ML12296A929
| ML12296A929 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 10/23/2012 |
| From: | Russell Felts Division of Security Policy |
| To: | Adam Wilson Plant Licensing Branch 1 |
| Lee P | |
| Shared Package | |
| ML12296A928 | List: |
| References | |
| Download: ML12296A929 (2) | |
Text
October 23, 2012 MEMORANDUM TO:
George A. Wilson, Jr., Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:
Russell Felts, Chief /RA/
Reactor Security Licensing Branch Division of Security Policy Office of Nuclear Security and Incident Response
SUBJECT:
DRAFT REQUEST FOR ADDITIONAL INFORMATION FOR INDIAN POINT UNITS 1 AND 2 (DOCKET NOs. 50-03, 50-247, AND 50-286), "PHYSICAL SECURITY, TRAINING AND QUALIFICATION, SAFEGUARDS CONTINGENCY PLAN, AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION SECURITY PROGRAM," REVISION 14 By letter dated August 7, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML1217A0457), Entergy Operations, Inc. (Entergy) submitted the Indian Point Energy Center (IPEC) Physical Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 14. The Reactor Security Licensing Branch (RSLB) staff is currently reviewing the changes to ensure that the licensee has complied with applicable regulatory requirements of Title 10 of the Code of Federal Regulations (10 CFR) 73, Physical Protection of Plants and Material, and the provisions of 10 CFR 50.54(p)(2), which allows licensees to make changes without prior U.S. Nuclear Regulatory Commission (NRC) approval.
The RSLB staff has determined that a request for additional information (RAI) is necessary to complete its review. The staff RAI is designated as publically available information. Please issue the enclosed RAI.
Please note that the changes described and implemented have reduced the plant configuration from two to a single access point, and the RAI included Entergys implementation of processes and determination results for meeting the requirements of 10 CFR 73.58, Safety/security interface requirements for nuclear power reactors. In addition, RSLB requests your assistance to: (1) review the adequacy of the licensees implementation of processes and confirm that the criteria set forth in the provisions of 10 CFR 50.59, Changes, tests and experiments, have been met for making the changes without prior NRC approval; and (2) lead the review on whether the licensee has adequately addressed the possible effects of the plant configuration change on the descriptions, analyses, and assumptions found in the Updated Final Safety Analysis Report, Emergency Plan, Fire Hazards Analysis, and other licensing basis documents.
Enclosure:
Request for Additional Information CONTACT: Peter Lee, NSIR/DSP (301) 415-8111
ML12296A928 OFFICE NSIR/DSP NSIR/DSP NAME PLee RFelts DATE 10 /23 /12 10 /23 /12