ML20082M066

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Proposed Tech Specs 3/4.2.1 Re Axial Flux Difference & 3/4.2.4 Re Quadrant Power Tilt Ratio
ML20082M066
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 08/30/1991
From:
HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20082M060 List:
References
NUDOCS 9109050017
Download: ML20082M066 (10)


Text

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Attachment 3 ,

harked-Up Technical SP ecification Pages F

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B usotet-224,co 9109050017 910s3o l

DR ADOCK 05000498

PDR

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4 3/4.2 -POWER D15TRIBUT10N L1 HITS g ,

3/4.2.1 AXI AL FLUX OlFFERENCE j

LIMITING _C M ITION FOR OEEFAT10N 3.2.1 The indicated AX'IAL' FLUX DIFFERENCE (AFO) shall be maintained within the target band (flux difference units) about the target flux difference as specified in the CORE OPERATING LIMITS REPORT.

I M n(icated AFD may deviate outside the above required target band at1r

' than or equa4 50% but less .than 90% of RATED THERMAL PDER-pr6vided the indi-caud AFD is within he-Acceptable Operation LJmits-orTigure 3.2-1 and the cumu-  !

iotive penalty deviation time 751!syg1 hour during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The. indicated AFD, cay-d side the abov than 15%

d1 erg t band at greater desii than 50% of RATED THERMAL POWER provided th(e comulative yalt deviation time does not excted 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 5%;

,APPLICABIL11Y: MODE 1, above 15% of RATED THERMAL POWER.*  ;

ACTION:

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j With the indicated AFD outside of the above re with THERMAL POWER greater than or equal to of 90kuired target"L' band and h

w %.

, within 15 minutes either.:: RATED THE

IW50RT I ,
1. Res th R .* re,\eindicatedAFDtowithinthetarge.t-andlimits,or

-2.

Reduce THERMAL POWER to less than 90% of RATED THERMAL POWER.

b. With the indicated side of the a e required target band for I more than I hour of cumulativMensTty deviation time during the -

previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or outsideEe %r.qeptable Operation Limits of Figure 3.2-1 and with THF.RMKL POWER Tus than 90% but equal to or greater than 50% of JATfD THERMAL POWER, N uce:

1. THERMAL PWER to less than 50% of RATED THE
  • 30minofes,and L POWER within 2 The Power Range--Neutron Flu 1* ** - High Setpoint to lessqhan or y equal to 55% of RATED THERMAL POWER within the next 4 hourid-
  • 5ee Special Test Exceptions Specificatien 3.10.2.

N%urve

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. pursuant ance teit'ing~Tf t

the PowerTange Neutron FTux channel m_awb e.rA raedd o Spec 441caQon 4.3.1.1 provicted 1h.e_.indicateCAFDTs h maintained within the Acceptable Operation Timjibokfiggle 3.2-1. A total of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> operation -

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may_ be accumula1edMth1 Tie AFD outside MEE7bove-required target band during tesjjng-dthBlit penalty deviation. N  %

i SOUTH TEXAS - UNITS 1 & 2 3/4 2-1 Unit 1 - Amendment No. 9 Unit 2 - Amendment No.1

. _ _ -_ - __ _. _ - _ __ _ _- ._= _ _ _

POWER DISTRIBUTION LIMIT 5 LiliLT1!(G_COM11101U0JL0EER&TJ0!L .

kT1044fontinued) ~~>7  !

c. Witti rd4 utside of tt . abo h re M e d for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of f alive:peni y deviation time during the  !

previous 24 ho puradTifh THERM 7il70WEQess than 50% but greater /'

i shall not be /

( f than 15Laf-RATED incelsed THERMAL equal to or greater POWER, than 50% of RATED TH the THERMATNOWEB': r

\ / the indicated AFD is within the above required target ban h Qf j >

l SUfYDil!SCEJEDVIREE10; r 4.2.1.1 The indicated AFD shall be determined to be within its limits during POWER OPERATION above 15% of RATED THERMAL POWER by:

gy M nitoring the indicated AFD for each OPERABLE excore channel: .

t t 1) l t Q east once per 7 days when the AFD Monitor Alarm s OPERABLE, IWRT and

2) At least once per txutt for the ,f.JrW24 hours af ter restoring the AFD Monitor Alarm T ABLE status.
b. Monitoring and lo 'ng-flie indica TD 4 r each OPERABLE excore t channel at 1 Ert e per hour for the firstD Q ours and at least l oncey minutes thereaf ter, when the AFD MonitoNLlarm is  !

i The logged values of the indicated AfD shal h e assumed k g , inoperable.

to exist during the interval preceding each logging. s*

4.2.1.2 The indicated AFD shall be considered outside of its target band wher L

two or more OPERABLE excore channels are indicating the AFD to be outside the

target band. Penalty deviation outside-of the above required target band shall i be accumulated on a time basis of
l l a. One minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels equal to or above  !

50% of RATED THERMAL POWER, and t

b. One-half minute penalty deviation for each I minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15% and i 50% of RATED THERMAL POWER.

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4.2.1.3 The target flux difference of each OPERABLE excore channel shall be i determined by measurement at least once per 92 Effective Full Power Days.

The provisions of Specification 4.0.4 are not applicable.

4.2.1.4 The target flux difference shall be updated at least once per 31 Effective full Power Days by either determining the target flux difference SoulH TEXA5 - UNI 15 1 & 2 3/4 2-2 i

POWf R D15TR180T10N l1M115 MRY f ] l 1 MK LP E_QU l F l P WJfdQ1iglug,_ __,__. _

oursuant to specification 4.2 1.3 above er by linear interpolation between the most recently measured value and the predicted value at the end of the cycle life. The provisions of Specification 4.0.4 are not applicable. .

SOUTH TEXA5 - UN115 1 & 2 3/4 2-3

___.______._m.___ ____._._ _ _._ -

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a. With the indicated AFD outside of the above required target band, l and with TilERMAL POWER:  ;

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1. greate r than or equal to 90% of RATED TilERMAL POWER. within 15 1 minutes either: i a) Restore the indicated AfD to within the target band l

limits, or b) Reduce TilEP. MAL POWER to less than 90% of RATED TilERMAL POWER.

2. greater than or equal to $06, but less than 90% of RATED TilERMAL POWER:

a) POWER OPERATION may continue provided:

1) The indicated AFD hes not been outside of t.he target band for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cumulative penalty deviation during the prrrvioas 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and
2) The indicated AFD is within t.he Acceptabic Operation

{ limits specified in the COLR.

Otherwise. reduce TilERMAL POWER to less than 50% of RATED TilERMAL POWER within 30 minutes and reduce the Power Range i Neutron Flux

  • liigh Trip Setpoint to less than or equal to

$$t of RATED TilERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

b) Surveillance testing of the Power Range Neutron Flux Channels may be performed pursuant to Specification 4.3.1.1, provided that the indicated AFD is maintained within the Acceptable Operation Limits specified in the l

Cola . A total of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> operation may be accumulated i with the AFD outside of the Target Band during this t

testing without penalty deviation.

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3. greater than 15%, but less than 50% ef RATED TilERMAL POWER:

TilERMAL POWER shall not be increased above 50% of RATED TilERMAL POWER unless the indicated AFD has not been outside of the target band for more than I hour cumulative penelty deviation during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

b. TilERMAL POWER whall- not be -Increased above 90% of RATED TilERMAL POWER unless the indicated AFD is within the target hand, and the indicated AFD has not been outside of the target band for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cumulative penalty deviation during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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USQ\ 91-224,001

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, MERI_2 I

a. Monitoring the indicated AFD for each OPERABLE excore channel at least once per 7 days when the AFD Honitor Alario is OPERABl.E,
b. Monitoring and logging the indicated AFD for each OPERAliLE ,

excore channel at least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,  ;

and at Icast once por 30 minutes thereaf ter, when the AFD l Monitor Alarin is inoperabic. The logged values of the i indicated AFD shall be assurr.ed to exist during the interval {

preceding each logging.  ;

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I POWER DI51RIBUT10N L1M115  !

3/4.2.4 QUADRANT POWER TILT RA110 r

LJM11114Gl.0NDUJ0LE0!L0ffRAllMt  ;

i l 3.2.4 The QUADuNT POWER TILT RATIO shall not exceed 1.02.  !

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APPLICABILITY: MODE 1, above 50% of RATED THERMAL POWER *. i t

l ACTION:

With the QUADRANT POWER TILT RATIO determined to exceed 1.02: ['

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a. Withir, 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> reduce THERMAL POWER at least 3% from RATED THERMAL POWER for each 1% of indicated QUADRANT POWER TILT RATIO in excess  !

of I and similarly reduce the Power Range Neutron flux-High Trip i Setpoint within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. L 1

b. Withir 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and every 7 days thereaf ter, verify that fg(Z) (by
  • F,y e;aluation) and f 3g are within their limits by performing Surveil-  !

lance Requirements 4.2.2.2 and 4.2..s.2. THEPMAL POWER and setpoint l l reductions shall then be in accordance with the ACTION statements of Specifications 3.2.2 and 3.2.3.

t I i EUMilLt A%REQlRE304U _ _._

j 4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be within the I limit above 50% of RATED THERMAL POWER by: ,

a. Calculating the ratio at least once per 7 days when the alarm is OPERABLE, and  ;

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b. Calculating the ratio at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during steady-state I l operation when the alarm is inoperable. i

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l i 4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the

  • l limit when above 75% of RATED THERMAL POWER with one Power Range channel inoperable by using the movable incore detectors to confirm indicated QUADRANT j POWER TILT RATIO at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by either: i

((spec 4.cabn M.M.a ehes nety )  :

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a. Using the four pairs of symmetric thimble locations, or  ;

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l b. Using the movable incore detection system to monitor the QUADRANT i POWER TILT RATIO subject to the requirements of Specification 3.3.3.2. ,

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  • 5ee Special Ten Exceptio is Spe, ;fication 3.10.2.  :

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SOUTH TEXAS - UN:TS 1 & 2 3/4 2-10 l

UNace.P J ' , '

ADMINI5TRATIVE CONTRQL,S _

CQRE OPERATING LIMITS REPORT h 0F ~W '

r 6.9.1.6.a Core operating limits shall be established and documented ,

in the CORE OPERATING LIMITS REPORT before cach reload cycle, or any part of a reload cycle for the following:

1. Moderator TcLperature coef ficient BOL and EOL limits, and 300 ppm surycillance limit for Specification 3/4.1.1.3,
2. Shutdown Bank Insertion Limit for Specification 3/4.1.3.5,
3. Control Bank Insertion Limits for Specification 3/4.1.3.6,
4. Axial Flux Difference limits and target band for Specification 3/4.2.1, 5.

Heat Flux Hot Chagl Factor, }((Z) , Power Factor Multiplier, and Fxy , for Specification 3/4. 2.2, and

6. Nuclear Enthalpy Rice Hot Channel Factor, and Power Factor Multiplier for Specification 3/4.2.3 The CORE OPERATING LIMITS REPORT shall be maintained available in the Control Room.

6.9.1.6.b The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:

1. WCAP 9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION- ---

METHODOLOGY", July, 1985 (H Proprietary) .

(Methodology for Specification 3.1.1.3 - Hoderator Temperature Coefficient, 3.1.3.5 - Shutdown Rod Insertion Limit, 3.1.3.6 -

Control Bank Insertion Limits, 3.2.1 - Axial Flux Dif ference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear l Enthalpy Rise Hot Channel Factor. )

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2. WCAP 8385, " POWER DISTRIBUTION AND LOAD FOLLOWING PROCEDURES TOPICAL REPORT", September, 1974 (H Proprietary) .

(Methodology for Specification 3.2.1 - Axial Flux Dif ference (Constant Axial Offset Control))

l,4 VfCAP 12A 42. - P- 8\ " .54 rcTY EVA Lu ATio4 suffbe.T NG A Mocc QCQAYWG got., MopCR ATCR 'rGM PCR ArdRC. COL FP1 C t CQ r y-dr.swcAL

$ fra PiCATioN FM. THE JouTH TETX45 PRNrCT ELEnrRA C.-

mr- = i .e . Q CNrR4r/N6 4

( MEtHmet.c4y toit sittipicArloN .3 f.l.3- Mooru1rA TTMPEMTtag st rMclegr};

SOUTH TEXAS - UNITS 1&2 6-P

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e REACTIVlTY CONTROL SYSTEM 5 i.

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, MODERATOR TEMPERATURE COEff1CIENT (Continued) d f N The most negative MTC, value equivalent to the most positive moderator  !

LA density <oefficient (MDC), was obtained by incrementally correctingTiie MDC  !

b used in thDSAf! analyses to nominal operating conditionsdhese corrections -

involved subtractlng4be incremental change in Jhe-NDfassociated with a core l condition of all rods iliser d(mostposyJW1DC)toanallrodswithdrawn l condition and, a conversion for he  !

{

temperature at RATED THERMALcoliif POWER'Jate f tfons. This of change value of of themoderator HDC was then density with !

transformed into the limit 4rfg'MTC value -4.0 P10-J Ak/k/ F. The MTC value j of -3.1 x 10

  • AL/JL/Yrepresents a conservative val'ucMwith corrections for  ;

burnup and spluble boron) at a core condition of 300 ppm e7q H4(rium boron concentratTon and is obtained by making these corrections to the rimQing MTC l fof -4.0 x 10 4 Ak/k/ F.

The Surveillance Requirements for measurement of the MTC at the beginning i and near the end of the fuel cycle are adequate to confirm that the MTC remains  !

within its limits since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup.

3/4.1.1.4 MINIMUM TEMPERATURE FOR CR]TICAllTY [

i This specification ensures that the reactor will not be made critical I with the Reactor Coolant System average temperature less than 561*f. This [

limitation is required to ensure: (1) the moderator temperature coefficient '

is within its analyzed temperature range, (2) the trip instrumentation is within r its normal operating range, (3) the pressurizer is capable of being in an  !

OPERABLE status with a steam bubble, and (4) the reactor vessel is above its  !

minimum RT temperature.  ;

NDT 3/4.1.2 BORAT10N SYSTEMS f The Boron Injection System ensures that negative reactivity control is  !

available during each mode of facility operation. The components required to i perform this function include: (1) borated water sources, (2) charging pumps, ,

l (3) separate flow paths, (4) boric acid transfer pumps, and (5) an emergency l l power supply from OPERABLE diesel generators.

With the RCS average temperature above 350 F, a minimum of two boron injection flow paths are required to ensure single functional capability in the event an assumed failure renders one of the flow paths inoperable. The boration capability of either flow path is sufficient to provide a SHUTDOWN ,

MARGIN from expected operating conditions of 1.75% Ak/k af ter xenon decay  !

and cooldown to 200 F. The maximum expected boration capability requirement j occurs at E0L from full power equilibrium xenon conditions and requires  ;

27,000 gallons of 7000 ppm borated water from the boric acid storage system [

or 458,000 gallons of 2500 ppm borated water from the refueling water storage 3 tank (RWST). The RWST volume is an ECCS requirement and is more than adequate J for the required boration capability. [

i l 50VIH TEXA5 - UNITS 1 & 2 B 3/4 1-2  !

fTEM h The most negativo MTC value, equivalent to the most positivo moderator density coef ficient (MDC) , was obtained by incrementally correcting the MDC used in the FSAR analysis to nominal operating conditions. These corrections involvedt (1) a conversion of the MDC used in the PSAR analysis to its equivalent MTC, based on the rato of change of moderator density with temperature at RATED TilERMAL POWER conditions, and (2) subtracting from this value the largest differences in MTC observed at EOL, all rods withdrawn, RATED TilERMAL POWER conditions, and those most adverse conditions of moderator temperature and pressure, rod insertion, axial power skewing, and xenon concentration that can occur in nominal operation and lead to a significantly more negative EOL HTC at RATED TilERMAL POWER. These corrections transformed the MDC values used in the FSAR analysis into the limiting EOL MTC value specified in the CORE OPERATING LIMITS REPORT (COLR) . The 300 ppm surveillanco MTC value specified in the COLR represents a conservative value (with corrections for burnup and soluble boron) at a core condition of 300 ppm equilibrium boron concentration, and is obtained by making these corrections to the limiting MTC value. '

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