ML20029E220
| ML20029E220 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 04/30/1994 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20029E219 | List: |
| References | |
| NUDOCS 9405170281 | |
| Download: ML20029E220 (20) | |
Text
{{#Wiki_filter:- -- --- - -- - - ---- -- -_ _ _ _ )O . O EDWIN I. HATCH NUCLEAR PLANT UNIT 2 'O CORE OPERATING LIMITS REPORT for FUEL CYCLE 12 O l O l O l Revision 0 April 1994 ' O F f C 66 P PDR
I- l Interoffice Correspondence l o e ..t P v L \ l l i f DATE: April 19,1994 O as: "etew ere!<1t sennori - tice, ies Core Operating Limits Report for Hatch 2 Cycle 12 Revision 0 File: Fuel Cycle Technical l Log: IIL-3300 -
.( /
l [q FROM: S. J. Bethay '; fe)' y> ! TO: ALL UNIT 2 TECHNICAL l SPECIFICATIONS MANUAL HOLDERS l ) By amendment 106 to the Unit 2 Technical Specifications, the NRC authorized relocation l of certain fuel-related limits from the Technical Specifications to the adjunct Core Operating Limits Report (COLR). This letter transmits to all Unit 2 Technical Specifications manual holders a copy of Revision 0 of the COLR for Hatch 2 Cycle 12. This document should be utilized in conjunction with the Unit 2 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 plant procedures.
Please discard Revision 0 of the COLR for Hatch 2 Cycle 11, which was issued in November 1992, since it is no longer applicable. If you have questions regarding Revision 0 of the Unit 2 COLR for Cycle 12, please contact me at extension 8-821-7392 or telephone number (205) 877-7392. SRPf sp l nan r Enclosure O cc: NORMS O O
.mJq y summeu$
- f. ,
O i
~O GEORGIA POWER COMPANY EDWIN 1. IIATC11 NUCLEAR PLANT UNIT 2 FUEL CYCLE 12 CORE OPERATING LIMITS REPORT REVISION 0 0
I l Lo ;
.l Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201 LO 4
________z__ _. - -
EDWIN 1. IIATC11 NUCLEAR PIANT UNIT 2 FUEL CYCLE 12 CORE OPERATING LIMITS REPORT O T^n's or cosTu"Ts l Section Ittle Page O : 1.0 Introduction 1 2.0 Rod Block Monitor 1 3.0 APLIIGR Limit 2 4.0 MCPR Limit 11 4.1 Two Recirculation Loop Operation 11
- O 4.2 siesie Recirceiettee LeeP oneretien 12 5.0 LilGR Limit 15 6.0 References -15 O l O
Revision 0 i April 1994
. _ _ _ - - - _ _ _ _ _ _ __---_--__-_-_____-a
n-TABLE OF CONTENTS (Continued) l O- 1 LIST OF FIGURES ! 1 Figure ! LO n m = t i 3-1 MAPFACp 3 L 32 MAPFACp 4
-l 33 APLHGR Versus Average Planar Exposure {
I (GE7B-P8DRB284-7G4.0-80M-150-T) 5-I i 3-4 APLHGR Versus Average Planar Exposure I (GE8B-P8DOB296-7GZ-80M 150-T) 6 l 3-5 APLIIGR Versua Average Planar Exposure (GE9B-P8DWB314-7G4.0-80M-150-T NOSHIP) 7 O 3-6 ^ e L H G R v erse a verese Piemer E xP osere 8 (GE9B-P8DWB314-804.0-80M-150-T) 37 APLHGR Versus Average Planar Exposure (GE11-P9 HUB 293-7G5.0/1G4.0-100M-146 T-LUA) 9 3-8 APLHGR Versus Average Planar Exposure ( G E9 B- P8 D W B314-8G 4.0A-80 M - 150-T) 10
-l 4-1 Power-Dependent MCPR Multiplier (Kg) 12 O 4-2 Flow-Dependent MCPR Limits (MCPRr) 13 I
4-3 MCPR Limit as Function of Average Scram Time 14 O O 1 i Revision 0 ii April 1994
. -. . _ ~ . . .
EDWIN 1. HATCH NUCLEAR PLANT
-j ; UNIT 2 FUEL CYCLE 12 CORE OPERATING LIMITS REPORT j 7 1.0 INTRODUCrlON 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 (Refe-rences 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 lleat Generation Rate (APLIIGR) -
Technical Specification 3/4.2.1. , c. Minimum Critical Power Ratio (MCPR) - Technical Specification 3/4.2.3.
- d. Linear IIcat Generation Rate (L.HGR) - 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 O- Technical Specification 3/4.1.4.3 and when:
- a. TilERMAL POWER is < 90% of RATED THERMAL POWER l- and the MCPR is < 1.70 or
- b. TIIERMAL POWER is.2. 90% of RATED THERMAL POWER-
,g and the MCPR is < 1.40. , >%)
- Revision 0 1 April 1994
9
, Plant Hatch Unit 2 Fuel Cycle 12
. Core Operating Limits Report O
3.0 APLHGR 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: l
- a. The factor given by Figure 3-1 or l \
l
- b. The factor given by Figure 3M l 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.
i As required by GESTAR Amendment 19, the hand-calculated APLHGR values for a multi-lattice (i.e., GE8-296 and Gell-LUA) fuel must be less than or equal to the APLIIGR limits shown in Figures 3-4 and 3-7, respectively. When .O ^ v ' " o n v"i"e> =re determi"ea 8 the 7 vroee>8 ee m n"ter the iettiee-dependent 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. l l l i, O O. Revision 0 2 April 1994
Plant liatch Unit 2 Fuel Cycle 12 Core Operating Limits Report J b l g y 4@ gD 187 64 O / / / igp os f' ~< / s is ,% eA A M $ t OW = $ $ I 0% e so - 0M --- - -
- O to -
M apt HORg = MAFT ACg
- M APtHORSID j M apt HGRggy = ST AND ARD M APLHOR ttMITS I M APT ACg = MINIMUM (MFRM)g, M APMULT,5
! MAPMULT = 10 FOR f LOW > 81%
= 0 88 FOR ILOW s01%
[i MF HPD,IFl = MINIMUM l10,Ag + B,Fl U ' 'O , F = FR ACilON OF R AllD CORE FLOW, AND A 7. ByARE FULL TYF'E Of PENDENT
- CONST ANIE GIVEN 8tt0W:
b F OR 7 X 7, M b M A ktMUM 8X8.8X8R RX9 lfA8 j 3 CORE FLOW i g 'F s o *o - is R Anni "F 'F ^F ; 102 6 04898 0 8667 04861 08784 107 0 0 4421 08633 04674 0 8768 112 0 0 4074 08681 0 4214 0 8807 117 0 0 3701 G 9666 0 3878 0 8888 e $o - 1 p 1
%) \
l oe 1 i i i i i !
- a
-l .,
C O Af f l ow it R a lf t)) FIGURE 3-1 MAPFAC r .- Revision 0 3 April 1994
, Plant Hatch Unit 2 FucI Cycle 12 Core Operating Limits Repod \
{- I' tu .-. M A Pl ltG H, e M APS A(,
- M APL HGM
-- M ape teGH
,g o S t aND4RO M APl HGH t tuill 0 0H 7%% D P 6,t) I' 6g( Hu Al 4 4 Mill M(INil OH tND Hl ull4 Hl O 6%lO Il4H Nt) { tusi1 $Pf L 68 et D 0v - Q p
$ ( p H /*a %LF(Jh T
f %t 1) ItIN go' O
- . , . . . , . o s . , . 0 m. , , . , _ m , , 4p s -
4 j f flH [ 50% ( 064f f t Dev
$s
$ M AP8 at , a 0 a ll e O Ge>S 7 J 4 :P- 1%e ua f tsH # Sug C ()M t f ( On f O H )7% { F i ;
4 ISL U ti Of St O lSINGL E 4 00P Orl f4 AllON) uapf at ,
- 9 0 6 S IMMI)4 IP - 100%I 5
I 5 O H 6 2 % '. h O 0 " 'I I br# at = 0 75 i ui P J - 2 l [ ( $0% (tlHS f i OW .
$ [
t I ub - s' t l l >w%rOHssiOW I b% * ! I I I
- 1 I
l i y
- n. ..l,_ _ L __1 L _ L ___1 1 1 1 i 1 t g i ,, i
#" JS 80 40 go 60 70 30 % t oss l'ipWI M 1% H A 1i DI I
1 FIGURE 3 2 M Al'FAC,. . I l 1 1 Revision 0 4 April 1994 1
;_________________________________________.____________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____________________________________1_
Plant IIatch Unit 2 Fuel Cycle 12 Core Operating I.imits Report O 1 !O 14 4 1 UNACCEPTABLE
- i i
' t
. l OPERATION :
13 - - - - - - - - - - - - - - - - -
, , , i
! ! 6 l 6 l
g -e es ! : ,
/ 12.4 12.4 f \ t [ !
12 . /- N- - - - + - -
} / I 11.9 I l {
2 I" s' p-1,0W EXPOSURE y . l IN . {
< 11 '[ ~ '-' ' ' - ~ ~ ~ ~'~ ~ 2 COORDl M FS (~ ~~ ~ ~~ ~ ~ ~~~f -
"" l x
y \ e. 10.6 l-h 0.0 10.8 E 10 - . 0.2 10.9 - ACCEI'I'ABLE _ ___ - . - __. 2.0 11.2 s; Je 11.5 OPERATION N.\ 6.0 11.8 , l H.0 12.1 ! 9 10.0 12.3 _. _ ;; 1- - - - ^ ~ ~ - ~ ~ - -- - 12.4 12.4 FUEL TYPE: \ GE711.P8DR11284 7G4.0 8051150.T , t 8.5 0 i 1 s 0 5 10 15 20 25 30 35 40 45 Q ArcRAGE Pl.ANAR EXPOSURE (GWd/st) FIGURE 3-3 O AVERAGE PLANAR LINEAR llEAT GENERATION ItATE VERSUS l AVERAGE PLANAR EXPOSURE (Fuel Type: G E711-P8DRIl284-7G.4.0-80M-150-T) Resision 0 5 April 1994
Plant Hatch Unit 2 Fuel Cycle 12 Core Operating Limits Report 1 O L Q a
-l .--{. :l.' J 13 -- :
i- UNACCEPTABLE-e - * ( *i-
- n. 12.u : xN 4 OPERATION -
/e>4 N- -
c
.uo9
.; ; ;;j N N
- r
@ 10 ~
q i 7 N [t-y .; I-l b - LOW EXi'OSURE [ l 9.79 I l 2 - t ; I 3 ,. Mm.%HE l 4
- l l
-X .- .L l N P 0.0 11.54 I ! \-
L .
- 2 s~
~
io n.52 i i ACCEPTABLE - O 2.e 4.0
".4 3238 i
i i l OPERATION l
)
3 7 i \ 8.0 12.73 ! { i 4 ! l 10.0 12.81 l
. , __J_. I' i j 6^
FUEL TYPE: N i j GE8B-P8DQB2907GZ-80M.150-T l
! O 5.u 0 $ 10 15 20 25 30 35 40 45 50 AVERACE PIANAR EXPOSURE (GWd/st) f 'N5TE:
APLHOR LIMIT FOR MOST LIMITING
~
LATTICE AS FUNCTION OF AVERAGE 1 PLAN AR EXPOSURE
.i FIGURE 3-4 I AVERAGE PLANAR LINEAR IIEAT GENERATION RATE j VERSUS AVERAGE PLANAR EXP,OSURE O (Fuel Type: GE811-P8DQll296 7GZ-80M-150-T) l I
Revision 0 6 April 1994 1
i
. Plant Ilatch Unit 2 Fuel Cycle 12 Core Operating Limits Report O
.t(
- 1. <., Ji x e- i- .i !
- l-
~
/_, ; 13.is X e :
UNACCEPTABLE 12 -
/ J I
l 12.45 N s ..} OPERATION ( 11.79 7 g LOW EXPOSURE g_ } __ p_\ -} ~
' 'I COORDINATES I
}.
N - x y ; $ j[. d 10 - 0.0 12.01 -. l 7 10.48 \ N. b ' 0.2 12.05 l 1 ! E 1.0 12.16 ! i 2 2.0 12J1 ! ,O ' 9 _ ___d 4 3.0 913
$ ~
12.46 f 4.0 12.62
] ,
}
5.0 :
%8 6.0 12.79 12.97 I iACCEPTABLE O 7-8.0 9.0 13.32 13J6 i
t-
+
OPERATION + j l l' 10.0 13.43 6- J- FUELTYPD 12.5 13.50
; GE9B.P8DWIl314-7G4.0-80M 150-T.NOSillP at 51.9 G W d/st
, [
3 0 5 10 15 20 25 30 35 40 45 50 ' AVERAGE PLANAR EXPOSURE (GWd/st)
- (]
1 I FIGURE 3 5 l AVERAGE PLANAR LINEAR HEAT GENERATION RATE l VERSUS
' 'I AVERAGE PLANAR EXI.OSURE
- \ (Fuel Type: GE911-P8DWIl314-7G4.0-80M-150-T-NOSIIIP) )
Revision 0 7 April 1994
. Plant IIatch Unit 2 Fuel Cycle 12 Core Operating Limits Report O
I O .
; . t , 1 ;
1 j t l ;
}j I .,5 dN_ , ___.L f I I l
! ,A V 12.85 l i
;. UNACCEPTABLE l' 12.15 g lQ 12 -
7-'8 - - - j OPERATION -;- d ,, _ . - - .! !!.52 x,$ , I.- j g_ _ LOW EXPOSURE I l I f ! { g COORDINATES .
! ) {
M x y !
! i
- h L 10 - 0.0 11.55 f f 10.23 $ l J 4 d 0.2 !!.62 l
} l j l i t .0 11.72 !
j
;% ,. 2.0 nu 3
G 3.o n.oS < 3,76 s . i t 4.0 12.24
] .
, {
g8 5.0 n..u -a O 6.0 12.63 l ACCEPTABLE l l l---- j
- 7. i2.8
< H.0 12.91 ---
' OPERATION _ !
L_--__.. l
\ .d'_._
9.0 12.9M I l l 10.0 13.08 , . _ _ . . - ..;_._____._..__._______ j , 6 g;,3 3 3,g g . FU El. TYPE: '
,_i __i GE98.PNDWR314-8G4.0-bONI.150.T l 5.70 l 4p 5
0 5 10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWd/st) O FIGUltE 3-6 O avEitacE >>Easait tisE4R iiE4r GExEitarios itarE VEllSUS AVERAGE l'LANAlt EXPOSURE ( Fuel Tvpe: G E9 B-P8 DWll314-8GA.0-80M-150-T) O
~
Revision 0 8 April 1994
. Plant IIntch Unit 2 Fuel Cycle 12 Core Operating Limits Report O
1 l l
- O
~
t l 13 -
! ! 1 ,
; ! i fUNACCEPTABLE I
i2 -- ;
' OPERATION --
W
! $~ $ 11.66 !
-, l11.70 N .f ,
.l 11 LOW EXPOSURE 3 g!jf kN '
i t
-- COORDINATES ! N' ; 1 l
;; . j i 10.60 d 10 -
0.0 11.64 p- - - " : ! O 4 - 4-1Om ! b 0.2 11.70 l l E 17.5 11.70 I I I . 934 N' I 3 , l
. _ - - l_ d
% i l .
8.99 i
% ; i j
; l l i
___l ACCEPTABLE 7 7 i OPERATION ! O 7 - - - - - - - - - - - - -- i l i
-----+--j--
l
-j 6 - - - - - - - - --- . FUEL TYPD (GEllLUA) ,7 G E l l .1911 U B293 7 G5.0/l G4.0 10051 146.T.1,UA i
0 5 10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWd/st) O 'NdTE: APLHGR LIMIT FOR MOST LIMITING LATTICE AS FUNCTION OF AVERAGE PLANAA EXPOSURE O nGUitE 3 2 AVEllAGE PLANAll LINEAll HEAT GENEllATION IRATE VEllSUS q AVEllAGE PLANAll EXI?OSUllE v (Fuel Type: G El1-P911Ull293-7G5,0/lG4.0-100M-146-T-LUA) Revision 0 9 April 1994 m -_---_m__ _ . _ _ _ _ . _ _ - _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _
.- .- = .--
l
, Plant flatch Unit 2 Fuel Cycle 12 Core Operating Limits Report lO l l
O ex;XT i i 1
'~
1 1
: p* 7 13.14
- . UNACCEPTABLE :
8 12.44 ' Kx : OPERATION: i2 - , i 11.79 I,0W EXPOSURE l ' l J + COORDINATES .j _ g -
\ e.}'
x y s - 3 l 10.47 l f
- 10 - -
0.0 11.80 b
- 0.2 11.87 i 11.98 l 5
4 1.0 i J 9 2.0 12.15 . !
! l 9.13 h 3.0 12.33 f l 4.0 12.52 i i
] )
g 8- - 5.0 12.72 l ;
- ACCEPTABLE-tj 6.0 12.93 i ;
!O 7- - 8.0 13.20
! i OPERATION j
l j y 9.0 13.28 l l' 10.0 13.38 , l 6- ; FUEL TYPD 12.5 13.48 5.89 j GE9B.P8DWB314 8G4.0A40M 150-T
! l l 5 . ,
0 5 to 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWd/st) O FIGURE 3-8 AVERAGE PLANAR LINEAR 11 EAT GENERATION RATE VERSUS AVERAGE PLANAR EXP.OSURE O (FU EL 'IYPE: G E911-PSDWil314-8G4.0A-80M-150-T) Revision 0 10 April 1994
. Plant Hatch Unit 2 Fuel Cycle 12 Core Operating Limits Report
- O 4.0 h1CPR LlhilT (Technical Specification 3/4.2.3)
The NICPR operating limit (OLh1CPR) 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, GESB, and GE9B fuels, and 1.28 for Gell fuel. Os 4.1 Two Recirculation Loon Operation For 259E.1 power < 309c, the OLMCPR is given in Figure 4-1. For power 2. 3092, the OLhiCPR is the greater of either:
- a. The applicable limit determined from Figure 4-2 or O a. The everegriete ur 8 ivee ie risere 4-1. meitivirea hr the appropriate limit shown in Figure 4-3. The scram time dependence is given in the Bases for Technical Specification j l
3/4.2.3. 4.2 Single Recirculation I 000 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. O Revision 0 11 April 1994 1-
. Plant Hatch Unit 2 Fuel Cycle 12 Core Operating Limits Report O
O l 2.6 - , , , ;
> 50% FLOW 7 3pERATING LIMIT MCPR(P) = Kp
- OPERATING LIMIT MCPR(100) l _ FOR P < 25% : NO THERMAL LIMITS MONITORING REQUIRED 14 NI NO LIMITS SPECIFIED _
g 3; FOR 25% < P < P mus (WHERE P mas = 30% FOR HNP 2)
$A% 23- Kp = [Km + 0.02(30% - P)]/OLMCPR(100)
V AND A k 2.2 - -- - Km = 2.00 FOR < 50% CORE FLOW L VjE -
<50% FLOWr- K "= 2.40 FOR > 50% COPE FLOW
~
$ $ 2.1 -- ' ' FOR 30% $ P < 45% :
Mg Kp = 1.28 + 0.0134 (45%-P) t2 FOR 45% $ P < 60% : - Kp = 1.15 + 0.00867 (60% - P)
@m g E2.0 - -13." g L '
FOR 60% < P : [ f:g ud
-~
Kp = 10 + 0.00375 (100%-P) 71 O. i.4 _ _ _ . _ _ . _. I I O 13 ; l ! f ' 1.. 3 1.1 IbYPASS- ! i 1.0 20 25 30 40 50 60 70 80 90 100 POWER (% RATEl)) O FIGURE 4-1 POWER-1)El'ENI)ENT MCPR MULTIPLIER (Kp) O Revision 0 12 April 1994
. Plant Hatch Unit 2 Fuel Cycle 12 Core Operating Limits Report O
V O l l l 1.7 l
/3 MAXIMUM F14W RATE =
Q } 117 % FOR We (% RATED CORE FIDW) > 40% , MCPR(19= MAX (1.20, AfWc/100+B0 ' 112 % 1.6 -\ / _ /' / ,
- 107% MAX FLOW Af Bf
/ / - 102.5%
- 117.0 -0.632 1.309
/ ; 112.0 -0.602 1.747 1.5 '
4 . 107.0 -0.586 1.697 L
\.! i /,
'/ l 102.5 0.571 -1.655 y ! / ;
h ! O ' i 1.3 . . _. d__ l l .
+ - - -
l t 1.2 -- FOR We (% RATED CORE FLOW) < 40% ,l j MCPR(F)=(AfWe/100+ BO ; i
* [1 + 0.0032(40.We)] i l l
1.1 - 30 40 50 60 70 80 90 100 110 120 fg CORE FLOW (% rated) U i FIGURE 4 2 FLOW-DEPENDENT MCPR LIMITS (MCPR y)
.O Revision 0 13 April 1994 )
i
Plant Ilatch Unit 2 Fuel Cycle 12 Core Operating Limits Report (~ lU 1.29 . , . < ! ! ! ! ! l l l i l l l l f ! l ; I l ! I '(O 1.28 )
; Gell
]i l l
- t l [
l 1.27 +- -
-; ; , q
------ 7 '
, ! I l l
/O j !
,0 l l I 1.26 - +- W 4 i i
$ i i O ,
i t i f . I i l C 1.25 . W r-i i I e
$ l ='
' ; i '
l [ GE9B ; i ! i t 7 1.24 - - - - - - - - - - - +--- . .i j ' i: > l , l Q l ; ! < C l l' i a 3 23 _ _ _ . . . _ _ - _ . _ _ . I l N , i ! . g ! l
- t j
< .22 ___ _. . .;__ _1. GE711 AND L i I
u i i I 5 '
; GE8B i .
c f 1.21 - u ' E , i 1.20 - _ _ _ _ _ _ _ . _ _ _ . . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ o : C ! ! 1.19 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0,7 OE 0.9 1.0 TAU 1 FIGUltE 4-3 l p N1CI'It LIN11T AS FUNCTION OF AVERAGE SCitAM TIME l d I i Revision 0 14 April 1994
Plant Hatch Unit 2 Fuel Cycle 12 O Core Operating Limits Report O 5.0 LHGR LIMIT (Technical Specification 3/4.2.4) L The LHOR limit is 13.4 kW/ft for GE7B fuel. The LHGR limit for GE8B, GE9B, and Gell fuels is 14.4 kW/ft. (O l i
6.0 REFERENCES
- 1. " General Electric Standard Application for Reactor Fuel," ,
NEDE-24011-P-A 10-US, March 1991. l
- 2. Letter, L P. Crocker (NRC) to J. P. O'Reilly (GPC), " Issuance of
( Amendment Nos.168 and 106 to Facility Operating Licenses DPR 57 and NPF Edwin 1. 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 11, Cycle 12," General Electric Document 23A7241, Revision 0. April 1994.
- 4. "Edwin I. IIatch Nuclear Plant Units 1 and 2 SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis," NEDC-31376-P, December 1986.
- 5. Edwin 1. Hatch Nuclear Plant Unit 2 Technical Specification _s, Bases 3/4.1.4.3, 3/4.2.1. 3/4.2.3, and 3/4.2.4.
O Revision 0 15 April 1994 _ _ - _ _ _ _}}