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Rev 0 to River Bend Station,Cycle 4 Core Operating Limits Rept
	ML20062H644
Person / Time
Site:	River Bend
Issue date:	11/21/1990
From:	; GULF STATES UTILITIES CO.
To:	;
Shared Package
ML20062H643	List: ML20062H644; ML20062H649; RBG-34085, Forwards Rev 0 to River Bend Station,Cycle 4 Core Operating Limits Rept & Rev 0 to Supplemental Reload Licensing Submittal for River Bend Station Reload 3 Cycle 4;
References
	NUDOCS 9012050205
	Download: ML20062H644 (21)
	v • d • e

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

NOVEMBER 1990 PREPARED BY: du h/r" ' / "* r fC 7DATE:

Sr .'JNucl, ar Engine ,

REVIEWED BY: 1 ,

, DATE: II/d o/90 ty Engineer f Nuclear S REVIEWED BY: % DATE: ll,/to/Tp 4 SupdrvTudr, Thermal / Hydraulic Analysis

. River Bend Nuclear Station APPROVED BY: kSupervisor, w he Core Analys..s cm DATE: )/-lo-9D River Bend Nuclear Station APPROVED BY: k,, DATE: k - 3D -) D 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 APPROVED BY: .

,. DATE: A~80-[0 '

l: FKcil . ties Reffa4 Committee l-River Bend Nuclear Station ,

APPROVED BY: I I. DATE: #-U-M Sbclec.r Review Board River Bend' Nuclear Station 9012050205 ?o12y fDR ADOCK OS00d43e PDC l

c e,

Page 2 of 21 RDS CYCLE 4 COLR Rev. 0

_ LIST OF EFFECTIVE PAGES Page (s) Revision 1-21 0

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

'the thermal power dependent MCPR limits MCPR , the LINEAR '

llEAT GENERATION RATE (LilGR) limits, and the' REACTOR PROTEC-TION SYSTEM'(RPS). response time for APRM thermal t me i 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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t Page 4 of 21 RBS CYCLE 4 COLR Rev. O i TECHNICAL SPECIFICATION 3.2.1 ,

POWER DISTRIBUTION LIMITS

~

, 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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TBCHNICAL SPECIFICATION 3.2.3 l POWER DISTRIBUTION LIMITS !

s-- r p- MINIMUM CRITICAL POWER-RATIO q

- The MCPR limits for use in Technical Specification 3.2.3 for MCPR arc shown an Figures 11 and 12. .These b valuesw$r.andMCPRe determEnod with the GEMINI methodology and 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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I Page 6 of 21 i 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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. TECHNICAL SPECIFICATION TABLES 3.3.1-2 and 4.3.1.1-1 !

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1 The simulated thermal power time constant for use in :

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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.

c. 5)' Letter, GSU to.GE, "OPL-7 Data for River. Bend / Reload 3,"

RBG-33996, November 13, 1990.

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VERSUS AVERAGE PLANAR EXPOSURE BS3228
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Page 19 of 21 RBS CYCLE 4 COLR Rev.0 1.80
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~~', Rev. 0 l~~
~~54 -EEEEEEEE i; oHMMMMMMe . oMMMMMMMMMe~~
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1 3 5 7 91113151719212325272931333537394143454749515355 FUEL TYPE r l A = BS3229' F = SP85RS278 B = B532tt, . G = SP85RB248 C = Gt88 P8508333 10GZ 12 % 4M 150 T H = BP85RB299 D = GE88 P8508331 116Z 120M 4W 150 T I = SPSSR8305 E = SPtsR8248 l Figure 13. As Loaded Core Loading Pattern
~~. . - . . . . . . . - . - . . - . . u.- - . . . .}}~~

@@ Line 2: / Line 2: @@
 | number = ML20062H644
 | issue date = 11/21/1990
-| title = Rev 0 to River Bend Station,Cycle 4 Core Operating Limits Rept.
+| title = Rev 0 to River Bend Station,Cycle 4 Core Operating Limits Rept
 | author name =
 | author affiliation = GULF STATES UTILITIES CO.

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