ML20216D706

Forwards Rev 45 to Braidwood Station Security Plan,Iaw 10CFR50.4(b)(4).Plan Includes Listed Changes.Rev Withheld, Per 10CFR73.21

ML20216D706
Person / Time
Site:	Braidwood
Issue date:	07/19/1999
From:	Krich R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9907300075
Download: ML20216D706 (2)

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SAFEGUARDS INFORMATION

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July 19,1999 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457

Subject:

Braidwood Station Security Plan, Revision 45 In accordance with 10 CFR 50.4(b)(4), " Security plan and related submittals,' attached is the originai and three (3) copies of the Commonwealth Edison (Comed) Company Braidwood Station Security Plan, Revision 45.

4 Braidwood Station Security Plan, Revision 45, includes the following changes.

10 CFR 73.55(d)(8), " Access Requirements," was amended in 1995 to allow licensees to delete the requirement for containment doors to be locked and alarmed, and to delete the requirement for controlling access to containment during high traffic periods. Revision 37 of the Braidwood Station Security Plan deleted the requirement for controlling access to containment during high traffic periods, but did not delete the requirement for containment doors to be locked and alarmed. This plan change deletes the requirement for containment doors to be locked and alarmed.

Provisions are made to move the boundary of the vital area during the performance of radioactive filter moves using existing locked and alarmed vital area doors. This change meets the requirements of 10 CFR 73.55(c), " Physical barriers."

The requirement to lock and alarm doors located within a vital area has been deleted. In addition, figures have been revised to reflect the vital area boundaries and doors.

The requirement for the number of security delay devices installed in the Essential Service Water Isolation Valve pits has been reduced.

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. U. S. Nuclear Regulatory Commission Page 2 NO. 3 In accordance with 10 CFR 73.55(d)(7)(i)(A), the maintenance of Access Lists for each vital area has been reduced.

To reflect changes in equipment technology, additional description for the control of ingress equipment calibration controls was added. Currently, access to calibration controls are required to have alarms or tamper switches. Much of the existing equipment is now password protected and computer operated.

These changes to the Braidwood Station beurity Plan were implemented May 18,1999.

Pursuant to 10 CFR 50.54 (p)(2), this descripta,.7 of the changes is required to be submitted by Ju'y 19,1999. i

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As required by 10 CFR 50.54(p)(2), we have concluded that these changes do not decrease the safeguards effectiveness of the Braidwood Station Security Plan.

The attachment contains Safeguards Information that must be protected from public disclosure as required by 10 CFR 73.21, " Requirements for the protection of safeguards information."

Should you have any questions concerning this letter, please contact Ms. K. M. Root at (630) 663-7292.

Respectfully, t

R. M. Krich Vice President - Regulatory Services

Attachment:

Braidwood Station Security Plan, Revision 45 cc: Regional Administrator- NRC Region lli (2 copies)

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