ML19327A490

Final Deficiency Rept Re Inadequate QA Program by Valve Suppliers for Nonpressure Retaining Parts & Components.Qa Programs for All Suppliers of Nonpressure Retaining Parts Have Been Approved as Complying W/Applicable Codes

ML19327A490
Person / Time
Site:	Grand Gulf
Issue date:	07/28/1980
From:	Mcgaughy J MISSISSIPPI POWER & LIGHT CO.
To:
References
AECM-80-167, NUDOCS 8008060257
Download: ML19327A490 (3)

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MISSISSIPPI POWER & LIGHT COMPANY i ]

Helping Build Mississippi P. O. S O X 16 4 0, J ACKSON, MISSISSIPPI 39205 umA PAcoucTICN CEPARTMENT July 28, 1980 Office of Inspection & Enforcement U. S. Nuclear Regulatory Coc: mission Region II 101 Marietta Street, N.W.

Suite 3100 Atlante, 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-80/07, Final Report, Inade-quate QA Program for Nonpressure Retaining Parts & Components AECM-80/167

References:

1) AECM-80/70, 4/4/80

2) AECM-80/111, 5/23/80

3) AECM-80/143, 6/27/80 During an inspection at the Grand Gulf Nuclear Station construc-tion site on March 6, 1980 your Mr. M. Gouge identified, as reporta-ble, a deficiency which had previously been determined as not repor- l table by our Architect / Engineer in their Management Corrective Action Report (MCAR) GGNS Number 41. The deficiency pertains to the lack of a Quality Assurance program by valve suppliers for nonpressure retaining parts and components.

We have since determined that this condition is not reportable within the meaning of 10CFR50.55(e). Our final report is attached.

Yours truly, f # y J. Assistant P. McGaughy, Vice President, Jr.

Nuclear Production O/7 ATR:st Attachment /

cc: Mr. N. I.. Stampley Mr. Victor Stello, Director Mr. R. B. McGehee Division of Inspection & Enforcement Mr. T. 3. Conner U. S. Nuclear Regulatory Co= mission Washington, D.C. 20555 g ooso e o.25 7 M * * "d d '

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Attachm:nt to AECM-80/167 s

• Paga 1 of 2 FINAL REPORT FOR PRD-80/07 I. Description of Deficiency i

An audit of a valve supplier in January, 1978, identified a problem with the supplier's control of non-pressure retaining parts or components. The supplier did noc btve a QA program for the control of these items. Our Architect / Engineer initiated an investigation which determined that a like condition existed for other suppliers of non-pressure retaining parts or components.

Upon concluding the investigation, the Architect / Engineer deter-mined the condition to be not reportable and documented the ra-tionale in MCAR GGNS-41. However, during an NRC inspection at the construction site, the rationale used for determination of non-reportability was questioned and the investigation was re-opened.

II. Safety Implications Thirty (30) specifications, involving twenty-seven (27)-different suppliers of non-pressure retaining parts or components, were reviewed to determine the extent of the problem. Eighteen (18) suppliers were found to have programs in compliance and nine (9) suppliers were found to have programs not in compliance with ASME Section III and ANSI-N45.2. Of the nine suppliers determined to not have QA programs, the Architect / Engineer determined that five (5) imposed controls from their approved ASME Section III ~

QA programs on non-pressure ASME parts and two (2) had complied with unapproved quality programs which were subsequently approved without significant changes. Of the remaining two (2) suppliers, one (1) was found to have been operating to an unapproved revision to his QA manual and had not specified applicable portions of ANSI-N45.2 for the procurement of some items. The revision to the QA Manual was subsequently approved and additional investi-gation determined that there was sufficient objective evidence of the control of procurement documents issued by this supplier.

The remaining supplier was found to have provided sixteen (16) valves for Units I & II of which ten (10) were determined to not adversely affect safety. The remaining six (6) valves, which could have adversely affected safety, were determined to have been assembled after approval of the supplier's QA program which includes provisions for identification and control of material.

Hence, it has been determined that, had the condition remained uncorrected, there would be no adverse impact on the safety of operations of the nuclear power plant throughout its lifetime.

III. Corrective Actions Taken QA Programs for all the suppliers of non-pressure retaining parts ,

or components have been approved as ccmplying with ASME Section III and ANSI-N45.2.

Attachment to AECM-80/167

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, Pags 2 of 2 The Architect / Engineer has established an engineering procedure by which ASME III Supplier QA Programs are critiqued to ensure that the non-pressure retaining parts and components are in compliance with requirements.

The Architect / Engineer has added an audit checklist to verify ap-proval of the Supplier's QA Program for the control of non-code safety related items, ccmponents, parts, and/or material; and to verify implementation of a QA program to control non-code safety related items, components, parts, and/or materials.

Details of the investigation and corrective action are available at the construction site in Bechtel MCAR GGNS-41.

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