ML20210A640

Corrects Ref in Item 4 of Which Constitutes Rev 2 of Authorization from Wf Kane, for Trojan Reactor Vessel Package as Approved Package for Shipment Under General License,Subj to Listed Conditions

ML20210A640
Person / Time
Site:	07109271, Trojan  File:Portland General Electric icon.png
Issue date:	07/19/1999
From:	Brach E NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Quennoz S PORTLAND GENERAL ELECTRIC CO.
References
NUDOCS 9907220164
Download: ML20210A640 (2)

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'4 e i UNITED STATES r

[ j NUCLEAR REGULATORY COMMISSION gi e wAswiwoTow, p.c. sones ooo1

% ,,,,, # July 19, 1999 l

- Mr. Stephen M. Quennoz Trojan Site Executive Trojan Nuclear Plant 2 71760 Columbia River Highway '

Rainier, OR 97048 1

SUBJECT:

AUTHORIZATION OF THE TROJAN REACTOR VESSEL PACKAGE l FOR TRANSPORT  !

Dear Mr. Quennoz:

I am writing to correct a reference in item 4. of my letter to you dated July 16,1999. This letter constitutes Revision 2 of the authorization to you from William F. Kane, dated October 29, 1998, for the Trojan Reactor Vessel Package (TRVP) as an approved package for shipment under the General License issued in 10 CFR 71.12, subject to the following conditions (changes made to Revision 1 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 M 9259, Sheets 1-2, Rev. 3: Sheet 3, Rev. 2; Sheet 4, Rev. 0; Sheet 5, Rev. 2; Sheets 6-7, Rev. 3 M-9260, Sheets 1-7, Rev. 3; Sheet 8, Rev. 0; Sheet 9, Rev. 3; Sheet 10, Rev. 4.

2. The TRVP must be transported in compliance with the specific exemption issued by the U.S. Department of Transportation (DOT). l

3. The TRVP must be transported in accordance with Portland General Electric ,

l Company's Transportation Safety Plan for the Reactor Vessel and Internals Removal Project, PGE-1077, Rev.1.

4. The TRVP must be prepared for shipment and operated in accordance with ,

Sections 7.0 and 8.0 of Portland General Electric Company's Safety Analysis l I Report for Reactor Vessel Package, PGE-1076, Rev.1. I j i

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l Please note that this authorization does not relieve the shipper from compliance with any 3-requirements in DOT's regulations in Title 49, unless those requirements are specifically waived t

by DOT exemption referenced in Condition 2. This amendment expires in December 2000.

Sincerely, l

E. William Brach, Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Docket Nos.: 50-344;71-9271 cc w/ encl: R. W. Boyle, Department of Transportation l Distribution:

NRC File Center PUBLIC NMSS r/f SFPO r/f Docket 719271 SWeiss DRathbun, OCA TJohnson, DWM LKokajko I

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l NAME: C d HLee  ! EKeegqh EEash DATE: Tff99 / /99 N / /99 7/f{99 )//f99  !

OFC: SFPO SFPpgg / SFPA NAME: MWHodges ,p SShknh Edkach DATE: 7/$99f h99 )/h99 N = NO COPY C = COVER E = COVER l ENCLOSURE OFFICIAL RECORD COPY l

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