ML20053D943
| ML20053D943 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/01/1982 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20053D938 | List: |
| References | |
| NUDOCS 8206070462 | |
| Download: ML20053D943 (1) | |
Text
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SPECIAL TEST EXCEPTIONS
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3/4.10.7 CONFIRMATORY FLOW INDUCED VIBRATION TEST
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LIMITING CONDITION FOR OPERATION 3.10.7 The provisions of Specifications 3.6.1.1 and 3.7.3 may be suspended to permit the drywell head to be removed and the RCIC system to be inoperable with a nitrogen supply line connected to the reactor vessel at the RCIC injection connection in order to perform the confirmatory flow induced vibration test prior to first reactor criticality.
In addition, the provisions of the following specifications which are applicable duri.
HOT SHUTDOWN may be suspended so that the uni?. may be brought to H0f SHUTDOWN and maintained in HOT SHUTDOWN for the duration of the test by non-nuclear heatup provided ', hat initial reactor criticality has not occurred.
Upon successful completion of the test or initial reactor criticality, whichever occurs first, this specification is cancelled.
a.
Specification 3.3.2, Table 3.3.2-1 for Trip Function A.l.c.1, Main Steam Line Radiation - High Monitor.
b.
Specification 3.3.7.10, Table 3.3.7.10-1 for Instrument 1.a., Liquid Radwaste Effluent Line Monitor.
c.
Specification 3.3.7.11, Table 3.3.7.11-1 for Instrument 1.a. Noble Gas Activity Monitor.
d.
Specification 3.4.3.1 for the primary containment atmosphere particulateandgaseousradioactivitymonitorj,ngsystems.
Specification 3.5.1 for the ADS valvesd* B LPcI Q e.
fQ f.
Specification 3.6.1.1, 3.6.1.2, 3.6.1.3, and 3.6.1.4.
Q g.
Specification 3.6.2.1.
h.
Specification 3.6.3, Table 3.6.3-1 for valves in a.1, Main Steam Isolation Valves; a.3, Reactor Coolant System Sample Line Valves; a.10, LPCS, HPCS, RCIC, and RHR Injection Testable Check Bypass Valves; a.12, Drywell Pneumatic Valves; and a.14, TIP Guide Tube Valve Ball Valve.
APPLICABILITY:
OPERATIONAL CONDITION 3, during performance of the confirmatory flow induced vibration test.
ACTION: With the provisions of the above specification not satisfied, be in COLD SHUTDOWN within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.10.7 The reactor shall be verified not to have been critical with any fuel assembly presently in the core within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to performance of the test.
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