ML021000402

Technical Specification Page for Browns Ferry, Unit 3, Amendment 234

ML021000402
Person / Time
Site:	Browns Ferry
Issue date:	03/29/2002
From:	NRC/NRR/DLPM/LPD2
To:	Tennessee Valley Authority
References
TAC MB3485
Download: ML021000402 (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 > 785 psig and core flow

> 10% rated core flow:

MCPR shall be > 1.08 for two recirculation loop operation or > 1.10 for single 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 Pressure SL Reactor steam dome pressure shall be < 1325 psig.

2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.

BFN-UNIT 3 2.0-1 Amendment No. 2--6, 234