ML20081D920

Rev 1 to Ei Hatch Nuclear Plant Unit 2 COLR for Fuel Cycle 12

ML20081D920
Person / Time
Site:	Hatch
Issue date:	02/28/1995
From:	GEORGIA POWER CO.
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ML20081D912	List: HL-4807, Forwards Rev 1 to Ei Hatch Nuclear Plant Unit 2 COLR for Fuel Cycle 12 ML20081D920
References
NUDOCS 9503210070
Download: ML20081D920 (20)

Text

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EDWIN I. HATCH NUCLEAR PLANT UNIT 2 i CORE OPERATING LIMITS REPORT for FUEL CYCLE 12 D

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l Revision 1 February 1995 0

!8n88=8888a.

PDR

i Interoffice Correspondence Georgia Power d l

i DATE: February 21,1995 i

RE: Hatch Project Support - Licensing Core Operating Limits Report for Hatch 2 Cycle 12 Revision 1 File: Fuel Cycle Technical Log: HL-4793 FROM: D. M. Crowe TO: ALL UNIT 2 TECHNICAL SPECIFICATIONS MANUAL HOLDERS By amendment 106 to the Unit 2 Technical Specifications, the NRC wthorized relocation of certain fuel-related limits from the Technical Specificatiot :o the adjunct Core Operating Limits Report (COLR). This letter transmits to all Unit 2 Technical SpecificaQns manual holders a copy ofRevision 1 l of the COLR for Hatch 2 Cycle 12. This document should be utilized in conjunction with the Unit 2 D Technical Specifications, reactor engineer will use this report. as Where referred necessary, to in the Specifications.

the fuel Normally, limits from the COLR the inshift technical advisor or are included 1 plant procedures.

Please discard Revision 0 of the COLR for Hatch 2 Cycle 12, which was issued in April 1994, since it is no longer applicable. If you have questions regarding Revision 1 of the Unit 2 COLR for Cycle 12, please contact me at extension 8-821-7248 or telephone number (205) 877-7248.

RDB/eb Enclosure cc: NORMS ]

I d

GEORGIA POWER COMPANY EDWIN I. IIATCII NUCLEAR PLANT UNIT 2 FUEL CYCLE 12 -

CORE OPERATING LIMITS REPORT REVISION 1 l

V

(/

r South:rn Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201 9

i e . l EDWIN I. IIATCII NUCLEAR PLANT D UNIT 2 FUEL CYCLE 12 CORE OPERATING LIMITS REPORT TABLE OF CONTENTS l Section Title Pace l

1.0 Introduction 1 2.0 Rod Block Monitor 1 l 3.0 APLHGR Limit 2 l

4.0 MCPR Limit 11 i 4.1 Two Recu culation Loop Operation 11 4.2 Single Recirculation Loop Operation 11 5.0 LHGR Limit 15 6.0 References 15 4

Revision 1 i February 1995

TABLE OF CONTENTS (Continued)

LIST OF FIGURES Figure No. Title Pane 3-1 MAPFACr 3 3-2 MAPFACp 4 3-3 APLHGR Versus Average Planar Exposure (GE7B-P8DRB284-7G4.0-80M-150-T) 5 3-4 APLHGR Versus Average Planar Exposure (GE8B-P8DQB296-7GZ-80M-150-T) 6 3-5 APLHGR Versus Average Planar Exposure (G E9B-P8 D WB 314-7G4.0-80M- 150-T-NOS HIP) 7 3-6 APLHGR Versus Average Planar Exposure (GE9B-P8DWB314-8G4.0-80M-150-T) 8 3-7 APLHGR Versus Average Planar Exposure ',

(G E l 1 -P9 H UB 293-7GS.0/l G4.0- 100M- 146-T-LUA) 9 ,

3-8 APLHGR Versus Average Planar Exposure (GE9B-P8DWB314-8G4.0A-80M-150-T) 10 4-1 Power-Dependent MCPR Multiplier (Kp) 12 ,

4-2 Flow-Dependent MCPR Limits (MCPRr) 13 4-3 MCPR Limit as Function of Average Scram Time 14 D . .

Revision 1 ii February 1995 i

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a e .

g EDWIN I. HATCH NUCLEAR PLANT UNIT 2 FUEL CYCLE 12 CORE OPERATING LIMITS REPORT

1.0 INTRODUCTION

The Core Operating Limits Report (COLR) for Plant Hatch Unit 2 Cycle 12 is prepared in accordance with the requirements of Technical Specification 6.9.1.11. The core operating limits presented herein were developed using NRC-approved methods (References 1 and 2). Results from the reload analyses for the General Electric (GE) fuel in Unit 2 Cycle 12 are documented in References 3 and 4.

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

a. Control Rod Program Controls - Technical Specification 3/4.1.4.3.

b. Average Planar Linear Heat Generation Rate (APLHGR) -

Technical Specification 3/4.2.1.

c. Minimum Critical Power Ratio (MCPR) - Technical Specification 3/4.2.3

d. Linear llent Generation Rate (LHGR) - Technical Specification 3/4.2.4.

2.0 ROD BLOCK MONITOR (Technical Specification 3/4.1.4.3)

Both Rod Block Monitor (RBM) channels 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 < l.70.

or

b. THERMAL POWER is 2 90% of RATED THERMAL POWER and the MCPR is < l.40.

Revision 1 1 February 1995

Plant Ilatch Unit 2 Fuel Cycle 12 Core Operating Limits Report 3.0 APLIIGR LIMIT (Technical Specification 3/4.2.1)

The APLHGR limit is given by the applicable rated-power, rated-flow limit taken from Figures 3-3 through 3-8, 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 through 3-8, the APLHGR limit shall be applied to each axial location in the fuel assembly. _

As required by GESTAR Amendment 19, the hand-calculated APLHGR values, l for a multi-lattice (i.e., GE8-296 and gel 1-LUA) fuel must be less than or j equal to the APLHGR limits shown in Figures 3-4 and 3-7, respectively. When l APLHGR values are determined by the process computer, the lattice-dependent h APLHGR limits are used. Under these conditions, some axial locations may have APLHGR values exceeding the values shown in Figures 3-4 and 3-7.

Revision 1 2 February 1995

____ _ _ _ _ _ _ _ -_______m__.__ _.-..__ ___

Plant flatch Unit 2 Fuel Cycle 12

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Plant flatch Unit 2 Fuel Cycle 12 Core Operating Limits Report 1.0 ,

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>= l (SLO TLO) 2 i MAPFAC p = 0.585

• 0.005224 (P . 30%)

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52 20 25 30 40 60 80 70 80 90 1 00 POWER (% rated)

FIGURE 3-2 MAPFACp Revision 1 4 February 1995

Plant flatch Unit 2 Fuel Cycle 12 Core Operating Limits Report -

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D Revision 1 5 February 1995 h _ ________.__.._m

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Revision 1 6 February 1995

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! Revision 1 7 February 1995

Plant Ilatch Unit 2' Fuel Cycle 12 Core Operating Limits Report I

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Revision 1 8 February 1995

Plant Hatch Unit 2 Fuel Cycle 12 l Core Operating Limits Report

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D Revision 1 9 February 1995 e

Plant Hatch Unit 2Tuel Cycle 12 l Core Operating Limits Report l

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Revision i 10 February 1995 v ----mm__-_-____-.__..___.__.-_m-____m___ _ _ _ _ _ _ _ _ _ _ _ _

t Plant flatch Unit 2 Fuel Cycle 12 Core Operating Limits Report 4.0 MCPR LIMIT (Technical Specification 3/4.2.3)

The MCPR operating limit (OLMCPR) is a' function of fuel design, average .

scram time, core flow, number of operating recirculation loops, and core power. -

Note that in Figure 4-3, the rated-power and rated-flow OLMCPR is fuel-type dependent; e.g., the Option B limits are 1.22 for GE7B, GE8B, and GE9B fuels, and 1.25 for Gell fuel. l 4.1 Two Recirculation Loon Operation For 25% s power < 30%, the OLMCPR is given in Figure 4-1. For power 2: 30%, the OLMCPR is the greater of either:

tn

a. The applicable limit determined from Figure 4-2 or

b. The appropriate Kp given in Figure 4-1, multiplied by the D appropriate limit shown in Figure 4-3. The scram time dependence is given in the Bases for Technical Specification 3/4.2.3.

4.2 Sinele Recirculation Loon Operation For single-loop operation, the OLMCPR shall be 0.01 greater than the two-loop value which is determined as specified in section 4.1.

Revision 1 11 February 1995

Plant Hatch Unit 2' Fuel Cycle 12 Core Operating Limits Report 2.8

> $0% FLOW - r 2.8 --

i OPERATNG LNIT MCPR(P) e Mp

• OPERATINO LMIT MCPR(100)

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l FOR P e 25%: NO THEfWilAL LNitS MONITORNQ REQUIRED 9

JA - . . ~ ~ NO LNITS SPECIPitD -

l FOR 25% s P e P emse (WMRE P emas e 30% FOR HNP = i ,2) l K, e (Kaw

• 0.02(30% . P)) # OLMCPR (100) 2.3 ,

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• 50% CORE FLOW E 2.2

• FOR 30% 5 7 4 45%:

$ N a m + 0.0134 (45%.P)

" e. FLOW 5, 50% FOR 4S% 5 P e 80%:

[ Me = 1.15

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FIGURE 4-1 POWER-DEPENDENT MCPR M ULTIPLIER (Kp)

Revision 1 12 February 1995

9 Plant IIatch Unit 2' Fuel Cycle 12 Core Operating Limits Heport l'I g i .

l POR We (% RATED CORE FLOW) a 40%

117% ucPR(r} = max (1.20, Af We l100 + 8f) 112%

107% uAx rtow Af af 102 5% st r.o a ss2 1. sos j .. 112.0 4.802 t.747 l 1.6 -- -

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11 , ... ..., , . . . .,, . .

30 40 60 60 70 80 30 100 110 120 CORE FLOW (% rated) l FIGURE 4-2 FLOW-DEPENDENT MCPR LIMITS, MCPR(F) h l

Revision i 13 February 1995

- Plant Hatch Unit 2' Fuel Cycle 12 Core Operating Limits Report 1.29 1.28

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GE96

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FIGURE 4-3 MCPR L.IMIT AS FUNCTION OF AVERAGE SCRAM TIME Revision 1 14 February 1995 I

9 Plant liatch Unit 2 Fuel Cycle 12 Core Operating Limits Report l 5.0 LIIGR LIMIT (Technical Specification 3/4.2.4)

The LHGR limit is 13.4 kW/ft for GE7B fuel. The LHGR limit for GE8B, GE98, and gel 1 fuels is 14.4 kW/ft.

6.0 REFERENCES

1

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

NEDE-24011-P-A-10-US, March 1991. r

2. Letter, L. P. Crocker (NRC) to W. G. Hairston (GPC), " Issuance of Amendment No.168 to Facility Operating License DPR-57 and Amendment No.106 to Facility Operating License NPF Edwin I.

l Hatch Nuclear Plant Units 1 and 2 (TACS 73614 and 73615)," Dece.mber 29,1989. l

3. " Supplemental Reload Licensing Submittal for Edwin I. Hatch Nuclear h Plan: Unit 2, Reload 11, Cycle 12," General Electric Document 23 A724L Revision 0. April 1994.

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

5. Edwin T. Hatch Nuclear Plant Unit 2 Technical Specifications. Bases 3/4.1.4.3, 3/4.2.1, 3/4.2.3, and 3/4.2.4.

6. Letter, C. J. Paone (GE) to K. S. Folk, (SNC), CJP:95-011, " Hatch-2 Cycle 12 MAPLHGR Limits for Extended Exposure History GE7B Fuel," January 20,1995.

l 1

1 Revision 1 15 February 1995

_ _ _ _ _______ _--