ML20086P477

Proposed Tech Spec Pages 2-9 & B 2-4 Re Reactor Trip Sys Instrumentation Trip Setpoints & Limiting Safety Sys Settings,Respectively.Fuel Assembly Design Parameters Encl

ML20086P477
Person / Time
Site:	Mcguire, McGuire
Issue date:	02/20/1984
From:	DUKE POWER CO.
To:
Shared Package
ML20086P467	List: ML20086P463 ML20086P477
References
TAC-53319, TAC-53320, NUDOCS 8402270195
Download: ML20086P477 (3)

Text

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TABLE 2.2-1 (Continued) g O

REACTOR. TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS x4 E m

u NOTATION (Continued) o '

u 'a g NOTE 1: (Continued)

'W d E.$ .. P = pressurizer pressure, psig, P' = 2235 psig (Nominal RCS operating pressure),

-1 S = Laplace transform operator, sec ,

and f y (AI) is a function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:

4ef af,(u.i.+ 2.), -9 'f. a-J '8.o n (.%Ii 833 y (i) for qt- "9b between -36% and +975%yAf j(AI) = 0, where qg and qb are percent E RATED TilERMAL POWER in the top andl bottom halve's of the core respectively, and qL+qb is total TilERMAL POWER in percent of RATED THERMAL POWER; '/o(u..+ d .

(u.;t d, - 4i j i (ii) for each percent that the magnitud of g b exceeds -36%g th e AT Trip Setpoint shall be automatically reduced by 0.0 2 f its value at RATED TiiERMAL POWER; and (m;h.), 3.tSt % (*d 8) g j (iii) for each percent that the magnitudgof g b exceeds + g gthe AT Trip Setpoint shall be autumatically reduced by e-903 gof its value at RATED !TilERMAL POWER.

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• ATTACHMENT 2 LIMITING SAFETY SYSTEM SETTINGS BASES *

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Power Ranae, Neutron Flux (Continued)

The Low Setpoint trip may be manually blocked above P-10 (a power level of approximately 10% of RATED THERMAL POWER) and is automatically reinstated below the P-10 Setpoint.

Power Range, Neutron Flux, High Rates g oo E nc r'** e vd = " "** "r F* *d ""-

The Power Range Positive Rate trip provides protection against rapid flux increases which are characteristic of 2 ruptsre of ; c;r.tr;I red drive

+=!% Specifically, this trip complements the Power Range Neutron Flux High and. Low trips to ensure that the criteria are met for rod ejection from

-id pe ,e.. f44r/46. FO M 4 The Power Range Negative Rate trip provides protection for control rod drop accidents. At high power, a rod drop accident of a single or multiple rods could cause local fiux peaking which could cause an unconservative local DNBR to exist. The Power Range Negative tite trip will prevent this from occurring by tripping the reactor. No credit is taken for operation of the Power Range Negative Rate trip for those control rod drop accidents for which DNBR's will be greater than 1.30.

}

Intermediate and Source Range, Neutron Flux . .

The Intermediate and Source Range, Neutron Flux trips provide core protection during reactor startup to mitigate the consequences of an uncon-trolled rod cluster control assembly bank withdrawal from a subcritical condition. These trips provide redundant protection to the Low Setpoint trip of the Power Range, Neutron Flux chgnnels. The Source Range channels will initiate a Reactor trip at about 10 5 counts per second unless manually blocked when P-6 becomes active. The Intermediate Range channels will initiate a Reactor trip at a current level equivalent to approximately 25% of RATED THERMAL POWER unless manually blocked when P-10 becomes active.

McGUIRE - UNITS 1 and 2 B 2-4

, . ATTACHMENT 3 TABLE 1 MCGUIRE UNIT 1 - CYCLE 2 FUEL ASSEMBLY DESIGN PARAMETERS Recion 1 2 3 4*

Enrichment (w/o U-235)* E.108 2.601 3.106 3.20 Density (*; Theoretical)* 94.53 94.56 94.84 94.5 Number of Assemblies 5 .54 64 60 Approximate Burnup at++ 14750' 17200 12000 0

. Beginning of Cycle 2 (MWD /MTU)

Approximate Burnup at++ 22850 26500 23000 10450 End of Cycle 2

-(MWD /MTU) 7

+ All fuel region values are as-built except Region 4 values which are nominal.

, ++ Based on EOCIA = 15150 MWD /MTU ~

• 59 fuel assemblies are of the optimized fuel design with zircalloy orids.

One demonstration 1 Fuel assembly is optimized fuel with intermediate . flow mixer grids and 88 removable fuel rods in the, assembly. The removable rods contain fuel enriched at 3.10 w/o U-235, and the remaining rods are

, 3.20 w/o U-235.

r 0827L:6 . 12

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