ML072700849

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Caldon Experience in Nuclear Feedwater Flow Measurement
ML072700849
Person / Time
Site: Beaver Valley, Millstone, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Salem, Nine Mile Point, Palo Verde, Perry, Indian Point, Harris, Saint Lucie, Point Beach, Watts Bar, Grand Gulf, Cooper, Sequoyah, Susquehanna, Summer, Prairie Island, Seabrook, North Anna, Turkey Point, River Bend, Ginna, Waterford, Clinton, Cook, Comanche Peak, Quad Cities, Fort Calhoun, FitzPatrick  Constellation icon.png
Issue date: 01/31/2005
From:
Caldon
To:
NRC/FSME
References
FOIA/PA-2007-0255
Download: ML072700849 (23)


Text

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Caldon Experience in Nuclear Feedwater Flow Measurement MLI62Rev.2 1/05 Couni on Caldon ML 162 Rov. 2 1/05 Count on Caldon

LEEM STORY The LEFM Story is an advanced technology story. Originally developed to measure water velocities over missile hatches on the George Washington Class Nuclear Submarine, the LEFM was later applied to accurate flow measurement challenges in rivers, open channels, large pipes in hydroelectric generating facilities, high temperature reactor coolant systems, and feedwater systems in nuclear power plants.

The LEFM was first applied in a commercial power plant in 1974 wvhere it was used to measure Reactor Coolant Flow in the Prairie Island Unit 2 Nuclear Plant. This version of the LEFM was called a Chordal System because it made velocity measurements at four "chords" of the circular cross section of the pipe. The results were used to determine Reactor Coolant Pump curves that are still used today.

The LEFM Chordal Technology was applied to measure feedwater flow in 1977. Venturi fouling had been identified as a significant bias source resulting in decreased power output in nuclear plants. LEFM technology was used to correct biases caused by venturi fouling and recover lost MW. Ultrasonic feedwater temperature measurement capability to within:F* 10F was soon added to the LEFM.

Caldon purchased the LEFM technology from Westinghouse in 1989 in an asset transfer transaction. A completely new electronic platform, taking advantage of the latest microprocessor technology was introduced by Caldon in 1990. This electronic unit was called the LEFM 8300 and its increased flexibility allowed Caldon engineers to use LEFM technology in new ways and in new applications.

The first radical new application was the LEFM External Feedwater Flow and Temperature System. The External LEFM has the advantage of being installed on existing pipes without shutting down the plant. The LEFM External System was introduced in 1991 for MW recovery.

its feedwater mass flowrate accuracy is +/- 1% and measures temperature typically within 1.5'F.

The chief uncertainty for the LEFM External System is the knowledge of the hydraulic velocity profile. This uncertainty is bounded through extensive parametric site specific model testing.

Mil-Spec External Flowrneter Another variant of the LEFM External technology was ruggedized to become the world's only MIL-SPEC ultrasonic flowmeter. This product is used on the latest generation Seawoif and Virginia Class submarines for the U.S. Navy in the Trim and Drain System. This model, called the LEFM 8400M, meets stringent requirements for shock, vibration, EMI/RFI, salt spray, and temperature.

RCS Flow and Temperature A version of the LEFM External technology was applied to RCS temperature and flow measurement in 1995. Pilot measurements were made at the R.E. Ginna Plant and Watts Bar Plant during hot functional testing.

ML 162 Rev. 2 1/05 Count on Caldon I

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Appendix K Uprates Caldon introduced the concept of Appendix K uprates to the NRC and utility customers in 1994. Appendix K uprates take advantage of the increased accuracy of the LEFM Chordal technology to increase licensed power and improve safety at the same time. The LEFM,/'

Topical Report ER-80P was submitted to the NRC for review in 1997 and approved for 1%

Uprates in 1999. Comanche Peak Unit 2, the lead plant for Appendix K Uprates increased power in October 1999. In January of 2001, based on the new Appendix K Ruling of June of 2000, Watts Bar was approved for a 1.4% Appendix K Uprate using the LEFM,/.

Caldon introduced the even more accurate LEFM CheckPlus System in 2001. The major improvements in the LEFM CheckPlus are more accurate measurement of velocity profiles and reduced sensitivity to changes in velocity profiles. Redundancy is another important feature of the LEFM CheckPlus System. The LEFM CheckPlus System was approved by the NRC for uprates up to 1.7% in December 2001.

New Developmnents New applications for the LEFM technology include high temperature gas and steam flow.

Development work is proceeding at Cal don to achieve the same high accuracies in tough applications that Caldon is known for.

MLI62Rev.2

~1/O5 Cow,! on Ca/don 2

ML 162 Rev. 2 1/05 Count on Caldon 2

Caldon Experience TimeLine 1962: LEFM developed for George Washington Class Submarine 1974: LEFM chordal technology applied to RCS flow measurement Prairie Island 2 1977: LEFM chordal technology applied to feedwater flow measurement +/- 0.5%

19 78: LEFM chordal technology used for feedwater temperature measurement 1989: Caldon, Inc. purchases LEFM technology from Westinghouse Electric 1990: Caldon introduces LEFM Model 8300 Electronic Unit 1991: Caldon introduces LEFM External feedwvater flow and temperature measurement system for megawatt recovery 1992: Caldon retrofits first LEFM system at Coffnanche Peak for megawatt recovery 1994: Mul-Spec LEEM 8400 developed for Seawoif and Virginia Class submarines Caldon introduces Appendix K uprate concept to NRC and utility customers 1995: LEFM external technology applied to RCS temperature and flow measurement at Ginna and Watts Bar 1999. NRC approves LEFM Check for Appendix K Power Uprates to 1 %, first uprate granted at Comanche Peak 2000: Caldon introduces LEFM CheckPlus technology for accuracy to +/- 0.3%

2001: NRC approved LEFM Check for 1.4% Appendix K Uprates NRC approved LEFM CheckPlus for 1.7% Appendix K Uprates MLI62Rev.2 1/05 Count on Caldon 3

ML162 Rev. 2 1105 Count on Caldon 3

r ES 0 LEFM FACTS AND DATA LEFM Syst emtsfor MWVReco very LEFM Systems are used for on-line calibration of installed differential pressure instrumentation.

Differential Pressure type instruments are subject to drift, bypass, and fouling which often changes over time. This creates the need to calibrate differential pressure type measurements on-line to maximize MW production. A few cases of biases caused by different effects are provided for reference in the section called "Changes in nozzle bias".

Caldon is the world leader in MW Recovery Systems.

External LEFM Systems have:

  • Been used to quantifly biases in differential pressure type devices in 53 nuclear plants

" Been permanently installed in 33 nuclear plants for on-line calibration of pl ant venturis

" Identified 435 MW for recovery Figure 1 lists the Peak NMW recovered in permanent installations and Figure 2 lists the MW for recovery that have been identified in test installations of External Systems.

MLI62Rev.2 1/05 Cowit on Caldon 4

ML162Rev.2 1/05 Count on Caldon 4

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utility TVA Nuclear TVA Nuclear TVA Nuclear Dominion Energy Constellation Energy Group Constellation Energy Group Florida Power & Light Co.

Entergy Nuclear Entergy Nuclear Entergy Nuclear Exelon Exelon Electrabel Electrabel Electrabel Electrabel South Carolina Electric & Gas Co.

Almnaraz-Tiillo NPP AIE Arizona Public Service Co.

Arizona Public Service Co.

Arizona Public Service Co.

Asociacion Nuclear Asco - Vandellos Hl Iberdrola, S.A.

FirstEnergy Chubu Electric Tokyo Electric Power Co.

Tokyo Electric Power Co.

Tokyo Electric Power Co.

Tokyo Electric Power Co.

Tokyo Electric Power Co.

Tokyo Electric Power Co.

Tokyo Electric Power Co.

Tokyo Electric Power Co.

Plant Sequoyah 1 Sequoyah 2 Watts Barr Mfillstone 3 Nine Mfile Point I Nine Mfile Point 2 St. Lucie 2 FitzPatrick River Bend Grand Gulf Quad Cities I Quad Cities 2 Doel I Doel 2 Doel 3 Doel 4 V.C. Summer Trillo I Palo Verde I Palo Verde 2 Palo Verde 3 Vandellos Unit 2 Cofrentes Perry I Hamaoka 3 Kashiwazaki Kariwa I Kashiwazaki Kariwa 2 Kashiwazaki Kariwa 4 Kashiwazaki Kariwa 5 1 Fukushinia Daichi 5 2 Fukushinia Daichi I Kashiwazaki Kariwa 7 1 Fukushima Daichi 4 MW Recovered 7

18 18 16 7

11 18 16 14 10 8

11 7

0 5

7 10 14 19 30 20 9

0 8

4 10 2

Os 8

00 01 Venturi biased low Total MW Recovered 307 Figure 1: LEFM External System Installations and Megawatts Recovered ML162 Rev. 2 1/05 Count onCaldon 5

ML162 Rev. 2 1105 Count on Caldon 5

'M 0 LU:: 0 utility Progress Energy Entergy Nuclear Entergy Nuclear Omaha Public Power District Florida Power & Light Co.

Exelon Exelon Constellation Energy Group Electrabel Electrabel Electrabel FirstEnergy Dominion Energy Dominion Energy Nebraska Public Power District Almaraz-Trillo NPP AIE Florida Power & Light Co.

Asociacion Nuclear Asco - Vandellos II, A.I.E.

Asociacion Nuclear Asco - Vandellos II, A.1.E.

Progress Energy Plant Shearon Harris Waterford ANO I Fort Calhoun Turkey Point 4 Dresden 3 Clinton Calvert Cliffs 2 Tihange I Tihange 2 Tihange 3 Davis Besse North Anna 2 North Anna]I Cooper Almaraz Unit I St. Lucie Unit I ASCO I ASCO 2 Brunswick MW Identified 2.7 7

14 3

7 15 0

14 7

4 4

3 19 4

0 0

0*

0*

0*

0*

0* Venturi biased low Total NM Identiried 128 Figure 2: LEFM External System Flow Test and Lost Megawatts Identified LEFM Chordal Systems have also been used for MW Recovery LEFM Chordal Systems have:

" Been installed in 32 nuclear power plants Been used to recover 61 MW through on-line calibration of plant differential pressure instruments.

Figure 3 lists the MW recovered by site through calibration of the differential pressure instruments.

ML162Rev.2 1/05 Cowil on Cakkn 6

ML162 Rcv. 2 1105 Couni on Caldon 6

i=7Q0 EZ1ZZilZ1 0 utility Entergy Nuclear Entergy Nuclear FPL Energy Nuclear Management Company, LLC Nuclear Management Company, LLC Rochester Gas and Electric Corp.

TXU Energy TXU Energy Public Service Enterprise Group, Inc.

Public Service Enterprise Group, Inc.

Nuclear Management Company, LLC TVA Nuclear FirstEnergy FirstEnergy PPL PPL Tberdrola, S.A.

Asociacion Nuclear Asco - Vandelios II, A.I.E.

TVA Nuclear TVA Nuclear Entergy Nuclear Entergy Nuclear Indiana Michigan Power Co.

Indiana Michigan Power Co.

Asociacion Nuclear Asco - Vandel~os 11, A.I.E:

Entergy Nuclear Exelon Exelon Progress Energy FirstEnergy Shikoku Electric Power Co., Inc.

Asociacion Nuclear Asco - Vandellos HI, A.I.E.

Dominion Energy 0* Venturi biased low N/IA - M W aiready recovered by Exderna1 LEFM System Plant Indian Point 2 Indian Point. 3 Seabrook Point Beach I Point Beach 2 Ginna Comanche Peak I Comanche Peak 2 Salem 1 Salem 2 Prairie Island 2 Watts Bar Beaver Valley I Beaver Valley 2 Susquehana I Susquehana 2 Cofrentes Vandellos 2 Sequoyahl Sequoyah 2 Grand Gulf Waterford DC Cook 1 DC Cook 2 Asco I River Bend Peach Bottom 2 Peach Bottom 3 Robinson Davis Besse Ikata 2 Asco 2 Millstone 3 Total MW Identified MW Identified 5

10 5

0*

0*

0*

0*

0*

3 7

N/A 0*

N/A N/A N/A 4

7 0*

N/A 0*

0 01 0*

0*

N/A 61 Figure 3: LEFM Chordal System Installation and Megawatts Recovered MLI62Rev.2 1/05 Count on Caldon 7

MLIURev.2 1/05 Count on Caldon 7

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LEFM Systems for Appen dix K Uprates Caldon pioneered efforts to gain approval for the Appendix K Uprate'Concept, and today is the leading supplier of Appendix K Uprate Systems. The LEFMI/ System is a chordal type design and has been approved for uprates up to 1.4% based on accuracies better than 0.5%. The LEFM CheckPlus System is accurate to better than 0.3% and has been approved for uprates up to 1.7%.

LEFM,/ and LEFM CheckPlus Systems have:

Been purchased for 34 plants

  • Uprated 25 plants by 368 MW Figure 4 shows the status as of January 1, 2005 for Appendix K power uprates.

ML162 Rev. 2 1105 Count on Caldon 8

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utility TXU Energy TXU Energy TVA Nuclear FirstEnergy FirstEnergy PPL PPL Entergy Nuclear FirstEnergy TVA Nuclear TVA Nuclear Entergy Nuclear Iberdrola, S.A, Asociacion Nuclear Asco - Vandellos II, A.IE.

Asociacion Nuclear Asco - Vandellos 11, ALIE.

Asociacion Nuclear Asco - Vandellos 11, A.LE.

Nuclear Management Company, LLC Nuclear Management Company, LLC Entergy Nuclear Entergy Nuclear Progress Energy Indiana Michigan Power Co.

Indiana Michigan Power Co.

Exelon Exelon Entergy Nuclear Dominion Energy Shikoku Electric Power Co., Inc.

Progress Energy Progress Energy Progress Energy Progress Energy Shikoku Electric Power Co., Inc.

Shikoku Electric Power Co., Inc.

Plant Comanche Peak I Comanche Peak 2 Watts Bar Beaver Valley 1 Beaver Valley 2 Susquehana I Susquehana 2 Grand Gulf Davis Besse Sequoyah I Sequoyah 2 Waterford Cofrentes Vandellos 2 Asco I Asco 2 Point Beach I Point Beach 2 Indian Point 3 River Bend Robinson DC Cook I DC Cook 2 Peach Bottom 2 Peach Bottom 3 Indian Point 2 Millstone 3 Ikata 2 Crystal River Shearon Harris Brunswick I Brunswick 2 Ikata 1 Ikata 3 System LEFM,/

LEFM,/

LEFMV' LEFM/(

LEFM./+

LEFM,(

LEFM%4/

LEFM./ +

LEFMV +

LEFM,(

LEFMI/

LEFM. +

LEFM/( +

LEFMV +

LEFM./ +

LEFMv/+

LEFM/(

LEFM.I LEFM\\4/

LEFM./+

LEFMv( +

LEFM/1+

LEFM./ +

LEFMV +

LEFMI/ +

LEFMV LEFM/ +

LEFM/( +

LEFM,/ +

LEFM./ +

LEFM,/ +

LEFM. +

LEFM..( +

LEFMV +

MIW Uprated 16 16 16 11 12 15 15 20 16 16 16 18 15 14 14 7

7 14 13 12 17 18 18 18 14 N/

N/A N/A

% Uprate 1.40%

1.40%

1.40%

1.40%

1.40%

1.40%

1.40%

1.65%

1.60%

1.30%

1.30%

1.50%

1.70%

1.40%

1.40%

1.40%

1.40%

1.40%

1.40%

1.60%

1.64%

1.66%

1.66%

1.70%

1.70%

1.40%

1.70%

N/A 1.64%

1.64%

1.64%

1.64%

N/A NIA Total MW Uprated 368

  • Instal~led but have not yet rece'ved SER (approval for uprate)
  • Received SER by have not yet inistaUed the system
  • Purchased the system but have not installed or received SER

-Orders e-pected N/A Not using for MUR Figure 4: LEFM/( and LEFM CheckPlus System Installations and Megawatts Uprated ML162 Rev. 2 1105 Count on Caldon 9

=--lo [==17-0 LEFM EXTERNAL VS. PLANT DIFFERENTIAL DEVICE DATA The LEFM External meter has been used in 53 nuclear plants worldwide. Figure 5 shows the results in the form of a histogram. These results are a snapshot. It is well known that venturi biases resulting from fouling and bypass flow are dynamic. Caldon has published reports (ER-262) and papers documenting that external systems are subject to dynamic biases owing to changes in velocity profiles. While these changes can be bounded within -+/- 1% through rigorous parametric hydraulic modeling, they can lead to additional dynamic differences.

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3.5 4

4.5 Nozzle mome than LEFM

.1

-0.5 0

0.5

(% FouUng)

Lctoswith header LEFM Systems assign equal difference values to all nozzles.

Figure 5: Comparison of Nozzle and LEFM External Flow Indications MLA62Rev.2 1/05 Count on Caldon I0 ML162 Rev. 2 1/05 Count on Caldon 10

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LEFM CHORDAL VS. PLANT DIFFERENTIAL DEVICE DATA The LEFM Chordal technology (8300, /, and CheckPius) has been used to recover power and uprate plants. Figure 6 is a histogram of the comparison data between the LEFM chordal technologies and plant differential pressure measurements.

Conclusions from the data are:

  • Biases owing to fouling have probably been reduced over the years owing to improved water chemistry.
  • The spread in actual nozzle uncertainty is +/- 1.4% and is approximated by a normal distribution.

24,

22 20 I Averapa Difference *0 16 S14

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-4

-3.5

-3

-2.5

-2

-1.5 Nozzle less than LEFM

-1

-0.5 0

0.5

(% Fouling) 1 1.5 2

2.5 3

3.5 4

Nozzle more than LEFM

  • Locations with header LEFM Systems assign equal difference values to all nozzles.

Figure 6: Comparison of Nozzle and LEFM Chordal Flow Indications ML162Rcv.2 1/05 on Caldon 11 ML162Rev.2 1105 Count on Caldon 11

CHANGES IN NOZZLE BIASES The most common cause of changes in nozzle bias is the phenomenon of fouling. Fouling induced biases have proven to be difficult to predict, both in magnitude and in variation over a fuel cycle.

Long term comparison of data from LEFM, nozzles, and other plant instruments have confirmed the presence of fouling in at least 21 plants (Figure 7). The average value is 1.0%. In addition, Duane Arnold, Susquehanna, and Diablo Canyon have also reported dynamic fouling on the order of 1-2%.

The average change in bias observed in 4 BW;R's with the LEFM is 0.6%. The average change in bias observed in 17 PWR's is 1.0%

Utility TVA Nuclear TVA Nuclear TVA Nuclear Northeast Utilities Niagara Mohawk Power Corp.

Niagara Mohawk Power Corp.

Florida Power & Light Entergy Operations, Inc.

Entergy Operations, Inc.

Entergy Operations, Inc.

Electrabel S.A.

Electrabel S. A.

South Carolina Electric & Gas Centrale de Trillo Entergy Operations. Inc.

North Atlantic Energy Service Corp.

TXU TXU Nuclear Management Company, LLC Arizona Public Service Co.

Arizona Public Service Co.

Plant Sequoyah I Sequoyah 2 Watts Bar Millstone 3 Nine Mile Point I Nine Mile Point 2 St. Lucie Unit 2 River Bend Grand Gulf ANO I Doe] I Doel 2 V.C. Summer Trillo I Indian Point 2 Seabrook Comanche Peak 1 Comanche Peak 2 Prairie I sl and 2 Palo Verde I Palo Verde 2 Bias Range 1.4%

1.4%

2.6%

1.4%

0.7%

1.0%

2.0%

0.2%

0.5%

0.5%

1.0%

1.0%

0.1%

0.25%

0.2%

0.2%

1.0%

1.0%

0.25%

2.0%

1.5%

Figure 7: Plants in Which Nozzle Bias Swrings During Fuel Cycle ML162Rev.2 1/05 Count on Ca/don 12 ML162Rev.2 1/05 Count on Caldon 12

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Changes in Nozzle Biases-Case Studies A growing number of cases where nozzle biases change over the course of a cycle have been documented both for BWVR's and PW~R's. Data from several cases are shown in Figures 8,9, 10.

Figure 8 shows changes in feedwater fouling at Watts Bar Nuclear Plant during the first cycle of operation. Sensitivity to plant trips and downpowers are of particular interest. T1hese reflect the dependence of fouling on water chemistry. Fouling up to 2.5% was verified and recovered during the cycle.

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1.50%

1 1.00%-____

n 5/15/96 7/10/96 9/4/96 10130/96 12/2519 2/1 9W9 4/16/97 6/11/97 8/

Notes:

1. Plant starts steady state operationt
2. Mid Cyle Outage on 10/1/96.
3. Downpower to 50% on 11/28/96.
4. Turbine inlet vele testing on 12/30/96.
5. Plant tripped on 1/22/97 and then tripped again on 1/27/97.
6. Plant tripped on 3/3/97 and in outage for se~eral weeks. D(hang this ouage the venturis were exposed to air.
7. Plant tripped on 4(20/97.
8. Phan runback to appromatmany 50% power on 6/17/97.

'6197 Figure 8: Feedwater Fouling at Watts Bar Nuclear Plant ML162Rev.2 1/05 Counf on Caldon 13 MLIURev.2 1/05 Cowit on Caldon 13

Q-0n 9

0M Figure 9 shows nozzle bias changes at Nine Mile Point 2 over an 8 month period. The effect represented as a flow correction factor, is shown for each of the two nozzles (Line A and Line B).

The nozzles in both lines show changes of 0.75% to 1.0% over the course of the cycle. Also of note is the 2% variation in Line A for a period of 2 months.

1.

1 0.............

CORRECTION FACTORS 1.0080

!\\LINE A 1.D000 -

0.9960 0.9900 0.980D 0.9780 0.9700 1 1..

i 1

1

1

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2 2

2 2

2 2

2 2

e Dato Figure 9. Feedwater Flow Correction Factor at Nine Mile Point 2 MLI62Rev.2 1/05 Cowul cm Caldon 14 ML162 Rev. 2 1/05 Couni on Culdon 14

In at least one case, at Millstone 3, the development of nozzle fouling was observed during power ascension (Figure 10).

A small zero offset bias in the DP transmitters is apparent at low flow conditions. A significant change in the nozzle bias occurs between 34Q0 and 400TF as Ph conditions for fouling become favorable. A rapid acceleration in fouling occurs between 400'F and the 437*F full power temperature.

Over 1.2% fouling occurred during this power ascension, before full power was reach ed. Fouling which occurs during power ascension is nearly impossible to detect by trending other plant indicators. Because of the absolute accuracy and repeatability of the LEFM however, it can be measured accurately as shown here.

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fentd We talaf~t lsre Yf Figure 10. Effect of Fouling and De-fouling of the Feed Flow-Measurement-Nozzles on Plant Output ML~162Rcv.2 1/05 Count on Caldon 15 MLIURev.2 1/05 Count on Caldon 15

The recalibration of plant instruments can also be a cause for a change in nozzle bias. One such case is shown for a BWR plant where the recalibration of a DP transmitter caused a conservative shift of 1.44% (Figure 11).

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Difference 1.44%Difrne 28'Y 4834 a 4800 4785 0 4756:..

.1 2 9 LEFM5117195 LoopA ~ifforerntial proustire transmitters Figure 11: LEFM vs. Plant Flows, Loop A MU 62 Rev. 2 1/05 Coin?! on Caldon 16 MLI 62 Rev. 2 1/05 Count on Caldon 16

G=L2 Q 9QL:Q12 Q CHANGES IN EXTERNAL SYSTEM BIASES Caldon has developed extensive and significant experience in understanding and bounding the sensitivities and uncertainties in External and Chordal ultrasonic technologies. An extensive study of these effects is documented and has been made available to the public in ER-262. Contact Caldon or visit our website for a copy of this report.

Figure 12 shows the effects of swirl on an external ultrasonic measurement system. In this case, a change in hydraulic profile increased the swirl present 45 diameters downstream from a bend. The net effects were:

" LEFMV meter factor change of 0.06%

" External meter factor change of 1.4%

WaftalBar I*External A Chordal SwirlI 10.00 W.00 1!500 15300 15100 LL14900 14700 25.00 20.00 15.00 10.00 5.00 14500 $--'

7/2B/01 0.00 11/5/01 11/28/01 12/15/01 1/4/02 8117/01 96101 9/2&/01 10/16/01 Timr Figure 12: Change in Velocity Profile at Watts Bar MLl62Rcv.2 1/05 Count on Ca/don 17 ML162 Rev. 2 U05 Count on Caldon 17

TEMPERATURE MEASURMENT BIASES ALL PLANTS LEFM Systems measure temperature by means of a correlation with the velocity of ultrasound. The uncertainty of LEFM temperature readings over the range of conditions found in feedwater lines is

+/-10F.

For the 46 plants from which final feedwater temperature LEFM and plant data are available, plant temperature indications (usually RTD's) ranged from 2.57F low to 2.51F high with on average, a 0.2'F high reading (Figure 13).

comparison of Plant RMD and LEFM Temperature Indications (Average Value per Plant) 7 6

3-2 IAweage Dillerenice

= 0.24og F

-4

-3.6

-3

-2.5

-2

.1.5

.1

-0.5 0

0.5 LEFM less than RiD Iap.,po.,elu Olfemrvr F 1.6 2

2.5 3

3.6 4

LEFM mar. than RTD Figure 13: Comparison of Plant RTD and LEFM Temperature Indications (Average Value per Plant)

ML162Rev.2 1/05 Count on Caldon ML162Rev.2 1105 Count on Caldon

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0 LABORATORY TESTING LEFM Flow Measurement Systems have been extensively tested at Alden Research Laboratories (ARL). The results are traceable to NIST Standards. Over 10,000 tests have been conducted with over 500 different piping configurations.

A typical result of this testing is shown below (Figurel4). The data are for three LEFM's removed from a nuclear power plant, tested at ARL, and reinstalled. The LEFM readings were within 0.06%

of the ARL weigh tank readings.

18000 16000 14000 12000 10000 ROOD 6000 4000 2000 4r-2000 4000 6000 8000 10000 12000 1400D 16000 ARL ]Row Figure 14: LEFM Performance vs. ARL Weigh Tank ML162Rcv.2 I/OS Count on Caldon 19 ML162Rcv.2 1/05 Cotmi on Caldm 19

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__W LER RISTORY WITH NOZZLES Inaccuracies in feedwater flow nozzles and temperature indications can lead to overpower events. A review of LEFM's for sustained overpower events from 1982 and 1999 (Figure 15) shows 38 events associated with inaccurate (non-conservative) feedwater and temperature measurements or calculations. All of these events could have been prevented if an LEFM had been continuously monitoring feedwater flow rates.

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ML162Rev.2 1/05 Count i~m Caldon 20 ML162 Rev. 2 1/05 Count on Caldon 20

~wu.===0 LEFM DESIGN STANDARDS Caldon uses the Codes and Standards shown in Figure 16 for the design and manufacture of LEFM Systems.

ANSI/JSO/ASQC Q9001 Quality Systems - Model for Quality Assurance in Design, Development, Production, Installation and Service 10CFR50 Appendix B Quality Assurance Criteria for Nuclear Power Plants 10CFR21 Reporting of Defects and Nonconformance ANSI N45.2 Quality Assurance program requirements for Nuclear Power Plants (V &

V software only)

ASME B3 1.1 - 2001 ASME Code for Pressure Piping ASME NQA-I -1999 Addenda Quality Assurance Requirement of Computer Software for Nuclear Subpart 2.7 Facility Applications ASME NQA-1-1997 Quality Assurance Requirements for Spool Piece Design, Material procurement and Product inspection and tests AINSIIIEEE-7-4.3.2 1993 Criteria for Programmable Digital Computer Systems in Safety Systems ASME PTC 19.1 ASME Performance Test Code for Measurement Uncertainty MIL-C17/176D 6/90 Cables, Radio Frequency, Flexible, Twin M17/176-00003 MIL-Cl7/186B 91 Cables, Radio Frequency, Flexible, Twin 78 Ohms, M 17/186-00001 EJA RS-232C-1969 Interface Between Data Terminal and Communication Equipment

______________________Employing Serial Binary Data Interchange EIA R.S-422-1975 Electrical Characteristics of Balanced Voltage Digital Interface Circuits ANSIIEIA-310-D-1992 Cabinets, Racks, Panels and Equipment Standards NEC 1993 Article 240 - Over Current Protection Article 250 - Grounding Article 300 - Wiring Methods EPRI TR-102323 Rev. 1 (1/97)

Guidelines for Electromagnetic Interference testing in power plants (Guideline states susceptibility required for safety related systems only)

- Special Configurations available which meet susceptibility requirements.

EPRI TR-1 03 29 1s-V 1-3 Handbook for Verification and Validation of Digital Systems IEEE Std. 1050-1989 Guide for instrumentation and control for equipment grounding in generation stations.

Figure 16: Caldon LEFM Design and Manufacture Standards ML162 Rev. 2 1/05 Count on Caldon 21

SERVICES Caldon's experience in Nuclear Power Plants has led to the development of a wide range of services and documentation.

Support Services Caldon provides a full range of services to support customers.

" A group of service engineer specialists to install, test, commission, and repair LEFM Systems

  • Classroom hands-on training of customer personnel

" Stock supply of emergency spare parts

  • A monitoring program permits each LEFM System to be regularly checked for accuracy of flow measurement and component degradation Design Basis Document
  • A comprehensive "Design Basis Document", including a bottom-up analysis of uncertainties, is provided for each system installed to recover megawatts
  • The profile factor used to calibrate LEFM Systems is determined from flow data taken at Alden Research Laboratories under conditions replicating plant piping.

ML162Rev.2 1/05 Count on Caldon 22 ML162 Rev. 2 1/05 Count on Caldon 22