ML20009B793
| ML20009B793 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/09/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20009B794 | List: |
| References | |
| NUDOCS 8107170175 | |
| Download: ML20009B793 (1) | |
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w-s 3.1.2 Pressurization, Heatuo and Cooldown Limitations Specification 3.1.2.1 Hydro Tests For thermal steady state system hydro tests, the system may be pressurized to the limits set forth in Specification 2.2 when there are fuel ~ assemblies in the core, under the provisions of 3.1.2.3, and to ASME Codc limits when no fuel assemblies are
- present provided the reactor coolant system limits are to the right of and below the limit line in Figure 3.1.2-1.
The pro-visions of Specificatio is 3.0.? and 3.0.4 are not applicable.
3.1.2.2 Leak Tests Leak tests required by Specification 4.3 shall be conducted under the provision of 3.1.2.3.
The provisions of Specifi-cation-3.0.3 are not applicable.
3.1.2.3 The reactor coolant pressure and the system heatup and cooldown rates (with the exception of the pressurizer) shall be limited in accordance with Figure 3.1.2-2 and 3.1.2-3, and are as follows:
Heatup:
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Allowable combinations of pressure and temperature shall be to the right of and below the limit line in Figure 3.1.2-2.
The heatup rates shall not exceed those shown in Figure 3.1.2-2.
Cooldown:
Allowable combinations of pressure and temperature for a specific cooldown shall be to the right of and below the limit line in Figure 3.1.2 3.
Cooldown rates shall not exceed those shown in f
Figure 3.1.2-3.
3.1.2.4 The secondary side of the steam ganerator-shall not be pressurized above 200 psig If the temperature of the steam generator shell is l
below 100F.
3.1.2.5 The pressurizer heatup and cooldown rates shall not excecd 100F/hr.
The spray shall not be used if the temperature difference between thc pressurizer and the spray fluid.is greater than 430F.
3.1.2.6~
With the limits of Specifications 3.1.2.3 or 3.1.2.4 or 3.1.2.5 l
exceeded, restore the temperature and/or pressure to within the limit within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the frac-ture toughness properties of the Reactor Coolant System; determine l
that the Reactor Coolant System remains acceptable for continued ~
operations or be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce the RCS Tavg and pressure to less than 200F and 500 psia, respectively, within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Amendment No. 22, 28, 57 18
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8107170175 810709 PDR ADOOK 05000313 p
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