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{{Adams|number = ML061440475}} | {{Adams | ||
| number = ML061440475 | |||
| issue date = 05/18/2006 | |||
| title = IR 05000352-06-007, 05000353-06-007; 04/04/2006 - 04/07/2006; Limerick Generating Station, Units 1 and 2; Access Control | |||
| author name = Lorson R | |||
| author affiliation = NRC/RGN-I/DRS/PSB1 | |||
| addressee name = Crane C | |||
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear | |||
| docket = 05000352, 05000353 | |||
| license number = NPF-039, NPF-085 | |||
| contact person = | |||
| document report number = IR-06-007 | |||
| document type = Inspection Report, Letter | |||
| page count = 4 | |||
}} | |||
{{IR-Nav| site = 05000352 | year = 2006 | report number = 007 }} | {{IR-Nav| site = 05000352 | year = 2006 | report number = 007 }} | ||
=Text= | =Text= | ||
{{#Wiki_filter | {{#Wiki_filter:May 18, 2006 | ||
==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 NRCs 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 your licenses as they relate to security and compliance with the Commissions rules and regulations and with the conditions of your licenses. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. | |||
NAME/TITLE: Raymond K. Lorson, | Warning: Violation of section 147 of the Atomic Energy Act, Safeguards Information is subject to civil and criminal penalties DETERMINATION MADE BY: | ||
0001; and the NRC Resident Inspector at the Limerick Generating Station. In accordance with 10 CFR 2.390 of the | NAME/TITLE: Raymond K. Lorson, Chief ORGANIZATION: RI/DRS/PSB1 BASIS: DG-SG-1:_(300) Physical Protection Program SIGNATURE___/RA/____________ DATE:_05/18/06_ Mr. This report documents one finding of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination 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 violation (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 NRCs 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 NRCs 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 letters 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 NRCs document system, ADAMS. If Safeguards Information 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 Safety Docket Nos. | |||
50-352, 50-353 License Nos. NPF-39, NPF-85 Enclosure: | |||
Supplemental Information(CONTAINS (SGI)cc w/encl; w/SGI M | NRC Inspection Report Nos. 05000352/2006007 and 05000353/2006007 w/Attachment: Supplemental Information (CONTAINS (SGI) | ||
cc w/encl; w/SGI M | |||
}} | }} | ||
Latest revision as of 08:46, 15 January 2025
| ML061440475 | |
| Person / Time | |
|---|---|
| Site: | Limerick |
| Issue date: | 05/18/2006 |
| From: | Ray Lorson Plant Support Branch 1 |
| To: | Crane C Exelon Generation Co, Exelon Nuclear |
| References | |
| IR-06-007 | |
| Download: ML061440475 (4) | |
Text
May 18, 2006
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 NRCs 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 your licenses as they relate to security and compliance with the Commissions 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 Atomic Energy Act, Safeguards Information is subject to civil and criminal penalties DETERMINATION MADE BY:
NAME/TITLE: Raymond K. Lorson, Chief ORGANIZATION: RI/DRS/PSB1 BASIS: DG-SG-1:_(300) Physical Protection Program SIGNATURE___/RA/____________ DATE:_05/18/06_ Mr. This report documents one finding of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination 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 violation (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 NRCs 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 NRCs 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 letters 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 NRCs document system, ADAMS. If Safeguards Information 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 Safety Docket Nos.
50-352, 50-353 License 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