ML022190445

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

ML022190445
Person / Time
Site:	Oconee
Issue date:	07/26/2002
From:	Mccollum W Duke Energy Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GL-96-006
Download: ML022190445 (1)

Text

S Duke Duke Energy rOEnergy.

Oconee Nuclear Station 7800 Rochester Highway Seneca, SC 29672 W R. McCollum, Jr.

(864) 885-3107 OFcE Vice President (864) 885-3564 FAx July 26, 2002 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001

Subject:

Oconee Nuclear Station, Units 1, 2 and 3 Docket Nos. 50-269, 50-270, and 50-287 Supplemental Response to Generic Letter 96-06:

Assurance of Equipment Operability and Containment Integrity During Design-Basis Conditions Generic Letter (GL) 96-06, "Assurance of Equipment Operability and Containment Integrity During Design Basis Conditions," dated September 30, 1996, requested licensees to determine (in part) if containment air cooler cooling water systems are susceptible to either waterhammer or two-phase flow conditions during postulated accident conditions. Duke Energy Corporation (Duke) responded to GL 96-06 in submittals to the NRC dated October 29, 1996, January 28, 1997, April 15, 1997, June 30, 1997, August 1, 1997, May 28, 1998, September 22, 1998, December 17, 1998, March, 23, 1999, and December 15, 1999.

Your letter dated May 2, 2002, requested that by July 30, 2002, Duke complete actions needed to address GL 96-06 and submit the information referred to in Section 3.3 of the NRC SER for EPRI Report TR-1 13594. In the December 15,1999 letter, Duke committed to supplement its GL 96-06 response within five months of approval of the above EPRI report.

Duke's efforts to resolve GL 96-06 have been structured around this previously communicated schedule. As agreed to by Mr. L. N. Olshan on July 18, 2002, Duke will provide its response by September 30, 2002.

Please address any questions to R. C. Douglas at 864-885-3073.

Site Vice Presidefit~

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