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| {{#Wiki_filter:From: Hughey, John Sent: Wednesday, September 19, 2012 2:33 PM To: 'michelle.patti@pseg.com' Cc: 'Duke, Paul R.'; Khanna, Meena | | {{#Wiki_filter:From: Hughey, John Sent: Wednesday, September 19, 2012 2:33 PM To: 'michelle.patti@pseg.com' Cc: 'Duke, Paul R.'; Khanna, Meena |
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| ==Subject:== | | ==Subject:== |
| Salem and Hope Creek Generating Stations - Request for Additional Information Regarding August 1, 2012, Security Plan Submittal Michelle, By letter dated August 1, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12216A150), PSEG Nuclear LLC, (the licensee) submitted the Salem and Hope Creek Generating Stations' Physical Security Plan (PSP), Training and Qualification Plan (T&QP), and Safeguards Contingency Plan (SCP), Revision 15. The enclosure to the 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. The questions below have been confirmed by the Office of Nuclear Security Incident and Response to contain only publicly available information. | | Salem and Hope Creek Generating Stations - Request for Additional Information Regarding August 1, 2012, Security Plan Submittal |
| The NRC staff requests that you provide a response to this request within 30 days from the date of this e-mail. If you are unable to meet the requested response date or if you would like a conference call to discuss this request, please contact me at (301) 415-3204. | | : Michelle, By letter dated August 1, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12216A150), PSEG Nuclear LLC, (the licensee) submitted the Salem and Hope Creek Generating Stations Physical Security Plan (PSP), Training and Qualification Plan (T&QP), and Safeguards Contingency Plan (SCP), Revision 15. The enclosure to the 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. The questions below have been confirmed by the Office of Nuclear Security Incident and Response to contain only publicly available information. |
| | The NRC staff requests that you provide a response to this request within 30 days from the date of this e-mail. If you are unable to meet the requested response date or if you would like a conference call to discuss this request, please contact me at (301) 415-3204. |
| Thank you, John D. Hughey, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION | | Thank you, John D. Hughey, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION |
| : 1. In section 9 of the PSP, the license e describes security personnel equipment. The equipment list in Revision 15 of the PSP is different than the equipment list in Revision 14 of the PSP. This was noted in the Evaluation of the Proposed Changes to the Site Security Plan or Implementing Procedure/T&RM provided by the licensee; however, there was no rationale for this change. Provide the rationale for this change and how the change was evaluated to ensure it complies with 10 CFR 50.54(p)(2). | | : 1. In section 9 of the PSP, the licensee describes security personnel equipment. The equipment list in Revision 15 of the PSP is different than the equipment list in Revision 14 of the PSP. This was noted in the Evaluation of the Proposed Changes to the Site Security Plan or Implementing Procedure/T&RM provided by the licensee; however, there was no rationale for this change. Provide the rationale for this change and how the change was evaluated to ensure it complies with 10 CFR 50.54(p)(2). |
| : 2. In section 11.2.2 of the PSP, the licensee describes the vehicle barrier system (VBS). In this section, the licensee does not describe what components make up the VBS. Also, the | | : 2. In section 11.2.2 of the PSP, the licensee describes the vehicle barrier system (VBS). In this section, the licensee does not describe what components make up the VBS. Also, the description in section 11.2.2 of the PSP in Revision 15 is different than in Revision 14 of the PSP. Describe the components that make up the VBS. Additionally, the licensee should make appropriate changes during the next revision of the sites PSP to ensure the language clearly describes the components that make up the VBS in accordance with 10 CFR 73.55(e)(1)(ii). |
| | | : 3. In section 15.1 of the PSP, the licensee describes illumination at the site. Describe how the use of alternative technology for the assessment of the PA perimeter in no-light or low-light |
| description in section 11.2.2 of the PSP in Revision 15 is different than in Revision 14 of the PSP. Describe the components that make up the VBS. Additionally, the licensee should | |
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| make appropriate changes during the next revision of the site's PSP to ensure the language clearly describes the components that make up the VBS in accordance with 10 CFR 73.55(e)(1)(ii).
| | conditions meets the requirements 10 CFR 73.55(e)(7)(i)(C) and 73.55(i)(2). 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(c)(3). |
| : 3. In section 15.1 of the PSP, the licensee describes illumination at the site. Describe how the use of alternative technology for the assessment of the PA perimeter in no-light or low-light conditions meets the requirements 10 CFR 73.55(e)(7)(i)(C) and 73.55(i)(2). Additionally, the licensee should make appropriate changes during the next revision of the site's 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(c)(3).
| | : 4. In section 15.3 of the PSP, the licensee describes intrusion detection equipment at the site. |
| : 4. In section 15.3 of the PSP, the licensee describes intrusion detection equipment at the site. In the last paragraph of this section, the licensee describes a system. Describe the intended function and purpose of this system. Is this system designed to meet the requirements of 10 CFR 73.55(i)? If so, describe how the system meets these requirements. Additionally, the licensee should make appropriate changes during the next revision of the site's PSP to ensure the language clearly describes the intended function and purpose of this system and how the system meets the requirements of 10 CFR 73.55.}} | | In the last paragraph of this section, the licensee describes a system. Describe the intended function and purpose of this system. Is this system designed to meet the requirements of 10 CFR 73.55(i)? If so, describe how the system meets these requirements. Additionally, the licensee should make appropriate changes during the next revision of the sites PSP to ensure the language clearly describes the intended function and purpose of this system and how the system meets the requirements of 10 CFR 73.55.}} |
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[Table view] |
Text
From: Hughey, John Sent: Wednesday, September 19, 2012 2:33 PM To: 'michelle.patti@pseg.com' Cc: 'Duke, Paul R.'; Khanna, Meena
Subject:
Salem and Hope Creek Generating Stations - Request for Additional Information Regarding August 1, 2012, Security Plan Submittal
- Michelle, By letter dated August 1, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12216A150), PSEG Nuclear LLC, (the licensee) submitted the Salem and Hope Creek Generating Stations Physical Security Plan (PSP), Training and Qualification Plan (T&QP), and Safeguards Contingency Plan (SCP), Revision 15. The enclosure to the 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. The questions below have been confirmed by the Office of Nuclear Security Incident and Response to contain only publicly available information.
The NRC staff requests that you provide a response to this request within 30 days from the date of this e-mail. If you are unable to meet the requested response date or if you would like a conference call to discuss this request, please contact me at (301) 415-3204.
Thank you, John D. Hughey, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION
- 1. In section 9 of the PSP, the licensee describes security personnel equipment. The equipment list in Revision 15 of the PSP is different than the equipment list in Revision 14 of the PSP. This was noted in the Evaluation of the Proposed Changes to the Site Security Plan or Implementing Procedure/T&RM provided by the licensee; however, there was no rationale for this change. Provide the rationale for this change and how the change was evaluated to ensure it complies with 10 CFR 50.54(p)(2).
- 2. In section 11.2.2 of the PSP, the licensee describes the vehicle barrier system (VBS). In this section, the licensee does not describe what components make up the VBS. Also, the description in section 11.2.2 of the PSP in Revision 15 is different than in Revision 14 of the PSP. Describe the components that make up the VBS. Additionally, the licensee should make appropriate changes during the next revision of the sites PSP to ensure the language clearly describes the components that make up the VBS in accordance with 10 CFR 73.55(e)(1)(ii).
- 3. In section 15.1 of the PSP, the licensee describes illumination at the site. Describe how the use of alternative technology for the assessment of the PA perimeter in no-light or low-light
conditions meets the requirements 10 CFR 73.55(e)(7)(i)(C) and 73.55(i)(2). 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(c)(3).
- 4. In section 15.3 of the PSP, the licensee describes intrusion detection equipment at the site.
In the last paragraph of this section, the licensee describes a system. Describe the intended function and purpose of this system. Is this system designed to meet the requirements of 10 CFR 73.55(i)? If so, describe how the system meets these requirements. Additionally, the licensee should make appropriate changes during the next revision of the sites PSP to ensure the language clearly describes the intended function and purpose of this system and how the system meets the requirements of 10 CFR 73.55.