ML20147D059
| ML20147D059 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/02/1988 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8803030221 | |
| Download: ML20147D059 (4) | |
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TENNESDEE VALLEY AUTHORITY CHATTANOOG A. TENNESSEE 37401
'15)B' Lookout Place t
MAR 2 1988
' U.S. Nuclear Regulatory Comission ATTN:- Document Control Desk Washington, D.C.
20555' Gentlemeru In the Matter of
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Docket Nos. 50-327 Tennessee Valley Authority.
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50-328 SEQUOYAH NUCLEAR PLANT (SQW)
! PIPING SUPPORT DESIGN CRITERIA As requested by John Fair in.a February 25, 1988 telephone conference call, enclosure 1 provides the NRC with information on'a proposed revision to pipe support design criteria SQN-DC-V-24.2 and the statur of certain pipe support calculations identified by Mr. Fair. Enclosure 2 provides a list of connitments being made by TVA in this submittal.
Very truly yours.
TL*NNESSEE VALLEY AUTHORITY
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, Directo Nuclear Licensing and Regulatory Affairs Enclosurs cct Sec page 2 9
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- U.S. ' Nuclear Regulatory Consalssion MR 2 M Enclosure cc (Enclosure):
Mr. K. P. Barr, Acting Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. G. G. Zech, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North
-11555 Rockville Pike Rockville, Maryland 20852 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 i
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ENCLOSURE 1 SEQUOYAH NUCLEAR PLANT INFORMATION REQUESTED BY JOHN FAIR IN FEBRUARY 25, 1988 TELECON I.
Revision to TVA Pipe Support Criteria SQN-DC-V-24.2 The note in Section 6.3.13 will be revised to read:
NOTE: Plastic design may be utilized on a selective basis provided that the stability of the structure is assured. Such cases shall be brought to the attention of the lead engineer for disposition.
SQN-DC-V-24.2 will be revised af ter restart of SQN unit 2.
II.
The following is a summary of evaluation results for four pipe support calculations requested by the NRC:
1.
2-H36-111 This support includes a structural steel beam that was attached between the top and bottom of an opening in the crane wall.
An evaluation of thermal effects indicated that the stress in the clip angle welds generated from the environmental thermal temperature change exceeded design allowables. This support has been modified.
2.
2-HIM-101 This' support consists of a series of structural steel members spanning between the walls of a tunnel. An evaluation of this suppoct indicated that the structural elements will not buckle due to the environmental thermal effects. The support is considered to be acceptable. Plastic analysis was used to qualify the end connections.
3.
2-HIM-102 This support consists of a serica of tube steel shapes spanning between the walls of a tunnet. An evaluation of this support indicated that the structural elements will not buckle due to the environmental thermal loading effects. The support is considered to be acceptable. Plastic analysis was used to qualify the end connections.
4.
2-HIM-103 This support consists of a series of structural steel membero spanning between the walls of a tunnel.
An evaluation of this support indicated that the structural elements will not buckle due to environmental thermal effects. The support is considered to be acceptable. Plastic analysis was used to qualify the end connections.
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ENCLOSURE 2 SEQUOYAH NUCLEAR PLANT LIST OF COMMITMENTS 1.
The note in Section 6.3.13 of TVA pipe support design criteria SQN-DC-V-24.2 will be revised after SQN unit 2 restart to read:
NOTE: Plastic design may be utilized on a selective basis provided that the stability of the structure is assured. Such cases shall be brought to the attention of the lead engineer for disposition.
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