ML19327A543

Interim Deficiency Status Rept 2 Re Reactor Pressure Vessel Feedwater Nozzle.Two Areas of Indications Identified.One Area Unacceptable Per ASME Section Iii.Nsss Vendor Will Grind Indications Off by mid-Sept.Final Rept by 801112

ML19327A543
Person / Time
Site:	Grand Gulf
Issue date:	07/30/1980
From:	Mcgaughy J MISSISSIPPI POWER & LIGHT CO.
To:
References
AECM-80-171, NUDOCS 8008060354
Download: ML19327A543 (2)

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jl ]I MISSISSIPPI POWER & LIGHT COMPANY

' Helping Build Mississippi P. O . B O X 16 4 0. J A C K S O N, MISSISSIPPI 39205 NUCLEAR PRCWCTICN CEPARTMENT July 30, 1980 Office of Inspection & Enforcement U. S. Nuclear Regulatory Ccemission Region II 101 Marietta Street, N.W.

Suite 3100 Atlanta, Georgia 30303 Attention: Mr. J. P. O'Reilly, Director

SUBJECT:

Grand Gulf Nuclear Station Units 1 and 2 Docket Nos. 50-416/4'17 File 0260/15525/15526 PRD-80/14, Status Report 12, Reactor Pressure Vessel.

Feedwater Nozzle Deficiency AECM-80/171 On April 7, 1980, Mississippi Power & Light Company notified Mr. F. Cantrell of your office of a Potentially Reportable Defi-ciency (PRD) at she Grand Gulf Nuclear Station construction site.

The deficiency concerns certain indications revealed during a liquid penetrant examination of the inner bore region of the N4-A Feedwater Nozzle on the Unit 1 Reactor Pressure Vessel (RPV). This examina-tion was performed as an augmented inservice inspection, pursuant

, to the requirements of NUREG-0312.

Two areas of indications have been identified. One area has been evaluated as acceptable per ASME Section III, NB-2546.3, 1974 Edition and applicable addenda. The second area, however, was eval-uated as unacceptable per ASME Section III, NE-2546.3(b)(4), 1974 Edition and applicable addenda.

The NSSS supplier has is' sued Field Deviation Disposition Request (FDDR) J31-216 to remove the indications by grinding. The corrective action has not been performed because personnel have not had access to the vessel. Repairs are scheduled to be completed by mid-September.

Our evaluation of the significance of the deficiency, had it remained uncorrected, is contingent on the extent of the indications which crn only be determined after the corrective action is complete.

Theretcre, we cannot determine reportability at this time. .

m S 8008060 Member Middle Souen utilities System Si/

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-- MISSISSIPPI POWER & LIGHT COMPANY Mr. J. P. O'Reilly- AECM-80/171 NRC Page 2

. We expect to determine reportability and submit a final report by November- 12, 1980.

Yours truly, J~

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[rJ.P.McGaughy,Jr.

' Assistant Vice President, Nuclear Production ATR:st cc: Mr. N. L. Stampley Mr. R. B. McGehee Mr. T. B. Conner Mr. Victor Stello, Director Division of Inspection & Enforcement U..S. Nuclear Regulatory Commission Washington, D.C. 20555 O O 1

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