ML20024H651

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Rev 0 to Ei Hatch Nuclear Plant Unit 2 Core Operating Limits Rept for Operating Cycle 10.
ML20024H651
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Site: Hatch Southern Nuclear icon.png
Issue date: 05/01/1991
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GEORGIA POWER CO.
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References
NUDOCS 9106070256
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Text

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I l Edwin I. Hatch g Nuclear Plant - Unit 2 I

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I I CORE OPERATING LIMITS REPORT for I Operating Cycle 10 I

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Interoffice Correspondence GeorgiaPower A I

I DATE: May la, 1991 RE: Core Operating Limits Report for .

Hatch 2 Cycle 10 File: Fuel Cycle Tecnnical I Log: HL-1637 FROM: S.J.Bethayah  %

T0: All Unit 2 Technical Speci cations Holders By Amendment 106 to the Unit 2 Technical Specifications (TS), the NRC authorized relocation of certain fuel-related limits from the Technical Specifications to the adjunct Core Operating Limits Report (COLR). This I letter transmits to all Unit 2 Technical Specifications holders a copy of Revision 0 of the Core Operating Limits Report for Hatch 2 Cycle 10. This document should be utilized in conjunction with the Unit 2 Technical ir l Specifications as referred to in the Specifications. Normally, the shift technical advisor (STA) or reactor engineer will utilize this report.

Where necessary, the fuel limits from the COLR have been included in plant l procedures.

If changes to the core operating limits contained in this report are I required,-a complete revised COLR will be issued and the appropriate procedures revised.

If there are any questions regarding this report, please contact me at I extension 8-821-7392 cr telephone number (205) 877-7392.

I RDB/cr 001621 Attachment cc: NORMS I

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lI i GEORGI; POWER COMPANY i

EDWIN 1. HATCH NUCLEAR PLANT 1

UNIT 2 FUEL CYCLE 10 CORE OPERATING LIMITS REPORT i
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^i REVISION 0 MAY 1, 1991

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I EDWIN 1. HATCH NUCLEAR PLA!iT I UNIT 2 CYCLE 10 CORE OPERATING LIMITS REPORT

1.0 INTRODUCTION

This CORE OPERATING LIMITS REPORT for Hatch Unit 2 Cycle 10 is I prepared in accordance with the requirements of Hatch Technical Specification 6.9.1.11. The core operating limits presented here were developed using NRC-approved methods (References 1 and 2).

Results from the reload analyses for the General Electric fuel in l Hatch Unit 2 Cycle 10 are documented in Reference 3.

The following cycle-specific core operating limits are included in this report:

a. Control Rod Program Controls - Rod Block Monitor (Technical Specification 3/4.1.4.3)
b. Average Planar Linear Heat Generation Rate (APLHGR) Limit (Technical Specification 3/4.2.1)
c. Minimum Critical Power Ratio (MCPR) Operating Limit (Technical Specification 4/4.2.3) l l d. Linear Heat Generation Rate (LHGR) Limit (Technical Spectfication 3/4.2.4)

I 2.0 R0D BLOCK HONITOR (TECHNICAL SPECIFICATI0F 3/4.1.4.3)

Both Rod Block Monitor (RBM) cSnnels shall be operable as specified in Technical Specification 3/4.1.4.3 and when:

a. THERMAL POWER is < 90% of RATED THERMAL POWER and the MCPR is I less than 1.70, or I

Revision 0 1 May 1, 1991

9 Unit 2 Fuel Cycle 10 Core Operating Limits Report

b. THERMAL POWER is 1 90'. of RATED THERMAL POWER and the MCPR is less than 1.40.

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3.0 APLHGR L1 HIT (TECHNICAL SPECIFICATION 3/4.2.11 The APLH"R limit is given by the applicable rated-power, rated-flow i limit taken from Figures 3-3 through 3-7, multiplied by the smaller of either:

a. The factor given by figure 3-1, or
b. The factor given by Figure 3-2.

for the fuel types whose APLHGR limits are shown in Figures 3-3 I through 3-7, the APLHGR limit shown shall be applied to each axial location in the fuel assembly.

- 4.0 NCPR LIMI* (TECHNICAL SPECIFICATION 3/4.2.31 The MCPR operating limit (0LMCPR) is a function of fuel design, average scram time, core flow, number of operating recirculation loops, and core power. Note the rated-power and rated-flow OLMCPR I is fuel-type dependent in Figure 4-3. For example, option B limits

! are 1.25, 1.27, and 1.31 for GE7 BP80RB284H, BP8DRB299, BP80RB30lL; GE9 BP80WB314; and Gell P9 HUB 293 fuel, respectively. The ANF lead assemblies will be monitored as GE7 BP80RB284H bundles.

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I Pevision 0 2 May 1, 1991 1I

I Unit 2 Fuel Cycle 10 Core Operating Limits Report

' Iwo Recirculation LooD Operation 4.1 for 25% < Power < 30%, the OLMCPR is given in Figure 4

4. For Power 2 30%, the OLMCPR is the greater of either:
a. The applicaole limit determined from Figure 4-2, or I b. The appropriate Kp given by figure 41, mt;ltiplied by the appropriate limit from Figure 4-3, where the scram time I dependence is given in the Bases for Technical Specification l 3/4.2.3.

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4.2 Sinale Recirculation looD ODeration For single-loop operation, the MCPR operating limit shall be 0.01 greater than the two-loop value which is determined as specified in lg Section 4.1.

iB-5.0 LUGR LIMIT (TECHNICAL SPECIFICATION 3/4.2.41 The LHGR limit shall be 13.4 kW/ft for all GE7 8x8 fuel (BP8DRB284H,

! BP8DRB299, and BP8DRB30ll) and 14.4 kW/f t for GE9 (BP80WB314) and Gell (P9HVB293) fuel. The ANF lead assemblies will be monitored as GE7 BP8DRB284H bundles.

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Revision 0 3 May 1, 1991

Unit 2 Fuel Cycle 10 Core Operating Limits Report 6.0 BEERENCES

1. " General Electric Standard Application for Reactor Fuel,"

NEDE-240ll-P A-9, September 1988.

I 2. Letter, L. P. Crocker (NRC) to J. P. O'Reilly (GPC), " Issuance of Amendment Nos. 151 and 89 to facility Operating Licenses OPR-57 and NPF Edwin 1. Hatch Nuclear Plant Units 1 and 2 (TACS 66524/66525)," January 22, 1988.

3. " Supplemental Reload Licensing Submittal for Edwin I. Hatch Nuclear Plant Unit 2, Reload 8, Cycle 9," GE Document 23A6470, Revision 0, April 1991.

I 4. "Edwin I. Hatch Nuclear Plant Units 1 and 2 SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis," NEDC-31376P, December 1986.

5. Technical Specifications Bases for Sections 3/4.1.4.3, 3/4.2.1, 3/4.2.3, and 3/4.2.4.

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000282 I

I Revision 0 4 May 1, 1991

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l HATCH 2 CYCLE 10 CORE OPERAT!"4 LIMITS REPORT REVISION 0. EFFECTIVE DATE: MAY 1, 1991

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OPERATING LIMIT MCPR(P) = Kp

  • OPERATING LIMIT MdPR(100)

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!g FOR P < 25% : NO THERMALI v4rTS MONITORING REQUIRED NO LIMITS SbECIFIED 3R 2.4- -

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o Ai 2.3 Kp = (Key,+ 0.02(30%- P)/OLMCPR(100))

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120 30 40 50 60 70 80 90 100 CORE FLOW (% rated) h 5 FIGURE 4-2 E FLOW-DEPENDENT MCPR LIMITS, MCPR(F)

I EDWIN 1. HATCH NUCLEAR PLANT UNIT 2 CYCLE 10

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BP80RB301L i 9 X 9 LFAs 1.25 l 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 TAU ll FIGURE 4-3 MCPR LIMIT AS FUNCTION OF AVERAGE SCRAM TIME REVISION O 14 MAY 1,1991

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