ML19344B111
| ML19344B111 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/18/1980 |
| From: | Crouse R TOLEDO EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 1-158, NUDOCS 8008250590 | |
| Download: ML19344B111 (2) | |
Text
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%m iEDiSON Docket No. 50-346 Aicsaac P. Caouss 74 7 ".5221 License No. NPF-3 14191253 Serial No. 1-158 August 18, 1980 Mr. James G. Keppler Regional Director, Region III Office of Inspection and Faforcement U.S. Nuclear Regulatory C-w ission 799 Roosevelt Road Glen Ellyn, Illinois 60131
Dear Mr. Keppler:
In our June 16, 1980 letter (Serial No. 1-137) we reported the completion of the follow-on analysis of identified discrepancies for normally accessible safety related piping required by IE Bulletin 79-14.
The results of this follow-on analysis supported our preliminary evaluation that the operability of safety related systems was unaffected.
Subsequent to our letter, further review of the co.pleted analysis for one stress calculation on the main steam line outside of containment (stress calculation 10A) revealed that the pipe support leads had been calculated utilizing a proposed modification support system instead of using the as-built configuration. This proposed pipe support was intended to be added to reduce the piping stress levels to below the long term acceptance levels.
Without this additional pipe support the stress level in the piping was still below our interim or short term acceptance levels. However, when the pipe support loads were recalculated using the current, as-built configuration it was discovered that the loads on three associated pipe supports were above the support's capacity. The system has therefore been declared inoperable.
This condition was promptly reported on August 1, 1980 under Section 6.9.1.8.1 of the Davis-Besse Nuclear Power Station Technical Specifications, Appendix A.
Additiona.~. details were provided in Revision 1 to our LER 80-048 fowarded on August 7, 1980.
The occurrence was reviewed with our architect engineer, Bechtel Power Corp-oration. An audit and review of all stress calculations used to assess the operability of normally accessible safety related piping systems was performed.
This condition was verified as the only isolated instance associated with this effort.
'O 3 b
'i THE TOLECO ED!SCN COMPANY EDISCN PLAZA 300 MACISCN AVENUE TCLECO. CH!O 43552 8008250870
/
i Docket No. 50-346 License No. NPF-3
. Serial No. 1-158 August 18, 1980 A new pipe support is being added to the system, prior to Mode 2 operation.
This will reduce the loads on the three affected supports to within acceptable levels.
f Yours very truly, RPC:CLM
'sj cc:
U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Division of Reactor Operation Inspection Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Operation Reactors Washington, D.C. 20555 i
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