ML20085E669
| ML20085E669 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 04/02/1965 |
| From: | Bovier R SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9110210102 | |
| Download: ML20085E669 (8) | |
Text
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SAXTON NUCIEJJ1 EXPDlIML!1TAL CORPoitATION
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Daeket llo. 50-146
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Chance llequest No.17 to Technical Specifications G.ks I c.,
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- A Amendment No.16 to Operating License UN sn 1.
Applicant hereby sulnite Change lloquest No.17 to the Saxton Technical Specifications as provided for in 10 CFl! $0.59.
2 Applicant submits Amenduent No.16 to Operating Licence to allow Saxton to receive, possess, and use the plutonium fueled subassembly describod in chtmge requent No.17.
S/J. TON liUCLEMt EXPUtIMEllTAL CORPOTLATION i
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Vice President 1
ATTEST:
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- 11. E. Sypher Secretary (S E A L) 1965 Sworn and subscribed to before me this 2nd day of April (G E A L)
/s/ Charles J. Ausel flotary Public Muhlenberg Township, Berks County Hy Commission Expires Oct. Ih, 1966
$dO2 pam[,{'_y2910424 n
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1 Docket No. 50-146 DPR 4 Technical Specification Change Request No. 17 Page 1
of 6
Pages 4
i 1.,
Description of Cnange In Supplement No.1 to Technical Specifications, page 2, change Ite F. 2. to read:
Uranium oxide (Uo )
nriched to 5 7% of U-235 shn11 te used in the fuel assemblies, 2except that the test fuel assemblics listed below having enrichments and other character 1ctics as described may be inserted in the reactor.
In test fuel assemblies the fuel rods as described may be replaced with regular fuel rods, that is, enriched j
to nominni 5 7% U435 and constructed as described in Technical Specification F.3 4
Test Assembly No. i one 61 rod assembly containing rods of the numbers and types listed in the following table:
mo Pellet Peak N.
f
'Ihickneos(1)
Diameter Enriebnent Power Rods Claddirc kW 30k ss 80 5 mils (l } o.29h ira o.b v/o 31hv/ft h(5) 30h s3 80 5 0.294 0.29w/o 2.2 3
304 ss -
15 0 357 (2) 16 3
304 ss 15 0 357 (2) 16 3
30k ss 15 0 357 (2) 16 3
304'ss is o.357 (2) 16 3
16 20 ss 15 o.357 (2) 16 3
348 ss 15 0,257 (2) 16 304 ss(9) 15 0 357 5.69v/o 1.35.
3 3
304 ss is i o.357 5 69 v/o(3) 13 5 Zr 4(6) 23 7 o.337 5.69 v/o 12.0 3
ZrA(6) 23 7 o.337 6.1v/o 13 5 s
N 3
Zr -2 23 7 o.337 (2) 14 Er-2(6)(Ni free) 23 7 0 337 (2) 14
-3 3
Zr 4 23 7
.o.337 (2) 14 Il0) 23 7 0 337 (2) 14 3
Zr A 5
3 ze 4 23 7 o.337 (2) 14 Zr 4(7 23 7 o.337 (2) 14 3
3 Zr 4 23 7 0 337 7 3 v/o 16 l
L a.
en-u ichnical Specification Change Request No. 17 Pnge 2 o4' 6 Pages Notes for Table (1) All roda are free standing 0 391 in. O.D. aominal (2) pirst 14 pellets 5.69 w/o next 5 pellets 6.81 v/o next 12 pellets 6.45 v/o next 5 pellets 6.81v/o next 13 pellets 5.69v/o (3) Contains approximately 100 ppm bcron as circonium diboride (4) RCC element with perforated guide tule (5) RCC element with solid guide tube (6) Autoclave pre-oxide on 0.D.
Autoclave pre-oxide on O.D. and I.D.
Furnace pre-oxide on O.D.
Compartmented rod, 3 sections (10) As pickled, no pre-oxide treaunent (11) RCC Rod 0.D. is 0.461 in. nominal Test Assemblies 11 and 111 Test Fuel Test Fuel Assembly No.11 Assembly No. iii 9-Rod 9-Rod Sub-as sembly Sub-assembly First ik pellets 5.69%
5.69%
Next 2 pellets 9 19%
7 30 %
Next 3 pelleth 8.57 %
6.81%
Next 12 pellets 8.13%
6.k6%
Next 3 pellets 8.57 %
6.81 %
Next 2 pellets 9.19%
7 30%
Next 14 pellets 5 69%
5 69%
NOTE: The 9-rod sub-assembly in the first column.shn11 not be used at reactor power levels greater than 20 }&t.
Test Fuel Assembly No. iv One 9-rod sub-assembly shall have four corner rods clad with Zircaloy 4 having a nominal thickness of 23 7 mile and shall contain uranium oxide (UO )
2 enriched to 6.1% U 235
'Ibe other five rods shall te clad with Type 304 stainless steel having n nominal thickness of 9 5 mils and shall contain uranium oxide (UO ) '"#i"h*0 t0 E'7$ U'235' 2
Ur 4 Te..nical Specification Change Request No. 17 Page 3 of
_6_
Pages Tert p1 Accembly No. y One 9-rod rut'-ascembly chull have four corner rods clad with Zirenloyd having h n:cinrd thickness of 23.'l milr. and shall cortain uranium oxide (UO )
2 enriched to 6.1% U-235 We other five rods shall be clad with Type 304 stainlecc steel havirs a nominni thickness of 9 5 mila and shall contain uranium oxide (UO ) hovin6 the came enrichment as Test Fuel Assembly No. iii.
2 Test Puel Actembly Ib. vi One k-rod sut%ssembly chall have rods clad with Type 304 stainless steel havira a nominal thickness of 23 5 mile and shall contain uranium oxide (UO,)
fuel pelleto uniformly enriched to 8 3% U-235 One of these rods may contaIn up to 100 rpm teron as zirconium diboride.
Test Puel Assembly No. vii One 9-rtd sub-assembly shall nave four corner rods and the center rod clad with Zirculoyd havinC a nominal thickness of 23 7 mile and shall contain uranium oxide (UO ) uniformly enriched to 7 3%. Two of the other rods shall 2
be clad with Type 304 stainlesa steel having a nominal thickness of 15 mile and shall contain uranium oxide (UO ) unif rmly enriched to 5 7% U435 One 2
other rcd shall te clad with Type 304 stairdens steel having a nominal 0.29% U-235, and shall be concentrically located within'y) having e. content o thicknest of 16.1 mils, shall contain uranium oxide (UO a solid stairdena steel guide tute.
The remaining rod shall be clad with Type 304 stainlass steel hoving a nominra thickness of 16.1 milo, shall contain uranium oxite -(UO )
2 havirg a content of 0 71% U-235 and shall be concentrically located within a perforated s sinless steel guide tube.
Test Puel Assembly 16. viii One 9-rod sub-assembly r. hall have three corner rods clad with Zirenloy4 havire a nominal thiehness of 23 7 mils and aball contain vibracionally compacted uranium dioxide (UO ) enri hed to 7.P% U-235 end ccepacted to 86 + 2% theoretical density. 27he fourth ccrner rod and the central rod shan be clad with Type 304 stainless steel having a nominal thickness of 15 mils and shall contain vibrationally compacted uranium dioxide (UO )
enriched to 7 2% U435 and compacted to 86 + 2% theoretical density. 2 Three of the remaining rods shall be clad with Zircaloy4 and shall contain uranium dioxide (UO ) pellete 0 337 inches in diameter which are enriched to 6.1% U435.
On$ of these rode shall have a previous irradiation exposure of ~7500 megawatt days per metric ton (WD/MT) and shr3 contain a 15 mil dinseter hole nachined through the clad. Se second o. these rode chall huve a previous irradiation exposure of N7500 WD/MT. The third of these rods shall have a 15 mil diameter hole machined through the clad. We final rod shall be clad with sensitized Type 304 stainless steel and shall contain uranium dioxide (UO ) pellets enriched to 5.69% U435 and the ten 2
central pellets shall have 20 mil chamfers on both ends.
DP Tecnnical Dpecification 4
Change Re:;uest No.17 hge 4 of 6 Pages i
i i
i Following a period of irradiation, the two defected, Zirealoy-4 cla? r @
mry te repinced by imilar, defected unirradiated Zircaloy-4 ciud rods.
r Test Fuel Assembly ix One 9 x 9 ibel assembly shall contain 51 rods clad with Type 304 stainless I
steel of 15 mile thickness and shall contain uranium dioxide (UO ) fuel pellets 2
of 5.69% U-235 enrichment. This assembly is made by removing the central 21 roda from a normal 9 x 9 fuel assembly.
The space left by removal of t.he central 22 rods shall te filled by a plug consisting of a stainless steel tube 0.125 inches thich and 2 75 inches in diameter velded to ptrforated stainless steel end plugs.
1he end plu6s shall be designed so that flow through the plug vill experience the stae enthalpy rise that is experienced by flov through a normal
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fuel assembly. 7hs plug shall contain three concentrically mounted stainless steel pipes 0.125 in thich and of 2.125, 1 50 and 0 75 in, diameters, respectively. Horizontal restraint for the plug shall be provided by the grids of the fuel assembly. Vertical support for the plug shall be provided by a 15 in. diameter stainless steel pipe extension of the reactor head port -
flange. When Change Request No.16 has been approved by the Atomic Energy Comirsion this clug may be reolaced by a fueled supercritical loop pressure w V.y.
subs v
Test Puel Assembly x l
One 9-rod sub-assembly chall have eight rods clad with Zircaloy h having a nominal thickness of 23 3 mile. ihe fuel shall be mixed natural uranium-plutonium dioxide enriched to 6.6 v/o pa0.
Four of the rods shall contain vibrationcompactedfuelandtheremainirkfour-shallcontainsinteredceramic l
pellet fuel. The ninth rod position vill be.a flux, thimble for use with in-core l
instrumentation.
Test Capsules Test capsules containing non. fuel material may be inserted in any of the eleven dummy fuel locations adjacent to the reactor core region or in any of the eight irradiation sample tubes on the periphery of the core provided thatt
- 1) Prior to Arradiation, the design of-the test capsule has been evaluated by the SNEC Safety Committee and fcund acceptable with regard to physical, thermal and hydraulic performance and effect -on core reactivity, - neutron flux and reactivity coefficients.
- 2) No foreseeable failure of a test capsule could result in mechanical damage to any core component or in any manner alter the ability of the control system to function.
1
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DP4 Technical Specification Change Request No. 17 page 5
of 6
Pages s
- 2) Purpose of Change ne purpose of this change is to permit insertion of test fue'l aqsembly x l
into the reactor. Test fuel assembly x is to be inserted in a peripheral location for the duratton of Core l' irradiation. Test assembly x is designed as a proof test experiment for the fabrication techniques of the plutonium enriched fuel rods for the central nine assemblies planned for Saxton Core II.
l
- 3) fafety Consideratfor.s I
The design charact.eristien of the fuel in test assembly x is given in Tuble 1.
Operation of the plutonium fueled test assembly will present ne nev hacards in the absence of any gross manufacturing errors which might enuse cladding failure.
'Ihe purpose of the irradiation of this test assembly is to proof test the manufacturing techniques that are being 4
employed in the construction of the Core II plutonium fuel rods.
l The health physics procedures employed at Saxton vill be updated to include alpha detection capability by means of portable surface contamination and air particulate contamination monitors.
'Ihes e instruments vill provide suffielent sensitivity to detect any plant site alpha contamination due to failure of this test assembly which might present a danger to operating personnel or the public.
- 4) Health and Safety of the Public It is mir conclusion that the health and safet.y of the public vill not be endangered by this change.
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SAXTON !!UCLih. LTPFRlMENTAL CORPORATION Application for 3
Reactor Construction Permit and Operating License s
Docket No. 50-lh6 Amendment No. 16 Saxton hereby requests that Section 2B of Operating License DPH-b be amended to read as follows:
"D.
Pursuant to the Act and Title 10 CFR, Chapter 1, Part 70 "Special Nuclear Materials," to receive, possess, and use at any one time 130 kilograms of contained Uranium-235 and 300 grams of contained Plutonium-239 as fuel for the operation of the reactor) and" The purpose of this change is to permit the receipt, on-site storage, and irradiation at Saxton of a nine rod subassembly using Po-239 as the fissile material.
Present plans for the Saxton second core include the use of nine Pu enriched assemblies in the center nine positions of the core. This second core program includes irradiation of a removable nine rod 3x3 subassembly in a peripheral location of the present core as a proof test of the mechanical design l
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