ML20033E300
| ML20033E300 | |
| Person / Time | |
|---|---|
| Site: | Hatch |
| Issue date: | 02/27/1990 |
| From: | Randy Baker GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20033E292 | List: |
| References | |
| NUDOCS 9003120219 | |
| Download: ML20033E300 (18) | |
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- Interoffice Core;rdence GeorgiaPower A
- I f-I DATE:
February 15, 1990 I,
-RE:
Core Operating Limits Report for Hatch 2 Cycle 9 File: Fuel Cycle Technical XREF: X7GJ13-H800 Log: HP-7
. PROM:
R. D. Baker TO:
ALL UNIT 2 TECHNICAL SPECIFICATIONS HOLDERS By Amendment 106 to-the Unit 2 Technical Specifications, the NRC has authorized relocation of certain fuel related limits out of the Technical Specifications into.an adjunct Core Operating Limits Report. This letter transmits to all Unit 2 Technical Specifications holders a copy of Revision 0
.I of the Core Operating Limits Report for Hatch 2 Cycie 9.
This document should be utilized in conjunction with Amendment 106 of the Unit 2 Technical -
Specifications, if changes to the core operating limits contained in this report are required during the operating cycle, a complete revised document will be issued at that time.
-E If there. are any nuestions regarding this report, please contact me at E
extension 8-821-7367, or telephone number (205)-877-7367.
RDB/
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S. J. Bethay NORMS l
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.l GEORGIA POWER COMPANY EDWIN I. HATCH NUCLEAR PLANT-
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UNIT 2 FUEL CYCLE 9 I
-CORE OPERATING LIMITS REPORT 1
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Prepared by:
SOUTHERN COMPANY SERVICES, INC.
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P.O. BOX 1295 L
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' FEBRUARY. 27, 1990 REVISION 0 l
LB HATCH t CYCLE 9 CORE OPERATING LIMITS REPORT l,
REVI510N 0. EFFECTIVE DATE: FEBRUARY 27, 1990 1.
INTRODUCTION This CORE OPERATING. LIMITS REPORT for Hatch Unit-2 Cycle 9 is prepared in accordance with'the requirements of Hatch Technical Specification 6.9.1.11.
g;
- The core operating limits presented here were developed using NRC-approved
.E methods (References 1 and 2). Results from the reload analyses for the General Electric fuel in Hatch Unit 2 Cycle 9 are documented in References f
3 and 4.
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 3/4.2.3) d.
Linear Heat Generation Rate (LHGR). Limit (Technical Specification-3/4.2.4) 2.
R0D 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 less
.g a
than 1.70, or _
1 I
- h' HATCH 2 CYCLE 9 CORE OPERATING LIMITS REPORT REVI5!0N 0. EFFECTIVE DATE: FEBRUARY 27, 1990 b.
THERMAL POWER is 190% of RATED THERMAL POWER and the MCPR is less than 1.40.
3.
gffit.j,lHIT (TECHNICAL $PECIFICATION 3/4.2.1) l.
The ~AR9GR limit is given by the applicable rated-power, rated-flow limit taken from Figures 3-3 through 3-7, multiplied by the smaller of either:
I a.
The factor given by Figure 3-1, or b.
The factor given by Figure 3-2.
h For the. fuel types whose APLHGR limits are shown in Figures 3-3 through-3-7, the APLHGR limit shown shall be applied to each axial location in the fuel assembly.
4.
MCPR LIMIT (TECHNICAL SPECIFICATION 3/4.2.3)
The MCPR operating limit (OLMCPR) is a function of fuel design, average I.
scram time, core flow, number of operating recirculation loops, and core
- power, 4.1 Two Recirculation LooD ODer8 tion For 25% 5 Power < 30%, the OLMCPR is given in Figure 4-1.
For Power 130%,
the OLMCPR is the greater of either:
l a.
The applicable limit determined from Figure 4-2, or I-b.
The appropriate Kp given by Figure 4-1, multiplied by the lh appropriate limit from figure 4-3, where IL I
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L HATCH 2 CYCLE 9 CORE OPERATING LIMITS REPORT I
REV!510N 0.. EFFECTIVE DATE: FEBRUARY 27, 1990
!I T=
0 or lave - TR-, whichever is greater
,g TA - TB
- 5 '.
g where:. TA = 1.096 see (Specification 3.1.3.3, scram time 1
5 limit to notch 36)
{
~
~
/2 1
l TB = p + 1.65 H1_
o n
!E INj
,5 i=1.
where: p
=
0.822 see (mean scram time used in the transient-analysis)
.018 sec (standard deviation of y) o
=
n INj Ti ave
- i"I T
1 I:-
n I
INj i=1 where:
n=
number of surveillance tests performed to date
.)
in the cycle --
Ni= number of active control rods measured in the 1
~
. ith surveillance test i
average scram time to notch 36 of rods in Ti
=
4
_the.ith surveillance test y
?
p',
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HATCN 2 CYCLE 9
[
CORE OPERATING LIMITS REPORT REVISION 0, EFFECTIVE DATE: FEBRUARY 27, 1990 N1= total number of active rods measured in Specification 4.1.3.2.a Note that.T= 1.0 prior to the initial scram time measurements-
, l for the cycle performed in accordance with Specification 4.1.3.2.a, because Tave is assumed equal to TA (Specification'4.2.3.1.a).
4.2 Sincle Recirculation Loon Doeration For single-loop operation, the MCPR operating limit shall be 0.01 greater h
than the two-loop value which is determined as specified in Section 4.1.
5.
LHGR LIMIT (TECHNICAL SPECIFICATION 3/4.2.4)
.The LHGR limit shall be 13.4 kw/ft for all 8x8 fuel. There is no corresponding limit for 9x9 fuel.
6.
REFERENCES 1.
" General Electric Standard Application for Reactor Fuel,"
NEDE-24011-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 DPR-57 I
and NPF-5 -- Edwin I. 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, Rev. 0 (November 1989).
lj
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'l HATCH 2 CYCLE 9 CORE OPERATING LIMITS REPORT REVISION 0. EFFECTIVE DATE: FEBRUARY 17. 1990 f h-Letter, CJP:90-006, " Hatch 2 Cycle 9 Operating Limik. MCPR 4.
Modification,' C. J. Paone to K. S. Folk, January 8,1990.
5.
NEDC-31376P, 'Edwin I. Hatch Nuclear Plant Units 1 and 2
'g SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis,' December IB-1986.
[
6.
Technical Specifications Bhses for Sections 3/4.1.4.3,3/4.2.1, 3/4.2.3, and 3/4.2.4.
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- 'l' HATCH 2 CYCLE 9 CORE OPERATINE LIMITS REPORT lE
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-1 I
i HATCH 2 CYCLE 9 CORE OPERATING LIMITS REPORT l
4 REV!sION 0. EFFECTIVE DATE: FEBRUARY 17, 1990 MCPR Limit os function of. Averoge. Scrom Tigne 1.32 1.31
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