Text

Rev 0 to Loop Error,Setpoint & Time Response Analysis for Narrow-Range Containment Bldg Pressure ESFAS & RPS Trip Functions
	ML20105B877
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/08/1992
From:	Greene W, Shamro H; ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	;
Shared Package
ML20105B870	List: 2CAN099207, Forwards Addl Info Re Instrument Error Calculations for Containment Bldg & Pressurizer Pressure Transmitters. Calculations 91-EQ-2002-02,Rev 0 & 92-EQ-0002-01,Rev 0(2) Encl.Info Submitted to Support 920709 TS Change Request; ML20105B877; ML20105B891;
References
	92-EQ-2002-02, 92-EQ-2002-02-R00, 92-EQ-2002-2, 92-EQ-2002-2-R, NUDOCS 9209210261
	Download: ML20105B877 (38)
	v • d • e

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Calculation No. 91-EQ.2002-02 Rev. O Page 1 of 36 TAllLE OF CONTENTS Section Title Page 1.0 PURPOSE / SCOPE.................

2 2.0 I NTR O D UCTI O N...............................

3 3.0 ASSUMPTIONS AND GIVEN CONDITIONS.......

4 4,0 P PS F U N CTI O N S...........................................

7 4.1 CONTAINM ENT PRESSURE...................

7 CONTAINMENT PRESSURE BLOCK DIAGRAMS.............

9;12

5.0 CONCLUSION

S..........

32

6.0 REFERENCES

34 h

EE<e Date: f+'il Checked by: M Y#mro Date: YlNL Prepared by:

Calculation No. 91-EO-2002-02 Res. O Page 2 of 36 1.0 PUl(POSE / SCOPE 1.1 PURPOSE The purpose of this calculation is to determine the uncertainties, setpoints, allowable values, and time responses of the ANO-2 Narrow Range Containment 13uilding Pressure ESFAS and RPS Trip instrumentation loops. This calculation supercedes the Containment Pressure portions of all previous ABB/CE setpoint calculations.

1.2 SCOPE This calculation is applicable to the following instrument loops:

Unit Instrument l oop No.

Service 2

2PT-5601-1 Containment Pressure 2

2PT-5602-2 Containment Pressure

~

2 21'l'-5603-3 Containment Pressure 2

2PT-5604-4 Containment Pressure Instrument loop uncertainties are calculated for the Reference Condition.

Abnormal Condition and Accident Condition.

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.dk Prepared by: O L 6d'e Date:_

Checked by: M E SMwe Date: M8AZ N ~'R

Calculation No. 91 EO 2002 02 Rev. O Page 3 of 36 2.0 INTitODUCI'lON The statistical method of the Square Root of the Sum of Squares (SRSS)is used to determine the random error on a component level and for the loop. Non-random errors are combined algebraically with the random error term to establish total error.

This calculation is done in accordance with the guidelines set forth in the instrument Loop Error Analysis and Setpoint Methodology Manual (Reference 6.2).

All percentages are expressed in terms of span unless otherwise noted.

All terms are considered random error terms unless noted by a lowercase "if suffix to indicate a bias error term, or "t" suffix to indicate the total of the bias and random error terms.

'32'L.

fff Prepared by: 0 L N(-t Date: F E Nhecked by: O Jhpra Date: SANZ

Calculation No. 91-EO-2002 02 Rev. O Page 4 of 36 3.0 ASSUMPTIONS AND GIVEN CONDITIONS 3.1

.C_alibration and Testing Environment The uncertainties provided are based on calibrating and testing the equipment under the following environmental conditions:

A.

Control Room The calibration temperature for PPS Equipment in the control room is assumed to be 75 deg F and the maximum operating temperature for PPS Equipment in the control room is assumed to be 84 deg F. All other conditions " normal" for a control room environment, per Reference 6.2.

H.

Containment The calibration temperature of the PPS Equipment inside containment is assumed to be 60 deg F and the maximum operating temperature of PPS Equipment inside containment is assumed to be 120 deg F. All other conditions " normal" for a containment environment, per Reference 6.2.

C.

Outside Containment The calibration temperature is assumed to be 60 F. This is a conservative temperature to envelope the expected amt>ient at the time of calibration. See Reference 6.2.

3.2 Calibration and Testingjiquipment The measurement and test equipment (M&TE) used to calibrate and test the PPS Equipment will have an accuracy twice as good as the accuracy of the

@ ^L inf Prepared by: "4d'**

Date:54 4' Checked by: N' E 84wd Date: J//[92

Calculat on No. 91 EO-2002-02 Rev. O Page 5 of 36 -

i device or loop being tested. For example: if a transmitter has a reference accuracy of + /- 1.0 % span, it's assumed M&TE uncertainty will be-

+/- 0.5 % of span. This assumed M&TE accuracy applies to all PPS Equipment unless otherwise specified. See Reference 6.2.

3.3 Calibration and Testing Interval A.

The PPS Cabinet (Bistable) will be calibrated and tested on an interval that does not exceed 39 days.

B.

The process instrumentation will be calibrated on an interval that does not exceed 22.5 months.

ANO 2 Technical Specifications, Section 4.0.2, permits a 25% extension of the monthly (31 days) and refueling (18 months) calibration intervals.

3A Power Sttpply Variation Unless specifically stated otherwise, the variation of the instrument power system is 120 i 10 VAC and the maximum power-supply variation is i 10%

of the nominal power supply. See Section 3.9.7 of Reference 6.2.

3.5 Deleted.

3.6 Seismic and Post-Seismic Errors Seismic and post-seismic errors are not considered with any design basis events because ANO-2 will, after each seismic event, determine that the post-seismic error are negligible or will recalibrate all effected PPS equipment, per Reference 6.28.

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Prepared by: R L Gee-e-Date: S H2-Checked by: M 6 6Adm/V Date: o#ff

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Calculation No. 91-EO 2002-02 Rev. O Page 6 of 36 3.7

.Sjgnal ('onverter Drift Unless otherwise stated, the drift for the signal converters is assumed to be no worse than its reference accuracy per Reference 6.27. The line voltage effect is assumed to be + /- 0.1% span, for a 10% change in line voltage since no vendor information is available per Reference 6.2.

3.8 Transmitter Background Radiation Effect Unless otherwise stated, the background radiation effect for the transmitters is assumed negligmle because the effect of background radiation is calibrated out each refueling, per Reference 6.2.

3.9 That combination of instrument uncertainties from various sources by the root-sum-square method is realistic and conservative enough when these uncertainties are random and independent of each other.

3.10 That combination of instrument uncertainties from various sources by algebraic summation is the most conservative method whenever the errors are non-random.

3.11 The calit> ration uncertainties for process instrumentation assumes that there are separate calibration devices on the input and output of the instrument being calibrated, per Reference 6.2.

3.12 Error terms that are less than 0.05% of SPAN are considered negligible and are not included in the calculation per Reference 6.2.

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i/[92' Prepared by: 62 L G '"s Date: U '

Checked by: M A / Marc Date:

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Calculation No. 91-EO-2002-02 Rev. O Page 7 of 36 4.0 PPS FUNCTIONS The PPS functions included in this calculation, per agreement with ANO-2, are the Containment Pressure - 111G11 and lilGil lilGH functions. The functional requirements of these PPS trips are given below.

4.1 CONTAINMENT PRESSURE 4.1.1 Functional Description The containment pressure function of the Plant Protection System (PPS) provides a reactor trip, a containment isolation actuation signal (CIAS), a containment cooling actuation signal (CCAS) and a safety injection actuation signal (SlAS) on a liigh Containment Pressure trip. Also, the containment pressure function provides a containment spray actuation signal (CSAS) on a Iligh-Iligh Containment Pressure trip. The reactor trip, the CIAS and SIAS, and the CSAS are initiated by separate bistables. See Figures 4.1 - 4.4. The CSAS cannot be initiated without a cancurrent CIAS or SIAS.

The containment pressure transmitter is calibrated from 0 to 27 psia and outputs at 4 to 20 mA signal. A 250 ohm droppi-resistor provides a 1 to 5 volt signal to the histables. It should be noted that the signal represents absolute pressure and not gage pressure.

4.1.2 Design liasis and Requiremlnn The purpose of the containment pressure function is to protect the containment vessel integrity and minimize the radioactive release during a postulated accident.

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[h Date: N #12 Checked by: NE bmro Date: 5'/MM Prepared by: UL-mo

Calculation No. 91 EO 2002 02 llev. O Page 8 of 36 The reactor trip function is not credited as the primary trip for any Chapter 15 event. It is however considered the back-up trip for many of the events. The reactor trip can be credited with limiting the temperature and pressure which the containment will reach prior to reactor trip. This function is often used to reduce the accident temperature errors prior to reactor trip for all PPS equipment which serve the same function as the high containment pressure.

The containment isolation function is credited in the SAll Chapter 6.0 Analysis.

The Chapter 6.0 Analysis determines the peak containment pressures and temperatures following a primary or secondary pipe break. Therefore, the CIAS analysis setpoint cannot be changed without determining the effect of tids change on the Chapter 6.0 Analysis. The CIAS setpoint must be sufficiently larger than the ambient pressure to prevent initiation due only to instrument errors and normal pressure variations.

The safety injection and containment cooling functions are credited in the SAll Chapter 15.01.OCA analyses with limiting the consequences of the LOCA events.

The containment spray function is credited with reducing the temperature, pressure and radioactivity level of the containment environment followi"g a primary or secondary pipe break. The containment spray contains chemicals to reduce the radioactivity level inside the containment and therefore reduce the amount of radioactivity released to the environment. The effect of the chemicals and the consequences of the clean up of the additional water in the containment are such that the 111G11-111G11 Containment Pressure trip setpoint should be sufficiently greater than ambient pressure to ensure that spray is initiated only during actual pipe breaks. The CSAS analysis setpoint is determined by the Salt Chapter 6.0 Contaimnent Analysis. Therefore, the analysis setpoint cannot be changed without determining the effect of this change on the Chapter 6.0 Analysis.

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Chiculation No. 91-EO-2002-02 Rev. O Page 9 of 36 FIGURE 4.1 i

CONTAINMENT PRESSURE BLOCK DIAGRAM CHANNEL A ce v'on ci sui.

RPS

-l su t

- Tne output HIGH aso n bi.',

= Z,,*

CONTAINMENT

l. sui NTn* c.'Anu a

outroT PRESSURE 2c,3,.c.,,

ca 10A E 55%

sur.

MM h JLJ EU2ot

- NN M ARM

' see SU2 PRESSURE 0

ourevT 1 63 tuna

_ r.4 n2.

scas a-oc ais

9 8Ca CONTAINMENT Tnx.

DUILDING 7px SC

_4Q n3.

S.l'u"v'on 2

sc.

PRESSURE m

v***

ESFAS wi =i

wi s.oi-u sua.

HIGH HIGH SU 3 CONTAINMENT ensTnsp atAnu

.su3 u

PRESSURE oufruv ac22a se,,,

3 r

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Calculation No. 91-EO-2002-02 Rev. O Page 10 of 36 i

FIGURE 4.2 CONTAINMENT PRESSURE BLOCK DIAGRAM CHANNEL B a

Ion e

RPS

- TW OuTPur F

HIGH C'.} ni.

SUI CONTAINMENT N.

PMir'r Atanu

. sus m Put PRESSURE na2 e.c e n c

ES AS itb t-oeur go EU$',

PRIMP ALARM YU2YE

' /d"

. sus ouTPur PRESSURE R2.

xu o sc ais CONTAINMENT BufwtNG THX SC fo, n3.

c PRESSURE

,,e

a' ESFAS 8" wa-*

n s.ca sa so).

HIGH HIGH SU 3 CONTAINMENT Mi ratTate ALAnu

. sus e Pur PRESSURE scu s aceu 4

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Calculation No. 91-110-2002-02 Rev. O Page 11 of 36 i

FIGURE 43 CONTAINMENT PRiiSSURI? HLOCK DIAGRAM CHANNEL C c2 (paean spa

'~

sut.

SPS

,,",, '",,, CONT AINMENT tilGil 2" ^

susa n i, SU 1 sut.

sui suia PRESSUHE ouwur 2C33C SC Ci3 ce C

akafon ESFAS sua.

HIGH suam '

su 2 CONTAINMENT sua.

N* ^(*""

PRESSURE

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E CONTAINMENT BullDING TRX SC

- i ant e

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k Calculation No. 91-l?Q-2002-02 Rev. 0 l' age 12 of 36 FIGURE 4.4 CONTAINMENT I'RESSURE BLOCK DIAGRAM CHANNEL D G

N.10n Q g ni.

"VT sui i CONTAINMENT

Parwr MAm

. sui e i.,

PRESSURE currut

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a Comer iose 2 440 ESFAS su2.

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nosi um.=as

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ian PRESSURE ESFAS suu m **a. 4 arv a.u T

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13'of 36-

. Calculation No. 91-EO-2002-02, Rev. 0 1

i 1

4.1.3 Containment Pressure Loop Error Calcu!ation 4.1.3.1 COMPONENT ID Source

[

Containment Pressure Transmitter '

Tag Number:

2 PT-5601 -1,2 PT-5602-2,2PT-5603-3,2PT-5604 -4 (6.22. 6.1.b.6.1.g)

Model:

Rosemount 1153AD5RB (6.22.6.1.f)

[

Range Limits:

0 to-'

27.0975 PS!A (0-750 inches of water, URL = 27.0975)

(6.3)

Cabbrated Range:

0 to 27 PSIA (6.22)

Calibrated Span:

27 PSt (6.22)

Time Response:

0.2 sec (6.3) l I

PROCESS / ENVIRONMENTAL CONDITIONS I

' Amb Cat Temp (AMB):

60 degF (3.1.b)

Abn AmbTemp(ABN):

120 degF (3.1.b) f Acc Amb Temp (ACC):

288 degF (6.25) i I

DT (ABN-AMB):

60 degF f

Power Supply Voltage:

24 VDC (6.7)

Power Supply Variance:

10.0%.

(3.4) i (DV) i 2.4 VDC f

Max Voltage :

26.4 VDC Calibration interval ':

22.5 MONTHS (18 months + 25% marigin)

(3.3) 3.3E+07 RAD (6.25) f Acc Radiation i

ERROR

SUMMARY

ERROR ERROR

[

% SPAN PSIA j

a. ACCURACY (RA):

, f(

0.25% SPAN) i 0.250 %

0.068 (6.3)

b..CAllBRATION (CAL):

( TIMES MORE ACCURATE THAN INSTRUMENT) i{ (0.5RA)^2+(0.5RA)^2]^0.5

% SPAN 0.177 %

0.048

- (3.2.,3.11)

I r

c. DRIFT (DR):

1(

0.20% URL FOR 30 MONTHS) 0.201 %

0.054 (6.4).

t

d. POWER SUPPLY EFFECT (PS):

(Less than 0.005% SPAN /voit) (NEGLIGIBLE) 0.000 %

0.000 (6.3)

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14 of 36 Calculation No. 91-EO-2002-02., Rev. O r

Source i

ERROR ERROR

'f

. % SPAN PSIA j

e. ABNORMALTEMPERATURE EFFECT(TE):

. i(

0.75% URL +

0.50% SPAN) per 100 degF 0.752 %

0.203 (6.3) calculated at 60 degF

' f. ACCIDENT TEMPERATURE EFFECT(ATE):

TESTED AT 420 degF (6.3) l f(

4.50% URL +

3.50% SPAN) 8.016 %

2.164 L

g. ACCIDENT RADIATION EFFECT(ARE):

TESTED AT 5.50E+07 rads TID i(

1.50% URL +

1.00% SPAN) 2.505 %

0676 (6.3) j The transmitter error (eTRX) for Reference (REF), Abnormal (ABN) and Accident (ACC) conditions is given as folfows:

(3.6) 0.427 % 1 0.115 REF eTRX =

i (RA + CAL)

ABN eTre 1 ((RA + CAL)*2 + DR*2 + TE'2)'0.5 1

0.887 % i 0.240 8.412 %

2.271 ACC (LOCA) eTRX =

i ((RA + CAL)*2 + DR"2 + ATE'2 + ARE^2)0.5 ACC (SLB) eTRX =

i ((RA + CAL)'2 + DR*2 + ATE'2)*0.5 i

8.030 %

2.168 f

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. Calculation No. 91-EO-2002-02, Rev. 0 1

' The transmitter output error (TRXo) for Reference (REF), Abnormal (ABN) and Accident (ACO) conditions is given as fo!!ows:

Source ERROR ERROR

% SPAN PS!A t

REF T'RXo '=

. i REF eTRX i

0.427 % i 0.115 i

ABN TRXo =

i ABN eTRX i

0.887 %

0.240 t

J

- ACC (LOCA) TRXo =

i ACC (LOCA) eTRX i

8.412 %

2.271 ACC (SLB) TRXo =

ACC (SLB) eTRX 8.030 %

2.168 l

l Source 4.1.3.2 Insulation Resistance i

The transmitter is located within the containment building, and as such the effects of harsh enviroment on the loop signal cabling must be considered. The accident environment effects are considered for cabling from the transmitter through the CJntainment electrical penetrations.

ERROR ERROR

% SPAN PSIA Cabte Length:

200 Ft (6.14) a Power Supply Voltage:

24 VDC (6.7)'

+

0.990% +

0.267 (6.11)

IRb:

+

0.99% SPAN The error attributed by the insulation resistance (iRb) for LOCA and SLB Accident (ACC) condition.

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17 of 36-i

' Catcuration No. 91-EO-2002-02, Rev. 0 The converter error (ESC) is as fo!!ows:-

ERROR ERROR Source

% SPAN PSIA REF ESC =

i (RA + CAL) 0.904 % 1 0.244 ABN ESC =

i ((RA + CAL)^2 + DR^2 + TE*2 + LV-2)'0.5 1.391 % i 0.376 ACC ESC =

((RA + C AL)^2 + DR-2 + TE'2 + LV"2)"0.5 1,391 %

0.376 The output error term for the signal converter (SC)is given as forfows:

0.999 %

0.270 REF SCo =

(TRXo 2 + ESC'2)"0.5 1.650 %

0.446 ABN SCo =

i (TRXo'2 + ESC"2)"0.5 8.526 %

2.302 ACC (LOCA) SCo =

(TRXo(LOCA)^2 + ESC *2)"0.5

+

0.990% +

0.267 ACC (LOCA) SCob =

IRb 9.516% +

2.569

+

ACC (LOCA) Scot =

+ SCo + SCob

- SCO 8.526 % -

2.302 ACC (SLB) SCo =

(TRXc(SLB)'2 + ESC'2)^0.5 i

8.150 %

2.200

+

0.990% +

0.267 ACC (SLB) SCob =

IRb

+

9.140% +

2.468

+ SCo + SCob ACC (SLB) Scot =

- SCo 3.150 % -

2.200 I

h Preparer: NN Date: ff/92. Checker:

Date: [Mf5

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21 of 36 Calculation No. 91-EO-2002-02,' Rev. 0 The output error terrn for the iesistor (R3) atter the signal converter is given as follows:

ERROR ERROR'

% SPAN PSIA i (SCo'2 + eR*2)'0.5 1.004 %

0.271 REF R30 = '

I ABN R3o =

(SCo'2 + eR'2)*0.5 i

1.653 %

0.446

' ACC (LOCA) R30 =

i (SCo(LOCA)'2 + eR'2) 0.5 8.527 %

2.302 i

ACC (LOCA) R3ob =

+ SCob

+

0.990% +

0.267 ACC (LOCA) R30t =

+ R30 + R3ob

+

9.517% +

2.570

- R30 8.527 % -

2.302 l

ACC (SLB) R3o =

.i (SCo(SLB)'2 + eR*2)'0.5 8.150 %

2.201 4

ACC (SLB) R30b =

+ SCob

+

0.990% +

0.267 ACC (SLB) R30t =

+ R30 + R3ob

+

9M4C% +

2.468 e

- R30 S.150 % -

2.201 l

1 5

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28 of 36 Catcu!ation No. 91-EO-2002-02, Rev. 0 t

i 4

To ensure that the reactor is tripped concurrently with to SIAS:

I i

j f

RPS Trip Setpoint f

SU1 (H ) Trip Setmint

=

I 18.3 psia i

=

5 SIAS/CIAS Setpoint SU2 (Hi) Actuation Seipoint

=

18.3 psia

=

i i

Therefore, the setpo;nts are established as foricws:

RPS Trip Setpoint SU1 (Hi) Trip Setpoint

=

18.3 psia

=

i SfASICIAS Setpoint i

SU2 (Hi) Actuation Setpoint '

=

18.3 psia

=

J CSAS Setpoint i

SU3 (Hi-Hi) Actuation Setpoint

=

23.3 psia

=

i l

4.1.4.2 A!!owabte Values r

s s

J SU1 Setpoint + SU1 PTE i

SU1 Attowabte Value

=

18.3 psia +

0.19 psi

=

I 18.49 psia

=

i' SU2 Setpoint + SU2 PTE SU2 Allowable Value

=

18.3 psia +

0.19 psi j

=

l 18.49 psa

=

4 SU3 Setpoint + SU3 PTE SU3 Allowable Value

=

f 23.3 psia +

0.19 psi

=

23.49 psia

=

)

i Y

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31 of 36

. Catculation No. 91-EO-2002-02 Rev. O i

4 4.1.6 Measurement Channel Response Times Source The RPS Channel Delay Tims is the time interval from when the monitored parameter exceeds the trip se point value at the inout to the channel sensor until electrical power is interrupted to the CEA Drive Mechanism.

i The ESF Channel Delay Time is the time interval from when the monitored parameter exceeds the trip j

setpoint value at the input to the channel sensor until the output of the actuation relays in the ESF cabinet changes state.

j The ESF response time provided does not include the actuated components (e.g. pumps, va;ves, etc.).

l See ANO-2 Technical Specification Tables 3.3-2 and 3.3-5.

SU1 SU2 SU3 l

Rosemount Transmitter:

0.20 sec.

Foxboro !!! Converter; n/a sec.

0.30 sec.

PPS Cabinet (Bistable):

[

0.15 sec.

Reactor Trip Switch Gear :

O.10 sec.

n/a sec.

(6.29)

ESFAS Relay Cabinet Delay Time :

n/a sec.

0.02 sec.

(6.29)

Total Channel Response Time:

0A5 sec.

0.67 sec.

The expected RPS Channel Delay Time for SU1 is ess than the 1.59 second response tirne of ANO-2 Technical Specif%ation Table 3.3-2.

The expected STAS /CCAS/CfAS Channel Detay Time for SU2 is not significant compared to the 28.1 second response time (including sequence loading delays) of ANO-2 Techr.ical opecification Table 3.3-5.

The expected CSAS Channel Delay Time for SU3 is not significant compared to the 27.1 second response time (including sequence loading delays) of ANO-2 Technical Specification Table 3.3-5.

j

)

Preparer: M

bWDate:I'

' Checker:/

_ Date:

8 2-

,w s

Calculation No. 91 l!O-2002-02 Rev. O l' age 32 of 36 5.C CONCLUSIONS a

The loop orrors for instrument loop nurnbers 2PT-5001-1,2PT-5002-2,2PT-6003-3 and PT-5604-4 at0:

% SPAN psia REF SU1o n i

1.035 %

1 0.279 i

ABN SU101 =

+

1.358 %

4 0.367 0.350 1.320 %

ACC (LOC A) SU10t u

+

9.490 %

+

2.564 2.280 8.408 %

ACC (SLO) SU101 =

4 9.117 %

+

2.402

~

8.089 %

2.184 REF SU2o a i

1.374 %

1 0.371 ADN SU20t =

+

1.950 %

4 0.528 1.918 %

0.518 i

ACC (LOC A) SU20t =

+

0.010 %

+

2.595 2.317 8.582 %

ACC (SLB) SU201 =

+

9.230 %

4 2.494 1

2.216 8.208 %

REF SU30 =

1 1.374 %

i 0.371 ABN SU301 =

+

1.956 %

+

0.528 0.518 1.918 %

+

9.010 %

+

2.595 ACC (LOCA) SU3o1 =

8.582 %

2.317 t

+

9.236 %

+

2.494 ACC (SLB) SU30t =

2.216

.8.208 %

I

.'jR

[

.Prepaten kl4f t-5 Dato: 5-0 @ Checkert/IN __ Date:__6 S f L

. a -

~...

Calculation No. 91-l?O.2002-02 Rev. O Page 33 of 36 2

The setpoints for those instrutnent loops are:

psia volts SU1 18.3 3.711 P

SU2 18.3 3.711 SU3 23.3 4,451

.1 The allowablo values for theso instrument loops are:

psia volts i

SUI 18.49 3.518 l'

SU2 18.49 3.518 SU3 23.49 3.962 The protrip setpoints for theso instrument loops are:

psia volts SUI 17.0 3.518 SU2 17.0 3,518 I

SU3 20.0 3.962 The response times for those instrument loops at0:

Sul 0.45 sec SU2 0.67 sec SU3 0.67 sec b

J r

GOL M L N* <- c Date: I~I~'ll Checker:

Date: YFf3_ _

Preparcr:

{

Calculation No. 91 EO 2002-02 Rev. O Page 34 of 36 4

6.0 REFERENCES

6.1 Letter to P. Collette from A. J. Wrape 111 (ENTERGY), ANO-912-00919, November 12,1991.

a)

Schematic Block Diagrams E-2205 Sh. 2, Rev. 3 b)

Schematie E 2753 Sh. 22 Rev.10, E-2753 Sh. 29, Rev.10 e)

Internal Connection 2C15: 6600 2-M2001-M1-48, Rev.13 6600 2 M2001 M1-50, Rev.16 6600-2-M2001 M1-52, Rev.12 6600-2-M2001-M1-54, Rev.13 6600-2-M2001-M155, Rev.12 6600-2-M2001-M156, Rev.12 6600-2-M2001-M158, Rev.13 6600-2 M2001 M159, Rev.12 d)

External Connections: E 2951 Sh.1, Rev.13 E 2951 Sh. 4, Rev.13 E-2951 Sh. 7, Rev. 9 E-2951 Sh. 9, Rev.10 E-2693 Sh. 9, Rev. 2 E-2693 Sh.10, Rev. 2 E-2693 Sh.11, Rev. 2 E-2693 Sh.12, Rev. 2 e)

Fig. 8-1 Sh. 2 (CE PPS Vol.11 TM C490.0850 Vol. 2 of 3) f)

SIMS Component List g)

P&lD M-2236 Sh 2, Rev. 9 h)

Instiument Data sheets M 2516 Sh. 5, Rev. 4 6.2 Instrument Imop Error Analysis and Setpoint Methodology Manual, Design Guide IDG 0010.

6.3 Rosemount Product Data Sheet 2388, Model 1153, Series D Alphaline Pressure Transmitter for Nuclear Senice, Revised 11/87.

(Vendor Manual TM R370.0010, TD R370.0150 Rev. 2; Installation Manual for Nuclear Service Model 1153 Series D Alphaline".)

6.4 Rosemount Report DS900126, Rev A,"30 Month Stability Specification for Rosemount Model 1152,1153 and 1154 Pressure Transmitters."

(Vendor EO File V43 liem 134) 6.5 Rosemount Oualification Report D8300040,"1153 Series D Rosemount Pressure Transmitters For Nuclear Service." (Vendor EO File V43 Item 90 (Rev. A),

l ltem 131 (Rev. C))

Stk Prepared by: WAN N Date: WR Checked by: - /N Date: 6/&IE

,--_n

.,.n..,,,..---,-

+w.n--

.,,,.,n..-,,.

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

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

Calculation No. 91 EO.2002 02 Rev. O Page 35 of 36 i

6.6 Foxboro General Specification GS2A 2DI A, Dec 1968.

(Vendor Manual TM F18.0970, TD F180.4.9.30 Rev. 0; " Instruction Book 2008 for Foxboro Current Repeater Model 6613")

6.7 I&C Periodic Test Procedure 23N.041, Rev.13, Plant Protection System Channel A Field Calibration.

I&C Periodie Test Procedure 2304.042, Rev.13, Plant Protection System Channel B Field Calibration.

I&C Periodic Test Procedure 2304.043, Rev.14, Plant Protection System Channel C Field Calibration.

I&C Periodic Test Procedure 2304.044, Rev.14, Plant Protection System Channel D Field Calibration.

6.8 Foxboro Diagram 660-M2204A-153, Rev.4 6.9 Rangedown Effect on Model 1153 Series 11 and D transmitters, RMT Report 108221, Rev. A.

6.10 Type Test Report for Pressure Transmitter Rosemount Models 1153 Series Il and D Output Code "R", RMT Report D8300131, Rev. A.

(Vendor EO File V43, item 57) 6.11 Calculation No. 86EQ.0001-05, Rev._01; Generic IR Errors 6.12 Control of Cale"lations, Procedure 5010.015, Rev. G.

6.13 Telecon from D. McQuade (A1111/CE) to W. Cottingham (ENTERGY) 11/27/91,3:00PM "PPS Loop Uncertainty /Setpoint Calculations" TIC-92-299.

6.14 Telecon from D. McQuade (AllB/CE) to M. Zuber (ENTERGY) 12/3/91, 2:20PM "PPS Loop Uncertainty /Setpoint Calculations incontainment Cable Lengths". TIC-91-1795.

6.15 Letter to C. II. Neuschaefer from R. Ilaker,3/17/77,1D 77-125, "PPS Equipment Uncertainty Errors and Time Delays for AP&L, LP&l, SCE 2,3."

6.16

" General Engineering Specification for a Plant Protection System", Specification No. 0000-lCE-3001, Rev. 03, May 13,1976.

6.17-Telecon from Pete llung to W. Cottingham,3/6/92,10:15, "ANO 2 PPS Loop.

Uncertainty /Setpoint Calculation", TIC-92 053.

r 2 02.

Prepared by: "L Gd **

Date: FE 'R Checked by: #8 Date: 58/fE 4

i Calculation No. 91 IIO 2002 02 Rev. O Page 36 of 36 6.18 "ANO 2 Miscellaneous PPS Uncertainty Information", TIC-92-068, April 6, 1992.

6.19 R. C. Thomas, " Data Transmittal for ANO-2 (511920)", Memo A PSA 067, to P. P. Slowik, dated 5/19/77.

6.20 Rosemount Product Data Sheet 2631, Model 1154 Series II Alphaline Nuclear Pressure Transmitters, Revised 4/89.

(Vendor Manual TM 11370.0010, TD R370.0300 Rev.1; " Instruction Manual for Rosemount Alphaline Pressure Transmitter Model 1154 Series 11")

6.21 Fischer & Porter Specification 50l?K1000, File: Section 49.

6.22 1.etter to P. Collette (Allll/Cli) from A. J. Wrape (ANO) dated 2/13/92, ANO 92-00370.

6.23 General Resistance, Inc "liconistor Types 81316/81?24" 1982.

6.24 NP#71, Rev. 4, Environmental Qualification Program Manual.

6.25 System Component Evaluation Worksheet #2A074 - 2A077, Rev.1.

6.26 I&C Periodic Fest Procedure 2304.089 Rev. 0; Plant Protection System Channel A Calibration.

I&C Periodic Test Procedure 2304.090 Rev. 0; Plant Protection System Channel 11 Calibration.

I&C Periodic Test Procedure 2304.091 Rev. 0; Plant Protection System Channel C Calibration.

I&C Periodic Test Procedure 2304.092 Rev,0: Plant Protection System Channel D Calibration.

6.27 Letter to P. Collette (AHil/CII) from A. J. Wrape (ANO) dated 11/20/91, ANO-91-2-00930, 6.28-ANO-2 Plant Protection System Methodology Review, 92-12 2014 01, Rev. O.

l 6.29 J. C. Winslow,

Response Times of the ESFAS Auxiliary Relay Cabinets end Reactor Trip Switch Gear", Memo ID-77-260, to P. P. Slowik, dated 6/16/77.

ELY 'l Of ~ T Checked by:-[I

_ Date: 8[//fE Prepared by: U - L 6d < s,_, Date:

m.w,,

---w-

--w..%

<%.-w,

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,,,,e...w, w.,,,,,v.,

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_ _ _ ~. _ _ _ _ _ _. _ _ _ _ _ _. _. _. _ _ _ _ _ _ _ _..

bblnchmppt_}

i J

j i

1,oop Error, Setroint, and Time Response Analysis for Low Pressurizer WJde Range pressure FSFAS and RPS Trip Functions l

J i

Since our submittal request Ing thn incronso in nilowable prnssurizer pressure range and lowering thn low pressurizer pressure setpoint for renctor trip, nnfety injectfon, anni containment coollt.n (intter 2CAN079202 dat ed July. 22, 1992) the calculation for the pressurizer pressure innt rumentation has been 3

revised twir Neither revision has affected our regnested values in our Technical Speciffcations change submittal.

Rev 0(D-The main purpose for revision O(1) was to changn the Variable Sotpoint Step lucrement from 400 pS1, which was estahl.ished per the eriginni calculatlon revision 0 in ant icipation of n Technical Specification change revising the step increment vnlun, back to thn existing valun of 200 PSI as.it was decided to pursue this particular change nt a intor date.

A secondary purpose was to add a note clarifying the insulation resistanco (1R) error valun selection as reinted to dif ferences between values cniculated for ench channel.

Rev 0(2J l

The main purposn of revision O(2) was to Incrense the error allowance for component. number 2PY-4624-2C, 2PY-4624-1A, 2PY-4624-2A, 2PY-4624-3A, and 2PY-4624-4A drift (DR) based on a review of pnst as-found/ns-lef t calibration history.

Also, excess conservatisms were removed from the IR orror eniculation.

6 T-w-

pgm-y---way-vrewwg.m,--g^-p g,

wwy-r ypr-wew----wg g ww.yHam-w ees, ewg w. -ymm%n--ms-

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.wg s.q w y s ty-.,ryvyWyy - p im w ginv Tg W wTy'r** = -WW7-wtyT a

ML20105B877

Contents

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5.0 CONCLUSION

6.0 REFERENCES

SUMMARY

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=

=

=

=

=

=

6.0 REFERENCES

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ML20105B877

Text

5.0 CONCLUSION

6.0 REFERENCES

SUMMARY

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=

=

=

=

=

=

6.0 REFERENCES

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