ML20037B346
| ML20037B346 | |
| Person / Time | |
|---|---|
| Site: | Dresden |
| Issue date: | 09/13/1973 |
| From: | US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML20037B345 | List: |
| References | |
| NUDOCS 8009150616 | |
| Download: ML20037B346 (3) | |
Text
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ATIACEMENT A CHA' IGE NO. 26 TO TEQEiICAL SPECIFICATIONS LICENSE No. DPR-2 COMM0 WEALTH EDISON COMPANY j
_ DOCKET No._50-10 1.
Revise Item 2 - Nuclear Core of Section B - DESIGN FIATURES to read in its entirety:
2.
Jiuclear Core F.nvimum core diameter (circumscribed circle) 129 in.
Maximum active fuel length, cold 112 in.
2 Marimum number of fuel assemblies by types:
Type III 36 Type III-F 52 I
Type V 82 I
Type VI 78 Type VII (equivalent to Type VI) 85 r
Type VII-Pu 11 Type VIII (equivalent to Type VI) 120 Type IX (equivalent to Type VI) 50 Maximum total number of fuel assemblies 483 The reactor may be operated at any power up to and including rated power with any configuration of the varicus types of fuel assemblics loaded essentially in a 1 in 4 scatter of fuel, provided the maxicum nuraber of assemblias is within the limits specified above.
s CrTICE >
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=* = "- i* -m '
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s m uc.u. % M r Arcu c:a 80093gg
2-2.
Revise Ite:: 3 - Determination of Maximum Reactor Powar of Section D
POWER OPERATION to read in its entirety:
3.
Determination of Mav4 mum Reactor Power he rated power of the reactor shall be limited to a t:axic:um steady state value of 700 E(t).
The==vimna# steady state heat flux shall never c::cced 360,000 hTU/ (hr)(f t ).
The reactor shall be operated within the above limit such that a =4ai=2m critical heat flux ratic of at least 1.5, evaluated at 125% of rated power, will be maintained in the fuel closest to burnout based on uniform steam quality over the cross sectinn of each channel. This critical heat flux ratio shall be based upon the correlation in Edison's "Reconsnended Curves of Burnout Limit for Design and Operation of Boiling Water Reactors", dated s
January 5, 1962.* The reactor shall be operated always well within the bounds of stability, as evidenced by the operation itself and any experimental data produced.
3.
Delete Table II (revised 9/25/70) and replace with the attached Table II (revised 10/4/72).
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o TAbiEII-Dic.L178 I WEL F1.Inlir DATA FOR CYCII 9 (lievi:ed 10/I.[/2) lwgular Rmts
__ Srfdel.C( rz.cr.I.Qt.
Cindu. irus C /o Nel w/o UO;,
Wel Thickr.eca Cvnfig.
14mber w/uFuel w/oU02 Wel fiumt.er w
7r-1 tion Er.richraent plas.e te s hel TyTe Katerial OD, 2n.
in.
usation Required Cce. position Enricha.ent Diameter Required 1.%
0.433 Zr.2 05%
0.035 6x6 31 9).05 UO s 1.03 0.418 5
99 85 UOg 2
0.055*
0.15 Er2 3 0.15 Er2 h 1.77 0.k @
0 23I 0.462 6
100 UO2 2r.2 '-
0 5625 0.0j5 6x6 29 190 Uag 1e 9% 3 A3 023 4.7 ca o3 2.34 0.465 g
1.Tl 0.442
.ste -lat pison rods)
Ir.2
- 0. % 25 0.035 6x6 29 100Ug 2 34 0.L32 6
100 U02 1
4 Special test rods Zr.2 0.5625 0.035 6x6 30 2 34 0.482 6
100 U0; 1 7~
0.482 2 34 0.482 6 ~
luo UO2 1.71
- 0. h t.!
Ea:)
Zr-2 0.*A25 0.035 6x6 29 100 UO2 93.26 Ua,0) le 174 Gd 2 34 0.k82 r.:a )
2 3-7.1 )
2.r.1) 1 71 0.482 2.34 0.482 6
100 U02
- .straented (VI.I))
Zr.2 0.5625 0.035 6x6 29a*
100 UO2 1
VII-II))
-stra entei dIII.!
r.s t....nt e i
.e:r..en,ed X.I]
1.77 C.482 2 34 0.482 6
100 UO2 Zr-2 0 5625 0.035 6x6 20 100 UO2 btcr.,ie.te wirg 9
917 U0,
0 71 (U nat.)
2 V*I.N])
23mo:a I
9%26 UO,
g 2 34 0.482 le-1.74 Gd 023 1 77 0.($
2 34 0.E82 6
100 UO2
- ..tc.!-4..tearira, Zr.2 0 5625 0.035 6x6 20 100 UO2 97 7 UO,,,
0 71 (U nat.)
, W (siclinian 2.3 3 d,:1
. (.;I.m. t p 1+
99 13 UO,
2 34 0.f.82 2
1 0.87 Gd 0 23
!in.learirg, Zr.2 0 5625 0.035 6 x 6$$
20 100 UO 2.34 0.482 6
100 UO 1 77 0.kfK 2
.9 917 U 0 71 (U nat.)
0.k62 ar.nr rtnteJ (VII.It.I{ }
p, 2 3 lbO s=s 2
et rr.tr rui:.
Identification DU = 7/% A1 0 3.0$ Gd 0, 0.465 in. OD;
- r. r:d. I CII*.tiz(.d. tere IcAJcd in Cycle 4 with oce of the follcwir.g types of se6;r.ented tsmable poison test rods:
23 23 car e ie 12.3." 1u 0 - 7 15 Cd 0, 0.465 in. OD; CW = 98.% U 2~1*1I* Od 0
- I"
'""*"*# O' 1"* % M " N*
00.2.3 M U
- 1* D '"'I*d O' I" * "
- 2 23 23 23 23 cf *:.e:e a neblies (GTI, 0 99, G.92, C.M1) were selected in Cycle 5 for replacement of the special poison rods with plutonnum rods of one of the f ollowing Ib eru leta.ents:
(<
)
v/c; 1.7 w/o; 1.2 a $ 1.1+ w/o; 1.2 w/o in r.atural uraniwa.
-:*3 ruis centain s all sr.c.onts of Gd 0, rec.ainder of rod 100% UO
- 2 2
2 3 use o.Ut%1n. clad kr. In starmlani asses.blies.
- w..cir.ir.4 C.1 0 3-- - J
.1.,. ::curiti by Icisco rut in Type VI (VII, Vill, and 1X) assembly is replaced by instrument channel in the instrun.cuted Type VI.I (VIF-I, VIII I. en! IX.I) asresibly.
.r.:.r. ented atte:blies cw.tain no Imrr.at,le poison.
e V 1%c1 asses.blies (DU-56, CU.102),.ar*1 replaced'with twc. gado11nia. alumina rcds during the fif th sefweling (t/c.6).
pt:.!!4a.4r:..ia ruts.cre ru.eved, or.s cuch fim two 38 39 240 241 242
- 1
- es:; x i:ler. cf platentus in atun p reent is W: W
=0.kf;
= 71 3%; N
= 20.65; N
= 6.1$; N
= 1.4 pj 4
r
.1;s 4e in trt.cr.t ch.u. 1; no poison rods.
c:.d of Cycle e one rod will be rcearveil frcas a few asecs.blics for gest.irra.11ation 'xemination. These assembiles win be re-insertext for Cycle 9 operation witt.uut repin.twnt of t
- .,1
.w t mi.
b (Issued with Change No. 26 dated September 13, 1973)
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