ML20023C078
| ML20023C078 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 05/05/1983 |
| From: | Haass W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| Shared Package | |
| ML20023C059 | List: |
| References | |
| NUDOCS 8305090632 | |
| Download: ML20023C078 (5) | |
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Mitter of
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TEXAS UTILITIES GENERATING Docket Nos. 50-445 COMPANY, et al.
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50-446
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(Comanche Peak Steam Electric
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Station, Units '. and 2)
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AFFIDAVIT OF WALTER P. HAASS I, Walter P. Haass, being duly sworn, do depose and state:
Q1. By whom are you employed and what is the nature of the work you perform?
A1.
I am employed by the U.S. Nuclear Regulatory Comission, Office of Inspection and Enforcement, where I am Deputy Chief of the Quality Assurance Branch, and the Acting Section Leader of the Licensing Section. A copy of my statement of qualifications is attached to this affidavit.
Q2. What is the nature of the responsibilities you have regarding the Comanche Peak Steam Electric Station ("CPSES")?
A2. My responsibilities include overseeing the review of the Quality Assurance ("QA") program description for the operations phase for Comanche Peak. This review entails Section 17.2 of the Final Safety Analysis Report ("FSAR") in addition to the QA list of structures, systems and components to which that program applies.
This review is in accordance with Section 17.2 of the Standard Review Plan, NUREG-75/087 8305090632 830505
{DRADOCK 05000445 PDR
-),
Q3. What is the subject matter of your affidavit?
A3. I will address Dr. Jordan's question regarding how the Staff has interpreted 10 C.F.R. Part 50, Appendix B at Comanche Peak. Speci-fically, Dr. Jordan wants to know "how the staff and applicant have interpreted Appendix B at Comanche Peak; namely does it apply only to safety-related equipment or does it apply to all equipment important to safety." Dr. Jordan cited the "Denton memo of November 20, 1981" and Board Notification 83-13. See Transcript of Telephone Conference Call, April 7, 1983, at 31.
Q4. Has the staff interpreted Appendix B to 10 C.F.R. Part 50 to apply only to safety-related equipment or does it apply to all equipment important to safety?
A4. The staff has and continues to interpret Appendix B to 10 C.F.R.
l Part 50 as applicable only to safety-related structures, systems, and components. The staff at this time has not developec; QA criteria that are applicable to the remaining set of structures, systems and components that are "important to safety." The definition of terms for the above is consistent with the Denton memorandum (" Memorandum For: All NRR Personnel, From: Harold R.
Denton, Director, Office of Nuclear Reactor Regulation,
Subject:
" Standard Definition for Commonly-Used Safety Classification Terms,"
l November 20,1981).
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The above statements and opinions are true and correct to the best of my personal knowledge and belief.
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Walter P. Haass Subscribed and sworn to me this f day of May, 1983 I'dt lkSE k bNI ti Notary Public 9)lf8(o My Commission expires:
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t WALTER P. HAASS PROFESSIONAL QUALIFICATIONS DEPUTY CHIEF, QUALITY ASSURANCE BRANCH DIVISION OF QUALITY ASSURANCE, SAFEGUARDS, AND INSPECTION PROGRAMS 0FFICE OF INSPECTION AND ENFORCEMENT U.S. NUCLEAR REGULATORY COMMISSION My name is Walter P. Haass.
I am the Deputy Chief, Quality Assurance Branch, Division of Quality Assurance, Safeguards, and Inspection Programs in the Office of Inspection and Enforcement, U.S.
Nuclear Regulatory Commission (NRC).
I am also the Section Chief (Acting) of the Licensing Section within the Quality Assurance Branch.
My duties ard responsibilities are to direct, supervise, and coordinate the review of nuclear power plant license applications and topical reports to determine compliance with the Commission's quality assurance criteria stated in Appendix B to 10 CFR Part 50 for plant design, construction, and operation to assure protection of the public health and safety.
I received a Bachelor of Science degree in Mechanical Engineering from Stevens Institute of Technology in 1952.
Upon graduation, I joined the Westinghouse Electric Corporation with an initial assignment on the Graduate Student Training Program. As part of this program, I spent one year at the Oak Ridge School of Reactor Technology. My next assignment was at the Atomic Power Division where I was engaged in the thermal-hydraulic and systems analysis aspects for the design of proposed nuclear power plants.
In 1959, I accepted a position at the Martin Marietta Corporation, Nuclear Division. My activities included project engineering work on
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the mechanical design aspects of the PM-1 and PM-3A portable nuclear power plants at Sundance, Wyoming and McMurdo Sound, respectively; and program management work for several radioisotopic SNAP programs including SNAP-11 and SNAP-13.
In 1968, I joined the Atomic Energy Commission's regulatory staff (now NRC) as a licensing program manager (LPM) responsible for overall management of the staff's review of several nuclear power plant applica-tions for construction permits.
I was also involved in the development of guidance for the review of quality assurance program descriptions based on the QA criteria given in Appendix B.
In 1972, I became the Technical Assistant for Boiling Water Reactors (BWRs), reporting to the Assistant Director for BWRs.
In 1974, I was assigned to the position of Special Assistant for Standardization with the responsibility for developing the programmatic requirements for the licensing of standardized nuclear power plants.
In June 1978, I was appointed to the position of Chief, Quality l
Assurance Branch in the Division of Engineering, Office of Nuclear Reactor Regulation. My duties and responsibilities were to direct, supervise, and coordinate the review of nuclear power plant license applications and topical reports to determine compliance with the Commission's quality assurance criteria stated in Appendix B to 10 CFR Part 50 for plant design, construction, and operation to assure protection of the public health and safety.
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