ML20210K213

Proposed Administrative Changes to TS 2.1.1.2 W/Note to Indicate Operating Cycle for Which SLMCPR Value Has Been Approved & TS 5.6.5 W/Note Providing Link to Specific GE Documents Used in Approving SLMCPR Changes for Given Cycle

ML20210K213
Person / Time
Site:	River Bend
Issue date:	08/15/1997
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20210K207	List: ML20210K213 RBG-44153, Forwards Proposed Administrative Changes to LAR 96-42 & LAR 97-18,to Modify TS 2.1.1.2 W/Note Indicating Operating Cycle for Which SLMCPR Value Has Been Approved & TS 5.6.5 W/Note Providing Link to Specific GE Documents
References
NUDOCS 9708190183
Download: ML20210K213 (2)

Text

- - - _--___- _ _ _ - _ -

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.

ued)

N VAvvE4 APPUCASW To CVCl E 7 [8] OPmDor/ OdL7 RIVER BEND 2.0-1 Amendment No. 81 9708190183 970815 PDR ADOCK 05000458 P PDR

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.

k FoR c-Ycts 7 [e] , s.recir-ic pccomears werb kPPftovFD ltJ Ttts $58 DATrP To suPP o?-T L,(cGtJ6 G kn16tJpM ENT - ,

M RIVER BEND 5.0-19 Amendment No. 81 l