ML20212D830
| ML20212D830 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 02/12/1987 |
| From: | Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| ANPP-40101-JGH, DER-86-29, NUDOCS 8703040214 | |
| Download: ML20212D830 (3) | |
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HECEIVED A
Hnc 1337 FE819 yt II: 10 Arizona Nuclear Power Project
. P.O. SOX 52034 e PHOENIX, ARIZONA 85072-2034 February 12, 1987 REGl0ilVlGE ANPP-40101-JGH/DJW/DRL-92.11 U. S. Nuclear Regulatory Commission Region V 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention:
Mr. D. F. Kirsch, Director Division of Reactor Safety and Projects Palo Verde Nuclear Generating Station (PVNGS)
Unit 3 Docket No. 50/530
Subject:
Time Extension For Report - DER 86-29 A 50.55(e) Potentially Reportable Deficiency Relating to Letdown Heat Exchanger Nozzle Crack File: 87-006-216
Reference:
(A)
Telephone Conversation Between R. C. Sorenson and D. R. Larkin on November 14, 1986.
(Initial Notification -
(B)
ANPP-39248, dated December 5, 1986.
(Interim Report -
(C)
ANPP-39651, dated January 9, 1987.
(Time Extension - DER 86-29)
Dear Sir:
The NRC was notified of a potentially reportable deficiency in reference (A),
an interim report by reference (B) and a time extension by reference (C). At that time it was estimated that a final report would be available by February 16, 1987.
Due to the extensive investigation and evaluation required, a time extension is needed. On January 24, 1987, a liquid penetrant inspection of nozzles on the letdown heat exchanger in Unit 1 revealed linear indications on the outside of the inlet nozzle. Liquid penetrant examinations have been completed on other nozzles of the Unit 1, 2, and 3 letdown heat exchangers.
No additional linear indications or cracks have been identified. However, since an indication was identified in the Unit 1 letdown heat exchanger nozzle, as well as the crack originally identified in Unit 3 and because the cause of these deficiencies is believed to be high stress, low cycle loadings, an evaluation of potential effects on other welds in the system is necessary.
This information was discussed with NRC Region V officials during a meeting held on February 4, 1987 in the ANPP offices.
8703040214 670212 PDR ADOCK 05000530 S
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c Time Extension - DER 86-29
. Mr. D. F. Kirsch
-Director Page Two February 12, 1987 ANPP-40101-JGH/DJW/DRL-92.11 It is now expected that this information will be finalized by February 23, 1987 'at which time a complete report will be submitted.
Very truly yours, p
J. G. Haynes Vice President.
Nuclear Production JGH/DRL:kp ces See Page Three
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Time Extension - DER 86-29 Mr. D. F. Kirsch.
Director.
Foge Three i!
- February 12,I1987 ANPP-40101-JGH/DJW/DRL-92.11 cci 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 l