Letter Sequence Other |
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MONTHYEARML0210605812002-04-15015 April 2002
Steam Generator Replacement Project - Topical Report No. 24370-TR-C-002, Rigging & Heavy Load Handling
Project stage: Request
ML0220005542002-07-10010 July 2002
Unit 2 - Technical Specification (TS) Change No. 02-03, Essential Raw Cooling Water (ERCW) Operability During Movement of Heavy Loads - One Time TS Change in Support of Steam Generator Replacement Project
Project stage: Other
ML0220003142002-07-10010 July 2002
Emergency Plan Implementing Procedure (EPIP) Revision
Project stage: Request
ML0225502792002-09-0909 September 2002
Memo, Draft Questions for the Unit 1 Steam Generator Replacement Topical Reports & Associated Technical Specification Amendment
Project stage: Draft Other
ML0232201222002-11-15015 November 2002
Unit 2 - Technical Specification (TS) Change No. 02-03, Revision 1, License Amendment Request (LAR) to Support Unit 1 Generator Replacement Project
Project stage: Request
ML0232201132002-11-15015 November 2002
Units 1 and 2 - 10CFR 50.59, Changes, Tests and Experiments Summary Report
Project stage: Request
ML0234005652002-11-29029 November 2002
Summary of Meeting with TVA to Discuss Sequoyah Unit 1 Steam Generator Replacement
Project stage: Meeting
ML0233807032002-12-0404 December 2002
RAI, Unit 1 Steam Generator Replacement Topical Reports and Associated TS Amendment
Project stage: RAI
ML0316109082002-12-24024 December 2002
Rev 3 to 24370-TR-C-002-A, Sequoyah Unit 1 Steam Generator Replacement Rigging and Heavy Load Handling Topical Report, Attachment 1 Through Figure 3
Project stage: Other
ML0316108992002-12-24024 December 2002
Rev 3 to 24370-TR-C-002-A, Sequoyah Unit 1 Steam Generator Replacement Rigging and Heavy Load Handling Topical Report, Table of Contents Through Figure 1
Project stage: Other
ML0301602402003-01-15015 January 2003
Steam Generator Replacement Project - Topical Report No. 24370-TR-C-002, Rigging and Heavy Load Handling Topical Report, Response to NRC Request for Additional Information
Project stage: Response to RAI
05000328/LER-2002-004, From Sequoyah, Unit 2 Regarding Reactor Trip Resulting from Loss of a Reactor Coolant Pump2003-02-0404 February 2003
From Sequoyah, Unit 2 Regarding Reactor Trip Resulting from Loss of a Reactor Coolant Pump
Project stage: Request
ML0306509802003-02-26026 February 2003
Tech Spec Change No. 02-03, Rev 2, License Amendment Request to Support Unit 1 Steam Generator Replacement Project
Project stage: Request
ML0308502292003-03-25025 March 2003
Safety Evaluation of Topical Report No. 24370-TR-C-002, Rigging and Heavy Load Handling
Project stage: Approval
ML0314902592003-05-19019 May 2003
Accepted Version of Topical Report No. 24370-TR-C-002-A, Rigging and Heavy Load Handling
Project stage: Other
2002-07-10
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Text
Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000 May 19, 2003 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D. C. 20555 Gentlemen:
In the Matter of Tennessee Valley Authority Docket No.
SEQUOYAH NUCLEAR PLANT -
ACCEPTED VERSION OF TOPICAL REPORT NO. 24370-TR-C-002-A, "RIGGING AND HEAVY LOAD HANDLING"
Reference:
NRC letter to TVA dated March 25, 2003, Safety Evaluation of Topical Report No. 24370-TR-C-002, "Rigging and Heavy Load Handling" (TAC NO.
MB5370)
The purpose of this submittal is to provide the accepted version of the subject topical report as requested in the reference letter.
The accepted topical report now includes a copy of the reference letter, historical review information, and any original report pages that were replaced.
The "-A" has been included in the topical report number to designate NRC acceptance.
There are no commitments contained in this letter.
This letter is being sent in accordance with NRC RIS 2001-05.
If you have any questions about this change, please telephone me at (423) 843-7170 or J. D. Smith at (423) 843-6672.
and Industry Affairs Manager Enclosure
-9D30 PrciMd l recycled paper 50-327
