ML12335A221

and Salem Nuclear Generating Station, Units 1 and 2 - Issuance of Amendments Approval of Change to Implementation Milestone 6 of Cyber Security Plan

ML12335A221
Person / Time
Site:	Salem, Hope Creek
Issue date:	12/10/2012
From:	John Hughey Plant Licensing Branch 1
To:	Joyce T Public Service Enterprise Group
Hughey J
References
TAC ME9153, TAC ME9154, TAC ME9155
Download: ML12335A221 (23)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 December 10, 2012 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236, N09 Hancocks Bridge, NJ 08038

SUBJECT:

HOPE CREEK GENERATING STATION AND SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 -ISSUANCE OF AMENDMENTS RE: APPROVAL OF CHANGE TO IMPLEMENTATION MILESTONE 6 OF CYBER SECURITY PLAN (TAC NOS. ME9153, ME9154 AND ME9155)

Dear Mr. Joyce:

The Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 192 to Renewed Facility Operating License (FOL) No. NPF-57 for the Hope Creek Generating Station (HCGS) and Amendment Nos. 302 and 285 to Renewed FOL Nos. DPR-70 and DPR-75 for the Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2, in response to your application dated July 26, 2012.

The amendments approve a change to the scope of an implementation Milestone 6 of the Cyber Security Plan (CSP) to apply to only technical cyber security controls. The amendments revise the existing license condition regarding physical protection in each of the three FOLs that require the licensee to fully implement and maintain in effect ali provisions of the NRC-approved CSP. The amendment requests were submitted pursuant to Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), "Application for amendment of license, construction permit, or early site permit."

T. Joyce -2 A copy of our safety evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

~D John D. Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-354,50-272, and 50-311

Enclosures:

1. Amendment No. 192 to Renewed License No. NPF-57

2. Amendment No. 302 to Renewed License No. DPR-70

3. Amendment No. 285 to Renewed License No. DPR-75

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

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 PSEG NUCLEAR, LLC DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 192 Renewed License No. NPF-57

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

A. The application for amendment filed by PSEG Nuclear LLC dated July 26, 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; S. 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 set forth in 10 CFR Chapter I; 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. Accordingly, paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-57 is hereby amended as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 192, and the Environmental Protection Plan contained in Appendix S, are hereby incorporated into the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

-2 In addition, the second paragraph of 2.E of Renewed Facility Operating License No.

NPF-57 is hereby amended, as follows:

PSEG Nuclear LLC shall fully implement and maintain in effect all provisions of the Commission-approved Cyber Security Plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Salem Hope Creek CSP was approved by License Amendment No. 189 as supplemented by a change approved by License Amendment No. 192.

3. This license amendment is effective as of the date of its issuance and shall be implemented by December 31,2012. The implementation of the Cyber Security Plan (CSP), including the key intermediate milestone dates and the full implementation date, shall be in accordance with the implementation schedule, as submitted by the licensee by letter dated June 6, 2011, as revised by letter dated July 26, 2012, and as 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 Meena Khanna, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License Date of Issuance: December 10, 2012

ATTACHMENT TO LICENSE AMENDMENT NO. 192 RENEWED FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 Replace the following pages of the Renewed Facility Operating License with the revised page.

The revised pages are identified by amendment number and contain a marginal line indicating the areas of change.

Remove Insert Page 3 Page 3 Page 16 Page 16

-3 reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any 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; and (6) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. Mechanical disassembly of the GE14i isotope test assemblies containing Cobalt-60 is not considered separation.

(7) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Part 30, to intentionally produce, possess, receive, transfer, and use Cobalt-60.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I 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 PSEG Nuclear LLC is authorized to operate the facility at reactor core power levels not in excess of 3840 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 192, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Renewed license No. NPF-57 Amendment No. 192

-16 exempting Type C testing for instrument lines and lines containing excess flow check valves (Section 6.2.6 of SS:::R 5): and an exemption from Appendix J, exempting Type C testing of thermal reHef valves (Section 6.2.6 of SS::::R 5).

These exemptions are authorized by iaw, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. These exemptions are hereby granted. The special circumstances regarding each exemption are identified in the referenced section of the safety evaluation report and the supplements thereto. These exemptions are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate, to tne extent authorized herem, in conformity with the appiication, as amended, the provisions of the Act, and tne rules and regUlations of the Commission.

E. The licensee 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 plans, submitted by letter dated May 19, 2006 are entitled: "Saiem-Hope Creek Nuclear Generating Station Security Training and Qualification Plan,n and "Salem-Hope Creek NUClear Generating Station Security Contingency Pian: The plans contain Safeguards Information protected under 10 CFR 73.21.

PS:::G Nuclear LLC small fully implement and maintain in effect all provisions of the Commission-approved Cyoer Security Plan (CSP), including changes made pursuant to tns autnority of 10 CFR 50.90 and 10 CFR 50.54(p). The Safem Hope Creek CSP was approved by License Amendment No. 189 as supplemented by a change approved by Ucense Amendment No.192.

F. DELETED G. The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of tne Atomic :::nergy Act of 1954, as amended, to cover public liability ciaims.

Renewed License No. NPF-57 Amendment No 192

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 PSEG NUCLEAR, LLC EXELON GENERATION COMPANY, LLC DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO.1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 302 Renewed License No. DPR-70

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

A. The application for amendment filed by PSEG Nuclear, LLC, acting on behalf of itself and Exelon Generation Company, LLC (the licensees), dated July 26,2012, com plies 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 Title 10 of the Code of Federal Regulations (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 set forth in 10 CFR Chapter I; 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 2.C.(2) of Renewed Facility Operating License No. DPR-70 is hereby amended, as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 302, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications, and the Environmental Protection Plan.

In addition, the second paragraph of 2.E of Renewed Facility Operating License No.

DPR-70 is hereby amended as follows:

PSEG Nuclear LLC shall fully implement and maintain in effect all provisions of the Commission-approved Cyber Security Plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Salem Hope Creek CSP was approved by License Amendment No. 300 as supplemented by a change approved by License Amendment No. 302.

3. This license amendment is effective as of the date of its issuance and shall be implemented by December 31,2012. The implementation of the Cyber Security Plan (CSP), including the key intermediate milestone dates and the full implementation date, shall be in accordance with the implementation schedule, as submitted by the licensee by letter dated June 6, 2011, as revised by letter dated July 26, 2012, and as 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 Meena Khanna, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License Date of Issuance: December 10, 2012

AITACHMENT TO LICENSE AMENDMENT NO. 302 RENEWED FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Replace the following pages of Renewed Facility Operating License No. DPR-70 with the attached revised pages as indicated. The revised pages are identified by amendment number and contain a marginal line indicating the areas of change.

Remove Insert Page 3 Page 3 Page 9 Page 9

-3 instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any 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; and (6) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed 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 PSEG Nuclear LLC is authorized to operate the facility at a steady state reactor core power level not in excess of 3459 megawatts (one hundred percent of rated core power).

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 302, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications, and the Environmental Protection Plan.

(3) Deleted Per Amendment 22, 11-20-79 (4) Less than Four Loop Operation PSEG Nuclear LLC shall not operate the reactor at power levels above P-7 (as defined in Table 3.3-1 of Specification 3.3.1.1 of Appendix A to this renewed license) with less than four (4) reactor coolant loops in operation until safety analyses for less than four loop operation have been submitted by the licensees and approval for less than four loop operation at power levels above P-7 has been granted by the Commission by Amendment of this renewed license.

(5) PSEG Nuclear LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Renewed License No. DPR-70 Amendment No. 302

-9 evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

(19) Appendix A of NUREG-21 01, "Safety Evaluation Report Related to the License Renewal of Salem Nuclear Generating Station," dated June 2011, and PSEG Nuclear LLC UFSAR supplement submitted pursuant to 10 CFR 54.21 (d), as revised on May 18, 2011, describe certain future programs and activities to be completed before the period of extended operation. PSEG Nuclear LLC shall complete these activities no later than August 13,2016, and shall notify the NRC in writing when implementation of these activities is complete.

(20) All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of American Society for Testing and Materials (ASTM) E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the !\IRC prior to implementation.

All capsules placed in storage must be maintained for future insertion. Any changes to storage requirements must be approved by the NRC. Changes to the withdrawal schedule or storage requirements shari be submitted to the NRC as a report in accordance with 10 CFR 5004.

(21) PSEG Nuclear LLC shall take one core sample in the Unit 1 spent fuel pool west wall, by the end of 2013, and one core sample in the east wall where there have been indications of borated water ingress through the concrete, by the end of 2015. The core samples1east and west walls) will expose the rebar. which will be examined for signs of corrosion. Any sample showing signs of concrete degradation and/or rebar corrosion will be entered into the licensee's corrective action program for further evaluation. PSEG Nuclear LLC shall submit a report in accordance with 10 CFR 50.4 no later than three months after each sample is taken on the results, recommendations, and any additional planned actions.

D. Paragraph 2.0. has been combined with paragraph 2.c. per Amendment No. 86, June 27, 19B8.

E. The licensee 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 plans. submitted by letter dated May 19,2006, are entitled: "Salem-Hope Creek Nuclear Generating Station Security Plan," "Salem-Hope Creek Nuclear Generating Station Security Training and Qualification Plan.~ and "Salem-Hope Creek Nuclear Generating Station Security Contingency Plan." The plans contain Safeguards Information protected under 10 CFR 73.21.

PSEG Nuclear LLC shall fully implement and maintain in effect all provisions of the Commission-approved Cyber Security Plan (CSPi, including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Salem-Hope Creek CSP was approved by License Amendment No. 300 as supplemented by a change approved by License Amendment No.3{)2.

Renewed License No. DPR-70 Amendment No. 302

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 PSEG NUCLEAR, LLC EXELON GENERATION COMPANY, LLC DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO.2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 285 Renewed License No. DPR-75

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

A. The application for amendment filed by PSEG Nuclear, LLC, acting on behalf of itself and Exelon Generation Company, LLC (the licensees), dated July 26,2012, 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 Title 10 of the Code of Federal Regulations (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 set forth in 10 CFR Chapter I; 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 2.C.(2) of Renewed Facility Operating License No. DPR-75 is hereby amended, as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 285, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications, and the Environmental Protection Plan.

In addition, the second paragraph of 2.E of Renewed Facility Operating License No.

DPR-75 is hereby amended as follows:

PSEG Nuclear LLC shall fully implement and maintain in effect all provisions of the Commission-approved Cyber Security Plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54{p). The Salem Hope Creek CSP was approved by License Amendment No. 283 as supplemented by a change approved by License Amendment No. 285.

3. This license amendment is effective as of the date of its issuance and shall be implemented by December 31, 2012. The implementation of the Cyber Security Plan (CSP), including the key intermediate milestone dates and the full implementation date, shall be in accordance with the implementation schedule, as submitted by the licensee by letter dated June 6, 2011, as revised by letter dated July 26, 2012, and as 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

~~

Meena Khanna, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License Date of Issuance: December 10, 2012

ATTACHMENT TO LICENSE AMENDMENT NO. 285 RENEWED FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Replace the following pages of Renewed Facility Operating License No. DPR-75 with the attached revised pages as indicated. The revised pages are identified by amendment number and contain a marginal line indicating the areas of change.

Remove Insert Page 3 Page 3 Page 11 Page 11

-3 (4) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive. possess and use at any time any byproduct, source or special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration and as fission detectors in amounts as required; (5) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any 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; and (6) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70. to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I 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 PSEG Nuclear LLC is authorized to operate the facility at steady state reactor core power levels not in excess of 3459 megawatts (thermal).

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 285, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Renewed License No. DPR-75 Amendment No. 285

- 11 issuance of the License for Fuel-Loading and Low-Power Testing, dated April 18, 1980.

The facility will operate, to the extent authorized herein, in conformity with the application as amended, the provisions of the Act, and the regulations of the Commission.

E. The licensee 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 plans, submitted by letter dated May 19, 2006, are entitled: "Salem-Hope CreeK Nuclear Generating Station Security Plan," "Salem-Hope Creek Nuclear Generating Station Security Training and QualifIcation Pian: and "Salem-Hope Creek Nuclear Generating Station Security Contingency Plan: The plans Contain Safeguards Information protected under 10 CFR 73.21.

PSEG Nuclear LLC shall fully implement and maintain in effect all provisions of the Commission-approved Cyber Security Plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Salem-Hope Creek CSP was approved by License Amendment No. 283 as supplemented by a change approved by License Amendment No. 285.

F. A temporary exemption from General Design Criterion 57 found in Appendix A to 10 CFR Part 50 is described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report, Supplement, No.5, Section 6.2.3.1. This Exemption is authorized by law and will not endanger life-ur property or the common defense and security and is otherwise in the public interest. The exemption, therefore, is hereby granted and shall remain in effect through the first refueling outage as discussed in Section 6.2.3.1 of Supplement 5 to the Safety .Evaluation Report. The granting of the exemption is authorized with the issuance of the Facility Operating License, dated May 20, 1981. The facility will operate, to the extent authorized herein, in conformity with the application as amended, the provisions of the Act, and the regulations of the Commission.

G. This renewed license is subject to the following additional condition for the protection of the environment:

Before engaging in additional construction or operational activities which may result in an environmental impact that was not evaluated by the Commission, PSEG Nuclear LLC shall prepare and record an environmental evaluation of such activity. When the evaluation indicates that such activity may result in a significant adverse environmental impact that was not evaluated, or that is significantly greater than that evaluated in the Final Environmental Statement or any addendum thereto, PSEG Nuclear LLC shall provide a written evaluation of such activities and obtain prior approval from the Director of Nuclear Reactor Regulation.

H. If PSEG Nuclear LLC plans to remove or to make significant changes in the normal operation of equipment that controls the amount of radioactivity in effluents from the Salem Nuclear Generation Station, the NRC shall be notified in writing regardless of whether the change affects the amount of radioactivity in effluents.

I. DELETED Renewed License No. DPR-75 Amendment No. 285

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 192,302 AND 285 TO RENEWED FACILITY OPERATING LICENSE NOS. NPF-57, DPR-70, AND DPR-75 PSEG NUCLEAR, LLC HOPE CREEK GENERATING STATION AND SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-354, 50-272, AND 50-311

1.0 INTRODUCTION

By application dated July 26, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12209A394), PSEG Nuclear, LLC (PSEG, the licensee) requested changes to the renewed facility operating licenses for the Salem Nuclear Generating Station, Units 1 and 2 and the renewed facility operating license for the Hope Creek Generating Station.

The proposed changes would revise the scope of Cyber Security Plan (CSP) Implementation Schedule Milestone 6 and the existing license conditions in the facility operating licenses.

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. PSEG is requesting to modify the scope of Milestone 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, "Cyber Security Plan for Nuclear Power Reactors," would be implemented concurrent with the full implementation of the Cyber Security Program (Milestone 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 July 26, 2012, contain sensitive unclassified non-safeguards information and, accordingly, those portions are withheld from public disclosure.

2.0 REGULATORY EVALUATION

The NRC staff reviewed and approved the licensee's existing CSP implementation schedule by License Amendment Nos. 300, 283, and 189, dated July 28, 2011 (ADAMS Accession No. ML111861560), 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:

Enclosure

-2

• 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 license includes a license condition that requires the licensee to fully implement and maintain, in effect, all provisions of the Commission approved CSP.

• Amendment Nos. 300, 283, and 189, dated July 28,2011, 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 by letter dated June 6, 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. 300 and 283 to Renewed Facility Operating License Nos. DPR-70 and DPR-75 for the Salem Nuclear Generating Station, Units 1 and 2, respectively, and Amendment No. 189 to Renewed Facility Operating License No. NPF-57 for the Hope Creek Generating Station were issued on July 28, 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 (CSs) and Critical Digital Assets (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;

8) Fully implement the CSP.

3.1 Licensee's Proposed Change Currently, Milestone 6 of Salem-Hope Creek's CSP requires PSEG 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 July 26, 2012, application, PSEG 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 D technical security controls. PSEG 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 Salem-Hope Creek (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 Cyber Security Assessment Team, 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 Salem-Hope Creek.

The NRC staff has reviewed the licensee's evaluation of the proposed change in its submittal dated July 26,2012, and finds that by completing Milestones 1 through 5, Milestone 6 with implementation of technical controls to target set CDAs, and Milestone 7, Salem-Hope Creek 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

- 4 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 Salem-Hope Creek CSP, will be achieved with full implementation of the Salem-Hope Creek Cyber Security Program by the date set in Milestone 8. That is, all required elements for the operational and management cyber security controls in accordance, with the Salem-Hope Creek 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 n[i]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 Revision to License Condition 2.E By letter dated July 26,2012, the licensee proposed to modify Paragraph 2.E of Facility Operating License Nos. DPR-70, DPR-75, and NPF-57, for Salem Nuclear Generating Station, Units 1 and 2, respectively, and Hope Creek Generating Station, which provides a license condition to require the licensee to fully implement and maintain in effect all provisions of the NRC-approved CSP.

The second paragraph of license condition 2.E of Renewed Facility Operating License No.

DPR-70 is modified as follows:

PSEG Nuclear LLC shall fully implement and maintain in effect all provisions of the Commission-approved Cyber Security Plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Salem Hope Creek CSP was approved by License Amendment No. 300 as supplemented by a change approved by License Amendment No. 302.

The second paragraph of license condition 2.E of Renewed Facility Operating License No.

DPR-75 is modified as follows:

PSEG Nuclear LLC shall fully implement and maintain in effect all provisions of the Commission-approved Cyber Security Plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p}. The Salem-Hope Creek CSP was approved by License Amendment No. 283 as supplemented by a change approved by License Amendment No. 285.

-5 The second paragraph of license condition 2.E of Renewed Facility Operating License No.

NPF-57 is modified as follows:

PSEG Nuclear LLC shall fully implement and maintain in effect all provisions of the Commission-approved Cyber Security Plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Salem-Hope Creek CSP was approved by License Amendment No. 189 as supplemented by a change approved by License Amendment No. 192.

3.4 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 that the proposed changes are acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the New Jersey State Official was notified of the proposed issuance of the amendments. 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: Monika Coflin Date: December 10,2012

T. Joyce - 2 A copy of our safety evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, IRA!

John D. Hughey, Project Manager Plant licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-354, 50-272, and 50-311

Enclosures:

1. Amendment No. 192 to Renewed License No. NPF-57

2. Amendment No. 302 to Renewed License No. DPR-70

3. Amendment No. 285 to Renewed License No. DPR-75

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

PUBLIC LPL 1-2 R/F RidsOgcRp Resource RidsNrrDorlLpl1-2 Resource RidsAcrsAcnw_MaiICTR Resource GHiII,OIS RidsNrrLAABaxter Resource RidsNrrDirsltsb Resource RidsNrrPMSalem Resource RidsRgn 1MailCenter Resource RidsNrrDorlDpr Resource MCoflin, NSIR ADAMS Accession No: ML12335A221 *via SE dated 9/6/2012 OFFICE LPL 1-2/PM LPL 1-2/LA NSIR/DSP/ISCPB/BC" OGC (NLO) LPL 1-2/BC NAME JHughey ABaxter CErlanger* BMizuno MKhanna DATE 12/05/2012 12/05/2012 09/06/2012 12/05/2012 12/10/2012 OFFICIAL RECORD COpy