ML20210A623
| ML20210A623 | |
| Person / Time | |
|---|---|
| Site: | 07109271 |
| Issue date: | 07/16/1999 |
| From: | Brach E NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Quennoz S PORTLAND GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 9907220156 | |
| Download: ML20210A623 (4) | |
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'.a UNITED STATES e4. j,
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 30666 0001 July 16, 1999-Mr. Stephen M. Quennoz Trojan Site Executive 1
Trojan Nuclear Plant
' 71760 Columbia River Highway Rainier,OR 97048
SUBJECT:
AUTHORIZATION OF THE TROJAN REACTOR VESSEL PACKAGE FOR TRANSPORT
Dear Mr. Quennoz:
As requested by your application dated June 1,1999, as supplemented June 10, July 7 and July 13,1999, the proposed revisions to the Trojan Reactor Vessel Package (TRVP) SAR are approved. This letter constitutes Revision 1 of the authorization to you from William F. Kane, dated October 29,1998, for the TRVP as an approved package for shipment under the General i
License issued in 10 CFR 71.12. subject to the following conditions (changes made to the authorization are indicated by vertical lines in the margin):
- 1. The TRVP as configured for shipment must comply with the following Portland General Electric Company Drawings:
M-9257, Sheet 1, Rev.1; Sheet 2, Rev. O M-9258, Sheets 1-4, Rev.1; Sheet 5, Rev. 2; Sheets 6-8, Rev.1 1
M-9259, Sheets 1-2, Rev. 3; Sheet 3, Rev. 2; Sheet 4, Rev. 0; Sheet 5, Rev. 2; I
Sheets 6-7, Rev. 3 1
M 9260, Sheets 1-7, Rev. 3; Sheet 8, Rev. 0; Sheet 9, Rev. 3; Sheet 10, Rev. 4.
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- 2. The TRVP must be transported in compliance with the specific exemption issued by the U.S. Department of Transportation (DOT).
- 3. The TRVP must be transported in accordance with Portland General Electric Company's Transportation Safety Plan for the Reactor Vessel and Internals Removal Project, PGE-1077, Rev.1.
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- 4. The TRVP must be prepared for shipment and operated in accordance with Sections 7.0 and 8.0 of the application dated March 31,1997, as supplemented on August 8, August 13, and September 23,1998.
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Please note that this authorization does not relieve the shipper from compliance with any requirements in DOT's regulations in Title 49, unless those requirements are specifically waived by DOT exemption referenced in Condition 2. This amendment expires in December 2000.
Sincerely, ORIGINAL SIGNED BY /s/
E. William Brach, Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Docket Nos.: 71-9271; 50-344
Enclosure:
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APPROVAL RECORD Trojan Reactor Vessel Package (TRVP)
Revision No.1 By application dated June 1,1999, as supplemented on June 10, July 7 and July 13,1999, 1
Portland General Electric Company (PGE) requested amendment of the letter authorization from William F. Kane, dated October 29,1998, for the one-time shipment of the TRVP for disposal. PGE provided revised drawings for the TRVP SAR, revised text for Sections 1 and 7 of the SAR, and a revised Transportation Safety Plan for the Reactor Vessel and Internals Removal Project.
The applicant prov!ded revised drawings that reflect the additional nozzle shielding, revised vessel shielding welds, and revised impact limiter attachments that were required during field fit-up. The drawings show the final, as-built, TRVP configuration. PGE also proposed revisions of SAR Sections 1 and 7 to reflect that the land route to be used for the TRVP at the US Ecology disposal facility near Richland, Washington, is similar, not identical, to that used for the Trojan pressurizer and four steam generators. Finally, PGE provided a proposed revision to the Transportation Safety Plan for the Reactor Vessel and Internals Removal Project, PGE-1077, Revision 1 to reflect changes in transportation arrangement details.
Staff has reviewed the requests and concluded that the proposed revisions will not have any adverse effects on the structuralintegrity of the package and that the original shielding evaluation is still valid. Further, a PGE radiation level survey of the as-built TRVP shows that the maximum radiation levels meet applicable U.S. Nuclear Regulatory Commission and DOT limits. The applicant has shown and the staff agrees that the package meets the applicable requirements of 10 CFR Part 71, as exempted.
E. William Brach, Director Spent Fuel Project Office Office of Nuclear Materials Safety and Safeguards
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