ML12258A268

Issuance of Amendments License Amendment Request - Cyber Security Plan

ML12258A268
Person / Time
Site:	Indian Point
Issue date:	11/28/2012
From:	Pickett D Plant Licensing Branch 1
To:	Entergy Nuclear Operations
Pickett D, NRR/DORL/LPL1-1, 415-1364
References
TAC ME8885, TAC ME8886, TAC ME8887, FOIA/PA-2016-0148
Download: ML12258A268 (19)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 28, 2012 Vice President, Operations Entergy Nuclear Operations, Inc.

Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249

SUBJECT:

INDIAN POINT NUCLEAR GENERATING UNIT NOS. 1, 2, AND 3 - ISSUANCE OF AMENDMENTS RE: CYBER SECURITY PLAN IMPLEMENTATION SCHEDULE MILESTONES (TAC NOS. ME8885, ME8886, AND ME8887)

Dear Sir or Madam:

The Commission has issued the enclosed Amendment No. 56 to Provisional Operating License No. DPR-5, for the Indian Point Nuclear Generating Unit No.1, Amendment No. 269 to Facility Operating License No. DPR-26 for the Indian Point Nuclear Generating Unit No.2 and Amendment No. 247 to Facility Operating License No. DPR-64 for the Indian Point Nuclear Generating Unit No.3. The amendments consist of changes to the Facility Operating Licenses in response to your application dated June 14, 2012.

The licensee's application for the proposed amendments would revise the scope of Cyber Security Plan (CSP) Implementation Schedule Milestone #6. Milestone #6 of the CSP implementation schedule concerns the identification, documentation, and implementation of cyber security controls (technical, operational, and management) for critical digital assets (CDAs) related to target set equipment. Entergy is requesting to modify the scope of Milestone

1. 6 to apply to the technical cyber security controls only. The operational and management controls, as described in Nuclear Energy Institute (NEI) 08-09, Revision 6, would be implemented concurrent with the full implementation of the Cyber Security Program (Milestone

1. 8). Thus, all CSP activities would be fully implemented by the completion date, identified in Milestone #8 of the licensee's CSP implementation schedule.

These license amendments are effective as of the date of its issuance and shall be implemented by December 31,2012.

V. P. Operations -2 A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.

Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.50-003, 50-247, and 50-286

Enclosures:

1. Amendment No. 56 to DPR-5

2. Amendment No. 269 to DPR-26

3. Amendment No. 247 to DPR-64

4. Safety Evaluation cc w/encls: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENTERGY NUCLEAR INDIAN POINT 2, LLC ENTERGY NUCLEAR OPERATIONS, INC.

DOCKET NO.50-003 INDIAN POINT NUCLEAR GENERATING UNIT NO.1 AMENDMENT TO THE PROVISIONAL OPERATING LICENSE (DPR-5)

AND TECHNICAL SPECIFICATIONS Amendment No. 56 License No. DPR-5

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Entergy Nuclear Operations, Inc. (the licensee) dated June 14, 2012, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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2. Accordingly, the license is amended as indicated in the attachment to this license amendment, and paragraph 3.b) of Facility Operating License No. DPR-5 is hereby amended to read as follows:

3.b) Technical Specifications The Technical Specifications contained in Appendices A and S, as revised through Amendment No. 56, are hereby incorporated in the license. ENO shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance and shall be implemented by December 31,2012.

FOR THE NUCLEAR REGULATORY COMMISSION Andrew Persinko, Deputy Director Division of Waste Management and Environmental Protection Office of Federal and State Materials and Environmental Management Programs

Attachment:

Changes to the License Date of Issuance: November 28, 2012

ATTACHMENT TO LICENSE AMENDMENT NO. 56 PROVISIONAL OPERATING LICENSE NO. DPR-5 DOCKET NO.50-003 Replace the following page of the License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Page Insert Page Page 2 Page 2

-2 designated location in Westchester County, New York, in accordance with the procedures and limitations described in the application and this license; b) ENO, pursuant to the Act and 10 CFR Part 70, to receive and possess up to 1918 kilograms of contained uranium-235 previously received for reactor operation; c) Deleted ENO, pursuant to the Act and Title 10, CFR, Chapter 1, Part 70, "Special Nuclear Material," to receive, possess and use six (6) grams of uranium 235 in fission counters; d) Deleted E~JO, pursuant to the ,A,ct and Title 10, CFR, Chapter 1, Part 30, "Licensing of Byproduct Material," to receive, possess and use six hundred (600) curies of Plutonium 210 encapsulated as Po Be neutron star up sources; e) ENO, pursuant to the Act and 10 CFR Parts 30 and 70, to receive Arndt. 45 and possess, but not to separate, such byproduct and special 1-31-96 materials as were produced by the prior operation of the facility; f) Deleted ENO, pursuant to the Act and Title 10, CFR, Parts 30 and 70, to possess and store the 1140.46 kilograms of special nuclear material and the byproduct materials contained in Core A.

3. This license shall be deemed to contain and is subject to the conditions specified in Sections 50.54 and 50.59 of Part 50, Section 70.32 of Part 70, Section 40.41 of Part 40, and Section 30.32 of Part 30 of the Commission's regulations; is subject to all applicable provisions of the Act and rules, regulations and orders of the Commission now and hereafter in effect; and is subject to the additional conditions specified below:

a) Maximum Power Level ENO is prohibited from taking the reactor to criticality, and the facility shall not be operated at any power level.

b) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 56, are hereby incorporated in the license. ENO shall maintain the facility in accordance with the Technical SpeCifications.

c) Records In addition to those otherwise required under this license and applicable regulations, ENO shall keep the following records:

1. Reactor operating records, including power levels Amendment No. 56

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENTERGY NUCLEAR INDIAN POINT 2, LLC ENTERGY NUCLEAR OPERATIONS. INC.

DOCKET NO. 50-247 INDIAN POINT NUCLEAR GENERATING UNIT NO.2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 269 License No. DPR-26

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Entergy Nuclear Operations, Inc. (the licensee) dated June 14, 2012, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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2. Accordingly, the license is amended as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-26 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A, B, and C, as revised through Amendment No. 269, are hereby incorporated in the license. ENO shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance and shall be implemented by December 31, 2012.

FOR THE NUCLEAR REGULATORY COMMISSION

/l;~~

George AWon, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License Date of Issuance: November 28, 2012

ATTACHMENT TO LICENSE AMENDMENT NO. 269 FACILITY OPERATING LICENSE NO. DPR-26 DOCKET NO. 50-247 Replace the following page of the License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Page Insert Page Page 3 Page 3

- 3 instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) ENO pursuant to the Act and 10 CFR Parts 30, 40 and 70, to Amdt. 42 receive, possess, and use in amounts as required any 10-17-78 byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) ENO pursuant to the Act and 10 CFR Parts 30 and 70, to Amdt. 220 possess, but not separate, such byproduct and special 09-06-01 nuclear materials as may be produced by the operation of the facility.

C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level ENO is authorized to operate the facility at steady state Amdt. 241 reactor core power levels not in excess of 3216 megawatts 10-27-04 thermal.

(2) Technical Specifications The Technical Specifications contained in Appendices A, B, and C, as revised through Amendment No. 269, are hereby incorporated in the license.

ENO shall operate the facility in accordance with the Technical Specifications.

(3) The following conditions relate to the amendment approving the conversion to Improved Standard Technical Specifications:

1. This amendment authorizes the relocation of certain Technical Specification requirements and detailed information to licensee controlled documents as described in Table R, "Relocated Technical Specifications from the CTS," and Table LA, "Removed Details and Less Restrictive Administrative Changes to the CTS" attached to the NRC staff's Safety Evaluation enclosed with this amendment. The relocation of requirements and detailed information shall be completed on or before the implementation of this amendment.

Amendment No. 269

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENTERGY NUCLEAR INDIAN POINT 3, LLC ENTERGY NUCLEAR OPERATIONS, INC.

DOCKET NO. 50-286 INDIAN POINT NUCLEAR GENERAliNG UNIT NO.3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 247 License No. DPR-64

1. The Nuclear Regulatory Commission (the Commission) has found that A. The application for amendment by Entergy Nuclear Operations, Inc. (the licensee) dated June 14, 2012, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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2. Accordingly, the license is amended as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-64 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A, B, and C, as revised through Amendment No. 247, are hereby incorporated in the license. ENO shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance and shall be implemented by December 31,2012.

FOR THE NUCLEAR REGULATORY COMMISSION "t-c...~

George ~Ison, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License Date of Issuance: November 28, 2012

ATTACHMENT TO LICENSE AMENDMENT NO. 247 FACILITY OPERATING LICENSE NO. DPR-64 DOCKET NO. 50-286 Replace the following page of the License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Page Insert Page Page 3 Page 3

- 3 (4) ENO pursuant to the Act and 10 CFR Parts 30, 40 and 70, Amdt. 203 to receive, possess, and use in amounts as required any 11/27/00 byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) ENO pursuant to the Act and 10 CFR Parts 30 and 70, to Amdt. 203 possess. but not separate, such byproduct and special 11/27/00 nuclear materials as may be produced by the operation of the facility.

C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level ENO is authorized to operate the facility at steady state reactor core power levels not in excess of 3216 megawatts thermal (100% of rated power).

(1) Technical Specifications The Technical Specifications contained in Appendices A, B, and C, as revised through Amendment No. 247, are hereby incorporated in the License. ENO shall operate the facility in accordance with the Technical Specifications, (3) (DELETED) Amdt. 205 2-27-01 (4) (DELETED) Amdt. 205 2-27-01 D. (DELETED) Amdt.46 2-16-83 E. (DELETED) Amdt.37 5-14-81 F. This amended license is also subject to appropriate conditions by the New York State Department of Environmental Conservation in its letter of May 2, 1975, to Consolidated Edison Company of New York, Inc., granting a Section 401 certification under the Federal Water Pollution Control Act Amendments of 1972.

Amendment No. 247

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 56 TO PROVISIONAL OPERATING LICENSE NO. DPR-5, AMENDMENT NO. 269 TO FACILITY OPERATING LICENSE NO. DPR-26 AND AMENDMENT NO. 247 TO FACILITY OPERATING LICENSE NO. DPR-64 ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NOS. 1, 2, AND 3 DOCKET NOS.50-003, 50-247, AND 50-286

1.0 INTRODUCTION

By application dated June 14, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12184A050), Entergy Nuclear Operations, Inc. (Entergy, the licensee) requested changes to the facility operating licenses for Indian Point, Units 1, 2, and 3 (Indian Point Energy Center [IPEC]). The proposed changes would revise the scope of Cyber Security Plan (CSP) Implementation Schedule Milestone #6. Milestone #6 of the CSP implementation schedule concerns the identification, documentation, and implementation of cyber security controls (technical, operational, and management) for critical digital assets (CDAs) related to target set equipment. Entergy is requesting to modify the scope of Milestone

1. 6 to apply to the technical cyber security controls only. The operational and management controls, as described in Nuclear Energy Institute (NEI) 08-09, Revision 6, would be implemented concurrent with the full implementation of the Cyber Security Program (Milestone

1. 8). Thus, all CSP activities would be fully implemented by the completion date, identified in Milestone #8 of the licensee's CSP implementation schedule.

Portions of the letter dated June 14, 2012, contain sensitive unclassified non-safeguards information and, accordingly, those portions are withheld from public disclosure.

2.0 REGULATORY EVALUATION

The U.S. Nuclear Regulatory Commission (NRC) staff reviewed and approved the licensee's existing CSP implementation schedule by License Amendment Nos. 55, 266, and 243 dated August 2, 2011 (ADAMS Accession No. ML11152A027), concurrent with the incorporation of the CSP into the facility current licensing basis. The NRC staff considered the following regulatory requirements and guidance in its review of the current license amendment request to modify the existing CSP implementation schedule:

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• Title 10 of the Code of Federal Regulations (10 CFR) 73.54 states: "Each [CSP]

submittal must include a proposed implementation schedule. Implementation of the licensee's cyber security program must be consistent with the approved schedule."

• The licensee's facility operating licenses include a license condition that requires the licensee to fully implement and maintain in effect all provisions of the Commission-approved CSP.

• Amendment Nos. 55, 266, and 243, dated August 2, 2011, which approved the licensee's CSP and implementation schedule, included the following statement: "The implementation of the CSP, including the key intermediate milestone dates and the full implementation date, shall be in accordance with the implementation schedule submitted by the licensee on July 8, 2010, as supplemented by letters dated February 18, April 1, and June 29, 2011, and approved by the NRC staff with this license amendment. All subsequent changes to the NRC-approved CSP implementation schedule will require prior NRC approval pursuant to 10 CFR 50.90."

• In a letter to NEI dated March 1, 2011 (ADAMS Accession No. ML110070348), the NRC staff acknowledged that the cyber security implementation schedule template was "written generically and licensees that use the template to develop their proposed implementation schedules may need to make changes to ensure the submitted schedule accurately accounts for site-specific activities."

3.0 TECHNICAL EVALUATION

Amendment Nos. 55, 266, and 243 to Facility Operating License Nos. DPR-5, DPR-26, and DPR-64 for IPEC were issued on August 2, 2011. The NRC staff also approved the licensee's CSP implementation schedule, as discussed in the safety evaluation issued with the amendments. The implementation schedule had been submitted by the licensee based on a template prepared by NEI, which the NRC staff found acceptable for licensees to use to develop their CSP implementation schedules (ADAMS Accession No. ML110600218). The licensee's proposed implementation schedule for the Cyber Security Program identified completion dates and bases for the following eight milestones:

1) Establish the Cyber Security Assessment Team (CSAT);

2) Identify Critical Systems and CDAs;

3) Install a deterministic one-way device between lower level devices and higher level devices;

4) Implement the security control "Access Control For Portable And Mobile Devices;"

5) Implement observation and identification of obvious cyber related tampering to existing insider mitigation rounds by incorporating the appropriate elements;

6) Identify, document, and implement cyber security controls as per "Mitigation of Vulnerabilities and Application of Cyber Security Controls" for CDAs that could adversely impact the design function of physical security target set equipment;

7) Commence ongoing monitoring and assessment activities for those target set CDAs whose security controls have been implemented; and

8) Fully implement the CSP.

3.1 Licensee's Proposed Change Currently, Milestone #6 of IPEC's CSP requires Entergy to identify, document, and implement cyber security controls for CDAs that could adversely impact the design function of physical security target set equipment by December 31, 2012. These cyber security controls consist of technical, operational and management security controls. In its June 14, 2012, application, Entergy proposed to modify Milestone #6 to change the scope of the cyber security controls due to be implemented on December 31,2012, to include only the NEI 08~09, Revision 6, Appendix o technical security controls. Entergy proposes to amend its CSP to provide that operational and management security controls, identified in Milestone #6, will be fully implemented by a later date, which is the completion date identified in Milestone #8 of the CSP implementation schedule. The licensee stated that implementing the technical cyber security controls for target set CDAs provides a high degree of protection against cyber~related attacks that could lead to radiological sabotage. The licensee further stated that many of its existing programs are primarily procedure~based programs and must be implemented in coordination with the comprehensive Cyber Security Program. The licensee also stated that the existing programs currently in place at Indian Point, Units 1, 2, and 3 (e.g., physical protection, maintenance, configuration management, and operating experience) provide sufficient operational and management cyber security protection during the interim period until the Cyber Security Program is fully implemented.

3.2 NRC Staff Evaluation The intent of the cyber security implementation schedule was for licensees to demonstrate ongoing implementation of their cyber security program prior to full implementation, which is set for the date specified in Milestone #8. In addition to Milestone #6 and its associated activities, licensees will be completing six other milestones (Milestones #1 through #5 and Milestone #7) by December 31,2012. Activities include establishing a CSAT, identifying critical systems and CDAs, installing deterministic one-way devices between defensive levels, implementing access control for portable and mobile devices, implementing methods to observe and identify obvious cyber related tampering, and conducting ongoing monitoring and assessment activities for target set CDAs. In the aggregate, the interim milestones demonstrate ongoing implementation of the cyber security program at Indian Point, Units 1, 2, and 3.

The NRC staff has reviewed the licensee's evaluation of the proposed change in its submittal dated June 14, 2012, and finds that by completing Milestones #1 through #5, Milestone #6 with implementation of technical controls to target set CDAs, and Milestone #7, Indian Point, Units 1, 2, and 3 will have an acceptable level of cyber security protection until full program implementation is achieved. Technical cyber security controls include access controls, audit and accountability, CDA and communications protection, identification and authentication, and system hardening. These controls are executed by computer systems, as opposed to people, and consist of hardware and software controls that provide automated protection to a system or application. Implementation of technical cyber security controls promotes standardization, trust, interoperability, connectivity, automation, and increased efficiency. For these reasons, the NRC staff concludes that the licensee's approach is acceptable.

The NRC staff also recognizes that full implementation of operational and management cyber security controls in accordance with requirements of the IPEC CSP will be achieved with full implementation of the IPEC Cyber Security Program by the date set in Milestone #8. That is, all

- 4 required elements for the operational and management cyber security controls in accordance with the IPEC CSP will be implemented in their entirety at the time of full implementation of the CSP.

The NRC staff does not regard the CSP milestone implementation dates as regulatory commitments that can be changed unilaterally by the licensee, particularly in light of the regulatory requirement at 10 CFR 73.54, that U[j]mplementation of the licensee's cyber security program must be consistent with the approved schedule." As the NRC staff explained in its letter to all operating reactor licensees dated May 9, 2011 (ADAMS Accession No. ML110980538), the implementation of the plan, including the key intermediate milestone dates and the full implementation date shall be in accordance with the implementation schedule submitted by the licensee and approved by the NRC. All subsequent changes to the NRC approved CSP implementation schedule, thus, will require prior NRC approval pursuant to 10 CFR 50.90.

3.3 Summary Based on its review of the licensee's submissions, the NRC staff concludes that the proposed changes to Milestone #6 of the licensee's CSP implementation schedule are acceptable. The NRC staff also concludes that, upon full implementation of the licensee's cyber security program, the requirements of the licensee's CSP and 10 CFR 73.54 will be met. Therefore, the NRC staff finds the proposed changes acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

This amendment relates solely to safeguards matters and does not involve any significant construction impacts. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(12). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

6.0 CONCLUSION

The NRC staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations; and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: Monika Coflin Date: November 28,2012

V. P. Operations - 2 A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.

Sincerely, IRA!

Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.50-003, 50-247, and 50-286

Enclosures:

1. Amendment No. 56 to DPR-5

2. Amendment No. 269 to DPR-26

3. Amendment No. 247 to DPR-64

4. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:

PUBLIC RidsOGCRp LPL1-1 R/F RidsRgn1 MailCenter RidsNrrDorl RidsAcrsAcnw_MaiICTR RidsNrrDorlLpl1-1 BVaidya, NRR/DORLlLPL 1-1 RidsNrrDorlDpr PPederson, NSIR/CSIRB RidsNrrPMlndianPoint MCoflin, NSIR/CSIRB RidsNrrLAKGoldstein MGray, Region 1 RidsNsirDspCsirb RidsFsmeDwmepRdb RidsNrrDirsltsb SGiebel, FSME/RDB APersinko, FSME ADAMS ACCESSION NO.: ML12258A268 OFFICE LPL 1 LA NRC/NSIR LPL 1-1/BC CSIRB/BC NAME CErlanger(*) APersinko GWilson 11/07/12 11/07112 09110/12 11/14/12 11/20/12 11/28/12 OFFICIAL RECORD COPY