ML20046C587
| ML20046C587 | |
| Person / Time | |
|---|---|
| Site: | 05200004 |
| Issue date: | 07/21/1993 |
| From: | Joshua Wilson Office of Nuclear Reactor Regulation |
| To: | Marriott P GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 9308110187 | |
| Download: ML20046C587 (4) | |
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July 21, 1993 Docket No.52-004 l
Mr. Patrick W. Marriott, Manager
-Licensing & Consulting Services i
GE Nuclear Energy 175 Curtner Avenue j
San Jose, California 95125
Dear Mr. Marriott:
SUBJECT:
REPRODUCTION OF PROPRIETARY INFORMATION RELATING TO THE SIMPLIFIED B0ILING WATER REACTOR (SBWR) DESIGN In discussions during the week of July 12, 1993, with Mr. David Foreman of GE Nuclear Energy (GE), Ms. Melinda Malloy of my staff informed GE of the U.S.
Nuclear Regulatory Commission's (NRC's) need to reproduce and transfer certain I
proprietary documents relating to the SBWR between NRC technical assistance contractors.
The NRC is in the process of transferring some of its technical assistance work on the SBWR / rom the Idaho National Engineering Laboratory (INEL) to Brookhaven National Laboratory (BNL) and has found that INEL needs to retain certain GE docume1ts in order to complete work for NRC.
- However, BNL also needs to refer to these documents to initiate work. To facilitate this document transfer. Ms. Malloy proposed that GE permit INEL to copy these documents and forward them to BNL.
Enclosed is a listing of 39 proprietary SBWR-related documents in INEL's possession.
Each of the documents is listed by author (if identified), title (or short description if a title is not apparent), and date (where available).
The last column of the table indicates which documents need to be copied and sent to BNL.
Unless you indicate otherwise to us by July 30, 1993, we will instruct INEL to proceed to copy the indicated documents for BNL, assuming these arrangements are acceptable to you.
Should you have any questions concerning this matter, please contact one of
(
the project managers assigned to this review, Melinda Malloy at (301) 504-1178, or Son Ninh at (301) 504-1125.
Sincerely, OAtet R'oned F Jerry N: Wifson, Acting Project Director
'i Standardization Project Directorate Associate Directorate for Advanced Reactors 9308110187 930721 PDR ADDCK 05200004 and License Renewal A
PDR Office of Nuclear Reactor Regulation 1
Enclosure:
As stated cc w/ enclosure:
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I p_IJTRIBUTION:
gb Docket File PDST R/F DCrutchfield JNWilson SNinh PDR RBorchardt MMalloy PShea-
.y DMcPherson, BE2 RBarrett, 8H7 Tlee, NLN353 JMoore, 15B18
.cp RElliott, 8H7 WMinners/TKing, NL5007 LShotkin, NLN353 ACRS (11)
AGody,Jr., 17G21 MFinkelstein, 15B18 AThadani/M rgilio,)
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LA:PDST:ADAR -# M AR PfpPDST:ADAR SC: POST:ADAR Jfi)d:PST:ADAR (A
Q NAME: PSheg g MMalloy:tz St% b RBorchardt son DATE: 07/}/93 07/p//93 07/14/93 07/4/93 07/2/ /93 d1 jh DOCUMENT AME: SBWR9313.MM
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Mr. Patrick W. Marriott Docket No.52-004
.i I
General Electric Company cc:
Mr. Laurence S. Gifford GE Nuclear Energy 12300 Twinbrook Parkway Suite 315 Rockville, Maryland 20852 Director, Criteria & Standards Division Office of Radiation Programs U.S. Environmental Protection Agency 401 M Street, S.W.
Washington, D.C.
20460 Mr. Sterling Franks U.S. Department of Energy NE-42 Washington, D.C.
20585 Mr. Jeffrey C. Baechler GE Nuclear Energy 175 Curtner Avenue, MC-782 San Jose, California 95125 Mr. Frank A. Ross Program Manager, ALWR Office of LWR Safety & Technology U.S. Department of Energy NE-42 19901 Germantown Road Germantown, Maryland 20874 Mr. Richard Schultz Idaho National Engineering Laboratory P.O. Box 1625 Mailstop 3895 Idaho Falls, Idaho 83415-3895 Mr. G. Slovik Brookhaven National Laboratories Building 475B Upton, New York 11973
List of SBWR Proprietary Inforrnation in the Possession of the INEL Needed No.
Author Title or Description Date by BNL 1
C3. Fletcher Penonal design notes from Apr.16N1 meetmg.
4/16N1 2
R.L. Huang SSWR Design Overview, presentation.
4/16/91 X
3 R. L. Huang SBWR Safety Analyses, presentation.
4/16/91 X
4 Reactor System Heat balance 23A6929, rev. a, sheets 5 & 7.
5 SBWR Heat Balance.
2/27/91 i
6 Reactor Kinetics Data (point model).
X 7
Main Steamline Volume Requirements.
X 8
SI.CS Accumulator Tank Documentation Package with 23A6806 4/17/91 X
Rev. A, sheets 1-13.
9 SBWR CRD Simplified P&lD and data.
X 10 Fuel and auxiliary pools cooling system schematic and otter con-3/27/91 X
tainment cooling data.
Il RWCU, SDC system schematic and description with Ansaldo X
document SBW 5230 SNPX N 001000 Rev. O. pgs 16 21 12 Containment Volumes Based on BAR-49.
2/13/91 X
13 Control rod housing, Hitachi drawing 310Q32.
X 14 GDCS Schematic and infonnation sheet, apparently from JRP 4/1691 X
15 P. F. Bilhg ICS and PCCS presentation to NRC/INEL.
4/1631 X
16 SLCS drawing (GE) 103E1771, rev A.
X 17 SLCS drawing (GE) 103E15S8. rev A.
X 3
18 High pressure ssolation condenser, Ansaldo, X
SBW5280THDW013000, sheets 25,26 & 27.
19 Reactor assembly.Toshiba drawing OKK000104, rev A.
X i
20 Summary of automatic acniation setpoints.
X 21 Isolation Condenser Jyuem, P&lD, GE drawing 107E5154, rev.
X _
A, sh 1.
22 Isolation Condenser System. P&lD, GE drawing 107E5:54, rev.
X A. sh 2.
23 Passise Containmer.t Cooling System, GE drawing 10?E5160, X
rev. A.
24 SBWR Layout drawing, No drawing no. sheets 2,4,7 & 13-20.
25 PCCS heat exchanger, Ansaldo drawing for two PCCS design X
]
Solutions.
26 PCCS concepts investigated.
27 SBWR Desi;;n. (sipc5 c4s:!1890309: jaw is tbc number at the txatom left of each page) 28 D. M. Olantz SBWR Safety and Auxiliary Sprem Design, presentation to the 7/1/91 X
NRC DMG 07/01/91 is the number at the bottom of each page.
29 P. W. Marnott Proprietary rey
'o INEL request for inf ormation, from 4/20/92 X
P.W.Marriott (Gt.
'obert C. Pierson (Document control desk, NRCL MFN No. 0w >2. Project No. 681, $LK 9258.
30 Reference PANTHERS PCCS test matnx.
6/30/92
{ 31 P. F. Billig PANTHERS Test Program. Pre wntation to ACRS 60/92 l
Enclosure j
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List cf SBWR Proprietary Information in the Pcssession of the INEL Needed No.
Author Title or Description Date by BNL 32 5.12vy Inc.
5WR Passive Finnt Heat Removal Assessment poim EPRJ.
3/91 X
CRIEPl Advanced LWR Studies) %1ume 1, EPRI NP 7128.SI, Volume 1, Project 2660-50, Final Repon, March 1991.
33 S. Levy Inc.
BWR Passive Plant Heat Removal Assessment (Joint EPRI-3/91 x
o CRIEPl Advanced LWR Studies) Volume 2, EPRI NP-7128 S1, Volume 2. Project 2660-50, Final Repon, March 1991.
34 J.G.M. Andersen TRACO Application to BWR and SSWR, JOMA Apr 22,1992 is 4/22N2 X
st the bottom of each page.
35 J. R. Fach SB\\VR Containment Parameters, Presentation to ACRS, F:jr-6/2/92 X
f921052634tjm is at the bortom of each page.
36 LO.M. Andersen TRACO Application to SBWR Analysis Melbods and Qualifica-6/2/92 X
tion. Presemation to ACRS.
37 P. F. Billig PANTHERS Isolation Condenser and Passive Containment Cool-4/22N2 X
i ing Systems Heat Exchanger Test Program 35 INEL SBWR Calculation Notebook for the revised RELAP5/ MOD 3 5/93 X
input model.
39 GE SBWR Standard Safety Analysis Repon.
2/93 i
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