ML20034F081

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Requests That Proprietary SPES-2 Instrumentation & Data Reduction Plan, Rev 0 & SPES-2 Component & Piping Drawings Be Withheld,Per 10CFR2.790
ML20034F081
Person / Time
Site: 05200003
Issue date: 02/23/1993
From: Liparulo N
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To: Borchardt R
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20034F035 List:
References
AW-93-420, NUDOCS 9303020251
Download: ML20034F081 (32)
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Text

{{#Wiki_filter:-__ l 9 Westinghouse Energy Systems f* 355 flectric Corporation Pin 20@ PennsyNania 15230 0355 AW-93-420 l Dccument Control Desk I U.S. Nuclear Regulatory Commission i Washington, D.C. 20555 ATTENTION: MR. R. W. BORCHARDT APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE 1

SUBJECT:

COMPONENT AND PIPING DRAWINGS FOR THE SPES-2 FACILITY IN SUPPORT OF THE AP600 DESIGN

Dear Mr. Borchardt:

The application for withholding is submitted by Westinghouse Electric Corporation (" Westinghouse") pursuant to the provisions of paragraph (b)(1) of Section 2.790 of the Commission's regulations, it contains commercial strategic information proprietary to Westinghouse and customarily held in confidence. The proprietary material for which withholding is being requested is identified in the proprietary version of the subject report. In conformance with 10CFR Section 2.790, Affidavit AW-93-420 accompanics 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 Westinghouse be withheld from public disclosure in accordance with 10CFR Section 2.790 of the Commission's regulations. Correspondence with respect to this application for withholding or the accompanying affidavit should reference AW-93-420 and should be addressed to the undersigned. Very truly yours, i NN c, <- N. J. Liparulo, Manager Nuclear Safety And Regulatory Activities /nja l cc: M. P. Siemien Office of the General Counsel, NRC l L Barnett NRC (12H5) 9303020251 930223 ""7^ r PDR ADOCK 0520 3 A )

l COPYRIGIIT NOTICE The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to make the number of copics of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.790 regarding restrictions on public j disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection not withstanding. With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public i document room in Washington, D.C. and in local public document rooms as may be required by NRC regulations if the number of copics submitted is insufficient for this purinse. The NRC is not authorized to make copies for the personal use of members of the public who make use of the NRC public document i rooms. Copics made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary. i h f i 0330A L I 1 r. e

~ - -.- -. =. -. -.-. PROPRIETARY INFORMATION NOTICE ( Transmitted herewith are proprietary and/or non-proprietary versions of documents fumished to the NRC in connection with requests for generic and/or plant specific review and approval, in order to conform to the requirements of 10CFR 2.790 of the commission's regulation concerning the protection of proprietary information so submitted to the NRC, the information which is proprietary in the proprietary versions is contained within brackets and where the proprietary information has been deleted in the non-proprietary versions on the brackets remain, the information that was contained within brackets and where the proprietary information has been deleted in the non-proprietary versions only the brackets remain, the information that was contained within the brackets in the proprietary versions having been deleted. The justification for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (i) contained within parentheses located as a 3 superscript immediately following the brackets enclosing each item of information being identified as proprietary or in the margin opposite such information. These lower case letters refer to the types of i information Westinghouse customarily holds in confidence identified in Section (4)(ii)(a) through (4)(ii)(f) of the affidavit accomp;mying this transmittal pursuant to 10CFR2.790(b)(1). i a a B I r 5 k i I i 4 ? 03 4A l t ? A f. .n-, w, .. r n -- ~ g

.m....~. - -... i AW-93-420 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA: i SS COUNTY OF ALLEGHENY: i Before me, the undersigned authority, personally appeared Peter J. Monis, who, being by me j duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf I of Westinghouse Electric Corporation (" Westinghouse") and that the averments of fact set forth in this l Affidavit arc true and correct to the best of his knowledge, information, and belief: I / e i w' hM i V Peter J. Morris, Manager Strategic Safety and Regulatory Issues Sworn to and subscribed before me this M3 day f of / .1993 0 f . bsa. arvJ \\ Notary Public j Notar,a! Seal % *MafePan,tnyy fje p y Cennigm eg,33 fg 4,,nt'044 Coro. Akr/EnyCou/y I Wm.Panyvarmeaxe,ggy i temA

- ~- 5 AW-93-420 (1) I am Manager, Strategic Safety and Regulatory Issues, in the Nuclear and Advanced Technology Division, of the Westinghouse Electric Corporation and as such, I have been t specifically delegated the function of reviewing the proprietary information sought to bc 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 the Westinghouse Energy Systems Business Unit. (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 Westinghouse application for withholding accompanying this Affidavit. + (3) I have personal knowledge of the criteria and procedures utilized by the Westinghouse Energy Systems Business Unit 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 l held in confidence by Westinghouse. (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, j 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. l 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 competitive advantage, as follows: 1 I Ch(A1A )

AW.93-420 l 1 (a) The information reveals the distinguishing aspects of a process (or component, i structure, tool, method, etc.) where prevention of its use by any of I Westinghouse's competitors without license from Westinghouse 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, manufactute, shipment, installation, assurance of quality, or licensing a similar product. (d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or supplicts. (c) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse. (f) It contains patentable ideas, for which patent protection may be desirable. l There are sound policy reasons behind the Westinghouse system which include the following: i 1 (a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors, it is, therefore, withheld from disclosure to protect the Westinghouse competitive position. (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, em j

AW-93-420. (c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resourecs at our expense. (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 punle, thereby depriving Westinghouse of a competitive advantage. (c) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition of those countries. l (f) The Westinghouse 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 10CFR 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 original manner or method to the best of our knowledge and belief. (v) Enclosed is Letter ET-NRC-93-3825, February 1993, being transmitted by j Westinghouse Electric Corporation (E letter and Application for Withholding Proprietary information from Public Disclosure, N. J. Liparulo (3'), to Mr. R. W. Borchardt, Office of NRR. The proprietary information as submitted for use by Westinghouse Electric Corporation is in response to questions concerning the AP600 plant and the associated design certification application and is expected to bc applicable in other licensec submittals in response to certain NRC requirements for justification of licensing advanced nuclear power plant designs. I l l MORA l

[ AW-93-420 This information is part of that which will enable Westinghouse to: (a) Demonstrate the design and safety of the AP600 Passive Safety Systems, f (b) Establish applicable verification testing methods. (c)_ Design Advanced Nuclear Power Plants that meet NRC requirements. (d) Establish technical and licensing approaches for the AP600 that will ultimately result in a certified design. (e) Assist customers in obtaining NRC approval for future plants. Further this information has substantial commercial vahe as follows. l (a) Westinghouse plans to sell the use of similar information to its customers for purposes of meeting NRC requirements for advanced plant licenses. (b) Westinghouse can sell support and defense of the technology to its customers I in the licensing process. Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar advanced nuclear power designs and licensing defense services for commercial power reactors without commensurate expenses. Also, publie i disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing 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 intersive Westinghouse effort and the expenditure of a considerable sum of money-0608A

AW-93 420 ? i in order for competitors of Westinghouse to duplicate this information, similar 1 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, t Further the deponent sayeth not. i b l 1 1 i 1 OtiO8A

a .] 1 i .l l ^ j i 'Information Package SPES (3-loop 312 Simulation) .) Steam Generator Pump Power Channel 1 Contents o Table 3.2/2, Volume comparison between SPES and PWR. PUN .Page 1 R o Table 3.3.41, Prisaary recurulation pump charactenstks Page 2 ' o Table 33.4/2, Nosebal data of the pump sealing system Page 3 o Table 3.3.6/1, Steam generator tube bundle data Page 4' o Table 33.6/2, Steam generator U.tabe bundle geometric data Page 5. o Table 33.6f3, U. tabes measured elevations Page 6 .o Table 3.4.1/1, Steam generator general data Page 7 ' i o Table 3.4.1/2, Steam generator thermahydraulic data Page 8 o Table 3.4.1/3, Steam generator volumes, cross flow areas and weights Page 9 o Table 3.4.2/1, Secondary piping system general data Page le o. Table 3.4.2/2, Secondary piping system characteristics Page 11 o Figure 3J.116, Detail of core support plate Page 14 i o Figure 3.3.2/1, Power channel rod detail Page 15 o Figure 33.2/2, Rod bundle spacer detail Page 16 o Figure 33.4/1, Primary recintulation pomp cross section Page 17 o Figure 3.3.4/2, Primary rwcirculadon pump H.Q characteristics Page 18 o Figure 33.4/3, Pump speed.nowrate theoretical curves Page 19 o Figure 33.4/4, Primary pump mechapical seal arrangement ' Page 28 i February 19,1993 s i 1

fd6 ja hjfj 4 SPE,5 Q 31a s y d n 1 SI'ES volume (dm3) PW11 volume (m3) l l l'HIMAltY SIDE ti 13 270.06 Cold legs 20 9.14 I l'ower channel 257 108.96 l l downcomer (upper liead bypass included) 47 20.31 lower plenum 58 25.12 i . core (core bypass included) 52 22.26 . upper plenum S1 20.49 upper head 49 20.77 llo t legs 40 9.41 Steam generator primary sides 1411 80.89 51 11.61 Pump suctioits ~ 9 Pumps 13 6.80 'u j Prenuur;zer (surge 1ine and spray Iane inc!uded) aud 43.26 [ SECUNDARY SIDE 1163 507.7 Steam generators . downcomers 263 91.95 . stuers 29tl 123.48 upper plena IPb 53.75 steam separators 66 2tl.19 steam domes 410 210.33 including inlet and outlet nozzles TAllt.E 3.2/2 - Volume comparison between SPES and PWR-PilN u m

.~ i 2 20 design pressure, MPa - design temperature. 'K 638 nominal conditions t . suction pressure, MPa 15.3 temperature. K 564 . capacity, Eg/s 10.6 77 . head, m rotational speed, rad /s 335 rated torque, Nm 59.7 l l . power, KW 20 efficiency, *. 40 . NPSHr, m 2.6 l speed regulation range, rad /s -628,+628 - maximum power, KW 50 - suction diameter, mm 66.7 - discharge diameter, em 66.' - inside fluid volume. dm3 4.3 g1 coal inertia, Kgm2 3.5 TABLE 3.3.4/1 - Primary recirculation pump characteristics q l e l 49 j i i

A - I'l u..h ii'd I'l'I t 'l 'le'aillera l i ze'l Wal et' ( pil it ) - 1lowsute, hg/si

18. 0t1.1

- injertion passsure, MPa 16.3 - DP arrons the seal, MPa s i.ne r ..b . t o t ersuedi a t e 14.3 . outer 1.5 - neal leakage, Kg/s inner O ** I ns t ei m.>d i + t o.noi outer O *** - seal pv, MPa m/s 8 Inner 5 intermediate 140 outer 15 sueli a value is kept automatically constant even diaring primary pressure transient

    • with a DP across the seal less then 7 MPa with a DP across the seal less then 2 MPa

--- L TAllt.E 1.3.4/2 - Nominal data of the pump sealing system (referred 1,o a single pump) 'JJ

4 - design pressure, MPa 20.0 - design temperature. 'K 638 - numoer of U-tubes 13 i SQUARE - array 24.89 - pit:n, mm - outer diameter, mm 17.46 - thie'cness, mm 1.02 - tune average length, mm 16742 - tuce active average length, mm 16564 - straight tube average length.mm 8210 - elevation of longest tube, mm 8323 - elevatien of shortest tube, em

  • 8153

- elevation of 7 grids (upper edge),mm 1115,2230,3345,4460 5575,6690.7805 - inlet plenum + outlet plenum volume, dm3 7.43 - heat transfer area referred I: 'D, m2 10.43 - heat transfer area referred :: :D. m2 11.81 - primary :ross flow area (mm2) 2428 secondary cross flow area (mm2: 12127 - tute material ASTM SS163 Inconel 600 The upper edge of the tube sneet is considered as reference elevati:n zero. Suncle :ene free of grid spa er and cold / hot zone diaphragm AB'.I 3.3.6/1 - Steam generator tube bundle data

hs Tube R, Z, L, Elevatica Imm) linm) (mm) (mm) 1 215 8132 16331 8153 2 215 8132 16331 8153 3 30.4 8157 16409 8187 4 52.8 8182 16529 8234 5 52.8 8207 16579 8259 6 42.4 8231 16596 8273 7 42.4 8231 16596 8273 8 42.4 8231 16596 8273 9 42.4 8231 16596 8273 ~ 10 42.4 8231 16596 8273 1 11 67.3 8256 16724 8323 12 67.3 8256 16724 8323 l 13 67.3 8256 16724 8323 i d i L, = 2Ze + 7t R, a = l I SG tube arrangement i I ii s = -O-G-1 'S i9 h O' 4 8 Q h,.' ' ' gi2__ "ON d 'sM>t#&' Iil I TABLE 3.3.W2 - Steam generator U-tube bundle geometrical data

tube design measured elevation elevation (mm) (mm) SG-1 g SG-3 1 8153 8120 8120 8115 2 8153 8120 8120 8115 3 8187 8185 8180 8185 4 8234 8230 8230 8225 5 8259 8250 8245 8245 6 8273 8270 8270 8265 7 8273 8270 8270 8265 8 8273 8270 8270 8265 9 8273 8270 S270 8265 10 8273 8270 8270 8265 11 8323 8325 8320 8315 12 8323 8325 8320 8315 13 8323 8325 8320 8315 TABLE 3.3.6/3 - U-tubes measured elevations (referred to tube sheet upper edge : ~ a t t b

m - aled i git pre:auttiv. MI'.i iqi - stesigan temperatuir, 'K b311 - Il-t ul>et, number 1:1 - tube average lengtle, m 16.7 - heat exchange surface, m2 LI.8 (referred to OD) - overalI height, m 15.594 - secointary Iluid volume, dm3 387 + - nozzle ID, mm . feed Iine 30.1 steam Iine 73.7 toilet / outlet plena 66.6 - elevation, m primary plena bottom 2.340 . primary plena top 2.559 . tutie sheet. top 2.648 . sepaaator inlet 13.255 separator outlet 16.313 . feedwater nozzle 14.352 . steam 1ine nozzle 17.768 - materlais primary plena, tube sheet ASTM-S A 182 F 304 lower vessel ASTM-SA 106 Gr 11 ititermediate vessel (sep, side) ASTM-SA 204 Gr C upper vessel (steam dome) ASTM-SA 204 Gr 11 loose flanges ASTM-SA 105 . separator, dryers AISI 304 . fillers Nickel plated TADI.E 3.4.1/1 - Steam generator general data J v +. a ~,

- primary side fluid subcooled water pressure, MPa 15,5 t flowrate, Kg/s 10.6 coolant inlet temperature, 'X 599 - secondary side fluid water /two phase mixture / steam [ pressure, MPa 6.7 feedwater flowrate, Kg/s 1.21 feedwater temperature. 'K 500 . nominal level, m (ref. to tu e sheet top) 12.75 heat removal capacity, KW 2165 . PORV set pressure. MPa 7.8 i . safety valve set pressure, MPa 8.5 . PORV discharge flow-rate ( 7.3 MPa, x=1 ), Kg/s 0.24* . SV disenarge flow-rate (8.5 MPa, x=1), Kg/s 1.72'* theoretical data with ID Orifice = 5.2 mm theoretical data ID orifice = 13.3 mm' TABLE 3.4.1/2 - Steam generator thermalhydraulic data k

STEAM GENERATOR CilAllACTElilSTICS - - - - - - - - - - - - - - - - - ~ ~ - - - - - - - - - - - - - - - - - . le:.c r i p t. t on elevaltuli i tii ersial s crusa sectioni volume we iglit. mm em2 dm3 Kg _ - - - = - - - - - - - - - - - - - - _ - iced water 14352-14352 / 1146 0.20 2.5 a...n l e Ihorus 14314-14390 / 833 0.40 1.2 1-nuzzle 14390-14419 / 283 0.01 0.1 .:.tial an' 16253-14463 / 14162 54.88 283 (vessel) ilowncomer 4656 (sep. duet.) 177.5 ()oose fIanges) 14463-13648 15695 (thorus zone) 2G343 13648-13523 20043/15495 13523-13265 15495 tubulur .lowncomer 13312-267/ / 1452x2 32.06 421 iaser 2648-4878 tubes / fillers 11773 141.30 1456.5 spacers / diaphragm 4408 (spacer) 4878-larJ/4 tubes /fi11ers 12127 spacers 4408 (spacer) 109 /4-132SS Iil1ers/ 18048 (falIern) butterfly valve 23527 18385 .urparutor 132b5-16313 / 7088 21.92 40 .j . t e.4.m ela.mc I f e'll 'l-17 / bit vlryarra 1 4 1817 ? . l.W.79 S?4 (vennel) 53.7 (tiryer) TOTAL 387.56 2960 _ = _ I AlllE ' 3.4.1/ 3 - Steam generator volumes, cross flow areas and weight s. O

___________________ __=-- - - - - - _- -=. _ _ = = - - _=_- - = - _ line tag inside outside length volume line pipe diameter (sam) diameter (mm) (nun ) (dm3) connect. ion material ______________________________________y_- =____________________________ main steam lines MSL 1/2/3 73.7 88.9 19625 62.17 SG 1/2/3,MSL 0 ASTM A 106 Gr main steam header MSt. O 97.2 114.3 28862 215.67 MSL 1/2/3.BV-OO4A ASTM A 106 Gr steam dump SDL 59.0 73

26242 71.74 MSL 0,BV-OO4B ASTM A 106.Gr li' feedwater lines FWL 1/2/3 38.1 48.3

t. 4869 5.55 SG,FWI.-O ASTM A 106 Gr l'eeilwa t er lane heatler FWl. O 49.2 60.3 24937 47.4S FWI,1/2/3,IIE 2 ASTM'A lob Gr preheates Iine I'lll. 49.2 60.3 7741 14.72 MSI. O,IlE ? ASTM A 106 Gr preheater bypass HP 03 24.3 33.4 16109 7.48 FWL 0,FWI. O ASTM A 106 Gr emergency feedwater Iines EFWL 1/2/3 13.9 21.3 3029 0.46 EFWL O FWL 1/2/3 -ASTM A 106 Gr emergency feedwater header EFWL 0 13.9 21.3 29529 4.46 FP 1 EFWL 1/2/3 ASTft A 106 Gr 3 ., t i TAllt.E 1.4.2/l - Seconstary piping system general data d[ O

i __________________4___ MAIN STEAM

l. I N E S

.i i from SG nozzle to MSIV f~ rom MSiv to main steam header - tutie size /scli 3" sch 80 3 " sch 80 - lenght, mm 7815 11810 - e aws sec t n uit area, mai2 4261 4261 - i nner voliune, dm3 31.84 50.33 - lit surface area, m2 1.756 2.733 - OD surface area, m2 2.536 3.416 - metal weight, Kg 183 cutve number / type 6 MSL-1 3/90 LH 4/90 LH 1/45 LH MSL-2 5/90 1.H 4/90 LR . MSL-3 4/90 LR 4/90 LR 1/45 1.R NA IN STEAN HEADER (from MSL connections to stop valve) ___7____._____----- 1 t - tube size /sch 4" sclk 80 i. - Ienght sum 28862i . cross sections area, mm2 7417:;<e - isiner volune, dm3 (*) 215.67 - ID surface area, m2 8.813 1 - OD surface area, m2 10.405 _ m.e t a l we i gte t.. l(g 66b - turve nun.her/4ype b/iJO l.it 2/45 LR (*) the valise includes the volume of preheater line from MSL 0 to isolation valve

  • m..n.tas y p i p i ng n y s t ee c hares l es s t.t s t n C

i Atil t t, t..* /.* - ....- m -.m m ,_p m - - - + = - - - -

STEAH D (1 M P (f' rom MSL 0 to isolation valve) i, --- -----------------------------------------------------------------,- m -----_-- 4 - tube aanze/sch 2"l/2 urb' $0 - Ienght, smte 26242 l - cross sectton area, em2 e 2734 - inner volume, dm3 75.74 - ID surface area, m2 4.864 - OD surface area, m2 6.119 - metal weight. Kg 311.2 - curve nun.ber/ type 7/90 1.H 1/15 IJt s PHEHEATEH

1. I N E t

- tube stze/sch 2" sch 80 - length, em 7741 - cross section, mm2 1901 l i s FEEDWATEH HEADEIt -i .I - - tube size /hch 2" sch 80 - length, em 24937 - Crush serttun, mm2 1901 g I t v..s e t '.I l 4 4 t*l 6 9 1 d - t m.-

l EEDW ATEli 1.lNES ( f t uin luolat ion valve to liG nozzle) - tube unze/ach 1"l/2 sch 80 - lenght, mm 4869 4 - cross section area, mm2 1140 - inner volume, dm'3 5.S5 - 10 suriece area, m2

0. 5t1.1

- OD surlare area, m2 G.911 - nie t a l weight, Kg 42.2 - curve number / type - ig- . IJWL 1 '3/90 LH i 1/45 1.H. . /.90 LR-2 FWL 2 ~1/45 LH . FWL 3 '1/90 LR 1/50 1.H !t e PREHEATEH BYPASS - tube size /sch 1" sch 80 - length, mm 16109 i: : E.il - cross secttone, mm2 464 k 1 EMERGENCY FEED WATER SYSTEM tube size / sch 1/?" sch 110 lenght, mm g header (total) 29529 i [gg } header (up to stop valve) 14107 . brancties 30pg crosu section, as2 151 l J i mi e i i i.,,,,.o

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