ML20134D875
| ML20134D875 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 10/24/1996 |
| From: | CENTERIOR ENERGY |
| To: | |
| Shared Package | |
| ML20134D852 | List: |
| References | |
| NUDOCS 9610310076 | |
| Download: ML20134D875 (1) | |
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PY-CEI/NRR-2104L Page 1of1 l
i SLs 2.0 2.0. SAFETY LIMITS (SLs) l 2.1 SLs j
2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core l
flow < 10% rated core flow:
THERMAL POWER shall be s 25% RTP.
2.1.1.2 With the reactor steam dome pressure 2 785 psig and core flow 210% rated core flow:
MCPR shall be 2M for two recirculation loop operation or for single recirculation loop operatiop.
2.1.1.3 Reactor vessel water level shall be greater than the top 1
of active irradiated fuel.
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2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be s 1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed:
2.2.1 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, notify the NRC Operations Center, in accordance with 10 CFR 50.72.
2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.2.1 Restore compliance with all SLs; and 2.2.2.2 Insert all insertable control rods, 2.2.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the plant manager and the corporate executive responsible for overall plant nuclear safety.
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i 9610310076 96t024 PDR ADOCK 05000440 P
PDR I
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PERRY - UNIT 1 2.0-1 Amendment No. 69
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