ML20059C322

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Forwards Response to NRC Request for Addl Info on Sbwr Design
ML20059C322
Person / Time
Site: 05200004
Issue date: 10/25/1993
From: Quirk J
GENERAL ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MFN-174-93, NUDOCS 9311010092
Download: ML20059C322 (21)
v • d • e


Text

6 GENuclect Energy Genera!Dectnc Company 17b Carmer Avenue. Sen hse. CA 95125 October 25,1993  :

MFN No.174-93 Docket STN 52-004 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Richard Borchardt, Director Standardization Project Directorate

Subject:

NRC Requests for Additional Information (RAls) on the Simplified Boiling Water Reactor (SBWR) Design

Reference:

Transmittal of Requests for AdditionalInformation (RAls) for the SBWR Design, Letter from M. Malloy to P. W. Marriott Dated August 26,1993 The reference requested additional information on the SBWR Design. In fulfillment of this request, GE is submitting responses to RAls 440.1 - 440.5. The responses to RAIs 440.3, .4 and .5 are proprietary.

Sincerely,

/K

/[6 ai<

ject Manager ABWR Certification Program M/C 782, (408)925-6219 w/o Enclosure cc M. Malloy, Project Manager (NRC) (

Enclosures:

Two (2) proprietary tapes)

LTRitK 9.%1 010009 ofy 9311010092 931025 ((f g

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PDR ADOCK 05200004 A PDR g ,-  ;

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GENERAL ELECTRIC COMPANY s AFFIDAVIT I, Joseph F. Ouirk, being My sworn, depose and state as follows:

.l (1) I am the Project Manage.r ABWR Certification Program, General Electric '

Company ("GE") and have been delegated the function of reviewing the information described in paragraph 2 which is sought to be withheld, and have been authorized to apply for its withholding.

(2) The information sought to be withheld is the GE proprietary responses to RAls .

440.3, .4 and .5. This'information is contained on GE proprietary tapes and delineated by bars marked in the margin adjacent to the specific written -

material. i

~

(3) In making this application for withholding of proprietary information of which it is an owner, GE relies upon the exemption from disclosure set forth in the -

Freedom of Information Act ("FOIA"),5 USC Sec. 552(b)(4), and the Trade Secrets Act,18 USC Sec.1905, and NRC regulations 10 CFR 9.17(a 4 ,

2.790(a)(4), and 2.790(d)(1) for " trade secrets and commercial or fin)a(

information obtained from a person and privileged or confidential" (Exemption 4). The material for which exemption from disclosure is here sought is all .

" confidential commercial information", and some portions also qualify under the narrower definition of" trade secret", within the meanin s assigned to those terms for purposes of FOIA Exemption 4 in, respective , Critical Mass Energy ,

Project v. Nuclear Regulatorv Commission. 975F2d871 DC Cir.1992), and Public Citizen Health Research Group v. FDA,704F2d1280 (DC Cir.1983).

(4) Some examples of categories ofinformation which fit into the definition of proprietary mformation are:

a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by General Electric's competitors without license from General Electric constitutes a competitive economic advantage over other companies;
b. Information which, if used 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 of a similar product;
c. Information which reveals cost or price information, production capacities, budget levels, or commercial strategies of General Electric, its customers, or its suppliers; ,

Affidavit Page 1 l

' L

d. Information which reveals aspects of past, present, or future General -

Electric customer-funded development plans and programs, of potential commercial value to General Electric;  ;

e. Informatian which discloses patentable subject matter for which it may  :

be desirable to obtain patent protection.

The information sought to be withheld is considered to be proprietary for the reasons set forth in both paragraphs (4)a. and (4)b., above The information sought to be withheld is being submitted to NRC in (5) .

confidence. The information is of a sort customarily held in confidence by GE, and is in fact so held. Its initial designation as proarietary information, and the subsequent steps taken to prevent its unauthonzet disclosure, are as set forth in (6) and (7) following. T he information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GE, no pubhc disclosure has been made, and it is not available in public sources. All  :

disclosures to third parties including any required transmittals to NRC, have e been made, or must be made, pursuant to regulatory provisions or proprietary ,

agreements which provide for maintenance of the information in confidence.

(6) Initial approval of proprietary treatment of a document is made by the manager of the on,ginating com nonent, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge.

Access to such documents within GE is limited on a "need to know" basis.

(7) The procedure for approval of external release of such a document typically 1 requires review by the staff manager, project manager, principal scientist or i other ec uivalent authority, by the manager of the cognizant marketing function  !

(or his c elegate), and by the Legal Operation, for technical content,~

competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GE are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, ,

and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.

1 (8) The information identified in paragraph (2) is classified as proprietary because it contains details of the methods development and supportmg data and  ;

analyses, including test data and modeling, relative to the TRACG computer program. This program is intended for use as the licensing-basis code for evaluating BWR response to transients, loss-of-coolant accidents, reactivity insertion accidents, and anticipated transients without scram. This code has j been under development b,y GE for over ten years, at a total cost in excess of $3 million. This information is considered to be proprietary for the reasons set i forth in both paragraphs 4.a and 4.b, on the previous page.

The development and performance of the test program was achieved at a significant cost, on the order of several million dollars, to GE.

J Affidant Page 2

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~ -- - - - - -.

. l (9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GE's competitive position and foreclose or reduce the availability of profit-making opportumties. The information is part of GE's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost. The value of the technology 1 base goes beyond the extensive physical database and analytical methodology and includes the value derived from providing analyses done with NRC-approved methods.

The research, development, engineering, analytical, and NRC review costs comprise a substantial investment of time and money by GE and its associate.

The precise value of the exaertise to devise an evaluation process and apply the' correct analytical methodol ogy is difficult to quantify, but it clearly is

  • substantial.

GE's competitive advantage will be lost ifits competitors are able to use the a results of the GE experience to normalize or verify their own process or if they .

are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions- -

The value of this information to GE would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GE- '

of the opportunity to exercise its competitive advantage to seek an adequate return on their large investment in developing these very valuable analytical tools. ,

STATE OF CALIFORNIA SS COUNTY OF SANTA CLARA Joseph F. Quirk, being duly sworn, deposes and says:

t That he has read the foregoing affidavit and the matters stated therein are true and -

correct to the best of his knowledge, Executed at San Jose, California, this 2 day of [92@Q,19M P l Jo's epp F. Quirk

  • General Electric Company Subscribed and sworn before me this [ day of hdtiw( ,_1933. ,

kosAY 4 Notary Public, State of Califdtnia V

g 9 Affidavit Page 3 -

PAULA F. HUSSEY F -

N gjouny putuc - CAurce-

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SANTA CUM COUNTY py comm. expires AFR 5.1994

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RAI Number: 440.1 Question:

Describe where the four fuel lattice types in GE's May 21,1993, letter are loaded axially into each bundle type in the core (i.e., axial fuel loading inap),

GE Response:

Axial loading map attached (Figures 3.1 & 3.2 NON-proprietary)

GE Nuclear Energy

(  ; ,,,, ,,, s,_ a REV A 3.1 Nuclear Data Summary for SBWR-8x8-E378-10GZ-80M-108 i

SBWR-8xS-E378-10GZ-80M-108 -

6 00 5x8-E071-NOG-80M Metal Heavy Metal Heaq'hment Enric Mass KG lb.00 6xS-E417-1004 0-80M 4,g5 3g,4gg 4.40 15.394 4.20 15.395 3.95 21.733 3.40 15.395 2.40 7.697 0.71 14.433 Bundle Average Enrichment = 3.781 w/o 75 00 6xS-E417-SG60 '2G5.0-50M Mass of Heavy Metal = 128.53 KG Channel Thickness = 0.08 inches Pellet Outside Diameter = 0.411 inches Active Fuel Length = 108.0 inches 6 00 8xS-E071-NOG-80M Figure 3.2 SBWR High Reactivity Bundle Nuclear Design

(G, GE Nuclear Energy ,,, s,_ w, w REV A 3.2 Nuclear Data Summary for SBWR-8x8-E378-12GZ-80M-108 SBWR-8x8-E378-12G Z-80M-108

f. 00 8x8-E071-NOG-80Ni Heavy Metal Heavy Metal Enrichment Mais KG 15.00 6xS-E417-1204.0-80M 4.85 38.486 4.40 15.394 4.20 15.395 3.95 21.493 3.40 15.395 2.40 7.697 0.71 14.433 78.(Kl Bundle Average Enrichment = 3.781 w/o 6x8-E417-SG6.0'4 gig-80M Mass of Heavy Metal = 128.29 KG Channel Thicknest = 0.08 inches Pellet Outside Diameter = 0.411 inches Active Fuel Length = 108.0 inches

(. 00 6xS-E071-NOG-80M Figure 3.15 SBWR Low Reactivity Bundle Nuclear Design

- - - - ~ .

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' RAI Number: 440.2 i

Question-  !

Provide the location of each bundle type in the core (i.e., radial fuel loading map). i GE Response:

Radial loading map attached (Figures 4.7 & 4.8 NON-proprietary) ,

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. GE Nuclear Energy 23A6391 Sh. No. 61 REV A 276 - Fresh Fuel 276 - 1 Cycle Fuel P -

180 - 2 Cycle Fuel 'e, '

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i Figure 4.7.SBWR 24 Month Equilibrium Cycle Loading Map  ;

GE Nuclear Energy

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J l  : Bundle '1)pe 1 2 = Reload Batch Designator J 1 - SBWR-8x8-E378-10GZ-80M Bundle l}pe =

) ) 3 3 2 - SBWR-8xS-E378-120Z-80M 2 2 2- 2 2 F - Fresh Fuel 1 1 1 1 1 1 I 2 2 F 1 F 1 F Batch Designator - 1 - 2nd Cycle 3 3 3 1 1 1 1- 1 2 2 - 3rd Cycle 2 2 1 F 1 F 1 F 1 1 1 1 1 2 2 1 2 2 2 'l 2 F 1 F 1 F 1 F 1 F 2 1 1 1 2 2 1 2 2 2 1:

2 F 1 F 1 F 1 F 1 F 1 1 1 1 1 2 2 2 2 1 2 1 1 2 F 1 F 1 F. 1 F 1 F 1 -F 1 1 1 1 2 2 1 2 1 1 1 1 1  ;

2 F 1 F 1 F 1 F 2 2 1 F 2 M M M 1 1 1 2 2 2 2 1 1 1 1 2- 1 2 1 F 1 F 1 F 1 2 2 F 1 2 1 2 1 2 2 1 2 2 1 1 .1 1 1 1 2 1 F 1 F 1 F 1 F 1 F 1 F 1 1 1 2- 2 2 2 1 l' 1 1 2. 1 I 1 .

2 F 1 F 1 F 1 F 1 F 1 F 1- F 1 1 1 2 1 2 l' 1 1 1 -2 -1 1 1 1 2 F 1 F 1 F 2 2 1 -F 2 2 1 F 2 M M M-M M -

1 1 1 1 2 1 1 1 1 2 1 1 1 1 2 2 1 F 1 F 1 - F 'l- 2 2 F 1 2 2 1 1 2 2 2. I 1 1 'l 1 1- 1 1- 2 2 F 1 F 1 F 1 F 1 F 1 F. 1 F 1  ;

1 1 1 2 2- 1 1 2 1 1- 1 1 .1 1-2 1 F 1 F .1. F 1 F- 1 F F 1 'F 1- 1 1 2 1 1 1 1 1 2 1 2- 2 2 1 F F 2 2 2 1 1 2 2 2 1 +! 2 2 2 1 l

1 Figure 4.8 SBWR 24 Month Equilibrium Cycle Loading Map l

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i RAl Number: 440.3 Question:

Provide the SD Exposure (Ex) and Void History (VH) distributions at beginning oflife, middle oflife, and end oflife for the equilibrium core. If these cross sections are not

  • for the equilibrium core, provide a discussion of their origin and purpose.

GE Response:

1 This information is PROPRIETARY and required a specific calculation with the SD core simulator (PANACEA). The attached TK50 tape is in VMS BACKUP format and provides the requested data. The file cycle.Ing is a PANACEA output edit, giving the 3-D exposure and void history distributions at 13 exposure points during the equilibrium cycle. The data is tabulated for each (IJ) hundle location, with a row entry for each axial node K.

The 3D exposure distribution is EXPOSURE (METRIC).

The void history distribution information is contained in -IllSTORY DEPENDENT RELATIVE WATER DENSITY which is an exposure weighted water.

It's computed as:

Integral of Relative Water density over exposure increments Integrated exposure The relative water density is the density relative to .7375 gm/cc.

An example of these edits is:

100351 0 OLP02 B0C CYCLE 10 092193 10.634 CASE 2 PAGE 27 0 HISTORY DEPDTDDrf RELATIVE WATER EDISITY OJ = 1 OR\1 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15  ;

18 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.5N16 0.5560 0.5481 0,5505 0.6051 17 0 0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0,0000 0.0000 0.5861 0.5600 0.5532 0.5556 0.6110 16 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.5939 0.5669 0.5605 0.5644 0.6188 15 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.6045 0.5761 0.5694 0.575R 0.6296 14 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.6173 0 5874 0.5f13 0.5896 0.6438 13 0.0000 0.0000 0.0000 0.0000 0.0000 0 ^000 0.0000 0.0000 0.0000 0.0000 0.6321 0.6008 0.5943 0.6052 0.6591 12 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.6495 D.6167 0.6094' O.6211 0.6776 11 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.6691 0.6352 0.6271 0.6437 0.6984 10 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.6934 0.6571 0.6481 0.6615 0.7225 9 0,0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 -0.7215 0.6832 0.6731 0.6955 0.7503 8 0.0000 0.0000 0.0000 0.0000 0.0000 0.D000 0.0000 0.0000 0.0000 0.0000 0.7546 0.?141 0.7028 0.7289 0.7826 1 0.0000 0.0000 0.0000 0,0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.'946 0.7530 0.7386 0.7691 0.8199 6 0,0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.9417 0.8003 0.7822 '0.8176 0.8630 5 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.8957 0.8579 0.8155 0.8749 0.9118 4 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 .0.0000 0.0000 0.0000 0.0000 0.9516 0.9232 0.9002 0.9366 0.9611 3 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0 0000 0.0000 0.0000 0,9992 0.9856 0.9685 0.9929 1.0024 2 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 1.0193 1.0175 1.0144 1.0185 1,0196 1 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 1.0227 1,0225 1.0223 1,0226 1.0227 100351 0 (RP02 EOC CYCLE 10 092193 10.701 Cast 16 FAGE- SS 0 EXPOSUkE (HETRIC) 03 a 1 OKi! 1 2 . 3 4 5 6 7 8 9 1D 11 12 13 14 15 18 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 00 0.0 6876.0 7840.1 8566.4 10129.2 9093.0 17 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 00 0.0 19953.0 22111.1 23834.2 27494.5 25824.4 16 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 26365.6 28997.8 30946.5 34972.4 33550.1 15 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0~0 0.0 30766.2 33756.2 35827.5 39300.5 30700.7 14 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 32780.1 36025.7 38142.0 40485.3 41150.0 13 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 34518.1 37978.9 40033.1 41323.9 43092.6

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12 . 0.0 0.0 0.0 - 0. 0 0.0 0.0 0.0 0.0 'O0 0.0 35958.1 39617.9 41592.3 42067.4 44646.5 11 0.0 ' O.0 0.0 0.0 0.0 0.0- 0.0 0.0 0.0 . 0.0 37173.4 41024.9 42916.4 42753.3 45911.7 10 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 38237.7 42289.0 44094.8 43391.8 46977.6 9 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0. 0 - 0.0 19191.6 43455.2 45172.3 43991.6 47s91.8 8 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0,0 0.0 40039.0 44541.4 46156.0 44546.9 48660.9 7 0.0 0.0 D.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 40740.5 45520.6 47036.2 45019.5 49244.3 6 0.0 0.0 - 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 41179.2 46285.7 47640.7 45300.2 49518.7 5 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 41097.0 46582.1 47777.3 45130.9 49220.9 4 0.0 0.0 0.0 0.0 0.0 0.0 - 0.0 0.0 0.0 0.0 39843.4 45711.5 46833.0 43884.9 47679.8

- 3 0.0 0.0 0.0 0.0 0.0 0.0 0.D 0.0 0.0 0.0 36039.1 42070.6 43273.8 40133.7 43400,7 2 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 . 0.0 27484.8 32835.8 34324.9 31302.8 33795.6 1 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 7586.9 9284.7 9895.1 8807.2 9537.1

- - .. . . ._. . . . ~ . - - .

1

)

RAI Numl$er: 440.4 Question:

Provide another set of cross sections for the moderator at another temperature to establish its effect on the nuclear parameters.

GE Response:

This information is PROPRIETARY and required specific calculations with the 3-D i core simulator (PANACEA). The attached TK50 tape is in VMS BACKUP format and I provides the requested data. The attached letter (R.M.Fawcett to Wayne Marquino 22.  !

September-1993 describes the files on the tape related to this RAI.) R RAI Number: 440.5  ;

Question:

For each lattice type, provide the variation in relative power required to determine the elTect of xenon on the nuclear parameters.

l GE Response: j

-l' This information is PROPRIETARY and required specific calculations with the 3-D core simulator (PANACEA). The attached TK50 tape is in VMS IIACKUP format and i provides the requested data. The attached letter (R.M.Fawcett to Wayne Marquino 22- l September-1993 describes the files on the tape related to this RAI.) ]

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%s GE Nuclocr Enargy GE Company Proprietary GeneralElectric Company 175 Curtner Ave. MIC 151 San Jose, CA 95125 September 22,1993 cc S. R Congdon TO: wayne Marquino FROM: R. M. Fawcett

SUBJECT:

SBWR Core Data Transmittal This letter is to transmit the SBWR core and fuel data requested by NRC. All requested data can be found on the following directory, VAX3:: DISK 06:[MARQUINO.RAMONA).

The PANACEA 3-D cxposure and void history data are contained on file, CYCL.E. LNG.

Infinite lattice calculations were performed using TGBLA for each lattice in the SBWR equi-librium core design at several cold temperatures for each standard void history. The tempera-tures utilized were 100 C,160 C,220 C and 286 C ( hot standby). The TGBLA output file names are structured as, latid_cccCDv.SHT, where, latid = lattice I.D. such as SE110 ccc = temperature such as 160 v = void history at which isotopics were accumulated.

Infinite lattice calculations were also performed to determine the effect of xenon on the nu-clear group constants. These calculations were performed at 3 power densities ( 25%,50%

and 75% of the average SBWR power density ) at a void history of 40%. The following expo-sure points were analyzed, 200 mwd /st 5000 MWD /st 10000 mwd /st 15000 mwd /st 25000 mwd /st 35000 mwd /st 55000 mwd /st.

t

I GE Nucloor Enorgy ff GE Company Proprietary \

l For cach exposure point,3 TGBLA calculations were performed at the desired power density, where a small amount of exposure was accumulated so that equilibrium xenon concentrations i at the desired power density could be attained. The third case at each exposure point should he representative of an equilibrium xenon concentration state. The TGBLA output file names are structured as, latid_xxP.SIIT wherc ,

1 latid = lattice I.D. l xx = percent of average power density.

If there are any questions, please contact me.

J ' Tf ,, . e g R. M. Fawcett Core and Fuel Advanced Design x1087, m/c 151 l

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, Sbb: ' List of files on tape for RAI .j

- Listing of save set (s)

Save set: RAI440.SAV Written by: FS0186 ]

. UIC; Date:

[000030,000001) 19-OCT-1993 08:24:08.00 j

1 Command: BACKUP / LOG DISK 06:[MARQUINO.RAMONA...] RAI440..SAV/SAV -l Operating system: VAX/VMS version V5.5 BACKUP version: V5.5-2 CPU ID register: 13000202  ;

Node name: _VAX3:: 1 Written on: _$6$DIA76: l 32256 Block size:

Group size: 10 Buffer count: 121-

[MARQUINO.RAMONA] CYCLE. LNG;1- 9797 21-SEP-1993 's 10:37

[MARQUINO.RAMONA}SE100CDO.SHT;l 1077 7-SEP-1993 .)

11:44 q

[MARQUINO.RAMONA}SE100CD4.SHT;1 1077 7-SEP-1993 1 11:49 R

[MARQUINO.RAMONA]SE100CD7.SHT;l 1077 7-SEP-1993 1 11:52 I

[MARQUINO.RAMONA]SE100HCO.SHT;1 462 7-SEP-1993 11:21

[MARQUINO.RAMONA}SE100HC4.SHT;1 462 '7-SEP-1993 ,

11:27 l

[MARQUINO.RAMONA]SE100HC7 SHT;1 462 7-SEP-1993 .j 11:28 I

[MARQUINO.RAMONA]SE100HDO.SHT;l

364 7-SEP-1993 11:35

[MARQUINO.RAMONA]SE100HD4.SHT;1 364 7-SEP-1993 11:42

[MARQUINO. RAMONA] SE100HD7. SHT;1 364 7-SEP-1993.

11:43

[MARQUINO.RAMONAlSE100HUO.SHT;1 855 7-SEP-1993~

10:35

[MARQUINO.RAMONA]SE100HU4,SHT;1 855 7-SEP-1993 10:39

[MARQUINO.RAMONA}SE100HU7.SHT;l 855 7-SEP-1993 10:40

[MARQUINO.RAMONA)SE100IVO.SHT;l 738 7-SEP-1993 11:29

- [ MARQUINO. RAMONA) SE100IV7. SHT;1 738 7-SEP-1993

= 11:33

[MARQUINO.RAMONA]SE100_00P.SHT;1 928 23-SEP-1993 09:14-

[MARQUINO.RAMONA]SE100_100CDO.SHT;1 1077- 21-SEP-1993.

08:25 i

[MARQUINO.RAMONA]SE100_100CD4.SHT;1 1077 21-SEP-1993  ;

08:26 {

25-Oct-93 BusinessTalk 2000:ROSS.KM J1854 EXT. 1287 'Page 1

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,8 3- [MARQUINO.RAMONA]SE100_100CD7.SHT;1' 1077' 21-SEP-1993

, 08':26 j

[MARQUINO.RAMONA]SE100_160CDO.SHT;l 1077. 21-SEP-1993 08:26'

[MARQUINO.RAMONA]SE100_160CD4.SHT;1 1077- 21-SEP-1993 08:26

[MARQUINO.RAMONA]SE100_160CD7.SHT;l 1077 21-SEP-1993 08:26

[MARQUINO.RAMONA]SE100_220CDO.SHT;l 1077 21-SEP-1993 08:26

[MARQUINO.RAMONA]SE100_220CD4.SHT;1 1077 21-SEP-1993 08:26 l

[MARQUINO.RAMONA]SE100_220CD7.SHT;1 1077 21-SEP-1993 08:26

[MARQUINO.RAMONA]SE100_25P.SHT;l 928 23-SEP-1993' 09:00

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. Total of 95 files, 103015 blocks l End of save set 125-Oct-93 .BusinessTalk 2000:ROSS.KM J1854 EXT. 1287 Page 4 c

I bec: J. A. Beard

. R. H. Buchholz R. W. Burke, Sr. (EPRI)

S. A. Delvin D. L Foreman  !'

J. E. Leatherman E. M. Lynch '

M. Malloy (NRC)  ;

P. W. Marriott W. A. Marquino  ;

F. A. Ross (DOE) i SBWR File MC-781 -

r b

f r

.5 '

i i

k E

LTRitK 9341 b

f

)

GENucle rEn:rgy Gerem!Dectnc Compary 175 Curtner Avenue, San Jose, CA 95125 October 25,1993 MFN No.174-93 Docket STN 52-004 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Richard Borchardt, Director Standardization Project Directorate

Subject:

NRC Requests for AdditionalInformation (RAls) on the Simplilled Holling Water Reactor (SBWR) Design

Reference:

Transmittal of Requests for Additional Information (RAls) for the SBWR Design, Letter from M. Malloy to P. W. Marriott Dated August 26,1993 The reference requested additionalinformation on the SBWR Design. In fulfillment of this request, GE is submitting responses to RAls 440.1 - 440.5. The responses to RAls 440.3, .4 and .5 are proprietary. ,

Sincerely, ,

?

i

').7.0rk oject Manager ABWR Certification Program M/C 782, (408)925-6219 1.1R11K 9341

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