ML20054H997

Proposed Revisions to Tech Specs,Reducing RCS Flow Rate for Remainder of Cycle 5 Operation Only

ML20054H997
Person / Time
Site:	Millstone
Issue date:	06/18/1982
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20054H995	List: B10524, Application to Amend License DPR-65,reducing Design RCS Flow Rate for Remainder of Cycle 5 Only ML20054H997
References
NUDOCS 8206250302
Download: ML20054H997 (7)

Text

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s i Docket No. 50-336 4

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I Attachment i

Millstone Nuclear Power Station, Unit No. 2 Proposed Revisions to Technical Specifications j Reactor Coolant Flow Rate-l l

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I June, 1982 l

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What e-o r,.

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

. UNACCEPTAeLE e I OPERAT8088 2 . WESSEL FLOW LESS ME ASUREMENT ,

UNCERT AIN1tES a 362,600 GPM

Q . tes

fe y POR PRE CLAO COLLAPSE g 3 OPE R ATION ONLY

$ LleMil CONT AIN soo ALLOWANCE g

$

• FOR IN$fRtsMENT ERROR OR g 5** '

F LisC ruAfiO=s ,

i U ACCEPTAeLE OPE R AllON l \ .

l 3  %%,g'1 Y a' h

itE ACTOR OPERAf TON LIMITED TO !gygg l:p sn en k i, y-LESS IHAN See F eV ACTUAf t04 x~ $,f gj"EE(>

Of THf MAIN STE AM LINE SAf f TV l WALvis l,= r g e I

w IN3%3

$ 23 g e1 s m

I ~= 3$C $C$

l =5 i 12 ;*.

4sen 8 a:S l c3I o oy .

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'., n .o n. e en i as i ao

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

a TABLE 2.2-1 L -

REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPO!HT LIMITS ALLOWABLE VALUES y FUNCTIONAL UNIT TRIP SETPOINT Manual Reactor Trip Not Appilcable Not Applicable

[ 1.

z Q 2. Power Level-High ,

PG Four Reactor Coolant Pumps < 9.6% above THERMAL POWER. < 9.71 above THERMAL POWER. with 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. with 4 pumps operating *.

k Operating Tiow with 4 pumps operating *.

Reactor Coolant Pump > 830 rpm > 823 rps 4.

Speed - Low

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

6. Containment Pressure - High 1 4.75 psig 1 5 23 psig

7. Steam Generator Pressure - -

> 500 psia -> 492 psia Low (2) (5)

8. Steam Generator Water > 36.0% Water Level - each > 35.25 Water Level - each steam l

steam generator generator

, Level - Low (5)

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

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

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

4.2.2.2 Ffy shall be calculated by the expression F = F,y(1+Tq ) and F xy shall be detemined to be within its limit at the following intervals

~

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

i each fuel loading,

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

l

c. Within four hours if the AZlMUTHAL POWER TILT (T 4

) is > 0.02.

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l 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 FT , defined as FT = F7 (1+Tq ), shall be 7 7 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 and F T 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.

4.2.3.2 F ~Tshall be calculated by the expression FT = F (1+T l' ' aid FT 7 7 y shall be determined to be within its limit at the followina intervals: ,

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

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

4.2.3.4 T shall be determined each time a calculation of FT7 is required l q j

and the value of Tq used to detennine Frshall be the measured value of 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

• Reactor Coolant Flow Rate !_'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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