ML20133A084

Final Part 21 & Deficiency Rept DER 85-15 Re Thin Wall Pipe Mfg by Phoenix Steel Corp & Supplied by Hub,Inc.Initially Reported on 850424.Condition Not Reportable Per 10CFR50.55(e) & Part 21

ML20133A084
Person / Time
Site:	Palo Verde
Issue date:	07/15/1985
From:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
REF-PT21-85-366-000 ANPP-33029-TDS, APPO-33029-TDS, DER-85-15, PT21-85-336, PT21-85-336-000, NUDOCS 8508050330
Download: ML20133A084 (4)

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RECEIVED flRC Arizona Nuclear Power ProJg93 y P.O. BOX 52034 e PHOENIX. ARIZONA 85072-2034 !hh July 15, 1985 M 'JN3S-TDS/TPS U. S. Nuclear Regulatory Commission @M Region V 1450 Maria Lane - Suite 210 2-5%

g syy Walnut Creek, California 94596-5368 Attention: Mr. D. F. Kirsch, Acting Director Division of Reactor Safety and Projects

Subject:

Final Report - DER 85-15 A 50.55(e) Condition Relating to Thin Wall Pipe from Hub, Inc.

File: 85-019-026; D.4.33.2

Reference:

A) Telephone Conversation between R. C. Sorensen and P. J. Coffin on April 24, 1985 B) Letter from E. E. Van Brunt, Jr. to D. F. Kirsch, dated May 24, 1985 C) Telephone Conversation between A. Hon and P. J. Coffin on May 28, 1985 D) ANPP-32752, dated May 30, 1985 (Interim Report)

Dear Sir:

Attached is our final written report of the Deficiency referenced above, which has been determined to be Not Reportable under the requirements of 10CFR 50.55(e) and 10 CFR Part 21.

Very truly yours, EDJ Pdh E. E. Van Brunt, Jr.

Executive Vice President Project Director EEVB/TPS/jb Attachment cc: See Page Two 8500050 PDR A g g5 h !28 1 PDR

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- Page Two; E cc: Richard DeYoung, Director Office-ofiInspection and Enforcement U. S._ Nuclear Regulatory Commission

! Washington, D. C. 20555 l

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.D. B. Karner

' W. E. Ide

, c- D. B. Fasnacht-L A. C. Rogers

. L. A. Souza D. E. Fowler T. D.1 Shriver-(. '

- C.:N. Russo i LB. S. Kaplan

' J. R. Bynum .

f J. M. Allen.

[' :D. Canady A. C. Gehr:

W. J. Stubblefield EW. G.~ Bingham R. L. Patterson R. W. Welcher

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~M.1 L.:Clyde B. T. Parker

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LJ. E.' Kirby-I

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' Records Center Institute of Nuclear. Power Operations (1100 Circle 75 Parkway, Suite 1500 ,

Atlanta Georgia :30339

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FINAL REPORT - DER 85 ,

DEFICIENCY EVALUATIOF 50'.55(e)

- E ARIZONA NUCLEAR POWER PROJECT (ANPP)

PVNGS UNITS 1, 2, 3 I. Description of Deficiency Hub,'Inc. has notifed Bechtel under 10 CFR 21 that, based upon the inspection method used by Phoenix Steel Corporation, certain

( ' pipe material manufactured by Phoenix Steel Corporation may have undersize wall. thickness. Discussion with Guyon Alloys (piping supplier) revealed that two years ago they found a short piece of

, forged pipe'which was under minimum wall'. Phoenix Steel Cor-i poration considered this to be an isolated case. The NRC, after _

learning of the incident in a recent. visit to Guyon Alloys,

- visited Phoenix Steel Corporationcto' determine.the extent of the problem. From a sample of four pieces, one'was found to be 12 percent under minimum wall. thickness (12-1/2 percent is per -

, .mitted). The NRC concluded that a potential-problem exists and

. required the issuance of the Part 21 notice. A Bechtel QA review of the Phoenix Steel process for producing forged pipe showed that

, all their production equipment fabricated pipe with a 5-digit heat

. number beginning with an 8 or 9. A review of heat number records at PVNGS revealed only one heat number from Phoenix Steel in this category. Heat number 93213 was procured on P. O. F152319 from Guyon Alloys and consists of 8 feet of schedule 40, SA106 Grade B pipe. A total'of four pipe spools have been fabricated-from this-

-piece and installed in Unit 2 under DCP 2SP-EW-016. The fabrication

of these spools used a total of 1 foot, 3 inches of the 8 feet supplied.

s In a letter dated May 21, 1985 (MIC #246053), Hub Inc. states that pipe made of material other than SA-100 was suspect. Since the Bechtel review addressed all material grades within the

, affected heat numbers, this new information has no impact on this DER.

Evaluation The records of Guyon Alloys'show the 8 foot pipe spool was fur-nished to an order on December 23, 1981, and processed under their quality assurance program', which required-the ends of all pipe to be completely measured for minimum wall thickness prior to shipment for nuclear or safety-related use. Bechtel issued NCR PX-10851 to measure the ends of the remaining 6 foot 9 inches of the above-mentioned pipe. Both measurements were within the allowable code and industry standards, so it is concluded that

.a nonconforming condition ~does not exist.

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Final Report; DER 85-15

.Page Two Ill.. Analysis of Safety Implications

-Based on the above, this condition is evaluated as not report-able under the requirements of.10 CFR 50.55(e) or-10CFR'21,

-since it does not represent a safety significant condition.-

III.' Corrective' Action

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~None Re' quired.

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