ML20249C239

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Refers to GL 96-06, Assurance of Equipment Operability & Containment Integrity During DBA Conditions, & Wepc Responses ,970625 & 971218.Forwards RAI Re Resolution of GL 96-06 Issues at Point Beach Units 1 & 2
ML20249C239
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 06/25/1998
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 9806260251
Download: ML20249C239 (4)


Text

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L Mr. Michael B. Eellman Chief Nuclear Officer Wisconsin Electric Power Company

, 231 West Michigan Street Milwaukee,WI 53201

SUBJECT:

POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RE: RESPONSES TO GENERIC LETTER 96-06.

(TAC NOS. M96852 AND M96853)

Ihar Mr. Sellman:

Generic Letter (GL) 96-06,'" Assurance of Equipment Operability and Containment integrity During Design-Basis Accident Conditions," dated September 30,1996, included a request for licensees to evaluate cooling water systems t' hat serve containment air coolers to assure that they are not vulnerable to waterhammer and two-phase flow conditions. Wisconsin Electric'(WE) Power Company provided its assessmErit of the waterhammer and two-phase flow issues for the Point Beach units in letters dated January 28, June 25, and December 18,1997, and related submittals dated September 9, September 30, and October 30,1996. To complete our review of WE's resolution of these issues, additional information is required. Please provide WE's' response to the enclosed request for additional informaticri by August 30,1998, in order to support our review schedule for GL 96-06.

Sincerely, ORIGINAL SIGNED BY Linda L. Gundrum, Project Manager Project Directorate lll-1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation 1

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k Mr. Michael B. Sellman Point Beach Nuclear Plant i

Wisconsin Electric Power Company Units 1 and 2 I

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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. Patulski 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 42 Mishicot, Wisconsin 54228 Chairman Public Service Commission of Wisconsin P.O. Box 7854 Madison, Wisconsin 53707-7854 Regional Administrator, Region lli U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Resident inspector's Office U.S. Nuc! car Regulatory Commission S612 Nuclear Road l

Two Rivers, Wisconsin 54241 Ms. Sarah Jenkins Electric Division Public Service Commission of Wisconsin P.O. Box 7854

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Madison, Wisconsin 53707-7854 l

i REQUEST FOR ADDITIONAL INFORMATION FOR RESOLUTION OF GL 96-06 ISSUES AT POINT BEACH UNIT NOS.1 AND 2 (TAC NOS. M96852 AND M96853)

Generic Letter (GL) 96-06, " Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions," dated September 30,1996, included a request for licensees to evaluate cooling water systems that serve containment air coolers to assure that they are not vulnerable to waterhammer and two-phase flow conditions. Wisconsin Electric Power Company (the licensee) provided its assessment of the waterhammer and two-phase flow issues for the Point Beach units in letters dated January 28, June 25, and December 18,1997, and related submittals dated September 9, September 30, and October 30,1996. The licensee has determined that the waterhammer and two-phase flow issues discussed in GL 96-06 are valid concems fer the Point Beach units and extensive analyses have been completed to address these issues. However, in order to fully assess the licensee's resolution of these issues, the following additional information is requested:

Note: Information that has been submitted previously may be referred to and supplemented as necessary to provide a complete response to the staff s questions.

1. If a methodology other than that discussed in NUREG/CR-5220, " Diagnosis of Condensation-induced Waterhammer," was used in evaluating the effects of waterhammer, describe this alternate methodology in dotail. Also, explain why this methodology is applicable and gives conservative results (typically accomplished through rigorous plant-specific modeling, testing, and analysis).
2. _ For both the waterhammer and two-phase flow analyses, provide the following information:
m. Identify any computer codes that were used in the waterhammer and two-phase flow analyses and describe the methods used to bench mark the codes for the specific loading conditions involved (see Standard Review Plan Section 3.9.1).
b. Describe and justify all assumptions and input parameters (including those used in any computer codes) such as amplifications due to fluid-structure interaction, cushioning, speed of sound, force reductions, and mesh sizes, and explain why the values selected give conservative results. Also, provide justification for omitting any effects that may be relevant to the analysis (e.g., fluid structure interaction, flow induced vibration, erosion).
c. Provide a detailed description of the " worst case" scenarios for waterhammer and two-phase flow, taking into consideration the complete range of event possibilities, system configurations, and parameters. For example, all waterhammer types and water slug scenarios should be considered, as well as temperatures, pressures, flow rates, load p

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combinations, and potential component failures. Additional considerations for two-phase flow include:

the effects of void fraction on flow balance and heat transfor; the consequences of steam formation, tr:msport, and accumulation;

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cavitation, resonance, and fatigue effects; and erosion considerations.

i Licensees may find NUREG/CR-6031, " Cavitation Guide for Control Valves," helpful in I

addressing some aspects of the two-phase flow analyses. (Note: it is important for licensees to realize that in addition to heat transfer considerations, two-phase flow also involves structural and system intr grity concerns that must be addressed).

d. Confirm that the analyses included a complete failure modes and effects analysis (FMEA) for all components (including electrical and pneumatic failures) that could impact performance of the cooling water system and confirm that the FMEA is documented and available for review, or explain why a complete and fully documented FMEA was not performed.
e. Explain and justify all uses of " engineering judgement."
3. Determine the uncertainty in the waterhammer and two-phase flow analyses, explain how the uncertainty was determined, and how it was accounted for in the analyses to assure conservative results.
4. Confirm that the waterhammer and two-phase flow loading conditions do not exceed any design specifications or recommended service conditions for the piping system and components, including those stated by equipment vendors; and confirm that the system will continue to perform its design-basis functions as assumed in the safety analysis report for the facility and that the containment isolation valves will remain operable.
5. Provide a simplified diagram of the system, showing major components, active cornponents, relative elevations, lengths of piping runs, and the location of any orifices and flow restrictions.
6. Describe in detail any plant modifications or procedure changes that have been made or are planned to be made to resolve the waterhammer and two-phase flow issues.