ML20205L732

Proposed Tech Specs,Removing Notes That Refer to Specific Cycles,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits

ML20205L732
Person / Time
Site:	River Bend
Issue date:	04/08/1999
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20205L728	List: ML20205L732 RBG-44965, Responds to 990324 Telcon RAI Re SLMCPR Calculation Method for RBS Cycle 9 Slmcpr,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits. Proposed TS Pages, Encl
References
NUDOCS 9904140272
Download: ML20205L732 (2)

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 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 2 1.12 for two recirculation loop operation or 2 1.13 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 Pressure SL Reactor steam dome pressure shall be s 1325 psig.

22 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 l with 10 CFR 50.72. l 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.

l 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.

(continued)

RIVER BEND 2.0-1 Mendment No. # M 90

~~

9904140272 990408 PDR ADOCK 05000458' P PDR _

Reporting Requirements 5.6 5.5 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

1) NEDE-24011-P-A. " General Electric Standard Application for Reactor Fuel" (latest approved version):

2) NEDC-32489P (April 1996). "T-Factor Setdown Elimination Analysis for River Bend Station" (for power and flow dependent limits methodology only as evaluated and approved by Safety Evaluation and License Amendment 100 dated October 10. 1997).

c. .The core operating limits shall be determined such that all applicable limits (e.g. fuel thermal mechanical limits, core thermal hydraulic limits.' Emergency Core Cooling Systems (ECCS) limits, nuclear limits sucii 3s SDM. transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR. including any cidcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

l-RIVER BEND- 5.0-19 Amendment No. 81 % GG 4M