ML20081D920
| ML20081D920 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/28/1995 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20081D912 | List: |
| References | |
| NUDOCS 9503210070 | |
| Download: ML20081D920 (20) | |
Text
.
i i
h EDWIN I. HATCH NUCLEAR PLANT UNIT 2 i
CORE OPERATING LIMITS REPORT for FUEL CYCLE 12 D
Revision 1 February 1995 0
!8n88=8888a.
i l
Interoffice Correspondence Georgia Power d 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, as referred to in the Specifications. Normally, the shift technical advisor or reactor engineer will use this report. Where necessary, the fuel limits from the COLR are included in 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Please discard Revision 0 of the COLR for Hatch 2 Cycle 12, which was issued in April 1994, since it is no longer applicable.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 l
e D
EDWIN I. IIATCII NUCLEAR PLANT 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
m
__________.__._m_._--_--__---
a e
EDWIN I. HATCH NUCLEAR PLANT g
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 Core Operating Limits Report
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February 1995 I
Plant flatch Unit 2 Fuel Cycle 12 Core Operating Limits Report 1.0 l
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FIGURE 3-2 MAPFACp Revision 1 4
February 1995
Plant flatch Unit 2 Fuel Cycle 12 Core Operating Limits Report I
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D Revision 1 5
February 1995 h
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Revision 1 6
February 1995
O Plant Hatch Unit 2 Fuel Cycle 12 Core Operating Limits Report l
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Revision 1 8
February 1995
Plant Hatch Unit 2 Fuel Cycle 12 l
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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 K given in Figure 4-1, multiplied by the D
appropriate limit shown in Figure 4-3. The scram time p
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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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%
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1.2 POR We (% RATED CORE FLOW)* 40%
MCPR(F)=( Af Wel100 + 8f )*[140032(40.We))
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 g
GE11 l
1.27 l
1.26 f
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1.25
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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
_--