ML20111B342
| ML20111B342 | |
| Person / Time | |
|---|---|
| Site: | Hatch |
| Issue date: | 05/10/1996 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20111B340 | List: |
| References | |
| NUDOCS 9605140338 | |
| Download: ML20111B342 (25) | |
Text
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1 GEORGIA POWER COMPANY EDWIN I. HATCH NUCLEAR PLANT l
]
UNIT 1 CYCLE 17 CORE OPERATING LIMITS REPORT Revision 1 i
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4 Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201 d
9605140338 960510 PDR ADOCK 0S000321 i
P PDR
.a.
EDWIN I. HATCH NUCLEAR PLANT UNIT 1 FUEL CYCLE 16 CORE OPERATING LIMITS REPORT AFFECTED PAGE LIST Unless noted otherwise, all pages are Revision 0.
Page Number Revision Cover 1
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4/26/96 Revision 1 y
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Edwin I. Hatch Nuclear Plant Unit 1 Cycle 17 Core Operating Limits Report TABLE OF CONTENTS Section lille Eage 1.0 Introduction 1
2.0 Rod Block Monitor -
1 f
3.0 APLHGR Limit 2
4.0 MCPR Limit 11 5.0
,APRM Flow Biased Simulated Thermal Power -Higli 20 l
Time Constant 6.0 References 20 l
6
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i e
i Revision 1
l TABLE OF CONTENTS (Continued)
LIST OF FIGURES i
Figure No.
Iitic Eaga 3-1 MAPLHGR Multiplier (MAPFACp ) Versus Core 3
Flow
[
3-2 MAPLHGR Multiplier (MAPFACp ) Versus Core 4
]
Power i
3-3 APLHGR Versus Average Planar Exposure (GE9B-P8DWB330-10GZ-80M-150-T) 5 3N APLHGR Versus Average Planar Exposure i
(GE9B-P8DWB314-8G4.0-80M-150-T)
.6 3-5 APLHOR Versus Average Planar Exposure
- (GE9B-P8DWB331-10GZ-80M-150-T) 7 3-6 APLHGR Versus Average Planar Exposure (GE13-P9HTB327-12GZ-100M-J 46-T-L UA-RECON) 8 3-7 APLHGR Versus Average Planar Exposure (GE9B-P8DWB346-10GZ-80U-150-T) 9 3-8 APLHGR Versus Average Planar Exposure (GE12-P10HSB331-6G5.0MG4.0-100T-150-T) 10 4-1 MCPR Multiplier (Kp) Versus Core Power 14 4-2 MCPR Limits (MCPRp) Versus Core Flow 15 4-3 MCPR Limit Versus Average Scram Time 16 (with Turbine Bypass Valves Operable and EOC-RPT System Operable) 4-4 MCPR Limit Versus Average Scram Time 17 l
(with Turbine Bypass Valves Operable and EOC-RPT System Inoperable) ii Revision 1
i i
l TABLE OF CONTENTS (Continued)
LIST OF FIGURES (Continued) i Figure No.
Title Eage 4-5 MCPR Limit Versus Average Scram Time 18 (with Turbine Bypass Valves Inoperable and EOC-RPTSystem Operable) 4-6 MCPR Limit Versus Average Scram Time 19 (with Turbine Bypass Valves Inoperable and EOC-RPTSystem inoperable)
LIST OF TABLES i
Table No.
Title Eage i
4-1 Operating Flexibility Options Applicability 13 h
s l
l 1
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s d
4 iii Revision 1
I
' Plant IIatch Unit 1 Cycle 17 Core Operating Limits Report 1.0 :
INTRODUCTION The Core Operating Limits Report (COLR) for Plant Hatch Unit 1 Cycle 17 is prepared in accordance with the requirements of Technical Specification 5.6.5. The production of this document is documented in a DRF under QA No. NFS-96-029. The core operating limits presented herein were developed using NRC-approved methods (References 1 and 2). Results from the fuel vendor's reload analyses for the fuel in Unit 1 Cycle 17 are documented in References 3,4, and 5.
l-The following cycle-specific core operating limits are included in this report:
a.
Control Rod Block Instrumentation - Technical Specification 3.3.2.1 b.
Average Planar Linear Heat Generation Rate (APLHGR) - Technical Specification 2.1 c.
Minimum Critical Power Ratio (MCPR) - Technical Specifications 3.2.2 and 3.3.2.1 i
d.
APRM Flow Biased Simulated Thermal Power' High -- Technical Specifications Surveillance Requirement 3.3.1.1.14 2.0 ROD BLOCK MONITOR (Technical Specification 3.3.2.1)
Both Rod Block Monitor (RBM) channels shall be operable as specified in Technical Specification 3.3.2.1 and when:
a.
Thermal Power is 2 29% and < 90% of Rated Thermal Power, and MCPR is < 1.70; or b.
Thermal Power is 2 90% of Rated Thermal Power, and MCPR is < l.40.
)
1 1
Revision 1 9
f
)
Plant Hatch Unit 1 Cycle 17 j
Core Operating Limits Report
,e 3.0 APLHGR LIMIT (Technical Specification 3.2.1) l The APLHGR limit for each fuel type is given by the applicable rated-power, rated-flow j
APLHGR limit taken from Figures 3-3 through 3-8, multiplied by the smaller of either:
. a.
The flow-dependent multiplier, MAPFACF, from Figure 3-1, or b.
The power-dependent multiplier, MAPFACp, from 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 (Reference 1), the hand-calculated APLHGR values for a multip lattice fuel (i.e., GE9-330, GE9-331, GE13-LUA, GE9-346, and GE12-331) must be less than or equal to the APLHGR limits shown in Figures 3-3,3-5,3-6,3-7, and 3-8, respectively. When APLHGR values are determined by the process computer, the lattice-dependent APLHGR limits are used. Under these conditions, some axial locations may have APLHGR values exceeding the values shown in Figures 3-3,3-5,3-6,3-7, and 3-8.
e r
2 Revision 0
4
' PlantIIatch Unit 1 Cycle 17 Core Operating Limits Report i
~
l
///A ~
107 %
~
0.90 112 %
r 0.as
[
l m%
id t
R 0.s0 l
MAPLHORp.MAPPAO'MAPLHOReto g
_R_..,_ _ _
u.
I MAPFAcee MNSILRI lMPRPDF, MAPMULTr]
3 0.70 l
l MAPMULT,e 1 A POR PLOW > 01%
8 j
= 0.88 POR PLOW W Si%
I 0.40 MPRPDF (P)e MINRlW [1.0,4+ Bp Fj
,,,,4c7,on o, n47,o cong, tow MAXIIALAA CORE PLOW l
(% RATEl)
102.5 0Aset 0.srs4 i
107.0 0A574 0.8750 l
112.0 OA214 0.0007 l
mA 0.u20 Ones l
l l
+
1 0.40 30 40 50 60' 70 00 90 100 61 l
CORE FLOW (% rated)
FIGURE 3-1 MAPLHGR MULTIPLIER (MAPFACv) VERSUS CORE FLOW 3
Revision 0
l t
~
Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report i
I
]
I' l
1.0 I
I
)
i i
_ 0.9 t
2 k
I i
i E
/
0.8 l$
5 I
SINGLE LOOP OPERATION (SLD) 0.rs - ----------- ---------- -----
s 90% CORE PLOW l
MAPLHOR p eISAPPAC e *IAAPLHOR es i
MAPLHOR em a STANDAlul1IAAPLHOR UtilTS SLO n$)
(OLO, TLO)M.APPAC, m 0.55 + SA.002M (P. 30%)
i a
g co Pt.
p,-
a
.A.,AC.
0
..A u (P.
)
1
=, m o TOW
- =am-l MAPPAC P e 1.0
- 0.005234 (P.100%)
8 POR $2%.P:(SLO) MAPPAC P e 0.75 i
8 h
4
,50% NE PLOW
'/ I t
0.4 g
I 52 20 26 30 40 50 60 70 00 90 100 POWER (% rated) 4 i
FIGURE 3-2 4
MAPLHGR MULTIPLIER (MAPFACp) VERSUS CORE POWER e
i t
4 Revision 0
PlantIIatch Unit 1 Cycle 17 Core Operating Limits Report
- %t 13 J
IJNACCEPTABLE 12 OPERATION ExPosuRs l
COORDINATES si x
y Er a00 ti.s2 g,,
a20 t i.m
(
1.00 11.71 h
1"lr' N
2.00 11.00 o
l 6.00 12.52
(
j l[7j ACCEPTABLE
-1 am 1105 OPERATION 8 00 1119 10.00 1130 12.80 13.30 15.00 13.12 y
~;
I i
20.00 12.48 h
26.00 11.72 GESB PIDWB330-10GZ 80M-160.T
\\
36.00 10.19 c
4s.00 s.79 si.e4 s 70 g
n a
in 15 20 25 30 35 40 46 80
{ NOTE:
AVERAGE PLANAR EXPOSURE (GWd/st)
- THISIS THE APLHOR UMff FOR THE i
MOST Uh5 TING LATTICE AS A l
FUNCTION OF AVERAGE PLANAR j
EXPOSURE g
4 FIGURE 3-3 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel T)pe: GE9B-P8DWB330-10GZ-80M-150-T) 5 Revision 0
Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report l
" j N N UNACCEPTABLE 7
,2%_
N OPERAVON comunits m
11 x
y 0.00 11 3 10 E20 11A 1.00 12.0 N
1 00 12.2 3
' aa
'2 '
l 9 9 6
17 e.00 119 ACCEPTABLE
[$II2 OPERAVON
}
9.00 113 10.00 114 1250 13.6
_i 16.00 112 h
20.00 116
\\
l ';"
i GE98-PSDWB3M4M04M150!T g
46.00 9.0 ll 61 A7 6 8 L
s 0
6 10 15 20 25 30 36 40 46 50 AVERAGE PLANAR EXPOSIRE (GWWut)
FIGURE 3-4 AVERAGE PL ANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB314-8G4.0-80M-150-T) 6 Revision 0
- Plantilatch Unit 1 Cycle 17 Core Operating Limits Report i
/WL
's f
I UNACCEPTABLE
,,7 EXPOSURE COORDINATES 11 x
Y i
(LOG 11.57 0.20 11.02 10 1.00 11.76
]
2.00 11.96 1 00 12.17 4.00 12.41 8
5.00 12.00
'2'o ACCEPTABLE
^
7.00 13.07 a m i122 OPERATION i
8.00 1132 l
10.00 1128 j
12.00 1113 1
16.00 12.00 y
20.00 12.15 l
I's ((
GE98 PSDWB33110GZ40M-180-T S
46.00 8.11
}
80.00 0 06 1
e a
in il 20 26 30 36 40 45 80 NOTE:
AVERAGE PLANAR EXPOSURE (GWatet)
! T>esisTHE APLHOR UMff FORTHE MOST UMITING LATTICE AS A FUNCTION OF AVERAGE PLANAR j
EXPOSURE FIGURE 3-5 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB331-10GZ-80M-150-T) 7 Revision 0
l l
Plant Hatch Unit 1 Cycle 17
)
Core Operating Limits Report 13 UNACCEPTABLE OPERATION d
11 E
EXPOSURE k10 COOR0lNATES X
Y X
Y 0 00 11.07 12 5 11.70 w
9 9
0.20 11.14 15 0 11.70 1
1.00 11.32
- ? 5 11.70 5
2.00 11.M 20.1 11.M
=
(
3.00 11.70 25L 10.M s
4 00 tu0 30 0 101e ACCEPTABLE 5.00 11.70 36 0 9.54
~
a00 tuo 40 r as0 OPERATION 7.00 11.70
- 45. J 8.25 1
7 1 00 11.70 50 0 7.57
~
l l
9.00 11.70 55.0 tas l
l 10.0 11.70 57.27 R$1 GE13-P9HTB327120Z 100M-146 T LUA RECON e
~~~~~
S e
a to il 20 25 30 36 40 48 50 H
NOTE:
AVERAGE PLANAR EXPOSURE (GWdlet)
THl418THE APLHOR LIMrf FORTHE WO57 UMTING LATTICE AS A i
FUNCTION OF AVERAGE PLANAR ExposuRs l
FIGURE 3-6 AVERAGE PLANAR LINEAR HEAT GENERATION RATE 1
VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE]3-P9HIB327-12GZ-100M-146-T-LUA-RECON) i 8
Revision 0
)
.O Plant' Hatch Unit 1 Cycle 17 Core Operating Limits Report l
A 13
- N
/
UNACCEPTABLE OPERATION EXPO 8URE COORDINATES
(
3 11
-f x
y
[
0.00 11.07 g10 0.20 11.73 1.00 11.e4 1
D 2.00 12.00 t
3 am 12.t e I
1 4 00 Itu
\\
l* -!
tm iui w
g' i
- " ' 2" ACCEPTABLE
_l
[$ IIS OPERATION 9.00 1t10 10.00 12.70 12.80 12.46 7 _l 16.00 12.52
. j 20.00 11.01
~ l
'd$[d' GE9B-PSDWB34410GZ 80U-160 T l
45.00 8.76 S
l 61.71 5.84 I>
.)
f a
o a
in 15 20 25 30 36 40 46 60 p NOTE:
AVERAGE PLANAR EXPOSURE (GWd/st)
! THisis THE Aptwon uur ron THE MOST UMTING LATTICE A8 A FUNCTION OF AVERAGE PLANAR j
ExposunE FIGURE 3-7 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB346-10GZ-80U-150-T) 9 Revision 0
Plant Ihtin Unit 1 Cycle 17 Core Operating Limits Report
(
l 1
i l
l EXPOSURE COORDINATES 13 1'
X Y
X Y
12 0.00 0.12 12.00 &to UNACCEPTABLE
- 2a *"
12 " *"
1.00 9.23
- 1. 00 E 68 OPERATION 2m as i5. au 100 tde 17.00 9.29 y9 4.00 9.M 20.00 9.02 5.00 0.01 26.00 &87 4 00 EST 30.00 tid p '*s, E. 1
.000 7.71 7.00 73 35 10 7,
3 10.00 10.03 50.00 4 43 A
I 11.00 0.M M.21 0.00 g
~
k ACCEPTABLE q
7 OPERATION N
f GE12#10HSB331-4G6.0/4G4.0-100T 150-T I
T e
a to 15 20 25 30 35 40 44 50 NOTE:
AVERAGE PLANAR EXPOSURE (GWd/st)
THis18 THE APLHOR LihWT FOR THE MOST L'WTING LATTICE AS A FUNCTION OF AVERADE PLANAR ExPoeuRE FIGURE 3-8 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE12-P10HSB331-6G5.0/4G4.0-100T-150-T) 10 Revision 0
' Plant 11atch Unit 1 Cycle 17 '
Core Operating Limits Report 4.0 '
MCPR LIMIT (Technical Specification 3.2.2) -
The MCPR operating limit (OLMCPR) is a function of core power, core flow, average scram time, fuel type, number of operating recirculation loops, operability of the end-of-cycle recirculation pump trip (EOC-RPT) system, and operability of the turbine bypass valves.
With both recirculation pumps in operation (TLO), the OLMCPR for each fuel type with various combinations of equipment operability, scram times, core flow and core power is determined as follows:
- a. For 25% $ power < 30%, the OLMCPR is given in Figure 4-1.
- b. For power 2 30%, the OLMCPR is the greater of either:
- 1) The flow-dependent MCPR limit determined from the applicable maximum core flow limit line of Figure 4-2, or L
- 2) The product of the values from Figure 4-1 and the applicable Figures 4-3 through 4-6 as determined by Table 4-1.
As stated in the note on Figures 4-3 through 4-6, with one recirculation pump operating l
(SLO), the calculated OLMCPR determined above is increased by 0.01.
i In Figures 4-3 through 4-6, Option A scram time MCPR limits correspond to t = 1.0, l
where t is determined from scram time measurements performed in accordance with Technical Specifications Surveillance Requirements 3.1.4.1 and 3.1.4.2. Option B values correspond to t = 0.0. For scram times between Option A and Option B, the MCPR limit for each fuel type corresponds to t. IfI has not been determined, Option A limits are to be used. Refer to Table 4-1 to determine the applicable set of fuel-type dependent curves.
11 Revision 1
Plant Hatch Unit 1 Cycle 17.
Core Operating Limits Report r
The average scram time of the control rods, t, is defmed as:
T.w - TB t
= 0,or
, whichever is greater.
TA - TB i
where:
ta = 1.08 sec (Technical Specification 3.1.4, Table 3.1.4-1, scram time
{
limit to notch 36).
t/2 Ns ta = p + 1.65 + o.
ens i
where:
= 0.822 sec (mean scram time used in the transient analysis).
o
= 0.018 sec (standard deviation of ).
[ Nit 6
T=
I, Ni where:
n
= number of surveillance tests performed to date in the cycle.
1 Ni = number of active control rods measured in the ith surveillance test.
ti
= average scram time to notch 36 of all rods in the ith surveillance test.
Ni = total number of active rods measured in Technical Specifications Surveillance Requirement 3.1.4.1.
6
=
i 12 Revision 0
Plant' Hatch Unit 1_ Cycle 17-f Core Operating Limits Report I
1 1
i TABLE 4-1 OPERATING FLEXIBILITY OPTIONS APPLICABILITY -
f
. WITH:
USE:
EOC-RPT Turbine Bypass Valves Operable Operable Figure 4-3 Inoperable Operable Figure 4-4 Operable Inoperable Figure 4-5 Inoperable Inoperable Figure 4-6 h
NOTE:
Operation within the licensed power / flow region with a single recirculation loop and intermittent operation with reduced feedwater temperature are included in the MCPR limits presented in Figures 4-3 through 4-6.
l 4
i 13 Revision 1
]
Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report 2.s l
>50% FLOW 2.5 OPERATINO LIMIT 1ACPR(P) e Mp
- OPERATINO Litsff AICPR(100)
I l
FOR P < 25% NO THER14AL LiterTS 840Nff0RINO REQUIRED i
NO LIMITS SPECtPIED i
g4 POR 25% g P < P - ee (WHERE P ewass e 30% POR HMP.1,2) l K, s (aen + 0.0.;10%. P)) i OLAACPR (100) i AND 2.3 -
i Ksw 2.00 PoR gsesCORE Plow g
Ksw e 2.40 POR > 60% CORE PLOW i
POR 30% g P < 45W N
E, = 1.2s + e.0134 (46%. P)
~
2.2 ~
PO't 45% c P < 40%
N i
"*
- 1.1s + e.cosef (se%. P) b h 50% FLOW POR 60% g P:
2.$.
x,. t.... m 1 %.,)
v, g$
I m-l 2.0 b e...M
%M M
" I
,. ~
!\\
N i
j 1.3 --
i i
i i
l l
l N
l 11-l l
l N
i
- P sw.t.
N w
i i
i i
1.0 i
20 25 30 40 50 60 70 80 90 100 POWER (% RATED)
FIGURE 4-1 MCPR MULTIPLIER (Kp) VERSUS CORE POWER 14 Revision 0
~
' Plant Hatch Unit 1 Cycle 17
~
Core Operating Limits Report 17 i
i i
i MAXNUM PLOW RATE e 117 %
POR We (% RATED CORE PLOW) e 40%
112 %
MCPRp e( AgW,i100
- sf )* {1+0.0032(40. W,j]
)
~
X 107 %
POR We (% RATED CORE PLOW)240%
McPR p= max (1.20. A W. I too + a )
' /
t r
~ \\
MAKPLoW A,
s, 1.5 -
117A eA32 1 Ass 112A eAe2 1,747 N
187A eAS4 1,gsy 102A eA71 1455 E 1.4 h
E E
h 1.3 i
M N
1.2 1.1 i i i
.iiiii i.
i6 i i 6 6. i 4. i 30 40 60 60 70 80 90 100 110 120 CORE FLOW (% rated) l 4
i FIGURE 4-2 MCPR LIMITS (MCPRr) VERSUS CORE FLOW 15 Revision 0
~
Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report i
l
)
un GE12 s N ow -
1.as E-d.as t!
GE13
@ 1.3.
g e
[
p h,1.32
-p 4.'
'GE9B 1
k N
s g 1.as
(
1.as 1.24 6
1.22 o
c.1 c.2 c.s o.4 oa o.s o.7 c.s o.s 1
NOTE: For SLO, increase the MCPR Limit obtained from this figure by 0.01.
FIGURE 4-3 MCPR LIMIT VERSUS AVERAGE SCRAM TIME (with Turbine Bypass Valves Operable andEOC-RPTSystem Operable) 16 Revision 0 L
l
~
' Plant Hatch Unit 1 Cycle 17 Core Operating Limits Repon 1.52 2
l l
l l
1.6 GE12 l
1.
g ue L e
l l
I I
l 9 1.44 l
=
GE13 4 l
W l
l
'I l
l 1
l N
i":
Y l
u2 1.3 l
i i
l 1-I u.
0 0.1 0.2 0.3 0.4 0.4 0.8 0.7 0.8 0.9 1
TAU (t)
NOTE: For SLO, increase the MCPR Limit obtained from this figure by 0.01.
FIGURE 4-4 MCPR LIMIT VERSUS AVERAGE SCRAM TIME l
(with Turbine Bypass Valves Operable and EOC-RPTSystem inoperable) 17 Revision 1
~
~
~ Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report
- (
1.4e i
l l
l i
i GE12 L 4
u4 x
3 j
h us s
=
{u GE13 '
s 3
l V
GE9B yd' I,,
l
~
u4 h
1,32 0
0.1 0.2 0.3 0.4 0.5 0.8 0.7 OA 0.9 1
TAU (t)
NOTE: For SLO, increase the MCPR Limit obtained from this figure by 0.01.
FIGURE 4-5 MCPR LIMIT VERSUS AVERAGE SCRAM TIME (with Turbine Bypass Valves Inoperable and EOC-RPTSystem Operable) 18 Revision 1
_1
' Plantilatch Unit 1 Cycle 17 Core Operating Limits Report 1.58
'I 1.u GE12 il:."
GE13 N
im l'"
x GE B w
.i y
a u ll #
i s.u o
0.1 0.2 0.3 0.4 0.5 0.8 0.7 0.8 0.9 1
TAU (t)
NOTE: For SLO, increase the MCPR Limit obtained from this figure by 0.01.
FIGURE 4-6 MCPR LIMIT VERSUS AVERAGE SCRAM TIME (with Turbine Bypass Valves Inoperable and EOC-RPTSystem inoperable) 19 Revision 1 i
1 Plant Hatch Unit 1 Cycle 17 Core Ope ating Limits Report 5.0 APRM FLOW BIASED SIMULATED THERMAL POWER - HIGH Time Constant (Surveillance Requirement 3.3.1.1.14)
)
The allowable value for the APRM Flow Biased Simulated Thermal Power - High time constant is s 7.0 seconds.
6.0 REFERENCES
1.
" General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A US, November 1995.
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. Hatch Nuclear Plant Units 1 and 2 (TAC Nos.
73614 and 73615)," December 29,1989.
3.
" Supplemental Reload Licensing Report for Edwin I. Hatch Nuclear Plant Unit 1, Reload 16, Cycle 17," General Electric Document 24A5353, Revision 0, March 1996.
6 4.
"Edwin I. Hatch Nuclear Plant Units 1 and 2 SAFER /GESTR - LOCA Loss-of-Coolant Accident Analysis,"NEDC-31376-P, December 1986.
5.
Letter No. 262-96-060, D. P. Stier (GE) to R.E. Kingston (GE), "Results of FWCF Tra isients without Bypass for Hatch-1 Cycle-17," April 25,1996.
N.
l 20 Revision 1