ML20217E595
| ML20217E595 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/20/1998 |
| From: | Gundrum L NRC (Affiliation Not Assigned) |
| To: | Sellman M WISCONSIN ELECTRIC POWER CO. |
| References | |
| GL-96-06, GL-96-6, TAC-M96852, TAC-M96853, NUDOCS 9804270351 | |
| Download: ML20217E595 (4) | |
Text
a April 20, 1998 Mr. Michul B. S:llman Chief Nucbar Officer Wsconsin Electric Power Company 231 West Michigan Street Milwaukee, WI 53201
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING RESPONSE TO GENERIC LETTER 96-06 FOR THE POINT BEACH NUCLEAR POWER PLANT, UNITS 1 AND 2 (TACs M96852 AND M96853)
Dear Mr. Sellman:
The staff has reviewed Wisconsin Electric Power Company's submittals dated January 28, June 25, and December 18,1997, for Point Beach Nuclear Power Plant, Units 1 and 2, in response to GL 96-06, " Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions." Additionalinformation is needed to complete the staff review. A response is requested within 30 days of receipt of this letter.
The staff is reviewing the GL 96-06 responses for thermally induced pressurization of piping runs penetrating the containment and for water hammer and two-phase flow. For the thermally induced pressurization of piping runs penetrating the containment review, the staff understands that Point Beach has a total of seven pipe lines penetrating the containment in each unit that are susceptible to thermally induced overpressurization. Wisconsin Electric has committed to modify two of the lines (penetrations P-11 and P-28b) in each unit by installing relief valves; to drain, cut, and cap the condensate return line (P-53-1) for Unit 1 (the condensate return line for Unit 2 was cut and capped); and to add valves and a drain line for penetration P-12a on the supply side of the containment isolation valves to ensure the line remains drained. Wisconsin Electric is relying on isolation valve leakage to prevent overpressure of the remaining three i
lines (P-30c, P-32b, and P-32c) in each unit. The December 18,1997, submittal referenced the l
June 25,1997, submittal for a description of the boundary valve relief features; however, no information was found. The request for additional information is for penetrations P-30c, P-32b, and P-32c.
If you have any questions, please contact Linda Gundrum at 301-415-1380.
Sincerely, ORIGINAL SIGNED BY L;nda L. Gundrum, Project Manager Project Directorate lil-1 Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301
Enclosure:
Request for Additional Information I
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Mr. Michael B. Sellman Point Beach Nuclear Plant Wisconsin Electric Power Company Units 1 and 2 cc:
Mr. John H. O'Neill, Jr.
Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW Washington, DC 20037-1128 Mr. Richard R. Grigg President and Chief Operating Officer Wisconsin Electric Power Company 231 West Michigan Street Milwaukee, Wisconsin 53201 Mr. Scott A. Patuiski Site Vice President Point Beach Nuclear Plant Wisconsin Electric Power Company 6610 Nuclear Road Two Rivers, Wisconsin 54241 Mr. Ken Duveneck Town Chairman Town of Two Creeks 13017 State Highway 47 Mishicot, Wisconsin 54228 Chairman Public Service Commission of Wisconsin 1
P.O. Box 7854 Madison, Wisconsin 53707-7854 Regional Administrator, Region ll1 U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Resident inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, Wisconsin 54241 Ms. Sarah Jenkins Electric Division Public Service Commission of Wisconsin l
P.O. Box 7854
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l Madison, Wisconsin 53707-7854
REQUEST FOR ADDITIONAL INFORMATION I
in the December 18,1997, submittal, Wisconsin Electric indicated that boundary valve relief l
features associated with penetrations P-30c, P-32b, and P-32c provide inherent relief to prevent overpressure of the pipe line. Please provide the following information for the pipe lines associated with these penetrations:
Describe the applicable design criteria for the piping and valves. Include the required load combinations.
l Provide a drawing of the valve. Provide the pressure at which the valve was determined to lift off its seat or leak and describe the method used to estimate this pressure.
Discuss any sources of uncertainty associated with the estimated lift off or leakage
- pressure, j
)
Provide the maximum-calculated stress in the piping run based on the estimated lift off or leakage pressure.
l l
l t
ENCLOSURE
DATED:
April 20, 1998 REQUEST FOR ADDITIONAL INFORMATION Docket File (50-266,50-301)
PUBLIC PDlli-1 Reading E. Adensam (EGA1)
C. Carpenter C. Jamerson L. Gundrum OGC K. Manoly J. Fair ACRS J. McCormick-Barger, Rlli l