Letter Sequence Meeting |
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MONTHYEARML0220005542002-07-10010 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
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Memo, Draft Questions for the Unit 1 Steam Generator Replacement Topical Reports & Associated Technical Specification Amendment
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Unit 2 - Technical Specification (TS) Change No. 02-03, Revision 1, License Amendment Request (LAR) to Support Unit 1 Generator Replacement Project
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Summary of Meeting with TVA to Discuss Sequoyah Unit 1 Steam Generator Replacement
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RAI, Unit 1 Steam Generator Replacement Topical Reports and Associated TS Amendment
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Steam Generator Compartment Roof Modification Topical Report
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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
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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
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Steam Generator Compartment Roof Modification Topical Report
Project stage: Other
ML0300801662003-01-0808 January 2003
Summary of Meeting with TVA to Discuss the Sequoyah Unit 1 Steam Generator Compartment Roof Modifications. (MB5387)
Project stage: Meeting
ML0300905912003-01-0808 January 2003
Summary of Meeting with TVA to Discuss the Sequoyah Unit 1 Steam Generator Compartment Roof Modifications. (MB5387). Enclosure 2
Project stage: Meeting
ML0301004422003-01-10010 January 2003
Steam Generator Compartment Roof Modification Topical Report Technical Assessment
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
ML0302201402003-01-16016 January 2003
Enclosure 2, Sketch, 01/16/2003, Meeting Handout Passed Out by TVA
Project stage: Request
ML0302402482003-01-22022 January 2003
Summary of Meeting with Tennessee Valley Authority (TVA) Re Sequoyah Unit 1 Steam Generator Compartment Roof Modifications (MB5387)
Project stage: Meeting
ML0303004772003-01-30030 January 2003
Withdrawal of an Amendment Request Concerning Essential Raw Cooling Water System Operability During Heavy Load Lifts (Tac No. MB5571)
Project stage: Withdrawal
ML0305102342003-02-14014 February 2003
Steam Generator Replacement Project - Topical Report No. 24370-TR-C-003, Steam Generator Compartment Roof Modification, Revision 1.
Project stage: Other
ML0305903182003-02-25025 February 2003
Attachments to 02/12/2003 Meeting Summary - Design Summary of the Steam Generator Enclosure Roof Support Frames
Project stage: Meeting
ML0305607242003-02-25025 February 2003
Summary of February 12, 2003, Meeting with Tennessee Valley Authority to Discuss the Sequoyah, Unit 1, Steam Generator Compartment Roof Modification
Project stage: Meeting
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
ML0307103552003-02-28028 February 2003
License Amendment (SQN-TS-03-03) to Utilize Methodology Described in Topical Report No. 24370-TR-C-003, Revision 1, for Modification of Steam Generator Roof Compartment
Project stage: Other
ML0307103472003-02-28028 February 2003
License Amendment (SQN-TS-03-04) to Utilize Methodology Described in Topical Report No. 24370-TR-C-001, Alternate Rebar Splice - Bar-Lock Mechanical Splices
Project stage: Other
ML0307205802003-03-10010 March 2003
FRN - Individual 30-day Proposed, Notice of Consideration of Issuance of Amendment
Project stage: Other
ML0307306162003-03-11011 March 2003
FRN - Individual 30-day Proposed
Project stage: Other
ML0307800152003-03-11011 March 2003
Notice of Consideration of Issuance of Amendment, Regarding 03/18/02 Request for Revision to the Plant Updated Final Safety Analysis Report
Project stage: Other
ML0307202202003-03-13013 March 2003
Safety Evaluation of Topical Report No. 24370-TR-C-001, Alternate Rebar Splice-Bar-Lock Mechanical Splices.
Project stage: Approval
ML0308502292003-03-25025 March 2003
Safety Evaluation of Topical Report No. 24370-TR-C-002, Rigging and Heavy Load Handling.
Project stage: Approval
ML0310803142003-04-18018 April 2003
Safety Evaluation of TVA Topical Report No. 24370-TR-C-003, Steam Generator Compartment Roof Modification, Rev. 1
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
2003-01-30
[Table View] |
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Category:Meeting Summary
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2024-01-18
[Table view] |
Text
November 29, 2002 LICENSEE: Tennessee Valley Authority FACILITY: Sequoyah Nuclear Plant, Unit 1
SUBJECT:
SUMMARY
OF OCTOBER 24, 2002, MEETING WITH TENNESSEE VALLEY AUTHORITY TO DISCUSS THE SEQUOYAH UNIT 1 STEAM GENERATOR REPLACEMENT (TAC NOS. MB5370, MB5371, MB5387, MB5571)
On October 24, 2002, the U.S. Nuclear Regulatory Commission (NRC) staff met with representatives of Tennessee Valley Authority (TVA, the licensee) and Bechtel at the NRC Headquarters in Rockville, Maryland. This meeting was held to discuss NRC staff questions concerning the three topical reports dealing with technical issues during the Unit 1 steam generator replacement (SGR) project and a one-time technical specification (TS) change concerning essential raw cooling water (ERCW) operability for Sequoyah Nuclear Plant (SQN)
Unit 2. The meeting was classified as a Category 1, providing an opportunity for members of the public to communicate with the NRC staff after the business portion of the meeting but before the meeting was adjourned. However, there were no members of the public in attendance. Enclosure 1 is a list of attendees, and Enclosure 2 is a copy of TVAs handout distributed during the meeting.
TVA submitted three topical reports to provide the technical justification for the:
C proposed use of an alternative methodology for concrete reinforcement (rebar) rod splicing, Topical Report Number (No.) 24370-TR-C-001 [ADAMS Accession No. ML020780612]
C details regarding rigging and heavy load handling, Topical Report No. 24370-TR-C-002
[ADAMS Accession No. ML021060581] and C proposed use of through-bolted splice-plate connections for reconstruction of the SG compartment roofs, Topical Report No. 24370-TR-C-003 [ADAMS Accession No. ML020910792]
The licensee gave two presentations during the meeting summarizing the SGR efforts for the topical reports on the SG compartment roof and the heavy load handing. These presentations are included in the aforementioned licensee handout attached to this summary. In advance of the meeting, the technical staff asked clarifying questions about the licensees program for the review of the vendors quality assurance program, the use of certain industry standards, and the administrative measures to be enacted to ensure that lifts of heavy loads are conducted safely.
The licensee discussed its response to the questions included in Enclosure 2. Additionally, the licensee indicated that corrections and clarifications to Topical Report No. 24370-TR-C-002 would be provided in a pending supplement to the original topical report. As a result of the discussions, one question was clarified and the NRC staff had five additional questions. A letter transmitting the NRC staffs request for additional information will be transmitted to the licensee.
The licensee also clarified the intent of a one-time license amendment requested for SGN Unit 2. The licensee requested this amendment to allow the continued operation of Unit 2 during movement of multiple heavy loads associated with the Unit 1 SGR over the ERCW system. This system serves both units and the licensee determined that a postulated drop of a heavy load could cause a loss of function of the Unit 2 ERCW supply. As a precaution, the licensee indicated its intent to conservatively declare the system inoperable as a result of the potential damage from a heavy load drop. The licensee indicated that in the event of an actual drop of a heavy load which disabled the ERCW the existing TS would be followed. The NRC staff indicated to the licensee that, if there was no actual failure of the ERCW system, there was no need for the proposed amendment to the TS. The NRC staff indicated its intention to discuss this issue with the Technical Specification Section in the Office of Nuclear Reactor Regulation. On October 28, the NRC staff contacted Mr. Pedro Salas to reaffirm the NRC staffs position regarding the lack of a need for an ERCW TS amendment. However, the NRC staff did indicate that an amendment to the license would be required consistent with the requirements of Title 10 of the Code of Federal Regulations, Section 50.59. Mr. Salas said TVA would withdraw the TS amendment and resubmit a revised amendment to the license.
The NRC staff noted that the above meeting was beneficial in gaining an understanding of TVAs plans and activities regarding the pending SGR for SQN Unit 1.
Sincerely,
/RA/
Ronald W. Hernan, Senior Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328
Enclosures:
- 1. List of Attendees
- 2. Licensee Handouts cc w/encls: See next page
ML023400565 OFFICE PDII-2\PM PDII-2\PM PDII-2\LA PDII-2/SC NAME RHernan for EBrown RHernan BClayton AHowe DATE 11/26/02 11/26/02 11/26/02 11/27/02 Meeting Summary dated November 29, 2002 Distribution:
PUBLIC PDII-2 R/F RHernan EBrown OGC ACRS/ACNW JZwolinski/TMarsh HBerkow AHowe BClayton MKotzalas GHatchell JMa MHart SRosenberg PFredrickson, RII
ATTENDANCE LIST NUCLEAR REGULATORY COMMISSION STAFF MEETING WITH TENNESSEE VALLEY AUTHORITY AT NRC HEADQUARTERS OCTOBER 24, 2002 NRC TVA Allen Howe Pedro Salas Ronald Hernan Paul Trudel Greg Hatchett Ed Craig John Ma David Ryder Michelle Hart Richard Cutsinger Eva Brown Bechtel Rigging International Cal Reid J.P. Roberts Joseph Cowhill Myron Anderson George Thomas J. V. Smith Charles Weaver Steven Kline William Johnson ENCLOSURE 1
SEQUOYAH NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Karl W. Singer, Senior Vice President Mr. Pedro Salas, Manager Nuclear Operations Licensing and Industry Affairs Tennessee Valley Authority Sequoyah Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Soddy Daisy, TN 37379 Mr. James E. Maddox, Acting Vice President Mr. D. L. Koehl, Plant Manager Engineering & Technical Services Sequoyah Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority 6A Lookout Place P.O. Box 2000 1101 Market Street Soddy Daisy, TN 37379 Chattanooga, TN 37402-2801 Senior Resident Inspector Mr. Richard T. Purcell Sequoyah Nuclear Plant Site Vice President U.S. Nuclear Regulatory Commission Sequoyah Nuclear Plant 2600 Igou Ferry Road Tennessee Valley Authority Soddy Daisy, TN 37379 P.O. Box 2000 Soddy Daisy, TN 37379 Mr. Lawrence E. Nanney, Director Division of Radiological Health General Counsel Dept. of Environment & Conservation Tennessee Valley Authority Third Floor, L and C Annex ET 11A 401 Church Street 400 West Summit Hill Drive Nashville, TN 37243-1532 Knoxville, TN 37902 County Executive Mr. Robert J. Adney, General Manager Hamilton County Courthouse Nuclear Assurance Chattanooga, TN 37402-2801 Tennessee Valley Authority 6A Lookout Place Ms. Ann P. Harris 1101 Market Street 341 Swing Loop Road Chattanooga, TN 37402-2801 Rockwood, Tennessee 37854 Mr. Mark J. Burzynski, Manager Mr. J. A. Scalice Nuclear Licensing Chief Nuclear Officer and Tennessee Valley Authority Executive Vice President 4X Blue Ridge Tennessee Valley Authority 1101 Market Street 6A Lookout Place Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801
