SVP-99-111, Informs NRC of Current Status of Actions on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions

Informs NRC of Current Status of Actions on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions

ML20206T243
Person / Time
Site:	Quad Cities
Issue date:	05/17/1999
From:	Dimmette J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-96-06, GL-96-6, SVP-99-111, NUDOCS 9905240101
Download: ML20206T243 (2)

Text

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Comed SVP-99-111 May 17,1999 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D C 20555  ;

Quad Cities Nuclear Power Station, Unit 1 '

Facility Operating License No. DPR-29 NRC Docket No. 50-254

Subject:

Change in status of NRC Generic Letter 96-06," Assurance of Equipment Operability and Containment integrity During Design-Basis Accident Conditions" Actions for Unit 1

References:

(1) Letter from J.P. Dimmette, Jr. (Comed), SVP-98-234, to USNRC, I dated October 30,1998," Change in Status of NRC Generic Letter 1 96-06 Resolution Actions for Unit 1" The purpose of this letter is to inform the NRC of the current status of our actions on Quad Cities Nuclear Power Station Unit 1 response to Generic Letter (GL) 96-06,

" Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions."

In the letter referenced above, we revised commitments for penetrations, X-12 (Residual Heat Removal Shutdown Cooling); X-14 (Reactor Water Cleanup); and X-41 (Reactor Recirculation Sample Line Piping). That letter informed the NRC of our 9y1 intention to perform an American Society of Mechanical Engineers Boiler and Pressure j Vessel Section lil Appendix F 1 (ASME Appendix F), " Rules for Evaluation of Service Loadings with Level D Service Limits," analysis for these penetrations in accordance with Supplement of GL 96-06. This task was completed as scheduled.

The results of the analysis allowed for qualification of penetrations X-12 and X-41. As a result of this qualification, no modifications, (i.e. relief valves) were required to be installed. O[

Prior to completion of the ASME Appendix F analysis for penetration X-14,it became I evident that this penetration could not be qualified. Based on these preliminary results, l we completed installation of a relief valve for penetration X-14 in our recent 01P02

) outage. The analysis of penetrations X-12 and X-41 and the installation of the relief valve for penetration X-14 completes our actions in response to GL 96-06 for Quad Cities Nuclear Power Station Unit 1.

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> May 17,1999 U.S. Nuclear Regulatory Commission

,.Page 2 Should you have any questions concerning this letter, please contact Mr. Wally Beck,

. Acting Regulatory Assurance Manager, at (309) 654 2241, extension 3100.

R ectfully,

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Ca Joel P. Dimmette, Jr.

$ite Vice President Quad Cities Nuclear Power Station cc: Regional Administrator-NRC Region til NRC Senior Resident inspector - Quad Cities Nuclear Power Station l

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