B12310, Proposed Tech Specs Allowing Reduction in RCS Flow Rate from Current Value of 350,000 to 340,000 Gpm & Reducing Total Integrated Radial Peaking Factor

Proposed Tech Specs Allowing Reduction in RCS Flow Rate from Current Value of 350,000 to 340,000 Gpm & Reducing Total Integrated Radial Peaking Factor

ML20215N819
Person / Time
Site:	Millstone
Issue date:	10/27/1986
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20215N814	List: B12310, Proposed Tech Specs Allowing Reduction in RCS Flow Rate from Current Value of 350,000 to 340,000 Gpm & Reducing Total Integrated Radial Peaking Factor ML20215N813 ML20215N827
References
B12310, TAC-63133, TAC-63198, NUDOCS 8611070308
Download: ML20215N819 (7)

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Docke't No. 50-336 B12310 Attachment I Millstone Nuclear Power Station, Unit No. 2 Proposed Revisions to Technical Specification Reduction of RCS Minimum Flow Limit

.4 October,1936 8611070308 861027 PDR ADOCK 05000336 P PDR-i

T TECHNICAL SPECIFICATIONS CHANGE PAGES Section No. Page No.(s) Section Title 2.2 ~ 2-2 Figure 2.1-1 - Reactor Core Thermal Margin Safety Limit -

Four Reactor Coolant Pumps Operating .

2 Table 2.2 Reactor Protective Instrumentation Trip. Setpoint Limits 3/42.2 3/42-8(a). Figure 3.2-3b - Total Radial Peaking Factor Versus Allowable Fraction of RATED THERMAL POWER 3/42-9 To'tal Integrated Radial Peaking Factor FJ 3/4 2-14 Table 3.2-1.- DNB Margin i

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l TADLE 2.2 _z I REACTOR PROTECTIVE INSTRIMENTATION TRIP SETPOINT LIMITS n

E FUNCTIONAL UNIT TRIP SETPOINT_ Alt 0WARLE VALUES

1. Manual Reactor Trip Not Applfcable Not Applfcable z

Z 2. Power Level-H1gh m

Four Reactor Coolant Pumps < 9.61 above THERHAL POWER. < 9.71 above THER.ALM POWER. wlth Operating with a minimum setpoint of a minimum of < 14.7% of RATED

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i < 14.6% of RATED 'HERHAL THERMAL POWER and a mantmum of i

F0WER, and a maximum or < 106.7% of nATED THERMAL POWER.

l < 106.6% of RATED TilERMAL F0WER.

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3. Reactor Coolant Flow - Low (1) m Four Reactor Coolant Pumps > 91.7% of reactor coolant > 90.1% of reactor coolant' flow k Operating Tiow with 4 pumps operating *, with 4 pueps operating *. .

! 4. Reactor Coolant Pump > 830 rpm > 823 rpm Speed - Low

5. Pressurtzer Pressure - High 1 2400 psia 1 2408 psia

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1 6. Containment Pressure - Mtgh < 4.75 psfg

< 5.23 psIg

& 7. Steam Generator Pressure - > 500 psia > 492 psfa 2 Low (2) (5)

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! 8. Steam Generator Water > 36.01 Water Level - each > 35.21 Water Level - each steam j .E . Level - Low (5) steam generator generator.

! 9. Local Power Density - High (3) Trip setpoint adjusted to not Trip setpoint adjusted to not i exceed the limit lines of exceed the lief t lines of Figures 2.2-1 and 2.2-2 (4). Figures 2.2-1 and 2.2-2 (4).

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• Design Reactor Coolant f' low with 4 pumps operating is 340,000 gpn

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F r: F (Fr x (1 + TQ) : F,y x (1 + Tq)) ,

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j 3 FIGURE 3.2-3b Total Radial Peaking Factor vs. Allowable Fraction of RATED THERMAL POWER

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. June 19. 1985 POWER DISTRIBUTION LIMITS T

TOTAL INTEGRATED RADIAL PEAKING FACTOR - F r LIMITING CONDITION FOR OPERATION 3.2.3 ThecalculatedvalueofFf,definedasFf=F(1+T)shallbelimited r q to 1 1.537. I APPLICABILITY: MODE 1*.

ACTION:

With FT>

r 1.537, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either: g

a. Reduce THERML POWER to bring the combination of THERML POWER andFftowithintheIfmitsofFigure3.2-3bandwithdrawthe full length CEAs to or beyond the Long Term Steady State Insertion Limits of Specification 3.1.3.6; or

b. Be in at least HOT STANDBY.

SURVEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 FfshallbecalculatedbytheexpressionF = F (1+T ) and Ff shall r r q be determined to be within its limit at the following interv'als:

a. Prior to operation above 70 percent of RATED THERMAL POWER after

each fuel loading,

b. At least once per 31 days of accumulated operation in MODE 1. and

c. Within four hours if the AZIMUTHAL POWER TILT (T q ) is > 0.020.

4.2.3.3 F r shall be determined each time a calculation of Ff is required by using the incore detectors to obtain a power distribution map with all full length CEAs at or above the Long Tern Steady State Insertion Limit for the

{ existing Reactor Coolant Pump Combination.

4.2.3.4 T q shall be determined each time a calculation of Ff is required and the value of Tq usedtodetermineFfshallbethemeasuredvalueofT. q

• See Special Text Exception 3.10.2.

l MILLSTONE - UNIT 2 3/4 2-9 Amendment No. Ji,52,7),fD, 99 i

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TAB'. E 3.2 1 DNB MA.RG1H L IF.ITS Four Reactor Coolant Ps.ps Paraceter Operating Cold Leg Teeperature 1 49'F 5

Pressurizer Pressure L 2225 psia

• Reactor Coolant flow Rate L 340,000 9;c

' AX1AL Sl%PE INDEX Figure 3.2-4

' Limit not applicable during either a THER.W POWER ramp increase in

' excess of 5% of RATED THERM POWER per r.inute or a THERML POWER step increase of greater than 10% of RATED THERw.AL POWER, MILL 5 TONE - UNIT 2 3/4 2-14 k.endment No.

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