ML20210L331

Proposed Tech Specs,Incorporating Note Which Indicates That Proposed Change to SL Mcrp Applicable for Current Operating Cycle (Cycle 16) Only

ML20210L331
Person / Time
Site:	Oyster Creek
Issue date:	08/15/1997
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20210L330	List: ML20210L324 ML20210L331
References
NUDOCS 9708210054
Download: ML20210L331 (1)

Text

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SECTION 2 SAFETY LlhilTS AND_ LIMITING SAFETY SYSTEhi SE'ITINGS 2.1 SAfflY LlhitT FUEL CLADDING INTEGRITY Applicahility: Applies to the interrelated variables associated with fuel thermal behavior.

Objecliys: To establish limits on the important thermal hydraulic variables to assure the integrity of the fuel cladding.

Spstifications:

A. When the reactor pressure is greater than or equal to 800 psia and the core flow is greater than or equal to 10% of rated, the existence of a minimum CRITICAL POWER RATIO (hiCPR) less than 1.09* shall constitute violation of the fuel j cladding integrity safety limit.

11. When the reactor pressure is less than 800 psia or the core flow is less than 10% of rated, the core thermal power shall not exceed 25% of rated thermal power.

C. In the event that reactor parameters exceed the limiting safety system settings in Specification 2.3 and a reactor scram is not initiated by the associated protective instrumentation, the reactor shall be brought to, and remain in, the COLD SIIUTDOWN CONDITION until an analysis is performed to determine whether the safety limit established in Specification 2.1. A and 2.1.B was exceeded.

D. During all modes of reactor operation with irradiated fuel in the reactor vessel, the water level shall not be less than 4'8" above the TOP OF ACTIVE FUEL.

Ihther The fuel cladding integrity safety limit is set such that no fuel damage is calculated to occur if the limit is not violated. Since the parameters which result in fuel damage are not directly observable during reactor operation the thermal and hydraulle conditions resulting in a departure from nucleate boiling have been used to mark the beginning of the region where fuel damage could occur. Although it is recognized that a departure from nucleate boiling would not necessarily result in damage to BWR fuel rods, the critical power at which boiling transition is calculated to occur has been adopted as a convenient limit liowever, the uncertainties in monitoring the core operating state and in the procedure used to calculate the

• Applicable for cycle 16 only.

OYSTER CREEK 2.1-1 Amendment No.: 75,135, 9708210054 970015 PDR ADOCK 05000219 P PDR '

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