ML20207D126

Forwards Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves

ML20207D126
Person / Time
Site:	Clinton
Issue date:	05/28/1999
From:	Hopkins J NRC (Affiliation Not Assigned)
To:	Sipek J ILLINOIS POWER CO.
References
TAC-M93448, NUDOCS 9906030216
Download: ML20207D126 (3)

Text

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Mr. Joseph V. Sipek May 28, 1999

, Dir:ctor- Licensing .

Clinton Pow;r St; tion P.O. Box 678 Mail Code V920 Clinton,IL 61727

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 95-07, " PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES," CLINTON POWER STATION, UNIT 1 (TAC NO. M93448) .

Dear Mr. Sipek:

On August 17,1995, the_NRC issued Generic Letter (GL) 95-07, " Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves," to request that licensees take actions to ensure that safety-related power-operated gate valves that are susceptible to pressure locking or thermal binding are capable of performing their safety functions.

In a letter dated February 9,1996, Illinois Power Company submitted its 180-day response to GL 95-07 for the Clinton Power Station. The NRC staff reviewed your submittal and requested additional information in a letter dated May 23,1996. In letters dated June 27, and August 5, 1996, you provided the additional information.

A telephone call was held with your staff on May 5,1999, to discuss your responses. From our review to-date, including the telephone call, we find that additional information is needed to complete our review. The desired information was discussed with your staff. Enclosed is a request for additional information (RAl) regarding the GL 95-07 program at Clinton. Please provide the requested information within 45 days of your receipt of this letter.

Contact me if you have any questions.

Sincerely, Origirial signed by Jon B. Hopkins, Senior Project Manager, Section 2 Project Directorate ill Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-461 Distribution:

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I Joseph V. Sipek Clinton Power Station, Unit 1 Illinois Power Company cc:

John. P. McElwain Illinois Department of Nuclear Safety Senior Vice President Office of Nuclear Facility Safety Clinton Power Station ATTN: Mr. Frank Nizidlek P.O. Box 678 - 1035 Outer Park Drive Clinton,IL 61727 Springfield,IL 62704 Wayne Romberg Leah Manning Stetzner Manager Nuclear Station VP, General Counsel & Corp. Secretary Engineering Department 500 South 27th Street Clinton Power Station Decatur,IL 62525 P.O. Box 678 '

Clinton,IL 61727 Resident inspector U.S. Nuclear Regulatory Commission RR#3, Box 22g A Clinton,IL 61727 R. T. Hill Licensing Services Manager General Electric Company 175 Curtner Avenue, M/C 481 San Jose, CA g5125 Regional Administrator, Region lil U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Chairman of DeWitt County c/o County Clerk's Office DeWitt County Courthouse Clinton,IL 61727 J. W. Blattner Project Manager Sargent & Lundy Engineers 55 East Monroe Street Chicago,IL 60603

REQUEST FOR ADDITIONAL INFORMATION FOR RESOLUTION OF GL 95-07 ISSUES AT THE CLINTON POWER STATION (TAC NO. M93448)

1. In a letter dated May 23,1996, the NRC requested your analysis or evaluation that demonstrated that the high pressure core spray pump suppression pool suction valve, 1222-F015, and the reactor core isolation cooling pump suppression pool suction valve, 1E51-F031, were not susceptible to thermalinduced pressure locking fo!!owing postulated accidents that cause the suppression pool temperature to increase. Your responses dated June 27, and August 5,1996, use engineering judgment to determine that the temperature of these valves would not increase; and therefore, these valves are not susceptible to thermal induced pressure locking. The NRC staff considers that it is not appropriate to use engineering judgment to determine that these valves are not susceptible to pressure locking due to the geometry of the piping between the valves and the suppression pool. Provide the calculations that demonstrate that heat will not be transferred from the suppression pool to the valves during a postulated accident.

2. During a postulated accident, the containment would be initially pressurized to a peak pressure and the bonnets of 1E22-F015 and 1E51-F031 could also be pressurized to containment peak pressure. When transferring to the recirculation phase of a postulated accident, containment pressure could be lower than the initial peak pressure but the pressure in the bonnets of 1E22-F015 and 1E51-F031 could still be at containment peak pressure. Discuss if the pressure in the bonnets of the valves could be higher than upstream and downstream pressure due to changes in containment pressure when the valves are required to open and, if applicable, if the valves will open during this pressure locking condition.

Enclosure

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