ML15008A455

Correction to Amendment Numbers of License Amendments Regarding Revision to Cyber Security Plan Implementation Schedule Completion Date

ML15008A455
Person / Time
Site:	Brunswick
Issue date:	01/09/2015
From:	Andrew Hon Plant Licensing Branch II
To:	William Gideon Duke Energy Progress
Hon A
References
TAC MF3263, TAC MF3264
Download: ML15008A455 (19)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 9, 2015 Mr. William R. Gideon, Vice President Brunswick Steam Electric Plant Duke Energy Progress, Inc.

P.O. Box 10429 Southport, NC 28461

SUBJECT:

BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2- CORRECTION TO AMENDMENT NUMBERS OF LICENSE AMENDMENTS REGARDING REVISION TO CYBER SECURITY PLAN IMPLEMENTATION SCHEDULE COMPLETION DATE (TAC NOS. MF3263 AND MF3264)

Dear Mr. Gideon:

On December 19, 2014, The Nuclear Regulatory Commission issued Amendments to Renewed Facility Operating License Nos. DPR-71 and DPR-62 for Brunswick Steam Electric Plant (BSEP), Units 1 and 2. The amendments were in response to your application dated December 19, 2013, as supplemented by letter dated March 31, 2014. These amendments revised the Cyber Security Plan (CSP) Implementation Milestone 8 completion date and the Physical Protection license condition regarding full implementation of the CSP in the facility operating licenses for BSEP, Units 1 and 2; After issuance, it came to our attention that the amendment numbers, 266 and 294, were incorrect for BSEP, Units 1 and 2, respectively. The enclosed pages have been corrected to show amendment numbers 265 and 293. The corrections are indicated by margin bars on the affected pages. Please replace the incorrect pages with the correct pages.

W. Gideon Thank you for bringing this matter to our attention. We regret any inconvenience this may have caused. If you have any questions, please call me at (301) 415-8480.

Sincerely, Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-324 and 50-325

Enclosures:

Corrected pages for Amendment No. 265 to DPR-71 Corrected pages for Amendment No. 293 to DPR-62 Corrected pages for Safety Evaluation cc w/enclosures: Distribution via Listserv

ENCLOSURES Corrected pages for Amendment No. 265 to DPR-71 Corrected pages for Amendment No. 293 to DPR-62 Corrected pages for Safety Evaluation

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 19, 2014 Mr. George T. Hamrick Mr. Benjamin C. Waldrep Vice President Site Vice President Brunswick Steam Electric Plant Shearon Harris Nuclear Power Plant Duke Energy Progress, Inc. Duke Energy P.O. Box 10429 5413 Shearon Harris Rd.

Southport, NC 28461 New Hill, NC 27562-0165 Mr. Terry D. Hobbs Mr. Richard M. Glover General Manager, Decommissioning Vice President Crystal River Nuclear Plant (NA2C) Duke Energy Progress, Inc.

15760 W. Power Line St. H. B. Robinson Steam Electric Plant, Unit No. 2 Crystal River, FL 34428-6708 3581 W. Entrance Rd.

Hartsville, SC 29550

SUBJECT:

BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2; CRYSTAL RIVER, UNIT 3 NUCLEAR GENERATING PLANT; SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1; AND H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 - ISSUANCE OF LICENSE AMENDMENTS REGARDING REVISION TO CYBER SECURITY PLAN IMPLEMENTATION SCHEDULE COMPLETION DATE (TAC NOS. MF3263, MF3264, MF3265, MF3266, AND MF3267)

Gentlemen:

The Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 265 to Renewed Facility Operating License No. DPR-71; Amendment No.293 to Facility Operating License No. DPR-62 for Brunswick Steam Electric Plant (BSEP), Units 1 and 2; Amendment No. 239 to Renewed Facility Operating License No. DPR-23 for H. B. Robinson Steam Electric Plant (HBRSEP}, Unit No. 2; Amendment No. 144 to Renewed Facility Operating License No. NPF-63 for Shearon Harris Nuclear Power Plant (SHNPP), Unit 1; and Amendment No. 245 to Facility Operating License No. DPR-72 for Crystal River (CR), Unit 3 Nuclear Generating Plant. The amendments are in response to your application dated December 19, 2013, as supplemented by letter dated March 31, 2014.

These amendments revise the Cyber Security Plan (CSP) Implementation Milestone 8 completion date and the Physical Protection license condition regarding full implementation of the CSP in the facility operating licenses for BSEP, Units 1 and 2; HBRSEP, Unit No.2; SHNPP, Unit 1: and CR, Unit 3 Nuclear Generating Plant.

The NRC staff has completed its review of the information provided by the licensee and is enclosing its Safety Evaluation (SE). The NRC staff has determined that its documented SE does not contain sensitive security-related information pursuant to Title 10 of the Code of Federal Regulations (CFR), Section 2.390, "Public inspections, exemptions, requests for withholding." However, the NRC will delay placing the enclosed SE in the public document room for a period of 10 working days from the date of this letter, to provide Duke Energy with the opportunity to comment on any sensitive aspects. If you believe that any information in the SE contains sensitive information, please identify such information line-by-line and define the basis pursuant to the criteria of 10 CFR 2.390. After 10 working days, the enclosed SE will be made publicly available.

Sincerely, Andrew Hon, Project Manager Plant licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-325, 5Q-324, 50-302, 50-261, and 50-400

Enclosures:

1. Amendment No. 265 .to DPR-71

2. Amendment No. 2_93 to DPR-62

3. Amendment No. 239 to DPR-23

4. Amendment No. 144 to NPF-63

5. Amendment No. 245 to NPF-72

6. Safety Evaluation cc w/enclosures: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY PROGRESS. INC.

DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PlANT. UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 265 Renewed License No. DPR-71

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

A. The application for amendment filed by Duke Energy (the licensee), dated December 19, 2013, as supplemented by letter dated March 31, 2014, 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.

Enclosure 1

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. 265 , are hereby incorporated in the license. Duke Energy Progress, Inc. 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 changes approved by License Amendment Nos. 261 and 265.

4. This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of the date of issuance. The implementation of the CSP, including the key intermediate milestone dates and the full implementation date, shall be in accordance with the implementation schedule submitted by the licensee on December 19, 2013, as supplemented by letter dated March 31, 2014, and approved by the NRC staff with this license amendment. All subsequent changes to the NRC-approved CSP implementation schedule will require prior NRC approval pursuant to 10 CFR 50.90.

FOR Tt;lENUCLEAR REGULATORY COMMISSION

I

~

Lisa M. Regner, Acting Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed License No. DPR-71 Date of Issuance: December 19, 2014

ATTACHMENT TO LICENSE AMENDMENT NO. 265 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 fines indicating the areas of change.

Remove Pages Insert Pages 4 4 5 5.

(2) Technical Specifications The Technical Specifications contained In Appendix A, as revised through Amendment No. 265, are hereby Incorporated In the license. Duke Energy Progress, Inc. 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 S.a and S.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 A. C. electrical power sources Inoperable, demonstrate the OPERABILITY of the remaining A.C.

sources by performing Surveillance Requirements 4.8.1.1.1.a and 4.8.1.1.2.a.4 within two hours and* at least once per 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> thereafter; restore at feast two offsite circuits and four diesel generators to OPERABLE status within 7 days or be in at feast HOT SHUTDOWN within the next 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> and in COLD SHUTDOWN within the following 24 hours1 days <br />0.143 weeks <br />0.0329 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 Renewed License No. DPR-71 Amendment No. 265

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. 258, as supplemented by changes approved by License Amendment Nos. 261 and 265.

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

a. Deleted per Amendment 54, 3-11-83

b. Deleted per Amendment 54, 3-11-83

c. The licensee shall comply with the effluent 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.

F. In accordance with the requirement imposed by the October 8, 1976, order of the United States Court of Appeals for the District of Columbia Circuit in Natural Resources Defense Council v. Nuclear Regulatory Commission, No. 74-1385 and 7 4-1586, that the Nuclear Regulatory Commission "shall make any licenses granted between July 21, 1976 and such time when the mandate is issued subject to the outcome of the proceedings herein," the license issued herein shall be subject to the outcome of such proceedings.

G. Deleted by Amendment No. 206.

H. This license is effective as of the date of issuance and shall expire at midnight on September 8, 2036.

I. Deleted per Amendment No. 70 dated 5-25-84.

J. Deleted per Amendment No. 70 dated 5-25-84.

K. Deleted by Amendment No. 206.

L. Pgwer Uprate License Amendment Implementation

.The licensee shall complete the following actions as a condition of the approval of the power uprate license amendment (Amendment No. 183):

( 1) Deleted by Amendment No. 206.

(2) Deleted by Amendment No. 206.

Renewed License No. DPR-71 Amendment No. 265

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555..0001 DUKE ENERGY PROGRESS. INC.

DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT. UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 293 Renewed license No. DPR-62

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

A The application for amendment by Duke Energy (the licensee), dated December 19,2013, as supplemented by letter dated March 31,2014, 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 (1 0 CFR) Chapter I;

8. 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.

Enclosure 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. 293 , are hereby incorporated in the license. Duke Energy Progress, Inc. 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 changes approved by License Amendment Nos. 289 and 293.

4. This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of the date issuance. The implementation of the CSP, including the key intermediate milestone dates and the full implementation date, shall be in accordance with the implementation schedule submitted by the licensee on December 19, 2013, as supplemented by letter dated March 31, 2014, 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.

~~:EAR REGUlATORY COMMISSION Lisa M. Regner, Acting Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed License No. DPR-62 Date of Issuance: December 19, 2014

A ITACHMENT TO LICENSE AMENDMENT NO. 293 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 6 a*

'Page 6 of the license OPR-62 is being replaced due to additional wording on page 5, which caused the last line of page 5 to move to the first line of page 6.

. 3.

(3) 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:

(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 April1979, 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 1: 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. 293 , are hereby incorporated in the license. Duke Energy Progress, Inc. shall operate the facility In accordance with the Technical Specifications.

Renewed License No. DPR-62 Amendment No. 293

next 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> and in COLD SHUTDOWN within the following 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />.

(3) Deleted by Amendment No. 236.

(4) Equalizer Valye Restriction The valves in the equalizer piping between the recirculation loops shall be closed at all times ouring 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 changes approved by License Amendment Nos. 289 and 293.

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 effluent 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.

F. Deleted per Amendment No. 98 dated 5-25-84.

Renewed License No. DPR-62 Amendment No. 293

G. Deleted per Amendment No. 98 dated 5-25-84.

H. Deleted by Amendment No. 236.

I. Power Uprate License Amendment Implementation The licensee shall complete the following actions as a condition of the approval of the power uprate license amendment (Amendment No. 214):

(1) Deleted by Amendment No. 236.

(2) Deleted by Amendment No. 236.

(3) Fuel Pool Decay Heat Evaluation The decay heat loads and the decay heat removal systems available for each refueling outage shall be evaluated, and bounding or outage specific analyses shall be used for various refueling sequences. Where a bounding engineering evaluation is in place, a refueling specific assessment shall be made to ensure that the bounding case encompasses the specific refueling sequence. In both cases (i.e.,

bounding or outage specific evaluations), compliance with design basis assumptions shall be verified.

(4) Deleted by Amendment No. 236.

(5) Deleted by Amendment No. 236.

J. The UFSAR supplement, as revised, submitted pursuant to 10 CFR 54.21 (d),

shall be included in the next scheduled update to the UFSAR required by 10 CFR 50.71 (e)(4) following the issuance of this renewed operating license. Until that update is complete, CP&L* may make changes to the programs and activities described in the supplement without prior Commission approval, provided that CP&L* evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

K. The UFSAR supplement, as revised, describes certain future activities to be completed prior to the period of extended operation. Duke Energy Progress, Inc.

shall complete these activities no later than December 27, 2014, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

• On Apri129, 2013, the name "Carolina Power & Light Company" (CP&L) was changed to "Duke Energy Progress, Inc."

Renewed License No. DPR-62 Amendment No."293j

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",...,.. .... "SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE FOLLOWING:

AMENDMENT NOS. 265 AND 293 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. 239 RENEWED FACILITY OPERATING LICENSE NO. DPR-23 H. B. ROBINSON STEAM ELECTRIC PLANT. UNIT NO. 2 DOCKET NO. 50-261 AMENDMENT NO. 144 RENEWED FACILITY OPERATING LICENSE NO. NPF-63 SHEARON HARRIS NUCLEAR POWER PLANT. UNIT 1 DOCKET NO. 50-400 AMENDMENT NO. 245 FACILITY OPERATING LICENSE NO. DPR-72 CRYSTAL RIVER. UNIT 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302

1.0 INTRODUCTION

By application dated December 19, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13357A189), as supplemented by letter dated March 31, 2014 (ADAMS Accession No. ML14092A293), Duke Energy (Duke) (the licensee) requested a change to the facility operating licenses (FOLs) for Brunswick Steam Electric Plant, Units 1 and 2 (BSEP, Units 1 and 2); Crystal River, Unit 3 Nuclear Generating Plant (CR-3); Shearon Harris Nuclear Power Plant, Unit 1 (SHNPP, Unit 1); and H. B. Robinson Steam Electric Plant, Unit No.2 (HBRSEP). The term 'licensee', as it is used to in this SE, includes the licensees for each of the Individual plants Identified above or in the initial application, and any conclusions or Enclosure 6

The licensee proposed a Milestone 8 completion date of December 31, 2017. The licensee stated that changing the completion date of Mil~stone 8 will provide the licensee sufficient time to plan work due to the unanticipated scope, as well as to align the implementation of Mifestone 8 throughout the licensee's fleet. The licensee stated that all CDAs for safety functions, important to safety functions, security functions, emergency preparedness functions, and balance of plant functions to the first Inter-tie (bus-line breaker) with offsite distribution system are weighted equally during work planning and execution. The NRC staff finds that based on the unanticipated complexity of CDA assessment and the remaining work to complete Milestone 8 described above, the licensee's methodology for prioritizing work is appropriate.

3.3 Technical Evaluation Conclusion The NRC staff concludes that the licensee's request to delay full implementation of its CSP until December 31, 2017, Is reasonable because the licensee's implementation of Milestones 1 through 7 adds additional protection that provides mitigation for significant cyber attack vectors for the most significant CDAs; that the licensee's explanation of the need for additional time is compelling as the scope of the work required to come into full compliance with the CSP was much more complicated than anticipated and was not reasonably foreseeable; and that it is acceptable for Duke to complete Implementation of Milestone 8, full implementation of the CSP, by December 31, 2017. The NRC staff also concludes that upon full implementation of the licensee's cyber security program, the requirements of the licensee's CSP and 10 CFR 73.54 will be met. Therefore, the NRC staff finds the proposed change acceptable.

3.4 Revision to License Condition By letter dated December 19, 2013, the licensee proposed to modify Paragraph 2.D of Renewed Facility Operating License No. DPR-71, Paragraph 2.C.(6) of Renewed Facility Operating License No. DPR-62, Paragraph 2.E of Renewed Facility Operating License No. NPF-63, Paragraph 2.D of Facility Operating License No. DPR-72, and Paragraph 3.F of Renewed Facility Operating License No. DPR-23 for BSEP, Units 1 and 2; SHNPP, Unit 1; CR-3; and HBRSEP, Unit No.2, respectively, which provide 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.D of Renewed Facility Operating License No. DPR-71 for BSEP, Unit 1 is modified as follows:

The licensee's CSP was approved by License Amendment No. 258, as supplemented by changes approved by License Amendment Nos. 261 and 265.

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

The licensee's CSP was approved by License Amendment No. 286, as supplemented by changes approved by License Amendment Nos. 289 and 293.

The license condition In Paragraph 2.E of Renewed Facility Operating License No. NPF-63 for SHNPP, Unit 1 is modified as follows:

ML15008A455 OFFICE DORLILPL2-2/PM DORLILPL2-2/LAiT DORLILPL2-2/LA DORLILPL2-2/BC(A) DORL/LPL2-2/PM NAME AHon LRonewicz BCiayton LRegner AHon DATE 01/08/15 01/08/15 01/08/15 01/09/15 01/09/15