ML19319B261
| ML19319B261 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/14/1972 |
| From: | US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19319B260 | List: |
| References | |
| NUDOCS 8001140569 | |
| Download: ML19319B261 (4) | |
Text
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-f Oconee Euclear Station Units 2 and 3 50-270/287 Docket Nos.
Structural Evaluation Report STROCTURAL DESCRIPTION: - facility include the
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The Seismic Class I structures of the s; the auxiliary build containnent and its internal structure f.
and the dsm'and spillway complex.
d concrete structure -
The contalusent is a steel lined prestresseht circ in the form of a vertical rig The structures interior to the base and a flat spherical done.
d concrete castructica f
containment are typically of rein orce The wer plants.
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with details typical to PWR type nuclear pore, likcwise, structures external to tho' containment a nuclear power plant configurations.
DESIGN LOADS AND COMBINATIONS:
for the usual wind, tornado,;
II.
The Cissa I structures vers designed h pressure, accident and operi-reicnic, dead, live, buoyant, eart ating loads.
d a 59 psis desige.
The containnent was designed to withstan setente d t temperature.
pressure' and a concurrent peak acci en i e basis earthquakes, loads resulting from operating basis and des g w
have, likewus, been considered.
i h tand wind loading using-
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The contahent was also designed to w t s
. A tornado loading ithe practica established in ASCE paper 3269.
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application of a wind with a 300 mph velocity and a decrease n,
in atmospharie press'ure of 3 psi in 5 seconds. We find the
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. methods of converting the. wind and tornado velocities inte loadings and the applications of loads to be acceptable since
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they are similar to those previously approved.
.III.
CONTAIEMENT DESIGE:-
.ne containment structure was designed in accordance with tha
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provisions of the ACI-318-63 and supplementary criteria as J.'.,.
established is. the SAR. no. containment prestressing consists 7,
mt L of a b'dop _... sad longitudinal prestressing tendocs in the cylinder g
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and meritional ten, dons in the doms. Radial shear in the cylinder
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i reinforcing b'ar splices are by the Cadeeld process.
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he containment structure was analyzed for Exi=ymmetrie loads
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using finite element' theory. He finite element approach was y.
j also employed to evaluate the effect of non-axisynsmetrie loads. -
j na general design and analysis procedures as prepared by the a
applicant and out11=ad above are appropriata and acce'ptable for the containment, since they are in accordence with the general i
i practice of the profession.
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Stresses resultant. frem smalysis have been s==anised in _ tabular' j
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form im Section Y of the safety. Analysis Report. S e stresses, in
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' general, lie well.withis established allowables and are acceptable.
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'W 3-IV. CLASS I STEUCTURES OTi1ER TilAN CONTAIEMENT:
The static analysis techniques espiged are those conventionally applied in bees, frame, and this shall analysis.
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He design of concrete structures internal and external to the contaf nment was accomplished in accordance with the provisicas f
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of ACI-318-63. Design of interior structures included consider-ation of local pressure (208 pai for the reactor cavity) and jet impingement loads.
All Class I steel structures other than cont'ainment were designed by the working ~ stress method in accordance sith the provisions of the AISC Specification. Stress resultant 7were maintained below allowables..
~ ne applicant has designed all Class II'struct'.res that, through collapse, could damage Class I items as Class I or relocata such structures-so that the cafety function of Class I items is unaffected.
These procedures are similar to procedures approved for previously
. licensed facilities and are therefore acceptable to us.
V.
STRUCIURAL MATERTATS, CONSTRUCTION TECHNIQUES, AND QUALITY COSTROL:- _
The structural materials, construction techniques, and quality control 'are, for the most part, similar to those applied on other recent maclear facility construction projects.- A 500 psi concrete'.
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was used for the containment. Reinforcing steel conforms to i
ASTM A-615 with Crade 60 being used in' the foundatica slab and
. Crade 40 being eployed in the cylinder and dome for crack eco :
~ Full tanzion Cadweld splices were employed for bar~aplicing
-trol.
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. of reinfoz ing bars of greater than size no.11.
Conventional construction sethods were used for this facility. The quality
. control procedures, which are similar in scope to those previously applied in other plants. such as Point Beach are acceptable to us for the Oconee Nuclear Power Plant.
t IV. STRUCTURAL ACCEPTANCE'TESTi.
The containment was pneumatically tested to l' 15 times the 4
dest pressure 'with gross deformation of the structure being recorded.
Tant wire'aystems,'. identical to the one employed a,--~~~~m~~~
T for Unit 1 were used for Units 2 and 3.
Crack pattern observa-4 tions were made in key areas.
Cafety Guide No.18, which was applied, includes a provision M
for lesser instrmientation for non-prototype containments.
In" view of the fact that Units 2 and 3 containments are identica11 f
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,. g in design to the Unit I contain=nt the lesser instrumentation.
21-providad is acceptable.
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