ML20037B031
| ML20037B031 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/17/1963 |
| From: | Wade I COMMONWEALTH EDISON CO. |
| To: | |
| References | |
| NUDOCS 8009030724 | |
| Download: ML20037B031 (13) | |
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.M t9 Septenber 17, 1963 A
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'tr. lohert Lowenstein, Director Division of Licensin7, and lequlation
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\\tomic Ener y Commission iashin; ton 23, J. C.
Jear '!r. Lowenstein:
Pursu: Int t o Pa r tgra ph 3.a. ( ') o f L ic an3e
Pi-2, as anended, onnenwe.11th Edison Co'ninv requests t':10 Appendix "A" of License 9P7-2 be amended as follows:
Amend ite, "3.
1eter i n,t ion of nxi: u, 7 3,ctor wer" m #
section "O.
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Determin' tion of 'hximum leactor 'ower n 3g
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"The maxi u, t!! awe le steadv state heat flux linits expressed in units of Stu/(hr)(ft 2) shall never exceed the following values:
Cuel Type I 350,000 Fuci Type II 130,000 Fuel Type III 360,000 Fuel Type PF-3 and PF-9 470,000 Fuel Type DC-10 through PF-12 510,000 "The reactor shall he operated within the above limits such that a minimum burnout ratio of at least 1.5, evaluated at 125 per cent of rated power, will be maintained in each type of fuel closest to burnout in the most limiting channel in the ccre based on a uniforn steam quality over the cross section of the channel.
This hurnout ratio shall he based upon the correlation in Edison's "Occomnended Curves of lurnout Linit for i
Design and Operation of 3 oiling '.'1:er leactors",
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'4r. Robert Lowenstein September 17, 1963
" dated January 3, 1962.
The reactor shall he operated always well within the bounds of stability, as evidenced by the operation itself and any experimental data produced."
In accordance with Paragraph 3.a.(4) of License DPR-2, a description and hazards evaluation report in support of the proposed amendnent to Appendix "A"
is attached hereto as " Exhibit I".
I "e r'r truly vaurs, i
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B EXHIBIT I DRESDEN NUCLEAR POWER STATION Reduction in Burnout Ratio and Increase in Heat Flux I.
INTRODUCTION The proposed amendment to Appendix A of DPR-2 reduces the licensed min 1=;= burnout ratio fro: 2.0 to 15 and increases the allovable heat flux for Type I, II, and III fuels to an amount corresponding to a steady state specific power of approximately 15 2 kilowatts per foot.
As discussed in sections n and In belov, these changes are considered to be consistent with existing technology and to provide adequate
=argin against fuel da= age.
The proposed changes vill allow greater flexibility in selecting control rod patterns and thus simplify operation of the reactor.
Flexibility in selecting control rod patterns vill also allow optimi-zation of fuel exposure and enable the licensee to i= prove fuel util1:atio and economics. A specific instance in which the new a
11=its will be useful is near the end of a fuel cycle when adverse
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power distributions could require a reduction in mactor power output.
I A reduction in =ini=u burnout ratio is needed more in Type II and Type III fuel than in TyIe I fuel since the coolant flow in ?ype I fuel assedlies is high-relative to the power being produced. The increase in allowable heat flux in Type I and Type UI fuel is needed since this fuel vill 0;.erate very clese to One exirc:.ng '" t.
Type I' 'uel, inich consists of s= aller dia eter fuel rods, could be operated within the existing heat flux limits since Type H fuel perfor:ance vill Sa ' " *ed by burnout ratio much before the existing heat flux limit is reached. In the interest of s1=plifying the license, however, the proposed limits should be applied to all Dresden fuel as stated in the proposed license a:end:ent.
II.
MINIMtM EURHOUT RATIO OF 1.5 Dresden cin1=u burnout ratio calculations are based on the burnout correlation in the Co=.cavealth Edison Co=pany's "Reco== ended Curves of Eurnout Limit for Design and Operation of Boiling Water Reactors,"
dated January 5, 1962. This is the sa=e General Electric Cc=pany correlation published in APED-3892, " Burnout Limit Curves for Boiling Water Reactors" by E. Janssen and S. Levy, April 14, 1962. This correlation is being used for burnout ratio calculations on all General Electric Cc=pany Atomic Power Equi;=ent Depart =ent (APED) power reactors.
The mini =um burnout ratio of 15 proposed in this license a=end::ent is the sa=e as that specified in the Consu=ers Big Rock operating license.
In discussions held between ACES and AEC staff = embers and S. Levy of APED, preli=inary to issue of the 313 Rock operating license, the question of =ini=u burnout ratio was thoroughly reviewed. Severai i=portant points =ade in the discussions are su==arized as follows:
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The possible effects on fuel elements of high heat flux which must be i
i considered are " burnout" or local increase in cladding temperature due to local steam blanketing and increase in the central temperature of the Protection against the possibility of " burnout" is dis-oxide fuel.
cussed in section II above. The effect of high heat flux on the central temperature of the oxide fuel vill be discussed here.
Work being done by the General Electric Company indicates that it =ay t
be possible to operate Dresden type fuel with so:e central =elting without deleterious effects. Since this work is not yet cc plete, however, it is considered advisable to continue to 11=1t heat flux such 2 at central fuel =alting at overpover vill not occur. This a quires that peak central fuel temperature not exceed 3CCO*F.
Calculation of central fuel terperature -equires knowledge of heat flux, fuel raterial diaceter, and fuel caterial (00 ) der:al conductivity, 2
assuming the te:perature rise crough the surface fils, clad, and I
ther:al con-l clad-to-pellet gap are known.
~41 2 tha exception of ~C2 ductivity, all these paracetars ara r? atively well known and easily specified. The value of UC2 cer=al conductivity at elevated temperatures is the subject of extensive experimental and theoretical investigation in de industry in general and at AFE3 in particular.
In the Coc=onwealth Zdison Company's March 2,1962 request for increased heat flux at Dresden, ther:al conductivity with te=perature reported by the variation c1 LD2 l
J. L. Bates of Hanford Atomic ?" educts Operation vas considered. Additional information on LD2 conductivity at elavated temperatures has since been developei by AFID. 7:13 '^~~ -- is reported in the ; aper entitled Thermal Conduct;vity at Elevated Temperatures" by Lyons, Straley, "LD2 Coplin, '4eidenbaum, and Pashos which was presented at the June,1963 meeting of the American Nuclen Society, ;- plot of UO2 de=al conduc-l tivity versus temperature taken from the report is presented in Figure 1.
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This conductivity data is based on work perfor:ed under the.Zuratom-002 High Perfo=ance Program, Contract No. AT(C4-3)-189, Project Agreement No. 17 Figure 2 is a plot of central fuel temperature versus heat flux using the data of ther:al conductivity with local Lyons, et al. The variation of 002 temperature across the fuel rod has been considered in calculating the Using the data presented in Figure 1, the proposed heat fluxes curve.
l will not result in central melting of the 002 fuel even in the unlikely event that all peaking factors, including the 1.25 overpower allowance, were to occur at the same time and location.
i Although the conductivity data presented in Figure 1 which was utilized in calculating central fuel temperature is considered to be conservative, a standard valua of CO2 thermal conductivity at high temperatures has not yet been established in the industry due to the scatter of experirental data. It is desirable, derefore, to have a =ethod of considering the effect of high heat flux on UCg fuel which does not require direct knowledge of the exact variation of UOo therral condue:1vity with Such a method, which utilizes a parameter defined as temperature.
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Page 4 f kdt with the units of kilowatts per foot is available+ where k is UO2 conductivity as a function of te perature t.
This =ethod allows comparison of fuel to:perature effects for varicas flux levels and fuel rod diameters on a co==ca basis.
The proposed heat flux limits and associated values of [ kdt (kilowatts per foot) for Type I, II, and III fuel at rated power are as follows:
Proposed Heat Flux Limit Proposed [kdt Limit Type I 3-^.0003*u/hr-ftj 15 2 kw/ft Type II L50,000 3tu/,hr-ftf.
15.2 kw/ft
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NOTE: The proposed value of [kdtat rated power of 15.2 kw/ft corre spond.: to an )( kdt overrever of about 19 0 kw/ft.
at In the Atomic Energy Co:: ssion findings dated Septe=ter k,1962, on Co:convcalth's request f:r increased heat flux, dated March 2,1962, heat flux l'
'ts at rated power equivalent to j kit parameters of ik kW/ft for Type I and Type II fuel asse:blies, and 17 kw/ft for two Type II, and the 12 develop ent (EP) fuel assemblies were approved.
The findings also stated that, "After operating experience is gained at these icvels, subsequent ex:_ nanons snould reveal whether regular operation at higher ;ower levels :nn be jastified."
Unfortunt.tely, the lh kw/'* ' *-'
'- Type I fuel prevented operation of the experimental asse:blics at 17 kw/f t.
As a result, it has not teen possible to obtain fuel fr^n the Dresden reactor for examination which has been operated at an kdt of 17 kw/f t.
It has been calculated, however, that the Type I fuel has been operating successfully at close to 14 kw/ft, Since cost of this operation has occurred since the first refueling, which was completed in March,1963, there has not been an opportunity to examine Type I fuel operated for any appreciable ti=e at lk kw/f t in the Eresden reactor.
Infor:ation from in-pile testing and some post irradiation examinations does exist, h vever, which is p[ertinent to operstion of Dresden Type I, II, and III fuel at values of kdt in excess of 14 kw/ft. Tables I, II, and III contain a surrary of data available at APED on high flux
- J. Belle, "Uranlur Dioxide: Properties and Nuclear Application", p. 577 U. S. Governrant Printing Office, July,1961.
Page 5 level perforrance of self-cupported clad over pellet fuel. The feel assembly identification in the above *abica is correlated with prc6 rams as followe:
l Acce bly Identification Progra Reported In l
l DP Dresden Development tiot published
?4L Creeden Eevelaprant
.' lot published l
AEC AEC Fuel Cycle Fr:gr:_s Fupc-tc on Project Age.:etent 11., Contract 2I0. At-(Ch-3)-189 EFD Ccteuners Ef ve.;pennt
?cpcrto on Contract tio. At-(Ch-3)-361 r
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i.3. Savanna': revelopment Ir: gram Reports en Froje:t Agree ent 2, Contract IIo. At-(CL-3)-lS9 Irradicticn sni metsilogmphic ex"mtion of fuel si:11ar to Dresden
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reported in "2AP-3771-8., Quarterly Progress Report :;o. 8, April 15,1963 by B. 'deldentaus and su==arized in Table II, indicates that swelling of fuel roda did not Oce=an.c until the heat flux cxceeded 575,000(2h.9'ce/ft).
The propoccd overpower heat fluxc3 in Type I, II, and III fuel, which are l
equivalent to an j kdt of 19.1 kv/ft, provide adequate cargin from the l
calculated values Of heat fluxes at which either center =elting or fuel cwelling begins.
S" n r-f of Justif:. cation fcr Frcpcsed Ecat Flux Limits The proposed ra*cd power flux 1.icits, which are equivalent to an [kdt of about 15 2 'ce/ft, are requi~:d to provide necess y operational flexibility.
The propocod limits arc considered to be adequate for the following reasons:
1.
Calculation of central fuel t :peraturc ustng a conservative value of U00 conductivity and considering the variation of conductivity with fuel temperature acrcas the fuel rod indicates that no telting vill occur even st the overpcVer conditi0n.
2.
Drceden has been ope = ting. mere;sfully far several conths at 14kv/ft.
1 Page 6
.3 Pe sult.: of irradiatien ind ; cit irra tiatica exa=ination vork t.erformed to date dw11ct.te the, 'ar at hast limite<i periods, either Zirculcy s1*.i " v v..'ly-
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powers up to 19.9 kw/ f-k.
Irradiation of fuel siriiar *4 Drescn Type I and IIT fuel in all
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of over 2L.9 kv/ft. The preposed overpower li= t of about 191 kv/ft la conscrts tively belcw t.is data.
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reeul*,ing frca provr.:us inalyais since tre rate.1 power peak fuel tempera-
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tc=perature dictribution ;h te fuel caterial results :.n icver calculated 7c.- ax,.' e,2, t ".e yea k v.d*h *he
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fuel te. perature was calcula*.ed ic b.: etbout 3900? using the old ther:al conductivity value and cc$cd of calculation. With the proposed rated power heat flux in rype
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om also ce lculat d to be a;pecx. ately 39CO*F as snc-T. On F:.gure 2.
The q m,,.,., y. s. a..
.m,..c. y... +,m.- c.,,, c.#a r ^. e p.'.,-o. s e d..%..a
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TABLE I VBWR IRRADIATION TES"aB AT HIoH SFECIFIC Po4ER ZIRCALoY CIAD Total Titr.e No.
outside Mscimum*
Eximuun Time Above of Average Assembly of Diameter Heat Flux Power 14 Kv/ft.
Irradiation Exposure Identification Rods Inches Btu /hr-ft2 Kw/ft.
hours hours 14fD/T Examination Results Satisfactory after 200 hot above 14 Kv/ft. Subsequent DP-4 9
0 565 460,000 19 9 1360 13000 7500 examinations not perforr.
AEC-6f.
16 0 565 407,000 17.6 50 2000 lo75 Continuing Satisfactory DP-5 9
0.565 398,000 17 3 loo 9200 5000 No central void in UOp.
Satisfactory DP-16 9
0 565 390,000
' 16 9 6
7 lo All rods had central void U,02 Satisfactory DP-3 9
0 565 385,000 16 7 50 50 loo All rods had central void Ho2 AEC-2OJ 16 0.424 510,000 16.6 175 5300 3200 Continuing DP-12 9
0.565 380,000 16.4 300 12000 7100 Satisfactory - continuins DP-31,32 & 33 27 0 565 380,000 16.4 50 50 1200 Satisfactory AEC-10J 16 o.424 500,000 16.2 200 5300 3hoo Continuing AEC-19 & 21J 32 0.424 500,000 16.2 100 5300 3000 Continuing AEC-25J 16 o.424 500,000 16.2 50 3000 2200 Continuing Clad failure at peak heat DP-29 9
o.565 500,000 16.0 300 10000 4232 flux zone of one rod.
AEC-12J 16 0.k24 480,000 15.6 150 5300 6100 Continuing AEC-22J 16 o.424 470,000 15 3 50 3400 2900 Continuing AFC-ll & 13J 32 0.424 450,000 14.6 150 5300 6000 Continuing Total Hods 241
- At neak flux zone
s TI,bLE II GE1E - WL TRRADIATION TESTM ZIl!CALOY CIAD Tot.a1 Timae No. Outside Maximum
)hximum TJw Above of Average Test of Diameter Heat Flux Power 11.Kv/fL Irradiation Exposure
~.
Identification Rods Inches Btu /hr-ft2 Kw/ft. _
hours _
hours WD/T Rramination Results Swelling in all roda a.t peak EI"f-10 4
0.565 1,010,000 43 7 357 1182 zone - AD = 74 mila Swelling in all roda at peak 1h1.2 ha t zone - AD 53 mila EPf-8 4
0 565 895,000 38 7 _ _ %S Clad swelling in 3 rods at EPT-6 4
0 565 645,000 27 9 SUI UfD peak heat zone AD : 47 mils WL-5 5
0 565 395,000 17 1 900 1000 1100 Satisfactory I
WL-4c 2
0 377 540,000 15.6
_ 310 312 773 satisfactory
h.uiB 1YI VBWR IRRADIAT10H %18 AT HIGH SPECIFIC EGIER BMIMLESS 8'11EL CLAD Total Time No.
Outside Mart===
E xiana.
Time Above of Average Assembly of Diameter Best Flur Power 14Kv/ft Irradiatioa Ly/Tsure Identification Bods Inches Btu /hr-ft2 Kv/ft Hours Ikxes EJD wantifum Besults Batisfactory, extensive AEC-kL 1
1 375 533,000 51.0 100 150 216 Ug melting,-2% decrease in dinaster Satisfactory SAV II-3 9
0 550
'400,000 16.8 100 120 All rods had central void in UO2 AEC-1L 8
0 515 500,000 19 7 1000 4200 4075 Continuing Satisfactory ItBo A n roas had central vota SAV II-2 9
0 550 360,000 15 1 in UO2 Satisfactory DP-6 9
0 550
~ 385,000 16.2 50 95 Au rods bad central void in UO2 HPD-3G 25 0 363 500,000 14.0 MS 7N3 "ta52 Three roas failed by inter-granular corrosion j
l EPD48 25 0.hoo 492,000 15 1 400 4660 h671 Continuing Total Rods M
i 1
i j
]!1 I
1
~
1' O
9 3
'i 0E T
2 1
-0 1
x 0
1 0
5 0
6 1
2 34 E
R 1
1 UT A
I R
E P
K M
E T
.sv Y e
T 01 Y
I W
T S 3
I N
V I
E T D C L f
U A D C f N I
R O T U C E T
R A L O 3 A E M
li PM R T E E T
i a.
i i
T T 0
2 R l
0 0 O 0
2 U F 1
E R
U G
IF s
tu 1
O 0
d 0
0 C
0 0
6
)
4 3
2 1
& l& RI" r
~
l
6000 D re sde t. Tyle I Fuel----
5000 Dresden Ty =: TTI Fue1-
_x
-r
-Dresden type II Fuel
~
i
/
i
/
BASEI10N "t10 IllEhMAL CONDUCTIVITY AT ELEVATED 7
IluPERA1URLS," ANS TRANSACTIONS, Vol.6 No.1. JUf4E 1963, p.152(LYONS) 1000 1
000 100 W10 300 400 500 ROD SURFACE HEAT FLUX ~ 10 uiU/liR-F12 3
FIGURE 2 ROD CENTER TEMPERAluRE VS. ROD SURFACE IlEAT FLUX
_= _.
i 4, ;..
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t
~.
F*
a s,ou:
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cart a
.ven No.
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o HER:
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AcetON NICESS ARY
{j CONCORRfMCE O
oa'Ea'$wtato:
cta s sw.r No Action Nrce suRv u
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DArE RECftVED RV DAIE e4 t - s i l t s t ' <., 9, c,
1, ce
- t. e Mj t11 min h*: r rmt* t r n i.i r,
f,.- ',o te lp f'
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'M E NCLOSURE S:
~~
~
3 % ta e r t < v l r ta s.
Fe i j O.%r ie {
r f <-. ;e: r>t vu t z x U.;.7.utr rer foot. o 7 !"r,'v 4:
F ?Je 9.I t I " et+t-t f n t is
-,3
., tiemt IFY*rf a r * ' r) at i. y '*
REMARMS:,t r. r4 r trt h d i
'r 4-fr46
?fJ.le 1 - f t.,- L T@
t f ",5 '
~
O t ~ *:.
te er
/ r' I
U. S. ATOMIC ENERGY COMMISSION MAIL CONTROL FORM rORn AEC-ases (e so)
O.M
@ED m
L n
- 4