ML20216G120

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Rev 3 to Rbs,Cycle 9 Colr
ML20216G120
Person / Time
Site: River Bend Entergy icon.png
Issue date: 09/09/1999
From: Jaw W, Sicard P, Vo J
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20216G118 List:
References
NUDOCS 9909280428
Download: ML20216G120 (56)
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RBS CYCLE 9 COLR l Revision 3 l l l l l i

RIVER BEND STATION, CYCLE 9 CORE OPERATING LIMITS REPORT (COLR) l l

1 PREPARED BY: g2/g'g/g Date: 9 ,/ <f 9 I Responsible Engineer j

REVIEWED BY: Vp Date: ( 2.-77 Review Engineer

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APPROVED BY: c -

i Date: $bdT.l33k Manager - Safety Ana p?i '

APPROVED BY: 6 Date: 9 Director, Engineering River Bend Nuclear Station APPROVED BY: / usa ge/$/ Date: 1hde) -

cilitieff Miew Committee ver Bend Nuclear Station 4

%h 4M PDR ADOCK 0 p

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RIVER BEND Jl1-03431SRLR r

Reload 8 Rev. 2 4

Important Notice Regarding Contents of'This Report  !

Please Read Carefbily l

This report was prepared by Ceneral Electric Company (GE) solely for Entergy Operations, 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 contained 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 i

the contract between EOl and GE for fuel bundle fabrication and related services for River Send 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 authonzed; and with respect to any unauthorized use, neither GE nor any of the contnbutors to this document makes any representation or warranty (expressed or implied), as to the completeness, accuracy or usefulness of the information contained in this document or that such use of such information may not infnnge privately owned rights; nor do they assume any responsibility for liability or damage of any kind which may result from such use of such information.

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, s' l RIVER BEND J11-03431SRLR Reload 8_ _ Rev. 2 I

Acknowledgement  ;

I The engineering and reload licensing analyses, which form the technical basis of this Supplemental l Reload Licensing Report, were performed by W. E. Russell. The Supplemental Reload Licensing Report was prepared by W. E. Russell. This document has been verified by S. B. Shelton.

Revision 2 of this Supplemental Reload Licensing Report was prepared by L. A. Leatherwood and  !

verified by W. E. Russell.

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, s' l RIVER BEND Jil-03431SRLR  ;

Reload 8 Rev. 2 i L j The basis for this report is General Electric Standard Applicationfor Reactor Fuel, NEDE-24011-P-A-  ;

13, August 1996; and the U.S. Supplement, NEDE-24011.P-A-13-US, August 1996.; and NEDC-32489P )

(April 1996),"T-Factor Setdown Elimination Analysis for River Bend Station",

1. Plant-unique !! ems l

l Appendix A: Analysis Conditions j 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 Standby Liquid Control System Shutdown Capability Appendix F: Off Rated MCPR and LHGR Multiplier Curves Appendix G: Group Designations of the GGE Fuel Type '

2. Reload Fuel Bundles Cycle Fuel Type ,

Loaded Number Irradiated: )

GE8B P8SQB333-10GZ-120M-4WR-150-T(GE8x8EB) 4 68 G E8 B-P8SQB334-10GZ- 120M-4WR- 150-T (G E8x8 EB) 5 4 G E8 B-P8 SQB334-10GZ2- 120M-4WR- 150-T (G E8x8EB) 6 8 GE8B-P8SQB334-1 I GZ- 120M-4WR-150-T (GE8x8EB) 6 4 G E l l-P9SUB354- 14GZ-120T-146-T (G E l l ) 7 40 l Gell P9SUB354-13GZ-120T-146-T(Gell) 7 64 Gell P9SUB353-10GZ-120T-146-T(Gell) 7 128  ;

. Em gel 1-P9SUB388-13GZ-120T-146-T (gel 1) 9 136 gel 1 P9SUB225-NOG-120T-146-T(gel 1) 9 112 G E l l-P9SUB400-13GZ-120T- 146-T (G E l l ) 9 60 Total 624 i

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c RIVER BEND Jl1-03431SRLR Reload 8 Rev. 2

3. Reference Core Loading Pattern The maximum allowed cycle exposure for Cycle 9 is 6454 mwd /ST cycle exposure. This corresponds to an assumed reload cycle core a .. age expcsure at end of cycle of 21151 mwd /ST.

Nominal previous cycle core average exposure at end of cycle: 28212 mwd /MT I

( 25593 mwd /ST)

Minimum previous cycle core average exposure at end of cycle 28212 mwd /MT from cold shutdown considerations: ( 25593 mwd /ST)

Assumed reload cycle core average exposure at beginning of 16201 mwd /MT <

cycle:

( 14697 mwd /ST)

Assumed reload cycle core average exposure at end of cycle: 23315 mwd /MT

( 21151 mwd /ST)

Reference core loading pattern: Figure 1

4. Calculated Core Effective Multiplication and Control System Worth - No Voids,20*C Beginning of Cycle, ke gegy, Uncontrolled 1.109 Fully controlled 0.941 Strongest control rod out 0.984 R. Maximum increase in cold core reactivity with exposure into cycle. Ak 0.000
5. Standby Liquid Control System Shutdown Capability Boron (ppm) Shutdown Margin (ak)

(at 20'C) (at 160 C. Xenon Free) 660 0,044

6. Reload Unique GETAB Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters Exposure: BOC9 to EOC9 I

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

Gell 1.15 l 1.58 l 1.32 1.035 l 7.156 104.2 l 1.18 Page 5

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l RNER BEND J11-03431SRLR Reload 8 Rev. 2 Exposure: SOC 9 to EEOC9 ICF HBB Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Asial' R-Factor Power Flow MCPR (MWt) (1000 lb/br)

- gel 1 1.45 1.56 1.33 1.035 7.083 113.1 1.21 i i

i Exposure: BOC9 to EEEOC9 ICF & FWTR- HBB Peaking Factors Fuel Bundle Busci Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (1000 lb/br) gel 1 1.45' l.56 l 1.36 1.035 7.031 l 113.9 1.24 i l

i Exposure: BOC9 to EOC9100P/100F-UNDERBURN Peaking Facton Fuel Bundle Bundle loisial Design Local Radial Axial R Factor Power Flow MCPR  ;

(MWt)

(1000 lb/hr) gel 1 1.45 1.71 1.65 1.035 7.760 99.0 1.12 ,

Exposure: BOC9 to EEOC9 ICF-UNDERBURN Peaking Factors Fuel Bundle Bundle laitial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (1000 lb/hr)

' gel 1 1.45 1.66 1.65 1.035 7.538 108.3 1.19 Exposurv: BOC9 to EEEOC9 ICF-FWTR-UNDERBURN Pesking Factors Fuel Bundle Bundle initial Design Local Radis.: Axial R Factor Power Flow MCPR I (MWt) (1000 lb/hr) l GEli 1.45 1.72 l 1,76 1.035 7.771 106.1 l 1. I o l Pace 6

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l' RIVER BEND J11-03431SRLR Reload 8 Rev. 2

! 7. Selected Margin Improvement Options Recirculation pump trip:

!- Yes Rod withdrawallimiter: Yes

. Hermal power monitor: Yes

. Improved scram time: No Measured scram time:. No Exposure dependent limits: No Exposure points analyzed: 1

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 %

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 Turbine bypass system OOS: No Safetyirelief valves OOS: Yes(See Appendix D) l ADS OOS: No EOC RPTOOS: No Main steam isolation vais es 005: No Feedwater Heater OOS: Yes 4

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RIVER BEND Jl1-03431SRLR Reload 8 Rev. 2

9. Core-wide AOO Analysis Results All core wide AOO GE8 analysis results are conservatively bounded by the following Gell analysis results.

Methods used: GEMINI: GEXL-PLUS Exposure range: BOC9 to EOC9 Uncorrected ACPR <

Event Flux Q/A Gell Fig.

(%NBR) (%NBR)

Load Reject w/o Bypass 143. 100. 0.06 2 Loss of feedwater heating . -

0.13 .

Exposure range: SOC 9 to dEOC9 ICF.HBB Uncorrected ACPR Event Flux Q/A Gell Fig.

(%NBR) (%NBR)

FW Controller Failure 151 104 0.08 3 Turbine Trip w/o Bypass 174. 100. 0.08 4 Load Reject w/o Bypass 170. 100. 0.08 5 Press. Regulator Failur: 123 106 0.06 6 l Exposure range: BOC9 to EEEOC9 ICF & FWTR- HBB i

Uncorrected ACPR Event Flux Q/A Gell Fig.

(%NBR) (%NBR)

FW Controller Failure 174 108 0.12 7 Turbine Trip w/o Bypass l 188. 102. 0.10 8 Load Reject w/o Bypass 183. 100. 0.09 9 Press. Regulator Failure 135 106 0.08 10 Page 8

RIVER BEND .Il1-03431SRLR pain A 8 Rev. 2 Exposure reage: BOC9 to EOC9100P/100F-UNDERBURN Uncorrected ACPR Event Flux Q/A Gell Fig.

(%NBR) (%NBR)

Load Reject wio Bypass 100. 100. 0.00 11 Exposure range: BOC9 to EEOC9 ICF-UNDERBURN a

Uncorrected ACPR l Event Flus Q/A Gell Fig.

(%NBR) (%NBR)

FW Controller Failure 105- 105 0.03 12 Load Reject wio Bypass 100, 100. 0.00 13 Turbine Trip w/o Bypass 100. 100. 0.00 14 Press. Regulator Failure 123 106 0.07 15 l

Exposure range: BOC9 to EEEOC9 ICF-FWTR-UNDERBURN j

Uncorrected .1CPR Event Flux. Q/A Gell Fig.

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. (%NBR) (%NBR)

FW Controlier Failure 112 108 0.07 16 Load Reject w/o Bypass ' 100. 100. 0.00 17 Turbine Trip w/o Bypass .100.. 100. 0.00 18 Press. Regulator Failure 135 106 0.07 19

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  • 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 applied. A cycle specific rod withdrawal analysis was found to be bounded by the generic RWE analysis reported in the referenced report.

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~ RIVER BEND  !

J1'. 03431SRLR Paland 8 Rev. 2

11. Cycle MCPR Values
  • 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 Evaluasion. May 24,1996) a cycle specific Safety Limit MCPR calculation 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 documented in GESTAR with the following exceptions:

1. The reference 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: 1.12 Single loop operation safety limit: 1.13 Non-aressurization events:

Exposure range: BOC9 to EOC9 GEli Loss of feedwater heating- 1.25 Fuel Loading Error (mislocated) 1.25 Fuel Loading Error (rotated) 1.27 Rod Withdrawal Error 1.24 Pressurization events:

Exposure reage: BOC9 to EOC9 Exposure point: EOC9 Option A GE11 Load Reject w/o Bypass 1.19

' For single loop operation. the MCPR operating limit is 0.01 greater than the two-loop value.

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RIVER BEND Jl1-03431SRLR l

Peload 8 Rev. 2 I I

Exposure range: SOC 9 to EEOC9 ICF-HBB Exposure point: EOC9 l Option A l Gell FW Controller Failure 1.22

[:rbine Trip w/o Bypass 1.22 i ILoad Reject w/o Bypns 1.21 Pcess. Regulator Failure

- 1.20 1

Exposure range: BOC9 to EEEOC9 ICF & FWTR - HBB Exposure point: EOC9 Option A Gell I FW Controller Failure 1.26 Turbine Trip w/o Bypass 1.23 Load Reject w/o Bypass l 1.22 Press. Regulator Failure 1.21 i

Exposure range: BOC9 to EOC9100P/100F UNDERBURN Exposure point: EOC9 Option A GE11 Load Reject w/o Bypass 1.12 Exposure range: BOC9 to EEOC9 ICF-UNDERBURN Exposure point: EOC9 Option A Gell FW Controller Failure 1.14 Load Reject w/o Bypass 1.12 l

Turbine Trip w/o Bypass 1.12 Press. Regulator Failure 1.21 4

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. RIVER BEND J11-03431SRLR Paland 8 Rev. 2 Eaposare range: SOC 9 to EEEOC9 ICF-FWTR-UNDERBURN l Eaposare point: EOC9 i

Option A l

Gell

! FW Controller Failure 1.17 Load Re,iect w/o Bypass 1.12 Turbine Trip w/o Bypass 1.12 Press. Regulator Failure 1.21

12. Overpressurization Analysis Summary Psl Pv Plant Event (psig) (psig) Response l MSIV Closure (Flux Scram) 1261 1293 Figure 20
13. Loading Error Results Variable water gap misoriented bundle analysis: Yes 2 Misoriented Feel Bandle ACPR gel 1 P95UB400-13GZ 120T-146-T(gel 1) 0.13 i Gell-P9SUB225 NOG 120T-146-T(Gell) 0.07 {

l gel 1-P9SUB388-13GZ 120T-146 T(gel 1) 0.15 i l

- 14. Control Rod Drop Analysis Results 1 i

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

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accident analysis is not required. NRC approval is documented in NEDE-24011-P-A-US.  ;

l 15. Stability Analysis Results l GE SIL-380 recommendations have been included in the River Bend Station operating procedures and l Technical Specifications: therefore, the stability analysis is not required. NRC approval for deletion of a l cycle-specific stability analysis is documented in Amendment 8 to NEDE-240ll-P-A-US. River Bend l

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includes a 0.00 penalty due to variable water gap R factor uncenainty.

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,. - if RIVER BEND Jl1-03431SRLR Reload 8 Rev. 2 Station recognizes the issuance of NRC Bulletin No. 88-07, Supplement 1, Power Oscillations in Boiling  ;

Fater Reactors (BFRs), and will comply with the recommendations contained therein.

l River Bend has been licensed in accordance with NEDO-32339-A Revision 1, Licensing Topica/ Report 1 Reactor Stability-Long-Term Solution: Enhanced Option I-A. Reference GENE-A13-00367-46, Revision 1, River Bend Cycle 7 Reactor Stability Long-Term Solution Enhanced Option I-A Stability Region Boundary Generation and Validation documents the enhanced Option I-A (EI 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 reference is the responsibility of EOI. RVM confirms best-estimate code boundary validation ytability criteria in accordance with NEDO-33229-A Revision 1, Section 8.3.3 (Optional IVM Adjusted Region Boundary Validation). .De River Bend Cycle 9 Option I A stability decay ratios can be found in Figure 21.

16; Loss-of-Coolant Accident Results' LOCA method used: SAFER /GESTR-LOCA l - 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. These analyses yielded a licensing basis peak cladding temperature (PCT) of l: 1300'F, a peak local oxidation fraction of <0.1%, and a core-wide metal-water reaction of <0.05%. The following tables list the least limiting and most limiting MAPLHORs for the fresh GE 11 fuel designs.

De LOCA analysis results presented in GENE Jil-03431-29-02P, July 1999, revised the MAPLHGR l limits for the Cycle 7 (GGE) fuel types in the current cycle. Dese analyses yielded a licensing basis l peak cladding temperature (PCT) of 1300'F, a total (initial steady-state plus post LOCA) peak local oxidation fraction of <10%, and a core wide metal-water reaction of <0.05%. The analyses for the GGE fuel types are valid for peak pellet exposures of s65 GWDNTU. The SLO analysis resulted in a y MAPLHGR multiplier of 0.79 for all gel I fuel types and 0.87 for GE8x8EB fuel types.

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8 For format explanation, see lett J. S. Charnley (GE) to M. W. Hodges (NRC), Recommended MAPLNGR TechnicalSpecificatioarfor Multiple Lattice FuelDesigns. March 9,1987. Most Limiting and Least Limiting refer to the lowest and highest limits, respectively, of any enriched lattice in the bundle.

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I' RIVER BEND J11-03431SRLR Reload 8 Rev. 2

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

Bundle Type: Gell-P9SUB400-13GZ-120T-146-T Average Planar Exposure l MAPLHGR ikw/ft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 10.92 11.15 0.20 0.22 10.99 11.18 1.00 1.10 11.07 11.25 2.00 2.20 11.21 11.39 3.00 3.31 11.39 11.55 4.00 4.4 I i1.56 11.70 5.00 5.51 11.70 11.87 6.00 6.61 11.85 12.03 l 7.00 7.72 11.95 12.14 8.00 8.82 12.06 12.25 9.00 9.92 12.16 12 36 10.00 11.02 12.27 12.47 12.50 13.78 12.27 12.50 15.00 16.53 12.07 12.26 l

17.50 19.29 11.78 11.93 20.00 22.05 11.46 11.60 25.00 27.56 10.83 10.94

. 30.00 33.07 10.20 10.30 35.00 38.58 9.58 9.68 40.00 44.09 8.95 0 03 45.00 49.60 8.31 8.38 50.00 55.12 7.63 7.71 55.00 60.63 6.93 7.01 57.37 l 63.24 l 6.59 6.67 57.41 l 63.28 --

6.67 57.88 l 63.80 - 6.60 l

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r- .p RNER BEND 311-03431SRLR

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

Bundle Type: gel 1-P95UB225-NOG-120T-146-T Average Planar Exposure MAPLHGR (kw/ft)

. (GWd/ST) . (GWd/MT) . Most Limiting Least Limiting 0.00. 0.00 13.28 13.40

~ 0.20 - 0.22 13.32 13.40 1.00 1.10 13.40 ,13.40 2.00 2.20 - 13.40 13.40 3.00 3.31 13.40 13.40

~

4.00 4.41 13.40 13.40 5.00 5.51 13.40 13.40 6.00 ' 6.61 13.40 13.40 7.00 7.72 13.40 13.40 8.00 8.82 13.40 - 13.40 9.00 9,92 13.40 13.40 10.00. I1.02 13.40 13.40 12.50 13.78 13.40 13.40 15.00 16.53 13.40 13.40 17.50- 19.29 13.I3 13.19 20.00 22.05 12.78 12.85 25.00 27.56 12.07 12.09 30.00 33.07 11.09 11.41 35.00 38.58 10.09 . 10.53 40.00 44.09 9.12 9.54 45.00 49.60- 8.21 8.62 50.00 55.12 7.35 7.76 55.00 ' 60.63 6.53 6.94 59.11 65.16 5.87 6.29 60.00 66.14 --

l 6.15 60.85 67.08 --

6.01 l

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RIVER BEND J1103431SRLR R*M 8 Rev. 2

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

Buulle Type: Gell-P95UB388-13GZ 120T-146-T Average Planar Exposure . MAPLHGR (kw/ft)

. (GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 10.89 < l1.11 0.20- 0.22 10.94 11.16 1.00 1.10 11.02 11.25 2.00 2.20 11.13 11.35 3.00. 3.31 11.23 11.46 4.00 4.41 11.34 11.56 5.00 5.51 11.45 11,67 6.00 6.6I I1,57 11.78 7.00 7.72 11,68 11.89 8.00 8.82 11.80 12.01 9.00 9.92 11.92 12.12 10.00 11.02 12.04 12.24 12.50 13.78 12.01 12.23 15.00 16.53 11.81 11.98 17.50 19.29 11.52 11.66 20.00 22.05 11.21 11.34 25.00 27.56 10.60 10.71 30.00 33.07 9.99 10.09 35.00 38.58 9.39 9.49 40.00 44.09 8.78 8.89 45.00 49.60 8.I4 8.26 50.00 55.12 7.48 7.61 55.00 60.63 6.78 6.93

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56.49 62.27 6.57 6.71 56.53 62.32 --

6.71 57.08 62.91 --

6.63 l

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  • RIVER BEND Jil-03431SRLR Reload 8 Rev. 2 l

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

l Group l' s

R Bundle Type: Gell P9SUB354-14GZ-120T-146-T Bundle Type: gel 1-P9SUB354-13GZ-120T-146-T Bundle Type: gel 1-P9SUB353-10GZ-120T-146-T Average Planar Exposure MAPLHGR(kw/ft)

(GWd/ST) (GWd/MT) Most/Least Limiting 1 0.0 0.0 10.00 33.9 37.4 10.00 ,

45.3 49.9 8.83 54.2 59.7 7.16 l

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  • See Appendix G for group designations.

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

I Group 2 / 3 s i

Bundle Type: Gell P9SUB354-14GZ-120T-146-T Bundle Type: gel l-P9SUB354-13GZ-120T-146-T i

Bundle Type: gel l-P9SUB353-10GZ-120T-146-T Average Planar Ex mure MAPLHGR(kw/ft)

(GWd/ST) . (GWd/MT) Most/Least Limiting l l 0.0 0.0 9.75 33.9 37.4- 9.75 i 45,3 49.9 . 8.08 l

l 54.2 59.7 7.16 I J

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8 See Appendix G for group designations.

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~ Reload 8 Rev. 2

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

. Group 4' Bundle Type: gel 1-P9SUB354-14GZ-120T-146 T Bund!e Type: gel 1-P9SUB354-13GZ-120T-146 T Bundle Type: gel 1-P9SUB353 10GZ-120T-146 T Average Planar Exposure MAPLHGR(kw/ft)

(GWd/ST) (GWd/MT) Most/Least Limiting 0.0 0.0 7.16

-33.9 37.4 7.I6 45.3 49.9 7.16 54.2 59.7 7.16

  • See Appendix G for group designations.

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RIVER BEND J11-03431SRLR

.p ,la.a g l Rev. 2

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

1 Bundle Tm: GE8B-P8SQB333-10GZ-120M-4WR-150 T Average Plasar Exposure -

MAPLHGR (kwift) l .

(GWd/ST) (GWd/MT) Most Limiting L*== Limiting 0.00 0.00 11,29 l 11.80 120 0.22 11.35 11.84 1.00 1.10 11.48 11.95 i

2.00 2.20 11.67 l 12.12

(. .3.00 3.31 11.87 12.28 4.00 4.41 12.07 l 12.45

i 5.00 5.5 I . 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 i 13.05 l 9.00 9.92 13.02 .
13.17 10.00 11.02 13.15 13.27 L

12.50 13.78 13.19. 13.22 i 15.00 , 16.53 12.90 - 12.92  !

20.00 '

22.05' 12.29 12.31 25.00 27.56 11.69 .I1.70 35.00 '38.58 10.44 10.46 45.00 49.60 8.98 9.07 50.00 55.12 6.45 -

6.55 i

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q RIVER BEND J11-03431SRLR Reload 8 Rev. 2

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 I l.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 16.53 13.31 13.32 20.00 22.05 12.64 12.64 25.00 27.56 11.96 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 i

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

Bundle Type: 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 0.20 0.22 11.42 11.91 1.00 1.10 11.54 12.00 2.00 2.20 11.71 12.13 3.00 3.31 11.89 12.28 4.00 4.4 I I2.08 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 12.9I i3.11 9.00 9.92 13.I3 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 20.00 22.05 12.63 12.64 25.00 27.56 11.95 11.96 35.00 38.58 10.46 10.52 45.00 49.60 9.08 9.21 50.00 55.I2 6.95 7.03 I

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RIVER BEND J11-03431SRLR l Reload 8 Rev. 2

16. Lns.1+f-Coolant Accident Results (cont.)

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

, (GWd/ST) (GWd/MT) Most Limiting Least Limitins 0.00 0.00 10.86 11.24 j 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 4.41 11.76 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 11.96 35.00 38.58 10.46 10.52 45.00 49.60 9.08 9.20 50.00 55.12 6.95 7.02 Page 23

^*

RIVER BEND J11-03431SRLR

' l Paw 8 Rev. 2 .

Sa gggggggg '

sa gg hhg hhhhhhh00

mMHMMME8MMEL mMMMMMMMMMMi%
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': "MMMMMMMMM5 "HMMMMMH" memammes liIIIIII 1 3 5 7 9 11 13 15 17 le il 28 25 27 23 31 33 35 37 30 41 el 45 47 49 51 53 55 Fuel Type A= Gell P95UB400-13GZ 120T 146-T (Cycle 9) F= Gell P95UB35310GZ 120T-146-T (Cycle 7)

B= Gell P9SUB225 NOG-120T-146-T (Cycle 9) G=GE88 P850B33310GZ-120M-4WR 150-T (Cycle 4)

C= Gell-P95UB388-13GZ 120T 146 T (Cycle 9) H-GE8B P850B33410GZ 120M-4WR 150-T (Cycle 5)

D= Gell-P95UB35414GZ 120T 146 T (Cycle 7)  !=GE8B P8SQB33410GZ2120M-4WR 150 T (Cycle 6)

E= Gell P95UB35413GZ 120T 146-T (Cycle 7) J=GE88-P850B334-ilGZ 120M 4WR 150 T (Cycle 6:

1 Figure 1 Reference Core Loading Pattern t

Page 24

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Page 25

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40 \- 10 se 40 30 09 40 30 Tbse tearJ Tbus tonal Figure 3 Plant Response to FW Controller Failure (BOC9 to EEOC9 ICF-HBB ) I Page 26

- 8 RIVF.R BEND Jl1-03431SRLR Reload 8 Rev. 2 4  ;

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Figure 4 Plant Response to Turbine Trip w/o Bypass (BOC9 to EEOC9 ICF HBB ) 2 s

9 Page 27

f RIVER BEND Jl1-03431SRLR Reload 8 Rev. 2 l ml~~

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ye, s. u g,., , u Figure 5 Plant Response to Load Reject w/o Bypass (BOC9 to EEOC9 ICF-HBB )

l Page 28

  • 1 1

RIVER BEND 311-03431SRLR Reload 8 Rev ._1

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Page 29

I i

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' Reload 8 Rev. 2 )

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Figure 7 Plant Response to FW Controller Failure (BOC9 to EEEOC9 ICF & FWTR -IIBB )

1 Page 30

i RIVER BEND J11-03431SRLR Reload 8 Rev. 2

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l Figure 8 Plant Respocse to T :rbine Trip w/o Bypass (BOC9 to EEEOC9 ICF & FWTR - HBB )

3-Page 31 L

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RIVER BEND J11-03431SRLR Reload 8 Rev. 2

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Figure 9 Plant Response to Load Reject w/o Bypass (BOC9 to EEEOC9 ICF & FWTR - HBB )

l Page 32

j i 9 RIVER BEND Jil-03431SRLR Reload 8 Rev. 2 l

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s.

s 4

Page 33

l l RIVER HEND Jl103431SRLR Reload 8 Rev. 2 i

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i Figure 11 Plant Response to Load Reject w/o Bypass (BOC9 to EOC9100P/100F-UNDERBURN )

Page 34

RIVER BEND J11-03431SRLR Reload 8 Rev. 2

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Page 35

i. l RIVER BEND J11-03431SRLR Reload 8 Rev. 2 l l l n.

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Page 36

.. l RIVER BEND J11-03431SRLR Reload 8 j Rev. 2

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f Pace 37 i

1 RIVER BEND J1103431SRLR Reload 8 Rev. 2 i mn. . w e a=. = mm

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t Page 38

RIVER BEND i

Jl1-03431SRLR.

Reload 8 Rev. 2 l

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Figure 16 Plant Response to FW Controller Failure (BOC9 to EEEOC9 ICF-F%TR-UNDERBURN )

Page 39

~

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RIVER BEND Jl1-03431SRLR I Reload 8 Rev. 2

)

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l ii Page 40

9 RIVER BEND J11-03431SRLR Reload 8 Rev. 2

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Pace 41 l

RIVER BEND 311-03431SRLR Reload 8 Rev. 2 i

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9 Pace 4:

i RIVER BEND Jl103431SRLR Reload 8 Rev. 2 1

.i ch.% .

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Page 43

3 l

RIVER BEND J11-03431SRLR  ;

Reload 8 Rev. 2 I

)

1-0.9 - -..

0.8 g' .. , ... ODYSY Stability l Criteria e'

0.7 ..

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0 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Channel Decoy Ratio Figure 21 Option I-A Stability Decay Ratios Page 44

p. .- i

! RIVER BEND Jl1-03431SRLR

! Reload 8 l

Rev. 2 -

Appendix A Analysis Conditions l {

! l 1

To reflect actual plant parameters accurately, the values shown in Table A-1 were used this cycle.

Table A-1 4 1

Analysis Value Parameter STANDARD ICF-HBB ICF & ICF-FWTR- Ur.derburn HBB Thermal power. MWt 2894.0 2894.0 2894.0 2894.0 Core flow. Mlb/hr 84.5 90.4 90.4 90.4 Reactor pressure. psia 1055.0 1056.4 1055.1 1056.4 Inlet enthalpy, BTU /lb 527.8 529.3 519.0 529.3 Non-fuel power fraction 0.037 0.037 0.037 0.037 Steam flow. Mlb/hr 12.46 12.46 11.00 12.46 Dome pressure psig 1025.0 1025.0 1025.0 1025.0 Turbine pressure. psig 964.3 964.3 978.1 964.3 No. of Dual Mode S/R Valves 9 9 9 9 Relicf mode lowest setpoint. psig i133.0 1133.0 1133.0 1133io Safety mode lowest setpoint. psig 1200.0 1200.0 1200.0 1200.0 l

l o

Page 45 f

l

I RIVER BEND J1103431SRLR Reload 8 Rev. 2 Appendix B Alternate Analysis for Feedwater Temperature Reduction l

To provide for improved operating flexibility and cycle extension for Cycle 9. 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 EEOC94exposure point using appropriate thermal hydraulic conditions. The analyses for cycle extension with ICF and FFWTR was performed at EEEOC95 exposure point achieved with ICF and FFWTR using the appropriate thermal hydraulic conditions. Contained in this license submittal are results of all analyses evaluated for this licensing activity. The transient MCPR values for all analyses are given in Section 11. The analyses for ICF and FFWFR bound the intermittent concurrent use of FFWTR from BOC to EEEOC operation with ICF ar.d FFWTR.

l l

' EEOC9 identifies the rated power operation exposure point attainable with a hard bottom burn (HBB) strategy.

using ICF only.

l 'EEEOC9 identifies the rated power operai%n exposure pomt attainable with a hard bottom burn (HBB) strate;> .

! using ICF only and FF%TR.

l

.. l Page 4 l

k

. . 1 RIVER BEND J11-03431SRLR Reload g Rev. 2 Appendix C Basis for Analysis of Loss-of-Feedwater Heater Event The loss-of feedwater heating event was analyzed at 100% rated power using the BWR Simulator Code l (Reference C-1). The use of this code is permitted in GESTAR II(Reference C-2). The transient plots, neutron flux and heat flux values normally reported in Section 9 are not an output of the BWR Simulator Code; therefore, these items are not included in this document.

l

References:

C-1. Steadv-State Nuclear Afethods. NEDE 30130-P-A. and NEDO 30130-A. April 1985.

C-2. GeneralElectricStandardApplicassonfor Reactor Fuel. NEDE 240l1 P A (latest approved version). l l

l l

t Page 47

i RIVER BEND Jl1-03431SRLR Reload g Rev. 2 Appendix D Basis for Analysis of Core-Wide and Overpressurization Transients He 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. De seven inoperable SRV's are applicable only to the Vessel Overpressure ASME Code Compliance upset condition and fuel thermal performance criteria. The analyses performed reflect the River Bend Station Technical Specifications. which permit operation with 4 valves in relief mode and 5 valves in safety (spring) mode.

Page 48

1i RIVER BEND Jl1-03431SRLR I Reload 8 Rev. 2 Appendix E Standby Liquid Control System Shutdown Capability The minimum required boron shutdown margin is dependent on the fuel design type and tne calculational method. The minimum required boron shutdown margin represents the biases and uncertainties needed to assure suberiticality. This is a GE recommended value and may be less restrictive than the River Bend specific technical specifications requirement for the liquid boron shutdown margin, in which case the technical specification value shall be used. For the analysis reported in this Sepplemental Reload Licensing Submittal fuel specific borated libraries were generated using lattice physics methods at 160 deg. C and 726 ppm boron. A boron concentration of 726 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 gel 1 in the core is 1.4%.

Page 49

al RIVER BEND J11-03431SRLR Reload 8 Rev. 2 1

1 Appendix F Off Rated Curves l For GE8 and GE11 Fuel (Except GE11 Cycle 7/ Reload G Fuel)

MCPR(p) l 2.20 l 2.00 .. 2 _ . . __

1.94 1.94 1.90 1.80 3 79 -

\

1.76 1.67 1.60 - - - - - - . =--

g 1.57 1 40 -- ' '~ ~

-+-Below P-Bypass. <= 50% Flow

-e-Below P.8ypass. > 50% Flow 1.32 1.28 l

+ Above P-Bypass 1.27 Ratec  !

1 1 00 I O 10 20 30 40 50 60 70 80 90 100 Percent Core Power (%)

Figure 22 Operating Limit MCPRp i

i i

Pace 50  ;

i

o O

RIVER BEND Jl1-03431SRLR Reload 8 Rev. 2 Appendix F Off Rated Curves (Continued)

For GE11 Cycle 7/ Reload 6 Fuel MCPR(p) 2.20 17 , . , . i 2.09 .

2.09 2.05 2.00 --

. 1.94 1.91 1.80 '

1.72 1

'a.

[ 1 60 '

i S

~

1.47 1'43

~'

1.40 --

Below P-By ass. <= 50% Flow 1.42 Ratec j

-e-Below P Bypass, > 50% Flow

-*-Above P Bypass 1 00 0 10 20 30 40 50 60 70 80 90 100 l Percent Core Power (%)

Figure 23 Operating Limit MCPRp i

I Page 51 i

I- 3 o

b RIVER BEND - Jl1-03431SRLR Reload 8 Rev. 2 Appendix F Off Rated Curves (continued)

For GE8 and GE11 Fuel (Except GE11 Cycle 7/ Reload 6 Fuel)

MCPR(f) 2.00

i 1.90 - -.

1.80 -

1.70 -

1.60 -- '

c k 1.50 -

N 1.47 1 40 - - -

-- i di . . . _, . _._

1.37 1.33 1.30 - - - - - - . --

1.24 1.20 - 1 20 1.12 1.10 - --

1 00 0 10 20 30 40 50 60 70 80 90 100 110 Percent Core Flow (%)

Figure 24 Operating Limit MCPRf 4

Page 52

n

+

g .

i RIVER BEND J11-03431SRLR I Reload 8 Rev. 2 I

Appendix F Off Rated Curves (continued)

For GE11 Cycle 7/ Reload 6 Fuel i

MCPR(f)  !

2.00 1.90 1.80 - - - - - -

1.70 - - - - -

- l 1.60 ----- A162 1.56 e

aT 1.52

m. 1.50 g 1.48 1.43 1.40 -- -- . - - - - - - ' ~ ~ ~ ~ ' ' " ~

1 39' 1.35 1.30 - - - - - - - - - - - - - -1U 1.20

. 1,10 - - - - - - - - - --

1 00 0 10 20 30 40 50 60 70 80 90 100 110 Percent Core Flow (%)

Figure 25 Operating Limit MCPRf E

Page 53

4' w

RIVER BEND Jl1-03431SRLR Reload 8 Rev. 2 Appendix F Off Rated Curves (continued)

LHGR(p) 8. MAPLHGR(p) Multiplier 1.1000

! I t ,

i 1.0000 1.0000 1.0000 - -

1 1.0000 0.9000 -

i 0.8500' 3 0.8000 d

5 0 7000 --

0-7000,-

1 a

a 5

0.6000 -

.5622 l J

0.4988 .

0.5000 -

7.4988 0.4000 0 10 20 30 40 50 60 70 80 90 100 Percent Core Power (%)

Figure 26 Operating Limit LHGRp Multipliers Page 54

s .

RIVER BEND Jl1-03431SRLR Edged 8 Rev. 2 Appendix F Off Rated CuNes (continued)

'4

, LHGR(f) & MAPLHGR(f) Multiplier 1.100

! I i i i g i i 1.000 ,

1.00(

1.000 -

1.000 0.977 0.900 8 0.908I t

0.834 c- 0.800 g  !

t i 0.700 -

C i ai '

O.663 E

a 0.600 - - - -

0.533 0.500 -

0 400 O 10 20 30 40 50 60 70 80 90 100 110 Percent Core Flow (%)

Figure 27 Operating Limit LHGRf Multipliers i

Page 55

' ~

I

"^ RIVER BEND J11-03431SRLR Reload 8 Rev. 2 Appendix G Group Designations of the GGE Fuel Type The following groupings of the GOE fuel type (bundles gel 1-P9SUB354-14GZ-120T-146-T, gel 1-P9SUB354-13GZ-120T-146-T, and gel l-P9SUB353-10GZ-120T-146-T are provided to ensure that the LOCA analysis results will remain within the licensing basis limits. Bundle identifications shown below correspond to the upper left quadrant.

To implement the requirements, each node of the bundles identified in the following table should remain below the MAPLHGR limits provided in Section 16 for each bundle type in each group.

Group i Group 2 Group 3 Group 4 GGE024 GGE012 GGE016 GGE004 GGE028 GGE040 GGE100 GGE008 GGE032 GGE048 GGE104 GGE020 GGE060 GGE076 GGE036 GGE064 GGE092 GGE044 GGE072 GGEll2 GGE052 GGE084 GGE120 GGE056 GGE096 GGE124 GGE068 GGE108 GGE156 GGE080 GGE128 GGE164 GGE088 GGE136 GGE168 GGEll6 GGE144 GGE188 GGE132 GGE184 GGE192 GGE! .0 GGE200 GGE148 GGE208 GGE152 GGE220 GGE160 GGE224 GGE172 GGE228 GGE176 GGE180 GGE196 GGE204 GGE212 GGE216 GGE232 l

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