ML20069C743

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Proposed Tech Specs Relocating Heat Flux Channel Factor, Fq(Z),Penalty of 2 Percent in Spec 4.2.2.2.f to cycle- Specific COLR to Allow for burnup-dependent Values of Penalty in Excess of 2 Percent
ML20069C743
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 05/20/1994
From:
GEORGIA POWER CO.
To:
Shared Package
ML20069C731 List:
References
NUDOCS 9406020096
Download: ML20069C743 (2)


Text

s POWER DISTRIBUTION LIMITS SURVEILLANCE REOUIREMENTS (Continued) (

f. Withmea$urementsindicating maximum  ! F0 (Z) over ( K(Z) /

C has increased since the previous determination of F0 (Z) either of f[e appropriale the following actions shall be taken:

C

/ hCfor spec /[dd 1) Increase Fq (Z) by nd verify that this value satisfies the

/gff6Q)f6 relationship in Specification, , or , 3, 3,2 d C

k 2) F q (Z) shall be measured at least once per 7 Effective Full Power Days until two successive maps indicate that XER)RT (COL R) )y

( maximum (F 0 is not increasing,

g. With the relationships specified in Specification 4.2.2.2d above not being satisfied:
1) Calculate the percent F q (Z) exceeds its limits by the following expression:

C

[ maximum 3 Fq (Z) x W(Z)

RTP l

over Z F O

x K(Z) -1 > x 100 for P > 0.5

( 7-

' ~ ~

/ maximum F C(Z)xh(Z) }

RTP l over Z F x K(Z) -1 x 100 for P 5 0.5, and i

O

_ rr- _

/

2) The following action shall be taken.

Within 15 minutes, control the AFD to within new AFD limits which are determined by reducing the AFD limits specified in the CORE OPERATING LIMITS REPORT by 1% AFD for each percent F (Z) exceeds 9

its limits as determined in Specification 4.2.2.2g.1. Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, reset the AFD alarm setpoints to these modified limits.

V0GTLE UNITS - 1 & 2 3/4 2-5 Amendment No. 44 (Unit 1)

Amendment No. 24 (Unit 2) 9406020096 940520 PDR ADOCK 05000424 P POR ,

ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) l

a. WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY",

W Proprietary). ,

July 1985 (y for Specifications 3.1.1.3 - Moderator Temperature (Methodolog Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limit, 3.1.3.6 -

Control Bank Insertion Limits and 3.2.3 - Nucleghalpy Rise kevision ih, Hot Channel Factor.) bruanh'IQy

b. WCAP-10216-P-A,V" RELAXATION OF CONSTANT AXIAL OFFSET C OLFQ SURVEILLANCE TECHNICAL SPECIFICATION",- L.e 1000 (W Proprietary).

(Methodology for Specifications 3.2.1 - Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (W(Z) surveillance requirements for Fq Methodology).)

c. WCAP-9220-P-A, Rev. 1, " WESTINGHOUSE ECCS EVALUATION MODEL-1981 VERSION", February 1982 (W Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.) ,

The core operating limits shall be determined so that all applicable limits (e.g. , fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

SPECIAL REPORTS 6.8.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.

i l

I l

V0GTLE UNITS - 1 & 2 6-21 Amendment No. 55 (Unit 1)

Amenoment No.34 (Unit 2)

. .