ML20198K270

Rev 1 to RBS Cycle 8 Colr

ML20198K270
Person / Time
Site:	River Bend
Issue date:	12/22/1998
From:	Law W ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20198K229	List: ML20198K270 RBG-44795, Forwards Results of GE Reanalysis Rept & Validation of Cycle 8.Mid-cycle Rev 1 to RBS COLR for Cycle 8,which Was Revised According to Results of Reanalysis Is Encl
References
NUDOCS 9812300393
Download: ML20198K270 (4)

Text

l#aga 1 of/ 27 RBS CYCLE 8 COLR Revision 1 RIVER BEND STATION, CYCLE 8 CORE OPERATING LIMITS REPORT (COLR)-

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FREPARED BY: Mm Mu Date: /.2/4/p>

Responsible Engineer i

i REVIEWED BY: W Date: /2/2/(([

l ReGiew Engineer APPROVED BY: [o4 -

Date: al SM[

i Manager - Safety & Engineering l Analysis APPROVED BY: <> -

Date: /2 2/ ((

Director, Engineering River Bend Nuclear Station APPROVED BY: Date: IL!22hf FaciliGes Review Committh  ;

River Bend Nuclear Station )

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9812300393 981223 PDR ADOCK 05000458i> l P PDR y -

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Pagt 2 of 27 RBS CYCLE O COLR Revision 1  ;

j INTRODUCTION AND

SUMMARY

This report provides the values of the AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) limits, the LINEAR HEAT GENERATION -

RATE (LHGR) limits, and the MINIMUM CRITICAL POWER RATIO

.(MCPR) limits for the Cycle 8 core. These limits are given as a function of

thermal power, core flow, and exposure. Also provided is the REACTOR j l PROTECTION SYSTEM (RPS) response time for APRM thermal time  ;

constant for River Bend Station for Cycle 8. Technical Specification i section 5.6.5 requires these values be determined using NRC-approved l methodology and are established such that all applicable limits of the plant safety analysis are met. l i

! In some cases limits in the COLR differ from the limits in the core i monitoring system. This is sometimes due to limitations in the core monitonng system to model the actual limits, in which case the core monitonng limits may be more conservative than the COLR limit. In other j cases the limits in the COLR are presented in less detail than in the core l

monitonng system. When these situations exist the core monitoring limits

. will explained or be referenced by the COLR and will be made available to

[

Operations.

, Control Rods The River Bend core utilizes both GE original equipment and ABB CR-

! 82M bottom entry cruciform control rods. These Control Rod designs are j discussed in more detailin reference 7.

l Revision History 4

l Figure 16 is changed in revision 1 to reflect the updated Operating Limit MCPR. As a result, the OLMCPR limits depicted in Figure 16 are identical

to that depicted in Figure 15.

l Reference 3(b) is added to page 7. Reference 5 is deletM l

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Page 7 of 27

, RBS CVCLE G COLR Remsion 1 REFERENCES

1) NEDE 24011-P-A-13 and US Supplement," General Electric Standard  :

Application for Reactor Fuel," August 1993.

2) Letter, J S. Charnley (GE) to M.W. Hodges (NRC), Recommended MAPLHGR Technical Specifications for Multiple Lattice Fuel Designs, March 9,1987

3) (a) J1103150SRLR Rev. O, " Supplemental Reload Licensing Report for River Bend Station Reload 7 Cycle 8," July 1997. (b) GE Letter to EOi, GFP 1243," River Bend Cycle 8 OLMCPR Recalculation and Licensing Evaluation," Dated December 17,1998.  ;

4) J1103150 MAPL, Revision 0 ' Lattice Dependent MAPLHGR Report for River Bend Station Reload 7 Cycle 8" July 1997. 1 1

5) Not Used. l

6) Letter, R.E. Kingston to G. W. Scronce, " Time Constant Values for Simulated Thermal Power Monitor" GFP-1032 November 30,1995.

7) RBS USAR Section 4.1 t

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Pags 23 of 27 RBS CYCLE D COLR Rsvision 1 i

i FIGURE 16 OPERATING LIMIT MCPR (MCPRp) i VERSUS CORE FLOW FOR EXPOSURES

$ GREATER THAN EOC-1820 mwd /ST*

3 i 1 800 3 _. . _ _ . _ . . _ _ _ . _ _ . _ _ . . , . _. ._ . _ .

g . -. . . _ . ...

j . . _ .._ . ..

1 1 600 L

i

- ^- - ~' ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

i 1 48

! 1 500 -

) i i 1 43 _- , ;

j .

. L -

] E \ 1 38 .

1 1 400 j

U 2 ) $ 34 i

4

-' ~ ~

.. 1.30' '

t300 . _ _

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._ _ . . . _ _ .- 1.29 l

1 100 ,

_ _ _ _ _ ~ __ ---

_y-. . _. . ._. .__ ____._. . _ . . _ . ._ _ _ _ _ _ _ . _ _ _

20 30 40 50 60 70 80 90 100 110 120 CORE FLOW (W), % OF RATED CORF, FLOW These values must be increased by 0.01 dunng single loop operation.

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