ML20073L688

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Rev 10 to SA-CA-0003-M, River Bend Station,Cycle 6 Colr
ML20073L688
Person / Time
Site: River Bend Entergy icon.png
Issue date: 10/05/1994
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20073L683 List:
References
SA-CA-94-0003-M, SA-CA-94-0003-M-R01, SA-CA-94-3-M, SA-CA-94-3-M-R1, NUDOCS 9410130242
Download: ML20073L688 (19)


Text

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SA-CA-94-0003-M Page 1 of 19 RBS CYCLE 6 COLR Rev. 1 RIVER BEND STATION, CYCLE 6 CORE OPERATING LIMITS REPORT (COLR)

October 1994

$ /WU AYU2S34-PREPARED By: &' W #oV4 7/S Date: - k/_7 8 9

Br. Nuclear Safety Engineer REVIEWED BY: _

ICM03dN Date: O y r.NuclegSafetyEngineer APPROVED BY: )f/&

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/ /_I// t A RW C77($ Date: /0[3/ 77h f

' Manager - Safety & Engineering Analysis

, APPROVED BY: Nb Date: _{ Df 9 flN Director, En@ineering River Bend Nuclear Station APPROVED BY:DNhh  %% C/TG Date: /O 9 '/

Facilities Review Committee River Bend Nuclear Station 9410130242 941007 PDR ADOCK 050004S9 P PDR

SA-CA-94-0003-M Page 2 of 19 RBS CYCLE 6 COLR Rev. 1 LIST OF EFFECTIVE PAGES

> Page(s) Revision 1-19 1 i

SUMMARY

OF CHANGES FOR REVISION 1 The COLR was revised to account for the change in-the core as loaded configuration made in mid-cycle 6 to replace a leaking fuel bundle. Except for the revision number on each page the-only pages effected by this revision are 1, 2, 4, 8 and 19. No core operating limits have changed.

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SA-CA-94-0003-M Page 3 of 19 RBS CYCLE 6 COLR Rev. 1 INTRODUCTION AND

SUMMARY

This report provides the values of the AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) limits, the core flow dependent MINIMUM CRITICAL POWER RATIO (MCPR) limits, MCPRf ,

the thermal power dependent MCPR limits MCPR , the LINEAR HEAT GENERATION RATE (LHGR) limits, andthekEACTOR PROTECTION SYSTEM (RPS) response time for APRM thermal time constant for River Bend Station, Cycle 6 as required by Technical Specification 6.9.3.1. Per Technical Specifications 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 safety analysis are met.

SA-CA-94-0003-M i Page 4 of 19 l RBS CYCLE 6 COLR Rev. 1 1

TECHNICAL SPECIFICATION 3.2.1 i 1

I FOWER DISTRIBUTION LIMITS l

I AVERAGE PLANAR LINEAR HEAT GENERATION RATE The limiting APLHGR value for the most limiting lattice 1 (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 and 8. These values were determined with the SAFE /REFLOOD LOCA methodology described in GESTAR-II (Reference 1). Core location by fuel type is provided in Figure 11, which is modified from the final core loading pattern in revision zero of this report per reference 3.

This is verified as the as loaded core configuration per 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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SA-CA-94-0003-M Page 5 of 19 RBS CYCLE 6 COLR Rev. 1 TECHNICAL SPECIFICATION 3.2.3 POWER DISTRIBUTION LIMITS MINIMUM CRITT_ CAL POWERJ'.ATIO The MCPR limits for use in Technical Specification 3.2.3 for MCPRf and MCPRo are showa in Figures 9 and 10. These values were determinea wi'h the GEMINI methodology and GEXL-PLUS critical power ratio correlation described in GESTAR-II (Reference 1) and are consistent with a Safety Limit MCPR of 1.07.

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'[ . SA-CA-94-0003-M Page 6 of 19 RBS CYCLE 6 COLR Rev. 1 TECHNICAL SPECIFICATION 3.2.4 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 types. The GE8x8EB fuel consists of fuel types GE8B-P8SQB322-8GZ-120M-4WR-150-T, GE8B-P8SQB322-9GZ-120M-4WR-150-T, GE8B-P8SQB333-10GZ-120M-4WR-150-T, GE8B-P8SQB331-11GZ-120M-4WR-150-T, GE8B-P8SQB334-10GZ-120M-4WR-150-T, GE8B-P8SQB334-10GZ2-120M-4WR-150-T and GE8B-P8SQB334-11GZ-120M-4WR-150-T. Core location by fuel type is provided in Figure 11.

The higher limit for GE8X8EB fuel is proprietary to GE and does not appear in Reference 1. The NRC SER on-the GE8B 4 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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, SA-CA-94-0003-M Page 7 of 19 RBS CYCLE 6 COLR Rev. 1 LECHNICAL SPECIFICATION TABLES 3.3.1-2 and 4.3.1.1-1 ,

The simulated thermal power time constant for use in Technical Specification Table.3.3.1-2, Footnote ** is:

6 0.6 seconds.

The maximum simulated thermal power time constant for use in Technical Specification surveillance Table 4.3.1.1-1 is:

6.6 seconds i

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SA-CA-94-0003-M Page 8 of 19 RBS CYCLE 6 COLR Rev. 1 REFERENCES

1) NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel," (latest approved version).
2) Letter, C.O. Thomas to J.S. Charnley, " Acceptance for Referencing of Licensing Topical Report," NEDE-24011-P-A-6, Amendment 10, General Electric Standard Application for Reload Fuel, May 28, 1985.
3) Letter, Charles J. Paone to Gary Scronce, " River Bend Verified Full Core Loading for Identified Leaker Replacemerit , " GFP-9 2 8, File No: G25.4.3, September 27, 1994.
4) " Single-Loop Operation Analysis for River Bend Station, Unit 1," NEDO-31441, May 1987.
5) Letter, Scott Young to Gary Scronce, " Cycle 6 Mid-Cycle Core Shuffle Core Verification Completion," RXE 94-091, September 29, 1994.

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.' SA-CA-94-0003-M Page 9 of 19 RBS CYCLE 6 COLR Rev.1

, FIGURE 1. MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)VERSUS AVERAGE PLANAR EXPOSURE BP8 SRB 299 y  ;; ,

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Rev.1 FIGURE 2. MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)VERSUS AVERAGE PLANAR ,

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Rev.1 FIGURE 8. MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE GE8B P8SQB33411GZ 120 M 4WR 150 T

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SA-CA-94-0003-M Pcge 17 of 19 RBS CYCLE 6 COLR Rev.1 FIGURE 9. MCPR f

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, SA-CA-94-0003-M Page 19 of 19 RBS CYCLE 6 COLR Rev. 1 56 ~~EEEEEEEE

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