ML20198R233

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Rev 2 to Quad Cities Unit 2 Cycle 145 Reload Analysis
ML20198R233
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 04/30/1997
From: Schnepp R
SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
To:
Shared Package
ML19313D060 List:
References
EMF-96-177, EMF-96-177-R02, EMF-96-177-R2, NUDOCS 9711130198
Download: ML20198R233 (43)
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Text

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SIEMENS

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EMF-96-177

. . Revision 2

. l Quad Cities Unit 2 Cycle 15 Reload Analysis O -

April 1997 a-1 1

Siemens Power Corporation O Nuclear Division i

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Siemens Power Corporation - Nuclear Divisi:n EMF 96177 O lasue Date: 4/18/97 Revision 2 Quad Cities Unit 2 Cycle 15 Reload Analyons I

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Prepared by:

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! . /h R. R. Schnepp, 5(gineer BWR Safety Analysis Nuclear Engineering

'O Analyses Prepared by:

G. D. Griffith D.M. Knee ,

R. R. Schnepp P. E. Smith A. W. Will April 1997 pa)

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C Customer Disclaimer Important Notice Regarding Contents and Use of This t)ocument Mmese Reed CeretiuW Siemens Power Corporation's warranties and representations concoming the subject matter of this document are those set forth in the aproement between Seemens Power Corporation and the Customer purauant to which this document is issued Accorchnoty, except as otherwise expressly provided ir, such acting on its behalf: agreement, nehher Siemens Power Corporation nor any person

s. makes any wer:anty or rg z..

.;vii, .w or implied,with respect to the accuracy, completeness, or u the information contained in this document, or that the use of any information, apparr.tus, method or process diecioned in this document will not inf ince privately owned rights; ~

or f

b. assumes any liabiltties with respect to the use of, or for damages resulting from the use of, any information, apparatus, method, or process discioned in this 6;Tw.i.

The information contained herein is for the solo use of the Customer.

In order to avoid tnpairment of rights of Siemens Power information contained in this document, the recieent, b acceptance of this 6;xa.i. agrees not to publish or make so authorized in wrtting by Siemens Power Corporation etter six (6) months following termmanon or expiration of the

' aforesaid Aeroement and any extension thereof, unless expressly provided in the Agreement. No rights or loconses in or to any patonn are implied by the fumishing of this document.

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EMF 96177

- Rivisi:n 2 PageI

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( Nature of Chan9es

' re: Quad Chios Unit 2 Cycle 15 Reload Analysis I supweeded i.eue: 1 l

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I Wu of Charkse 1, 4,5,12, Updated MCPR safety limit results consistent with Revision 1 of 14,15.19 EMF 96-180(P) (Reference 9.3).

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02. 12 Updated MCPR. operating limits consistent with Revision 1 of EMF-96-180(P) (Reference 9.3).
3. 30,31,32 Updated reduced flow MCPR limits consistent with Revision 1 of EMF 96180(P) (Reference 9.3).
4. 16 Added Reference 8.8.

5, 17 Updated Reference 9.3 to current report revision. {

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i woTE: The changed items are denoted by a vertical bar ( l ) in the left hand margin.

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.. EMF-96177-.

Revision 2 P g e 11 O

V Contents ,

1

1.0 INTRODUCTION

2.0 - FUEL MECHANICAL DESI tK AN.' LYSIS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 3.0 THERMAL-HYDRAULIC DESlON ANALYSIS . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3.2 Hydraulic Characterit ation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3.2.1 Hydraulic C ompatibility . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3.2.3 Fuel Centerline Tom'perature ........................- 4 3.2.5 Bypa s s Flow . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3.3 MCPR Fuel Cladding integrity Safety Limit (SLLiCP3) .............. 4 3.3.1 Coolant Thermodynamic Condition . . . . . . . . . . . . . . . . . . . . . 5 3.3.2 Design Basis Radial Power Distribution . . . . . . . . . . . . . . . . . . 5 3.3.3 Design Basis Local Power Distribution . . . . . . . . . , . . . . . . . . . 5 4.0 NUCLEAR DESIGN ANALYSIS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 i

4.1 Fuel Bundle Nuclear Design Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . 6

( 4.2 Core Nuclear Design Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 i .4.2.1 Core Configuration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 4.2.2 Core Reactivity Characteristics . . . . . . . . . . . . . . . . . . . . . . . . 7 4.2.4 Core Hydrodynamic Stability . . . . . . . . . . . . . . . . . . . . . . . . . 8 5.0 ANTICIPATED OPERATIONAL OCCURRENCES . . . . . . . . . . . . . . . . . . . . . . . 10 5.1 Analysis of Plant Transients at Rated Conditions ................ 10 5.2 Analysis for Reduced Flow Operation ........................ 10 5.3 Analysis for Reduced Power Operation ....................... 10 5.4 ASME Overpressurization Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . 11 5.5 Control Rod Withdrawal Error . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 5.6 Fuel Loading Error . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 5.7 Determination of Thermal Margins . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 6.0 POSTULATED ACCIDENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 6.1 Loss-of-Coolant Accident . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 6.1.1 Break Location Spectrum . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 6.1.2 Break Size Spectrum . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 6.1.3 MAPLHGR Analyses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 6.2 Controt Rod Drop Accident . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 6.3 Spent Fuel Cask Drop Accident . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13

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EMF 96177 t R;visi:n 2 Page iii

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Contents (Continued) -

7.0 TECHNIC AL SPECIFn ':ATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 7.1 Limiting Safety System Settings . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 1 7.1.1  ;

MCPR Fuel Cladding Integrity Safety Limit . . . . . . . . . . . . .. . 14 7.1.2 Steam Dome Pressure Safety Limit . . . . . . . . . . . . . . . .  !

7.2 14 I Limiting Conditions for Operation . . . . . . . . . . . . . . . . . . . . . . . ....

. . 14 7.2.1 Average Planer Linear Heat Generation Rate .'. . . . . . . . . . l 7.2.2 14' i

  • Minimum Crttical Power Ratio . . . . . . . . . . . . . . . . . . ,, . .... . 15 7.2.3 Lineer Heat Generation Rate . . . . . . . . . . . . . . . . . . . . . . . . . 15  !

8.0 METHODOLOGY REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 9.0 i ADDITIONAL REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 .

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. .- _ _ EMF-96-177 ,

Revision 2 Pageiv L

r Tables EOD and EOOS Operatirk Condit;ons ............................. 18 1.1 4.1 Neut.onic Design Values . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 Figures i

19 3,1 Radial Power Distribution for SLMCPR Determination . . . . . . . . . . . . . . . . . .

,'3.2- Quad Cities Unit 2 Cycle 15 Safety Limit Local Peaking Factors With Channel Bow at 22,500 (SPCA9-372811GZH-ADV) . . . . . . . . . 20 3.3 Quad Cities Unit 2 Cycle 15 Safety Limit Local Peaking Factors With Channel Bow at 20,000 (SPCA9 358811GZL-ADV) . . . . . . . . . 21 I

4.1 Quad Cities Unit 2 Cycle 15 SPCAS-396L-11G6.5 23 Enrichment Distribution . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

4.2 Quad Cities Unit 2 Cycle 15 SPCA9 396L-11G7.5 24 Enrichment Distribution . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Quad Cities Unit 2 Cycle 15 SPCA9-423L 11G7.5 l 4.3 25 Enrichment Distribution . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

4.4 Quad Cities Unit 2 Cycle 15 SPCAS 396L-11G5.5 26 Enrichment Distribution . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

14.5 Quad Cities Urdt 2 Cycle 15 SPCA9 396L 10G6.5 27 Enrichment Distribution . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

4.6 Quad Cities Unit 2 Reload Batch OCB-1 Axial Fuel Assembly Designs ................................... 28 l-i 4.7 - Quad Cities Unit 2 Cycle 15 Referance Loading Map

! (Quarter-Core Sy.T..T hic Loading) ............................... 29 15.1' - Reduced Flow MCPR Limit for Manual Flow Control 30

- (SLMCPR = 1.10) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

5.2 Reduced Flow MCPR Limit for Automatic Flow Contml . . . . . . . . . . . . . . . . . 31 5.3 Reduced Flow MCPR Limit for Automatic Flow Control

.................... 32 (EOD/EOOS OLMCPR) ................ .

' 7.1- Protsetion Against Power Transient LHGR Limit for ATRIUM'"-98 Offset Fuel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 33

EMF-96-177 _

R:visi:n 2 Pcge 1 Quad Cities Unit 2 Cycle 15- .

Reload Analysis

1.0 INTRODUCTION

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- This report provides the results of the analysis performed by Siemens Power Corporatinn -

Nuclear Division (SPC) in support of the Cycle 15 reload for Quad Cities Unit 2. This report is intended to be used in conjunction with the SPC topical Report XN-NF-80-19(P)(A),

, Volume 4, Revision 1, Amo#cstion of the ENCMethodWogy to SWRRedoods, which describes the analyses performed in support of this reload, identifies the methodology used for those analyses, and provides a generic reference list. Section numbers in this report are the same

- as corresponding section numbers in XN NF-80-19(P)(A), Volume 4, Revision 1. Methodology used in this report which supersedes XN NF-8019(P)(A), Volume 4, Revision 1 is referenced ,

in Section 8.0. The NRC Technical Limitations presented in the methodology documents, including the documents referenced in Section 8.0, have been satisfied by these analyses.

O For Quad Cities Unit 2 Cycle 15, Commonwealth Edison Company (Comed) has responsibility

for portions of the reload safety analysis. This document describes only the Cycle 15 analyses
performed by SPC; Comed analyses are described elsewhere. Hence, this document alone does not necessarily identify the limiting events or the appropriate operating limits for Cycle i 15. The limiting events and operating lunits must be determined in conjunction with results from Comed analyses.

l The Quad Cities Unit 2 Cycle 15 core consists of a total of 724 fuel assemblies, including 216 l

l unirradiated QCB 1 ATRIUM *-9B* offset assemblies,144 Irradiated GE10 assemblies, and l

l 364 irradiated GE9 assemblies.The reference core configuration is described in Section 4.2.1.

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The design and refety analyses reported in this document were based on the design and operational assumptions in effect for Quad Cities Unit 2 during the previous operating cycle.

The effects of channel bow are explicitly accounted for in the safety limit analysis. SPC has O

  • ATRIUM is a trademark of Siemens.

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R;visi:n 2 l

Page 2 performed time step size sensitivity studies to assure that the numerical solution in the COTRANSA2 code converged.

Analyses and limits presented in this report support operation with various extended operating domain (EOD) and equipment out-of service (EOOS) conditions. The EOD/EOOS conditions eddressed in this report are identified in Table 1.1.

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Revision 2 l . P ge 3 l

i 2.0 . FUEL MECHANICAL DESIGN ANALYSIS O Applicable SPC Fuel Design Reports

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References 9.1,9.7 and 9.8 To ccsure that the power history for the fuel to be irradiated during Cycle 15 of Quad Cities Unit 2 is bounded by the assumed power history in the fuel mechanical design analysis, LHGR cperating limits have been specified, in addition, LHGR limits for Anticipated Operational 03:urrences have been specified in the references. Transient LHGR limits are provided in S:ction 7.2.3 as Figure 7.1.

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EMF-96-177 Revision 2 Page 4 3.0 THERMAL 44YDRAULIC DESIGN ANALYSIS C

d 3.2 Hydraulic Characterization  !

3.2.1 Hydraulic Comontibility Component hydraulic resistances for the constituent fuel types in the Quad Cities Unit 2 l

- Cycle 15 core have been determined in single-phase flow tests of full-scale assemblies. The hydraulic demand curves for SPC ATRIUM 98 offset, GE9, and GE10 fuelin the Quad Cities Unit 2 core are provided in Reference 9.7 (Figures 5.2 and 5.3 in the reference).

3.2.3 Fuel Centerline Temnerature ATRIUM 9B Reference 9.7, Figure 3.2 3.2.5 Bvoans Flow Calculated Bypass Flow Fraction at 12.3% Reference 9.3 100% power /100% flow at E00" 3.3 MCPR Fuel Claddino Inteority Safetv Limit (SLMCPR) l Two Loop Operation - 1.10" Reference 9.3 l Single-Loop Operation - 1.11" Includes water rod / channel flow.

includes the effects of channel bow with up to 40% of the TIP strings out of service 4 -

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\ (but 100% TIP strings available at startup), a 2000 EFPH calibration interval, and up

'to 50% of the LPRMs out of service (LPRM' substitution model on or off).

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  • EMF 96177 R:visiin 2 Page 5 3.3.1 Coolant Thermodynamic condition l 4158 MWt l Thermal Power (at SLMCPR) 16.1 Mlb/hr j Feedwater Flow Rate (at SLMCPR) 1030 psia Core Pressure l Feedwater Temperature 340'F 3.3.2 Desion Basis Radial Power Distribution Figure 3.1 shows the limiting radial p6wer distribution used in the MCPR Fuel Cladding integrity Safety Limit analysis.

3.3.3 Desion Basis Local Power Distribution

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Figures 3.2 and 3.3 show the conservative local power distributions used in the MCPR Fue Cladding integrity Safety Limit analysis.

Figure 3.2 SPCA9 372B-11GZH-ADV Figure 3.3 SPCA9-3588-11GZL-ADV

Revision 2 Page 6 i

' 4.0 . NUCLEAR DESIGN ANALYCIS i O._ 4.1 Fuel Bundle Nuclear Dealan Analysis .

l Assembly Average Enrichment i

ATRIUM-98 offset (OCB 1 Type H) 3.72 wt%

(OCB 1 Type L) 3.58 wt%

Radial Enrichment Distribution SPCA9 396L-11G6.5 Figure 4.1 SPCA9 396L-11G7.5 - Figure 4.2 SPCA9-423L-11G7.5 Figure 4.3 GPCA9-396L-11G5.5 Figure 4.4 SPCA9 396L-10G6.5 Figure 4.5 Axial Enrichment Distribution Figure 4.6 Burnable Absorber Distribution Figure 4.6 Non Fueled Rods Figures 4.1-4.5 l

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Neutronics Design Parameters Table 4.1 l Fuel Storage'd i

Quad Cities New Fuel Storage Vault Reisiances 9.10 The OCB 1 Reload Batch fuel designs meet the fuel dwign limitations defined in Table 2.1 of Reference 9.10 and therefore can be safety stored in the vault.

Quad Cities Spent Fuel Storage Pool Reference 9.9 i The QCB-1 Reload Batch fuel designs may be stored in the storego pool provided the array k-off 50.95 as determined by the procedure defined in Section 6.5 of Reference 9.9.

\ The ATRIUM-9B offset fuelis bounded by the referenced analyses.

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R vi i n 2 4.2 Page 7 Core Nuclear Desion Analysis 1

4.2.1 Core Confiouration_

Figure 4.7 Core Exposure at EOC14, MWdMTU (nominal value) 25,813 Core Exposure at BOC15 MWdMTU (from nominal EOC14) 14,881 Core Exposure at EOC15 MWdMTU (licensing basis) 28,576 NOTE:

EOD/EOOS cycle extension analyses ,

ycle 15 (Reference 9 provided MWdMTU. full power capability is lost prior to reaching a core ixposur e of 28,576

< Cycle 15 short window exposure to be fumished by Comed > .

04.2.2 Core Reactivity Characteristics

< This data is to be fumished by Comed. >

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Revtion 2 P:ge 8 l 4.2.4 Core Hydrodynamic Stub))gy Reference 8.5 I

The results of STAIF calculations for several points along the current exclusion region boundary on the powertflow map for a flow runback from normal operation are shown below.

These calculated decay ratios are for demonstrating and tracking reistive core stability behavior from cycle to cycle. The Cycle 15 design basis control rod step-through projection w s used in the ana!ysis. A cycle exposure search was made to determine the highest decay r:tio throughout the cycle. Similar calculations for Cases 1 and 2 were made for Cycle 14 (all GE fuel in cora). These calculations show that for the limiting mode (values shown in bold),

there is no significant difference in the stability behavior of Cycle 15 compared to the previous cy:le (Cycle 14).

Decay Ratio (ADR*)

Case / Description Global Asgional

1. 68.5/45" (% Power /% Flow) 0.78 (- 0.23) 0.62(- O.17)

, 2. 23/19.48*8 0.36(-0.02) 0.28 (0.06) p 3. 58.5/45" 0.53 0.41 1

4. 37/38.8* 0.24 0.18
5. 64/38.8'8 1.0 0.79
  • DRevis - DRevi, values are in parentheses a*

APRM rod block line and 45% flow 8*'

70% tod line and netural circulation

  • 100% rod line and 45% ficw 70% rod line and minimum flew APRM rod block line and minimum flow

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EMF 96177 R: vision 2 Page 9 For reactor operation under conditions of coastdown, single loop, final feedwa reduction (FFTRI, and/or feedwater heaters out of service, it is possible th

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ratios could be achieved for these conditions than are showri for normal ope i for both cycles. Because all of these operating conditions were allowed in C ,

concluded '. hat operation under these conditions wili tikewise S e acceptable i

long as the same operating procedures and precautions used in Cycle 14 SWROG interim Corrective Actions) are followed in Cycle 16.

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EMF 96177 -

Revisiin 2 >

Page 10

~.0 ANTICIPATED OPERATIONAL OCCURRENCES

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Applicable Generic Transient Analysis Report Reference 9.2 5.1 Analveig of Plant Transients at Rated Condhions References 9.3 and 9.6 I

Limiting Transients: Load Rejection No Bypass (LRNB)

Feedwater Controller Failure (FWCF).

Loss of Feedwater Hosting (LFWH)'d Maximum Peek Maximum Power Plow Heat Plum Neuron Preneure Event ,,1%)_ .13L i Plux (%) M ACPR" Madel UIN8*

  • 100 100 133 803 1305 0.45 / 0.40 / 0.34 L,TRANSA2 PWCP** 100 108 138 587 1200 0.47 / 0.42 / b.37 COTRANSA2 lO 5.2 Analysis for Reduced Flow Operation Reference 9.3 p

Limhing Transient: Recirculation Flow increase s'ransient (Pump Run-Up Event) 5.3 Analysis for Reduced Power Operation References 9.3 and 9.6 Limit;ng Transient: Feedwater Controller Frilure (FWCF) i

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- This data to be furnished by Comed. '

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  • ACPR resuhs for tnird-cycle GE9/secondqcle GE10/first cycle ATRIUM-9B offset fuel.

O ECO o on wkh a y be FFTR FH oestdown condhions, a generic 0.04 MCPR operstmg limh penalty is appiesd. For other 4

EODEOOS condhions no penalty is needed.

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EMF 96177 Rtvision 2 Pcge 11 5.4 ASME Ovemressurization Analysis

  • O Limiting Event MSIV Closure Worst Single Failure Valve Position Scram Maximum Pressure (Lower Plenum) 1323 psig Maximum Steam Dome Pressure" 1290 psig 5.5 Control Rod Withdrawal Error *

< This data is to be fumished by Comed. >

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5 .6 Fuel Loadina Error O

< This data is to be fumished by Comed. >

EOD/EOOS operation with coastdown conditions requires a generic pressure penalty of 5.0 psi. For other EOD/EOOS conditions no penalty is needed.

Maximum steam dome pressure corresponds to the analysis that resulted in the maximum vessel pressure.

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EMF 96177 Revision 2 Page 12 I 7' Determination aflha' mal Marnins Summary of Thermal Margin Requirements Power Flow Event t%) X - _ AGPR* MCPR Limit"  !

l LMNB 100 -108- 0.45/ 0.40 /0.34 _1.55 /1.50 /1.44" l FWCF 100 108 0.47 / 0.42 /0.37 1,57 /1.52 /1.47" MCPR Operating Limit" 1.57 /1.52 /1.47"**

l MCPR Operating Limit With EOD/EOOS Pen.Jty" 1,61 /1.56 /1.515 *

  • l MCPR Operating Limits at Off Rated Conditions" Reduced Flow MCPR Limits:

Manual Flow Control Figure 5.1

- Automatic Flow Control Figures 5.2 and 5.3 lY 1

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  • Values for third-cycle GES/second-cycle GE10/first-cycle ATRIUM-9B offset fuel. ,

, l* Based on plant Technical Specification two-loop MCPR safety lim!t of 1.10 and Technical Specification limiting scram performance parernsters. For operation in single-

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, _ loop, the Technical Spscification single-loop MCPR safety limit of 1.11 increases the MCPR operating I'mit by 0.01.

  • These limita may nood to be increased if Comed CRWE analyses resuits are more l6miting. -

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For EOD/EOOS operation with any combination of FFTR, FHOOS, and coastdown l' conditions, a generic 0.04 MCPR operating limit penalty is applied. For other

[ EOD/EOOS conditions no pensity is needed.

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l EMF 96177 Revision 2

[ Page 13 GO POSTULATED ACCIDENTS

.V 6.1 : Loss-of-CoolanLAccident .

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, 6.1.1 Break Lgention Soectrur9 Reference 9.4 and 9.5 6.1.2 Break Size Snectrum Reference 9.4 and 9.5 6.1.3 MAPLHGR Analyses Reference 9.5 The MAPLHGR limits of Reference 9.5 are valid for the Quad Cities Urdt 2 ATRIUM 98 offset (OCB 1) fuel for Cycle 15 operation. MAPLHGR limits are presented in Section 7.2.1.

Limiting Break: Double-Ended Guillotine Pipe Break

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Recirculation Pump Suction Line  :

1.0 Dischar9e Coefficient

,O LPCI injection Valve Failure Considering all exposures yW the Cycle 15 ATRIUM-98 offset fuel type, peak clad t:mperature, peak metal watc w nion (MWR), and total core MWR are 1880*F, <1.59%

locally, and <0.12% core wide, respectively. '

6.2 Control Rod Dron Accident -

< This data is to be fumished by Comed. >

6.3 Sonnt Fuel Cask Dron AccMant i- The Quad Chies UFSAR analysis of record for the Spent Fuel Cask Drop Accident is not fuel -

type dependent; thus, the results reported in UFSAR Section 15.7.3 are applicable for the SPC mioed fuel.

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EMF-96-177 Revision 2

. Page 14 i TECHNICAL SPECIFICATIONS 1

7.1 Limitina Safety System Settins

.7.1.1- MCPR Fuel Claddina intearity Safety Limit l

l MCPR Safety Umit (all fuel) - Two-Loop Operation 1.10" -

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l__ MCPR Safety Limh (all fuel) - Single-Loop Operation 1.11* l i

7.1.2 Steam Dome Pressure Safety Limit ,

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Pressure Safety Umh 1345 poig l

. 7.2 Umhino Conditions for Onoration I

.i 7.2.1 Averaae Planar unear Heat Generation Rate O 1 ATRIUM 98 l Planar Average Offset GE9 GE10 ,

Exposure MAPLHGR MAPLHGR MAPLHGR l (GWd/MTU) (kW#t) (LW#tl (kW#t) l O 13.5 < To be fumished by Comed. >

20 13.5 60 - 8.7

- SPC performed LOCA analyses from single-loop conditions and determined an appropriate SLO MAPLHGR ~ multiplier of 0.9 for ATRIUM-98 offset fuel. The ECCS analysis results are presented in Reference 9.5. All calculations were performed with the NRC-appic.md EXEM/8WR ECCS Evaluation Model according to Appendix K of 10CFR50.

> ' Includes the effects of channel bow with up to 40% of the TIP stririgs out of service (but 100% TIP strings available at startup), a 2000 EFPH calibration interval, and up

- to 50% of the LPRMs out of service (LPRM substitution model on or off).

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Page 15  :

7.2.2 Minimum Critta=8 Power Ratio O Rated Conditions MCPR Limit Based on "

Technical Specification ~ Scram Times '

Off Rated Conditions MCPR Umits:

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i Manua! Flow Control Figure 5.1 Automatic Flow Control Figures 5.2 and 5.3 7.2.3 Linear Heat Generation Rate Figure 2.1 of Reference 9.7 i

Steady State LHOR Umits GE9 and GE10 ATRIUM-9B Offset Fuel Planar Average Planar Average Exposure LHGR Exposure LHGR j (GWd/MTU) (kW#t) (GWd/MTU) *

(kW#t)

O.0 14.4

< To be fumished by Comed. >

15.0 14.4 61.1 8.32 l The transient linear heat generation rate curve is Figure 2.2 of Reference 9.7 for ATRIUM-98 I

offset fuel. This figure is presented in the report as Figure 7.1 for convenience.

{ Composite power history curvec for the FWCF and the LRNB/TTNB analyses are provided in Referencs 9,11. Yhe coroposita power history curves provided in Reference 9.11 can be used i

by Comed to assess compliance wkh mechanical design limits (1% strain criteria) for the l coresident CE9 anu GE10 fuel.

(- Based on resutts from Section 5.7 and results from Comed's scope of responsibility.

l .( The MCPR operating limit is based on a TeeSnical Specification two-loop MCPR safety l limit of 1.10 and the limiting ACPR for Cycle 15.

l i

l -. ._ . .- . - . _ . . - .--;.-.--.-. - . . - - .-. . ..

i:MF 96177 -

Revision 2 Pa9e 16 8.0 - METHODOLOGY REFERENCES O See XN NF-80-19(P)(A), Volume 4, Revision 1' for a complete bibliography.

8.1 ' COTRANSA2: A Computer Program for Bonne Wster Reector Transient Analysis, ANF-913(P)(A), Volume 1, Revision 1, Supplements 1,2,3 and 4, Advanced Nuclear Fuels Corporation, August 1990.

8.2 ' Advanced NucAner Fuek Critkel Nwer Methodo6agy for Banhg wister Reactors, XN NF 524(P)(A), Revision 2, and Supplements, Advanced Nuclear Fuels Coegeratio:.. .

November 1990.

' 8.3 ANFB CrfricalP6wer CorreAstion, ANF 1125(P)(A), Supplements 1 and 2, Adv nced Nuclear Fuels Corporation, April 1990.

> 8.4 Advanced NucAner Fuels Methoddogy for BonHg WsterReectors: Benchmern Resutts for the CASMO-3G/MICROBURN-B CalcuAstion Me*hoddogy, XN-NF-90-19(P)(A),

Volume 1 oruf Supplement 3, Appendix F and Supplement 4, Advanced Nuclear Fuels Corporation, November 1990.-

, 8.5 STAIF: A Computer Program for BWR StabNty Analysis k the Frensancy Domek, EMF-CC-074(P)(A), Volume 1 and Volume 2, Siemens Power Corporation - Nuclear Division, July 1994.

, 8.6 Application ofANPB CridcolP6wer Correintion to Coronident GEFuelat the Guad Cities I cod LaSa#e NucJoer P6wer Stations, EMF-95-049(P), Siemens Power Corporation -

Nuclear Division, October 1995. l

. 8.7 Applocation of ANFB CriticalP6wer CriticalP6wer Correlation to Coresioent GEFuelfor Oued C/ ties Un/t 2 Cycle 15, EMF-96-051(P), Siemens Power Corporation - Nuclear Division, May 1996.

' 8.8 ANFB Critical Power Correlation Uncertainty for Limited Dets Sets, EMF 1125(P),

Supplement 1, Appendix D, Siemens Power Corporaten - Nuclear Division, April 1997.

4 5'

!~

uO l

- ~....,. _ _

' EMF 96177 Revisi:n 2-Page .17 O ADDmONAL REFERENCES 9.1. Gensnic MechenicalDes@n &BWR FuelDes@ns, ANF-89 38(P)(A), Revision 1, and Revision 1 Supplement 1, Advanced Nuclear Fusts Corporation, May 1995.

9.2 Eaon Nucteer Mont Transient Methodboogy for Bomng Water Reactors, XN-NF 71(P), Revision 2, including Supplements 1.throu9h 3(P)(A), Exxon Nuclear Company, inc., Mamh 1986.

l

.l 9.3 Quad C.Wes Urdt 2 Cycie 16 Mont Transient Analysis, EMF 96180(F). Revision 1, '

1 Siemens Power Corporation - Nuclear Division, April 1997.  !

9.4 LOCA Broek Spectrum Analysis for Quad Cities Units 1 and 2, EMF-96184(P),

Siemens Power Corporation - Nuclear Division, December 1996.

9.5 OuedCldesLOCA-ECCSAnelysisMAPLHGRResatts WA TRIUM* 98, EMF 96-185(P),

Siemens Power Corporation - Nuclear Division, Revision 1, March 1997.

l 9.6 Ext: waled Operating Domek (EODiand Equ> ment Out of Service (EOOS) Safety Anel;

  • for ATRIUM *-9K Fuel, EMF-96 037(P), Revision 1, Siemens Power l Corporation - Nuclear Division, September 1996.

i O' Fuel Design Report for Quod Cities Unit 2 CycAs 16 A1RIUM*-98 fu 1996.

' 9.8 Generic Mechanical Design for Advanced NucAner fveis 9x9-IX and 9x9-9X BWR Reload fuel, ANF-89-014(P)(A) Revision 1 and Supplements 1 and 2, Advanced Nuclear Fuels Corporation, October 1991.

9.9 CriticeMty Safety Analysis for A TRIUM' 98 fuel Oued CNies Units 1 and 2 Spent Fuel Storspe Pbo,'s (SorefAex Rocks), EMF-96 013(P), Siemens Power Corporation - Nuclear Division, June 1996.

[ 9.10 Criticoury Safety Analysis for ATRIUM'-98 fuel Dresden and Quod Cines New Fuel Storspe Vaults, EMF-94-148(P), Revision 1, Siemens Power Corporation - Nuclear

- Division, September 1996.

9.11 Letter, J. H. R6ddle (SPC) to R. J. Chin (Comed), " Updated Transient Power History Data for Confirming Mechanical Limits for GE Fuel for Quad Cities Unit 2 Cycle 15,*

i

' JHR:96:389, October 4,1996.

of a &

_ , _ - m.... . . .. - . , _ . .m.._ , . . . . . _ _ , . _ . _ . . . _ . , ~ . _ . , _ - - _ , ~ . . _ . . , , . . . . . .

EMF-96177 Revision 2 Page 18 Table 1.1 EOD and FOOS Operating Condtions Extended Opernefng Domahr Com0tions e

increased Core Flow (ICF)

  • Coastdown Combined ICF/FFTR Combined IC?/Coastdown Combined FFTR/Coastdnwn Combined ICF/FFTR/Coastaown 1 Equ> ment Out of Service Conddons*

l Feedwater Hester(s) Out of Service (FHOOS)

Single-loop Opetution (SLO)- Recirculation Loop Out of Service Relief Valve Out of Service (RVOOS)

Safet// Relief Valve Safety Function Out of Service (SRVOOS) for ASME Events ,

Up to 40% TIP Strings Out of Service (TIPOOS)"

i EOOS conditions a e suppo:ted for both EOD conditions and standard operating domain conditions, t

40% TIPOOS with 100% TIP strings svallable at startup,50% of the LPRMs out of service (LPRM substitution model on or off), and 2000 EFPH LPRM calibration intervat.

EMF.96- :"77 Revisibn 2 Page 19 0 100 .

. 4

,o .

30 .

70 -

m .

G .

]so m

o M -

b. _' _

-x .

~~~ ~ ~ ~

lO 2o -

10 -

o

.0 .2 .4 .6 A 1.0 1.2 1.4 .1.6 1A Radial Power Peaking Figure 3.1 Radial Power Distribution for SLMCPR Determination

EMF.96-177 R:visi:n 2 Pcge 20 1 Control Io RodCorner 1.007 1.015 1.028 1.026 1.088' 1.074 , 0.999 1.010 0.973 10 l1 1.015 1.074 1.081 l 1.084 0.%3 1,023 1.015 0.955 1.036 IR ll 1.028 1.081 1.076 1.103 1.118 1.075 I

1.014 ' O 989 1.023 iC lo 1.026 1.084 1.103 lr ,

Internal 0.939 0.967 1.009 le 1.088 0.963 1.118 ' Water' 1 059 0.841 0.988 I

^

' ..,; Channel l 1.074 1.023 1.075 '

1

- 1.009 0.924 0.971 I

l 0.999 1.015 1.014 0.939 I 1.059 1.009 0.834 i l 0.917 0.947 1,010 0.955 0.989 0.967 0.841 0.924 0.917 0.829 0.915 I

I 0.973 1.036 1.023 1.009 0.988 I 0.971 0.947 0.915 0.826 I

Floure 3.2 l

i ou d ces urde 2 cycs.1s

' l Safety Lindt Local Peaking Factors

!  ! With Channel Bow at 22,500 mwd /MTU

! (SPCA9 3728-11GZH ADV)

,O

\

l Revision 2 -

Page 21

l C o n t r oil R o'd C o r n e r-l- . l o:

f: '1.011 1.022 .1.032 1.028 1.0'93 -1.079 1.000 1.015 -0.977 '

'l r 1.o f .'l -1.022 1.085 1.084 1.085 0.963 -1.021 1.013 0.958 1.042 l- .- ,

1: R

.l ll 1.032. 1.084 1.075 1.105. 1.121 1.075 1.008 0.985 1.024 l C:-

-l~o 1.028- 1.085 1.105 0.937 0.960 1.007

l-[ Internal-I e~ 1.093 0.963 1.121 Wate

~'

Ir 1.057 0.837 0.985 l m ; channel s- _

l 1.079' 1.021 1.075 f,

m- 1.005 0.918 0.968 g a. . a4 m .

I l i 1.000 - 1.013 1.008 0.937

- : l- 1.057 1.005 0.829 0.910 0.945 1.015 0.958 0.985 0 %0 0.837 0.918 0.910

, 0.828 0.915 l

l 1 0.977 1.042 1.024 1.007 0.985 0.968- 0.945 0.915 0.823 -

I 4

l- Figure 3.3 I Quad cities unit 2 cyone 15

-I safety Limit Local Peaking Feetore I with channel now at 20,000 MwdAWTu l (sPcAs.assa.11azL.Any) ,

O '

t e- g , w- ---n , -an+, - -e-e , , , .

EMF 96-177 R:vis!on 2 P:ge 22 Table 4.1 Neutronic Design Values

' Number of Fuel Assemblies 724 Rated Thermal Power, MWt 2511 '

Rated Core Flow, Mibm/hr .

98.0 Core inlet Subcooling, Btu /lbm

' 21.6*

Moderator Temperature, 'F 546" Advanced Channel Thickness (comer), inch

, 0.100 Channel internal Face-to-Face ' Dimension, inch 5.278 Fuel Assembly Pitch, inch 6.0 Wide Water Gap Thickness, Inch 0.630" Narrow Water Gap Thickness, inch 0.414" i

ControlReef Dete*

O Absorber Material 8'4C Total Blade Spen, inch 9.810 Total Biade Support Span, inch 1.580 Blade Thickness, inch 0.312 Absorber Rods Per Blade- 84 Absorber Rod OD, inch --

0.188 Absorber Rod ID, inch 0.138 Absorber Density, % of theoretical

. 70

  • - ~

Based on actual operating ' experience.

Value corresponds tothe ATRIUM 98 offset fuel with advanced channel gap measured at the top and bottom of the bundle, i.e., from the'100-md-thick channel wall.

The control rod data represents original equipment control blades at Quad Cities whic O that equipment reactivity bladet. characteristics of replacement control blade 1

p , , . -,--s, -n - --

R: vision 2 Pcge 23 oControl RodCorner n 1 2 3 4 5 t 2.000 5 4 4 2.600 3.000 3.200 2 3.800 3.800. 3.200 3.200 2.600 0

I 2 8 6 7 8 6 6 2.600 3.800 4.250 4.500 8 5 3.800 4.250 4.250 R 3.800 L 3.800 o 3 6 7 7 7 7

d. 3.000 4.250 7 7 6 4.500 4.500 4.500 4.500 4.500 4.500 4.250 C

4 7 7 0

3.200 4.500 8 7 r 4.500 .

3.800 7

4.500 4.500 Internal-5 8 7 *

, f 3.800 3.800 4.500 Water 7 8 7 4.500 3.800 4.500 5 Channel-6 7 .

3.800 4.250 4.500 ' 7 7 7 4.500 4.500 4.500 4 6 7 8 7 7 3.200 4.250 4.500 8 7 6 3.800 4.500 4.500 3.800 4.500 4.250 4 8 7 7 8 7 3.200 3.800 4.500 4.500 7 8 5 3.800 4.500 4.500 3.800 3.800 2 5 6 7 7 7 2.600 3.800 4.250 4.500 6 5 2 4.500 4.500 4.250 3.800 2.600 1 Rods ( 1) --

2.000 wt% U-235 2 Rods ( 5) --

3 2.600 wt% U 235 Rods ( 2) --

3.000 wt% U-235 4 Rods ( 6) --

5 3.200 wt* U-235 Rods ( 8) --

3.800 wt% U-235 6 Rods'(10) --

7 4.250 wt% U-235 Rods (29) --

4.500 wt% U-235 8 Rods (11) --

3.800 wt% U-235 + 6.50 wt% GdA i

Figure 4.1 Quad Chios Urdt 2 Cycle 16 O SPCAS-396L-1106.5 Enrichment Distribution

. tg l

l _ _

_ _ - . _ . _ ~ _ .. _ _. _ _ _ _ _ _ . _ __ ___ _ _ -__ ___

EMF 96 *~7 R:visio- 2 Page 24 C o n t, r o 1 RodCorner O o n 1 2 3 4 5 5' 4 4 '2 t -2.000 2.600 3.000 3.200 3.800 3.800 3.200-- 3.200 2.600 r

y 2 8 6 7 8 6- 6 8 5 2.600 3.800 4.250 4.500 3.800 4.250 4.250 3.800 3.800 R '

o -3 6 7 7 7 7 -

7 7 6 d 3.000 4.250 4.500 4.500 4.500 4.500 4.500 4.500 4.250 C

4 7 7 0 8 7 7 3.200 4.500 4.500 3.800 4.500

' 4.500

[ In ernal e 5 8 7 7 8 7 3.800 r 3.800 4.500 C[ 4.500 3.8's 4.500 5 6 7

' Channel 7

3.800 4.250

  1. 7 7 7 4.500 4 4.500 4.500 4.500 4 6 7 8 7 7 8' 7 6
3.200 4.250 4.500 3.800 4.500 4.500 3.800 4.500 4.250 4 8 7 7 8 7- 7 8 5-3.200 3.800 4.500 4.500 3.800 4.500 4.500 3.800 3.800 2 5 6 7 7 7 6 5 2 2.600 3.800 4.250 4.500 4.500 4.500 4.250 3.800 2.600 1 Rods ( 1) -

2.000 wt! U-235 2 Rods'( 5) --

2.600 wt! U-235 3 Rods ( 2) --

3.000 wt! U-235 4 Rods ( 6) --

3.200 wt! U-235 5 Rods'( 8) --

3.800 wt! U-235 6 Rods (10) --

4.250 wt! U-235 7 Rods (29) --

4.500 wt! U-235 8 Rods (11) -

3.800 wt! U-235 + 7.50 wt3 GdA f

W Fleure 4.2 ounsi chies uret 2 cyci 1s y sPCAS 396L-17G7.5 Enrichment DistrRsution

-(-

\

EMF 96177 Moviolon 2 Pope 25

(

l

c. o n t r 0 1 R o d C o r n e r i t

O. t 2.000 1 2 3 4 5 5 4 4-2 t

2.600 3.000 3.600 3.800 i r <

3.800 3.600 3.600 2.600 i

j 2 8 6 6 8 6 t

2.600 6 8 5 4.050 4.500 4.500 -4.050 4.500 4.500 4.050 3.800 R

o 3 6 7 i 7 7 7 d 3.000 7 7 6 4.500- 4.950 4.950 4.950 4.950

. 4.950 4.950 4.500 '

C O

4 6- 7 -

l ~

3.600 8 7 7

r. 4.500 4.950 4.050 4.950 4.950 n i l Inter $il...-

4-

_c 5 8 7 "

r 3.800- 4.050 .4.950 hf ?; 7 8 7'  !

s

, ,w ,

x- 4.950 4.050 4.950 i

-P~'

i

-5 6 7- *

'H T "4 "

3.800 4,500 6 7 7 4.950

, L l.4. f. , 4.500 4.950 4.950 s

4 6 7 8 7 6 8 3.600 4.500 4.950 4.050 7 6

4.950 4.500 4.050 4.950 4.500 i

/ O,3.600 4.050 4 8 4.950 7 7 8 7 7 8 5 4.950 4.050 4.950 4.950 4.050 3.800 i

i 2 'S 6 7

7 7 6 2.600 3.800 4.500 5 2 4.950 4.950 4.950 4.500 t

, ,_ 3.800 2.600 i

i i

1 Rods ( 1) --

2.000 wtt U-235  !

2 Rods ( 5) -

3 2.600 wt! U 235 Rods ( 2) -

3.000 wt! U-235 4 Rods ~( 6) --

5 3.600 wtt U 2J5 ,

1 Rods ( 8) -

3.800 wtt U 235 1 E Rods (14)

o

" 7 Rods (25) 4.500 wtt U 235 +

4.950 wt! U 235  :

8 Rods (11) -- *

~4.050 wt! U 235.+ 7.50 wtt GdA .

i l

Pigme 4J O =*=^ *==' ' 'a7 = =

Quad chies' unit 2 c yste i s

' a' ' - ,

i i

Revision 2 Page 26 Control o

RodCorner I n 1 2 3 4 5 5 4 4 t 2.000 2.600 2 3.000 3.200 3.800 3.800 3.200 3.200 2.600 0

I 2 8 6 7 8 6 6 8 5 2.600 3.800 4.250 4.500 3.800 4.250 4.250 3.800 3.800 R

o 3 6 7 7 7 7 7 7 d 3.000 4.250 6 4.500 4.500 4.500 4.500 4.500 4.500 4.250 C

4 7 7 0 8 7 7 3.200 4.500 4.500 '

I 3.800 4.500 4.500 Internal e 5 8 7 .

7 8 r 3.800 3.800 4.500 ' " 'I.

4.500 7

3.800 4.500 Channel 5 6 7 7 7 7 3.800 4.250 4.500 4.500 4.500 4.500 4 6 7 8 7 7 8 3,200 4.250 4.500 7 6 3.800 4.500 4.500 3.800 4.500 4.250 4 8 7 7 8 7 7 8 3.200 3.800 4.500 4.500 3.800 5

4.500 4.500 3.800 3.800 2 5 6 7 7 7 6 5 2.600 3.800 4.250 4.500 4.500 2

4.500 4.250 3.800 2.600 1 Rods ( 1) --

2.000 wt! U 235 2 Reds ( 5) --

3 2.600 wt! U-235 Rods ( 2) --

3.000 wtt U 235 4 Rods ( 6) --

5 3.200 wtt U-235 Rods ( 8) --

3.800 wtt U 235 6 Rods (10) --

7 4.250 wt! U 235 Rods (29) --

4.500 wtt U 235 8 Rods (11) --

3.800 wt! U 235 + 5.50 wtt GdA i

Phpure4.4 Quod Chies Urdt 2 Cycle 15 SPCAS 396L 1105.5 Enriedwnent Distinnution

[J

, e l

EMF 96177 Revision 2 Page 27 Cantro1 RodCorner n( )1 2 3 4 5 t 5 4 4 2 2.000 2.600 3.000 3.200 3.800 r 3.800 3.200 3.200 2.600 y 2 8 6 7 8 6 6 8 5 2.600 3.800 4.250 4.500 3.800 4.250 4.250 3.800 3.800 R

o 3 6 7 7 7 7 7 d 3.000 7 6 4.250 4.500 4.500 4.500 4.500 4.500 4.500 4.250 C

4 7 7 3 8 7 3.200 4.500 4.500 7 3.300 4.500

] 4.500 Internal' i 5 8 7 3.800 Water ' 7 8 7 3.800 4.500 4.500 3.800 4.500 Channel 5 6 7. .

3.800 7 7 7 4.250 4.500 4.500 4.500 4.500 4 6 7 8 7 7 5 7 3.200 4.250 4.500 6 3.800 4.500 4.500 3.800 4.500 4.250 4 8 7 7 8 7 7 8 3.200 3.800 4.500 4.500 5 3.800 4.500 4.500 3.800 3.800 2 5 6 7 7 7 6 2.600 3.800 4.250 5 2 4.500 4.500 4.500 4.250 3.800 2.600 1 Rods ( 1) --

2.000 wtt U 235 2 Rods ( 5) --

2.600 wt% U-235 3 Rods ( 2) --

4 3.000 wt% U-235 Rods ( 6) --

3.200 wt! U-235 5 Rods ( 9) --

6 3.800 wt* U-235 Rods (10) --

4.250 wt% U-235 7 Rods (29) -

8 4.500 wt% U-235 Rods (10) --

3.800 wt! U-235 + 6.50 wttGd/h Figure 4.5 g CWad Chies Urdt 2 Cycle 15

() SPCAS 396L 1006.5 Enrichment Distribution

EMF 96177 Revision 2  !

Page 28 I SPCAG.3728110ZH ADV SPCA9 358811GZL ADV f (OCB 1 Type H) (OCB 1 Type L)

Natural Uranium Blanket Natural Uranium Blanket SPCA9 396L 1106.5 SPCAS 396L 11G5.5  !

1 SPCA9 396L 11G7.5 SPCA9 396L 1106.5 i

O SPCA9-423L 1107.5 SPCA9 396L 10G6.5

)

Natural Uranium Blanket Natural Uranium Blanket i

J Fi9ure 4.s I l

l O Quad Chios Unit 2 Reload Batch QCB 1 Axial Fuel Ar:. Mi Designe j l

L i

~ .. . -.. .-

EMF 96177 R; vision 2 P ge 29 17 3 16 15 16 3 15 16 16 3 16 2 16 18 17 3 16 3 16 3 2 3 2 3 2 3 3 4 18 18 16 3 16 3 2 3 16 3 16 3 2 4 17 17 12 15 16 3 16 15 1 3 17 16 3 4 16 2 18 12 16 3 2 15 17 3 2 15 1 4 2 2 18 18 14 3 2 3 1 3 16 3 2 3 2 4 4 18 14 15 3 16 3 2 3 2 3 16 4 2 18 14 16 2 3 17 15 2 3 17 2 4 17 17 12 16 3 16 16 1 3 16 2 17 2 18 17 14 ,

3 2 3 3 4 2 4 4 2 2 18 14 16 3 2 4 2 4 2 17 18 18 14 2 3 4 16 2 4 18 17 17 14 16 4 17 2 18 18 14 12 14 18 18 17 18 18 14 17 18 12 12 14 Number of .

Cycle Fuel Type Assemblies Bundle Description Loaded 1 16 GE10-P8HXB312 7GZ 100M 145 CECO 14 2 128 GE10 P8HXB316 8GZ2100M 145 CECO 14 3 152 SPCAS 372811GZH ADV 15 4 64 SPCA9 358B-11GZL ADV 15 12 24 GE9B-P8DWB29911GZ 80M 145 T 11 14 44 GE98-P8DWB310 9GZ 80M 145-T 11 15 32 GE98 P8DWB310 7G3.0 80M 145 CECO 13 16 112 GE99-P8DWB30810GZ-80M 145-CECO 13 17 72 GE9B P80WB286 9GZ-80M 145-T 12 18 80 GE9B P8DW8286 7G3.0 80M 145 T 12 Route 4.7 Quad Cities Urdt 2 Cycle 15 s

Reference Leading Map (Quarter Core Symmetric Lo ding)

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

EMF 96177 R: vision 2 Pcge 30 2.6 ..

E9 WCPR(f) Umit -

' 2.4 GE10 WCPR(f) Um!t ,"

- ATRLM-98 Offset .

' ' ' WCPR(f) Umit -

+ GE9 Reeds

.~

a -

x GE10 Reeds I

- + ATRUW-98 Offset -

Reeds '

E *" : ~

~

M  : * .

a IA -  :

+

I 1A _

e cr; et n

t.  : - -

g .

1.2 -

O  :

. N:

io .............. ...... . . .....

0 20 40 60 80 100 120 Total Core Flow (% Roted) l Roure 5.1

]

Reduced Row MCPR Lindt for l

4 Manuel Row Control (SLMCPR = 1.10) 0 .

,.--,c.- .,-- ,,, ,--,,.., ,,.--,, ,n....,--- ,n, - . , , . , , - . , , - , - . , - - - . - ., - . - . . ,

EMF 96177 R; vision 2 Page 31 0 . i 44 . . . . . . . . . , . . . , ,. . , , . . . . , . . .

~ -

i 3,3 c 3 GE9 OUCPR = 1.57 .

c 3 GE10 OUCPR = 1.52 .

3.s 2 ATed'4-98 Offset -

CUCPR = 1.47 .

3.4 - .

. 3.2 - -

3.0 - . -

2a - -

g -

{ 2.s .

7 2.4 .

2.2 - .

g .

2.0 - -

1A -

1.s - -

1.4 . . . . i . . . .i....e . . . . i . . . . i . . .'

O 20 40 to 80 100 120 Total Core Flow (% of Roted) l Figure 5 2 l Reduced Row MCPR Undt for l A*. stomatic Flow Control O

G

EMF 96177 Revisl6n 2 Pcge 32 L

O .

44 . . , , , , .

y c 3 GE9 OLWCPR = 1.61 [

c 3 GE10 OLMCPR = 1.56 .

M - - - ATRUW-98 Offset .

OLMCPR = 1.51 .

, 1.4

. n - -

s.o .

u . -

g . .

S" .

' ~

] 2.4 -

2.2 -

g 2.0 -

O 1.8 1.6 i.4 . . . . . . . . ...... .............

0 20 40 00 80 100 120 Total Core Flow (% of Roted) l Route 5.3 l Reduced Flow MCPR Urrdt for l Automatic Row Control l (EOD/EOOS OLMCPR)

O

__.. _ ,.___.____,,___ _ __, _ _, EMF 96177 Revisi6n 2 Page 33

~

O 22 20- (0.# 4) (#'# 4) w-w-

w-u-

(ettn2) w-s-

s-O 4-2-

0 5 N S N N N N N N N N N N M Average Planor Exposure, GW4MTU Figure 7.1 Protection Against Power Trenenent LHOR Umh for ATRIUM 95 Offset Fuel 4

O I

.j__________

R;visi6n 2 ,

i t

s Quod Chios Urdt 2 Cyo6e 15 Reloed Anahens j 1

I ,i Distribution 4

'1 O. C. Brown, 34  :

D. G. Carr, 34 M. E. Garrett, 34 J. G. Ingham, 36 D. M. Knee, 34

~

J. L. Maryott, 34 J. H. Riddle, 31 (8 custon er copies)

R. R. Schnepp, 34 4 P. E. Smith, 34 J. A. White, 31 A. W. Will, 34 4

Document Control (2) 4 b

4

(- .

\

- -- - - - - 4 y , _ ,..-.-, , - , , , , ._ , . _ . . . - . . . _ _ , , _ . , _ , . _ , , , ,. , _ _ , _ , . _ , . _ _ , , . , . , . . , . , , _ ,

l 0 l COLR ATTACHMENT 2 t

'Q2C15 PLANT TRANSIENT ANALYSIS, EMF-96-180(P) REV.1, Q NDIT970068 t

B 4

0

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

I i

NUCLEAR PUEL 5FJtVICES DEPARTMENT [

NUCLEAR DE580N INMNtM ATION TRAN5MITTAL 5 m RE AN Onsinniing Organisation M No. M "

D NON SAfWTY RELATED D Nacicar FeelServues nev. No. O O RSOULATORY RELATED 3 Ostwrespecify) $PC PageiofI i

Seamen Quad Canes Unit 2 Cycle 19 Omnene no -

To: J. M. Pisket ,

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Sehpset M Comme Umt 2 Cvcir 15 Man Tranuent Anniva FMF.EltorP) Rev 1 mis Mov. - - . v2w p,,,,,,, p[cp.4_E : - - ) pas, John M Psussaan .

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O Unwnried O Easiasenns Judsen ni Meehad and Schaeole of VenAcassen for Unvenfed NDITs:

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