ML20085F174
| ML20085F174 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 07/28/1966 |
| From: | Neidig R SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 2214, NUDOCS 9110220068 | |
| Download: ML20085F174 (5) | |
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4 SAXTON !!UC'IAR ETERITI: TAL CORP 0itATIO!I DOCKIT UO. 50-146 LICLSE DPR-4 1.
CHA!;GE FG;UH5T NO. 24 r
Applicant hereby sulnits Change Request No. 24 in corapliance with 1
paragraph 3B of License DPR-L for change of the Technical Specifications to be authorized by the Conraission as provided in 10 CFR 50.59.
SAXTON NUCLEAR EXPERIliEHTAL CORPORATION gy
/s/
R. E. NEIDIG President ATTEST:
c2 R. E. SYPiER Secretary (S E A L)
Sworn and subscribed to before ne this 28th day of July
, 1966.
(S ~r A L)
/s/ Charles J. Ausel
~
Notary Public Muhlenberg Township, Berks County My Co=ission ExFires Oct.1h,1966 ol10220068 910424 PDR FOIA I
DEKOF01-17 PDR gg
Docket No. 50-146 1
DPR-L Technical Specificatior, Change Request No. 24 Page 1 of } Pages
- 1) DmCRIPTION'0F CHANGE In Supplcnent No. I to Technical Specificatione, add the following Test Puel Assemblies to Item F.2.
j Test Fuel Assen51v xv one 9-rod subassenbly shall have the four corner rods and the center rod clad with type 304 stainless steel having a noninal thickness of 15 mils i
and shall contain uranium dioxide (UO2) pellets enriched to 5 7% U-235, having a previous irradiation exposure of approximately 42501MDAITU.
The four remaining rods shall be chosen in any ecmbination f som ancng the fcllowing:
a) Rods clad with Zircaloy-L having a noninal thickness of 23 5 mils and containing a series of Zirealoy-L capsules.
Each capsule shall contain one or more circonium alloy test specimens. The circonium alloy test specimens consist of portions of 0.016 inch thick grid strap material loaded within the capsule.
Some of the tpecimens are actual spring fingers of an advanced fuel rod grid design and ~ some are materials test strips formed into an arc.
b) Rods identical to standard fuel rods except that they are internally pressurized to produce tensile stresses of approximately 41,500 psi in the clad at reactor operating conditions.
Rods identical to standani fuel rods except that they are internally c) pressurized to produce tensile stresses of approximately 27,500 psi in the clad at reactor operating conditions.
Rods clad with Zirealoy-k having a nominal thickness.of 23.5 mils and d) containing uranium dioxide (UO ) pellets uniformly enriched to 17 43 2
These rods have a previous exposure of. approximately_1900 }MD/MTU U-235.
and are internally pressurized to produce a maximun tensile stress of approximately 22,000 psi in the clad at reactor operating conditions.
This test subassembly may be operated only in a peripheral core location while containing the-17.4% enriched fuel rods.
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Docket No. 50-146 DPR-4 Technical Specification Unanne Request No. 24 Page 2 of i Pages Fuel Assenblv xvi One 9-rod subascembly sinilar to Fuel Assembly xy except that the four corner rods and the center rc have a previous irradiation exposure of approximately 1000 MID/l!TU and that the end closures on these five rods are C.ubstandard for test purposes. The four remaining rods shall be chosen in any combination from among the followingi a) Rods clad with Zircaloy-4 having a nominal thickness of 23 5 mile and containing a series of Zircaloy-4 capsules. Each capsule shall contain one or more ?.irconium alloy test specimens. The airconium alloy test specinens consist of portions of 0.016 inch thick crid strap material loaded within the capsule. Some of the specimens are actual sprinc fingers of an advanced fuel rod grid design and some are naterials test stripa fomed into an arc.
b) Rods identical to standard fuel rods except that they are internally pressuriced to produce tensile stresses of approximately 41,500 ps1 in the clad at reactor operating conditions, c) Rods identic11 to standard fuel rods except that they are internally pressurised to produce tensile stresses of approximately 27,500 psi in the clad at reactor operating conditions.
d) Rods clad with Zircaloy-L having a nominal tnickness of 23.5 mils and containing uranium dioxide (UO2) pellets uniformly enriched to 17.4% U-235 These rods have a previous exposure of-approximately-1900 BIDA!TU and are internally pressurised to produce a maximum tensile stress of approximately 22,000 psi in the clad at reactor operating conditions.
This test subassembly may be operated only in a peripheral core location while containing the 17.6% enriched fuel rods.
- 2) PURPOSE OF CHANGE The purpose of this change is to permit the insertion of test fuel assenblies xv and xvi into the reactor. The scope of this experiment involves modification of two 9-rod subaseemblies previously inserted into the reactor.
I
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Tech. ten! Lpe ! T ;ctit ' en Chanc,e de:iuent i.1, S.
Face 1 of j Fwn The objective of the e:tperinent, involving accenbly xv in to provide infor-nation on the in-pile perfornance of zirconiun alloy test specinens subjected to conbined themal and radiation fluxes, with particular mphasis on the anount of strens relanation experienced w4th the.1pecinen.; lortded to simulate conditions which would be present in a fuel assenbly sprinc clip.
The c5jective of the experiment involyd-e assenbly xvi is to centinue the accunulation of neutron expoouro on be he Zircaloy-l. and stainless steel clad, internnQv pr tesurized rodo, and deter ine the effects of continucd in-pile oparation on various kinds of sub.etandt.nl weld features.
- 3) SAFETY C0!!SILD!i3IO!!S c
For aceenbly xv the design characteristics of the four rods containing the capsules and nrconiun alloy test specinens are given in Table I.
Tne four rods are identical in design, naterial, quality control, and nesenbly to a standard fuel rod. The atnonphere within each rod will be hellun under one atnosphere pressure at roon temperature.
The thirteen Zircaloy-4 capsules conta',1cd in each of the above rode, are attached end-to-end by neans of a threaded joint.
The string of capsules is in turn attached to the top cud plug of the rod and is suspended in the rod with a 0.375 inch nominal cap at the botton end to acconnodate tolerance accumulations and slight differential thornal expansion from differences in clad and enpoule temperatures.
Sich zirconium alloy test specimen is contained in a special nachined cavity in the capsule which Dubjects the test specinen to a specified pre-load and deflection.
Chenical analyees and descriptions of test specinens are given in Table 11. Stainlesb steel sprirc, pins are used to secure each specimen in its capsule and to lock the threads joining the capsules in order to secure the parts during assembly and remote dicascambly operations.
The pins are installed with an interference fit in the capoules.
The assenbly consisting of the top end plug and capsule string is nado an integral part of the rod by welding the end plug to the rod cladding.
Thus the primary containment for the capsules and test. specimens is provided by 4 -
the rod cladding.
The anall dinnetral clearance (22 nils) between the capsules and the I.D. of the cladding will prevent the stainless suel pins and test npecinens from being dislodged during the in-pile test. The tmperature rice in the capsules, due to ganna heating, is calculnted to be 39-780F uhen the subannenbly is operated in the periphery of' the core and will inerence to 70-1560F when the subassembly is operated in the center of
-the core. The cladding tenperature will be approxirntely the sane as the reactor coolaat. Therefore, the streoses in the cladding during operation vill be no nare nevero than tiuse in a fuel red,_ and the structural integrity of the roa 4 11 be nainthined.
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Docket lio. 50-146 DPR-4 Technical Specification Change Request 11o. 24 Page } of } Pages TAMI_.I
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Rod Utsign Charneterist h 0.391 inches Rod 0.D.
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0.343 inches Rod I.D.
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0.024 inches Wall Thichncos
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0 321 inchen Capsule 0.D.
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TABIE II Description and Rsterials Etress-Relaxation Exper' ment Description of Tent Specin_e_n Material Arc-Type Zr 2$Nb (Annealed)
Arc-Type Zr2) lib (HeatTreated)
Arc-Type Zr-2[ fib-lCu (Annealed)
Arc-Type Zr-23!ic-dCu (Heat Treated)
Arc-Type Zr-4 Spring Fingere Zr-23!1b Spring Fingere Zr-2ilib-lCu
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