ML20085E934
| ML20085E934 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 02/24/1966 |
| From: | Neidig R SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9110210279 | |
| Download: ML20085E934 (5) | |
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SAXTON NUCLFAR EXPDtllDiTAL CORPORATION
.c n-DOCrrr NO. 50146 LICD;SE DPR 4 CHA!GE REQUEST !E.22 1.
Applicant hereby submits Change Request No. 22 in compliance w$ th paragraph 3B of License DPR.h for ebange of the Technical Specifications to be authorized by the Comission as propded in 10 CFR 50 59 0AITON NUCLEAR EXPERI}C;TAL CORPORATION l
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/s/
R. E. Neidig President ATTEST:
/s/
R. E. Sypher Secretary (SEAL)
Sworn and subscribed to before me this i t?._ day of February
. 1966
/s/ Martin A. Kohr (S E A. L)
Notary Public Muhlenberg Township, Berks County
}tr Commission Expires February h,1970 s
9110210279 910424
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Docket lic. 50-146 DPR-4 fechni:a1 Specification Change Request No. 22 Page 1 of _L Pages 1)
DECRIPTIO!' 0F CHAIGE In Supphnent lio.1 to Techni:a1 Specifications, add the following Test Fuel Assenblies to Iten F.2.
Test Fuel Assenbly xii One 9-rod subassenbly shall have the four corner ro.ls and the central rod clad with type 304 stainless steel having a ncainal thickness of 15 r.ile_and shall contain uranium dioxide (UO ) pellets uniformly enriched to 5.7% U-235,N These 2
five rods are identical to standard fuel rods with the exception that the end closure welds are sub-standard _ for testprpora The renkining four rods" shal be c a.ad wu.n typo Joh s'.ninless steel having a naninal thickness of 15 mile and shall contain uranium dioxide (UO ) pellets unifoml;* enriched to 2
5 7% U-235.
These four rods are also 1,denligaLto standard fuel rods except that they are internally pressurized toyoduce teogils..:LtgejLsfis_i!1_91e clad at reactor operatfrig conditions. No~of these rods shall have maximum operating stresses of approximately 23,100 psi and two shall have maximum operating stresses of apprcxinately 36,140 psi.
Test Fuel Assembly xiii One 9-rod subassembly sha n have the four corner rods and the conter rod clad with type 304 stainless steel having a nominal thickness of 15 mils and shall contain uranium dioxide (UO2) pellets enriched to 5.7% U-235, having a previous irradiation exposure of approximately 3300 WD/HTU.
Two of the remaining rods shall be clad with Zircaloy-4 having a nominal thickness of 23.5 mile and shall contain uranium dioxide (UO2) pellets unifomly enriched to 1. # U-235 and shall be interna 11;, pressurized to produce maximum operating > resbes of approximately 21,730 psi. One of the rmaining rods shall be clad with type 304 stainless steel having a nominal thickness of 9.7 mils and containing uranium dioxide (UO ) pellets unifomly enriched to 5.7% U-235 with a previous 2
irradiation exposure of 8900 WD/MTU.
The last rod shall be clad with Zircaloy-2 (Ni free) having a nominal thickness of 23.5 ::.ils and containing uranium dioxide (UO2) pellets enriched to 7.3% U-235 with a previous irradiation exposure of approxinately 7400 WD/MTU.
The last rod will be intentionally defected by machining a small slit through the clad wall at the region of peak burnup.
This test subassembly may be operated only in a peripheral core location while containing the 17 4% enriched fuel rods.
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DPR-4 Technical Specification Change Request No. 22 Page 2 of 4_ Pages 4
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2)
PURPOSE OF CHAfGE The purpose of this change is to permit the insertion of test fuel assemblics l
i xii and xiii into the reactor.
The scope of these exper!nents involves one new 9-rod cubassembly and modification of a 9-rod subassembly previously I
inserted into the reactor.
1 The objectives of these experiments are to provide infomation on the in-pile perfomance of sub-standard end closure welds, and of fuel rods that are operating with various types of cladding subjected to large tensile stresses to continue the in-pile defect test experinent using a previously irradiated fuel rod and to continue the exposure of a previously irradiated, thin-walled rod representing plastic defomation.
4 3)
SAFETY CONSIDERATIONS The design characteristics of the fuel rods in the two test subassemblies are given in Table I.
In general, all of these rods are similar to fuel rods which have been reviewed in Addenda to the Phase I Safeguards Report and in various Technical Specification Change Requests. There arn ';rvo i
l new items represented by these assemblies not previously reviewed.
l The first item is the inclusion of two fuel rods enriched to 17.4% U-235.
Although this enrichnent is above any previously used in the Saxton reactor, operation of these rods in a peripheral location will make the maximum linear power density about 8 kw/ft which is below the nominal maximum for the core of 16 kw/ft. This higher enrichment has been included to provide sufficient burnup and surface heat flux on the pressurized Zircoloy-4 clad rods.
The second item is the inclusion of some internally pressurized fuel rods.
The nomal practice for these fuel rods is to design so that there will be no tensile stress in the clad at the end of life due to fission gas As shown in Table I, six rods (four stainless and two Zircaloy) pressure.
will be internal.17 pressurized with Argon to cause significant tensile stress in the clad throughout-the operation of these test assemblies.
Operation of these rods in this test assembly will provide infomation on the effects of high stress combined with irradiation exposure on the clad perfomanc e.
The third itan is the inclusion of five standard Saxton fuel rods with end-closure welds that are sub-standard. These fuel rods are part of the group that were nanufactured _ for loading into Core 11 but did not quite meet the specifications for end closure welds. These welds have been thoroughly inspected and the sub-standard features documented.
These rods have been included to deternine the effects of in-pile operation on various kinds of suo-standard weld features.
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I DPR-4 Technical Specification l
Change Request No. 22 Page 3 of 4 Pages 1
The fourth iten is the possible inclusion of two new types of grid materiale in test subassenbly xii.
One type is AM 350 which is a precipitation hardening stainless steel and the second type is AM 362 which is a mar-aging high nickel steel. These materials are being tested for possible use as grid materials in the future and no problems are anticipated with their perfornance as
...,v both braze and fabricate well.
The fifth item is the re-insertion of a previously irradiated, thin-walled stainless steel fuel rod which experienced plastic deformation due to a hydrostatic test conducted during its previous exposure period. A detailed report on the post collapso evaluation of the thin clad stainless steel rode is given in WCAP-3269-36.
The other characteristics of these test assemblies have been reviewed in previous change requests and Phase I Safeguards Report Addenda.
The new items described above have been included in these removable test subassemblies because of their versatility and ease of insertion into and removal from the reactor. The major safety consideration of these new assemblies is the possibility of a fuel rod failure because of the inclusion of the pressurized rods and the sub-standard end closure welds.
Failure of these rods is not anticipated although the probability of failure is higher than that for the normal Saxton fuel rods.
The exposure and ournup of these rode in the periphery of the Saxton core will be quite low so that even if some of these rods did fail, the failure would not create a severe hazard and could easily be handled by removal and storage of the failed assembly.
It is-our conclusion that the operation of these test assenblies does not present any significant hazards considerations not previously reviewed and described in the Saxton Final Safeguards Report and its Addenda.
4)
HEALTH A!!D SAFETY lt is our opinicn that the health and safety of the public will not be endangered by this change.
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TABIE I FUEL ROD DESIGN PARAMETERS - T5T FUEL ASSHiBLIES xii an xiii 4
Test Clad (l)
Fac1(2)
Est. Meut.
No.
Rod No.
Type Material Thickness (mils)
Enrichment (w/o U) Power (kw/ft)[y)
Clad Notes l
Assembly 1
.711,712 Rmovable Zr-4 23.5 17.4 9.5 (4)
{
}
123 Renovable Zr-2 (Ni Free) 23.5 7.3 5.5 (5)(6)
[
1 1
Reovable 304 S/S 9.7 57 4.6 (7)(8)
{
xiii 753,755,756, Non R movable 304 S/S 15 5.7 -
4.6 (9,
L757,762 f
'781,782
. Removable 304 S/S 15 5.7 4.6 (10) xii 783,784 Removabic 304S/S 15 57 4.6 (11) 37,125,191, Non Rmovable 304 S/S 15 5.7 4.6 (12)
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i NOTES:
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(1) All rods (except #1) are " freestanding" with O.391" O.D.
f (2) En-ichnents are uniform throughout rod.
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. 3) When operatine. in a Saxton peripheral core location.
((4) Internally pressurized to produce a m ximum in,911e clad O.D. tensile stress of 21,730 psi.
I (5) Previously irradiated to 7400 MWDAiTU.
(6) contains 1/2" long and 1/32" wide *1it machined through clad at 17-1/2" from bottom.
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-(7) Previously irradiated to 8900 MWDAITU.
l (8) " Thin-walled" design representing plastic deromation.
(9) Previously irradiated to 3300 MWDAITU.
Internally pressurized to produce a maximum in-rile clad O.D. tensile stress of 23,100 psi.
(10). Internally pressurized to produce a naximir.n in-pile clad O.D. tensile stress of 36,140 psi.
(11)
(12) Sub-standard end closure welds are represente..
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UNITED STATES ATCR41C ENERGY CCHMISSION DOCKET Ho,_50-146 SAXTON NUCLEAR EXPERIMENTAL CORPORATION NOTICE OF P'10 POSED ISSUANCE OF OPERATING 1.ICENSE A@NDME Please take notice that pursucnt to Section 189 of the Atomic ';nergy Act f
of 1934, as axnded, the Atomic Energy Cotraission is consiaring the issuance o
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At endmen'e No. 2, set forth below, to Operating License No. DPR-4 which author-imee Saxton Nuclear Experimental Corporation to oprate its light water moders.ted and cooled, pressurizad water reactor located near the Borough of Saxton in Lioerty Townshin, Bedford County, Pennsylve.nia. The proposed amend-1 ment uuld authorize the 1 ensee to replace its present uranium-oxide reactor core wish a partial plutonium co a (Corn JI). On April 30, 1965, Amendment No.
I to Operacing Lic nse "o. DPK-4 v s issued, sattorizing the conduct of proof tests for the partial plutoniu:n core.
Within thirty (30) days fece the date of publication of this notice in the Federal Register, the applicant may file a request for a hearing, and any person whose interest may be affected by tt proceeding may file a petition for leave Requests for a hearing and patition to intervene shall be filed to intervene..
If a request in accardance with the Commission's " Rules of Practice," 10 CFR 2.
for a hearing or a petition for leave to intervene is filed within the time prescribed ir this notice, a notice of hearing or an appropriate order will be If no request for a hearing or petition for leave to intervene is issued.
filed within t.he time prescribed in this notice, the Cour isaion will issue the license amendment thirty days from the date of publication of this notice in the Federal Register.
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2-For further details with respect to this propoud amendment, see (1) the application for licence amendment dated April 2, 1965, and supplement chereto dated May 28, 1965, (?) the report of the Advisory Comnittee on Reactor Safe-guards dated July 19,1965, and (3) a related safety evatustic.a prepared by the Research and Power Reactor Safety Branch of the Division of Reactor Licensing, all of which are available for public inspection at the Commission's Public Documsat Room,1717 H Street, N. W., Washington, D. C.
Copies of items (2) and (3) above may be obt.ained at the Comnission's Public Document Room, or upon request addressed to the Atomic Energy Commission, Washington, D. C. 20545, 2
Attention: Directvr, Division of Reactor Licensing.
FOR THE ATOMIC ENERGY CG9tISSION OrigiMI Signed By R.LDcan R. L. Doan, Director Division of Reactor Licensing Dated st-Bethesda, Maryland this day of August,1965.
AUG 161965 1
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9 SAITON NUCQAR EXPERIMENTAL CORPORATION DOCTIT No. 50-146 PR_0 POSED OPERATIMC LICENSE AXENDMENT License No. DPR-4 Amendment No. 2 The Atomic Epirgy Comission having found that:
a.
The application for license amendment dated April 2,1965, as supplemented May 28, 1965, complies with the requirements of the Atomic Energy Act of 1954, as emended, and the Comission's regu -
lations set forth in Title 10, Chapter 1, CFR; b.
There is reasonable assurance (i) that the facility can be operated in accordance with the license, as amended, without endangering the health and safety of the public and (ii) such activities will be conducted in compliance with the rules and regulations of the Com-mission; I
c.
The licensee is technically an,1 IMncially qualified to engage in the activities authorized by this license, as amended, in accordanc.e with the rules and regulations of the Comission; and d.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; Operating License No. DPR-4, as amended, which authorizes Saxton Nuclear Experi-mental Corporation to operate its nuclear reactor located near thu Borough of Saxton in Liberty Township, Bedford County, Pennsylvania, is further amended in accordancu with the application, as follows:
4 Subparagraph 2.3. is : suded in its entirety to read:
"2.B.
Pur suat..: to the Act and Title 10, CFR, Chapter 1, Part 70,
'Spe-ial Nuclear Material,' to receive, possess and use at
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2-any one time 130 kilograms of contained Uranium-235 and 25 kilograms of contained Plutonium-239 as fuel for operation of the reactor."
Tt.is amendment is ef fective as of the date of issuance.
FOR THE ATOMIC ENERGY CCHMISSION R. L. Dean, Director Division of Reactor Licensing
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