ML20094K471
| ML20094K471 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/16/1992 |
| From: | Joshua Wilson TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TAC-R00420, TAC-R420, NUDOCS 9203200367 | |
| Download: ML20094K471 (2) | |
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k mu e March 16, 1992 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of
)
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 SEQUOYAH NUCLEAR PIANT (SQN) - ALTERNATE ANALYSIS REVIEW PROGRAM PHASE II
- PIPE SUPPORT DEFLECTION CRITERIA (TAC NO. R00420)
Reference:
TVA's letter to NRC dated August 26, 1991 In the above reference, TVA provided the results of an additional evaluation of the deflection criteria used to verify rigidity of pipe supports for alternately analyzed (AA) piping. This additional evaluation was performed to address 4-inch piping and was extrapolated to 6-inch piping. As conveyed in a September 12, 1991, conference call, NRC agreed with TVA's evaluation of the 4-inch piping, but not the extrapolation to the 6-inch piping.
In the same conference call. TVA agreed to reevaluate the 6-inch AA piping. During a December 13, 1991, conference call, TVA provided the results of that evaluation. Of the 276 supports evaluated, only one did not have adequate stiffness and will require modification. Revision 3 of Calculation N2-AA-SUPTFLEX documents this evaluation. Additionally, s problem evaluation report (SQPER910409) was writirn to document the identified deficiency. The piping and support system associated with the support discussed above has been evaluated and determined to remain operable.
For recurrence controls, the AA criteria have been revised to provide a minimum design load for 6-inch-diameter AA pipe s.jports.
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9203200367 920316 PDR ADOCK 05000327 P
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_.,_.m U.S. Nuclear Regulatory Connission Page 2 March 16,1992 As discussed in tt3 December 13, 1991, conference call, this latest effort resolved the concern on the alternate analysis pipe support deflection criteria.
No commitments-are contained in this submittal.
Please direct questions concerning this' issue to W. C. Ludwig at (615) 843-7460.
Sincerely,
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(IdL. Wilson j
cc:
Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 I
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