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Category:Letter
MONTHYEARML24158A6282024-06-0707 June 2024 Transmittal Letter for Certificate of Compliance No. 9253, Revision 15, for the Model No. TN-FSV Transportation Package and the Safety Evaluation Report ML24106A0832024-04-15015 April 2024 The U.S. Department of Energy (DOE) Requests Renewal of NRC Certificate of Compliance (CoC) Number 9253, for Model TN-FSV, Docket 71-9253 ML13228A3992013-08-12012 August 2013 Letter to Holders of Independent Spent Fuel Storage Installation (ISFSI) Licenses Re Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit - Rin 3150-AI64 (NRC-2009-0163) EA-02-109 ML12359A0312012-12-11011 December 2012 Ft. St. Vrain, Three Mile Island, Unit 2, and Idaho Spent Fuel Facility NRC Licenses - Notification of Facility Director Change ML11165A2192011-06-0606 June 2011 Us Dept. of Energy Submittal of Fort St. Vrain Independent Spent Fuel Storage Installation Safety Analysis Report Update (Docket 72-09) (EM-FMDP-11-062) ML1105507092011-02-16016 February 2011 D. Diaz-Toro Ltr. Ft. St. Vrain Independent Fuel Storage Installation Proposed License Renewal ML1031405702010-11-24024 November 2010 Letter to Governor Marcelino Aguino Initiation of Section 106 Process for Environmental Review of Fort St. Vrain Independent Spent Fuel Storage Installation Proposed License Renewal ML0823901062008-08-25025 August 2008 Notification of Potential Part 21 on Failure of F and G Switches ML0714104442007-05-29029 May 2007 5/29/07 Ltr E. Sellers, DOE-Idaho Operations, Fort Saint Vrain Issuance of Order Imposing Fingerprinting and Criminal History Check Requirements for Unescorted Access to Fort Saint Vrain Power Station Independent Spent Fuel Storage Installa ML0232901771995-12-0707 December 1995 Letter Responding to Requesting for License Amendment to Permit Certain Radioactive Materials at Fsv Ispsi ML0232901671995-12-0707 December 1995 Letter Responding to Request for Additional Information Regarding License Amendment to Permit Certain Radioactive Materials at Fsv ISFSI ML0232901951994-06-14014 June 1994 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 ML0232902091994-06-0202 June 1994 Letter Submitting Revised Pages to the Safety Analysis Report for Model No. TN-FSV Packaging, Related to Pressure Rise Leakage Tests ML0635306621994-02-24024 February 1994 Letter Submitting Response to Nrc'S Request for Additional Information Regarding Model No. TN-FSV Packaging ML0232901221993-03-31031 March 1993 Request for Certification of New Irradiated Fuel Transport Package for Fort St. Vrain Model No. TN-FSV ML0233007231982-03-0909 March 1982 Confirmation of Intent to Delete References to U-233 in Greater than 200 Times a Type a Quantity as Authorized Content & to Transmit Renewal Fee ML1008202791972-01-20020 January 1972 Fort St. Vrain Safety Evaluation Report, January 20, 1972 2024-06-07
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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