ML20134E573

Responds to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions

ML20134E573
Person / Time
Site:	San Onofre
Issue date:	10/30/1996
From:	Rainsberry J SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-96-06, GL-96-6, NUDOCS 9611010204
Download: ML20134E573 (2)

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Southem Califomia E4ison Company P. O. BO) d SAN CLEMENTE CALIFORNIA 92674-0128 October 30,.1996 n.nANseEnny MANAGER, PLANT LICENSING (714) 368-7420 4

CAN ONOFFIE NUCLEAR GENERATING STATION

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U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C.

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Gentlemen:

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Subject:

Docket Nos. 50-361 and 50-362 i

Response to Generic Letter 96-06: " Assurance of Equipment Operability and Containment Integrity During Design-Basis i

Accident Conditions" San Onofre Nuclear Generating Station 1

Units 2 and 3 i

j This letter provides the 30-day response to Generic Letter 96-06 (GL 96-06).

1 Southern California Edison (Edison) will perform the actions as requested by j

GL 96-06. Specifically, Edison will determine:

4 (1) if containment' air cooler cooling water, systems are susceptible to 1

either waterhammer or two-phase flow conditions during postulated 1

i accident conditions; I

I (2) if piping systems that penetrate the containment are susceptible to thermal expansion of fluid so that overpressurization of piping l

could occur.

l Also as requested, Edison will submit, by January 21, 1997, a written summary i

report stating actions taken in response to the requested actions noted above, conclusions that were reached relative to susceptibility for waterhammer and two-phase flow in the containment air cooler cooling water system and 3

overpressurization of piping that penetrates containment, the-basis for continued operability of affected systems and components as applicable, and j

j corrective actions that were implemented or are planned to be implemented.

If systems are found to be susceptible to the conditions discussed in GL 96-06, Edison will identify the systems affected and describe the specific i

circumstances involved.

4 9611010204 961030 PDR ADOCK 05000361 P

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Document Control Desk '

J If you have any questions or would like additional information, please let me know.

Si,ncerely, e

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i State of California n

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before me, Scv #

. M F17 # N, personally appeared fact 4. Ar/nf4euv, personally known'to me to be the person whose name is subscribed to the within instru' ment and acknowledged to me that he executed the same in his authorized 4

capacity, and that by his signature on the instrument the person, or the entity upon behalf of which the person acted, executed the instrument.

j WITNESS my hand and offi

• l seal.

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L. J. Callan, Regional Administrator, NRC Region IV J. E. Dyer, Director, Division of Reactor Projects, Region IV K. E. Perkins, Jr., Director, Walnut Creek Field Office, NRC Region IV J. A. Sloan, NRC Senior Resident Inspector, San Onofre Units 2 & 3 M. B. Fields, NRC Project Manager, San Onofre Units 2 and 3 1

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