ML20129F858

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Supplemental Reload Licensing Rept for Perry Nuclear Power Plant Unit 1,Reload 5 Cycle 6
ML20129F858
Person / Time
Site: Perry 
Issue date: 06/30/1996
From: Reda R, Robert Williams
GENERAL ELECTRIC CO.
To:
Shared Package
ML20129F730 List:
References
J11-02581SRLR, J11-02581SRLR-R01, J11-2581SRLR, J11-2581SRLR-R1, NUDOCS 9610020109
Download: ML20129F858 (23)
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GENuclearEnergy i

J11-02581SRLR Revision 1 Class I June 1996 i

1 Supplemental Reload Liceremg Report t

for PERRY NUCLEAR POWER PLANT UNIT 1 Reload 5 Cycle 6 t

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GENuclearEnergy J11-02581SRLR Revision 1 Class I June 1996 J11-42581SRLR, Rev.1 l

Supplemental Reload Licensing Report for Perry Nuclear Power Plant Unit 1 Reload 5 Cycle 6 i

l N.

U Approved Approvedh

.I A

R.J Reda, Manager R.D. Williams Fuel and Facility Licensing Fuel Project Manager

- - ~.= ~

PERRY 1 J11-02581SRLR Reload 5 4

Rev.1 1

i i

Important Notice Regarding Contents of This Report i

Please Read Carefully i

This report was prepared by General Electric Company (GE) solely for Cleveland Electric liluminating Company. The information contained in this report is believed by GE to be i

an accurate and true representation of the facts known, obtained or provided to GE at the time this report was prepared.

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The only undertakings of GE respecting information in this document are contained in the contract between Cleveland Electric liluminating Company and GE, and nothing con-tained in this document shall be construed as changing the contract. The use of this in-tomiation by anyone other than CEI for any purpose other than that for which it is in-j tended, is not authorized; and with respect to any such unauthorized use, neither GE nor j

- any of the contributors to this document makes any representation or warranty (ex-i pressed or implied) as to the completeness, accuracy or usefulness of the information i

contained in this document or that such use of such information may not infringe privately owned rights; nor do they assume any responsibility for liability or dama0e of any kind j

which may result from such use of such information.

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PERRY 1 Reload 5

'J11-02581SRLR l

Rev.1 i

l Acknowledgement The engineering and reload licensing analyses, which form the technical basis of this Supplemental Reload

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Licensing Report, were perfonned by J.E. Fawks. The Supplemental Reload Licensing Report was prepared by J.E. Fawks. This revision has been verified by B.R. Fischer.

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PERRY 1 Reload 5 J11-02581SRLR Rev.1 The basis for this report is GeneralElectric Standard Applicationfor Reactor Fuel, NEDE-24011-P-A-11, November 1995; and the U.S. Supplement, NEDF -24011-P-A-11-US, November 1995.

1.

Plant-unique Items Appendix A: Analysis Conditions Appendix B: Basis for Analysis ofLoss-of-Feedwater Heating Event Appendix C: Analyzed Operating Domain Appendix D: Wansient Analysis Appendix E: Power and Flow Dependent MCPR and MAPLHGR Multipliers Appendix F: GE8x8NB-1 Rotated Bundle Analysis 2.

Reload Fuel Bundles Cycle Fuel Type Loaded Number Irradiated; GE8B-P8SQB322-7GL120M-150-T (GE8x8EB) 3 16 GE8B-P8SQB320-90L120M-150-T (GE8x8EB) 3 24 GE10-P8SXB306-10GZ2-120M-150-T (GE8x8NB-1) 4 136 GE10-P8SXB306-110Z3-120M-150-T (GE8x8NB-1) 4 68 GE 10-P8SXB306-11GZ3-120M-150-T (GE8x8NB-1) 5 224 Nem GE10-P8SXB 306-11GZ3-120M-150-T (GE8x8NB-1) 6 44 gel 1-P9SUB338-10GZ-12(Tr-146-T (GE11) 6 152 Gell-P9SUB338-12GZ-120T-146-T (Gell) 6 84 Tbtal 748 3.

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

25662 mwd /MT (23280 mwd /ST)

Minimum previous cycle core average exposure at end of cycle 25551 mwd /MT from cold shutdown considerations:

(23180 mwd /ST)

Assumed reload cycle core average exposure at beginning of 13084 mwd /MT cycle:

( 11870 mwd /ST)

Assumed reload cycle core average exposure at end of cycle:

25155 mwd /MT

( 22820 mwd /ST)

Reference core loading pattem:

Figure 1 Page 4

PERRY 1 R* load 5 J11-02581SRLR Rev.1 4.

Calculated Core Effective Multiplication and Contml System Worth -No Voids,20 C Beginning of Cycle, kege,.

Uncontmiled 1.116 Fully contmiled 0.952 Stengest control rod out 0.988 R, Maximum increase in cold com reactivity with exposure into cycle, Ak 0.000 5.

Standby Liquid Control System Shutdown Capability Boron Shutdown Margin (Ak)

(ppm)

(20'C, Xenon Free) 660 0.033 6.

Reload Unique GETAB Anticipated Operational Occurances (AOO) Analysis Initial Condition Parameters Exposure: BOC6 to EOC6 Increased core How/Feedwater temperature 420 F Peaking Factors Fuel Bundle Bundle Initial Design local Radial Axial R-Factor Power Flow MCPR (MWt)

(1000lb/hr)

Gell 1.45 1.34 1.57 1.035 6.275 122.2 1.23 GE8x8NB-1 1.20 1.59 1.40 1.000 7.408 114.3 1.19 GE8x8EB 1.20 1.49 1.40 1.051 6.975 118.6 1.16 Exposure: BOC6 to EOC6 Increased core flow /Feedwater temperature reduction to 250 F Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt)

(1000lb/hr) gel 1 1.45 1.44 1.57 1.035 6.703 120.0 1.22 GE8x8NB-1 1.20 1.65 1.40 1.000 7.700 111.6 1.20 GE8x8EB 1.20 1.56 1.40 1.051 7.295 115.7 1.17 Page 5 l

PERRY 1 Reload 5 J11-02581SRLR Rev.1 7.

Selected Margin Improvement Options Recirculation pump trip:

Yes Rod withdrawallimiter:

Yes Thermal powermonitor:

Yes Impmved scram time:

No (ODYN Option B)

Measured scram time:

No Exposure dependentlimits:

No Exposure points analyzed:

1 8.

Operating Flexibility Options Single-loop operation:

Yes Loadline limit:

No Extended load line limit:

No Maximum extended load line limit:

No Increased core flow thmughout cycle:

Yes Flow point analyzed:

105.0 %

Increased core flow at EOC:

Yes Feedwater temperature reduction thmughout cycle:

Yes Temperature reduction:

170.0 F Final feedwater temperature reduction:

Yes ARTS Program:

No Maximum extended operating domain:

Yes Moisture separator reheater OOS:

No Turbine bypass system OOS:

No Safety /relicf valves OOS:

Yes ADS OOS:

No EOC RI'I' OOS:

No Main steam isolation valves OOS:

No Page 6

PERRY 1 J11-02581SRLR Reload 5 Rev.1 9.

Core-wide AOO Analysis Results Methods used: GEMIN1; GEXL-PLUS Exposure range: BOC6 to EOC6 Increased con flow /Feedwater temperature 420 F Uncorrected ACPR Event Flux Q/A Gell GE8x8NB-1 GE8x8EB Fig.

(%NBR)

(%NBR)

Load Reject w/o Bypass 332 112 0.15 0.12 0.09 2

Loss of 100 F Feedwater 115 115 0.12 0.12 0.12 Heating Exposure range: BOC6 to EOC6 Increased core flow /Feedwater temperatum reduction to 250 F Uncorrected ACPR Evert Mux Q/A Gell GE8x8NB-1 GE8x8EB Fig.

(%NBR)

(%NBR)

FW Controller Failure 244 117 0.15 0.12 0.11 3

10. Local Rod Withdrawal Error (With Limiting Instrunnent Failure) ADO 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 ACPR to be 0.12 based upon a one foot withdrawal, 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 fmm M.A. Smith to the Document Control Desk,10CFR Part 21, Reportable Condition, Sqf' ty LimitMCPR Evaluation, May 24,1996 ) a cycle-specific Safety Limit e

MCPR calculation was performed, and has been reported in both the Safety Limit MCPR and the Operating Limit MCPR show below. This cycle specific SLMCPR was determined using the analysis basis documented in GESTAR with the following exceptions:

1. The Cycle Management Report ( Jll - 02791CMR Rev. 0 ) loading was analyzed.
2. The actual bundle parameters ( e.g., local peaking ) were used.
3. The full cycle exposure range was analyzed.
1. For single 4oop operation, the MCPR operating limit is 0.01 greater than the twW value. 'Ihe MCPR limit does not change because of channel bow. Channel bow is reflected in the morutoring of the core.

Page 7

PERRY 1 Reload 5 J11-02581SRLR Rev.I

11. Cycle MCPR Values (cont)

Safetylimit:

1.09 Single loop operation safety limit: 1.10 Non-Presenrintian evente-Exposure range: BOC6 to EOC6 Option A Gell GE8x8NB-1 GE8x8EB Rod Withdrawal Error 1.21 1.21 1.21 Fuel Loading Enor ( misoriented ) ( see App. F )

1.24 1.25 1.23 FuelLoading Enor(mislocated) 1.24 1.24 1.24 loss of100 FFeedwaterHeating 1.21 1.21 1.21 Pmari= tion events:2 Exposure range: BOC6 to EOC6 Increased core flow /Feedwater temperature 420 F Exposure point: EOC6 Option A Gell GE8x8NB-1 GE8x8EB Load Reject w/o Bypass 1.26 122 1.19 Exposure range: BOC6 to EOC6 Increased core flow /Feedwater temperature reduction to 250 F Exposure point: EOC6 Option A Gell GE8x8NB-1 GE8x8EB FW Contmiler Failure 1.25 1.23 1.21

2. ECCS MCPR value is 1.17.

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4 PERRY 1 i

1 Reload 5 J11-02581SRLR i

Rev.I

12. Overpressurization Analysis Summary 3 i

Pal Pv Plant Event (psig)

(psig)

Response

MSIV Closure (Flux Scram) 1264 1294 Figure 4 i.

13. Loading Error Resultsd

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Variable water gap misoriented bundle analysis: Yes Mislocated bundle analysis:

Yes 1

ACPR Event Gell GE8x8NB-1 GE8x8EB 4

Fuel loading ermr ( misoriented ) ( see App. F) 0.15 0.16 0.14 Fuelloading error (mislocated) 0.15 0.15 0.15 i

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14. Control Rod Drop Analysis Results This is a banked position withdrawal sequence plant, therefore, the control md dmp accident analysis is not required. NRC approval is documented in NEDE-240ll-P-A-US.

2 I

15. Stability Analysis Results GE Sll,-380 secommendations have been included in the operating procedures; therefore, no stability analy-sis is required. NRC approval for deletion of a cycle-specific stability analysis is documented in NEDE-24011-P-A-US. This plant recognizes the issuance of NRC Bulletin No. 88-07, Supplement 1, Power Oscillations in Bolling WaterReactors (BWRs), and will comply with the recommendations contained therein.
3. The MslV closure (flux scram) analysis is performed using GEMINImethods at the 102% powerlevel to account for the powerlevel un-certainties specified in Regulatory Guide 1.49. The dome pressure is set to 1045psig as specified in the OPL-3 Design Guide,46311A247 Revision 2.1he analysis was performed with the 13 highest sespoirs safety valves operational
4. Delta CPR penality of 0.02 for the tilted rmsonented bundle has been applied.

Page 9

o PERRY 1 J11-02581SRLR Reload 5 Rev.I 1

16. hf-Coolant Accident Results LOCA method used: SAFE /REFLOOD o

The peak clad temperature (PCT) is s 2185'F at all exposures; the local oxidation (fraction) is $ 0.065 at all exposures. The core-wide metal water reaction is 0.20%. The MAPLHGR multiplier for single-loop op-eration (SLO) is 0.78. The MAPLHORs forge 10- P8SXB306-11 GZ3-120M-150-T are contained in docu-ment 23A7227.

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PERRYl' Reload 5 J11-02581SRLR Rev.I

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

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

PCT Oxidation (GWd/ST)

(GWd/MT)

Most Limiting Least Limiting

(*F)

Fraction 0.00 0.00 11.65 11.67 0.20 0.22 11.69 11.69 2179 0.065 1.00 1.10 11.79 11.79 2175 0.063 2.00 2.20 11.83 11.83 3.00 3.31 11.86 11.86 4.00 4.41 11.90 11.90 5.00 5.51 11.93 11.93 2179 0.063 6.00 6.61 11.93 11.93 7.00 7.72 11.93 11.93 8.00 8.82 11.93 11.93 2180 0.063 9.00 9.92 11.92 11.92 10.00 11.02 11.90 11.90 2179 0.063 12.50 13.78 11.81 11.81 2180 0.062 15.00 16.53 11.76 11.76 2185 0.064 17.50 19.29 11.72 11.72 20.00 22.05 11.67 11.67 2182 0.062 25.00 27.56 11.32 11.43 2148 0.056 30.00 33.07 10.70 10.71 35.00 38.58 10.02 10.08 1970 0.031 40.00 44.09 9.34 9.42 45.00 49.60 8.68 8.74 1780 0.015 50.00 55.12 8.00 8.04 55.00 60.63 7.25 7.35 1557 0.002 59.17 65.22 6.62 6.72 59.26 65.32 6.71 59.73 65.84 6.64 Page 11

l PERRY 1 Reload 5 J11-02581SRLR Rev.1

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

Bundle Type: Gell-P9SUB338-12G2,'-12(TT-146-T Average Planar Exposure MAPLHGR(kW/ft)

PCT Oxidation (GWd/ST)

(GWd/MT)

Most Limiting Least Limiting

(*F)

Fraction 0.00 0.00 11.50 11.50

~

0.20 0.22 11.53 11.53 2148 0.059 1.0G 1.10 11.67 11.67 2153 0.059 2.00 2.20 11.76 11.76 3.00 3.31 11.84 11.84 1

4.00 4.41 11.93 11.93 5.00 5.51 12.01 12.01 2175 0.062 6.00 6.61 11.99 11.99 7.00 7.72 11.96 11.96 8.00 8.82 11.94 11.94 2180 0.064 9.00 9.92 11.91 11.91 10.00 11.02 11.88 11.88 2180 0.063 12.50 13.78 11.79 11.79 2180 0.063 15.00 16.53 11.74 11.74 2182 0.064 17.50 19.29 11.71 11.71 20.00 22.05 11.67 11.67 2184 0.064 25.00 27.56 11.31 11.42 2153 0.057 30.00 33.07 10.70 10.71 35.00 38.58 10.01 10.07 1970 0.031 40.00 44.09 9.33 9.42 45.00 49.60 8.67 8.73 1779 0.015 50.00 55.12 7.99 8.03 55.00 60.63 7.25 7.34 1559 0.002 59.15 65.20 6.61 6.71 59.17 65.22 6.71 59.67 65.78 6.63 i

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18:!:1 Figure 1 Reference Core Loading Pattern Page 13

PERRY 1 Reload 5 J11-02581SRLR Rev.1 Neutron Flux Vessel Press Rise (psi)

- - - - Ave Surface Heat Flux

- - - - - Safety Valve Flow 150.0

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

--- Bypass W!ve Flow

\\,

~ f\\

100.0 200.0 e

%.y. '~~- _~

e t

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~-

50.0 100.0 7

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\\

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\\\\

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0.0 O.0 I

O.0 3.0 6.0 0.0 3.0 6.0 Eme (SOC)

Eme (SOC)

Level (inch-REF-SEP-SKRT) activity

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

--- Feedwater Flow Total activity k

~

g y

\\

g 100.0 g g

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-100.0

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

Figure 2 Plant Response to Load Reject w/o Bypass (BOC6 to EOC6 Increased core flow /Feedwater temperature 420 F)

Page 14 l

PERRYl J11-02581SRLR Reload 5 Rev.I Neutron Flux VesselPress Rise (psi)

- - - - - Ave Surface Heat Flux

- - - - - Safety Valve Flow 150.0

--- Core inlet Flow 125.0 - --- Relief Valve Flow

- -- Core Irdet Subcooling

--- Bypass Valve Flow U-g 100.0 g 75.0 5

N 5

E

',N E

',g

~

~.

50.0 25.0

~ ~ ~ ' ~ ~ ~ ~

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0.0

-25.0 O.0 6.0 12.0 0.0 6.0

'!2.0 Eme (SOC)

Ema(SOO)

Level (inch-REF-SEP-SKRT)

Void Reactivity

- - - - - Vessel Steam Flow

- - - - - Doppler Reactivity 150.0 :-. -.- _ LgbM.Samm fimr..

1.0 - --- Scram Reactivity

--- Feedwater Flow

\\

--- TotalReactivity b

\\

g r.

V 100.0

\\

g A.\\

- 0.0 E

k g

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....)\\l,

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g l::i\\

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i,.,,.'.

,.,,6 i::

N g *'

0.0 I

-2.0 O.0 6.0 12.0 0.0 6.0 12.0 mme (sec)

Time (sec)

Figure 3 Plant Response to FW Controller Failure (BOC6 to EOC6 Increased core flow /Feedwater temperature reduction to 250 F)

Page 15

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1

l l

PERRY 1 l

Reload 5 J11-02581SRLR i

Rev.1 N tron Flux Vessel Press Rise (psi)

A Surface Heat Flux

- - - - - Safety Valve Flow 150.0

.C Inlet Flow 300.0

--- Re!io! Valve Flow

--- Bypess Wlve Flow

~

2~~~*

g 100.0 h

g200.0

  • s '.

5

-E N

s-E

'h.~ ~~ ~

50.0 100.0 e

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

Eme (sec)

Level (inch-REF-SEP-SKRT)

Void Reactii

- - - - - Vessel Steam Flow

- - - - - Doppler 200.0 - --- Turbine Steam Flow 1.0 R ctivi

- - - Feedwater Flow I

ctivity

/

n

~

i

~

\\

/

g 100.0 y

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t

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-2.0 O.0 4.0 8.0 0.0 4.0 8.0 Time (sec)

Time (sec)

Figure 4 Plant Response to MSIV Closure (Flux Scram)

Page 16

e PERRY 1 Reload 5 J11-02581SRLR Rev.1 Appendix A Analysis Conditions

'Ib reflect actual plant parameters accurately, the values shown in Table A-1 were used this cycle.5 Table A-1 Increased core flow /Feedwater temperature 420 F Parameter Analysis blue Thermal power, MWt 3579.0 Core flow, Mib/hr 109.2 Reactor pressure, psia 1056.0 Inlet enthalpy, BTU /lb 528.8 Non-fuel power fraction 0.038 Steam flow analysis,Mlb/hr 15.41 Dome pressure, psig 1025.0 hrbine pressure, psig 974.8 No. of Dual Mode S/R Valves ( see footnote 5 )

19 Relief mode lowest setpoint, psig ( see footnote 5 )

1133.0 Safety mode lowest setpoint, psig ( see footnote 5 )

1200.0 Increased core flow /Feedwater temperature reduction to 250 F Parameter Analysis Value Thermal power, MWt 3579.0 Core flow, MitVhr 109.2 Reactor pressure, psia 1023.7 Inlet enthalpy, BTU /lb 508.4 Non-fuel power fraction 0.038 Steam flow analysis, Mlb/hr 12.59 Dome pressure, psig 994.6 hrbine pressure, psig 960.3 No. of Dual Mode S/R Valves ( see footnote 5 )

19 Relief mode lowest setpoint, psig ( see footnote 5 )

1133.0 Safety mode lowest setpoint, psig ( see footnote 5 )

1200.0 J. There are a total of 19 valves; the two lowest setpoint safetyhelier valves are assumed to be outw6 service in the transient analysis. For the MSIVFS overpressurizauon analysis,6 safety valves are assumed out-of-service.

1 Page 17

PERRY 1 Reload 5 J11-02581SRLR Rev.1 Appendix B Basis for Analysis of Loss-of-Feedwater Heating Event The loss of feedwater heating event was analyzed with the 3D BWR simulator code described in NEDE-24011-P-A, which permits 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.

The transient analysis inputs nonnally reported in Section 6 of this document am intemally calculated in the 3D BWR simulator code.

Page 18 i

PERRY 1 J11-02581SRLR Reload 5 Rev.1 l

Appendix C Analyzed Operating Domain The core-wide adnonnal operational occunence (AOO) analysis results reponed in Section 9 are the most limiting values over the entire allowable operating range. This range covers the following operating options:

1. Standard 100% power / flow map;
2. End-of-cycle power coastdown;
3. MEOD with 100% power, flow range fmm 75% to 105% of rated; and
4. Panial feedwater heating to 320*F during the cycle with final feedwater temperature reduction to 250 F after AllRods Out at end of cycle.

Limiting events and conditions analyzed are based on NEDE-240ll-P-A-US and the USAR analytical re-suits. The Reload 5/ Cycle 6 analyses were performed assuming all four turbine contml valves in a full are mode of operation. This is conservative for panial are configuration.

t Page 19 l

Udload 5 J11-02581g

  1. 1 Appendix D Transient Analyses The 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 increased core flow.

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

'Ihe 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.

Page 20

PERRY 1 J11-02581SRLR Reload 5 Rey,1 I,

Appendix E Power and Flow Dependent MCPR and MAPLHGR Multipliers The original MEOD offrated MCPR and MAPLHGR multipliers were confirmed to be applicable to this cycle. The original MEOD absolute MCPR powerlimit at or below 40% power and the absolute MCPR flow limit above the OLMCPR need to be multiplied by the ratio of 1.09/1.07. Furthermore,the absolute power and flow dependent MCPR limit must be limited to the cycle 6 rated OLMCPR. For the power dependent MCPR curves, the MEOD original MCPR equations et or below 40% rated power must be multiplied by the p

ratio of 1.09/1.07; and the MEOD original K equations above 40% rated power must be multiplied by the p

rated OLMCPR in order to obtain the equivalent MCPR equation. The MEOD original MCPR equations p

t must be multiplied by the ratio of 1.09/1.07 and limited to the rated OLMCPR. Futhermore, for fuel types GE8x8EB and GE8x8NB-1 the MCPR equation at or below 40% rated flow needs to be multiplied by t

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

Page 21 l

PERRY 1 Reload 5 J11-02581SRLR Rev.1 Appendix F l

GE8x8NB-1 Rotated Bundle Analysis

'Ihe results for each GE8x8NB-1 fuel type are listed in 'Ihble F-1. These results do not change from the pre-vious cycle.

Table F-1 ACPR GE10-P8SXB306-11GZ3-120M-150-T 0.16 GE10- P8SXB306-10GZ2-120M-150-T 0.09 Page 22 l

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