ML023290195

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Submittal of Additional Pages to the Safety Analysis Report for the Model No. TN-FSV Packaging, Related to Failure of Tie-Down Devices Under Excessive Load
ML023290195
Person / Time
Site: Fort Saint Vrain, 07109253  Xcel Energy icon.png
Issue date: 06/14/1994
From: Warembourg D
Public Service Co of Colorado
To: Chappell C
NRC/NMSS/IMNS
References
-RFPFR, P-94056 NUDOCS 9406230094
Download: ML023290195 (3)


Text

Public Service Company of Colorado SPublic Service 16805 WCR 19 1/2; Platteville, Colorado 80651 June 14, 1994 Fort St. Vrain ISFSI P-94056 Mr. Cass R. Chappell, Section Leader Cask Certification Section Storage and Transport Systems Branch Division of Industrial and Medical Nuclear Safety, NMSS U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket No. 71-9253

SUBJECT:

Revision to the Safety Analysis Report for the Model No.

TN-FSV Packaging, Related to Failure of Tie-down Devices Under Excessive Load

REFERENCE:

PSC Letter, Warembourg to MacDonald, dated March 31, 1993 (P-93033)

Dear Mr. Chappell:

Public Service Company of Colorado (PSC) submitted an application for Certification of a New Irradiated Fuel Transport Package for Fort St. Vrain, Model No. TN-FSV, in the referenced letter. This application included the Safety Analysis Report (SAR) for the TN FSV Packaging. In a phone conversation between Ms. Nancy Osgood (NRC) and Mr. Mike Mason (Transnuclear, Inc.) dated June 9, 1994, the NRC pointed out that the SAR for the TN-FSV Packaging does not address the requirement in 10 CFR 71.45(b) (3), which states: "Each tie-down device which is a structural part of a package must be designed so that failure of the device under excessive load would not impair the ability of the package to meet other requirements of this part."

9406230094 940614 PDR ADOCK 07109253 C PDR

P-94056 June 14, 1994 Page 2 The purpose of this letter is to submit an additional page to the TN-FSV SAR which explicitly addresses the above requirement of 10 CFR 71.45(b)(3). The Attachment to this letter contains the new page 2-32a, to be inserted into the previously submitted SAR.

Should you have any questions on this information, please contact Mr. M. H. Holmes at (303) 620-1701.

Sincerely, D. W. Warembourg Decommissioning Program Director and ISFSI Manager DWW/JRJ Attachment cc: Regional Administrator, Region IV Mr. Robert M. Quillin, Director Radiation Control Division Colorado Department of Health

P-94056 June 14, 1994 Attachment NEW PAGE TO THE SAFETY ANALYSIS REPORT FOR THE TN-FSV IRRADIATED FUEL SHIPPING PACKAGING