ML20024C177
| ML20024C177 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/27/1983 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Sternber D, Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML20024C178 | List: |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, ANPP-24173-BSK, DER-82-63, NUDOCS 8307120366 | |
| Download: ML20024C177 (32) | |
Text
9 CECE!VED tinC Arizona Public Service Company P.O. BOX 2i666 e PHOiNIX. ARIZONA 85036 ES3 JUI. -5 P.1 1: 39 June 27, 1983 ANPP-24173-BSK/RQT REGICAV te U. S. Nucicar Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. D. M. Sternberg, Chief Reactor Projects Br::nch 1
Subject:
Final Report - DER 82-43 A 50.55(e) Report Relating to Design Calculation Error In Refueling Water Tank Seismic Response File: 83-019-026; D.4.33.2 Ref erence: A) Telephone Conversation between A. D'Angelo and G. Duckworth on Oc t.
26, 1982.
B) ANPP-22375, dated Nov. 24, 1982 (Interim Report)
C) AhTP-22844, dated Jan 27,1983 (Time Extension)
D) ANPP-23277, dated March 27, 1983 (Time Extent, ion)
E) ANPP-23469, dated April 12, 1983 (Time Extension)
Dear Sir:
Attached is our final written report of the deficiency referenced above, which has been determined to be Not Reportable under the requirements of 10CFR50.55(e).
Very truly yo s,
ca.c E. E. Van Brunt, Jr.
APS Vice President, Nuclear Projects Management ANPP Project Director EEVB/RQT:ru Enclosure cc: Page 2 B307120366 830627 PDR ADOCR 05000528 8
PDR Ell [fjj f
h4 U. S. Nuclear Regulatory Commission Page 2 cc: Richard DeYoung Director Office of Inspection and Enforcement U.~ S. Nuclear Regulatory Commission Washington, D. C. 20555
.T. G. Woods, Jr.
G. C. Andognini J. A. Roedel D. B. Fasnacht A. C. Rogers B. S. Kaplan W. E. Ide J. Vorees J. R. Bynum P. P. Klute/D. D. Green A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher R. M. Grant D.
R.- Hawkinson L. E. Vorderbrueggen G. A. Fiorelli S. R. Frost J. Self Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339 Torrey Pines Technology P. O. Box 81608 San Diego, California 92138 m
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F FINAL REPORT - DER 82-63 DEFICIENCY EVALUATION 50.55(e)
PVNGS UNITS 1, 2, & 3 I.
Description of Deficiency Thir report was initiated as a result of the Torrey Pines Technology Independent Evaluation of PVNGS which requested that the design of the Condensate Storage Water Tank (CST) be reevaluated.
The Refueling Water Tank (RWT) is designed to resist stresses resulting from operating and extreme environmental / accident loads.
During a Bechtel review of the RWT calculation package (Calculation 13-CC-CT-015), an error was found in the determination of the tank-wall bending moment at the junction of the basemate. The correction of this error in the calculation without a more detailed three-dimensional finite element analysis would result in calculated stresses in some of the inside-face vertical rebar of the tank-wall that exceed Design Criteria allowables.
Since the analysis and design of the Condensate Water Storage Tank (CST) was based upon the analysis of the RWT (see Calculation 13-CC-CT-010, Revision 0), the CST is likewise affected.
II.
Analysis of Safety Implications This condition is evaluated as not reportable.
Based upon independent detailed analysis of the RWT and the CST, the existing designs of both structures have been determined to be adequate for all load combination specified in the Project Design Criteria (see attached report). Therefore, a safety significant condition does not exist, hence the subject condition is not reportable under the requirements of 10CFR50.55(e).
.III. Corrective Action 1.
Bechtel Engineering has performed independent detailed analysis for the RWT (Calculation 13-CC-CI-015, Revision 4) and the CST (Calculation 13-CC-CT-010, Revision 1).
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l Final Report DER 82-63 Page 2 Details of this analysis are presented in the attached report
" Engineering Evaluation for the Design of the Condensate Water 1
i Storage Tank and the Refueling Water Tank", dated May,1983.
Based upon the results of the detailed analysis, it has' been determined that local yielding of some of the inside-face vertical rebar at the wall basemat junction occurs for the RWT and the CST under certain load conditions. The 1/4 inch stainless steel liner plate, attached to the inside surface of each tank, ensures the leak tight integrity of each structure.
Under the extreme loading condition that might locally crack the concrete' at the wall-basemat junction, the strain in the liner will remain well below allowable strain for stainless steel based upon ASME Section III Division 2 Code. Therefore, it has been demonstrated that this local yielding of the rebar in no I
way impairs the design function of the tanks or poses any threat to any other Category I structure or equipment.
2.
Safety Analysis Report Change Notice 1100 is being issued to revise Section 3.8.4.1.8 (subtitled " Refueling Water Tank") of the FSAR. This revision clarifies the following for the RWT:
a) the concrete shell will retain the hydrostatic pressure without reliance upon the stainless steel liner; and b) the welded stainless steel liner _ ensures the leak tight integrity of the structure, i
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