ML20024C034
| ML20024C034 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 07/08/1983 |
| From: | Ignatonis A, Spraul J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| Shared Package | |
| ML20024C019 | List: |
| References | |
| NUDOCS 8307120193 | |
| Download: ML20024C034 (8) | |
Text
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
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UNITED STATES DEPARTMENT OF ENERGY
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Docket No. 50-537 PROJECT MANAGEMENT CORPORATION
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TENNESSEE VALLEY AUTHORITY
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(Clinch River Breeder Reactor Plant
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NRC STAFF TESTIMONY OF JOHN G. SPRAUL AND ALGIS J. IGNAT0NIS ON BOARD QUESTION 6 CONCERNING QUALITY ASSURANCE
- 01. Please state your names, by whom are you employed and the nature of your responsibilities regarding Clinch River Breeder Reactor ("CRBR")?
A1. My name is John G. Spraul.
I am a Quality Assurance Engineer (Nuclear) in the Quality Assurance (QA) Branch of the Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission.
I reviewed and evaluated the QA programs of the CRBR Applicants and their principal contractors.
My name is Algis J. Ignatonis.
I am a Project Engineer for the Region II office of the U. S. Nuclear Regulatory Comission.
I am responsible for inspectinn activities at CRBR, and have assisted in the development of the inspection program for CRBR.
Q2. Gentlemen, have you prepared a statement of professional qualifica-tions?
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A2. Yes. Copies of our professional qualifications statements are l
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2 Q3. What is the purpose of your testimony?
A3. My testimony addresses the concern raised by the Atomic Safety and Licensing Board (" Board") in Board Question.6, which states as follows:
The SER discussion of quality seems to emphasize quality assurance and the various separate contractor organiza-tions that will implement it. Does the staff consider that QC responsibilities and activities are separate from QA or an integral part thereof? The staff is requested to discuss its answer to this question and to explain briefly how it will monitor QA and QC efforts for adequacy.
Q4. Please define the terms " quality assurance" and " quality control".
A4. Appendix B provides the following definitions:
As used in this appendix, " quality assurance" comprises all those planned and systematic actions necessary to provide adequate confidence that a structure, system, or component will perform satisfactorily in service. Quality assurance includes quality control, which comprises those quality assurance actions related to the physical characteristics of a material, structure, component, or system which provide a means to control the quality of the material, structure, component, or system to predetermined requirements.
Q5. Does the Staff consider QC responsibilities and activities to be an integral part of QA?
A5. Yes. This is consistent with the Introduction to Appendix B, quoted above, which states: " Quality assurance includes quality control...."
Q6.
Is the QC function treated as an integral part of the QA programs of l
l the CRBR Applicants and their principal subcontractors?
A6. Yes. The QA programs for CRBR are described in Section 17 of the CRBR Preliminary Safety Analysis Report ("PSAR"). As set forth in l
the PSAR, the Applicants and their principal contractors are either directly responsible for QC functions and activities, or have ade-quate controls over QC functions and activities, to assure that they are properly performed. The Staff's evaluation of the adequacy of the CRBR QA and QC commitments is set forth in Section 17 of the CRBR Safety Evaluation Report ("SER")( NUREG-0968, March 1983).
Q7. Will the Staff monitor QA and QC activities throughout the construction of CRBR?
A7. Yes.
In this regard, it should be noted that QA/QC is the responsibility of the Applicants; the Staff's QA/QC responsibility is to review the Applicants' QA/QC plan and to audit its implemen-tation.
In order to monitor QA and QC efforts for adequacy, the Staff is developing a construction inspection program for the CRBR.
The program will be based on the Staff's IE Manual for construction inspection of light water reactors, modified as necessary to be appropriate for the CRBR. Staff inspection procedures have been developed for the pre-construction permit ("CP") phase of the work, with inspections starting in the first half of 1983.
(The Staff performed a number of CRBR inspections during 1976-1977.) Upcoming Staff inspections will be "after-the-fact" inspections concerning design and manufacturing of completed components and equipment, and the storage of those components and equipment. The Staff expects that these inspections will involve reviews of documentation by Applicants and their contractors as to procedures, inspection and test reports, manufacturing data, " shop travelers", design review
reports, specifications, drawings and other such records. Subse-quent Staff inspections will focus on site preparation, Applicants' site surveillance program, foundations, environmental protection, and subsequent activities as work progresses. The Staff will also inspect fuel fabrication activities.
Furttier information concerning the Staff's QA/QC inspection program is set forth in Section 17.5 of the CRBR SER.
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JOHN G. SPRAUL PROFESSIONAL QUALIFICATIONS QUALITY ASSURANCE BRANCH OFFICE OF INSPECTION AND ENFORCEMENT
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I am a Quality Assurance Engineer in the Quality Assurance Branch in the Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission.
In this position, I am responsible for the review and evaluation of appli-cants' descriptions of quality assurance programs proposed for the design, construction, and operation of nuclear power plants as assigned to me.
I received a Bachelor of Chemical Engineering degree from the Georgia Institute of Technology in 1951.
In 1971, I completed the requirements for the Professional Designation in Quality Control at the University of California, Los Angeles. My nuclear experier.ce prior to joining the NRC includes 2 years of engineering work in gaseous diffusion with the Good-year Atomic Corporation and 12 years of nuclear fuel and nuclear power plant component design, manufacture, and testing with the Atomics Inter-national Division of Rockwell International. My quality assurance experience prior to joining the NRC includes 2 years as Chief Inspector and 4 years as Director of Quality Assurance at Atomic International, where I was responsible for managing the entire quality assurance program.
I joined the Quality Assurance Branch of the NRC in 1974. Since joining the NRC, I have reviewed the quality assurance program descriptions for l
design and construction reports on quality assurance submitted by utilities, architect-engineers, NSS suppliers, and constructors.
I am a member of the American Nuclear Society and a senior member of the American Society for Quality Control.
In 197?, I was certified as a Quality Engineer by the American Society for Quality Control.
(i This certification has been renewed to cofer the 1983-1985 time period.
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a-PROFESSTONAL QUALIFICATIONS ALGIS J. IGNAT0NIS My name is Algis J. Ignatonis. I am employed by the U. S. Nuclear Regu-latory Commission, Region II, as a Project Engineer.
My primary assignment as a Project Engineer is to perform inspections of nuclear power reactor facilities during the construction, startup and operational phases. My duties include the review and evaluation of appli-cant and license management and their organization; implementation of procedures and practices and their effect on the safety of plant opera-tion; and compliance with licensed conditions, rules, orders, and regula-tions. This responsibility includes the auditing of licensees' and appli-i cants' quality assurance programs for the construction and operation of their nuclear power plants.
I coordinate the inspection efforts of resi-dent and region-based inspectors and consultants for assigned and special inspections.
In my present assignment as project engineer, I am responsible for inspec-l tion activities at four nuclear power plant sites (7 reactors), including the Clinch River Breeder Reactor (CRBR). Five units are operational and two are under construction (not including the CRBR). I have assisted in the developnent of the inspection program for CRBR.
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I Also, during my current assignment I have had dual responsibilities through April 1983 as an Acting Section Chief.
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I have been employed with the Nuclear Regulatory Comission since September 1974. My major duties perfomed during this tenure are as follows:
October 1980 Senior Resident Inspector at Turkey Point.
to August 1981 April 1979 Detailed to the Three Mile Island Technical to Support Task Force as a Senior Reactor Engineer September 1980 following the March 28, 1979 accident. Respon-sibilities included:
(1)analysisofplant conditions and proposed changes in system design or operation mode; (2) review of standard opera-ting procedures, emergency procedures, and Technical Specification Surveillance proce-dures; and (3) design review of plant modifica-tions for maintaining reactor coolant system pressure and core cooling, containment cleanup, and recovery operations.
March 1978 Perfomed reactor systems plant reviews for to the Grand Gulf, Susquehanna, and WNP-2 OL April 1979 applications.
In addition, I participated in the Systematic Evaluation Program, reviewing older vintage design plants, in particular the Palisades plant and San Onofre Unit 1.
Also, I perfomed primary review and coordinated staff review on the generic safety issue of reactor coolant pump overspeed following a loss-of-I coolant accident.
March 1977 Perfomed similar work as stated above, except to plant reviews included the Sundesert Nuclear March 1978 Plant (CP application) and the Fast Flux Test Facility (OLapplication).
Served on the Power Burst Facility Program l
(fuel research) review group representing NRR's viewpoint for reactor system licensing l
needs in research.
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September 1974 Reviewed GESSAR and Hartsville PSAR applications to and plant reloads. Also, served as the princi March 1977 pal reviewer for the GE GETAB application to licensed operating plants, and CP and OL applications.
Prior to my employment with the Nuclear Regulatory Commission I was employed by NASA, Marshall Space Flight Center for eight years. My duties included performance n* technical investigations in the analysis and support testing of environmental control and life support systems for Skylab, Apollo, and Saturn IB/V Instrument units.
I reviewed contractor work engaged in design, development, manufacture, and testing of environmental control hardware.
I was extensively involved in testing of equipment.
I graduated from Illinois Institute of Technology, Chicago, Illinois, in 1965 with the degree of Bachelor of Science in Mechanical Engineering.
In 1974 I graduated from University of Alabama in Huntsville, Alabama with the degree of Master of Science.
I have also taken graduate courses in reactor safety and nuclear reactor theory at the Catholic University in Washington, D.C., and have successfully completed appropriate NRC inspector training courses.
I am a member of the American Society of Mechnical Engineers.'
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