ML20090F493
| ML20090F493 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/17/1983 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML20090F496 | List: |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, ANPP-24075-BSK, DER-82-50, NUDOCS 8307060013 | |
| Download: ML20090F493 (3) | |
Text
{{#Wiki_filter:c-- 50- 527. n Arizona Public Service Companygy //) PO BOX 21666
- PHOENIX ARIZONA B5036 s
fil 39 H June 17, 1983 ANPP-24075-BSN8QT, j U. S. Nuclear Regulatory Commission Region V Creekside Oaks Of fice Park 1450 Maria Lane - Suite 210 Walnot Creek, CA 94596-536S Attention: Mr. D. M. Sternberg, Chie f Reactor Projects Branch 1
Subject:
Final Report - DER 82-50 A 50.55(e) Reportable Condition Relating to Flexible Conduit Couplings Between Unit 1 Auxiliary And Control Buildings May Be Damaged If Seismic Event Exceeds 3/4 Inch Movement File: 83-019-026; D.4.33.2
Reference:
A) Telephone Conversation between J. Eckhardt And G. Duckworth dated September 10, 1982. B) ANPP-21974, dated October 81982 (Interim Report) C) ANPP-22612, dated December 22, 1982 (Time Extension) D) ANPP-23417, dated April 4,1983 (Time Extension) E) ANPP-23944, dated June 1,1983 (Time Extension)
Dear Sir:
Attached is our final written report of the deficiency referenced above, which has been detennined to be _Not_ Reportable under the requirements of 10CFR50.55(e). Very truly yo s, Cc. on cA E. E. Van Brunt, Jr. APS Vice President, Nuclear Projects Management ANPP Project Director EEVB/RQT:ru Enclosure cc: See Page 2 8307060013 830617 PDR ADOCK 05000528 f =
l i 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 1 R. M. Grant D. R. Hawkinson L. E. Vorderbrueggen G. A. Fiorelli S. R. Frost j Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339 i l l l l I
p FINAL REPORT - DER 82-50 l DEFICIENCY EVALUATION 50.55(e) ARIZONA PUBLIC SERVICE COMPANY (APS) PVNGS UNIT 1 I. Description of Deficiency During Field Inspection, the Field Engineer questioned the seism c i capability of installed electrical conduit expansion / deflection couplings in the dead space between the Unit 1 Auxiliary and Control Buildings. Note 4 on Bechtel Drawings 13-E-ZJC-052 and 13-E-ZJC-053 specify the use of " Standard Flexible Fittings" for all conduit installed between the Auxiliary and Control Building; however, expansion / deflection type couplings without seismic qualification had been installed. II Analysis of Safety Implications A detailed analysis (attached), based on testing, of the electrical conduit connections between the auxiliary and Control Buildings was perfrormed by Wyle Laboratories. Details and results of the analysis are provided in Wyle Report No. 26406-1 (Bechtel Log No. E600-22-1), entitled " Evaluation of Electrical Conduit Connections Between the Auxiliary and Control Buildings for the APS Palo Verde Nuclear Generating Station". In this analysis, flexible fittings were characterized from obtained test data, from which the critical design case was identified and evluated. The Wyle Laboratories 4 analysis demonstrated the structural integrity of the couplings under all installed conditions. Since the evaluated case represents the critical or worst scenario, it has been determined that all conduit expansion / deflection couplings between the Auxiliary and Control Buildings will withstand all postulated relative motion between these buildings during an SSE event without damage to couplings or cable contained therein. Based upon the above analysis this condition has been determined to be not safety significant and hence not reportable under the 4 requirements of 10CFR50.55(e). If left uncorrected, it would not have adversely affected the safety of operations of the plant during the lifetime of the plant. III. Corrective Action
- 1) NCR EJ-2285 will be dispositioned use as is.
- 2) Note 4 on Bechtel Drawings 13-E-ZJC-052 and 13-E-ZJC-053 and Bechtel Drawing 13-E-ZJC-050 (" Conduit and Tray Notes, Symbols and Details") have been revised to clarify the type l
of conduit fitting to be used between the Auxiliary and Control Buildings. Future installations will be made in accordance with the revised notes. =}}