ML20082E871

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Rev a to Setpoints for Power Uprate
ML20082E871
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 03/21/1995
From: Moman J
SOUTHERN COMPANY SERVICES, INC.
To:
Shared Package
ML20082E861 List:
References
SINH-95-003, SINH-95-3, NUDOCS 9504110373
Download: ML20082E871 (7)
v • d • e


Text

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l Design C lculations - Nu:le:r S*,UTHERN COMPANY SERVICES, INC.

i Calculation Number SINH 95-003 l

Project D6scipl6ne E. I. Hatch Nuclear Plant - Unit (s): 01 E3 2 I&C l Objective Job Number  !

Provide Instrument Setpoints for Power Uprate Conditions DCR 94-035/036 l Subject / Title Setpoints for Power Uprate

, Design Engineer's Signature -

g Date Last Page Number

, James D. Moman, Jr. -

/ 3-2o-45 4

/

i l Contents j

i v4c Page Attachments Number (Computer Printouts. Techrucal Papers, Sketches. Correspondents) of p Purpose of Calculation / Summary of Conclusions 1 Attachment A - Lotus 123, Release 5 2 Setpoint Calculations Cntena ]

Major Equation Sources /Denvation Methods [

j Assumptions 2 Listed References 2 Body of Calculations 3 l

1 l Safety Related 9 Yes O No l Nonsafety-related That Could Impact Safety-Related O Yes O No l I

Record of Revisions Rev. No, Desertption Originator i Date Revieweri Date supervkori Date l A Issued for DCR 94-035 and DCR 94-036 -

3 'N M

to support Power Uprate Project H[/- /3/ /[95

i ,

i l l

. l

~~

! f!EFERENCE ONLY i

4

" " ' os-$ew 9504110373 950405 PDR ADOCK 05000321 P PDR l

l l

Design C:.leulations - NucleTr SOUTHERN COMPANY SERVICES, INC.

Project Calcu!stion Number E. I. Hatch Nuclear Plant - Unit (s): O1 92 SINH 95-003 Subject /TWe Sheet Setpoints for Power Uprate 1 of 4 Purpose / Scope: l EFERENCE ONLY ,

Operation of Plant Hatch at uprated power (105% of original design power) requires reactor pressure to be increased approxomately 30 Psig. In order to operate at this elevated pressure, reactor l pressure related setpoints such as Reactor High Pressure Scram, ATWS RPT High Reactor Pressure and ARI High Pressure setpoints must be increased. This calculation provides revised setpoints for those instruments as required to allow operation at uprated conditions.

Summary of

Conclusions:

Revised Analytical Limits for Power Uprate conditions are provided in Table 5-1 of the General Electric Safety Analysis Report for Edwin I. Hatch Plant Units 1 & 2 (NEDC-32405P). The new setpoints were calculated based upon these analytical limits in accordance with guidelines as provided in Regulatory Guide 1.105 and ISA 67.04 using General Electric Setpoint Methodology and documented performance specifications for the Rosemount 1153GB8 PAN 0097 pressure transmitters and GE/Rosemount 510/710 Analog Trip Units.  ;

Instrument MPL Setpoint Process Setpoint Signal 2B21 N642A 1170 Psig 4.70 Vdc 2B21-N642B 1170 Psig 4.70 Vdc 2B21-N643A 1170 Psig 18.80 mAdc 2B21-N643B 1170 Psig 18.80 mAdc 2B21-N678A 10U0 Psig 15.20 mAdc 2B21-N678B 1080 Psig 15.20 mAdc 2B21-N678C 1080 Psig 15.20 mAdc ,

2B21-N678D 1080 Psig 15.20 mAdc l l

Criteria:

Setpoints have been selected such that the probability for LER avoidance is 95% or greater, i

Equation Sources / Derivation Methods: j e General Electric Trip Setroint Methodology for the E. I. Hatch Nuclear Plant Analog Transmitter Trip System Instrumentation i e Regulatory Guide 1.105 i e Instrument Society of America (ISA) Standard 67.04 - Setpoints for Nuclear Safety-Related  ;

Instrumentation CALC DOT Rev. 1 06 16-94

4 Design CCiculations - Nuclect SOUTHERN COMPANY SERVICES, INC.

Project Calculation Number E. I. Hatch Nuclear Plant - Unit (s): O1 02 SINH 95-003  !

Subject /Dtle Sheet Setpoints for Power Uprate 2 of 4 Assumptions:

1. The transmitters are located in a benign environment; therefore, radiation effect is not considered.
2. The seismic effect of a DBE (Design Basis Earthquake) for Plant Hatch is less severe than the 7.5 q ZPA cited by Rosemount in their report D8400102. Seismic effect is therefore not considered in this calculation. ,
3. The Rosemount Model 1153GB8 PAN 0097 transmitter (0 - 1000 Psig transmitter factory calibrated 800 - 1200 Psig) has been tested and performance specifications certified; since the accuracy and temperature effect factors are specific for this tested calibrated range, they have been used without adjustments for turndown ratio. All other uncertainity factors have been '

adjusted to compensate for zero and span errors.

References / Attachments:

1. General Electric Setpoint Methodology for the Hatch ATTS Instrumentation
2. ISA Standard S67.04
3. General Electric Power Uprate Safety Analysis Report for E. I. Hatch Plant Units 1 & 2 (NEDC-32405P)
4. DOCR 50-366, dtd 1/13/1995 - Request for License Ammendment: Power Uprate Operation 1
5. Rosemount Product Data Sheet 2471, dtd. 4/87 - Model 710 DU Trip System  ;
6. SX-18610, Rev. D - Nuclear Equipment Analysis Report, Rosemount 1153 Series B Pressure  ;

^

Transmitters l

7. Rosemount Nuclear Instruments, Inc. Memo, dtd. 3/13/1995 - Performance Specifications for the N0097 Option l

CALC DOT Rev 1 06 18-94

D:cign C:lcul:tions - Nuclzar SOUTHERN COMPANY SERVICES, INC.

Project Calculation Number E. I. Hatch Nuclear Plant - Unit (s): O1 92 SINH 95-003 Subject / Title Sheet Setpoints for Power Uprate 3 of 4 Body of Calculation:

Instrument Loon Uncertainity Calculation Equations 2 2 A= (TXA YI PSE YCTX YCCA + Ro + Tg + Tv4cY 2

D= '

(Txo E Dni }

ST = 0.13%

  • CS U = i [ A + D + ST j For Results of Uncertainity Calculations see Attachment A.

CALC DOT Rev 1 OSig.g4

Design Calculations - Nuclear SOUTHERN COMPANY SERVICES,INC.

Project Calculation Number E. I. Hatch Nuclear Plant - Unit (s): O1 G5 2 SINH 95-003 Subject / Title sheet Setpoints for Power Uprate 4 of 4 Calculation Summary Design Limits .1350 psig

= 1250 psig Design Safety Limit Analytscal Limit ,.

A b inor if A !owaose Valuo

)I O REO'D A ST k E?CAUB 1 ( )f SETPOINT

)N YN ST N!cAuB V V A A O RECAUB REco II II Allowacle Limit

)N YY'**

A V

/

7ls' i

i Normal Operation 1050 psia CALC DOT Rev i 06-16 94

r SINH 95-003, Attechment A SETPOINTS FOR ATWS RPT HIGH REACTOR PRESSURE AND ARI HIGH PRESSURE " h 8

hh h m t Em % 5.

l WITH NEW RANGE 800 TO 1200 PSIG (TRANSMITTER AND MTU)

(

2B21-N642A,B and 2B21-N643A,B l RL Range Lower Limit 800.000 Psig j RU Range Upper Limit 1200.000 Psig IL Current Lower L!mit 4.000 made IU Current Upper Limit 20.000 made DB Design Basis 1250.000 Psig 4

Mar Margin =DB-Analytical Limit 70.000 Psig AL Analytical Limit 1180.000 Psig 1 CS Calibration Span of instrument 400.000 Psig 2Ims Maximum Span of Instrument 1000.000 Psig 3 Txa Transmitter Accuracy (.5% of CS) 2.000 Psig 4 Tdr Turndown Ratio (Ims/CS) 2.500 Pse - Power Supply Effect 0.005 / volt Psa - Power Supply Accuracy 0.015 Psv- Power Supply Voltage 24.000 vde 5 TPse Total Power Supply Effect 0.021 Psig

! Pse*Psv'Psa".75%*Tdr 6 Txd Transmitter Drift /30 months 2.000 Psig

i. .2%*lms 7 Ctx Transmitter Calibration Effect 2.500 Psig

.0065*CS

8 Dtu Trip Unit Drift (.1%
  • Ime) 1.000 Psig i 9 CCa Calibration Current Accuracy 0.110 Psig 2.75%*CS
10 Ro Trip Unit Readout Accuracy (5%*CS) 0.200 Psig j 11 Te Temperature Effect Mxot - Evaluation Temperature 102.000 DegF l REFT - Reference Temperature 80.000 DegF Te =CS* 4%(Mxot-REFT)/100 3.520 Psig j 12 Tuac Trip Unit Accuracy .32% of CS 1.280 Psig

, 13 ST Setpoint Tolerance .13% of CS 0.520 Psig l 14 Se Seismic effect I

(.5% of Ims)+(.75% of CS*Tdr) 0.000 Psig 1 15 A Loop Accuracy 4.933 Psig

, Sqrt(TXA^2 +TPSE^2+CTX^2+CCA^2+ RO^2+TE^2+ SE^2+TUAC^2)

D Drift Accuracy 2.236 Psig 4 Sqrt(TXD^2+DTU^2)

U Loop Uncertainty 7.689 Psig A+D+ST AVmax Maximum Allowable Value= Analytical Limit - A 1175.067 Psig AV Allowable Value (Tech. Spec. Limit) 1175.000 Psig SPmax Maximum Setpoint=AV-( D+ST) 1172.244 Psig SP Setpoint 1170.000 Psig Isp Setpoint Signal (MTU) 18.800 made Esp Setpoint Signal (STU) 4.700 Vdc R Reset 1155.600 Psig Ir Reset Signal (MTU) 18.224 made Er Reset Signal (STU) 4.556 Vdc 1 1 Z LER Avoidance Probability 1.838
Z= lSP - AVj/Sqrt(A/2^2+D/2^2+ST/2^2)

It Z>1.65, LER Avoidance Probability is > 95%

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SINH 95-003, AttSchment A SETPOINT FOR REACTOR HIGH PRESSURE SCRAM WITH NEW RANGE 800 TO 1200 PSIG (TRANSMITTER AND MTU) 2B21-N678A-D RL Range Lower Limit 800.000 Psig l RU Range Upper Limit 1200.000 Psig l lL Current Lower Limit 4.000 made i IU Current Upper Limit 20.000 made i l

DB Design Basis 1250.000 Psig Mar Margin =DB-Analytical Limit 148.900 Psig AL Analytical Limit 1101.100 Psig 1 CS Calibration Span of instrument 400.000 Psig  ;

2Ims Maximum Span of Instrument 1000.000 Psig 3 Txa Transmitter Accuracy (.5% of CS) 2.000 Psig 4 Tdr Tumdown Ratio (Ims/CS) 2.500 j Pse - Power Supply Effect 0.005 / volt

' Psa - Power Supply Accuracy 0.015 Psv- Power Supply Voltage 24.000 vde 5 TPse Total Power Supply Effect 0.021 Psig
' Pse*Psv*Psa*.75%"Tdr 6 Txd Transmitter Drift /30 months 2.000 Psig

.2%*lms 7 Ctx Transmitter Calibration Effect 2.500 Psig

.0065*CS

, 8 Dtu Trip Unit Drift (.1%

  • Ims) 1.000 Psig .

9 CCa Cahbration Current Accuracy 0.110 Psig 2.75%'CS 2 10 Ro Trip Unit Readout Accuracy (5%*CS) 0.200 Psig -

! 11 Te Temperature Effect

Mxot- Evaluation Temperature 105.000 DegF 1

REFT - Reference Temperature 80.000 DegF Te =CS* 4%(Mxot-REFT)/100 4.000 Psig 12 Tuac Trip Unit Accuracy .32% of CS 1.280 Psig 13 ST Setpoint Tolerance .13% of CS 0.520 Psig .

14 Se Seismic effect

(.5% of Ims)+(.75% of CS*Tdr) 0.000 Psic j 15 A Loop Accuracy 5.286 Psig

, S q rt(TXA^2 +TPS E^2 + CTX^2 + C CA^2 + R O^2 +TE^2 + S E^2 +TUAC^2)

D Drift Accuracy 2.236 Psig
Sqrt(TXD^2+DTU^2) ,

4 U Loop Uncertainty 8.042 Psig '

A+D+ST j

AVmax Maximum Allowable Value= Analytical Limit-A 1095.814 Psig AV Allowable Value (Tech. Spec. Limit) 1085.000 Psig

, SPmax Maximum Setpoint=AV-(D+ST) 1082.244 Psig SP Setpoint 1080.000 Psig Isp Setpoint Signal (MTU) 15.200 made 4

Esp Setpoint Signal (STU) 3.800 Vdc R Reset 1065.600 Psig l Ir Reset Signal (MTU) 14.624 made Er Reset Signal (STU) 3.656 Vdc 3

Z LER Avoidance Probability 1.735

, Z= lSP - AVl/Sqrt(A/2^2+D/2^2+ST/2^2) i If Z> 1.65, LER Avoidance Probability is > 95%

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