ML20037B030
| ML20037B030 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/26/1964 |
| From: | Bower D COMMONWEALTH EDISON CO. |
| To: | |
| References | |
| NUDOCS 8009030722 | |
| Download: ML20037B030 (13) | |
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.4 Jivision of Licensing and '.egulation U
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-Q Mr. Robert Lowenstein, Director
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.v' Pursuant to ?aragraph 3. a. (4 ) of *.,1:ense JP3 't, is :=endad ("?b2"),
Conmonwealth Edisen C:=pany requests ths: Ap;endix " \\" of JP?.-2 he arended to allow operating; a special fuel assenbly, desi;;nated 3A-1, in the Dresden reactor. The amendments proposed are as follows:
Amendment :!o. 1 Amend item "2.
.iuclear Core" of section "3.
3:3I33 FCATU?E3" of Appencix
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- o 3??.-2 to read in its antirety:
"2.
iuclear Core
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Maximun active fuel length - cold 112 in.
'!aximum number of fuel assemblie: by ty.en Type I 352 Type II 107 Type III 200 Type FT-8 through PT 2 (one each) 5 Type SA-1 1
Maximum total number of fuel assemblies 488 "The various fuel assemblies may be located in any position of the reactor, provided over-all cora symmetry is praserved and provided that fuel assemblies Type FT-8 through 12 are each separated frem any other such assembly by at least four Type I, Type II, or Type III fuel assemblies.
"The reactor may be opersted at any power up to and inciacini! rated power with any number of the various types of fuel assembl:es in-stalled, provided the maximum number and location are within tie limits specified above."
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. 2-Mr. Robert Iowenstein Februan 26, 1964 Amendment No. 2 Amend item "3.
Detemination of waximum Feacter Power" of section "D.
F06 R GPERATICN" of Appendix "A" to DPR-2 to read in its entirety:
"3.
Detemination of Maximum Reactor Pcwer "The rated 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 expressed in units of 3tu/(hr)(ft2) shall never exceed the following values:
3 Tuel Type !
320,330 Tuel Type II 410,300 Fuel Type !!I 330,000 Tuel Type PT-8 and ?T-9 470,330 Fuel Type FT-10 thrcuch ??-12 513,300 Fuel Type SA-1 425,000
The mactor shall be operated within the above limits such that s minimu:n burnout ratio of at least 2.0, svaluated at 125 per cent of rated pcwer, will be -aintained in each type of fuel closest to bum-out in the hettest channel in the core based en a uniform steam quality over the cross sectien of the channel. This burnout ratio shall bo based upon the correlation in ~'dison's "'%cm.e:Med Ourves
- f 2urnout ' i-it "o r 2aa t"a :"d Cpernien " bilin? *t r N et ~s,"
dated January 5,1962.
The read;r shall be operated always well within the bounds of stability, as evidsaced by the operation itself and any experimental data produced."
Amendment No. 3 Amend Appendix "A" to CPR-2 by deleting Table II (revised 12/31/61) attached thersto and substituting Table II (revised 2/19/54) attached herewith.
In accordance with paragrachs 3. a. (4) of OPR-2, a Description and Ha::ards Evalu-ation Report in support of the proposed amendments to Appendix "A" is attached hers-to as" Exhibit I."
In our opinion, the data in this document indicatss that operation of special assembly SA-1 in the Dresden reactor will not involve hazards greater than or materially different frem those censidered by the Commission in authorizing License DPR-2, as amended, nor will use of special assembly GA-1 constitute a material alteration to the facility.
I Submitted and sworn to befmar me this ] 7 day of February, COMMONWEALTH EDISCN COMPANY 1964 by said O. R. Bower r^/
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t EXHIBIT I DRESE N NUCIEAR P0w'ER STATION 1
DESCRIPTION AND HAZARDS EVALUATION l
SPECIAL ASSE' GLY SA-1 C0!CENIS SECTION I Description of Proposed Acend:ents' to Appendix "A" to DFR-2 SEC* ION II mysical Characteristics and Mechanical Design of Fuel SECTION-III Nuclear Characteristics SECTICN IV Ther:a1 and Hydraulic Characteristics SECTION V Safety Evaluation This report provides technical infor:ation in support of the attached app)ication for amendment of Dresden Operating License DPR-2, as acended.
It is not intended that the material contained herein constitutes
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" Technical Specifications" in the sense of the Licensing regulations (10 CFR, Part 50, Section 50.36).
4 February 19, :196k 1
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.m SECTION I I:ESCRIPTION OF PROPOSED AMENINENTS TO APPENDIX "A" TO DPR-2 These amend:nents to Appendix "A". to DPR-2 are proposed to obtain authority to load and operate a special assembly, designated SA-1, in the Dresden reactor.
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-SECTION II--
PHYSICAL CHARACTERISTICS AND MECHANICAL DESIGN OF SPECIAL ASSEMBLY SA-1 General Description The basic design featuns of.SA-1 are tabulated in Table II (Revised 2/19/64) of DPR-2 as part of the proposed amendments to Dresden License DPR-2. The special assedly, SA-1, consists of. two subasse:blies. stacked one on top of :
de other in a channel of standard'di::ensions for the Dresden reactor as shown in Figure 1.. Each subassembly consists of. a -seven by seven array of Zircaloy clad nonsegnented fuel rods as shown in Figure 1.
The basic constituent of the fuel is a' sintered solid cylindrical pellet of about 95 percent theoretical density. - The pellet size is given in Table II.
2e ' pellets are enclosed by a Zircaloy jacket _ for=ing a fuel red about LC-3/L inches leng. The fuel rods :est on a to::o= grid and are held in position by four spring type spacers located axially alor.g the long-h of de fuel.
Se spring-type spacers serve -- * * ' e ieflection and vitration of de fuel rods._ 2e spacers are supported by comer angles which are attached to the botton grid and ax# '-= "" 'ength of -he subassedly, to fo= an integral tasket for de fuel rods. The comer angles are fastened at the top to a band which extends about 1/h inch above de top of de fuel rods..
The first sutassedly sits on a stand at ached to a ?/pe III cose piece vith a par-iallI cut ou: grid. The second sd asse=bly rests on the first. The two stacked subassedlies form an active fuel leng-h of slightly over six feet. The subasse=blies are held down by a spring loaded fixture attached to a cla=p which fits into slots in the sides of the channel near the top.
A standard shape handle is attached to de clamp for handling the assedly.
The exterior dinensions and characteristics of the asse bly are si=11ar to de Type II and Type III fuel assemblies.
Fuel Rods The SA-1 fuel rods were fabricated for the AEC Fuel Cycle Progra=* as par ~ of a perfomance demonstration of UO2 rod type fuel to long life in 2e V3WR.
The design and fabrication of these fuel rods are described in detail in GEAP-3653, "AEC Fuel Cycle Progra=, Design and Fabrication of the Basic Fuel Asse=blies," March 15, 1963 The fuel rods' were fabricated to be representa-tive of current commercial power reactor fuels and to this end were fabricated by the APED fuel rod manufacturing facility, with standard commercial practices and quality control.
The fuel rods were asse= bled into V3WR assemblies and irradiated to exposures -
as high as approximately 10,000 MWD /T at peak heat fluxes up to 500,000 2
Stu/hr-ft. The subject Zircaloy-2 clad fuel rods were operating satisfactorily.
at the time of-the V3WR shutdown.
- Contract No. AT(0L-3)-lc9, Project Agreenen: No. 11 4
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An interim destructive exa=ination was perfor:ed on a typical fuel rod of
- this type after about 5,000 WD/T exposure. The integrf,ty of the fuel rod was satisfactory with no unexpected changes in characteristics of the fuel or clad. Additional destructive examinations are unde:vay on rods with about 10,000 MWD /T exposure.
All of the rods to be used in SA-1 vill 'ce visually and ultrasonically exa=ined to deter =ine dat they are in satisfactory condition for continued irradiation.
Subasse blies The subassedlies vill be loaded with irradiated fuel rods at the VAL Radio-active Materials laboratory. A representative s2asse=bly loading pattern for fuel rods of various initial enrichnents is shown in Figure 2.
Rods with the highest accuculated exposures will te chosen from each group of enrichtents for loading into 'he sdassemblies. To de extent practical de,
two scassedlies will te loaded vid rods of equal exposures. Se final sutassedly leading pattern vill te established based on de availability of rods of various initial enrichments sfter exasination.
2e botto sdassedly, A, vill be leaded with de fission gas plenuns pointed toward de botto: grid. 2e top sd asse d ly, 3, vill be loaded'vith fission gas plenuns pointed up :ovard the top ta-d
s wi
- '-* e de nonfueled gap between te sdassedlies at about 1-1/h inches.
Assedly The sdassedlies vill be loaded through the top end of the channel 'n the Msden fuel handling pool. 2e top end _ of the chan.:el vill be closed with the fuel holi-down fixture. 2e fuel, hold-down fixture has a spring loaded plate at de bottom which vill press. against the top of de top subassedly.~ The.
fuel hold-dor. fixture has a clamp at the top which when properly' positioned will rotate into slots in the sides of the channel near the top cla= ping the hold-down fixture in place and to the channel. The clamp is fastened in position by two cap screws. The cap screws vill te prevented fro = backing out by attached tabs which will be bent after the cap screv is in place. -
A handle ec=patible with the Dresden fuel grapples is attached to the fuel hold-down fixture. The ec=plete asse=bly is shown in Figure 1.
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m SECTION III NLClEAR CHARACTERISTICS Nuclear characteristics of fuel asse bly SA-1 and its effect on the Dresden core have been dete mined. Results of the physics analyses are given in the following paradraphs.
Fuel Assedly Nuclear Characteristics The high initial enricP en: of de SA-1 fuel rods is compensated by the depletion of U-235 and buildup of fission products resul*ing fro: irradiation in V3WR, in addition to the effect of the large amount of stainless steel used in de fuel assedly structure. As a result, de reactivity of the SA-1 assedly when installed in Dresden vill te less dan the initial reactivity
. of a Type I, II or III fuel assembly.
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and exposure distribution of de fuel rods used to make up SA-1.
Representa-tive location of fuel reds by initial enrichnent is sh0Vn in Figure 2. ' local peaking is also reduced by de adjacent stainless steel structure.
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the control red syste. large stainless steel rods have been used between de :Vo subassedlies to reduce -he effect of the water gap te:veen de vo fuel secticns 0: the power shape vicin the SA-1 assedly snd the surr02nding fuel.
2.e water at te cp and bot:ca of the fuel sections will no: cause significant changes in de axial pc.er profiles Of adjacent fuel asse d lies.
Core Nuclear Charsc: eristics The SA-1 issed ly has been cale"' "ad
'o have a negligible effect On the pcVer distribut,n in surrounding fuel.
In addition, calculations indicate tha SA-1 has a negligible effect on other over-all core properties such as radial power distribution, temperature and void coefficients, ' and total core reactivity.
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SECTION I7 THERMAL A'iD HEEAtJLIC CEARACTERISTICS -
.ae ther=al-hydraulic perfo=ance of SA-1 in the Dresden core has been evaluated. The following conclusions have been derived from the calculations.
A.
power Distribution On a power per foot basis, SA-1 vill produce 15% ore power than a-Type III assembly in -he same location. This is compensated by the shor er active fuel length of SA-1, resulting in an integrated power.
generation in SA-1 equal to that of a new Type III assedly in a ec= parable location.
3.
Hea: 71 :x SA-1 can te located in any position in the core vi hout exceeding a rated 125,000 Stu/hr-f 2
.21s hest flux corresponds to a. -
p[owerheatfluxof kd: of ik kv/ft, which is consistent with existing co ~ '*
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Minimu= Eurnout Eatio Location of SA-1 in the peak power position of the core would result in urnou ratio of 1.8 at 125% overpower. The mininu burnout a
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k ratic at overpower would te greater than 2.0 for alnos any other core location. SA-1 vill be placed in a location consistent with license li=itatiens at the time SA-1 is loaded.+
Since SA-1 has negligible effect on the _ operation of surrounding fuel assedlies, -
it vill no: affec: aver-all core ther.21 hydraulics.
Ton =onwealth Edison Company letter dated September 17, 1963, requested a reduction in the core minisr burnout ratio license limit from 2.0 to 15 and an increase in allowable rated power heat fluxes to values corresponding to an / kdt of 15.2 kv/ft. SA-1 is capable of being operated to these revised li=1ts.
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- SECTION V - SAFETY EVALt'ATION The design features of SA-1 fuel ~ rods are similar to the fuel which is currently.
approved for operation in-the Dresden core.
Since the SA-1.asse=bly has been conservatively designed and has a negligible'.
effect on surrounding fuel and over-all' core perfor=ance,.it -is concluded that SA-1 vill.have a. negligible effect on core safety..
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FIGL~dE 2 DEESEEN SECIAL ASSDELY SA-1 2 76 2.76 2.76 2.76 2'.76 2.76 2 76 0 ~s a=
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