ML20154L346

Proposed Tech Specs,Reducing Heat Flux Hot Channel Factor Fq(Z) to 2.25 at 100% Power

ML20154L346
Person / Time
Site:	Vogtle
Issue date:	05/19/1988
From:	GEORGIA POWER CO.
To:
Shared Package
ML20154L335	List: ML20154L331 ML20154L346
References
SL-4442, NUDOCS 8805310258
Download: ML20154L346 (3)

Text

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Georgia Power d ENCLOSURE 3 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 REQUEST TO REVISE TECHNICAL SPECIFICATION 3.2.2 INSTRUCTIONS FOR INCORPORATION The proposed change to the Technical Specifications (Appendix A to Operating License NPF-68) would be incorporated as follows:

Remove Paae Insert Page 3/4 2-4 3/4 2-4 B3/4 2-1 B3/4 2-1 l

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l l 0864m E3-1 05/19/88 SL-4442 8805310258 88051 PDR ADOCK 05000 P DD

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POWER DISTRIBUTION LIMITS 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - Fn(Z)

LIMITING CONDITION FOR OPERATION 3.2.2 Fn(Z) shall be limited by the following relationships:

Fn(Z) < 2.25 P

[K(Z)] for P > 0.5 l Fn(Z) < 4.50 [K(Z)] for P < 0.5 l Where: P = THERMAL POWER , and RTEiffHERMAL POWER K(Z) = the function obtained from Figure 3.2-2 for a given core height location.

APPLICABILITY: MODE 1.

ACTION:

With Fgf Z) exceeding its limit:

! a. Z) exceeds the Reduce THERMAL limit within POWER 15 minutes and at least 1% reduce similarly for eacht 1% Fo(he Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; POWER l

OPERATION may proceed for up to a tot'al of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; subsequent

' POWER OPERATION may proceed provided the Overpower AT Trip Setpoints have been reduced at least 1% for each 1% Fn(Z)

! exceeds the limit; and

b. Identify and correct the cause of the out-of-l imit condition prior to increasing THERMAL POWER above the reduced limit l required by ACTION a., above; THERMAL POWER may then be j increased provided Fn(Z) is demonstrated through incore mapping to be within its limit.

! V0GTLE - UNIT 1 3/4 2-4 l

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r 3/4.2 POWER DISTRIBUTION LIMITS BASES The specifications of this section provide assurance of fuel integrity during Condition I (Normal Operation) and II (Incidents of Moderate Frequency) events by: (1) maintaining the minimum DNBR in the core greater than or equal to 1.30 during normal operation and in short-term transients, and (2) limiting the fission gas release, fuel pellet temperature, and clasiding mechanical properties to within assumed design criteria. In additfe'1, ifmiting the peak linear power density during Condition I events prov!jes assurance that the initial conditions assumed for the LOCA analyses are met and the ECCS acceptance criteria limit of 2200 F0 is not exceeded.

The definitions of certain hot channel and peaking factors as used in these specifications are as follows:

Fg(Z) Heat Flux Hot Channel Factor, is defined as the maximum local -

heat flux on the surface of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing for manufacturing tolerances on fuel pellets and rods; FNAy Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of the integral of linear power along the rod with the highest integrated power to the average rod power; and Fxy(Z) Radial Peaking Factor, is defined as the ratio of peak power density to average power density in the horizontal plane at core elevation Z.

3/4.2.1 AXIAL FLUX DIFFERENCE The limits on AXIAL FLUX DIFFERENCE (AFD) assure that the Fn(Z) upper bound envelope of 2.25 times the normalized axial peaking factof is [

not exceeded during either normal operation or in the event of xenon redistribution following power changes.

Target flux difference is determined at equilibrium xenon conditions. The rods may be positioned within the core in accordance with their respective insertion limits and should be inserted near their normal position for steady-state operation at high power levels. The value of the target flux difference obtained under these conditions divided by the fraction of RATED THERMAL POWER is the target flux l difference at RATED THERMAL POWER for the associated core burnup l

conditions. Target flux differences for other THERMAL POWER levels are l obtained by multiplying the RATED THERMAL POWER value by the appropriate l fractional THERMAL POWER level. The periodic updating of the target flux

! difference value is necessary to reflect core burnup considerations.

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