ML20054H997

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Proposed Revisions to Tech Specs,Reducing RCS Flow Rate for Remainder of Cycle 5 Operation Only
ML20054H997
Person / Time
Site: Millstone Dominion icon.png
Issue date: 06/18/1982
From:
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20054H995 List:
References
NUDOCS 8206250302
Download: ML20054H997 (7)
v • d • e


Text

-...-

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Docket No. 50-336 4

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I Attachment i

Millstone Nuclear Power Station, Unit No. 2 l

Proposed Revisions to Technical Specifications Reactor Coolant Flow Rate-j l

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l June, 1982 f

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What e-o r,.

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""* cst.t'L*L' 2"*'.!?".: - -

,a,--

UNACCEPTAeLE I

OPERAT8088 e

WESSEL FLOW LESS ME ASUREMENT 2

Q

. tes UNCERT AIN1tES a 362,600 GPM fe y

POR PRE CLAO COLLAPSE g

3 OPE R ATION ONLY LleMil CONT AIN soo ALLOWANCE FOR IN$fRtsMENT ERROR OR g

g 5**

F LisC ruAfiO=s U

ACCEPTAeLE l

\\

3

% g'1 i

OPE R AllON l

Y a'

!gygg k i,

h itE ACTOR OPERAf TON LIMITED TO x~

$,f LESS IHAN See F eV ACTUAf t04 l:p sn en gj"EE(>

y-Of THf MAIN STE AM LINE SAf f TV l

I WALvis l,= r g e IN3%3 w

$ 23 e1 s

g I ~= $ C $

m 3$C l

=5 i 12 ;*.

4sen 8 a:S l c3 o o I

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..wi n.o n.

e en i as i ao ien

. i se i se a.es 8 it ACTIO80 Of M Af t D THERMAL POWER Reu.sen C.ne llenul M.neguibleiv Linut - Four Rowtor Coolant Piniops Opsvatwig FIGUIRE 21 I

a TABLE 2.2-1 L

REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPO!HT LIMITS y

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

[

1.

Manual Reactor Trip Not Appilcable Not Applicable zQ 2.

Power Level-High PG

< 9.71 above THERMAL POWER. with Four Reactor Coolant Pumps

< 9.6% above THERMAL POWER.

Operating with a minimum setpoint of a minimum of < 14.7% of RATED

~

< 14.6% of RATED THERMAL THERMAL POWER and a maxtpum of F0WER and a maximum of

< 106.7% of RATED THERMAL POWER.

~

< 106.6% of RATED THERMAL F0WER.

3.

Reactor Coolant Flow - Low (1)

Four Reactor Coolant Pumps

> 91.7% of reactor coolant

> 90.1% of reactor coolant flow e.

k Operating Tiow with 4 pumps operating *.

with 4 pumps operating *.

4.

Reactor Coolant Pump

> 830 rpm

> 823 rps Speed - Low 5.

Pressurizer Pressure - High 1 2400 psia 1 2408 psia 1

23 psig 5

6.

Containment Pressure - High 1 4.75 psig 7.

Steam Generator Pressure -

> 500 psia

-> 492 psia Low (2) (5) l 8.

Steam Generator Water

> 36.0% Water Level - each

> 35.25 Water Level - each steam Level - Low (5) steam generator generator 9.

Local Power Density - High (3)

Trip setpoint adjusted to not Trip setpoint adjusted to not exceed the limit lines of exceed the Ilmit line4 of Figures 2.2-1 and 2.2-2 (4).

Figures 2.2-1 and 2.2-2 (4).

Design Reactor Cbolant flow with 4 pumps operating is 362,600 GPM

.e n

POWER DISTRIBUTION LIMITS TOTAL PLANAR RADIAL PEAKING FACTOR - F LIMITING CONDITION FOR OPERATION T

ThecalculatedvalueofFfy,definedasF,=F (1+T ), shall 3.2.2 x

q be limited to < l.583.

APPLICABILITY:

MODE 1*.

ACTION:

With Ffy > 1.583, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either:

a.

Reduce THERMAL POWER to bring the combination of THERMAL POWER T

and F to within the limits of Figure 3.2-3 and withdraw the xy full length CEAs to or beyond the Long Term Steady State Insertion Limit of Specification 3.1.3.6; or b.

' Be in at least HOT STANDBY.

SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.

Ffy shall be calculated by the expression F

= F,y(1+T ) and 4.2.2.2 q

F shall be detemined to be within its limit at the following intervals:

xy

~

I l

a.

Prior to operation above 70 percent of RATED THERMAL POWER af ter each fuel loading, i

b.

At least once per 31 days of accumulated operation in MODE 1, l

and l

Within four hours if the AZlMUTHAL POWER TILT (T ) is > 0.02.

l c.

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See Special Test Exception 3.10.2.

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P0'rlER DISTRIBUTION LIMITS T

TOTAL INTEGRATED RADI AL PEAKI!G FACTOR - F r LIMITlHG CONDITION FOR OPERATION 3.2.3 The calculated value of F, defined as FT = F (1+T ), shall be T

7 7

7 q

limited to < 1.597.

APPLICABILITY: MODE 1*.

ACTION:

With FT > 1.597, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either:

y a.

Reduce THERMAL POWER to bring the combination of THERMAL POWER T

and F to within the limits of Figure 3.2-3 and withdraw the 7

full length CEAs to or beyond the Long Tern Steady State Insertion Limits of Specification 3.1.3.6; or

.i b.

Be in at least HOT STANDBY.

l 1',

SURVEILLANCE REQUIRDiENTS 4.2.3.1 The provisions of Specification 4.Q.4 are not applicable.

~T T

4.2.3.2 F shall be calculated by the expression FT = F (1+T l' ' aid F 7

7 y

shall be determined to be within its limit at the followina intervals:,

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

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 l. is > 0.020.

j q

T 4.2.3.3 F shall be determined each time a calculation of F is required 7

7 by using the incore detectors to obtain a power distribution map with all full length CEAs at or above the Long Term Steady State Insertion

,j Limit for the existing Reactor Coolant Punp Combination.

T l

4.2.3.4 T shall be determined each time a calculation of F is required q

7 and the value of T used to detennine F shall be the measured value of j

q r

q.

l

  • See Special Test Emception 3.10.2.

MILLSTONE - UNIT 2 3/4 2-9 l

l

TABLE 3.2-1 DNB MARGIN LIMITS

~

i Four Reactor Coolant Pumps Parameter Operating Cold Leg Temperature 1 549'F Pressurizer Pressure t 2225 psia

!_'362,600 9pm AXIAL SHAPE INDEX Figure 3.2-4

  • Limit not applicable during either a THERMAL POWER ramp increase in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step increase of greater than 10% of RATED THERMAL POWER.

1 I

MILLSTONE - UNIT 2 3/4 2-14

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