ML20080B437

Interim Deficiency Rept DER 83-37 Re Missed Factory Operations on Steam Generator.Initially Reported on 830628. Bechtel Corresponding w/C-E to Obtain Technical Justification for Corrective Action.Next Rept by 831101

ML20080B437
Person / Time
Site:	Palo Verde
Issue date:	07/22/1983
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-27368-BSK, DER-83-37, NUDOCS 8308050488
Download: ML20080B437 (5)

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Arizona Public Service Company @J pn P O BOX 21666 . PHOENIX, ARIZONA 85036

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July 22, 1983 ANPP-27368-BSK/RQT U. S. Nuclear 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 Branch 1

Subject:

Sf- 5 $

Interim Report - DER 83-37 A 50.55(e) Potentially Reportable Deficiency Relating to Missed Factory Operations On Unit 3 Steam Generator #2.

File: 83-019-026; D.4.33.2

Reference:

Telephone Conversation between A. D'Angelo and R. Tucker on June 28, 1983.

Dear Sir:

The NRC was notified of a potentially reportable deficiency in the referenced telephone conversation. At that time, it was estimated that a determination of reportability would be made within thirty (30) days.

Due to the extensive investigation and evaluation required, an Interim Report is attached. It is now expected that this information will be finalized by November 1, 1983, at which time a complete report will be submitted.

Very truly yours, CLLA A LLL &

E. E. Van Brunt, Jr.

APS Vice President, Nuclear Projects Management ANPP Project Director EEVBJr./RQT:rb Enclosure cc: See Page Two 8309050489 830722 PDR ADOCK 05000530 PDR

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c U. S. Nuclear Regulatory Commission

-Page Two ec: 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 i

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 l

Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339 i

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U. S. Nuclear Regulatory Commission DER 83-37 Page Three

. INTERIM REPORT - DER 83-37 POTENITAL REPORTABLE DEFICIENCY ARIZONA PUBLIC SERVICE COMPANY (APS)

PVNGS UNIT 3 I. Potential Problem NCR ZC-010 Entiy into Steam Generator #2 disclosed CE Chattanooga delivered the item with missed factory orperations.

Dryer Region Upper Side There are twelve (12) nuts that do not have full thread engagement from the bolts that come up from the bottom of the dryer support beams.

The two (2) steam outlet nozzles have low pressure taps that have stainless steel elbows seal welded to the I.D. of the nozzels.

The welds are cracked approximately one-half (1/2) way around each fitting.

Inspection of channel / beam fillet welds revealed twenty-one (21) have crater cracking.

Approximately 50% of the lock washers used in bolting dryers to channels do not have solid backing behind the locking joint.

On one (1) beam, piece #273-3501L, there is a 6" long cut that appears to be a false start on cutting the beam.

Approximately 50% of the nuts, piece #273-3503, that go between the dryer assemblies have been installed backwards.

Two (2) bolts, piece 273-3511, were found not to be tight against the support beam.

While removing the steam separators, eight (8) of the-orifice plates were found to be loose.

Dryer deck area is not clean, appears debris was generated during fitup and welding of steam outlet piping.

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/ e U. S.. Nuclear Regulatory Commission DER 83-37 l Page Four Two (2) steam dryer corner velds were found to be separated from

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base metal.

These problems would have gone undetected had it not been for

! entry to perform- this inspection.

NCR ZC-012 Inspection- of .the secondary side of steam generator #1 disclosed the

- following discrepancies related to C-E factory operations.

Dryer Deck Two (2) are strikes were found on the vessel wall. One strike approximately 1/4" in diameter. The other is an arc strike

" trail" 1/16 wide approx. 3" long. Both are surface indications with no burn-in depth..

ll Nine (9), 1/2" hex nuts, PCf 273-3503 section F-F on Dwg.

271-020, are not tack welded.

Three (3) arc strikes were found on the steam outlet nozzle projections Maximum.of 1/8" diameter with no depth.

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-Some areas of the dryer deck were not clean. A large amount of burned paper was found under the steam outlet nozzles. This i material was used during field welding of the steam piping.

CAN DECK i

Inspection of the channel / beam fillet welds seam, #2006-271 I revealed 36 with-crater cracking. Also, one (1) weld has

cracking that extends the entire length of the weld.

. Nine (9) dryer drain pipes are loose.

Weld #1503-271 on PCf 286-228, (feedwater " candy cane" coupling) is missing. The candy canes are loose at the coupling and will require tightening prior to making the tack weld.

Approximately 50% of the lockwashers used in bolting dryers to channels will have to be rotated.to have a solid backing behind

.the locking joint. In addition, several of the slotted holes have been enlarged leaving insufficient plate on which to seat the washer.

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o a U. S. Nuclear Regulatory Commission DER 83-37 Page Five One steam dryer weld (3206-273) was found separated.

On Dwg. 79273-271-021, Detail "U", weld #2101-271 is missing.

One area approx. 6" square of weld splatter located on vessel wall. The area is at the 180* end of the first beam inside the 90* manway.

Cleanliness of the can deck area is inadequate. The primary concern is beneath the steam dryers. These areas have unacceptable accumulations of dust and foreign material.

II. Approach To And Status Of Proposed Resolution Bechtel engineering is corresponding with C-E engineering to obtain reportability dispostion and technical justification for the corrective action.

III. Projected Completion Of Corrective Action And Submittal Of The Final Report.

Evaluation of this condition and submittal of the final report is forecast to be completed by November 1,1983.