ML20054F615

Testimony of Jh Williams Re Prairie Alliance Contention 6j Re Criteria Imposed Following Tmi.Prof Qualifications Encl

ML20054F615
Person / Time
Site:	Clinton
Issue date:	06/11/1982
From:	Williams J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20054F597	List: ML20054F596 ML20054F601 ML20054F604 ML20054F609 ML20054F612 ML20054F615 ML20054F618 ML20054F622 ML20054F627
References
ISSUANCES-OL, NUDOCS 8206170158
Download: ML20054F615 (4)

Text

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o UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of ILLIN0IS POWER COMPANY, et al ) Docket No. 50-461 OL i )

(ClintonPowerStation, Unit 1) )

NRC TESTIMONY OF J. H. WILLIAMS REGARDING CRITERIA IMPOSED FOLLOWING TMI

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(Prairie Alliance Contention 6j)

Q. Please state your name and position with the NRC, A. My name is J. H. Williams. I am employed as a Licensing Project Manager for the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Licensing, Standardization and '

Special Projects Branch. A copy of my professional qualifications is attached.

J Q. What is the purpose of your testimony?

l A. The purpose of this testimony is to respond to Prairie l

l Alliance Contention 6j, which reads as follows:

"The design and fabrication of the CPS control room layout and instrumentation have not been modified to meet current regulatory requirements in NUREG-0660, -0694, -0737. Specifically:

(j) The FSAR contains no documentation of how the power station can or will be modified to meet the new criteria imposed following the TMI accident.

Q. Does the FSAR contain documentation of how the power station will be modified to meet the new criteria imposed following the TMI accident?

I 8206170158 820611 PDR ADOCK 05000461 l T PDR 1

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A. Yes, Amendment No. 7 to the FSAR contained information on how the station would be modified to meet the new criteria imposed following the THI accident. The Stuff has reviewed this information and documented its review in the Clinton SER, NUREG-0853. Table 1.1 of the SER lists each TMI requirement and identified the section where the item is discussed. For example, reading from this table:

I.C.4 - Control room access is discussed in Section 13.5 I.D.1 - Control room design reviews are discussed in Section 18 I.D.2 - Plant safety parameter display console is discussed in Section 7.5.2.3

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMISSION 4

BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of i

) ILLIN0IS POWER COMPANY, et _al Docket No. 50-461 OL (Clinton Power Station, Unit 1) )

NRC TESTIMONY OF J. H. WILLIAMS REGARDING NRC REQUIREMENTS FOR CONTROL-R0OM DESIGN (Prairie Alliance Contention 6f)

Q. Please state your name and position with the NRC.

A. My name is J. H. Williams. I am employed as a Licensing Project Manager for the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Licensing, Standardization and i special Projects Branch. A copy of my professional qualifications is attached.

Q. What is the purpose of your testimony?

A. The purpose of this testimony is to respond to Prairie Alliance Contention 6f, which reads as follows:

i "The design and fabrication of the CPS control room layout and instrumentation have not been modified to meet current regulatory requirements in NUREG-0660, -0694, -0737. Specifically:

(f) IP has not demonstrated its ability to comply I with current NRC requirements for overall control-room design standards.

Q. Has IP demonstrated its ability to comply with current NRC requirements for overall control-room design standards?

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A. Yes, IP has demonstrated its ability to comply with current 3 NRC requirements for overall control-room design standards.

! In particular, IP has demonstrated its ability to comply with current NRC requirements for overall control-room design as evidenced by the results of the NRC review in this area reported in the SER for Clinton, NUREG-0835 dated February 1982. Specifically: Chapter 7,

" Instrumentation and Controls"; Chapter 18 " Control Room Design i

Review"; Section 6.4 " Control Room Habitability"; Section 6.5

" Engineered Safety Features Filter Systems"; Section 9.4 " Ventilation Systems"; Section 9.5 " Fire Protection Systems"; and Section 9.6 "Other Auxiliary Systems" documents this review. Chapter 1 of the SER summarizes the status of this review.

J. H. WILLIAMS STANDARDIZATION & SPECIAL PROJECTS BRANCH DIVISION OF LICENSING , , , . .

PROFESSIONAL QUALIFICATIONS I am employed as a Project Manager in t.he Standardization & Special Projects Branch of the Division of Licensing. Since May 1981, when I was hi' red by

- the USNRC, I have been assigned to work on the Clinton Project as Licensing Project Manager.

As the Clinton Project Manager for the USNRC, I have responsibilities for '

the management and coordination of the safety and environmental reviews associated with the Operating License application. I am responsible for preparing the staff's Safety Evaluation Report and Environmental Impact Statements using inputs prepared by the technical review branches.

I hav'e over nineteen years experience in the riuclear industry. From 1971 until joining the USNRC, I was empicyed by the Tennessee Valley Authority as nuclear engineer working in the research and development area. This included work on light water reactors, breeders, and other advanced nuclear power concepts. I was employed by the U. S. Army Engineer Reactors Group for about seven years. My responsibilities during those seven years included reactor operations support, safety and engineering evaluations, health physics evaluations, environmental monitori'ng, and research. I was employed by the University of Florida as a Research Assistant in Engineering, responsible .

for the operations and mainten;nce of the Training Reactor Facility. In this position, I held a USAEC Senior Operator's License.

I hold a BS degree in Physics from Virginia Polytechnic Institute and a MS degree in Nuclear Engineering from the Catholic University of America. I have graduated from the Oak Ridge School of Reactor Technology, which is a year long graduate level program in nuclear safety and engineering. I have attended numerous other courses in nuclear engineering and safety over the y past nineteen years.

I am a member of the American Nuclear Society, the American Society of Mechanical Engineers and the Sigma Xi, The Scientific Research Society. I have served on technical committees of both the ANS and the ASME.

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