ML20206D846

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Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7 Cycle 8
ML20206D846
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 03/31/1999
From: Watford G, Robert Williams
GENERAL ELECTRIC CO.
To:
Shared Package
ML20206D786 List:
References
J11-0331SRLR, J11-0337SRLR-R01, J11-331SRLR, J11-337SRLR-R1, NUDOCS 9905040253
Download: ML20206D846 (26)
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GE NuclearEnergy Jil-03371SRLR Revision 1 Class I March 1999 J11-03371SRLR, Rev.1 Supplemental Reload Licensing Report for Perry Nuclear Power Plant Unit 1 Reload 7 Cycle 8 l

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Approved Approved

.A. Watfo , Manager R.D. Williams Nuclear Fuel Engineering Fuel Project Manager 9905040253 990430 PDR 0

ADOCK 05000440 F P pm g

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I PERRY 1 Reload 7 J11-03371SP.LR l Rev.1 .

Important Notice Regarding ,

1 Contents of This Report 1

Please Read Carefully This report was prepared by General Electric Company (G E) solely for Cleveland Electric illuminating Company. 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 the contract between Cleveland Electric illuminating Company and GE, and nothing con-tained in this document shall be construed as changing the contract. The use of this in-formation by anyone other than CEI for any purpose other than that for which it is in-tended, is not authorized; and with respect to any such unauthorized use, neither GE nor any of the contributors to this document makes any representation or warranty (ex-pressed or implied) as to the completeness, accuracy or usefulness of the information contained in this document or that such use of such infqrmation may not infringe privately owned rights; nor do they assume any responsibility for liability or damage of any kind which may result from such use of such information.

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PERRYl J11-03371SRLR Rgload 7 Rev.1 3

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Acknowledgement  !

l l I The engineering and reload licensing analyses, which form the technical basis of this Supplemental Reload Licensing Report, were perfonned by J.E. Pt.wks. The Supplemental Reload Licensing Report was prepared by J.E. Fawks. This document has been verified by G.M. Baka. Revision 1 includes PCT impact for MEOD. ,

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i PERRY 1 Reload 7 J11-03371SRLR

. Rev.1 l The basis for this report is GeneralElectricStandardApplicationforReactorFuel, NEDE-24011-P-A-13, August 1996; and the U.S. Supplement, NEDE-24011-P-A-13-US, August 1996.

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1. Plant-unique Items I

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Appendix A: Analysis Conditions Appendix B: Basis for Analysis of Loss-of-Feedwater Heating Event Appendix C: Analyzed Operating Domain l

Appendix D: Transient Analysis Appendix E: Power and Flow Dependent MCPR and MAPLHGR Multipliers j

2. Reload Fuel Bundles I i

Cycle  ;

Fuel Typ. Loaded Number j Irradiated:

GE10-P8SXB306-110Z3-120M-150-T (GE8x8NB-1) 6 36  ;

gel l-P9S UB 338-10GL12W-146-T (GE l l) 6 120 ,

gel l-P9SUB338-12GL120T-146-T (GE11) 6 60 l GE12-P10SSB369-14GL12W-150-T (GE12) 7 92 GE12-P10SSB369-12GL12W-150-T (GE12) 7 160 Nem GE12-P10SSB 399-16GL12W-150-T (GE12) 8 168  !

GE12-P10SSB399-14GL12W-150-T (GE12) 8 112 1 1

Tbtal 748 4

3. Reference Core Loading Pattern Nominal previous cycle core average exposure at end of cycle: 27721 mwd /MT (25148 mwd /ST)

Minimum previous cycle core average exposure at end of cycle 27308 mwd /MT for cold shutdown considerations: (24773 mwd /ST)

Assumed reload cycle core average exposure at beginning of 13965 mwd /MT cycle
( 12669 mwd /ST)

Assumed reload cycle core average exposure at end of cycle: 2%91 mwd /MT (26936 mwd /ST)

Reference core loading pattem: Figure 1 Page 4

l-PERRYl J11-03371SRLR Reload 7 Rev.1

4. l Calculated Core Effective Multiplication and Control System Worth -No Voids,20'C j

l Beginning of Cycle, kerrective Uncontrolled 1.126 l Fully controlled 0.953 l

Strongest control rod out 0.989 l R, Maximum increase in cold core reactivity with exposure into cycle, Ak 0.000

5. Standby Liquid Control System Shutdown Capabilityl Boron (ppm) Shutdown Margin (Ak)

(at 20 C) (at 160'C, Xenon Free) 1 816 0.018 i

l 6. Reload Unique GETAB Anticipated Operational Occurrences (AOO) Analysis l Initial Condition Parameters l

l Exposure: BOC8 to EOC8 Increased core flow /Feedwater temperature 420 F Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (1000 lb/hr) l GE12 1.45 1.50 1.38 1.040 6.990 116.2 1.28 Gell 1.45 1.41 1.38 1.035 6.607 119.0 1.23 GE8x8NB-1 1.20 1.60 1.40 1.000 7.494 115.0 1.18 Exposure: BOC8 to EOC8 Increased core now/Feedwater temperature reduction to 250 F Peaking Factors Fuel Bundle Bundle Initial

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

GE12 1.45 1.62 1.38 1.040 7.515 112.8 1.27 Gell 1.45 1.52 1.38 1.035 7.047 116.4 1.23 GE8x8NB-1 1.20 1.66 1.40 1.000 7.733 112.7 1.19

1. %e analysis was perfonned with irradiated bundles using 660 PPM and new bundles using 800 PPM. 'Ihis is conservative compared to 816 PPM.

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l l PERRY 1 J11-03371SRLR

,. , Reload 7 Rev.1

1 i 7. Selected Margin Improvement Options j i Recirculation pump trip: Yes t

l Rod withdrawallimiter: Yes l l

Thermalpowermonitor: Yes  !

Improved scram time: No (ODYN Option B)

Measured scram time: No Exposure dependentlimits: No i

Exposure points analyzed: 1 (EOC)

8. Operating Flexibility Options Single-loop operation: Yes ,

Loadline limit: No Extended loadlinelimit: No Maximum extended load linelimit: No i

d Increased core flow throughout cycle: Yes Flow point analyzed: 105.0 %

Increased core flow at EOC: Yes Feedwater temperature reduction throughout cycle: Yes l

Temperature reduction: 170.0*F Final feedwater temperature reduction: Yes ARTS Program: No Maximum extended operating domain: Yes i Moisture separator reheater OOS: No hrbine bypass system OOS: No ]

Safety / relief valves OOS: Yes )

1 ADS OOS: No 1 EOC RPT OOS: No Main steam isolation valves OOS: No Page 6 .

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l PERRYl J11-03371SRLR Reload 7 Rev.1 l

9. Core-wide AOO Analysis Results Methods used: GEMIN1; GEXL-PLUS l Exposure range: BOC8 to EOC8 Increased core How/Feedwater temperature 420 F Uncorrected ACPR Event Flux Q/A GE12 Gell GE8x8NB-1 Fig. l

(%NBR) (%NBR)

Load Reject w/o Bypass 324 112 0.19 0.15 0.09 2 Loss of 100 F Feedwater 119 119 0.12 -

Heating l

Exposure range: BOC8 to EOC8 Increased core How/Feedwater temperature reduction to 250 F l Uncorrected ACPR Event Flux Q/A GE12 Gell GE8x8NB-1 Fig.

(%NBR) (%NBR)

FW Controller Failure 227 117 0.18 0.13 0.10 3

10. Local Rod Withdrawal Error (With Limiting Instrument Failure) AOO Summary The generic bounding BWR/6 rod withdrawal error analysis described in NEDE-24011-P-A-US is applied.
11. Cycle MCPR Values 2 In agreement with commitments to the NRC ( letter from M. A. Smith to the Document Control Desk,10CFR Part 21, Reportable Condition, Safety LimitMCPR Evaluation, May 24,1996 ) a cycle-specific Safety Limit MCPR calculation was perfonned, and has been reported in both the Safety Limit MCPR and the Operating Limit MCPR shown below. This cycle specific SLMCPR was determined using the analysis basis docu-mented in GESTAR with the following exceptions:
1. The reference core loading pattem in Figure I was analyzed.
2. 'lhe actual bundle parameters ( e.g., local peaking ) were used.
3. The full cycle exposure range was analyzed.

l f 2. For single-loop operation. the MCPR operating limit is 0.02 greater than the two-loop value. The MCPR limit does not change because of channel bow. Channel bow is reflected in the monitoring of the core.

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PERRYl J11-03371SRLR Reload 7 Rev.I

11. Cycle MCPR Values (cont)

Safetylimit: 1.09 Single loop operation safety limit: 1.11 Non-nressurinflon events:

Exposure Range: BOC8 to EOC8 Option A GE12 Gell GE8x8NB-1 Rod Withdrawal Error 1.20 Fuel Loading Error (misoriented) 1.28 1.24 1.25 Fuel Loading Error (mislocated) 1.24 1oss of 100 F Feedwater Heating 1.21 Pressurization events:3 Exposure range: BOC8 to EOC8 Increased core now/Feedwater temperature 420 F '

Exposure point: EOC8 Option A GE12 Gell GE8x8NB.-1

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Load Reject w/o Bypass 1.30 1.25 1.19 Exposure range: BOC8 to EOC8 Increased core now/Feedwater temperature reduction to 250 F Exposure point: EOC8 Option A GE12 Gell GE8x8NB-1 FW Controller Failum 1.28 1.24 1.20

3. ECCS MCPR value will be provided in the SAFElWESTR-IDCA report, see section 16.

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PERRY 1 Reload 7 Jil-03371SRLR

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12. Overpressurization Analysis Summary 4 Psi Pv Plant Event (psig) (psig) Response MSIV Closure (Flux Scram) 1258 1289 Figure 4
13. Loading Error Results5 Variable water gap misoriented bundle analysis: Yes Mislocated bundle analysis: Yes Misoriented Fuel Bundle ACPR GE10-P8SXB306-11GZ3-120M-150-T (GE8x8NB-1) 0.16 GE l 1-P9S UB 338-10GL12W-146-T (gel 1) 0.15 GE11-P9SUB338-12GL12W-146-T (GE11) 0.14

. GE12-P10SSB 369-14GL12W-150-T (GE 12) 0.19 GE 12-P10SSB 369-12GL12W-150-T (G E 12) 0.11 GE12-P10SSB399-14GL12W-150-T (GE12) 0.11 GE 12-P10SS B 399-16GL120T-150-T (GE12) 0.11 Mislocated Fuel Bundle ACPR FuelLoading Error (mislocated) 0.15

14. Control Rod Drop Analysis Results This is a banked position withdrawal sequence plant, therefore, the control axi drop accident analysis is not required. NRC approvalis documented in NEDE-240ll-P-A-US.
15. Stability Analysis Results GE SIL-380 recommendations have been included in the operating procedures; therefolt, no stability analy-sis is required. NRC approval for deletion of a cycle-specific stability analysis is documented in NEDE-240ll-P-A-US. This plant recognizes the issuance of NRC Bulletin No. 8&-07, Supplement 1, Power Oscillations in Bolling WaterReactors (BWRs), and will comply with the recommendations contained therein.
4. b Ms!V doeure (tlux scram) analysis is performed using GEMINImethods at the 102% powerlevel to account for the power level un-certainties specified in Regulatory Guide 1.49. The dame pressure is set to 1045 psig as specified in the OPL-3 Design Guide, TDP487 Revision 1. The analysis was performed with the 13 highest setpoint safety valves operational.
5. Includes a 0.02 penahy he to variable water gap R-factor uncertainty, Page 9

PERRY 1 J11-03371SRLR Reload 7 Rev.1 i

15. Stability Analysis Results (cont) f Perry 1 is implementing B WROG Long Tenn Stability Option III as described in NEDO-31960-A, Supple-l ment 1, "BWR Owners' Group long-Term Stability Solutions Licensing Methodology", November 1995. The basis for the reload application analysis to demonstrate safety limit MCPR pmtection is documented in l NEDO-32465-A," Reactor Stability Detect andSuppress Solutions Licensing Basis Methodologyfor Reload Applications", August 1996. Plant specific analysis for the Perry 1 Option III haniware is described in GE-NE-Al 3-00368-14,"Reactorlong-Term Stability Solution Option 111: Licensing Basis Hot Bundle Oscilla-tion Magnitudefor Perry", September 1996. Current power and flow dependent limits pmvide adequate protection against violation of the safetylimit MCPR for a worst case oscillation at 45% rated com flow. The safety limit MCPR is protected for a two pump trip transient from rated power as long as the operating limit is greater orequal to the following:

. OPRM Setpoint OLMCPR (2PT) 1.05- 1.21 1.09 1.30 1.10 1.32 1.15 1.46 l

16. Loss-of-Coolant Accident Results LOCA method used: SAFER /GESTR-LOCA The SAFER /GESTR-LOCA analysis results for GE10, Gell and GE12 are documented in " Perry Nuclear Power Plant SAFERIGESTR-LOCA Loss-of-Coolant Accident Analysis", NEDC-32872P, issued Decem-ber 1998. This analysis establishes a new Licensing Basis for Perry with the GE SAFER /GESTR-LOCA methodology. The results are valid for fuel designs with comparable geometry to the fuels analyzed.

The limiting LOCA is the largest postulated break (DBA) in the recitrulation suction line coincident with HPCS DG failure. The calculated Licensing Basis peak cladding temperature (PCT)is <1230 F for GE10;

<1330 FforGEll;and<1170 FforGE12. TheLicensingBasisPCI'forMEODconditionis<1350 F. The maximum local oxidation (fraction) is <0.2%. The core-wide metal water reaction is <0.1%.

The MAPLHGR multiplier for single-loop operation (SLO)is calculated to be 0.69 for GE10; 0.64 for GE11; and 0.64 for GE12. The most and least limiting MAPLHGRs for the fuel are as follows.

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PERRY 1 J11-03371SRLR

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

Bundle Type: GE10-P8SXB306-1IGZ3-120M-150-T Average Planar Exposure MAPLHGR(kW/ft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 11.55 12.43 0.20 0.22 11.61 12.47 1.00 1.10 11.71 12.58 2.00 2.20 11.92 12.72 3.00 3.31 12.17 12.88 4.00 4.41 12.41 13.04 5.00 5.51 12.61 13.20 6.00 6.61 12.81 13.33 7.00 7.72 12.99 13.41 8.00 8.82 13.16 13.50 9.00 9.92 13.31 13.56 10.00 11.02 13.34 13.43 12.50 13.78 13.23 13.40 15.00 16.53 12.92 13.07 20.00 22.05 12.16 12.40 25.00 27.56 11.44 11.76 30.00 33.07 10.79 11.08 35.00 38.58 10.14 10.40 40.00 44.09 9.56 9.78 45.00 49.60 8.90 9.15 50.00 55.12 6.65 6.79 51.73 57.02 5.87 6.03 51.75 57.04 -

6.02 51.86 57.17 -

5.97 51.90 57.22 -

5.95 Page 11

f l PERRYl J11-03371SRLR Reload 7 Rev.1 l

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

, Bundle Type: Gell-P9SUB338-10GZ-120T-146-T Average Planar Exposure MAPLHGR(kW/ft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 11.65 12.09 0.20 0.22 11.70 12.13 1.00 1.10 11.81 12.22 2.00 2.20 11.96 12.34 3.00 3.31 12.06 12.47 4.00 4.41 12.16 12.55 5.00 5.51 12.26 12.64 6.00 6.61 12.36 12.73 7.00 7.72 12.46 12.82 8.00 8.82 12.56 12.91 9.00 9.92 12.67 13.01 10.00 11.02 12.78 13.09 12.50 13.78 12.82 13.06 15.00 16.53 12.55 12.74 17.50 19.29 12.24 12.41 20.00 22.05 11.93 12.09 25.00 27.56 11.32 11.44 30.00 33.07 10.70 10.71 35.00 38.58 10.02 10.08 40.00 44.09 9.34 9.42 45.00 49.60 8.68 8.74 50.00 55.12 S.00 8.04 55.00 60.63 7.25 7.35

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59.17 65.22 6.62 6.72 59.26 65.32 -

6.71 59.73 65.84 -

6.64 i

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PERRY 1 J11-03371SRLR Reload 7

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

Bundle Type: gel 1-P9SUB338-120Z-120rl'-146-T Average Planar Exposure MAPLHGR(kW/ft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting l 0.00 0.00 11.50 11.65 0.20 0.22 11.55 11.70 1.00 1.10 11.69 11.81 2.00 2.20 11.81 11.96 l 3.00 3.31 11.92 12.13 4.00 4.41 12.03 12.31 5.00 5.51 12.15 12.42 6.00 6.61 12.27 12.54 7.00 7,72 12.39 12.66 8.00 8.82 12.52 12.78 9.00 9.92 12.64 12.90 10.00 11.02 12.77 13.03 12.50 13.78 12.82 13.05 15.00 16.53 12.54 12.73 17.50 19.29 12.23 12.41 20.00 22.05 11.92 12.08 25.00 27.56 11.31 11.44 30.00 33.07 10.70 10.71 35.00 38.58 10.01 10.07 40.00 44.09 9.33 9.42 45.00 49.60 8.67 8.73 50.00 55.12 7.99 8.03 55.00 60.63 7.25 7.34 59.15 65.20 6.61 6.71 59.17 65.22 -

6.71 59.67 65.78 -

6.63 l

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

Bundle Type: GE12-P10SSB369-14G2,'-120T-150-T l

Average Planar Exposure MAPLIIGR(kW/ft) i (GWd/ST) (GWd/MT) Most Limiting Least Limiting 1 0.00 0.00 9.00 9.46 0.20 0.22 9.04 9.48 1.00 1.10 9.12 9.56 2.00 2.20 9.23 9.68 3.00 3.31 9.36 9.81 4.00 4.41 9.50 9.95 5.00 5.51 9.65 10.10 6.00 6.61 9.77 10.26 7.00 7.72 9.89 10.41 8.00 8.82 10.01 10.54 9.00 9.92 10.14 10.60 10.00 11.02 10.26 10.60 l 11.00 12.13 10.36 10.60 1

12.00 13.23 10.33 10.60 l

13.00 14.33 10.28 10.60 14.00 15.43 10.21 10.60 ,

15.00 16.53 10.14 10.57 17.00 18.74 9.97 10.38 20.00 22.05 9.72 10.09 i 25.00 27.56 9.29 9.63 30.00 33.07 8.86 9.17 35.00 38.58 8.43 8.67 40.00 44.09 7.99 8.14 1 45.00 49.60 7.52 7.66 50.00 55.12 7.04 7.20 55.00 60.63 6.53 6.77 58.24 64.20 6.19 6.48 58.32 64.29 -

6.47 60.00 66.14 -

6.32 60.11 66.26 -

6.31 Page 14

l PERRY 1 Reload 7 J1.1-03371SRLR

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16. Loss-of-Coolant Accident Results (cont) l t Bundle Type: GE12-P10SSB369-120Z-12(TP-150-T i

Average Planar Exposure MAPLHGR(kW/ft)

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 8.89 9.31 0.20 0.22 8.94 9.37 1.00 1.10 9.05 9.48 2.00 2.20 9.19 9.62 3.00 3.31 9.32 9.77 4.00 4.41 9.46 9.92 5.00 5.51 9.61 10.08 6.00 6.61 9.75 10.24 ,

7.00 7.72 9.90 10.4I 8.00 8.82 10.05 10.58 9.00 9.92 10.19 10.60 10.00 11.02 10.33 10.60 11.00 12.13 10.41 10.60 12.00 13.23 10.38 10.60 13.00 14.33 10.32 10.60 14.00 15.43 10.25 10.60 15.00 16.53 10.17 10.60 17.00 18.74 10.00 10.41 20.00 22.05 9.74 10.12 25.00 27.56 9.31 9.66 30.00 33.07 8.88 9.20 35.00 38.58 8.45 8.70 40.00 44.09 8.00 8.17 45.00 49.60 7.54 7.68 50.00 55.12 7.05 7.22 55.00 60.63 6.54 6.79 58.22 64.18 6.20 6.49 58.30 64.27 -

6.49 60.00 66.14 -

6.33 60.08 66.22 -

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16. Loss-of-Coolant Accident Results (cont) j Bundle Type: GE12-P10SSB399-14GZ -120T-150-T Average Planar Exposure MAPLHGR(kW/ft)  !

(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 9.05 9.26 0.20 0.22 9.10 9.30 )

1.00 1.10 9.18 9.36 l

2.00 2.20 9.29 9.45 j 3.00 3.31 9.40 9.53 i 4.00 4.41 9.51 9.62 l 5.00 5.51 9.62 9.72 6.00 6.61 9.74 9.83

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7.00 7.72 9.86 9.95 8.00 8.82 9.97 10.08 9.00 9.92 10.09 10.20 10.00 11.02 10.19 10.33 11.00 12.13 10.27 10.45 12.00 13.23 10.27 10.49 13.00 14.33 10.27 10.51 14.00 15.43 10.26 10.52 15.00 16.53 10.24 10.50 17.00 18.74 10.16 10.39 20.00 22.05 9.95 10.14 25.00 27.56 9.53 9.72 30.00 33.07 9.11 9.30 35.00 33.58 8.64 8.83 40.00 44.09 8.10 8.30 45.00 49.60 7.57 7.79 50.00 55.12 7.05 7.31 55.00 60.63 6.53 6.84 59.18 65.24 6.09 6.41 59.24 65.30 -

6.41 60.00 66.14 -

6.33 60.18 66.34 -

6.31 Page 16

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PERRY 1 J11-03371SRLR l Reload 7 I

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16. Loss-of-Coolant Accident Results(cont) l Bundle Type: GE12-P10SSB399-160Z-12(TT-150-T l

l Average Planar Exposure MAPLHGR(kW/ft) .

(GWd/ST) (GWd/MT) Most Limiting Least Limiting j 0.00 0.00 8.84 9.04 O.20 0.22 8.89 9.09

~

4 1.00 1.10 8.98 9.16 2.00 2.20

)

9.10 9.25

{

3.00 3.31 9.22 9.35 l 4.00 4.41 9.34 9.44 5.00 5.51 9.46 9.54 6.00 6.61 9.59 9.65 7.00 7.72 9.71 9.78 8.00 8.82 9.84 9.91 j 9.00 9.92 9.96 10.05 10.00 11.02 10.07 10.20 l l

11.00 12.13 10.15 10.31 l 12.00 13.23 10.16 10.35 13.00 14.33 10.17 10.40 l 14.00 15.43 10.17 10.43  !

15.00 16.53 10.17 10.43 17.00 18.74 10.13 10.37 20.00 22.05 9.94 10.12 25.00 27.56 9.52 9.71 30.00 33.07 9.10 9.29 35.00 38.58 8.63 8.79 40.00 44.09 8.09 8.26 45.00 49.60 7.56 7.76 1

50.00 55.12 7.04 7.28 l 55.00 60.63 6.52 6.82 l- 59.07 65.11 6.10 6.41 i 59.12 65.17 -

6.41 60.00 66.14 -

6.32 60.07 66.21 -

6.31 '

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PERRY 1 J11-03371SRLR

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sm!MMMMBs! m
.m MMMMMMP!&BMs ll m M M B E M M M M i+s M M M m
mMBBBEMBEMBsBBBBBBBEMBim
-miMBEMMMBEMMBEMMMHis l
HMMMMMMMMMBi&EMMM
MBEMMMMMMBis+8MMMMM
MMi+sMMMMMMMMMMMM
MMMMMMMMMs+8MEEMMM
MMMMMMBEMMMBEBEMBBBi

!:- " i M B E M M M M M i+ 2+s B i B E M M E "

i: *MMMMMMMMBBBBBBBEH" ll *MMMMMMBBBEMMM*

  • MMMMMMMMM" l ""iM M M BEBEE""

l IIIIIIIIIII 1 3 5 7 91113151719 2123 25 27 29 3133 35 37 39 il 1315 if 19 5153 55 57 59 FuelType A=GE10-P8SXB306-110Z3-120M-150-T (Cycle 6) E=GE12-P10SSB369-12GL12W-150-T (Cycle 7)

B= Gell-P9SUB33&-10GL12W-146-T (Cycle 6) F=GE12-P10SSB399-14GL12W-150-T (Cycle 8)

C Gell-P9SUB338-12GL12W-146-T (Cycle 6) G=GE12-P10SSB399-16GL12E-150-T (Cycle 8)

D=GE12-P10SSB369-14GL12W-150-T (Cycle 7)

Figure 1 Reference Core Loading Pattern i

Page 18

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PERRY 1 J11--03371SRLR

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i l

l I

Neutron Flux Vessel Press Rise (psi)

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

-- Core inlet Flow 300.0 l

--- Relief Valve Flow l

--- Bypass Valve Flow

. J 100.0  %~) , 'y' 200.0 -

m e g -

s~~s~-~~

, g -

. ~~

50.0 -

., 100.0 -

, 7_ _

\

~..~ ., g I

g \

I \

' ' 'I I 0.0 O.0

O.0 3.0 6.0 0.0 3.0 6.0 mme (sec) mme (sec) l l

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

- - - - - Vessel Swam Flow ----

Dopp rReactivity 200.0 - --- Turbine Steam Flow 1.0 - -

Ser Reactivity

--- Feedwater Flow Total activity

. S _ ri m \

E ,

8 \ '

t3 100.0 g g ,. -,s

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

g o 0.0 v.j . , -

-e , ,,

, o \ ,i ,

j

.. . O \'

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t. l g, , . 2 t.

0.0 L --l- ,- - - - - - - - - -% j -1.0 -

I j

.: e ,

\,

- 100.0 - I '

-2.0 ' ' '

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

I Figure 2 Plant Response to Load Reject w/o Bypass (BOC8 to EOC8 Increased core flow /Feedwater temperature 420 F) i Page 19

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r PERRY 1 J11-03371SRLR l

, Reload 7 Rey,1 l

Neutron Rux Vessel Press Rise (psi)

- - - - - Ave Surface Heat Flu) - - - - Safety Valve Flow 150.0 - ---

Core Inlet Flow 125.0 - --- Relief Valw Flow j

- -- Core Inlet Subcooling --- Bypass Valve Flow I

y 100.0

- ( '. 75.0 -

w 's . w E . s %. E

'.  % $ ~

50.0 -

'., 25.0 -

~ ~~

l

[

m I ---

0.0 ' ' ' I '

-25.0 O.0 6.0 12.0 0.0 6.0 12.0 Eme (sec) Time (sec)

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

- - - - - Vessel Steam Flow - - - - - Doppler Reactivity 150.0 : N 'NimrSleam11em 1.0 - --- Scram Reactivity

--- Feedwater Row --- TotalReactivity

, , $ - p ,

\ h , ,'

y 100.0

- . 0.0 -- - - r.... ,,, 3 ; ,,,,

e i.

\ a -

V-i: ,

..i\x

.2:

t l'

  • I l 50.0 -

I 'i N -1.0 -

1.. a> t I..... . ,, m I

l...... * . * *

- 1 i

l no . i  !" , 's -2.0 ' ' '

O.0 6.0 12.0 0.0 6.0 12.0 Time (sec) Time (sec) l Figure 3 Plant Response to FW Controller Failure (BOC8 to EOC8 Increased core flow /Feedwater temperature reduction to 250 F)

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i PERRY 1 J11-03371SRLR o

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I

.Jouron Flux -

VesselPr'.4 Rise (psi) ove Surface Heat Flux - - - - - Safety ei . + low 150.0 - --.. oreinlet Row 300.0 - --- Relief Valve Flow

--- Bypass Valve Flow d % .'

  • g 100.0 N '., g200.0 g 's's? ,~ is E

' . %s'-

l

, s s

50.0 -

'., 100.0 -

.e ,

.., ..,~..

e -

o 0A ' I 0.0 ' ' ' '

p 0.0 4.0 8.0 0.0 4.0 8.0 l

Time (sec) mme (sec) i Level (inch-REF-SEP-SKRT) Void Re tivity j

- - - - Vesset Steam Flow - - - - - Do Reactivi 200.0 - --- Turbine Sis?m Flow 1.0 - ---

m Reactivity /

--- FeedwaterFlow ---T I Reactivity /

n ew .

E

\

\ .-

. .. I g 100.0 m 0.0 ,'

l g ,,\s x'., _

O

, x....-

\

', \

s,

.. k i

\.

j 0.0 -  %.%.

' ' '.\ %-- h ---_

m -1.0 -

g

. t E \'

l - \

\

i g i

-100.0 - I '

-2.0 ' I I '

O.0 4.0 8.0 0.0 4.0 8.0 Eme(sec) Time (sec)

Figure 4 Plant Response tr, MSIV Closure (Flux Scram)

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[ PERRY 1 J11-03371SRLR a I}eload 7 i<ey,1 l

l I

Appendix A i l Analysis Conditions

'Ib refles actual plant parameters accurately, the values shown in 'l le A-1 were used this cycle.6 Table A-1 -

Increased core flow /Feedwater temperature as noted Analysis Value Parameter /Feedwater temperature 420 F 250 F Thermal power, MWt 3579.0 3579.0 1

Com flow, Mlb/hr 109.2 109.2 l

Reactorpressure, psia 1056.0 1023.7 Inlet enthalpy, BTU /lb 528.8 508.3 Non-fuel power fraction 0.037 0.037 l

Steam flow analysis, Mlb/hr 15.41 12.59 Dome pressure,psig 1025.0 994.6 Turbine pressure, psig 973.4 959.4 No. of Dual Mode S/R Valves ( oec footnote 6 ) 19 19 Relief mode lowest setpoint, psig ( see footnote 6 ) 1133.0 1133.0 i Safety mode lowest setpoint, psig ( see footnote 6 ) 1200.0 1200.0 i

I i

l

6. 'Ihere are a sotal of 19 valws; the two lowest setpoint safetyhelief valves are assurned to be out-of-service in the transient analysis. For the MsIVFS overpressurization analysis,6 safety valves are assurned out-of-service.

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! l l

Appendix B  !

l Basis for Analysis of Loss-of-Feedwater Heating Event l

The loss of feedwater heating event was analyzed with the 3D BWR simulator code described in NEDE-24011-P-A, which pennits the use of this code for this analysis.The transient plots nonnally reported in Section 9 are not outputs of the 3D BWR simulator code; therefore, these items are not included in this  ;

document. 1 The transient analysis inputs normally reported in Section 6 of this document are internally calculated in the 3D BWR simulator code.

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i L I L i

Appendix C )

. Analyzed Operating Domain  ;

! The core--wide adnonnal operational occurmnce (AOO) analysis results reported in Section 9 are the most limiting values over the entire allowable operating range. This range covers the following operating options: 1

1. Standard 100% power / flow map; j i
2. End-of-cycle power coastdown; l
3. MEOD with 100% power, flow range from 75% to 105% of rated; and
4. Partial feedwater heating to 320 F during the cycle with final feedwater temperature reduction to 250 F after All Rods Out at end of cycle.

Limiting events and conditions analyzed are based on NEDE-240ll-P-A-US and the USAR analytical re- l suits. The Reload 7/ Cycle 8 analyses were performed assuming all four turbine control valves in a full arc mode of operation. This is conservative for partial uc configuration.

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. 7 Rev.1 Appendix D Transient Analyses T"ae turbine trip without bypass (ITNBP) analysis is a pressure increase event that is bounded by the load rejection without bypass (LRNBP) analysis.

The LRNBP is limiting at normal feedwater temperature and incmased core flow.

The feedwater contmiler failure (FWCF) is limiting at reduced feedwate temperature and increased core flow.

The pressure regulator failure down scale (PRFDS) is not limiting.

Transients were not run for the intermediate feedwater temperature cases (320 F and 370 F) because the op-erating limit would not improve for those conditions. The LRNBP and fuel loading error analysis sets the operating limit and does not change with feedwater temperature.

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i Appendix E Power and Flow Dependent MCPR and MAPLHGR Multipliers The original MEOD offrated MCPR and MAPLH 7R multipliers were confinned to be applicable to this cycle. The MEOD original MCPR equations t must be multiplied by the ratio of 1.09/1.07. Funhenaore, for fuel GE8x8NB-1 the MCPRr equation at or below 40% rated flow needs to be multiplied by

- (1.0+0.0032(40-F)) where Fis core flow in tenns of % rated.

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