ML20128D323
| ML20128D323 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/01/1992 |
| From: | Zeringue O TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-92-01, GL-92-1, NUDOCS 9212070224 | |
| Download: ML20128D323 (10) | |
Text
.
.; g 4
d trem von /#w, ma eu a w arn tw urna.en :un December 1, 1992 O J "lW Zenngue w, %su mms r.m o m e m U.S. Nuclear Regu!atory Commission ATTN:
Document Control Desk Hashington, D.C.
20555 Gentlemen:
In the Matter of
)
Docket Nos. 50-259 Tennessee Valley Authority
)
50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - COMPLETION OF COMMITMENT MADE IN RESPONSE TO GENERIC LETTER 92.-01, " REACTOR VESSEL STRUCTURAL INTEGRITY"
Reference:
Letter from TVA to NRC dated July 7, 1992, " Browns Ferry Nuclear Plant (BFN) - Sequoyah Nuclear Plant GQN), and Watts Ba/ Nuclear Plant (HBN) - Response to Generic Letter 92-01 (Reactor Vessel Structural Integrity" In the referenced 1etter, TVA committed to provide the staff a summary-evaluation of BFN's accumulated fluence at operation below 525'F, the affect on the reference temperature,.for nil ductility transion-(RNDT) and the effect on Charpy upper shelf energy.
The enclosure contains the evaluation results.
There are no commitmerits contained in this letter.
If you hate any questions, please contact G. D. Pierce, Interim Manager of Site Licensing, at 20E-729-7566.
Sincerely,
?-
/
0- J. Zeringue Enclosure cc:
See page 2 l
y L
G7n004 gy
~9212070224'921201 l\\ p
- PDR :- ADOCK050002J9
.e
- 2
,zU.S: NuclearfRegulatory; Commission.
December-1, 1992 i
-En.losure cc (Enclosure):
=
fiRC Resident' Inspector Browns ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611 Mr. Thierry H. Ross, Project Manager
~
V.S. Nuclear Regulatory Commission One White Filnt, North
-11555 Rockville Pike Rockville,.Haryland 20852 Mr B. A. Hilson, Project Chief U.S. Nuclear Regulatory Commission Region 11 101 Harletta Street, NW,-Suite 2900 Atlanta, Georgia 30323 S
t 1 :-
P L
t E
q
' ~
ENCLOSURE BROWNS FERRY NUCLEAR PLANT (BFN)
REACTOR VESSEL STRUCTURAL INTEGRITY Summary _oLAccumulateILfluence_below_525 E A review of the Browns ferry recirculation suction temperatures for the most' recent cycles of operation for all three units has been conducted. The cycles chosen for evaluation are Unit 1 Cycle 6, Unit 2 Cycles 4, 5 and 6, and Unit 3
-Cycles 5 and 6, which are considered typical for BFN operating cycles. Data for U2C6 included operution through October 20, 1992.
For Units 1 and 3, the summary includes the last full and/or partial cycle of operation before shutdown. The data, given in Tables 1 through 6, are presen% d as a summary of the cumulative fluence as a function of the number of days or core critical0 operation at each degree Fahrenheit of recirculation temperature below 525 F.
The values given are. considered conservative-In that each day the reactor log indicated operation, a full day of core criticality was assumed.
The number of days at each degree of reduced temperature is adjusted to reflect effective full power days (EFPD) based on the indicated reactor operating power level as.
a percent of full power.
The fluence per EFPD (at 1/4 thickness) is based on 1/365 nr the EFPY data contained in the reference.
This analysis shows the three BFN reactors to be operated in a similar manner.
0 with the recirculation suction temperature typically n the rang: 525 to 528 F 0
at full or near ir l power. Operation-below 525.' is attributable to transients, lind u.d low power operation and coastdowns preceding refueling outages.
The summary data for individual cycles given in Tables 1 through 6 0
showtheaccumulatedvesselflgnceattempegturesbelow525fforindividual to 1.8 x 10 n/cm cycles to range from 0.46 x 10 t
fflec.t_on_ Refer 1ncLIemnerature L
The effects of irradiation on embrittlement are normally quantifled through the evaluation or credible surveillance data in accordance with Regulatory Guide 1.99, Revision 2.
However, the first surveillance capsules containing i
- Charpy specimens are not scheduled to be-removed from the BfN vessels until the end of each-unit's cycle which most closely approximates 8 effective full-power years. This projects the initial-capsule-removal for the BFN to be.
at the U2C7 refueling outage (one additlor,a1 cycle).
'tT"Y-D-w a semee Pi T-uP v-c=
- =F-r "a'w
-Ti-ed 63
-r wF-r may-y T+d--
- --M-6
~
' ENCLOSURE (Continued) i BROWNS FERRY NUCLEAR PLANT (BFN)
REACTOR VESSEL STRUCTURAL INTEGRITY The controlling materials for the reactor beltline regions are the circumferential weld WF-154 for Unit 1 and the vertical electroslag welds
<eams for Units 2 and 3; During the records review for establishing reference temperatures for the beltline materials, specific test results for the electroslag weld snams on the three vessels could not be determined.
Likewise. specific est data for the Unit I circumferential weld scam could not be established.
As a result, the bounding value for procedure qualification records at the time of fabrication of the she'l courses were for the electroslag welds, and the generic bounding value adopted as the RTNDT for B&W submerged arc weld metal was adopted as the weld WF-154 RTNDT. These bounding reference temperatures in lieu of actual test data are considered conservative.
Therefore, TVA believes that an adequate margin currently exists in the initial RTNDT values to compensate for the limited fluence 0
exposure below 525 F of the Browns ferry vessels.
When credible surveillance data from the surveillance capsules, becomes 0 available which envelopes those periods of time for operation below 525 F for the Browns Ferry vessels, the actual data will be used to determine the significance of the low temperature operation.
EffrLan_UpneriShe1f Energy (J5E)
As summarized l'n Table 1 of the reference letter, all initial upper shelf-energy values for Units 2 and 3 exceed 75 ft-lbs and each are predicted to exceed 65 ft-Ibs at End of Life (EOL)-(32-Effect Full Power Years CEFPY]).
The 15+ ft-lb margin is considered adequate until credible USE data can be obtained at 8 EfPY, Unit I circumferential weld WF-154, which was fabricated with Linde-80 flux and is characterized by bounding chemical and mechanical parameters, is predicted to have an upper shelf energy of 50.8 ft-lbs'at-32 EFPY based.on the methodology of Regulatory Guide 1.99, Revision 2.. When evaluated on the basis of BAW-1803, " Effects of Neutron Irradiation on Linde-80 Weld Metal Upper
-Shelf Energy," a prediction of 56.8 ft-Llbs forLthe USE at end of'llfe-(Enclosure 1 Section 2.a. of the reference letter).
Based on the latter evaluation, TVA considers Unit 1 beltline materials to have adequate USE margins.
1 I
e
>+J--
+-
4-.-.
a-
-~... -.. -
DFH 81EACTOR VESSEL STRUCTURAL INTEGR!iY Table 1-
$UMMARY Of ACCUHULATED 1/4T FLUEN;E FOR RECIRC $Ur. TION TEMPERATURE DELOW 525'r-DIN UI CYCLE 6 1
Days at l Average Power lAdjustedEffectliel Estimated" l
Cumulative- ]
TMstrat.UIt__l Lett 1 lJull f9xtLfayL l -
Figence l
'T I
l(%offullpower)l l (n/cm per EfPD' x100_)_. l flygo_tx10 k l.
ltTRerAtyte_l E
1 2
l (n/cm l
l l.-
I-
'I l-1 I
I
-l i
i 105d-50611-0 1
O __ _ I n
l-0 l
0 1-1 i
-1 I
I I
1 J
1-0 I
o 1
0-1 506d:5aLLL 0
I I
I I
l-1
- 50Ld=50all 0
1.
O l_
0 1
0 1
0 l
I I
I I
I I
5ea,5:509 1 L..
2 I
O I
0.
1 0
'I
-0 1
I I
I l
l-l-
50hi:51Rd.l_.
D._
l S
l 0
l 0
._ l 0
l 1
I I
I I
I 5 1 5:51 h li 1.
l 0170 l __
0.7 l
51 l
_0A05 1
I I
I I
i
-1 illd-51211 3-l OJ3 I-1.9 l
13.9 l
2 419 l
l l
l l
1 l
E1215At31l 2
i Od5 l
13 l
9.5 1.
0.028 l~
1 l
I l-1 I
l 5134:hWLi.
I
_l 0 10 l
1A I
J013 1
0J39 I
l l
l l
l l-
.._ l DJO l.
ZA_
_]_
17.6
_1 0J56 l
5R5:11111 4
l l
l 1 l-
$15d:11hil 5
1_
0 2L l
_L5 l
2L7_
l _ _q 082 1-I I
I I
I I
SE5-51L5_l
_U
_l 0J5 60 l
44 0 l'
O.13 l
1 1
I I
I I
I
. 51Z d:510 1 L l
1
-0.77
-l 5.4 l
3h6 1
0,27 l
1 1
1 I
1 I
e 0J15 l._
ZJ l
19.8 1:
Od9 l
ElBJ-51h5l.
l l
l l
1 i
112d:52LLl 14 l
0 0L i
11.3 l
82.9 l'
O.21 l-1 I
I I
I I:
SZLS:52LLI.
6
_l 0,09 I
ImL 1.
52d 1
0.J2 l
I I
I I
I' I
5 i-DJS
'l 4. 3.
I 31.5' I
0.35 l'
I I
i l
I-I-
b2Zd:5231]
15 l_
0,97 l__
14.6
- l __
107.1 l
0.46 l.
I I
I I
I l--
- 523J:5&Ll
- _13 1
0.99 l
42.6 l
312.4 l
0.77 l-
"EFPD = Ef fective Full Po.sor Days 6
EstlWed 1/4T fluence per EIPO m 2.677 x 10 /365 x 7,33 x 10 n/ car d
.... - -..-. ~....... - -.
OfN REACTOR VESSEL $TRUCTURAL INTEGRITY
-Tabla 2
SUMMARY
Of ACCUtfJLAT[D 1/4T FLUENCE FOR RECIRC SUCTION T[MPERATURE BELOW 525'r BfH U2 CYCLE 4 l.
Days at
'l Average Power -lAdjustedEffectivel Estimated "
ll LCumulative l.
D)-ll -
ltrRCIAtil.EC I itTPetalure I
level l _h11 Power Days l
Fluente l
Flu ne
- f
-l
. l(7 :f full power)l l-(n/cm per EfrDI x1013) l (n/cm x10 2
l l
1
_1 1
-l
/-
1 I
I I
l I
_1 l
0.60 1
-0.6 I
38
[
0.0038
-l 1
1 I
I
-l l-l
$ES:50LLI-1 l-L20 l
Q,7 l
4,4
-l 0 00a2 1-l l
l l
l 1
50L5:500,5_l.
O I
Q l
0 l
0 l
0JOS2 l
1 I
I I
I I
500,5:5 E Ll
_Q l
J l
0 l_
0
-1 0,0032 l
l l
1 l
l l
50L5:5101.1 -
3 1
0.73 l
2.2 l
1318 1
0.D22
-l 1
I I
I i
.I 515:llid_l 3
i_
DJL i
1.8 l
11.3 l
0.033
-- l l
l l
l
- I~
h1L5:512 Li 1
_l 020 1
01 l
44 1
0 J38 l:
1 I
i l-l-
1 51L5-513J_l 2
l odQ l
1.4 l
8.8 l
0J46 l
4 l
l l
l 1
l-513J-5141Ll 3
l 0.77 l
13 l
14,4
[
0.061-l:
1 I
I I
I l-514dd1hLl.
6
,_ I 0.78 l
4.7 l_.
22,5 l
0.090
_I I
I I
i 1
l 511J:515A.l 2
l 0.60
.I 1.2 l
7.6 l
0.098
-l_
l 1
l-l
.l-
.l.
5& h511tLl 6
l 0,17 l
4.6 l
28.8-l 0.13
-l:
I I
I l
-l-51L541LLl_
11
_l 0.84 l
9.2 1
57.7 l
0.18 l-I l
I i
l l'
110J:51LLl-8 l.
- L29 l
6.3 l
39.5 l
'0,22 l
I I
l l
l 5&5:5204Ll __
8 l
0,20 l
1.Z__
_l d5.1 l
0.27
- l i
l l-I
- I
-l
'I-
- 52LE:51LLI 18 i
OJ4 1
16.9
[
101 0 l
Laa _-
1 I
I I-
-I I
I 5;L5-522ill 44 l
0.21 1
4L2 l
264.'6 l
0.64 1.
I I
I l
=1-5ZL5:5ZLLI 64 l.
0 99 I
63.6 l
.397.5 i
_l l
l 1
1 1
1:
5th5MhLl 120 i_
0 99-l 11915
[.
744.9
'l "1.7a l'
4
'EFPD z Effective full Power Days 16 I3 2
"Estime' *.. < 4T fluence per EfPD = 2.287 a '10 /365 = 6.27 x 10 n/ m g
k
BfN REACTOR _ VESSEL STRUCTURAL IMTEGRITY iy Table'?-
SUMMARY
Of ACCU'fULATED 1/4f FLUENCE FOR RECIRC SUCTION TEMPERATURE BELOW 525'r BfN 04 CYCLE 5 l'
Days at l.. Average _ Power lAdjustedEffectivel~
Es'timated l
Cumulative' l.
'I 33)l Flugnsx10 k l ItMarJlert.l_ ltmp1EAlstti I
__Lt1tL I_fJtll_hwer._D#ys _ ]
Fluente 2
l (n/cm f
l l(%of_fullpower)l l.(n/cm per EfPD x10 O
_._ I I
l-L I
1 1.
I-l-
I l-l M5a:5aLLI 0
1 0
L 9=
1 0
1 0
1-1 I
I I
I I
'5944 50 /,Ll
_L_
l._
0 l
0 l
'0 l'
0 l~
l i
I I
l-l-
10L5:591Ll
.0 1
0 1.
0 l
0 1
0 I
I I
I I
I l
Staa=s9.Ll
)
I L40 1
04 I:
L3 1
0.razs I
a924-3]cd l.
4 1
020__
l i
I l
I 1
1 z.4
_I La l
Lola.
1-1 I
I I
I I
SlL5:511,3_l _
23 l
940 l
168 l
86.5 l
0.10 l
1 I
l-1 I
l-h]L5:5]Pd l 15 l
QJ1 l
9.2 l
57.7 l
0.16 l'
I I
i i
l I
sizath1LLI._
is l_
- Lsi.
l_
sa
,_ I si.4 l
0.22 l
1 1
I
-l 1:
1 513. 5-514. Ll _ __
14 l
0,64 l
9.0 l
56.4 l
- 0 20-l' I
I I
I
-l I
l l
~ 0 52 l
13.0 l_
81.6 l_
0.36_
514.5-515, LI 21 Sl5d:bir.Ll.
7 l_
0.61
]
4.3 l_
l l-1 I
I I
28,0 l-0.39 l
n l
1 1
I I
I hlLS:51L Ll_
- 12 l_
QJ7 l
8,0 l
50.2 l-0.44~
-l 1
1 I
l-I l--
$12J:51LLl 13 l-0,E6 l
8.6 l
53.9 l
0.49 l'-
1 I
I I
I I
Elgd: SILL l 19 l
0.67 l_
J2.7 l
79.6 l
0.s7 l
1 1
l l
I l~
$JLS-32LLl 23 l
0.62
_l 10 l
62 7 l
0.66 l
1 l-I
-l l
l 3RQA-5Z11.l 13
_ DJ8 8.0 l
SL2 '
l 0.72 l_
2 i
I I-I I
521.5-522.Ll 20 l'
O.n l
1s.4 l
96.6 l
0.81-
[.
l-1 I
I I
l
~
52L5mLLI 18 l_
0,89-l-
16.0 l
100.3 l
0.91 I_
l i
I I
I l-
'3L5:52id_l_
42-
.l 1 39 l_
41.6 l
260.8 l'
1.17
-l
- EFr0 = Ef fective full Power Days 16 33 2
- Estimated 1/4T fluence per ErPD = 2.287 x 10 /365 = 6.27 x 10 n/cm 4
e a.
e,,
e
.e w..
n s.
,.c-4
7
.- _ _ _ -. _ _.. _ ~., _... -
.m_.
- DfN REAC10R VESSEL STRUCTURAL INTEGRITY
.u.
-Table 4 SUttiARY Or ACCUNULATED 1/4T rLUENCE FOR RECIRC SUCTION TEMPERATURE BELOW S25'r-;
BrH U2 CYCLE 6 l
Days at l Averag'e Power lAdjustedEffectivel Estimated-l Cumulative l
- Llewerature_i__lempentere
.l --
Lent
_l hlLtower_ht._ I
- rivrote_,
U_)l1-(n/cmr19gnsqkl 2
l(%ofrullpower)l I (n/cm per ErPD. a10 x10 l
r l
I l
I.
l I
li:
I i
i I
I
= l:
50LS:50ia_l ~
0 I
o I
_-- O I
O l-0-
l-1 I
I I
'l l
5005:50LLI 9
_I O
i 0
l_
0 l_
0 l-1 I
I I
I I
I-0 1
0 l
50LS-50LLl_ _0 1
0_. _._I 0-l' I
I I
I I
I-0
_I o
l O
I-0 l
I I
I I
l
-1 sa%5-fdod_l
_.9 l_
0 1
0
__l 0
1 0
l-4 1
I I
I l-I ilL51112Ll D
l 0
1 0
l_
0-l 0
l l
l l
l l
l-11L5:51LLI 1
l L10 _
l 0.7 l
4.4 1
0J044 I
I I
I I
I
-1 ilZJ:51L5_l 0
l_
0 L
0 1
0 l
- 0. 0a4. 4 l
I I
I I
i 1
- l LZ3 l
L2 l
12.8 l_
0.018 l
'. I
- l i
l 1
l
')
__J.
l _.__S J3 l
lJ l_
1hD l
0.Q28 i
1 I
i 1.
.1-115d:!il6,LI'
.___3 l
0J0 l_
1.5 l-9.4 1 -
DJ38 -
[
l 1
l i
I I
516.5-517.5l 12 l
QJ9 l
8.3 1
52.0 l
0.090 l
l l
l l
1
.I 51L5:51LLI 13 l
0 72 l_
9.4 l
-.Iad 1
0.15 l
1 I
i l
i l
i 11ad:SlLLI 7
l OJO l
s.6 1
35.1 l.,.
0.18 l
I I
I I
I l
51L5:52DJ_l_
_4 I
LZ15_
l 3,1 ~
l 19.4 1
0220
(
l-I i
l 1
1 l
52h5:511J_l 6
l_
hao l-4.a _ -
l 30.1 l-0 23
'l l
I I
I I
l-L il1J:52hLl 11 l_
0.745 i
LZ l
51 4 1
0.ga~
l l
l 1-1 I
l l-l 52LS:52JLLI
'7 l'
O.74 l.
'52 1
JL6 1
0.32 l_
-1 1
I
'l I
i l-
_$13 d-12_4 A l 24
__l_
0.975 l
23.4 l
1.45 7 1
DJ6
-l~
l'
- ErPD m Effective rull Power Days.
16 13 2
" Estimated 1/4T fluence per ErPD.: 2.287 x 10 /365 = 6.27 x 10 n/cm I
i.
i-l
~
L
+-.-wabe w
m-w'w w
e
'M-le dem'--
awe y.a
=+
myg.r3 g
a mW tw g
y
("
.BFN REACTOR VESSEL $1RUCTURAL. INTEGRITY.
Table 5 sl
$UMMARY Of ACCUNULATED 1/4T FLUENCE FOR RECIRC SUCTION TEHPCRATURE BELOW $25'r BIN U3 CYCLE 5 l
D'ays at l.AveragePower lAdjustedEffectivel Estimated" l
Cumulative l_~ J; (n/cm' n10 k lrio i
itsenture_l Testuivtr__l taxel.
l_Iull_Ecrer_D m _ l r1uese l
2
'f I
l(%offullpower)I I (n/cm per EFPO x10 l
-l l-
_l l
1
_.I I
I I
I l
-l-SEL:5 ell 0_
l 0
l-0 l
_0 l-0 l
i l
l I
l --
l-50u-50LLI
_s
__._ I 0
I o
l__
o l
L I-1 I
'l l-1 I
Snu-50LLI
-o I
o l
O I
o I
o-l-
1 I
I I
I l'
50 u :59 M l-
.0 I
o I
o I
o I
o 1-1 I
I I
l-ll 50u:5L1 l_
o l-o I-o I-o I
o I
1 I
I I
I I
sms-sii.sl 2
l_
omo l
_Lz I
7.4 I
o.co74 I
I I
I I
I i
l odo i
L3 l
9.2
_l 0.017 l
l l
l 1
-l
-l SILS:5ELI 2
__ l 0Jo_
l _ _-
L_4 i
ad_
i OJ25 l-I i
i l
I ilM:51M_l_
3 l
odo l
1.8 l
11.1
- l.
o.036 l-1 I
i i
l; SRE-115aLl 6
- l 0.75 l
4. 5.,
I Z2 7 l
0.064 l
I I
I I
I I-SE5-ILLI-5 l
-Oda l
L4 l
24.2 l
o.08L l
i I
I I
I I
ELi-5LLI _
6 1
0;78
[
41
_I 28.9 l
odi' ll 1
1 I
I I
l 11L5:5m tl 9
I o.ea l
7.z i
44.3 I
a.16 l
I I
- l l
l l-1510J:5 E Ll_
s 1
0,80 l
4.3 l
26 4 l
0,10 l-1 I
I l-I l-t-
7 l
La7 l
6J l
37.5 l_
o.22 If lE1L5:520J !
I I
l-I.
I l-:
5204:51L.Ll -
0 l
OMS I
7.0 l --
43.0-
-I_
o.26-I I
I I
I I
I 5ZLS:522 i_l 2
l o.92 l
oJ l
51,0 l
oJ2
-l:
I i
1 l
.I I
l_._.0 41
.1
-- 52Zil:5ZLLl
._.17 1
DJ15 l
15J -
'l
_i' l
I:
i I
I i
5Zh5-52.4 Ll _
26_
l o J55 l_.
25 1 1
151 4 l
o.57 l_
"EFPD = Ef fective full Power Days
~
II I3 2
" Estimated 1/4T fluence per ErPD 2.245 x 10 '/365 = 6.15 x 10 n/cm l
l' l
.?
I I
n-.~...-
-. -_-.~....-. - -.. ~..
~
i BfH REACTOR VESSEL STRUCTURAL INTEGRITY Table 6 i
'$UMMARY Of ACCUMULATED 1/4i rLUENCE FOR' REC!RC SUCTION 1EMPERATURE DELOW 525'r' BrH V3 CYCLE 6 l
Days al
- l. Average. Power'lAdjustedEffectivel Estimated 7 i
Cumulative
-l-Ierperature.1 impe ra tuts._._.1 terel 1_Lu1Ltower_.Dus _.!
_L19en [e_ 2 k l (n/cm-riugsq5_)
l 2
'f.
l l(%ofFullpower)I l-(n/cm per Er x10 1
l i
I I
I i
l' i
l i
I 50h5-5ELI Q -
I Q
l o
l~
0 L.._ J I.
I l-1 I
I I
LES:50Lh_l 0
1 0
l 0
l 0
..- l 0
l-1 I
I I
I I
50L 5-50011 0
l
_9 l
0 l
0
- 1. _
0 l
I I
I I
I l-50LS:5DLLI 1
1 OJO I
DJ l
3.7
_l 0J037 l
l 1
1 I
I I
50L5:51011 1
1 0.60 L.
0.6 l
J.7_
'l 0.0074 I
I I
I I
I I
510d=5JLLI O
l 0
l
_0 1
0 l
0J274 J:
I 1.
I I
I il-EIL5-51Z11.
Q l
_A -
1.
O' l
0
_l' DaQL4 I
I I
I I
I IL 512.5:51311__
0 1
0 l_
0 1
0 1.
0 0014 l
1 1
1 I
I I
l-513d:51411 Z
l 0 <61 l
1.3 l
Bo I
1 41E
.l i
I I
i 1.
il?
51A&5154_l-.
_Z
' ul Qd5 i
Od i
is l
DJ21 1;
'l I
I I
't 1
515d 5LLI 1
1 0 30 l
OJ...
L.
1.8 l
- LO23
- I-1 I
i 1
l I
115:531.11 0
l~
0 l_
0 l
o --
ll 0.023
_1 I-1 I
I l
1-111J:51011-1 l
0,10 l
_h7 l__
41 l
'0.227 I
l l
l-l-
-l l
h & 5:519.5l.
0 l
0 1
0 l
0 l
0.027
-l 9
I I
I I
I I
51L5-520 1 1 1
1 0,30
.I OJ-L 5, s L
_ 0,032 l
l l
l 1-l I.
52QJ:5ZLLI 1
_l 0,90 _,_ _ l 0.9 I
5.s
[
0.03a
{
1 1
I I
-I.
I 5ZL5-5'lZ11 q
l 0
l_
0 1_
0 1
DJ38 l.
I I
i-1 i-I 522 d:523 1 1
._4 I
^Ji j-
-_._.LD L1 23.4'
-l' 0 00
-l-l-
1 I
l-I i
t; 513J--514.1.l._ _ ___lG -
__l
. _0Ja6 l.
_.E3 1
J 0D42 f.__
'O.I6
.I e
, Plant shutdown duri_ng Lycle_6 EFPD z Ef f ective full Power Days 16 l3 n/cd
" Estimated ?'4T fluence per EFPD = 2.245 x 10 /365 = 6.15 x 10 PLLIC207/tB3 i
el8
~.
..