ML12279A295

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Request for Additional Information 10 CFR 50.54(p)(2) Changes to Security Plan
ML12279A295
Person / Time
Site: Millstone, Monticello  Xcel Energy icon.png
Issue date: 10/12/2012
From: James Kim
Plant Licensing Branch 1
To: Heacock D
Dominion Nuclear Connecticut
Kim J
References
Download: ML12279A295 (4)


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~O October 12, 2012

      • 11<1' Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.

Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060~6711

SUBJECT:

MILLSTONE POWER STATION, UNITS 1,2 AND 3 - REQUEST FOR ADDITIONAL INFORMATION RE: 10 CFR 50.54(p}(2) CHANGES TO SECURITY PLAN

Dear Mr. Heacock:

By letter dated July 30,2012 (Agencywide Documents Access and Management System Accession No. ML12214A581), Dominion Nuclear Connecticut, Inc., submitted Dominion's Physical Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 15 for the Millstone Power Station. 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, Section 50.54(p)(2).

The NRC staff has determined that the enclosed request for additional information (RAI) is needed in order to complete the review. A response to this RAI is requested to be provided within 45 days of the date of this letter.

If you have any questions regarding this matter, please contact me at 301 ~415-4i 25.

Sincerely.

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James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-26:3, 50-336 and 50-423

Enclosure:

As stated cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION REGARDING MILLSTONE POWER STATION UNITS 1, 2 AND 3 10 CFR 50.54{p)(2) CHANGES TO SECURITY PLAN DOCKET NOS: 50-263, 50-336 AND 50-423 By letter dated July 30,2012 (Agencywide Documents Access and Management System Accession No. ML12214A581), Dominion Generation, submitted Dominion's Physical Security Plan (PSP), Training and Qualification Plan (T&QP), and Safeguards Contingency Plan (SCP),

Revision 15 for the Millstone Power Station. 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.

1. Section 15.1 of the PSP describes illumination at the site. Describe the type of alternative technology being implemented at the protected area perimeter to augment illumination. Describe how the alternative technology provides the capability to perform protected area perimeter assessment in no-light or low-light conditions and specifically during the loss of normal power. Describe how the alternative technology is integrated within the protected area perimeter intrusion detection and assessment systems to meet the requirements of 10 CFR 73.55(e)(7)(i)(C), 10 CFR 73.55(i)(2},

and 10 CFR 73.55(i)(3)(vii}. See Security Frequently Asked Question (SFAQ) 10-15.

Additionally, appropriate changes should be made during the next revision of the site's PSP to ensure the language clearly describes the type(s) of technology used to augment illumination for the assessment of the protected area perimeter in no-light or low-light conditions and during the loss of normal power, and how the technology meets the requirements of 10 CFR 73.55(c)(3), 10 CFR 73.55(e)(7)(i)(C), 10 CFR 73.55(i)(2), 10 CFR 73.55(i)(3)(vii), and 10 CFR 73.55(i)(6)(iii).

Regulatory Basis:

Consistent with 10 CFR 73.55(c)(3), the licensee shall establish, maintain, and implement a Physical Security Plan which describes how the performance objective and requirements set forth in this section will be implemented.

Consistent with10 CFR 73.55(e)(7)(i)(C), isolation zones shall be monitored with assessment equipment designed to satisfy the requirements of Section 73.55{i) and provide real-time and play-back/recorded video images of the detected activities before and after each alarm annunciation.

Consistent with 10 CFR 73.55(i)(2), intrusion detection equipment must annunciate and video assessment equipment shall display concurrently, in at least two continuously staffed onsite alarm stations, at least one of which must be protected in accordance with the requirements of the central alarm station within this section.

Enclosure

- 2 Consistent with 10 CFR 73.55(i)(3)(vii), the licensee's intrusion detection and assessment systems must be designed to ensure intrusion detection and assessment equipment at the protected area perimeter remains operable from an uninterruptible power supply in the event of the loss of normal power.

Consistent with 10 CFR 73.55(i)(6)(iii), the licensee shall describe in the security plans how the lighting requirements of this section are met and, if used, the type(s) and application of low-light technology.

October 12, 2012 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.

Innsbrook Technical Center SOOO Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

MILLSTONE POWER STATION, UNITS 1,2 AND 3 - REQUEST FOR ADDITIONAL INFORMATION RE: 10 CFR SO.S4(p)(2) CHANGES TO SECURITY PLAN

Dear Mr. Heacock:

By letter dated July 30, 2012 (Agencywide Documents Access and Management System Accession No. ML12214AS81), Dominion Nuclear Connecticut, Inc., submitted Dominion's Physical Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 1S for the Millstone Power Station. 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, Section SO.S4(p)(2).

The NRC staff has determined that the enclosed request for additional information (RAI) is needed in order to complete the review. A response to this RAI is requested to be provided within 4S days of the date of this letter.

If you have any questions regarding this matter, please contact me at 301-41S-412S.

Sincerely, IRA by DPickett fori James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. SO-263, SO-336 and SO-423

Enclosure:

As stated cc w/encl: Distribution via Listserv Distribution:

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