ML20133M352
| ML20133M352 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/05/1985 |
| From: | Domer J TENNESSEE VALLEY AUTHORITY |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8508130100 | |
| Download: ML20133M352 (4) | |
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a J9 TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374ol 400 Chestnut Street Tower II August 5, 1985 Director of Nuclear Reactor Regulation Attention: Ms. E. Adensam, Chief Licensing Branch No. 4 {i Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Ms. Adensam:
In the Matter of the ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 By letters dated June 27 and October 9, 1984, TVA transmitted a request for our Watts Bar (WBN) and Bellefonte (BLN) Nuclear Plant to utilize new techniques in the seismic analysis of piping. The new techniques utilize a higher variable damping value as described in ASME Code Case N-411 and an alternate peak broadening technique in seismic piping anaylysis as described in ASME Code Case N-397. We are now requesting NRC approval to utilize the same techniques at the Sequoyah (SQN) Nuclear Plant which includes approval to utilize ASME Code Cases N-411 and N-397. Since these techniques may be used during the installation of fire protection piping to satisfy previous commitments on Appendix R, we request an expeditious review and approval.
Enclosed is the request and justification for the request.
If you have any questions concerning this matter, please get in touch with Jerry Wills at FTS 858-2683.
Very truly yours, TENNESSE VALLEY AUTHORITY y
J. A. Domer, Chief Nuclear Licensing Branch Sworn 3 and subscCibed before me this O day of /lAl AM 1985 0 -
Notary Public My Comission Expires o[" ,'oo pp Enclosure cc: See page 2 hD 0500130100 050005 i PDR ADOCK 05000327 i i p PDR An Equal Opportunity Employer
I i
I Director of Nuclear Reactor Regulation August 5, 1985 l
l.
cc (Enclosure):
l U.S. Nuclear ' Regulatory Connaission Region II Attn: Dr. J. Nelson Grace, Regional Administrator i
101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 R
l Mr. Carl Stahle Sequoyah Project Manager i
- U.S. Nuclear Resulatory Conunission 7920 Norfolk Avenue Bethesda, Maryland 20814 l
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,. . I I
ENCLOSURE ;
l SEQUOYAH NUCLEAR PLANT REQUEST FOR NRC APPROVAL FOR USE OF HIGHER VARIABLE DAMPING VALUE FOR THE SEISMIC ANALYSIS OF PIPING SYSTEMS The current piping analysis techniques used by TVA in the analysis of the piping at SQN are conservative in the area of dynamic analysis. TVA proposes to utilize the following two developments reported by the Pressure Vessel Research Committee (PVRC) in any future dynamic analysis of the rigorously analyzed piping at SQN. These developments by PVRC (with TVA participating) have been submitted by PVRC to NRC for their approval.
Variable Damoinz Values for Pininz Analysis !
1 In the dynamic analysis of class 1, 2, and 3 piping systems, the value of I the damping used in the spectral analysis method are 0.5 percent for operating base earthquake, 1 percent for safe shutdown earthquake, and t 2 percent for the dynamic loads resulting from the design basis accident.
These damping values are very conservative and result in the overdesign of pipe supports. The cost of design and fabrication of these supports add to the plant cost overruns.
+ The Task Group on Damping Values of the PYRC Technical Committee on Piping Systems has recently completed a review of a significant data base of damping tests. The results of the review clearly indicate the justification for increasing the present damping values for dynamic design '
of nuclear power plant piping above those in use at SQN. Based upon their evaluations, the current recommendation of the Task Group members is that .
damping of 5 percent is acceptable to 10 Hz linearly decreasing to !
2 percent.at 20 Hz and held constant at 2 percent to 33 Hz. -
Recommendations are independent of pipe diameter.
These higher recommended damping values, also described in ASME Code Case N-411, can translate into substantial savings in time, effort, and cost towards the requalification of the existing piping systems or in the design ;
of new piping systems.
If, as a result of using the damping values in ASME Code case N-411, piping supports are moved, modified or eliminated, the expected increased piping displacements due to greater piping flexibility will be checked to assure that they can be accommodated and that there will be no adverse interaction with adjacent structures, components and equipment.
Soectra Shifting Regulatory Guide 1.122 recommends that the calculated dominant peaks of the floor response spectra be broadened to account for uncertainties in the structural frequencies owing to uncertainties in the materia 1' properties of the structure and soil and to approximations in the modeling techniques.
This method of peak broadening is very conservative. An alternative method of broadening of the structural pesks as described in Code Case N-397 can . ;
be based on a probabilistic approach. In the particular casa where there is more than one piping frequency located within the frequency range of a 024194.03
2 widened spectrum peak, the floor spectrum curve may be more realistically applied in accordance with this code case.
It is obvious that the analysis utilizing spectra peak shifting becomes cumbersome and less efficient for multiple support motion (multiple zones) and if there is more than one peak within a defined frequency range of interest. It is TVA's intent to use spectra peak shifting technique only if relief is required on a particular pipe support or where substantial i redesign is required.
Recommendations The proposed recommendations have been accepted by the PVRC Task Group on Damping, the Technical Committee on Piping Systems, and the Steering Committee on Piping Systems. The proposals have been forwarded to NRC (reference 1) and considered by ASME (reference 2) for review and approval on a generic basis. NRC was represented on the PVRC committees.
Dr. S. N. Hou and Dr. W. F. Anderson were on the Technical Committtee on 7 Piping Systems, Task Group on Damping, and R. J. Bosnak participated on the Steering Committee on Piping Systems. The response spectra peak shifting method has been accepted by NRC for inclusion in Standard Review Plan 3.9.2. NRC has accepted the use of higher damping values in Southern l
California Edison's San Onofre Nuclear Plant unit 1 seismic reevaluation program (reference 3).
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l We feel that the changes proposed by PVRC for higher damping values and for an alternative to peak broadening are more realistic and constitute a conservative design. Such findings were substantiated by the Lawrence Livermore National Laboratory on three piping systems at Zion Nuclear Plant (reference 4). TVA proposes that these two techniques be used in future rigorous analysis efforts at SQN for the requalification of existing design and in the analysis of new systems. Use of these methods could result in more flexible piping systems which, according to current industry thinking, would result in more reliable systems.
References
- 1. Letter from L. J. Chockie, Chairman of PVRC, to N. J. Palladino, Chairman of NRC, dated June 9, 1983.
- 2. Minutes of the Special Working Group on Dynamic Analysis of ASME Section III, February 6, 1984.
- 3. Letter from Harold R. Denton, Director of the Office of Nuclear Reactor Regulation, to K. Baskin, Vice President Nuclear Engineering Licensing and Safety Department of Southern California Edison Company, dated February 8, 1984.
- 4. " Impact of Changes in Damping and Spectrum Peak Broadening on the Seismic Responso of Piping Systems," NUREG/CR-3526, December 1983.
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