ML20236T121

Proposed Tech Specs Pages for Amend to License DPR-16,to Establish That Existing SLMCPR Contained in TS 2.1.A Is Applicable for Next Operating Cycle (Cycle 17)

ML20236T121
Person / Time
Site:	Oyster Creek
Issue date:	07/23/1998
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20135G042	List: ML20236T109 ML20236T114 ML20236T121
References
NUDOCS 9807270445
Download: ML20236T121 (3)

Text

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l SECTION 2 i

S AFETY LLMITS AND LIMITING S AFETY SYSTEM SETITNGS

2.1 S AFETY LIMIT - FUEL CLADDING INTEGRITY l Aeolicability

Applies to the interrelated vadables associated with fuel thermal behavior.

l Obiective: To establish lirnits on the important thermal hydraulic vadables to assure the l

integrity of the fuel cladding. I Specifications:

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

B. 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 :nd a reactor scram is not initiated by the associated protective instrumentation, the reactor shall be brought to, and remain in, the COLD SHUTDOWN CONDITION until an analysis is performed to determine whether the safety limit established in Speci5 cation 2.1.A and 2.1.E was exceeded.

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

Bases-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 hydraulic conditions resulting in a departure from nucleate boiling have been used to maric the beginning of the region where fuel damage could .

occur. Although it is recognized that s deparatre from nucleate boiling would not necessarily result in damage to BWR fuel rods, the cdtical power at which boiling transition is calculated to occur has been adopted as a corueaient limit. However, the uncertainties in monitodng the core operating state and in the procedure used to calculate the

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• Applicable for cycle only.

OYSTER CREEK 2.1-1 Amendment No.: 75,135,192 9007270445 980723 PDR ADOCK 05000219 P PDR j 1

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Attachment 5 l Oyster Creek Technical Specification Change Request No. 260

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Revised Technical Specification Page 1

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o SECTION 2 SAFETY LIMITS AND LIMITING S.AFETY SYSTEM SETTINGS 2.1 S AFETY LIMIT - FUEL CLADDING INTEGRITY Applicability: Applies to the interrelated variables associated with fuel thermal behavior.

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

Specifications 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 (MCPR)less than 1.09* shall constitute violation of the fuel cladding integrity safetylimit.

B. 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 se 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 SHUTDOWN 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, j the water level shall not be less thar 4'8" above the TOP OF ACTIVE FUEL. I Bases 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 hydraulic 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 thel rods, the critical power at which boiling transition is calculated to occur has been adopted as a convenient limit. However, the uncertainties in monitoring the core operating state and in the procedure used to calcukte the j

• Applicable for cycle 17 only.  !

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l OYSTER CREEK 2.1-1 Amendment No.: 75,135,192, L____._________________._..____ .__ _