ML19260A764

Proposed Tech Specs 3/4.2 Re Power Distribution Limits

ML19260A764
Person / Time
Site:	North Anna
Issue date:	11/29/1979
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19260A763	List: ML19260A762 ML19260A764
References
NUDOCS 7912030210
Download: ML19260A764 (5)

Text

,

POWER DISTRIBUTION LIMITS HEAT FLUX HOT CHANNEL FACTOR-Fo(Z)

LIMITING CONDITION FOR OPERATION 3.2.2 Fq shall be llmited by the following relationships:

Fq(Z) < [2.10] [K(Z)] for P > 0.5 P

Fq(Z) < [4.20] [K(Z)] for P < 0.5

, , THERMAL POWER

^

RATED THERMAL POWER and K(Z) is the function obtained from Figure 3.2-2 for a given core height location.

APPLICABILITY: MODE 1 ACTION:

With Fq(Z) exceeding its limit:

a. Comply with either of the following ACTIONS:

1. Reduce THERMAL 20WER at least 1% for each 1% Fq(Z) exceeds the limit within 15 minutes and similarly reduce the 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 OPERATION may proceed for up to a total of 7_ hours; subsequent POWER OPERATION may proceed provided the Overpower AT Trip Set-points have been reduced at least 1% for each 1% Fq(Z) exceeds the limit. The Overpower AT Trip Setpoint reduction shall be per-formed with the reactor in at least HOT STANDBY.

2. Reduce THERMAL POWER as necessary to meet the limits of Specifica-tion 3.2.6 using the APDMS with the latest incore map and updated R.

b. Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER above the reduced limit required by a, above; THERMAL POWER ma'J then be increased providedQ F (Z) is demonstrated tnrough incore mapping to be within its limit.

1460 342 14 c

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Figure 3.2-2 K(Z)-Nort:alized F (Z) as a Function of Core Height q

1460 343 NORTH ANNA - UNIT 1 3/4 2-8

POWER DISTRIBUTION LIMITS AXIAL POWER DISTRIBUTION LIMITING CONDITION FOR OPERATION 3.2.6 The axial powar c<.stribution shall be l hited by the following relationship:

(2.10 ] (K(Z)]

[F (Z)]S " (R )(P )(1.03)(13 + c(1.07) )

Where:

a. Fj (Z) is the normalized axial power distribution from thimble j at core elevation Z.

b. PL is the fraction of RATED THERMAL POWER.

c. K(Z) is the function obtained from Figure 3.2-2 for a given core height location.

d. Rj, for thimble j, is determined from at least n=6 in-core flux maps covering the full configuration of permissible rod patterns above 95% of RATED THERMAL POWER in accordance with:

Rj = f R ij i=1 Where:

yMeas R =

Qi 3

[F (Z)]

and (Fij (Z)] Max is the maximum value of the normalized axial distribution at elevation Z from thimble j in map i which had a measured peaking factor without uncertainties or densification I

allowanceofF{eas, 1460 344 NORTH /NNA - UNIT 1 3/4 2-16

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: (a) maintaining the minimum DNBR in the core > 1.30 during normal operation and in short term transients, and (b) limiting the fission gas release, fuel pellet temperature & cladding mechnical properties to within assumed des'.gn criteria. In addition, limiting the peak linear power density during Condition I events provides assurance that the initial condi* ions assumed for the LOCA analyses are met and the ECCS acceptance criteria limit of 2200 F is not exceeded.

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

Fq (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 man-ufacturing tolerances on fuel pellets and rods.

FfH 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.

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 (AF')

The limits on AXIAL FLUX DIFFERENCE assure that the Fq (Z) upper bound envelope of 2.10 times the normalized axial peaking factor is not exceeded during either normal operation or in the event of xenon redis- l tribution following power changes.

Target flux difference is determined at equilibrium xenon conditions with the part length control rods withdrawn from the core. The full length 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 difference at RATED THERMAL POWER for the associated core burnup con : :tions. Target flux dif ferences for other THERMAL POWER levels are obtained by multiplying the RATED THER>M1 POWER value by the appropriate fractional THERMAL POWER level. The periodic updating of tha target flux difference value is necessary to reflect core burnup considerations.

NORTH ANNA - UNIT 1 B 3/4 2-1 1460 545

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