ML20216D003

Proposed Tech Specs Re Moveable Incore Detector Sys

ML20216D003
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Site:	Farley
Issue date:	09/03/1997
From:	SOUTHERN NUCLEAR OPERATING CO.
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ML19317C700	List: ML20216C923 ML20216C966 ML20216D003 ML20216D017
References
NUDOCS 9709090188
Download: ML20216D003 (19)

Text

.c Enclosure 3 Revised Technical Specification Pages

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9709090188'970903'

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Pen and Ink Mark Up Technical Specification Pages

Technical Specification Inserts

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Insert <\

when the map is taken with more than 37 OPERABLE detector thimbles. For Unit 1, Cycle 15 only, with 25 to 37 OPERABLE thimbles the measurement uncertainty is determined from the following algorithm Fo measurement uncertainty = 5% + (2(3-(T/12.5))),

where T = the number of OPERABLE thinbles, insert B When the map is taken with more than 37 OPERABLE detector thimbles, the measurement uncertainty is 56. For unit 1, Cycle 15 only, with 25 to 37 OPERABLE thimbles the measurement uncertainty is determined from the following algorithm.

Fg measurement uncertainty = 5% + [ 2 ( 3- (T/12. 5 ) ) ) ,

where T = the number of OPERABLE thimbles.

Insert C:

when the map is taken with more than 37 OPERABLE detector thimbles. For Unit 1, Cycle 15 only, with 25 to 37 OPERABLE thimbles the measurement uncertainty is determined from the following algorithm.

b4H measurement uncertainty = 4% + [1.5(3-(T/12.5))],

where T = the number of OPERABLJ thimbles.

Insert I)

• For Unit 1, Cycle 15 only, at least 50% of the detector thimbles are required. With less than 75% of the detector thimbles, a minimum of 3 detectors thimbles per core quadrant are required, where quadrant includes both the horizontal-vertical quadrant and diagonally bound quadrants (eight quadrants total).

Insert E with more than 37 OPERABLE detector thimbles. With 25 to 37 OPERABLE detector thimbles, the allowance for measurement uncertainty is calculated by the algorithm in 4.2.2.2.b. for Unit 1, Cycle 15 only.

1 1

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, .a

9#

insert F with more than 37 OPEPABLE detector thimbles. With 25 to 37 OPERABLE detector thimbles, the allowance for measurement uncertainty is calculated by the algorithrr defined by 4.2.3.2 for Unit 1, Cycle 15, only.

Insert G For Unit 1 Cycle 15 only, the definition of quadrants includes both the horizontal-vertical quadrant and diagonally bound quadrants (eight quadrants total) as defined in Westinghouse Report CAA-97-234.

powtR DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

b. Determining the computed heat flux hot channel factor Fg (3), as followes Increase the measured Fg(2) obtained froni the power distribution map by 3t to account for manufacturing tolerances and further g increase the value by 5% to account for measuresent uncertainties / < - 3

c. Verifying that Fg C(Z), obtained in Specification 4.2.2.2b above, fAW satirhee the relationship in Specification 3.2.2. N

d. Satisfying the following relationships Fo* (Z ) s F "" x K (Z ) fo r P > 0.5 P x W (Z)

F"(Z) n s F0.5""xxWK(Z) (2) for P s 0.5 C

Where Fq (5) is obtained in Specification 4.2.2.2b above, Fg is the Fg limit, K(I) is the normalised FQ(3) as a function of core height, P fe the fraction of RATED THERMAL POWER, and W(!) is the ,

cycle dependent function that accounts for power distribution transients encountered during normal operation. I Fg , K(1), and W(3) are specified in the COLR as par Specification 6.9.1.11.

I

a. Measuring Fg(I) according to the following schedules

1. Upon achieving equilibrium conditions after exceeding by 20%

or more of RATED THERMAL POWER, the THERMAL POWER at which Fg(1) was last detemined*, or

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

• During power escalation after each fuel loading, power level may be increased until equilibrium conditions at any power level greater than or equal to 50% of RATED THERMAL POWER nave been achieved and a power distribution map obtained.

i FARLEY-UNIT 1 3/4 2-4 AMENDKENT NO.126

1 PO4fER DISTRIBUTIOR LIMITS SURVIILIJJECE REQUIREMENTS (Continued)

h. The limite specified in specification 4.2.2.2c are applicable in all core plane regions, i.e., 0 - 100%, inclusive.

1. The limite specified in specifications 4.2.2.2d, 4.2.2.22, and 4.2.2.2g above are not applicable in the following core plane regione l

1) Lower core region from 0 to 15%, inclusive.

2) Upper core region from s5 to 100%, inclusive.

. 4.2.2.3 When Fg(s) is measured for reasons other than meeting tha requirements of specification 4.2.2.2, an overall measured Fg(I) shall be obtained from a power distribution map and increased by 34 to account for manufacturing tolerances and further increased M o account for measurement uncertainty,fg

[MF .

• e rami.rr-crit 1 3/4 2-6 auxxonatmT wo. 1 21 w

N

e LOWERDISTRIBUTIONLIMITS SURVEILLANCE REQUIREMENTS 4.2.3.1 F N shall be determined to be within its limit by using the movable incore detNtors to obtain a power distribution map:

a. Prior to operation above 75% of RATED THERMAL POWER after each fuel loading, and ,

b. At least once per 31 Effective Full Power Days.

c. The provisions of Specification 4.0.4 are not applicable.

N 4.2.3.2 The measured F of 4 me surement uncertainty b .2.3.1 above, shall be increased by ,4% for l

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4 1

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4 4

4 6

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• w FARLEY-UNIT 1 3/4 2-9 AMENDMENT NO. 26 e

INSTRUMENTATION r

MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The movable incore detection systaa shall be OPERA 8LE with:

a. At leas'c 75 of the detector thimbles, b.

A minimum of'2 detector thimbles per core quadrant, and i

c.

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

APPLICABILITY: When the movable incore detection systes is used for:

a.

Recalibration of the excore neutron flux detection system,

b. Monitoring the QUADRANT POWER TILT RATIO, or

, c. MeasurementofFh,F(Z)andF q xy ACTION:

With the movable incore detection systee inoperable, do not use the systes for the above applicable monitoring or calibration functions. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. f

\

SURVEILLANCE REQUIREMENTS 4.3.3.2 The hovable incore detection system shall be demonstrated OPERA 8LE, by normalizing each detector output during use when required for:

a.

Recalibration of the excore 'outron flux detection system, or b.

Monitoring the QUADRANT Po, i TILT RATIO, or c.

MeasurementofFkF(Z)andF q 9

' a uc6 D e

FARLEY-UNIT 1 3/4 3-42 AMENOMENT NO. 26

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gM DT2?R9ttTTION LIMITS BASES 3/4.2.2 and 3/4.2.3 MEAT FLITX HOT CHANNTL PAC?OR. NUCLEAR ErfTMALPY MOT CHANNEL PACTO4 The limits on heat flux hot channel factor, and nuclear enthalpy rise hot channel factor ensure that 1) the design limit on peak local power density is not exceeded, 2) the DNB design criterion is met, and 3) in the event of a LOCA the peak fuel clad temperature will not exceed the 2200*F ECCS acceptance criteria limit,

i. ch of these is measurable but will normally only be determined periodically as specified in specifications 4.2.2 and 4.2.3. This periodic surveillance is e>fficient to insure that the limits are maintained provided:

a. Control rode u a single group move together with no individual rod insertion differing by more than 1 12 steps, indicated, from '

the group demand positice, b.

Control rod banks are sequenced with overlapping groupe as described in specification 3.1.3.6.

c. The control rod insertion limits of specificati me 3.1.3.5 and 3.1.3.6 are maintained. .

d. The axial power distribution, expressed in terms of AZIAL FLUX DIFFERENCE 7 is maintained within the limits.

N Fg will be maintained within its limits provided conditions a. through i

d. above are maintained. The relaxation of Fh as a function of TIERMAL POWER allows changes in the radial power shape for all permissible rod insertion limits.

When an Fg measurement is taken, an allowance for both amperimental error and manufacturing tolerance must be made. An allowance of 5% is appropriate for a full core map taken with the incere detector fluz mapping s et a#/34 allowance is appropriate for manufacturing tolerance.

W The heat flum hot channel factor Fg(I) is measured periodically and increased by a cycle and height dependent power factor appropriate to RAOC operation, W(I), to provide assurance that the limit on the heat fluz hot channel factor Fg(E) is met. W(1) accounts for the effects of normal operational transients within the AFD limits and was determined from expected power control maneuvers over the full range of burnup conditions in the core.

The-W(1) function for normal operation and the AFD limits are provided in the COLR per specification 6.9.1.11.

FARLEY-UNIT 1 B 3/4 2-2 AMENDKENT No.126

(

l 3 POWER Df5TR28UTION 1fM2TS BAsrs Wnen rh is measured, experimental error aus be allowed for and 44 is the appropriate allowance for a full core map ta n with the incore detectijo systemj The specified 1 it for Th contains lowance for @ L[tt u d uncertainties. The llowance is based on the following considerations

a. htA10 Abnormal perturbat one in the radial power shape, such as from rod misalignment, affect Th more directly than Fg, b.

Althcugh rod movement has a direct influence upon limiting Fg to within its limit, suchcontrolisnotreadilyavailabletolimitTh,and

c. Errors in prediction for control power shape detected during startup physics tests can be compensated for in Fg by restricting axial flux distribution. This compensation for Th is,less readily available.

If Fh exceeds its limit, the unit will be allowed 4 imurs to restore Fh to within its limits. This restoration may, for example, invclve realigning any misaligned rods or reducing power snough to bring Th within its power dependent limit. When the rh limit is exceeded, the DNBR limit is not likely violated in steady state operation, because events that could significantly perturb the rh value, e.g., static control rod misalignment, are considered in the safety analyses. However, the DNBR limit may be violated if a DNB limiting event occurs while Th is above its limit. The increased allowed action time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> provides an acceptable time to restore Ph to within its limits without allowing the plant to remain in an unacceptable condition for an extended period of time. -

Once corrective action has been taken, e.g., realignment of misaligned

' rods or reduction of power, an incore flux map must be obtained and the measured value of Fh verified not to exceed the allowed limit. Twenty additional hours are provided to perform this task above the four hours allowed by Action statement 3/4.2.3.a. The completion time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is, acceptable because et the low probability of having a DNR ilmiting event within this 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period and, in the event that power is reduced, an increase in DNR margin is obtained at lower power levels. Additionally, operating experience has indicated that.

this completion time is sufficient to obtain the incore flux map, perform tha requiredcalculations,andevaluateTh.

FARLEY-UNIT 1 8 3/4 2-4 AMENDMENT No. 121 k

e s

essa

• e -

• u l INSTRUMENTATION RAsrs' RADf aTION MONf?ORINC TNsTRUMENTaTION (Continued)

The alarm / trip setpcLat for the fuel storage pool area has been established based on a flow rate of 13,000 scia; a release in which Ze-133 and Kr-45 are the predominant isotopee, on concentration values equal to or less than the effluent conceraration limits stated in lo crR 20, Appendix a (to paragrapha 20.g001 - 30.24011, Table 2, Colume 1 for these lootopee, and on a X/c of 1.6 a 10 sec/m at the site boundary.

3/4.3.3.2 seovhaf* fuerm_* Lu mG-s The OPERASII.ITT of the sovable incere detectors with the specified =ini==

complement of equipammt ensures that the measurements obtained from uso of this system accurately represent the spatial neutros flam distribution of the reactor core. Ylie OPERASILITY of 'this system is demonstrated by irradiating each detector used and determiaing the acceptability of its voltage curve.

For the purpose of measuring F (S), Pfg, and F a fu is used. Quartar-core flux mapa,g as defined in d-ases,ll.7une incore flusmay 1 sis, may be O used la recalibratica of the encore neutroa flux detection system. Full taeare flux maps or ayumetric incore thlestes may be used for man oring the gunDRANT PouRR TILT RATIO when one Power Range Channel le inoper is. '

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9 rin tr-UwzT 1 a 3/4 3-2a Axr.nourut mo. 116

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Changed Technical Specification Pages Unit 1 Page 3/4 2-4 Replace Page 3/4 2-6 Replace-Page 3/4 2-9 Replace Pa ge 3/4 3-42 Replace Paige B 3/4 2-2 Replace Phge B 3/4 2-4 Replace Page B 3/4 3-2a Replace

i 1

POWER DISTRIBUTION LIMITS

--SURVEILLANCE REQUIREMENTS (Continued)

b. Determining the computed heat flux hot channel factor Fg'(Z), as follows:

Increase the measured Fo(Z) obtained from the power distribution map by 3% to account-fer manufacturing tolerances and further increase the value by 5% to account for measurement uncertainties when the map ia taken with more than 37 OPERABLE detector thimbles. For Unit 1, Cycle 15 only, with 25 to.37 OPERABLE thimbles the measurement uncertainty is determined from the followi ? algorithm Fa measurement uncertainty = 5% + [2(3-(T/12.5))],

where T = the number of OPERABLE thinbles.

c. Verifying that FoC(Z), obtained in Specification 4.2.2.2b above, satisfies the relationship in Specification 3.2.2.

d. Satisfying the following relationships F"'"

x K(Z)

$ for 0.5 F0(Z) F x W(Z)

P >

F"T' x K(Z)

P'(Z) 9 5

0.5 x for P 5 0.5 W(Z)

Where Fo (Z) is obtained in Specification 4.2.2.2b above, Fo"" is the Fo limit, K(Z)- is the normalized Fo(Z) as a function of core height, P is the fraction of RATED THERMAL POWER, and W(Z) is the cycle dependent function that accounts for power distribution transients encountered during nornal operation.

Fo"', K(Z),'and W(Z) are specified in the COLR as per Specification 6. 9.1.11.

e. Measuring Fo(Z) according to the following schedules

1. Upon achieving equilibrium conditions after exceeding by I 20% or more of RATED THERMAL PO'CR, the THERMAL POWER at

- which Fo(Z) was last determined *, or

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

• During power escalation after each fuel loading, power level may be increased until equilibrium conditions at any power level greater than or equal to 50% of RATED THERMAL POWER have been achieved and a power distribution map obtained.

FARLEY-UNIT 1 3/4 2-4 AMENDMENT NO.

I

, ,_ i .

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

h. The limits specified in Specification 4.2.2.2c are applicable l-. in all core plane _ regions, i.e., 0 - 100%, inclusive.

1. The limits specified in Specifications 4.2.2.2d, 4.2.2.2f, and 4.2.2.2g above are not applicable in the following core plane regions:

1) Lower core region from 0 to 15%, inclusive

2) Upper core region from 85 to 100%, inclusive.

4.2.2.3- When Fg(Z) is measured for reasons other than meeting the requirements of Specification 4.2.2.2, an overall measured Fg(Z) shall'be obtained from a power distribution map and increased by 3% to account for manufacturing tolerances and further increased to account for measurement uncertainty. When the map is taken with 3re than 37 OPERABLE detector thimbles, the measurement uncertainty is 5%. For unit 1, Cycle 15 only, with 25 to 37 OPERABLE thimbles the measurement uncertainty is deterndned from the following algorithm.

Fo measurement uncertainty = 5% + [2(3-(T/12.5))),

where T = the number of OPERABLE thimbles, FARLEY-UNIT 1 3/4 2-6 AMENDMENT NO.

1 l POWER DISTRIBUTION LIMITS

- SURVEILLANCE REQUIRD4ENTS

-4.2.3.1 F$Hshallbedeterminedtobewithinitslimitbyusingthe movable incore detectors to obtain a power distribution maps-

a. Prior to operation above 75% of RATED THERMAL POWER after each I- fuel loading, and

b. At least once per 31 Effective Full Power Days.

c. The-provisions of Specification 4.0.4 are not applicable.

4.2.3.2 ThemeasuredF$Hof4.2.3.1above, shall be increased by 4% for measurement uncertainty when the map is taken with more than 37 OPERABLE detector thimbles. For Unit 1, Cycle 15 only, with 25 to 37 OPERABLE thimbles the measurement uncertainty is determined from the following algorithm.

Fu measurement uncertainty = 4% + (1.5(3-(T/12.5))],

where T = the number of OPERABLE thimbles.

FARLEY-UNIT 1 3/4 2-9 AMENDMENT NO.

POWER DISTRIBUTION LIMITS BASES 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR, NUCLEAR ENTHALPY HOT CHANNEL FACTOR The limits on heat flux hot channel factor, and nuclear enthalpy rise hot channel factor ensure that 1) the design limit on peak local power density is not exceeded, 2) the DNB design criterion is met, and 3) in the event of a LOCA the peak fuel clad temperature will not exceed the 2200*F ECCS acceptance criteria limit.

Each of these is measurable but will normally only be determined periodically as specified in Specifications 4.2.2 and 4.2.3. This periodic

) surveillance is sufficient to insure that the limits are maintained provided:

a. Control rods in a single group move together with ao individual rod insertion differing by more than i 12 steps, indicated, from the group demand position,

b. Control rod banks are sequenced with overlapping groups as described in Specification 3.1.3.6.

4

c. The control rod insertion limits of Specifications 3.1.3.5 and 3.1.3.6 are maintained,

d. The axial power distribution, expressed in terms of AXIAL FLUX DIFFEREdCE, is maintained within the limits.

F$g will be maintained within its limits provided conditions a.

through d. above are maintained.

The relaxationofF$Hanafunctionof THERMAL POWER allows changes in the radial power shape for all permissible rod insertion limits.

When an Fg measurement is taken, an allowance for both experimental error and manufacturing tolerance must be made. An allowance of 5% is appropriate for a full core map taken with the incore detector flux mapping system with more than 37 OPERABLE detector thimbles. With 25 to 37 OPERABLE detector thimbles, the allowance for measurement uncertainty is calculated by the algorithm in 4.2.2.2.b. far Unit 1, Cycle 15 only. A 3%

allowance is appropriate for manufacturing tolerance.

The heat flux hot channel factor Fg(Z) is measured periodically and increased by a cycle and height dependent power factor appropriate to RAOC operation, W(Z), to provide assurance that the limit on the heat flux hot channel f actor Eq(Z) is met. W(Z) accounts for the effects of normal operational transients within the AFD limits and was determined from expected power control maneuvers over the full range of burnup conditions in the core. The W(Z) function for normal operation and the AFD limits are provided in the COLR per Specification 6.9.1.11.

FARLEY-UNIT 1 B 3/4 2-2 AMENDMENT NO.

(1 I

POWER DISTRIBUTION LIMITS BASES WhenF$H is measured, experimental error must be allowed for and 4%

is the appropriate allowance for a full core map taken with the incore detection system with more than 37 OPERABLE detector thimbles. Wita 25 to 37 OPERABLE detector-thimbles, the-allowance for measurement uncertainty is calculated by the algorithm defined by 4.2.3.2 for Unit 1, cycle 15 only.

ThespecifiedlimitforF$Hcontainsa4% allowance for manufacturing uncertainties. The total uncertainty allowance is based on the following considerations:

a. Abnormal perturbations in the radial power shape, such as from rod misalignment, affectF$HmoredirectlythanFg,

b. Although rod movement has a direct influence upon limiting Fg to within its limit, suchcontrolisnotreadilyavailabletolimitF$He and c.- Errors in prediction for control power shape detected during startup physics tests can be compensated for in Fg by restricting axial flux distribution. ThiscompensationforF$gislessreadilyavailable.

IfF$3exceedsitslimit, the unit will be allowed 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to restore F$gtowithinitslimits. This restoration may, for example, involve realigninganymisalignedrodsorreducingpowerenoughtobringF$Hwithin its power dependent limit. WhentheF$H limit is exceeded, the DNBR limit is not likely violated in steady state operation, because events that could significantlyperturbtheF$Hvalue, e.g., static control rod misalignment, are considered in the safety analyses. However, the DNBR limit may be violatedifaDNBlimitingeventoccurswhileF$H is above its limit. The increased allowed action time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> provides an acceptable time to restore F$H-towithinitslimitswithoutallowingtheplanttoremaininan unacceptablu condition for an extended period of time.

Once corrective action has been taken, e.g., realignment of misaligned rods or reduction of power, an incore flux map must be obtained andthemeasuredvalueofF5Hverifiednottoexceedtheallowedlimit.

Twenty additional hours are provided to perform this task above the four hours allowed by Action Statement 3/4.2.3,a. The completion time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is acceptable because of the low probability of having a DNB limiting event within-this 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period and, in the event that power is reduced,

-an increase in DNB margin is obtained at lower power levels. Additionally, operating experience has indicated that *.his completion time is sufficient to obtain the incore flux map, perform the required calculations, and evaluateF$3 FARLEY-t! NIT 1 B 3/4 2-4 AMENDMENT NO.

_ _ _ _ _ _ _ l

INSTRUMENTATION BASES-t i

l-RADIATION MONITORING INSTRUMENTATION (continued)

The alarm / trip setpoint for the fuel storage pool area has been established based on a flow rate of 13,000 scfms a release in which Xe-133 and Kr-85 are the predominant isotopes, on concentration values equal to or less than the. effluent concentration limits stated in 10 CFR 20, Appendix B, (to paragraphs 20.1001 - 20.2401), Table 2, Column 1 for these isotopes, and on a X/Q of 5.6 x 10-6 sec/m3 at the site boundary.

3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core. The OPERABILITY of this-system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.

For the purpose of measuring Fg(Z), . F$H, and'Fx a full incore flux map is used. Quarter-core flux maps, asdefinedinWbAP-8648, June 1976, may be used in recalibration of the excore neutron flux detection system.

For Unit 1 Cycle 15 only, the definition of quadrants includes both the horizontal-vertical quadrant and diagonally bound quadrants (eight quadrants total) as defined in Westinghouse Report CAA-97-234. Full incore flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range Channel is inoperable.

FARLEY-UNIT 1 B 3/4 3-2a AMENDMENT NO.

9 Enclosure 4 Westinghouse Reports CAA-97-234 (proprietary)

CAA-97-235 (non-proprietary)

Farley Unit I Cycle 15 Thimble Deletion Study And Supporting Aflidavit CAW-97-Il60

• *9 . . _ _ . _ .