ML20062N880

Proposed Rev to Page 1 of 8 from Colr

ML20062N880
Person / Time
Site:	Monticello
Issue date:	01/04/1994
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20062N866	List: ML20062N863 ML20062N869 ML20062N873 ML20062N880
References
NUDOCS 9401240163
Download: ML20062N880 (2)

Text

_ . . _ . . . . _ _ . - . . m - . . _ . . - _ ._ _ . . . _ .

. 6 4 -

s' ,

3 Exhibit D

.f Monticello Nuclear Generating Plant i

License Amendmeqt Reauest dated Januarv 4. 1994 Proposed Revision to the core Operating Limits Report Exhibit D consists of the existing page 1 of 8 from the Monticello Core  !

Operating Limite Report marked up with the proposed changes based on approval of this proposed amendment. ,

t t ,

h l

i i

t i

I i

9401240163 940104 e fDR ADOCK 05000263 h r' PDR P un .-

9 Page 1 of 8

[-

This report provides the values of the limits for Cycle 16 as required by Technical Specification Section 6.7.A.7. These values have been established using NRC approved methodology and are established such that all applicable limits of the plant safety analysis are met.

Rod Block Monitor Operability Reauirements The MCPR limit associated with the Rod Block Monitor operability is:

if thermal power < 90% of rated and MCPR < 1.72 or if thermal power a 90% of rated and MCPR < 1.55.

Reference Technical Specification Section: 3.2.C.2.a Epd Block Monitor Unscafe Trio Setooints Low Trip Setpoint (LTSP) $ 120/125 of full scafe Intermediate Trip Setpoint (ITSP) s 115/125 of fu!! scale High Trip Setpoint (HTSP) s 110/125 of fuil scale (These values are unchanged from the Cycle 15 trip setpoints)

[G Reference Technical Specification Sections: Tablo 3.2.3 Item 4.a, Table 3.2.3 Note 8.

Maximum Avernoe Linear Heat Generation Rate as a function of boosure When hand calculations are required, the Maximum Average Linear Heat Generation Rate (MAPLHGR) for each fuel bundle design as a function of average planer exposure shall not exceed the limiting lattice (excluding natural uranium) provided in Table 1 (based on straight line interpolation between data points) multip!ied by the smaller of the two MAPFAC factors determined from Figures 1 and 2.

The MAPLHGR limits in Tab!c 1 are conservative values bounding all the fuel fattice types (excluding natural uranium) in a given fuel bundle design and are intended only for use in hand calculations as described in Technical Specification 3.11.A Channel bow effects are included in l the bounding MAPLHGR values below. MAIL iCr. : , ,;; f;; ;;d ' .5vidua! 'uct ba?ce d::!gn 5 ::

burd!: design, with cpprop;~;tc channeRow-odjustmenture4eeded4rt-the-pec;c;; :::nputcr and 0:0 =d M cerc Htcr ~; cc' cut:Fe~

i

+

Reference Technical Specification Section: 3.1 1.A.  ;

i MAPLilGR limits for each individual fuel lattice" design in a bundle design as a function of axial location and average planar exposure, with appropriate

( _

channel bow adjustments, are determined based on the approved methodology referenced in Monticello Technical Specification 6.7. A.7.b and loaded in the process computer for use in core monitoring calculations.