ML20049F931
| ML20049F931 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/30/1981 |
| From: | Jensen W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20049E246 | List: |
| References | |
| NUDOCS 8110020426 | |
| Download: ML20049F931 (4) | |
Text
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION I
BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of METROPOLITAN EDIS0N COMPANY ET AL.
Docket No. 50-289 (Restart)
(Three Mile Island Nuclear Station Unit 1)
AFFIDAVIT 0F WALTON L. JENSEN, JR 1.
I, Walton L. Jensen, Jr., being duly sworn, depose and state that: I am a senior engineer assigned to the Reactor Systenis Branch, Division of Systems Integration, Office of Nuclear Reactor Regulation of the U.S. Nuclear Regulatory Commission.
I am currently responsible for the branch review associated with TMI-1. A copy of my professional qualifications is attached.
2.
I testified at the hearing with regard to UCS contention Number 5 concerning i
the PORV and block valve. My position as reflected in my testimony is that the function of the PORV is to prevent unnecessary opening of pressurizar safety valves and to provide a backup means of depressurization and of low temperature overpressure protection, also, that the proper operation of the PORV and block valve is not required to mitigate the consequences of any design basis accident.
l 8110020426 810730 PDR ADOCK 05000289 PDR O
' 3.
I was not aware of the Memorandum from J. M. Allan NRC, Region I, to N. C. Moseley, October 16, 1979,
Subject:
Operations Team Recomendations -
IE/TMI Unit 2 Investigation (Martin Report). However, I have examined the information in the Martin Report cited by UCS relevant to the matters about which I testified at the hearing (Recomendation C.I.C.2, "Electromatic Pressurizer Relief Valve, RC-R2", and Recommendation C.I.C.3, " Pressurizer Block Valve", RC-V2).
I have considered the Martin Report information and recommendations and find they do not affect my tecnnical position as reflected in my testimony at the hearina. The statement in Martin Report Recomendation C.I.C.2 that "This valve (PORV) as attached to the pressurizer prevents a potential single failure when needed to protect against overpressurization at low temperature" is not applicable to TMI-1. The NRC Safety Evaluation of Amendment No. 56 to the TMI-1 license concludes that either the operetion of the PORV or operator action would limit RCS pressures below Appendie G litits and that "The TMI-1 (Overpressure Migatigating Sys um) OMS is both redundant and functionally diverse."
l 4.
Accordingly, my direct testimony on UCS contwtion 5 would be unaffected by the Operations Team Recomendations of the Martin Report.
The above statements are true and correct to the best of my personal knowledge and belief.
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VA-eAM
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g, v S Walton L. Jensen, Jr.
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.n. fau %
w' J dy L.y' Butts, Notary Public l
Subscribed & sworn to i
before me thi: 30th My Commission Exoires: July 1, 1982 day of September,1981.
~
fi WALTON L. JENSEN, JR.
PROFESSIONAL QUALIFICATIONS g
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I am a Senior Nuclear Engineer in the Reactor Systems Branch of the Nuclear Regulatory Commissinn.
In this position I am responsible for the technical analysis and evaluaticr, of the public health and safety aspects of reactor systems.
Frcm June 1979 to December 1979, I was assigned to the Bulletins and Orders Task Fnrce of the Nuclear Regulatory Commission.
I participated in the preparation of NUREG-0565, " Generic Evaluation of Small Break Loss-of-Coolant Accident Eehavior in Babcock & Wilcox Designed 177-FA Operating Plants."
From 1972 to 1976, I was assigned to the Containment Systems Branch of the NRC/AEC, and from 1976 to 1979, I was assigned to the Analysis Branch of the NRC.
In these positior.s I was responsible for the development,and evaluation of computer programs and techniques to calculate the reactor system and containment system response to postulated loss-of-coolant accidents.
From 1967 to 1972, I was employed by the Babcock and Wilcox Company at Lynchburg, Virginia.
There I was lead engineer for the development of loss-of-coolant computer programs and the qualification of these programs by comparison with experimental data.
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From 1963 to 1967, I was employed by the Atomic Energy Commission in the Division of Reactor Licensing.
I assisted in the safety reviews of large power reactors, and I led the reviews of several small research reactors.
I received an M.S. degree in Nuclear Engineering at the Catholic University of America in 1968 e.nd a B.S. degree in Nuclear Engineering at Mississippi State University in 1963.
I am a graduate of the Oak Ridge School for Reactor Technology, 1963-1964.
I am a mecber of the American Nuclear Society.
I am the author of three scientific papers dealing with the response of B&W reactors to Loss-of-Coolant Accidents and have authored one scientific paper dealing with containment analysis.
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