Ff

-_.J.....

I I

0.0

- 25.0 0.0 9.5 19.0 0.0 9.5 19.0 Time (sec)

Time (sec)

Level (inch-REF-SEP-SKRT)

Void Reactivity

- - - Vessel Steam Flow

- - Doppler ReactMty 150.0 - --- Tuttine Steam Flow 1.0 - --- Scram React 6vity

- - - Feedwater Flow

- - - Total ReactMty w

v

_C 1

g 0.0

- -,-m -,-.n q ;. -

7 100.0 4

L. \\

4 3

ll l\\

e

- l,. ( \\

\\'

l 2

I';; \\

1

)-1.0 I'

50.c 1:::

Y.,*..

m i

F.... W e.e =

j l.e e. e '.*

I c

l*...

l 0.0 I

l 'l

- 2.0 I

' l' O.0 9.5 19.0 0.0 9.5 19.0 Time (sec)

Time (sec)

L Figure 70 Plant Response to FW Controller Failure (BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) MELLL & FWHOOS - HBB)

Page 97

RIVER BEND J110il50SRLR Reload 7 Rev.0 Neutron Flux Vessel Press Rise (psi)

)

Ave Surface Heat Flux

- - - Safety Vefve Flow 150.0

--- Core inlet Flow 300.0 - --- Relief Valve Flow l

--- Bypasa Valve Flow g 100.0 g 200.0 h

A jS e,,_,

g g

~ %._ s

.7

.,,,,_ ' ~ ~

50.0 100.0

/

0.0 O.0 O.0 30 6.0 00 3.0 6.0 Time (sec)

Time (sec) l l.

I Level (inch-REF-SEP-SKRT)

Void actMty

- - - - Vosssi Steam Flow r Reacts 200.0 - --- Turb6ne Steam Flow 1.0 Scrra

--- Feedwater Flow

-- Total ReactMty G

. ~..*......

m 2

Ij g 100.0 0.0 r.,,,..-

y e

\\

g t

l ',

\\

g!

-,-- k f - - - - -

- 1.0

{

0.0 x

c It li

\\

-100.0

-2.0 i

t 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec)

Time (sec)

Figure 71 Plant Response to Load Reject w/o Bypass (BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) MELLL & FWHOOS - HBB)

Page 98 1

l

___ d

RIVER BEND J1103150SRLR Reload 7 Rev.0 Neutron Flux Vessel Press Rise (psi)

Ave Suriace Heat Flux

- - - Safety Valve Flow 150 0 - --- Coro inlet Flow 300.0 - --- Relief Valve Flow

--- Bypass Valve Flow L

I g 100.0 g 200.0

,1

\\ y'.,

e

~.

e s

50.0 100 0 0.0 O.0 O.0 3.0 6.0 0.0 3.0 6.0 Time (sec)

Time (sec)

I Level (inch-REF-SEP-SKRT)

Void eactMty

- Vessel Steam Flow rR 200.0 - --- Tuttine Steam Flow 1.0

-- Scram

--- Foeow.ter Fio.

-- Toimi R.aciuty g

- - .=..,,

m l!!

f,,.,,.**

g 100.0 0.0 is r-t j

i, e

e il,, ' '

p

(

.a g1 0.0 L-

, -p - - - - -

- 1.0 l

C 11 l\\

p\\

\\

I l

-100.0

-2.0 O.0 3.0 6.0 0.0 3.0 6.0 Time (sec)

Time (sec)

Figure 72 Plant Response to Turbine 'IYip w/o Bypass (BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) MELLL & FWHOOS - HBB)

Page 99

RIVER BEND J1103150SRLR teload 7 Rev, O Neutron Flux Vessel Press Rise (psi)

- * - Ave Surface Heat Flux

SafetyVaNo Flow 150.0

-- Coro inlet Flow 300.0

--- Relief Valve Flow

--- Dypass Valve Flow 100.0 200.0 g

\\

Y-b

'.] s s

$0.0 100.0

~,

r---'-'"'-"'---"'-"'--'---'

' ~

O.0 O.0 O.0 5.0 10.0 0.0 5.0 10.0 Eme (deC)

Eme (SGC)

Level (inch-REF-SEP-SKRT)

V Re vity

- - - - - Vessel Steam Flow r ReactMty 200.0 - --- Turbine Steam Flow 1.0 - - - Scram ReactMty

--- Feedwater Flow

- Total ReactMty g

g 100.0 0.0 g

7

~._

-)i\\,..

i g

. \\'

i t

4 0.0

\\---

- 1.0 I.

d

=

1

\\\\

-100.0 I

- 2.0 0.0 10 10.0 0.0 5.0 10.0 Eme (Sec)

Eme (SGC)

Figure 73 Plant Response to Press. Regulator Failure (BOC8 to EOC8-2006 mwd /MT (1820 mwd /ST) MELLL & FWHOOS - HBB)

Page 100

UVER BEND J1103150.C'1LR

,lejoad 7 -

'aev. 0 Flux -

Vessel Press Rise (psi)

A Surface Heat Flux

- Safety Valve Flow 150.0 - ----

Ir#1 Flow 300 0

--- Relief Valve Flow

--- Bypass Valve Flow 100.0 g 200.0

's w

C N

E s~%s' Y

Y

~~,

50.0 100 0

/*

0.0 I

0.0 O0 4.0 8.0 0.0 4.0 8.0 lime (sec)

Time (sec)

.i f

Level (inch-REF-SCP-SKRT)

Void

' ty

..... Vessel Cleem Flow r

200.0

--- Turbine Steam Flow 1.0 Reactivity

--- Foodwater Flwr

---T Reactivity G

i i

0.0 h 100.0m m', \\.N.%

./.#

'.\\

<e

,s s,.

+\\g...,-

e

, s g

x

\\

i

&' ' ' '*ls

\\

0.0 N--------

- 1.0 l

C g ',,

\\

.1.

-100.0 I

I

- 2.0 O0 4.0.

8.0 0.0 40 8.0 Time (sec)

Time (sec)

Figure 74 Plant Response to MSIV Closure (Flux Scram)

Page 101

RIVER BEND J1103150SRLR l

Rejo_a_d,,7 Rev.0 m

River Bend Cycle 8 Option I A Stability Decay Ratios 1.00 0.90

"""" Boundary 0.80 0 B f

A A'

+

x B' o H1 FRE

\\'

o HOFRE

+ A' LOFH g 0.60 B' LOFH g

0 0.50 o

L e

o a

o o,40 0

0.30 0.20 0.10 0.00 0.00 0.10 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 Channel Decay Ratio Figure 75 Option I-A Stability Decay Ratios i

l Page 102

UVER BEND J1103150SRLR teload 7 Rev.O Appendix A Analysis Conditions t

To reflect actual plant param:ters recurately, the values shown in Table A-1 were used this cycle.

Table A-1 HBB Parameter Analysis Value inermalpower MWt 2894.0 Core fl v MIMhr 84.5 Reactor pressure, psia 1055.0 Inlet enthalpy, BTU /lb 527.9 Non-fuel power fraction 0.038 Steam flow analysis, Mlb/hr 12.46 Dome pressure, psig 1025.0 Turbine pressure, psig 985.9 No. of Dual Mode S/R Valves 9

4 Relief mode lowest setpoint, psig i133.0 Safety mode lowest setpoint, psig 1200.0 FWHOOS - HBB

~

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 0.038 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 i133.0 Safety mode lowest setpoint, psig 1200.0 Page 103

-~

(IVER BEND J1103150SRLR Teload 7 Rey, 0 ICF - HBB l

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 I

Non-fuel power fractinn -

0.038 Steam flow analysis, Mlb/hr 12.46 -

Dome pressure, psig 1025.0 hrbine 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

?

ICF & FWTR-HBB 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 Nor-fuel power fraction 0.038 Steam flow analysis, Mlb/hr 11.00 Dome pressure, psig 1025.0 Turbine pressure, psig 994.7 I

No. of Dual Mode S/R Valves 9

Relief mode lowest setpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0 i

Page 104

.~

RIVER BEND J1103150SRLR Rcload 7 Rev.0 l

MLLLL-HBB Parameter Analysis Value Thermal power, MWt 2894.0 Core flow, Mlb/hr 63.4 Reactor pressure, psia 1050.5 Inlet enthalpy, BTU /lb 520.3 Non-fuel power fraction 0.038 Steam flow analysis, Mlb/hr 12.45 Dome pressure, psig 1025.0 hrbine pressure, psig 986.0 No. of Dual Mode S/R Valves 9

Relief mode lowest setpoint, psig i133.0 Safety mode lowest setpoint, psig 1200.0 MELLL & FWHOOS - HBB Parameter A nalysis Value Thermal power, MWt 2894.0 Core flow, Mlb/hr 63.4 Reactor pressure, psia 1049.7 Inlet enthalpy, BTU /lb 505.6 Non-fuel power fraction 0.038 Steam flow analysis, Mlb/hr 10.99 Dome pressure, psig 1025.0 hrbine pressure, psig 994.8 No. of Dual Mode S/R Valves 9

Relief mode lowest setpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0 Page 105

UVER BEND J1103150SRLR

.Leload 7 Rev.O HALING Parameter Analysis Value Thermal power, MWt 2894.0 Core flow, MIMr 84.5 Reactor pressure, psia 1055.0 Inlet enthalpy, BTU /lb 527.9 Non-fuel power fraction 0.038 Steam flow analysis, MIMr 12.46 Dome pressure, psig 1025.0 hrbine pressure, psig 985.9

^

No. of Dual Mode S/R Valves 9

Relief mode lowest setpohn psig i133.0 Safety made lowest setpoint, psig 1200.0 FWHOOS - HALING Parameter Analysis Value Hermal power, MWt 2894.0 Core flow, MIMr 64.5 Reactor pressure, psia 1053.9 Inlet enthalpy, BTU /lb 516.8 Non-fuel power fraction 0.038 Steam flow analysis, MIMr 11.00 Dome pressure, psig 1025.0 lbrbine 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 t

Page 106

(IVERBEND Jl103150SRLR

.leload 7 Rev.0 ICF-HALING Parameter Analysis Value Thermal power, MWt 2894.0 Core Dow, Mlb/hr 90.4 Reactor pressure, psia 1056.4 inlet enthalpy BTU /lb 529.3 Non-fuel power fraction 0.038 -

Steam now analysis, Mlb/hr 12.46 Dome pressure, psig 1025.0 hrbine pressure, psig 985.9 No. of Dud Mode S/R Valves 9

Relief mode lowest setpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0 ICF & FMTR HALING Parameter Analysis Value Thermal power, MWt 2894.0 Core Dow, Mitvhr 90.4 Reactor pressure, psia 1055.1 Inlet enthalpy, BTU /lb 519.0 Non-fuel power fraction 0.038 Steam Dow analysis, Mlb/hr i1.00 Dome pressure, psig 1025.0 -

hrbine 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 4

Page 107

UVER BEND J1103150SRLR

. Reload 7 Rev.O MELLL-HALING Parameter Analysis Value Thermal pow.tr, MWt 2894.0 Core Dow, Mlb/hr 63.4 Reactor pressure, psia 1050.5 Inlet enthalpy, BTU /lb 520.3

~

Non-fuel power fraction 0.038 Steam Cow analysis, Mlb/hr 12.45 Dome pressure, psig 1025.0 Turbine pressure, psig 986.0 No. of Dual Mode S/R Valves 9

Relief mode lowest setpoint, psig i133.0

~

Safety mode lowest setpoint, psig 1200.0 MELLL & FWHOOS-HALING Parameter Analysis Value Thermal power, MWt 2894.0 Core flod, Mlb/hr 63.4 Reactor pressure, psia 1049.7 Inlet enthalpy, BTU /lb 505.6 Non-fuel power fraction 0.038 Steam flow analys 3, Mlb/hr 10.99 Dome pressure, psig 1025.0 Tbrbine pressure, psig 994.8 No of Dual Mode S/R Valves 9

Relief mode lowest setpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0 4

Page 108

'tIVER BEND J1103150SRLR teload 7 Rev.0 l

1 HBB Parameter Analysis Value hermal power, MWt 2894.0 Core flow, Mlb/hr 84.5 Rt ctor pressure, psia 1055.0 i

Inlet enthalpy, BTU /lb -

527.9 Non--fuel power fraction 0.03ff 1

Steam flow analysis, Mlb/hr 12.46 Dome pressure, psig 1025.0 Turbice pressure, psig 985.9 No. of Dual Mode S/R Valves 9

Relief mode lowest setpoint, psig 1133.0 Safety mode lowest setpoint, psig l

1200.0 i

FWHOOS - HBB Parametor Analysis Value Hermal 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 0.038 Steam flow analysis, Mlb/hr 11.00 4

Done pressure, psig 1025.0 i '

Turbine pressure, psig 994.7 No. of Dual Mode S/R Valves 9

Relief made lowest s:tpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0 i

l 1

1 i

Page 109

UVER BEND J1103150SRLR Reload 7 Rev.0 ICF-HBB Parameter Analysis Value Thermal power MWt 2894.0 Core flow, Mi%r 90.4 Reactor pressure, psia 1056.4 Inlet enthalpy, BTU /lb

$29.3 Non-fuel power fraction 0.038 Steam flow analysis, MIMr 12.46 Dome pressure, psig 10'25.0 Tbrbine pressure, psig 985.9 No. of Dual Mode S/R Valves 9

Relief mode lowest setpoint, psig

!!33.0 Safety mode lowest setpoint, psig 1200.0

~

ICF & FMTR -HBB Parameter Analysis Value Thermal power, MWt 2894.0 Core flow, MIMr 90.4 Reactor pressure, psia 1055.1 Inlet enthalpy, BTU /lb 519.0 Non-fuel power fraction 0.038 Steam flow analysis, Ml%r 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 i133.0 Safety mode lowest setpoint, psig 1200.0 Page 110

(IVER BEND J1103150SRLR (eload 7 Rev,d MELLL-HRH Parameter Analysis Value nermal power, MWt 28's.0 Core flow, Mlb/hr 03.4 Reactor pressure, psia 1050.5 Inlet enthalpy, BTU /lb

$20.3 Non-fuel power fraction 0.038 Steam flow analysis, MlWhr 12.45 Dome pressure, psig 1025.0 hrbine prenure, psig 981 0 No. of Dual Mode S/R Valves 9

Rellet mode lowest setpoint, psig i133.0 Safety mode lowest setpoint, psig 1200.0

~

MELLL & FWHOOS - HBB Parameter Analysis Value Wnial power, MWt 2894.0

Core flow, Mlb/hr 63.4

' Acactos pess*tse, psia 1049,7 Inlet enthalpy. BTU /lb

$05.6 Non-fuel power fractici.

0.038 Steam f.ow analysis,'~ ib/N 10 S '

M Dome pressure, psig 1025.0 hrbine pressure, pa.g 994.8 No. of Dual Mode S/R Valves 9

elicf mode lowest setpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0 4

i Page 111 l

.. _ ~ _

IIVER BEND Jil03150SRLR teload 7 Rev.0 Appendix B Alternate Analysis for Feedwater Temperature Reduction l

i To provide for improved operating flexibility and cycle extension for Cycle 8, expanded operating domain analyses were performed for increr,ed Core Flow (ICF) at 10M rated and intermittent use of Final Feedwater i

Temperature Reduction (I%VTR) to a temperature (at full power) of 320 degrees F. The analyses for cycle extension with ICF were performed at EEOC880cxposure point using appropriate thermal hydraulic condi.

~

tions. The analyse, for cycle extension with ICF and FF#TR was performed at EEEOC818 exposurc point achieved wid ICF and IFYTR using the appropriate thermal hydraulic conditions. Contained in this license submittal are results of all analyses evaluated for this licensing ac vity. The transient MCFR values for o

all analyses are given in Section 11. The analyses for ICF and Fi%TR bound the intermittent concurrent use of FFWTR from BOC to EEEOC operation with ICF and FFWTR.

10 EEOC8 identiries the rated power operanon caposwe potet anainable, using ICF only, for Cycle 8 the core average eaposure for EEOC8 is 29072 mwd /MTU(26374 mwd /ST).

11. EEEOCs ideatirws the tau d power operanon exposure point attainable, using ICF and FFWTR. For Cycle 8 tte core average exposure for LEEOC8 is 29,723 Mwd'MTU (26%$ Mwd /st).

Page 112

. - _-_.=_-_._ __ - _.- _

(IVERBEND J1103150SRLR teload 7 Rev.O Appendix C Basis for Analysis of Loss-of-Feedwster Heater Event The loss-of-feedwater heating event was analyzed at 102% rated power using the BWR Simulator Code (Reference C-1). De use of this code is permitted in GESTAR 11(Reference C-2) %e transient plots, neutron flux and heat flux values normally reported in Section 9 are not an output of the BWR Simul.nr Code; therefore, these items are not included in this document.

References; C-1. Steady-State Nuclear Methods, NEDE-30130-P-A, and NEDO-30130-A, April 1985.

C-2 General Electric Standard Application for Reactor Fuel, NEDE-240ll-P-A (latest approved version).

4 Page 113

(IVER BEND J11031509RLR teload 7 key.0 I

Appendix D Basis for Analysis of Core-Wide and Overpressurization Transients De Core-Wide and Overpressuritation Transients were analyzed with four valves out of sixteen operable

(

in relicf mode and five valves out of sixteen operkole 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. De analyses performed reflect the River Bend Station Technical Specifications, which permit opration with 4 valves in relief mode and 5 valves in safety (spring) mode.

l I

l Page 114 I

ggyEND Jl103150g Appendix E Basis for Analysis of Standby Llquid Control System Shutdown capability The minimum required boron shutdown margin is dependent on the fuel design type and the calculational method. De minimum required boron shutdown margin represents the biases and uncertainties needed to assure suberiticality. His is a OE recommended value and may be less restrictive than the River Bend specific technical specifications requirement for the liquid boron shutdown margin,in which esse 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%

4 Page 115

llVER13END Jil03150SRLR (eload 7 Rev, O I

Appendix F Off Rated Curves MCPR(p) l (Including EOlo.01 Conservative Adder) l 2.00 1.90

.' "O l.3

+

4,0 @

1.80

. l01 1.70 1 71

.h71 1.60-E 1.54

[ 1.50 N

-+-Below P Bypass, <= 50% Flow 1.40

-e-Below P Bypass, > 50% Flow tag

-e-Above P Bypass 1.32 1.20 1.10 1.00 O

20 40 60 80 100 Percent Core Power (%)

Figure 76 Operating Limit MCPR(p)

Page 116

11VER IlEND J1103150SRLR (eload 7 Rev.O Appendix F Off Rated Curves MCPR(f)

(including EOl 0,01 Conservative Adder) 2.00 1.90 1.80 1.70 1.60 a:

1,50 1.48 1.43 1.40 1.38 1.34 1.30 130 1.26 1.20 1.22 1.10 1.00 0

10 20 30 40 50 60 70 80 90 100 Percent Core Flow (%)

Figure 77 Operating Limit MCPR(f)

Page 117

(IVER DEND Jil03150SRLR leload 7 Rev. O Appendix F Off Rated Curves LHGR(p) & MAPLHGR(p) Multiplier 1.1000 1.0000 0 44000

[

1.0000 0.9523 0.9000 it 0.8000 ii O

5 l

l 0.7250 0.7000 4

5 5

0.6000 0.5894 0.5389 l

[5391 0.4000 0

10 20 30 40 50 60 70 80 90 100 Percent Core Power (%)

Figure 78 Operating Limit LHGR(p) & MAPLHGR(p) Multipliers Page 118

IIVER BEND Jil03150SRLR Reload 7 Rev, 0 J

Appendix F Off Rated Curves l

LHGR(f) & MAPLHGR(f) Multiplier 1.1000 1.0000 0 00000

^

1 0000 0.9779 0.9141 0.9000 0.8481 g

g 0.8000 8

5 n.

5

.7000 0

0.6873' is O

5 0.6000 0.5457 l

I 0.5000 0.4000 O

10 20 30 40 50 60 70 80 90 100 Percent Core Flow (%)

Figure 79 Operating Limit LHGR(O & MAPLHGR(O Multipliers Page 119

(IVER HEND J1103150SRLR (cload 7 Rev.0 Appendix G River Band Cycle 8 Rated OLMCPR Summary i

Section 11 of this report identifies all the MCPR values for pressurization and non-pressurization events.

The following table summarizes the limiting transients for the GE8x8EB and Gell fuel types at rated condi-tions.

Limiting MCPR at Rated Conditions (WITilOUT the EOl 0.01 conservative adder)

Exposure Range Gell GE8x8EB BOC to EOC8-2006 mwd /MT 1.28(set by: rtI-Mislocated) 1.28(set by: rt.thMislocated)

(1820 mwd /ST)

EOC8-2006 mwd /MT(1820 mwd /ST) 1.33 (see by: toad Rejection @ ICF) 128(set by: FitLMislxated) to EEEOC At EOl's request, the OLMCPRs reported for the limiting event at each exposure in the SRLR and the RBS COLR will be modified to include a 0.01 adder. This adder is at Entergy's request to provide an additional conservatism which could be drawn on if needed. The following table summarizes the limiting transients for the GE8x8EB and Gell fuel types at rated conditions with the EOI conservative 0.01 adder.

Limiting MCPR at Rated Conditions (WITH the EOI 0.01 conservative adder)

Exposure Range Gell GE8x8EB BOC to EOC8-2006 mwd /MT 1.29 1.29 (1820 mwd /ST)

EOC8-2006 MWo/MT(1820 mwd /ST) 1.34 1.29 to EEEOC

'Ihe MCPRp and MCPRf curves provided in Appendix F include the EOl conservative 0.01 adder.

Page 120

ML20212A729

Text

Response

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