ML111740077

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Issuance of Amendments Revised Cyber Security Plan
ML111740077
Person / Time
Site: Point Beach  
Issue date: 07/21/2011
From: Beltz T
Plant Licensing Branch III
To: Meyer L
Point Beach
beltz T, NRR/DORL/LPL3-1, 301-415-3049
References
TAC ME4248, TAC ME4249
Download: ML111740077 (25)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 21, 2011 Mr. Larry Meyer Site Vice President NextEra Energy Point Beach, LLC Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, WI 54241

SUBJECT:

POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: REVISED CYBER SECURITY PLAN (TAC NOS. ME4248 AND ME4249)

Dear Mr. Meyer:

The Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 243 and 247 to Renewed Facility Operating License Nos. DPR-24 and DPR-27, for the Point Beach Nuclear Plant, Units 1 and 2, respectively. The amendments consists of changes to the Renewed Facility Operating Licenses in response to your application dated July 8, 2010, as supplemented by letters dated September 28,2010, November 12,2010, November 23,2010, March 31, 2011, and June 29, 2011.

The amendments approve the Cyber Security Plan (CSP) and associated implementation schedule, and revises License Condition D of the Renewed Facility Operating Licenses for Units 1 and 2. The amendments will specify that NextEra Energy fully implement and maintain in effect all provisions of the Commission approved CSP as required by 10 CFR 73.54.

A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, r~

Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301

Enclosures:

1. Amendment No. 243 to DPR-24
2. Amendment No. 247 to DPR-27
3. Safety Evaluation cc w/encls: Distribution via ListServ

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NEXTERA ENERGY POINT BEACH, LLC DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 243 License No. DPR-24

1.

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

A.

The application for amendment by NextEra Energy Point Beach, LLC (the licensee), dated July 8,2010, as supplemented by letters dated September 28,2010, November 12, 2010, November 23,2010, March 31,2011, and June 29, 2011, 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.

- 2

2.

Accordingly, paragraph 4.0 of Renewed Facility Operating License No. DPR-24 is hereby amended to read as follows:

D. Physical Protection NextEra Energy Point Beach shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Point Beach Nuclear Plant Physical Security Plan, (Revision 4)," submitted by letter dated May 10, 2006. NextEra Energy Point Beach, LLC shall fully implement and maintain in effect all provisions of the Commission-approved Point Beach Nuclear Plant Cyber Security Plan (CSP),

including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The NextEra Energy Point Beach CSP was approved by License Amendment No. 243.

3.

This license amendment is effective as of the date of issuance. 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 March 31,2011, 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.

FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Attachment Changes to the Renewed Facility Operating License Date of issuance: July 21, 2011

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 NEXTERA ENERGY POINT BEACH, LLC DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT. UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 247 License No. DPR-27

1.

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

A.

The application for amendment by NextEra Energy Point Beach, LLC (the licensee), dated July 8,2010, as supplemented by letters dated September 28,2010, November 12, 2010, November 23,2010, March 31, 2011, and June 29, 2011, 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 Oi) 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.

- 2

2.

Accordingly, paragraph 4.D of Renewed Facility Operating License No. DPR-27 is hereby amended to read as follows:

D. Physical Protection NextEra Energy Point Beach shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Point Beach Nuclear Plant Physical Security Plan, (Revision 4)," submitted by letter dated May 10, 2006. NextEra Energy Point Beach, LLC shall fully implement and maintain in effect all provisions of the Commission-approved Point Beach Nuclear Plant Cyber Security Plan (CSP),

including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The NextEra Energy Point Beach CSP was approved by License Amendment No. 247.

3.

This license amendment is effective as of the date of issuance. 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 March 31, 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.

FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License Date of issuance: July 21, 2011

ATTACHMENT TO LICENSE AMENDMENT NO. 243 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-24 AND LICENSE AMENDMENT NO. 247 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NOS. 50-266 AND 50-301 Replace the following pages of the Renewed Facility Operating Licenses with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

REMOVE INSERT Unit 1 License Page 4 Unit 1 License Page 4 Unit 2 License Page 4 Unit 2 License Page 4

-4 D. Physical Protection l\\IextEra Energy Point Beach shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54{p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Point Beach Nuclear Plant Physical Security Plan, (Revision 4)," submitted by letter dated May 10, 2006. NextEra Energy Point Beach, LLC shall fully implement and maintain in effect all provisions of the Commission-approved Point Beach Nuclear Plant Cyber Security Plan (CSP).

including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54{p). The NextEra Energy Point Beach CSP was approved by License Amendment No. 243.

E. Safety Injection Logic The licensee is authorized to modify the safety injection actuation logic and actuation power supplies and related changes as described in licensee's application for amendment dated April 27, 1979, as supplemented May 7, 1979. In the interim period until the power supply modification has been completed, should any DC powered safety injection actuation channel be in a failed condition for greater than one hour, the unit shall thereafter be shutdown using normal procedures and placed in a block-permissive condition for safety injection actuation.

F. NextEra Energy Point Beach shall implement and maintain in effect all provisions of the approved fire protection program as described in the FSAR for the facility and as approved in the Safety Evaluation Report dated August 2,1979 (and Supplements dated October 21, 1980, January 22, 1981, and July 27, 1988) and the safety evaluation issued January 8, 1997, for Technical Specification Amendment No. 170, subject to the following provision:

NextEra Energy Point Beach may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

G. Secondarv Water Chemistrv Monitoring Program NextEra Energy Point Beach shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:

1. Identification of a sampling schedule for the critical parameters and control points for these parameters;
2. Identification of the procedures used to quantify parameters that are critical to control points;
3. Identification of process sampling points;
4. Procedure for the recording and management of data;
5. Procedures defining corrective actions for off control point chemistry condition; and Renewed License No. DPR-24 Amendment No. 243

-4 D. Physical Protection NextEra Energy Point Beach shall fully implement and maintain in effect all provisions of the Commission~approved physical security, training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Point Beach Nuclear Plant Physical Security Plan, (Revision 4)," submitted by letter dated May 10, 2006. NextEra Energy Point Beach, LLC shall fully implement and maintain in effect all provisions of the Commission-approved Point Beach Nuclear Plant Cyber Security Plan (CSP),

including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The NextEra Energy Point Beach CSP was approved by License Amendment No. 247.

E. Safety Injection Logic The licensee is authorized to modify the safety injection actuation logic and actuation power supplies and related changes as described in licensee's application for amendment dated April 27, 1979, as supplemented May 7,1979. In the interim period until the power supply modification has been completed, should any DC powered safety injection actuation channel be in a failed condition for greater than one hour, the unit shall thereafter be shut down using normal procedures and placed in a block-permissive condition for safety injection actuation.

F. NextEra Energy Point Beach shall implement and maintain in effect all provisions of the approved fire protection program as described in the FSAR for the facility and as approved in the Safety Evaluation Report dated August 2, 1979 (and Supplements dated October 21,1980, January 22,1981, and July 27,1988) and the safety evaluation issued January 8, 1997, for Technical Specifications Amendment No.

174, subject to the following provision:

NextEra Energy Point Beach may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

G. Secondary Water Chemistry Monitoring Program NextEra Energy Point Beach shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:

1. Identification of a sampling schedule for the critical parameters and control points for these parameters;
2. Identification of the procedures used to quantify parameters that are critical to control points;
3. Identification of process sampling points;
4. Procedure for the recording and management of data;
5. Procedures defining corrective actions for off control point chemistry condition; and Renewed License No. DPR-27 Amendment No. 247

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR SECURITY AND INCIDENT RESPONSE RELATED TO AMENDMENT NO. 243 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-24 AND AMENDMENT NO. 247 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-27 NEXTERA ENERGY POINT BEACH. LLC POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-266 AND 50-301

1.0 INTRODUCTION

By letter dated July 8, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML101970011), as supplemented by letters dated September 28, 2010, November 12, 2010, November 23, 2010, March 31, 2011, and June 29, 2011 (ADAMS Accession Nos. ML102720248, ML103200081, ML103280366, ML110950164 and ML111810098, respectively), NextEra Energy Point Beach submitted a license amendment request. Included in that license amendment request was a request for approval of the licensee's cyber security plan (CSP) and implementation schedule for the Point Beach Nuclear Plant (PBNP), Units 1 and 2, as required by Section 73.54, "Protection of Digital Computer and Communication Systems and Networks," of Title 10 of the Code of Federal Regulations (10 CFR). The U.S. Nuclear Regulatory Commission (NRC, the Commission) staff provided the licensee requests for additional information (RAls) regarding the staff's concerns with the CSP.

By letters dated March 31, and June 29,2011, the licensee submitted its response to these RAls. Additionally, on March 31, 2011, the licensee supplemented their CSP (ADAMS Accession No. ML110950170), to address: (1) scope of systems in response to the October 21, 2010, Commission decision (Reference 1); (2) records retention; and (3) implementation schedule. The licensee submitted a Revision 0 of the CSP incorporating all of the changes and/or additional information as referenced in the RAI responses. A portion of the letters dated July 8, and November 12,2010, and March 31,2011, contains sensitive unclassified non safeguards information (security-related) and, accordingly, those portions are withheld from public disclosure.

- 2 The amendments would approve the CSP and associated implementation schedule, and revise Paragraph 4.0 of the Renewed Facility Operating License Nos. OPR-24 and OPR-27 for the Point Beach Nuclear Plant, Units 1 and 2, respectively. The license condition would require the licensee to fully implement and maintain in effect all provisions of the NRC-approved CSP. The proposed amendment is consistent with Nuclear Energy Institute (NEI) 08-09, Revision 6, "Cyber Security Plan for Nuclear Power Reactors," (References 3 and 4).

The supplemental letters provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published in the Federal Register on April 12, 2011 (76 FR 20380).

2.0 REGULATORY EVALUATION

2.1 General Requirements Consistent with 10 CFR 73.54(a), the licensee must provide high assurance that digital computer and communication systems, and networks are adequately protected against cyber attacks, up to and including the design basis threat (OBT), as described in 10 CFR 73.1. The licensee shall protect digital computer and communication systems and networks associated with: (i) safety-related and important-to-safety functions; (ii) security functions; (iii) emergency preparedness functions, including offsite communications; and (iv) support systems and equipment which, if compromised, would adversely impact safety, security, or emergency preparedness (SSEP) functions. The rule specifies that digital computer and communication systems and networks associated with these functions must be protected from cyber attacks that would adversely impact the integrity or confidentiality of data and software; deny access to systems, services, or data; or provide an adverse impact to the operations of systems, networks, and associated equipment.

In the Staff Requirements Memorandum (SRM) COMWCO-1 0-0001, "Regulation of Cyber Security at Nuclear Power Plants," dated October 21, 2010 (Reference 1), the Commission stated that the NRC's cyber security rule at 10 CFR 73.54 should be interpreted to include structures, systems, and components (SSCs) in the balance of plant (BOP) that have a nexus to radiological health and safety. The NRC staff determined that SSCs in the BOP that have a nexus to radiological health and safety are those that could directly or indirectly affect reactivity of a nuclear power plant (NPP), and are, therefore, within the scope of important-to-safety functions described in 10 CFR 73.54(a)(1).

2.2 Elements of a CSP As stated in 10 CFR 73.54(e), the licensee must establish, implement, and maintain a CSP that satisfies the Cyber Security Program requirements of this regulation. In addition, the CSP must describe how the licensee will implement the requirements of the regulation and must account for the site-specific conditions that affect implementation. One method of complying with this regulation is to describe within the CSP how the licensee will achieve high assurance that all SSEP functions are protected from cyber attacks.

- 3 2.3 Regulatory Guide 5.71 and Nuclear Energy Institute (NED 08-09, Revision 6 NRC Regulatory Guide (RG) 5.71, "Cyber Security Programs for Nuclear Facilities" (Reference 2), describes a regulatory position that promotes a defensive strategy consisting of a defensive architecture and a set of security controls based on standards provided in the National Institute of Standards and Technology (NIST) Special Publication (SP) 800-53, "Recommended Security Controls for Federal Information Systems" and NIST SP 800-82, "Guide to Industrial Control Systems Security," dated September 29,2008. NIST SP 800-53 and NIST SP 800-82 are based on well-understood cyber threats, risks, and vulnerabilities, coupled with equally well understood countermeasures and protective techniques. RG 5.71 divides the above-noted security controls into three broad categories: technical, operational, and management.

RG 5.71 provides a framework to aid in the identification of those digital assets that licensees must protect from cyber attacks. These identified digital assets are referred to as "critical digital assets" (CDAs). Licensees should address the potential cyber security risks to CDAs by applying the defensive architecture and addressing the collection of security controls identified in RG 5.71. RG 5.71 includes a CSP template that provides one method for preparing an acceptable CSP.

The organization of RG 5.71 reflects the steps necessary to meet the requirements of 10 CFR 73.54. Section C.3 of RG 5.71 describes an acceptable method for implementing the security controls, as detailed in Appendix B, "Technical Controls," and Appendix C, "Operational and Management Controls." Section CA of RG 5.71 discusses the need to maintain the established Cyber Security Program, including comprehensive monitoring of the CDAs and the effectiveness of their security protection measures, ensuring that changes to the CDAs or the environment are controlled, coordinated, and periodically reviewed for continued protection from cyber attacks. Section C.5 of RG 5.71 provides licensees and applicants with guidance for retaining records associated with their Cyber Security Programs. Appendix A to RG 5.71 provides a template for a generic cyber security plan which licensees may use to comply with the licensing requirements of 10 CFR 73.54. Appendices Band C provide an acceptable set of security controls, which are based on well-understood threats, vulnerabilities, and attacks, coupled with equally well-understood and vetted countermeasures and protective techniques.

The NEI 08-09, Revision 6, closely maps with RG 5.71; Appendix A of NEI 08-09, Revision 6, contains a CSP template that is comparable to Appendix A of RG 5.71. Appendix D of NEI 08-09, Revision 6, contains technical cyber security controls that are comparable to Appendix B of RG 5.71. Appendix E of NEI 08-09, Revision 6, contains operational and management cyber security controls that are comparable to Appendix C of RG 5.71.

In its letter to NEI dated May 5, 2010 (Reference 5), the NRC stated that licensees may use the template in NEI 08-09, Revision 6, to prepare an acceptable CSP, with the exception of the definition of "cyber attack." The NRC staff subsequently reviewed and approved by letter dated June 7,2010 (ADAMS Accession No. ML101550052) a definition for "cyber attack" to be used in submissions based on NEI 08-09, Revision 6. The licensee submitted a CSP for PBNP that was based on the template provided in NEI 08-09, Revision 6, and included a definition of cyber

-4 attack acceptable to the NRC staff in Enclosure 1 of the CSP. Additionally, the licensee submitted a supplement to its CSP on March 31, 2011, to include information on SSCs in the BOP that, if compromised, could affect NPP reactivity.

The RG 5.71 and NEI 08-09, Revision 6, are comparable documents; both are based on essentially the same general approach and the same set of technical, operational, and management security controls. The licensee's CSP submittal was reviewed against the corresponding sections in RG 5.71.

3.0 TECHNICAL EVALUATION

The NRC staff performed a technical evaluation of the licensee's submittal. The licensee's submittal, with the exceptions of deviations described in Section 4.0, generally conformed to the guidance in NEI 08-09, Revision 6, which was found to be acceptable by the NRC staff and comparable to RG 5.71 to satisfy the requirements contained in 10 CFR 73.54. The NRC staff reviewed the licensee's submittal against the requirements of 10 CFR 73.54 following the guidance contained in RG 5.71. The NRC staff evaluation of each section of the licensee's submittal is discussed below.

3.1 Scope and Purpose The licensee's CSP establishes a means to achieve high assurance that digital computer and communication systems and networks associated with the following functions are adequately protected against cyber attacks up to and including the DBT:

1. Safety-related and important-to-safety functions;
2. Security functions;
3. Emergency preparedness functions, including offsite communications; and
4. Support systems and equipment which, if compromised, would adversely impact SSEP functions.

The licensee's submitted CSP describes achievement of high assurance of adequate protection of systems associated with the above functions from cyber attacks by:

Implementing and documenting the "baseline" security controls as described in Section 3.1.6 of NEI 08-09, Revision 6, which is comparable to Regulatory Position C.3.3 described in RG 5.71; and

  • Implementing and documenting a Cyber Security Program to maintain the established cyber security controls through a comprehensive life cycle approach as described in Section 4 of NEI 08-09, Revision 6, which is comparable to Appendix A, Section A.2.1 of RG 5.71.

Thus, the licensee's CSP, as originally submitted, is comparable to the CSP in NEI 08-09, Revision 6. However, in its submittal dated March 31, 2011, the licensee clarified its original

-5 submission and indicated that the scope of systems includes those BOP SSCs that have an impact on NPP reactivity if compromised. This is in response to and consistent with SRM COMWCO-10-0001, in which the Commission stated thatthe NRC's cyber security rule at 10 CFR 73.54 should be interpreted to include SSCs in the BOP that have a nexus to radiological health and safety. The NRC staff determined that systems that have a nexus to radiological health and safety are those that could directly or indirectly affect reactivity of a NPP, and are therefore within the scope of important-to-safety functions described in 10 CFR 73.54(a)(1 ).

On June 29, 2011, the licensee withdrew its clarification to NEI 08-09, Revision 6, regarding Emergency Preparedness functions with the scope of the CSP as provided in the July 8, 2010, license amendment request, Enclosure 1, Section 3.0. As a result, the licensee indicated that there is no deviation from NEI 08-09, Revision 6, relating to Emergency Preparedness functions.

The NRC staff reviewed the above information and found no deviation from Regulatory Position C.3.3 in RG 5.71 and Appendix A, Section A.2.1 of RG 5.71. The NRC staff concludes that the licensee established adequate measures to implement and document the Cyber Security Program, including baseline security controls.

Based on the above, the NRC staff concludes that the licensee's CSP adequately establishes the Cyber Security Program, including baseline security controls.

3.2 Analyzing Digital Computer Systems and Networks and Applying Cyber Security Controls The licensee's CSP describes that the Cyber Security Program is established, implemented, and maintained as described in Section 3.1 of NEI 08-09, Revision 6, which is comparable to Regulatory Position C.3.1 described in RG 5.71 to:

  • Analyze digital computer and communications systems and networks; and Identify those assets that must be protected ~gainst cyber attacks to satisfy 10 CFR 73.54(a).

The licensee's submitted CSP describes how the cyber security controls in Appendices D and E of NEI 08-09, Revision 6, which can be compared to Appendices Band C in RG 5.71, are addressed to protect CDAs from cyber attacks.

This section of the CSP submitted by the licensee is comparable to Regulatory Position C.3.1 in RG 5.71, without deviation.

Based on the above, the NRC staff concludes that the licensee's CSP adequately addresses security controls.

-6 3.3 Cyber Security Assessment and Authorization The licensee provided information addressing the creation of a formal, documented, cyber security assessment and authorization policy. This included a description concerning the creation of a formal, documented procedure comparable to Section 3.1.1 of NEI 08-09, Revision 6.

The NRC staff concludes that the licensee established adequate measures to define and address the purpose, scope, roles, responsibilities, management commitment, and coordination, and facilitates the implementation of the cyber security assessment and authorization policy.

The NRC staff reviewed the above information and found no deviation from Section 3.1.1 of NEI 08-09, Revision 6, which is comparable to Regulatory Position C.3.1.1 and Appendix A, Section A.3.1.1 of RG 5.71.

Based on the above, the NRC staff concludes that the licensee's CSP adequately established controls to develop, disseminate, and periodically update the cyber security assessment and authorization policy and implementing procedure.

3.4 Cyber Security Assessment Team The Cyber Security Assessment Team (CSAT) responsibilities include conducting the cyber security assessment, documenting key findings during the assessment, and evaluating assumptions and conclusions about cyber security threats. The licensee's submitted CSP outlines the requirements, roles and responsibilities of the CSAT comparable to Section 3.1.2 of NEI 08-09, Revision 6. It also describes that the CSAT has the authority to conduct an independent assessment.

The licensee's submitted CSP describes that the CSA T will consist of individuals with knowledge about information and digital systems technology; NPP operations, engineering, and plant technical specifications; and physical security and emergency preparedness systems and programs. The CSAT description in the CSP is comparable to Regulatory Position C.3.1.2 in RG 5.71.

The licensee's submitted CSP lists the roles and responsibilities for the CSA T which included performing and overseeing the cyber security assessment process; documenting key observations; evaluating information about cyber security threats and vulnerabilities; confirming information obtained during tabletop reviews, walk-downs, or electronic validation of CDAs; and identifying potential new cyber security controls.

This section of the CSP submitted by the licensee is comparable to Regulatory Position C.3.1.2 in RG 5.71, without deviation.

Based on the above, the NRC staff concludes that the licensee's CSP adequately establishes the requirements, roles and responsibilities of the CSA T.

- 7 3.5 Identification of CDAs The licensee's submitted CSP describes that the licensee will identify and document CDAs and critical systems (CSs), including a general description, the overall function, the overall consequences if a compromise were to occur, and the security functional requirements or specifications as described in Section 3.1.3 of NEI 08-09, Revision 6, which is comparable to Regulatory Position C.3.1.3 of RG 5.71.

Based on the above, the NRC staff concludes that the licensee's CSP adequately describes the process to identify CDAs.

3.6 Examination of Cyber Security Practices The licensee's submitted CSP describes how the CSAT will examine and document the existing cyber security policies, procedures, and practices; existing cyber security controls; detailed descriptions of network and communication architectures (or network/communication architecture drawings); information on security devices; and any other information that may be helpful during the cyber security assessment process as described in Section 3.1.4 of NEI 08-09, Revision 6, which is comparable to Regulatory Position C.3.1.2 of RG 5.71. The examinations will include an analysis of the effectiveness of the existing Cyber Security Program and cyber security controls. The CSA T will document the collected cyber security information and the results of their examination of the collected information.

This section of the CSP submitted by the licensee is comparable to Regulatory Position C.3.1.2 in RG 5.71, without deviation.

Based on the above, the NRC staff concludes that the licensee's CSP adequately describes the examination of cyber security practices.

3.7 Tabletop Reviews and Validation Testing The licensee's submitted CSP describes tabletop reviews and validation testing, which confirm the direct and indirect connectivity of each CDA and identify direct and indirect pathways to CDAs. The CSP states that validation testing will be performed electronically or by physical walkdowns. The licensee's plan for tabletop reviews and validation testing is comparable to Section 3.1.5 of NEI 08-09, Revision 6, which is comparable to Regulatory Position C.3.1.4 of RG 5.71.

Based on the above, the NRC staff concludes that the licensee's CSP adequately describes tabletop reviews and validation testing.

3.8 Mitigation of Vulnerabilities and Application of Cyber Security Controls The licensee's submitted CSP describes the use of information collected during the cyber security assessment process (e.g., disposition of cyber security controls, defensive models, defensive strategy measures, site and corporate network architectures) to implement security

-8 controls in accordance with Section 3.1.6 of NEI 08-09, Revision 6, which is comparable to Regulatory Position C.3.3 and Appendix A.3.1.6 to RG 5.71. The CSP describes the process that will be applied in cases where security controls cannot be implemented.

The licensee's submitted CSP notes that before the licensee can implement security controls on a CDA, it will assess the potential for adverse impact in accordance with Section 3.1.6 of NEI 08-09, Revision 6, which is comparable to Regulatory Position C.3.3 of RG 5.71.

Based on the above, the NRC staff concludes that the licensee's CSP adequately describes mitigation of vulnerabilities and application of security controls.

3.9 Incorporating the Cyber Security Program into the Physical Protection Program The licensee's submitted CSP states that the Cyber Security Program will be reviewed as a component of the Physical Security Program in accordance with the requirements of 10 CFR 73.55(m). This is comparable to Section 4.1 of NEI 08-09, Revision 6, which is comparable to Regulatory Position C.3.4 of RG 5.71.

This section of the CSP submitted by the licensee is comparable to Appendix A, Section A.3.2 in RG 5.71, without deviation.

Based on the above, the NRC staff concludes that the licensee's CSP adequately describes review of the CSP as a component of the physical security program.

3.10 Cyber Security Controls The licensee's submitted CSP describes how the technical, operational and management cyber security controls contained in Appendices D and E of NEI 08-09 Revision 6, that are comparable to Appendices Band C in RG 5.71, are evaluated and dispositioned based on site specific conditions during all phases of the Cyber Security Program. The CSP describes that many security controls have actions that are required to be performed on specific frequencies and that the frequency of a security control is satisfied if the action is performed within 1.25 times the frequency specified in the control, as applied, and as measured from the previous performance of the action as described in Section 4.2 of NEI 08-09, Revision 6.

This section of the CSP submitted by the licensee is comparable to Appendix A, Section A.3.1.6 in RG 5.71, without deviation.

Based on the above, the NRC staff concludes that the licensee's CSP adequately describes implementation of cyber security controls.

- 9 3.11 Defense-in-Depth Protective Strategies The licensee's submitted CSP describes the implementation of defensive strategies that ensure the capability to detect, respond to, and recover from a cyber attack. The CSP specifies that the defensive strategies consist of security controls, defense-in-depth measures, and the defensive architecture. The submitted CSP notes that the defensive architecture establishes the logical and physical boundaries to control the data transfer between these boundaries.

The licensee established defense-in-depth strategies by: implementing and documenting a defensive architecture as described in Section 4.3 of NEI 08-09, Revision 6, which is comparable to Regulatory Position C.3.2 in RG 5.71; a physical security program, including physical barriers; the operational and management controls described in Appendix E of NEI 08-09, Revision 6, which is comparable to Appendix C to RG 5.71; and the technical controls described in Appendix D of NEI 08-09, Revision 6, which is comparable to Appendix B to RG 5.71.

This section of the CSP submitted by the licensee is comparable to Regulatory Position C.3.2 and Appendix A, Section A.3.1.5, of RG 5.71, without deviation.

Based on the above, the NRC staff concludes that the licensee's CSP adequately describes implementation of defense-in-depth protective strategies.

3.12 Ongoing Monitoring and Assessment The licensee's submitted CSP describes how ongoing monitoring of cyber security controls to support CDAs is implemented comparable to Appendix E of NEI 08-09, Revision 6, which is comparable to Regulatory Positions CA.1 and CA.2 of RG 5.71. The ongoing monitoring program includes configuration management and change control; cyber security impact analysis of changes and changed environments; ongoing assessments of cyber security controls; effectiveness analysis (to monitor and confirm that the cyber security controls are implemented correctly, operating as intended, and achieving the desired outcome) and vulnerability scans to identify new vulnerabilities that could affect the security posture of CDAs.

This section of the CSP submitted by the licensee is comparable to Regulatory Positions CA.1 and CA.2 of RG 5.71, without deviation.

Based on the above, the NRC staff concludes that the licensee's CSP adequately describes ongoing monitoring and assessment.

3.13 Modification of Digital Assets The licensee's submitted CSP describes how cyber security controls are established, implemented, and maintained to protect CDAs. These security controls ensure that modifications to CDAs are evaluated before implementation, the cyber security performance objectives are maintained, and acquired CDAs have cyber security requirements in place to achieve the site's CSP objectives.

- 10 This section of the CSP submitted by the licensee is comparable to Section 4.5 of NEI OB-09, Revision 6, which is comparable to Appendices A.4.2.5 and A.4.2.6 of RG 5.71.

Based on the above, the NRC staff concludes that the licensee's CSP adequately describes modification of digital assets.

3.14 Attack Mitigation and Incident Response The licensee's submitted CSP describes the process to ensure that SSEP functions are not adversely impacted due to cyber attacks in accordance with Section 4.6 of NEI OB-09, Revision 6, which is comparable to Appendix C, Section C.B of RG 5.71. The CSP includes a discussion about creating incident response policy and procedures, and addresses training, testing and drills, incident handling, incident monitoring, and incident response assistance. It also describes identification, detection, response, containment, eradication, and recovery activities comparable to Section 4.6 of NEI OB-09, Revision 6.

This section of the CSP submitted by the licensee is comparable to Appendix C, Section C.B of RG 5.71, without deviation.

Based on the above, the NRC staff concludes that the licensee's CSP adequately describes attack mitigation and incident response.

3.15 Cyber Security Contingency Plan The licensee's submitted CSP describes creation of a Cyber Security Contingency Plan and policy that protects CDAs from the adverse impacts of a cyber attack described in Section 4.7 of NEI OB-09, Revision 6, which is comparable to Regulatory Position C.3.3.2.7 and Appendix C.9 of RG 5.71. The licensee describes the Cyber Security Contingency Plan that would include the response to events. The plan includes procedures for operating CDAs in a contingency, roles and responsibilities of responders, processes and procedures for backup and storage of information, logic diagrams of network connectivity, current configuration information, and personnel lists for authorized access to CDAs.

This section of the CSP submitted by the licensee is comparable to Regulatory Position C.3.3.2.7 of RG 5.71, without deviation.

Based on the above, the NRC staff concludes that the licensee's CSP adequately describes the cyber security contingency plan.

3.16 Cyber Security Training and Awareness The licensee's submitted CSP describes a program that establishes the training requirements necessary for the licensee's personnel and contractors to perform their assigned duties and responsibilities in implementing the Cyber Security Program in accordance with Section 4.B of NEI OB-09, Revision 6, which is comparable to Regulatory Position C.3.3.2.B of RG 5.71.

The CSP states that individuals will be trained with a level of cyber security knowledge commensurate with their assigned responsibilities in order to provide high assurance that

- 11 individuals are able to perform their job functions in accordance with Appendix E of NEI 08-09, Revision 6, which is comparable to Regulatory Position C.3.3.2.8 of RG 5.71 and describes three levels of training: awareness training, technical training, and specialized cyber security training.

Based on the above, the NRC staff concludes that the licensee's CSP adequately describes the cyber security training and awareness.

3.17 Evaluate and Manage Cyber Risk The licensee's submitted CSP describes how cyber risk is evaluated and managed utilizing site programs and procedures comparable to Section 4.9 of NEI 08-09, Revision 6, which is comparable to Regulatory Position C.4 and Appendix C, Section C.13 of RG 5.71. The CSP describes the Threat and Vulnerability Management Program, Risk Mitigation, Operational Experience Program; and the Corrective Action Program and how each will be used to evaluate and manage risk.

This section of the CSP submitted by the licensee is comparable to Regulatory Position C.4 and Appendix C, Section C.13 of RG 5.71, without deviation.

Based on the above, the NRC staff concludes that the licensee's CSP adequately describes evaluation and management of cyber risk.

3.18 Policies and Implementing Procedures The CSP describes development and implementation of policies and procedures to meet security control objectives in accordance with Section 4.10 of NEt 08-09, Revision 6, which is comparable to Regulatory Position C.3.5 and Appendix A, Section A.3.3 of RG 5.71. This includes the process to document, review, approve, issue, use, and revise policies and procedures.

The CSP also describes the licensee's procedures to establish specific responsibilities for positions described in Section 4.11 of NEI 08-09, Revision 6, which is comparable to Appendix C, Section C.10.10 of RG 5.71.

This section of the CSP submitted by the licensee is comparable to Regulatory Position C.3.5, Appendix A, Section A.3.3, and Appendix C, Section C.1 0.1 0 of RG 5.71, without deviation.

Based on the above, the NRC staff concludes that the licensee's CSP adequately describes cyber security pOlicies and implementing procedures.

3.19 Roles and Responsibilities The licensee's submitted CSP describes the roles and responsibilities for the qualified and experienced personnel, including the Cyber Security Program Sponsor, the Cyber Security Program Manager, Cyber Security Specialists, the Cyber Security Incident Response Team (CSIRT), and other positions as needed. The CSIRT initiates in accordance with the Incident Response Plan and initiates emergency action when required to safeguard CDAs from cyber

- 12 security compromise and to assist with the eventual recovery of compromised systems.

Implementing procedures establish roles and responsibilities for each of the cyber security roles in accordance with Section 4.11 of NEI 08-09, Revision 6, which is comparable to Regulatory Position C.3.1.2, Appendix A, Section A3.1.2, and Appendix C, Section C.10.10 of RG 5.71.

Based on the above, the NRC staff concludes that the licensee's CSP adequately describes cyber security roles and responsibilities.

3.20 Cyber Security Program Review The licensee's submitted CSP describes how the CSP establishes the necessary procedures to implement reviews of applicable program elements in accordance with Section 4.12 of NEI 08-09, Revision 6, which is comparable to Regulatory Position C.4.3 and Appendix A, Section A4.3 of RG 5.71.

Based on the above, the NRC staff finds that the CSP adequately describes Cyber Security Program review.

3.21 Document Control and Records Retention and Handling The licensee's submitted CSP describes that the licensee has established the necessary measures and governing procedures to ensure that sufficient records of items and activities affecting cyber security are developed, reviewed, approved, issued, used, and revised to reflect completed work. The CSP describes that superseded portions of certain records will be retained for at least 3 years after the record is superseded, while audit records will be retained for no less than 12 months in accordance with Section 4.13 of NEI 08-09, Revision 6. However, this guidance provided by industry to licensees did not fully comply with the requirements of 10 CFR 73.54.

In a letter dated February 28, 2011 (ADAMS Accession No. Ml11 0600204), NEI sent to the NRC proposed language for licensees' use to respond to the generic records retention RAI, to which the NRC had no technical objection (

Reference:

letter from NRC dated March 1, 2011, ADAMS Accession No. Ml11 0490337). The proposed language clarified the requirement by providing examples (without providing an all-inclusive list) of the records and supporting technical documentation that are needed to satisfy the requirements of 10 CFR 73.54. All records will be retained until the Commission terminates the license, and the licensee shall maintain superseded portions of these records for at least 3 years after the record is superseded, unless otherwise specified by the Commission. By retaining accurate and complete records and technical documentation until the license is terminated, inspectors, auditors, or assessors will have the ability to evaluate incidents, events, and other activities that are related to any of the cyber security elements described, referenced, and contained within the licensee's NRC-approved CSP. It will also allow the licensee to maintain the ability to detect and respond to cyber attacks in a timely manner, in the case of an event. In its letter dated March 31, 2011, the licensee responded to the records retention RAI using the language proposed by NEI in its letter dated February 28,2011.

This section of the CSP submitted by the licensee is comparable to Regulatory Position C.5 and Appendix A, Section A5, of RG 5.71, without deviation.

-13 Based on the above, the NRC staff concludes that the language the licensee proposes to adopt provides for adequate records retention and will support the licensee's ability to detect and response to cyber attacks. The NRC staff further concludes that this section is comparable to Regulatory Position C.5 and Appendix A, Section A5, of RG 5.71, without deviation.

Accordingly, the NRC staff concludes that the licensee's CSP adequately describes cyber security document control and records retention and handling.

3.22 Implementation Schedule The licensee's submitted CSP provides a proposed implementation schedule for the CSP. In a letter dated February 28,2011 (ADAMS Accession No. ML110600206), NEI sent to the NRC a template for licensees to use to submit their CSP implementation schedules, to which the NRC had no technical objection (

Reference:

Letter from NRC dated March 1, 2011, ADAMS Accession No. ML110070348). These key milestones include:

Establish the CSAT; Identify CSs and CDAs; Install a deterministic one-way device between lower level devices and higher level devices; Jmplement the security control "Access Control For Portable And Mobile Devices";

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

  • Commence ongoing monitoring and assessment activities for target set CDAs whose security controls have been implemented.

In its letter dated March 31, 2011, the licensee provided a revised implementation schedule using the NEI template. The NRC staff considers this March 31, 2011, supplement the approved schedule as required by 10 CFR 73.54.

The NRC staff acknowledges that, in its submittal dated March 31,2011, the licensee proposed several CSP milestone implementation dates as regulatory commitments. 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 "[i]mplementation of the licensee's cyber security program must be consistent with the approved schedule." As the NRC staff explained it its letter to all operating reactor licensees dated Mary 9,2011 (ADAMS Accession No. ML110980538), the implementation of the plan, including key intermediate milestone dates and the full implementation date, shall be in accordance with the implementation schedule submitted by the

- 14 licensee and approved by the NRC. All subsequent changes to the NRC-approved CSP implementation schedule this will require prior NRC approval pursuant to 10 CFR 50.90.

Based on the provided schedule ensuring timely implementation of those protective measures that provide a higher degree of protection against radiological sabotage, the NRC staff finds the Cyber Security Program implementation satisfactory.

3.23 Revision to License Condition 4.0 By letter dated March 31, 2011, NextEra Energy Point Beach proposed the following change to the license condition addressing Physical Protection (i.e., Paragraph 4.0) of the Renewed Facility Operating License for both Unit 1 and Unit 2:

NextEra Energy Point Beach, LLC shall fully implement and maintain in effect all provisions of the Commission-approved Point Beach Nuclear Plant Cyber Security Plan submitted by letters dated July 8, 2010, supplemented by letter dated September 28,2010, November 12,2010, November 23,2010, and March 31, 2011, and withheld from public disclosure in accordance with 10 CFR 2.390.

On June 16. 2011. the NRC staff discussed with the licensee a modification to the language in the proposed license condition. The change would maintain consistent language for all licensees and provide a similar language to the license condition currently in-place for physical security. The licensee concurred with the appropriateness and intent of the revised license condition language.

The following license condition will be added to Paragraph 4.0 of Renewed Facility Operating License No. OPR-24 for PBNP. Unit 1:

NextEra Energy Point Beach, LLC shall fully implement and maintain in effect all provisions of the Commission-approved Point Beach Nuclear Plant Cyber Security Plan (CSP). including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The NextEra Energy Point Beach CSP was approved by License Amendment No. 243.

The following license condition will be added to Paragraph 4.0 of Renewed Facility Operating License No. OPR-27 for PBNP, Unit 2:

NextEra Energy Point Beach, LLC shall fully implement and maintain in effect all provisions of the Commission-approved Point Beach Nuclear Plant Cyber Security Plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The NextEra Energy Point Beach CSP was approved by License Amendment No. 247.

Based on the information in Section 3.0 of this safety evaluation and the modified license condition described above, the NRC concludes this is acceptable.

- 15 4.0 DIFFERENCES FROM NEI 08-09, REVISION 6 The NRC staff notes the following additional differences between the licensee's submittal and NEI 08-09, Revision 6:

In Section 3.1, "Scope and Purpose," the licensee clarified the definition of important-to-safety functions, consistent with SRM COMWCO-10-0001. The license amendment request letter included a clarification from NEI 08-09, Revision 6, which narrowed the scope of emergency preparedness systems within the scope of the Rule; after discussions with NRC staff, the licensee retracted this clarification.

In Section 3.21, "Document Control and Records Retention and Handling," the licensee clarified the definition of records and supporting documentation that will be retained to conform to the requirements of 10 CFR 73.54.

In Section 3.22, "Implementation Schedule," the licensee submitted a revised implementation schedule, specifying the interim milestones and the final implementation date, including supporting rationale.

The NRC staff concludes that all of these deviations are acceptable as discussed in the respective sections of the safety evaluation.

5.0

SUMMARY

The NRC staff's review and evaluation of the licensee's CSP was conducted using the staff positions established in the relevant sections of RG 5.71. Based on the NRC staff's review, the NRC finds that the licensee addressed the relevant information necessary to satisfy the requirements of 10 CFR 73.54, 10 CFR 73.55(a)(1), 10 CFR 73.55(b)(8), and 10 CFR 73.55(m),

as applicable and that the licensee's Cyber Security Program provides reasonable assurance that digital computer and communication systems and networks associated with the following are adequately protected against cyber attacks, up to and including the DBT as described in 10 CFR 73.1. This includes protecting digital computer and communication systems and networks associated with: (i) safety-related and important-to-safety functions; (ii) security functions; (iii) emergency preparedness functions, including offsite communications; and (iv) support systems and equipment which, if compromised, would adversely impact SSEP functions.

Therefore, the NRC staff concludes that the information contained in the licensee's CSP is acceptable and, upon successful implementation of this program, operation of the Point Beach Nuclear Plant will not be inimical to the common defense and security.

6.0 STATE CONSULTATION

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

- 16

7.0 ENVIRONMENTAL CONSIDERATION

The amendment changes requirements with respect to the use of facility components located within the restricted area as defined in 10 CFR Part 20, and changes a surveillance requirement. The NRC staff has determined that the amendment involves no significant increase in the amounts and no significant change in the types of any effluent that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously published a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding (76 FR 20380). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b),

no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

8.0 CONCLUSION

The Commission 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) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

9.0 REFERENCES

1.

Vietti-Cook, A. L., memorandum to R W. Borchardt, U.S. Nuclear Regulatory Commission, "Staff Requirements - COMWCO-10-000 - Regulation of Cyber Security at Nuclear Power Plants," dated October 21,2010 (ADAMS Accession No. ML102940009).

2.

U.S. Nuclear Regulatory Commission, Regulatory Guide 5.71, "Cyber Security Programs for Nuclear Facilities," dated January 2010 (ADAMS Accession No. ML090340159).

3.

Roe, J., Nuclear Energy Institute, letter to Scott Morris. U.S. Nuclear Regulatory Commission, "NEI 08-09, Revision 6, 'Cyber Security Plan for Nuclear Power Reactors; April 2010,'" dated April 28, 2010 (ADAMS Accession No. ML101180434).

4.

NEI 08-09 [Rev. 6], "Cyber Security Plan for Nuclear Reactors." April 2010 (ADAMS Accession No. ML101180437).

5.

Correia, R, U.S. Nuclear Regulatory Commission. letter to Jack Roe. Nuclear Energy Institute, "Nuclear Energy Institute 08-09, 'Cyber Security Plan Template; Revision 6,'"

dated May 5.2010 (ADAMS Accession No. ML101190371).

Principal Contributor: Roberta Spitzberg. NSIR Date of issuance: July 21, 2011

Mr. Larry Meyer July 21, 2011 Site Vice President NextEra Energy Point Beach, LLC Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, WI 54241

SUBJECT:

POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: REVISED CYBER SECURITY PLAN (TAC NOS. ME4248 AND ME4249)

Dear Mr. Meyer:

The Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 243 and 247 to Renewed Facility Operating License Nos. DPR-24 and DPR-27, for the Point Beach Nuclear Plant, Units 1 and 2, respectively. The amendments consists of changes to the Renewed Facility Operating Licenses in response to your application dated July 8, 2010, as supplemented by letters dated September 28, 2010, November 12,2010, November 23,2010, March 31, 2011, and June 29, 2011.

The amendments approve the Cyber Security Plan (CSP) and associated implementation schedule, and revises License Condition D of the Renewed Facility Operating Licenses for Units 1 and 2. The amendments will specify that NextEra Energy fully implement and maintain in effect all provisions of the Commission approved CSP as required by 10 CFR 73.54.

A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, lRAI Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301

Enclosures:

1. Amendment No. 243 to DPR-24
2. Amendment No. 247 to DPR-27
3. Safety Evaluation DISTRIBUTION:

PUBLIC RidsOgcRp Resource CErlanger, NSIR LPL3-1 rtf RidsNrrDorlLpl3-1 Resource PPederson, NSIR RidsNrrPMPointBeach Resource RidsRgn3MailCenter Resource RSpitzberg. NSIR RidsNrrLABTully Resource RidsAcrsAcnw_MailCTR Resource TWengert, NRR RidsNrrDirsltsb Resource RidsNrrDorlDpr Resource BSingal, NRR Accession Number: ML111740077

  • Safety evaluation transmitted by memo of July 6, 2011 I

I OFFICE NRRIDORUPM NRRlDORULA NSIRIDSP/ISCPB/BC OGC (NLO w/comments NRRlDORUBC NAME TBeltz BTuily CErlanger

  • BMizuno RPascarelli DATE 06/30/11 06/30/11 07/06/11 07/18/11 04/21/11 OFFICIAL RECORDS COPY
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