ML20104A298
| ML20104A298 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/05/1992 |
| From: | Bethay S GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20104A296 | List: |
| References | |
| NUDOCS 9209110132 | |
| Download: ML20104A298 (18) | |
Text
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- c. Edwin 1. Hatch gn Nuclear Plant - Unit 2 91 1 _
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Interoffice Correspondence \
Georgia Poner at.
- O DATE: August 5, 1992 RE: Hatch Pro.iect Support - Licensina Core Operating Limits Report for Hatch 2 Cycle 10, Revision 1 File: Fuel Cycle Technical I Log: HL-2368 FROM: S. eihh"'
TO: ALL UNIT 2 TECHNICAL SPECIFICATIONS HOLDERS Enclosed is Revision 1 to the Plant Hatch Unit 2 Core Operating Limits Report (COLR) for Cycle 10 which imposes a Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) penalty while operating above 63 percent of rated thermal power. The penalty was imposed in response to a concern related to the potential for a complete loss of feedwater heating. The MAPLHGR power factor I"APFACp) graph in the COLR (Figure 3-2) has been revised accordingly. The concern .s not applicable to Unit 1.
The COLR is required to be retaineu and maintained consistent with the Technical Specifications. The Unit 2 COLR, Revision 0 for Cycle 10, currently in possession should be discarded and replaced with the enclosed Revision 1 for Cycle 10.
If there are any questions regarding this retransmittal, please centact me at extension 7301.
OCV/cr 003840 cc: NORMS O
interoffice Correspondence Ge(Hgial'imel n\
rO DATE: July 24, 1991 RE: listch Pritiect Support - Licensing Core Operating Limits Report for Hatch 1 Cycle 13 and Hatch 2 Cycle 10 File: Fuel Cycle Technical Log: HL-1750 fROM: S . J . Be t h ay --) -[' /bv nu-ave.
T0: ALL UNIT 1 AND UNIT 2 TECHNICAL SPECIFICATIONS HOLDERS Recent discrepancies have been identified relative to the retention of the adjunct Core Operating Limits Report (COLR) and the previous distribution system. As a result, this letter retransmits to all Unit I and Unit 2 Technical Specifications holders a copy of the COLR for Hatch 1
- ycle 13 and Hatch 2 Cycle 10. The purpose of the retransmittal is to baseline the distribution to correct the discrepancies. The COLR is required to be retained and maintained consistent with the Technical Specifications. The Unit I and Unit 2 COLAS currently in possession should be discarded and replaced with the retransmitted COLRs.
If there are any questions regarding this retransmittal, please contact me at extension 8-821-7392 or telephoe number (205) 877-7392.
JKB/cr 001990 2 cc: NORMS O
l
interofflee Correspondence Georgial\mer d DATE: May 13, 1991 h RE: Core Operating Limits Report for Hatch 2 Cycle 10 File: Fuel Cycle Technical Log: HL-1637 FROM: S.J.Bethay4h 9 T0: All Unit -2 Technical Spect ications Holders Ry Amendment 106 to the Unit 2 Technical Specifications (TS), the NRC wthorized relocation of P2*tain fuel-related limits from the Technical Specifications to tha adjunct Core Operating Limits Report (COLR). This letter transmits to all Unit 2 Technical Specifications holders a copy of Revision 0 of the Core Operatirtg Limits Report for Hatch 2 Cycle 10. This document should be utilized in conjunction with the Unit 2 Technical Specifications as referred to in the Specifications. Normally, the shift technical advisor (STA) or reactor engineer will utilize this report.
Where necessary, the fuel lhits from tLe CCLR have been included in plant g procedures.
If changes to the core operating limits contained in this raport are required, a cor.plete revised COLR will be issued and the appropriate procedures revised, if there are any questions regarding this report, please contact me at extension 8-821-7392 cr telephone number (205) 877-7392.
RDB/cr 001621 Attachment cc: NORMS O
- e N .
lO 1
O at0RGia e0wER C0seANv EDWIN I. HATCH NUCLEAR PLANT UNIT 2 FUEL CYCLE 10 CORE OPERATING LIMITS REPORT l
1 I
I O
l l
I e
O O REVISION 1 AUGUST 7, 1992
W EDWIN I. HATCH NUCLEAR PLANT UNIT 2 CYCLE 10 CORE OPERATING LlHITS REPORT 1.0 INTRODUC110N
[ This CORE OPERATING LIMITS REPORT for Hatch Unit 2 Cycle 10 is
- prepared in accordance with the iequirements of Hatch Technical Specification 6.9.1.11. The core operating limits presented here were developed using NRC-approved methods (Referer.ces 1 and 2).
Results from the reload anelyses for the General Electric fuel in l Hatch I. kilt 2 Cycle 10 are decumented in Reference 3.
The following cycle specific : ore operating limits are included in this report:
- a. Control Rot Program Controls - Rod Block Monitor (Technical Specification 3/4.1.4.3)
- b. Average Planar Linear Heat Generation Rate (APLHGR) Limit
,l (Technical Specification 3/4.2.1)
- c. Minimum Critical Power Ratic (MCPR) Operating Limit (Technical Specification 3/4.2.3)
- d. Linear Heat Generation Rate (LHGR) Limit (Technical Specification 3/4.2.4) 2.0 R00 6 LOCK MONITOR (TECHNICAL SPECIFICATION SjL 1,4,3)
Both Rod Block Monitor (RBM) channels shall be oparable 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 than 1.70, or Revision 0 1 May 1, 1.
w-------------,----- , - - - - - - - - . . - -
Unit 2 Fuel Cycle 10 Core Operating Limits keport io
- b. THERHAL POWER is 1 90% of RATED THERMAL POWER and the MCPR is less than 1.40.
3.0 AEWOR LIMIT fTECHNICAL $PECIFICATION 3/4All The APLHGR limit is given by the applicable rated-nower, rated-flow _
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.
g For the fuel types whose APLHGR limits are shown in Figures 3-3 through 3-7, the APLHGR limit shown shall be appl,?d to each axial location in the fuel assembly.
I 4.0 IKLPR LIMIT (TECHNICAL SPECIFICATION 3,1.2.31 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 is fuel-type dependent in Figure 4-3. For example, option B limits are 1.25, 1.27, and 1.31 for CE7 BP80RB284H, BP80RB299, BP80RB30ll; GE9 BP8DWB314; and Gell P9 HUB 293 fuel, respectively. The ANF lead assemblies will be monitored as GE7 BP8 URB 284H bundles.
O Revision 0 2 May 1, 1991
II Unit 2 fuel Cycle 10 Core Operating Limits Report 4.1 Two Recirculation loop 0perat19D for 25% s Power < 30%, the OLMCPp is given in Figure 4-1. For Power 2,30%, the OLMCPR is the greater of either:
-I a. The applicable limit determined from Figure 4-2, or
- b. The appropriate Kp given by Figure 4-1, multiplied by the appropriata limit from figure 4-3, where the scram time I dependence is given in the Bases for Technical Specification 3/4.2.3.
4.2 Sincie Recirculation loop OperatiqD for single-loop operation, the MCPR operating limit shall be 0.01 greater than the two-loop value which is determined as specified in Section 4.1.
5.0 LtLGB_ LIMIT (TECl"llCAL SPECIFICATION 3/4.2.41 The LHGR limit shall be 13.4 kW/ft for all GE7 8x8 fuel (BP8DRD284H, BP8DRB299, and BP8DRB30ll) and 14.4 kW/ft for GE9 (BP8DWB314) and Gell (P9 HUB 293) fuel. The ANF lead assemblies will be monitored as GE7 BP80RB284H bundles.
E*
I O
.I Revision 0 3 May 1, 1991
Unit 2 Fuel Cycle 10 Core Operating Limits Report 6.0 RffERENCES l 1. " General Electric Standard Application for Reactor Fuel,"
NEDE-24011-P-A-9, September 1988.
- 2. Letter, L. P. Crocker (dRC) to J. T. O'Reilly (GPC), " Issuance of Amendment Nos. 151 and 89 to facility Operating Licenses DPR-57 and NPF Edwin I. Hatch Nuclea4 Plant Units 1 and 2 (TACS66524/66525)," January 22, 1988.
- 3. " Supplemental Reload Licensing Submittal for Edwin 1. Hatch
.: Nuclear Plant Unit 2. keload 8, Cycle 9," GE Document 23A6470, Revision 0, April 1991.
I 4. "Edwin 1. Hatch Nuclear Plant Units 1 and 2 SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis," NEDC-31376E, December 1986.
- 5. Technical Specifications Bases for Sections 3/4.1.4.3,3/4.2.1, 3/4.2.3,and3/4.2.4.
I i
000282 I
18 I
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,_ Revision 0 4 May 1, 1991
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b 10 0.0 11.83 \. Er gI 3
0.2 11.90 mN J 1.0 12.01 .
U" 9-l
- 2.0 12.17 I
g $$
0z 0 8.98 3.0 12.34 b5 3 1 4.0 12.54
% 8:
5.0 2.74 ACCEPTABLE s. #6m 6.0 12.94 \
7.0 13.12 OPERATION \ g 7- -
8.0 13.22 g ,
\
4 9.0 13.30 1 10.0 13.40 FUEL TYPE:
\
G- -
12.5 13.50 5.84 l GE9B-P8DWB314-8G4.0-80M-150-T (GE8X8NB)
St ... ... .i 1 . .!.i, !.... ,, 4 . .'.... ,, , ,
AVERAGE PLANAR EXPOSURE (GWd/st) h C FIGURE 3-6 AVERAGE PLANAR LINEAR E HEAT GENERATION RATE LIMIT vs. AVERAGE PLANAR EXPOSURE
' - ~
use o me amm = uma au amm num num - mer O % uma I ins amm I I um O O m t l l
13 5 : UNACCEPTABLE z '
12
~L ," 7 OPERATION 11.66
- LOW EXPOSURE -
U:'~ H.13 COORDINATES
- 25, X Y 10.60' hO E 5 -- -
F 10- -
0.0 11.64 10 07 5 -
0.2 11.70 $I
=
J 5 *:
[ 17.5 11.70 9.54
\' .
si 5 : 8.1 9 E8
" r-
- c. 9
< 8
-^
ACCEPTABLE =
OPERATION y
_ 5 6 FUELTYPE: (GE11LUA)
GE11 -P9 H U B293-7 G5.0/1 G4.0-100 M-146-T-LU A
~
5 ..... .............. ....!.. . ....!....'...........50 0 5 10 15 20 25 30 35 40 45 h, AVERAGE PLANA 3 EXPOSURE (GWd/st)
^^"""""*""""""" FIGURE 3-7 AVERAGE PLANAR LINEAR E CCC ""^* " HEAT GENERATION RATE LIMIT vs. AVERAGE PLANAR EXPOSURE
m 77ug 3 2.6 -
i i i i I
g ,
g g > 50% OPERATING UMIT MCPR(P) = Kp
- OPERATING UMIT MCPR(100)
O _ i FOR P < 25% : NO THERMAL UMITS MONITORING REQUIRED
' ' NO UMITS SPECIFIED _.
g 2.4-(WHERE P wa = 30% FOR HNP-1,2) gg _
l i
FOR 25% < P < P wa=
Kp = (K + 0.02(30%-P))/OUWCPR(100) o A ' 2.3-i AND m g
{ '
v "E 2.2_ K = 2.00 FOR < 50% CORE FLOW _
a _
R > M CORE MW g i V' d50% FLOW
"=
Er g 12E 2.1-FOR 30% < P < 45%:
Ay gE _
j Kp = 1.28 + 0.0134 (45%P)
FOR 45% < P < 60%: _. "y e $ 2.0 Kp = 1.15 + 0.00867 (60%- P) -< at
. O ~3 gis FOR 60% < P : @Z M
' 9: 1 .5_ ;'
Kp = 1.0 + 0.00375(100%P) m8 Eb e Uh h$
so II_
N ,=
1 om 1.3-l
' g m 2i
- l l l x t t t l N l ',N i l % dash l
,x 1.0 . , , , , . . . . . , ,
20 25 30 40 50 60 70 80 90 100 l
g POWER (% RATED)
C FIGURE 4-1 l 4
- POWER-DEPENDENT MCPR MULTIPLIER (Kp) u
~
7 -
.t
'#~ '
= ' *
' *- iP'
- gid j, y_g 'd
' c
, 'M I6 .
,, .eg . ,' .
g , ,
@ ,1 - ; , ,$
> eMt 2
- #q3jgL w
, 15k% +* . 9%v r ym 2*a sus
+ '-ess vasi sur 'uma as mas issa amt aus maa wry
(; u tfi$f* h (aus'p; ~ ~
^
au-
. :s 1.7 . ' *
- '- " i
@, MAXIMUM FLOW PkTE = l W -$ 1 FOR We (% RATEC
- i' s
g ,
i 5
~
117% t MCPR(F)=" , * ' W+Bf) 2 -
112%
/j/[j
~
1.6- ' ~
MAXt ./ <
Af Bf 107%
102.5 %
117., -0.632 1.809
! 112.0 -0.602 1.747 m
- 107.0 -0.586 1.697 -
h
\ !'[b 1.5- #
' ! 102.5 -0.571 1.655 E E .-
e /
t- O 14 !
x
\
x .m
-L no I
i v.
n 3 Ni Oz y \
_ I O
wxNix, :
j,3
- E I J N -
12 '
-- FOR We (% RATED CORE FLOW) < 40% ; '
_ MCPR(F)=(AfWc/100+Bf)
- [1 + 0.0032(40-Wc)]
~
d l
, . ,,,,...,,, m ~, , , , , . .,
1.1 . , , ,,
120 40 50 60 70 80 90 100 110 JO rc
- W CORY FLOY/ (% rated) 5 FIGURE 4-2 E FLOW-DEPENDENT MCPR t ni ,, MC?R(F) 9
~ wy e
.. m
E L
EDWIN 1. HATCH NUCLEAR PLANT UNIT 2 CYCLE 10 1.35 l
- L) 1.34 GE11-P9 HUB 293 #
l g
1 LEAD BUNDLES [
I 1.33
[l -
B
/ '
g 1.32 f
/
4 1.31
- GE99-P8DWB314 e
1.30 #
/ -
7
- s /
i o 1.29 - / I g
1
/ #
/
n 128 / / ,
' J 1.27 o '
E BP8DRB284H 1.26 y BP8DRB299
/ E98DRB301L 9 X 9 LFAs 1.25 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 TAU FIGURE 4-3
(] MCPR LIMIT AS FUNCTION OF AVERAGE SCRAM TIME REVibiON O 14 MAY 1,1991
- _ _ - _ _ - _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ _ _ -__