ML20129J434

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Advises That Written Summary Rept Will Be Submitted to NRC Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions, within 120 Days
ML20129J434
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 10/30/1996
From: Link B
WISCONSIN ELECTRIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-96-06, GL-96-6, VPNPD-96-090, VPNPD-96-90, NUDOCS 9611060256
Download: ML20129J434 (2)


Text

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Wisconsin Electnc POWER COMPANY 231 W Michigott PO Box 2046. Milwoukee.WI 53201 2046 (414)221-2345 VPNPD-96-090 October 30,1996 Document Control Desk US NUCLEAR REGULATORY COMMISSION Mail Station PI-137 Washington, DC' 20555 Ladies and Gentlemen:

DOCKETS 50-266 AND 50-301

~ OENERIC LETTER 96-06 ASSURANCE OF EOUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN BASIS ACCIDENT CONDITIONS P0lNT BEACH NUCLEAR PLANT. UNITS 1 AND 2 l

Generic Letter 96-06 requests licensees to perform evaluations and take actions if necessary to ensure that containment cooling water systems and other water-filled piping sections inside containment remain operable during design basis accident (DBA) conditions. This letter identified concerns for potential waterhammer and two-phase flow in containment cooling systems under certain postulated post-DBA conditions. Also identified was a concern for overpressurization ofisolated fluid systems due to containment heatup post-accident.

Herein, we provide the required 30-day response which indicates that: (1) the requested actions have been or will be completed; (2) the requested information has been or will be submitted; and (3) the requested information will be submitted within the 120-day requested time period. Dese three actions are discussed below:

(1) The requested actions have been or will be completed.

With respect to waterhammer and two-phase flow conditions in containment cooling systems, the requested actions have been completed. We have determined that the PBNP containment fan cooler (CFC)/ service water systems are susceptible to waterhammer and two-phase flow conditions during postulated accident conditions. We have assessed the system's operability with respect to NUREG/CR-5220,10 CFR 50 Appendix B, the Technical Specifications, and Generic letter 91-18. We have reported the results in letters to the NRC; VPNPD-96-065 dated September 9,1996 and VPNPD-96-080 dated September 30, 1996. These evaluations conclude that the systems are presently operable; however, long-term corrective j

actions are planned to restore the systems to full compliance with the original design basis. Permanent corrective actions are being evaluated and a schedule for final corrective actions is presented in the above submittals: Hese letters also constitute our submittal for a " written summary report" within 120 days of the date of the Generic Letter.

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4 Document Control Desk October 30,1996 i

Page 2 l

With respect to thermally-induced overpressurization of water-filled piping sections inside containment, the l

requested actions will be completed. We have previously evaluated PBNP systems and determined that six (6) water-filled piping sections in each containment are potentially susceptible to thermally-induced overpressurization. The results of these evaluations and subsequent corrective actions will be provided with our 120-day response. Any identified operability concerns will be addressed commensurate with the t

guidance of GL 91-18.

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(2)

The requested infonnation will be submitted.

l As stated above, the requested information (a " written summary report") related to waterhammer and two-i l

phase flow conditions has been submitted previously to the NRC. The requested information related to thermally-induced overpressurization will be submitted. This submittal will describe our plans for long-term corrective action.

l I

i (3)

The requested information will be submitted within the 120-day requested time period.

l As stated above, the requested information related to waterhammer and two-phase flow conditions has been submitted previousiy to the NRC. The results ofthe evaluations and other requestedinformation related to thermally-induced overpressurization will be submitted within the 120-day requested time period.

t We would be pleased to answer any questions regarding the above information.

j l

Sincerely, l

l Bob ink Vice President Nuclear Power GDA Subscribed and sworn to before me this 3Y day of Sc4/c r 1996 ts u M1 a{)Public, State of Wisconsin My Commission expires p/R hc00

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l cc:

NRC Resident Inspector, NRC Regional Administrator-Region Ill

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