IR 05000352/2006007
| ML061440475 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 05/18/2006 |
| From: | Lorson R K Plant Support Branch 1 |
| To: | Crane C M Exelon Generation Co, Exelon Nuclear |
| References | |
| IR-06-007 | |
| Download: ML061440475 (4) | |
Text
May 18, 2006
Enclosure Contains Safeguards Information.When Separated from enclosure, this
document is not Safeguards Information.
Mr. Christopher Crane President and CEO
Exelon Nuclear
Exelon Generation Company, LLC
200 Exelon Way, KSA 3-E
Kennett Square, PA 19348
SUBJECT: LIMERICK GENERATING STATION - NRC SECURITY INSPECTION REPORT NOS. 05000352/2006007 AND 05000353/2006007
Dear Mr. Crane:
On April 7, 2006, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at your Limerick Generating Station. The inspection covered one or more of
the key attributes of the security cornerstone of the NRC's Reactor Oversight Process. The
enclosed report documents the inspection results, which were discussed on April 7, 2006, with
Mr. Ron DeGregorio, Site Vice President, and other members of your staff.
The inspection examined activities conducted under y our licenses as they relate to security and compliance with the Commission's rules and regulations and with the conditions of your
licenses. The inspectors reviewed selected procedures and records, observed activities, and
interviewed personnel. Warning: Violation of section 147 of the AtomicEnergy Act, "Safeguards Information" is subject to civil and criminal penalties DETERMINATION MADE BY:
NAME/TITLE: Raymond K. Lorson, ChiefORGANIZATION: RI/DRS/PSB1BASIS: DG-SG-1:_(300) Physical Protection ProgramSIGNATURE___/RA/____________ DATE:_05/18/06
_ Mr. C. Crane2 This report documents one finding of very low security significance (i.e., Green as determined by the Physical Protection Significance Determ ination Process). The deficiency was promptly compensated for, and the plant was in compliance with applicable physical protection and
security requirements within the scope of this inspection before the inspectors left the site.
NRC is treating this violation as a non-cited violati on (NCV) consistent with Section VI.A.1 of the NRC Enforcement Policy because of the very low security significance of the violation and
because it is entered into your corrective action program. If you contest this non-cited violation, you should provide a response within 30 days of the date of this inspection report, with the basis
for your denial, to the Nuclear Regulatory Commission, ATTN.: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator Region I; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-
0001; and the NRC Resident Inspector at the Limerick Generating Station.
In accordance with 10 CFR 2.390 of the NRC's "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 (PARS) component of NRC's document system, ADAMS. ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). However, because of the security-related concerns contained in the
enclosure, and in accordance with 10 CFR 2.390, a copy of this letter's enclosure will not be
available for public inspection.
In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response, if any. This practice will ensure that your response will not be made available electronically for public inspection in the NRC Public Document Room or from the NRC's
document system, ADAMS. If Safeguards Inform ation is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
Sincerely,/RA/Raymond K. Lorson, Chief Plant Support Branch 1
Division of Reactor SafetyDocket Nos.50-352, 50-353License Nos.NPF-39, NPF-85
Enclosure:
NRC Inspection Report Nos. 05000352/2006007 and 05000353/2006007
w/Attachment:
Supplemental Information (CONTAINS (SGI)
cc w/encl; w/SGI M