ML19350C949
| ML19350C949 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/08/1981 |
| From: | Wiesemann R WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19260G961 | List: |
| References | |
| CAW-81-30, NUDOCS 8104100462 | |
| Download: ML19350C949 (24) | |
Text
{{#Wiki_filter:- p @,T C Nuclear Tectnclogy Divisicn Westinghouse Water Reactor Electric Corporation Divisions ec,333 Pitiscurgn Pennsy!vania 15230 Director of Nuclear Reactor Regulation April 8, 1981 Attn: Mr. S. A. Varga, Chief CAW-81-30 Operating Reactor Branch 1 Division of Licensing U. S. Nuclear Regulatory Commission Phillips Building 7920 Norfolk Avenue Bethesda, Maryland 20014
SUBJECT:
Beaver Valley Unit 1 Cycle 2 Rod Misalignment Analysis (Proprietary) REF: Duquesne Light Company letter, J. J. Carey to S. A. Varga, April 8, 1981
Dear Mr. Varga:
The proprietary material for which withholding is being requested by Duquesne Light Company is of the same technical type as that proprietary material sub-mitted by Westinghouse previously in application for withholding AW-76-8, and was accompanied by an affidavit signed by the owner of the proprietary infor-mation, Westinghouse Electric Corporation. Further, the affidavit AW-76-8 submitted to justify the previous material was approved by the Commission on November 9,1977, and is equally applicable to the subject material. The subject proprietary material is being submitted in support of Duquesne Light Company, Beaver Valley Unit 1. Accordingly, this letter authorizes the utilization of the previously furnished affidavit in support of Duquesne Light Company, Beaver Valley Unit 1. A copy of the affidavit is attached. Correspondence with respect to the proprietary aspects of the application for withholding or the Westinghouse affidavit should reference CAW-81-6 and should be addressed to the undersigned. Very truly yours,
/bek Robert A. Wiesemann, Manager Attachment Regulatory & Legislative Affairs cc: E. C. Shomaker, Esq.
Office of the Executive Legal Dirtctor, NRC 810.4100 g
AW-76-8 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA: C011NTY OF ALLEGHENY: Before me, the undersigned authority, personally appeared Robert A. Wiesemann, who, being by me duly sworn according to law, de-poses and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Corporation (" Westinghouse") and that the aver-ments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief: t' ! M'??(Uut Robert A. Wiescmann, Manager Licensing Programs l . Sworn to and subscribed before me this #8 day ) of d/imI 1976. l 0 s l I L. & #4@
/Notary Public/
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AW-76-8 (1) I am Manager, Licensing Programs, in the Pressurized Water Reactor Systems Division, of Westinghouse Electric Corporation and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public dis-closure in connection with nuclear power plant licensing or rule- , making proceedings, and am authorized to apply for-its withholding l on behalf of the Westinghouse Water Reactor Divisions. f (2) I am making this Affidavit in confomance with the provisions of 10 CFR Section 2.790 of the Commission's regulations and in con-l junction with the Westinghouse application for withholding ac-companying this Affidavit.
- (3) I have personal knowledge of the criteria and procedures utilized by Westinghouse Nuclear Energy Systems in designating infomation as a trade secret, privileged or as confidential comercial or l financial information.
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Comission's regulations, the following is furnished br consideration by the Commission in determining whether the in-famation sought to be withheld from public disclosure should be withheld. l ~ l (1) The information sought to be withheld from public disclosure l is owned and has been held in confidence by Westinghouse. i 1
AW-76-8 (ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public. Westinghouse 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 Westinghouse 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 com-petitive 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 Westinghouse's competitors without license from Westinghouse consti-tutes 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. ..,
AW-76-8 (c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product. It reveals cost or price information, production cap-
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(d) ' acities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers. - (e) It reveals aspects of past, present, or future West-inghouse or customer funded development plans and pro-grams of potential commercial value to Westinghouse. (f) It contains patentable ideas, for which patent pro-taction may be desirable. (g) It is not the property of Westinghouse, but must be ! treated as proprietary by Westinghouse according to agreements with the owner. j There are sound policy reasons behind the Westinghouse system which include the following: (a) The use of such information by Westinghouse gives l Westinghouse a competitive advantage over its com-l peti tors. It is, therefore, withheld from disclosure to protect the Westinghouse competitive position. l l l l
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1 i AW-76-8 (b) It is information which is marketable in many ways. The extent to which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information. (c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense. , (d) Each component of proprietary information pertinent i to a particular competitive advantage is potentially as valuable as the total competitive advantage. If i competitors acquire components of proprietary infor-mation, any one component may be the key to the entire i puzzle, thereby depriving Westinghouse of a competitive advantage. l , (e) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition in those countries. (f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success l in obtaining and maintaining a competitive advantage. i
'O AW-76-8 (iii) The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR Section 2.790, it is to be received in confidence by the Commission.
(iv) The information is not available in public sources 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 the attach-ment to Westinghouse letter number NS-CE-ll39, Eiche1dinger to Stolz, dated July 19, 1976, concerning supplemental infor-mation for use in the Augmented Startup and Cycle 1 Physics Program. The letter and attachment are being submitted as part of the above mentioned program in response to concerns of the Advisory Committee on Reactor Safeguards with the new Westinghouse PWR's, which are rated at higher power densities than currently operating Westinghouse reactors. This information enables Westinghouse to: (a) Justify the Westinghouse design correlations. (b) Assist its customers to obtain licenses. (c) Provide greater flexibility to customers assuring them
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of safe reliable operation. (d) Optimize performance while maintaining a high level of fuel integrity.
AW-76-8 (e) Justify operation at a reduced peaking factor with a wider target band than normal. (f) Justify full power operation and meet warranties. Further, the information gained frem the Augmented Startup and Cycle 1 Physics Program is of commercial value and is sold
- for considerable sums of money as follows: ,
(a) Westinghouse uses the information to perform and justify analyses which are sold to customers. (b) Westinghouse uses the information to sell to its customers for the purpose of meeting fEC requirements for full power licensing. (c) Westinghouse could sell testing services based on the experience gained and the analytical methods developed using this information. Public disclosure of this information concerning the Augmented Startup program is likely to cause substantial harm to the competitive position of Westinghouse by allcwing its ccm-petitors to develop similar analysis methods and models at a much reduced cost.
AW-76-8 The analyses performed, their methods and evaluation repre-sent a considerable amount of highly qualified development effort, which has been underway for many years. If a com-petitor were able to use the results of the analyses in
- the attached document, to normalize or verify their own methods or models, the development effort and monetary expen-I diture required to achieve an equivalent capability would be significantly reduced. In total, a substantial amount of money and effort has been expended by Westinghouse which could only be duplicated by a competitor if he were to invest similar sums of money and provided he had the appro-l priate talent available.
Further the deponent sayeth not. I O
OLWP0-42 bec: M. H. Judkis 4L, 4A J. A. Triggiani ll, l A B. Voltig 1L NSD Central File 3L, 3A r I f 1 l l
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BEAVER VALLEY UNIT 1 CYCLE 2 ROD f1ISALIGNME!!T ANALYSIS Backaround During the Cycle 2 startup of Beaver Valley Unit 1 (DLW), Duquesne Light Co. (DL Co.) experienced problems with their Analog Rod Position Indicators (ARPI's). The cause of the problem was the temperature sensitivity of the ARPI hardware.
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l Because of the changing temperature of the control rod drive shaft with changes in power level, the ARPI calibration performed at HZP temperatures was not main-tained as the plant escalated to higher powers. Consequently, DL personnel saw significiant deviations in the ARPI readings relative to the bank' demand step counters. The deviations stabilized to approximately 30 steps as transient thermal effects dissipated. It should be emphasized that DL Co. did not observe actual rod misalignments; rather, they observed indicated rod misalignments as the result of temperature induced misreadings by the ARPI's. l To circumvent the problem, DL Co. silb.nitted a Tech Spec change which would allow an alternate method for inferring rod position. The ARPI system utilizes a linear variable transfamer consisting of primary and secondary coils alternately stacked on a stainless steel cylindrical tube. An extensi.on shaft from the rod drive { mechanism extends up into the tube and serves as the variable " core" for the transfomer. As the rod moves, the voltage at the secondary and primary coils. changes due to the position change of the transformer " core". The ARPI, then, infers the rod position by sensing the voltage changes at the secondary coils. l DL Co. has found, however, that the primary coil voltage is less sensitive to temperature than the secondary coil voltage. The alternate method proposed in the Tech Spec change perm'.ts utilization of the primary coil voltage to infer rod position in those instances when the ARPI reading indicates a misalignment of i 12 steps or greater. DL Co. is currently using the new spec for Cycle 2 operation. As an alternative to the Tech Spac change described above, DL Co. wanted to be able to submit another Tech Spec change, if necessary, which would pennit indicated misalignments of greater than i 12 steps. To support this proposed Tech Spec, Westinghouse was asked to evaluate the Cycle 2 peakina factor penalties associated
k with a 132 step misalignment (16 step indicated misalignment olus 16 step ARPI errorallowance). The original Tech Soec permitted a 112 step indicated misalign-ment. This, together with the 12 steo ARPI error allcwance, limited the maximum possible undetected misalignment to 1 24 steps. Thus, the proposed Tech Spec would cermit an additional undetected misalignment of 3 steps (5.1 inches). c0 3
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i I , I The objective of this analysis was to assure that the conservatism in the design calculations was maintained with the rod misalignment of 132 steps. l i 1 l l
- one rod either fully inserted or fully withdrawn
Methodoloay To support the 1 32 Tech Spec, rod misalignment calculations were performed to assess the peaking factor penalties resulting from 132 step misalignments of single D and C Bank rods. Coarse mesh 3D-TURTLE calculations were done (2x2, 21 axial meshes) with the 3D-TURTLE peaking factors coarse mesh corrected to discrete 2D-TURTLE. Calculations were made at various power levels with control rods positioned at the appropriate insertion Ifmits (Figure 1). The 3D-TURTLE control rod constants were chosen so as to reproduce the discrete TURTLE rod worths. Each D and C bank rod was misaligned by 1 32 steps and the resulting effects on peaking factors were deterinined (Fxy(z), FaH, Fg ). The Beaver Valley Unit 1 control rod pattern is shown in Figure 2. The potentially misaligned rods are indicated on an eighth core basis. F g Penalty Table 1 shows the 30-TURTLE calculated misalignment F3g penalty as a function of power level. The 150 MWD /MTU step was used as the base case since peaking was a maximum at that burnup. The calcula3fons assumed equilibrium xenon except at zero power where no xenon was assumed. Note that the penalty is small at high powers where ONB is a concern. At low powers the penalty increases due to the increased rod insertion (especially C-Bank) and reduced feedback effects. f i l - l _
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I i Rod Misalionment FyQJ, Worst case Fxy(z) values were collected from the misalignment 3D-TURTLE .ases for each axial mesh. Coarse mesh F,y's were corrected to the 2D-TURTLE discrete base case. Figures 4 and 5 show the maximum calculated Fxy(z) values for power
' - **'M w --m- w,erw- ,p-, , . , , _
levels of 100% and 45%, respectively. Also shown are the axial and cower dependent F xy limits from the Beaver Valley Unit 1 Tech Specs. The calculated F xy 's include an 3% uncertainty factor. 4,f-- RodMisalignmentFg Associated with the limiting Fxy(z) values discussed above are the limiting Fq (z) values shcwn in Figure 6. These limiting F 's were conservatively generated by n synthesizing the limiting Fxy(z) with the worst axial relative power for each axial mesh. The reference Fg (z) values are also shown in Figure 6. HFP equilibrium
. xenon conditions were assumed and the rods were set at the HFP insertion limits. ,
The plotted values include the 1.0!i.and 1.03 Tech Spec uncertainty factors. Note that misalignment penalty occurs primarily at the top of the core (in the rodded region) and that considerable margin to the LOCA Fg envelope exists in all core elevations. r ._ _ _ _ _ . _ _ _ _ __ l
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5-The above argument does not account for the power distribution perturbation resulting from xenon distribution changes induced by the load following misaligned rod. This effect was judged to be small, however, since the axial newer distri-bution in the static misalignment cases was not severely perturbed; [_ _ _ _ _ _ _
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- J 4L To conclude, the F g enalties p resulting from + 32 step single rod misalignments can be accomodated within the existtng FAC Analysis conservatism.
Measured Peakino ractors The results presented in the previous sections were based entirely on analytical models "or the Beaver Valley Unit 1 Cycle 2 core. Measured power distributions confirm that the models used in this analysis are quite adequate when appropriate uncertainties are aoplied. Table 2 shows the results of several moveable detector incore flux maps. Note that the predicted F 6g peaking factors, with uncertainties applied, are equal to or greater than the measured F H eaking factors (including uncertainties). Thus, it is clear from these results that the nuclear design methods used in this analysis adequately predict peaking factors.
For this analysis, the control rods were conservatively assumed to be at the insertion ( limits shown in Figure 1. It should be noted, however, that as Table 2 indicates, the plant typically operates with control rods essentially withdrawn from the core. Typically, even at low power, the rods are positioned almost fully out of core. Consequently, the assumption of rods at the insertion limit used in this analysis conservatively estimates the effect of rod misalfonment on peaking factors. Sumary
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I 1 Analysis done here has shown that the peaking factor penalties resulting from mis-alignments of + 32 steps are small at significant power levels and are within the conservatism used in the Cycle 2 design. Comon practice is to operate the plant with rods essentially withdrawn. This combined with the fact that actual rod misalignments are very rare in Westinghouse plants makes the occurrence of large misalignments very unlikely. e i
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TABLE I Beaver Valley Unit 1 Cycle 2 32 Step Rod Misalignment F vs. Power Check
- AH S
Discrete Discrete F syn 3D-TURTLE Ff,"with 3 20-TyglE aH Rod Hisal. Misalignment Quadrant Power F,g Including 0% Uncertainty Penalty (1) Penalty Tilt (1) Ak s l
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- TURTLE calculations employed Eq Xenon at all power levels and zero xenon at zero power.
Best estimate power sharings were used for the F 3g synthesis. All calculations were done assuming the rods to be positioned at tlie insertion limits. , l
1 TABLE 2 Typical Normal Operation Flux Hap Results AL\ ; map 8 l Burnup (HWD/HTU) , Power (%) : ! D-Bank Insertion (steps) i Heasured 3gF* l 4 Predicted F 3g* ' 3g Limit F 1 Heasured Fq Predicted Fq Fq Limit HeasuredTilt(%) ! Predicted Tilt (%) Tilt Limit ! I L- i
- Measured F 3g includes 4% uncertainty. Predicted F aH values include 8% uncertainty.
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