ML20210K213
| ML20210K213 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 08/15/1997 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20210K207 | List: |
| References | |
| NUDOCS 9708190183 | |
| Download: ML20210K213 (2) | |
Text
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SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core $ls 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:
THERMAL POWER shall be s 25% RTP.
2.1.1.2 With the reactor steam dome pressure a 785 psig and core flow a 10% rated core flow:
MCPR shall be a 1.07 for two recirculation loop operatio o
. 1.08 for single recirculation loop operatio. W 2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
1 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 I hour, 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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Reporting Requirements 5.6 l
5'. b Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued) 1)
NEDE 24011-P A, " General Electric Standard p
ation for Reactor Fuel" (latest approved version c.
The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic liinits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
d.
The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
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