ML021020430
| ML021020430 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 04/05/2002 |
| From: | NRC/NRR/DLPM |
| To: | |
| Olshan L, NRR/DLPM,415-1419 | |
| Shared Package | |
| ML021050042 | List: |
| References | |
| TAC MB3756 | |
| Download: ML021020430 (1) | |
Text
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:
THERMAL POWER shall be : 25% RTP.
2.1.1.2 With the reactor steam dome pressure Ž 785 psig and core flow Ž 10% rated core flow:
MCPR shall be Ž 1.07 for two recirculation loop operation or : 1.09 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System (RCS)
Pressure SL Reactor steam dome pressure shall be < 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, the corporate executive responsible for overall plant nuclear safety, and the offsite review committee.
(continued)
Amendment No.
229 2.0-1 HATCH UNIT I