ML20108B772

Final Deficiency Rept PRD-84/09 Re Defective Pieces of Steel Received from Dubose Steel,Inc.Initially Reported on 840601.Std Practices for Inspecting Defects Will Be Followed.Item Not Reportable,Per 10CFR50.55(e)

ML20108B772
Person / Time
Site:	Grand Gulf
Issue date:	10/31/1984
From:	Dale L MISSISSIPPI POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
AECM-84-2-0019, NUDOCS 8411160173
Download: ML20108B772 (5)

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MISSISSIPPI POWER & LIGHT COMPANY MI

] Helping Build Mississippi P. O. B O X 164 0, J A C K S O N, M I S S I S S A'F)'{) 3 9 2 0 5 October 31, 1984 ///g ,

NUCLEAR LICEN51NG & 5AFETY DEPARTMENT p U.S. Nuclear Regulatory Commission Region 11 101 Marietta St., N.W., Suite 2900 Atlanta, Georgia 30323 Attention: Mr. J. P. O'Reilly, Regional Administrator

SUBJECT:

Grand Gulf Nuclear Station Unit 2 Docket No. 50-417 License No. NPF-13 File: 0260/L-835.0 Ref: AECM-84/0357, July 6, 1984 Final Response for PRD-84/09, DuBose Steel, Inc., Potentially Defective Pieces AECM-84/2-0019 On June 1, 1984, Mississippi Power & Light Company notified Mr. R.

Carroll, of your office, of a Potentially Reportable Deficiency (PRD) at the Grand Gulf Nuclear Station (GGNS) Unit 2 construction site. the deficiency concerns potentially defective pieces of steel received for use from DuBose Steel, Inc.

As previously reported, MP&L has evaluated this deficiency and determined that it is not reportable for Unit 1. Subsequently, MP6L has l determined that this de.ficiency is not reportable for Unit 2. Details are

( provided in our attached Final Report.

l Yours truly, L. F. Dale Director EBS/SHH:vog l Attachment cc (See Next Page) 1 1

E.411160173 841031 PDR ADOCK 05000 NFiCIAL COPY Member Middle South Utilities System #-

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AECM-84/2-0019~

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1. E" MISSISSIPPI POWER Q Ll2HT CO.... "NY 4-cc: Mr.-J. B._ Richard (w/a)-

Mr. R. B. McGehee (w/o)

Mr. N. S. Reynolds (w/o)

Mr. G. B. Taylor - (w/o)

..Mr. Richard C. DeYoung, Director (w/s) .

Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555

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Attcchment t:; AECM-84/2-0019

- Pcg2 1 of 3 FINAL RETORT FOR PRD-84/09 I. Description of Deficiency A. Definition of the Problem as it is Known to Date:

DuBose Steel, Inc. notified Bechtel by letter dated 5/16/84 that six (6) pieces of W6X20 - 20 feet long steel beams, heat number 77052, supplied to GCNS were potentially defective. The exact nature of the potential defects were investigated by DuBose Steel, Inc. and their subsupplier, Northwestern Steel & Wire Co. through an independent testing laboratory, Hanson Engineers, Inc. DuBose Steel, Inc. shipped samples from heat number 17052 to Northwestern Steel & Wire Co. for testing the week of 6/18/84. The material was thcaght to have contained twisted or skewed webs, shallow fillets, and net tross-sectional area less than required.

B. Names of Plant Systems Affected:

E12, G33 E21, E22, E51, and B21 C. Applicability to Units 1 and/or 2:

Applicable to Unit 2 and Unit 1 (This report will address Unit 2 only).

D. Part 21 Applicability:

10 CFR Part 21, is not Applicable to Unit 2, since these items have not been turned over to MP&L.

E. Part 21 Report:

Reference DuBose Steel, Inc. Letters dated May 15, 1984 and Mey 16, 1984 addressed to NRC Region 2 and Grand Gulf Nuclear Station respectively.

F. Cause of the Deficiency:

Some material samnles appeared to contain shallow fillets at the junction of the flange and web. These shallow fillets were evaluated by Hanson Engineers, Inc. to have occurred in the rolling process and were found to be within the mill fabrication tolerances of ASTM A6. Chemical analyses and tensile tests of the suspect material were conducted and found to meet the requirement of ASTM A36 - Standard Specification of Structural Steel. Physical measurements showed the sample meeting all physical dimensional requirements.

G. Applicability to NSSS Vendor:

The deficiency is not applicable to the NSSS Vendor.

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Attrehment'to AECM-84/2-0019 -

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.w FINAL REPORT FOR PRD 84-09 l II. Analysis of Safety Implications

~A. Identification of Interfacing Systeus and Interactions:

See-Item I.B. above.-

B. Recommendation of Reportability:

The condition cited in I.A. has been determined to have no impact on safett. (See I.D. , I.F. , and III.B.) . ,

III. Corrective Actions Taken A. Cause and Extent of the Deficiency:

DuBose Steel notified the NRC by letter dated May 15, 1984 that potentially defective steel was then presently knoun to exist in three heats: 80551, 89728 and 77052. _only steel from heat number 77052 was supplied to GGNS and was of a nature described in Item I. A. above.

B. Description of Actions Taken to Correct. Identified Deficiencies:

Samples of the potentially defective steel were sent to Forthwestern Steel & Wire Co. (NSWCo.) by DuBose Steel, Inc. NSWCo. engaged the services of Hanson Engineers, Inc. to examine the samples. The material was found to meet the required chemical and physical. .

requirements of ASTM A36 and ASTM A6 respectively, as well as the AISC Code of Standard Practice for mill fabrication.

A complete survey of the location of steel at Grand Gulf Units 1 and  ;

2 from the potentially defective heat was performed and documented in Bechtel NCR 6786. The material was used to fabricate pipe i supports for several safety related piping systems. The design calculations for each pipe support were reviewed to determine the stress levels within the potentially defective steelumembers in each pipe support. Using 18.6 KSI allowable bending stress and 12.4 KSI allowable shear stress for A36 material (36.0 KSI yield strength),

the highest calculated stress interaction was found to be 0;93fL 1.0. Generally interaction was in the range of 0.5 $11.0.

A visual inspection of the highly stressed supports containing the potentially defective steel was performed to verify that no significant visual defects were present in the material used in Grand Gulf Unit 2.

Based on the review of calculations and visual inspections ,

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performed, the material identified by NCR 6786 was dispositioned "use-as-is".

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.Attcchment to AECM-84/2-0019

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i-FINAL REPORT FOR PRD-84/09 C.- Action Taken to Prevent Future Occurrence:

Standard mill fabrication practices for inspecting for deficiencies will continue to be followed.

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