Text

Rev 3 to 24A5188, Supplemental Reload Licensing Rept for Rbs,Reload 6,Cycle 7
	ML20212A740
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
	24A5188, 24A5188-R03, 24A5188-R3, NUDOCS 9710240223
	Download: ML20212A740 (90)
	v • d • e

.. .. - - . .- _ _ - . - .-_ . - _.- - -. . .. . . .

GE Nuclear Energy

' 24A5188 Revision 3 ClassI July 1997 24A5188, Rev. 3 Supplemental Reload Licensing Report i for River Bend Station Reload 6 Cycle 7 Approved Approved R. J. Reda, Manager J. L. Tuttle Fuel and Facility Licensing Fuel Project Manager 9710240223 971017 PDR ADOCK 05000458 p PDR

'IIVER BEND 24A5188 teload 6 Rev. 3 Important Notice Regarding Contents of This Report Please Read Carefully This report was prepared by General Electric Company (GE) solely for Entergy Opera-tions, Inc. (EOl) for EOl's use with the U. S. Nuclear Regulatory Commission (USNRC) for amending EOl's operating license of the River Bend Station. The information con-tained in this report !s 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 contraci between EOl and GE for fuel bundle fabrication and related services for Riv-er Bend Station and nothing contained in this document shall be construed as changing said contract. The use of this information, except as defined by said contracts, by anyone other than EOl for any purpose other than that for which it is intended, is not authorized; and with respect to any unauthorized use, neither GE nor any of the contributors to this document makes any representatlon or warranty (expressed or implied), as to the com-pleteness, accuracy or usefulness of the information contained in this document or that l such use of such information may not infringe privately owned rights; nor do they assume l any responsibility for liability or damage of any kind which may result from such use of l such information.

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UVER BEND 24A5188 teload 6 Rev.3- -l Acknowledgement The engineering and reload licensing analyses, which form the technical basis of this Supplemental Reload Licensing Report, were performed by D. P. Stier. This Revision to the Supplemental Reload Licensing Repon was prepared by W. E. Russell Revision 3 of this document has been verfied by M. Harding.

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RIVER BEND 24A5118 Reload 6 Rev.1 ne basis for this report is General Electric Standant Applicationfor Reactor Fuel, NEDE-24011-P-A-10, February 1991; and the U.S. Supplement, NEDE-24011-P-A-10-US, March 1991.

1. Plant-unique Items Appendix A: Analysis Conditions Appendix B: Alternate Analysis for Feedwater Temperature Reduction Appendix C: Basis for Analysis of Loss-of-Feedwater Heater Event Appendix D: Basis for Analysis of Core-Wide and Overpressurization Transients Appendix E: Basis for Analysis of Loss-of-Coolant Accident Appendix F: Basis for Analysis of Standby Liquid Control System Shutdown Capability Appendix G: Plant Operation Above the Rated Load Line Up to Rated Power Appendix H: Off Rated Curves

2. Reload Fuel Bundles Cycle Fuel Type Loaded Number Irradiated:

GE8B-P8SQB 333-10GZ-120M-4WR-150-T (GE8x8EB) 4 8 GE8B-P8SQB 334-10GZ-120M-4WR-150-T (GE8 x8EB) 5 1%

GE8B-P8SQB 334-10GZ2-120M-4WR-150-T (GE8x8EB) 6 132 GE8B-P8SQB 334-11 GZ-120M-4WR-150-T (GE8x8EB) 6 56 Utx gel 1 -P9 SUB353-10GZ-120T-146-T (gel l) 7 128 gel 1 -P9SUB354-13GZ-120T-146-T (gel 1) 7 64 GE l l-P9S UB 354-14GZ-120T-146-T (GE l l ) 7 40 Total 624

3. Reference Core Loading Pattern Nominal previous cycle core average exposure at end of cycle: 26043 mwd /MT

( 23626 mwd /ST)

Minimum previous cycle core average exposure at end of cycle 25259 mwd /MT from cold shutdown considerations: ( 22915 mwd /ST)

Assumed reload cycle core average exposure at beginning of 13188 mwd /MT cycle: ( 11964 mwd /ST)

Assumed reload cycle core average exposure at end of cycle: 26250 mwd /MT

( 23814 mwd /ST)

Reference core loading pattern: Figure 1 Page 4

11VER BEND 24A5188 Reload 6 Rev.3

4. Calculated Core Effective Multiplication and Control System Worth - No Volds,20 C Beginning of Cycle, kenecove Uncontrolled 1.118 Fully controlled 0.953 Strongest control rod out 0.981

- R, Maximum increase in cold core reactivity with exposure into cycle, Ak 0.003

5. Standby Liquid Control System Shutdown Capability (S" Appendix F)

Boron Shutdown Margin (Ak)

(ppm) (20*C, Xenon Free) 660 0.021

6. Reload Unique GETAB Anticipated Operational Occurrences (AOO) Analysis Initial Conditim Parameters Exposure: BOC7 to EOC7100%P/100*r' Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (1000 lb/hr) gel 1 1.45 1.39 1.36 1.035 6.307 112.4 1.27 GE8x8EB 1.20 1.51 1.40 1.051 6.821 109.7 1.17 Exposure: BOC7 to EEOC7 WITH ICF 100%P/107%F Peaking Factors

Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR 4

(MWt) (1000 lb/hr) gel 1 1.45 1.40 1.38 1.035 6.333 120.9 1.27 GE8x8EB 1.20 1.51 1.40 1.051 6.826 118.3 1.18 Exposum BOC7 to EEEOC7 WITH ICF AND FFWTR 100%P/107%F 320 Deg. F Peaking Factors

~

Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (1000 lb/hr)

Gell 1.45 1.46 1.37 1.035 6.612 119.6 1.25 GE8x8EB 1.20 1.55 1.40 1.051 7.016 116.9 1.18 Page 5 d

'UVER BEND 24A5188 Teload 6 Rev.3 Exposure: BOC7 to ECC7 FWTR 100%P/100%F 320 Deg. F Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (10001%r) gel 1 1.45 1.46 1.34 1.035 6.58I Ii1.1 1.25 GE8x8EB 1.20 1,55 1.40 1.051 6.990 i 108.4 1.17 Exposure: BOCHo EOC7- HALING 100%P/100%F Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axlal R-Factor Power Flow MCPR (MWt) (1000 IMr)

Gell 1.45 1.50 1.16 1.035 6.768 108.0 1.25 GE8x8EB 1.20 1.56 1.40 1.051 7.079 108.0 1.12

Exposure: BOC7 to EEOC7 WITH ICF - HALING 100%P/107%F Peaking Factors

, Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Fl<,w MCPR (MWt) (10M 1%r) gel 1 1.45 1.50 1.18 1.035 6.778 116.5 1.26 l

GE8x8EB 1.20 1.57 1.40 1.051 7.123 116.3 1.13 Exposure: BOC7 to EEEOC7 WITH ICF AND FFWTR - HALING 100% P/107%F 320 Deg.F Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flo r MCPR (MWt) (1000 IMr) gel 1 1.45 1.55 1.23 1.035 6.993 115.4 1.25 GE8x8EB 1.20 1.61 1.40 1.051 7.273 115.1 1.14 Exposure: BOC7 to EOC7 WITH FFWTR - HALING-100%P/100%F 320 Deg. F Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (1000 lMr) gel 1 1.45 1.54 1.21 1.035 6.947 107.1 1.24 GE8x8EB 1.20 1.60 1.40 1.051 7.245 106.7 1.12 i

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RIVER BEND 24A5188 a- Reload 6 Rev. 3 Exposure: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100%P/100%F Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flew MCPR (MWt) (10001%r)

Gell 1.45 . 56 1.41 1.035 7.056 105.0 1.24 GE8x8EB 1.20 1.60 1.40 1.051 7.261 106.9 1.09 Exposure: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100%P/107#/cF Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (1000 lMr)

GEIi 1.45 1.57 1.39 1.035 7.093 113.0 1.26 GE8x8EB 1.20 1.61 1.40 1.051 7.301 115.1 1.10 Exposure: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100%P/107 %F 320 Deg. F Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial K-t a tor Power Flow MCPR (MWt) (1000 lb/hr)

GEI1 1.45 1.66 1.42 1.035 7.489 110.0 1.22 GE8x8EB 1.20 1.66 1.40 1.051 7.513 111.1 1.09 Exposure: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100% P/100%F 320 Deg. F Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR

~

( M W t) (1000 IMr) gel 1 1.45 1.65 1.44 1.035 7.449 102.1 1.20 GE8x8EB 1.20 1.66 1.40 1.051 7.500 102.9 1.08 J

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UVER BEND 24A5188 teload 6 Rev. 3

7. Selected Margin Improvement Options Recirculation pump trip: Yes-4 Rod withdrawallimiter: Yes Thermal power monitor: Yes 4

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 (See Appendix G)

Extended load line limit: No Maximum extended load line limit: No increased core flow througitout 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: No Moisture separator reheater OOS: No "Ibrbine bypass system OOS: No Safety / relief valves OOS: No(See Appendix D)

ADS OOS: No EOC RIT OOS: No Main steam isolation valves OOS: No Feedwater Heater OOS Yes Page 8

RIVER BEND 34A5188 Reload 6 Rev. 3

9. Com-wide AOO Analysis Results Methods used: GEMIN1; GEXL-PLUS Exposure range: BOC7 to EOC7 100% P/100 % F Uncorrected ACPR Event ) ux Q/A Gell GE8x8EB Fig

(%NBR) (%NBR)

FW Controller Failure 291 113 0.18 0.09 2 Load Reject w/o Bypass 386 114 0.20 0.10 3 Turbine Trip w/o Bypass 336 112 0.18 0.08 4 '

Press. Regulator Failure 144 104 0.09 0.04 5 Exposure range: BOC7 to EEOC7 EEOC WITH ICF 100%P/107%F Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR) (%NBR)

FW Controller Failure 329 115 0.18 0.10 6 Load Reject w/o Bypass 429 116 0.20 0.12 7

'Ibrbine Trip w/o Bypass 381 113 0.19 0.10 8 Press. Regulator Failure 144 105 0.09 0.04 9 Exposure range: BOC7 to EEEOC7 WITH ICF AND FFWTR 100%P/107%F 320 Deg. F. -

Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR) (%NBR) '

FW Controller Failure 311 118 0.18 0.11 'l Load Reject w/o Bypass 381 115 0.18 0.10 1I Turbine Trip w/o Bypass 335 112 0.16 0.08 12 Press. Regulator Failure 146 105 0.10 0.05 13 Exposure range: BOC7 to EOC7 - 100%P/100% F 320 Deg. F L

Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR) (%NBR)

FW Controller Failure 289 116 0.18 0.10 14 Load Reject w/o Bypass 361 114 0.18 0.09 15 Turbine Trip w/o Bypass 314 111 0.16 0.07 16 Press. Regulator Failure 144 105 0.10 0.04 17 ,

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1 RIVER BEND 24A5188 Reload 6 Rev.3 Exposure range: BOC7 to EOC7 - HALING 100%P/100%F Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

^

(%NBR) (%NBR)

FW Controller Failure 198 107 0.16 0.04 18 Load Reject w/o Bypass 267 108 0.18 0.05 19 hrbine Trip w/o Bypass 231 105 0.16 0.03 20 Press. Regulator Failure 142 103 0.07 0.03 21 Exposure range: BOC7 to EEOC7 WITH ICF - HALING 100%P/107%F Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

, (%NBR) (%NBR)

FW Controller Fai'are 229 109 0.17 0.05 22 Load Reject w/o '.sypass 313 110 0.19 0.07 23 hrbine Trip w/.' Bypass 266 107 0.17 0.05 24 Press. Regulator Failure 143 104 0.07 0.03 25 Exposure range: BOC7 to EEEOC7 WITH ICF AND FFWTR - HALING 100%P/107%F

, Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR) (%NBR)

FW Controller Failure 234 112 0.18 0.07 26 Load Reject w/o Bypass 310 110 0.18 0.07 27 hrbine Trip w/o Bypass 256 107 0.16 0.04 28 Press. Regulator Failure 144 104 0.09 0.03 29 Exposure range: BOC7 to EOC7 - HALING-100% P/100% F 320 Deg. F Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR) (%NBR)

FW Controller Failure 205 110 0.17 0.05 30 Load Reject w/o Bypass 274 108 0.17 0.05 31 Turbine Trip w/o Bypass 228 105 0.15 0.03 32 Press. Regulator Failure 144 104 0.08 0.03 33 Page 10

RIVER BEND 24A5188 l

, Reload 6 Rev. 3

, l Exposure range: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100%P/100%F l

Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR) (%NBR)

FW Controller Failure 153 104 0.14 0.03 34 Load Reject w/o Bypass 204 104 0.17 0.02 35

)

Turbine Trip w/o Bypass 184 102 0.15 0.00 36 Press Regulator Failure 143 103 0.06 0.03 37 Exposure range: BOC7 to EOC7-3693 mwd /MT (3350 mwd /St) 100%P/107%F Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR) (%NBR)

FW Controller Failure 174 105 0.16 0.03 38 Load Reject w/o Bypass 234 106 0.19 0.03 39 Turbine Trip w/o Bypass 205 103 0M 0.01 40 Press. Regulator Failure 143 103 0.06 0.03 41 Exposure range: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100%P/107%F 320 Deg. F Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR) (%NBR)

FW Controller Failure 144 108 0.14 0.06 42 Load Reject w/o Bypass 196 104 0.15 0.01 43 Turbine Trip w/o Bypass 168 101 0.13 0.00 44 Press. Regulator Failure 144 104 0.06 0.03 45 Exposure range: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100% P/100%F 320 Deg. F Uncorrected ACPR Event Flux Q/A Gell GE8x8EB Fig.

(%NBR) (%NBR)

FW Controller Failure 129 108 0.13 0.05 46 Load Reject w/o Bypass 173 102 0.13 0.01 47 Turbine Trip w/o Bypass 150 100 0.11 0.00 48 Press. Regulator Failure 144 103 0.06 0.03 49 Page 11

RIVER BEND 24A5188 Reload 6 Rev.3

10. Local Rod Withdrawal Error (With Limiting Instrument Failure) AOO Summary The generic bounding BWR/6 rod withdrawal error analysis described in NEDE-240ll-P-A-US is not ap-plied. A cycle-specific rod withdrawal analysis found the AMCPR to be 0.13 based upon a one foot with-drawal, and is not bounded by the generic RWE analysis reported in the referenced report.

11. Cycle MCPR Valuest In agreement with commitments to the NRC (letter from M. A. Smith to the Document Control Desk,10CFR Part 21, Reportable Condition. Safety Limit MCPR Evaluation, May 24,19%) a cycle-specific Safety Limit MCPR calculation was performed, and has been reported ii. 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.

3. The full cycle exposure range was analyzed.

Safety limit: 1.10 Single loop operation safety limit: 1.12 Non-nressurization events:

Exposure range: BOC7 to EOC7 Gell GE8x8EB Rod Withdrawal Error 1.23 1.23 Loss of Feedwater Heating 1.21 1.21 Fuel Loading Error- Rotated 1.20 1.25 Fuel Loading Error- Mislocated 1.25 1.25 Pressurization events:2 Exposure range: BOC7 to EOC7100%P/100F Exposure point: EOC7 Gell GE8x8EB FW Controller Failure ; 1.29 1.20 Load Reject w/o Bypass l.31 1.21 Turbine Trip w/o Bypass 1.30 1.19 i Press. Regulator Failure 1.20 1.15

1. Deleted.

Page 12 l

l I

RIVER BEND 24A5188 Reload 6 Rev. 3 Exposure range: BOC7 to EEOC7 WITH ICF 100%P/107%F Exposure point: EEOC7 Gell GE8x8EB FW Controller Failure 1.30 1.21 Load Reject w/o Bypass 1.32 1.22 Turbine Trip w/o Bypass 1.30 1.20 Press. Regulator Failure 1.20 1.15 Exposure range: BOC7 to EEEOC WI'FH ICF AND FFWTR 100%P/107%F 320 Deg. F Exposure point: EEEOC7 Gell GE8x8EB FW Controller Failure 1.30 1.22 Load Reject w/o Bypass 1.29 1.21 hrbine Trip w/o Bypass 1.28 1.19 Press. Regulator Failure 1.22 1.16 Exposure range: BOC7 to EOC7100%P/100%F 320 Deg. F Exposure point: EOC7 Gell GE8x8EB FW Controller Failure 1.29 1.21

~

Load Reject w/o Bypa9 1.29 1.20 hrbine Trip w/o Bypass _ l.28 1.18 Press. Regulator Failure 1.21 1.15 Exposure range: BOC7 to EOC7 - HALING 100%P/100%F Exposure point: EOC7 Gell GE8x8EB FW Controller Failure 1.27 1.15 Load Reject w/o Bypass 1.30 1.16 hrbine Trip w/o Bypass 1.28 1.14 Press. Regulator Failure . 1.18 1.14

2. ECCS MCPR value is imuting for Gell fuel (1.28), the ECCS MCPR value for GE8 fuel is 1.17.

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1 RIVER BEND 24A5188 Reload 6 Rev. 3 Exposure range: BOC7 to EEOC7 WITH ICF - HALING 100%P/107%F Exposure point: EOC7 Gell GE8x8EB FW Controller Failure 1.28 1.16 Load Reject w/o Bypass 1.31 1.17 Turbine Trip w/o Bypass 1.29 1.15 Press, Regulator Failure 1.18 1.14 Exposure range: BOC7 to EEEOC7 WITH ICF AND FFWTR - HALING 100%P/107%F Exposure point: EEEOC7 Gell GE8x8EB

~

FW Controller Failure . 29 1.18 Load Reject w/o Bypass 1.30 1,17 Turbine Trip w/o Bypass 1.28 1.15 Press. Regulator Failure 1.21 1.14 Exposure range: BOC7 to EOC7 FFWTR -HALING-100%P/100%F Exposure point: EOC7 Gell GE8x8EB FW Controller Failure 1.28 1.16 Load Reject w/o Bypass 1.28 1.16 Turbine Trip w/o Bypass 1.26 1.13 Press. Regulator Failure 1.20 1.14 Exposure range: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100%P/100%F Exposure point: EOC7-3693 mwd /MT (3350 mwd /ST)

, Gell GE8x8EB FW Controller Failure 1.22 nc*

Load Reject w/o Bypass 1.26 nc

'Ibrbine Trip w/o Bypass 1.24 nc Press. Regulator Failure 1.18 nc ne . noi calculated Exposure range: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) li,0%P/107%F Exposure point: EOC7-3693 mwd /MT (3350 mwd /ST)

Gell GE8x8EB FW Controller Failure 1.24 nc Load Reject w/o Bypass 1.28 nc Turbine Trip w/o Bypass 1.26 nc Press. Regulator Failure 1.18 nc Page 14

RIVER BEND 24A5188 Reload 6 Rev.3 Exposure range: BOC7 to EOC7-3693 mwd /MT (3350 6tWd/ST) 100%P/107% F 320 Deg.F. ,

Exposure point: EOC7-3693 mwd /MT (3350 mwd /ST)

Gell GE8x8EB FW Controller Failure 1.23 nc Load Reject w/o Bypass 1.24 nc Turbine Trip w/o Bypass 1.22 nc Press. Regulator Failure 1.18 nc Exposure range: BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) 100%P/100%F 320 Deg. F.

Exposure point: EOC7-3693 mwd /MT (3350 mwd /ST)

Gell GE4x8EB FW Controller Failure 1.21 nc Load Reject w/o Bypass 1.22 nc Turbine Trip w/o Bypass 1.19 nc Press. Regulator Failure 1.18 nc

12. Overpressurization Analysisliummany Psi Pv Plant Event (psig) (psig) Response MSIV Closure (Flux Scram) 1282 1311 Figure 50

13. Loading Error Results3 Variable water gap misoriented bundle analysis: Yes4 Misoriented Fuel Bundle ACPR I G E8 B -P8S Q B 334- 10GZ2- 120M-4 WR- 150-T 0.15 gel 1-P9SUB353-1OGZ-120T-146-T 0.10 Misloested bundle analysis: Yes ACPR 0.15

3. see letter, J. F Klapproth (GE) to R. C. Jores. Jr. (NRC), Rotated Bundle Evaluation, July 20.1992. This letter identifies that the totation orc-lattiec fuel designs inay result in a significant CPR change.

4. Includes a 0.02 penalty due to vanable water gap R-factor uncertainty.

Page 15

UVER BEND 24A5188 Jelnd 6 - Rev.3

14. Control Rod Drop Analysis Results ,

River Bend Station is a banked position withdrawal sequence plant; therefore, the control rod drop accident -

. analysis is not required. NRC approval is documented in NEDE-240ll-P-A-US.

i r

15. Stability Analysis Results GE SIL-380 recommendations have been included in the River Bend Station operating procedures and Tech.

E nical Specifications; therefore, the stability analysis is not required. NRC approval for deletion of a cycle-specific stability analysis is documented in Amendment 8 to NEDE-240ll-P-A-US. River Bend Station recognizes the issuance of NRC Bulletin No. 88-07, Supplement 1, Power Oscillations in Boiling Water Rt 2ctors (BWRs), and will comply with the recommendations contained therein.

16. Loss-of-Cooit 't ident Results LOCA eethod used: SAFE /GESTR

The LOCA analysis results for all fuel types loaded in the current cycle are presented in Section 5 and Section 6 of River Bend Station SAFER /GESTR-LOCA loss-of-Coolant Accident Analysis, NEDC-32640P, June 1997. Tcese 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%. 'Ihe SLO analysis resulted in a

. MAPLHGR nultiplier of 0.79 for Gell and 0.87 for GE8x8EB. The following table lists the least limiting and most ihniting MAPLHORs for the Cycle 7 fuel:

4 k

t

't a

4 Page 16

. RIVER BEND 24A5188 Reload 6 Rev.3

16. Loss-of-Coolant Accident Results (cont)s Bundle Type: GE8B-P8SQB333-10GZ-120M--LWR-150-T Average Planar Exposure MAPLHGR(kW/ft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 11.29 11.80 0.20 0.22 11.35 11.84 1.00 1.10 11.48 11.95 2.00 2.20 11.67 12.12 3.00 3.31 11.87 12.28 4.00 4.41 12.07 12.45 3 5.00 5.51 12.29 12.64 6.00 6.61 12.53 12.79 7.00 7.72 12.71 12.92 8.00 8.82 12.87 13.05 9.00 9.92 13.02 13.17 10.00 11.02 13.15 13.27 12.50 13.78 13.19 13.22 15.00 16.53 12.90 12.92 20.00 22.05 12.29 12.31 25.00 27.56 11.69 11.70 35.00 38.58 10.44 10.46 45.00 49.60 8.98 9.07 50.00 55.12 6.45 6.55 e

f

5. For fonnat explananon. see letter J. S. Charnley (GE) to M. W. Hodges (NRC). Recommended MAPUfGR Technical Spect/lcations for MulapIt Imtsce fuelDesigns. March 9.1987, Most Linuting and least Limaung refer to the lowest and highest hnuts, respectively. of any ennched latuce in the bundle.

Page 17

IIVER BEND 24A518 Reload 6 Rev.

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

Bundle Type: gel 1-P9SUB354-14GZ-120T-146-T Average Planar Exposure MAPLHGR(kW/ft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 l1.23 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. I3.78 12.65 12.82 15.00 16.53 12.40 12.55 17.50 19.29 12.10 12.14 20.00 22.05 11,73 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 -

6.66

6. For format explanation. see letter J. S. Charnley (GE) to M. W. Hodges (NRC), Recommend.*d MAPUlGR Technical Spec @canonsfor i Malnple immce feel Desitas. March 9.1987. Most Limiting and Least Limiting refer to the lowest and highest linuts. respecuvely. of any ennched lamcc in the bundle.

Page 18

IIVER BEND 24A5188 Relo-d 6 Rev.3

16. Loss-of-Coolant Accident Results (cont)7 Bundle 1)pe: GEIl-P9sUB354-13GZ-120T-146-T Average Planar Exposure MAPLHGR(kW/ft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 11.39 11.65 0.20 0.22 11.44 11.69 1.00 1.10 11.53 11.77 2.00 2.20 11.65 11.88 3.00 3.31 11.77 11.99 4.00 4.4 I i1.89 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 12.64 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 l

7. For fornw explanation, see letter J. S. Charnley (GE) to M. W. Hodsts (NRC). Recommended MAPulGR Technica1 Specifications for

. -r *

w M :. n av ,'

% sr. March 9,1987. Most Linuung and Least Linuung refer to the lowest and highest hnuts, respecovely, of any

/

>~

Page 19 w't x~

RJVER BEND 24A5188 Reload 6 Rev, 3 16, lef-Coolant Accident Results (cont)8 Bundle 'I)pe: gel 1-P9SUB 353-10GZ-120T-146-T Average Planar Exposure MAPLHGR(kW/ft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 11.65 12.00 0.20 0.22 11.69 12.03 1.00 1.10 11,77 12.09 2.00 2.20 11.88 12.17 3.0G 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 4 7.00 7.72 12.46 12.63 8.00 8.82 12.56 12.72 9.00 9.92 12.64 12.82 10.00 11.02 12.72 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 11.19 30.00 33.07 10.25 10.59 35.00 38.58 9.58 9.93 40.00 44.09 8.95 9.26 45.00 49.60 8.35 8.63 50.00 55.12 ~ 7.76 7.%

55.00 60.63 7.16 7.23 58.86 64.88 6.65 6.71 59.19 65.25 -- 6.67 59.25 65.31 -

6.66 8 For format explanacon, see letter J. S. Charnley (GE) to M. W. Hodges (NRC). Recommanded MAPUlGR Technical Specificationsfor Matriple forrice fuel Designs. March 9.1987. Most Unuting and Least Liminog refer to the lowest and highest hrruts. respecovely, of any ennched latuce in the txmdle.

Page 20

UVER BEND 24A5188 Reload 6 Rev. 3

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

Bundle Type: GE8B-P8SQB334-10GZ-120M-4WR-150-T Average Planar Exposure MAPLHGR(kW/ft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 11.36 11.90 0.20 0.22 11.42 11.93 1.00 1.10 l1.54 12.03 2.00 2.20 11.71 12.18 3.00 3.31 11.90 12.34 4.00 4.41 12.09 12.51 5.00 5.51 12.30 12.68 6.00 6.61 12.52 12.86

. 7.00 7.72 12.74 13.05 8.00 8.82' 12.97 13.23 9.00 9.92 13.21 13.41 10.00 11.02 13.41 13.56 12.50 13.78 , 13.60 13.65 15.00 i 16.53 13.31 13.32 20.00 22.05 12.64 12.64 25.00 27.56 -

11.% 11.97 35.00 38.58 10.46 10.53 45.00 49.60 9.08 9.21 50.00 55.12 6.97 7.04

9. For formas explanation, see letter J. S. Chamley (GE) to M. W. Hodges (NRC), Recommended MArulGR Technical SpecVicationsfor Multiple Lomce fuel Designs. March 9.1987. Most Unuting and Least Limiting refer to the lowest and highest h.mts, respectively. of any ennchedlamce in the bundle.

Page 21

'IIVER BEND 24A5188 teload 6- Rev. 3

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

Bundle Typei GE8B-P8SQB334-10GZ2-120M-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 2

0.20 0.22 11.42- 11.91 l.00 1.10 11.54 12.00 2.00 2.20 11.71 12.13 3.00 3.31 11.89 12.28 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 8.82 12.91 13.11 9.00 9.92 13.13 13.29 10.00 11.02 13.34 13.48 12.50 13.78 13.57 13.63 15.00 16.53 13.30 13.31 20.0i 22.05 12.63 12.64 25.00 27.56 11.95 11.%

35.00 38.58 10.46' 10.52 45.00 49.60 9.08 9.21 50.00 55.12 6.95 7.03 10.For format explanation, see letter J, S. Charnley (GE) to M. W. Hodges (NRC). Recommended MAPufGR Technical Specificationsfor Mulaple latrice fuel Desigar. March 9.1987. Most Linuting and Least Linuting refer to the lowest and lughest htmts, respectively. of any enriched lattice in the bundle.

Page 22

RIVER BEND Reload 6 24A5188 Rev.3

16. Loss-of-Cooiant Accident Results (cont)ll Bundle Type: GE8B-P8SQB334-11GZ-120M-4WR-150-T Average Planar Exposure MAPL 11GR(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 3.31 11.53 11.83 4.00 4.4 I 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 13.36 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 I1.For format explanation, we letter 1 S. Charnley (GE) to M. W. Hodges (NRC). Recommanded MArulGR Technical Spervicar Mulaple Larnce fuel Designs. March 9.1987. Most Umiting and Least Unuung refer to the lowest and highest limits, respecovely, ennched latace in the bundic.

Page 23

UVER BEND 24A5188

.teload 6 Rev.3 58 @@@@@@@@

5 WWY Y YY@ W

m8+8MBEMMMMBsMo

mM M BsME+s M M M M M Mm

M M M M 8+s M M M M M M M M

-mM M M M M M M M M M M M Mo

MMMMMMMMMMMMEs

sMMMMMMMMMMME+8ME

sMMBEBEBEMMMMMMMi+si

-*Ms+sMMMMMMMMMMM* ,

!: M M M M M M M M M M Mi+EM i !: *MB8MMMMMMMMM* ~

': *M Ms+sM M M M M M 2

MMMMMMM5 omosommo i ll Il1IJ l 1 5 5 7 e il la 15 17 19 21 23 25 27 25 si is as of as 41 43 45 47 es 51 53 55 a Fuel Type A=GE8 B-P85QB 333- 10GZ- 120M -4WR-150-T (Cycle 4) E=Gw B-P8SQB 334- 10GZ- 120M-4WR- 150-T (Cycle 5)

B= Gell-P9SUB354-14GZ-120T-146-T (Cycle 7) F=GE8B-P8SQB334-10GZ2-120M-4WR-150-T (Cycle 6)

C= Gell-P9SUB354-13GZ-120T-146-T (Cycle 7) G=GE8 B-P8SQ B 334-l l GZ-120M-4WR- 150-T (Cycle 6)

D=GE]l-P9SUB353-10GZ-120T-146-T (Cycle 7)

Figure 1 Reference Core Loading Pattern Page 24

RIVER BFED 24A5188 Reload 6 Rev. 3 Neutron Flux l 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 100.0 - -

' " - - ~~- - -- h~;'

. g 75.0 E '\ lii K '\ E

$ 's y $

. \

50.0 - ' ,\

25.0 -

l

-~~

.J .

i i 0.0 I

- 25.0 '

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

Level (incMEF-SEP-SKRT) Voed Reactivtty Vessel Steam Flow .

- - - Doppler Reacevity 150.0 - --- Turtnne Steam Flow 1.0 - --- Scram Reactivity I

--- Feedwater Flow - - - Total Reacevtty '

G

~

m 0.0 ,'

g 100.0 ,

W (

E 8 '

e p

E 50.0 --

($.' ' ' , h-1.0 - 1 l- ,,i,. t$

h' +. ', " "'

l ' , '

e ,.

0.0 ' l8' - 2.0 ' 1 II O.0 20.0 0.0 20.0 Time (sec) Time (sec)

Figure 2 Plant Response to FW Controller Failure (BOC7 to EOC7 STANDARD)

Page 25

RIVER BEND 24A5188

- Reload 6 Rev. 3 Neutron Flux Vessel Press Rise (psi)

Ave Surface Heat Flux -

Safety VaNo Flow 150 0 - -

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

--- Bypass Valve Flow

g. ,

.3

$ '. 200.0 -

]e100.0 #~% M E b.r'.s \ %s E E

',**%s,~~~~

3R 50.0 -

100.0 -

i

/ ,.- ......,

0.0 'j - .

0.0 - '

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

Level (inch-REF-SEP-SKRT) Void vity

. . . . . Vessel Steam Flow Doppler eacti 200.0 - --- TurtWne Steam Flow 1.0 - -

Scram R

--- Feedwater Flow -

Total Re6. vtty Q

?\

g **.

g 100.0 w.

,~ ~.

0.0 ,\ ,

w ; ',

.- v.... .

E .', '

(i *', , , , l

.i

., 8 g m . ', , ,,- /

1 x gi 0.0 - - - - -

- 1.0 -

,- ,* e

,, , E

.i 4

\.

' I

-100.0 -2.0 ' ' '

O.0 3.0 6.0 0.0 3.0 6.0

~ Time (sec) Time (sec)

Figure 3 Plant Response to Load Reject w/o Bypass (BOC7 to EOC7 STANDARD)

Page 26

TlVER BEND 34 45188 (Cl0&d 6 MCV. 3

, Neutron Flux Vettel Press Ri6e (pol) l Ave suri.co Heat rium satory v.ve riow 160 0 - - --

core wei now 300 0 -

--- n.het valve rio.

~ ~ ~ Bypass Vatve Flow s n' '

'00 0 '

200 0

t gt %% s * -

l $

'.,,a.,,-,, ~~~<

t 60.0 -

100 0 -

i j

o, no i ..

0.0 3.0 60 0.0 30 60 mme (we) Time (see)

Level (inch-REF-SEP-5KRT) Void R vity

..... Vessel Steam Flow

Doppler 200.0 ---

- Turtwne Steam Flow 1.0 -

- Scram Feedwater Flow Total Reactivtty a .

\ .-

\ .*

100 0 00 ,) ,.-

7{, .%, ,,

~.-. .- .L. -

, U p., /, /' .. . .......... y W

i 00 h':, , ' -

- 1.0 -

(

'g'b

\

-100 0 ' ' '

-20 '

O0 3.0 60 0.0 3.0 6.D Time (sec) Time (sec)

{

Figure 4 Plant Response to'Ihrbine nip w/o Bypass (BOC7 to EOC7 STANDARD)

Page 27

(IVER BEND 34A5188 teload 6 _

Rev, .4 Neutron Flum Vessel hose Ree (psi)

* * *

Ave Surface Heat Flus * * *

Safety Valve Flow 160 0 -

--- Core inlet Flow 300 0 -

- _ - Roset Vatve F6ow

pypane Valve Flow 100 0 #N '

\

200 0 -

. s

. Ng gt ., N p s~%~~ ~.<

60 0 -

100.0 -

, . ,I .....,... ....

on oo 00 60 .10 0 00 5.0 10 0 Emo(Sec) Emt (SGC)

Level (inch-REF-SEP-SKRT) Void %Mty Vessel Steam Flow * *

Dopp6er ReactMty 200.0 - --- Turtune Steam Flow 1.0 - --

Scram ReactMty

--- Feedwater Flow --

Total ReactMty ,,..**,,,..

R 100 0 00 g ,- ,-

7.s,N.

t

\*.

.f.- \

\

$ s. \

s'. .

.,,.... .............. 1, ,

0.0 - c____ - i .0 g,

i 1

., \

l

- 100.0

- 2.0 I" ' '

O0 5.0 10 o 0.0 5.0 10 0 Eme (SOC) Eme(Sec)

Figure 5 Plant Response to Pmss. Regulator Failure (BCC7 to EOC7 STANDARD)

Page 28

tlVER END 24A518 teload Rev, ,

)

1 Neutron Flur l Vessel Prete Rise (pol)

* *

Ave Surface Heat Flus * * *

Safety Valve Flow 160 0 -

--- Coro inlet Flow 125 0 - --- Relief Valve Flow

~ ~ ~ Core inlet $ubooohng --- Bypese Valve Flow

- d _, ,_ _ _ _ _ _ _ _ ._ [ ,

-''''''~

100.0 --

A 75 0 -

J' ig

'. \

$ '\

'. g%

60 0 -

'., - 25.0 -

l~ ~ ~

I -

0.0 -250 1 0.0 20 0 00 20 0 mme (sec) nme (Sec)

Level (inch-REF-SEP-SKMT) Void ReactMty

. . . . Vessel Steam Flow

Doppler ReactMty 350 0 - --- Turt*. St.am now 1.0 -

--- Scram Reacto l

--- Feedwater Flow --- Total ReactMty ,

t j

100.0 --- \ ,

0.0 -.,<.v...-.--..-,,, ,'

Y

f i>s E, 1

$0.0 -

J f, - 1.0 -

l

-l,.',*... C

l'

\' l

. l 0.0 ' '

- 2.0 ' ' l" 00 20.0 0.0 20.0 Eme(Sec) Emo (SOC)

Figure 6 Plant Response to FW Controller Failutt (BOC7 to EEOC7 WITH ICF)

Page 29

tlVER BFED 34A5188 (eload 6 Rev 3 i

Neutron Flus Vessel Press Rise (pal)

Av surface Heat riva see ty varve rio. 4 160 0 - - --

core wet rio. 300.0 - --- Reiet vwve rio. ;

~

--- eype.e vatv Fiow

\* .,

\,5 .

100 0 4 f.\ 200.0 -

Qs N *., ''%,,,, N 60.0 - ..* - .. .. 100.0 -

w <

.1

/~. * ............'

on on , -

00 3.0 60 00 30 60 Time (Sec) Time (sec)

Level (inch-REF-SEP- SKRT) VokiR vity

..... Vessel Steam Flow . . Doppler 200 0 - --- Turbine Steam Flow 1.0 - -

Scram Foodwater Flow - Total React #vtty E ,,...***

j - " '

r r . ~ . _ . .__ . . -

g)4(.....-

l '. , , ' . , ,' '....

$ l .....,,,

0.0 L-d-h-----

- - - - - - - - 1.0 -

, e' .,'

?.I ).

I \' '

-100 0 -20 '

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

Figure 7 Plant Response to Load Reject w/o Bypass (BOC7 to EEOC7 WITH ICF)

J Page 30

l tlVER BEND 34A5188 teload 6 Rev.3 l

l l

Neutron Flum Vessel Press Rise (psi)

Ave Sudace Heat Flux .

* *

Safety Valve Flow i 160 0 - - --

Core irdet Flow 300 0 -

--- Relief Valve Flow l

- - - Bypass Valve Flow a

- y ,

100 0 . 200 0 -

\%* .,v g % ,,,,

1 .

,~~ $

i 60 0 -

' ..,.., 100.0 -

I o_n ,

on .i ..

t .:-

00 3.0 6.0 0.0 30 60 Eme(Sec) Eme(SOC)

Level (inch-REF-SEP-SKRT) VoulR vtty

* *

Vessel Steam Flow +

Doppler .-

200 0 - --- Turtaine Steam Flow 1.0 - -

Scram

--- Foodwater Flow Total Reactivtty a \ ...... -

\

100 0 0.0 T

i,

~ ,, ----. . .

.s '. I.

p .. .**

I' l',

1, , ., . *

.. .....,, p \(.

i \

t 0.0 h ',,,,'

y'w--

c

~ 1.0 -

i .

t h'd

\'

I 1

- 100.0 - 2.0 ' '

00 30 6.0 0.0 3.0 60 Eme (SOC) Eme(Sec) l Figure 8 Plant Response to 'Ibrbine 'IYip w/o Bypass (BOC7 to EEOC7 WITH ICF)

Page 31

tiVER BEND 24A5188 (eload 6 Rev.3 I

I Neutron Flux Vessel Press Rise (pol)

* * *

Ave Surface Heat Flux *-

Safety Valve Flow 160 0 -

--- Core inlet Fbw 300 0 - --- Releef Valve Flow Bypass Valve Flow

-N 7 *

\

100 0 ., 200 0 -

'.

N s

$ '.'. N*N s s y%

+

60.0 - '. 100 0 -

n., , i ,I ...c..........

no 0.0 60 10.0 0.0 6.0 10 0 mme (see) mme (sec)

Level (inch-REF-SEP-SKRT) I- VokfMvity

. . . . . Vessel Steam Flow a. . Dopp6er ReactMty 200.0 - --- Turtnne Steam Flow 1.0 - --

Scram ReactMty

--- Feedwater Flow --

Total ReactMty ,,.***,,..<

W

~ . *,.***

100 0 g-.%,N.

N. .#*f._

0.0 g',

\

\ \

g

\..

\' * )

,.. ................., .{

q

}

g' O0 - - -- ~ 1.0 -

g c: \,

1

.. )

1

-100.0 ' '

- 2.0 '

00 60 10.0 0.0 60 10.0 Eme (sec) Bme (soc)

Figure 9 Plant Response to Press. Regulator Failure (BOC7 to EEOC7 WITH ICF)

Page 32

UVER BEND 34A5188 leload 6 Rev. 3 Ne p f [ Vessel Press Rise (pal)

- - - Safety Valve Flow 150 0 W p Ave Surface Heat Flux

- Core Wet F6ow 125 0 - --- Rehof Valve F6ow

- -- Core Wet Subcooling ---

Bypass Valve Flow g-,....... - 's 100 0 ---

g 75 0 -

$.% N 4% '. \ 4%

50 0 -

25.0 -

g" ~ ~

J *._1....

0.0 - 25 0 '

O.0 90 18 0 0.0 9.0 18 0 Time (sec) hTie(sec) e Vo6d Reactivity 1.evel(Inch-REF-SEP-SKRT)

* * *

Vessel Steam Flow * * * *

Dopp6er Reactivity 150 0 - --- Turb6ne Steam Flow 1.0 -

--- Scr.am Reactivity }

~ ~ ~ Foodwater Flow --- Total Reactivity

~

~* * *

100.0 -

\ }00 --

w.m m ; m 3i l

,\ . \ .'

ll . ] Y.

gt l. .

\

ll ?,\s. \,

50 0 - 'a * - 1.0 -

' e' o l' ' ', i l j' i .i \

00 ' ' ' '

-20 ' ' ' '

00 9.0 18 0 00 9.0 18.0 Time (sec) Time (sec)

Figure 10 Plant Response to FW Controller Failure (BOC7 to EEEOC7 WITH ICF AND FFWTR) 4 Page 33 -

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

(IVER BEND 34A5188 teload 6 Rev.3 l

Neutron Flus Vessel Press Rise (psi)

Ave Surface Heat Flux Safety Valve Flow 150.0 - -

-- Core Wet Flow 300 0 -

--- Relief Valve Flow

- - - Bypass Vatve Flow

/\ ' '. )

100.0 k '* jh 200 1

2 S.w 10 -

N 4

. ~ e

'.. ~_' ~~

e j e 60 0 -

100 0 -

i ,/ ..i.......... . .

on o, 0.0 3.0 6.0 00 3.0 60 T.me (seC) Time (sec) 1.evel(inch-REF-SEP-SKRT) Void R vtty Vessel Steam Flow Doppler ty 200 0 -

--- Turbine Steam Flow 1.0 -

-- Seram R vtty

--- Feedwater Flow

Total Roachvity ,

g

~ . ,, .

nl ' , **... *.

0.0 -

g 1000 s.

\ ',.

2 e

T ..,' i I ', /*

~ . ~ .

3{l y

0.0 ,,-;-,----- ---

0 -

h,'

a s,

\

l - 2,0 I

-100.0 >

_ t-

0.0 30 60 0.0 3.0 60 Time (sec) Time (sec)

Figure 11 Plant Response to Load Reject w/o Bypass (BOC7 to EEEOC7 WITH ICF AND FFWTR)

Page 34

(IVER BEND 24A5188 teload 6 Rev.3 -

Neutron Flux Vessel Press Rise (psi)

*

Ave Surface Hoat Flux * *

Safety VaNo Flow 5

1^0 - -

-- Core inlet Flow 300 0 -

--- Rehof Valve Flow

- - - Bypass Valve Flow

/ *.

100.0 \*' j ., g

',Ns 200.0 -

~s.'-..

.** ,,,~,.

gt 60.0 - .,*.. ,, ., 100.0 -

00 ' / I*

0.0 ' * - - --

0.0 30 6.0 0.0 3.0 60 Time (sec, Time (sec)

Level (inch-REF-SE*-6KRT) oid R vtty Vestel Steam Fkva

Doppler vity 200.0 -

--- Turbine Stearn Slow 1.0 - --

Scram vtty

--- Foodwater Flow -

Total Reactivity S .**,. -

100 0 -

ilQ

< 1 g 0.0 , .

7-.

i, ,, ,. .p :

i Y'(..***

s1

1,,

o i y

.. ........ 5 0.0 m - , r- ,-r - - - - - - ----

1.0 -

4 4

I \'

-100.0 '

- 2.0 I '

, 0.0 30 6.0 0.0 30 60 Time (sec) Time (sec)

Figure 12 Plant Response to 'Ibrbine Trip w/o Bypass (BOC7 to EEEOC7 WITH ICF AND FFWTR)

Page 35

l (IVER BEh'D 34A5188 l leload 6 Rev.3 ;

I l

i Neutron Flum Vessel Press Rise (psi)

* * *

Ave Surface Heat Flux * * * *

Safety Valve Flow 160.0 -

--- Core inlet Flow 300 0 - --- Rel6ef Valve Flow

--- Bypass Valve Flow "N

100 0 ** * , s 200.0 -

'. \

sN

/ ', '

s~%s $

I ., 's 60 0 -

s% ,'-

100.0 -

j_____________,

0.0 -

0.0 # ' '

O0 6.0 10.0 0.0 50 to 0 Eme(60C) Eme($4C)

Level (inch-REF-SEP-SKRT) VoidIoactivity

Voteel Steam Flow *

Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 - --

Scram Reactivity

-- - Feedwater Flow --

Total Reactivity **,,***,...-

100.0 -

00 '

g--* # . # , _ .s\' *%1.*

g- % , % . '

\

$ \' . '

\

.' . ................ \

N w--

\ ,i 0.0 - ---------- - 1.0 -

gl

\' ,

\

I

\i

-100 0 ' ' '

- 2.0 i'I ' '

O.0 50 10.0 0.0 5.0 10 0 Eme (SOC) Eme(Sec)

Figure 13 Plant Response to Press. Regulator Failure (BOC7 to EEEOC7 WITH ICF AND FFWTR)

Page 36

tlVER BEND 24A5188 teload 6 Rev.3 i

NM Flux Vessel Press Rise (psi) l d ve Suriace A Heat Flux * * *

Safety Valve Flow f '

150.0 -

--- Core in!st Flow 125 0 -

--- Rehof Valve Flow

- -- Core trWet Sutcooling --- Bypase Valve Flow i.

's, j 4 .....

j n , _

<g 4

$ '\s ,

50 0 -

25.0 -

l'" ~ ~

I

_L+_1....

0.0 '

- 25.0 ' '

O.0 9.0 18 0 0.0 90 18 0 Time (sec) Time (sec)

Level (6ncMEF-SEP-SKRT) Vold Reactivity

+ Vessel Steam Flow *

Doppler ReactMty 150.0 -

--- Turbine Steam Flow 1.v -

--- Scram ReactMty

--- Foodwater Flow - - - Total ReactMty

)

W 100.0 -

g 0.0 - -

- e6v WC,k ,,'

}' \' z

l. z\ }

ll a.*. \.

50 0 -

g, s ., l -1.0 -

)

l ,' +. .'}..

i

.. ,'. I

~

Il'll ,'i.'s ,

', e' \

O.0

' ' 'l' r . ' - 2.0 * ' ' '

0.0 9.0 18.0 00 9.0 18 0 Time (sec) Time (sec)

Figure 14 Plant Response to FW Controller Failure (BOC7 to EOC7 FWTR-100%P/100F)

Page 37

(IVER BEND 34A5188 teload 6 Rev. 3 I

Neutron Flux Vessel Press Rise (pol)

Ave Surface Heat Fluu * * * *

Safety Valve Flow 160 0 - -

-- Core inlet Flow 300 0 -

--- Releef Valve Flow

--- Bypass Valve Flow 100.0 ',

/J %,

200.0 -

g E .*

g '.,

g

..,' ~~~~,

60 0 -

..**a. 100.0 -

' .i............ .

oo ,

oo. ,

00 E.0 60 00 3.0 60 Time (sec) Time (sec)

Level (inctwREF-SEP-SKRT) oid R ivity

* *

Vessel Steam Flow . . . . . Dopp6er o 200.0 - --- Turtene Steam Flow 1.0 -

-- Scram v6ty

--- Foodwater Flow -

Total Reactivity '

g ,

). ........

100.0 -

00 .,{

N.,..* ** ..

W * --- . %

, - - . .p \

$ t, I , . l '. ,,

~~.......

0.0 , ,-.;-* - - - _ - - - -- ---

E 1.0 -

, g

.)

4

-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 Rypass (BOC7 to EOC7 FWTR-100%P/100%F)

Page 38

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

l (IVER BEND 21.55168 teload 6 P.-v. 3 Neutron Flux Vessel Press Rise (psi)

Ave Surface Heat Flux

Safety Valve Flow 160 0 - -

-- Core inlet Flow 300.0 -

--- Rehet Valve Flow

- - - Bypass Valve Flow

] 100.0

$ w** ' .,

.,, %.,,,~~~.

] 200 0 60 0 -

.,,, 100 0 -

o.o

- i oo / .L............ .

0.0 3.0 60 00 3.0 6.0 Eme(seC) Eme(seC)

Level (inch-REF-SEP-SKRT) old R vity

- Vessel Steam Flow +* Doppiot ty 200.0 - -- - TurtWne Steam Flow 1.0 -

-- Scram R vity

- - - Feedwater Flow - TotalReactivity

@ .{ ,,,.*

\' l . *,,.***

o q

\...p rl, ,,

$ 1: l '. ,'.

\

f g.

0.0 - 3 , r-- ,r------ ----

M. -

1

'i i'

d 4

\UI '

-100.0 - 2.0 '

O.0 3.0 60 0.0 3.0 60 Eme (sec) . Vme (sec)

Figure 16 Plant Response to 'Ibrhine Trip w/o Bypass (BOC7 to EOC7 FWTR 100%P/100%F)

Page 39

(IVER BEND 34A5188 teload 6. Rev. 3 Neutron Flux Vessel Press Rise (psi)

* * *

Ave Surface Heat Flux * * * *

Safety Vaive Flow 150 0 - --- Core inlet Flow 300 0 - --- Relief Valve Flow Bypass Valve Flow

.r4 'I, s 200.0 -

l 100.0 *

.\ s

. a Y

'.,s%s*

s Y

50.0 -

., - 100 0 -

j--_.._------._-.

00 0.0

'I -

0.0 5.0 10 0 00 50 10.0 Eme (SOC) Eme (SOC)

Level (inch-REF-SEP-SKRT) # Vo6dIoactMty

* * *

Vessel Steam Flow a . *

Dopp6er ReactMty 200 0 - --- Turtune Steam Flow 1.0 - --

Scram ReactMty 4

- - - Feedwater Flow --

Total Reactivtty

. ee , **.*,..

0.0 3 1000 c- g'%.*.

2 .N '. s

\

8 %, a , 3l_ \

s -.

\

\,

0.0 - ---------- - 1.0 -

g

\

\,

.. \

I

-100.0 ' I '

- 2.0 \ ' '

O.0 50 10 0 0.0 5.0 10.0 Eme (SOC) Eme (SOC)

Figure 17 Plant Response to Press. Regulator Failure (BOC7 to EOC7 FWTR 100%p/100F) 1 Page 40

RIVER BEND 24A5188 Reload 6 Rev.3 Neutron Mus Vessel Press Rise (psi) \

Ave Surface Heat Flux *

Safety Valve Flow 150.0 - --- Core inlet Flow '

125 0 -

--- Releet Vatve Flow

- - - Core inlet Subcooling --- Bypass Valve Flow

'~~~*

, . i 100.0 -

" ~ ^ ~ " " - - - - - - - - h 75.0 -

S .\ [

e -

.N e

', \

\ ~~~

50 0 -

25.0 -

, l

.J .

i i 0.0 ' ' '

- 25.0 -

O0 20.0 0.0 20.0 Time (sec) Time (sec)

Level (Inch-REF-SEP-SKRT) Void Reactivity 9

Vessel Steam Flow .

Doppler Reactivtty 150.0 - --- Turtnne Steam Flow 1.0 -

--- Scram Reactivity )

--- Foodwater Flow --- Total Reactivity w ,

100.0 --- --- _

00 -

-.-. m yg-..... /

.f 1 l,

60.0 -

E hl'

- n - 1.0 -

1. I ,'(f.\,.,. .t,,, -

" Dl ', ,

i t ll l, N I' 't 0.0 -2.0 -

0.0 20 0 0.0 20.0 Time (sec) Time (sec)

Figure 18 PWt Response to FW Controller Failure (BOC"/ to EOC7 STANDARD-HALING)

Page 41

._ . _ _ _ _ _ _ _ . . _ -_ ._. _. __ - . . _ . __ . - . _ _ . _ _ _ _ _ _ . _ _ ___.__w-RIVER BEND 24A5188 Reload 6 Rev.l I

Neutron Rum Vessel Press Rite (psi)

*

Ave Surface Heat Flux +

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

--- Bypass Vatvo Flow !

j\, . . -

] 100 0 -

s ] 200.0

~~~%,_'

~~

50 0 -

.,,'.** 100.0 -

.i

/- .- ............

t . .

n_n n, 00 3.0 60 00 30 60 mme (sec) mme (sec)

-- Level (6nch-REF-SEP-SKRT) ' Vo6d R 'vity l

. *

Vessel Steam Flow -- Doppler eacti 200 0 - ---- Turtune Steam Finw 1.0 -

Scram R vity

--- Foodwater Fkw Total Reactivity g

s ,,..***

100 0 i~..,,,, 0.0 l\.,

+.,

' *' * *~~"~~_ p 1**,,,..

l , .

,, \

i e H l '. :. . .""'"*.

.. . .... \,

y-0.0 W, y - ;,-'r- '

- - - - - - - - - 1.0 -

\g

's

' t.

, \\

.. \\

' I l -100 0 -

- 2.0 - '

00 3.0 6.0 00 3.0 6.0 Eme (Sec) Eme (Sec)

Figure 19 Plant Response to Load Reject w/o Bypass (BOC7 to EOC7 STANDARD-HALING)

Page 42

--e ? --we-vw= - - - ,i r vy ww-T y-re - s M r

(IVER BEND 24A5188 teload 6 Rev.2 Neutron Flum Vessel Press Rise (psi)

Ave Surface Heat Flum * * *

Safety Valve Flow i 160 0 - -- -- Core Irwet Flow 300 0 -

--- Relief Valve Flow

- - - Bypart Valve Flow

~

e e

~__~_

60 0

..***.., 100 0

~~~~~~~~~~~~~~

i j . .

. , ..i . . -

o.o on .

0.0 3.0 60 0.0 30 6.0 Eme(84C) Eme (SOC)

Levei(inch-REF-SEP-SKRT) Vod R ctivity Vessel Steam Flow - . Doppler 200.0 - --- Turt>ine Steam Flow 1.0 -

Scram R vity

- - - Feoo..ier rio. -

Toimi Re.ctivity a

/\ ... ..... -

m 4 l 100 0 p' .%'N-.

l, .' l 00 f.,'***,.<'

,5

' ..... .., d i e l l ',, ., .". .

s!

y y%

0.0 mh y- ' ,-- , - 1.0 -

gj lsl C

' . \'\

\

\,

l '

I

-100 0 - 2.0 '

, . 00 30 ,

60 00 3.0 60 Eme (sec) Emc(sec) e Figure 20 Plant Response to 'Ibrbine Trip w/o Bypass (BOC7 to EOC7 STANDARD-HALING)

Page 43

(IVER QEND 24A5188 teloadI Rev. 3

\

t .

Neutron Flux Vo66el Press R$e (pol)

* * *

Ave Surface Heat Flux * * * *

Bafety Valve Flow 150 0 -

--- Core iniel Flow 300 0 -*

--- Relief Valve Flow

--- Bypass Valve Flow 100 0

<.,-%\g\ ,

200 0 -

g N

$ '. \ s $

., , * =. .

50 0 - * ,'-

., 100.0 -

' I 00

00 ' ' ----'-

00 60 10 0 00 5.0 10 0 Emt(SOC) Eme (60C)

I Level (inch-REF-SEP-SKRT) VoidMwty

. . . .

Vessel $taam Flow ***

Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 -

--- Scram HoectMty

--- Foodwater Flow -- - Total ReactMty **,,...***,,, ,

100.0

0.0 g--.,% p. q. , . , , , , .

\, \ .

$ \',

..................... i, ,

g}

0.0 - - ---- -----~~ -10 -

g ,

l{

\ )

\'

\

-100.0 ' I '

- 2.0 O.0 - s0 10.0 00 s0 10 0 Bme (sec) Eme(sec)

Figure 21 Plant Response to Press. Regulator Failure (BOC7 to EOC7 STANDARD-HALING)

Page 44

,-~

(IVER BEND 34A5188 teload 6 Rev.3 l

l L

Neutron Flus - Vessel Press Rise (psi) b

* *

Ave Surface Heat Flus * * * *

Safety Valve Flow 160.0 - --- Coro inlet Flow 125 0 - --- Relief Valve Flow

- -- Core inlet Subcooling - - - Bypase Valve Flow

, s * ~~~~~ * *

.:.d -~~~~~~

'h i 100 0 ,

S 76.0 -

\

'\

$ 's \ $

'., \

60 0 - '

, 26.0 - I ~ ~~ '

A .....

00 1 '

- 25.0 '

00 20 0 00 20 0 Vme (Sec) Vme(sec)

Level (inch-REF-SEP-SKRT) Vok! Reactivtty

* * *

Vessel Steam Flow I

* * *

Doppier ReactMty 160.0 - --- Turbine Steam Flow 1.0 - --- Scram ReactMty j

~ ~ ~ Foodwater r* low --- Total ReactMty 6 '

(*..-

100 0 ---- --- -

00 .x,,s,,.,,,,,-

l e h, ;

U

( ,' l . t 50.0 - , - 1.0 -

i L y". . [

, li'j ,' I g

t ', r 00 ' k l* -20 ' '

00 20 0 00 20 0 Eme(sec) Eme(sec)

Figure 22 Plant Response to FW Controller Failure (ROC 7 to EEOC7 WITH ICF- '

HALING)

Page 45

t!YRPm 24ta!M uo- nu. ve.,e,F,0. R..e<,,o

Ave Surface Heat Flus * * *

Safety Valve F ow 160 0 - -

-- Core Wet Flow 300 0 - - - Rehof Valve Few

- - - Bypa.s Valve Flow

/ \,4 100.0 ,/ M,,\ 200 0 .- -- -

60 0 -

.*..** ..., 100 0 -

/~~~, ........

00 00 0.0 30 60 00 30 60 Eme(Sec) Eme(60C)

Level (inch-REF-SEP-SKRT) Void R in/

Vennel Steam Flow . Doppier 200.0 - --- TurtHne Steam Flow 1.0 -

Scram R tMty

- - - Foodwater Flow Total Reactivity G ,...*****

.\. ,.*.....

100 0 r-., 00 t,

, ~~-. . .- <... . . . , . '

[' l', *. \

$ ll l '. l ', , ' ' . . * *' ,..

. .....,. \;

g

\

00 , y* - r r- - - - - - - - - - - - 1.0 -

)

i i' g,

l I\ ').\

-100.0 ' ' '

-20 \ L I '

00 30 60 0.0 30 6.0 Emo (See) Emo(sec)

Figure 23 Plant Responu to Lal Reject w/o Bypass (BOC7 to EEOC7 WITH ICF-HALING)

Page 46

VER HEND 24A5188 load 6 Rev. 3 Neutron Fluu ** Vei4et Press Roe (pol)

Ave Saiace heat Flus * *

Safety Valve Flow 160 0 -

-- Core Irdet Fbw 300 0

--- Reet Valve Flow

--- Bypass Valve Flow

/ \ .

100.0 e je 200 0 -

60 0 -

.....~ ***...

~~ .

100 0 -

nn

.no

,f----~~.T..~.--~~--

00 30 60 0.0 30 60 Eme(Sec) Eme(Sec)

I Level (inch-REF SEP-SKRT) Vo6d R vity Voteel Steam Flow .

+-

Dopplef 200 0 -

--- Turtune Steam Flow 1.0 -

Scram vety

--- Feoowater Flow Total Reactivity ,

E t

,s ,.... .

aa j'v

~. _. .

e ,' .

l' .,

..... s! \

m7,--

00 k *'

- - - - - - - - - - 1.0 - y{ g It i.,,

i

.. \l \.

\

-100 0 ' ' ' I '

- 2.0

0.0 30 60 00 30 60 Eme (SOC) Eme (SOC)

Figure 24 Plant Response to 'Ihrbine IYip w/o Hypass (BOC7 to EEOC7 WITH ICF -

HALING)

Page 47 I

i i

(IVER BEND 24A5188 (eload 6 Revd Neutron Flum Veoool Press Race (psi) ,

* * *

Ave Surface Heat Flus * * * *

Safety Valve Flow '

160 0 -

--- Core intet Flow 300.0 -

--- Rehef Valve Flow '

- - - Bypass Valve Flow f-% \

i 100 0 ** * \ 200 0 g ,

, N -

'. N g Y ',

%s Y 60.0 -

*% s ' % 100.0 I

i ' L 00 00 O0 60 10 0 0.0 60 10.0 Em9 (SGC) Emt(60C) -

Level (inch-REF-SEP-SKRT) VoldIoactMty

* * *

Vessel Star,m Flow ***

Doppler ReactMty 200 0 -

--- Turtune Steam Flow 1.0 -

--- Scram ReactMty

--- Feedwater Flow - - TotalReacttW **,..*****, '

g 100.0 0.0

g--- * % , N .

N(,

'*p,- g, ,

\ .

Y \* , '

\ '

00 -- -- - 1,0 -

\

4

\' g

\

-100 0 ' ' I' '

-20 -

00 60 10.0 0.0 5.0 10 0 Eme (sec) Eme(sec)

Figure 25 Plant Response to Press. Regulator Failum (BOC7 to EEOC7 WITH ICF-HALING) l- Pag: 48

tlVER BEND 24A5188 teload 6 Rev.3 i l

Nep[ Vessel Press Rise (psi) \

r p Ave surface Heat rius safety vatve rio.

160 0 - core iniei riow its 0 -

--- Rehet vwve rio.

- -- cora iniet subcoohng --- sypass vwve riow 300 0 _ _ 4 rso -

yt '

,\ gt 4

60 0 -

25 0 - ' ' ~ ~

l 1..J.... .l 00 -25.0 I '

OO 90 18.0 0.0 9.0 18.0 Emo(sec) Vme (sec)

Level (inch-REF-SEP-SKRT) Vod ReactMty Vessel Steam Flow Doppler ReactMty 8 1$0 0 - --- Turtdne Steam riow 1.0 - --- Scram ReactMty

--- rowwater riow --- Total ReactMty }

. W ,

100 0 g00

- ww--=& .' . ,*

Q;, .

I j \

t i' 50.0 - hl'\

g., j -1.0 -

[

E l' .;;;; i.* K' l'. ,-

l'.

1 l l,'

l. - .

00 ' ' ' " .". '

- 2.0

I '

00 9.0 18.0 0.0 9.0 18.0 Emo (sec) Vme (sec)

Figure 26 Plant Response to FW Controller Failure (BOC7 to EEEOC7 WITH ICF AND FFWTR HALING)

Page 49

tiVER BEND 34A5188 teload 6 Rev. 3 Neutron Fium Vessel Press Rise (psi)

*

Ave Surface Heat Flux *

Safety Valve Flow 150 0 - -

-- Core Wet Flow 300 0 - --- Rolsof Valve Flow

- - - Bypase Valve Flow

/ \. .,

4)"s 100 0

2000 -

x~'~,,~- Y l

60 0 100.0 -

/

00 O0 ' - -----

00 30 60 0.0 30 60 Eme (SOC) Eme(SOC)

Level (inch-REF-SEP 4KRT) Vo6d R ttvity

Vessel Steam Flow .. Doppler vtty 200 0 -

--- Turbine Steam Flow 1.0 -

Scram R tvety

--- Feedwater Flow Total Reactivity g

s

..=,,..**,

100 0 -

0.0 *

- . ~ .

g gt I'

\

Q. * ' ' , e' 's *

'..*** . .... f

\,

00 , - , ' d, -.- ------- - 1.0 -

g

',.,i l.

.. \\.

-100.0 '

- 2.0 b I ^

0.0 30 6.0 0.0 30 60 Eme (SOC) Eme(SOC)

Figure 27 Plant Response to Load Reject w/o Bypass (BOC7 to EEEOC7 WITH ICF AND FF%TR HALING)

Page 50

l UVER BEND 34A5188 teload 6 Rev,3 Neutron Flux Vessel Press Rise (psi)

* - Ave Suriace Heat Flux *

Safety Valve Flow 160,0 - - --

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

--- Bypass Valve Flow s

/s \, ,

100 0 t. l' Jgy 200.0 -

%~,- $

50 0 -

100.0 -

' I '

0.0 O0 O.0 30 6.0 0,0 3.0 6.0 Eme(Sec) Eme(Sec)

Level (inch-REF-SEP-SKRT) VoktRe' vtty

+ **- Vessel Steam Flow . . Doppler ety 200.0 - --- TurtWne Steam Flow 1.0 -

Scram R vety Feedwater Flow Total Reactivity G

~~- , ,,.**,..**

0.0 j.

l 100.0 7 ,-- . ~ . . .

.- ~;).

$ o :: e. .. . . , t\

' . . * * ' . . * '... }

0.0 m ,r- -a ,

1.0 -

g

,;l t.

.o \

^

I

-100.0 '

-2.0 -- I 0.0 30 6.0 0.0 3.0 6.0 mme (sec) mme(Sec)

Figure 28 Plant Response to 'Ibrbine 'IYip w/o Bypass (BOC7 to EEEOC7 WITH ICF AND FFWTR HALING)

Page 51

'llVER BEND 24A5188 (eload 6 Rev. 3

?

~

Neutron Flux Vessel Press Fiise (psi)

Ave Surface Heat Flux

Safety VaNo Flow 150 0 -

--- Core inlet Flow 300 0 -

--- Relief Va..e Flow

- - - Bypass Valve Flow

\

100 0 .* .* . \ 200.0 -

., N

'. N k

s's N w%

50.0 - *

. 100.0 -

~~~--~~~<

0.0 00 OO 5.0 10.0 00 5.0 toO Eme(Sec) Eme(Sec)

I Level (inch-REF-SEP-SKRT) VoidNactivtty Vessel Steam Flow - Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 .--- Scram Reactvity

--- Feedwater Flow -

- Total R4 activtty **,,,. ***,, ,

G 4 ,.

100.0 -

,- 0.0 g. . ,'

r4. ~. s 7..

Y.

O 1{5

\ l

$ N. s ) '

',\..' ,. ................... f \

0.0 - % - -- ----------- - 1.0 -

g 1

- \

t<

l

-100.0 ' ' I' '

-20 O.0 50 10.0 00 5.0 10.0 Eme (SGC) Eme (SGC)

Figure 29 Plant Response to Press. Regulator Failure (BOC7 to EEEOC7 WITH ICF AND FFWTR HALING)

Page 52

.- IVER BEND 24A5188 eload 6 Rev. 3 w#on nu,

d Ave Surface Heat Flux ve i er... R,.. o.i>

* *

Safety Valve Flow 160 0 -

--- Core truet Flow 125 0 - --- Releef Va'.1 Flow

- -- Core trWet Subcoohng --- Bypa Vatve Flow 120 e g a.. h 5

r\ 30 75 -

i 4% .

.\

60 0 -

25.0 -

g'" "- ~

.L-).... .l I I 0.0 '

- 25.0 '

00 9.0 18.0 00 9.0 18.0 Time (sec) Time (see)

Level (6nch-REF-SEP-SKRT) Voed Reactivtty Vessel Steam Flow _ Doppler ReactMty f 150.0 - --- TurtWM Steam Flow 1.0 -

--- Scram ReactMty 3

--- Feedwater Flow - - - Total ReactMty V E

~* * * * - *

\

,e

- 00 - w 2 .-ir ,7.e - ,- ', . ' , .

g 1000

, -- --- ,\ ,

l' ' h I

~

l,i .A. . t Y i

50.0 -

g i' g,., - 1.0 -

t

l. . * \' <

G: Q I;!;; P 00 ' ' 'l" ' - 2.0 I I' O.0 90 18.0 0.0 90 18.0 Time (sec) Time (sec)

Figure 30 Plant Response to FW Controller Failure (BOC7 to EOC7 WITH FFWTR HALING-100%P/100%F)

Page 53

(IVER BEND 24A5188 (eload 6 Rev. 3 Neutron Flux Vessel Press Rise (psi)

Ave Surface Heat Flux * *

Safety Valve Flow 150.0 -

- -- Core Wet Flow 300 0 -

--- Rehet Valve Flow

--- Bypass Valve Flow s,< .

100.0 L '. 200.0 -

/ " %,

E * % E

~

s' '% bl

~.

s0.0 - .,'.***.. 100.0 -

~ ....

i ,/

oo n.o i ......... .

00 30 6.0 0.0 3.0 60 Dme (sec) Eme(sec)

Level (inch-REF-SEP-SKRT) Vod R vity

Vessel Steam Flow - Doppler 200 0 - --- Turtnne Steam Flow 1.0 -

Scram R vtty _

--- Feedwater Flow Total Reactivtty 3 ,\ . **. * .

I\ .

100.0 -

0.0 ',I r --- . *J.***,.

', ,. ' ' --- * *",- g*

$ I' .

.. ,- \

.. ** .. ~... { \

0.0 ,-,--*----~~- - - - - - - - - 1.0 -

g w-

t,

-1000 ' ' '

- 2.0 h I '

00 3.0 00 0.0 3.0 60 Dme (sec) Eme (sec)

Figure 31 Plant Response to Load Reject w/o Bypass (BOC7 to EOC7 WITH FF%TR HALING-100%P/100%F)

Page 54

RIVER BEND 24A5188 Reload 6 .tev. 3 d

Neutron Flur -

Vessel Press Rise (psi)

Ave Surface Heat Flux -

- Safety Valve Flow 150.0 - <- -- Core Wet Flow 300.0 - --- Relief Valve Flow

- - - Bypass Valve Flow 100.0 (s.'\'

E g

%. 30 g

200 -

'O7s e .

~~,' e

~.

50 0 -

.**..,, 100.0 -

00 O.0 '

i 0.0 30 60 0.0 3.0 6.0 Time (hec) Eme (sec)

Level (inch-REF-SEP-SKRT) Void R vtty Vessel Steam Flow - Doppier ty

, 200.0 - --- Turbine Steam Flow 1.0 -

Scram R vtty

--- Foodwater Flow Total Reactivity g . ... **

,1 g 100.0 0.0 ,

~ '

h '%,,.. . *?

i

iLf I

, - , .' y-----

. .. . .. ... .. .. .. . g j-1.0

~ \\ \ 11 0.0 .----- -

g E

,,',, \.

- n gg l-

-100.0 ' I '

- 2.0 - II ' ' '

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

Figure 32 Plant Response to 'Ihrbine Trip w/o Bypass (BOC7 to EOC7 WITH FFMTR HALING-100%P/100%F)

Page 55

IIVER BEND 24A5188 teload 6 , Rev.3 Neutron Fluu Vessel Press Rise (psi)

Ave Surface Heat Flus -

Safety Valve F'ow

~ 150.0 -

--- Coro inlet Flow 300.0 - --- Relief Valve Flow

--- Bypass Valve Flow v 100.0 < f. -( e 200.0 -

S '. % $

h '. '

y N

k

, s /

N

', . w 50.0 --

s* 100.0 -

~ 0.0 O.0 O.0 5.0 10.0 0.0 5.0 10 0 Eme (SGC) Eme (SGC)-

Level (inch-REF-SEP-SKMT) # VoidIoactMty

- - - Vowel Steam Flow --- - Doppler ReactMty 200.0 - --- Turbine Steam Flow 1.0 - --- Scram ReactMty **,.

--- Feedwater Flow -

- Total ReactMty ,..

G w *,.,.***,

m ..

0.0 ,'

g 100.0 ,

y V-----.. \

E \(, -

g'

$ \' . y \ 1

... .. .............. ,y \

\ t )

0.0 - s- ----_-__--- m -1.0 -

a \t,'\

g i

' I I '

-100.0 - 2.0 O.0 5.0 10.0 0.0 5.0 10.0 Eme (sec) Eme (sec) l Figure 33 Plant Response to Press. Regulator Failure (BOC7 to EOC7 WITH FFWTR HALING-100%P/100%F)

Page 56

UVER BEND- 24A5188 teload 6 Rev. 3 s

Neutron Flux [ Vessel Press Rise (psi)

Ave Surface Heat Flux

Safety Valve Flow l

150.0 -

--- Core Wet Flow 125 0 - --- Relief Valve Flow

- - Core Wet Subcooling - - - Bypass Valve Flow 100.0 g 75.0 a '.\ Tu 0: i\ E BI i g 8

. \

50.0 -

25.0 -

l~ ~ ~

, .I .

F _L .J . . . . .

0.0 ' I

- 25.0 0.0 20.0 0.0 20.0 Eme (Sec) Eme (SGC)

Level (Inch-REF-SEP-SKRT) Void Reactivity Y Vessel Steam Flow - - - Doppler Reactivity 150.0 - --- Turbine Steam Flow 1.0 -

--- Scram ReactMty

--- Feedwater Flow --- Total Reactivttv ,

S ,

e 0

--- ---

0.0 g 100.0 , + . . ., =. . . .-;c . . .7, ,,

lii t C

gt -

(l\ { l.

50.0 -

l '\[* { eTg-1.0 it

\'

)

.'*s*-

Il R .. . +

l' O.0 - 2.0 '

O.0 - 20.0 0.0 20.0 Eme (Sec) Eme (SOC)

Figure 34 Plant Response to FW Controller Failure (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) STANDARD)

Page 57 l

UVER BEND - 34A5188 (eload 6 Rev. 3

. Neutron Flux Vessel Press Rise (psi)

Ave Surface Heat Flux e

SafetyValve Flow t50 0 - --

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

. 1 I -

b.$e'.

3. 100.0 E .\. . ~ N 3. 200.0

, d 8 '

sN $

50.0 -

. 100 0 -

, ,/ .....

o_, o, ..r ...

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

I\ #

Level (inch-REF-SEP-SKRT)

Vessel Steam Flow - h Void DopplerReRescUvity 200.0 - --- Turbine Steam Flow 1.0 -

-- Scram Reacovity

--- Feedwater Flow -- Total Reactivtty a

m ..

n ,f. ,

p 100.0 . 0.0 i ..'

cc .

t.

t.f. , s . .

1

h. i'. .

. :\ ... .'. . .. .

.. ..... g \:

0.0 W_._9.__-

_ _ _ _ _ - . _ _ . ~ ~ u 2~

-;i \.

'. E 1i

\\\.

-100.0 ' ' '

~ 2.0 \\'

I ' '

O.0 3.0 - 6.0 0.0 3.0 6.0 Time (sec) Tin e (sec)

Figure 35 Plant Respoi.se to Load Reject w/o Bypass (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) STANDARD)

Page 58

UVER BEND 24ASl88 (cload 6 Rev. 3 Neutron Flus Vessel Press Rise (psi)

- Ave Surface Heat Flux Safety Valve Flow -

160 0 - ----- Core inlet Flow 300 0 -

--- Rehet Valve Flow

--- Bypass Valve Flow e

y tw0 { ,*.vy r,

e

3.2@ 0 E

.N '., s \ = % ' '" -

~~

50.0 -

.,* ., - 100.0 -

o,

/ .L... - ..

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

Level 0nch-REF-SEP-SKRT) Void RM Vessel Steam Flow - - Doppler ReactMty 200.0 - --- Turtune Steam Flow 1.0 -

-- Scram ReactMty

--- Feedwater Flow -- Total Reecevity a ... -

, t ...

,l . '

7,1m O e

r,. ._,-.

0.0

\

~[I l

j ,', , ' . , ' ,,*, ...

i.

'# 1 , .....,, g g

' e *

.2

% l 0.0 - - ~ ~ ~ ~ ~ - - k -1.0 -

N: j"'-4'5- "

\'\

. i - I.

-100.0 I

- 2.0 I ' ' '

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

Figure 36 Plant Response to 'Ibrbine 'IYip w/o Bypass (BOC7 to EOC7-3693 mwd /MT 4

(3350 mwd /ST) STANDARD)

Page 59

(IVER BEND 24A5188 teload 6 Rev. 3 Neutron Flux Veseel Press Rise (psi)

-- Ave Surface Heat Flux *

Safety Valve Flow 150.0 -

--- Core trdet Flow 300.0 -

--- Relief Valve Flow -

-- - Bypass Valve Flow 100.0 e- " . , \

g g 200.0 s

~

's,~ e 60 0 -

,%,,,,'- 100.0 -

0.0 O.0 ' '

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

I Level (inctAEF-SEP-SKRT) Void Reactivtty Vessel Steam Flow -

- Dopp6er Reactivity 200.0 -

--- TertWne Steam Flow 1.0 - -

- Scram Reactivity

--- Feedwater Flow - - Total Reactivity ,,,... **

g w ..

g lE ,

100.0 7% . s , . _ . *

. g0.0 g.....*

a l 8-

\'.

g j N'., g.A s, l ............... g 0.0 -.

_ _ _ _ _ _ _ _ _ _ _ _ . _ _ \

g -i.0 .- ,

" \

\ .

\

-100.0 - ' - '

- 2.0 >

0.0 ' 5.0 10.0 0.0 5.0 10.0 Time (sec) Time (sec)

Figure 37 Plant Response to Press. Regulator Failure (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) STAdDARD)

Page 60

UVER BEND 24A5188 teload 6 Rev.3 Neutron Flux Vessel Press Rise (psi)

Ave Surface Heat Flux -

Safety VaNo Flow itA0 - --- Core trWet Flow 125.0 - --- Rehof Valve Flow

- -- Core ardot Subcoohng ,

--- Bypass Vane Flow

.-J -

100.0

=#.- - '' '

b 75.0 -

i e '..\\

e

~

'.N s

50.0 -

', 25.0 -

l - ~~ ~~

.J' .

O0 ' '

- 25.0 O0 20.0 0.0 20.0 Time (sec) Time (sec)

+

Level (Inch-REF-SEP-SKRT)

Vessel Steam Flow Void Reactivtty

- - - - Doppler Reactivtty kY 150.0 - --- Turbine Steam Flow 1.0 - --- Scram Reactivity

--- Feedwater Flow --- Total Reactivity G

w -

} 0.0 'g l q\

g 100.0 ,

.r+- e = m ,,

e ( ,

C V*'

t* {

n

\

\.

50.0 -

,, s e -1.0 -

g

{

1,, , , l"$',i .. ' ' . " ' l.

t

$. ' ', 1; 0.0 ' I'

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

Figure 38 Plant Response to FW Controller Failure (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) WITH ICF)

Page 61

RNER BEND - 24A5188 Rcload 6 Rev,3 s

Neutron Flux Vessel Press Rise (psi)

- Ave Surface Heat Flux - * - Safety Valve Flow 150.0 - - --

Core inlet Flow 300.0 - --- Relief Valve Flow

--- Bypass Valve Flow

/ sg ,

, >#\ 200.0 -

3 100.0 '

e

'. % . s 3

. s $

BR

~~~, 3R 50.0 -

.... 100.0 -

~......

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

oo o.o .

0.0 3.0 60 0.0 3.0 6.0 Eme (Sec) Time (sec)

I # Void ReWytty Level (inch-REF-SEP-SKRT)

Vessel Steam Flow -

Doppler Reactivtty 200.0 - --- Turtune Steam Flow 1.0 -

-- Scram Reactivity Feedwater Flow - -- Total Reactivtty .

g .... -

E ,

f. .. ..

g 100.0 0.0

7 ,

~ - . _ _ . .

- f. , ,q..,-

m . ,', ,

V '

i 1 3e

.., ... ..,,. ~

. . i. .

........ y \

j; O.0 _ _ _ _ _ _ _ _ _ E -1.0 _

E lt

~ \\1,

-100.0 ' ' '

- 2.0 1(

I ' ' '

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

Figure 39 Plant Response to Load Reject w/o Bypass (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) WITH ICF) :

Page 62

RIVER BEND 24A5188 Reload 6 Revd T

Neutron Flux Vessel Press Rise (psi)

- - Ave Surface Heat Flux

Safety Valve Flow 150.0 - --.-- Core inlet Flow 300.0 - --- Relief Valve Flow

--- Bypass Valve Flow n

_/

5 ' ~

'..' N

, s

[

e .

s ~~

e 50.0 -

. 100.0 -

' / L--*--

0.0 00 ' ----

00 3.0 6.0 0.0 3,0 6.0 Time (sec) Time (sec)

\ #

Level (inch-REF-SEP-SKRT) - Y Void ReaMty !

Vessel Steam Flow Doppler Reactivity 200.0 -

--- Turbine Steam Flow 1.0 -

-- Scram Reactivity

--- Feedwater Flow - - Total Reactivity G .*

w - ,4 m

g 100.0 p. 0.0 , ,1 , ,.

y ;i, e . ,, I i e ', ,

q,

i >,

y 0.0 r t - r," - - - - - - - - - - - - -

g-1.0 -

g1

'.,' C l i s ',. \s

~

\

-100.0 ' '

- 2.0 '

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

Figure 40 Plant Response to 'Ibrbine 'IYip w/o Bypass (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) WITH ICF)

Page 63

RIVER BEND 24A5188 B,gload 6 Rev. 3 Neutron Flux Vessel Press Rise (psi)

Ave Surface Host Flux -

Safey Valve Flow 150.0 - --- Coro inlet Flow 30 0 - --- Relief Valve Flow

--- Bypass Valve Flow

./ \

100.0

g 200.0 2 ', -

's s !

e -

~, '

e

~'s%

$0.0 -

% 100.0 -

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

I Level (incNEF-SEP-SKRT) Void Reactivity Vessel Steam Flow Doppler Reactivity 200.0 - --- Turbine Steam Few 1.0 - -

- Scram Reactivt

--- Feedwater Flow -

- Total Reactvity ,,..

. g y ... *..

8 .-

0.0 g.. . . . -

3 100.0 3

9--% . s , N - "*

l c N'.

e -

\'.,s ., .

\'.

s ,

-................ { g 0.0 - ------------- ts 1 g-1.0

= i i i.

\

-100.0 ' \ '

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

Figure 41 Plant Response to Press. Regulator Failure (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) WITH ICF)

Page 64

RIVER BEND 24A5188 Reload 6 Rev.3 s

Ne p Yiux Vessel Press Rise (psi)

W y Ave Surface Heat Flux - Safety Valve Flow 150.0 - Core inlet Flow 1250 - --- Relief Valve Flow

- - - Core inlet Subcoohng i

--- Bypass Valve Flow .

l.

__ l

- - - - ~,n-+

100 0 " k 75 0 -

' \, b e , N 2 Y '\

, Y

~

50.0 -

25.0 - " " " ~

I

.l -

l

_J....

l 0.0 ' I

- 25.0 '

O.0 90 18.0 0.0 9.0 18 0 Time (sec) Time (sec)

Level (inct>-REF-SEP-SKRT) Void ReactMty I

- - Vessel Steam Flow - - - - Doppler Reactivity 150 0 -

--- Turbine Steam Flow 1.0 -

--- Scram Reactivtty

--- Feedwater Flow - - - Total Reactivtty G

h _-3 f ,-

g 100.0

's 0.0 - - W ; . -Q - ,-- :Si ,'

,,\

x C

l' . h !

' ~

~

h,.\ f i.

50.0 -

N-1.0 -

l., l* '\* . e \

ll .' ', ' .# ,' '. ' ' i lil ' '.* . ,",l'. : . , ,, I I

P.

0.0 '

- 2.0 I h 0.0 9.0 18.0 0.0 9.0 18.0 Time (sec) Time (sec)

Figure 42 Plant Response to FW Controller Failure (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) FWHOOS with ICF)

Page 65 i ms

IIVER BEND 24A5188 teload 6 Rev. 3 Neutron Flux Vesul Press Rise (psi)

Ave Surface Heat Flux - - - Safety Valve Flow 150.0 - ,- -- Core Wet Flow 300.0 -

--- Relief Valve Flow

-- - Bypass Valve Flow l u g 100.3 , ,. r, s 200.0 -

E

., 'N ,~~ 5 N e .

. e 50.0

.,,, 100.0 -

c---- .

0.0 O.9 - '

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

A / Void Reactivity Level (inch-REF-SEP-SKRT)

Vessel Steam Flow -

Doppler Reactivity 200.0 - --- Turt>ine Steam Flow 1.0 -

- Scram Reactivtty

--- Feedwater Flow _

-- Total Reactivity 2

m t\

7 100.0 0.0 f.,{..,,..

, ----._, .~.- p .

e r; -g i l ', , ,,, ,,

, g, 1 ,

. , e i,,,., ... ..- ... .2 \ i 0.0 --l y' ---- -------

x

- 1.0 -

.

. 1 4

Ik g

I'

-100.0 I '

- 2.0 II l '

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

Figure 43 Plant Response to Load Reject w/o Bypass (BOC7 to EOC7-3693 mwd /MT i

(3350 mwd /ST) FWHOOS with ICF)

Page 66

UVER BEND 24A5188 !

teload 6 Rev. 3 Neutron Flux Vessel Press Rise (psi)

* . Ave Surface Heat Flux -

- Safety Valve Fksw 150.0 - - .j-- Core inlet Flow 300.0 - --- Relief Valve Flow

- - - C;.ess Valve Flow

/n u i

100.0 /, 200 0 2 e w g

. 'N~~ ~s~~.

g 50.0 -

100.0 -

(-.----.--.-

0.0 O.0 I I 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) . Time (sec)

Level (inch-REF-SEP-SKRT) /\ / Void ReactMty

- Vessel Steam Flow - Doppler Reactivtty 200.0 - -- - Turt4ne Steam Flow 1.0 -

-- Scram Reactivity

--- Feedwater Flow -- Total Reactivity .

g -

- ,p,,,,,......-

l 0.0 7 100.0

}.g [ ' ,' - - - -. . .-

n:'. .. - \/

,. ' ,.. .. ...... { (1 0.0 W'..,.., ;- ; f h 1, ,

. . - - - - - - - 3-1.0 g

\!1

.-' e

)

g.

-100.0 I '

- 2.0 \)'

I ' '

O.0 3.0 6.0 0.0 3.0 6,0 Time (sec) Time (sec)

Figure 44 Plant Response to 'Ihrbine Trip w/o Bypass (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) FWHOOS with ICF)

Page 67

UVER BEND 24A5188 teload 6 Rev.3 Neutron Flux Vessel Press Rise (psi)

Ave Surface Heat Flux - -

Safety Valve Flow 150 0 - --- Core inlet Flow 300,0 - --- Rehof Valve Flow

- - - Bypass Valve Flow

,_ ./ ~ 's g 100.0

-* '., \s g 200.0 s a :

%* s [

g. -

A l

's' '

50.0 %

., 100.0 -

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

I Level (inct>-REF-SEP-SKRT) Void ReactMty Vessel Steam Flow - -

Doppler Reactivity

200.0 - --- Turtnne Steam Flow 1.0 - - - Scram Reactivity

--- Feedwater Flow - - TotalReactivity . .

m

,.=.. ***,, ,

E ,.

g 100.0 0.0 g',,,,.

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

\ \

8 ~

\- , , p- \ 'l A.

.. ................... .n 5 0.0 -

\ ~. ..

n - ;

g -1.0

\

\

\ ,

t

-100.0 * ' L '

- 2.0 '

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

Figure 45 Plant Response to Press. Regulator Failure (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) FWHOOS with ICF)

Page 68

RIVER BEND 24A5188 Reload 6 Rev. 3

- I N[utron Flux Vessel Press Rise (psi) d Ave Surface Heat Flux *

Safety Valve Flow 150 0 -

--- Cors inlet Flow 1250 -

--- Relief Valve Flow

- -- Core inlet Subcooling ---

Bypass Valve Flow J

100 o a ____ - d._****** 75.0 -

2 % e Y }

,\

50.0 -

25.0 - r -- -

I w.j -

.___-.J....

- 0.0 ' ' ~ l

- 25.0 0.0 90 18.0 0.0 9.0 18.0 Time (sec) Time (sec)

Level (inch-REF-SEP-SKRT)

Void ReactMty N '

- - Vessel Steam Flow - * - - - Doppler ReactMty 150.0 - --- Turbine Steam Flow 1.0 -

--- Scram ReactMty

--- Feedwater Flow --- TotalReactMty n

-. . . . . y ,

C j .'

- n . V - , ,q - , - g O.0 ,.

g 100.0 n - . - - - ---

,\

C 8

I i

l. g ll ., .a I 50.0 -

j-1.0 -

()i l' ' ll',' ,,' , ' ',,

, , [-

ll * *, o, '

If I: : : .' ',' l l Ij i 1. ' , ' ,

l 0.0 ' ' ## '

- 2.0 ' ' '

0.0 9.0 18.0 0.0 9.0 18.0 Time (sec) Time (sec) t l

Figure 46 Plant Response to FW Controller Failure (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) FWTR-100%P/10057cF)

Page 69

IIVER BEND 24A5188 teload 6 - Rev. 3 E

f-Neutron Flux

- Ave Surface Heat Flux Ve6sel Press Rise (psi)

Safety Valve Flow 150 0 - -- -- Core inlet Flow 300 0 - --- Relief Valve Flow Bypass Valve Flow 100 0 '

' '. 200.0 -

N\ - - -

a.

e

?, w ' ~ ~~

a e -

, ~~~.

50.0 - '.,' .,- 100.0 -

.,, . i 0.0 O.0 O.0 3.0 6.0 0.0 3.0 60 Time (sec) Eme (sec)

^I Void ReaYty Level (inch-REF-SEP-SKRT)

- - Vessel Steam Flow -

Doppler ReactYty 200.0 - --- TurtWne Steam Flow 1.0 -

-- Scram Reactivity

--- Feedwater Flow -- TotalReactivtty

~ 6 **.....

s n ,. ....-

e i g 100.0

- 0.0 .,

y 7,7 ~. . .

g c...

c: : ', .. . . .

y ~ ,\, ,

0.0 p---.,f

.g-1.0 -

.,'.'l E l, g

i.

-100.0 , t .

- 2.0 ' '

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

Figure 47 Plant Response to Load Reject w/o Bypass (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) FWTR-100%P/100%F)

Page 70 a

IIVER BEND - 24A5188 teload 6 Rev.3 i

i f Neutron Flux - Vessel Press Rise (pal)

Ave Surface Heat Flux Safety Valve Flow I

150 0 -

--- Core inlet Flow 300.0 - --- Relief Valve Flow k - - - Bypass Valve Flow I

e 1000 /s

e 200.0 -

,3

/,W\ 9.

'e" '% N en E - C N gt

%'- ,,,,,' pt 50.0 -

100.0 -

0.0 O0 '

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

Level (inch-REF-SEP-SKRT) Void Mvtty

- - - Vessel Steam Flow Doppler Reactivity 200.0 -

--- Turbine Steam Flow 1.0 -

-- Scram Reactivity

- * - Feedwater Flow -- Total Reacavity g"'

l V 100.0 -

0.0 ..-

-F.'

g 7,~.. .

e c : ~. ., '

Y\ -

.- ,.. ... ... {

0.0 ,-r,,----- - - - - . - - -

] -1.0 1

,.: m \

\ 1, 4

I. l

\\ l

-100.0 1 -

-2.0 i1- I -

0.0 3.0 6.0 l

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

Figure 48 Plant Response to 'Ihrbine ' Rip w/o Bypass (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) FWTR-100%P/100%F)

Page 71

(IVER BEND 24A5188 teload 6 .Rev.3 Neutron Flux Vessel Press Rise (psi)

* *

Ave Surface Heat Flux

Safety Velve Flow 150.0 - --- Core inlet Flow 300.0 - --- Rohef Valve Flow

--- Bypass Valve Flow s~%

100 0 < ' "". \ 200.0 -

' \

+

. g g ', \ @ _.

Y ',

. ~s Y

$0,0 -

's*-~ '- 100.0 -

a...

0.0 '

O.0 O.0 5.0 10.0 0.0 5.0 10 0 Time (secs Titre (sec)

I Level (inch-REF-SEP-SKRT) Void Reactivity

- Vessel Steam Flow --

Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 - -

- Scram Reactivity

--- Feedwater Flow - - Total Reactivity **

g -

2 5

100.0 -

0.0 g'. ,,*,'

, F *'--, - - - , p # _, g g L N',

8 .

N'

)*h,e

.' * ................ \

N. ,.

0.0 - %- ------------

tcc -1.0 - I

$ g e

\

g l

-100.0 ' ' ' ' I I

- 2.0 '

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

Figure 49 Plant Response to Press. Regulator Failure (BOC7 to EOC7-3693 mwd /MT (3350 mwd /ST) FWTR-100%P/100%F)

Page 72

IIVER BEND 24A5188

.teload 6 Rev, ).

utron Flux Vessel Press Rise (pal) surface Heat Fluu * * * *

Safety Valve Flow 150.0 - ----

Inlet Flow 300 0 - --- Relief Valve Flow f --- Bypass Valve Flow h"N , s '. '

100.0 -

200 0 -

E 2 %k*% 2 g- ^'s . s 8

.,'~-.

50 0 - *

., 100.0 -

a. ,, ,

0.0 I 0.0 #' '

O.0 4.0 8.0 00 4.0 8.0 Time (sec) Time (sec)

Level (inch-REF-SEP-SKRT) Void vtty

* * *

Vessel Steam Flow ***** Reacti 200.0 - --- Turbine Steam Flow 1.0 - - - - Sc Reactivtty

--- Feedwater Flow ---

Reactivity G

w .

N,,

t 100.0 *

m w', \ .N %*

,/.# 0.0 ,-

$ \ * ,

,g s ,\ .

g ,

g g ,'.***-*****..,,***., g, , ..'

g- i g

g i N

< \\

0.0 -

hi** _N--------- - 1.0 -

gi E l 't

~ -

\

... ll

-\

l '

-100.0 -2.0 ' I '

0.0 - 4.0 8.0 0.0 4.0 8.0 Time (sec) Time (sec)

Figure 50 Plant Response to MSIV Closure (Flux Scram)

Page 73

UVER BEND - 24A5188 Reload 6 Rev.3 Appendix A Analysis Conditions To reflect actual plant parameters accurately, the values shown in Table A-1 were used this cycle.

Table A-1 STANDARD Parameter Analysis Value Thermal power, MWt 2894.0 Core flow, Mlb/hr 84.5 Reactor pressure, psia 1055.0 Inlet enthalpy, BTU /lb 527.9 Non-fuel power fraction -

0.039 Steam flow analysis, 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 EEOC WITH ICF 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 0.039 Steaniflow analysis, Mlb/hr 12.45 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 Page 74 L

UVER BEND 24A5188 lt'oad 6 Rev.3 Appendix A Analysis Conditions (continued)

EEEOC WITIIICF AND FFWTR Parameter Analysis Value Thermal power, MWt 2894.0 Core flow, Mlb/hr 90.4 Reactor pressure, psia 1055.1 Inlet enthalpy, BTU /lb 519.0 Non-fuel power fraction 0.039 Steam now analysis, Mlb/hr 11.00 I)ome pressure, psir 1025.0

'Ibrbine pressure, psig 994.7 No of Dual Mode S/R Valves 9 Relief mode lowest serpoint, psig 1133.0 Safety mode lowest secpoint, psig 1200.0 FWTR-100%P/100%F Parameter Analysis Value Thermal power, MWt 2894.0 Core flow Mlb/hr 84.5 Reactor pressure, psia 1053.9 Inlet enthalpy, BTU /lb 516.8 Non-fuel power fraction 0.039 Steam flow analysis, Mlb/hr 11.00 Dome pressure, psig 1025.0 Turbine pressure, psig 994.7 No. of Dual Mode S/R Valves 9 Relief mode lowest setpoint, psig i133.0 Safety mode lowest setpoint, psig 1200.0 Page 75

IIVER BEND 24A5188 Reload 6 Rev. 3 Appendix A Analysis Conditions (continued)

STANDARD-HALING Parameter Analysis Value Thermal power, MWt 2894.0 Core Dow, Mlb/hr 84.5 Reactor pressure, psia 1055.0 Inlet enthalpy, BTU /lb 527,9 Non-fuel power fraction 0.039 Steam Dow analysis, Mlb/hr 12.46 Dome pressure, psig 1025.0 Turbine pressure, psig 985.9 No. of Dual Mode S/R Valves 9 Relief mode lowest setpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0 EEOC WITH ICF- HALING Parameter Analysis Value Thermal power, MWt 2894.0 Core flow, Mlb/hr 90.4 Reactor pressure, psia 1056.4 Inlet enthalpy, BTU /lb 529.3 Non-fuel power fraction 0.039 Steam Dow analysis, Mlb/hr 12.45 Dome pressure, psig 1025.0 Turbine pressure, psig 985.9 No. of Dual Mode S/R Valves 9 Relief mode lowest setpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0 Page 76

I RIVER BEND 24A5188 l Reload 6 Rev. 3 Appendix A Analysis Conditions (continued)

EEEOC WITH ICF AND FFWTR HALING Parameter Analysis Value Thermal power, MWt 2894.0 Core flow, Mlb/hr 90.4 Reactor pressure, psia 1055.1 Inlet enthalpy, BTU /lb 519.0

'Non-fuel power fraction 0.039 Steam flow analysis, Mlb/hr 11.00 Dome pressure, psig 1025.0 Turbine pressure, psig 994.7 No. of Dual Mode S/R Valves 9 Relief mode lowest setpoint, psig i133.0 Safety mode lowest setpoint, psig 1200.0 EOC WITH FFWTR HALING-100%P/100%F Parameter Analysis Value Thermal power, MWt 2894.0 Core flow, Mlb/hr 84.5 Reactor pressure, psia 1053.9 Inlet enthalpy, BTU /lb 516.8 Non-fuel power fraction 0.039 Steam flow analysis, Mlb/hr 11.00 Dome pressure, psig 1025.0 Thrbine pressure, psig 994.7 No. of Dual Mode S/R Valves 9 Relief mode lowest setpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0 Page 77

UVER BEND 24A5188 Teload 6 Rev. 3 Appendix A Analysis Conditions (continued)

STANDARD-MOC Parameter Analysis Value Thermal power, MWt 2894.0 Core now, Mlb/hr 84.5 Reactor pressure, psia 1055.0 Inlet enthalpy, BTU /lb 527.9 Non-fuel power fraction 0.039 Steam flow analysis, Mlb/hr 12.46 Dome pressure, psig 1025.0 Turbine pressure, psig 985.9 No. of Dual Mode S/R Valves 9 Relief mode lowest setpoint, psig i133.0 Safety mode lowest setpoint, psig 1200.0 MOC WITH ICF Parameter Analysis Value Thermal power, MWt 2894.0 Cure flow, Mlb/hr 90.4 Reactor pressure, psia 1056.4 Inlet enthalpy, BTU /lb 529.3 Non-fuel power fraction 0.039 Steam flow analysis, Mlb/hr 12.45 Dome pressure, psig 1025.0 Turbine pressure, psig 985.9 No. of Dual Mode S/R Valves 9 Relief mode lowest setpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0 Page 78

RIVER BEND 24AS188 Reload 6 Rev.3 1

Appendix A i Analynis Conditions (continued)

MOC-FWHOOS with ICF

Parameter Analysis Value Thermal power, MWt 2894.0 Core flow, Mlb/hr 90.4 Reactor pressure, psia 1055.1 Inlet enthalpy BTU /lb 519.0 Non-fuel power fraction 0.039 Steam flow analysis, Mlb/hr . 11.00 Dome pressure, psig 1025.0 Turbine pressure, psig 994.7 No. of Dual Mode S/R Valves 9 Relief mode lowest setpoint, psig 1133.0 Safety mode lowest setpoint, psig 1200.0 MOC-FWTR 100%P/100%F

- Parameter . Analysis Value Thermal power, MWt 2894.0 Core flow, Mlb/hr 84.5 Reactor pressure, psia 1053.9 Inlet enthalpy, BTU /lb 516.8 Non-fuel power fraction 0.039 Steam flow analysis, Mlb/hr 11.00

~

Dome pressure, psig 1025.0 lbrbine 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 i

Page 79

RIVER BEND 34A5188 Reload 6 Rev. 3 Appendix B Alternate Analysis for Feedwater Temperature Reduction To provide for improved operating flexibility and cycle extension for Cycle 7, expanded operating domain analyses were performed for increased Core Flow (ICF) at 107% rated and intermittent use of Final Feedwater Temperature Reduction (FFWTR) to a temperature (at full power) of 320 degrees F. The analyses for cycle extension with ICF were performed at EEOC712 exposure point using appropriate thermal hydraulic condi.

tions. The analyses for cycle extension with ICF and FFWTR was performed at EEEOC713 exposure point achieved with ICF and FFWTR using the appropriate thermal bydraulic conditions, Contained in this license submittal are results of all analyses evaluated for this licensing ac;ivity. The transient MCPR values for all analyses are given in Section 11. The analyses for ICF and FFWTR bound the intermittent concurrent use of FFWTR from BOC to EEEOC operation with ICF and FFWTR.

The Final Feedwater Temperature Redu: tion (FFWTR) extension flexibility option cannot be exercised until the GE Nuclear Service organization has completed their work and evaluation.

12. EEOC7 identifies the rated power operation exposure point attainable. using ICF only. For Cycle 7 the core average exposure for EEOC7 is 26,476 Mwd /MTU.

13 EEEOC7 identaries the rated power operation exposure point att. unable, using !CF and FFwTR. For Cycle 7 the cote average exposure for EEEOC7 is 27,133 Mwd /MTU, Page 80

n J ~- A - J A.J-. .1 _ _

IIVER B8dND 24A5188 teload 6 Rev. 3 Appendix C Basis for Analysis of Loss-of-Feedwater Heater Event The loss-of-feedwater heating event was analyzed at 102% rated power using the BWR Simulator Code (Reference B-1). The use of this code is permitted in GESTAR II(Reference B-2). The transient plots, nectron flux and heat flux values normally reported in Section 9 are not an output of the BWR Simulator Code; therefore, these items are not included in this document.

References:

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

B-2 General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A (latest approved version),

o Page 81

RIVER BEND 24A5188 Reload 6 Rev. 3 Appendix D Basis for Analysis of Core-Wide and Overpressurization Transients The Core-Wide and Overpressurization Transients were analyzed with four valves out of sixteen operable in relief mode and five valves out of sixteen operable in safety mode. The seven inoperable S/RV's are appli-cable only to the Vessel Overpressur. ASME Code Compliance upset condition and fuel thermal performance criteria. The analyses performed reflect the River Bend Station Technical Specific tions, which permit operation with 4 valves in relief mode and 5 valves in safety (spring) mode, In addition , the core-wide pressurization transients and overpressurization transients were evaluated with new opening setpoints on the S/RV's. The GE Nuclear Services analysis is still not complete and these set points cannot be implemented until such time as their evaluation has been completed.

Page 82

$$8' 3#N$ ,

1 i

Appendix E l Basis for Analysis of Loss-of-Coolant Accident l

'Ihe 081) MAPLHOR's for Cycis 7 have been generated assuming a MCPR of 21.28 and a diesel stanup time of 10 seconds, which is the sarne as the FS AR basis. By having generated the OEl 1 M APLHOR's with the above assumptions the potentially lower OLMCPR MOC points reported in this submittal are not applicable until further analyses are performed or S AFER/OESTR is implenwnted, o

e Page 83

. . . . . , . . _ . _ . _ _ s_ . _ _ _ . _ _ . _ . . _ . . . . _ _ . , _ _ _ . _ . . _ . . _ . _

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

(IVER BEND 34A5188 teload 6 Rev. 3 Appendix F 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 methe ne minimum required boron shutdown margin represents the biases and uncertainties needed to assure subniticality. Als 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 case the technical r,peci.

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 GElI in the core is 1.4%.

Page 84 l . - - . . _ -. .-. - - . --

(IVER HEND 24A5188.

teload 6.

, Rev. 3 4

Appendix G Plant Operation Above the Rated Load Line Up to Rated Power For River Bend Station, Reload 6/ Cycle 7 analyr.es have been performed in addition to the standard reload analyses to support operation in the extended operation region. De consequences of the AOO's liave been evaluated to determine if operating limits reported in Section 11 are bounding for operation

in the extended operating range. The analyses were perfonned at 100% power and 91% now with both normal feedwater temperature and reduced feedwater temperature. The results nf the calculations are reported below and are bounded by the OLMCPR operating limits for exposure ranges BOC7 to EEOC7 t

and BOC7 to EOC7-3693 mwd /MT(3350 mwd /ST) reported in Section 11.

Exposure ranges BOC7 to EOC7100%Phl%F Exposure point: EOC7 Gell GE8x8EB FW Controller Failure 1.28 nc a Load Reject w/o Bypass 1.30 nc Turbine Trip w/o Bypass 1.28 nc Press. Regulator Failure 1.20 nc Exposure range BOC7 to EOC7100%PN1%F 320 Deg. F Exposure point: EOC7 Gell GE8x8EB FW Controller Failure 1.28 nc Load Reject w/o Bypass 1.28 nc hrbine Trip w/o Bypass 1.27 ne IWss. Regulator Failure .. 1.21 nc

. nc . nm calcutmed Page 85

(IVER BEND 21A5108 teload 6 Rev. 3, l

1 Appendix G (cont!nued) !

Plant Operation Above the Rated Load Line Up to Rated Power Exposure range: EOC7 to EOC7-M93 M Wd/MT (3350 mwd /ST) l00% P91 % F Exposure point: EOC7-M93 mwd /MT (3350 mwd /ST)

Gell GE8x8EB FW Controller Failure 1.21 nc*

Load Reject w/o Bypass 1.23 ne hrbhe Trip w/o Bypass 1.22 nc Press. Regulator Failure 1.17 nc Exposure range HOC 7 to EOC7-M93 mwd /MT (3350 mwd /ST) 100%P/91 % F 320 Deg.F.

Exposure point: EOC7-M93 mwd /MT (3350 mwd /ST)

Gell GE8x8EB FW Controller Failure 1.19 nc Load Reject w/o Bypass 1.20 nc hrbine Trip w/o Bypass 1.18 ne IYess. Regulator Failure 1.17 nc

' nc a run calculated Page 86

\ ,

RIVER BEND 24A5188 Beload 6 Rev. 3 Appendix H Off Rated Curves 1.0 ,

(30.0.1.735) 1.6 -

(40.0.1.608) l 1.5 -

1.4 -

'# ~

GE11 (84,92.1.28) ,

(89.03.1.25) 1,3 I . I I t t i

> , , . t , t , i , i ,

0.0 10.0 20.0 30.0 40.0 50.0 40.0 70.0 80.0 90.0 100.0 110.0 Core Flow (W), % of Rated Core Flow Figure 51 Flow Dependent MCPR Limits, MCPR(f)

(BOC to EOC-3350 MWD /ST)

Page 87

(IVER BEND 24A5188 teload 6 . Rev.3 4

Appendix H (Continued)

Off Rated Curves 4

1.s

~

(40.0,1.758) 4 1.7 -

1.6 -

(40.0,l.614) 1.5 - '

, (70.0,1.491) 1.4 -

(70.0,1.357) 1.s -

GE11 (89.47,1.28) '.,

(97.06,1.25) jy 1 . t . 1 . t . I , I . l . l . t , I 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70 0 40.0 90.0 100.0 110.0 Thermal Power, % of Rated Thermal Power Figure 52 Power Dependent MCPR Limits, MCPR(p)

(BOC to EOC-3350 MWD /ST)

Page 88

UVER BEND 34A5188 teload 6 Rev. 3 Appendix H (Continued)

Off Rated Curves 1.s I

(30.0,1,735) l 1.7 -

l

~

(40.0,1.008) 1.5 -

E

o. .

S 1.4 -

GE11 1.3 -

'e (79.44,1.32) ',

,

GE8 (89.03,1.25) 1.2 ' ' ' ' - 1 - 1 - ' - 1 1 1

. . 1 . I .

0.0 10.0 20.0 30.0 40.0 30.0 40.0 70.0 80.0 90.0 100.0 110.0 Core Flow (W), % of Rated Core Flow Figure 53 Flow Dependent MCPR Limits, MCPR(f)

(EOC-3350 MWD /ST to EEOC) l Page 89

~

IVER END 24A5188 teload Rev. 3 Appendix H (Continued)

Off Rated Curves 1.0 (40.0.1.758) 1.7 -

~

(40.0,1.614) 1.5 -

(70.0.1.491) 2 1.4 -

(70.0,1.357) 13 -

i (79.36,1.32) ' . ,

" '., GE8 (97.06,l.25) l 1.2 ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' -

o.0 10.0 20.o so.o 40.0 50.0 e0.0 70.0 a0.0 90.0 100.0 110.o Thermal Power, % of Rated Thermal Power Figure 54 Power Dependent MCPR Limits, MCPR(p)

(EOC-3350 MWD /ST to EEOC)

Page 90 m

U

ML20212A740

Text

References:

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