ML20104B400

Rev 1 to Calculation RXE-TA-CP1/0-027, Undervoltage/ Underfrequency Reactor Trip Setpoints

ML20104B400
Person / Time
Site:	Comanche Peak
Issue date:	02/13/1992
From:	TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20104B391	List: ML20104B388 ML20104B393 ML20104B400
References
RXE-TA-CP1--2, RXE-TA-CP1--27-R1, RXE-TA-CP1-0-02, RXE-TA-CP1-0-027-R01, NUDOCS 9209150305
Download: ML20104B400 (25)

Text

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TU ELECTRIC REACTOR ENGINEERING CALCULATION COVER SHEET 4 Calculation No.ibE M~ C8' '- CU Revision No. I Subject u t)}u f Qcrrea 700 ,<,rposrs S Nuclear Safety Related O Computer Output Listing (s) attached Originator 7dkb Date 2//oN2-Reviewer , 6ho P Date O I

Attachrt.ents Af,z f' 3j>9 I Approval Id Ml, AM Date 2/t 3 /92, A r t, 2 . 2. gt -

ti r 7 1 . 2 P]

Abstract:

The nominal setpoint, allowabla w.lue, the "S" and "Z" terms and the total allovance for use in Table 2.2-1 of the CPSES-1 Technical Specifications

m the underfrequency and undervoltage reactor trip setpoints were ,

tlated. The following values are used in the 5 column Technical Specification format shoal in Tech Spec Table 2.2-1. Unless otherwise noted, all values are in units of percent of instrument span.

Un 1."oltage Underfrequency r* x Trip Reactor Trip TA 7.7 4.4 2 1.2 0.0 S 0.0 0.0 Ncminal Trip Setpoint 4830V 57.2 Hz Allowable Value 4753V 57.1 M2 Also provided in this calculation package is an alternate calculation of the UF reactor trip setpoint and associated input for the CPSES-1 Technical Specifications. This alternate calculation (Contained in Section VI.) will supersede the calculation contained in Section III. when LDCR TS92-010 is approved by the NRC. LDCR 1S92-010 is a Tech Spec change ittplementing the results of the alternate calculation for the UF reactor trip setpoint and incorporating the change to the "Z" tem for the UV reactor trip setpoint.

Until LDCR 92-010 is approved by the NRC,' the alternate UF calculation merely forms the basis for tine IDCR submittal.

9209150305 920910 ntv no PDR ADOCK 05000445 p PnR

TU ELECTRIC REACTOR ENGINEERING REVISION SHEET Calculation No. U[-7;#- CM/r -O '.L7 Rev. No.

Description:

Revision 1.of this calculation provides an alternate calculation of the UF reactor trip setpint and associated input for the CPS 55-1 Technical Specifications. This alternate calculation (Contained in Secticri VI.) vill supersede the calculation contained in Secticn III, for the UF reactor trip setpoint when LDQ TS92-010 h approved by the IEC. LDCR TS 92-010_is a Tech Spec charme ituplement' q b results of the alternate calculation for the UF reactc trip setpol _ ' < incorprating the change to the "Z" tenn for the UV reactor trip see - .. Until LDG 92-010 is approved by the 1 0 the alternate UF calculation i.arely forms the basis for the LDCR sutznittal.

Revision 1 is reissued in its entirety; thus, Revision 0 is superseded.

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TU ELECTRIC REACTOR ENGINEERING CALCULATION SHEET Subject UV/LT Reactor Trip Setroints calc. No. RXE-TA-CP1/0-027 Rev. i Sheet 1 Originator Date Reviewer Date Table of Contents I. Purpose 2 II. Background 2 3

III. Calculatione 2 IV. Assuriptions 12 V. References 12 2 VI. Alternate Calculation for the UF Reactor Trip Setpoint 13

TU ELECTRIC REACTOR ENGINEERING CALCULATION SHEET Subject W/UF EgagigtTrip Setroints Calc. No. RXE-TA-CP1/0-027 Rev._1__

Sheet 2

' Originator Date Reviewer Date I. Purpose One Form FX 91-1658 [3] describes a condition wherein the allowable calibration tolerances specified in the El-2400 document wre inconsistent with the tolerances used in the calculation of the Undervoltage (W) and Underfrequency (UF) reactor trip setpoints for CPSES-1 ( 2 ] . Further, an additional uncertainty has been identif. led which was not originally included in the setpoint calculation. 'Ihe purpose of this calculation is to calculate revised setpoints for CPSES-1 for inclusion into the plant Technical Sin::ifications, and to establish new calibration tolerances for the W and UF relays within the confines of the current CPSES-1 Technical Specifications.

Also provided in this calculation package is an alternate calculstion of the UF reactor trip setpoint and associated input for the CPSES-1 Technical Specifications. This alternate calculation (Contained in Section VI.) will supersede the calculation contained in Section III. when LDCR 'IS92-010 is approval by the NRC. LDCR TS92-010 is a Tech Spec change inplccenting the results of the alternate calculation for the UF reactor trip setpoint and incorporating the change to the "2" term for the W reactor trip setpoint. Until LDCR 92-010 is approved by the NRC, the alternate UF calculation m- ;ly forms the basis for the IDCR submittal.

II. Background The calculations of the ncrainal and allowable values of the setpoints, and of the "S" and "Z" terms included in the Technical Specifications, will be performed'using the_same methodology used by Westinghouse to calculate the Unit 1 setpoints (1, 2). This-methcdology, the assumptions, and the bases for those assumptions are provided in Reference 1. 'Ihe actual Unit I calculaticns are -

provided in Reference 2.

III. Calculations A. Trip Functions As described on pages 55 and 56 of Reference 1, the RCP undervoltage reactor trip function provides a prirrary reactor trip for the complete loss of RCS flow event. This trip

-function monitors the bus voltage for the RCPs. A loss of voltage results in tripping the undervoltage relays prior to a reactor trip due to lcu RCS coolant flow. Below the P-7 interlock, this function is autcreatically blocked, and is autcxnatically enabled above P-7.

(

TU ELECTRIC REACTOR ENGINEERING CALCULATION SHEET Subject UV/UF Reactor Trip Setooints calc. No. -RXE-TA-CP1/0_027 Rev.1 Sneet 3-Originator Date

,. Reviewer Date a-As descrited in page 56 of Reference 1, the RCP underfrequency reactor trip function provides a backup function for the undervoltage for the carplete loss of RCS flow. The frequency of the RCP busses is manitored dasnstream of the RCP breakers. A reduction in the frequency is an indication of a significant reduction in the bus voltage. Below the P-7 interlock, this function is autaratically blocked, and is autaratically enabled above P-7.

B. Operating Environnent As described on Page 56 of Reference 1, the accidents upon I

which the UV/UF trip functions are relied do not result in adverse containment environments; therefore, no adverse environment effects must be considertd.

C. Safety Analysis Limits As noted in Reference 4, there is no explicit accident analysis limit assumed for the undervoltage reactor trip. Berefore, for ansistency with the Unit 1 Technical Specifications, a safety analysis limit of 68% of the nominal voltage of 6.9kV is assumed.

This limit, derived from the ncminal value and total allowance values of the Unit 1 Technical Specifications [5), carresponds to 4692 V.

As noted in Reference 4, the safety analysis linit for the UF event is 57.0 Hz.

D. Instrumentation The Undervoltage and Underfrequency relay model numbers, nminal settings and tolerance settings are described in Attachment 1.- This information was provided to Westinghouse as the basis for the Unit 1 setpoint study (2]. From conversations with various CPSES personnel, it is highly desireable to relax the tolerance settings. Because this calculation package forms the basis for the tolerance settings, new tolerances will be developed and used in this calculation. We new tolerances, including allowances will be provided in Section IV.

As described in Attachment 1,- the detection of the undervoltage condition is provided by G.E. bbdel #12NGV13AllA relays. These relays have-a dropout range of 70-100V. The potential transformer ratio is 7200/120. As shown in Attachment 2, there is an uncertainty of 0.3% associated with this ratio. As described in Attachment 1,-

the underfrequency relays are Westinghouse type KF underfrequency relays, Style #6718287A17. These relays have a frequency range of 55 to 59.5 Hz.

i TU-ELECTRIC' REACTOR ENGINEERING CALCULATION SHEET Bubject W/UF Reactor Trip SetDoints Calc. No. RXE-TA-CP1/0-027 Rev._L_

Sheet 4 originator _ Date Reviewer _ Date i

E. Naminal Setpoints The nominal setpoints are based on consideraticns other than this ,

statistical setpoint study. The relay setting tolerances are based  !

on the such considerations as this setpaint study and the ease of j calibration. For the purposes of this calculation, the tolerances are developed, based on verbal input- from CPSES personnel. The incorporation of these tolerances into the appropriate plant documents is outside the scope of this calculation'(see Section IV.)

As described in Attachnent 1, the nminal undervoltage relay setting is 80.5V. Note that this voltage is reduced from the actual bus voltage by the patential transformer by a factor of-60 (the P.T.

ratio).

As described in Attachme t 1, the underfrequency relay setting is 57.2 Hz.

i F. Channel Statistical Allomnce As defined in Section 4.2 of Reference 1, the channel statistical allcvance is expressed as:

CSA = ((PMA)2 + (PEA)2 + (SCA + SHTE + SD)2 ,

+ (SPE)2 + (STE)2 + (RCA + RMrE +RCSA' + RD)2

+ (RTE)2)1/2 + EA

where the relevant acronyms will be defined belcu.

+

For the trip functions under consideration, the relays can be considered as part of the rack.- As described on page 192 of Reference 1, for simple ch mnels that have only a power supply, the inclusion of an RCA term is not necessary. However, an allowance-for-the settings of the relays will be included. -Only the rack terms and ~

the uncertainty associated with the P.T. ratio are included in the

calculation of the CSA. Therefore, the definition of CSA relevant to the W/UF reactor. trip functions is

. GA = (( PEA)2 +(RCA + RMIE +RCSA + RD)2 + (RTE)2)1/2 1

]c i

4

3 i TU ELECTRIC REACTOR ENGINEERING CALCULATION SHEET

} Subject UV/UF Reactor Trip Setroints Calc. No. RXE-TA-CP1/0-027 Rev. L

! Sheet 5

j. Originator Date i Reviewer Date_

l-l WHERE, for the LtOEMOLTICE trip function:

i l PEA = Primary Element Accuracy i

l As noted in Attachment 3, the uncertainty associated with j the potential transformer is f0.3%. _ Thus, the P.T. ratio i may vary from (0.997*60 =) 59.82 to (1.003*60 =) 60.18.

! The nominal bus voltage is 6900 V; however, to i conservatively maximize the effect of the ratio

! uncertainty, a bus voltage of 7200V is assumed. Therefore, 5

the relay voltage can vary from (7200V/59.82 =) 120.36V to (7200V/60.18 =) 119.64V about the nominal value of 120V.

3 This uncertainty can be expressed as 10.36V. Given the

!- voltage span of 30V, the uncertainty becmes 21.2% span.

Note that this uncertainty could be expressed as a " process j measurement accuracy" term; howver, during a telephone conversation on 1/15/92, C. R. Tuley of' Westinghouse

indicated that it was W practice to represent this i uncertainty as a PEA. The effect on the final calculated j results is the same, regardless of how the uncertainty is

expressed.

j RCA = rack calibration accuracy = f2.25% span I The relay calibration is confirmed as an integral part of the rack. From Reference 1, the rack calibration tolerance j is defined as the accuracy to which the relay can be set.

i As alluded to earlier, conversations with CPS E personnel 3

indicated that a calibration accuracy of -12% span would be considered acceptable. A calibration accuracy of !2.25%

span is selected =in order to maximize the allowable

. calibration-tolerance, while ensure the RMTE allowance can a be incorporated into the rack uncertainty. total which form i

the basis for the current plant Technical Specifications.

For the UV relay, the lower setpoint tolerance would i becoce:

1

-22.25% = (Nminal setting - lowest tolerance)/ span

• 4- 100%

+2.25% =

(80.5V - xV)/30V *100%

j x = 79.83 V 4

4

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TU ELECTRIC REACTOR ENGINEERING CALCULATION SHEET Subject W/UF Reactor Trip Setooints -Calc.-No. RXE-TA-cpl /0-027 - Rev.1 Sheet 6 Originator Date Reviewer Date RMIE = rack measuring and test equipment allo.rance It is assumed that the measuring and test equipTent is sufficiently accurate to ensure that the RCA : RMTE ratio is at least 4:1. Hence, the allowance for the RMIE is ,

20.56% span. Howver, in order to keep the allowable value (to be calculated later) the sa:re as in the current plant Technical Specifications, the PMrE allowance vill be increased to 10.61% span.

RCSA = rack comparator setting accuracy = 20.0% span Because there is no separate bistable in this channel, no RGA allowance is reqJired.

BD = rack drift An alloannce for rack drift over the surveillance intervals required by the plant Technical Specifications will be made which corresponds to the original rack drift allowance made by-Westinghouse in Reference 2, i.e., 1.43% span. (The value reported in Reference 2 is 1.4%-span, rounded frcm the rigorous calculation of RD using Attachment 1, i.e.,

RD = RCA = (80.5V - 80.07V)/30V

• 100% = 1.43% span).

RTE =

rack temperature effects = 20.0% of span a As noted on page 201 of Reference 1, the effect of voltage and frequency shifts are negligible. Because this channel consists of only a relay, and no additional circuitry is involved, there is no need for the RTE allowance. 'Ihis approach is consistent with the original calculation performed by W for Unit 1 (2).

Therefore, for the Ut0ERVOLTAGE reactor trip function, G3 = ((PEA)2 + (RCA + RMIE +RCSA + RD)2 + (RTE)2)l/2

=

((1.2)2 + (2.25 + 0.61 + 0.0 + 1.43)2 + (0.0)2)l/2

= 4.45% span

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TU ELECTRIC REACTOR ENGINEERING CALCULATION SHEET Subject (N/UF Reactor Trip Setroints calc. No. RXE-TA-cpl /0-027 Rev.1 Sheet 7 Originator Date Reviewer Date For the UNDDURECUDCY trip function:

RCA = rack calibration accuracy = 1.0% span The relay calibration is confirmd as an integral part of the rack. Similar to the calculation perforned for the the Undervoltage relay, a Rack Calibration Accuracy of 11.0%

span is provided. This allomnce corresponds to a calibration tolerance of:

RCA = (thninal setting - lowest tolerance)/ span

• 100%

1.0% = (57.2Hz - xHz)/4.5Hz *100%

x = 57.155 Hz REE = rack measuring and test egaipnent allomnce It is assumed that the measuring and test equipment is sufficiently accurate to ensure that the RCA : RMTE ratio is at least 4:1. Hence, the allowance for the REE is 0.25% span. However, in order to preserve the allowable value reported in the current CPSD3-1 Technical Specifications, the RMTE allowance will be increased to 0.34% span.

RCSA = rack comparator setting accuracy = 10.0% cpan Because there is no separate bistable in this channel, no RCSA allowance is required.

RD = rack drift An allcvance for rack drift over the surveillance intervals required by the plant Technical Specifications will be made

'hich

. corresponds to value used by W in the original serpoint calculations. This value is 0.67% span. (The value reported in Reference 2 is 0.7% span, rounded frcxn the rigorous calculation of FD using Attachwnt 1, i.e.,

-RD = RCA = (57.2Hz - 57.17Hz)/4.5Hz

• 100% = 0.67% span).

RTE =

rack temperature effects = 10.0% of span As noted on page 201 of Reference 1, the effect of voltage and frequency shifts are negligible. Because this channel consists of only a relay, and no acEitional circuitry is involved, there is no need for the RTE allowance. This approach is consistent with Unit 1 [2].

. . - . - - - .. ~ . . ~. , -_

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L-TU ELECTRIC REACTOR ENGINEERING CALCULATION SHEET l Subject W/UF Reactor Trip SetDoints . Calc. No. RXE-TA-CP1/0-027 _ Rev.1 Sheet 8 l _

Originator. Date-

> Reviewer Date Therefore, for the UNDERFREQUD CI reactor trip function,

! CSA = ((RCA + REE +RCSA + RD)2 + (RTE)2}l/2 -

2

=

((1.00 + 0.34 + 0.0 + 0.67)2 + (0.0 ))l/2 i

l

= 2.01% span  :.

l t

G. "A" l The "A" term will be used in the evaluation of the allowable value of

! the setpoint. The allowable value will be specifled in the plant i

Technical Specifications.

l As noted on page 29 of Reference 1,

= 2 A (PMAlg + (PMA2)2 + (PEA)2 + (SPE)2 + (STE)2 +

l d

(RTE) i = 1.44% span for the W trip function. (PEA is only non-zero tem)

= 0.0% span for the UF trip function.

H. "2" "2" is used with the variables "S" and "R" in the Tech Specs i when actual measured data is available for the racks or transmitters.

Frcxn Page 29 of Reference 1,

.2 = A1/2 + EA

= 1.2% span for the W trip function.

{

'= 0.0% span for the UF trip function.

I. "S" j

"S" represents the transmitter terms in the determination of the channel operability per the Tech Specs.

From Page 30 of Reference 1, S = SCA + S!EE + SD

=

0.0% for both the W and UF trip functions l

r TU ELECTRIC REACTOR ENGINEERING CALCULATION SHEET 4 I

Subject UV/UF Reactor Trip Setoo1 DIS __.

Calc. No. RXE-TA-CP1/0-027 . Rev. _1_

Sheet 9

' -Originator Date Reviewer Date J. Total Allo 'ance ,

I The Total Allcvance (TA) represents the difference between tM i ncninal setpoint and the safety analysis limit in terms of ,

% spin. As inferred frcrn Page 26 of Reference 1, the total l allo.ance is:

TA = ABS ((SAL - ncninal setpoint)]/ span

• 100%

For the UNDERVOLTAGE trip function, the safety analysis limit setpoint is converted to relay voltage by using the nominal P.T. ratio of 60. Hence, the safety analysis limit is:

4692V / 60V/V = 78.2V.

The TA then beccres:

= ABS ((78.2V - 80.5V)]/30V

• 100% span

= 7.67% span, rounded to 7.7% span For the 20ERFRErJJEC1 trip function, the safety analysis limit setpoint 57.0 Hz. The TA then beccxnes:

= ABS ((57.2Hz - 57.0Hz)]/4.5Hz

• 100% span

4.44% span, rounded to 4.4% span K. Tl Tl is a trigger used to develop the allavable value developed in Section M. Frcn Page 33 of Reference 1, T1 = RCA + RbTIE + RCSA + RD For the 20ERVOLTAGE trip function, T1

2.25 r 0.61 + 0.0 + 1.43

= 4.29% span For the UNDERFREQUDCf trip function, T1 = 1.00 + 0.34 + 0.0.+ 0.67

=

2.01% span

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TU ELECTRIC REACTOR ENGINEERING CALCULATION SHEET Subject UVM Reactor Trip Setooints calc. No. rdE-TA-cpl /0-027 Rev.1 Sheet 10 Originator Date Reviewer Date L. T2 is a trigger used to develop the allowable value developed in Section M. From page 33 of Reference 1, 2

T2 =

TA - ({A + S )l/2 + EA}

For the the UV trip function T2 =

7.7 - ((1.44 & O.02 )l/2 + 0.0)

= 6.5% span For the UF trip function T2 = TA = 4.4% span M. Allowable Value The allowable value is used in the Tech Specs as a trigger to indicate when a protection loop is inoperable. The allowable value is the based on the lesser of T1 or T2, or T. Frcm Section 4.7 of Reference 1, Allwable Value (AV) = Nominal Setpoint i T (depending upon the application)

For the UNDERVOLTAGE trip function, AV =

80.5V - (4.29% span

• 30V/100% span]

=

79.213V (relay voltage)

= 4753V _(bus voltage)

For the UNDERFREQUENCY trip function, AV = 57.2Hz - (2.01% span

• 4.5Hz/100% span]

= 57.lHz

\ ..

• 4 TU ELECTRIC REACTOR ENGINEERING CALCULATION SHEET Subject (NAJF Reactor _ Trio setpoints__. calc. No. -

RXE-TA-CP1/O-027 Rev.1 Sheet 11 Originator Date Reviewer .Date _ _

N. Sumrary

'Ihe following values are used in the 5 column Technical Spacification fornat stan in Tech Spec Table 2.2-1. Unless otherwise roted, all values are in units of percent of instrument span.

Undervoltage Underfrequency Reactor Trip Reactor Trip TA 7.7 4.4 2 -1.2 0.0 S 0.0 0.0 lbninal Trip Setpaint 4830V 57.2 Hz Allowable Value 4753V 57.1 H2

+

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TU ELECTRIC REACTOR ENGINEERING CALCULATION SHEET Subject UV/UF Reactor Trip _Seto31nts Calc. No. RXE-TA-CP1/0-027 Rev.1 Sheet 12 Originator Date Reviewer _

Date IV. Assu:Tptions (to be transmitted with results of this calculation)

• • Note that these assumptions will be affected by the-inplementation of LDCR 92-010, as described in Sections I and VI.

1. An allowance for a RCA:RMTE ratio of 4:1 is included in the uncertainty calculations.

2. Allowances for Rack Drift for the Undervoltage and Underfrequency trip functions are 1.43% span and 0.67% span, respectively.

3. Allowances for the following nominal relay setting and tolerances (low end only) have been included in the setpoint study:

UV Reactor Trip Function: (ncminal - 80.5V; minimum - 79.83V)

UF Reactor Trip Function: (ncminal - 57.2Hz; minimum - 57.155Hz)

V. References

1. " Bases Document for Westinghouse Setpoint Methodology for Cmanche Peak Protection Systems", WCAP 12485, March,1990.

2. " Westinghouse Setpoint Methodology for Protection Systems, Cmanche Peak Unit 1, Revision 1,", WCAP 12123, Revision 2, April 1990.

3. OE Form FX-91-1658, initiated 12/9/91.

4. " Accident Analysis Assumptions Checklists", WCAP-12368, Revision 1, August 1990.

5. CPSES-1 Technical Specifications, Table 2.2-1, through Amendment 7.

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e* TU ELECTRIC REACTOR ENGINEERING CALCULATION SHEET Subject UWUF Reactor Trip Setroints Oale. No. - RXE-TA-cpl /0-02]_ Rev.1 Sheet 13 Originator _Date Reviewer Date VI. Alternate Calculation for the UF Reactor Trip Setpoint This section contains an alternate calculation of the UF reactor trip setpoint. This alternate calculation provides for a relay setting tolerance of +2% span for the UF relay. Note that in order to provide this relaxed tolerance, the " Allo able Value" term reported in the current CPSES-1 Tech Specs for the UF reactor trip setpoint must be changed. Therefore, this calculation shall not be used in CPSES-1 applications until the Tech Spec change has been approved by the NRC. Until NRC approval is attained, this alternate calculation foms the basis for the Tech Spec change suhaittal', LDCR TS92-010.

A. Channel Statistical Allowance As defined in Section 4.2 of Reference 1, the channel statistical allosance is expressed as:

CSA = ((PMA)2 + (PEA)2 + (SCA + SMIE + SD)2

+ (SPE)2 + (STE)2 + (RCA + RMIE +RCSA + RD)2

+ (RTE)2)l/2 + EA

-here

• the relevant acronyms will be defined belos.

For the trip functions under consideration, the relays can be considered as part of the rack. As described on page 192 of m Reference 1, for simple channels that have only a power supply, the inclusion of an RCA term is_not necessary.

However, an allowance for the settings of the relays vill be included. Only the rack terms are included in the calculation of'the CSA. Therefore, the definition of GA relevant to the UF reactor trip function is:

CSA = ((RCA + RMTE +RCSA + RD)2 + (RTE)2)l/2 For the UNDERFRECUD Cl trip function:

RCA =

rack calibration accuracy The relay calibration is confirmed as an integral part of.-

the rack. Similar to the calculation performed for the Undervoltage relay, a Rack Calibration-Accuracy of 12.0%

span is provided. This allowance corresponds to a calibration tolerance of:

RCA =

(Nominal setting - lowest tolerance)/ span

• 100%

2.0% = (57.2Hz - v.Hz)/4.SHz *100%

x = 57.11 Hz

{

- 'l '

TU ELECTRIC REACTOR ENGINEERING. CALCULATION SHEET Subject (N/UF Reactor Trip Setroints Calc. No. RXE-TA-cpl /J-D2*L Rev.L Sheet. 14 Originator Date Reviewer -Date PMrE = rack measuring and test equipTent allosance It is assumed that the measuring and test equiptent is sufficiently accurate to ensure that the RCA : RMTE ratio is at least 4:1. Hence, the allo <ance for the RMIE is 0.50% span.

RCSA = rack catparator setting accuracy = 20.0% span Because there is no separate bistable in this channel, no RCSA allo.ance is required.

RD = rack drift i

An alloeance for rack drift over the surveillance inter'rals required by the plant Technical Specifications will be made which corresponds to value used by El in the original setpoint calculations. This value is 0.67% span. -(The value reported in Reference 2 is 0.7% span, rounded fran the rigorous calculation of RD using Attachment 1, i.e.,

RD = RCA = (57.2Hz - 57.17Hz)/4.5Hz

• 100% = 0.67% span).

RTE =

rack te"perature effects = 10.0% of span As noted on page 201 of Reference 1, the effect of voltage and frequency shifts are negligible. Because this channel consists of only a relay, and no additional circuitry is involved, there is_no need for the RTE allosance. This approach is consistent with the original setpoint calculation performed for Unit 1 [2).

/

Therefore, for the LEDERERDNENCY reactor trip function, CSA = {(RCA + RMTE +RCSA + RD)2 + (RTE)2)l/2

= 2

((2.00 + 0.50 + 0.0 + 0.67)2 + (0.0 ))1/2

= 3.17% span B. "A" The "A" term will be used in the evaluation of the allosable value of the setpoint. The alloaable value will be sp r ified in the plant Technical Specifications.

As noted on.page 29 of Reference 1, A =

(R4A1}2 + (H4A2)2 + (PEA)2 + (gpg)2 + (STE)2 +

(RTE)

=

0.0% span for the UF trip function. J

TU ELECTRIC REACTOR ENGINEERING CALCULATION SHEET Subject UV/UF Reactor Trip Selpoints Calc. No. RXE-TA-CP1/0-027 Rev.1 Sheet 15

-Originator- Date Reviewer Date_.

C. "2" "Z" is used with the variables "S" and "R" in the Tech Specs when actual neasured data is aveable for the racks or transmitters.

Frm Page 29 of Reference 1, 2 = A1/2 + EA

= 0.0% span for the UF trip function.

D. "S" "S" represents the transmitter terms in the determination of the channel operability per the Tech Specs.

Frcra Page 30 of Reference 1, S = SCA + SMIE + SD

=

0.0% span for the UF trip functions E. Total Alleence The Total Allowance (TA) represents the difference between the nminal setpoint and the safety analysis limit in terms of % span.

As inferred frm Page 26 of Reference 1, the total allowance is:

TA =

ABS [(SAL - nominal setpoint)}/ span

• 100%

For the UNDERFRIUJDU trip function, the safety analysis limit setpoint 57.0 Hz. The TA then beccmas:

=

ABS {(57.2Hz - 57.0Hz)]/4.5Hz

• 100% span

=

4.44% span, rounded to 4.4% span F. Tl T1 is a trigger used to develop the allowable value developed.in Section M. Erm Page 33 of Reference 1, T1 = RCA + RMTE + RCSA + RD For the UNDERFRIUJDC trip function, T1 = 2.00 + 0.50 + 0.0 + 0.67

=

3.17% span

TV ELECTRIC REACTOR ENGINEERING CALCULATION SHEET Subject WM Reactor Trip Setroints Calc. No. RXE-TA-CP1/O-Oll, Rev.1 Sheet 16

-Originator Date Reviewer Date G. T2 is a trigger used to develop the allosable value developed in Section M. Fran page 33 of Reference 1, 2

T2 =

TA - ((A + S )1/2 + EA)

For the UF trip function T2 = TA = 4.4% span H. Allovable Value The allosable value is used in the Tech Specs as a trigger to indicate when a protection loop is inoperable. The allosable value is the based on the lesser of Tl or T2, or T. Fran Section 4.7 of Reference 1, Allovable Value ( AV) = Naninal Setpoint + T (depending upon the application)

For the UtOERFREUJDT3 trip function, AV =

57.2H2 - [3.17% span

• 4.5Hz/100% span)

= 57.06Hz I. Alternate Calculation Surmary The follosing values are used in the 5 column Technical Specific.ation format shosn in Tech Spec Table 2.2-1. Unless othervise noted, all values are in units of percent of instrurrent span.

Underfrequency Reactor Trip

( Alternate Calculation)

TA 4.4 2 0.0 S 0.0 -

Naninal Trip Setpoint 57.2 Hz Allowable Value 57.06 Hz

TU ELECTRIC REACTOR ENGINEERING CALChi.aTION SHEET Subject tNAJF Reactor Trip Setroints Calo. No. RXE-TA-CP1/0-027 Rev._L.

Sheet A1.1 Originator Date Reviewer Date AITIONDil' 1 SWDC Letter SWW-0207 dated July 27, 1988

~ . ~. . .- - . - _ - - _-- - . __ ._- _ __

l syG-p-ch/c ~d7/bvL 1 ,

h i

• . - .-.. - .~

l 1, s .s, l

4 Copy to:

JLyota-Westinghouse (ene)

C 00150207 .

l , CVLowe-TU/107 (coc)

RCamp.W/C07

TTylar-TU/C07

TJ office-145/7

, . AJut2=TU'806 1 LYseger I'J/ Elf 03tomer,treet TV DRaynerson-TU/E14

! CGCreamer-TU/E09 (ens)

5.*0taynes-TV/E09 i > CGLovett-Westinghouse (ene)

V

~

! Mr. J. L. Vota. Project Massger

! Vestinghouse Nuclear Energy Systems July 27, 1933

! . P.O. Bos 355 J.0.No. 18051 i

I Pittsburgn, PA 15230 SW- 0207 No Response Aetstred

! STATISTICAL SETPOINT STUDT INFORMATION REQUEST CCMANCHE PEAK STIAM ELECTRIC STATICN - UNIT 1 TJ ELECTitIC l Westinghouse Electric Corporation (VEC) Letter WPT=9570, dated January 12, l . 1988, requested statistical setpoint study information for various.

l instrument channels. The majer concerns were to verify that the original

! traosaitters shipped were installed and to identify any uncertainties associated with the perfomance of calorimetrics (flow and power) and the i accuracies associated with the equipment used to calibrate the tranaattters and racks, f .

l Ston T Webster Engineering Corporation (SVEC) has identified the tag nos, i , associated wtth tue inst ruisent channels from Attachment II of WT-9570.

Attacned are the cospisted Instrument Channel Input data sheets for your

! ' use.

l Tor calibrating equipment accuracies a 1 to I ratto (accursey of calibrating i equipsent to accuracy of instrumaat being calibrated) is being used to

calibrata the transmitters and ract sounted cards at the Comanene Peak site.

1 l If you have any questions, please contact Mr. R. L. Poltrino at (617) l 589 889 4

. . Carty i o Pr ject Enginsee r

/

Enclosures MCI:gre i

l ..._,_,~..--..::==_ .L.-. L

(Ly FT4'CYO ~0.11 1 bL

. & n.3 CF5ES Protective Relay Settinga jg, 6.tKV Normal luses 86.19 Underveltale relays and time delay relays for reactor trip.

4.19.1 Undervelta8e relays devices 27-l/ LA1. 27-1/1A2. 27-1/1A3, 27-1/1A4. 27-l/2Al. 27-l/2A2. 27-1/2A3. 27-l/2A4 C.E. Model fl2WCT13AllA.

Lated 120V, 40 Es. dropout range 70 1007 One ein81e phase relay per bue P. T. Ratie 7200/120 settina of Relays Dropeut voltage e 80.3V (80.07V to 46.33V) 4.19.2 Time delav relays, devices 27-lT/LAl . 27-lT/lA2,17-lT/lA3, .

27-lT/lA6. 27 1T/2A1. 27-lT/2A2. 27-lT/2A3. 27-LT/2A4 Syracuse. Model f?T100300. 0.1-1.0 sec., 113 V.A.C.

s. .

g Setties of Relays:

Time settin8 = 0.5 sec. (0.4 see. to 0.6 sec.)

e6.20 Underfrequency relays and *ias delay relays it reactor trip. -

4.20.1 Onderf requency relays, devices 41/1Al. 81/lA2. 81/lA3. 81/lA4 81/2A1. 81/2A2. 81/2A3. 81/2A6

~*

Vestin8 house type KT underfrequency relay. Style 86713287AL7 without time delay.

Rated 120V at 60 M:.

Frequency ran8s SS to $9.1 H Settina of Relays:

Fesquenc7 setting = $7.2 Ha ($7.17 Hs to 58.0 Ht) 4.20.2 Time delay relays, devicae 81T/l A1. 81T/L A2. 81T/l A3. 817/l A1, 81T/2Al. 81T/2A2. 81T/2A3. 817/2A6 Syracuse Medal f?T100300, 0.1-1.0 sec. ILS T.A.C.

Settina of Relays:

Tias settin8 - 0.1 sec. (0.09 sec. to 0.11 sec.)

• sen Tech. Specs. Section 4.3.1.1 and 6.3.1.2 for surveillance

, e,,i . .

i a

h 4-10 Revision 9 emme= h l

~* -

TU ELECTRIC REACTOR ENGINEERING CALCULATION SHEET Subject (N/UF Reactor Trip SGtroints Calc. No. RXE-TA-CP1/0-027 Rev.1 Sheet A2.1 A Originator Date Reviewer Date Attachment 2 Excerpt frca Specification 2323-ES-5 Potent'.al Transforme Metering Accuracy Class e

-f f[ND/k-f itu-ru-cf c -027

/ f.>s .

o*

• ^ '

(Tem. DgTA Sem)

Gibbs & Hill, Inc.

Specification-No. 2323-58-5 "

~~

~*

Revision 1-Sheet 6 of_). _ . . . - -

. DATE 1/13/75 ._

Res NAME OF SELLER ITE Imoerial comoration .

Performance Data (Continued) .

4. Potential Transformers ,

t. Ratio 7200-120V-

b. Type JMV-5 -

~ '

Manufacturer G.E.

c. ._

Insulation Butyl-Molded' d .,

e. Thermal Rating 1000VA with 55 c. ambient

f. Impulse level - full wave , 95KV _

g. racy Class- W,X,Y,Z = 0.3 3 Res

5. Current Transformers .

a. Type _Mc15-Al'& Mcs-21

b. Manufacturer ITE

c. Insulation - Epoxy

d. Mechanical' Limit - Ampores* same as-Lrsaker -

e.- Impulse Level - Full Wave 95xV

f. Accuracy classification see Table sheet'7 -

D 1

9

.e .

, TU ELECTRIC REACTOR ENGINEERING CALCULATION SHEET <,

Subject INATP Reactor Trip Setr;oints Calc. No. RXE-TA-CP1/0-027_ Rev. l__

sheet A3.1 Originator Date Reviewer Date ,

Attachment 3 Excerpt frcm ANSI /IEEE 57.13 - 1978 Voltage Transformer Metering Accuracy Class 3

.~- - - -- - - _ _ _ _ _ _ _ _ _ _ _ _ - - - . _ _ l

_ ~ _ _ _ - _ _ _ _ _ _ _ ___ _ ____ ____

ID:8178970963 --- JAN 1M92 10:5S J Wo9 LOS w ousemasse-(A7,g3197>

• - ANutIOtetAstfi Table e dyg -g c///p.02.7 j

Standard Aeoarsay Class for h/

i Motauu flervios and Corroepending Limita of /)y d I

• Transformer Cerroetion Factor j

(0.0 to 1.0 Percent Power Factor of Metered Lpad. l.ug# ring

- - . . - * . .::. s. . ... . .

}

Vehage Tronareroses Current Tranedermere l ( At 90 ta 480 Percent

[

klated Veitseek At 100 Perevet Kated Current

• At 60 Pete.at Kates Onierent Maaneg Aecasacy i

M uwsmrio Menneem Minimum Mournum Minimum Math n j clam 0.997 1.003 0 991 IM n tSt ( 1or f

c1 n.98a 1.011 0.004 1.006 0.004 1. Quin 0.4 l a sse t.011 0.94n 1.U13 U itte 1 034

1.2

~-- - 1 . , :.:. ,. u: -

{ .ree rue,,eg trenewiners tne nuo pem,4 rama current hinet slas evoore et irw ruirers entremoisneens in the renamuses saiarme6.

l I tunens esims isctar.

?

l 5.3 Standard Accuracy Cluace. Stnndard ni Fn quencs n.n fin Ill lla:..rt pr onarv ..nti r...nnair rueresuh occuracy ciniuuen hmna ni transintmer enrrecuini factar in standarri acrutary rinc.au unall lir as ( l nhits u and (na shown in Table ti. iM Accurnev s law- at standard burnen.

[ ' f"bleh 6 "nd i t , unner 'Cl and ti.4 4 I

S.4 I.imiting Values of flatio Correction Factor and Phase Angle for Standard Ac. ('O C'""'nunn..thermai.curreni rauni: fartnr l

curacy Classes. The limitina vnauen of IlCF hased e 30*C andnunt mr Irmiwrnture tus H.fd

0) Short tune meciumican current raune and must Do the name as those for TCF (see 5.21. Far snart. time thermal current rating (are n.0) any known value of f(CF for a stvco trenatormer the limitio valueel of ansie derived from tne en. 0.2 Standard llurdene..Standant hurdens for preenien in 8.2) are given hy: current tronsformers wah fi A ratcti necendary (1) For voltage transformven. current snall imvu remtance and inductance nr.

7., 2000 (TCF-1(CF) curdms: h 'r.dds. I1 (2) For current trar.sformera. u.3 Asatunment of Accuracy llatinga inr 11 2000 (if CF. 7'CF) Metering Serview 0.3.1 A current trnntinemer (nr metteme ser in witich TCFim taken as the maximum and mm. s or whau he gn t n nn At ni.n > raung for cuch smum values given m Table G for the speettied nr.

curacyclann.

siandortl hmdun (nr u mth a i. drwoed for es.

'""l"e. the un uracy rmm- n=enns tn a rurrent These reinucas are convemenuy uiown urnph.

ically in Fig 2 for r.urrent anti in Fo: a Int voitnre """d "'"" """ ' I "' " d * " i '""I SU L U E IbO 'A transformers. G.3.2 Tapin ri Ser'anniurv nr Alniciple,liasm

(*urrent Trnnsfurerser Arn;urm s Itnistic The

"'eter'na necurney raung unphn, un iho fun wenn.

6. Current Transforrners dary wimhne, uniema ntherwise upcettied.

0.1 Terms in Whleh Ratings Shall be lix. H.4 Accuracy Claesos for Relaying. A cut.

pressed. The ratmg of a current tranMormer rent trnnsintmer lor rulaying nervice shall he giv.

' ahall include:

- en an arruracy ruung neenromar to 14A.1. t (1) Ilasic impulso inzulauon level in turma nf g,4,g jg,,g, fg, ggeluy,nc An umev Clown. A full wave tant voltage (see Tablen 1 and H) retuyiru. norurm y rinsa amdi he deinmiteid by twis (2) Nominal system voltage, or maximum myn. nymbnin that citeruvely duncr ho the steudy state tem voltage (ace Tabitz 7 ant! 8) perin,mutwe na fullnwn: '

~

s 1%e in snee of reem =d.m u.e re w at oic cen, ore t i) "f ' ' nr '"/"* Clauilit.ntion U classirivnimn

. moetense ocewecr etainen, roverm current tennatormt ru in which the lenkage l

If) h

..f **k*