ML022110343
| ML022110343 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 01/31/2002 |
| From: | Augenstein D, Madera E Caldon |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| ER-267N, Rev 0 | |
| Download: ML022110343 (28) | |
Text
ER-267N REVISION 0 JANUARY 2002 CAL DON, INC.
ENGINEERING REPORT: ER-267N BOUNDING UNCERTAINTY-ANALYSIS FOR THERMAL POWER DETERMINATION AT CP&L ROBINSON NUCLEAR POWER STATION USING THE LEFM/ + SYSTEM Prepared By: Ed Madera Reviewed By: Don Augenstein NON-PROPRTARY VERSION ER-267N Rev 0 ICaldon, Inc. Page - I
Ica 0 c t--' 0 Engineering Report: ER-267N Revision 0 BOUNDING UNCERTAINTY ANALYSIS FOR THERMAL POWER DETERMINATION AT CP&L ROBINSON NUCLEAR POWER STATION USING THE LEFMI + SYSTEM Table of Contents
1.0 INTRODUCTION
2.0
SUMMARY
3.0 APROACH 4.0 OVERVIEW
5.0 REFERENCES
APPENDICES A Information Supporting Uncertainty in LEFM/ + Flow and Temperature Measurements, Proprietary in its Entirety B Total Thermal Power Uncertainty due to the LEFM/ +, Proprietary in its Entirety C LEFM,/ + Interface and Reconciliation Documents, Calorimetric Uncertainties with the LEFMIf and LEFM ' +
ER-267N Rev 0 Caldon, Inc. Page - 2
cZL 0 IM0 Engineering Report: ER-267N BOUNDING UNCERTAINTY ANALYSIS FOR THERMAL POWER DETERMINATION AT CP&L ROBINSON NUCLEAR POWER STATION USING THE LEFMI+ SYSTEM
1.0 INTRODUCTION
The LEFM,/ and LEFM,/ + are advanced ultrasonic systems that accurately determine the mass flow and temperature of feedwater in nuclear power plants. Using feedwater pressure signal input to the LEFMI and LEFM/ +; its mass flow and temperature outputs are used along with other plant data to compute reactor core thermal power. The technology underlying the LEFMI ultrasonic instruments and the factors affecting their performance are described in a topical report, Reference 1, and a supplement to this topical report, Reference 2. The LEFM/ + is described in another supplement to the topical report, Reference 3. This supplement demonstrates that plants using the LEFM,/ + can increase their licensed thermal power rating by as much as 1.7%. The exact amount of the uprate allowable under a recent revision to 10CFR50 Appendix K depends not only on the accuracy of the LEFM, + outputs but also on the uncertainties in other inputs to the thermal power calculation.
It is the purpose of this document to provide an analysis of the uncertainty contribution of the LEFM, +
to the overall thermal power uncertainty of CP&L Robinson Nuclear Power Station. The total uncertainty contribution is documented in the Interface and Reconciliation document (included with this document as Appendix C) as the term AB. This uncertainty is the aggregate power uncertainty due to the feedwater flow, temperature and pressure measurements.
The uncertainties in mass flow and feedwater temperature are also provided. If desired, these data may also be used in the calculation of the overall thermal power uncertainty. If this method is used, a special procedure is required for combining the mass flow uncertainty and the uncertainty in feedwater enthalpy due to temperature. The procedure is necessary because some elements of the temperature uncertainty are systematically related to elements of the mass flow uncertainty and others are not. Instructions and constants necessary for the use of this procedure are provided.
Revision 0 of this analysis is a preliminary bounding analysis for the CP&L Robinson plant. This revision utilizes nominal dimensions for the spool piece(s) and current values for full power mass flow, final feed temperature and steam conditions. Bounding values for the uncertainties in length measurements, time measurements and calibration coefficient (profile factor) are employed.
Revision 1 of this uncertainty analysis will be published following the calibration of the spool piece(s),
when a precise estimate of the uncertainty in the profile factor(s) is available. In Revision 1, the as-built dimensions are input for all computations, and it is confirmed that the uncertainties in these dimensions lie within the bounding values used in the Revision 0 analysis. The analysis may use either the bounding dimensional uncertainties or the actual uncertainties, which ever is greater. In Revision 1, bounding values for the uncertainties in time measurements are again used. The commissioning tests for the LEFM,/ +, performed following its installation in the plant, confirm that in fact time measurement uncertainties are within the bounding values used in the Revision 1 analysis.
ER-267N Rev 0 Caldon, Inc. Page - 3
El- 0 EC= (- 0 2.0
SUMMARY
For the CP&L Robinson Nuclear Power Station, Revision 0 results are asfollows:
- 1. The uncertainty in the mass flow of feedwater is [ ].
- 2. The uncertainty in the final feedwater temperature is less than 0.6°F.
- 3. The total power uncertainty due to the LEFMI + is [
- 4. For an overall thermal power uncertainty analysis in which mass flow and temperature errors are treated separately, the bounding 0.6°F temperature error should be [
3.0 APPROACH
[I ER-267N Rev 0 Caldon, Inc. Page - 4
- =,7za 0 0 I
4.0 OVERVIEW
[
]
Appendix A.1, LEFMI + Inputs
- - - This Appendix is Proprietary in its Entirety - -
[
I ER-267N Rev 0 Caldon, Inc. Page - 5
LaL-0 =C= 0 Appendix A.2, LEFM,/ + Mass Flow and Temperature Uncertainties
- - - This Appendix is Proprietary in its Entirety - -
This appendix calculates the uncertainties in mass flow and temperature as computed by the LEFM,/ + using the methodology described in Appendix E of Reference 1 and Appendix A of Reference 31, with uncertainties in the elements of these measurements bounded as described in both references2 . [
Revision 0 of this appendix utilizes the bounding values of Reference 3 for all uncertainty elements3 in the computation of plant specific uncertainties. [
Appendix A.3, Profile Factor (Calibration) Uncertainties INCLUDED WITH REVISION 1 ONLY - N/A FOR REVISION 0 As noted above, the calibration test report for the spool piece(s) establishes the overall uncertainty in the profile factor of the LEFM/+. [
Reference 3 (ER 157P) develops the uncertainties for the LEFM ,/+ system. Because this system uses two measurement planes, the structure of its uncertainties differs somewhat that of an LEFM,/.
2[
3[
ER-267N Rev 0 Caldon, Inc. Page - 6
La 0 C===-- 0 Appendix A.4, Uncertainties in the Measurement of Time Differences (At's)
I I
Appendix A.5, Uncertainties in the Measurement of Transit Times (t's)
[
I Appendix B, Total Thermal Power Uncertainty due to the LEFM/ +
The total thermal power uncertainty due to the LEFMI/ + is calculated in this appendix, [
I Appendix C, Interface and Reconciliation Document For completeness, an Interface and Reconciliation Document for this project is included as Appendix C. An interface and reconciliation document is provided to each LEFM/ + customer in the initial phase of an upgrade project. This document breaks down the uncertainties that Caldon will calculate and justify for a specific uprate project, as well as those outside Caldon's scope. It provides a preliminary set of uncertainties, based on the results of Revision 0 of this document, for use by the customer or the customer's agent in establishing the amount of the power uprate.
Appendix C also reconciles the results of Revision 0 analysis with the uncertainties calculated in the Topical Report and its supplements (References 1, 2, and 3).
ER-267N Rev 0 Caldon, Inc. Page - 7
Ica-0 ==Z = 0
5.0 REFERENCES
- 1) Caldon Topical Report ER-80P, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM Check System", Rev. 0.
- 2) Caldon Engineering Report ER 160P Rev. 0, "Supplement to Topical Report ER 80P: Basis for a Power Uprate with the LEFM System", May 2000
- 3) Caldon Engineering-157P, "Supplement to Caldon Topical Report ER-80P: Basis for Power Uprates with an LEFM Check or an LEFM CheckPlus", dated October 2001, Revision 5
- 5) ISA-RP67.04.02-2000, Methodologies for the Determination of Set Points for Nuclear Safety Related Instrumentation ER-267N Rev 0 Caldon, Inc. Page - 8
Appendix A.1 is Proprietary to Caldon in its Entirety ER-267N Rev 0 Caldon, Inc. Appendix A
Lao----
- - ' o Appendix A.2 is proprietary to Caldon in its Entirety ER-267N Rev 0 Caldon, Inc. Appendix A
Ca-00 r N "
Appendix A.3 LEFM, + Spool Piece(s) Profile Factor and Profile Factor Uncertainty is proprietary to Caldon in its Entirety ER-267N Rev 0 Caldon, Inc. Appendix A
_ ::7'-xO LZ*£=D2£ 0a Aa 0P C=
Appendix A.4 is Proprietary to Caldon in its Entirety ER-267N Rev 0 Caldon, Inc. Appendix A
A7c:
- o 0 Appendix A.5 is Proprietary to Caldon in its Entirety ER-267N Rev 0 Caldon, Inc. Appendix A
Appendix B is Proprietary to Caldon in its Entirety ER-267N Rev 0 Caldon, Inc. Appendix B
Appendix C LEFMI/+ Interface and Reconciliation Documents, Calorimetric Uncertainties with the LEFMI/ and LEFM /+
ER-267N Rev 0 Caldon, Inc. Appendix C
CPL ROBINSON LEFM Interface and Reconciliation Document Calorimetric Uncertainties with the LEFM Check and Check Plus JANUARY 17, 2002 I. Purpose It is the purpose of this document to define precisely the uncertainties that Caldon will calculate and justify for a specific Appendix K uprate project. The uncertainties that are outside Caldon's scope are also defined, as well as the method for combining all uncertainties to obtain a power uncertainty. This document also breaks down the relationship between the uncertainties tabulated in Caldon reports covering the operation of the LEFM Check and LEFM CheckPlus instruments and the data that Caldon will provide for a specific uprate project.
II. Background Reports covering the operation of the LEFM Check and LEFM CheckPlus instruments describe how the use of these instruments reduces the uncertainties in feedwater mass flow and feedwater enthalpy.1 In combination with the uncertainties in the determination of other variables (steam enthalpy, for example), the uncertainties in feedwater mass flow and enthalpy establish the uncertainty in the core thermal power. The amount of a power increase allowable under an Appendix K uprate is directly dependent on achieving a thermal power uncertainty within bounds defined by the reports cited above.
The uncertainties in the variables measured by an LEFM, either mass flow or derived from its outputs (feedwater temperature and pressure, which are converted to enthalpy) are made up of several elements. These elements relate to the LEFM's measurements of time, to its dimensions, to the hydraulics of the installation and to correlations relating fluid temperature and density to sound velocity and pressure. With respect to the correlations and the measurements of time and dimensions, some of the uncertainties in mass flow are systematically related to the uncertainties in feedwater enthalpy while others are not. The structure and combination methods for power uncertainties are described further below.
III. Structure of the Thermal Power Uncertainties The core thermal power as determined by a heat balance around the steam supply is given by:
(1) QRx = WFW (hs - hFw) + Qwoss NET Where Qpx is the core thermal power WFw is the mass flow rate of the feed to the steam supply, the product of feedwater volumetric flow rate and feedwater density,
'Caldon Engineering Reports ER-80P, ER-i 60P and ER-I 57P I
hs is the enthalpy of the steam delivered by the steam supply, a function of its pressure and moisture content for saturated steam supplies and its pressure and temperature for superheated steam supplies, hFw is the enthalpy of the feedwater, a function of its temperature and pressure, and QLoss NET is the net loss or gain in power from coolant pump heating, blowdown and/or reactor water purification, convective and radiant losses, etc.
The contributing uncertainties to the thermal power computation are defined by differentiating equation (1):
(2) dQpx = dWFW (hs - hFw) + WFW dhs - WFW dhFw + dQLoss NET The contributors can be expressed per unit by dividing equation (2) by QPx.
(3) dQRx/QRx = dW~F/Wvw [1 - (QLoss NET/QRX)] + [dhs/ (hs - hFw)] [1 (QLoss NET/QRX)] - [dhpw / (hs - hFw)] [1 - (QLoss NET/QRx)] +
dQOoss NET/ QRX Since the net gains and losses term is typically less than 1% of the reactor thermal power, the term [1 - (QLoss NET/QRx)] may be taken as approximately 1.0. Hence, (4) dQrx/QRx = dWvw/Wvw + [dhs/ (hs - hFw)] - [dhFw/ (hs - hFw)] +dQLoss NET/ QRX It should be pointed out that equation (4) applies algebraically only if all error contributors are systematically related to each other. Most of these components are not systematically related. If all of the components were random errors or biases the power uncertainty of equation (4) would be the square root of the sum of the squares of the individual terms on the right hand side of the equation. In fact, a combination of the two procedures is appropriate as described below.
The feedwater enthalpy is a function of its temperature and pressure. Likewise, the density of the feedwater, which the LEFM combines with the volumetric flow to compute mass flow, is a function of temperature and pressure. Because of this and other factors, certain elements of the uncertainty in feedwater enthalpy are combined systematically with the mass flow uncertainty, while other elements, unrelated to the mass flow measurement, are combined randomly. For convenience in defining the combination of terms, the feedwater enthalpy will be related to its temperature and pressure by the following:
(5) hFw = 8h/8p I T (pFw- PO) + 6h/8T Ip (TFw - To) + ho The computation of feedwater enthalpy from temperature and pressure by the plant computer-part of the thermal power computation-may be carried out by a more complex algorithm than that of equation (5), or the enthalpy may be determined from a look up table. Equation (5) is used here simply as a convenience for developing the 2
elements of the error contributors to feedwater enthalpy. Using equation (5), the uncertainty in feedwater enthalpy is:
(6) dhFw = 8h/Ip IT dpsw + 5h/5T Ip dTFw + dho Here dh0 represents the potential bias in the enthalpy algorithm of the plant computer.
Rewriting equation (4) to incorporate equation (6), and rearranging terms:
A B (7) dQix/QRx = {dWFw/WFw) - {[1/ (hs - hFw)] [6h/6p IT dpFW + 6h/6T IpdTFw]}
C D E
+ {[1/ (hs - hFw)] dh 0 }+ {[l/ (hs - hFw)] dhs} +{dQLoss NE/ QRX}
In the determination of overall thermal power uncertainty, terms A and B will be provided by Caldon, based in part on a feedwater pressure uncertainty provided by the utility. [ ]
Terms C, D, and E are outside of Caldon's scope, are based on other plant instruments, and are to be provided by others.
Caldon will provide a single uncertainty, AB, expressed as a percentage of the rated thermal power, that encompasses terms A and B. Under normal circumstances, there will not be a systematic relationship between term AB, on the one hand, and terms C, D, and E, on the other. Likewise, there will normally not be systematic relationships among terms C, D, and E. Therefore, the utility will normally compute the total thermal power uncertainty from the following.
(8) dQOx/QO = [(AB) 2 + (C) 2 + (D) 2 + (E)2]1/2 IV. Reconciliation of Uncertainties for CPL ROBINSON With the Uncertainties Quoted in Caldon Engineering Reports Table I below compares the expected site-specific bounding uncertainties for CPL ROBINSON to the following Caldon Engineering Reports:
"* ER-80P, Rev. 0, the original Caldon topical report from 1997 that requests a 1%
power uprate based on an accuracy of the LEFM Check system bounded by 0.6%
thermal power accuracy.
"* ER-160P, Rev. 0, which presents instrument uncertainties exactly the same as those in ER-80P. ER-160P recognizes that, in accordance with NRC Rulemaking in June 2000, a power uprate up to and including 1.4% power can be requested for the LEFM Check System (since ER-80P demonstrates that its accuracy supports a thermal power uncertainty of+/- 0.6%).
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ER-157P, Rev. 5, which describes Caldon's next generation LEFM CheckPlus. ER 157P revises the uncertainty analyses of ER-80P to reflect actual LEFM Check data as applied to a typical single flow measurement application (similar to CPL ROBINSON). It also shows that the LEFM Check system can achieve power uncertainties as low as +/- 0.5% thermal power accuracy. Additionally, ER-1 57P demonstrates that the LEFM CheckPlus can support power uncertainties as small as +/-
0.3%.
It should be reiterated that the data of column 5 of Table 1 are bounding. [
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I o tI p i p I t C entirety.
Information on this page is proprietary to Caldon in its entirety.
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Information on this page is proprietary to Caldon in its entirety.
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United States Nuclear Regulatory Commission Attachment IV to Serial: RNP-RA/02-0104 6 pages H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AFFIDAVIT AND APPLICATION FOR WITHOLDING FROM PUBLIC DISCLOSURE
ZZE1 i LrL L, Caldon, Inc.
July 11, 2002 CAW 02-01 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
Subject:
"Caldon, Inc. Engineering Report: ER- 267, Bounding Uncertainty Analysis for Thermal Power Determination at CP&L Robinson Nuclear Power Station Using the LEFM,/+ System" Gentlemen:
This application for withholding is submitted by Caldon, Inc. ("Caldon") pursuant to the provisions of paragraph (b)(1) of Section 2.790 of the Commission's regulations. It contains commercial strategic information proprietary to Caldon and customarily held in confidence.
The proprietary information for which withholding is being requested is identified in the subject submittal. In conformance with 10 CFR Section 2.790, Affidavit CAW-02-01 accompanies this application for withholding setting forth the basis on which the identified proprietary information may be withheld from public disclosure.
Accordingly, it is respectfully requested that the subject information, which is proprietary to Caldon, be withheld from public disclosure in accordance with 10 CFR Section 2.790 of the Commission's regulations.
Correspondence with respect to this application for withholding or the accompanying affidavit should reference CAW-02-01 and should be addressed to the undersigned.
Very truly yours, Calvin R. Hastings President and CEO Enclosures 1070 Banksville Avenue
- Pittsburgh, PA 15216 Tel: 412-341-9920
- Fax: 412-341-9951
- Web: www.caldon.net
July 11, 2002 CAW-02-01 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:
ss COUNTY OF ALLEGHENY:
Before me, the undersigned authority, personally appeared Calvin R. Hastings, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Caldon, Inc. ("Caldon") and that the averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:
Calvin R. Hastings, President and CEO Caldon, Inc.
Sworn to and subscribed before me this //t day of
,2002 Notarial Seal 4aSnn 8. Thomas, Notary Public Pittsbllrgh, Allegheny County Mry-CMmmision Expires July 28, 2003 MePe "YivaniaAssciaoofNotNarile I
- 1. I am the President and CEO of Caldon, Inc. and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rulemaking proceedings, and am authorized to apply for its withholding on behalf of Caldon.
- 2. I am making this Affidavit in conformance with the provisions of 10CFR Section 2.790 of the Commission's regulations and in conjunction with the Caldon application for withholding accompanying this Affidavit.
- 3. I have personal knowledge of the criteria and procedures utilized by Caldon in designating information as a trade secret, privileged or as confidential commercial or financial information.
- 4. Pursuant to the provisions of paragraph (b) (4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.
(i) The information sought to be withheld from public disclosure is owned and has been held in confidence by Caldon.
(ii) The information is of a type customarily held in confidence by Caldon and not customarily disclosed to the public. Caldon has a rational basis for determining the types of information customarily held in confidence by it and, in that connection utilizes a system to determine when and whether to hold certain types of information in confidence. The application of that system and the substance of that system constitutes Caldon policy and provides the rational basis required.
Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential advantage, as follows:
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Caldon's 2
competitors without license from Caldon constitutes a competitive economic advantage over other companies.
(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.
(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, and assurance of quality, or licensing a similar product.
(d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Caldon, its customer or suppliers.
(e) It reveals aspects of past, present or future Caldon or customer funded development plans and programs of potential customer value to Caldon.
(f) It contains patentable ideas, for which patent protection may be desirable.
There are sound policy reasons behind the Caldon system, which include the following:
(a) The use of such information by Caldon gives Caldon a competitive advantage over its competitors. It is, therefore, withheld from disclosure to protect the Caldon competitive position.
(b) It is information that is marketable in many ways. The extent to which such information is available to competitors diminishes the Caldon ability to sell products or services involving the use of the information.
(c) Use by our competitor would put Caldon at a competitive disadvantage by reducing his expenditure of resources at our expense.
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(d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Caldon of a competitive advantage.
(e) Unrestricted disclosure would jeopardize the position of prominence of Caldon in the world market, and thereby give a market advantage to the competition of those countries.
(f) The Caldon capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.
(iii) The information is being transmitted to the Commission in confidence, and, under the provisions of IOCFR Section 2.790, it is to be received in confidence by the Commission.
(iv) The information sought to be protected is not available in public sources or available information has not been previously employed in the same manner or method to the best of our knowledge and belief.
(v) The proprietary information sought to be withheld in this submittal is that which is appropriately marked in "Caldon, Inc. Engineering Report: ER-267 Bounding Uncertainty Analysis for Thermal Power Determination at CP&L Robinson Nuclear Power Station Using the LEFM /+ System". This information is submitted for use by the NRC Staff in their review of the MUR uprate license amendment request of CP&L Robinson Nuclear Power Station.
Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Caldon because it would enhance the ability of competitors to provide similar flow and temperature measurement systems and licensing defense services for commercial power reactors without commensurate expenses. Also, public disclosure of the information would 4
enable others to use the information to meet NRC requirements for licensing documentation without the right to use the information.
The development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Caldon effort and the expenditure of a considerable sum of money.
In order for competitors of Caldon to duplicate this information, similar products would have to be developed, similar technical programs would have to be performed, and a significant manpower effort, having the requisite talent and experience, would have to be expended for developing analytical methods and receiving NRC approval for those methods.
Further the deponent sayeth not.
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