ML20037B026
| ML20037B026 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/09/1967 |
| From: | Julie Hughes COMMONWEALTH EDISON CO. |
| To: | |
| References | |
| NUDOCS 8009030708 | |
| Download: ML20037B026 (13) | |
Text
aa~oo'
."2eo w,.. ~., _ s o -- u Jihh.n7(Guqf Commonwealth Edison Company u
c-......
.m....
January 9, 1967 Dr. Peter A. Morris, Director Division of Reactor Licensing U. S. Atomic Energy Commission Nashington, D.C.
20545
Subject:
Request for Amendment of Operating License DPR-2, as amended, Dresden Nuclear Power Station, including Exhibit I
Dear Dr. Morris:
Pursuant to 10 CFR 50.59 and Paragraph 3.a.(4) of License i
DPR-2, as amended ("DPR-2"), Commonwealth Edison Company requests that Appendix "A" of DPR-2 be amended to allow operation of four Type III-F fuel assemblies with a plutonium fuel rod substituted in each for the removable gadolinia-urania in the Dresden Unit I reactor.
Authority to operate Dresden Unit I reactor with III-F fuel assemblics, re-quested by letter dated December 24, 1964 was granted March 23, 1965 designated Change No. 10.
The amendments proposed are as follows:
Amendnent No. 1 Amend item "2.
Nuclear Core" of Section "A pDESIGN FEATURES" of Appendix "A" to DPR-2 to read Yn its 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 I 166 Type III 192
,e-Type III-F (standard)
S8 A, '
Type III-F (removable experimental N.,
segmented poison rod) 2 o'
. ' d\\
Type III-F (plutonium fuel rod) 4 h
w,.
I\\
Type III-F (powder) 10 i
-i Type V 106 I 7-2,
' 2 IEi7x Zl Type PF-10 1
Type SA-1 1
d' 4
.f Maximum total number of fuel assemblies 488
,;X-1 j
\\ h,,, \\
"The reactor may be operated at any power up to and
,1 including rated power with any configuration of the Y
various types of fuel assemblies installed, provided g,'
,,7,.y g-4 T ~lPs ogj,0 the maximum number is within the limits specified P
~
,u above."
!M q --1 ::7 r
- c
,,.3,,,,, - ~ ~, 3 m.a' s ; * < a== = * " -
n_
},
8009080f9k
~
?
\\
Dr. Peter A. Morris 2-January 9, 1967 Amendment No. 2 Amend item "3.
Determination of 'faximum Reactor Power" of Section "D.
PUNER OPERATION" of Appendix "A" to DPR-2 to read in its entirety:
4 "3.
Determination of Maximum Reactor Power The rate power of the reactor shall be limited to a maximum steady state value of 700 MW(t).
"The maximum allowable steady state heat flux limits such that a minimum burnout ratio of at least 1.5, evaluated at 125 percent 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 steam quality over the cross section of the channel.
This burnout ratio shall be based upon the correlation in Edison's " Recommended Curves of Burnout Limit for Design and Operation of Boiling.f ater Reactors", dated 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."
Amendment No. 3 Amend Appendix "A" to DPR-2 by deleting TABLE II (revised 8/25/66) attached thereto and substituting 1
j Table II (revised 1/ 9/67 attached herewith.
Pursuant to 10 CFR 50.59 and 3.2.(4) of DPR-2, a Description l
and ilazards Evaluation Report in support of the proposed amendments to Appendix "A" is attached hereto as " EXHIBIT I".
In our opinion the proposed changes shall not result in hazards which are greater j;
than or different from, those analyzed in the Hazards Summary Report, j
specifically there is (1) no increase in the probability of, or (2) no increase in the possible consequences of, or (3) the creation of a credible probability of an accident different from, those accidents previously analyzed in the Hazards Summary Report as amended or in connection with amendments to Licenre DPR-2.
1 Very truly yours, COMMONWEALTH EDISON COMPANY k.w u
,/,
4 cr 7
John 11. Hughes
/ uclear Licensing-A'dministrator N
Attachments:
Table II Exhibit I 3
SUBSCRI3ED and SWORN to before me this 97/, day j
of L. t o, g.a 1967 D'
/j I
C l & $ vve le d Notary Public
/
I L
/
t m
t.
1-9-67 j
i-
.e
,3 b*u A..
_ fd~/O~
L 3
EXflISIT I 2113 CWh"ff
.l i -
Page Section I Description of Proposed A;aendment I-1 Section'II
.ticchanical Characteristics II-2 Section III Nuclear Characteristics of Pu Fuel III-4 Section IV Thermal and Ilydraulic Characteristics IV-6 Section V Safety Implications V-7 i
l h
9
,- s \\ b I f5 f
/
?t)'ua.q;10 s
.~e Isj; C:..,::s y
9'4
'.._ s
- 7 ' F5 l
)
~,'.' l"if
,D l
v a.ru re
.A
.. - g A
/
(01 [ } gi i
l i
i i
?
P l
l l
s
{
y v
e
,,,.y
1 m
=
SECTION I DESCRIPTION OF PROPOSED NIEND.' TENT The purpose of this amendment is to request authority to insert four plutonium fuel rods into the Dresden 1 reactor.
The use of four plutoniun fuel rods in the Dresden 1 reactor is part of a joint program between the Edison Electric Institute and the Nucicar Energy Division of General Electric'to evaluate the use of plutonium as a fuel in boiling water reactors.
One such fuel rod will be placed in each of four Type III-F fuel assemblics.
The plutonium l
l rod will replace a gadolinia-urania rod being removed during the outage scheduled to commence in January, 1967.
The mechanical, thermal-hydraulic, and physics behavior of the pilot plutonium assemblies are l
i discussed in Sections II through IV of this report.
Section V contains l
l the safety inplications associated with these four fuel rods, l
t l
I-1
e:
. ~.
m
~
SECTION II SIECIIANICAL CllARACTERTSTICS The fuel rods will be segmented into four pieces of approxi-mately equal length.
The exterior appearance of each will be-identical
}
to the gadolinia-urania rod which it is replacing.
Figure 1 in L
Exhibit I o! the Type V fuel amendment shows the general details I
of a fuel assembly typical of both the Type V and Type III-F fuel The plutonium rod is slightly different from the gadolinia-urania rod because it has (1) slightly increased plenum lengths to accommodate fission gas release, (2) natural uranium wafers 1/4 inch long at each end of each segment (3) hafnium sleeves used as flux depressors running the full length of each plenum and (4) the use of Pu0 -UO 2
2 l
fuel pellets.
l The mixed oxide pellets are fabricated by hot pressing techniques developed at the Vallecitos Laboratory of the Nuclear Technology Department.
- lot-presse'd pellrts have been successfully irradiated in the CETR and seventy-seven rods containing hot-pressed pellets are awaiting irradiation under power reactor conditions at l
l PRTR.
Two of the rods have uniform enrichment of 1.2 weight l
percent Pu in natural uranium.
One rod contains 1.4 weight percent l
Pu in each end segment and 1.2 weight percent Pu in the middle segeents-all in natural uranium.
The fourth rod contains 1.7 weight percent Pu in natural uranium.
The approximate isotopic composition of the plutonium is 75% Pu-239, 19% Pu-240, 5% Pu-241 and 1% Pu-242 The fuel assemblics which are to contain one plutonium rod each are identified below by assembly number and location at the begin-ning of the cycle.
II-2
[:
l
-..s m
..__.._l i
l i
Assembly.
Location Pu Enrichment G-77 66-24 1.2 wt %
-G-90'
.63-10 1.7'wt %
l G-92' 63-06 1.2 and 1.4 wt %
G-111 62-03 1.2 wt %
9 The layout of the Type III-F assembly with_ the plutonium bearing rod i
in place is shown schematical?y in Exhibit II.
i i
I l
I t
l i!'
e t
f r
II-3 e-L
u
{
~
SECTION III NUCLE AR CIIARACTERISTICS OF Pu FUEL l
The key.nucicar characteristics of the plutonium fuel 1
assemblies are given in the following paragraphs.
The nuclear per-l fornance of the core is unaffected by the addition of the four fuel rods.
A representative core loading is shown in the Type V fuel license ancndment (Figure 2, therein).
A.
Power Distribution l
The addition of plutonium rods to four of the-III-F assemblies will not affect fuel in other locations of the core.
In addition, the assembly mismatch and gross power peaking are unchanged by the replacenent of gadolinia-urania with plutonium.
The maximum local rod powers in the III-F assemblics with plutonium are slightly reduced by the addition of the 1.2 l
weight percent plutonium and still occur in the uranium rods.
The local power peak in the rods with 1.4 weight percent l
l plutonium in the top and bottom segments occurs simultaneously l
l in a uranlun rod and in the plutonium rod at the beginning of l
the cycle.
The plutonium rod end segments quickly burn down with exposure and at the end of the cy.cle operate at 80% of the heat flux produced by the peak rod in the assembly at that time.
The 1.7 weight percent enriched Pu rod produces about 1.2 times the peak uranium rod heat flux in this assembly at the beginning of the cycle.
At the end of the cycle, the plutonium rod heat flux is slightly less than the peak heat flux in the assembly.
B.
Temperature and Void Cosfficients The four plutonium rods have essentially no effect on'the core void and temperature coefficients.
III-4 t
s j
C.
Reactivity Control There is essentially no change in the Cycle 5 control systen caused by insertion of the four plutonium rods, e
a III-5 e
r\\
~N m
~
SECTION IV THERMAL AND flYDRAULIC C!!ARACTERISTICS
.The addition of four plutonium fuel rods to the reactor core does not alter the gross power distributions, and the rods do not change the hydradlic diameter of the four assemblies concerned.
Thus, there is essentially no change in hydraulic behavior of the l
fuci caused by replacenent of the gadolinia-urania rods with plutoniun rods.
l
-The peak heat flux in the 1.7 weight percent Pu rod will 2
initially be about 2/5,000 STU/hr-ft and the MCilFR at 125% of rated power will be about 2.5, both of which are well within licensed e
limits.
At the end of the cycle this plutonium rod will not linit operation of the core since its heat flux will be less than ot.her uranium rods in the same assembly.
1 l
l l
IV-6 I
l
m SECTION V SAFETY IN!PLICATIONS There are no foreseen problems in the general area of safety which should prevent the safe performance of this program.
The plutonium loaded into these rods is only two to three times that l
contained in typical irradiated rods in' the core.
(Dresden Type I l
fuel with 10,000 3r.fD/T operating at 20% voids has 0.5% plutonium).
As the rods operate, the plutonium is depleted so that their final i
plutonium content is less than was originally loaded.
The uncertainty in.the performance of this fuel is slightly greater than that in typical reload fuel; however, no failures are expected.
The.itCilFR and the peak heat flux in the four rods occur in the rod containing 1.7 percent plutonium.
Initially these numbers 2
are 2.5 at 125% of rated power and 275,000 BTU /hr-ft respectively, numbers well within licensed limits.
Even if there were a failure in one or nore of the four fuel rods, there would be no serious l
l consequences.
Of approximately seventy (70) kilograms of plutonium recently discharged from Dresden and commercially reprocessed, less than 300 grams will be reinserted.
Care will be exercised in the safe handling of the fuel prior to irradiation.
Although breaching of the clad by accidental damage to the fuel will not create a serious hazard with pelletized fuel, it would require careful cleanup and decontamination.
Insertion of the rods iato the assemblies will take place in the Dresden Unit I storage pool.
h V-7
?ABIE II (Revised 1-S-67)
Claddir.g Regular Rods Special Coriser Rods Wall o.D.
Thickness Rod Number
% Fuel
% Uo2 Fuel Number
% Wel
% UO3 Wel Fuel Tyne Material (inches) finches)
Confisuration Peautred Cmoosition Enrich:nent Dis:neter Required comoosition Farich$ent Diameter
- I zr-2 0.567 0.030 6x6 36 100 Uos 1.5 0.498 99.85 U4 6x6 31 99.85 UO2 III Ir-2 0.555 0.035(1) 0.055 0.15 Er2o, 1.83 o.478 5
0.15 Eredt 1.83 0.438 29 100 U02 2.34 0.482 III-F Ir-2 C.5625 o.035 6x6 1(2) 95.3 Al 023 o.W5 6
100 Uo2 1 77 0.482
'.7 Gd 01 2
III-t 29 100 Uos 2 34 c.482 (special naison)
Zr-2 c.5625 c.035 6x6 6
100 Uo2 1.77 0 462 Rods) 1 (Special test rods - see Note (4)
D 2*N 0* W 6
100 00 1.77 o.l.82 l
(F1 t um Roda) 2 r-2 0.5625 0.035 6s6 2
1 1
(Plutonium Feel Bod - see Note (7) 28 100 U(h 2.34 o.4925 ill-F Zr-2 0.*425 0.035 626 1(2I 95.3 A1 023 o.W5 6
100 U%
1 77 0.4)25 (Powder; 4.7 Cd20)
I3) 100 U(b 2 34 0.482 I
V 2r-2 0 5625 0.035 6x6 30
- ee note (5) 2.34 o.482 6
100 UOo 1 77 0.482 zr-2 0 5625 o.0e 6x6 30 we note (5) 2.34 0.498 6
loo Uo2 1 77 4.">3 Itin Clad PF-1G Z.r-4 U.412 0.025 8x8 54 99.65 uoa 2.0 0 358 9
99.65 Uo2 15 c.358 0 35 Er.,03 c.35 Er A GA-1 zr-2
,0.424 0.022 7x7 25 100 UO3 3 0-3 5 0. 37 5 24 100 Uo, 2 76 t.375 (1) Five corr.er ras (2) Poison rod - Pelletized (3) Spacer capture rod - Pelletized (4) Six assemblies will Le loaded with one of the following types of segmeated bu.rnable poison test rods: Identification W = 97% A102 3 - 3 0% Gd 0, 0.W 5 inch 0.D.;
23 3 - 7.1% Gd 0, 0.W5 inch 0.D.; DW = 98.9% UO2 - 1.1% Gd 0,1.77% enriched, 0.482 inch 0.D.; DX = 77 3% U02 - 2 7% Gd 0,177% enriched, DV = 92.9% A120 23 23 23 O.kS2, inch 0.D.
(5) Selected rods contain small amounts of Gd20, zusainder of rod 100% UO2 3
(6) Rods containir.s Gd 02 3 use o.035 inch cisd as in standard assemblies (7) Four of the six assemblies originally shown on Table II (Revised 8/25/66) will be selected for replacement of its Special Poison Rods with Plutoniun Rods of one of the following Ptl enrichments: 1.2NTl; 1.7 Wit; 1.2 and 1. 4 'f f t ;
i.2 4Tl in natural uranium.
9 a
w..
no..AoA
W REACIOR DATA INPUT FORM Cc7 trol #112 A.
IDENTIFYING & DESCRIPTIVE DATA REAcr0RS
~43 Pao Gn Au 32.PeoJ.
03.ooCMET No.
ot. TASK lo. TYPE oF nEArTon 31.CLAst oF nE AC Ton l
l Coot 44 No.
211 50-10 To1 E_
-APPLICANT l..NAME oF REACTon E
E
- ------a
_3, sin EE T..u l ho lN G MH LEiE g
TYPE UNif atoutsTEo oEslGN g AUTMonlZEo
.s.
.7
- g...
2A.cify 7.sfATE so. zip EI.EC.
5,
,8 TIIER.
I a
iB.
ACTION DATA BASIC PROCESSING STAGES
,,3 F
f ioiTPiP E' E sto.
g Acrises 7 A., inst Action PRE-APPLICATICN
(
n.
ma o,y n.
Nm oAy 3g CONSIDERATICN f
J
/
,"'"J P 3#aMR 91!'"s?uM" v n.
o.
oAv APP u c. a tc.
PRCCESSING APPLICA.
35
I
FOR CONSTRUCTION
,I o.
N cour'- oATE 38 sTARTEo 8 PRov. oP. AuTMonITY Issuto Y n.
M o.
oAY
' v a-
"S
v a.
" o-oav ExPiaario" 36 o a 'C,'o.
S-PROCESSING g
oA TE OPERATING s1AerEo a
roll rEA. Au w
.s su o AIKliORITY
- LL o a 'g * *-
'S d "-
"o-oav I, -
SUPPLEMENTERY, ACTION v n.
wo.
cAv
.s I. T.
v n.
. o.
ony
' r A s = N o.
(sau E As oATE SUPPLE.
bbb I
oATE suPPLEwENTAny =Eauts?
b7 d2-d nCoutsT n E c o.
67 01 11 I
(T A s o c o= Pi.E T E o E
42.
PunPost or.iCovEsr(TAsn>
gs4 nEsuLr or T A sx % N o.. c A N s E u E T c.,
amendment Beq.
g
[/fu w )7o./3 C.
STATISTICS
"""3
')
u.
a gsi.
Voto INPUT ENTEnEo UNoEn CooEs IN TYPE OF ACTION REQUESTED AND TAKEN n Eo.E T An.
r ELos 01 os on it. ANo on As g
REconoEo AeovE ANo ActiveTv E
4 mEACTom CONCEPT nEVIEs j
Coot B
PnELIMINAnY slTE nEviE*
E C
PnEcoNstnucTroM sTAoE nEviEu E
coNsolloATE INPUT ENTEnto UNoEn o
coNsTnuctioN PEnvirtC.P.nEvitet g
cooEs IN FtELos o1 os on 12 ANo E
AuTMon:Tv To oPEnATEtoP.sTAoE nEviEwl I
os As nEConoEo Atovt ANC r
Aufwonity To possess oNLv 3
G AMENou(NT To CoNsTPuCitoN PEnwlT g
ACTIVITY Coot elTH PaoG.
PaoJ.
H AM E N cWE N T To oPERAftNG LICENSE g
I T Asn AcT.
i cwANoE To TEcNNicAL sPEciricArioNs x3y J
EXEMPfloN g'
K CcNsfavCTioN PEnWlf EXTENilo4 g
L oPEn Ar,Na o CENSE con AuTwenifv> EXTENSION a
u ont onoEn l
I sPECIAL AuTMontTY g
4 I LICENSEIon AuTHoelTY)TEnulNATEo on EXPinto l
7 i
I -
-r u r v., A i Ni I
e I
l
}
I e
_~- -
_..,. -. _ ym,..
-.m., -e _..,
y,.
s._.,,,....-
---._._..em..=~* sqe,y%
g -
1L.
= * = = -
v o-l y
y# :x~m,c +:.
- ay.
i-7 ca s.
,n,B,, onwen us t f/*i7&pm,.x.m..y--sm;y 9: c
' ks en :, :... e, abc
..- e "; g : A W, a 1.,, _
~
1 l,
P Fem na========1 th mH anna Co.
cATE or poCuwENT:
DATE REcErvED No.,
Chicago, ril h is 60650 1-9-67 1-11-67 112 LTR.:
MEMO:
R EPO RT:
CTH ER :
gg l
x is emel=. (30 TAT 7231-9-67)
TO:
ORIG.:
CC:
OTH ER:
8 l
Dr. Morris 1
3 20 wi= M cys. ree'd ACTION NECESS ARY C
CONCURRENCE C O ATE ANSWERED:
t NO ACTION NECESSARY C ' COMMENT C! BY:
CL A S$1FIC ATION; POST OFFICE FILE CODE:
50-10 REG.NO.:
D E S C RIPTIO N : 1 Must Bg UNCL45$6FIEQ >
REFERRED TO i DATEl RECEIVED BY jDATE Ltr. req. that Appendix "A" of DPE-2 be j
ammeded to allow operation of fDer (4) 3ag 1-12 f ps In-r fuel au-Mi== with a Pm fuel w/.n exsras - som a: Tion f
rod substituted in each for the removable i
F N C'.Q SU R ES :
gadolinin-urania in the Dresden (hit 1 lir. Marriss 1 12 rasetor........and tranas w/infocy.
l (24 cys. rec'l)
Table II (revised 1-9-67) of ppendix "a" 20 \\0 REMOVE I
- 31, 1 - a tio 1-v REM ARMS:
distributions 1-f0 mal file Copf l
l gt-suppl.filecopy
!! 1 -
1-ac im 1-am 1-8taner 2 ~=$ i ='a I
f U. S. ATOMIC ENERGY COMMISSION Mall CONTROL FORM r agg.. <
l l
l l
l 0
1
- -