ML19339B165

Testimony Supplementing Jh Correa,Gt Urquhart & Rc Jones 800915 Testimony,In Response to ASLB Question on Ucs Contentions 5 & 6 Re Valves & Valve Testing.Safety Valves Designed to Discharge two-phase Fluid.W/Prof Qualifications

ML19339B165
Person / Time
Site:	Three Mile Island
Issue date:	10/28/1980
From:	Correa J, Urquhart G BABCOCK & WILCOX CO., GENERAL PUBLIC UTILITIES CORP., METROPOLITAN EDISON CO.
To:
Shared Package
ML19339B163	List: ML19339B162 ML19339B165 ML19339B167
References
NUDOCS 8011060399
Download: ML19339B165 (8)

Text

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. . ATE.D CORhMMU O

LIC 10/28/80 g \ \'

, N UNITED STATES OF AMERICA '

NUCLEAR REGULATORY COMMISSION .

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f Usc . \,

a- CC7 3 01980 >~ E!

is BEFORE THE ATOMIC SAFETY AND LICENSING BOAFy Opfgf the Segrga g ,

q, Stanch s'N M

In the Matter of )

)

METROPOLITAN EDISON COMPANY ) Docket No. 50-289

) (Restart)

)

(Three Mile Island Nuclear )

Station, Unit No. 1) )

LICENSEE'S TESTIMOLY OF JAMES H.. CORREA AND GARY T. URQUHART IN RESPONSE TO THE BOARD QUESTION ON UCS CONTENTION 6 80310603)

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OUTLINE ,

This testimony supplements Licensee's Testimony of James H. Correa, Gary T. Urquhart and Robert C. Jones, Jr. in i Response to UCS Contentions 5 and 6 (Valves and valve Testing),

4 dated September 15, 1980. In particular, this testimony responds to the Board Question relating to UCS Contention 6.

The testimony explains that while the pressurizer safety valves perform a safety function, the PORV does not. Because of the design of the safety valves, it is expected that they can perform the required safety function of opening and discharging liquid or two-phase fluid if necessary. In addition, the experience during the Crystal River transient of February 26, 1980, and in the fossil power industry generally, provides some assurance that the results of the EPRI test i

program will be favorable.

INTRODUCTION This testimony, by Mr. James H. Correa, Engineer, j

Mechanical Components, GPU, and Mr. Gary T. Urquhart, Unit Manager, Auxiliary Equipment Unit, Babcock & Wilcox Company, is

addressed to the following Board Question regarding UCS Contention 6

The board wants more than just a schedule for testing of reactor coolant system safety and <

relief valves, as is required pursuant to NUREG-057'8. Is there reasonable assurance that the tests will be successful, e.g., that there is good evidence that the valves will indeed perform in an accident environment?

RESPONSE

BY WITNESSES CORREA AND URQUHART:

The original design and testing of the pressurizer power i operated relief valve (PORV) and safety valves was described in Licensee's testimony in response to UCS Contentions 5 and 6 (Valves and Valve Testing) (pages 4-6). As also addressed in that testimony (pages 2, 3 and 7) the PORV does not serve a pressure relief safety function. The safety valves, however, do serve a safety function in that they provide Reactor Coolant System overpressure protection. The safety valves may also serve as a safety-grade discharge path for reactor coolant fluid during feed and bleed operation - see Licensee's testi-mony in response to UCS Contentions 1 and 2 (Natural and Forced Circulation) (page 12). l l

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The only function required of the safety valves in order to provide overpressure protection or for feed and bleed

operation is to open and discharge fluid. The disc lifts in 1

response to the system pressure force on the disc face. The l pressure at which the disc lifts - i.e., at which the valve opens, or functions - is dependent on the opposing force applied by the valve spring. Because of the construction of l

the valves there is no reason to expect that liquid or two-phase flow conditions would have a detrimental effect on the ability of the valves to perform their requ' ired function.

l This conclusion is specifically supported by the experi- ,

ence at Crystal River on February 26, 1980, and the examina-tions subsequent to that transient - see Licensee's testimony in response to UCS Contentions 5 and 6 (pages 6 and 7). The valve opened at 2400 psig; was open for approximately 20 minutes; experienced saturated steam, two-phase fluid and water at 2400 psig, 410*F with a maximum flow rate of 700 gpm; and reseated at 2300 psig (4% blowdown). These conditions are similar to those in one of the valve tests in the EPRI test program, in which the valve is set to open at 2500 psig, pass 450*F water at a maximum flow rate of 1000 gpm, and reseat at approximately 2375 psig (5% blowdown).

Also, safety valves are used extensively in fossil power J

applications. Many of those valves are similar in basic design to the valves at TMI-1 and have experienced flow conditions

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other than steam. There is no known power industry incident of a properly set and maintained safety valve failing to open upon demand, even though liquid and two-phase flow through these valves has occurred.

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JAMES H. CORREA

! Business Address: GPU Service Corporation 100 Interpace Parkway Parsippany, New Jersey 07054 Education: B.S., Mechanical Engineering , Rensselaer Polytechnic Institute, 1969.

Experience: Mechanical Engineer III, GPU Service Corporation, 1973 to present. Responsible for providing technical engineering on valves for GPU system nuclear power plants; providing technical support to resolve i field prcblems, including repair i

recsmmendations and field technical guidance; providing technical support for plant modifications, including writing technical specifications for valves and modification documentation packages. Other responsibilities have included reviewing flow diagrams for proper valve selection; reviewing architect-engineer technical specifications for technical content including referencing the proper codes and standards and valve design features.

Mechanical Design Engineer, Foster Wheeler Corporation, 1972 to 1978. Performed engineering work on primary sodium valves for the fast flux test facility and

, steam generators for a high temperature gas cooled reactor. Responsibilities included preparing material and sub-contracted machining requisition packages; vendor surveillance; preparing and issuing shop fabrication releases which include drawings and shop procedures; and the resolution of vendor material and machining problems and shop fabrication problems in the areas of manufacturing, materials and quality Control, Cognirant Engineer, Machinery Apparatus Operation, General Electric Company, 1970 te 1972. Performed technical engi.neering

work on Naval Nuclear Heat Exchangers and Pressurizers, including definition of specifications, vendor selection, design review and analysis, f abrication surveillance ,

, and the resolution of installation problems. Engineering work included the solving of technical problems in a number of technical disciplines such as mechanical analysis, hea: transfer, quality control, materials and welding, and manufacturing.

Engineer, Mechanical Facilities Planning, Missile and Space Division and.Re-entry and Environmental Systems Division, General Electric Company, 1969 to 1970.

Performed design and cost estimates for specific projects such as ventilation systems and piping systems. Provided design direction for construction and renovation projects.

il Prcfessional Affiliations: Registered Professional Engineer, New l

Jersey.

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J GARY T. URQUHART 4

n Business Address: Babcock & Wilcox Company Nuclear Power Generation Division P.O. Box 1260 Lynchburg, Virginia 24505 Education: B.S., Mechanical Engineering, State University of New York at Suffalo, 1970. M.B.A., Lynchburg College, 1979.

Excerience: Unit Manager , Auxiliary Equipment Unit, Equipment Engineering Section, Babcock & Wilcox Co., 1980 to present.

Responsible for preparation of-equipment specifications for equipment such as valves, heat exchangers, small pumps and tanks, evaluation of vendors' designs, review and approval ef vendor submitced documentation, and

esolution of field problems. l Senior Engineer and supervisory Engineer , RCS Mechanical Design Unit, Component Engineering Section, Babcock

& Wilcox Co., 1976 to 1980.

Responsible for detail design and analysis, manufacturing liaison and resolution of shop and field problems for the reactor internals (core support assembly).

Various assignments in Quality Control (Assurance) and Materials Engineering for the Fossil Power Generation Division, Nuclear Equipment Division and Nuclear Power Generation Division, Sabcock & Wilcox Co., 1970 to 1976.

Responsibilities included preparation.

of manufacturing procedures such as non-destructive examination and welding, material selection, eval-uation and analysis for fossil boilers and the per formance of internal and vendor quality audits.

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