ML12243A472

Request for Additional Information Related to Security Plan Submitted

ML12243A472
Person / Time
Site:	Byron
Issue date:	09/13/2012
From:	Joel Wiebe Plant Licensing Branch III
To:	Pacilio M Exelon Generation Co, Exelon Nuclear
Joel Wiebe, NRR/DORL, 415-6606
References
TAC ME9221, TAC ME9222
Download: ML12243A472 (4)

Text

September 13, 2012 Mr. Michael J. Pacilio Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)

Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

BYRON STATION, UNIT NOS. 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO SECURITY PLAN SUBMITTED (TAC NOS. ME9221 AND ME9222)

Dear Mr. Pacilio:

By letter to the U.S. Nuclear Regulatory Commission (NRC) dated July 13, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12198A299), Exelon Generation Company, LLC submitted the Byron Station, Unit Nos. 1 and 2, Physical Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 12. The enclosure to this letter contained Safeguards Information and has been withheld from public disclosure.

The NRC staff is currently reviewing the submittal to ensure compliance with Title 10 of the Code of Federal Regulations (10 CFR), Section 50.54(p)(2). The NRC staff has determined that additional information is needed to complete its review. The specific information requested is addressed in the enclosure to this letter. A response is requested within 30 days.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC=s goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-6606.

Sincerely,

/ RA /

Joel S. Wiebe, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-454 and STN 50-455

Enclosure:

Request for Additional Information cc w/encl: Listserv

Mr. Michael J. Pacilio Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)

Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

BYRON STATION, UNIT NOS. 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO SECURITY PLAN SUBMITTED (TAC NOS. ME9221 AND ME9222)

Dear Mr. Pacilio:

By letter to the U.S. Nuclear Regulatory Commission (NRC) dated July 13, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12198A299), Exelon Generation Company, LLC submitted the Byron Station, Unit Nos. 1 and 2, Physical Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 12. The enclosure to this letter contained Safeguards Information and has been withheld from public disclosure.

The NRC staff is currently reviewing the submittal to ensure compliance with Title 10 of the Code of Federal Regulations (10 CFR), Section 50.54(p)(2). The NRC staff has determined that additional information is needed to complete its review. The specific information requested is addressed in the enclosure to this letter. A response is requested within 30 days.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC=s goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-6606.

Sincerely,

/ RA /

Joel S. Wiebe, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-454 and STN 50-455

Enclosure:

Request for Additional Information cc w/encl: Listserv DISTRIBUTION:

PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 Resource RidsNrrPMBraidwood Resource RidsNrrLASRohrer Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource ADAMS Accession No.: ML12243A472 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC LPL3-2/PM NAME JWiebe SRohrer MDudek JWiebe DATE 9 / 13 /12 9 / 10 /12 9 /12 /12 9 / 13 /11

OFFICIAL RECORD COPY REQUEST FOR ADDITONAL INFORMATION 10 CFR 50.54(p)(2) CHANGES TO SECURITY PLAN EXELON GENERATION COMPANY, LLC BYRON, UNIT NOS. 1 AND 2 DOCKET NOS. 50-454 AND 50-455 LICENSE NOS. NPF-37 AND NPF-66 By letter dated July 13, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12198A299), Exelon Generation Company, LLC (the licensee) submitted the Byron Station, Unit Nos. 1 and 2, Physical Security Plan (PSP), Training and Qualification Plan, and Safeguards Contingency Plan (SCP), Revision 12. The enclosure to this letter contained Safeguards Information and has been withheld from public disclosure. The U.S. Nuclear Regulatory Commission (NRC) staff is currently reviewing the submittal to ensure compliance with Title 10 of the Code of Federal Regulations (10 CFR), Section 50.54(p)(2). The NRC staff has determined that the additional information requested below is needed to complete its review:

1. In Section 14.5 of the PSP, the licensee describes vital areas at Byron Station. The list of vital areas in Revision 11 of the PSP is different than in Revision 12. This change was not adequately described in the Description of Changes Report in Revision 12. Provide an explanation of the rationale for the change and how this change was evaluated to ensure it complies with 10 CFR 50.54(p)(2).

2. In Section 15.1 of the PSP, the licensee describes illumination at Byron Station.

Describe how the use of alternative technology for the assessment of the protected area (PA) perimeter in no-light or low-light conditions meets the requirements 10 CFR, Sections 73.55(e)(7)(i)(C) and 73.55(i)(2). Describe the technology used for assessment of the PA perimeter in no-light or low-light conditions. Additionally, the licensee should make appropriate changes during the next revision of the sites PSP to ensure the language clearly describes what technology is used for assessment of the PA perimeter in no-light or low-light conditions in accordance with 10 CFR 73.55 73.55(c)(3).

3. In Section 15.5.1 of the PSP, the licensee describes owner controlled area (OCA) surveillance methods. The second numbered paragraph does not adequately address the language in the bracketed text of the Nuclear Energy Institutes 03-12, Revision 7; it solely discusses facility procedures. Describe what equipment and/or personnel are used for OCA surveillance. Also, the licensee should make appropriate changes during the next revision of the sites PSP to ensure the language clearly describes the equipment and/or personnel used for OCA surveillance in accordance with 10 CFR 73.55(c)(3).

Enclosure

4. In Section 4.1.2 of the SCP, the licensee describes the security chain of command and delegation of authority. The description of the security chain of command and delegation of authority in Revision 11 of the SCP is different than in Revision 12.

This change was not described in the Description of Changes Report in Revision 12.

Describe the rationale for the change, and who is responsible for command and control when the individuals listed are not available. Additionally, the licensee should make appropriate changes during the next revision of the sites SCP to ensure the language clearly describes the security chain of command and delegation of authority in accordance with 10 CFR 73.55(c)(5).

5. In Section 5.4 of the SCP, the licensee describes facility operations personnel response. The description of training in Revision 11 of the SCP is different than in Revision 12. This change was not described in the Description of Changes report in Revision 12. Describe the change and whether the change was evaluated to ensure it complies with 10 CFR 50.54(p)(2). The licensee should make appropriate changes during the next revision of the sites SCP, Section 5.4, to ensure the language clearly describes the training related to facility operations personnel response in accordance with 10 CFR 73.55(c)(5).