ML20148Q891

Proposed Tech Specs Defining Incore Detection Sys as Combination Sys of Both Fixed & Movable Detectors & Associated Equipment

ML20148Q891
Person / Time
Site:	Yankee Rowe
Issue date:	04/04/1988
From:	YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML20148Q853	List: ML20148Q891 ML20148Q903
References
NUDOCS 8804140029
Download: ML20148Q891 (11)

Text

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REACTIVITY CONTROL SYSTEMS LIMITING CONDRIDN FOR OPERATION (Continu.cd)

b. The SHUTDOWN MARGIN requirement of Specification 3.1.1.1.1 is determined at 1 cast once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and

c. A power distribution map is obtained from the incore N

detection system and Fg and F aH are verified to be within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

d. The THERMAL POWER level is reduced to 175% of RATED THERMAL POWER within one hour and within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the Power Range and Intermediate Power Range Neutron Flux high trip setpoint is reduced to 1108% of the 75% of allowable THERMAL POWER, or

e. The remainder of the rods in the group with the inoperable rod are aligned to within 18 inches of the inoperable rod within one hour while maintaining the rod sequence and insertion limits of Figure 3.1-2. The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.5 during subsequent operation.

$11RVEILLANCE REOUIREMENTS f 4.1.3.1.1 The position of each control rod shall be determined to be within the limit by verifying the individual rod positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4.1.3.1.2 Each control rod not fully insertid shall be determined to be OPERABLE by movement of at least 4 inches in any one direction at least once per 31 days.

4.1.3.1.3 The maximum reactivity insertion rate due to withdrawal of the highest worth control rod group shall be determined not to exceed 1.5 x 10-4 ok/k per second at least once per 18 months.

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l 3/4 1-24 YANKEE-ROWE Amendment No. ) [

' 8804140029 880404 PDR ADOCK 05000029 MD p

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REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS LIMITING CONDITION FOB OPERATION 3.1.3.2 All control rod primary and secondary position indicator channels shall be OPERABLE and capable of determining the control rod positions within

+3 inches.

APPLICABILITY: MODES 1 and 2.

ACTION:

a. With a maximum of one primary rod position indicator channel per group inoperable either:

1. Determine the position of the non-indicating rod (s) indirectly by the incore detection system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and l immediately af ter any motion of the non-indicating rod which exceeds 8 inches in one direction since the last determination of the rod's position, or

2. Reduce THERMAL POWER to <50% of THERMAL POWER allowable for the main coolant pump combination within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

b. With a maximum of one secondary position indicator per group inoperable either:

1. Verify that all primary rod position indicators for the affected group are OPERABLE, or

2. Reduce THERl4AL POWER to <50% of THERMAL POWER allowable for the main coolant pump combination within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SURVEILIANCE REOUIREMENTS 4.1.3.2 Each rod position indicator channel shall be determined to be OPERABLE by verifying the primary position indication system and the secondary position indicator channels agree within 3 inches at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

3/4 1-25 YANKEE-ROWE

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3/4.2 POWER DISTRIBUTION LIMITS i

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PEAK LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION _

I j 3.2.1 The peak linear heat generation rate (LHCR) shall not exceed the limits  ;

of Figure 3.2-1 during steady state operation.

APPLICABILITY: MODE 1.

I ACTION:

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j With the peak LHCR exceeding the limits of Figure 3.2-1:

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a. Within 15 minutes reduce THERMAL POWER to not more than that l fraction of the RATED THERMAL POWER as expressed below: l

' Limiting LHGK 4 Fraction of RATED THERMAL POWER = Peak Full Power LHGR l

b. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> reduce the Power Range and Intermediate Power Range  !

Neutron Flux high trip setpoint to 1108% of the fraction of RATED ,

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4 THERMAL POWER.  !

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,l SURVEILLANCE REOUIREMENTS '

4.2.1.1 The peak LHGR shall be determined to be within the limits of Figure 3.2-1 using the incore detection system to obtain a power distribution l [

t maps Prior to initial operation above 75% of RATED THERMAL POWER af ter $

a.

each fuel loading, and l

b. At least once per 1,000 EFPH. i j

j c. The provisions of Specification 4.0.4 are not applicable.  ;

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YANKEE-ROWE Amendment No. ##, 55, 72.,S5' f 8

i POWER DISTRIBUTION LIMITS SURVEILlgff_EEQQQQgNTS (Conlinne_d) 4.2.1.2 The below factors shall be included in the calculation of peak full power LHGR:

a. Heatfluxpowerpeakingfactor,Fy,measuredusingtheincore detection system at a power 110%.

J b. The multiplier for xenon redistribution is a function of core lifetime l as given in Figure 3.2-3. In addition, if Control Rod Group C is ,

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inserted below 80 inches, allowable power may not be regained until power has been at a reduced level defined below for a least twenty-four hours with Control Rod Group C between 80 and 90 inch 64.

Reduced Power = Allowable fraction of full power times multiplier given in Figure 3.2-4.

Exceptions: 1. If the rods are inserted below 80 inches and power does not go below the reduced power calculated above, hold at the lowest attained power level for at least l

twenty-four hours with Control Rod Group C between 80 and 90 inches before returning to allowable power.

2. If the rods are inserted below 80 inches and zero power is held for more than forty-eight hours, no reduced '

I power level need be held on the way to the allowable 4

fraction of full power.

! c. Shortened stack height factor, 1.009.  :

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d. Measurement uncertainty:*

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1. 1.05, when at least 17 incore detection system neutron detector thimbles are OPERABLE, or

2. 1.068, when less than 17, and greater than or equal to 12, incore detection system neutron detector thimbles are OPERABLE.

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1 i 3/4 2-2 YANKEE-ROWE Amendment No. 43, 53, 11, 11, 85,,100' 1

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POWER DISTI'IBUTION LIMITS HEAT FLUX HOT CHAN?iEL FACTOR-F 4 LIMITING _C0ATITION FOR_0ffEAT10N 3.2.2 Fq shall be limited by the following relationships:

F 1(* } for P > 0.5 F 1 (5.52] for P 1 0.5 THERMAL POWER p , RATED THERMAL POWER APPLICABILITY: MODE 1 ACTION:

With Fq exceeding its limits:

a. Reduce THERMAL POWER at least 1% for each 1% Fq exceeds the limit within 15 minutes and similarly reduce the Power Range and Intermediate Power Range Neutron Flux-Tligh Trip Setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. ,

b. Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER above the reduced limit required by a, above; THERMAL POWER may then be increased provided Fq is demonstrated through measurement with the incore detection system to be within its limit.

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3/4 2-8 YANKEE-ROWE Amendment No. M .,69'

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' POWER DISTRIBUTION LIMITS SURVEILLANCE REOUIREMENTS 4.2.2.1 F shall be determined to be within its limit by:

q

a. Using the incore detection system to obtain a power distribution map:

1. Prior to initial operation above 75% of RATED THERMAL POWER after each fuel ic.ading, and

2. At least once per 1000 Ef f ective Full Power Hours.

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b. Increasing the measured Fq component of the power distribution map by:

1. 4% to account for engineering tolerances,

2. 5% when at least 17 incore dete. tion system neutron detector thimbles are OPERABLE, to account for measurement uncertainty,

3. 6.8% when less than 17, and greater than or equal to 12, incore detection system neutron detector thimbles are OPERABLE, to account for measurement uncertainty, and

4. 3% to account for fuel densification. ,

4. 2. 2. 2 WhenqF is measured pursuant to Specification 4.10.2.2, an overall measured qF shall be obtained from a power distribution map and increased by:

1. 4% to account for engineering toicrances,

2. 5% when at least 17 incore detection system neutron detector thimbles are OPERABLE, to account for measurement uncertainty, 6.8% when less than 17, and greater than or equal to 12, incore 1

3.

detection system neutron detector thimbles are OPERABLE, to account for measurement uncertainty, and

4. 3% to account for fuel densification.

4.2.2.3 The provisions of Specification 4.0.4 are not applicable. .

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! 3/4 2-9 YANKEE-ROWE Amendment No. 53, 11,77, g j

POWER DISTRIBUTION LIMITS N1JCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - F"H LIMITING CONDITION FOR OPERATION 3.2.3 F{Hshallbelimitedbythefollowingrelationship:

H I 1.80 (1.0 + 0.2 (1-P)].

THERMAL POWER p , RATED THERMAL POWER APPLICABILITY: MODE 1 ACTION:

WithF{Hexceedingitslimit:

a. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range and Intermediate Power Range Neutron Flux-high trip setpoints to 155% of RATED THERMAL 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. Demonstrate through measurement with the incore detection system l thatF$H is within its limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding the limit or reduce THERMAL P0k'ER co less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, ano

c. Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER above the reduced limit required by a or b, above; subsequent POWER OPERATION may proceed provided that i F{H is demonstrated through measurement with the incore I detection system to be within f cc limit at a nominal 50% of RATED T11ERMAL POWER prior to exceeding this THERMAL POWER, at a nominal {

75% of RATED THERMAL POWER prior to exceeding this THERMAL power and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter attaining 95% or greater RATED THERMAL POWER.

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3/4 2-10 YANKEE-ROWE AmendmentNo.g I

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POWER DISTRIBUTION LIMITS t

t SURVE111ANCE REOUIREMENTS t 4.2.3.1 FhHshallbedeterminedtobewithinitslimitbyusingthe  ;

incore detection system to obtain a power distribution map: l

a. Prior to operation above 75% RATED THERMAL POWER af ter each fuel  :

loading, and

b. At least once per 1000 Effective Full Power Hours.

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

4.2.3.2 ThemeasuredF$Hof4.2.3.1aboveshallbeincreased,for measurement uncertainty, by:

a. 5%, when at least 17 incore detection system neutron detector thimbles are OPERABLE; or

b. 6.8%, when less than 17, and greater than or equal to 12, incore e l

detection system neutron detector thimbles are OPERABLE. g I

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i j 3/4 2-11 I i

Amendment No. (3, 53, 72, 77. )ACF f YANKEE-ROWE

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IJ@TRUMENTATION INCORE DETECTION SYSTEM L1B IIIEG_C0E LIl01S__E@_0 PlfpT I ON 3.3.3.2 The incore detection system shall be OPERABLE with:

a. At 1 cast twelve (12) neutron detector thimbles OPERABLE.

b. A minimum of two (2) OPERABLE neutron detector thimbles per core quadrant, and

c. Sufficient OPERABLE incore neutron detectors, with:

1. Suf ficient drive and readout equipment to map the OPERABLE movable neutron detector thimbles, and/or

2. Sufficient readout equipment to map the OPERABLE fixed neutron detector thimbles.

APPLICABILITY: When the incore detection system is used for core power distribution measurements.

ACTION With the incore detection system inoperabic, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specifications 3.0.3 and 3.0.4 are not applicabic.

SURVEILIANCE_REQUIREffENTS 4.3.3.2 The incore neutron detectors shall be demonstrated OPERABLE by:

a. Normalizing each movable detector output to be used within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to its use for core power distribution measurements.

b. Having three out of five OPERABLE fixed neutron detectors per string.

3/4 3-23 Amendment No. 69, 53, 71, 77, 95, 100, M YANKEE-ROWE

3/4.2 POWER DISTRIBUTION LIMITS MSESlConLinucD The limits on power 1cvel and control rod position following control rod insertion were selected to prevent exceeding the maximum allowabic linear heat generation rate limits in Figure 3.2-1 within the first few hours following return to power after the insertion. With Yankee's highly damped core, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> hold allows sufficient time for the initial xenon maldistribution to accommodate itself to the new power distribution. The restriction on control rod location during these 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> assures that the return to allowabic f raction of full power will not cause additional redistribution due to rod motion.

Af ter 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> at zero power, the average xenon concentration has decayed to about 207, of the full power concentration. Since the xenon concentrations are so low, an increase in power directly to maximum allowable power creates transient peaking well below the value imposed by the xenon redistribution multiplier. Thus, any increase in power peaking due to this operation is below the value accounted for in the calculation of the LHGR.

These conclusions are based on plant tests and on calculations performed with the SIMULATE three dimensional nodal code used in the analysis of Core XI (reference cycle) described in Proposed Change No. 115, dated March 29, 1974.

Tbc Factors d, e, and f in Specification 4.2.1.2 will be combined statistically as the "root-sum-square" of the individual parameters. This method for combining parameter uncertainties is valid due to the independence of the parameters involved. Facter d accounts for uncertainty in the power distribution measurement with the incore detection system. Factor e accounts l for uncertainty in the calorimetric measurement for determining core power level. Factor f accounts for uncertainty in engineering and fabrication tolerances of the fuel. Together these factors, when combined statistically, yield an uncertainty of 8.57. for less than 17 and greater than or equal to 12 operating incore thimbles, and 7.17. for greater than or equal to 17 operating thimbles. This factor and Factors a, b, c, and g will be combined multiplicatively to obtain peak IEGR values.

3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR 'AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR l The limits on heat flux and enthalpy hot channel factors ensure that l

1) the design limits on peak local power density and minimum DNBR are not exceeded, and 2) in the event of a LOCA the peak fuel clad temperature will not exceed the 22000F ECCS acceptance c.riteria limlt.

Each of these hot channel factors are measurable but will normally only be determined periodically ac specified in Specification 4.2.2.1 and 4.2.3.1.

This periodic surveillance is sufficient to insure that the hot channel factor limits are maintained provided:

B3/4 2-2 YANKEE-ROWE Amendment No. O , 88,,1 6

3/4.2 POWER DISTRIBUTION LIMITS BASES (Cofithtued)

a. Control rods in a single group move together with no individual rod insertion differing by more than 18 inches fcom any other rod in the group.

b. Control rod groups re sequenced with overlapping groups as described in Specification 3.1.3.5.

c. The control rod insertion limits of Specification 3.1.3.5 is maintained.

The relaxation in F{g as a function of THERMAL POWER allows changes in the radial power shape for ai.1 permissible rod insertion limits.

F$HwillbemaintainedwithitslimitsprovidedConditionsathroughc above are maintained.

When an F q measurement is taken, experiment.11 error, engineering tolerance, and fuel densification must be allowed for. 5% is the appropriate allowance for a full core map taken with the incore detection system, 4% is l the appropriate allowance for engineering tolerance and 3% is the appropriate allowance for fuel densification.

WhenF3H is measured, experimental error must be allowed for and 5% is the appropriate allowance for a full core map taken with the incore detection system.

l 3/4.2.4 DNB PARAMETERS The limits on the DNB related parameters assure that each of the parameters are maintained within the normal steady state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the acciJent analysis assumptions and have been analytically demonstrated adequately to maintain a minimum DNBR of 1.30 throughout each analyzed transient. The Main Coolant System inlet temperature assumed in the analysis i i is conservatively 40F in excess of the limit to allow for uncertainty in l plant measurement. The Main Coolant System pressure assumed in the analysis I is 1925 psig, conservatively 25 psig less than the limit to allow for uncertainty in plant measurement. The assumed operating deadband of 150 psig i is applied to the nominal 2000 psig limit, yielding a minimum operation limit l of 1950 psig. l The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their limits following load changes and other expected transient operation. The 18 month periodic measurement of the Main Coolant System total flow rate is adequate to detect flow degradation and ensure correlation of the flow indication channels with measured flow such that the indicated percent flow will provide suf ficient verification of flow rate on a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> basis.

B3/4 2-3 YANKEE-ROWE Amendment No. H ., (

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