Text

Proposed Tech Specs,Revising Modified TS Section 15.3.1.G, Operational Limitations, Spec 3.b,to Reduce RCS Raw Measured Total Flow Rate Limit by 4000 Gpm for Unit 2
	ML20093K144
Person / Time
Site:	Point Beach
Issue date:	10/19/1995
From:	; WISCONSIN ELECTRIC POWER CO.
To:	;
Shared Package
ML20093K112	List: ML20093K109; ML20093K144;
References
	NUDOCS 9510240108
	Download: ML20093K144 (3)
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2) Cold Shutdown The reactor is in the cold shutdown condition when the reactor has a shutdown margin of at least 1 percent Ak/k and reactor coolant temper-J ature is 200*F. ]

3) Refueling Shutdown !

The reactor is in the refueling shutdown condition when the reactor is j subcritical by at least 5 percent Ak/k and T ., is 140*F. A refueling shutdown refers to a shutdown to move fuel to and from the reactor core.

4) Shutdown Margin Shutdown margin is the instantaneous amount of reactivity by which the reactor core would be subcritical if all withdrawn control rods were tripped into the core but the highest worth withdrawn RCCA remains fully withdrawn. If the reactor is shut down from a power condition, the hot shutdown temperature should be assumed. In other cases, no !

change in temperature should be assumed.

h. Power Operation The reactor is in power operating condition when the reactor is critical and the average neutron flux of the power range instrumentation indicates greater than 2 percent of rated power.

i. Refuelino Operation Refueling operation is any operation involving movement of core components (those that could affect the reactivity of the core) within the containment l when the vessel head is removed.

j. Rated Power Rated power is here defined as a steady state reactor core output of 1518.5 MWT.g

k. Thermal Power l Thermal power is defined as the total core heat transferred from the fuel to the coolant. l

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' ^#179,000lg@nj biitjil 69 s 5.0.0jspmdUM tj 2jishh111bM1 imi isd30js98pfaisdjpjsed l Unit 1 - Amendment No. 86 15.1-4 May 22, 1005 Unit 2 - Amendment No. 90 October 5, 1084 9510240108 951019 PDR ADOCK 05000266 P _.

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G. OPERATIONAL LIMITATIONS The-following DNB related parameters shall be maintained within the limits :

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shown during Rated Power operation: !

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1. T , sh'all be maintained below 578 F.

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2. Reactor Coolant System (RCS) pressurizer pressure shall be maintained: ,

a. Unit 1: 22205 psig during operation at 2250 psia, or ;

21955 psig during operation at 2000 psia, j

b. Unit 2: 21955 psig during operation at 2000 psia. ;

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3. Reactor Coolant System raw measured Total Flow Rate (See Basis). I 1

a. Unit 1 2 181,800 gpm Unit 1

b. Unit 2 2 174,000 gpmUnit2f

'l Basis:

The reactor coolant system total flow rate for Unit 1 of 181,800 gpm is based on an assumed measurement uncertainty of 2.1 percent over thermal design flow (178,000 gpm). The reactor coolant system total flow rate for Unit 2 ef E((@f((

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'p[owid'is' 174,000 gpm'. l,Thii is based on an assumed measurement uncertainty of 2.1 percent over i thermal design flow 5f 170,400 gpm. HoWsje'F'['yniti2;ij/adily)'id l

t'6's'up'po'rt 'opeFation with ije'actop' coo] Int'fiystsm t6ti);f]oh'~fiti'}isJt"'of 169,500, gpm'.'~Th'is,,1s' bas'sd ora 6 asiumed'iisV'sErsmsifit' un'cirtajiity, off 2,,1[pff'c'iK,t

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' ver' o a'the~rmilj design flow of '16,6~,,0001'#m'",',',If;th'e Unjt['2~'!tCS ' ray'jnes'iuFe{t'ot'il flow ratels less than;174,00f gpm,_but'ireatenthaH"of'ehdlili~tl6'169;500]ipm^,'

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operation l1s']jmit' ed, tb"'less ^ thfiiil'o'r[e(d'al ~tb',98%'e fat' dfposit 's's'~~discriji{i[thi note to Specification,15,.341;G.3'b.' The raw measured flow is based upon the use of normalized elbow tap differential pressure which is calibrated against a precision flow calorimetric at the beginning of each cycle.

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Unit 1 - Amendment No. M 6 15.3.1-19 Octcber 20, 1004 Unit 2 - Amendment No. M 0 i i

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Figure 15.2.1-2 REACTOR CORE SAFETY LIMITS POINT BEACH UNIT 2 670 660 -

650 2425 psia 640 -

2250 psia 630 -

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3 620 -

a 2000 psia b610 -

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1775 psia 590 -

580 -

570 -

560 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 1.1 1.2 Core Power (fraction of 1518.5 MWt)

Unit 2 - Amendment No. 460 October 28,1991

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