ML20247G408

Submits Rough Draft of Proposed Tech Spec Changes,For Info

ML20247G408
Person / Time
Site:	McGuire, Mcguire
Issue date:	07/18/1989
From:	Nardoci P DUKE POWER CO.
To:	Hood D Office of Nuclear Reactor Regulation
References
NUDOCS 8909190061
Download: ML20247G408 (16)

Text

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.c 16 We t er F Atc Aw or McGuits Unit 1 This is one July 14 flux say could only acess 43 of 58 flux thimble tubes.

d the less than the 75% criterion called fer in the Technical Specifications an l thimbles unit will be forced to shut down on July 24 unless sither additiona c2n be accessed or an emergency Tech Spec change is approved.

E Bacharound Information h last The thimbles in Unit I were cleaned ar.d addy current asamtned during t s l

Upon restart the datectors had cutag,e as required in NRC bulletin 88.C9.

ting sticking problems that eventually disr.ppeared as the plant reach temperatures and the drivas were exercised.

cud subsequent return to power, the plant has ass.in experienced detect instrument sticking problams that won't allow the detectors to go into the thimbles.

d at n burnup of 4,091 MC/MTU that measure 16, 1989 A flux map var, run on June The one parformed July 14 could only acce.ss 43 locations.

45 locations.

Cortsetive Actions ble to Plant has readjustad clutches on the dessetor drives and h accass one additional location.

They may be able to access 44 or they may not.

taken.

f The plant is also going to replace a depleted detectors however, a locations have already bass accessed by other detectors.

i d operation.

Duke has prepared an emergency Tech Spec change to allev cont nue h 45 The technical justification is based on comparing the 43 trace map to frem the 45 tracs map and traes zap, delsting the unavailable detector:The two naps are then ecspared a reprocessing the power distribution.

The sean plus two times and F 1 cations analysed.

error on the top 20 Fq 2

ddixtenal sensurement the standard deviation of the errorn is used as an a he and P margin to their Haits.

uncertainty before evaluating Fq gg i

k E

additional uncertainty in this case was 0.043% for F and 0.32% for F Duh q

AB.

propcses to perform this error analysis for each nap that does not contain the required 44 traces and requesta this to allowed until the end of t!.e current cycle.

Additional information is that the avs.ilable detectors are well distributed i

throughout the core and are close to t.t.e high peaking assamblies. We core is behaving as predicted and the peak from here to the end of cycia stays in the same assembly and only changes about 11.

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FIWM 2.5 H0VMLt DETECTOR AM) TERM 000tT3 LOCATIONS 2-12 o

INSTRUMENTATION B

).

i

-MOVA8LE INCORE DETECTORS LIMITING CONDITION FOR OPERATION i

3.3.3.2 The Movable Incore Detection System shall be OPERABLE with:

At least 75% of the detector thimbles, #

[]

a.

b.

A minimum of two detector thireles per core quadrant, and I

I c.

Sufficient movable detectors, drive, and readout equipment to map these thimbles.

l APPLICABILITY: When the. Movable Incore Detection System is used for:

a.

Recalibration of the Excore Neutron Flux Detection System,

)

b.

Monitoring the QUADRANT POWER TILT RATIO, or Measurement of F h and F (Z) c.

q ACIIAN:

a With the Movable Incore Detection Systen inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS I

l The Movable Incore Detection System shall be demonstrated OPERABLE at 4.3.3.2 least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by normalizing each detector output when required for:

Recalibration of the Excore Neutron Flux Detection System, or i

a.

b.

Monitoring the QUADRANT POWER TILT RAT!0, or l

MeasurementofFhandF(I) c.

q r'

for the reunaonde r e f #

• G " * *t'* l CyClt by if

$ t's $ W W l0 o n, Is' U*

of he r hu m bles a re vnolpes (kamgg Dgh,wgo<o A hlatg.a /

M $ pusht a

-s be pn W w.l to d * + u rs o r,.e Brn f% *nd fAH u

ustdihe.1 ) meaw,e 4 u.uv>hoon%

McGUIRE - UNITS 1 and 2 3/4 3=45 Amendment No. 87 (Unit 1)

)

Amaradment No. 68 (Unit 2) l J

i..

POWER DISTRIBUTION LIMITS

=

SURVEILLANCE REQUIREMENTS I

1 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.

m 4.2.2.2 For RAOC operation, F (z) shall be evaluated to determine if F (z) 9 0

is within its limit by:

f Usir.g the movable incere detectors to obtain a power distribution a.

map at any THERMAL POWER greater than 5% of RATED THERMAL POWER.

b.

Increasing the measured F (r) component of the power distribution 9

map by 3% to account for manufacturing tolerances and furtner increasing the value by 5% to account for measurement uncertainties.

Verify the requirements of Specification 3.2.2 are satisfied.

c.

Satisfying the following relationship:

O (t) < } 32 x qz) for P > 0.5 N

F P x W(z)

N 2.32 x 42) for P < 0.5 F0 (z) ~<

W(z) x 0.5 where F (z) is the measured F (z) increased by the allowances far q

manufacturing tolerances and measurement uncertainty, 2.32 is the l

F limit, K(z) is given in Figure 3.2-2, P is the relative THERMAL q

POWER, and W(t) is the cycle dependent function that accounts for power distribution transients encountered during normal operation.

This function is given in the Peaking Factor Limit Report as per Speci-fication 6.9.1.9.

N d.

Measuring Fq (z) according to the following schedule:

1.

Upon achieving equilibrium conditions after exceeding by 10% or more of RATED THERMAL POWER, the THERMAL POWER at which F (z) was last determined,* or q

2.

At least once per 31 Effective Full Power Days, whichever occurs first.

"During power escalation at the beginning of each cycle, power level may be increased until a power level for extended operation has been achieved and a power distribution map obtained.

N f7 e fhe reoua nder e, f th e G u u *t Cy c le 4, Th-ocr e casi be

.wsw.vd an e e M rrty s n, (u %,,

s e u, ya,fe k sas.

s e.

e es a

case A 3.3.?_ a.

(

C50cCmG N3.73 (Uni,t 1) un M

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POWFM DISTRIBUTION LIMITS 3/4.2.3 RCS FLOW RATE AND NUCLEAR QTHALPY RISE HOT CliANNEL FACTOR LIMITING CONDITION FOR OPERATION 3.2.3 The combination of indicated Reactor Coolant System (RCS) total flow rate and R shall be maintained within the region of allowable operation shown l

on Figure 3.2-3 for four loop operation:

Where:

N p

AH N " 1.49 [1.0 + 0.3 (1.0 - F)]

THERMAL POWiR b.

P = RAIED THERMA.'DWER Fh=MeasuredvaluesofFhobtainedbyusingthemovableincere c.

detectors to obtain a power distribution map..The measured valuesofFhshallbeusedtocalculateRsinceFigure3.2-3 i

includes penalties for undetected feedwater venturi fouling of,

0.1% and for measurenant uncertainties of 1.7% for flow and 45 forinceremeasur.ementofFlg.

9 APPLICABILITY: MODE 1.

ACTION:

With the combination of RCS total flow rate and R outside the region of acceptable operation shown on Figure 3.2-3:

a.

Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either:

1.

Restore the combination of RCS total flaw rate and R to within the above limits, or 2.

Reduce THERMAL POWER to less than 50% of RATED THERNAL POWER and reduce the Power Range Neutron Flux - High Trip setpoint to less than or equel to 55% of RATED TERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

%,- the reame o.,dr< e f RIe Gw <e { Gjcle f, k

maw,e.ne.2 anew hwty c.,

be

\\

en Cow sycri he Vas a.

)

} increme.1 See Speci bcs. ben

3. 3 6. 2 a licGUIRE - UNITS 1 and 2 3/4 2-14 Amendnent No.42(Unit 1)

Amendment No.23(Unit 2)

I

.