ML20057C339

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Proposed Tech Specs Revising Safety Limit Section 1.1.A to Reflect Limits for GE11 Fuel
ML20057C339
Person / Time
Site: Peach Bottom Constellation icon.png
Issue date: 09/15/1993
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20057C328 List:
References
NUDOCS 9309280232
Download: ML20057C339 (2)


Text

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ATTACHMENT 2 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 Docket No. 5-277 License No. DPR REVISED TECHNICAL SPECIFICATION PAGES List of Attached Pages Unit 2 9

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f 9309280232 930915 U PDR ADDCK 05000277 's!

P. PDR sid ,

Unit 2 PBAPS SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING 1.1 FUEL CLADDING INTEGRITY 2.1 FUEL CLADDING INTEGRITY Apolicability: Apolicability:

The Safety Limits established The Limiting Safety System to preserve the fuel cladding Settings apply to trip ,

integrity apply to those settings of the instruments j variables which monitor the and devices which are provided  ;

fuel thermal behavior, to prevent the fuel cladding integrity Safety Limits from Obiectives: being exceeded.

The objective of the Safety Obiectives:

Limits is to establish limits which assure the integrity of The objective of the Limiting the fuel cladding. Safety System Settings is to define the level of the process variables at which Specification: automatic protective action is initiated to prevent the fuel ,

A. Reactor Pressure h 800 osia cladding integrity Safety and Core Flow 2 10% of Limits from being exceeded.

Rated  !

Specification: t The existence of a minimum -

critical power ratio (MCPR) The limiting safety system '

l less than 1.07 for two settings shall be as specified recirculation loop below:

operation, or 1.08 for '

l single loop operation, A. Neutron Flux Scram .i shall constitute violation l of the fuel cladding 1. APRM Flux Scram Trio .

integrity safety limit. Settina (Run Mode) '

To ensure that this safety When the Mode Switch is in  !

limit is not exceeded, the RUN position, the APRM neutron flux shall not be flux scram trip setting above the scram setting shall be:

established in l specification 2.1.A for S 5 0.58W + 62% - 0.58 AW longer than 1.15 seconds as indicated by the process where:

l computer. When the process computer is out of service S= Setting in percent of

  • this safety limit shall be rated thermal power assumed to be exceeded if (3293 MWt) the neutron flux exceeds its scram setting and a W= Loop recirculating l control rod scram does not flow rate in percent ,

occur. of design. W is 100 for core flow of 102.5 million lb/hr or  ;

greater.

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