ML20236X498

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Forwards RAI Re GL 96-06, Assurance of Equipment Operability & Ci During DBA Conditions. Response on Issues of Thermally Induced Pressurization of Piping Runs Penetration Containment,Requested by 981130
ML20236X498
Person / Time
Site: Catawba  
Issue date: 07/30/1998
From: Tam P
NRC (Affiliation Not Assigned)
To: Gordon Peterson
DUKE POWER CO.
References
GL-96-06, GL-96-6, TAC-M96794, TAC-M96795, NUDOCS 9808100049
Download: ML20236X498 (5)


Text

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s July 30,1998 Mr. Gary R. Peterson Site Vice President Catawba Nuclear Station Duke Energy Corporation 4800 Concord Road York, South Carolina 29745-9635

SUBJECT:

CATAWBA NUCLEAR STATION - REQUEST FOR ADDITIONAL INFORMATION REGARDING RESPONSE TO GENERIC LETTER 96-06 (TAC NOS. M96794 AND M96795)

Dear Mr. Peterson:

By letter dated January 28,1997, Duke Energy Corporation (Duke) responded to Generic Letter (GL) 96-06, " Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions." Duke's submittal addressed the issues of waterhammer, two-phase flow, and thermally induced pressurization of piping runs penetrating the containment for Catawba Nuclear Station, Units 1 and 2. The staff had issued a request for 1

additional information on the waterhammer and two-phase flow issues, and Duke responded by letter dated June 24,1998.

Enclosed is an RAI on the issue of thermally induced pressurization of piping runs penetrating the containment. Please respond to this RAI by November 30,1998. I have discussed this schedule with Martha Purser of your staff. If you need clarification of the questions, please contact me at 301-415-1451.

Sincerely, hV c I M { S no { loy c

Peter. Tam, Senior Project Manager Project Directorate 11-2

'1g[#*.d Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414

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WASHINGTON, D.C. 20606 0001 July 30,1998 Mr. Gary R. Peterson Site Vice President Catawba Nuclear Station Duke Energy Corporation 4800 Concord Road York, South Carolina 29745-9635

SUBJECT:

CATAWBA NUCLEAR STATION - REQUEST FOR ADDITIONAL INFORMATION REGARDING RESPONSE TO GENERIC LETTER 96-06 (TAC NOS. M96794 AND M96795)

Dear Mr. Peterson:

By letter dated January 28,1997, Duke Energy Corporation (Duke) responded to Generic Letter (GL) 96-06, " Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions." Duke's submittal addressed the issues of waterhammer, two-phase flow, and thermally induced pressurization of piping runs penetrating the containment for Catawba Nuclear Station, Units 1 and 2. The staff had issued a request for additional information on the waterhammer and two-phase flow issues, and Duke responded by letter dated June 24,1998.

Enclosed is an RAI on the issue of thermally induced pressurization of piping runs penetrating the containment. Please respond to this RAI by November 30,1998. I have discussed this schedule with Martha Purser of your staff. If you need clarification of the questions, please contact me at 301-415-1451.

Sincerely,

~. "

Peter S. Tam, Senior Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414

Enclosure:

As stated cc w/ encl: See next page I

Catawba Nuclear Station cc:

Mr. M. S. Kitlan North Carolina Electric Membership Regulatory Compliance Manager Corporation Duke Energy Corporation P. O. Box 27306 4800 Concord Road Raleigh, North Carolina 27611 York, South Carolina 29745 Senior Resident inspector Mr. Paul R. Newton U.S. Nuclear Regulatory Commission Legal Department (PB05E) 4830 Concord Road Duke Energy Corporation York, South Carolina 29745 422 South Church Street Charlotte, North Carolina 28242 Regional Administrator, Region 11 U. S. Nuclear Regulatory Commission J. Michael McGarry, Ill, Esquire Atlanta Federal Center Winston and Strawn 61 Forsyth Street, S.W., Suite 23T85 1400 L Street, NW Atlanta, Georgia 30303 Washington, DC 20005 Max Batav:a, Chief North Carolina Municipal Power Bureau of Radiological Health Agency Number 1 South Carolina Department of 1427 Meadowwood Boulevard Health and Environmental Control P. O. Box 29513 2600 Bull Street Raleigh, North Carolina 27626 Columbia, South Carolina 29201 i

County Manager of York County L. A. Keller York County Courthouse Manager-Nuclear Regulatory j

York, South Carolina 29745 Licensing j

Duke Energy Corporation Piedmont Municipal Power Agency 526 South Church Street 121 Village Drive Charlotte, North Carolina 28242-0001

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Greer, South Carolina 29651 Saluda River Electric Ms. Karen E. Long P. O. Box 929 Assistant Attorney General Laurens, South Carolina 29360 North Carolina Department of Justice P. O. Box 629 Raleigh, North Carolina 27602 Elaine Wathen, Lead REP Planner Division of Emergency Management 116 West Jones Street Raleigh, North Carolina 27603-1335 L

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Catawba Nuclear Station cc:

Mr. T. Richard Puryear Owners Group (NCEMC)

Duke Energy Corporation 4800 Concord Road York, South Carolina 29745 l

Richard M. Fry, Director l

Division of Radiation Protection l

North Carolina Department of Environment, Health, and l

Natural Resources 3825 Barrett Drive Raleigh, North Carolina 27609-7721 l

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4 0-REQUEST FOR ADDITIONAL INFORMATION CATAWBA NUCLEAR STATION. UNITS 1 AND 2 RESPONSE TO GENERIC LETTER 96-06 h the January 28,1997, submittal, Duke Energy Corporation (Duke) indicated that a total of three pipe segments in each unit were susceptible to thermally induced pressurization, which are isolated by soft seat plug valves. Duke stated that testing has been performed that demonstrated that these valves would leak enough fluid to prevent overpressurizing the piping above the maximum Code-allowable pressure.. In order to complete its review of Duke's response, the staff needs the following information for these penetrations:

Describe the applicable design criteria for the piping and valves. Include the required i

load combinations;

)

1 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; Provide the maximum-calculated stress in the piping run based on the estimated lift off or leakage pressure, in its submittal, Duke also indicated that the Equipment Decontamination (WE) piping has a design pressure of 8015 pounds per square inch absolute, which would withstand the pressurization due to heatup. In order is complete its review, the staff needs the following information for these penetrations:

J Provide the applicable design criteria for the piping and the valves. Include the required

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load combinations; Provide a drawing of the piping run between the isolation valves. Include the lengths and thicknesses of the piping segments and the type and thickness of the insulation;

)

Prxide the maximum-calculated temperature and pressure for the pipe run. Describe, in detail, the method used to calculate these pressure and temperature values. This should include a discussion of the heat transfer model used in the analysis and the basis for the heat transfer coefficients used in the analycis.

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Enclosure I

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