ML20063N916

Final Deficiency Rept Re Steam Generators Loose Internal Nuts & Couplings.Nonconformance Repts Will Be Dispositioned to Repair Defects to Conform w/C-E Drawing Requirements. Unit 2 & 3 Will Be Inspected for Similar Defects

ML20063N916
Person / Time
Site:	Palo Verde
Issue date:	09/21/1982
From:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Sterberg D, Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
10CFR-050.55E, 10CFR-50.55E, ANPP-21887-GHD, DER-81-43, NUDOCS 8210070354
Download: ML20063N916 (4)

Text

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Docket Nos. 50-528/529/530 50.55(o) Rcport

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sTA. 3003 ,.o, ,ox ,3... . , noon,x, anizo'NA 85036 September 21, 1982 ANPP-21887-CHD/BSK

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U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. D. M. Sternberg, Chief Reactor Projects Branch 1 Subj ect: Final Report - DER 81-43 A 50.55(a) Report Relating to Unit 1 Steam Generators l Loose Internal Nuts and Couplings File: 82-019-026 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 i9, 1982 (Time Extension)

(D) ANPP-20966, dated May 14, 1982 (Interim Revision 1)

Dear Sir:

l l Attached is our final written report of the deficiency referenced l above under the requirements of 10CFR50.55(e).

Very truly yours,

. . Cllk GL E. E. Van Brunt, Jr.

APS Vice President Nuclear Projects Management ANPP Project Director EEVBJr/GHD:db Attachment cc: See Attached Page 2

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U. S. No. lear Regulatory Commission September 21, 1982 Attentiota: Mr. D. M. Sternberg, Chief ANPP-21887-Gild /BSK Page 2 cc- Richard DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 T. G. Woods, Jr.

J. A. Roedel D. B. Fasnacht G. C. Andognini A. C. Rcgers Bl S. Kaplan W. E. Ide J. Vorees J. A. Brand A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher R. M. Grant D. R. Hawkinson L. E. Vorderbrueggen G. A. Fiorelli Lynne Bernabei, Esq.

Harmon & Weiss 1725 "1" Street, NW Suite 506 Washington, D. C. 20006 fi. L. Greenfield Assistant Attorney General Bataan Memorial Building Santa Fe, New Mexico 87503

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l FINAL REPORT - DER 81-43 DEFICIENCY EVALUATION 50.55(e)

• ARIZONA PUBLIC SERVICE COMPANY (APS)

PVNGS UNIT 1 I. DESCRIPTION OF DEFICIENCY Entry >y Bechtel into Steam Generator #2 for special instrumentation

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installation disclosed Combustion Engineering, Chattanooga, delivered the item with missed factory operations.

Marmon Couplings holding steam separators were not tightened.

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 wel6ing of steam outlet piping.

These problems would have gone undetected had it not been for entry to incorporate instrumentadon modification.

Entry into Steam Generator #1 revealed the following nonconformances (NCR NC-661) in regard to C-E drawing E-78273-371-021 Rev.1:

Forty-nine (49) nuts, PC No. 273-3503, were not tack welded as I per View T-T of the darwing.

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.

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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Final Report - DER 81-43 Page 2 III. CORRECTIVE ' ACTION The nonconformance reports BC-043, BC-044, NC-633 and NC-661 will be dispositioned to repair the various defects to conform to the C-E drawing requirements.

The C-E Site Construction Manager and APS Construction QA/QC will make an inspection of the Unit 2 steam generators and, based on this inspection, determine if the Unit 3 steam generators are to be entered and inspected for similar defects.

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