ML20062H644

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Rev 0 to River Bend Station,Cycle 4 Core Operating Limits Rept
ML20062H644
Person / Time
Site: River Bend Entergy icon.png
Issue date: 11/21/1990
From:
GULF STATES UTILITIES CO.
To:
Shared Package
ML20062H643 List:
References
NUDOCS 9012050205
Download: ML20062H644 (21)
v • d • e


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Page 1 of 21 RBS CYCLE 4 COLR Rev. 0 RIVER' BEND STATION, CYCLE 4 CORE OPERATING LIMITS REPORT (COLR)

NOVEMBER 1990

/ "* r fC h/r" 7DATE:

PREPARED BY:

du Sr.'JNucl, ar Engine REVIEWED BY:

DATE:

II/d o/90 1

f Nuclear S ty Engineer ll,/to/Tp REVIEWED BY:

DATE:

4 SupdrvTudr, Thermal / Hydraulic Analysis

. River Bend Nuclear Station k w he cm DATE: )/-lo-9D APPROVED BY:

Supervisor, Core Analys..s River Bend Nuclear Station k - 3D -) D APPROVED BY: k,,

DATE:

Di

tor, En neering Analysis l

Riv_er Bend.N clear Station APPROVED BY:

t' M.- /68d DATE:

l Manager, Engineering l

River Bend Nuclear Station DATE:

A~80-[0 APPROVED BY:.

l:

FKcil. ties Reffa4 Committee l-River Bend Nuclear Station I I.

DATE: #-U-M APPROVED BY:

Sbclec.r Review Board River Bend' Nuclear Station 9012050205 ?o12y fDR ADOCK OS00d43e PDC l

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Page 2 of 21 RDS CYCLE 4 COLR Rev. 0

_ LIST OF EFFECTIVE PAGES Page (s)

Revision 1-21 0

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i-Page 3 of 21 RDS CYCLE 4 COLR Rev. 0 INTRODUCTION AND

SUMMARY

This report provides the values of the AVERAGE PLANAR j

LINEAR llEAT GENERATION RATE (APL11GR) limits, the core flow

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dependent MINIMUM CRITICAL POWER RATIO (MCPR) limits, MCPR,

f

.'the thermal power dependent MCPR limits MCPR, the LINEAR llEAT GENERATION RATE (LilGR) limits, and the' REACTOR PROTEC-h i

TION SYSTEM'(RPS). response time for APRM t ermal t me r

Lconstant for River Bend-Station, Cycle 4 as required by Technical ~ Specification 6.9.3.1.

Per Technical Specifica-tione 6.9.3.2 and-6.9.3.3, these values have been determined using NRC-approved methodology and are established such that all applicable limits of the plant nafety analysis are met.

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TECHNICAL SPECIFICATION 3.2.1 POWER DISTRIBUTION LIMITS

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, AVERAGE PLANAR LINEAR 11 EAT GENERATION RATE I

The limiting APL11GR value for the most limiting lattice (excluding natural uranium) of each fuel type as a function of AVERAGE-PLANAR EXPOSURE is given in Figures 1, 2,

3, 4, 5, 6, 7, 8, 9 and 10.

These values wore determined with the

' SAFE /REFLOOD LOCA methodology described in GESTAR-II (Reference 1).

Core location by fuel 6.ype is provided in

' Figure 13, which is a modification of the-reference core

-loading pattern-in-Reference 3 to reflect the as loaded core configuration described in Reference 5.

These figures are-used if alternate calculations are required.

The limits of these figures shall be reduced to a value of 0.84 times the two recirculation' loop operation limit when.in-single loop

, operation (Reference 4).-

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l RBS CYCLE 4 COLR Rev. 0 s

'r' TBCHNICAL SPECIFICATION 3.2.3 l

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POWER DISTRIBUTION LIMITS s - -

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- The MCPR limits for use in Technical Specification 3.2.3 for MCPR arc shown an Figures 11 and 12..These valuesw$r.andMCPRe determEnod with the GEMINI methodology and b

GEXL-PLUS? critical power ratio correlation described in GESTAR-IIT(Reference 1) and are concistent with a Safety J

Limit MCPR.of 1.07.

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RBS CYCLE 4 COLR Rev. 0 TECHNICAL SPECIFICATION 3.2.4 t

POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE The LHGR limits for use in Technical Specification 3.2.4 are'14.4.kw/ft for GE8x8EB fuel and 13.4~kW/ft for all other-fuel.

The GE8x8EB fuel consists of fuel types BS322B, DS322C, GE8B-P8 SOB 333-10GZ-120M-4WR-150-T and GE8B-P8SQB331 -

11GZ-120M-4WR-150-T.

Core location by fuel type is provided in Figure 13.

The higherElimit for GE8X8EB fucl is= proprietary to GE, and does not appear-in Reference 1.

The NRC SER on the GE8B' 6

design -(Reference 2) recognizes the change to the LHGR limit, and the proprietary value is found in References 18.and 19 of Reference.2.

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RBS CYCLE 4 COLR Rev. 0 t.-

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. TECHNICAL SPECIFICATION TABLES 3.3.1-2 and 4.3.1.1-1 1

1 The simulated thermal power time constant for use in C

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' REFERENCES L-1)-

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

2)

Letter, C.0; Thomas tx) J.S. Charnley, " Acceptance for-Referencing of Licensing Topical Report,"

NEDE-24011-P-A-6, Amendmcnt 10, General Electric Standard Application,for Reload Fuel, May 28, 1985.

3);

' Document 23A6503, Revision 0,

" Supplemental Reload Licensing Submittal for River Bend Station Reload 3, Cycle 4,'" May 1990.

ll)

" Single-Loop Operation Analysis for River Bend Station, Unit 1,"'NEDO-31441, May 1987.

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Letter, GSU to.GE, "OPL-7 Data for River. Bend / Reload 3,"

RBG-33996, November 13, 1990.

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