ML20237D928

Provides Description of Approach Being Taken by Comed to Develop Dsar.New Safety Classification Will Be Developed for Equipment Determined to Be Important to Defueled Condition

ML20237D928
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	08/24/1998
From:	Krich R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9808280035
Download: ML20237D928 (2)

Text

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(d Commonurahh fdmon Compan) l,l* ' 40) Opus Place

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August 24,1998 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Zion Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-39 and DPR-48 NRC Docket Nos. 50-295 and 50-304

Subject:

Updated Final Safety Analysis Report

Reference:

NRC letter, " Exemption from Requirements of 10 CFR 50.71 -Zion Nuclear Power Station Units 1 and 2," dated June 30,1998 The Nuclear Regulatory Commission (NRC) issued Commonwealth Edison (Comed) Company an exemption from the requirements of 10 CFR 50.71(e)(4) in the referenced letter. The exemption extended the Updated Final Safety Analysis Report (UFSAR) update interval so Comed would have sufficient time to develop a Defueled Safety Analysis Report (DSAR) for Zion Nuclear Power 1

Station. The OSAR will define those structures, systems, components, activities and postulated events that are relevant to safety in thG permanently defueled  ;

condition of Zion Nuclear Power Station. This letter describes the approach being taken by Comed to develop the DSAR.

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Since-Zion Nuclear Power Station, Units 1 and 2 are permanently defueled, many of the previously analyzed accidents are no longer possible. Those accident analyses will be deleted from the UFSAR under 10 CFR 50.59. Other 'y g/

remaining accident analyses will be updated to refleci the permanently defueled condition. Classification of structures, systems and components (SSCs) will be redefined consistent with the revised accident analyses. A new safety classification, and corresponding quality requirements, will be developed for equipment determined to be important to the defueled condition. For SSCs classified as important to the defueled condition, descriptive information will be included in the DSAR at about the same level of detail that currently exists in the UFSAR. Many of the SSCs currently described in the UFSAR liave been determined to not be important to the defueled condition. The Ciscussion of

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August 24,1998 U. S. Nuclear Regulatory Commission Page 2 those SSCs will not be included in the DSAR since they are no longer relevant to the defueled condition of Zion Nuclear Power Station, Units 1 and 2.

The result of the approach outlined above will be a DSAR for Zion Nuclear Power Station that is similar to the " Maine Yankee Defueled Safety Analysis Report" and the " Trojan Nuclear Power Plant Defueled Safety Analysis Report."

If you have any questions concerning this letter, please contact K. A. Ainger at (630)663-7350.

Respectfully,

, R. M. Krich Vice President - Regulatory Services cc: NRC Regional Administrator, Region til

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