ML20058N811

Proposed Tech Specs Concerning Eol Moderator Temp Coefficient

ML20058N811
Person / Time
Site:	Farley
Issue date:	07/13/1990
From:	ALABAMA POWER CO.
To:
Shared Package
ML19298E400	List: ML20058N808 ML20058N811 ML20058N814 ML20058N818
References
NUDOCS 9008150139
Download: ML20058N811 (11)

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REACTIVITY CONTROL SYSTEMS j MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION i 1

3.1.1.3 The moderator temperature coefficient (NTC) shall be:

a. Less than or equal to 0.5 x 10 delta k/k/'F for the all rods )

withdrawn, beginning of cycle life (BOL), belov 70% THERNAL POVER condition. Less than or equal to O delta k/k/'F at or l above 70% THERMAL POWER.

b. Less negative than -4.3 x 10 delta k/k/'F for the all rods l vithdrawn, end of cycle life (EOL), RATED TRERMAL POWER condition.

APPLICABILITY: Specification 3.1.1.3.a - MODES 1 and 2* only#

Specification 3.1.1.3.b - MODES 1, 2 and 3 onlyt ACTION: ,

a. Vith the NT: more positive than the limit of 3.1.1.3.a above, operation !e 10 DES 1 and 2 may proceed provided:

1. Contu god withdroval limits are established and maintained suffipxent to restore the NTC to within its limit within 24 1 l

hours or be in HOT STANDBY vithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. These r withdrawal limits shall be in addition to the insertion limits of Specification 3.1.3.6.

l 2. The control rods are maintained within the withdrawal ifeits t l

established above until a subsequent calculation verifies that the HTC has been restored to within its limit for the all rods  :

vithdrawn condition.

3. A Special Report is prepared and submitted to the Commission pursuant to specification 6.9.2 vithin 10 days, describing the value of the measured NTC, the interim control rod withdrawal limits and the predicted average core burnup necessary.for restoring the positive MTC to within its limit for the all  ;

rods withdrawn condition. "

b. Vith the MTC more negative than the limit of 3.1.1.3.b above, be in HOT SHUTD0VN vithin 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• With K,,, greater than or equal to 1.0 r

l 4 See Special Test Exception 3.10.3 FARLEY-UNIT 1 3/4 1-4 Amendment No.

6 REACTIVITY CONTROL SYSTEMS i l l SURVEILLANCE REQUIREMENTS  ;

4.1.1.3 The MTC shall be determined to be within its limits during each fuel cycle as follows:

a. The NTC shall be measured and compared to the BOL limit of Specification 3.1.1.3.a. above, prior to initial operation above -

5% of RATED THERMAL POVER, after each fuel loading.

b.TheMTCsha}1bemeasuredatanyTHERMALPOVERandcomparedto 5

-3.65 x 10' delta k/k/'F (all rods withdrawn, RATED THERMAL l  ;

POVER condition) within 7 EFPD after reaching an equilibrium ,

boron concentration of 300 ppe. In the event this f indicates the NTC.is more negative than -3.65 x 10'gosparison delta l k/k/'F, the NTC shall be remeasured, and compared to the EOL NTC limit of specification 3.1.1.3.b, at least once per 14 EFPL during the remainder of the fuel cycle. (1) l i

i (1) Once the equilibrium boron concentration (all rods withdrawn, RATED y THERMAL POVER condition) is 100 ppm or less, further measurement of the MTC in accordance with 4.1.1.3.b may be suspended, providing that the measured NTC at an equilibrium boron concentr equal to 100 ppm is less negative than -4.0 x 10'gtion delta less than or k/k/'F.

FARLEY-UNIT 1 3/4 1-5 -Amendment No.

l 3/4.1 REACTIVITY CONTROL SYSTEMS BASES l

3/4.1.1 BORATION CONTROL ]

3/4.1.1.1 AND 3/4.1.1.2 SHUTDOVN MARGIN i A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made 1 suberitical from all operating conditions, 2) the reactivity transients 1 associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor vill be maintained sufficiently suberitical to preclude inadvertent criticality in-the shutdown condition.  ;

SHUTDOVN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T,y . The most ,

restrictive condition occurs at EOL, with T at no load operating  ;

temperature,andisassociatedwithapostulaledsteamlinebreakaccident and resulting uncontrolled RCS cooldovn. In the analysis of this accident, .

a minimum SHUTDOVN MARGIN of 1.77% delta k/k is required to control the reactivity transient. Accordingly, the SHUTDOVN MARGIN requirement is based upon this limiting condition and is consistent with FSAR safety analysis assumptions. With T l resulting from a postuls,ted sleInline essbreak than cooldown 200'F,'theare reactivity minimal transients and a 1%

delta k/k SHUTDOWN MARGIN provides adequate protection.

3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to i

ensure that the value of this coefficient remains within the limiting condition assumed in the FSAR accident and transient analyses.

The MTC values of this specification are applicable to a specific set of  ;

plant conditions: accordingly, verification of MTC values at conditions l other than those explicitly stated vill require extrapolation to those l conditions in order to permit an accurate comparison.

The most negative MTC value equivalent to the most positive moderator

~

density coefficient (MDC) was obtained by incrementally correcting the MDC  :

used in the FSAR analyses to nominal operating conditions. -These .I corrections involved (1) a conversion of the MDC used in the FSAR safety analyses to its equivalent MTC, based on the rate of change of. moderator density with temperature at RATED THERMAL POVER conditions, and (2) l subtracting from this value the largest differences in MTC observed l between EOL, all rods withdrawn, RATED THEMAL POVER conditions, and those most adverse conditions of moderator temperature and pressure, rod 1

( insertion, axial power skeving, and xenon concentration that can occur in l normal operation and lead to a significantly more negative EOL MTC at RATED THERMAL POVER. These corrections transformed the MDC value

( the FSAR safety analyses into the limiting MTC value of -4.3 x,10'ysed in delta k/k/'F. The surveillance requirement MTC value of -3.65 X 10' delta k/k/'F represents a conservative MTC value at a core condition of 300 ppm equilibrium boron concentration, and is obtained by making correptions for burnup and soluble boron to the limiting HTC value of -4.3 x 10' delta l k/k/'F. l 1

l FARLEY-UNIT 1 B 3/4 1-1 Amendment No.

i l

REACTIVITY CONTROL SYSTEMS 1

BASES MODERATOR TEMPERATURE COEFFICIENT (Continued)

Once the equilibrium boron concentration falls below 100 ppa, NTC l measurements may be suspended provided the measured NTC value at an .l equilibriuy boron concentration < 100 ppe is less negative than  !

-4.0 x 10' delta k/k/*F. The diffe  ;

limiting.EOL NTC value of -4.3 x 10'gence deltabetween this value and k/k/*F conservatively the bounds '

the maximum change in MTC between the 100 ppa equilibrium boron concentration (all rods withdrawn, RATED THERNAL POVER condition) and the i licensed end-of-cycle, including the effects of boron concentration reduction, fuel depletion, and end-of-cycle coastdown.

The surveillance requirements for measurement of the HTC at the beginning  ;

and near the end of the fuel cycle are adequate to confirm that the NTC remains within its limits since this coe.tficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup.  !

3/4.1.1.4 HINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor vill not be made critical with the Reactor Coolant System average temperature less than 541'F. This limitation is required to ensure 1) the moderator temperature coefficient is within its analyzed temperature range, 2) the protective instrumentation  ;

is within its normal operating range, 3) the F-12 interlock is above its '

setpoint, 4) the pressurizer is capable of being in an OPERABLE status with  ;

a steam bubble, and 5) the reactor pressure vessel is above its minimum ,

RT,,, temperature.

3/4.1.2 BORATION SYSTEMS The boron injection system ensures that negative reactivity control is available during each mode of facility operation. The components required to perform this function include 1) borated water sources, 2) charging pumps, 3) separate flow paths, 4) boric acid transfer pumps, and 5) an ,

emergency power supply from OPERABLE diesel generators. '

Vith the RCS average temperature above 200'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 SHUTDOVN s

FARLEY-UNIT 1 B 3/4 1-2 Amendment No.

I l

REACTIVITY CONTROL SYSTEMS l \

l MODERATOR TEMPERATURE COEFFICIENT i LIMITING CONDITION FOR OPERATION l

3.1.1.3 The moderator temperature coefficient (MTC) shall be  ;

a. Less than or equal to 0.5 x 10 delta k/k/'F for the all rods withdrawn, beginning of cycle life (bOL), belov 70% THERMAL POWER condition. Less than or equal to O delta k/k/'F at or above 70% THERMAL POVER.  ;

b. Less negative than -4.3 x 10 delta k/k/'F for the all rodswithdrawn,ando APPLICABILITY: Specification 3.1.1.3.a - MODES 1 and 2* onlyt Specification 3.1.1.3.b - MODES 1, 2 and 3 only#

ACTION:

a. Vith the MTC more positive than the limit of 3.1.1.3.a above, operation in MODES 1 and 2 may proceed provided: '

1. Control rod withdrawal limits are established and maintained sufficient to restore the MTC to within its limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />  ;

or be in HOT STANDBY vithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. These withdrawal limits shall be in addition to the insertion limits of Specification 3.1.3.6. L

2. The control rods are maintained within the withdrawal limits established above until a subsequent calculation verifies that the l MTC has been restored to within its limit for the all rods '

vithdrawn condition. '

3. A Special Report is prepared and submitted to the Commission '

l pursuant to Specification 6.9.2 within 10 days, describing the value of the measured MTC, the interim control rod withdrawal l limits and the predicted average core burnup necessary for l

restoring the positive MTC to within its limit for the all rods i l vithdrawn condition.

b. With the MTC more negative than the limit of 3.1.1.3.b above, be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

I

• With K,,, greater than or equal to 1.0

1. See Special Test Exception 3.10.3 l

l FARLEY-UNIT 2 3/4 1-4 Amendment No.

,, a - ,,---,.,,.,eaw , - ,wae. ..ma-,., _e ~, men-. mv,w--,,m--s--- , --yp. y , , , ,,r.,n v .4 4 e

i REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMERTS 4.1.1.3 The NTC shall be determined to be within its limits during each fuel cycle as follows:

a. The NTC shall be measured and compared to the BOL limit of l Specification 3.1.1.3.a. above, prior to initial operation above-5% of RATED THERMAL POVER, after each fuel loading. ,

b.TheNTCsha}1bemeasuredatanyTHERMALPOVERandcomparedto

-3.65 x 10' delta k/k/'F (all rods withdravn, RATED THERMAL l 'l '

POVER condition) within 7 EFPD after reaching an equilibrium boron concentration of 300 ppa. In the event this .

indicates the NTC is more negative than -3.65 x 10'gomparison delta l k/k/'F, the MTC shall be remeasured, and compared to the EOL NTC ,

limit of specification 3.1.1.3.b, at least once per 14 EPPD during the remainder of the fuel cycle. (1) l l

l i

i (1) Once the equilibrium boron concentration (all rods withdrawn, RATED l THERMAL POVER condition) is 100 ppm or less, further measurement of i the HTC in accordance with 4.1.1.3.b may be suspended, providing that I

the measured MTC at an equilibrium boron concentr equal to 100 ppa is less negative than -4.0 x 10'gtion deltaless k/k/'F. than or r

FARLEY-UNIT 2 3/4 1-5 Amendment No.

h 3/4.1 REACTIVISf CONTROL SYSTEMS BASES l

l 3/4.1.1 BORATION CONTROL l 3/4.1.1.1 AND 3/4.1.1.2 SHUTDOVN MARGIN f i

A sufficient SHUTDOVN MARGIN ensures.that 1) the reactor can be made suberitical from all operating conditions, 2) the reactivity transients i

associated with postulated accident conditions are controllable within '

acceptable limits, and 3) the reactor vill be maintained sufficiently ,

suberitical to preclude inadvertent criticality in the shutdown condition.

t SHUTDOVN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T,y . The most restrictive condition occurs at EOL, with T at no load operating temperature, and is associated with a postulaled steam line break accident  ;

and resulting uncontrolled RCS cooldown. In the analysis of this accident,  !

a minimum SHUTDOVN MARGIN of 1.77% delta k/k is required tc control the

• reactivity transient. Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting condition and is consistent with FSAR safety analysis assumptions. 'fi th T less than 200'F, the reactivity transients l resulting from a postulated sleIn line break cooldovn are minimal and a 1%

delta k/k SHUTDOVN MARGIN provides adequate protection.

3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the value of this coefficient remains within the limiting j condition assumed in the FSAR accident and transient analyses.

• The MTC values of this specification are applicable to a specific set of i plant conditions accordingly, verification of MTC values at conditions other than those explicitly stated vill require extrapolation to those conditions in order to permit an accurate comparison.

The most negative MTC value equivalent to the most positive moderator density coefficient (MDC) was obtained by incrementally correcting the MDC used in the FSAR analyses to nominal operating conditions. These corrections involved (1) a conversion of the MDC used in the FSAR safety analyses to its equivalent MTC, based on the rate of change of moderator density with temperature at RATED THERMAL POVER conditions, and (2) subtracting from this value the largest differences in MTC observed between EOL, all rods withdravn, RATED THEMAL POVER conditions, and'those most adverse conditions of moderator temperature and pressure, rod insertion, axial power skeving, and xenon concentration that can occur in  ;

normal operation and lead to a significantly more negative EOL MTC at RATED THERMAL POWER. These corrections transformed the MDC value theFSARsafetyanalysesintothelimitingMTCvalueof-4.3x,10'ysedin delta k/k/'F. The surveillance requirement MTC value of -3.65 X 10' delta k/k/'F represents a conservative MTC value at a core condition of 300 pp:2 equilibrium boron concentration, and is obtained by making corre

• l burnup and soluble boron to the limiting MTC value of -4.3 x 10'ptions delta for k/k/'F.

FARLEY-UNIT 2 B-3/4 1-1 Amendment No.

1. --, , - - ege g- +e-= +ps-a "---#'r-v'rtEl**MW89- *- -* ^'~mu-F' "-'-^-W=-*-* *- - - - * + - -

- 8* - - ------ - ------ --

REACTIVITY CONTROL SYSTEMS

]

BASES  !

4 MODERATOR TEMPERATURE COEFFICIENT (Continued)

Once the equilibrium boron concentration falls belov 100 ppa, NTC measurements may be suspended provided the measured HTC value at an i

equilibriupboronconcentration<100ppaislessnegativethan

-4.0 x 10' delta k/k/'F. The diffe  !

limiting EOL MTC value of -4.3 x 10'{ence deltabetween this value andbounds k/k/'F conservatively the

the maximum change in MTC between the 100 ppm equilibrium boron concentration (all rods withdravn, RATED THERMAL F0VER condition) arid the licensed end-of-cycle, including the effects of boron concentration .

reduction, fuel depletion, and end-of-cycle coastdown. .

The surveillance requirements for measurement of the NTC at the beginning

and near the end of the fuel cycle are adequate to confirm that the NTC '

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 CRITICALITY This specification nsures that the reactor vill not be made critical with the Reactor Coolant System average temperature less than 541*F. This limitation is required to ensure 1) the moderator temperature coefficient is within its analyzed temperature range, 2) the protective instrumentation is within its normal operating range, 3) the F-12 interlock is above its setpoint, 4) the pressuriser is capable of being in an OPERABLE status with a steam bubble, and 5) the reactor pressure vessel is above its minimum ,

RT,,n temperature.

3/4.1.2 BORATION SYSTEMS I The boron injection system ensures that negadve reactivity control is available during each mode of facility operation. The components. required to perform this function iM1ude 1) borated water sources, 2) charging

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

l Vith the RCS average temperature above 200'F, a minimum of two boron i

injection flow paths are required to ensure single functional capability in l

the event an assumed failure renders one of the flow paths inoperable. The boration capability of either flow path is sufficient to provide a SHUTDOVN ,

c I

FARLEY-UNIT 2 B 3/4 1-2 Amendment No.

4 4

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j PROPRIETARY INFORMATION NOTICE l

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