ML20133F147

Affidavit of Eh Girard Re Applicant Motion for Summary Disposition of Joint Intervenors Contention 8 Concerning Qa. No Programmatic Breakdown in Qa/Qc Program at Facility Identified

ML20133F147
Person / Time
Site:	Vogtle
Issue date:	08/05/1985
From:	Girard E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20133F075	List: ML20133F072 ML20133F096 ML20133F120 ML20133F147 ML20133F161 ML20133F179 ML20133F206 ML20133F226 ML20133F235 ML20133F249 ML20133F269
References
OL, NUDOCS 8508080162
Download: ML20133F147 (6)

Text

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UNITED STATES OF AMERICA

,, NUCLEAR REGULATORY COMMISSION

. BEFORE THE ATOMIC SAFETY AND LICENSING BOARD Nh In the Matter of  : '85 AUG -7 A10:56 GEORGIA POWER COMPANY,  : Docket Nos(p . y  :.

ej al.  : 50-424anddo-424fg$.,l g'

BRAMH (Vogtle Electric Generating  :

Plant, Units 1 and 2)  :

AFFIDAVIT OF EDWARD H. GIRARD EDWARD H. GIRARD, states under oath that:  :

1. My name is Edward H. Girard. My business address is U. S. Nuclear Regulatory Comission,101 Marietta Street, Suite 2900, Atlanta, GA 30323.

I am employed as a Reactor Inspector for the Nuclear Regulatory Comission, Region II. In that position, my responsibilities primarily involve inspec-tions and evaluations of nuclear power plant work and programs in the areas of welding, nondestructive examination and pump and valve testing.

A sumary of my professional qualifications is attached.

2. I make this Affidavit with regard to the Applicants' Motion for Sumary Disposition of Joint Intervenors' Contention No. 8 (Quality Assurance). I have personal knowledge of certain related matters, as stated herein, which

! believe to be trae and correct. These matters, which I will address in the following paragraphs, are the August 22, 1983 meeting (regardingPullman quality control inspectors) and liquid penetrant examination deficiencies g5[0 p Q

5 (described with reference to coolant and containment systems) as referred to by the Tntervenors.

The August 22, 1983 Meeting Regarding Pullman QC Inspectors -

3. Based on discussions with the NRC personnel who were present, I understand that the August 22, 1983, meeting partly addressed a matter in which I had subsequent involvement. That is the matter of the alleged harassment and intimidation of Pullman Power Products (PPP) quality control (QC) inspec-tors. Prior to the subject meeting the NRC had received and performed an investigation of allegations of harassment and intimidation of PPP QC inspectors. The investigation was performed and documented by the NRC Office of Investigations (01). Georgia Power Company (GPC) conducted their own broad investigation and their findings were described to NRC management during the August 22 meeting.

4 Having reviewed both the NRC 0! findings and the GPC findings reported in the August 22 meeting, NRC Region !! management determined that additional NRC followup inspection of the concerns should be undertaken. Prior to initiation of this followup, the PPP manager, who was allegedly the primary source of the harassment and intimidation, was removed from the project.

5. I was assigned to perform the initial followup inspection. Evidence of harassment and intimidation of QC inspectors by PPP construction management had been confirmed and docun.ented in the NRC 0! investigation. My inspec-tion included interviews with a number of PPP QC inspectors.

6. The PPP QC inspection personnel I interviewed, generally indicated that they i' no longer' felt intimidated or harassed by the Project Manager or other craft l

l supervisors or personnel. No evidence of any hardware deficiencies attrib-uted to the harassment and intimidation was found during my followup inspec- -

tion or extensive related followup inspections, i

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7. The results of my inspection are reported in NRC Inspection Report No.

l 50-424,425/84-05.

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Coolant and Containment Systems

8. I have direct knowledge of the matter of the licensee's failure to specify "

liquid penetrant examination for reactor coolant pressure boundary welds, in that I found the omission and documented it as a violation in Inspection i Report 50-424/83-15. I also was responsible for closing this violation in Report 50-424/84-12. There was no evidence of any widespread or serious deficiency in the GPC QA program indicated by the penetrant examination omission. Other inspection requirements were satisfactorily specified and the omission appeared to be the result of a relatively isolated error.

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9. Based on a review of examples of related documentation and discussions with some of the involved personnel, I found that GPC had investigated the item to i

assure that it was not indicative of a generic problem and that they had j promptly corrected the example identified. This violation had no relation

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to the other liquid penetrant examination violation referred to in the Intervenors' petition or the supplement thereto.

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The other violat,lon, identified by the intervenors, involved a different organization working to a different CC program and procedures.

This viola-tion is discussed in the offidavit of Wilbert F. Sanders.

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In sumary, based on ry knowledg2 described above on the specific issues raised by Intervenors, and based Uri fly OV4PA11 knowledge of CA/QC activities at Plant Vogtle as applied to my areas of expertise as set forth above, I do not believe there has been a progaamatic breakdown in the QA/QC program at Vogtle.

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J PROFESSIONAL QUALIFICATIONS U.S. NUCLEAR REGULATORY COMMISSION - REGION II

, , . Edward H. Girard My name is Edward H. Girard. My business address is 101 Marietta Street, NW, Suite 2900, Atlanta, Georgia 30323. I am employed by the United States Nuclear Regulatory Commission, Region II, as a Reactor inspector in the Materials and -

Processes Section of the Engineering Branch, Division of Reactor Safety.

I graduated from Georgia Institute of Technology in Atlanta, Georqia in 1959 with the degree of Bachelor of Ceramic Engineering and obtained a Master of Science degree in Metallurgy from the same institution in 1963. I am a member of the American Welding Society; the American Welding Society Sebcommittee D14A on Welding of Industrial and Mill Cranes; and the American Society of Mechanical Engineers Committee on Cra.1es for Nuclear Facilities.

From 1959 to 1961, I was employed as a Ceramic Engineer in the Research Depart-ment of the Carborundum Company in Niagara Falls, New York. My primary functions included research on refractory glass fibers and refractory hard metals.

From 1961 to 1963, I attended college, as described previously, and worked part time with an assistantship in the X-ray Diffraction Lab at Georgia Tech.

From 1963 to 1966. I was a Metallurgist at the Metals and Controls Division of Texas Instruments in Attleboro, Massachusetts where my duties included conducting programs on development of protective coatings for refractory metals, ceramic-metal joining research, and supervision of the Research Department's metallo-graphy laboratory.

From 1966 to 1967, I was employed as a Senior Metallurgist at Jim Walter Research Corporation in Des plaines, Illinois. I worked on development of fiber glass insulation and ceramic acoustical tile manufacturing processes.

From 1966 to 1971, I was employed as a Senior Metallurgist at the General Atomic Company in San Diego, California. I was responsible for various materials engineering process development activities (brazing, welding, adhesive bonding, powder metallurgy, cleaning and coatings) for use in nuclear fuel manufacture and production of a nuclear powered direct energy conversion generator.

From 1971 to 1972, I continued my employment at the General Atomic Company in the position of a QA Engineer responsible for auditing processing and records in manufacture of nuclear reactor fuel elements.

From 1972 to 1976, I continued my employment with the General Atomic Company as a Senior Engineer /QA Engineer responsible for review and approval of customer and internal documents involving welding, heat treatment, and other special process requirements. I also served a coqnizant QA engineer on various programs for manufacture of ASME B&PV Code (Section !!! and VI!!) and RDT (Reactor Development andTechnology)vesselsandANSIB31.1 piping.

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From 1976 to 1978, .I was employed as a Senior Engineer at the Westinghouse-owned i Offshore Power Systems in Jacksonville, Florida. I was responsible for i development tl materials and processing requirements for nuclear plant compo-nents, piping and supports.

In 1978, I accepted a position as a Reactor Inspector with the U.S. Nuclear Regulatory Commission. My duties since joining the NRC have primarily involved .

inspections, and evaluations related to fabrication, inspection and testing of 3 nuclear components and systems - with particular attention directed to welding, nondestructive examinations, and pump and valve testing. The results of the inspection and evaluations which ! performed are documented in inspection reports issued by Region !! and in Safety Evaluation Reports issued by the Division of -

Licensing.

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