IR 05000387/2008008

IR 05000387-08-008, and IR 05000388-08-008, on 09/08/2008 to 09/12/2008, Susquehanna Steam Electric Station; Temporary Instruction 2515/171, Verification of Site Specific Implementation of B.5.b Phase 2 & 3, Mitigating Strategies. Letter On

ML082960592
Person / Time
Site:	Susquehanna
Issue date:	10/20/2008
From:	Rogge J Engineering Region 1 Branch 3
To:	Mckinney B Susquehanna
References
IR-08-008
Download: ML082960592 (5)

Text

ber 20, 2008

SUBJECT:

SUSQUEHANNA GENERATING STATION - NRC TEAM INSPECTION REPORT NOS. 05000387/2008008 and 05000388/2008008

Dear Mr. McKinney:

On September 12, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed a team inspection of your Susquehanna Generating Station Units 1 and 2. The enclosed report documents the teams results, which were discussed on September 12, 2008, with Mr. J. Tucker and other members of your staff.

The inspection examined activities conducted under your license as they relate to the implementation of B.5.b Phase 2 and 3 mitigating strategies, your compliance with the Commissions rules and regulations, and with the condition of your operating license. Within these areas, the inspection involved examination of selected procedures and records, observation of activities, and interviews with station personnel. No findings of significance were identified.

In accordance with 10 CFR 2.390 of the NRC Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of the NRC Agency-wide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). However, When separated from the Enclosure, this document is DECONTROLLED. because of the sensitive information contained in the enclosure, and in accordance with 10 CFR 2.390, a copy of this letters enclosure will not be available for public inspection.

Sincerely,

/RA/

John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-387; 50-388 License Nos. NPF-14, NPF-22 Enclosure: Inspection Report 05000387/2008008 and 05000388/2008008 w/Attachment: Supplemental Information