NLS2007069, Calculation Nedc 06-035, Revision 0, Reactor Core Thermal Power University, Enclosure 7

Calculation Nedc 06-035, Revision 0, Reactor Core Thermal Power University, Enclosure 7

ML073300575
Person / Time
Site:	Cooper
Issue date:	10/23/2007
From:	Nebraska Public Power District (NPPD)
To:	Office of Nuclear Reactor Regulation
References
NLS2007069 NEDC 06-035, Rev. 0
Download: ML073300575 (64)

Text

NLS2007069 ENCLOSURE 7 NEDC 06-035 REACTOR CORE THERMAL POWER UNCERTAINTY CALCULATION APPENDIX K MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE COOPER NUCLEAR STATION DOCKET NO. 50-298, DPR-46

Page 1 of 63

Title:

Reactor Core Thermal Power Uncertainty Calculation Number: NEDC 06-035 CED/EE Number: 07-01 System/Structure: None Setpoint Change/Part Eval Number: None Component: .None Discipline: Instrumentation and Control Classification: [ ) Essential; I X I Non-Essential SQAP Requirements Met? [ ] Yes; I X ] N/A Proprietary Information Included? [ ] Yes; [X] No

Description:

The purpose of this calculation is to determine the total uncertainty in the thermal power calculation performed by the GARDEL heat balance. The calculation is being performed in support of the Meter Uncertainty Power Uprate (MUR)

Licensing Application Request (LAR).

Conclusions and Recommendations:

The total uncertainty associated with the HEABAL (Reference 5.5.1) when feedwater flow is measured with the ASME Flow nozzles is -1.2973%/+1.8954%.

The total uncertainty with the HEABAL (Reference 5.5.1) when feedwater flow is measured with the Caldon UFM is

-0.3112%I+0.3118%.

o / W5 11, 4A 7 *

• tllo ,o**

Rev. Approved Number Status rep Reviewed By/Date IDVed By/Date By/Date Status Codes

1. Active 4. Superseded or Deleted 7. PRA/PSA

2. Information Only 5. OD/OE Support Only

3. Pending 6- Maintenance Activity Support Only

Page: 2 of 63 NEDC:06-035 Rev. Number:0 Nebraska Public Power District DESIGN CALCULATION CROSS-REFERENCE INDEX ITEM REV. PENDING CHANGES NO. NO. TO DESIGN INPUTS 1 Drawing 2004, Sheet 2 N46 N/A 2 Drawing 2039 N53 DCN 07-0899, 07-0900 3 Drawing 2049, Sheet 4 N13 N/A 4 Drawing 2849-4 N10 DCN 07-0091 5 Drawing 556-26811 4 N/A 6 Drawing 3043, Sheet 12 N15 DCN 06-1711 7 Drawing 3254, Sheet 13 N22 DCN 04-1569 8 Drawing 117C3485, Sheet 1 19 N/A 9 Drawing 117C3485, Sheet 2 7 N/A 10 Drawing 158B7077 2 N/A 11 Drawing 730E148BB, Sheet 1 1 N/A 12 Drawing 791E252, Sheet 1 N10 DCN 04-0616, 07-0084 13 Drawing 791E254, Sheet 1 N08 N/A 14 Drawing 791E263, Sheet 2 N17 N/A 15 Drawing 0199F0377 N12 DCN 04-1444 16 Drawing 0199F0380 N12 DCN 04-1445 17 Drawing E515, Sheet 9 N01 N/A 18 Drawing E515, Sheet 55 N02 N/A 19 Drawing E515, Sheet 60 N01 N/A 20 Drawing E515, Sheet 82 N01 N/A 21 Drawing E515, Sheet 88 N01 N/A 22 Drawing E515, Sheet 121 N01 N/A 23 Drawing E515, Sheet 144 N01 N/A 24 Drawing CP008, Sheet 1 N04 N/A 25 Procedure 3.26.3 6 N/A 26 Procedure 14.NBI.301 4 Rev. 5 27 Procedure 2.2.8 64 N/A 28 Procedure 15.RR.301 3 N/A 29 Procedure 2.2.66 86 N/A 30 Studsvik Scandpower Report: SSP- 0 N/A 04/414-C 31 Rosemount 00809-0100-4801 AA N/A 32 RTP Bulletin RTP7436 Series N/A N/A Nebraska Public Power District

Page: 3 of 63 NEDC:06-035 Rev. Number:O DESIGN CALCULATION CROSS-REFERENCE INDEX ITEM DESIGN INPUTS REV. PENDING CHANGES NO. NO. TO DESIGN INPUTS 33 RTP 981-0021-211A A N/A 34 KEPCO 146-1869 N/A N/A 35 Rosemount 00813-0100-2654 FA N/A 36 Rosemount 00813-0100-4021 FA N/A 37 Rosemount Cal. Report 1/5/06 N/A 38 Rosemount 00809-100-4360 AA N/A 39 Badger Cal. Data Report N/A 40 GE 198 4532K30-010 N/A N/A 41 Scientific Columbus Bulletin N/A N/A 42 Daniel Technical Bulletin N/A N/A 40 Barton Bulletin G1-25 N/A N/A 43 Part Eval. Tech. No. 10511159 0 N/A 44 NEVC 70-263 (Roll 00111, Frame 0 N/A 0033) 45 GE 21A1379AR (Roll 09021, 4 N/A Frame 1898) 46 Alden Report (Roll 08118, Frame 7/70 N/A 1295) 1 47 GE FDI 71/101000 (Roll 17524, 1 N/A Frame 0604 1 48 CED 6010820 0 CCN 1-16, OSC 1-16 49 NEDC 00-095A 4 N/A 50 NEDC 94-018 3 3C1 THRU 3C21 51 CED 2000-0032 0 N/A 52 Cameron Report ER-592 1 N/A

Page: 4 of 63 NEDC:06-035 Rev. Number:0 Nebraska Public Power District DESIGN CALCULATION CROSS-REFERENCE INDEX ITEM AFFECTED DOCUMENTS REV. NUMBER NO.

______None.

Page: 5 of 63 NEDC:06-035 Rev. Number:0 The purpose of this form is to assist the Preparer in screening new and revised design calculations to determine potential impacts to procedures and plant operations.@

SCREENING QUESTIONS YES NO UNCERTAIN 1 Does it involve the addition, deletion, or manipulation of [] [X] [ ]

a component or components which could impact a system lineup and/or checklist for valves, power supplies (breakers), process control switches, HVAC dampers, or instruments?

2 Could it impact system operating parameters (e.g., [] [X] [ ]

temperatures, flow rates, pressures, voltage, or fluid chemistry)?

3 Does it impact equipment operation or response such as [ ] [X] []

valve closure time?

4 Does it involve assumptions or necessitate changes to the [ [X] [II sequencing of operational steps?

5 Does it transfer an electrical load to a different circuit, or [ ] [X] [ I impact when electrical loads are added to or removed from the system during an event?

6 Does it influence fuse, breaker, or relay coordination? [ ] [X] [ ]

7 Does it have the potential to affect the analyzed [ ] [X] [ ]

conditions of the environment for any part of the Reactor Building, Containment, or Control Room?

8 Does it affect TS/TS Bases, USAR, or other Licensing [] [X] [ I Basis documents?

9 Does it affect DCDs? [] IX] [I I 10 Does it have the potential to affect procedures in any way not already mentioned (refer to review checklists in [ ] IX] I]

Procedure EDP-06)? If so, identify:

If all answers are NO, then additional review or assistance is not required.

If any answers are YES or UNCERTAIN, then the Preparer shall obtain assistance from the System Engineer and other departments, as appropriate, to determine impacts to procedures and plant operations. Affected documents shall be listed on Attachment 2.

Page: 6 of 63 NEDC:06-035 Rev. Number:0 Nebraska Public Power District DESIGN CALCULATIONS SHEET

1. PURPOSE:

To determine the uncertainty of the reactor thermal power (heat balance) calculation performed by the process computer (GARDEL). Cooper Nuclear Station (CNS) will be installing highly accurate ultrasonic feedwater flow meters. This calculation will determine the uncertainty in reactor thermal power calculation when the reactor heat balance is performed using the installed ASME flow nozzles to measure feedwater flow and when the process computer is using a corrected feedwater flow measurement provided by the Caldon LEFM Check Plus Ultrasonic Flow Meters (UFMs).

On June 1, 2000 Appendix K to Part 50 of Title 10 of the Code of Federal Regulations was changed allowing licensees to use a power uncertainty of less than 2 percent 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 Application Request (LAR) for a Measurement Uncertainty Recapture (MUR) power uprate.

2. ASSUMPTIONS:

2.1. The heat balance per Reference 5.5.1 assumes 0.0 for steam moisture fraction. The fraction assumed for steam moisture is a conservative value and results in a higher calculated power than actual power. Since this parameter is always conservative it is not accounted for in the heat balance thermal power uncertainty calculation.

2.2. The energy lost due to radiation and heat transferred through vessel is assumed to be 0.6 MW in the heat balance. There is no plant* or fleet specific uncertainty number for the losses assumed in the plant process computer. Per Reference 5.6.10 the uncertainty in this number is high and a

+50% uncertainty in the number would result 0.015% uncertainty in CTP for a 3400 MWth plant. It is assumed a +50% bounding uncertainty can be associated with 0.6 MW radiative loses at CNS. This results in a radiative loss uncertainty of +/-0.3 MW.

2.3. The plant process computer uses mathematical operators, conversions and algorithms to process the signals from the process instrumentation. In addition, tables based on ASME and Keenan and Keyes are used to determine fluid enthalpies and per Reference 5.6.10 the differences in the different steam tables are negligible when compared to other uncertainties in the overall core power determinations. The operations performed by the process computer are carried to many significant digits and are considered very accurate. It is therefore concluded that no considerations are necessary for computation uncertainties of the process computer.

Page: 7 of 63 NEDC:06-035 Rev. Number:0 2.4. Control Rod temperature is not measured and it is assumed in the process computer that Control Rod Drive (CRD) temperature is always 100 *F. The CRD pumps take suction on the hotwell level makeup line. The line is from Condensate Storage Tank A, suction of the Condensate Booster Pumps, and Condenser Hotwell (

References:

5.1.2, 5.1.5, and 5.1.9). The water is norimally 102.83. °F per Reference 5.1.60 and the water in Condensate Storage Tank A is maintained above 40'F per Reference 5.1.15. Although it is possible the CRD pumps may take suction directly on the Condensate Storage tanks it is highly unlikely except during a outage. It has therefore been assumed in this calculation that CRD temperature when at or near 100%

power is 102.83°F with a +10°F band added for conservatism. Furthermore, as given in Reference 5.6.10 the calculated core thermal power is insensitive to the temperature assumed for control rod water temperature.

2.5. CRD system provides Reactor Recirculation (RR) pump purge seal flow, Reactor Water Clean-up (RWCU) mini-purge pump seal flow, and continuous cold reference leg backfill. The flow paths are upstream of the CRD flow element and the flow is not accounted for in the measured CRD Flow. RR pump purge seal is adjusted to be between 1.65 and 1.85 gpm per pump (Reference 5.3.7), RWCU mini-purge is adjusted be between I and 2 gpm per pump (Reference 5.3.5), and each reference leg (2) backfill is adjusted to be between 0.0095 to 0.0105 gpm (Reference 5.3.8). The total maximum flow not accounted for in the CRD measured flow is 7.721 gpm. The heat balance accounts for this flow by adding a constant 6 gpm to the measured CRD flow (Reference 5.5.1). The error associated with the flows and the contribution the flows would have to the core thermal power uncertainty is assumed very small and negligible.

2.6. The original calibration data for the RWCU flow elements (orifices) was not retrievable.

However, in Reference 5.4.1, paragraph 11-111-7, when it is not possible to calibrate an orifice in the meter tube assembly the discharge coefficient can be calculated. The discharge coefficient in the calculation is not expected exceed +1.0%. Another +/-1.0% was added to the assumed and expected accuracy to conservatively account for lack of the original manufacturer's calibration data.

2.7. The calculation was performed at based line conditions for the current licensed power of 2381 MWth. However, the calculation is considered applicable when operating near 100% thermal power and for 1.7% increase in the thermal power increase. A 1.7% power increase will for most parameter result in no change and for some parameters (e.g. feeedwater parameters) only a slight change (< 2 °F and 5 psi).

3. METHODOLOGY:

Page: 8 of 63 NEDC:06-035 Rev. Number:0 Reactor Thermal Power is calculated in the heat balance program HEABAL (Reference 5.5.1). The thermal power is determined by the simple relationship of Q = Energyout - Energyj". HEABAL uses the below equation to determine Core Thermal Power (CTP).

CTP = Qs + QCU + QFL - QFW - QCR - QP Where:

Qs = Steam Energy Qcu = RWCU Energy QFL = Radiative Power Losses QFW = Feedwater Energy QCR = CRD Energy QP = Recirculation Pump Energy Per Reference 5.5.1 each of the terms of the heat balance equation are determined using the below listed plant parameters (instruments). The calculation also uses several constants for conversion and assumed factors (e.g. 0.0 for moisture).

PC Signal GARDEL Description Plant Instrument Name B031 TFWA I FW Loop A Temperature RF-TE- 140C B033 TFWA2 FW Loop A Temperature RF-TE-140D B030 TFWBI FW Loop B Temperature RF-TE-140A B032 TFWB2 FW Loop B Temperature RF-TE-140B B015 WFWA2 FW Loop A Flow RFC-FT-50A B016 WFWB2 FW Loop B Flow RFC-FT-50B B025 PR1 Steam Dome Pressure NBI-PT-53A or 53B B014 WCR1 Control Rod Drive Flow CRD-FT-204 B023 TCUI RWCI Inlet Temperature RWCU-TE-92 B024 TCUO RWCU Outlet Temperature RWCU-TE-109 B017 WCU RWCU F/D A Flow RWCU-PE-77A

Page: 9 of 63 NEDC:06-035 Rev. Number:0 B018 WCU RWCU F/D B Flow RWCU-PE-77B B019 PP1 RR A Pump Motor Power RR-XFMR-TRIA B020 PP2 RR B Pump Motor Power RR-XFMR-TRIB The calculation will determine the individual instrument loop uncertainties used in the heat balance using the methodology given in Reference 5.4.2. Not each instrument loop used in the heat balance contributes equally to the thermal power calculation uncertainty. Therefore, baseline conditions will be established at 100 percent reactor power and then a sensitivity analysis will be performed to determine the effects or weighting factors that each loop uncertainty has on the heat balance calculation. The results of the loop uncertainties and weighting factors will be combined and the individual loops will than be totalized to determine the total uncertainty in the reactor thermal power heat balance calculation.

Vendor documentation (non-As-Built) has been used for determination of instrument accuracy. The information is contained mainly in Manufacturer's Equipment Specifications and Technical Bulletins. The vendor documents are prime and many times the only source for determining the accuracy of the instrument.

Listed below are the various instrument module uncertainties considered for each of the process instrument loops.

DE Instrument Drift Effect FE Flow Element Fouling Effect IE Flow Element Installation Effect MTE Meter and Test Equipment Effect OE Other Effects PSE Power Supply Effect RA Reference Accuracy RE Resistor Effect RES Resolution Effect ST Calibration Setting Tolerance TnD Te....erature Effect on Density

Page: 10 of 63 NEDC:06-035 Rev. Number:0 TE Temperature Effect TLU Total Loop Uncertainty 3.1. Feedwater Flow Uncertainty 3.1.1. Feedwater Flow Elements RF-FE-I1A Mfr.: Permutit ASME Flow Nozzle Serial Number: T-12125 RF-FE-11B Mfr.: Permutit ASME Flow Nozzle Serial Number: T-12126 3.1.1.1. Reference Accuracy:

Per Reference 5.6.2 the Feedwater Flow Element has a +/-0.5% accuracy. The accuracy is based on the discharge coefficient and represents an uncertainty on the actual flow. Per Reference 5.6.3 the flow element were calibrated in a test line and had a calibration accuracy of 0.00096 and 0.00219 for T-12125 and T-12126, respectively. Therefore, as a matter of conservatism the accuracy of Reference 5.6.2 will be used as the reference accuracy for the flow elements.

RAFWFE = +/-0.5% of Actual Flow 3.1.1.2. Installation Effect:

The installation effect of the flow elements is dependent of whether the flow nozzles were installed per industry standards. Per Reference 5.4.1 paragraph 11-I-3 if the installation meets the minimum pipe lengths upstream and downstream than the errors due to piping configuration is less than +/-0.5 % otherwise an addition tolerance of +/-0.5 % should be applied to the flow measurement. In accordance with Figure Il-II-1 a minimum of 16 Diameters upstream and 2.3 Diameters downstream of straight pipe should be installed for a flow nozzle with a 13ratio of slightly greater than 0.5. Per Reference 5.1.13 and Reference 5.6.3 nozzles T-12125 and T-12126 have P3 ratios of 0.5192 and 0.5187, respectively.

The upstream and downstream number of pipe diameters per References 5.1.12 and 5.1.13 are given in the below table.

Page: 11 of 63 NEDC:06-035 Rev. Number:0 T-12125 T-12126 Required Upstream >18D >18D 16D Downstream >4D >4D 2.3D Since, the installation of the flow elements meets the minimum requirements of Reference 5.4.1 the uncertainty due to the installation effect is:

IEFWFE = +/-0.5% of Actual Flow 3.1.1.3. Fouling Effect:

Feedwater Flow nozzles have been known to foul due to the plate-out of iron oxides which result from the corrosion of carbon steel condensate and feed water systems. In Reference 5.5.17 a flow verification test and analysis was performed on reactor feedwater using the Caldon External LEFM Feedwater Flow Measurement System. The report concluded the LEFM flow rate was higher than the plant instrumentation value by -0.007%. It can be inferred from the test results that there little or no fouling of the ASME flow nozzles at CNS. However, as a matter of conservatism the value given in Caldon Report (5.5.16) on flow uncertainty due to fouling will be used to envelope any fouling of the flow nozzles at CNS.

FEFWFE = +0.6% of Actual Flow (Bias Term) 3.1.1.4. Temperature Effect:

A change in feedwater temperature can affect both the density and nozzle expansion. Both nozzle expansion and density corrections are made on the feedwater mass flow rate by the Process computer. Per Reference 5.4. 1, Figure 11-1-3, the Thermal Expansion Factor (Fa) is 1.0054 for the rated temperature of 367.1 'F. The calculated errorfor feedwater temperature is < 1 'F. The error introduced on the Area Factor due to the temperature error is a very small factor, not readable on Figure 11-1-3 ( on the order of 1.OXIOE-5), when operating off the rated feedwater temperature (367.1 'F) and can be neglected. The affect on density due to the temperature error with respect to differential pressure will be conservatively evaluated at a +/- I 'F at the rated conditions of 367.1 'F and 1175 psia (Reference 5.6.4).

Page: 12 of 63 NEDC:06-035 Rev. Number:0 p-1 (1175 psia, 366.1°F) = 55.291 ibm/ft33 p (1175 psia, 367.1 'F) = 55.252 ibm/ft p+i (1175 psia, 368.1 'F) = 55.214 IbM/ft3 The original calibration data for the transmitters based on the flow nozzles is given in Reference 5.6.4 as:

Flow T-12125 T-12126 FLOW Inches H2 0 at 68'F Inches H20 at 68'F Mlb/HR Zero 0 0 0.0 Rated 733.7 739.6 4.761 Full Scale 1165.2 1174.6 6.000 CED6010820 will respan the transmitter to 10 Mlb/HR full scale. Therefore, the new calibration pressures will be established using the relationship for flow versus differential pressure.

W = K (pDP)0 5 Taking the ration of the two flow conditions:

0 5 W2 = K (p 2DP 2)

Where: T, = T2 & P1 = P 2 therefore: p1 = P2 and the new full scale DP becomes:

2 DP 2 = DPI (W 2 / W1 )

Flow T-12125 T-12126 FLOW Inches H20 at 68°F Inches H20 at 68°F Mlb/HR Zero 0 0 0.0 Rated 733.7 739.6 4.761 Full Scale 3,236.7 3,262.8 10.000

Page: 13 of 63 NEDC:06-035 Rev. Number:0 The new respanned transmitter differential pressure values for full scale indication will be used in the forthcoming evaluation.

The percent DP at the rated conditions:

Loop A: (733.7/3236.7) X 100 = 22.6681% DP Span Loop B: (739.6/3262.8) X 100 = 22.6676% DP Span Using the larger of the two DP's for conservatism and keeping flow constant (rated) for the two conditions.

DP 2 = DPI(pl/p 2)

P-1:

22.6681%(55.252/55.291) = 22.6521%

22.6521% - 22.6681% = -0.0160%

P+I:

22.6681%(55.252/55.214) = 22.6837%

22.6837% - 22.6681% = +0.0156%

TDEFWFE = -0.0160%/+0.0156% or +/- 0.0160% of Span (Temperature Dependent) 3.1.2. Feedwater Flow (Differential Pressure) Transmitters RFC-FT-50A Manufacturer: Rosemount Model: 3051S Ultra RFC-FT-50B Manufacturer: Rosemount Model: 3051S Ultra Per Reference 5.6.5 the installed Rosemount 1151DP transmitters will be replaced with Rosemount 305 1S Ultra Differential Pressure Transmitters (Part Number: 3051 S-1-C-D-4A-2-A 11-A-I A-D1-M5-Q4-TI -A 1266).

3.1.2.1. Reference Accuracy:

Rosemount Reference Manual (Reference 5.5.2) lists a Reference Accuracy of:

+0.04% of span; for spans less than 10:1, accuracy=

Page: 14 of 63 NEDC:06-035 Rev. Number:0

+/-[0.005 + 0.0035(URL/Span]% of Span The specification is for 3 sigma, however the accuracy will not be converted to 2 sigma for added conservatism. The Upper Range Limit (URL) for a Range 4 is 300 psi. Converting to inches of water gives:

(300 psi) X (27.7277 "H20/psi) = 8318.31 "H20 Using the smaller of the spans (3,236.7"H 20) for conservatism, the reference accuracy becomes:

+/-[0.005 + 0.0035(8318.31 "H 2 0 /3,236.7"H20 ]% of Span

= +/-0.0140% Span RARFFT +/-0.0140% Span 3.1.2.2. M&TE Effect:

The test equipment calibration standards used to calibrate the transmitters are traceable to National Institute of Standards and Technology (NIST) and the test equipment is as least as accurate if not better than the equipment being calibrated.

Therefore, the M&TE uncertainty will be taken as the Reference Accuracy of the transmitters.

MTERFFT +/- 0.0140% Span 3.1.2.3. Setting Tolerance:

The Setting Tolerance is taken as the As-Left tolerance of the instrument. Per Reference 5.2.5 and 5.2.6 the as Left- Tolerance is +/-_0.1 mvDC for the transmitters. So the equivalent uncertainty of a 4 to 20 maDC loop is:

(0.1 ma/16 ma) X 100 = 0.6250%

STRFFT= +/- 0.6250%

3.1.2.4. Temperature Effect:

The transmitters are located in the Turbine Building Basement Control Corridor on Instrument Rack IR-1 D per Reference 5.1.18. The Control Corridor has a minimum temperature of 78'1F and a maximum temperature of 1 10 F per

Page: 15 of 63 NEDC:06-035 Rev. Number:0 Reference 5.6.1. The ambient change in temperature from the minimum calibration temperature to the maximum operating temperature is:

(110-F- 78°F) = 22-F Per Reference 5.5.2 the temperature effect is:

+/-(0.009%URL + 0.04%Span) per 50°F Using the larger of the spans (3,262.8"H 20) the temperature effect is:

+/-(0.00009 X 8,318.3 1"H20 + 0.0004 X 3,262.8"H 20)22/50

= +/-0.9037"H 20 Converting to percent span:

+/-(0.9037"H 2 0/3,262.8"H 20)X 100 =4+/-0.0277%

TEpFFT - --+/-0.0277%

3.1.2.5. Drift Effect:

Per Reference 5.5.2 the stability of the 305 IS is +/- 0.20% of the Upper Range Limit (URL) for 10 years. The transmitter is a Range 4 transmitter and has a URL of 300 psi. Converting pressure into inches of water at 68 'F gives a value of:

(300 psi) X (27.7277 "H20/psi) = 8318.31 "H 20 (8318.31 "H2 0) X (0.0020) = 16.6366"H 2 0 Using the lower of the two transmitter spans for conservatism to find drift per percent span:

+/-(1 6.6366"H 20 / 3236.7"H 20) X 100 = +/-0.5140% Span The transmitters are calibrated every 18 months versus 120 months and using the relationship given in Reference 5.3.1:

VDM = (M/VD 6)I12VD 6mo

Page: 16 of 63 NEDC:06-035 Rev. Number:0 (18/120)'/2(0.5141% Span) = 0.1991% Span DERFFT +/-0.1991% Span 3.1.2.6. Static Pressure Effect:

Some differential pressure transmitter experiences an output shift in the output due to line pressure. The effect is on both the zero point and the span of the transmitter. Model 3051 Series Ranges 4 and 5 are subject to this static pressure shift; however the zero error from the static pressure effect is calibrated. The span error per Reference 5.5.2 is +/-0. 1% of reading per 1000 psi. Using the total span for conservatism the Static Pressure Effect is:

+/-(0.001 X 3,262.8"H 2 0)(1175psi/1 000psi)

= +/-3.8338"H20 Converting to %Span:

(+/-3.8339"H2 0/3,262.8) X 100 = +/-0.1175%

SPERFFT = +/-0.1175% Span 3.1.2.7. Power Supply Effect:

The transmitters have less than a +/-0.005% of calibrated span per volt per Reference 5.5.2. The transmitters are powered from (or will be powered from after the implementation of CED6010820) two 24 VDC auctioneered KEPCO power supplies. The KEPCO power supplies are powered from either 115 AC Inverters RFC-IVTR-INVA or RFC-IVTR-fNVB. The inverters are powered from the 125 VDC Batteries (Reference 5.6.5). The power to the KEPCO power supplies is extremely reliable and stable. Per Reference 5.5.5 the KEPCO power supplies have a maximum reference variation of 0.3% combined effects from source, load, temperature, and time (drift). Using the maximum variation of the power supplies and stated power supply effect of the transmitters the following evaluation determines the power supply effect on the transmitters.

(24 VDC) X (0.003) X (0.005%/volt) = 0.0004%

PSERFET = +/-0.0004% Span

Page: 17 of 63 NEDC:06-035 Rev. Number:0 3.1.2.8. Resistor Effect:

The transmitter output provides a signal to the process computer by converting the current to a voltage by means of the voltage drop across a 15 Ohm +/--0.1% resistor (Reference 5.6.5). Therefore, the effect of the resistor in the instrument loop is given as:

RERFFT = +/-0.1% Span 3.1.2.9. Process Computer Effect:

The voltage drop off the precision resistor is used to provide an input to the MUX card which converts the analog signal to a digital signal. Per Reference E515, Sheet 144 the MUX card is Part Number RTP 021-5234-003 (Model Number:

RTP 7436/50-003) which is a 8-Channel Universal High-Speed Wide Range Gate Card. The card is part of a set and per computer applications personnel and the PMIS Database Information Editor the associated card in the set is an RPT 038-5097-000 (Model Number: RPT 7436/21-0008) which is the Analog-to-Digital (A/D) Converter Card. The card set per References 5.5.3 and 5.5.4 have a linearity of +/- 0.025% of full scale and a gain accuracy of less than +/- 0.025% of full scale.

The linearity and gain accuracy are combined using SRSS method to determine the Reference Accuracy.

RApc = +/- [(0.025)2 + (0.025)2]0-5 % Span RApc = +/-0.0354% Span The resolution effect (quantizing uncertainty) for the AID card is +/- 1/2 LSB (Least Significant Bit). The card is 14 bits so the resolution becomes:

RESpc = +/-(LSB / 2 Number Bits)X 100 %

RESpc = +(0.5 / 214) X 100%

RESpc = +0.0031% Span Setting Tolerance effects are errors introduced during the calibration process. Per Reference 5.5.3 the cards are not calibrated and no operator adjustments are made which could introduce an error due to a calibration process therefore, the Setting Tolerance and M&TE are negligible. Furthermore, the instrument drift is

Page: 18 of 63 NEDC:06-035 Rev. Number:0 negligible.

The cards are located in MUX 9-86 which is located in the Computer Room (Reference 5.1.28). The Computer Room is an air-conditioned controlled environmental space. For this reason any temperature effect is considered negligible.

The process computer uses algorithms and conversions to process the plant parameters. The computer also uses tables such as the ASME steam tables.

These tables are highly accurate and the computations are digitally performed to many significant digits. The error associated with the computations is miniscule compared to loop inaccuracies and are therefore negligible.

3.1.3. Total Loop Uncertainty Feedwater Flow Tabulated below are the uncertainties associated with the Feedwater flow loop.

RAFWFE +/- 0.5% of Actual Flow IEFWFE +/-0.5% of Actual Flow FEFWFE +0.6% of Actual Flow (Bias)

TDEFWFE +/-0.0160% (Dependent)

RARFFT +/-0.0140% Span MTERFFT +/-0.0140% Span STRFFT +/- 0.6250% Span TERFFT +/-0.0277% Span DERFFT +/- 0.1991% Span SPERMFT +/-0.1175% Span PSERpFT +/- 0.0004% Span RERFFT +/- 0.1% Span RApc +/-+0.0354% Span RESpc +/- 0.0031% Span TLUFWFI = +/- (RAFWFE2 + IEFWFE2)05 TLUFWFI +/-0.7071% of Actual Flow

+/-

Page: 19 of 63 NEDC:06-035 Rev. Number:0 2

2 TLUFWF2 = +/- (RARFFT + MTERFF2 + STRFFT 2

+ TERFFT2 + DERFFT2 + PSERFFT2 + SPERFFT

+ RERFFT2 + RApc2 + RESpc2)0"5 TLUFWF2 = +/- 0.6780% Span FEFWFE = +0.6000% of Actual Flow (Bias)

TDEFWFE = +0.0160% Span (Dependent with Temperature) 3.2. Feedwater Temperature Uncertainty 3.2.1. Feedwater Temperature Elements:

RF-TE- I40A Manufacturer: Rosemount Model: 0078L21C30NO80AX8X9Q4 RF-TE- I40B Manufacturer: Rosemount Model: 0078L21 C30NO80AX8X9Q4 RF-TE- 140C Manufacturer: Rosemount Model: 0078L21C30NO80AX8X9Q4 RF-TE- I40D Manufacturer: Rosemount Model: 0078L2 1C30NO80AX8X9Q4 3.2.1.1. Reference Accuracy:

The RTD Model Numbers are the new RTD's to be installed per CED6010820.

The RTD's are 100 Ohm, 4-Wire, Platinum, Single Element RTD's. Per the Rosemount RTD calibration data sheets the accuracy of the RTD's is +/-0.22 'F (Reference 5.5.8).

RAPTE = +/--0.22°F The RTD's are not adjustable and are not calibrated so there is no Setting Tolerance uncertainty or M&TE uncertainty.

The lead wire resistance effect is negligible for a 4-Wire RTD's.

The feedwater flow velocity at the piping location of the RTD's is approximately 20.48 ft/sec. Therefore, the self heating affect of the RTD's can be neglected.

Page: 20 of 63 NEDC:06-035 Rev. Number:0 3.2.2. Feedwater Temperature Transmitters:

RF-TT-168A Manufacturer: Rosemount Model: 3144PDIAINAB4M5T1C4Q4 RF-TT-168B Manufacturer: Rosemount Model: 3144PDIAINAB4M5T1C4Q4 RF-TT-168C Manufacturer: Rosemount Model: 3144PDIA1NAB4M5T1C4Q4 RF-TT-168D Manufacturer: Rosemount Model: 3144PDIAINAB4M5T1C4Q4 3.2.2.1. Reference Accuracy:

The RTD's are Class A Sensors per Reference 5.5.6. Per the I&C Calibration Sheets the span of the transmitters are from 0.0 to 150.0 mV for 280'F to 430'F.

Per Reference 5.5.7 the accuracy of the temperature transmitters is +/-0.18 'F plus

+/-_0.02% of span this gives a reference accuracy of:

+/-[((430 'F- 280 'F) X (0.0002)) + 0.18 'F)] = + 0.21 'F RARFTT =+/-0.21 'F 3.2.2.2. Setting Tolerance:

The Setting Tolerance is bounded by the "As-Left" Tolerance of the temperature transmitter: Per References 5.2.1 through 5.2.4 the "As-Left" for the old transmitter is given as +/- 0.3 mV for 0 to 150 mV span, this equates to +/-0.2% span which is the Setting Tolerance of the new transmitters.

+/-(0.002)(430 'F - 280 'F) = +/- 0.3°F STRFTT = +/-0.3 °F 3.2.2.3. M&TE effect:

The test equipment calibration standards used to calibrate the temperature transmitters are traceable to NIST and the test equipment is as least as accurate if not~better than the equipment being calibrated. Therefore, the M&TE uncertainty will be taken as the Reference Accuracy of the transmitters.

MTERFFT= +/-0.21 'F

Page: 21 of 63 NEDC:06-035 Rev. Number:O 3.2.2.4. Drift Effect:

Per Reference 5.5.7 the stability (drift) is +/- 0.1 % of reading or 0.1 'C (0.18°F) which ever is greater. At the maximum span temperature of 430 'F the error becomes:

+/-0.001(430'F) = _ 0.43°F DERFTT = +/-0.43 F 3.2.2.5. Power Supply Effect:

Per Reference 5.5.7 the power supply effect is less than +/- 0.005% span per volt.

The temperature transmitters are to be power from the same source as the reactor feedwater transmitters (See Step 3.1.2.7), therefore:

+(24 VDC) X (0.003) X (0.00005/volt) X (150 'F) = +/-0.0005°F PSERFTT= +/- 0.0005'F 3.2.2.6. Temperature Effect:

The temperature transmitters are located in panel 9-21 in the Cable Spreading Room per Reference 5.1.35. The Cable Spreading Room is an air-conditioned controlled environmental space. The possible change in temperature from the calibration temperature to the normal operating temperature is considered to be very small and therefore, the temperature effect is considered negligible.

3.2.2.7. Resistor Effect:

Per References 5.6.5 the voltage drop to the process computer is across a 15 Ohm

+/- 0.1% resistor. In a 4 ma to 20 ma loop the span is 60 to 300 mV and the resistor effect at maximum span becomes:

+(300 mV X 0.001)((150 'F/(300 mV - 60 mV) = +/-0.1875°F RERFTT= +/-0.1875°F

Page: 22 of 63 NEDC:06-035 Rev. Number:0 3.2.2.8. Process Computer Effect:

Per References 5.1.46, 5.1.47, 5.1.48, and 5.1.51 the reactor feedwater temperature loops uses the same mux cards as the reactor feedwater differential pressure loops (Refer to Step 3.1.2.9).

RApc = +/-0.035% Span = +/- (150'F)(0.000354) = +/-0.0531 'F RESpc = 0.00305% Span = +/- (150'F)(0.000031) = +/-0.0047°F 3.2.3. Total Loop Uncertainty Feedwater temperature.

Tabulated below are the uncertainties associated with the Feedwater temperature loop.

RAFWTE +/-0.22°F RAFWTT +/-0.21 'F STRFTT +/-0.3'F MTERFTT +/-0.21 'F DERFTT +/-0.43'F PSERFTT +/-0.0005'F RERFTM +/-0.1875°F RApc +/- 0.0531 'F RESpc +/-0.0047°F 2

2 TLURFTEMP--+/-+(RAFwTE + RAFWTT + STRFrT 2

+ MTERFTT2 + DERFFT 2 + PSERFTT

+F RRFTT2

+ RE 2 + 2+ usiC 0 5.

P-RARFFT2-REpc05 TLURFTEMP = +/-0.6704'F There are four feedwater temperature loops and per Reference 5.5.1 one loop temperature from each loop is used to determine the loop enthalpy and loop enthalpies are averaged in the power calculation. The averaging of the loop enthalpies is equivalent to the individual feedwater loop temperatures being averaged and therefore, the TLU becomes:

TLUAVERAGE = +/- (TLURFTEMp/(2) 0 -5)

TLUAVERAGE = +/-0.4741 °F

Page: 23 of 63 NEDC:06-035 Rev. Number:0 3.2.4. Ultrasonic Flow Meter RF-CC-4 Manufacturer: Caldon Model: LEFM 4,+2000FC Measurement System The Caldon Ultrasonic Flow Meter (UFM) will be used to correct feedwater flow signal.

Per Reference 5.6.11 the UFM has a total bounding mass flow accuracy of+/- 0.30 %. The quoted accuracy is the total accuracy of the mass flow signal from the Caldon UFM it incorporates: installation effects, piping effects drift effects, power supply effects, calibration effects, temperature effects and density.

RAUFM = +/-0.30% Flow 3.3. Vessel Pressure Uncertainty 3.3.1. Pressure Transmitter:

NBI-PT-53A Manufacturer: Rosemount Model: 305 IS Ultra NBI-PT-53B Manufacturer: Rosemount Model: 3051S Ultra 3.3.1.1. Reference Accuracy:

Per Reference 5.6.5 the installed Rosemount 151DP pressure transmitters will be replaced with Rosemount 305 1S Pressure Transmitters (Part Number: 305 IS-I-C-G-5A-2-A 1l-A-IA-DI -M5-P 1-Q4-TI-Al 266-Q8). Either NBI-PT-53A or NBI-PT-53B is used to provide the pressure signal depending on the position of the level switch on panel 9-5 (Reference 5.1.38). The transmitters have a span of 14 psig to 1214 psig (14 psi for head correction) for a 4 ma to 20 ma output (Reference 5.3.2). A range 5 transmitter per Reference 5.5.2 has an URL of 2000 psi and has a Total Performance of +/-0.125% of span (combined error of reference accuracy, ambient temperature and line pressure effect).

RAPT +/- 0.125% of Span 3.3.1.2. Setting Tolerance:

The Setting Tolerance is bounded by the "As-Left" Tolerance of the transmitter:

Per References 5.3.2 the "As-Left" is given as +/- 0.08 Ma of the output, so the Setting Tolerance is:

STPT = +/-(0.08 Mail6 Ma) x 100 = +/-0.5% of Span

Page: 24 of 63 NEDC:06-035 Rev. Number:O 3.3.1.3. M&TE:

The test equipment calibration standards used to calibrate the transmitters are traceable to NIST and the test equipment is as least as accurate if not better than the equipment being calibrated. Therefore, the M&TE uncertainty will be taken as the Reference Accuracy of the transmitters.

MTEPT 0.125% of Span 3.3.1.4. Drift Effect:

Per Reference 5.5.2 the stability of the 3051 S is +/- 0.20% of the Upper Range Limit (URL) for 10 years and +/- 50 'F. The transmitter is a Range 5 transmitter and has a URL of 2000 psi.

+/- (2000 psi) X (0.0020) = +/-4 psi

+/-+(4/1200) X 100 = +/-0.3333 % of Span for 10 years The transmitters are calibrated every 18 months versus 120 months and using the relationship given in Reference 5.3. 1:

VDM = (M/VD 6)I12VD 6mo (18/120)"/2(0.3333% Span) = +0.1291% Span DEPT +/-0.1291% Span 3.3.1.5. Power Supply Effect:

The transmitters have a +/-0.005% of calibrated span per volt per Reference 5.5.2.

The transmitters are powered from (or will be powered from after the implementation of CED6010820) two 24 VDC auctioneered KEPCO power supplies. The KEPCO power supplies are powered from either 115 AC Inverters RFC-IVTR-INVA or RFC-IVTR-INVB. The inverters are powered from the 125 VDC Batteries (Reference 5.6.5). The power to the KEPCO power supplies is extremely reliable and stable. Per Reference 5.5.5 the KEPCO power supplies have a maximum reference variation of 0.3% combined effect from source, load, temperature, and time (drift). Using the maximum variation of the power supplies and stated power supply effect of the transmitters the following evaluation

Page: 25 of 63 NEDC:06-035 Rev. Number:0 determines the power supply effect on the transmitters.

(24 VDC) X (0.003) X (0.005%/volt) = +/-0.0004%

PSEPT = +/-0.0004% Span 3.3.1.6. Temperature Effect:

The pressure transmitters are located on instrument rack 25-56 which is located in the Reactor Building, South East, Elevation 903'. Reference 5.6.6 gives the normal temperature variation as 70'F to 104'F. This is a delta T of less than 50

'F which is accounted for in the Total Performance (Reference Accuracy).

3.3.1.7. Resistor Effect:

The transmitter output provides a signal to the process computer by converting the current to a voltage by means of the voltage drop across a 15 Ohm +/-0.1% resistor (Reference 5.6.5). Therefore, the effect of the resistor in the instrument loop is given as:

REPT 0. 1% Span 3.3.1.8. Process Computer:

Per References 5.1.46 the reactor feedwater temperature loops uses the same mux cards as the reactor feedwater differential pressure loops (Refer to Step 3.1.2.9).

RApc = +/-+0.0354% Span RESpc = +/-0.0031% Span

Page: 26 of 63 NEDC:06-035 Rev. Number:0 3.3.2. Total Reactor Pressure Loop Uncertainty Tabulated below are the uncertainties associated with the Reactor Pressure loop.

RAPT +/-+0.125% of Span STPT +/- 0.5% of Span MTEPT +/-+0.125% of Span DEPT +/- 0.1291% Span PSEPT +/-0.0004% Span REPT +/-0.1% Span RApc +/- 0.0354% Span RESpC +/-_0.0031% Span 2 2 0 5 2 2 TLUPT = +/-(RAPT + STPT + MTEPT + DEPT +

2 2 PSEPT 2 + REPT2 + RApc + RESpc )

TLUPT = +/- 0.5560% of Span 3.4. Control Rod Drive Flow Uncertainty 3.4.1. Control Rod Flow Element CRD-FE-203 Manuf.: Badger Meter Co. Style: PVF-B Serial No.: G38823-1 3.4.1.1. Reference Accuracy:

Per Reference 5.1.32 the accuracy of the venturi is + 1% and the manufacturer calibration data sheets (Reference 5.5.10) state a resolution of 1.00% of maximum. The reference accuracy is therefore given in percent actual flow.

RACRDFE = +1.0% Actual Flow 3.4.1.2. Installation Effect:

The venturi is installed in 2-inch diameter pipe and has a beta ratio of 0.51 (Reference 5.5.10). Per Figure I1-1-1 of Reference 5.4.1 the venture requires 32 inches of upstream straight pipe. By inspection of Reference 5.1.54 the flow

Page: 27 of 63 NEDC:06-035 Rev. Number:O element does not meet the installation requirement, so an additional +0.5%

installation error will be added to the +0.5% standard installation error as stated in paragraph 11-11-3 of Reference 5.4.1.

IECRDFE = +/-1.0% Actual Flow 3.4.1.3. Temperature Effect on Nozzle Expansion:

Per Reference 5.5.10 the flow element calibration differential pressure is based on demineralized water at 150 'F and a flow rate equivalent to 100% power. The CRD pumps take suction on the hotwell level makeup line. The line is from Condensate Storage Tank A, suction of the Condensate Booster Pumps, and Condenser Hotwell (

References:

5.1.2, 5.1.5, and 5.1.9). The water is normally 103.1 'F per Reference 5.1.60 and the water in Condensate Storage Tank A is maintained above 40 *F per Reference 5.1.15. Per Reference 5.4.1, Figure 11-1-3, the Thermal Expansion Factor (Fa) is approximately 0.9995 and 1.001 for 40 'F and 150 'F, respectively. Using the equation 1-5-32 of Reference 5.4.1 for volumetric flow and for given differential pressure (calibration pressure value for fluid at 150 *F) the error in the flow measurement is determined as temperature deviates from the calibration temperature to 40 'F.

05 Q = a Fa K (2gh)

• Since, the calibration differential pressures are for calibrating at 68 °F for 150 'F fluid.

Q68 = (a(2gh)° 5 )/ Fa,, 0 Q40 = Fa40(O 68)

Q40 = (Fa 4o/Fa] 5o) (a(2gh)° 5 )

Q40 = (0.9985/1.001) (a(2gh)° 5 )

Q40 = 0.9975 (a(2gh)0° 5)

So actual volumetric flow at 40 ° is 0.9975 of the indicated flow. Since CRD fluid temperature is always less than 150 OF the error due to the thermal expansion of nozzle (actually contraction of the nozzle) is small and always conservative because the calibration data has been biased high and therefore can be ignored.

Page: 28 of 63 NEDC:06-035 Rev. Number:O 3.4.1.4. Temperature Effect on Density:

The Process Computer does not correct for changes in density of the CRD fluid.

The calibration data used to scale the loop for 0 gpm to 160 gpm is based on a fluid temperature of 150 'F and 2000 psia whereas the fluid temperature may be as low as 40 'F (highly unlikely except during an outage), pressure may be as low as 1425 psig (1425 + 14.7 = 1439.7 psia) and cooling water is set 50 gpm (Reference 5.3.3). The error due to density is conservatively accounted for by deviating CRD temperature from the calibration data temperature to 40'F.

DP at 50 gpm and 160 gpm, per Reference 5.5.10, is 77.14 and 789.1 inches of water, respectively and as a percent span:

(77.14/789.1) X 100 = 9.7757% DP Span The base conditions are:

pl( 2 0 0 0 psia, 150 °F) = 61.576 lbmr/ft3 P2( 1 4 4 0 psia, 40 *F) = 62.735 lbm/ft3 DP 2 = (P1 / P2) DPI

= (61.576/62.735) X 9.7757%

= 9.5951%

9.5951% -9.7757 % = -0.1806%

Therefore, the maximum percent of span error due to density is:

TDEcRDFE = -0.1806% of Span (Temperature Bias) 3.4.2. Differential Flow Transmitter CRD-FT-204 Manufacturer: Rosemount Model: 1151DP 3.4.2.1. Reference Accuracy:

Per Reference 5.5.9 the accuracy of the 1151 DP transmitter, Range Code 6 is +

0.25% of the calibrated span.

RACRDFT = +/-0.25% of Span

Page: 29 of 63 NEDC:06-035 Rev. Number:0 3.4.2.2. Setting Tolerance:

The Setting Tolerance is bounded by the "As-Left" Tolerance of the transmitter:

Per References 5.2.8 and Instrumentation and Calibration Supervisor the Generic tolerance is +/-2%.

STCRDFr = +2.0% of Span 3.4.2.3. M&TE:

The test equipment calibration standards used to calibrate the test is traceable to NIST and the test equipment is as least as accurate if not better than the equipment being calibrated. Therefore, the M&TE uncertainty will be taken as the Reference Accuracy of the transmitters.

MTEcRDFr = +/-0.25% of Span 3.4.2.4. Drift Effect:

Per Reference 5.5.9 the stability of the 1151 Range 6 is +/-_0.25% of the Upper Range Limit (URL) for 6 months. The transmitter is a Range 6 transmitter and has a URL of 100 psi.

+/-(100 psi) X (0.0025) = +/-0.25 psi

+/-(0.25 psi)(27.7277 "H 20/psi) = +/-6.9319 "H20

+/-(6.9319/789.1) X 100 = +/-0.8785% of Span for 6 months The transmitters are calibrated every 18 months versus 6 months and using the relationship given in Reference 5.3. 1:

VDM = (MJVD 6) 1 2VD 6mo (18/6)/2(0.8785% Span) = +/-1.5216% Span DEcRDvr = +/--1.5216% Span

Page: 30 of 63 NEDC:06-035 Rev. Number:0 3.4.2.5. Static Pressure Effect:

The 115 1DP transmitters are subjected to a static pressure shift which is not calibrated out. The shift is constant over the range of the transmitter and can be in either direction. Per Reference 5.5.9 the zero error is +/- 0.25% URL for 2,000 psi and the span error is correctable to +/- 0.25% of input reading per 1000 psi. For conservatism the span error will be applied to the calibrated span of the transmitter. Per Reference 5.3.3 CRD pump discharge pressure is set between 1425 psig and 1475 psig.

Zero Error as a %Span is:

Zero Error = +/-[((0.0025)(100 psi ))(27.7277 "H 20/psi/789.1 "H 20))X 100] [1475 psi/2000psi]

Zero= +0.6479%

Span Error= +/-(0.0025%)(1475 psi/l000 psi)X 100 = +/-0.3688%

Since the errors are additive: SPECRDFT = +/-(0.64792 + 0.36882)0_5 %

SPECRDFT = +0.7455% Span 3.4.2.6. Power Supply Effect:

The transmitters have less than a +/- 0.005% of calibrated span per volt per Reference 5.5.9. The transmitters are powered from CRD-ES-309 (Reference 5.1.36) which is a GE Type 570 Power Supply. Per Reference 5.5.11 the line voltage of the power supply can fluctuate between 107 volts and 127 volts ac with output voltage holding to 52.5 Vdc +/- 8%. Using the maximum variation of the power supplies and stated power supply effect of the transmitters the following evaluation determines the power supply effect on the transmitters.

(52.5 VDC) X (0.08) X (0.005%/volt) = +/-0.021%

PSECRDFr +/-0.021% Span 3.4.2.7. Temperature Effect:

The transmitters are located on the south-east wall of the Reactor Building, Elevation 903' per Reference 5.1.54. Reference 5.6.6 gives the normal

Page: 31 of 63 NEDC:06-035 Rev. Number:0 temperature variation as 70'F to 104 'F. This is a delta T of 34 'F. Reference 5.5.9 gives a total temperature effect of +/-(0.5% URL + 0.5% of calibrated span) per 100*F.

+/-0.5% URL is:

+/-(0.005)(100 psi)(27.7277 "H 20/psi) = 13.8639 "H 20

+/-0.5% URL as %Span:

(13.8639 "H 2 0/ 789.1 "H 20) X 100 = 1.757% Span Adding 0.5% of Span:

+/-(1.757% + 0.5%) 34 -F /100 -F =+/-0.7674%

TECRDFT = +/-0.7674% Span 3.4.2.8. Resistor Effect:

The transmitter output provides a signal to the process computer by converting the current to a voltage by means of the voltage drop across a 6 Ohm + 0.1% resistor (Reference 5.1.36). Therefore, the effect of the resistor in the instrument loop is given as:

REPT = +0. 1% Span 3.4.2.9. Process Computer:

Per References 5.1.47 the CRD flow loop uses the same mux cards as the reactor feedwater differential pressure loops (Refer to Step 3.1.2.9).

RApc = +/-0.0354% Span RESpc = +/-0.0031% Span

Page: 32 of 63 NEDC:06-035 Rev. Number:0 3.4.3. Total Loop Uncertainty for CRD Flow Tabulated below are the uncertainties associated with the CRD flow loop.

RACRDFE +/-1.0% Actual Flow IECRDFE +/-1.0% Actual Flow TDECRDFE - 0.1806% Span RACRDFT +/-0.25% Span STCRDFT +/-2.0% Span MTECRDFr +/-0.25% Span DECRDFT +/-1.5216% Span SPECRDFT +/-0.7455% Span PSECRDFT +/-0.021% Span TEcRDFT +/-0.7674% Span RECRDFT +/-0.1% Span RApc +/-0.0354% Span RES pc +/-0.0031% Span TLUCRDFI = +/-( RACRDFE2 + IECRDFE2)0.5 TLUCRDFI = 1.4142% Flow TLUCRDF2 = - 0.1806% Span (Temperature Bias) 2 TLUcRDF3 = +/-( RACRDFT2 + STcRyFF2 + MTECRDFT2 + DEcRDFT2 + SPECRDFT + PSEcpDFT 2 0 5

+ TECRDFT2 + REcRDF2r + RApc2 + RESpc ) .

TLUcRDF3 = +/-2.7562% Span

Page: 33 of 63 NEDC:06-035 Rev. Number:0 3.5. CRD Temperature Uncertainty The process computer does not have a CRD temperature, the heat balance program HEABAL (Reference 5.5.1) assume CRD temperature is 100 *F. However, the condensate pumps are 33% capacity pumps and continuously recirculate a portion of the discharge to maintain proper system flow (Reference 5.3.6) and the recirculated flow is through the same line as the suction of the CRD pumps . It has therefore been assumed in this calculation that CRD temperature when at or near 100% power is 103.1 °F (Reference 5.1.60) with a +/-100 F band added for conservatism.

TLUCRDT +/- 10 °F 3.6. Reactor Recirculation Power Uncertainty 3.6.1. Reactor Recirculation Pump Power Watt Meter RR-XFMR-TRIA Manuf.: Scientific Columbus Model: XL3IK5A2-SC-ER RR-XFMR-TR IB Manuf.: Scientific Columbus Model: XL31 K5A2-SC-ER 3.6.1.1. Reference Accuracy:

Reference 5.5.12 states an accuracy of +/-(0.2% Reading + 0.0 1% RO), where RO is the rated output for the AC Watt Transducers. In accordance with Reference 5.5.12 the rated output of the transducer is +/-1 mAdc. The 0 to 160 mV signal to the Process Computer is taken off a 160 ohm + 0.1% resistor for 0 to 6.0 MW indication (References 5.1.43 and 5.1.44). Using the maximum span value for conservatism the reference accuracy becomes:

+/-(0.002(160) + 0.0001(160))/160 X 100 +/- 0.21% Span RARRwM = +/-0.21% Span 3.6.1.2. Setting Tolerance:

The Setting Tolerance is bounded by the "As-Left" Tolerance of the transmitter:

Per References 5.3.4 the "As-Left" is given as +/- 8 mV of the output, so the Setting Tolerance is:

+/-(8mV/1 60mV) X 100 = +/-5.0% Span STRRWM = +/-5.0% Span

Page: 34 of 63 NEDC:06-035 Rev. Number:0 3.6.1.3. M&TE:

The test equipment calibration standards used to calibrate the watt meter are traceable to NIST and the test equipment is as least as accurate if not better than the equipment being calibrated. Therefore, the M&TE uncertainty will be taken as the Reference Accuracy of the transducer.

MTERRWM = +/-0.21% Span 3.6.1.4. Drift Effect:

Per Reference 5.5.12 the stability per year of the transducer is + 0.1% of the RO, and since the RO is same as the span the drift effect becomes:

+( 18/12)0-(0.1% Span) = +/-0.1225% Span DERRWM = +/-0.1225% Span 3.6.1.5. Power Supply Effect:

The transducers have an external power requirement of 85 to 135 Vac (120vAC nominal) and a frequency of 50 to 500 Hz per volt per Reference 5.5.12. The accuracy quoted is maintained if the external power requirements are within specification. The transducers are powered from power panels 2-184-12A and 2-184-12B which in turn are powered from Critical Instrument and Control Power Panels EE-PNL-CCPIA and EE-PNL-CCPIB, respectively (Reference 5.6.8).

The power supplies are highly reliable and have a minimum and maximum voltage of 102.8 and 127.9 Vac per Reference 5.6.7. Therefore, the power supply affect can be neglected.

3.6.1.6. Temperature Effect:

The transducers are located in panels 2-184-12A and 2-184-12B (Reference 5.6.8) which are located in the Reactor Building, West, Elevation 976'. Per Reference 5.6.6 the normal temperature for the area is 70 'F to 104 °F and Reference 5.5.12 states a temperature effect of+/- 0.005%/°C.

+/-[(34 -F)(5/9 -C/°F)(+/- 0.005%/°C) = +/-0.0944%

TERRWM = +/-0.0944% Span

Page: 35 of 63 NEDC:06-035 Rev. Number:0 3.6.1.7. Resistor Effect:

The transmitter output provides a signal to the process computer by converting the current to a voltage by means of the voltage drop across a 160 Ohm +/- 0.1%

resistor (References 5.1.43 and 5.1.44). Therefore, the effect of the resistor in the instrument loop is given as:

RERRWM =0.1% Span 3.6.1.8. Process Computer Per References 5.1.46 and 5.1.47 the RR power loops uses the same mux cards as the reactor feedwater differential pressure loops (Refer to Step 3.2.1.9).

RApc= +/-0.0354% Span RESpc = +/-0.0031% Span 3.6.2. Reactor Recirculation Power Total Loop Uncertainty Tabulated below are the uncertainties associated with the RR Power loops.

RARRWM +/-0.21% Span STRRwM +/-5.0% Span MTERRWM +/-0.21% Span DERRwM +/-0.1225% Span TERRWM +/-0.0944% Span RERRWM +/-0.1% Span RApc +/-0.0354% Span RESPC +/-0.0031% Span TLURRWM = +/-( RARRWM 2 + STRRWM2 +MTERRWM 2 + DERRWM2+ TE RRWM2 + RAPC2 ++/-

RESpc)° TLURRWM = +/-5.0123% Span

Page: 36 of 63 NEDC:06-035 Rev. Number:0 3.7. Reactor Water Clean-up (RWCU) Flow Loop Uncertainty 3.7.1. Flow Elements RWCU-FE-74A Manuf.; Daniel Industries Inc. Model: 520 Paddle RWCU-FE-74B Manuf.; Daniel Industries Inc. Model: 520 Paddle 3.7.1.1. Reference Accuracy The Daniel Model 520 Paddle orifice is a standard concentric flat plate orifice and the orifice bore tolerance is in strict accordance with A.P.I., Chapter 14, Section 3 (Reference 5.5.13). The original manufacturer's calibration data sheets for the orifice plates are no longer retrievable. However, in Reference 5.4.1, paragraph 11-111-7 (also Chapter II-V), when it is not possible to calibrate an orifice in the meter tube assembly the discharge coefficient can be calculated. The discharge coefficient in the calculation is not expected exceed +/- 1.0%. Another +/- 1.0% will be added to the assumed accuracy to account for manufacturer's tolerances and to ensure conservatism. The bore of the orifice is 1.522 inches by visual inspection of the stamping and the piping is Y'CU-3S which is schedule 40 stainless steel (3.068" ID).

RWCU Flow= (101 gal/min)(min/60sec)(233 in3/gal)(ft3/1728 in 3)(1/(7u/4(d/2) 2 )

= 17.965 ft/sec Rd = pVd/li Rd = ((61.92 lbm/ft3 )(17.965ft/sec)(1.522 in/12 in/ft))/(3.8E-4 Ibm/sec-ft)

Rd = 371,285 13= d/D 1.522 inr3.068 in f3=0.4961 Per Reference 5.4.1, Tables 11-111-2(a) and (b) the discharge coefficient is approximately 0.6058 and meets the requirement of paragraph 11-111-7.

RACUFE = +2.0% Flow

Page: 37 of 63 NEDC:06-035 Rev. Number:0 3.7.1.2. Installation Effect:

The flow elements do not meet the installation requirements of Reference 5.4.1 and so 1/2% error must be added to the standard error of 1/2% for the installation effect.

IECUFE +1.0% Flow 3.7.1.3. Temperature Effect on Nozzle Expansion Per Reference 5.3.5the fluid temperature to the filter/deminerlizers is maintained

< 130 0 F and per Reference 5.1.33 the normal temperature is 120 *F. The flow elements are just upstream the filter/demineralizers and since the system temperature operating band is small there is little change in the nozzle expansion factor, Fa. The change in Fa from Figure 11-1-3 of Reference 5.4.1 is on the order of 0.0002 or less for temperature range of 110°F to 1300. The temperature affect on nozzle expansion can be neglected.

3.7.1.4. Temperature Effect on Density During normal operations the temperature band for the fluid entering the filter/demineralizers is approximately 120 'F to 130'F. Although the fluid temperature is normally maintained in a small band, the affect temperature has on density will conservatively be evaluate at +10 'F from the base condition of 120°F at 1143 psia at Flow Element (Reference 5.1.33).

p-1o (1143 psia, 110 'F) 62.073 lbm/ft3 p (1143 psia, 120 'F) 61.920 lbm/ft3 3

p+io (1143 psia, 130°F)= 61.767 Ibm/ft The flow through each filter/demineralizer during normal operations is approximately 101 gpm (Reference 5.1.33). The loop is spanned 0 to 120 gpm per References 5.2.9 and 5.2.10.

Per Reference 5.2.9 and 5.2.10:

103.9 gpm = 158.80 "H20 120gpm = 211.74 "1120 So the D/P at 101 gpm is:

2 D/Pi01 = 158.80 "H20 (101 gpm/103.9gpm)

= 150.06 "H20

Page: 38 of 63 NEDC:06-035 Rev. Number:0 As a percent of the total Span:

(150.06 "H 2 0/211.74 "H 20) X 100 = 70.87%

Therefore:

DP2 = (PI / P2)(DPI)

DP-io = (61.920 lbm/ft3/62.073 lbm/ft3)(70.87%)

= 70.695%

70.695% -70.87% = -0.1750%

DP+io = (61.920 lbm/ft3 /61.767 lbm/ft3 )(70.87%)

= 71.046%

71.046% - 70.87% = +0.1755%

TDEcUFE = -0.1750%/+0.1755%

TDECUFE = +/-0.1755% Span 3.7.2. Flow Transmitter RWCU-FT-75A Manufacturer: Barton Inst. Systems Model: 273A RWCU-FT-75B Manufacturer: Barton Inst. Systems Model: 273A 3.7.2.1. Reference Accuracy:

Per Reference 5.5.14 the Model 273A Pneumatic Transmitters have a linearity of

+ V % of full range output pressure for differential pressure span to 150 psi.

Converting the total span to pressure:

211.74 "H 2 0 X 0.036065 = 7.636 psi at 68 *F RACUFT = +/-0.5% Span

Page: 39 of 63 NEDC:06-035 Rev. Number:O 3.7.2.2. Setting Tolerance:

The Setting Tolerance is bounded by the "As-Left" Tolerance of the transmitter:

Per References 5.2.9 and 5.2.10 the "As-Left" is given as +/- 0.06 psi of the output and the output span of the instrument is 0 to 15 psi. However, the instrument is calibrated as a loop so the Setting Tolerance is applied to the output of the final instrument in the loop prior to the process computer which is the Pneumatic to Current Converter.

3.7.2.3. M&TE:

The test equipment calibration standards used to calibrate the test is traceable to NIST and the test equipment is as least as accurate if not better than the equipment being calibrated. Therefore, the M&TE uncertainty will be taken as the Reference Accuracy of the transducer.

MTEcUFT = +/-0.5% Span 3.7.2.4. Drift Effect:

Due to the mechanical nature of the instrument the drift effect is negligible.

3.7.2.5. Temperature Effect:

Due to the mechanical nature of the instrument the temperature effect is negligible.

3.7.2.6. Static Pressure Effect:

Reference 5.5.14 does not state any static pressure effect for the flow transmitter.

However, conversations with Prime Measurement Products (formerly Barton) indicated there is a slight static pressure shift. For a differential pressure of 60 psi and below the shift is +/- 0.1% per 1000 psi on the span and for above 60 psi the shift is +/- 0.25% per 1000 psi. Because the shift was listed on an internal document the Vendor was unwilling to provide it as a reference. The span is 15 psi and the operating pressure is 1143 psia (Reference 5.1.33).

+/-0.1% (1143 psi/1000 psi) = +/-0.1143%

SPEcuFT = +/-0.1143% Span

Page: 40 of 63 NEDC:06-035 Rev. Number:O 3.7.3. Pneumatic to Current Converter RWCU-PE-77A Manufacturer: Moore Model: PIX/33-15PSIG/10-50MA/12-42DC RWCU-PE-77B Manufacturer: Moore Model: PIX/33-15PSIG/10-50MA/12-42DC 3.7.3.1. Reference Accuracy:

Reference 5.5.15 the accuracy of pneumatic to current converter is +0.2% of span.

Since, the error should be in both directions the reference accuracy will be taken as +/-0.2% Span RAcup = +/-0.2% Span 3.7.3.2. Setting Tolerance:

The Setting Tolerance is bounded by the "As-Left" Tolerance of the transmitter:

Per References 5.2.9 and 5.2.10 the "As-Left" is given as +/- 0.1 mA of the output for a 10 to 50 mA loop, so the Setting Tolerance is:

+/-(O. 1 mA/40 mA) X 100 = +/-0.25% Span STCip = +/-0.25% Span 3.7.3.3. M&TE:

The test equipment calibration standards used to calibrate the converter are traceable to NIST and the test equipment is as least as accurate if not better than the equipment being calibrated. Therefore, the M&TE uncertainty will be taken as the Reference Accuracy of the transducer.

MTEcup = +/-0.2% Span 3.7.3.4. Temperature Effects:

The transducers are located in the Reactor Building, West, Elevation 958', RWCU Valve Room. Per Reference 5.6.6 the normal temperature for the area is 70°F to 104'F and Reference 5.5.15 states a temperature effect of less than +/-2.0% of full scale input over the specified ambient temperature operating range of 30°F to 130°F. The input full scale is the span, so:

+/-(2%)((104-F - 70°F )/(130TF- 30°F) +/- 0.68%

TEcup = +/-0.68% Span

Page: 41 of 63 NEDC:06-035 Rev. Number:0 3.7.3.5. Other Effects:

The Moore Products (Reference 5.5.15) does not state any effects for drift and states power supply effect of less than +/-0.01% of rated span be volt of change in line voltage. Power supply effects are very small and drift effects have been less than 0.2% so the other effects will be conservatively assumed as +/-0.25%.

OEcup = +/-0.25% Span.

3.7.3.6. Resistor Effect:

The transmitter output provides a signal to the process computer by converting the current to a voltage by means of the voltage drop across a 6 Ohm +/- 0.1% resistor (Reference 5.1.39). Therefore, the effect of the resistor in the instrument loop is given as:

REcup= +/-0.1% Span 3.7.3.7. Process Computer Per References 5.1.48 and 5.1.51 the RWCU Flow loops uses the same mux cards as the reactor feedwater differential pressure loops (Refer to Step 3.1.2.9).

RApc= _+/-0.0354% Span RESpc = +/-0.0031% Span 3.7.4. Reactor Water Cleanup Flow Total Loop Uncertainty Tabulated below are the uncertainties associated with the RWCU flow loops. Since the instruments are calibrated as a loop only the final Setting Tolerance (STcup) is considered in the total loop uncertainty.

RACUFE +/-2.0% Flow IECUFE +/-1.0% Flow TDEcUFE +/-0.1755% Span RACUFT +/-0.5% Span MTEcUFT +/-0.5% Span SPEcuFr +/-0.1143% Span

Page: 42 of 63 NEDC:06-035 Rev. Number:0 RAcup +/-0.2% Span STcup +/-0.25% Span MTEcup +/-0.2% Span TEcup +/-0.68% Span OEcup +/-0.25% Span REcup +/-0.1% Span RApc +/-0.0354% Span RESpc +/-0.0031% Span TLUCUFI = +/-( RACUFE + IlEcUFE 2+ TDEcUFE2)05 TLUCUFI = 2.2429% Flow 2 2 TLUcUF2 = +( DTEcUFE + RACUFT + MTEcUFT + SPEcuFT + RAcuP + STcup2 2 2 2 2 2 2 05 2

+MTEcup 2+ TEcup + OEcup + REcup + RApc +RESpc) "

TLUcUF2 = +/-1.0917% Span 3.8. Reactor Water Clean-up Temperature Loop Uncertainty RWCU-TE-92 GE Provided P/N: 117C3485P017 IST CONAX Nuclear Inc.

RWCU-TE- 109 GE Provided P/N: 117C3485P017 ARI Industries Inc.

3.8.1. Temperature Elements The temperature elements used to determine inlet and outlet RWCU temperature are Type T (Copper - Contantan) thermocouples (References 5.1.30 and 5.1.31). Per Reference 5.1.39 the temperature loop span is 0 'F to 600 *F and the Standard Limit Error (ANSI MC 96.1, Reference 5.4.4) for a type T thermocouple in the temperature range of> 32 'F to 662 *F is 1.8 'F or 0.75% which ever is greater. Reference 5.1.33 gives a normal operating temperature at the inlet thermocouple of 532 'F and at the outlet thermocouple of 435 *F:

+/-(532-F)(0.0075) = +/-3.9900-F RACUTI = +/-3.99000F

+/-(435-F)(0.0075) = +/-3.2625-F RACUT 2 = +/-3.2625°F There are no adjustments to be made on the thermocouples, no calibrations are performed

Page: 43 of 63 NEDC:06-035 Rev. Number:0 and no resistors in the temperature loops. The thermocouples are feed directly to the process computer mux cards.

3.8.2. Process Computer Per References 5.1.49 and 5.1.50 the temperature loops uses the same mux cards as the reactor feedwater differential pressure loops (Refer to Step 3.1.2.9).

RApc +/-0.035% Span = +/- (600 'F)(0.000354) = +/-0.2124oF RESpc = +0.00305% Span = +/- (600 'F)(0.000031) = +/-0.0186°F 3.8.3. Total RWCU Temperature Loop Uncertainty Tabulated below are the uncertainties associated with the Temperature loops.

RACUTI +/- 3.9900 'F RACUT2 +/- 3.2625 °F RApc +/- 0.2124°F RESpc +/- 0.0186 °F 2 205 TLUcuTI = +( RACUTI + RApc + RESpc )

TLUCUTI = +/-3.9957 'F 2 2 2*0.5 TLUcuT 2 = +/-( RACUT22 + RApc2 RESPC)

TLUcuT2 = +3.2695 -F

Page: 44 of 63 NEDC:06-035 Rev. Number:0 3.9. Sensitivity Analysis The individual loop uncertainties do not contribute equally to the uncertainty in the core thermal power calculation. To determine the contribution that the error in a single parameter makes to the uncertainty in the power calculation baseline conditions are established and the sensitivity of that measured parameter is determined. The sensitivities are determined from the baseline plant conditions at 100% thermal power The baseline conditions are those values given in the Thermal Kit (Reference 5.1.60) for CNS main turbine at 100% thermal power. The operating points established in the Kit represent the most accurate representation of the present performance of the station secondary components and systems. It will provide the baseline conditions for the most important of the parameters of interest (e.g., FW flow, temperature, pressure, and temperature). CRD parameters with exception of temperature will be taken from Procedure 2.2.8 (Reference 5.3.3) and RWCU parameters at 100% power will be taken from the GE process drawing for the system (Reference 5.1.33). Using the baseline parameters weighting factor are established for each of the instrument loops and then the loop uncertainties are multiplied by the weighing factor to determine the contribution to the power uncertainties. The values derived are then combined statistically to determine the uncertainty in the thermal power calculation. In general a 5% span on the parameter baseline value will be used to determine the parameter weighting factor.

Derived values of enthalpy and density are taken from the ASME Steam Tables - 1967 (Reference 5.4.3). These values were also used in the loop uncertainty calculations.

Page: 45 of 63 NEDC:06-035 Rev. Number:0 BASEL[NE VALUES Parameter Value Reference FW Total Flow 9.489 Mlbm/hr 5.1.60 FW A Flow 4.745 Mlbm/hr 5.1.60 FW B Flow 4.745 Mlbm/hr 5.1.60 FW Pressure 1165 psia 5.1.60 FW Temperature 364.68 'F 5.1.60 FW Enthalpy 338.73 Btu/lbm 5.1.60 Vessel Dome Pressure 1019.99 psia 5.1.60 Saturated Steam 1191.55 Btu/lbm 5.1.60 Enthalpy CRD Flow 50 gpm 5.3.3 CRD Pressure 1450 psig (1465 5.3.3 psia)

CRD Temperature 102.83 *F 5.1.60 CRD Enthalpy 75.105 Btu!lbm 5.4.3 RWCU Flow 202 gpm 5.1.33 RWCU A Flow 101 gpm 5.1.33 RWCU B Flow 101 gpm 5.1.33 RWCU Pressure (FE) 1143 psia 5.1.33 RWCU TempeatuInlet Temperature 532 'F 5.1.33 RWCU Outlet 435 'F 5.1.33 Temperature RWCU Inlet Enthalpy 527.606 Btu/lbm 5.4.3 RWCU Outlet 414.015 btu/lbm 5.4.3 Enthalpy RWCU Inlet Pressure 1193 psia 5.1.33 RWCU Outlet Pressure 1075 psia 5.1.33 RR A Pump Power 1.9 Mw 5.5.1 RR B Pump Power 1.9 Mw 5.5.1

Page: 46 of 63 NEDC:06-035 Rev. Number:0 3.9.1. FW Flow Sensitivity The uncertainties calculated for FW flow measurement was in percent actual flow and percent differential pressure.

For percent actual flow both feedwater flow element and Ultrasonic Flow Meter uncertainties are significantly less than 1%, however a 5% will be used to determine the weighing factor.

Error Flow (lbm/hr) = 0.05(9.489 Mlbm/hr) = 474,450 lbm/hr The difference from feedwater enthalpy to steam enthalpy:

Ah = 1191.55 Btu/Ibm - 338.73 Btu/lbm = 852.82 Btu/lbm The error in power due to a flow error:

Error (MW) = (474,450 lbm/hr)( 852.82 Btu/lbm)(l hr/60 min)

(17.5796 Watts/BTU/min)(1 MW/I E6 Watts)

=+/-118.5511 MW As percent Reactor Power:

+/-(118.5511 MW/2381 MW) X 100 = 4.9790%

-4.9790%Pwr Error/5% Flow Error = 0.9958 So error in Thermal Power per error in Flow:

WFFWF = 0.995 8 %Pwr Error/% Flow Error Using 22.6681% DP span from Section 3.1.1.4 the error for a 5% span becomes-

+5% = 27.6681% and -5% = 17.6681%

In terms of flow:

W+5%= 100(27.6681%/100)'-5 = 52.6005%

W-5% = 100(l7.6681 %/100)" = 42.0334%

Page: 47 of 63 NEDC:06-035 Rev. Number:0 The 100% flow value per loop as percent span is:

(4.745 Mlbm/ 10 Mlbm) X 100 = 47.45%

52.6005% - 47.45% = +5.1505%

42.0334% - 47.45% = -5.4166%

Using the higher value for conservatism:

Error Flow (lbm/hr) = 0.054166(10.0 Mlbm/hr) = 541.660 lbm/hr The individual loops are summed, so:

Total Flow Error = (541,6602 + 541,6602)05 = 766,022.92 lbm/hr Error (MW) = (766,022.92 Ibm/hr)( 852.82 Btu/Ibm)(1 hr/60 min)

(17.5796 Watts/BTU/min)(IMW/1E6 Watts)

Error(MW) 191.4066 In Percent:

(191.4066 MW/2381 MW) X 100 = 8.0389%

So the error in Thermal Power per error in DP:

8.0389%/5% = 1.6078 %Power/%DP Span WFFWDP = 1.6078 %Pwr Error/% Span 3.9.2. FW Temperature Sensitivity Per Section 3.2.2.1 the FW Temperature has a span of 150 *F so a +/- 5% error will result in +/- 7.5 ° and using 100% baseline temperature of 364.68 'F and baseline pressure of 1165 psia:

Hf-7.5 (357.18 'F, 1165 psia) = 330.877 Btu/lbm Hf (364.68 'F, 1165 psia) = 338.737 Btu/lbm Hf+7.5(372.18 °F, 1165 psia) = 346.621 Btu/lbm 330.877 Btu/lbm - 338.737 Btu/lbm = -7.860 Btu/lbm 346.621 Btu/lbm - 338.737 Btu/lbm = +7.884 Btu/lbm Pwr Error (MW) = (9.489E6 lbm/hr)( 7.884 Btu/lbm)(1 hr/60 min)

Page: 48 of 63 NEDC:06-035 Rev. Number:0 (17.5796 WattsIBTU/min)(1MW/i E6 Watts)

Pwr Error (MW) = 21.9192 MW

% Pwr Error = (21.9192 MW/2381 MW) X 100 = 0.9206%

%Power/Temp Error = 0.9206%/7.5 'F = 0.1229 %Power/°F WFFWT = 0.1227 %Pwr Error/0 F 3.9.3. Reactor Pressure Sensitivity Reactor pressure is used to determine steam enthalpy and is used to determine the energy added to the CRD flow and Feedwater flow. So CRD and Feedwater flows are added together to determine the error in Reactor Thermal Power per error in Steam Pressure.

The instrument spans is 0 to 1200 psig so +/-5% is 60 psi.

Vessel Dome Pressure = 1019.99 psia- 1020 psia Hgs5%(Saturation, 960 psia) = 1194.4 Btu/lbm Hg (Saturation, 1020 psia) = 1192.2 Btullbm Hg+5 %(Sturation, 1080 psia) = 1189.9 Btu/lbm 1194.4 Btu/lbm - 1192.2 Btu/lbm = +2.2 Btu/lbm 1189.9 Btu/lbm - 1192.2 Btu/Ibm = -2.3 Btu/lbm CRD Flow = (50 gal/m)(60ni/hr)(62.22 lbm/ft3)(233 in 3/gal)(ft3/1728 in 3)

= 25169 ibm/hr Pwr Error (MW) = (9.489E6 +25169 lbnrlhr)(2.3 Btu/lbm)(1 hr/60 min)

(17.5796 Watts/BTU/min)(1MW/1 E6 Watts)

= 6.4115 MW (6.4115 MW/2381 MW) X 100 = 0.2693 %Pwr Error 0.2693 %Pwr Error/5% Press. Span Error = 0.0539 WFp = 0.0539 %Pwr Error/% Span Error

Page: 49 of 63 NEDC:06-035 Rev. Number:0 3.9.4. CRD Flow Sensitivity CRD flow uncertainty is expressed in % Actual Flow and % DP span so two weighting factors are developed.

(50 gpm)(0.05) = 2.5 gpm CRD Flow = (2.5 gal/m)(60m/lhr)(62.22 lbm/ft3)(233 in 3/gal)(fi3/1728 in 3)

= 1258.443 Ibm/hr Ah =1191.55 -75.105 = 1116.445 Pwr Error (MW) = (1258.433 lbm/hr)(1 116.618 Btu/lbm)(1 hr/60 min)

(17.5796 Watts/BTU/min)(IMW/1 E6 Watts)

= 0.4117 MW (0.4117 MW/2381 MW) X 100 = 0.01729 %Pwr Error 0.01729 %Pwr Error/5% Flow Error = 0.0035 WFCRDF = 0.0035 %Pwr Error/% Flow Error Per Section 3.4.1.4, 50 gpm is at 9.7757% DP Span.

So +/-5% = 4.7757% and 14.7757%

Taking the square root(converting to %flow): 21.853% and 38.439%. The difference with nominal percent flow of 50 gpm/1 60 gpm X 100 = 31.25%.

21.853 - 31.25% = -9.397%

38.439% - 31.25% = +7.189%

(160 gpm)(0.09397) = 15.0352 gpm CRD Flow = (15.03 52 gal/m)(60m/hr)(62.22 lbm/ft3 )(233 in 3/gal)(ft3/1 728 in 3)

- 7568.3751 Ibm/hr Pwr Error (MW) = (7568.3751 lbm/hr)(1 116.445 Btu/lbm)(1 hr/60 min)

(17.5796 Watts/BTU/min)(IMW/1 E6 Watts)

= 2.4757 MW

Page: 50 of 63 NEDC:06-035 Rev. Number:0 (02.4757 MW/2381 MW) X 100 = 0.1040 %Pwr Error 0.1040 %Pwr Error/5% Press. Span Error = 0.0208 WFCRDDP = 0.0208 %Pwr Error/% Span Error 3.9.5. CRD Temperature Sensitivity It has therefore been assumed in Section 3.5 that CRD temperature when at or near 100%

power is 102.83 *F with a +/-10 °F band added for conservatism. Therefore, +/-10 'F band will be used in determining the CRD Temperature Weighting Factor.

Hf0o(92.83 *F, 1465 psia) = 64.743 Btu/lbm Hf (102.83 'F, 1465 psia) = 74.664 Btu/lbm Hf+io(1 12.83 *F, 1465 psia) = 84.589 Btu/lbm 64.743 Btu/lbm - 74.664 Btu/lbm = -9.921 Btu/lbm 84.589 Btu/lbm - 74.664 Btu/lbm = +9.925 Btu/Ibm CRD Flow = (50 gal/m)(60m/hr)(62.22 lbm/ft3)(233 in3/gal)(ft3 /1728 in3)

= 25,168.854 ibm/hr Pwr Error (MW) = (25,168.854 lbm/hr)( 9.925 Btu/lbm)(1 hr/60 min)

(17.5796 Watts/BTU/min)(1MW/1 E6 Watts)

Pwr Error (MW) = 0.0732 MW

% Pwr Error = (0.0732 MW/2381 MW) X 100 = 0.0031%

%Power/Temp Error = 0.0031 %/10 "F = 0.0003 %Power/0 F WVFCRDT = 0.0003 %Pwr Error/*F 3.9.6. RR Watt Meter Sensitivity The Watt Meter indication is 0 to 6 MW. Since this is one to one correspondence to megawatts, the weighting factor can conservative be taken as the fraction of 100%

Reactor Power the watt meter power can represent.

6 MW/2381MW =0.0025 WFwM = 0.0025 %Pwr Error/% Span Error

Page: 51 of 63 NEDC:06-035 Rev. Number:0 3.9.7. RWCU Flow Sensitivity RWCU flow uncertainty is expressed in % Actual Flow and % DP span so two weighting factors are developed. Per Reference 5.1.33 the temperature out of the non-regenerative Heat exchanger is 120 'F.

(202 gpm)(0.05) = 10.1 gpm RWCU Flow (10.1 gal/m)(60m/hr)(61.921bm/ft 3)(233 in3/gal)(ft 3 /1728 in3)

= 5,059.60 lbm/hr Hin (533 *F, 1193 psia) = 527.606 Btu/lbm Hour (435 °F, 1075 psia) = 414.015 Btu/lbm Ah = 527.606 Btu/lbm - 413.765 Btu/lbm = 113.591 Pwr Error (MW) = (5,5059.60 Ibm/hr)(1 13.591 Btu/lbm)(1 hr/60 min)

(17.5796 Watts/BTU/min)(1MW/I E6 Watts)

= 0.1684 MW (0.1684 MW/2381 MW) X 100 = 0.0071 %Pwr Error 0.0071 %Pwr Error/5% Flow Error= 0.00 14 WFcUF = 0.0014 %Pwr Error/% Flow Error Per Section 3.7.1.4 the normal flow of 101 gpm is 70.87% DP Span.

So +/-5 % = 65.87% and 75.87%

Taking the square root(converting to %flow): 81.160% and 87.103%. The loop has 120 gpm span. So the percent of span the nominal percent flow is:

101 gpm/120 gpm X 100 = 84.167%.

And the difference becomes:

81.160% - 84.167% = -3.007%

87.103% - 84.167% = +2.936%

RWCU Flow = (120 gal/m)(60m/hr)(61.921bm/fi3 )(233 in3/gal)(ft3/1728 in3)

= 60,114 Ibm/hr (60,114 lbmlhr)(0.03007) = 1807.628 Ibm/hr

Page: 52 of 63 NEDC:06-035 Rev. Number:O The individual loops are combined in the process computer:

((1807.628)2 + (1807.628)2)o-5 = 2556.372 Pwr Error (MW) = (2556.372 Ibm/hr)(1 13.841 Btu/lbm)(1 hr/60 min)

(17.5796 Watts/BTU/min)(1MW/1 E6 Watts)

= 0.0853 MW (0.0853 MW/2381 MW) X 100 = 0.0036 %Pwr Error 0.0036 %Pwr Error/5% Press. Span Error = 0.0007 WFCUDP = 0.0007 %Pwr Error/% Span Error 3.9.8. RWCU Temperature Sensitivity The inlet and outlet temperature (532 *F and 435 'F, respectively) are evaluated at the baseline conditions independent of each other. The temperature span of the instruments is 0 to 600 °F per Section 3.7.1. and 5% would be 30°F which is too large considering the total inlet and outlet loop uncertainties are +/- 4.0031 °F and +/- 3.2693°F, respectively, (Section 3.7.3), so a +/-5 'F will be used instead.

H-5% (527 'F, 1193 psia) = 520.183 Btu/lbm H (532 "F, 1193 psia) = 526.357 Btu/lbm H+st (537 -F, 1193 psia) = 532.603 Btu/lbm 520.183 Btu/lbm - 526.357 Btu/lbm =- 6.174 Btu/lbm 532.603 Btu/lbm- 526.357 Btu/lbm = +6.246 Btu/lbm RWCU Flow = (202 gal/m)(60m/hr)(61.92fi3)(233 in3/gal)(ft3 /1728 in 3)

- 101,191.9 Ibm/hr Pwr Error (MW) = (101,191.9 lbmlhr)(6.246 Btu/lbm)(1 hr/60 min)

(17.5796 Watts/BTU/min)(1MW/1 E6 Watts)

= 0.1852MW (0.1852 MW/2381 MW) X 100 = 0.0078%Pwr Error 0.0078 %Pwr Error/5SF =0.0016

Page: 53 of 63 NEDC:06-035 Rev. Number:0 WFcutr = 0.00 16 %Pwr Error!0 F H. 5% (430 TF, 1075 psia) = 408.520 Btu/lbm H (435 TF, 1075 psia) = 414.015 Btu/lbm H+5%t(440 TF, 1075 psia) = 419.510 Btu/Ibm 408.520 Btu/lbm - 414.015 Btu/lbm = -5.495 Btu/lbm 419.510 Btu/lbm-414.015 Btu/Ibm = +5.495 Btu/lbm Pwr Error (MW) = (101,191.9 lbm/hr)(5.495 Btu/lbm)(1 hr/60 min)

(17.5796 Watts/BTU/min)(1MW/i E6 Watts)

= 0.1629 MW (0.1629 MW/2381 MW) X 100 = 0.0068%Pwr Error 0.0001 %Pwr Error/5°F = 0.00 14 WFCUT2 = 0.0019 %Pwr Error/! F 3.9.9. Radiative Power Sensitivity The weighting factor for radiative power losses is the ratio of percent power to megawatts thermal power.

100%/2381 MW = 0.0420 WFRP = 0.0420%/MW

Page: 54 of 63 NEDC:06-035 Rev. Number:0 3.10. Total Reactor Thermal Power Calculation Uncertainty The reactor thermal power calculation uncertainty is determined for two cases. The first case is for feedwater flow measurements using the installed ASME flow nozzles and the second case is for feedwater flow measurements using the Caldon Ultrasonic Flow Meters. In both cases the loop uncertainties are multiplied by the respective weighting factor and then the individual contributions to reactor thermal power is combined using SRSS. Bias errors are added to the total SRSS.

Case 1 (ASME Flow Nozzle)

Parameter Uncertainty Sensitivity Contribution FW Flow +0.7071 0.9958 +/-0.7041 FW D/P +/-0.6756 1.6078 +/-1.0863 FW Dependent +/-0.0160 1.6078 +/-0.0257 FW Temperature +/-0.4741 0.1227 +/-0.0582 Reactor Pressure +/-0.5560 0.0539 +/-0.0300 CRD Flow +/-1.4142 0.0035 +/-0.0049 CRD D/P +/-2.7562 0.0208 +/-0.0573 CRD Temp. +/-10.000 0.0003 +/-0.0030 RR Pump Power +/-5.0123 0.0025 +/-0.0125 RWCU Flow +/-2.2429 0.0014 +/-0.0031 RWCU D/P +/-1.0917 0.0007 +/-0.0008 RWCU Inlet Temp. +/-3.9957 0.0016 +/-0.0064 RWCU Outlet Temp. +/-3.2695 0.0014 +/-0.0046 Radiative Losses +/-0.3000 0.0420 +/-0.0126 Total SRSS _+/-1.2979 FW Nozzle Bias +0.6000 0.9958 +0.5795 CRD Bias -0.1806 0.0035 -0.0006 Total Uncertainty I -1.2973%/+1.8954%

Page: 5.5_5 of 63 NEDC:06-035 Rev. Number:0 Case 2 (Ultrasonic Flow Meter)

Parameter Uncertainty Sensitivity Contribution FW Ultrasonic Flow +/-0.3000 0.9958 +/-0.2987 FW Temperature +/-0.4741 0.1227 +/-0.0582 Reactor Pressure +/-0.5560 0.0539 +/-0.0300 CRD Flow +/-1.4142 0.0035 +/-0.0049 CRD D/P +/-2.7562 0.0208 +/-0.0573 CRD Temp. +/-10.000 0.0003 +/-0.0030 RR Pump Power +/-5.0123 0.0025 +/-0.0125 RWCU Flow +/-2.2429 0.0014 +/-0.0031 RWCU D/P +/-1.0917 0.0007 +/-0.0008 RWCU Inlet Temp. +/-3.9957 0.0016 +/-0.0064 RWCU Outlet Temp. +/-3.2695 0.0014 +/-0.0046 Radiative Losses +/-0.3000 0.0420 +/-0.0126 Total SRSS +/-0.3118 CRD Bias -0.1806 0.0035 -0.0006 Total Uncertainty -0.3112%/+0.3118%

4. CONCLUSION:

The total uncertainty associated with the HEABAL (Reference 5.5.1) when feedwater flow is measured with the ASME Flow nozzles is -1.2973%/+1.8954%.

The total uncertainty with the HEABAL (Reference 5.5.1) when feedwater flow is measured with the Caldon UFM is -0.3112%/+0.3118%.

Page: 56 of 63 NEDC:06-035 Rev. Number:O

5.

REFERENCES:

5.1. Drawings

5.1.1. Retention Number 454003582, Drawing 2004 Sheet 1, Rev. N30.

5.1.2. Retention Number 454003583, Drawing 2004 Sheet 2, Rev. N46.

5.1.3. Retention Number 454003584, Drawing 2004 Sheet 3, Rev. N46.

5.1.4. Retention Number 454003616, Drawing 2026 Sheet 1, Rev. N57.

5.1.5. Retention Number 454003632, Drawing 2039, Rev. N53.

5.1.6. Retention Number 454003635, Drawing 2042, Sheet 1, Rev. N32.

5.1.7. Retention Number 454003683, Drawing 2042, Sheet 2, Rev. N13.

5.1.8. Retention Number 454003684, Drawing 2042, Sheet 3, Rev. N20.

5.1.9. Retention Number 454003678, Drawing 2049, Sheet 4, Rev. N13.

5.1.10. Retention Number 454012990, Drawing 2608-9, Rev. 9.

5.1.11. Retention Number 454012771, Drawing 2608-10, Rev. 7.

5.1.12. Retention Number 454012666, Drawing 2849-4, Rev. N10.

5.1.13. Retention Number 452005574, Drawing 556-26811, Rev. 4.

5.1.14. Retention Number 454003883, Drawing 3010, Sheet 1, Rev. N67.

5.1.15. Retention Number 454003926, Drawing 3043, Sheet 12, Rev. N15.

5.1.16. Retention Number 454004197, Drawing 3254, Sheet 11, Rev. N10.

5.1.17. Retention Number 454004198, Drawing 3254, Sheet 12, Rev. N18.

5.1.18. Retention Number 454004199, Drawing 3254, Sheet 13, Rev. N22.

5.1.19. Retention Number 454004201, Drawing 3254, Sheet 15, Rev. N05.

5.1.20. Retention Number 454004222, Drawing 3255, Sheet 8, Rev. N31.

Page: 57 of 63 NEDC:06-035 Rev. Number:O 5.1.21. Retention Number 45004248, Drawing 3255, Sheet 34, Rev. N23.

5.1.22. Retention Number 454004250, Drawing 3255, Sheet 36, Rev. NI 8.

5.1.23. Retention Number 454004333, Drawing 3257, Sheet 13, Rev. N07.

5.1.24. Retention Number 454004349, Drawing 3257, Sheet 29, Rev. N16.

5.1.25. Retention Number 454004351, Drawing 3257, Sheet 31, Rev. N17.

5.1.26. Retention Number 454240980, Drawing 3257, Sheet 89B, Rev. NOO.

5.1.27. Retention Number 454240981, Drawing 3257, Sheet 89C, Rev. NOO 5.1.28. Retention Number 454240990, Drawing 3257, Sheet 90D, Rev. NOO.

5.1.29. Retention Number 454241010, Drawing 3257, Sheet 92F, Rev. NOI.

5.1.30. Retention Number 452209416, Drawing 117C3485, Sheet 1, Rev. 19.

5.1.31. Retention Number 452209417, Drawing 11 7C3485, Sheet 2, Rev. 7.

5.1.32. Retention Number 4540006910, Drawing 158B7077, Rev. 2.

5.1.33. Retention Number 454005663, Drawing 730E148BB, Sheet 1, Rev.1 5.1.34. Retention Number 454005392, Drawing 730E197BB, Sheet 5, Rev. N06.

5.1.35. Retention Number 454006837, Drawing 791E252, Sheet 1, Rev. N10.

5.1.36. Retention Number 454006497, Drawing 791E254, Sheet 1, Rev. N08.

5.1.37. Retention Number 454006804, Drawing 791E257, Sheet 2, Rev. N12.

5.1.38. Retention Number 454006806, Drawing 791E257, Sheet 4, Rev. N26.

5.1.39. Retention Number 454006668, Drawing 791E263, Sheet 2, Rev. N17.

5.1.40. Retention Number 452006647, Drawing 791E446 Sheet 1, Rev. N22.

5.1.41. Retention Number 452006747, Drawing 791E540, Rev. N19 5.1.42. Retention Number 454006752, Drawing 791E523, Sheet 2, Rev. N18

Page: 58 of 63 NEDC:06-035 Rev. Number:O 5.1.43. Retention Number 454006290, Drawing 0199F0377, Rev. N12.

5.1.44. Retention Number 454006962, Drawing 0199F0380, Rev. N 12.

5.1.45. Retention Number 452001513, Drawing E507, Sheet 115, Rev. N07.

5.1.46. Retention Number 450213825, Drawing E515 Sheet 9, Rev. NO0.

5.1.47. Retention Number 450218224, Drawing E515 Sheet 55, Rev. N02.

5.1.48. Retention Number 450218225, Drawing E515 Sheet 60, Rev. NO 1.

5.1.49. Retention Number 450213874, Drawing E515, Sheet 82, Rev. NOL.

5.1.50. Retention Number 450213879, Drawing E515, Sheet 88, Rev. NOI.

5.1.51. Retention Number 450218236, Drawing E515 Sheet 121, Rev. N01.

5.1.52. Retention Number 450213972, Drawing E515, Sheet 144, Rev. NOI.

5.1.53. Retention Number 453225711, Drawing E507, Sheet 228, Rev.N07.

5.1.54. Retention Number 454015176, Drawing CPOO8, Sheet 1, Rev. N04.

5.1.55. Retention Number 450245488, Drawing 10741-980500, Sheet 1.

5.1.56. Retention Number 450245489, Drawing 10741-980500, Sheet 2.

5.1.57. Retention Number 451245490, Drawing 10741-980500, Sheet 3.

5.1.58. Retention Number 451245491, Drawing 10741-980500, Sheet 4.

5.1.59. Retention Number 451245492, Drawing 10741-980500, Sheet 5.

5.1.60. Retention Number 451245493, Drawing 10741-980500, Sheet 6.

5.1.61. Retention Number 451245494, Drawing 10741-980500, Sheet 7.

5.1.62. Retention Number 451245495, Drawing 10741-980500, Sheet 8.

5.1.63. Retention Number 451245496, Drawing 10741-980500, Sheet 9.

Page: 59 of 63 NEDC:06-035 Rev. Number:0 5.1.64. Retention Number 451245497, Drawing 10741-980500, Sheet 10.

5.2. Instrument Data Sheets:

5.2.1. 14.5.1 Instrument Calibration Data Sheet, RF-TT- 168A.

5.2.2. 14.5.1 Instrument Calibration Data Sheet, RF-TT-168B.

5.2.3. 14.5.1 Instrument Calibration Data Sheet, RF-TT-168C.

5.2.4. 14.5.1 Instrument Calibration Data Sheet, RF-TT-168D.

5.2.5. 14.15.2 Instrument Calibration Data Sheet, RFC-LOOP-8.

5.2.6. 14.15.2 Instrument Calibration Data Sheet, RFC-LOOP-9 5.2.7. RWCU Generic Calibration Data, RWCU-LOOP-6 5.2.8. CRD Generic Calibration Data Sheet, CRD-LOOP-6.

5.2.9. 14.5.1 Instrument Calibration Data Sheet, RWCU-LOOP-3 5.2.10. 14.5.1 Instrument Calibration Data Sheet, RWCU-LOOP-4

5.3. Procedures

5.3.1. Procedure 3.26.3, "Instrument Setpoint and Channel Error Calculation Methodology",

Revision 6.

5.3.2. Procedure l4.NBI.301, "Reactor Pressure Channel Calibration", Revision 4, 5.3.3. Procedure 2.2.8, "Control Rod Hydraulic System", Revision 66.

5.3.4. Procedure 15.RR.301, "RRMG Calibration of MG Output Power Transducer and Wattmeter", Revision 3.

5.3.5. Procedure 2.2.66, "Reactor Water Cleanup", Revision 87.

5.3.6. Procedure 2.2.6, "Condensate System", Revision 63.

Page: 60 of 63 NEDC:06-035 Rev. Number:0 5.3.7. Procedure 2.2.68, "Reactor Recirculation System", Revision 64.

5.3.8. Procedure 4.6.1, "Reactor Vessel Water Level Indication", Revision 28.

5.4. Codes and Standards:

5.4.1. ASME, "Fluid Meters Their Theory and Application" Sixth Edition, 1971.

5.4.2. ISA-RP67.04 - Part II - 1994, "Methodologies for the Determination of Setpoints For Nuclear Safety-Related Instrumentation", September 30,1994.

5.4.3. ASME Steam Tables, 1967.

5.4.4. ANSI MC96.1-1975, "Temperature Measurement Thermocouples."

5.5. Vendor Documentation:

5.5.1. Studsvik Scandpower Report: SSP-04/414-C, "GARDEL-BWR for Cooper Nuclear Station Heat Balance Method Description", Revision 0.

5.5.2. Rosemount Reference Manual 00809-0100-4801, "Model 3051 S Series Pressure Transmitter Family", Revision AA.

5.5.3. RTP Technical Bulletin, RTP7436 Series.

5.5.4. RTP Technical Manual 981-0021-211 A, "RTP8436 Series Universal Analog Input Card Set", Revision A.

5.5.5. KEPCO Technical Bulletin 146-1869.

5.5.6. Rosemount Temperature Sensor Product Data Sheet, 00813-0100-2654, Revision FA.

5.5.7. Rosemount 3144P Temperature Transmitter Product Data Sheet, 00813-0100-4021, Revision FA.

5.5.8. Rosemount, Report of Calibration, Model Option Code X9Q4, 1/5/2006.

5.5.9. Rosemount Technical Manual 00809-0100-4360, "Model 1151 Alphaline Pressure Transmitters" Rev. AA.

Page: 61 of 63 NEDC:06-035 Rev. Number:0 5.5.10. Badger Meter Inc., "Differential Meter Flow vs Differential Calculations".

5.5.11. GE Instructions, 198 4532K30-010, "Type 570-06, 07 Isolated Power Supply.

5.5.12. Scientific Columbus Technical Bulletin, "Exceltronic AC Watt or Var Transducers".

5.5.13. Daniel Technical Bulletin, "Orifice Plates and Plate Sealing Units".

5.5.14. Barton Product Bulletin G1-25, "Models 273A and 274A Pneumatic Transmitters."

5.5.15. Part Evaluation Technical Evaluation Number 10511159, Revision 0, 5.5.16. Caldon Report ML162, "Caldon Experience in Nuclear Feedwater Flow Measurement,"

Revision 2.

5.5.17. Caldon Report FR04.PM5. "Feedwater Assessment Program Report for Nebraska Public Power District Cooper Nuclear Station", Revision 0.

5.6. Miscellaneous 5.6.1. Calculation NEVC 70-263, Rev. 0 (Roll 00111, Frame 0033).

5.6.2. GE Purchase Specification 21A1379AR, "Cooper Flow Element Data Sheets", Revision 4 (Roll 09021, Frame 1898).

5.6.3. Alden Research Laboratories, "Calibration Two Flow Nozzles Serial Numbers T-12125 and T- 12126", July 1970 (Roll 08118, Frame 1295).

5.6.4. GE FDI Number 71/10100, " Feedwater Flow Element", Revision I (Roll 17524, Frame 0604).

5.6.5. CED6010820 5.6.6. Calculation NEDC 00-95A, Revision 4 5.6.7. Calculation NEDC 94-018, Revision 3, 5.6.8. CED 2000-0032

Page: 62 of 63 NEDC:06-035 Rev. Number:O 5.6.9. Contract E69-4, Piping Specifications.

5.6.10. GE DRF A13-00461-02, "Impact of Steam Table Basis on Process Computer Heat Balance Calculations," Revision 1.

5.6.11. Cameron Engineering Report ER-592, "Bounding Uncertainty Analysis For Thermal Power Determination At Cooper NPPD Using LEFM4 + System," Revision 1.

6. ATTACHMENTS:

6.1. Rosemount Reference Manual 00809-0100-4801, "Model 3051 S Series Pressure Transmitter Family", Revision AA (Excerpt).

6.2. RTP Technical Bulletin, RTP7436 Series.

6.3. RTP Technical Manual 981-0021-211 A, "RTP8436 Series Universal Analog Input Card Set",

Revision A (Sections I & 2).

6.4. KEPCO Technical Bulletin 146-1869.

6.5. Rosemount 3144P Temperature Transmitter Product Data Sheet, 00813-0100-4021, Revision FA.

6.6. Rosemount, Report of Calibration, Model Option Code X9Q4, 1/5/2006.

6.7. Rosemount Technical Manual 00809-0100-4360, "Model 1151 Alphaline Pressure Transmitters" Rev. AA (Excerpt).

6.8. Badger Meter Inc., "Differential Meter Flow vs Differential Calculations".

6.9. GE Instructions, 198 4532K30-010, "Type 570-06, 07 Isolated Power Supply.

6.10. Scientific Columbus Technical Bulletin, "Exceltronic AC Watt or Var Transducers".

6.11. Daniel Technical Bulletin, "Orifice Plates and Plate Sealing Units".

6.12. Barton Product Bulletin GI-25, "Models 273A and 274A Pneumatic Transmitters."

6.13. Fisher & Porter Instruction Bulletin 50EW1020, "Series 50EW1020 & 50EW1030 Pneumatic-To-Current Converters," Revision 3.

Page: 63 of 63 NEDC:06-035 Rev. Number:0 6.14. Caldon Report ML162, "Caldon Experience in Nuclear Feedwater Flow Measurement,"

Revision 2.

6.15. Cameron Engineering Report ER-592, "Bounding Uncertainty Analysis For Thermal Power Determination At Cooper NPPD Using LEFM4 + System," Revision 1.