ML20148M595
| ML20148M595 | |
| Person / Time | |
|---|---|
| Site: | Green County  |
| Issue date: | 11/07/1978 |
| From: | Watt J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20148M544 | List: |
| References | |
| NUDOCS 7811220077 | |
| Download: ML20148M595 (6) | |
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4 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
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POWER AUTHORITY OF THE STATE
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Docket No. 50-549 0F NEW YORK (Greene County Nuclear Power
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Plant)
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i SUPPLEMENTAL TESTIMONY OF NRC STAFF IN RESPONSE TO CITIZENS TO PRESERVE THE HUDSON VALLEY, STIPULATED CONTENTION I.B.4 (VALVE SUBMERGENCE) by 3
James J. Watt
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4 James J. Watt 1
Intervenor Citizens to Preserve the Hudson Valley has questioned 2
various design features and safety aspects of the proposed Greene 3
County Nuclear Power Plant. Tnis testimony addresses I.B.4 which 4
states:
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The Preliminary Safety Analysis Report ("PSAR") prepared 6
by the Applicant does not provide reasonable assurance, as 7
required by 10 CFR is 50.46 and 50.40 that (a) the health and 8
safety of the public will not be endangered, and (b) the Applicant 9
is financially qualified to engage in the proposed activities in 10 accordance with the Comission's regulations in the following gj respects...
B.
The PSAR is deficient with regard to its description 12 13 and analysis of the following design features or principal safety consideration as required by 10 CFR 550.34:
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The likelihood that valves designed to mitigate 15 accident consequences may become submerged during operation of 16 the Emergency Core Cooling System.
g The contention expresses a concern that valves required to perform 18 a safety function following an accident may be submerged during the g
Course of the accident. The assumption being that a submerged valve or more properly a submerged valve operator or valve motor will not operate.
23 The Applicant has assured the staff in response to question 212.35 24 that no safety related valve motors located inside containment will be 1
A
James J. Watt r
1 submerged following a loss-of-coolant accident. This will be accomplished 2
by locating valve motors above the maximum possible water level. The 3
final design will be reviewed for conformance at the operatinal if cense 4
stage.
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James J. Watt PROFESSIONAL QUALIFICATIONS I am employed as reactor engineer in the Reactor Systems Branch, Division of Systems Safety, Office of Nuclear Reactor Regulation.
My responsibilities include perfoming safety reviews and evaluations of applications for nuclear power plant construction pemits and operating licenses.
Safety review includes analyzing and evaluating proposed designs in the nuclear, themal, and hydraulic areas.with specific emphasis on systems capability and characteristics.. The comercial p~lants I currently have in various stages of review liiFiude-the SNUPPS plants Thfeelile I'l'aFd' Unit 2~ Greens county
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s Nuclear Power Plant, North Anna Units 3 and 4, Perkins Units 1, 2 1
and 3, and Ft. St. Vrain.
My standard plants include RESAR-35 and J
GASSAR-6.
I perfomed the Safety Evaluation on the LOFT' facility and am currently a member of the NRC LOFT review group for the LOFT programs.
I am also j
a member of NRC technical review groups on Accident Delineation for i
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i HTGRs and the Reactor Safety Study Follow-on Program.
In addition, I am a member and imediate past chaiman of the Heat Transfer
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Comittee of Gas Turbine Division of ASME and am active in local 4
activities of the AIAA.
I graduated from Purdue University in 1951 with a Bachelor of Science degree in Mechanical Engineering.
In 1961, I received a Master of Science degree in Engineering from Purdue University.
I have served
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as an evening instructor at Purdue University and at Cleveland State University.
1 In January of 1951, I joined the Allison Division of General Motors as a Test Engineer.
In this capacity I became responsible for the testing of prototype turbojets and turboprop aircraft engines. As a facility designer I modified or designed new facilities for the testing of prototype aircraft engines and also component development facilities. On occasion, these duties included supervising facility I
construction and conducting initial engine tests. As Senior Project Engineer of the Engine Components Development Laboratory, the duties included the design and development of facilities for the testing of prototype fuel, hydraulic and pneumatic system components.
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Professional. Qualifications In 1957 I transferred from Allison Division Test Operations to the Research Department. As a member of the Preliminary Design Activity I participated in design studies of advance air breathing engines and energy conversion devices. Air breathing engine projects in-cluded turboprops (one is now the T-63) turbojets, ram jets (designed and tested a pyrophoric fueled one) and air-turbo rockets. Of the energy conversion devices, a Sterling engine and a Thermo-electric generator were built and tested.
Basic responsibilities were for the mechanical design and arrangement.
Developed specialties in heat transfer analysis and aerodynamic design.
With the formation of a Nuclear Engineering Department I became responsible for mechanical design, heat transfer and flow analysis and the design of heat exchange equipment.
Participated in AEC supported programs for a " Mobile Compact Reactor" and a " Logistics Train." Participated in proposal preparation for the MCR and NERVA programs and programs for research in liquid metal boiling.
Respon-sible for fluid system and heat transfer design and analysis of inhouse liquid metal fuel cell program.
Included, design of reactor internals.
In 1961 I joined the Nuclear Propulsion Branch, NASA, Lewis Research Center. As head of the Fluid Flow Section, I was responsible for the development of analysis methods to define the startup and shutdown characteristics of the Nuclear Rocket (NERVA).
The group designed and conducted cryogenic experiments to support the development of flow and heat transfer analysis methods. Provided technical backup for the Space Nuclear Propulsion Office.
In 1966 I was appointed to a Panel in the Air Breathing Engine Division. The function of the panel was to identify the " state of the art" in air br'eathing engine technology and to identify areas of effort and programs for NASA-Lewis in anticipation of the Super Sonic Transport Program.
I was active in compressor and turbine aerodynamics and in turbine cooling.
Conducted programs investigating the limits to the use of the heat sink of fuels for cooling and promoted a liquid methane fueled SST.
In 1968 I joined the Westinghouse Electric Corporation as Engineering Manager. Directed group responsible for the design of industrial gas turbines. Specific responsibilities for cooled turbine design, cooling system design and heat transfer analysis.
Conducted field tests of prototype turbines and older frames with problems.
Directed technology programs in turbines and turbine cooling.
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an Professional Qualifications 3-In 1973 I transferred to the Westinghouse Nuclear Energy Systems Division. My duties included the analysis of experimental results from a series of bicwdown, refill, and reflood tests performed on an electrically heated core bundle. Tests were performed with and without upper head injection.
In 1974 I joined the Nuclear Regulatory Commission as a Reactor Engineer and assumed my present duties.
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