ML12339A067

Issuance of License Amendments Regarding Cyber Security

ML12339A067
Person / Time
Site:	Harris, Brunswick, Crystal River, Robinson
Issue date:	12/18/2012
From:	Billoch-Colon A Plant Licensing Branch II
To:	Annacone M, Franke J, William Gideon, Hamrick G Carolina Power & Light Co
Billoch, Araceli
References
TAC ME9545, TAC ME9546, TAC ME9547, TAC ME9548, TAC ME9549
Download: ML12339A067 (34)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 December 18, 2012 Mr. Michael J. Annacone, Vice President Mr. Jon A. Franke, Vice President Brunswick Steam Electric Plant Crystal River Nuclear Plant (NA2C)

Carolina Power & Light Company ATTN: Supervisor, Licensing &

Post Office Box 10429 Regulatory Programs Southport, North Carolina 28461 15760 West Power Line Street Crystal River, Florida 34428-6708 Mr. William R. Gideon, Vice President Mr. George Hamrick, Vice President H. B. Robinson Steam Electric Plant, Shearon Harris Nuclear Power Plant Unit No.2 Carolina Power & Light Company Carolina Power & Light Company Post Office Box 165, Mail Zone 1 3581 West Entrance Road New Hill, North Carolina 27562-0165 Hartsville, South Carolina 29550-0790

SUBJECT:

BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2, H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO.2, SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1, AND CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT -5SUANCE OF LICENSE AMENDMENTS REGARDING CYBER SECURITY PLAN IMPLEMENTATION SCHEDULE MILESTONES (TAC NOS. ME9545, ME9546, ME9549, ME9548, AND ME9547)

Gentlemen:

By letter dated September 12,2012, Carolina Power & Light Company (CP&L) and Florida Power Corporation (FPC) (the licensees) submitted a request to amend Renewed Facility Operating License Nos. DPR-71, DPR-62, DPR-23, and NPF 63; and Facility Operating License No. DPR-72 for Brunswick Steam Electric Plant, Units 1 and 2, H.B. Robinson Steam Electric Plant, Unit No.2, Shearon Harris Nuclear Power Plant, Unit 1, and Crystal River Unit 3 Nuclear Generating Plant, respectively.

The licensees' submittal for the proposed amendments revises the scope of Cyber Security Plan (CSP) Implementation Schedule Milestone #6 and the existing license condition 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 related to target set equipment. CP&L and FPC are 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 the Nuclear Energy Institute (NEI) 08-09, Revision 6 "Cyber Security Plan for Nuclear Power Reactors;' dated April 2010, 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 licensees' CSP implementation schedules.

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

M. Annacone, et al.

- 2 A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice. If you have any questions, please contact me at 301 415-3302.

Sincerely, Araceli T. Billoch Colon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-325, 50-324, 50-302, 50-261, and 50-400

Enclosures:

1. Amendment No. 261 to DPR-71

2. Amendment No. 289 to DPR-62

3. Amendment No. 242 to DPR-72

4. Amendment No. 230 to DPR-23

5. Amendment No. 140 to NPF-63

6. Safety Evaluation cc: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 261 Renewed License No. DPR-71

1.

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

A.

The application for amendment filed by Carolina Power & Light Company (the licensee), dated September 12, 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; 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, the license is amended as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-71 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 261, are hereby incorporated in the license. Carolina Power &

Light Company shall operate the facility in accordance with the Technical Specifications.

3.

In addition, Paragraph 2.D of Renewed Facility Operating License No. DPR-71 is revised to add the following language:

The licensee 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 licensee's CSP was approved by License Amendment No. 258, as supplemented by a change approved by License Amendment No. 261.

4.

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

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to Renewed License No. DPR-71 Date of Issuance: December 18,2012

ATTACHMENT TO LICENSE AMENDMENT NO. 261 RENEWED FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Replace the following pages of Renewed Operating License DPR-71 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages 4

4 4a 4a

- 4 (2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 261, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.

For Surveillance Requirements (SRs) that are new in Amendment 203 to Renewed Facility Operating License DPR-71, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 203. For SRs that existed prior to Amendment 203, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 203.

(a)

Effective June 30, 1982, the surveillance requirements listed below need not be completed until July 15,1982. Upon accomplishment of the surveillances, the provisions of Technical Specification 4.0.2 shall apply.

Specification 4.3.3.1, Table 4.3.3-1, Items 5.a and 5.b (b)

Effective July 1, 1982, through July 8, 1982, Action statement "a" of Technical Specification 3.8.1.1 shall read as follows:

ACTION:

a. With either one offsite circuit or one diesel generator of the above required AC. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining AA sources by performing Surveillance Requirements 4.8.1.1.1.a and 4.8.1.1.2.aA within two hours and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter; restore at least two offsite circuits and four diesel generators to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(3)

Deleted by Amendment No. 206.

D.

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, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Physical Security Plan, Revision 2," and "Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006, and "Guard Training and Qualification Plan, Revision 0,"

submitted by letter dated September 30, 2004.

Renewed License No. DPR-71 Amendment No. 261

- 4a The licensee 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 licensee's CSP was approved by License Amendment No. 258, as supplemented by a change approved by License Amendment No. 261.

Renewed License No. DPR-71 Amendment No. 261

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 289 Renewed License No. DPR-62

1.

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

A.

The application for amendment filed by Carolina Power & Ught Company (the licensee), dated September 12, 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; 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, the license is amended as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-62 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 289, are hereby incorporated in the license. The Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.

3.

In addition, Paragraph 2.C.(6) of Facility Operating License No. DPR-62 is revised to add the following language:

The licensee 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 licensee's CSP was approved by License Amendment No. 286, as supplemented by a change approved by License Amendment No. 289.

4.

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

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to Renewed License No. DPR-62 Date of Issuance: December 18, 2012

ATTACHMENT TO LICENSE AMENDMENT NO. 289 RENEWED FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Replace the following pages of Renewed Operating License DPR-62 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages 3

3 5

5

- 3 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; (4)

Pursuant to the Act and 10 CFR Parts 30,40 and 70, to receive, possess and use in amounts as required any byproduct, source, and special nuclear materials without restriction to chemical of physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5)

Pursuant to the Act and 10 CFR Parts 30 and 70 to posses, but not separate, such byproduct and special nuclear materials as may be produced by the operation of Brunswick Steam Electric Plant, Unit Nos. 1 and 2, and H. B. Robinson Steam Electric Plant, Unit No.2; (6)

Carolina Power & Light Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Report dated November 22, 1977, as supplemented April 1979, June 11, 1980, December 30, 1986, December 6, 1989, July 28, 1993, and February 10, 1994 respectively, subject to the following provision:

The licensee 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.

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; 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 The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2923 megawatts (thermal).

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 289, are hereby incorporated in the license.

Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.

Renewed License No. DPR-62 Amendment No. 289

-5 diesel generators to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(3)

Deleted by Amendment No. 236.

(4)

Equalizer Valve Restriction The valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation, except for one bypass valve which is left open to prevent pressure build-up due to ambient and conduction heating of the water between the equalizer valves.

(5)

Deleted by Amendment No. 233.

(6)

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, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Physical Security Plan, Revision 2," and "Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006, and "Guard Training and Qualification Plan, Revision 0," submitted by letter dated September 30, 2004.

The licensee 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 licensee's CSP was approved by License Amendment No. 286, as supplemented by a change approved by License Amendment No. 289.

D.

This license is subject to the following additional conditions for the protection of the environment:

a.

Deleted per Amendment 79,3-11-83

b.

Deleted per Amendment 79,3-11-83

c.

Deleted per Amendment 79,3-11-83

d.

The licensee shall comply with the etnuent limitations contained in National Pollutant Discharge Elimination System Permit No. NC0007064 issued pursuant to Section 402 of the Federal Water Pollution Control Act, as amended.

E.

This license is effective as of the date of issuance and shall expire at midnight on December 27,2034.

Renewed License No. DPR-62 Amendment No. 289

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO.2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 230 Renewed License No. DPR-23

1.

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

A The application for amendment by Carolina Power & Light Company (the licensee), dated September 12, 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 (ij) 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, the license is amended as indicated in the attachment to this license amendment, and paragraph 3.B. of Renewed Facility Operating License No. DPR-23 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 230 are hereby incorporated in the license.

3.

In addition, Paragraph 3.F of Renewed Facility Operating License No. DPR-23 is revised to add the following language:

The licensee 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 licensee's CSP was approved by License Amendment No. 226, as supplemented by a change approved by license Amendment No. 230.

4.

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

FOR THE NUCLEAR REGULATORY COMMISSION leF.Q~

lant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed License No. DPR-23 Date of Issuance: December 18, 2012

ATTACHMENT TO LICENSE AMENDMENT NO. 230 RENEWED FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Replace the following pages of the Renewed Facility Operating License No. DPR-23 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages 3

3 4

4

- 3 neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; D.

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 and equipment calibration or associated with radioactive apparatus or components; E.

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 operation of the facility.

3.

This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR 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:

A.

Maximum Power Level The licensee is authorized to operate the facility at a steady state reactor core power level not in excess of 2339 megawatts thermal.

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 230 are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

(1)

For Surveillance Requirements (SRs) that are new in Amendment 176 to Final Operating License DPR-23, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 176. For SRs that existed prior to Amendment 176, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 176.

Renewed License No. DPR-23 Amendment No. 230

- 4 C.

Reports Carolina Power & Light Company shall make certain reports in accordance with the requirements of the Technical Specifications.

D.

Records Carolina Power & Light Company shall keep facility operating records in accordance with the requirements of the Technical Specifications.

E.

Fire Protection Program Carolina Power & Company shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Fire Protection Safety Evaluation Report dated February 28, 1978, and supplements thereto. Carolina Power & Light Company 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.

F.

Physical Protection and Cyber Security 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 the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "H. B. Robinson Steam Electric Plant Security, Training and Qualification, and Safeguards Contingency Plan, Revision 0" submitted by letter dated October 1, 2004, as supplemented by letter dated October 20, 2004.

The licensee 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 licensee's CSP was approved by License Amendment No. 226, as supplemented by a change approved by License Amendment No. 230.

G.

The following programs shall be implemented and maintained by the licensee:

(1) DELETED Renewed License No. DPR-23 Amendment No. 230

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CAROLINA POWER & LIGHT COMPANY, et al.

DOCKET NO. 50-400 SHEARON HARRIS NUCLEAR POWER PLANT. UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 140 Renewed License No. NPF-63

1.

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

A.

The application for amendment by Carolina Power & Light Company (the licensee), dated September 12, 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; 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, the license is amended as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-63 is hereby amended to read as follows:

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 140, are hereby incorporated into this license, Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

In addition, Paragraph 2,E of Renewed Facility Operating License No, NPF-63 is revised to add the following language:

The licensee 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 licensee's CSP was approved by License Amendment No. 136, as supplemented by a change approved by License Amendment No. 140.

4.

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

FOR THE NUCLEAR REGULATORY COMMISSION I

. Quic ocho, Chief ant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed License No. NPF-63 Date of Issuance: December 18, 2012

ATTACHMENT TO LICENSE AMENDMENT NO.140 FACILITY OPERATING LICENSE NO. NPF-63 DOCKET NO. 50-400 Replace the following pages of Renewed Facility Operating License No. NPF-63 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages 4

4 8

8

- 4 C.

This 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 a" 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 Carolina Power & Light Company is authorized to operate the facility at reactor core power levels not in excess of 2948 megawatts thermal (100 percent rated core power) in accordance with the conditions specified herein.

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 140, are hereby incorporated into this license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

Antitrust Conditions Carolina Power & Light Company shall comply with the antitrust conditions delineated in Appendix C to this license.

(4)

Initial Startup Test Program (Section 14)1 Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.

(5)

Steam Generator Tube Rupture (Section 15.6.3)

Prior to startup following the first refueling outage, Carolina Power & Light Company shall submit for NRC review and receive approval if a steam generator tube rupture analysis, including the assumed operator actions, which demonstrates that the consequences of the design basis steam generator tube rupture event for the Shearon Harris Nuclear Power Plant are less than the acceptance criteria specified in the Standard Review Plan, NUREG-0800, at 15.6.3 Subparts 11(1) and (2) for calculated doses from radiological releases. In preparing their analysis Carolina Power &

Light Company will not assume that operators will complete corrective actions within the first thirty minutes after a steam generator tube rupture.

1The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.

Renewed License No. NPF-63 Amendment No. 140

-8 Physical and Cyber Security 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.SS (S1 FR 27817 and 27822) and the authority of 10 CFR SO.90 and 10 CFR SO.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:

"Guard Training and Qualification Plan" submitted by letter dated October 19,2004, "Physical Security Plan" and "Safeguards Contingency Plan" submitted by letter dated October 19, 2004 as supplemented by letter dated May 16, 2006.

The licensee 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 SO.90 and 10 CFR SO.S4(p). The licensee's CSP was approved by License Amendment No. 136, as supplemented by a change approved by License Amendment No. 140.

F.

Fire Protection Program Carolina Power & Light Company shall implement and maintain in effect all provIsions of the approved fire protection program that comply with 10 CFR S0.48(a) and 10 CFR S0.48(c), as specified in the revised license amendment request dated October 9,2009, supplemented by letters dated February 4, 2010, and April S, 2010, and approved in the associated safety evaluation dated June 28, 2010. Except where NRC approval for changes or deviations is required by 10 CFR S0.48(c) and NFPA 80S, and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR S0.48(a) and 10 CFR S0.48(c), the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.

(1)

Risk-Informed Changes that May Be Made Without Prior NRC Approval A risk assessment of the change must demonstrate that the acceptance criteria below are met. The risk assessment approach, methods, and data shall be acceptable to the NRC and shall be appropriate for the nature and scope of the change being evaluated; be based on the as-built, as-operated and maintained plant; and reflect the operating experience at the plant. Acceptable methods to assess the risk of the proposed change may include methods that have been used in the peer-reviewed Fire PRA model, methods that have been approved by the NRC via a plant-specific license amendment or through NRC approval of generic methods specifically for use in NFPA 80S risk assessments, or methods that have been demonstrated to bound the risk impact.

Renewed License No. NPF-63 Amendment No. 140

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEMINOLE ELECTRIC COOPERATIVE, INC.

DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 242 License No. DPR-72

1.

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

A.

The application for amendment by Florida Power Corporation, et al. (the licensees),

dated September 12, 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; 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

-2 The issuance of this amendment is in accordance with 10 CFR Part S1 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-72 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 242, are hereby incorporated in the license. Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.

3.

In addition, Paragraph 2.D of Facility Operating License No. DPR-72 is revised to add the following language:

The licensee 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 SO.90 and 10 CFR SO.S4(p).

The licensee's CSP was approved by License Amendment No. 238. as supplemented by a change approved by License Amendment No. 242.

4.

This license amendment is effective as of the date of its issuance and shall be implemented by December 31.2012.

FOR THE NUCLEAR REGULATORY COMMISSION Sl.~~

lant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to License No. DPR-72 Date of Issuance: December 18, 2012

ATTACHMENT TO LICENSE AMENDMENT NO. 242 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 Replace the following pages of Facility Operating License DPR-72 with the attached revised pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Pages Insert Pages 4

4 5d 5d

- 4 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:

2.C.(1) Maximum Power Level Florida Power Corporation is authorized to operate the facility at a steady state reactor core power level not in excess of 2609 Megawatts (100 percent of rated core power level).

2.C.(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 242, are hereby incorporated in the license. Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.

The Surveillance Requirements contained in the Appendix A Technical Specifications and listed below are not required to be performed immediately upon implementation of Amendment 149. The Surveillance Requirements shall be successfully demonstrated prior to the time and condition specified below for each.

a) SR 3.3.8.2.b shall be successfully demonstrated prior to entering MODE 4 on the first plant start-up following Refuel Outage 9.

b) SR 3.3.11.2, Function 2, shall be successfully demonstrated no later than 31 days following the implementation date of the ITS.

c) SR 3.3.17.1, Functions 1, 2, 6,10,14, & 17 shall be successfully demonstrated no later than 31 days following the implementation date of the ITS.

d) SR 3.3.17.2, Function 10 shall be successfully demonstrated prior to entering MODE 3 on the first plant start-up following Refuel Outage 9.

e) SR 3.6.1.2 shall be successfully demonstrated prior to entering MODE 2 on the first plant start-up following Refuel Outage 9.

f)

SR 3.7.12.2 shall be successfully demonstrated prior to entering MODE 2 on the first plant start-up following Refuel Outage 9.

g) SR 3.8.1.10 shall be successfully demonstrated prior to entering MODE 2 on the first plant start-up following Refuel Outage 9.

h) SR 3.8.3.3 shall be successfully demonstrated prior to entering MODE 4 on the first plant start-up following Refuel Outage 9.

Facility Operating License No. DPR-72 Amendment No. 242

- 5d 2.0 Physical and Cyber Security 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 2781.7 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Physical Security Plan, Revision 5," and "Safeguards Contingency Plan, Revision 4," submitted by letter dated May 16, 2006, and "Guard Training and Qualification Plan, Revision 0," submitted by letter dated September 30, 2004, as supplemented by letters dated October 20, 2004, and September 29, 2005.

The licensee 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 licensee's CSP was approved by License Amendment No. 238, as supplemented by a change approved by License Amendment No. 242.

Facility Operating License No. DPR-72 Amendment No. 242

\\.~p.1\\ REGU, _

UNITED STATES

~"

....,~

~

0."

NUCLEAR REGULATORY COMMISSION P

~

WASHINGTON, D.C. 20555*0001 0

~

~

~

'C/.

~

1-"

...0

• • • • i< SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE FOLLOWING:

AMENDMENT NOS. 261 AND 289 RENEWED FACILITY OPERATING LICENSE NOS. DPR-71 AND DPR-62 BRUNSWICK STEAM ELECTRIC PLANT, UNITS. 1 AND 2 DOCKET NOS. 50-325, AND 50-324 AMENDMENT NO. 230 RENEWED FACILITY OPERATING LICENSE NO. DPR-23 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO.2 DOCKET NO. 50-261 AMENDMENT NO. 140 RENEWED FACILITY OPERATING LICENSE NO. NPF-63 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 AMENDMENT NO. 242 FACILITY OPERATING LICENSE NO. DPR-72 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302

1.0 INTRODUCTION

By application dated September 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12268A055), Carolina Power & Light Company (CP&L) and Florida Power Corporation (FPC) (the licensees) submitted a request to amend Renewed Facility Operating License Nos. DPR-71, DPR-62, DPR-23, and NPF 63; and Facility Operating License No. DPR-72 for Brunswick Steam Electric Plant (Brunswick) Units 1 and 2, H.B. Robinson Steam Electric Plant, Unit No.2 (HBRSEP), Shearon Harris Nuclear Power Plant, Unit 1 (Harris), and Crystal River Unit 3 Nuclear Generating Plant (Crystal River),

respectively. The proposed changes would revise the scope of Cyber Security Plan (CSP)

- 2 Implementation Schedule Milestone #6 and the existing license condition 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. CP&L and FPC are 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 the Nuclear Energy Institute (NEI) 08-09, Revision 6 "Cyber Security Plan for Nuclear Power Reactors," dated April 2010, 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 September 12, 2012, contain sensitive unclassified non-safeguards information and, accordingly, those portions are withheld from public disclosure.

2.0 REGULATORY EVALUATION

The U.S. Nuclear Regulatory Commission (NRC) staff reviewed and approved the licensees' existing CSP implementation schedule by License Amendment Nos. 258, 286, 238, 136, and 226 dated July 29,2011 (ADAMS Accession No. ML11193A028), concurrent with the incorporation of the CSP into the facilities 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:

• Title 10 of the Code ofFederal Regulations (10 CFR), Part 73, Section 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 licensees' facility operating licenses includes a license condition that requires the licensees to fully implement and maintain in effect all provisions of the Commission-approved CSP.

• Amendment Nos. 258, 286, 238, 136, and 226 dated July 29, 2011, which approved the licensees' CSP and implementation schedule, included the following statement: "The implementation of the CSP, including the key intermediate milestone dates and the full implementation date, shall be in accordance with the implementation schedule submitted by the licensee on April 7, 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 the 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

3.0 TECHNICAL EVALUATION

Amendment Nos. 258, 286, 136, and 226 to Renewed Facility Operating License Nos. DPR-71, DPR-62, DPR-23 and NPF-63; and Amendment No. 238 to Facility Operating License No. DPR-72 for Brunswick, Unit Nos. 1 and 2, HBRSEP, Harris, and Crystal River, respectively, were issued on July 29, 2011. The NRC staff also approved the licensees' CSP implementation schedule, as discussed in the safety evaluation issued with the amendments. The implementation schedule had been submitted by the licensees based on a template prepared by NEI (ADAMS Accession No. ML110600218), which the NRC staff found acceptable for licensees to use to develop their CSP implementation schedules. The licensees' proposed implementation schedule for the Cyber Security Program identified completion dates and bases for the following eight milestones:

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

2) Identify Critical Systems and CDAs;

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

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

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

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

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

8) Fully implement the CSP.

3.1 Licensee's Proposed Change Currently, Milestone #6 of Brunswick, Unit Nos. 1 and 2, HBRSEP, Harris, and Crystal River CSP requires CP&L and FPC 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 their September 12,2012, application, CP&L and FPC 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. CP&L and FPC propose to amend their 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 licensees 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 licensees further stated that many of their existing programs are primarily procedure-based programs and must be implemented in coordination with the comprehensive Cyber Security Program. The licensees also stated that the existing programs currently in place at Brunswick, Unit Nos. 1 and 2, HBRSEP, Harris, and Crystal River (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.

-4 3.2 NRC Staff Evaluation The intent of the cyber security implementation schedule was for licensees to demonstrate ongoing implementation of their Cyber Security Program prior to full implementation, which is set for the date specified in Milestone #8. In addition to Milestone #6 and its associated activities, licensees will be completing six other milestones (Milestones #1 through #5 and Milestone #7) by December 31,2012. Activities include establishing a CSAT, identifying critical systems and CDAs, installing deterministic one-way devices between defensive levels, implementing access control for portable and mobile devices, implementing methods to observe and identify obvious cyber related tampering, and conducting ongoing monitoring and assessment activities for target set CDAs. In the aggregate, the interim milestones demonstrate ongoing implementation of the Cyber Security Program at Brunswick, Unit Nos. 1 and 2, HBRSEP, Harris, and Crystal River.

The NRC staff has reviewed the licensees' evaluation of the proposed change in their submittal dated September 12,2012, and finds that by completing Milestones #1 through #5, Milestone

1. 6 with implementation of technical controls to target set CDAs, and Milestone #7, Brunswick, Unit Nos. 1 and 2, HBRSEP, Harris, and Crystal River by December 31,2012, will have an acceptable level of cyber security protection until full program implementation is achieved.

Technical cyber security controls include access controls, audit and accountability, CDA and communications protection, identification and authentication, and system hardening. These controls are executed by computer systems, as opposed to people, and consist of hardware and software controls that provide automated protection to a system or application. Implementation of technical cyber security controls promotes standardization, trust, interoperability, connectivity, automation, and increased efficiency. For these reasons, the NRC staff concludes that the licensees' approach is acceptable.

The NRC staff also recognizes that full implementation of operational and management cyber security controls in accordance with requirements of the CP&L and FPC CSP will be achieved with full implementation of the CP&L and FPC 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 CP&L and FPC 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 "[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.

-S 3.3 Revision to License Conditions By letter dated September 12, 2012, the licensees proposed to modify Paragraphs 2.0, 2.C.(6),

3.F, 2.E, 2.0 of Renewed Facility Operating License Nos. DPR-71, DPR-62, DPR-23 and NPF-63 for Brunswick, Unit Nos. 1 and 2, HBRSEP, Harris, respectively and Facility Operating License No. DPR-72 for Crystal River, which provides a license condition to require the licensees to fully implement and maintain in effect all provisions of the NRC-approved CSP.

The license condition in Paragraph 2.0 of Renewed Operating License No. DPR-71 for Brunswick, Unit No.1 is modified as follows:

"The licensee 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 SO.90 and 10 CFR SO.S4(p). The licensee's CSP was approved by License Amendment No. 2S8, as supplemented by a change approved by License Amendment No. 261."

The license condition in Paragraph 2.C.(6) of Renewed Operating License No. DPR-62 for Brunswick, Unit No.2 is modified as follows:

"The licensee 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 SO.90 and 10 CFR SO.S4(p). The licensee's CSP was approved by License Amendment No. 286, as supplemented by a change approved by License Amendment No. 289."

The license condition in Paragraph 3.F of Renewed Operating License No. DPR-23 for HBRSEP, is modified as follows:

'The licensee 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 SO.90 and 10 CFR SO.S4(p). The licensee's CSP was approved by License Amendment No. 226, as supplemented by a change approved by license Amendment No. 230."

The license condition in Paragraph 2.E of Renewed Operating License No. NPF-63 for Harris is modified as follows:

"The licensee 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 SO.90 and 10 CFR SO.S4(p). The licensee's CSP was approved by License Amendment No. 136, as supplemented by a change approved by License Amendment No. 140."

- 6 The license condition in Paragraph 2.0 of Operating License No. DPR-72 for Crystal River is modified as follows:

"The licensee 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 licensee's CSP was approved by License Amendment No. 238, as supplemented by a change approved by License Amendment No. 242."

3.4 Summary Based on its review of the licensees' submissions, the NRC staff concludes that the proposed changes to Milestone #6 of the licensees' 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 licensees' CSP and 10 CFR 73.54 will be met. Therefore, the NRC staff finds the proposed changes acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the North Carolina official was notified of the proposed issuance of the amendments for Brunswick Units 1 and 2 and Harris, and the South Carolina officials were notified of the proposed amendment for HBRSEP. The North Carolina and South Carolina State official had no comments.

Based upon a letter dated May 2, 2003, from Michael N. Stephens of the Florida Department of Health, Bureau of Radiation Control, to Brenda L. Mozafari, Senior Project Manager, U.S. NRC, the State of Florida does not desire notification of issuance of license amendments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments relate solely to safeguards matters and do not involve any significant construction impacts. Accordingly, these amendments meet 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 the amendments.

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 18, 2012

ML12339A067 Sincerely, IRA!

Araceli T. Billoch Colon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrLABClayton T. Wengert, NRR RidsRg n2MailCenter C. Erlanger, NSIR LPL2-2 RtF RidsOgcRp P. Pederson, NSIR RidsNsirDsp M. Cotlin, NRR

• By memo NSIRtDSP/CSIRB/BC' LPL2-2/PM LPL2-2/PM LPL2-2/LA II OFFICE BClayton CErlanger*

ABiliochCol6n ABiliochCol6n tor FSaba

!NAME i~

1216/12 12/6/12 11/19/12 112/6/12 LPL2-2/PM LPL2-2/BC OGC NLO ABiliochCol6n BMizuno JQuichocho 12/18/12 12/18/12 12/6/12

.!DATE