Text

Attachment 3, Exelon Generation Company, Calculation LE-0113, Rev. 1, Reactor Core Thermal Power Uncertainty Calculation Unit 1
	ML102070197
Person / Time
Site:	Limerick
Issue date:	03/12/2010
From:	Ugorcak P; Exelon Generation Co, Exelon Nuclear
To:	; Office of Nuclear Reactor Regulation
References
	LE-0113, Rev 1
	Download: ML102070197 (96)
	v • d • e

ATTACHMENT 3 Exelon Generation Company, LLC Calculation LE-01 13, Rev. 1, "Reactor Core Thermal Power Uncertainty Calculation Unit 1"

MWmelon.

Design Analysis Major Revision Cover Sheet Design Analysis (Major Revision)

I Last Page No. 194 Analysis No.: I LE-01 13 Revision: 1 1

Title:

3 Reactor Core Thermal Power Uncertainty Calculation Unit 1 EC/ECR No.:'

LG 09-00096 Revision: 1 1 Station(s):

Limerick Compon nt(s):

Unit No.:a 1

Discipline:,'

LEDE Descrip. Code/Keyword:,0 N/A Safety/QA Class: "

N System Code: 12 006,041.042,043,044,047 Structure:,3 N/A CONTROLLED DOCUMENT REFERENCES" 5

Document No.:

From/To Document No.:

From/To LEAE-MUR-0001 From LM-562 From LM-0552 From L-S-15 From LM-553 From L-S-19 From LE-01 16 From L-S-36 From LEAM-MUR-0038 To LEAM-MUR-0046 To LEAM-MUR-0039 To LEAM-MUR-0041 To LEAM-MUR-0048 To Is this Design Analysis Safeguards Information? 16 Yes E] No ]

If yes, see SY-AA-101-106 Does this Design Analysis contain Unverified Assumptions? 17 Yes El No 0 If yes, ATI/AR#:

This Design Analysis SUPERCEDES: 11 LE-0113 Revision 0 in its entirety.

Description of Revision (list affected pages for partials): "9 This revision incorporates the revised uncertainty number from LEAE-MUR-0001 (Caldon ER-739) and the revised parameter values at MUR rated power from GEH task report T0100. Although this is a major revision, the changes themselves are not significant with regard to the final result. This calculation is prepared to support a License Amendment Request for an increase in licensed power so there is no effect on any operating margin. All pages reformatted and reprinted.

Changes to text on pages 1-2, 4-8, 18, 21-22, 24-25, 33-34, 40, 43-44, 48-49, 52-58, 60

. Replaced Att. 5 (p.

70-75) & Att. 6 (p. 76).

Iii Preparer:

Patricia A. Ugorcak

6, A A

tr t 3-3-2010 Print Name

-Sign

-Name Datse Method of Review:

Detailed Review ED Alternate Calodlatlo? s (attached) C]

Reviewer:

John Pehush

'/

j Testing El 3-3-2010

-#v--

L*m Print Name Sign Pane Date Review Notes: 13 Independent review [

Peer review E]

Performed a line by line review of the calculation and verified revised design input were correctly incorporated.

All comments were resolved to the satisfaction of the reviewer. This calculation supports the MUR by reducing the measurement uncertainty of Core Thermal Power from 2/9 % to 0.35 %.

(For External Analmss Oily)

External Approver: 2' Richard Brusato

//a J.P fJ

&xge#J a

&W

"+'¶;[oCJ Print Name Roy N

Date Exelon Reviewer:

Niranian Roy 3-12 -(0 Td Print Name Sign Name Date Independent 3 rd Party Review ReqdV Yujv No*

R,

-1"t

{ h z.-ý Exelon Approver: 2 Raymond George sZ*

-'..,Q

1 Print Name Sign Name

<-D Dare

LE-0113 Revision I Exeleon.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 CC-AA-309 Revision 9 ATTACHMENT 1 Owners Acceptance Review Checklist for External Design Analysis DESIGN ANALYSIS NO. LE-0113 REV.

I Yes No

-I/

1.

Do assumptions have sufficient rationale?

2.

Are assumptions compatible with the way the plant is operated and with the licensing basis?

3.

Do the design inputs have sufficient rationale?

Are design inputs correct and reasonable with critical parameters identified, if appropriate?

Are design inputs compatible with the way the plant is operated and with the licensing basis?

6.

Are Engineering Judgments clearly documented and justified?

7.

Are Engineering Judgments compatible with the way the plant is operated and with the licensing basis?

8.

Do the results and conclusions satisfy the purpose and objective of the Design Analysis?

Are the results and conclusions compatible with the way the plant is operated and with the licensing basis?

10.

Does the Design Analysis include the applicable design basis documentation?

Have any limitations on the use of the results been identified and transmitted to the appropriate organizations?

12.

Are there any unverified assumptions?

13.

Do all unverified assumptions have a tracking and closure mechanism in place?

Have all affected design analyses been documented on the Affected Documents List (ADL) for the associated Configuration Change?

Do the sources of inputs and analysis methodology used meet current technical requirements and regulatory commitments? (If the input sources

15.

or analysis methodology are based on an out-of-date methodology or code, additional reconciliation may be required if the site has since committed to a more recent code)

Have vendor supporting technical documents and references (including GE DRFs) been reviewed when necessary?

17.

Have margin impacts been identified and documented appropriately for any negative impacts (Reference ER-AA-2007)?

EXELON REVIEWER: _NI,,/',JjA-,\\J P0 '/.__, L,;2 Print / Sign (JO

[3 E]

'El 1 1~El 131/El B/ 'El El El El E?

F1 0l aEl N/A El El El El El El El El/

El El D*,

[]

[

3/

El 0

DATE:

3_-/Z1

/1 Page 1A of 94

LE-0113 Epp Reactor Core Thermal Power Uncertainty Revision 1I Calculation Unit 1 TABLE OF CONTENTS 1.0 P U R P O S E......................................................................................................................................................

4 1.1 FUNCTIONAL DESCRIPTION AND CONFIGURATION......................................................................

4 2.0 DESIGN BASIS..............................................................................................................................................

4 2.1 IN P U T S......................................................................................................................................................

4 2.2 REACTOR WATER CLEANUP (RWCU) FLOW LOOP UNCERTAINTY.............................................

7 2.3 REACTOR'CLEANUP SYSTEM TEMPERATURE.................................................................................

11 2.4 CRD FLOW RATE UNCERTAINTY....................................................................................................

14 2.5 RECIRCULATION PUMP MOTOR UNCERTAINTY..........................................................................

18 3.0 ASSUMPTIONS AND LIMITATIONS.....................................................................................................

21

4.0 REFERENCES

23 4.1 M ETHODOLOGY....................................................................................................................................

23 4.2 PROCEDURES.............................................................

23 4.3 DESIGN BASIS DOCUMENTS................................................................................................................

23 4.4 SPECIFICATIONS, CODES, & STANDARDS....................................................................................

23 4.5 LIMERICK STATION DRAW INGS......................... I.................................................................................

23 4.6 GENERAL ELECTRIC (GE) DOCUMENTS.......................................................................................

24 4.7 VENDOR INFORMATION........................................................................................................................

24 4.8 CALCULATIONS AND ENGINEERING ANALYSIS..........................................................................

24 4.9 OTHER REFERENCES...........................................................................................................................

25 5.0 IDENTIFICATION OF COMPUTER PROGRA MS...................................................................................

25 6.0 METHOD OF ANALYSIS.............................................................................................................................

26 6.1 M e th o d o lo g y.............................................................................................................................................

2 6 6.2 CORE THERMAL POW ER (CTP) CALCULATION:...........................................................................

26 7.0 NUMERIC ANALYSIS..................................................................................................................................

33 7.1 Feedwater Flow Uncertainty....................................................................................................................

33 7.2 Steam Dome Pressure Measurement Uncertainty............................................................................

33 7.3 Reactor W ater Clean-up (RW CU) Flow Loop Uncertainty.................................................................

33 7.4 RW CU Temperature Loop Uncertainty..............................................................................................

41 7.5 CRD Flow Rate Uncertainty....................................................................................................................

44 7.6 Recirculation Pump HEAT UNCERTAINTY........................................................................................

50 7.7 Determination of CTP Uncertainty.........................................................

54 7.8 Total CTP Uncertainty Calculation.....................................................................................................

59

8.0 CONCLUSION

S...........................................................................................................................................

60 9.0 A tta c h m e nts..................................................................................................................................................

6 1 Page 2 of 94

LE-0113 Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 TABLE OF TABLES T a ble 2 -1. D e sig n In p uts....

5 Table 2-2. RWCU System Inlet Flow Element - Unit 1.........................................................................................

7 Table 2-3. RWCU System Inlet Flow Differential Pressure Transmitter...............................................................

8 Table 2-4. RWCU System PPC Precision Signal Resistor Unit...........................................................................

9 Table 2-5. RWCU System PPC Analog Input Card Unit 1...................................................................................

10 Table 2-6. RWCU System Local Service Environments.....................................................................................

11 Table 2-7. RWCU System Inlet Thermocouple...................................................................................................

11 Table 2-8. RWCU System Outlet Thermocouple................................................................................................

12 Table 2-9. RWCU System Thermocouple PPC Analog Input Card Unit 1..........................................................

13 Table 2-10. RWCU System Thermocouple Local Service Environments..........................................................

13 Table 2-11. CRD Hydraulic System Flow Element-Unit 1................................................................................

14 Table 2-12. CRD Hydraulic System Differential Pressure Transmitter..............................................................

15 Table 2-13. CRD Hydraulic System PPC Precision Signal Resistor Unit..........................................................

16 Table 2-14. CRD Hydraulic System PPC Analog Input Card Unit 1..................................................................

16 Table 2-15. CRD Hydraulic System Local Service Environments........................................................................

17 Table 2-16. Recirculation Pump Motor Watt Transducer...................................................................................

18 Table 2-17. Recirculation Pump Motor Watt Transducer PPC Precision Signal Resistor Unit............................

19 Table 2-18. Recirculation Pump Motor Watt Transducer PPC Analog Input Card Unit 1...................................

19 Table A7-1. CTP Calculation Sensitivity Analysis..............................................................................................

77 Table A8-1. Relationship between a,, Y(ai), a,(, and n.......................................................................................

80 Page 3 of 94

LE-0113 Ow Reactor Core Thermal Power Uncertainty Revision 1 meI____

n.

Calculation Unit 1 1.0 PURPOSE The purpose of this calculation is to determine the uncertainty in the reactor core thermal power (heat balance) calculation performed by the Plant Process Computer (PPC). This calculation will evaluate the contribution of the different instrument channel loop uncertainties to the uncertainty of the Core Thermal Power (CTP) value using the reactor heat balance relationship when the plant is operating at 100% rated power under steady state conditions.

This calculation is being performed in support of the licensing amendment for Measurement Uncertainty Recapture (MUR) power uprate. The calculation provides the uncertainty in the value of CTP calculated by the Plant Process Computer at MUR rated conditions for use in requesting an increase in the CTP licensing limit for Limerick Generating Station Unit 1. Therefore, there are no acceptance criteria. The number is simply stated for use in preparation of the License Amendment Request.

1.1 FUNCTIONAL DESCRIPTION AND CONFIGURATION Limerick Generation Station (LGS) Unit I will be installing highly accurate ultrasonic feedwater flow meters per Engineering Change Request (ECR) LG 09-00096. This calculation will determine the uncertainty in Core Thermal Power calculation when the reactor heat balance is performed using the process computer with the feedwater flow and temperature measurement input supplied by the Caldon Leading Edge Flow Meters Check Plus (LEFMv$+) System Ultrasonic Flow Meters (UFM).

2.0 DESIGN BASIS Various plant parameters are monitored by the NSSS computer to develop the reactor core thermal power calculation. On June 1, 2000 Appendix K to Part 50 of Title 10 of the Code of Federal Regulations was changed to allow licensees to use a power uncertainty of less than 2 % in their LOCA analysis. The change allowed licenses to recapture power by using state-of-art devices to more precisely measure feedwater flow. Feedwater flow inaccuracy is a large contributor in the uncertainty determination of reactor power. This calculation is being performed in the support of a License Amendment Request (LAR) for a MUR power uprate.

2.1 INPUTS Table 2-1 lists the parameters which specify input to the core thermal power calculation, their uncertainty values, and the source of these values.

The values for Feedwater Flow, Feedwater Temperature, and Reactor Narrow Range Dome Pressure are specified by separate calculations as follows (Ref. 4.8.6 thru 4.8.8):

LEAE-MUR-0001, Bounding Uncertainty Analysis for Thermal Power determination LE-01 16, Reactor Dome Narrow Range Pressure Measurement Uncertainty The uncertainties for Reactor Water Clean-up (RWCU) Flow Rate, RWCU Inlet Temperature Thermocouple, Control Rod Drive (CRD) Flow Rate, and Recirculation Pump Power are calculated in individual sections of this calculation. Recirculation Pump Efficiency is given in calculation LM-0552 (Ref. 4.8.2). The thermal loss due to radiated heat loss to the drywell is specified by separate calculation LM-553 (Ref. 4.8.3) for calculating the reactor heat balance by hand.

Other inputs and the related source references are listed in the Table 2-1.

Page 4 of 94

LE-0113 Revision 1I Exelon.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 Table 2-1.

Design Inputs Description Inst. Tag Computer Nominal Value Uncertainty Uncertainty No.

Point Basis CRD Enthalpy N/A N/A 68.00 Btu/Ibm

+ 0.005 (Ref. 4.9.10)

Btu/Ibm (Ref. 4.9.3)

CRD Water Flow 97.20F Discharge TE-046-103 Al 201 (Ref. 4.9.10) 0.7 °F (Ref. Attachment 1)

Temperature Nominal Flow CR0 Water Flow FT-046-A1711 0.0320 MIbm/hr 0.0017 (Section 7.5.6)

Rate 1N004 MIbm/hr (Ref. 4.9.10)

Feedwater N/A N/A 405:30 Btu/Ibm

+/- 0.005 (Ref. 493)

Enthalpy (Ref. 4.9.10)

Btu/Ibm Feedwater Mass 15.255 Mlbm/hr Flow Rate (LEFM 10-C986 N/A

+/-0.28 %

(Ref. 4.8.6) v'+ System)

(Ref. 4.9.10)

Feedwater NIA N/A 1155 PSIG

10 psi (Section 3.11)

Pressure (Ref.4.4.1)

Feedwater TE-006-A1744 thru 427.1 'F Temperature 1N041A-F A1750 (Ref. 4.9.10)

Radiated Reactor 0.89 MW Pressure Vessel N/A N/A

+/- 10 %

(Section 3.12)

(RPV) Heat Loss (Ref. 4.8.3, Sec. 2.0)

Reactor Dome PT-042-E1234 1060 PSIA

120 psi (Ref. 4.8.8)

Pressure 1N008 (Ref. 4.9.10)

Saturated Steam 1190.0 Btu/Ibm Enthalpy N/A N/A

+/- 0.85 Btu/Ibm (Section 7.7.2.2)

(Ref. 4.9.10)

Recirculation 948% (Attachment 10 &

Pump Motor 1A(B)-P201 N/A Ref.

N/A N/A efficiency Ref. 4.8.2)

Recirculation 7700 Hp (5.74 MW)

Pump Motor 1A(B)-P201 N/A 7

1.4 %

(Section 7.6.8)

Power (Ref. 4.3.3)

RWCU Discharge N/A N/A 418.40 Btu/Ibm

+ 0.005 (Ref. 4.9.3)

Enthalpy (Ref. 4.9.10)

Btu/Ibm Page 5 of 94 I

Exel6n.

LE-0113 Revision 1 Reactor Core Thermal Power Uncertainty Calculation Unit 1 Table 2-1.

Design Inputs Description Inst. Tag Computer Nominal Value Uncertainty Uncertainty No.

Point Basis RWCU Discharge TE-044-439 OF Temperature 1N015 (Ref. 4.9.10)

RWCU Inlet Flow FT 044-0.1540 Mlbm/hr

+ 0.0035 (Section 7.3.6) 1N036A A1718 Ref. 4.9.10)

MIbm/hr RWCU Regen Heat Exchanger TE-044-535.3 7F Inlet Temperature 1N004 (Ref. 4.9.10)

+/- 4.37 *F (Section 7.4.6)

RWCU Suction 530.6 Btu/Ibm

+/- 0.005 Enthalpy N/A N/A (Ref. 4.9.10)

Btu/Ibm (Ref. 4.9.3)

Page 6 of 94

LE-0113 Revision I

&el6n.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 2.2 2.2.1 REACTOR WATER CLEANUP (RWCU) FLOW LOOP UNCERTAINTY Reactor Water Cleanup System Equipment Design Data (Ref. 4.3.4)

System flow rate (Ibm/hr)

Normal operation "A" pump Normal operation "B" plus "C" pump 154,000 133,000 Main Cleanup Recirculation Pumps "A" Pump "B" & "C" Pumps Number required Capacity, % (each) 1 100 2

50 "A" pump capacity is greater that the combined capacity of the "B" and "C" pumps 2.2.2 RWCU Flow Measurement Loop Diagram RWCU flow is measured by an orifice plate (FE-044-1 N035) located on the suction side of the RWCU Recirculation Pumps, which provides a AP signal to a Rosemount transmitter (FT-044-1 N036A). The transmitter supplies a milliamp signal to the PPC for display in the Control Room. The instrument loop consists of the following: flow element, flow transmitter, a signal resistance unit and a PPC input/output (1/O) module. The loop configuration is shown below (Ref. 4.5.10):

Tubing The loop components evaluated in this document (the applicable performance specifications and process parameter data):

2.2.3 RWCU System Inlet Flow (Ref. 4.4.1,4.5.6, 4.5.7, 4.5.10, 4.5.11,4.5.16, 4.6.4, and 4.9.1)

Table 2-2.

RWCU System Inlet Flow Element - Unit 1 Component i.D.:

FE-044-1N035 "RWCU SUCTION FLANGE UPSTREAM OF VALVE HV-44-1 F001" Device Type:

Orifice Plate Manufacturer/Model No.:

Vickery Simms Inc./145C3227P037 Reference Accuracy (Al):

+/-1.50% of actual flow rate Installation Accuracy:

+/- 0.5%

Environmental Conditions (Temp.):

407F (min.) to 156°F (max.)

Environmental Conditions (Press.):

(-) 1.0 (min.) to (+) 7.0 inches H20 (max.)

Page 7 of 94

LE-0113 Revision I

&ebn.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 Table 2-2.

RWCU System Inlet Flow Element - Unit I Environmental Conditions (RH %):

20 (min.) to 90 (max.)

Pipe Size:

6 inch schedule 80 Flange Rating:

600#

Pipe Class Service No.:

DCA-101 "RWCU from Recirc. Pump Suction Valve F004 Normal Operating Temperature:

539 °F Design Temperature:

582 OF Maximum Operating Temperature:

582 OF Normal Operating Pressure:

1060 psig Design Pressure:

1250 psig Maximum Operating Pressure:

1360 psig Normal flow Rate:

360 gpm Maximum Flow Rate:

477 gpm AP @ Max. Flow Rate:

200 inches H20, nameplate data: 1178 psig & 545 OF 2.2.4 RWCU System Inlet Flow (Ref. 4.2.1, 4.2.2, 4.5.6, 4.5.10, 4.5.19, 4.5.20, 4.6.4, 4.7.2, 4.7.6, 4.7.7, 4.9.5, and 4.9.7)

Table 2-3.

RWCU System Inlet Flow Differential Pressure Transmitter Component I.D.:

FT-044-1 N036A "REACTOR WATER CLEANUP INLET" Location (AREA I EVEL I RM):

016 / 283'/ 506 Device Type:

Differential Pressure Transmitter Manufacturer/Model No.:

Rosemountl 153DB5RCN0039 Quality Classification:

Q (Not Required)

Accident Service:

N/A Seismic Category:

N/A Tech Spec Requirement:

N/A Upper Range Limit @ 68 OF:

750 inches H20 Lower Range Limit @ 68 OF:

0-125 inches H20 Calibrated Range:

0 to 218.3 inches H20 - static pressure corrected Operating Range:

0 to 220 inches H20 at 1060psig Calibration Span:

218.3 inches H20 Page 8 of 94

WW meloin.

LE-01 13 Revision 1 Reactor Core Thermal Power Uncertainty Calculation Unit 1 Table 2-3.

RWCU System Inlet Flow Differential Pressure Transmitter Output Signal:

4 - 20 mA Setpoint:

N/A Calibration Period:

24 months Accuracy (A2):

+/- 0.25 % calibrated span (see note)

Calibration Accuracy:

+/- 0.5 %

Stability (Drift, D2):

+/- 0.2 % URL for 30 months [2a]

Temperature Effect (DTE1), per 100°F +/- (0.75 % of upper range limit + 0.5 % span)

Temperature Normal Operating Limits: 40 to 200 *F Overpressure Effect:

Maximum zero shift of +/- 1.0 % URL above 2000 psig Static Pressure Zero Effect:

+0.2 % of upper range limit Static Pressure Span Effect (SPNE2):

+/- 0.5 % input reading per 1,000 psi.

Seismic (vibration) Effect (SEIS2):

Accuracy within +/-0.5 % of upper range limit during and after a seismic disturbance defined by a required response spectrum with a ZPA of 4 g's.

Power Supply Effect (PSE2):

< 0.005 % of calibrated span per volt Mounting Position Effect:

No span effect. Zero shift of up to 1.5 inH20 EMI/RFI Effect:

Not Specified Response time (damping):

Code N - Adjustable damping; max. 0.8 seconds Harsh temperature effect (HTE2):

Accuracy within t 5.0 % of URL during and after exposure to 265 'F (129.5 °C), 24 psig, for 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br />.

Humidity limits:

0 to 100 % Relative Humidity (RH)

Safety Classification:

Application - Non-safety-Related Radiation Effect (e2R):

Accuracy within t 4.0 % of URL during and after exposure to 2.2 x10 7 rads, TID of gamma Note: Includes combined effects of linearity, hysteresis, and repeatability RWCU System Signal Resistor Unit (Ref. 4.1.1, 4.5.10, 4.5.17, and 4.7.3):

Table 2-4.

RWCU System PPC Precision Signal Resistor Unit Dwg. Designation:

SRU-1 Device Type:

Precision signal resistor unit Manufacturer/Model No.:

Bailey Type 766 Selected Range:

250 Ohm 2.2.5 Page 9 of 94 I

FPOmelion.

LE-0113 Revision I Reactor Core Thermal Power Uncertainty Calculation Unit 1 Table 2-4.

RWCU System PPC Precision Signal Resistor Unit Accuracy:

+/- 0.1%, (1 0.25 ohm)

Safety Classification:

N/A Temperature Effect:

+ 0.5 % for 40- 120°F Input Signal Range:

4 to 20 mAdc 2.2.6 RWCU System Computer Point - Plant Process Computer (PPC) (Ref. 4.5.10 and Attachment 4):

The PPC calculates Core Thermal Power based in part on the measurement of Reactor Water Cleanup flow. The PPC uses an analog input card, which read the voltage drop across a precision 250 ohm resistor.

Table 2-5.

RWCU System PPC Analog Input Card Unit 1 Component I.D.:

A1718 Location:

10-C603 (H12-P603)

Device Type:

PPC - Potentiometer (Analog) Input Card Manufacturer/Model No.:

Analogic/ANDS5500 Quality Classification:

N/A Accident Service:

N/A Seismic Category:

N Tech Spec Requirement:

N/A Selected Full Scale Span:

+ 5 VDC Calibration Span:

(-) 5 VDC to (+) 5 VDC Calibration Period:

24 months Accuracy (A3):

+/- 0.5 % of full scale span Input Impedance (resistance):

10 Meg Ohms Analog to Digital Converter:

Not Specified Power Supply Effect (PSE3):

N/A EMI/RFI Effect:

N/A Response time (damping):

N/A Operating Temperature Limits:

32 to 122 'F (0 to 50 'C)

Humidity limits:

Not Specified Safety Classification:

Non Safety-Related Page 10 of 94

Exelkn.

LE-0113 Revision 1 Reactor Core Thermal Power Uncertainty Calculation Unit 1 2.2.7 RWCU System Local Service Environments (Ref. 4.4.2):

Table 2-6.

RWCU System Local Service Environments Flow Transmitter Plant Process Computer Area / Room.

Area 016 Area 008 - Control Room Location 506C - Cont. H2 Recombiner Control Room (Comp. Rm. 553)

Normal Temp. Range ('F) 65 min / 106 max / 85 norm 65 min / 78 max / norm N/A Normal Pressure

(-) 0.25 inches WG

+ 0.25 inches WG Normal Humidity (RH %)

50 average / 90 maximum 50 average /90 maximum Radiation 2.50E-03 Rads/hr, 8.78E+02 TID N/A 2.3 REACTOR CLEANUP SYSTEM TEMPERATURE 2.3.1 RWCU System Regenerative Heat Exchanger Inlet Temperature (Ref. 4.4.1,4.5.6, 4.5; 11, 4.5.16, 4.5.18, 4.5.19, 4.6.4, 4.9.5, and 4.9.7)

TE-044-1N004 PPC Al 741 Thermocouple Table 2-7.

RWCU System Inlet Thermocouple Component Numbers:

TE-044-1N004 "REACTOR WATER CLEANUP SYSTEM REGEN HEAT EXCH INLET TEMP" Device Type:

Type T Copper - Constantan (CU/CN)

Manufacturer/Model No.:

California Alloy Co/Model 117C3485P073 Element Range:

(-)200* to (+)700 'F Calibrated Range 0 - 600'F Rated Accuracy:

_ 0.75°F Output Signal:

(-) 0.674 mV to (+)1 5.769 mV Safety Classification:

N/A Pipe Class Service No.:

DCC-101 "RWCU pump discharge thru Regen HXs Normal Operating Temperature 530 *F (See Note 1)

Normal Operating Temperature Spec:

535 'F Design Temperature:

582 'F Maximum Operating Temperature:

582 'F Page 11 of 94

LE-01 13 Revision 1 Exel6n.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 Table 2-7.

RWCU System Inlet Thermocouple Normal Operating Pressure:

1235 psig Design Pressure:

1290 psig Maximum Operating Pressure.

1542 psig Normal flow Rate:

360 gpm Note 1: Reactor Engineering provided normal operating temperature based on 100% power operation for both Units. Data was retrieved once per hour for one week. Unit 2's value of 530 'F is more conservative than Unit 1's value of 528 'F. Per the GEH task report the value of 535.5 'F will be used (Ref. 4.9.10).

2.3.2 RWCU System Regenerative Heat Exchanger Outlet Temperature (Ref. 4.1.1,4.5.6, 4.5.16, 4.5.18, 4.5.19, 4.6.4, 4.5.11,4.9.5, and 4.9.7)

TE-044-1N015 PPC A1742 Thermocouple Table 2-8.

RWCU System Outlet Thermocouple Component Numbers:

TE-044-1N015 "REACTOR WATER CLEANUP SYSTEM REGEN HEAT EXCH OUTLET TEMP" Device Type:

Type T Copper - Constantan (CU/CN)

Manufacturer/Model No.:

California Alloy Co/Model 117C3485P073 Element Range:

(-)200- to (+)700 -F Input Range 0' - 600'F Rated Accuracy:

+ 0.75°F Output Range

(-) 0.674 mV to (+)15.769 mV Safety Classification:

N/A Pipe Class Service No.:

ECC-1 05 "RWCU Regen HX to HV-1 F042 Normal Operating Temperature 440 'F (See Note 2) based on actual plant data Normal Operating Temperature:

438 'F Design Temperature:

434 'F Maximum Operating Temperature:

434 'F Normal Operating Pressure:

1168 psig Design Pressure:

1290 psig Maximum Operating Pressure:

1542 psig Normal flow Rate:

360 gpm Note 2: Reactor Engineering provided normal operating temperature based on 100% power operation Page 12 of 94

LE-0113 Revision 1 Exe6n.

Reactor Core Thermal Power Uncertainty Calculation Unit I for both Units. Data was retrieved once per hour for one week. However, the value of 439 'F from the GEH Task Report will be used (Ref. 4.9.10).

2.3.3 RWCU System Plant Process Computer (PPC) (Ref. 4.5.6, 4.5.16, and Attachment 4):

Table 2-9.

RWCU System Thermocouple PPC Analog Input Card Unit 1 Component I.D.:

A1718 and Al 742 Location:

10-C603 (H12-P603)

Device Type:

PPC - Potentiometer (Analog) Input Card Manufacturer/Model No.:

Analogic/ANDS5500 Quality Classification:

N/A Accident Service:

N/A Seismic Category:

N Tech Spec Requirement:

N/A Selected Range:

Upper: -25 mV to + 25mV Calibration Span:

(-) 0.674 mV to (+)15.769 mV Calibration Period:

24 months Accuracy (A2):

+/- 0.5 % of full scale span Input Impedance (resistance):

10 Meg Ohms Analog to Digital Converter:

Not Specified Signal Source Resistance:

2800 n. maximum Power Supply Effect (PSE2):

N/A E-MI/RFI Effect:

N/A Response time (damping):

N/A Operating Temperature Limits:

32 to 122 *F (0 to 50 'C)

Humidity limits:

Not Specified Safety Classification:

Non Safety-Related RWCU System Local Service Environments (Ref. 4.4.2):

Table 2-10.

RWCU System Thermocouple Local Service Environments Thermocouple Plant Process Computer Area / Room.

Area 016 Area 008 - Control Room Location 506C - Cont. H2 Recombiner Control Room (Comp. Rm. 553)

Normal Temp. Range (*F) 65 min / 112 max / 104 norm 65 min / 78 max / norm N/A 2.3.4 Page 13 of 94

LE-0113 Revision I W,mebn.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 Normal Pressure

(-) 0.25 inches WG

+ 0.25 inches WG Normal Humidity (RH %)

50 average / 90 maximum 50 average / 90 maximum Radiation 2.50E-03 Rads/hr, 8.78E+02 TID N/A 2.4 CRD FLOW RATE UNCERTAINTY 2.4.1 CRD Hydraulic System Flow Loop Diagram Each analyzed instrument loop consists of a flow element supplying a differential pressure to a pressure transmitter, and a PPC input/output (i/O) module with a precision resistor (8 (2) across the input. The loop is shown as follows:

The loop components evaluated in this document (and the applicable performance specification and process parameter data):

2.4.2 CRD Hydraulic System Flow Element (Ref. 4.4.1, 4.5.8, 4.5.12, 4.6.2, 4.6.3, 4.8.5, and 4.9.5)

Table 2-11.

CRD Hydraulic System Flow Element - Unit 1 Component I.D.:

FE-046-1N003 "CRD HYDRAULIC SYS DRIVE WTR FLOW CONT" Device Type:

Flow Nozzle Manufacturer/Model No.:

GE - Vickery Simms Inc./ 158B7077AP016 Reference Accuracy (Al):

+/- 1.0 % flow Design Temperature:

150°F Design Pressure:

2000 psig Pipe Size:

2 inch schedule 80 Material Stainless Steel Maximum Flow 100 gpm Pipe Class ServiceNo.:

DCD-112, "Control Rod Drive Hyd. from DBD-I 08 to Hydraulic Control Units Normal Operating Temperature:

100 *F (See Note 1)

Design Temperature:

150 'F Maximum Operating Temperature:

150 'F Normal Operating Pressure:

1448 psig Design Pressure:

1750 psig Maximum Operating Pressure:

1750 psig Page 14 of 94 I

LE-0113 Revision I r=el6n, Reactor Core Thermal Power Uncertainty Calculation Unit 1 2.4.3 Table 2-11.

CRD Hydraulic System Flow Element - Unit 1 Normal flow Rate:

105 gpm @ 1515.8 psig AP @ Max. Flow Rate:

200 inches H20 @ 100 gpm Note 1: The value of 97.2 *F will be used based on the GEH Task Report (Ref. 4.9.10).

CRD Hydraulic System Flow Transmitter (Ref. 4.5.8, 4.5.12, 4.6.2, 4.6.3, 4.7.4 and 4.9.5)

Table 2-12.

CRD Hydraulic System Differential Pressure Transmitter Component I.D.:

FT-046-1N004 "CRD HYDRAULIC SYS DRIVE WTR FLOW CONT" Location (AREA / EVEL / RM):

015 / 253' / 402 Device Type:

Differential Pressure Transmitter Manufacturer/Model No.:

Rosemount/ 1151DP5D22PB Quality Assurance Classification:

N Accident Service & Seismic Category:

N/A Tech Spec Requirement:

N/A Upper Range Limit:

750 inches H20 Lower Range Limit:

0-125 inches H20 Calibrated Span:

0 to 197.5 inches H20 - static pressure corrected Operating Span:

0 to 200 inches H20 at 100 gpm Output Signal:

4-20 mA, Corresponding to 0- 100 gpm Calibration Period:

24 months Accuracy (A2):

+/- 0.25 % calibrated span Calibration Accuracy:

+/- 0.5 %

Stability (Drift, D2):

+/- 0.25 % of URL for 6 months [2a]

Temperature Effect (DTEl), per 100°F

+/- 1.5% of URL per 100 'F

+/- 2.5 % for low range (URIJ6)

This taken to be equal to 2.4 % at 197.5 inches H20 span Temperature Normal Operating Limits:

(-)40 to 150 *F (Amplifier)

Overpressure Effect:

Zero shift of less than +/- 2.0 %

Static Pressure Zero Effect:

+/- 0.5 % of upper range limit for 2000 psi Static Pressure Span Effect (SPNE2):

(-) 0.5 % +/- 0.1% input reading per 1,000 psi. This is a systematic error which can be calibrated out for a particular pressure before installation.

I Page 15 of 94

LE-01 13 Revision 1

. Exeltn.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 Table 2-12.

CRD Hydraulic System Differential Pressure Transmitter Seismic (vibration) Effect (SEIS2):

+/- 0.05 % of URL per g at 200 Hz in any axis.

Power Supply Effect (PSE2):

< 0.005 % of calibrated span per volt.

Mounting Position Effect:

No span effect. Zero-shift can be calibrated out.

EMI/RFI Effect:

Not Specified Response time (damping):

Not Specified Harsh temperature effect (HTE2):

Not Applicable Humidity limits:

0 to 100 % RH Safety Classification:

Non-safety related Radiation Effect (e2R):

Not Specified 2.4.4 CRD Hydraulic System Flow Signal Resistor Unit (Ref. 4.1.1, 4.5.12, Attachment 12, and 4.7.3):

Table 2-13.

CRD Hydraulic System PPC Precision Signal Resistor Unit 2.4.5 Dwg. Designation:

8 f Device Type:

Precision signal resistor unit (wire-wound).

Manufacturer/Model No.:

Bailey Type 766 Selected Range:

8 Ohm Accuracy:

+/- 0.008 ohm (+/- 0.1 %)

Safety Classification:

N/A Temperature Effect:

+/- 0.5 % for 40 - 120'F Input Signal Range:

4 to 20 mAdc CRD Hydraulic System Flow PPC I/O (Refs. 4.5.8, 4.5.12, and Attachment 4):

Table 2-14.

CRD Hydraulic System PPC Analog Input Card Unit 1 Component I.D.:

A1711 Location:

10-C603 (H12-P603)

Device Type:

PPC - Potentiometer (Analog) Input Card Manufacturer/Model No.:

Analogic/ANDS5500 Quality Classification:

N/A Accident Service & Seismic Category:

N/A Tech Spec Requirement:

N/A Selected Full Scale Span:

+/- 160 mV Page 16 of 94

OMme6n.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 LE-01 13 Revision 1 Table 2-14.

CRD Hydraulic System PPC Analog Input Card Unit 1 Calibration Span:

(-) 160 mV to (+) 160 mV Calibration Period:

24 months Accuracy (A3):

+ 0.5 % of full scale span Calibration Accuracy:

N/A Input Impedance (resistance):

10 Meg Ohms Analog to Digital Converter:

Not Specified Power Supply Effect (PSE3):

N/A EMI/RFI Effect:

N/A Operating Temperature Limits:

32 to 122 -F (0 to 50 -C)

Humidity limits:

Not Specified Safety Classification:

Non Safety-Related 2.4.6 CRD Hydraulic System Flow Process Parameters (Refs. 4.3.2 and 4.8.5):

Process Temp Maximum: 150 *F Process Temp Minimum: 45°F

The minimum water temperature is based on the CST being outside and exposed to winter elements.

The maximum temperature is based on 140'F of the condensate and condenser system plus 10'F nominal heat addition from the CRD Water pump. (Ref. 4.3.2) 2.4.7 CRD Hydraulic System Local Service Environments (Ref. 4.4.2):

Table 2-15.

CRD Hydraulic System Local Service Environments Flow Transmitter Plant Process Computer Area / Room.

Area 015 / Room 402 Area 008 - Control Room Location Room 402 Control Room (Comp. Rm. 553)

Normal Temp. Range ('F) 65 min / 106 max / 90 norm 65 min / 78 max / norm N/A Normal Pressure

(-) 0.25 inches WG

+ 0.25 inches WG Normal Humidity (RH %)

50 average / 90 maximum 50 average / 90 maximum Radiation 1.OOE-01 Rads/hr, 3.51 E+04 TID N/A Page 17 of 94 I

LE-0113 Revision 1 Exel6n.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 2.5 RECIRCULATION PUMP MOTOR UNCERTAINTY 2.5.1 Recirculation Pump Motor Loop Diagram Each analyzed instrument loop consists of a Watt Transducer, and a PPC input/output (I/O) module.

The uncertainty magnitude of the CT and PT is negligible for this calculation.

PT CT Potential Current Transformer Transformer Watt Transducer PPC Analog Input Card Computer Points - Al 725 & Al 726 2.5.2 Recirculation Pump Motor Watt Transducer (Ref. 4.5.13 to 4.5.15, 4.6.6, Attachment 9, 4.9.5, and 4.9.7)

Table 2-16.

Recirculation Pump Motor Watt Transducer Component I.D.:

MT1A and MT1B Location:

10-C603 (H1I2-P603)

Device Type:

Watt Transducer Manufacturer/Model No.:

Ametek Power Systems/ XL3-1K5A2-25 Quality Classification:

N/A Accident Service & Seismic Category:

N/A Tech Spec Requirement:

N/A Rated Output (RO) 10.5 MW Current Input (Current Transformer):

0 - 5 Amps (1500/5)

Voltage Input (Potential Transformer):

0 - 120 V (4160/120)

Output Range:

0 - 1 mAdc Calibration Period:

24 months Accuracy (Al):

+/- (0.2% Reading + 0.01% Rated Output) at 0-200% Rated Output Stability (Drift, D1) per year:

+/- 0.1% RO, Non-cumulative Temperature Effect:

+ 0.005 % / ° C PF Effect on Accuracy

+/- 0.1% VA (maximum)

EMI/RFI Effect:

N/A Page 18 of 94

FFPcxe6n.

LE-0113 Revision I Reactor Core Thermal Power Uncertainty Calculation Unit 1 Table 2-16.

Recirculation Pump Motor Watt Transducer Operating Temperature Limits:

(-)4°F to 158 'F (-20' C to +70' C)

Operating Humidity:

0 to 95 % RH non condensing Safety Classification:

Non Safety-Related 2.5.3 Recirculation Pump Motor Watt Meter Transducer Precision Signal Resistor (Ref. 4.5.13 to 4.5.15, and 4.9.7):

2.5.4 Table 2-17.

Recirculation Pump Motor Watt Transducer PPC Precision Signal Resistor Unit Dwg. Designation:

R3A & R3B Device Type:

Precision signal resistor unit (wire-wound)

Manufacturer/Model No.:

GE/Type HR41D5B Selected Rating:

160 Ohm Accuracy:

+/- 0.1% of input signal range, 0.1 watt Safety Classification:

N/A Temperature Effect:

N/A Input Signal Range:

0- 1 mAdc Recirculation Pump Motor Watt Transducer PPC Analog Input Card (Ref. Attachment 4):

Table 2-18.

Recirculation Pump Motor Watt Transducer PPC Analog Input Card Unit 1 Component I.D.:

A1725 and Al 726 Location:

10-C603 (H12-P603)

Device Type:

PPC - Potentiometer (Analog) Input Card Manufacturer/Model No.:

Analogic/ANDS5500 Quality Classification:

N/A Accident Service & Seismic Category:

N/A Tech Spec Requirement:

N/A Selected Full Scale Span:

+/- 160 mV Calibration Span:

(-) 160 mV to (+) 160 mV Calibration Period:

24 months Accuracy (A2):

+/- 0.5 % of full scale span Page 19 of 94

WOmelein.

LE-0113 Revision 1I Reactor Core Thermal Power Uncertainty Calculation Unit 1 Table 2-18.

Recirculation Pump Motor Watt Transducer PPC Analog Input Card Unit 1 Input Impedance (resistance):

10 Meg Ohms Analog to Digital Converter:

Not Specified Power Supply Effect (PSE2):

N/A EMI/RFI Effect:

N/A Operating Temperature Limits:

32 to 122 'F (0 to 50 'C)

Humidity limits:

Not Specified Safety Classification:

Non Safety-Related Page 20 of 94

LE-0113 WP Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 3.0 ASSUMPTIONS AND LIMITATIONS 3.1 Standard practice is to specify calibration uncertainty in calculations equal to the uncertainty associated with the instruments under test (Ref. 4.1.1).

3.2 Instrumentation uncertainty caused by the operating environment's temperature, humidity, and pressure variations are evaluated when these error sources are specified by the instrument's vendor.

If the instrument's operating environment specifications bound the in-service environmental conditions where the equipment is located and separate temperature, humidity, and pressure uncertainty terms are not specified for the instrument, then these uncertainties are assumed to be included in the manufacturer's reference accuracy specification.

3.4 Published instrument vendor specifications are considered to be based on sufficiently large samples so that the probability and confidence level meets the 2cr criteria, unless stated otherwise by the vendor.

3.5 Seismic effects are considered negligible or capable of being calibrated out unless the instrumentation is required to operate during and following a seismic event.

3.6 The insulation resistance error is considered negligible unless the instrumentation is required to operate in an abnormal or harsh environment.

3.7 Regulated instrument power supplies are assumed to function within specified voltage limits; therefore, power supply error is considered negligible with respect to other error terms unless the vendor specifically specifies a power supply effect.

3.8 Measurement of CRD hydraulic system purge water temperature is found to be accurate within t 0.7 'F per Attachment 1. The enthalpy of water at the CRD normal operating pressure of 1448 psig as listed in P-300 (reference 4.4.1) and normal operating temperature of 97.2 *F (Table 2-1) are used to determine uncertainty of the CRD hydraulic system enthalpy because this is more conservative than using the higher temperatures normally found during operation.

3.9 The CRD system uses a Rosemount 1151 differential pressure transmitter (Section 2.4.3), which is mounted in a radiation exposure area. A radiation exposure effect is not specified for the Model 1151 transmitter; therefore the radiation effect applicable to this transmitter is assumed to be 10 % of span.

This assumption is considered conservative based on three factors: (1) periodic surveillance is performed on this transmitter and it is required to operate within 0.5 % of span or maintenance activities must be performed. Existing calibration records did not indicate anything unusual occurring with the calibration of these transmitters in this service. (2) A Rosemount Model 1153 series B transmitter is rated for radiation exposure and may be expected to have a radiation effect of +/- 4 % of upper range limit (URL) during and after exposure to 2.2 x 107 rad (Section 7.3.1.16). However, this exposure is over a 1000 times the expected exposure for the CRD system flow transmitter s during normal service. The estimated TID during normal service for the CRD flow transmitter is 3.51 x 104 rad (Section 4.4.2). The 10 % span estimated effect is more than an order of magnitude greater than the threshold for maintenance activity and of the same order of magnitude of the effect on a similar transmitter with 1000 times the exposure.

3.10 Interim results are rounded to the level of significance of the input data to avoid implying that a higher level of precision exists in the calculated values. For example, uncertainty may be specified by a supplier to one significant figure (e.g., 0.5 %). This value says that the level of significance associated with this uncertainty is one part in two hundred. The results are rounded when the numeric value of a result implies a higher level of significance than what the input data suggests.

Page 21 of 94

LE-01 13 Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 3.11 An uncertainty of +/- 10 psig is assumed for the feedwater pressure and the CRD outlet pressure to conservatively cover the variations in the actual steam dome or reactor vessel pressure. The variation in pressure has a negligible effect on the enthalpy of the feedwater.

3.12 An uncertainty of 10 % is assumed for the RPV thermal radiation heat loss term, QRAD, based on a review of calculation LM-0553 (Reference 4.8.3). LM-0553 determined the RPV heat loss by calculating the actual heat load in the drywell, subtracting the heat load attributed to any operating equipment in the drywell, and proportioning the heat load based on the shared chilled water system design flows assigned to Unit 1 drywell and Unit 2 drywell on a percentage basis. LM-0553 assumes Unit 1 and Unit 2 are operating at 100 percent power and the drywell air cooling fans are aligned as designed.

3.13 Steam table excerpts have been provided for convenience as Attachment 6, National Institute for Standards and Technology (NIST) Thermophysical Properties of Water, as extracted from the NIST fluid properties WebBook (Reference 4.9.3). For conservatism, factors of one-half the least significant figure in the tables are used for the interpolation error. The factors are 0.05 Btu/ibm for vapor and 0.005 Btu/Ibm for liquid.

Page 22 of 94 I

LE-0113 Reactor Core Thermal Power Uncertainty Revision I

__________________Calculation Unit 1

4.0 REFERENCES

4.1 METHODOLOGY 4.1.1 CC-MA-103-2001, Rev 0, "Setpoint Methodology for Peach Bottom Atomic Power Station and Limerick Generating Station 4.1.2 IC-1 1-00001, Rev. 4, Calibration of Plant Instrumentation and Equipment 4.2 PROCEDURES 4.2.1 ST-2-044-400-1, Rev. 23, Reactor Water Cleanup High Differential Flow Isolation Calibration 4.2.2 IC-C-1 1-00307, Rev. 5, Calibration of Rosemount Model 1153 and 1154 Transmitters 4.3 DESIGN BASIS DOCUMENTS 4.3.1 L-S-11, Rev. 15, DBD Feedwater System 4.3.2 L-S-15, Rev. 10, DBD Control Rod Drive System 4.3.3 L-S-19, Rev. 10, DBD Recirculation System 4.3.4 L-S-36, Rev. 10, DBD Reactor Water Makeup System 4.3.5 L-S-42, Rev. 09, DBD Nuclear Boiler System 4.4 SPECIFICATIONS, CODES, & STANDARDS 4.4.1 P-300, Rev. 45, Specification "Piping Materials and Instrument Piping Standards" 4.4.2 M-171, Rev. 16, Specification for Environmental Service Condition LGS Units 1 & 2 4.5 LIMERICK STATION DRAWINGS 4.5.1 M-06 Sheet 3, Rev. 58, P&ID Feedwater 4.5.2 M-23 Sheet 4, Rev. 33, P&ID Process Sampling 4.5.3 M-41 Sheets 1/2, Rev. 46/62, P&ID Nuclear Boiler 4.5.4 M-42 Sheets 1/2, Rev. 41/34, P&ID Nuclear Boiler Vessel Instrumentation 4.5.5 M-43 Sheets 1/2, Rev. 48/39, P&ID Reactor Recirculation Pump 4.5.6 M-44 Sheets 1/2, Rev. 56/47, P&ID Reactor Water Clean-up 4.5.7 M-45 Sheet 1, Rev. 30, P&ID Cleanup Filter and Demineralizer 4.5.8 M-46 Sheet 1, Rev. 51, P&ID Control Rod Drive Hydraulic-Part A 4.5.9 M-47 Sheet 1, Rev. 45, P&ID Control Rod Drive Hydraulic-Part B 4.5.10 B21-1050-E-008, Rev. 13, Elem. Diagram Steam Leak Detection Schematic 4.5.11 G31-NO1I-C-003, Rev 002,. Purchased PT. ORF. PLT. SH 1 4.5.12 C1 1-1060-E-002, Rev. 23, Elem. Diagram. CRD Hydraulic System, LGS U1 4.5.13 B32-1030-E-050, Sheet 18, Rev. 5, Elem. Diag. Reactor "A" Recirc Pump an MG Set, Unit I Page 23 of 94 I

LE-0113 Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 4.5.14 B32-1030-E-050, Sheet 19, Rev. 4, Elem. Diag. Reactor "B" Recirc Pump an MG Set, Unit 1 4.5.15 B32-1030-E-050, Sheet 3, Rev. 7, Elem. Diag. Reactor "A" & "B" Recirc Pump an MG Set, Parts List, Unit 1 4.5.16 G31-1040-E-003, Rev. 28, Elementary Diag. Reactor Water Cleanup System, Unit 1 4.5.17 C32-1020-E-003, Rev. 33, Elem. Diag. Feedwater Control System, Unit 1 4.5.18 B21-1040-E-003, Rev. 21, Elem. Diag. Nuclear Boiler*Process 4.5.19 E-0701, Sheets 6/16, Rev. 9/8, Schematic & Connection Diagram NSSS/BOP Computer Analog Inputs, Unit 1 4.5.20 G31-1030-G-001, Rev. 20, Process Diagram Reactor Water Clean-Up System (High Pressure) 4.5.21 B32-C-001-J-023, Rev. 1, Recirculation Pump Curve (Attachment 10) 4.6 GENERAL ELECTRIC (GE) DOCUMENTS 4.6.1 C11-4010-H-004, Rev. 13, Control Rod Drive System 4.6.2 C11-N003-C-001 Rev 002 PPD-Flow Nozzle 4.6.3 C11-3050-H-001, Rev. 14, CRD Instrumentation System 4.6.4 G31-3050-H-001, Rev. 26, Reactor Water Clean-Up System 4.6.5 B21-3050-H-001, Rev. 27, Nuclear Boiler System 4.6.6 B32-3050-H-001, Rev. 6, Reactor Recirculation System 4.7 VENDOR INFORMATION 4.7.1 M-1-B32-CO01-K7, Recirculation Pump Vendor Manual 4.7.2 Rosemount Product Data Sheet 00809-0100-4302, Rev BA, January 2008, Rosemount 1153 Series B Alphaline@ Nuclear Pressure Transmitter 4.7.3 A41-801O-K-01 8.6 - Bailey Signal Resistor Unit (SRU) Type 766 (Attachment 12) 4.7.4 Rosemount Inc., Instruction Manual 4259, Model 1151 Alphaline A Flow Transmitter, 1977 (Attachment 11) 4.7.5 C95-0000-K-002(1 ).2 - ANDS4810 - Data Acquisition System Instruction Manual 4.7.6 Rosemount Specification Drawing 01153-2734, "N0039 Option - Combination N0016 & N0037" (Attachment 13) 4.7.7 Rosemount Product Data Sheet 00813-0100-2655, Rev. AA June 1999 "N-Options for Use with the Model 1153 &l 1154 Alphaline Nuclear Pressure Transmitters" (Attachment 14) 4.7.8 Fluke 8050A - Digital Multimeter Measurement P/N 530907 Rev 2 1984, Instruction Manual 4.7.9 Ametek Power Instruments, Digital & Analog Transducers, Power Measurement Catalog, Scientific Columbus Exceltronic AC Watt Transducer Specification (Attachment 9) 4.8 CALCULATIONS AND ENGINEERING ANALYSIS 4.8.1 LM-547, Rev. 2, Reactor Core Thermal Power Calculation Correction for Unaccounted Flow to Reactor Vessel Page 24 of 94 I

LE-01 13 Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 4.8.2 LM-552, Rev. 7, Reactor Heat Balance Calculation for Limerick Units 1 & 2 4.8.3 LM-553, Rev. 0, Determination of the Reactor Pressure Vessel (RPV) Heat Loss 4.8.4 EE-94LGS, Rev. 16, Proper Calibration of Feedwater Elements FE-006-1(2)N001A, B, C (GE SIL 452) 4.8.5 LM-562, Rev. 2, CRD Flow Rates and System Pressures 4.8.6 LEAE-MUR-0001, Rev. 1, Bounding Uncertainty Analysis for Thermal Power determination at Limerick Unit 1 Using the LEFM,v+ System 4.8.7 Deleted 4.8.8 LE-01 16, Rev. 0, Reactor Dome Narrow Range Pressure Measurement Uncertainty 4.8.9 Deleted 4.9 OTHER REFERENCES 4.9.1 ASME, "Fluid Meters Their Theory and Application" Sixth Edition, 1971.

4.9.2 Limerick Updated Final Safety Analysis Report, R14 4.9.3 Lemmon, E.W., McLinden, M.O., and Friend, D.G., "Thermophysical Properties of Fluid Systems", in NIST Chemistry WebBook, NIST Standard Reference Database Number 69, Eds. P.J. Linstrom and W.G. Mallard, National Institute of Standards and Technology, Gaithersburg MD, 20899, http://webbook.nist.gov, (retrieved January 22, 2010) (Attachment 6) 4.9.4 NUREG/CR-3659, Dated January 1985, NRC Guidance, A Mathematical Model for Assessing the Uncertainties of Instrumentation Measurements for Power and Flow of PWR Reactors 4.9.5 Plant Information Management System (PIMS) Data 4.9.6 TODI Tracking No: SEAG #09-000167, Plant Process Computer Data of various plant parameters, to support Core Thermal Power Uncertainty Calculations, Station/Unit(s) U1/U2, 9/3/09 4.9.7 IISCP (Improved Instrument Setpoint Control Program) Datasheets) Version 7.5 4.9.8 Edwards, Jerry L. Rosemount Nuclear Instruments letter in reference to "Grand Gulf Nuclear Station message on INPO plant reports, subject Rosemount Instrument Setpoint Methodology, dated March 9, 2000". Letter dated 04/04/2000. (Attachment 3) 4.9.9 TODI A169446-80, Source Document "Steam Carryover Fraction on Process Computer Heat Balance Calculations" (Attachment 2) 4.9.10 TODI Al 695446-87, Source Document "GE Task Report T0100, December 2009, Revision 1" (Attachment 5) 5.0 IDENTIFICATION OF COMPUTER PROGRAMS The results of calculations by special computer programs were not directly used in this design analysis.

Microsoft@ Office Excel 2003 SP 3 was used to confirm the arithmetic results.

Page 25 of 94 I

LE-01 13 Revision 1I Exelein.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 6.0 METHOD OF ANALYSIS 6.1 METHODOLOGY The methodology used to calculate Section 6 is based on CC-MA-103-2001, "Setpoint Methodology for Peach Bottom Power Station and Limerick Generating Station" (Ref. 4.1.1).

These are non-safety-related indication loops, but the indication is used to calculate Core Thermal Power, which is a licensing limit. This analysis will use the Square Root of the Sum of the Squares (SRSS) methodology for combining the random and independent uncertainties. The dependent uncertainties will be combined according to their dependency relationships and biases will be algebraically summed in accordance with the Reference 4.1.1. The level of confidence for each uncertainty will be normalized to a 2a confidence level.

6.2 CORE THERMAL POWER (CTP) CALCULATION:

The process computer provides a calculation of the CTP based on a system heat balance, where CTP is the difference between the energy leaving the system and the energy input into the system from energy sources external to the core. The process computer steady state reactor heat balance equation is based on a summation of all heat sources raising the inlet feedwater and other cold water to steam exiting the pressure vessel. Figure 5-1 shows the Limerick heat balance control volume.

Figure 5-1, Limerick Heat Balance Control Volume Diagram Page 26 of 94

LE-0113 Reactor Core Thermal Power Uncertainty Revision I

_Calculation Unit 1 CTP = Energy out - Energy in (Equation 1)

Energy in = QFW-1N + QCRD-IN + QP (Equation 2)

Energy out = Qs.Fw + QOCRD-OUT + QRAD + QRWCU (Equation 3)

Where, CTP Core Thermal Power generated by nuclear fuel QFW-IN Energy of feedwater required to raise inlet FW to Steam Energy of CRD purge water and recirculation pump seal purge water QCRO-IN going to feedwater Qp Heat added by the recirculation pumps QS-FW Energy of steam from feedwater supply QCRD-OUT Energy of CRD purge water and recirculation pump seal purge water going to steam QRAD Radiative heat losses from the reactor pressure vessel Heat removed by the RWCU system regenerative heat exchangers QRwcu (includes both a heat removal term and a heat additions term) 6.2.1 Energy In Each of the above heat contributors are individually evaluated as follows:

6.2.1.1 Energy of feedwater (QFw-IN) is equal to the feedwater mass flow rate (WFw) multiplied by the enthalpy of the water at the bulk temperature of the feedwater (hFw(TFw)) entering the reactor. Changes to the bulk temperature of the feedwater due to the influx of recirculation water and RWCU water are ignored because these mass flows represent less than 1 % of the total mass flow and the temperature change caused by their influx negligible.

QFW-IN = wFW-hF(TFW)

(Equation 4) 6.2.1.2 Energy of Control Rod Drive purge water and recirculation pump seal purge water (QcRD.[N) is taken to be fixed at the enthalpy of water for a given temperature and pressure.

QCRO-IN = WCRD" hF(TcRo)

(Equation 5) 6.2.1.3 Energy of recirculation pumps (Qp)

Energy of recirculation pumps (QF) is taken as the number of pump motors (n) multiplied by the efficiency of the pump motors (qrm) multiplied by the power of the pump motors (WE). This is a conservative value because the combined net energy of the two recirculation pump motors contributes to the energy of the recirculation water. This estimate is fixed relative to CTP because relatively large random variations in Qp will be negligible compared to QFW.

Qp= n,

- WE (Equation 6)

Page 27 of 94

LE-0113 FF=

Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 6.2.2 Energy out 6.2.2.1 Energy of Steam Energy of steam from feedwater (Qs.Fw) is equal to the feedwater mass flow rate (WFw) multiplied by the enthalpy (hG(Ps)) of the steam (hG) at the steam dome pressure (Ps). The moisture carryover mass fraction is conservatively set to 0 (See Attachment 2).

Qs-Fw = WFW-hG(Ps)

(Equation 7) 6.2.2.2 Energy of CRD Purge Water In a Boiling Water Reactor (BWR), the energy of CRD purge water and recirculation pump seal purge water going to steam (QCRO-OUT) is equal to the mass flow rate of control rod drive and recirculation pump seal purge water (WcRD) multiplied by its enthalpy. However, the Feedwater mass flow rate will makes up greater than 99 % of the steam mass flow rate; therefore, WCRD will be quantified as a fixed number because relatively large random variations in WCRD will be negligible in determining Qs.

QCRD-OUT r WCRD-hG(Ps)

(Equation 8) 6.2.2.3 Energy of Reactor Pressure Vessel Radiative Heat Loss Energy of reactor pressure vessel radiative heat loss (QRAo) includes both heat loss due to thermal radiation as well as heat loss through convection. This value is fixed relative to CTP because relatively large random variations in ORAD will be negligible in determining Qs.

6.2.2.4 Energy of Reactor Water Clean-up Energy of reactor water clean up (QRwcu) is based on the net heat removed by the non-regenerative heat exchanges from the recirculated water stream bypassed from Recirculation Loop B to the RWCU.

The actual contribution to the heat removed from the reactor pressure vessel is negligible because the non-regenerative heat exchangers cool the stream going to the cleanup filters and demineralizers and the regenerative heat exchangers use the incoming stream to reheat the RWCU flow back up to the feedwater temperature. The mass flow rate is equal to the nominal pump flow rate the higher of Pump A or the combination of Pump B & C. The pump flow rate is fixed relative to CTP because relatively large random variations in QRwcu will be negligible in determining Qs. The net heat removed is equal to the mass flow rate (WRwcu) multiplied by difference of enthalpies across the RWCU.

QRWCU = WRWCU - [hF(TRPV) -

hF(TFw)]

(Equation 9) 6.2.3 Heat Balance Equation The reactor heat balance is based on the principle that heat input to the reactor water equals heat out.

Substituting Equations 2 and 3 into Equation 1 yields:

(QS-FW + QCRD-OUT + QPAD + QRWCU) = CTP + (QFW-IN + QCRD-IN + QP)

(Equation 10)

Solving for CTP yields, CTP = (Qs-Fw + QCRD-OUT + QRAD + QRWCU) - (QFW-IN + QCRD-IN + QP)

- [WFW-hG(Ps) + WCRD hG(Ps) + QRAD + WRWCU - [hF(TRPv) - hF(TFw)l

- [w* - hF(TFw) + WCRD-hF(TcRD) + n. rim - W0]

(Equation 11)

Combining like terms, Page 28 of 94

RMcxeltn.

LE-0113 Revision I Reactor Core Thermal Power Uncertainty Calculation Unit 1 CTP = ((WFW - hG(Ps) - WFw. hF(Trw)] + [WORD hG(Ps) - WCRD-hF(TCRD)l

+ QRAD + WRWCU " [hF(TRPv) - hF(TFw)] - n. rnm WE]

(Equation 12)

CTP = WFW " [hG(Ps) - hF(TFw)] + WCRD* [hG(Ps) - hF(TCRD)]

+ QRAD + WRWCU -[hF(TRPv) - hF(TFw)I - n qrnm WE (Equation 13)

Equation 13 is the form of the equation used by the Plant Process Computer (PPC) to calculate CTP (Reference 4.8.2). The CTP can now be expressed as a function of WFW, hG(Ps), QCRD-OUT,

QRAD, QRWCU. hF(TFw), QCRD-IN, Qp.

CTP : If (WFW, hG(Ps), QCRD-OUT, QRAD, QRWCU, hF(TFw), QCRD-IN, QP)

(Equation 14)

Further simplification of Equation 14 can be made by setting variables with negligible input into the uncertainty of the CTP to constant values. The variables that have negligible contribution to the determination of the uncertainty of the heat from CTP are QCRD-OUT, QRAD, QRWCU, QCRD-IN, and Qp as discussed above (Sections 6.2.2.2, 6.2.2.3, 6.2.2.4, 6.2.1.2, and 6.2.1.3).

CTP = [WFw

hG(Ps) + QCRD-0UT + QRAD + QRWCUI -

[WFW

hF(TFw) + QCRD-IN + QP]

= WFW * [hG(Ps) - hF(TFw)] + (QCRD-OUT - QCRD-IN) + QRAD + QRWCU - QP (Equation 15) 6.2.4 Uncertainty Determination From NUREG/CR-3659 (Ref. 4.9.4), the standard uncertainty (uc) of a function (y) containing multiple statistically independent terms may be expressed as follows:

y = f(x1, x2,....

XN)

N=

N

Where, aIf ciaXi and ui(y) = I q-I U(Xi)

(Equation 17)

The standard uncertainty, uc, is multiplied by a coverage factor, k, which is equivalent to the number of standard deviations for a given confidence level toarrive at the measurement uncertainty U and the expected value of y, Y, is taken as y plus or minus the measurement uncertainty.

U = ku,,(y) and Y =y +/-U (Equation 18)

Page 29 of 94

a=cxelein, LE-0113 Revision 1I Reactor Core Thermal Power Uncertainty Calculation Unit 1 6.2.4.1 Standard Uncertainty for CTP The standard uncertainty for CTP can be determined by taking the square root of the sum of the squares of the partial derivatives of each subcomponent of CTP multiplied by the square of the uncertainties of the subcomponents as shown in Equation 19 (Reference 4.9.4).

aW T uFW

C T

) 2.

h

(

a aCTP

(

hGS

+

C 8 T ah CTP (Ih(TW )2 ]C+

2 (QCRD-OUT

?

F (TF

)

j

)C O

U

[n rCTD

.1H CT

'2 UCTP -

(Equation 19) l CRu

_IN) t.I aQpD I

¶[CCTP j2 *(7RWU

+ [CaCTP1)

OQ

ýRWCU p

The partial derivative terms can be solved for by recalling CTP from Equation 15.

CTP = W~v. (hG(Ps) - hF(TFw)) + (QoRO-OUT - QCRD-IN) + QRAD + QRWCU - QP The partial derivatives are determined from Equation 15 and shown below, remembering that the terms QCRD-OUT, QCRDIN, QRAD, QRWCU, and Qp are fixed relative to the determination of the uncertainty of CTP.

aCTP

-w = (hG (Ps) - hF (TFW))(Euto20 OWFw (Equation 20) a CTP L9 hG(PS)

(Equation 21) a CTP ThF(TFW)

WFW a CTP a Q CRDOUT 19CTP aQCRDIN 0 CTP a9 QRAD a CTP a QRWCU 9CTP aQp (Equation 22)

(Equation 23)

(Equation 24)

(Equation 25)

(Equation 26)

(Equation 27)

Page 30 of 94

EF0txelein.

LE-0113 Revision I Reactor Core Thermal Power Uncertainty Calculation Unit 1 The Feedwater mass flowrate uncertainty, crWFw, is equal to the measurement uncertainty as shown in Equation 28.

a WFw =UFw "WFW The steam enthalpy uncertainty, O'hG, is determined by Equation 29.

'PT I'

,II-0T 2 +(6h G o.2 + &_hG I 2

0 h So(PS, o)I TS

.2

-- 9 p

Substituting finite differences for the partial derivatives:

(Equation 28)

(Equation 29)

( AhG 2

UT 2+

(_ýh

.(J2

+ PAhG )2 Al0

.Ocrio 2 (Equation 30)

Noting that for saturated steam, pressure determines the temperature of the steam; thus, 0 T 0.

In addition, the steam tables used were derived from NIST Chemistry WebBook (Reference 4.9.3). The interpolation error for steam enthalpy, a' = +/- 0.05 Btu/Ibm.

O-h 6 (Pslo)=

S/AhG(Ps)_2, 0p2 + (Ah(o)Q 2

y

. 2 The Feedwater enthalpy uncertainty, O'hF, is determined by Equation 32.

(Equation 31)

Cyh, (TFW, PF, 1.)=

2 (ahF '~2

OT

+1l~

,-2 +

8hF I 2

y Olo)

".0 (Equation 32)

Substituting finite differences for the partial derivatives yields

=IC AhT J OT2

/.

'P\\

O2

/ **oJ."° CrT2 + Ah_ýo 2 +( Ah

~

ý A

T+

0 P + y j

01 The interpolation error for liquid enthalpy, 010 = +/- 0.005 BTU/Ib, and that the enthalpy of subcooled water varies with temperature and slightly with pressure; thus, cy,,(TFW, PF, 1.) =

0T 2 +

Ahp(P)

0hF 2

~

2

01 (Equation 33)

The following uncertainty terms are relatively insignificant in the determination of CTP uncertainty; therefore, it is only necessary to quantify the uncertainty to within a reasonably conservative value.

Refinement of the uncertainty of these items after this initial determination is not required given that the uncertainty is within the tolerances shown in the sensitivity analysis (See Attachment 7).

The Control Rod Drive (CRD) outlet energy uncertainty, O-QCRD OUT, is determined by Equation 34, where XCRg is the uncertainty calculated for the CRD flow stream.

CrOCRD-OUT

= XCRD % -QCRD OUT (Equation 34)

Page 31 of 94

LE-0113 Elm Reactor Core Thermal Power Uncertainty Revision 1

_______________I Calculation Unit 1 The CRD inlet energy uncertainty, 00CRIN, is determined by Equation 35, where XCRD is the uncertainty calculated for the CRD flow stream.

0OCRO.N

= XCRD %* QCRDIN (Equation 35)

The reactor pressure vessel heat loss uncertainty, ORJRAD, is determined by Equation 36, where XRAD is the uncertainty assigned to the heat loss value calculated by LM-0553 (Reference 4.8.3).

CO'RAD

= XRAD %* QPZA (Equation 36)

The RWCU heat removal uncertainty, CORWCU, is determined by Equation 37, where xawcu is the uncertainty calculated for the RWCU heat balance terms.

0QRWCU = XRWCU %" QRwcu (Equation 37)

The Recirculation Pump heat addition uncertainty, oQp, is determined by Equation 38, where xp is the uncertainty calculated for measurement of the recirculation pump motor power.

(yap =Xp%*Qp (Equation 38) 6.2.5 Extended Instrument Drift Instrument drift specifications are usually published for a defined period of time. The instrument drift for one period of time is independent from the instrument drift of any other equivalent period of time.

Therefore, the drift specification D for a period of X months can be expanded to n.X months (where n is the station surveillance interval divided by the vendor drift interval and n is an integer greater than zero) by the SRSS method. Instrument drift for surveillance intervals exceeding the instrument suppliers' specified drift interval is calculated using Equation 39 (Section 4.1.1 of reference 4.1.1,).

Dn = [n. (Dx) 211/ 2 (Equation 39)

Page 32 of 94

LE-0113 Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 7.0 NUMERIC ANALYSIS 7.1 FEEDWATER FLOW UNCERTAINTY The uncertainty of the feedwater mass flow rate measurement for the Caldon Ultrasonics Leading Edge Flow Meter CheckPlus (LEFM/+) system is taken from Reference 4.8.6, Section 2.0, using Equation 28.

WFw = UFW measurement

WFW = 0.28 %

WFW

= 0.0028

15,255,000 Ibm/hr

= 42,714 Ibm/hr 7.2 STEAM DOME PRESSURE MEASUREMENT UNCERTAINTY The uncertainty of the steam dome pressure measurement is taken from Reference 4.8.8.

-ps = +/- 20 psig 7.3 REACTOR WATER CLEAN-UP (RWCU) FLOW LOOP UNCERTAINTY 7.3.1 RWCU Flow Loop Accuracy (LARWCU Flow) 7.3.1.1 RWCU Flow Element Reference Accuracy (Al)

Reference Accuracy is specified as +/- 1.50% of actual rate of flow (Section 2.2.3).

Al 2o

=

+/- 1.50% Flow 7.3.1.2 RWCU Flow Element Installation Effect (IE1)

The flow elements meet the installation requirements of Ref. 4.6.5. Therefore, IE1

= +/- 0.50% Flow 7.3.1.3 RWCU Flow Element Temperature Effect on Flow Element Expansion (TN1)

Per section 2.2.3, the maximum temperature of the water passing through the flow element is 582 *F and the normal temperature is 539 'F with the flow elements located just upstream of the RWCU Recirculation Pumps. Since the system temperature operation band is small, there is a minor change in the flow element expansion factor. The change is in order of 0.003 inches or less for the temperature range of 515 'F to 560 'F. Therefore the temperature effect on flow element expansion can be neglected.

TN1

= +/- 0% Flow 7.3.1.4 RWCU Flow Element Temperature Effect on Density (TD1)

During normal operations the temperature of the fluid passing through the flow element at the inlet of the RWCU system is approximately 535.3 *F. The effect temperature has on density will be evaluated at +/- 4.37 'F (Section 7.4.6) from the base condition of 535.3 *F at 1060 psig (1074.7 psia) at the flow element (Section 2.2.3). Density is relatively constant at 1060 psig; however, for conservatism a variation of +/- 10 psig is used to show that the pressure effect is negligible even at four times the nominally specified transmitter reference accuracy of 0.25 %. The uncertainty in the density, cp(T,P),

as a function of temperature and pressure will follow Equation 33. Density values are from Reference 4.9.3 (printout included as Attachment 6).

Page 33 of 94 I

LE-0113 Reactor Core Thermal Power Uncertainty Revision I nCalculation Unit 1 IIbm (Ibm o'(TRwU)= 0.

9 0

ft__

t Divide

- p(530.9) 3°F

+ psi 070)-p(050) t c

v t o p

c ia v upsi

)

.(TRWcu) 5997

(

1070)-1050 psi Ibm2j Ib j(46.693-47.275)

.4 V

(4.94 4690 (10'siY2

The percent change in density, ax, as a function of the percent change in flow, 0 1, is given by the following equation (Reference Attachment 8, Equation A8-10):

Rearranging Equation A8-10 and substituting a*, for ax to solve for the unknown flow uncertainty, o*:

TD flow 2 "TMD 9

%density

=-. 0.619%

2

-0.309 %

TDloo,%ow

=

0.3 %Fof flow 7.3.1.5 RWCU Flow Element Humidity Error (elH)

The flow element is a mechanical device installed within the process. Therefore, humidity effects are not applicable.

elH

=0 7.3.1.6 RWCU Flow Element Radiation Error (eAR)

The flow element is a mechanical device stinstal within the process. Therefore, radiation effects are not applicable.

elR

=

0 7.3.1.7 RWCU Flow Element Seismic Error (elS)

For normal error analysis, normal vibrations and seismic effects are considered negligible or capable of being calibrated out. Therefore, there is no seismic error for normal operating conditions (Section 3.5).

elSow 0

Page 34 of 94

LE-0113 FPO Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 7.3.1.8 RWCU Flow Element Static Pressure Offset Error (eISP)

The flow element is a mechanical device installed within the process. Therefore, static pressure effects are not applicable.

e1SP

=

0 7.3.1.9 RWCU Flow Element Ambient Pressure Error (el P)

The flow element is a mechanical device installed within the process. Therefore, therefore the flow element is not subject to ambient pressure variations.

elP

=

0 7.3.1.10 RWCU Flow Element Process Error (elPr)

Any process errors have been accounted for as errors associated with Temperature Effect on Density.

Therefore, elPr

=

0 7.3.1.11 RWCU Flow Element Temperature Error (e 1T)

Temperature error is considered to be a random variable for the flow elements and is addressed under Temperature Effect on Flow Element Expansion (Section 7.3.1.3). Therefore, elT

=

0 7.3.1.12 RWCU Flow Transmitter Reference Accuracy (A2)

Reference Accuracy is specified as +/- 0.25 % of span considered to be a 3a value (Section 2.2.4). The reference accuracy is set to the calibration accuracy per plant procedure (Reference 4.1.1).

A23o

=

+/- 0.50 % [3a]

Converting to a 2cr value A22o

+/- 0.50 %

2 / 3 A2 2o

=

+/- 0.3333 % of span Converting % span to % flow Rearranging Equation A8-10, crap = 2

GFLOW, to solve for flow (Reference Attachment 8):

A 2 2a%FIow

=

A 2 %Span / 2

=

+0.3333 % of span / 2

+/- 0.1667 % of Flow A 2 2o,%oFow

=

- 0.1667 % of Flow 7.3.1.13 RWCU Flow Transmitter Power Supply Effects (u2PS2)

Power supply effects are considered to be negligible (Section 3.7). Therefore, a2PS2 =

+/-0 Page 35 of 94

LE-0113 Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 7.3.1.14 RWCU Flow Transmitter Ambient Temperature Error (GF2T)

The temperature effect is +/- (0.75 % URL + 0.5 % span)/100°F [3cF] (Section 2.2.4). The maximum temperature at the transmitter location is 106 'F, and minimum temperature during calibration could be 65 'F, so the maximum difference = 106 -65 OF = 41 OF (Section 2.3.4) cy2T 3,

=

+/- [(0.0075

750 INWC + 0.005

220 INWC)

41 -F/ 100 -F]

=

+/- [(5.625 1NWC + 1.1 INWC)

0.41]

a2T3a

=

+ 2.76 INWC [3a], rounded to level of significance Converting to a 2or value (y2T 20,

=

+/- 2.76 INWC

2 / 3 a2T2a

=

+/- 1.8382 INWC Converting to % span iy2T 2.

=

+/- 1.8382 INWC / 220 INWC

=

+/- 0.008355 = 0.8355 %

Converting % span to % flow Rearranging Equation A8-10, aAP = 2

UFLOW, to solve for flow (Reference Attachment 8):

o'2 T2o%FIow

=

a 2T2oSpan / 2

+/- +0.8355 % 12

+/- +/-0.4178 %

a2T2oF/ow

=

+/- 0.418 %

7.3.1.15 RWCU Flow Transmitter Humidity Error (e2H)

The manufacturer specifies the transmitter operating humidity limits between 0 and 100 % RH (Section 2.2.4). The transmitter is located in Containment H2 Recombiner Room 506C, Area 16 where humidity may vary from 50 to 90% RH (Reference 4.4.2). Humidity errors are set to zero because they are considered to be included within the reference accuracy specification under these conditions.

(Section 3.2) e2H

=

0 7.3.1.16 RWCU Flow Transmitter Radiation Error (e2R)

The manufacturer specifies the transmitter operating radiation effect during and after exposure to 2.2 x 107 rads TID (Section 2.2.4). The transmitter is located in Containment H2 Recombiner Room 506C, Area 16, where total integrated dose (TID) could be as high as 8.78 x 102 rad (Reference Section 4.4.2). Therefore, e2R

+/- (4.0 % of URL)

dose / rated dose

=

+/- (0;04.750 INWC)

8.78 x 102 / 2.2 x 107

=

+/- 30 INWC

3.99 x 10-5 e2R

=

+/- 1.20 x 10-3 INWC Converting to % span e2Rspa

=

+/- 1.20 x 10 3INWC /220 INWC

+/- 5.44 x 10"6 = 5.4 4 x 104 b%

Page 36 of 94

LE-01 13 Reactor Core Thermal Power Uncertainty Revision 1 Calculation Unit 1 Converting % span to % flow Rearranging Equation A8-10, a,,p = 2

GFLOW, to solve for flow (Reference Attachment 8):

e2R %FIow

=

e2R %Span / 2

+/- +5.44 x 10"4 %/2

+/-

+2.72 x 10-4%

=

+/- 2.72 x 104 %, which is negligible e 2 R %FIow 0

7.3.1.17 RWCU Flow Transmitter Seismic Error (e2S)

The transmitter's accuracy is within +/- 0.5% of URL (upper range limit) during and after a seismic disturbance defined by a required response spectrum with a ZPA of 4 g's. A seismic event defines a particular type of accident condition. Therefore, there is no seismic error for normal operating conditions (Section 3.5) e2S

=

0 7.3.1.18 RWCU Flow Transmitter Ambient Pressure Error (e2P)

The flow transmitter is an electrical device and therefore not affected by ambient pressure.

e2P

=

0 7.3.1.19 RWCU Flow Transmitter Temperature Error (e2T)

Temperature error is considered to be a random variable for a Rosemount transmitter. Therefore e2T 0

7.3.1.20 RWCU PPC I/O Module and SRU Reference Accuracy (A3)

Reference accuracy of the computer input is taken to be the SRSS of the reference accuracies of the SRU and the I/O module. The reference accuracy of the SRU is 0.1 % of span (Section 2.2.5).

Reference Accuracy for the I/O module is specified as +/- 0.5 % of span (Section 2.2.6).

A32o

=0.12

+0.52 = 0.5099 = 0.51 % span Converting % span to % flow Rearranging Equation A8-10, YAp

= 2

CVFLOW, to solve for flow (Reference Attachment 8):

A 3%FIow A 3%span / 2

+/- +0.51%/2 A 3 %Flow

=

+/- 0.255 %

7.3.1.21 RWCU PPC I/O Module Humidity Error (e3H)

The manufacturer specifies the I/O module operating humidity limits between 0 and 95 % RH (Section 2.2.6). The I/O module is located in the Control Room 533, where humidity may vary from 50 to 90%

RH (Reference 4.4.2). Humidity errors are set to zero because they are considered to be included within the reference accuracy specification under these conditions (Section 3.2).

e3H 0

Page 37 of 94

LE-0113 Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 7.3.1.22 RWCU PPC 110 Module Radiation Error (e3R)

No radiation errors are specified in the manufacturer's specifications. The instrument is located in the Control Room 533, a mild environment (Section 4.4.2). Therefore, it is reasonable to consider the normal radiation effect as being included in the reference accuracy.

e3R

=

0 7.3.1.23 RWCU PPC I/O Module Seismic Error (e3S)

No seismic effect errors are specified in the manufacturer's specifications. A seismic event defines a particular type of accident condition. Therefore, there is no seismic error for normal operating conditions (Section 3.5).

e3S

=

0 7.3.1.24 RWCU PPC I/O Module Static Pressure Offset Error (e3SP)

The I/O module is an electrical device and therefore not affected by static pressure.

e3SP

=

0 7.3.1.25 RWCU PPC I/O Module Ambient Pressure Error (e3P)

The I/O module is an electrical device and therefore not affected by ambient pressure.

e3P

=

0 7.3.1.26 RWCU PPC I/O Module Process Error (e3Pr)

The I/O module receives an analog current input from the flow transmitter proportional to the pressure sensed. Any process errors associated with the conversion of pressure to a current signal have been accounted for as errors associated with Flow Element. Therefore, e3Pr

=

0 7.3.1.27 RWCU Flow Loop Accuracy (LARWCU_Flow)

LARwcu Flow

+/-+ [(A1)2 + (IE1) 2 + (TN1) 2 + (TD1) 2 + (elH)2 + (elR)2 + (elS)2 + (e1SP)2 + (e1P)2 +

(ell Pr l

+ (elT)2 + (A21 2 + (s2PS2)2 + (s2T)2 + (e2H)2 + (e2R)2 + (e2S) + (e2P) +

(e2T) + (A3)2 + (e3H) + (e3R)2 + (e3S)2 + (e3SP)2 + (e3P) 2 + (e3Pr) ]112 0+/-

[(1.5)2 + (0.5) 2 (O)2+ (0.3)2+(0)2 + (0)2 + (0)2 + (0)2 + (0)2 + (0)2 + (0)2 +(0.1667)2

+(0)2 +(0.418)2 (0)2 + (0)2 + (0)2 + (0)2 + (0)2 + (0.255)2 + (0)2 + (0)2 + (0)2 +(0)2 +

(0)2 + (0)2]1/2

= +/- 1.690425 %

LARwCU_Flow

+/-

+ 1.7 %

7.3.2 RWCU Flow Loop Drift (LDRWCU Flow) 7.3.2.1 RWCU Flow Element Drift Error (Dl)

The flow element is a mechanical device; drift error is not applicable for the flow elements. Therefore, D1

= +/- 0.00% Flow 7.3.2.2 RWCU Flow Transmitter Drift Error (D2)

Drift error for the transmitter is +/- 0.2% of URL / 30 months, taken as a random 2a value (Section 2.2.4). The calibration frequency is 2 years, with a late factor of 6 months.

D2 2.

=

+ (0.2%

URL)

Drift is applied to the surveillance interval (SI) using Equation 39 (Section 6.2.5) as follows Page 38 of 94

LE-0113 Reactor Core Thermal Power Uncertainty Revision 1

_Calculation Unit 1

D22,

=

+ [n (D2)2]112,

=

4 ([(24 months + 6 months) / 30 months]- [0.002 URL] 2)112

+/- ([(30 / 30)]. [1.5 INWC]2)112 D2 20

=

+/- 1.50 INWC Converting to % span D2%span =

1.5 INWC / 219.8 INWC

+/- 0.00682439 = 0.682439 %

Converting % span to % flow Rearranging Equation A8-10, (Ap = 2

GRFow, to solve for flow (Reference Attachment 8):

D 2%FIow =

D2%Span / 2

+/- +0.682439% / 2

+/- +/-0.341219 %

D2%Flow =

+/- 0.34 %

7.3.2.3 RWCU Flow PPC I/O Module Drift Error (03)

The vendor does not specify a drift error for the I/O module. Therefore, per Ref. 4.1.1 Section I, it is considered to be included in the reference accuracy.

D3

+/-0 7.3.2.4 RWCU Flow Loop Drift (LDRWCU_Flow)

LDRwcu_Fow = [(D1 )2 + (D2)2 + (D3)2]12

= [(0)2 + (0.34)2 + (0)2]1/2

= +/- 0.341219 %

LDRWcUFlow = +/- 0.34 %

7.3.3 RWCU Flow Loop Process Measurement Accuracy (PMARWCU_Flow)

No additional PMA effects beyond the effects specified in the calculation of loop accuracy.

PMARWCU_Flow =

0 7.3.4 RWCU Flow Loop Primary Element Accuracy (PEARWCU Flow)

No additional PEM effects beyond the effects specified in the calculation of loop accuracy.

PEARWCU_Flow = 0 7.3.5 RWCU Flow Loop Calibration Accuracy (CARwcU_Flow)

Standard practice is to specify calibration uncertainty in calculations equal to the uncertainty associated with the instruments under test (Reference 4.1.1).

Therefore, CARWCU_Flow =

[(Al) 2 + (A2)2 + (A3)2]1/2

=

[(1.5 %)2

+ (0.1667 %)2 + (0.255 %)211I2 CARWCUFlow =

1.5 %

Page 39 of 94

LE-0113 Reactor Core Thermal Power Uncertainty Revision i M elon.________

Calculation Unit 1 7.3.6 Total Uncertainty RWCU Flow Loop (TURWCU-oFl,).

TURwcU_Flow = + [(LA)2 + (LD)2 + (PMA)2 + (PEA)2 + (CA) 2]112

= +/- [(1.7)2 + (0.34)2 + (0)2 + (0)2 + (1.5)21112

- + 2.29251%

TURwcu_Fl.o

= +/- 2.3 % of flow To convert 2.3% flow error to Ibm/hr rated flow of flow 0.1540 Mlbm/hr (Table 2-1):

Converting to Ibm/hr for water at rated conditions:

TEMASS

=

+/- (2.3 %)*(0.1540 Mlbm/hr)

TEMASS

=

+/- 3542 lbm/hr, or +/- 0.0035 MIbm/hr This value is entered into Table 2-1 for the uncertainty associated with RWCU flow.

Page 40 of 94

LE-0113 am Reactor Core Thermal Power Uncertainty Revision I m

elon.________

Calculation Unit 1 7.4 RWCU TEMPERATURE LOOP UNCERTAINTY 7.4.1 RWCU Temperature Loop Accuracy (LARWCUT) 7.4.1.1 RWCU Temperature Element Reference Accuracy (Al)

RWCU Temperature Element Reference Accuracy is provided in Section 2.3.1.

Al

+/-0.75 'F 7.4.1.2 RWCU Temperature Element Power Supply Effects (l PS)

Power supply effects are considered to be negligible (Section 3.7). Therefore, CIPS 0

7.4.1.3 RWCU Temperature Element Ambient Temperature Error (alT)

All thermocouple extension wire junctions are on adjacent terminals and are assumed to be at the same temperature. Therefore, for the thermocouple, cIT10= 0 7.4.1.4 RWCU Temperature Element Humidity Error (el H)

The manufacturer does not specify the thermocouple operating humidity limits (Section 2.3.1). The thermocouple is located in the RWCU System Room 506, where humidity may vary from 50 to 90%

RH (Reference 4.4.2). Humidity errors are set to zero because they are considered to be included within the reference accuracy specification under these conditions (Section 3.2).

elH 0

7.4.1.5 RWCU Temperature Element Radiation Error (elR)

No radiation errors are specified in the manufacturer's specifications. The instrument is located in the Control Room 533, a mild environment (Reference 4.4.2). Therefore, it is reasonable to consider the normal radiation effect as being included in the reference accuracy. Therefore, elR

=

0 7.4.1.6 RWCU Temperature Element Seismic Error (elS)

No seismic effecterrors are specified in the manufacturer's specifications. A seismic event defines a particular type of accident condition. Therefore, there is no seismic error for normal operating conditions (Section 3.5).

elS 0

7.4.1.7 RWCU Temperature Element Vibration Effect (elV)

The error due to vibration is considered to be negligible because it is small and unaffected by vibrations in the system.

elV

=

0 7.4.1.8 RWCU Temperature Element Static Pressure Error (elSP)

The thermocouple output is not subject to pressure variations.

elSPlo =

0 Page 41 of 94

LE-0113 IF Reactor Core Thermal Power Uncertainty Revision I Calculation'Unit 1 7.4.1.9 RWCU Temperature Element Ambient Pressure Error (elP)

The thermocouple is an electrical device and therefore not affected by ambient pressure.

elP

=

0 7.4.1.10 RWCU Temperature Element Temperature Error (elT)

The temperature error is assumed to be included in the reference accuracy (Reference 4.1.1).

Therefore, elT

=

0 7.4.1.11 RWCU Temperature Loop PPC 1/0 Module Reference Accuracy (A2)

Reference Accuracy is specified as +/- 3.0 'F (Section 2.3.3) and considered to be a 2a value (Section 3.4)

A2 2,

3.0 'F 7.4.1.12 RWCU Temperature Loop PPC 110 Module Humidity Error (e2H)

The manufacturer specifies the I/O module operating humidity limits between 0 and 95 % RH (Section 2.3.3). The I/O module is located in the Control Room 533, where humidity may vary from 50 to 90%

RH (Reference Section 4.4.2). Humidity errors are set to zero because they are considered to be included within the reference accuracy specification under these conditions. (Section 3.2) e2H

=

0 7.4.1.13 RWCU Temperature Loop PPC I/O Module Radiation Error (e2R)

No radiation errors are specified in the manufacturer's specifications. The instrument is located in the Control Room 533, a mild environment [Section 4.4.2]. Therefore, it is reasonable to consider the normal radiation effect as being included in the reference accuracy. Therefore, e2R

=

0 7.4.1.14 RWCU Temperature Loop PPC I/O Module Seismic Error (e2S)

No seismic effect errors are specified in the manufacturer's specifications. A seismic event defines a particular type of accident condition. Therefore, there is no seismic error for normal operating conditions (Section 2.8).

e2S 0

7.4.1.15 RWCU Temperature Loop PPC I/O Module Static Pressure Offset Error (e2SP)

The I/O module is an electrical device installed in the control room and is not subject to pressure effects.

e2SP

=

0 7.4.1.16 RWCU Temperature Loop PPC I/O Module Ambient Pressure Error (e2P)

The I/O module is an electrical device and therefore not affected by ambient pressure.

e2P

=

0 Page 42 of 94

LE-0113 FJW Reactor Core Thermal Power Uncertainty Revision I Calculation Unit I 7.4.1.17 RWCU Temperature Loop Accuracy (LARWcU Fow)

LARWCU T

= +/- [(Al) 2 + (aIPS)2 + (alT)2 + (elH)2 + (elR)2 + (elS)2 + (el V) 2 + (elSP)2 + (elp)2 +

(elT) + (A2)2 + (e2H) 2 + (e2R)2 + (e2S)2 + (e2Sp)2,+ (e2p)2]112

= + [(0.75)2 + (0)2 + (0

+ (0)2 + (0)2 + (0)2 + (0)2 + (0)2 + (0)2 + (3.0)2 + (0)2 + (0)2

+ (0)2 + (0)2 + (0)2]1/)

0 F

=+/- (0.5625 + 0 + 0 + 0 + 0 + 0 + 0 + 0 + 0 + 0 + 9.0 + 0 + 0 + 0 + 0 + 01112 °F

- +/- [9.5625 °F2] 112 LARWCUT

= +3.09 'F 7.4.2 RWCU Temperature Loop Drift 7.4.2.1 RWCU Temperature Element Drift Error (D1)

The error associated with the thermocouple is already included in the reference accuracy (Section 3.2). Therefore, for the thermocouple, D1

=

+0 7.4.2.2 RWCU Temperature Loop PPC t/O Module Drift Error (D2)

The vendors do not specify drift errors for the SRU and I/O module. Therefore, per Section 3.2, it is considered to be included in the reference accuracy.

D2 0

7.4.2.3 RWCU Temperature Loop Drift (LDRwcur)

LDRwcUT

= [(D1) 2 + (D2)2]112

= [(0)2 + (0)2]112

= +/-0.0 %

LDRWCUT

= +/- 0 %

7.4.3 RWCU Temperature Loop (PMARWcUT)

No additional PMA effects beyond the effects specified in the calculation of loop accuracy.

PMARwcu T = +/- 0 7.4.4 RWCU Temperature Loop (PEARWCUT)

No additional PMA effects beyond the effects specified in the calculation of loop accuracy.

PEARwcu T = 0 7.4.5 RWCU Temperature Loop Calibration Accuracy (CARWCUT)

Standard practice is to specify calibration uncertainty in calculations equal to the uncertainty associated with the instruments under test (Reference 4.1.1).

Therefore, CARWCUT

[(Al )2 + (A2)2 + (A3)21112

[(+/- 0.75 'F) 2 + (+/- 3.0 OF) 2]11 2 CARwcUT

=

+/- 3.09 'F Page 43 of 94

LE-01 13 90 Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 7.4.6 Total Uncertainty RWCU Temperature Loop (TURWCUT)

TURwCU_T

= + [(LA)2 + (LD) 2 + (PMA)2 + (PEA)2 + (CA) 2]V/2

= +/- [(3.09)2 + (0)2 + (0)2 + (0)2 + (3.09)211/2

=+4.370 IF TURWCUT

=+4.37 IF 7.5 CRD FLOW RATE UNCERTAINTY 7.5.1 CRD Flow Rate Loop Accuracy (LACRoFrow) 7.5.1.1 CRD Flow Element Reference Accuracy (Al)

The accuracy of the flow element is t 1% of actual rate of flow (Section 2.4.2).

Therefore, Al

=

+1%flow 7.5.1.2 CRD Flow Element Humidity, Radiation, Pressure, and Temperature Errors (elH, elR, elP, elT)

The flow element is a mechanical device mounted in the process and its output is not subject to environmental or vibration effects. Therefore; elH = elR = elP = elT = 0 7.5.1.3 CRD Flow Element Seismic Error (elS)

A seismic event is an abnormal operating condition and is not addressed by this calculation (Section 3.5). Therefore; elS 0

7.5.1.4 CRD Flow Element Static Pressure Error (elSP)

The flow element is constructed of stainless steel and is not affected by process pressure. Therefore, eISP

=

0 7.5.1.5 CRD Flow Transmitter Reference Accuracy (A2)

Reference Accuracy is +/- 0.25 % of span (Section 2.4.3). The reference accuracy is set to the calibration accuracy per plant procedure (Reference 4.1.1 ).

A2

=

+/- 0.50 %

Converting % span to % flow Rearranging Equation A8-10,

,p = 2

GFLOW, to solve for flow (Reference Attachment 8):

A 2 %FIow =

A 2 %span / 2

=

+/- 0.50 % of span /2

=

+/- 0.25 % of Flow A2%Flow =

+/- 0.25 % of Flow 7.5.1.6 CRD Flow Transmitter Power Supply Effects (a2PS)

Power supply effects are considered to be negligible (Section 3.7). Therefore, a2PS

=

+/-0 Page 44 of 94

LE-0113 Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 7.5.1.7 CRD Flow Transmitter Ambient Temperature Error (T2T)

The temperature effect is +/- 2.4 % of span per 100 'F at 197.5 INWC span (Section 2.4.3). The calibrated span is 197.5 INWC. The maximum temperature at the transmitter location is 106 IF, and minimum temperature during calibration could be 65 OF, so the maximum difference = 106 - 65 OF = 41 OF (Section 2.3.4).

a2T

=

[(0.024.197.5 INWC) / 100 OF].41 IF

[3a]

=

[ [(4.74 INWC)1100 IF].41 OF

=

+/- 1.943 INWC Converting to % span a2T20

=

1.943 INWC/ 197.5 INWC

=

+ 0.0098 Converting % span to % flow Rearranging Equation A8-10, cAp = 2

GFLOW, to solve for flow (Reference Attachment 8):

a 2 T2.%FIow

=

o 2 T2I%Span / 2

=

+/-0.98%/ 2

=

+0.49 %

O2T2 0 %FIow

=

+ 0.49 %

7.5.1.8 CRD Flow Transmitter Humidity Error (e2H)

The manufacturer specifies the transmitter operating humidity limits between 0 and 100 % RH (Section 2.4.3). The transmitter is located in the CRD Equipment Area, Room 402, where humidity may vary from 50 to 90% RH (Reference 4.4.2). Humidity errors are set to zero because they are considered to be included within the reference accuracy specification under these conditions. (Section 3.2) e2H

=

0 7.5.1.9 CRD Flow Transmitter Radiation Error (e2R)

Radiation error is assumed to be 10 % of span (Section 3.9).

e2R

=

10 % of Span

=

10 %. 197.5 INWC e2R

=

19.75 INWC Converting to % span a2R

+/- 19.75 INWC/ 197.5 INWC

+/- 0.10 = 10%

Converting % span to % flow Rearranging Equation A8-10, *p = 2

GROW, to solve for flow (Reference Attachment 8):

cT2RooFI

=

Y2 R2coosan / 2

=

+10.0% / 2

+/- +/- 5.00%

cI2RFIow

+/- 5.0%

Page 45 of 94

LE-0113 Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 7.5.1.10 CRD Flow Transmitter Seismic Error (e2S)

No seismic effect errors are specified in the manufacturer's specifications. A seismic event defines a particular type of accident condition. Therefore, there is no seismic error for normal operating conditions (Section 3.5) e2S

=

0 7.5.1.11 CRD Flow Transmitter Vibration Effect (e2V)

The error due to vibration is considered to be negligible because it is small and unaffected by vibrations in the system.

e2V

=

0 7.5.1.12 CRD Flow Transmitter Static Pressure Zero Error (e2SP)

The transmitter has a Zero Error of +/- 0.5 % of URL for 2000 psi (Section 2.4.3). The calibrated range shown in Table 2-12 shows the static pressure adjustment made to account for the span error effect.

Therefore, the total Static Pressure Error is e2SP

=

+/- 0.5 % of URL for 2000 psi The normal operating pressure (Table 2-11) is 1448 psig. Therefore, e2SP

=

+ 0.5 % 750 INWC. 1448 psig / 2000 psi

=

+2.715 INWC e2SP

=

+ 2.72 INWC, rounded Converting to % span cv2SP

=

+/- 2.72 INWC/200 INWC

=

+/- 0.01316 = 1.32 %

Converting % span to % flow Rearranging Equation A8-10, yp= 2

UFLOW, to solve for flow (Reference Attachment 8):

a2SPFIow

=

a 2 SP2a%span / 2

+/-- 1.32%/2 U2 SP%Flow

+/- 0.66 %

7.5.1.13 CRD Flow Transmitter Ambient Pressure Error (e2P)

The flow transmitter is an electrical device and therefore not affected by ambient pressure.

e2P

=

0 7.5.1.14 CRD Flow Transmitter Temperature Error (e2T)

Temperature error is considered to be a random variable for a Rosemount transmitter. Therefore e2T

=

0 7.5.1.15 CRD Flow Loop PPC I/O Module Reference Accuracy (A3)

Reference accuracy of the computer input is taken to be the SRSS of the reference accuracies of the SRU and the I/O module. The reference accuracy of the SRU is 0.1 % of span. Reference Accuracy for the I/O module is specified as +/- 0.5 % of span (Sections 2.4.4 and 2.4.5).

A32,

= 40.12 + 0.52 = 0.5099 = 0.51 % span Converting % span to % flow Page 46 of 94

LE-0113 Reactor Core Thermal Power Uncertainty Revision 1

__________________Calculation Unit 1 Rearranging Equation A8-10, a(p = 2 * (aFLOW, to solve for flow (Reference Attachment 8):

A 3 %FlOw =

A3%span / 2

+/- +0.51%/2 A3%FIow

+/- 0.255 %

7.5.1.16 CRD Flow Loop PPC I/O Module Humidity Error (e3H)

The manufacturer specifies the I/O module operating humidity limits between 0 and 95 % RH (Section 2.4.4). The I/O module is located in the Control Room 533, where humidity may vary from 50 to 90 %

RH (Reference 4.4.2). Humidity errors are set to zero because they are considered to be included within the reference accuracy specification under these conditions. (Section 3.2) e3H 0

7.5.1.17 CRD Flow Loop PPC I/O Module Radiation Error (e3R)

No radiation errors are specified in the manufacturer's specifications. The instrument is located in the Control Room 533, a mild environment [Reference 4.4.2]. Therefore, it is reasonable to consider the normal radiation effect as being included in the reference accuracy. Therefore, e3R

=

0 7.5.1.18 CRD Flow Loop PPC I/O Module Seismic Error (e3S)

No seismic effect errors are specified in the manufacturer's specifications. A seismic event defines a particular type of accident condition. Therefore, there is no seismic error for normal operating conditions (Section 3.5).

e3S

=

0 7.5.1.19 CRD Flow Loop PPC I/O Module Static Pressure Offset Error (e3SP)

The I/O module is an electrical device and therefore not affected by static pressure.

e3SP

=

0 7.5.1.20 CRD Flow Loop PPC I/O Module Ambient Pressure Error (e3P)

The I/O module is an electrical device and therefore not affected by ambient pressure.

e3P

=

0 7.5.1.21 CRD Flow Loop PPC I/O Module Process Error (e3Pr)

The I/O module receives an analog current input from the flow transmitter proportional to the pressure sensed. Any process errors associated with the conversion of pressure to a current signal have been accounted for as errors associated with flow transmitter. Therefore, e3Pr

=

0 7.5.1.22 CRD Flow Loop Accuracy (LACRD Flow)

LACRD OFow

[(Al) 2 + (elH)2 + (elR)2 + (elP)2 + (elT)2 + (elS)2 + (elSP) 2 + (A2)2 + (a2PS2)2 +

(cy2T) 2 + (e2H)2 + (e2R)2 + (e2S)2 + (e2V)2 + (e2SP)2 + (e2P) 2 + (e2T)2 + (A3)2 +

(e3H) 2 + (e3R) 2 + (e3S)2 + (e3SP)2 + (e3P) 2 + (e3Pr)2]1 p[(1)2 +(0)2+(0)2

+(0)2

+(0)2 +(0)2

+(0) 2 +(0.25)2

+ () 2

.49)2 +(0)2 +(5.02

+

(0)2 + (0)2 + (0.66)2 + (0)2 + (0)2 + (0.255)2 + (0)2 + (0)T+ (0) + (0)2 + (0)2 + (0) ]112

=

5.177183 %

LAcRD Flow

= + 5.2 %

Page 47 of 94

LE-0113 Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 7.5.2 CRD Flow Loop Drift (LDCRD_Flow) 7.5.2.1 CRD Flow Element Drift Error (Dl)

The flow element is a mechanical device; drift error is not applicable for the flow elements. Therefore, D1

= +/- 0.00% Flow 7.5.2.2 CRD Flow Loop Transmitter Drift Error (D2) 7.5.2.3 CRD Flow Loop Drift Error (D2)

Drift error for the transmitter is +/- 0.25 % of URL / 6 months, taken as a random 2cy value (Section 3.4).

The calibration frequency is 2 years, with a late factor of 6 months.

D2 2,

=

+/- (0.25 %

URL)

Drift is applied to the surveillance interval as follows (Section 6.2.5):

D2 2,

=

+/- ([(24 months + 6 months) / 6 months] * [0.0025 URL] 2)1/2

+ ([30/6]'[0.0025

750 INWC]2)112

=

+[17.578125]"'

=

+/- 4.192627458 INWC D22o

=

+/- 4.19 INWC, rounded to level of significance Converting to % span D2%Span =

+/- 4.19 INWC / 197.5 INWC

+/- 0.02121 = 2.121 %

Converting % span to % flow Rearranging Equation A8-10, ap = 2

aFLOW, to solve for flow (Reference Attachment 8):

D2%FooW =

D2ospan / 2

=

+/-2.121%/2

=

+/-1.0608 %

D2%FIOW :

+/- 1.0 %

7.5.2.4 CRD Flow Loop PPC I/O Module Drift Error (D3)

The vendor does not specify a drift error for the I/O module. Therefore, per Ref. 4.1.1 Section I, it is considered to be included in the reference accuracy.

D3

=

+/- 0 7.5.2.5 CRD Flow Loop Drift (LDRWCUFlow)

LDcRDFlow

= +/- [(D1) 2 + (D2)2 + (D3) 2]11/2

[(0)2 + (1.0)2 + (0)2]1/2

[

+ 111112 LDcRDFlow 1.0 %

7.5.3 CRD Flow Loop Process Measurement Accuracy (PMACRD Fl.ow)

No additional PMA effects beyond the effects specified in the calculation of loop accuracy.

PMARWcu Flow ;

0 Page 48 of 94

Exelon.

LE-0113 Revision 1 Reactor Core Thermal Power Uncertainty Calculation Unit 1 7.5.4 CRD Flow Loop Primary Element Accuracy (PEACRD_Flow)

No additional PEM effects beyond the effects specified in the calculation of loop accuracy.

PEARwcu Flow = 0 7.5.5 CRD Flow Loop Calibration Accuracy (CAcRDFlow)

Standard practice is to specify calibration uncertainty in calculations equal to the uncertainty associated with the instruments under test (Section 4.1.1).

Therefore, CARWCU_Flow =

[(Al )2 + (A2)2 + (A3)2]1/2 p [(1%)2 + (0.25 %)2 + (0.255 %)21112

=

1.06185%

CARWCU_Flow =

1.06185 % = rounded to 1.1 7.5.6 Total Uncertainty CRD Flow Loop (TUcRD_Flow)

TUCRD Flow

= [(LA)2 + (LD) 2 + (PMA)2 + (PEA)2 + (CA)2]112

= [(5.2)2 + (1.0)2 + (0)2 + (0)2 + (1.1)211/2

= t 5.4083 %

TUCRD_Flow

= +/- 5.4 % of flow To convert to Ibm/hr, at rated flow of 0.0320 Mlbm/hr (Table 2-1):

TECRDMASS = +/- (5.4 %)*(32000 Ibm/hr)

TEcORDMASS = +/- 0.0017 Mlbm/hr This value is entered into Table 2-1 for the uncertainty associated with CRD flow.

I Page 49 of 94

LE-0113 Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 7.6 RECIRCULATION PUMP HEAT UNCERTAINTY 7.6.1.1 Recirculation Pump Motor Power (Qp)

The recirculation pump system consists of two parallel pumps that maintain forced circulation flow loops in the reactor core. The water originates in the core and returns to the core at a higher pressure. The work performed by the recirculation pumps includes the specific work of the pump plus the pump inefficiency. This energy can be estimated by measuring the power consumed by the pump motor and multiplying the pump motor power by the motor efficiency. The maximum design output of the recirculation motor M-G set is 7700 HP, which is monitored by the watts transducer. The 7700 HP is conservatively used in lieu of the motor 7500 HP rated in determining the recirculation pump heat uncertainty.

Motor Pm WEWA WW

= WA WE, motor efficiency; where WA = 17M

WE, motor output to pump (brake horsepower (HP))

,7P W -,

pump efficiency WA W, ideal work energy input to fluid system (fluid HP)

WE = electric power input to motor (measured power, Watts)

The difference between the input (actual pump power) and the output (ideal) pump power is the power lost to friction in the pump. The heat added to the pump is due to inefficiency.

Heat Added by Pump = ((1-r/V100 )"WA The calculation of the total recirculation pump heat input, Qp, is taken from Equation 6 (Section 6.2.1.3).

Qp 2 - 77m -WE (Equation 40)

Motor Efficiency, %7m, is 94.8% at maximum speed of 1690 rpm (Reference 4.8.2) 2

0.948

5.74 MW (based on 7,700 Hp motor (Table 2-1) 10.8866 MW Multiply by 3,412,000 Btu/hr per MW to convert to Btu/hr

=

10.8866 MW

3,412,000 Btu/hr/MW

=

37,145,079 Btu/hr QP

=

37,145,000 Btu/hr, rounded to level of significance Page 50 of 94

LE-01 13 Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 Where, standard conversion factors are:

1 HP = 550 ft-lbf/s 1 ft3 = 7.48 gal I W = 3.412 Btu/hr I HP 0.7457 kW 1 HP = 2544.43 Btu/hr 7.6.2 Recirculation Pump Motor Watt Transducer Loop Uncertainty 7.6.2.1 Recirculation Pump Motor Watt Transducer Reference Accuracy (Al)

The accuracy of the transducer is +/- 0.2 % of Reading + 0.01 % Rated Output at 0 to 200% of the Rated Output (reference Section 2.5.2).

Maximum error is when the reading is equal to the recirculation pump motor power rating in MW, i.e.,

7700 HP (5.74 MW, Reference 4.3.3).

Al 2c =

+/- (0.2%

5.74 MW + 0.01%

10.5 MW)

=

+/-0.01253MW A12a =

+/- 0.013 MW, rounded to level of significance 7.6.2.2 Recirculation Pump Motor Watt Transducer Power Supply Effects (al PS)

Power supply effects are considered to be negligible (Section 3.7). Therefore, alPS

=

0 7.6.2.3 Recirculation Pump Motor Watt Transducer Ambient Temperature Error (UlT)

The Watt Transducer is located in the auxiliary electrical room. This is a controlled environment; therefore, temperature error can be neglected.

alT

=

0 7.6.3 Watt Transducer Humidity, Radiation, Pressure, and Temperature Errors (elH, elR, elP, elT)

The watt transducer is an electrical device and the output is not subject to environmental or vibration effects. Therefore; elH =elR =elP = elT = 0 7.6.3.1 Recirculation Pump Motor Watt Transducer Seismic Error (elS)

A seismic event is an abnormal operating condition and is not addressed by this calculation.

Therefore; elS

=

0 7.6.3.2 Recirculation Pump Motor Watt Transducer Static Pressure Error (el SP)

The watt transducer is an electrical device not affected by process pressure. Therefore; elSP 0

7.6.3.3 Recirculation Pump Motor Watt Transducer PPC I/O Module Reference Accuracy (A2)

Reference accuracy of the computer input is taken to be the SRSS of the reference accuracies of the SRU and the I/O module. The reference accuracy of the SRU is 0.1 % of span as given in Section 2.5.3. Reference Accuracy for the 1/O module is specified as +/- 0.5 % of span (Section 2.5.4) and considered to be a 2a value (Section 3.4).

Page 51 of 94 I

LE-0113 Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 A2 2

= 10.12 +0-52 = 0.509901951= 0.51%

A2 2,

=

+0.51% *range

A22,

+/- 0.0051

10.5 MW = 0.05355 MW 7.6.3.4 Recirculation Pump Motor Watt Transducer PPC I/O Module Humidity Error (e2H)

The manufacturer specifies the [/O module operating humidity limits between 0 and 95 % RH (Section 2.4.4). The I/O module is located in the Control Room 533, where humidity may vary from 50 to 90 %

RH (Reference 4.4.2). Humidity errors are set to zero because they are considered to be included within the reference accuracy specification under these conditions. (Section 3.2) e2H

=

0 7.6.3.5 Recirculation Pump Motor Watt Transducer PPC I/O Module Radiation Error (e2R)

No radiation errors are specified in the manufacturer's specifications. The instrument is located in the Control Room 533, a mild environment (Section 4.4.2). Therefore, it is reasonable to consider the normal radiation effect as being included in the reference accuracy. Therefore, e2R

=

0 7.6.3.6 Recirculation Pump Motor Watt Transducer PPC I/O Module Seismic Error (e2S)

No seismic effect errors are specified in the manufacturer's specifications. A seismic event defines a particular type of accident condition. Therefore, there is no seismic error for normal operating conditions (Section 3.5).

e2S

=

0 7.6.3.7 Recirculation Pump Motor Watt Transducer PPC I/O Module Static Pressure Offset Error (e2SP)

The I/O module is an electrical device and therefore not affected by static pressure.

e2SP

=

0 7.6.3.8 Recirculation Pump Motor Watt Transducer PPC I/O Module Ambient Pressure Error (e2P)

The I/O module is an electrical device and therefore not affected by ambient pressure.

e2P

=

0 7.6.3.9 Recirculation -Pump Motor Watt Transducer PPC I/O Module Process Error (e2P)r Any process errors associated with the conversion of pressure to a current signal have been accounted for as errors associated with Watt Transducer. Therefore, e2Pr

=

0 7.6.3.10 Recirculation Pump Motor Watt Transducer Loop Accuracy (LAp)

LAp

=

+/- [(A1) 2 + (alPS)2 + (aIT)2 + (elH)2 + (elR)2 + (elP)2 + (elT)2 + (elS)2 + (elSP)2 +

(A2)2 + (e2H)2 + (e2R)2 + (e2S)2 + (e2SP) + (e2P)2 + (e2Pr)2]112

+/- [(0.013)2+ (0)2+ (0)2+

+(0)2+(0)2

+ (0)2+ (0)2 + (0)2 + (0)2 + (0.05355)2 + (0)2+ (Q)2 +

(0)2 + (0)2 + (0)2 + (0)11/2

=

+ 0.05511 MW LAp

=

+/-0.055 MW Page 52 of 94

LE-0113 V-ýO Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 7.6.4 Recirculation Pump Motor Watt Transducer Loop Drift (LDp) 7.6.4.1 Recirculation Pump Motor Watt Transducer Drift Error (D1)

The drift will be considered random and independent over time. The surveillance frequency is 30 months; therefore, drift error follows Equation 39 (Section 6.2.5 and reference 2.5.2).

D1

+/- 0.1% of RO per year

=

[(30/12). (+/- 0.1,%

RO)2) 1/2

=

[2.5. 0.00011025 MW2]1/2 0.016601958 MW D1 0.017 MW, rounded to level of significance 7.6.4.2 Recirculation Pump Motor Watt Transducer PPC I/O Module Drift Error (D2)

The vendor does not specify a drift error for the I/O module. Therefore, per Ref. 4.1.1 Section I, it is considered to be included in the reference accuracy.

D2

+/- 0 7.6.4.3 Recirculation Pump Motor Watt Transducer Loop Drift (LDRWcUFIOW)

LDp

=

_(D1) 2 + (D2)2]1"2

+/- [(0.017)2 + (0)21112 LDp

+/- 0.017 MW 7.6.5 Recirculation Pump Motor Watt Transducer Process Measurement Accuracy (PMAp)

No additional PMA effects beyond the effects specified in the calculation of loop accuracy.

PMAp =

0 7.6.6 Recirculation Pump Motor Watt Transducer Primary Element Accuracy (PEAp)

No additional PEM effects beyond the effects specified in the calculation of loop accuracy.

PEAP 0

7.6.7 Recirculation Pump Motor Watt Transducer Loop Calibration Accuracy (CAp)

Standard practice is to specify calibration uncertainty in calculations equal to the uncertainty associated with the instruments under test.

Therefore, CA,

+/- [(Al) 2 + (A2.)2112

=

+ [(0.013)2 + (0.05355)2]1/2

=

+/- 0.05511 CAp

+/- 0.055 MW 7.6.8 Total Uncertainty Recirculation Pump Motor Watt Transducer Loop (TUp)

TUp

=

+/- [(LA)2 + (LD) 2 + (PMA)2 + (PEA)2 + (CA)2]1 /2

= [(0.055)2 + (0.017)2 + (0)2 + (0)2 + (0.055)1/2

+/- 0.079618 MW, round to +/- 0.08 MW Page 53 of 94

LE-0113 DI Reactor Core Thermal Power Uncertainty Revision 1 Calculation Unit 1 Converting to % motor power TUp

=

0.08 MW / 5.74 MW

=

_+ 0.013937

=

+1.4%

7.7 DETERMINATION OF CTP UNCERTAINTY 7.7.1 Numerical Solutions for the Partial Derivative Terms Solutions are found in two parts by first substituting values from Table 2-1 into Equations 20 through 27, as shown.

,CTP

= (hG (pS)- hF (TFW))

6 WFW

= (hG (Ps) - hF (427.1 0F)) Btu/lbm (Reference Equation 20)

= (1190.0 - 405.30)Btu/lbm

784.70 Btu/lbm 6C TP

12 P-WFW = 15,255,000 Ibm/hr (Reference Equation 21) caho (Ps) 6C TP_ =FTw WFW = -15,255,000 Ibm/hr (Reference Equation 22)

ThF (TFw )

C OCTP -1 (Reference Equation 23)

SQRDOUT CTP 1

(Reference Equation 24)

QCRDIN OCTP =1 (Reference Equation 25) 9QR.AD 1CTP (Reference Equation 26) aQRWCU aCT__P (Reference Equation 27)

Page 54 of 94

LE-0113 Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 7.7.2 Component Uncertainty Terms The component uncertainty terms, uo, are found by substituting values into Equations 31, 33 through 37, as shown.

7.7.2.1 Feedwater Mass Flowrate Uncertainty awm = 42,714 Ibm/hr (Section 7.1) 7.7.2.2 Steam Enthalpy Uncertainty rhG(PsIo)

AhG(Ps)2.

p2,

'AhG('o)j*

2 2

(Reference Equation 31)

PG 5

).

(

AIo )

The nominal steam dome pressure is evaluated for saturated steam at 1060 psia (Reference 4.9.10) with an uncertainty of +/- 20 psig (Section 7.2). Steam table interpolation error is taken to be one-half of the least significant figure shown, i.e., +/- 0.05 Btu/Ibm for 1190.0 Btu/Ibm. In Equation 31, the partial derivative with respect to interpolation of the enthalpy value from the steam table (AhG(Io)/Alo) = 1, because this represents the enthalpy as read from the steam/pressure curve divided by the enthalpy as read from the steam/pressure curve. Enthalpy values are from Reference 4.9.3.

Btu / Ibm )2, (20 psi Btu /

/bm 2

2.05 Btu 2 1.9OO h~l 4 ) 2(BtU/1bM) 2 s

Btu /lbm 2

Btu )

=

1080 - 1040 ps-i

( 2 s)

Btu /

(0.05 Ibm.5

= 0.85147 Btu/ Ibm GhG (Ps, 10) 0.85 Btu/Ibm, rounded to the inherent uncertainty of the steam table.

Page 55 of 94 I

LE-01 13 Revision I Exelaln.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 7.7.2.3 Feedwater Enthalpy Uncertainty ahF(TFW -PW,lo.) = ~(Ah,(T) 2 C 0 T 2+

(*h(p) 1 2

+(AlhF) 2 2 (Reference Equation 33)

A--PJ

'P Alo From Table 2-1, feedwater pressure is given as 1155 psig (1169.7 psia) +/- 10 psi and feedwater temperature is given as 427.1 +/- 0.57 OF. Enthalpy of water is from Attachment 6. Steam table interpolation error is taken to be one-half of the least significant figure shown, i.e., +/- 0.005 Btu/Ibm. In Equation 33, the partial derivative with respect to interpolation of the enthalpy value from the steam table (AhF(Io)/AIO) = 1, because this represents the enthalpy as read from the steam/pressure curve divided by the enthalpy as read from the steam/pressure curve.

Ch,(TFW, PFW, 10) hF(4 27.67 ) - hF(426.53))2 (Btu / lbm' 2. (0.57 °FY +

[FQ 79.7) -

hF(1l5 9.7)) (Btu/l bm

.(

py+

=

1179.7-1159.7 psi p

tul-m 2 2t,

_______/_Ib

0.005Bt

,Btu Ilbm)

(

Ibm) 406.28-405.04 (Btu !Ibm'2, (0.57F +

ý427.67 - 426.53 )O F) 405.67-405.65) (Btullbm

(

1-psi,.

+,(Btu/lbm2 0.005 Btu 2 1179.7 -1159.7 (si o

('.Btu/lbm) ibm) 0.6201Btu Ibm Btu

'h, (TFw, PFW, 1) 0.620 Bt, rounded to the inherent uncertainty of the steam table.

Ibm The accuracy of the temperature measurement determines the feedwater enthalpy uncertainty.

Variations in pressure and steam table interpolation are negligible.

Page 56 of 94

LE-0113 Reactor Core Thermal Power Uncertainty Revision I Calculation Unit I 7.7.2.4 Control Rod Drive Outlet Energy Uncertainty The control rod drive outlet energy uncertainty is dominated by the uncertainty of the mass flow rate.

The steam table interpolation error is negligible and is not used in the following computation. CRD mass flow rate uncertainty, XCRD, is 5.4 % of flow (Section 7.5.6). The uncertainty is determined for a temperature of 97.2 'F +/- 0.7 °F (Table 2-1) and a pressure of 1448 psig (1462.7 psia). 10 psi (Sections 2.4.2 and 3.11). Enthalpy values are from Reference 4.9.3.

The variation in hf is shown below.

hf(96.5 2 Btu I Ibm) 2 (0.7.F ) 2

,,h (TCRD 97--

-- -*.9

- 96. --T

(- -

(.,,

+[ ( hf (1472.7) -hf (1452.7* )2 Btu /llbm '

(,._

.*2 1472.7 -1452.7

,OFs)

(69.848 )-(68.458 2 ( Btu / Ibm -2 *(0.70F2 97.9*-.-5 Ob

(

/*+((69.180)-(69.127 "2 (Btu /Ibm (1

lOsi)2

= 0.696 Btu/Ibm Converting ahf to % of hf

= +/- 0.696 Btu/Ibm / 69.153 Btu/lbm

+/-0.01006= +/-1.01%

The SRSS method is used to combine the mass flow rate and enthalpy uncertainty terms.

XCRDOUT %

=

t5.42 + 1.012 = 5.5 % = 6 %, conservatively rounded up

'QCRD-OrLT

= XCRDOUT %

QCRDOUT (Reference Equation 34)

Using steam enthalpy (1190.0 Btu/Ibm) and CRD mass flow rate (0.0320 Mlbm/hr) from Table 2-1:

CYCRDOUT

= +/- 6 %

hG(Ps)

WCRD

= +/- 6 % * (1190.0 Btu/Ibm) * (0.0320 Mlb/hr)

= +/- 2,284,800 Btu/hr

= +/- 2,285,000 Btu/hr, rounded to level of significance Page 57 of 94 I

LE-0113 Revision 1 Exelon.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 7.7.2.5 Control Rod Drive Inlet Energy Uncertainty The control rod drive inlet energy uncertainty is dominated by the uncertainty of the mass flow rate.

CRD mass flow rate uncertainty, XCRD, is taken at +/- 6 % of mass flow, conservatively rounded up from the +/- 5.5% mass flow uncertainty in Section 7.7.2.4). The CRD mass flow (0.0320 Mlb/hr) and enthalpy (68.0 Btu/Ibm) are from Table 2-1.

0 OCRDIN

XCRDIN % - QCRDIN (Reference Equation 35)

= 6 %

hA(CRD)

WCRD

= +/- 6 % * (68.00 Btu/Ibm) * (0.0320 Mlbm/hr)

= + 130,560 Btu/hr

= 131,000 Btu/hr, rounded to level of significance 7.7.2.6 Reactor Pressure Vessel Heat Loss Uncertainty Reference 4.8.3 determines the Unit 1 reactor heat loss as 0.89 MWt. A conservative variance of 10

%of the heat loss rate is used to estimate the heat loss uncertainty.

(

0 RAD

= XRAD % -QRAD (Reference Equation 36)

= 10 %

0.89 MWt

3,412,000 Btu/hr / MWt

+/- 303,668 Btu/hr 7.7.2.7 RWCU Heat Removal Uncertainty The RWCU flow loop uncertainty is +/- 2.3 % of mass flow (Section 7.3.6). The RWCU temperature measurement uncertainty is +/- 4.37 'F (Section 7.4.6). The variation in enthalpy over the range of temperatures in this loop of about 0.5 % is negligible compared to the -2.3 % flow variation. From Table 2-1, the RWCU suction and discharge enthalpies are:

hF (TRwcu-s) = 530.6 Btu/Ibm hF (TRWCU-D) = 418.4 Btu/Ibm (Reference Equation 37) 0 QRWCU

= XRWCU %

QRWCU XRWCU is set +/- 2.3 % based on the mass flow uncertainty Remembering that QRWCU = WRWCU * [hF(TRWCU-S) - hF(TRwcU-D)] (See Equation 9)

WRWCU

= 154,000

-rm (Pump A) and 133,000 rm (Pump BandC) hr hr (Section 2.2.1 )

Maximum heat removal occurs with Pump A running, therefore, WRWOU = 154,000 Ibm/hr.

OQRwcU 2.3 %"WRWCU

- [hf (TRwcu-s) - hf (TRwcu-D)]

0 Q-Rwcu = - 2.3% * (154,000 Ibm/hr) * (530.6 -418.4) (Btu/Ibm) aQ-RWCU = +/- 397,412 Btu/hr

= +/- 397,400 Btu/hr, rounded to level of significance Page 58 of 94

MWtxelain.

LE-01 13 Revision I Reactor Core Thermal Power Uncertainty Calculation Unit 1 7.7.2.8 Recirculktion Pump Heat Addition Uncertainty The power of the recirculation pumps (WE) is measured by a watt-meter with a calculated uncertainty of 1.4 % (Section 7.6.8).

Xp

= +/- 1.4 %

The uncertainty of the power measurement multiplied by the pump power, Qp, is the uncertainty of the pump power, yQp. Qp is 37,145,000 Btu/hr (Section 7.6.1.1).

= + Xp %. Qp

+/- 1.4%

37,145,000 Btu/hr

+/- 520,030 Btu/hr (See Equation 38)

G

= +/- 520,000 Btu/hr, rounded to level of significance 7.8 TOTAL CTP UNCERTAINTY CALCULATION Total CTP uncertainty, UCTP, is calculated by using Equations 19, 20 through 27, 28, 31, 33, and 34 through 37.

(Reference Equation 19) o aCTP *(1

)2 aCTP (yh(S )2 +

'F)

WFW O~L hG(S)*

0 GP)j UCTP =

F 6CTP 2

OCTP 1

(a

)-

I FW) aQ~~

CR I

Q OUT+

D~lhF(TFw))

ah t +

,o~,,

L

~aTP 2

1

.2 1

t9 CR T P

( aCR 0 _IN y) j + (ý jC * ( UG 0

A )2 j+

t,16cRD_,N 6Q t

)*-

I) a(DCTP I*

I 2 ('Cý'

)21 +

l-aCTPI)2 * (7Q, )21

[aQWGU 9ý 0

t-aQp9 aCTP aT

= (hG (PS) - hF (TFW))

aCTP ahG(Ps) w Fw (Reference Equation 20)

(Reference Equation 21) a CTP hF (TFW

-- WFW a CTP aQCRDOUT (Reference Equation 22)

(Reference Equation 23)

(Reference Equation 24) aCTP L9 Q CRDIN Page 59 of 94

LE-0113 Revision I Exel6n.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 a CTP

-C1AD (Reference Equation 25) aQRAD a CTP 1

(Reference Equation 26) a QRWCU CT*P (Reference Equation 27)

Substituting the previously determined values for the variables shown gives:

ý784.70 Btu ý)2 * (4,1Ib 2+((

5250 bm 2 0.5 Btu )2)

Ib500lm hr)J~

hr J )

lbm J

-15250 Ib 2 0.20 Bt

+/-2+(ly Z85000 Bt

+/-2) hr 01) Ibm hr) hr Bu)i UCTP =

397,4 00Btu 2 +'~

1)

(520, 000 Btu 2 (l~ly Y

hr))

hr UCTP = 37,239,573 Btu/hr UCTP = 37,240,000 Btu/hr rounded to level of significance Divide UcTP by 3,412,000 Btu/hr to convert units to megawatts thermal (MWt)

UCTP = (37,240,000 Btu/hr)/(3,412,000 (Btu/hr)/MWt)

UCTP = 10.91442 MWt = 10.914 MWt, rounded Limerick MUR rated thermal power megawatts = 3515 MWTH The uncertainty in the CTP calculation performed by the Plant Process Computer as a percentage of MUR rated thermal power is:

UCTP-2, = 10.914 MWTH / 3515 MWTH = 0.00310 = 0.310%

The determination of total CTP uncertainty is sensitive to two measured parameters, feedwater mass flow rate measurement uncertainty and feedwater temperature measurement uncertainty.

8.0 CONCLUSION

S The total uncertainty associated with reactor thermal power (heat balance) calculation performed by the Plant Process Computer is 10.914 MWTH or 0.310 % of the MUR rated reactor thermal power limit of 3515 MWTH. This is a 2o value.

Page 60 of 94

LE-0113 Reactor Core Thermal Power Uncertainty Revision I Calculation Unit 1 9.0 ATTACHMENTS Telecon URS and TemTex Accuracy of RTDs for TE-046-103..............................................

62 TODI Al 695446-801 - Steam Carryover Fraction Design Input (1 page).................................

63 Rosemount Nuclear Instruments customer letter to Grand Gulf (2 pages).............................. 64 Analogic Analog Input Card ANDS5500 (4 pages)...................................................................

66 TODI Al 695446087 Source Document "GE Task Report TO100 December 2009 Revision 001" (6 P a g e s )....................

7 0 NIST Thermophysical Properties of Water.............................................................................

76 CTP Calculation Results Sensitivity Analysis..........................................................................

77 Derivation of the relationship between flow, AP, and density................................

...................... 78 Ametek Scientific Columbus Exceltronic AC Watt Transducer Specification (4 pages)........... 81 0 B32-C-001 -J-023, Rev. 1, Recirculation Pump Curve (1 pages).........................................

85 1 Rosemount Inc., Instruction Manual 4259, Model 1151 Alphaline A Flow Transmitter, 1977 (PA G E S 1, 6, 14, 24, A N D 29).....................................................................................................................

86 2 Bailey Signal Resistor Unit Type 766 (2 pages).....................................................................

89 3 Rosemount Specification Drawing 01153-2734, N0039 Option - Combination N0016 & N0037 (2 P a g e s ).................................................

9 1 4 Rosemount Product Data Sheet 00813-0100-2655, Rev. AA June 1999 "N-Options for Use with the Model 1153 & 1154 Alphaline Nuclear Pressure Transmitters" (2 Pages).....................................

93 Page 61 of 94

LE-0113 Reactor Core Thermal Power Uncertainty Revision I Calculation Unit I Telecon URS and TemTex Accuracy of RTDs for TE-046-103 Shah. Pravin From:

Pebush. John Sent Friday. September 25. 2009 9:58 AM To:

Kimura. Stephen; Shah. Pravin Cc:

Oconnar. John: Low. Richard

Subject:

CRD Drive Water Discharge Temperature Pravin:

CRD Drive Water Discharge Temperature is measured by TE-046-103 (Unit 2 TE-046-203), which is supplied by-TeinTex Temperature Systems, Inc.

700 E-Houston St.

Sherman, TX 75090 Phone: (903) 813-1500 Per telecom between John Pehush and TemTex application engineering an 09124109, the RTOs supplied to Limerick Unit 1 ame 100 ohm platinum. The model number 10457-8785 specified in PIMS is the TemTex drawing number. The RTD was manufactured to the industry standard IEC-751, which means the accuracy is

" 1- 0.12% (of resistance) at OC, commonly knows as Class B. Therefore the RTD will provide an accuracy of "1- 0.3*C at O'C (+/- 0.54°F at 327F). The 'Temperature Coefficient of Resistance' (TCR), as so called the ALPHA, is the average increase in resistance per degree increase. The TCR of a platinum RTD is 0.00385

.OJENC=.

The range of TE-046-103 is 0 to 200°F (-17.78 to 93.33°C). The overall accuracy is conservatively calculated at 93.332C (200°F), which is +1- 0.359°C (+I- 0.65'F). Therefore, temperature accuracy of TE-N46-103 used is rounded to ÷1- 0.71F.

John E. Pehush, P.E.

Washington Group URS Supervising Discipline Engineer - I&C (609) 720-2274 w (609) 216-1392 c John.Pehushrwgint.com Page 62 of 94

LE-0113 Revision 1I Exeltne Reactor Core Thermal Power Uncertainty Calculation Unit 1 TODI Al1695446-801 - Steam Carryover Fraction Design Input (1 page)

EXELON TRANSMITTAL OF DESIGN INFORMATION EIZSAFETY-RELATED Originating Organization Tracking No:

INION-SAFETY-R ELATED NExelon LIREGULATORY RELATED

-IEOther (specify)

Al695446-80 Station/Unit(s) Limerick Units 1 & 2 Page 1 of 1 To: John Pehush WGI - Mid Atlantic

Subject:

Transmittal of information.

Steve Draqovich cgltk' 6.

_/z_-_/o_

Preparer P parer's Signature Date Chris Wiecland

/

1 Approver.

A* p r's Signatur

'/Date

-,7 MUR Project Reviewer MUR Erect Signature D te 1"

For Quality/Completeness Status of Information: ZApproved for Use EI-Unverified Description of Information:

The following information was requested by URS Washington Division (WGI) for input to Limerick's core thermal power (CTP) uncertainty calculations (units 1 & 2).

The steam carryover fraction that should be used as design input to the calculations is zero.

Purpose of Issuance and Limitations on Use: This information is being supplied solely for the use as design input for the Limerick CTP-uncertainty calculations (units I & 2).

1 Source Documents:

G.E. Document "Impact of Steam Carryover Fraction on Process Computer Heat Balance Calculations",

September 2001.

Distribution:

Original: Limerick file CC: Ray George, Electrical Design Manager, Limerick John Pehush, I&C Lead, WGI - Mid Atlantic Page 63 of 94

LE-0113 Reactor Core Thermal Power Uncertainty Revision 1I Calculation Unit 1 Rosemount Nuclear Instruments customer letter to Grand Gulf (2 pages)

Rosemount Nuclear Instruments RoS*oet.

ar tnurursen~s. lns.

Eden PraMe PAN M5:44 (ISA

-l T

56121 82858252 4 April 2000 Ref: Grand Gulf Nuclear Station message on INPO plant reports, subject Rosemount Instrument Setpoint Methodology, dated March 9, 2000

Dear Customer:

This letter is intended to eliminate any confusion that may have arisen as a result of the reference message from Grand Gulf. The message was concerned with statistical variation associated with published performance variables and how the variation relates to the published specifications in Rosemount Nuclear Instruments, lnc.(RNII) pressure transmitter m'oiels 1152, 1153 Series B;.

1153 Series 0, It 54 and 1154 Series H. According to our understanding, the performance variables ofpriinary concern are those discussed in GE Instrument Selpoint Methodology document NEDC 31336, namely I. Reference Accuracy

2. Ambient Teltlictature Effect

3. Overpressure Effect

4. Static Pressure Effects

5.

Power Supply Effect It is RNII's undcrstantding that GE and the NRC have accepted the methodology of using transmilter testing to insure specifications are met as a basis for confirming specifications are

+3o. The conclusions we draw regarding specifications being +3a are based on manufacturing testing and screening, final assembly acceptance testing, periodic (e.g., every 3 months) audit testing oftransaiitter samples and limited statistical analysis. Please note that all performance specifications are based ott zero-basced ranges under rcifrence conditions. Finally, we wish to make clear that no inferences are made with respect to confidence levels associated with any speci ication.

I. Reference Accuracy-.

All (100%) RNII transmtitters, including models I 152, 1153 Series B, 1153 Series D, 1154 and 1154 Series H, are tested to verify accuracy to+0.25% of span at 0%, 20%, 40%, 60%,

80% and 100% ofspan. Therefore, the reference accuracy published in our specifications is considered 43o.

2.

Ambient Temperature Effect All (100%) amiplifier boards are tested for compliance with their temperature effect specifications prior to final assembly. All sensor modules, with the exception of model 1154, are temperature compensated to assure compliance with their temperature effect specifications. All (100%) model 1154, model 1154 Series H and model 1153 gage and absolute pressure transmitters are tested following final assembly to verify compliance with specification. Additionally, a review of audit test data performed on final assemblies of

!model 1152 and model 1153 transmitters not tested following final assembly indicate RSiHE-RSEMOUI'T Page 64 of 94

LE-O 13 IF=

Reactor Core Thermal Power Uncertainty Revision I

= e__

Calculation Unit 1 conformance to specification. Therefore, the ambient temperature effect published in our specifications is cotnsidered ÷3a.

3. Overpressure Effect Testing of this variable is done at the module stage. All (100%) range 3 through 8 sensor modules are tested for compliance to specifications. We do not test range 9 or 10 modules for overpressure for safety reasons. However, design similarity permits us to conclude that statements made for ranges 3 through 8 would also apply to ranges 9 and 10. Therefore, the overpressure effect published in our specifications is considered +3o.

4.

Static Pressure Effects All (100%) differential pressure sensor modules are tested for compliance with static pressure zero errors. Additionally, Models 1153 and I 15,4 Ranges 3, 6,7 and Sare 100% tested after final assembly for added assurance of specification compliance. Audit testing performed on ranges 4 and 5 have shown compliance to the specificatjon. Therefore, static pressure effects published in our specifications are considered +3a.

5.

Puwer Supply Effect leslitig for conformance to this speciftiction is pcrfoitred on all (ransitittcrs undergoing s"ample (Iudit) testing. This vat iable has historically exhibiled extremcly small performance errors and small standard deviation (essentially a mean error of zero with a standard deviation typically less than 10% of the specitication). All transmitters tested were found in compliance with the specification. "herelbre, power supply eflect published in our specilicalions is considered +/-3a.

Should you have any further questions, please contact Jerry Edwards at (612) 828-3951.

Sincerely, Jerry L. Edwards Manager, Sales, Marketing and Contracts RosemIount Nuclear Instrumetlts, tise.

FISIIEH-RUSEMOUNT Page 65 of 94

LE-0113 Revision I Exelein.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 Analogic Analog Input Card ANDS5500 (4 pages)

PEABODY, MA 01960 POTENTIOMETER INPUT CARD ANDS5500 SPECIFICATION 2-15227 REV 01 First Used On: ANDS5500 Page 1 of 8 Code Ident: 1BMOO File Name: 2-15227rev01.doc Printed:

April 4, 2003 REVISION HISTORY REV DESCRIPTION DWN APVD DATE 01 SEE E.C.O K.Q RWA 08/25/83 Approvals for Release:

Richard Lane Originator Richard Lane Engineer 2/13/03 Date 3/31/03 Date Page 66 of 94 I

Exebna LE-0113 Revision 1I Reactor Core Thermal Power Uncertainty Calculation Unit 1 ANDS5500 POTENTIOMETER INPUT CARD SPECIFICATION 2-15227 RELATED DOCUMENTS:

Schematic Theory of Operation D5-88114 A2-5568 I.

GENERAL DESCRIPTION The Potentiometer Card is a user card for the ANDS 5500 Data Acquisition System. It consists of a power supply and voltage reference, an output multiplexer and four identical signal conditioning channels. There are two 44-pin edge-card connectors (male) on the PC board, one is connected internally to the system and the other is for user connection.

Each signal channel consists of an excitation output section and a signal input section. The latter can be preset to accept a variety of valtage ranges and types via jumpers. It provides a DC voltage to, and permits low frequency and DC measurement of the signals from, appropriate external devices such as piezoelectric accelerometers.

II.

SPECIFICATIONS

1. GENERAL Number of Channels:

4 Size and Shape:

Operating Temperature:

Storage Temperature:

Input & Output Connection:

Approximately 7 11/2" x 4 1/2" x 1/2" (similar to Analogic D4-7443) 0'-- 50 Degrees C. 85 Degrees C.

EDGECARD, gold plated

2. ELECTRICAL a) Power Requirement:

+5v (+/-5%) at 100mA

+15v (+/-5%) at 100mA

-15v (+/-5%) at 100mA Page 67 of 94 I

LE-0113 Revision I Exel6n.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 Uncontrolled Document. Source Unknown ANALOGI-PEABODY, MA01960 2-15227 REV 01 POTENTIOMETER INPUT CARD ANDS5500 Page 4 of 9 Code Ident: 1BM00 File Name: 2-15227revO1.doc Printed:

April 4, 2003 b) Excitation Voltage Output (1 per channel)

Voltage Level:

+5v and -5v Voltage Accuracy:

+/- 0.2% over operating temperature range Output Current:

IOmA max.

Output Impedance:

< 0.1 ohm Protection:

Tolerate direct short circuit or short to

+/-30vdc protected up to 250v by a thermistor c) Signal Input (1 per channel)

Input Impedence:

Input Signal Ranges:

Primary Frequency Content:

Signal Source Resistance:

Overall Accurancy: (includes excitation accurancy)

Protection:

Amplifier Upper Bandwidth:

Input Coupling INPUT RANGE (F.S)

GAIN

+I-5v 2

+1-2.5v 4

+I-1.5v 8

1OMeg ohm

+/-5v, +/-2.5v, +/-1.25v, +/-500mv,

+/-250mv, +/-125mv Jumper selected (see Table 1) and fine adjustment by trimpot DC to 100Hz 2800 ohm max.

+/- 0.5% over operating temperature range Input protected up to 250v continuous 10Hz, 45Hz and 100Hz (2-pole filter)

Jumper selected (see Table 2)

Jumper selected for either, AC OR DC.

Lower AC bandwidth is 0.5Hz (see Table 2).

JUMPER 2 JUMPER 3 6 to 7 9 to 10 5 to 7 9 to 10 4 to 6 9 to 10 Page 68 of 94 I

LE-0113 Revision I IN"=e6n.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 Uncontrolled Document. Source Unknown ANALOGIC - PEABODY, MA 01960 2-15227 REV 01 POTENTIOMETER INPUT CARD ANDS5500 Page 5 of 9 Code [dent: 1BMO0 File Name: 2-15227rev01.doc Printed:

April 4, 2003

+/-500mv 20 6 to 7 8 to 9

+I-250mv 40 5 to 7 8 to 9

+/- 125mv 80 4 to 6 8 to 9 TABLE 1.

INPUT RANGE (CHANNEL GAIN) VS. JUMPER POSITION BANDWIDTH DC to 10Hz DC to 45Hz DC to 100Hz 0.5 to 10Hz 0.5 to 45Hz 0.5 to 100Hz JUMPER I 2 to 3 2 to 3 2 to 3 1 to 2 lto2 1 to 2 JUMPER 4 12 to 13 13 to 14 17 to 18 12 to 13 13 to 14 17 to 18 JUMPER 5 16 to 17 11 to 12 15 to 16 16 to 17 11 to 12 15 to 16 TABLE 2.

CHANNEL BANDWIDTH VS. JUMPER POSITION d) Analog Signal Output to Bus Analog Output Signal:

Output Offset:

Full Scale Output Range:

Maximum Output Voltage in Hiz state:

e) Digital Signal Input From Bus:

Ch.1, Ch.2, Ch.3, Ch.4 or Hiz (high impedance state),

digitally selected

+/- 5mv over operating temperature Range, adjustable to zero by trimpot

+1-10v (+/-0.5%) with full scale input

+/- 15v Channel select (see Table 3)

Page 69 of 94

LE-0113 Revision I SW At txelwn.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 TODI A1695446087 Source Document "GE Task Report TO 100 December 2009 Revision 001" (6 Pages)

EXELON TR~ANSMITTAL OF DESIGN INFORMATION GISAFETY-RE.ATED Originaling Organization Tracking No:

CIN ONSAFETY-fl ELATED OExeton

[3REGULATORY RELAT90

[]Other fsp#Cfy)

Al1695446-87 (iev. 0) station/Unit(s) Umeujh U I/U2PaeIo6

Subject:

Transmittal of informationi requested b~y Washington Ov~son q URS (WGI).

Steve Dragg cir/&

/7 Preparer Preparer's S. ature Vato MU tiMU eioe AR Project Sognaiure Date For QuolM Cornplelene-55 Sttsof Information'. EAPPrved tot Use ElUelverified Oscriptlon of Information:

This TODI provkles the thearynal power heat 0alance data at uprated conditions (10 1.65%) based 00i the final G.E. Task Report T0100. December 2009, Revision 1. This informaiion is being supplied to WGI for incorporation as a revision to the Utnerick Core Thermal Power uncertainty calcutatlons (CTP) LE0113 and LE-0t 14, units I and 2 iespectively, Attachments to this TOOl Include a mark-up to the "design inputs' page of each CTP crulatinn. In addition, Figure 3-3, "Reactor Heal talarce - Revised TLTP (101,65% CLTP)" from GE. Task Report T010O is also included to show the source of the revised inlformation, Putpose* f lasuanee and iUmilatlons on Use: This information is being suppliead soaefy for the use of revising the tfinerick Core Thermal Power uncertainty calculations L-01 13 (Unit 1) and L-01 14 (Unit 2).

Source Documenis, G.E. Task Report 1"0100. December 2009, Revision 1.

Distbtution:

Original: TOOl file CC: Ray Goerge, M1anager Design Eneg.ineaeng, Limerick Allan Chades, Power Urrate Sito Ergineei Page 70 of 94

YOrxelalln, LE-0113 Revision 1I Reactor Core Thermal Power Uncertainty Calculation Unit 1 Iq / 6 q q -7 E.-el,-n.

Reador Core rheuris Power Unceriainiy Caktlcfiston Un~it I LE-O1 13 Revision a3 Table 2-1.

0 --An Inputs InkSt Tag Computer Nominmil Value Uncertsinty IUprermint Description NO.

PonI ai cR0 f!halpy NIA WA 611,14.6tlb 810&n (gal 4 23 Al, fl BlflhMQQe..93 CAD TaorFow r-048-103 A120i 7.4W F0A61. 4A* 1)

O.7 'F I~cr, AlIac*hinent iI

'Temperatuxe t

Nominal Flow CR0 Vwaier nlow lFT-046-A7

~

(e~If 55 1

Rale IN004 A 11*GMH54 S~n756 Fnedyw-4tr WA WA 0-0115mr Feedwa!nrMawss

'gagae LFU I-C8 NfA 0.32

( ReL. 4.8.6)

W/A W/A I 16 PSIG t 10 Iniq jSaoion 3.1tj T)MiPOr.'hz 1 1`1041A-F I

A1750 4~4.,

T, t 057 I 444e 40-6 fladlated Rearlar 0 9W U1 Pnn1stue Vessel N-tA MA 10 (Sc~o 3.Lii (r4PV) Heat Lass 1.04 MN (V2)

O

~

(eIln3 S(1141.

4,&3, Ste. 2.0)

Reacto! DOWe PMV.sUre PT-a42-INODJB E1234

/060O IG43 Pri 5,,t

....0 t 20pa Ir Satuer.Ved Stainn Ew~faAby N/A K/A j 10; ý 1 utwlbln l;Q43P6!,P;j lot (Mat 460JArmOý t 0.05 BIbM

,Alet. 448)

W/A RrO4MtAS~lon P,.np Mo1dr

~mp 1Atyar I A~BJ-~'31 lMa14~o 14/A 94.8 % (AIIor-hillerit 10 &

RetI. 48.62)

M1O Hp (5174 ON)

(Ref-43.3.Z)

WA a1.4 'R RICLI Ofs;Cha"g Enthalpy N/A trW-i'44A~~DL~~l jRef. 4.0,31 Page 71 of 94

LE-0113 Revision I Exelan.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 LE-0113 Revision 0 eJ(e 1.

Reacor C~ore Thermai Powef Unce rtainty Cntelaý laion Unit I lawo 2. 1.

_________Design Inputs No.

PointBai RWCU OWc'0' TE04d4-A1742

-440-W(

tSudllon 7.4.6)

RWCU InLa1 Flow 300044 W6PM 4max) 3%

(w1o73)

RnWI NMA A?171 Ref. 4.3.11 tI-%)Sdo 730 RWCLI ReG4 3

W

~

eian70 Heat Exc~hanger TE0444' A1741 (Sectia 7A.60~

Inlet Temnpemlrebme CO AWCU'Suc~ion EMIWAp MIA 4.9.5l

+/-O.ý'

(1,13 "1:

1 ace;6*

t1011nA Page 72 of 94

LE-0113 Revision I OWmelon.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 A,~q5~'9~- 87

-,- xe).,cn.

Reactor Core Thermal Prower UrWizrtainlY Cak W14tijoi Unit 2 LE-0114 Revjison 0 Table 2-1.

PunV NrNi~lri

-A~

NO,-

94.0 % (Alkcmn 10 &

f~n~r~or

.ZA)-p20 91 4.2) 77%~ Hip (5.74 ¶VWJ NurfIp W~vf 2ACRM-M2 WA I'A NA O"

Page 73 of 94

LE-0113 Revision I OWmelitin.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 A

Pit le d 4.

__ExeI'~;n.

RatrCix~e Theo-naI Pc'wto LE-01 14 Revision 0 Tabibo 2-I1.

oe-sign sImpu~s ant.

f rnj oputer Mma ai

~tit Daaerlpftn 0o6 POWioinlntA ne"ll WfKCU Dixhorqa TE-044-o Temperanfire 2NG1i 5

.7'F (erln746 PWOCU In et4cMOPwhp3 171.1

~~~~~A27, 3Z

' Ok 7a13 I3TJhCU Regor,

.11I

~

Heat Ex~.hainger ITEý04.

7.+

Inlet Fren~porafure i tdr.ýý4ý43

.1

rioy uc~

iI NIA,,

NIA

'-DO 'Fr~nd VfA1p4 t0.005 Ut-lw.On AA 4-9:311.

¶>~2-;'Ak~ ~cc0r Page 74 of 94

LE-0113 Revision I Exelain.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 A)q5 S7 Al o'C (

I A5K PE'OT TOQUY GFiH FIAR I1OMr24 Figure 3-3: Reactor Heat Balance - Revised TLTP 1-101.65% CLTPI (TFw =427.1°F/ POmF=, 1060 psial rulnp 4.44 3-10 Page 75 of 94

LE-0113 Revision I Exelon.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 NIST Thermophysical Properties of Water Isobaric and Isothermal Properties of Water Temperature Pressure Density Volume Enthalpy Phase (F)

(psia)

(Ibm/ft3)

(ft3/Ilbm)

(Btu/Ibm) 97.200 1452.7-62.299 0.016052 69.127 liquid 97.200 1462.7 62.301 0.016051 69.153 liquid 97.200 1472.7 62.303 0.016051 69.180 liquid 96.500 1462.7 62.309 0.016049 68.458 liquid 97.200 1462.7 62.301 0.016051 69.153 liquid 97.900 1462.7 62.292 0.016053 69.848 liquid 530.90 1074.7 47.275 0.021153 525.50 liquid 535.30 1074.7 46.987 0.021282 531.00 liquid 539.70 1074.7 46.693 0.021416 536.56 liquid 535.30 1064.7 46.980 0.021286 531.02 liquid 535.30 1074.7 46.987 0.021282 531.00 liquid 535.30 1084.7 46.994 0.021279 530.99 liquid 427.10 1159.7 52.801 0.018939 405.65 liquid 427.10 1169.7 52.804 0.018938 405.66 liquid 427.10 1179.7 52.808 0.018936 405.6.7 liquid 426.53 1169.7 52.830 0.018929 405.04 liquid 427.10 1169.7 52.804 0.018938 405.66 liquid 427.67 1169.7 52.779 0.018947 406.28 liquid Saturated Steam (Water Vapor) Properties Temperature Pressure Density Volume Enthalpy Phase (F)

(psia)

Ibm/ft3)

(ft3/Ibm)

Btu/Ibm) 549.43 1040.0 2.3426 0.42688 1191.9 vapor 551.77 1060.0 2.3934 0.41781 1191.1 vapor 554.08 1080.0 2.4446 0.40907 1190.2 vapor "Thermophysical Properties of Fluid Systems" by E.W. Lemmon, M.O. McLinden and D.G. Friend in NIST Chemistry WebBook, NIST Standard Reference Database Number 69, Eds. P.J. Linstrom and W.G. Mallard, National Institute of Standards and Technology, Gaithersburg MD, 20899, http://webbook.nist.gov, (retrieved January 22, 2010).

Page 76 of 94

LE-0113 Revision 1I "Mt: I xelon.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 CTP Calculation Results Sensitivity Analysis The sensitivity of the calculation of core thermal power to variations in the energy terms is determined using estimated values for the energy out, energy in, and CTP.

Table A7-1 shows the results from Cases 1, 2 and 3. For this analysis, the error rate assumed for Qs is set equal to a predicted error for the measurement of feedwater flow.

In Case 1 and Case 2, the Qs error is kept the same; even though, the errors for the QRAD, QRWCU, QP, and QCRo terms are varied from 1 % to 19 % (29 % for Qcd). Case 1 and Case 2 show that CTP is relatively insensitive to the accuracy of the QRAD, QRWCU, Qp, and CCRD terms, when the CTP error is rounded to level of significance.

Case 3 varied the error rate assumed for Qs. A step change in the mass flow error rate of 0.01 % (from 0.31 %

to 0.32 %) was found necessary to change the CTP error by 0.02 % (a change of 1 MW from 17 MWtto 18 MWt and 0.500 % to 0.520 %).

The step change error rate was calculated to determine how fine the parameters used to calculate Qs and QFW need to be to effect the results. Parameter changes that would result in changes in the parameter's overall error rate less than 0.02 % were found to be negligible. Small variations in the flow measurement uncertainty were found to affect the CTP uncertainty.

For example, CTP is the difference between the energy leaving the reactor and the energy put into the reactor from other sources outside of the core. The enthalpy of saturated water varies with changes in pressure. For every 1 % change in pressure, the enthalpy of saturated water vapor (and by inference the energy of the flow) between 800 and 1,300 psig will vary by an average of 0.03 %. This change in enthalpy is less than the 0.04 %

found necessary to cause a significant change in the CTP error rate. Thus, CTP can be said to be tolerant of the steam dome pressure measurement error specified the pressure measurement loop is shown to be accurate to about -10 psig, which is approximately 1 % of the maximum allowable steam dome pressure.

Table A7-1. CTP Calculation Sensitivity Analysis Sensitivity Analysis Case 1 Case 2 Predicted Predicted Energy in Assumed error as Assumed error as percent of error rate Percent of error rate Percent of CTP Case 1 CTP Case 2 CTP Case 3 Predicted Assumed error as error rate Percent of Case 3 CTP 0.32%

0.489%

1%

0.000%

1%

0.001%

Qs QRAD Qcu O out QFW Oip Qcrd Q in QcTP Energy Out 18,030,078,635 Btu/hr 152.70%

0.31%

0.473%

3,754,300 Btu/hr 0.03%

1% 0.0003%

16,407,160 Btu/hr 0.14%

1% 0.0014%

18,050,240,095 Btu/hr 152.87%

Energy In 6,201,235,621 Btu/hr 52.52%

0.31%

0.163%

37,146,642 Btu/hr 0.31%

1% 0.0031%

4,578,000 Btutnr 0.04%

1% 0.0004%

6,242,960,263 Btu/hr 52.87%

CTP 11,807,279,832 Btu/hr SRSS all error terms' 0.500%

SRSS only Qs and Qfw error terms t 0.500%

0.31%

0.473%

10%

0.003%

10%

0.014%

0.31%

0.163%

0.32%

0.168%

10%

0.031%

1%

0.003%

10%

0.004%

1%

0.000%

0.500%

0.5001/6 tError rounded to 3 significant figures Convert to MW Btu/hr per W 3.412 Btu/hr per MW 3,412,000 In MWt Q out 5,290 MWt Q in 1,830 MWt CTP 3,461 MWt t Error rounded to 2 significant figures 0.520%

0.520%

Case 3

+/- 18.00 MWI Case 1 Relative errors MWt Case 2

+/- 17.31 MWt

+/- 17.31 MWt Page 77 of 94 I

LE-0113 E

(

Reactor Core Thermal Power Uncertainty Revision 1 o___

Calculation Unit 1 Derivation of the relationship between flow, AP, and density A8-1 Basic Flow Equation Given that the basic flow equation (Reference A8.3-1) applicable to orifice plates, flow nozzles, and venturis is Q

A C 1

, where C is a constant (Equation A8-1).

Then the relationship between flow (Q) and differential pressure (AP) and density (p) can be derived.

A8-1.1.

Relationship between Q. AP and D For constant density, the flow can be shown to vary with the square root of AP such that, 0,1

_A' 1.

Q2 Al'2 (Equation A8-2)

If the variation around some nominal flow, Q0, is equal to some known uncertainty, a1, then Q1 = Qo * (10 -

1 )and Q2 = Qo * (1 + al)

(Equation A8-3)

Similarly, if the variation around some nominal differential pressure, AP0, is equal to some unknown AP uncertainty, ax, then AP1 = Po * (1 -

ax )and AP2 = Po * (1 +

7x )

(Equation A8-4a)

For constant AP, if the variation around some nominal density, PO, is equal to some unknown p uncertainty, oT, then P1 = Po * (1 - o-x)and P2 = Po * (1 + Gx)

(Equation A8-4b)

These values can be substituted into Equation A8-2 and the equations manipulated to solve for a,.

Q0 *(-,)

Po *('-ax)

Qo*1+ai Po*1+ax),AP (Equation A8-5a)

Q. *(0-a,)_ Po0

,)

Q* F1+ a1 )

1+o-x )for p (Equation A8-5b)

Crossing out like terms from the numerator and denominator, rearranging, and squaring both sides yields E

(-a,) 2 (1i-cr7)

,~

^,

(Equation A8-6)

Equation A8-6 can be simplified by defining a new function of a1:

Page 78 of 94 I

LE-0113 Reactor Core Thermal Power Uncertainty Revision 1 Calculation Unit 1 Y(1) 1 )

(1 + a,)

(Equation A8-7)

Substituting Y(ai) into Equation A8-6 and rearranging, gives y(o1 )2 = (1-0x)

T _70-J (Equation A8-8) 1+0"

+a).

Y(oFq)2 = (1-O)

Haio) 2 + Y(0-1)2. U.x)= (1--x Solving for a), gives the relationship between the uncertainty y,, for either AP or p, and the known uncertainty of flow, al.

a), + Y(al)2.,Tx (I iy(,1)2 )

a.(1 +y(,i)2)r(1 y(,_i)2)

" -Y c )2)

Fx -- _

,,,Y1

)2 (Equation A8-9)

Table A8-1 shows the relationship between the uncertainties in pressure or density, a(, and the uncertainty in flow, a1, to be essentially linear with a constant of proportionality equal to 2, see A8-11.2, provided a* is small, which is taken to be less than or equal to 15 %.

Thus for small flow uncertainties, small a1, Equation A8-9 can be simplified as a linear function f(al),

Equation A8-10, which says the uncertainty in differential pressure or the uncertainty in density is approximately equal to 2 times the flow uncertainty. The inverse is also true; given a differential pressure or density uncertainty, the uncertainty of the flow is one-half the differential pressure or density uncertainty.

rx = n a a1,

(Equation A8-10)

A8-1.2.

The Limit of n The limit of the constant of proportionality, n, in Equation A8-10 as c0 approaches zero is found to confirm that n can be considered as a constant within the range of a1 less than 15 % to 0.

Limr(n)= Lim r0-x:Lim 1+ y(.J7

= Lim(

1-Y(-1)2, Recalling Y(al) and expanding Y(ai) 2 in terms of 01 Lim 1_-Y(()

2

= Lim (1+ 2c, ++-1 2 2 uj ýOa 1I+_+Y(ai) 2 )

0_

1_0 1+ 1-2a, 2

a,2 (1 1+ 2oa1 +0a12~

Page 79 of 94

LE-01 13 Revision I amrxel6n.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 Lim( (1+20.a +uj2 )-(1-22a,+0-2)

_12 )

Limr 4-1 Lim C a,O O-I 1-40 rj 1

2o-j +0-12 )--(I1--2a,

-+-0_12 a]j -ý (al Ol2-+

2a-12))

i--0 T2 + 2 1

2

, which after substituting 0 for a1 gives Lim (n) = 2 A8-1.3.

References

1. ASME PTC 19.5-2004, Flow Measurement, Performance Test Code, ASME International Table A8-1.

Relationship between ca, Y(ai), ax, and n 1'

Iý 7)'x I-Y(0-1Y)2 n :f O-x):

o.__

0Y(°1)=

TX

+y(

.1)2) 0.0000001 %

99.9999998 %

2.OE-09 2.0000000585 0.001 %

99.998%

2.OE-05 1.9999999998 0.4 %

99.2 %

0.008 2.0000000004 5.0%

90.5 %

0.100 1.995 10.0%

81.8%

0.198 1.980 15.0 %

73.9 %

0.293 1.956 20.0%

66.7 %

0.385 1.923 25.0 %

60.0 %

0.471 1.882 30.0 %

53.8 %

0.550 1.835 35.0%

48.1%

0.624 1.782 40.0 %

42.9%

0.690 1.724 45.0 %

37.9 %

0.748 1.663 50.0 %

33.3 %

0.800 1.600 55.0 %

29.0%

0.845 1.536 60.0 %

25.0%

0.882 1.471 65.0%

21.2%

0.914 1.406 70.0%

17.6%

0.940 1.342 75.0 %

14.3 %

0.960 1.280 80.0%

11.1%

0.976 1.220 85.0 %

8.1 %

0.987 1.161 90.0 %

5.3 %

0.994 1.105 95.0 %

2.6 %

0.999 1.051 100.0%

0.0%

1.000 1.000 Page 80 of 94

LE-0113 Revision I WOtmelein.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 Ametek Scientific Columbus Exceltronic AC Watt Transducer Specification (4 pages)

Exceltronic watt and var transducers provide utility and industrial users with a high degree of accuracy for applications requiring precise measurements. These transducersprovidea dc-outpurtsignal proportional to input warts orvars. All models are available with a wide range of input and output options.

Accuracy to 0.2% of reading

Exceptional reliability

Excellent long-term stability

Self-or externally powered

+ No zero adjustment required

Most popular models are UL Recognized

Substation monitoring

SCADA

Energy-management systems

Distribution monitoring

Process control

0 to +/-1 mAdc 0 1-5 or 1-3-5 mAdc

4-20 or 4-12-20 mAdc

10-50 or 10-30-50 mAdc Also available,inXLo odiJdarrplug9i40 ormat for*limited--

~,.~.space applicafions rqu~nng lrenmeso rndcr 4.To four or eight moidules in one enclosure:i Easyto

.istall expand or repair

'0 Convenient front panel access or calibrationý andotu currentejacks avalable:

{:...:';'.

!.{ :! : i, :See.p'ages.77 494 ifor mr e6 infor'maion*h. "i;ii;i:.i;7i i' i :i * :i AMETEKO Power Instruments 255 North Union Street Rochester, New York 14605 Phone: 1-800-274-5368 Fax: 585-454-7805 42 Page 81 of 94

LE-0113 Revision I 15Wtxel6n.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 EXETRIONI AC WTTVA~R

.omimam 5A Eaeae.

ir Range~

0-10 A A Overload F

oanHnuous 20 A

-.*Overload I Second/He 250 A rnANominal nva rlod Cottanueu e

2u V 1Burden/Element D.035 VA 0

maximum at 120 v Cemi Inepu Range 85-135 Vac ee Oe-130 Vac 85-135 Vac 100-130 Va 4

DAepy Frequency Range 50-5OD Hz 50-500 Hz 5D-500 Hz 50-500 Hz E Ee _.A1 Burde n 3 VA Nominal Nominal 3 VA Nominal 6VANomnt l I~*!~~*:i : [.!i.

+ mfor V.

ar 50,nAdc lor

+/-t mAdcto, In 5, 20, or50 mAdcftor Ste t aard l-"ni Standard Calibrng ion Sid.Cal um rtln, dependingon Standard Calibration Sgd. Calibration, dependingmon s e,_i d output range-selected output rang.*

[d+/-e0 Zero

.2%Readinone+equite ) +/-50.2% eadin +i.i5%R)

N+/-1o2%

Readqng+O2%RD) +/-(0.3% Rerding 0.05%m R)

,::::l'i.at 0-200% Re 0-1ý20% AD at G-200% Re at 0-120% RD

Y--

05 /I C

.01175%

/ C

+/-O 909%/ C

+/-0.012% /I GC p oe;i64 eneW ue an r 2.Co+T.CCt+01C-2D'"

C to +60V C

-20*'

C to +50" C

nSee ble onPage 40.

S o

e SeTle 2 on page 40.

O.0.25%

R.

0.0% Rlem 0.25% R0

< 400msto99%

<1 ;econd to 99%

c<400 Is to99%

< I Second tog99%

Pw r fcuL-.'-:*-.!

Any p F Egglbi"A~b a* * :': :

-0.1 % VA (mnaximnu, 1

+/-:0.35% VA [maximum)

.. lir.

i"Ifi[

Gainj

2% off Reding (minimnum) I l+*0 f Span (minimum)

_+2% of Reading (mini-u)_20 ofSa mnmm

!A bi s.:!::

i.Z*NoeRequired 15 fero Point (minimum)

None Required 1+/-5% of Zero Point (minimuml 58"42 Hz, 60 Hz "St bil _/(p e'6*.

e

.02F

+/-0.1% RD, 015% of Spn RD.2 gO+/-

10.25c%.1 Span,

i;'::i*'.i::.i:i.';:.*.:',*i Noncumulative

I oncumulative Noncumulative Nocmulative Of-eriNngnHonddtns0-95 t......

j Complet (PPInVOutpult/PoweF/Cass) 0ieleciii ciIN~hsi;;'di.

.;ii i!" :.':!

2500 VRMS*** et 60 H, SrANSI/IEEE C37.90.1

,Maxinin'm Pet W ight 3:: Ii

(.

tbs., 5 Wz. J1.5 kg) 4 tbs., a oz, tZkg) 3 lbs., 5 oz. (1.5 k0l 4 lbs., 8 oz. 12 kg)

(ext!~l:gn nn*pat 0t12 mMWx`99 mlm x I119 ram) I]

Mm X94 MM x 142 Mo)a 12mm) 9m 9m in"m x9 ix 1

m (17811 11m x4mr x 142 mm)

i:!iii,*i:.*:~i~*:!:!!

Style 11Case, seep e 22 te C....

paget122 atl Il Case, see page 122 Style 11 Casa, see page 122 2

.fiO veoa

.a -.g ft t Li ni d.io

rh

[.

500-1000 W atts/Elem en t 50040 0 W atts/Ele. ent 500--1000 Va /5

- 00 V s/El em en t N addition error within voltage compliance. Reduce faod resitance as r equired.

P.a Ppton inctudes t-5ft-3-5, 4-2 0 0. coo 5 0I, e" output,.

tpecitieetioes subjecto ehange without notice.

Total input not to exceed 2O0% of stanudnOt i

ts or -

h naUits molt to +/-1 mAde output.

o0tal input not to exceed 120% of mania ooali raton wane otoc en units with P-Option outputs.

0ieteetri, tenets as indicated tar UL Recon 'red moeans; levels mvry earn nootUL Recognized models.

AMETEK0 Power Instruments 255 North Union Street Rochester, New York 14605 Phone: 1-800-274-5368 fax:585-454-7805 43 Page 82 of 94

LE-0113 Revision 1 Exelevin.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 Ordering Procedure Exceltronic AC Watt or VarTransducers ORDERING PROCEDURE Specify by base model numbor and appropriate selection or option suffixes in the order shown in the following example.

Auxiliary Current Voltage

-RS/Freq.

Option Option External Base Model No.

Output Power Input Input Option #1

2

3 Aux. Power Table I Table 2 Table 3 Table 4 Table 4 Table 5 Table 6 Tablet6 Table 3 Oto+/-1 mAde output P-Option outputs EXAMPLES:

XL342K5A2-5-l-RS-SM-SC 3-element, 0 to +/-1 rAdc Watt Transducer', 120 Vac external auxiliary power; 10 A input; 240 V input, resistor scaling (converts current output to voltage output); seismic brace; special calibration (example: 7200 WI.

XL342K5PAN7A4-5-1-RS-SM-SC 3-element, 4-20 rnAdc Watt Transducer, internal auxiliary power, 10 A input; 240 V input; resistor scaling (converts current output to voltage output); seismic brace; special calibration (example: 7200 W).

Table 1 Base Model Number Selection Element 2

21/z" 3

Watt Model Noe.

XL-5C5 XL5C5l1/2 XL31KS XL31 K521nO XL342K5 Var Moedl No.

XLV5C5 XLV5C5Iv2 XLV31K(5 XLV031 K52 11 XLV342K5 Connection Single Phase 3 Phase, 3 Wire 3 Phase, 3 Wire 3 Phase, 4 Wire 3 Phase, 4 Wire Calibration at Rated Output (5 A. 120 V Nominal Inputl 500 W or Vars 1000 W or Vote tgO W Or Vars 1500 W or Vars 1500 W or Vats win-and2m-element its require a balanced voultaau, Taible 2 Oatput Selectiont Oto f1 mAd;o eutpati isý standard and to spacitied byte Bane Madel:ý-

rnumers-Pot outputs other 6bee tto +1:iit4de; in~dicate

-the aprpia.te peatiot at the cempolete-moeal comnbat!;:

P-Option PAN6 PAN7 PAN8 PAN&-B PAN7-B PANO-B PA6 PA7 PAt PA6-B PA7-B PA8-B Otputot Rane 1-5 mAdc 4-20 mAde 10-50 mAdc 1-3-5 mAdc 4-12-20 mAdc 10-30-50 mAdc 1-5 mAdc 4-20 mAdc 10-50 mAdc 1-3-5 mAdc 4-12-20 mAdc 10-30-50 mAdc Compliance Voltage/

Maximum Load 15 Vdc/3000 D 15 Vdcel50 a 15 Vdc/3000 15 Vdc/3000 Q, 15 Vdcf75O 15 Vdc/300 a 40 Vdc/8000 Q 40 Vdc/2000 QI 30 Vdc/600 0 40 Vdc8000Q Q 40 Vdc/2000 Q3 30 Vdc/600.L Maximum Open Circuit Volttae 30 Vdc 30 Vdc 30 Vdc 30 Vdc 30 Vdc 30 Vdc 70 Vdc 70 Vdc 70Vdc 70 Vdc 70 Vdc 70 Vdc AMETEK0 Power Instruments 255 Nortlh Union Street Rochester, New York 14605 Phone: 1-80-274-5368 Fax: 58$5-454-7805 44 Page 83 of 94

LE-0113 Revision I IFO 1AMMOAft Wcelein.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 Ordering Procedure Exceltronic AC Watt or VarTransducers TWbO Auxiliary Power Supply Selection (D to +/-11 made Units)

A4 lP-Option Units)

A2r. (leave blank)

A4 Descriptitr fnat Range Frequency Ranne External Auxiliary Power (120 Vac std.)85-135 Vac 50-510 Hz Internal Auxiliary Power (self-powered) 70-112% of Nominal Aux. PowerVoltage Equals Input Frequency External Auxiliary Power (120 Vac std.)

100-130 Vac 50-500 Hz Internal Auxiliary Power (self-powered) 84-108% of Nominal Aux. PowerVoltage Equals Input Frequency Burden 3 VA 3 VA 6VA 6 VA Foe external auxiliary pewervoltages other than 120 Vac. specifythe olitage In the last positionl fthe complete model number. lExamrple:

240 Vac Aox.l 1 Table 4 Input Selection I

Current

-3

.4 Std.-I

-11

-5 15A Current Range Nominal WIU Accuracy IA 0-2A 2.5A 0-5A 5A 0-10A 7.5 A 0-15 A 10A 0-20 A 0-20 A1500 W or Vars/Element 25 A 0-30 A Ca libration at Rated Output 15 A Nominal inputl 100 W or Va rs/Element 250 W or Va rs/Element 500 W or Vars/Element 750W or Vars/Element 1000 W or Vors/Element 2500 W or Vars/Element Voltage Voltage Range Calibration at Rated Output iatigon Nani es

/Accuracy f120 V Nominal Inpull

-0 69 V 0-75 V 250 W or Vors/Element Std.e**

120V 0-150V 500 W or Vars/Elemeet

-1 240 V 0-300 V 1000 W or Vars/Element

-9 277 V 0-340 V 1200W or Vars/Element

-2 480 V 0-600 V 2000 W or Vars/Element -7

L e..

2 r!

pŽ~ioix nblank in the mudel number.

Option -t requires a Style I case. (See page 122 to case dimenonius. 1 Maxhmum heightaeterminal stelp(s) is 1.0ta or units with -8 option.) I Table 5 Scaling Resistor (-RS)/Frequency Options Rualie Dlescription I You must specify the desired output eoltage:

-RS Scaling Resistor ForOtos+/-! mAdeunits specify range from litoe

+/-0Vdc. Load

-6 400 Hz impedance is I ML0/Vdc (minimum).

-12 50 Hz (not UL Recognized)

For P-teiaon units, specify range tram 0-15 Vdc (PAN models) or RSt 400 Hz and Scaling Resistor 0-40Vdc(PAmodelsl. Load impedance is 200. 50. er2OillVdc) RSt 50 Hz and Scaling Resistor lminimm)for units with outputs of 5,20. oru50 mAde. respectively.

This informatlio is not part at the medal number. bet masc be provided ia the factory when you place your order.

Table 6 Other Options

-20

-21

-24

-CE

-SCIT

-SM Description tt You must specity the desired input value:

50-200% Ca libration Adjustment (current outputsol Blo+/-1.eAc1z can be calibrated within 90-1113%

ityheir standard-50-200% Calibration Adjuostment (voltage outputs) calibration input wans or ears. tExample:

A 2-element wall trans-(available only with 0 to +/-1 mAdc units) ducer is calibhated io aw 1

Wstundard. The-SC option can be 24Vdc Loop-Powered (PA7 and PA7-B models only) added for input levels from 90DW a90%)In 18ta W (lte%).l Mind (consult factory for specifications) af aceea he calibrated within 6e-180%

of theirstandard-ealibratoex Analog Output Shorting Relay Input wats orvars.

{available only with 0 to +/-1 mAdc units)

This Infnation is not part of the model number. but must he provided Special Calibration to the factory when you place yourorder.

Seismic Brace (available with 0to+/-1 mAdc units) icontssaltacntoy it youdesire this option wioth a Wtxrqmeedtna praunthwhr e

pc Zero-Based Output Calibration (ex.: PA7-Z = 0-20 mAdc) eýth- 'h..p-ioth'ya mstlirst cu-lt the.l.tIry-af:-

a P-Ops:;,:morie ptxe en ith pa ione 120 Whey e rden aonyspuctet pnax f

acr~fr (available only with P-Option units, except PAN-B

p:!riic n: and

n

-l-delivXer eutriates

ý'

-1.

. : :1; :!**

.1 - ::

models)

AMETEK6 Power Instruments 255 North Union Street Rochester, New York 14605 Phone: 1-800-274-5368 Fax: 515-454-7105 45 Page 84 of 94 I

LE-01 13 Revision 1 Exe6n.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 0 B32-C-001-J-023, Rev. 1, Recirculation Pump Curve (1 pages)

WC NC3 2fiLla~r. rrA A.j9 A014 OII CO 0

' 21 Ep

.C 1

.I

.~I

[

-~~~~

r j:

Ii' rA: :~:d

/I lb-

iit1-1

"/-3ý01t'3 -

Page 85 of 94

LE-0113 Revision I Exel6n.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 1 Rosemount Inc., Instruction Manual 4259, Model 1151 Alphaline A Flow Transmitter, 1977 (PAGES 1,6, 14, 24, AND 29)

INSTRUCTION MANUAL:4259 MODEL 1151DP ALPHALIKE4 FLOW TRANSMITTER CAUTION:

READ BEFORE ATTEMPTING tHSTAýLLA-T1Ot4 OR MAIINTEiNANHCE TO AVOID POSSIBLE WARRANTY 'INVALIDATION CONTENTS INSTALLATiON C~aldbratOn Spý Coqrrectiqnr f9' High Line Pressures OPERATION

Specifications I 115DP Square Root SMIN TENANCE PARTS LISTM/DPAW.INGS Oesign. Specifications Parts List Drawings and Schematicsý Pael page 4 Page.4 Page 5f Page 11 Page 14:

Page 15 coP pyin~s normot't!Nwi

??r?4. 79?,5 '976

'ALPH *ALINE: AND',5-CELL' are Rosemount Trademarka Fia.,a Obe 0airy 1 Grrc~

! :.'a L'Ii6ýil t...lrgrs y~.3.27, ?.6 3.3r5 3.618.390;3.ýe465a8:

a:/e79.F&S

r~d2.41;~74C.2 3;r5.e8; ard.659.534.

Cii-lar Prfehlrýf sass. 4a7J.

Noe~

)ei~eaer.

M5$ 7 Othw U.S. arw5 ForcF~irPzsrsrvs isljvd~or pL,;qq*

RoseMoUnlt.

POST OFFICE BOX.35129 t4INhhAPObLS, idNNE. TAi1,54?.5 PHONE; (612)941.5S6. TWX; 955.576.9103 TELEX: 29-0133 CASLE; POSEMOUNT,CT, R~evised 11/77.

Page 86 of 94 I

LE-01 13 Revision I V.XG16n.

Reactor Core Thermal Power Uncertainty Calculation Unit I Specifications -. I 1510 iP VA"P FloIw Transmitter Functional Specifications Service Liquid. gas or vapor.

Rang"s 0M5/30 inches H20 0-25/150 inches HO 0.125/756 ii,cheg t-,O Outputs"

' 4;21 mADG. squAre'rooi dilnput Power Supply External p5owio supply required. Up to"45 VDC. Transmilter operates on. 12 VaC with no load.

Load Limitations See Figure. 7.

Indication Optifonal.meter with 1-3/4:' linear scale, O-.100.

'di' dtliOnracc* (lrcy is "f2%" f span.

Hazardous Locations

'Ea~lptoon proof:. Apprqed. by Foictoiy Mutual for Class I, Division 1, Groups B, C "nd).;:Clais it. lDivis'on 11, Groups E*YF

and 0; and Class Ill.

OIvision 1.

Cerliiicatib nby Canadian Standar'ds Association (CSA) for Class: I. GroUpssC and 0 available as an optionm intrinstcally safe: FMeeijifcafio'nt (ptioasl torClass

1. Division 1; Groups B, COand D when used wilh listed barifer systems.

Span and Zero Continuously. adjustable externally.

Zero Elevation and.Suppression Zero elevation oIzero suppression uplto 100%1 ot r6Fibrated san!n Temperalure Limits Fto +150"F'Arrpllfier operating,

-400 F to

+220°1F Sensing. element operating.

-60c1F to + t80°F Stbrase.

Static Pressuie aid OvDrpreswure Limits o psii to20no p,*ig on eithoeridob wilhbOt damage :to lih6e transmitter. Operates within speciflcations betweenstatic line piessiires ui lit plsi am), 2000 psly.

10,000 psig proof. pressure on the flanges.

Humidity Limits 0-00o% RH.

Volumetric I!sp.lacermenl Loss than.0.01 cubic inches.

"o m.n r rer. 'eot sppro,,c. for. Gro.p S.

Domping:.

Fixed..response-tinme o-11/3.second.

(Iorner t' equericy tf 0.4 H-zi" Turn-on time ID Seconds. NO. warmup re.tuired.

Performance Specifications

!ZSSOý eASED SPANS nrEFrEtCE CON0,.

rVONS; 3i(rSS lSOL~AriNG tniAlh!qAGM5A Accuracy;

.:025% or calibrated span.lor a rangeof.

25%6q i6' 1 d foa (V S1(6%t 100% of inpiut pressurel. Includes:combined effecls-ol.

hysteresis, repeatability and conformity of ihe square root function.

Dead Basd-None;:

Stabilty,

+/-0.25% of upper ranrge limit.for 6 months Temperature Effect The Iota! effect'including zero'an, span.

errors: :t.5, of upper range limit per.

100°F. (12.5% foi lovw range.)-

Overpressure Effect Zeroý shift of tess than,O6.54 ol..upper range limit tor 2000 psi (+2.0%. or rango.

5).

Static Pressure Effect Zero ErrOr: i0.5% of upper rangelirnit for 2000 psi. (.1.0%4 Ior ian*e 3).

Span Error.,.- 0o5.t% of rading. per 1000 psi (-0.7510. i% tlo range 3l. Tints is a

systomatic error.which can be-calibrated out for a particular pressure I ftore Installation.

Vibration Effect

-Os.05% o upper rangllii it per g 1o0200 Hz in any eais.

Power Supply Effect Less than 0.005% of output span pIr vblt:-

.Load Eifecl No'toaa eflect cother thIii U4icmirige f6 "power supplied to thetrensmiller.

Mounting Position Effect:

.Zero shift of up. to. 1"-H0 which can be calibrrtodout. No-s:ari ifb~t. No 0:tffb'i' in Plane.of diaphrtagm.

Physical Specifications Materials of Constructiont

IsolaInlig Dlapfhragms and" Dr infVert.

-Valves:*

315655.-HASTELLOY C or MONEL Process:Flanges and Adapters:

Cadmidm.Plated.Ca/boh Stdel; 316SSi

HAPTELLOY q or. MONEL.

Wetled "0-Rings VITON.

Fill Fluid:

.Silicone Oil.

Bolls:

C.dmium Plated CarbonsSteel.

Electronlca.Housing:

.vw-copper a!umninu.m (NEMA4' Paint.

.Ptlyansfer-Epoxy.

Process Connections 1i4-NPT on 218 oentl.es. on).tlanges.,

1/2-NPT on 2" 2-118" or 2-li4" centers sith" adipimer

,Eletricala Connections

/!2-lilei cohridirri whiii scfew lerrrrirlfs and.tintegral fest jacks compatible:with miriature banana plugs (Pormrona 2944, 3646 or rta)

Weight 1"2 boiids excluding opoirins.

FIGURE 7 LOAD LiFAITATIONS io.........!ii*i **~b * ;

LOS*.

,a 20 ac,

.55 POWER SJherLV.,DC!

7.

fMJHClrC is a Oradr,vrh or rle,rOli-ral iý; ail'.

Co. HASTFLLOY. is J.A9er~r~

ir s;s Corp. VITON ir a..C,&omtriadema~i Trtasrolegt, per SCAMA Stauar,drrPIC.2 is IM3 Page 87 of 94

LE-0113 Revision 1I

_Exe6n.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 PARTS LI ST/DRAWINGS SECTION Design Specifications I MO0EL IALPHAILINE -A-P FOW TRANSMITTER I. I,11)p I

LCODE RANGES 4

0-'51o q 0.1Inc hes

, j I-. O O. l 7 t

-O R lom ZO.I..0 S10125 t~o U;75'01clas H, O (0ý317ii tb*-1500m I

iO ICODE OUTPUT I

c 4-26 rrAbd. btluar rotits! Input MATERIALS'OF CONS7RsCT1ON.

OtIAIN.yEir VA~L~VE 130LATINGOIAPHIIAGMS CODEI FLANGES AND ADAPTERS 12Cadmiawr Pilate C; E.

3.16-SS18 (3

CadmnI um Plaied C, 5.

FIAsTELCOYC r-ATLO

7 ti Cadmium P~latd CIS.

.ELMOL 23:- 3655316S6 HAST.ELLOY C-276 24:. 316S§ 3 18.55 IJONEL

.33 HASTI-LOY C IIASTBIACNyC

'A-TELLO.YT7.4745 14 MONEL MOiEl.

MONEL CODE 1oPTIONS LM M9 pa; F;3

,n I.

02

CE Linear. MettO 0-100%5 scale OPIeCsal Muollvnq Bracket for Mount~inglt 26, P'ipe op~loý imoalmfi g.a ioa(

1w.nbl' Mwnllj,,5 OpI5 ial F1,11 Moas,,

tBra

~vx4 ' w1w MUI 1.pipe S5,iln Vt1101.41 Tn~p SýIo "e lnovoin. B.4Iv, CeoadiaLv Slad1fnds AssoCjwibn (dSAl Eoplonbon P~rottl:Crtlicaiar;o 1w Clasii.

.GrnOUs C end 0:Cia.s II..G,'ovps E..F anti G:.Class !$.I: l(si. IV).

9iý IN TAINSI IC SAFETY APPR'OVAL (AD Are AýProaod*ý Sn aclw Muuai(

CLASS 1, DIV. 1, BARRIER GROUPS AGENICY MANUFACTURER AAvRIER MODEL a

PMFub2 AI-I2(J-P13. 2AI-(3V-F!OR x

Y FM

T.y6o 124511 34; 12ý f4l x

x 124S9INS19.12S53 x

X 12451234, 12451264 FMwentingro"Se 76S01 x

FM LnyANcrnhap-316569. 31 6247-X F i1 PjScaC, & I'rlre, 805H623U0I. 805H027UOix FM 1`F60er CoOi~oIs XC3 X F3 F4.

F?

I FM Hontqell 38S4S5XXkOt (0

-11,1 l2-56

.4

.4 Fte

.4 C

12 LM. Me COM1101PLETIED DESIGN SPECIFICATION STANDARD.ACCESSORIES All Models-are ship-ped with flange adapter, vent/drain valves and one Ins~trUCtIlo' mnnual per shipme'nt.

OPTIONAL THREE-VALVE MANIFOLD3 (Packaged Separately)

Pa31 No. 115 1.150-1: 3valveltMar.itold, Carbon.StIee (Anderson, Greenwood &.Co., M4AVC).

Part No.

1151-150-2: 3-Valve MPgnifold.

316SS (Anderson, Greenwood & Co., M4A V S)

TAGGING ALPHALINE Dilferentia I: Pressure Trans-mitters will be taggedl in accordance wilt customer requ rements. Al: tags are stinles steel.

CALIBRATION Transmlites -are factory Calibrate,!

to customer's: specified, span. It calibralion is not specified.transmitters Pre roalibrated at meximnum range. Calibration is at amb ient temperature and pressure.

0.-

11 Page 88 of 94

LE-01 13 Revision II Ff X,cxel6n,..

Reactor Core Thermal Power Uncertainty Calculation Unit 1 2 Bailey Signal Resistor Unit Type 766 (2 pages)

GEK-75733 VOLUME IV EQUIPMENT NOMENCLATURE Pressure Transmitter Power Supply Conductiv ity Elemeut Trip Calibration Unit Relay Switch Recorder Switch Pressure -Switch Recorder Pressure Transmitter Signal Resistor Unit Inverter Inverter TABLE OF CONTENTS VENDoR/MODREL NTMBP Rosemount Model 115IDP General Electric Models

9T66y987, 9T66Y988 and 9T66Y989 Balsbaugh Model GVI-2-N/910.IT-IEN Rosemount Model 510D0-2 General Electric Modal HKA General Electric Model C1940 Westronics Model MSE General Electric Models SB-1. SB-9, SB-10 and SDM Barksdale Model BIT-MI2SS-GE Leeds and Northrup Speedomax Model M Rosemount Model llS1DP Alpha line Bailey Type 766 Topaz 5000 Series Topaz Modal

)M50-GWRS-125-60 1

2 3

4 S

6 7

9 10 11 12 13 14 iv Page 89 of 94

LE-01 13 Revision I Ulmrxel6n.,

Reactor Core Thermal Power Uncertainty Calculation Unit I RM Page 23 4576K16-001 REEWAL PARTS FIG. &

REF.

UNITS INDEX NO.

PART NO.

DES.

DESCRIPTION PER/ASSY 3

6146K15P277 R3 RESISTO TYPE T-2C) 4 61468IK68P0 MR3

RESISTOR, 242 OilS, -

O. M FIXED,

4 614SK68POIS R4

RESISTRo, S OHMS, iO.17, FIXED, WIRE-WOUND, 0.66 WATT, (V17870, TYPE R1375) 5 6149K92P303 RI

RESISTOR, 12100 OHMS,

+/-0.1T. FIXED WIRE-WOUND, (V17870, TYPE R1391-0030),' 0.25 WATT 5

6148K60P217 R2 RESISTOR, 400 OHMS, 0.1% FIXED, WIRE-WOUND, 0.66 WATT, (V17870, TYPE 1375) 6 6146K15P226 R3

RESISTOR, 100 OHMS, t0.L% FIXED, WIRE-WOUND, 2.5 WATT, (V91637, TYPE RS-2C)

(V00213, TYPE 1200S) (V12463, TYPE T-ZC) 7 6146K15P271 R3 RESISTOR, 96.8 OMIdS, tO.1% FIXED, WIRE-WOUND, 2.5 WATTS 7

6148K68P522 R4

RESISTOR, 3.2 OHMS,

-0.17. FIXED, WIRE-WOUND, 0.66 WATT (V17870, TYPE R1375 8

6146K15P277 R3

RESISTOR, 250 OHMS,

-0.1% FIXED, WIRE-WOUND, 2.5 WATTS, (V91637, TYPE RS-ZC) (V00213, TYPE l.00S) (V12463, TYPE T-2C) 9 6146K15P280 R3

RESISTOR, 242 O4S, tO.17. FIXED, WIRE-WOUND, 2.5 WATTS (V91637, TYPE RS-2*)

(V00213, TYPE 1200S)

(V12463, TYPE T-2C) 9 6148K68PO15 R4 RESISTOR, 8 OHMS,

-0.1% FIXED, WIRE-WOUND, 0.66 WATT (V17870, TYPE R1375) 10 6146K15P226 R1

RESISTOR, 100 O01iS, -O.17, FIXED, WIRE-WOUND, 2.5 WATT (V91637, TYPE RS-2C)

(VO0213, TYPE IZOOS) (V12463, TYPE T-2C) 11 6146K15P271 R1 RESISTOR, 96.8

0H4S,

+/-0.1% FIXED, WIRE-WOUND, 2.5 WATTS, (V91637, TYPE RS-2C)

(V002l3, TYPE 1200S) (V12463, TYPE T-2C) 11 6148K68P522 R2 RESISTOR, 3.2 0M4S, -0.1% FIXED, WIRE-WOUND, 0.66 WATT, (V17870, TYPE R1375)

L2 6149K94P007 R1

RESISTOR, 150 OHmS,

+/-5% FIXED, WIRE-WOUND, S WATTS, (V44655, TYPE 995) 12 Page 90 of 94 I

LE-0113 Revision II Exel*n.

Reactor Core Thermal Power Uncertainty Calculation Unit 1 3 Rosemount Specification Drawing 01153-2734, N0039 Option - Combination N0016 & N0037 (2 Pages)

V N0039 9 T" nEscReleoa ECO NO.

I APP-DA*E A jOr ignal Release 626853

ýM 1'/-4?ý I

I I.

SCOPE This specification defines a Model 1153 Series B pressure transmitter with combined options N0016 -

a stainless steel 1/2 -

14 NPT pipe plug installed in one of the conduit hubs, and N0037 -

a 4-2OmA output signal with adjustable damping.

I1. DETAILS

1.

The pipe plug is to be assembled on the nameplate/vent valve side of the transmitter.

The plug will be sealed with thread sealant and torqued to 150 in.-lbs.

2.

The standard "R" calibration and amplifier boards are replaced with the special damping calibration and amplifier boards.

III.

SPECIFICATIONS Maximum damping for the electronics, measured at the 63% time constant is:

Range 3 Range 4 Range 5-9 Maximum Damping not applicable 1.2 seconds 0.8 seconds The damping electronics are not intended for the range 3 because the slower response Is not required for this transmitter pressure range.

IV.

APPLICABILITY AND APPROVALS This specification is limited to the Model 1153 Series B with "R" electronics.

Qualification with the pipe plug was addressed in Rosemount Report 108026 (see paragraph 5.3.1).

Qualification of the damping option was addressed in CLASS IE USAGE 1Iosen

_n.,t.

MINNEAPOLS. mINNESOTA OILm By ATE Hidbad 11/

Specification Drawing NOo39 Option - Combination N0016 & N0037 SOO OD IDENT NO,13RAWING NM 3

A 0427401 A 11N3-2734 ISHEET IOF 2 MASTER DRAWINC I _________________

I Form No. 60299-1, Rev. A Page 91 of 94

I"meleing LE-0113 Revision 1 Reactor Core Thermal Power Uncertainty Calculation Unit 1 Rosemount Report 08800053.

The damping option is qualified to the levels of the 1154 transmitter.

However, when being used in the Model 1153 transmitter, the qualified requirements are those for the original Model 1163 transmitter.

They are not altered because of the presence of the damping electronics.

MASTER DRA\\AlING SCLASS E USAGE O DI04E 4E.

NO 0RA Wi 4

NO.

CLS tEUAE 47 01153-27 34 I

I*EEr 2 0*2 I SHEET 2 o2 Form No. 60299-2. Rev. A Page 92 of 94

awmelon.

LE-0113 Revision I Reactor Core Thermal Power Uncertainty Calculation Unit 1 4 Rosemount Product Data Sheet 00813-0100-2655, Rev. AA June 1999 "N-Options for Use with the Model 1153

& 1154 Alphaline Nuclear Pressure Transmitters" (2 Pages) 008.13-0100-;;655 Julie M999 Rev. AAk N-Options for Use. with the Model 1153 and Model 1154 Aiphaline Nuclear Pressure Transmitters ROSEMOUNNUCLAR FISHER-HOSEfNT MrulihO Tha Pmcm iuttar.

Page 93 of 94

LE-0113 Revision 1 ffo Reactor Core Thermal Power Uncertainty Calculation Unit 1 INTRODUCTION RosemountPModel 1153 and Model 1154 Alphalineo Nuclear Pressure Transmitters are designed for precise pressure measurements in nuclear applications which require reliable performance and safety over an extended service life. These transmitters have been qualified per IEEE Std 323-1974 and IEEE Sit 344-1975 as documented in the corresponding Rosemount qualification reports.

Model 1153 and Model 1154 Transmitters are available in a variety of configurations for differential, flow, gage, absolute, and level measurements. To accommodate specific customer requirements, special N-Option features have been developed to provide greater application flexibility.

For example, the NO010 option allows a transmitter to be calibrated up to 5%. over its standard upper range limit. The N0026 option allows a Range Code 4 Transmitter to be calibrated up to 210 inH20 rather than the standard Range Code 4 upper range limit of 150 inH0.

Following is a summary of selected N-Options. For additional information on these and other N-Options, contact Rosemount Nuclear Instruments, Inc.

SUMMARY

OF N-OPTIONS N0002 Specifies a reverse-acting gage pressure transmitter:

N0004 Specifies factory calibration of the transmitter at temperatures above or below room temperature. Transmitters may be calibrated at temperatures between 40 and 200 'F.

N0010 Allows the transmitter to be calibrated up to 5% above the standard upper range limit. For example, if the stated upper range limit of the transmitter is 1,000 psi, an N0010 transmitter may be calibrated up to 1,050 psi. This option is available on all ranges.

N0011 Allows 180' rotation of the electronics housing.

N0016 Specifies a stainless steel pipe plug installed on the nameplate/vent valve side of the 1153,Series B Transmitter.

Rosemou*tl Nucleam Inslrumenls, Inc.

12001 Technology Otsve Eden PMrle, MN 55344 Tel j612) 828-8252 Telex 4310012 Fax (612) 828-8280 0 195 Rosemount Nuclear instsume*t. Sic.

[ll$1111PA1.1a

%lolntcomn 00813-0100-2655 Rev. AA N0018 Specifies a maximum static pressure rating of 3,200 psi rather than the standard 3,000 psi on any high-line differential pressure transmitter.

N0022 Specifies a welded '/4-in. Swagelok" compression fitting on differential and high-line transmitters.

N0026 Allows an 1153 Series D or 1154 Range Code 4 transmitter to be calibrated up to 210 inH2 0 rather than the standard Range Code 4 upper range limit of 150 inH20. Thie maximum and minimum span limits are 155 and 75 inH20, respectively.

N0029 Specifies factory calibration of the transmitter at a customer-specified elevated line pressure.

N0032 Specifies a Range Code 3 or 8 differential pressure transmitter with a maximum static pressure rating of 2,500 psi rather than the standard 2,000 psi. Applicable to Model 1153 Series Transmitters only, N0033 Allows 90' clockwise rotation of the electronics housing. The terminal block lines up with the vent/drain valve side.

N0034 Specifies a Model 1153 Series D or Model 1154 Transmitter with a special mounting bracket that has no panel mounting holes.

N0037 Specifies adjustable damping on any Model 1153 or Model 1154 Transmitter.

N0077 Specifies a Model 1153 Series F with a SST electronics housing, SST housing covers and SST mounting bracket.

N0078 Allows 180' rotation of the process flanges N0088 Allows 90° counterclockwise rotation of the electronics housing. The terminal block lines up with the process connections.

ORDERING INFORMATION Consult the appropriate transmnitter Product Data Sheet for a transmitter model number. Append the N-Option number to the end of the transmitter model number. An example of a typical model number with N-Option added is 1 153DB5RAN0010.

Posemn'J'rt, the Rosemount inpo, nd AdlpanDne are registered trademarks 0f Rosemnount Inc.

sivagelo is a registereed rsemars of Cromord Fitting Co.

AMay be protected by one or moe or the oilowing U.S. Patent mos.

3,646,538 3,793.865: 3,800,413; 3,975,7 t9 Re. 30,603. Canada patented (srevete) 1974, !975, tO70, and t979. May depend on modet Other foreign patents issued and pending.

Cover po-to: t153-3OOtAS SFiser-Rosemount satisfies all obligations coming from legisiation to harmonize product requirements in the C

E uropean union.

Page 94 of 94

ML102070197

Contents

Text

Title:

4.0 REFERENCES

8.0 CONCLUSION

4.0 REFERENCES

784.70 Btu/lbm 6C TP

8.0 CONCLUSION

Subject:

Subject:

Dear Customer:

Subject:

SUMMARY

Navigation menu

ML102070197

Text

Title:

4.0 REFERENCES

8.0 CONCLUSION

4.0 REFERENCES

784.70 Btu/lbm 6C TP

8.0 CONCLUSION

Subject:

Subject:

Dear Customer:

Subject:

SUMMARY

Navigation menu

Search