ML20073F673
| ML20073F673 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/29/1983 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, ANPP-23385-BSK, DER-81-43, NUDOCS 8304150522 | |
| Download: ML20073F673 (4) | |
Text
Docket Nos. 50-528/529/530
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Arizona Public Service Company
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P O. box 21666
- PHOENIX. ARIZONA 85036 l 3 March 29, 1983
,7, ANPP-23385-BSK/GHD' U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 l
Walnut Creek, CA 94596-5368 l
l Attention: Mr. D. M. Sternberg, Chief Reactor Projects Branch 1 I
Subject:
Final Report, Revision 1 - DER 81-43 l
A 50.55(e) Report Relating to Units 1 & 2 Steam Generators Loose Internal Nuts and Couplings File: 83-019-026; D.4.33.2
Reference:
A) Telephone Conversation between J. Eckhardt and G. Duckworth on November 23, 1981 B) ANPP-19678 dated December 23, 1981 (Interim Report)
C) ANPP-20220 dated February 19, 1982 (Time Extension)
D) ANPP-20966 dated May 14, 1982 (Interim Revision 1)
E) ANPP-21887 dated September 21, 1982 (Final Report)
Dear Sir:
Attached is Revision 1 to our final written report of the deficiency referenced above, under the requirements of 10CFR50.55(e).
Very truly yours C11A.
S LR E. E. Van Brunt, Jr.
APS Vice President, Nuclear Projects ANPP Project Director EEVB/GHD:wp Attachment cc: See Attached Page Two l
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I B304150522 830329 9DR ADDCn 05000528 l
73 PDR l
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l U. S. Nuclear Regulatory Commission l
Page Two l
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 t
l J. R. Bynum D. D. Green P. P. Klute A. C. Gehr W. J. Stubblefield i
W. G. Bingham R. L. Patterson R. W. Welcher R. M. Grant D. R. Hawkinson L. E. Vorderbrueggen G. A. Fiorelli i
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FINAL REPORT REVISION 1 - DER 81-43 DEFICIENCY EVALUATION 50.55(e)
ARIZONA PUBLIC SERVICE COMPANY (APS)
PVNGS UNITS 1 AND 2 1.
Description of Deficiency Entry by Bechtel into Unit 1 Steam Generator #2 for special instrumentation installation disclosed that Combustion Engineering, Chattanooga, delivered the item with the following missed factory 3
operations:
Marmon Couplings holding steam separators were not tightened.
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Approximately 50% of nuts in steam dryers above can deck were not tightened.
One area of incomplete drilling through facing plate resulted in only three (3) of four (4) bolt locations being installed.
Sixty (60) Nuts PC No. 273-3503 are not tack welded per View T-T of Drawing E-78272-371-020, Rev. 1.
Dryer deck area is not clean, appears debris was generated during fit up and welding of steam outlet piping.
These problems would have gone undetected had it not been for entry to incorporate instrumentation modification.
Entry into Unit 1 Steam Generator #1 revealed the following nonconform-ances (NCR NC-661) in regard to CE drawing E-78273-371-021, Rev. 1:
Forty-nine (49) nuts, PC No. 273-3503, were not tack welded as per View T-T of the drawing.
In place of tackwelds, lockwashers have been installed under nuts.
Four (4) large nuts were not tack welded as per Section S-S.
One (1) bolt and nut assembly is missing as per Section F-F.
The CE Site Construction Manager has made an inspection of the Unit 2 steam generatore and based on the results, NCR ZC-004 was initiated to repair similar defects. As a result of this inspection the Unit 3 steam generators are to be entered and inspected for similar defects.
II.
Analysis of Safety Implications Loose parts inside the Steam Generators could cause wear or damage resulting in tube leaks which might have adverse effects on the operation of the Nuclear Steam Supply System. The exact nature or magnitude of such effects are indeterminate, however, this Final Report submits all information as required under 10CFR50.55(e).
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l FINAL REPORT REVISION 1 - DER 81-43 Page Two i
III. Corrective Action-All the identified nonconformances will be corrected via nonconformance reports BC-043, BC-044, NC-633, NC-661,.and ZC-004, plus any future NCRs generated as a result of additional inspections, to conform to the CE drawing requirements.
A copy of this report will be transmitted to CE to preclude recurrence of similar defects on equipment not yet delivered.
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