ML18150A083
| ML18150A083 | |
| Person / Time | |
|---|---|
| Site: | Surry, 07200002  |
| Issue date: | 05/01/1987 |
| From: | Cunningham R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Barnhart V GENERAL NUCLEAR SYSTEMS, INC. |
| References | |
| REF-PROJ-M-37 NUDOCS 8705070053 | |
| Download: ML18150A083 (3) | |
Text
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Project M-37 General Nuclear Systr.ms, Inc.
ATTN:
Mr. Victor J. Barnhart President 220 Stoneridge Drive Columbia, SC 29210 Gentlemen:
MAY
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Subject:
REQUEST FOR WITHHOLDING INFORMATION FROM PUBLIC DISCLOSURE By your suhmittals and affidavits dated January 18, 1984, January 28, 1985, January 31, 1986, March 25, 1986, August 15, 1986, September 30, 1986, and February 5, 1987, you submitted the docu~ents listed below and requested that they ~e withheld from public disclosure pursuant to 10 CFR ?.790.
The documents you reouested to be withheld include:
- 1.
Appendices 3, 5, 6, and 12 of Revision O of the Topical Safety Analysis Report for the CASTOR V Cask Independent Spent Fuel Storage Installation (Dry Storage) rAppendix 3, "CASTOR Cask Pressure Gauge Behavior During Storage Operation," GNS B119/82; Appendix 5, "Opinion Based on an Assessment of the Cast Material GGG 40 As to Its Suitability for CASTOR Shipping ard Storage Casks, 11 BAM 1.2-H.A. 1.02/3022-T.A. 1.20/1:?521, March 14, 1982; Appendix 6, "Fracture Toughness Ev-aluation of Nodular-Graphite Cast Iron for Nuclear Shipping Cask Applications," October 198?.; and Appendix 12, "Assessrnf>nt of Cask-Specific Questions on Dry Interirn Storage of Spent Fuel Assemblies in a Shipping Cask Storage Site at AHAUS," BAM Opinion, File No. 1.02/3023, November 1982].
?.
Appendices 1, 3, and 6 of Revision of Topical Safety Analysis Report for the CASTOR V/21 Cask Independent Spent Fuel s~orage Installation (Dry Storage) [Appendix 1, hParts List and Compilation of Drawings for the CASTOR V/21 Shipping and StoragP Cask;" Appendix 3, "Material Specifica-tions for - Cask body (RS 04) - Fuel Basket (BS 05) - Trunnions, Lids and Bolts for Lids (BS 06) - Bolts (BS 07); and Appendix 6, "Calculation of Fuel - Rod Temperatures in the CASTOR V/21 Cask."]
- 3.
By letter, cask basket design information:
8525.106-544 Revision a Rasket CASTOR V/21, Welding Plan; A500.ll-15, Revision d Basket CASTOR V/21 VEPCO; and A500.ll-15/2 Revision 5 Basket Parts List.
- 4.
By letter, cask basket design information:
GNS Drawing AS00.11-15 (Draft) CASTOR V/21 Basket; GNS Drawing B525.106-544 (Draft) CASTOR V/?l Pasket Welding Plan.
8705070053 870501 PDR ADOCK 05000280 p
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General Nuclear Systems, Inc.
MAY 11987
- 5.
Ry letter, cask basket desi9n information:
(1) Material Specification for Radionox A-18 (X2 Cr Ni B 1911) Used for Dry Spent Fuel Storage Cask CASTOR V/21 Fuel Basket.
Specification BS 05, Rev. 1, July 1986.
(TSAR Appendix 3); (2) Summary of Basket Dimension Measurement Technique.
(TSAR Appendix 8); and (3) Material Evaluation Report for CASTOR V/21 Basket Material, August :J86.
- 6.
By letter, cask basket design information:
GNS Drawing A500.ll-15, Basket CASTOR V/21 VEPCO; and GNS Drawing 8525.106-544 CASTOR V/21 Basket Welding Plan.
- 7.
By letter, cask basket design information:
(1) Appendix to the GNSI Response to NRC Comments en CASTOR V Basket Analysis, January 1987; (2)
Material Evaluation Report for CASTOR V/21 Basket Material, Rev. 1, January 1987; (3) Material Specification for Radionox A-18 (X2 Cr Ni R 1911) Used for Dry Spent Fuel Storage Cask CASTOR V/21 Fuel Basket.
Specification ~S 05, Rev. 2, January 1987.
(TSAR Appendix 3); ard (4)
Summary 0f Basket Dimension Measurement Technique.
(TSAR Appendix 8).
Your reasons for requesting our withholding of this information were set forth in the affidavits citin~ 10 CFR 2.790(b)(4) regarding the confidentiality in which this information washed and the competitive position and Pconomic damage that could result from its release. Also, you cited 10 CFR 2.790(d)(2) with respect to documents required to be withheld because they reflected licensing activities by German licensing authorities. Subsequently, Appendix 12 of Revision O of your topical report was declassified. Accordingly, Appendix 12 has been released to the public and is available in the NRC Public Document R00m under this docket.
We have reviewed your submittals and ~~terial based on the requirements and criteria of 10 CFR 2.790 and have detPrmined that the above-mentioned documents, except Appendix 12, cited above, sought to be withheld contain trade secrets or confidential or prcprietary commercial or financial information.
We also have found at this time that the right of the public to be fully appraised as to the bases for and effect~ of the proposed action does not outwei~h the demonstrated concern for protection of your competitive position.
Accordi11gly, we have determined that the infomation should be withheld from public disclosure.
We therefore approve your request for withholding pursuant to Ser.tion 2.790 of 10 CFR Part 2 and are withholding the docu~ents listed and described above from public inspection as proprietary.
Withholding from public inspection shall not affect thP. right, if any, of persons pr0perly and directly concerned to inspect the documents.
If the need arises, we may send copies of this information t0 our consultants working in this area.
General Nuclear Systems, Inc.
3 MAY 1 1987 If the basis for withholding this information from public inspection should change in the future such that the information could then be made available for public inspection, you should promptly notify the NRC.
OISTRIBUTION Please return original concurrence copy to FBrown SS396
/ Pro.iect M-37
~/F FCIF R/F LCRouse
,JRobert5 FSturz EShomaker, OGC JSchneider nmrach OSP1ith JGray CPa tel FBrown DWeiss PDR & LPDR Docket Tl-?.
(50-260/26])
WHollar.d, RII MYoung, OGC bee:
MSchwartz MSmith, VEPCO Sincerely, Original Signed by
>Richard E:. Cunningham Richard E. Cunningham, Director Division of Fuel Cycle, Medical, Academic, and Co1TJ11erci al l1se Sa fr.ty
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