ML20003D944

Part 21 Rept Re Reactor Controls,Inc Issuance of Drawings Prior to Verification of Design Adequacy.Caused by Lack of Requirement for Providing Objective Evidence of Design Adequacy Verification.Final Rept by 810806

ML20003D944
Person / Time
Site:	Grand Gulf
Issue date:	03/16/1981
From:	Mcgaughy J MISSISSIPPI POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
REF-PT21-81-388-000 PT21-81-388, PT21-81-388-000, NUDOCS 8104010567
Download: ML20003D944 (4)

Text

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 #UsO[[vNNN[                                               March 16, 1981 Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission 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. 50-416/417 File 0260/15525/15526 PRD-80/60, Status Report #3, RCI Design Drawing Verification AECM-81/110 On September 25, 1980, Mississippi Power & Light Company notified Mr. M. liunt, of your office, of a Potentially Reportable Deficiency (PRD) at the Grand Gulf Nuclear Station (GGNS) construction site. The deficiency concerns teactor Controls, Inc. (RCI) issuance of drawings prior to verification of usign adequacy. Our investigations into reportability under 10CFR50.55(e) and 10CFR21 continue. As is outlined in our status report, attached, we expect to provide our final report by August 6, 1981. Yours truly,

                                              /      J. P. McCaughy, Jr.

CWH:mt Attachment cc: See page 2 . i l l l Member Middle South Utilities System

MIL 71551PPI POWER Q LIGHT COMPANY Mr. ; J. P. O'Reilly ' AECM-81/110 t NRC- Page 2 , cc: Mr. N. L. Stampley i Mr. R. B. McGehee

Mr. T. B. Conner Mr. Victor Stello, Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555

                      'Mr. G. B.. Taylor South Miss. Electric Power Association P. O. Box 1589 Hattiesburg, MS 39401 i

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nr STATUS REPORT #3 TO PRD-80/60 I. i=W-i ~ Description of the Deficiency

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u. Tid [$[ . Design adequacy verification was not performed by Reactor C\ 7[g. (RCI) prior component to issuance supports. of drawings for fabricationsaand in t ll ation of

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Hydraulic System (Cil) and the Neutron Monitoring Units I and 2 are affected. The impact on safety has not been . Both Syste determined. II. _ Approach to Resolution of Problem E This deficiency was caused by a lack of a RCI program requi rement for providing objective evidence of design adequacy verification Any design activity performed by RCI could be involved . design issuance. documents for evidence of design s on adequac on prior to Our constructor has issued a Stop Work on any safety relat d performed by RCI until verification of design adequacy substantiated. e work has tobebe en RCI will evaluate the condition for effect on safetyantof pl opera tions. III. _ Status of Proposed Resolution effects on safety caused by this condition.Our on of theArchitect / The present "as-built" condition that do not will meetbe re-analyzed using "new loads" criteria. loads. Any supports the new loads criteria will be anal This re-evaluation is currently in progress.yzed to the original complete place. and accepted by our constructor, Until it is the Stop Work uill remain in IV. Reason for Delay in Final Report RCI is re-evaluating effects on safety. V. i Date When Final Report Will Be Submitted We project that corrective actions will be completed and of reportability under 10CFR21 and 10CFR50 35(e) a determination be made by A 1981, the date we project for our final response. ugur.t 6, s

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