ML20037B214
| ML20037B214 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/05/1971 |
| From: | US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML20037B212 | List: |
| References | |
| NUDOCS 8009080604 | |
| Download: ML20037B214 (4) | |
Text
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ATTACICENT A CHANGE NO. 22 TO TECICiICAL SPECIFICATIONS LICENSE NO. DPR-2 COMMONWEALTH EDISON COMPANY I
DOCKET NO. 50-10 1.
Revise Item 2 - Nuclear Core of Section B - DESIGN FEATURES to read in its
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entirety:
"2.
Nuclear Core Maximum core diameter (circumscribed circle) 129 in.
Maximum active fuel length, cold 112 in.
Maximum number of fuel assemblies by types:
Type III 103-Type III-F 72 Type V 97 1
Type VI 96 Type VII (equivalent to Type VI) 85 Type VII-Pu 11 1
Type VIII (equivalent to Type VI) 120 j
Maximum total number of fuel asse=blies 438 The reactor may be operated at any power up to and including rated i
power with any configuration of the various types of fuel assemblies loaded s asentially in a 1-in-4 scatter of fuel, provided the maxi =u=
number of assemblies is within the limits specified above."
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2.
Kevise Item 3 - Determination of Maximum Reactor Power of Section D - POWER OPERATION to read in its entirety:
f; "3.
Determination of Maximum Reactor Power The rated power of the reactor shall be limited to a maximum i
steady-state value of 700 MW(t).
E i
The maximu= allowable sjeady-state heat flux limits expressed in units of Bru/(hr)(f t ) shall never exceed the following values:
I Fuel Type III 360,000 Fuel Type III-F 360,000 Fuel Type V 360,000
~'_.,;
i-Fuel Type VI (VII & VIII) 360,000 JZ:
Fuel Type VII-Pu 360,000 The reactor shall be operated within the above limits such that l
a minimum critical heat flux ratio of at least 1.5, evaluated at 125%
i of rated power, will be maintained in each type of fuel closest to burnout in the hottest channel in the core based on a uniform j
steam quality over the cross section of the channel.
This critical heat flux ratio shall be based upon the correlation in Edison's "Recc= mended Curves of Burnout Limit for Design and
+
j Operation of Boiling Water Reactors," dated January 5, 1962.*.
i The reactor shall be operated always well within the bounds of I
stability, as evidenced by the operatien itself and any experi-menta' da ta produced. "
a 3.
Delete Table li (Revised 5/15/69) and replace with the attached Table II j
(Revised 9/25/73).
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.i s r; i n. -
w, fiM isc,1 113 7M
'Al.13 It hi5 s
c3.i1 Cogn, i
CI SI I.a n
I
.ta Wall I h.i,
l i:0 t Con-Nu.nber wJoI l
w/o l'O-I'uct Num!.. r o I r1 Rgairef l Cpmm tP n 1]nric! r:f at, thata ter U crp:irnt.
C.nm. r tt :..I:M -k
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r
O. bl OD o:.
n"
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fi :u r :ihn
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i:t Zr-2 0.353 0.o33 6x6 31 09.83 1:0.
1.33 0.473 S
93.53 UO.
1.33 3.03 3.1iI:r.0 l
1
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0.0 n
- 0.15 Er:03 3
_. _ g..
II.
Ir-2 0.5G23 0.033 6x6 29 100 UO.
2.34 0.432 6
100 t'O, 1.77 O.432 It 95.3 A1:03 0.465 1
4.7 Gd;O3 I!!-r ( gei11 Zr-2 0.5G25 0.035 6x6 29 100 UO, 2.34 0.482 6
100 UO 1.77 0.432 2
Special test reds!
p.V.on rn 5) 1
+-
VIi Z r -2 0.5G23 0.033 6x6 30 1
2.31 0.432 6
NO UO if7 l 0.;??
v (.t.m cirl)
Zr-2 0.5G25 0.02G T 6x6 30 1
2.38 0.493 6
100 UO 1.77
! 0.0 Vi fr.or cut)
Zr-2 0.5C23 0.035 6x6 23 100 1*O:
2.34 0.422 6
100 UO, 1.77 j 0.42 VII 6.,rnul)
Jt 98.26 UO:,
2.34 0.482 l
1.74 Gd O i
2 3
\\UI (r,rnal)
VI [t n* tru-Zr-2 0.5G25 0.035 6x6 29 "
100 UO 2.34 0.482 G
100 UO 1.77 0.;32 2
2 mr nte d (VI-!)]
VII [h ;t ra-r.wnt. ! (VII-IJ )
VTM lir.stre-nwnt e d (VIII-!)]
l
- I e e corner rods.
f t'ni.. a t el, pelletized.
! ELx.i amblic ; were loaded in Cyc!c 4 with one of the following types of segmented burnable poison test rods: Identification DU = 97"e A1 O -3.0"o Cd:0, 0.435 in. OD.
2 3 3
DW = 08.n'.i UO -1.1C' Gd O,1.77?o enriched 0.482 in. OD; DX - 07.3's UO:-2.77o Gd 0,1.77"t' enriched 0.4C2 tr. OD. To= c!
DV 02.fi.b.V.0 -7.1"l, Gd O, 0.G5 in. OD, 2
o 2 3 2 3 3
2 3 th< c rrc: 51tes (G-77, G-90. G-92, G-111)were selected in Cycle 5 for replxecment of the special roison rods with phtonium rods of nr.e of the followirg 1'a enrict c.c..ts:
h
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- 1. 2 - o: 1.7 wso; 1.2 and 1.4 w/o; 1.2 w /o in natural uranium.
g g i % < t,.i rot. < n.itain small amounts of Gd:0. remainder of rat 100*o UO2,except that the remainder of two rods will contain 10')% A1,0 i
~ 3 3
W.:0 "Ihh cor.tain!n". Gd 0 use 0.035-in. clad as in star.dard assemblics.1.n ".
- c. ocetipie 1 by poison rod in Type VI (VII and VIIllassembly is replaced by instrument channel in the instrumented Type VI-I (VII-I and VIII-I) assembly. The i.-
3 e:r a ented ;,semblics contain no turna' ole poison.
O tiTv o p?.itnia-urania rods ware removed, one each from two Type V fuel assenibt'.es (00-56, DU-1G2), and replaced with two gadolinla-alumina rods during the hfth rr f uelir : (110C-6 ).
b ed (It sued w/ Change No. 22 dated 4/5/ 71)
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