NEI 99-04, Oyster Creek - Commitment Change Summary Report - 2007
| ML082310640 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/08/2008 |
| From: | Rausch T S AmerGen Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NEI 99-04, RA-08-022 | |
| Download: ML082310640 (2) | |
Text
AmerGen.AmerGen Energy Company Oyster Creek US Route 9 South, P.O. Box 388 Forked River, NJ o8731-0388 www.exeloncorp.com An Exelon Company NEI 99-04 RA-08-022 August 8, 2008 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 -0001 Oyster Creek Nuclear Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219
Subject:
Commitment Change Summary Report -2007 Enclosed is the 2007 Commitment Change Summary Report for Oyster Creek Nuclear Generating Station. The content and format of information submitted in this report is in accordance with the guidance provided by NEI 99-04.Please contact Calvin Taylor at (609) 971-4031 if any further information or assistance is needed.Sincerely, Timothy S. Rausch Vice President, OCNGS Enclosure cc: S. J. Collins, Administrator, USNRC Region I G. Edward Miller, USNRC Senior Project Manager, Oyster Creek Marc Ferdas, USNRC Senior Resident Inspector, Oyster Creek File No. 07101 AJ(1/
Enclosure
-RA-08-022 Page 1 of 1 Oyster Creek Nuclear Generating Station 2007 Commitment Change Summary Report The following NRC Commitment tracked in the Oyster Creek Nuclear Generating Station (OCNGS) commitment-tracking database was changed during the calendar year 2007.This change was evaluated in accordance with Exelon Procedure LS-AA-1 10, Commitment Management, and determined to require NRC notification during the next Commitment Change Summary Report, consistent with NEI 99-04 guidance.Response to Generic Letter 96-01 Original Commitment
-GPU will review and compare OCNGS electrical schematic drawings and logic diagrams for those portions of the reactor protection system, emergency diesel generator load shedding and sequencing, and actuation logic for engineered safety features systems required for design basis accident mitigation against the OCNGS Technical Specification surveillance procedures.
The purpose of this review is to ensure that all applicable portions of the logic circuitry are adequately covered in the surveillance procedures to fulfill Technical Specification requirements.
Surveillance procedure inadequacies identified as part of this review, if any, will be addressed as necessary by surveillance procedure revision or request for technical specification amendment where justified.
Revised Commitment
-This commitment was implemented as a one-time commitment to ensure OCNGS was in compliance with NRC regulations.
Documentation of completion is contained in letter 6730-96-2112 to the NRC dated April 18, 1996.Justification
-OCNGS's response to Generic Letter 96-01 provided a docketed commitment to the NRC to ensure that a full surveillance testing validation was performed to address potential design vulnerabilities identified by the NRC for all reactor licensees.
This was a one-time commitment to ensure OCNGS was in compliance with requirements of 10 CFR 50.36(c)(3) and related regulatory requirements.
10 CFR 50 Appendix B design and procedure change control processes at OCNGS are credited for maintaining continued compliance with Technical Specification surveillance testing requirements.