ML20059F999

Proposed Tech Specs Reflecting Use of Generally Approved Fuel Type GE 8x8NB in Reload Cycle 12 & Resultant Change in Min Critical Power Ratio Safety Limit to 1.06

ML20059F999
Person / Time
Site:	Quad Cities
Issue date:	08/31/1990
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20059F994	List: ML20059F990 ML20059F999
References
NUDOCS 9009120083
Download: ML20059F999 (3)

Text

..,.. , -.s ATTACEMENT 3'-

?ROPOSED CBANGES TO APPENDIX.A, TECEMICAL SPECIFICATICEIS =

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QUAD CITIES DPR-29 1.1/2.1 FUEL. CLADDING INTEGRITY l SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING j Applicability: Applicability:' d i

The safety limits established to preserve = ~The. limiting safety system settings apply? l the fuel cladding integrity apply to to trip settings.of the instruments and ' -i those var.iables which monitor the fuel devices which are provided-to prevent the '

thermal behavior, fuelcladdingintegritysafetylimitsfrom'l being exct ded.. 1 i

Objective: Objectivoi j The objective of the safety limits is to -Theobjectiveofthelimiting'safetysys-'1 establish limits below which the integ. tem settings is to define the level of-  !

-rity of the fuel cladding is preserved, the process variables at which automaticj .;

protective action is initiated to, pre- z 1

vent.the fuel cladding integrity-safety l limits.from being exceeded.

j SPECIFICATIONS A. Reactor. Pressure > 800 psig and Core A.- Neutron Flux Trip Settings Flow > 10% of Rated f 7

The existence of a minimum critical The'11miting safety system trip set- l power ratio (MCPR) less than 1.07" tings shall be as specified.below: j shall constitute violation of the.

fuel cladding integrity safety limit. 1. - APRM Flux Scram Trip Setting ~ _

L(Run Mode) l When the reactor mode switch is '

, /, O f in the Run position,,the APRM I flux scram setting shall-be as.  !

shown in Figure 2.1-1 and shall-be:- l S 5,( 58WO + 62)~ {

with'amaximumsetpointof.120%-1 for core. flow equal.to 98 x -.

108 lb/hr and greater.

i where S = setting in percent of rated power ,

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1.1/2.1-1 Amendment No. 114-

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.,, > .- ATTACIBGENT - 4 EVALDATION & EO SICBIIFICANT BAZARDS CONSIDERATICEI 1 Commonwealth Edison Company proposes' an amendment to Facility .

Operating License. DPR-29 which. would change the Technical j 2

- Specifications to allow for operation during Cycle.12_and subsequent cycles with a fuel type which, while new to Quad Cities reload, has been previously_ approved by the NRC on a generic: basis.

As discussed'in the Description for the Amendment, request, l j

Commonwealth Edison proposes-to revise,to the MCPR' safety limit-from 1.07 to 1.06, which corresponds,to the MCPR safety limit for GE8X8NB  ;

fuel in D-lattice reactors. j BARIS_EELEQ_SIGIIFICANT BAEA8tDS CONSIDERATION ,

Commonwealth Edison has evaluated this proposed amendment and '

determined that the change does'not involve a significant hazards  ;

consideration. In ' accordance with 10CFR50. 92 (c) :

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1. The proposed change does not involve a significant= increase i in - the probability or consequences of an accident 'previously evaluated.  !

The primary fission product barrier will continue to be- '

protected during normal and transient operation.1 Operation.

of all secondary fission product barriers are unaffected by this change.

The 1.06 MCPR safety lindt value will preserve the, required' ,

margin of safety for' clad integrity. This MCPR safety lindt-ensures that 99.9% of the fuel rods would be expected to  :

avoid boiling transition.during steady-state or transient conditions with a 95% confidence level.- Theinew1 fuel type ,

(GE8x8NB) and-analytical methods for establishing the safety ,

lindt have received NRC approval. Thus, this change does not '

increase the probability or consequences of a.previously .

evaluated accident.  !

2. The proposed change does not create the possibility of a-new :i or different kind of accident from any accident previously _

l evaluated.

• The primary fission product barrier will continue to be protected during normal and transient operation. Operation of all secondary fission product: F eriers are unaffected by this change. No new operationalin,Jes are introduced by this E

change. Thus, the possibility _of new or different accidents is not created. ,

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3. The proposed change does not involve a significant reduction- )

in.the margin of-safety.

L The required margin will be< maintained for all fuel. types'and L increased for some fuel types. The proposed' Technical Specification change reflects the required' safety limit for GE8x8NB~ fuel, while establishing a MCPR safety limit that.is '

more conservative than required-for all other fuel types.

The margin of safety is therefore not significantly reduced.  ?

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