ML20197B326
| ML20197B326 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/13/1986 |
| From: | Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| ANPP-38656-JGH, DER-86-20, NUDOCS 8610280358 | |
| Download: ML20197B326 (3) | |
Text
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Arizona Nuclear Power Project
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P O. BOX 52034 e PHOENIX. ARIZONA 85072-2034 h
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G October 13, 1986 ANPP-38656-JGH/DJW/DRL-92.11 U. S. Nuclear Regulatory Commission Region V 1450 tiaria Lane - Suite 210 Uninut Creek, California 94596-5368 Attention:
Mr. D. F. Kirsch, Acting Director Division of Reactor Safety and Projects Palo Verde Nuclear Generating Station (PVNGS)
Unit 3 Docket No. 50-530
Subject:
Update to Interim Report - DER 86-20 A 50.55(e) Potentially Reportable teficiency Relating to Damper Seals Not Meeting Required Specifi.:ations File: 86-006-216; D.4.33.2
Reference:
(A) Telephone Conversation between R. C. Sorenson and D. R. Larkin on June 3,1986 (Initial Notification - DER 86-20)
(B) ANPP-37195, dated July 2, 1986.
(Interim Report - DER 86-20)
(C) ANPP-38392, dated September 24, 1986. (Time Extension - DER 86-20)
Dear Sir:
The NRC was notified of a potentially reportable deficiency by reference (A),
an interim report by reference (B) and a time extension by reference (C). At that time, it was estimated that a determination of reportability would be made by October 17, 1986.
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Due to the extensive research and evaluation required to determine root cause, an update to our interim report noted in reference (B) above, is attached.
It is now expected that this information will be finalized by November 13, 1986, at which time a complete report will be submitted.
Very truly yours, SW J. G. Haynes Vice President Nuclear Production JGH/DRL/ dim ec: See Page 2 8610280358 861013 PDR ADOCK 05000530 S
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DER 86 Update to Interim Report Mr. D. F. Kirsch Acting Director Page Two October 13, 1986 ANPP-38656-JGH/DJW/DRL-92.11 cc:
J. M. Taylor Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.
20555 A. C. Gehr.
(4141)
R. P. Zimmerman (6295)
Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339
Update to Interim Report DER 86-20 As stated in the Interim Report. letter no. ANPP-37195, dated July 2, 1986, while doing rework'per NCR SM-6272, the HVAC subcontractor discovered that the blade seal on a Unit 3 damper had a tear.
Since that time, Ruskin Manufacturing Company has completed testing at their facility and The Waldinger Corporation did investigation and testing at the site.
Sub-sequently, all 25 "Q" class bubbletight dampers, installed in Unit 3, were inspected and repaired, as necessary.
The Unit I and 2 damper integrity has been verified by the control room pressurization test 73ST-9HJ01. The test results have shown that the control room pressure has met the technical specification requirements of maintaining the control room at a positive pressure greater than or equal to 1/8-inch water-gauge. This indicates that the dampers are performing their intended function. However, radioactive in-leakage may occur through four large 48-inch dampers if these dampers have seal damage. The 48-inch dampers (four per unit) have been inspected and repaired, as necessary, to ensure continued safe operation.
The complete evaluation and final report are forecast for November 13, 1986.