GNRO-2010/00047, Operating License Amendment Withdrawal and Request, Cyber Security Plan

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Operating License Amendment Withdrawal and Request, Cyber Security Plan
ML102070558
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 07/22/2010
From: Richey M
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2010/00047
Download: ML102070558 (12)


Text

Entergy Operations, Inc.

7003 Bald Hill Road PO. Box 756 Port Gibson, MS 39150 Tel 601 437 6787 Marty L. Richey Director Nuclear Safety Assurance GNRO-2010/00047 July 22, 2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Operating License Amendment Withdrawal and Request Grand Gulf Nuclear Station Cyber Security Plan Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29

REFERENCES:

1. NRC Letter GNRI-2010/00070, Grand Gulf Nuclear Station, Unit 1 -

License Amendment Request for Approval of the Cyber Security Plan (TAC No. ME2644), dated May 24, 2010

2. Entergy Letter GNRO-2009/00059, Operating License Amendment Request - Grand Gulf Nuclear Station Cyber Security Plan and Implementation Schedule, dated November 18, 2009
3. NRC Letter to Nuclear Energy Institute, "Nuclear Energy Institute 08-09, Cyber Security Plan Template, Rev. 6," dated June 7, 2010

[ML101550052]

Dear Sir or Madam:

In accordance with the 60-day request provided in Reference 1, Entergy Operations, Inc.

(Entergy) is hereby withdrawing the request for an amendment to the Facility Operating License (FOL) for Grand Gulf Nuclear Station, Unit 1 (GGNS), as submitted in Reference 2, and in accordance with the provisions. of 10 CFR 50.90, Entergy is submitting a new request for an amendment to the FOL for GGNS. The proposed amendment adds a sentence to the existing FOL Physical Protection license condition to require Entergy to fully implement and maintain in effect all provisions of the Commission-approved cyber security plan. Additionally, Entergy requests NRC approval of the GGNS Cyber Security Plan, and associated implementation schedule in accordance with 10 CFR 73.54. This submittal supersedes, in its entirety, the previous GGNS submittal in Reference 2.

Entergy utilized Nuclear Energy Institute (NEI) 08-09, "Cyber Security Plan for Nuclear Power Reactors," Revision 6, dated April 2010, in development of the GGNS Cyber Security Plan which resolves NRC generic issues (described in Reference 1) with the previous GGNS submittal in Reference 2. In addition, Entergy is utilizing the definition of "cyber attack" as delineated in Reference 3.

Attachments 4, 5, and 6 to this letter contain security sensitive information (aKDCD1A-and are withheld from public disclosure in accordance with 10 CFR 2.390

GNRO-2010/00047 Page 2 of 3 provides an analysis of the proposed FOL change for the GGNS Cyber Security Plan. Attachment 2 provides the existing FOL page marked-up to show the proposed change, and Attachment 3 provides the final typed FOL page. Attachment 4 identifies new regulatory commitments made in this submittal. Attachment 5 provides the proposed milestone implementation schedule. Attachment 6 provides a copy of the GGNS Cyber Security Plan which is a stand-alone document to be incorporated by reference into the GGNS Physical Security Plan upon NRC approval. Entergy requests that Attachments 4, 5, and 6, which contain security sensitive information, be withheld from public disclosure in accordance with 10 CFR 2.390.

The proposed change has been evaluated in accordance with 10 CFR 50.91 (a)(1) using criteria in 10 CFR 50.92(c), and it has been determined that this change involves no significant hazards consideration. The bases for these determinations are included in .

Entergy requests approval of the proposed amendment and the GGNS Cyber Security Plan as soon as practical. Although this request is neither exigent nor emergency, your review is requested within approximately one year of this submittal. Once approved, the amendment will be implemented within 60 days of receipt of the approval letter. The implementation of the GGNS Cyber Security Plan will be in accordance with the proposed implementation schedule (Attachment 5).

If you have any questions regarding this submittal, please contact Peggy R. Rescheske at 601-437-1781.

I declare under penalty of perjury that the foregoing is true and correct. Executed on July 22, 2010.

Sincerely, MLR/PRR Attachments: 1. Analysis of Proposed Operating License Change - GGNS Cyber Security Plan

2. Proposed GGNS Operating License Change (markup)
3. Proposed GGNS Operating License Change (typed final)
4. List of Regulatory Commitments Plan [Security-Related Information -

Withhold from public disclosure under 10 CFR 2.390]

5. GGNS Cyber Security Plan Proposed Implementation Schedule

[Security-Related Information - Withhold from public disclosure under 10 CFR 2.390]

6. GGNS Cyber Security Plan [Security-Related Information - Withhold from public disclosure under 10 CFR 2.390]

GNRO-2010/00047 Page 3 of 3 cc:

NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission ATTN: Mr. Elmo E. Collins, Jr. (w/2)

Region Administrator, Region IV 612 East Lamar Blvd, Suite 400 Arlington, TX 76011-4125 U. S. Nuclear Regulatory Commission ATTN: Mr. Carl F. Lyon, NRR/DORL (w/2)

Mail Stop OWFN/8 B1 Washington, DC 20555-0001

Attachment 1 GNRO-2010/00047 Analysis of Proposed Operating License Change -

GGNS Cyber Security Plan to GNRO-2010/00047 Page 1 of 4 1.0 Summary Description The license amendment request (LAR) adds a sentence to the existing Facility Operating License (FOL) Physical Protection license condition requiring Entergy Operations, Inc.

(Entergy) to fully implement and maintain in effect all provisions of the Commission-approved cyber security plan. This submittal also includes the proposed Grand Gulf Nuclear Station, Unit 1 (GGNS) Cyber Security Plan (Plan) and an implementation schedule.

2.0 Detailed Description The proposed change includes three parts: the proposed Plan, an implementation schedule, and a proposed sentence to be added to the existing FOL Physical Protection license condition to require the licensee to fully implement and maintain in effect all provisions of the Commission approved cyber security plan as required by 10 CFR 7.3.54 (Rule). Federal Register Notice 74 FR 13926, dated March 27, 2009, issued the final rule that amended 10 CFR Part 73. The regulations in 10 CFR 73.54, "Protection of digital computer and communication systems and networks," establish the requirements for a cyber security program. This regulation specifically requires each licensee currently licensed to operate a nuclear power plant under Part 50 of this chapter to submit a cyber security plan that satisfies the requirements of the Rule. Each submittal must include a proposed implementation schedule and implementation of the licensee's cyber security program must be consistent with the approved schedule. The background for this application is addressed by the NRC Notice of Availability published on March 27, 2009, in Federal Register Notice 74 FR 13926 (Reference 1).

3.0 Technical Evaluation Federal Register Notice 74 FR 13926 issued the final rule that amended 10 CFR Part 73.

Cyber security requirements are codified in the new 10 CFR 73.54 and are designed to provide high assurance that digital computer and communication systems and networks are adequately protected against cyber attacks up to and including the design basis threat established by 10 CFR 73.1(a)(1)(v). These requirements are substantial improvements upon the requirements imposed by NRC Order EA-02-026 (Reference 2).

This proposed amendment conforms to the model Cyber Security Plan contained in Appendix A of Nuclear Energy Institute (NEI) 08-09, "Cyber Security Plan for Nuclear Power Reactors," Revision 6, dated April 2010 (Reference 3), for use by licensees in development of their cyber security plans. A deviation from Appendix B of NEI 08-09, Revision 6, is the use of a revised definition of "cyber attack" as delineated in NRC letter dated June 7, 2010 (Reference 4). The revised definition of cyber attack is "any event in which there is reason to believe that an adversary has committed or caused, or attempted to commit or cause, or has made a credible threat to commit or cause malicious exploitation of a critical digital asset."

This LAR includes the proposed Plan (Attachment 6) that conforms to the model Cyber Security Plan contained in Appendix A, "Cyber Security Plan Template," of NEI 08-09 Revision 6. In addition, the LAR includes the proposed change to the existing FOL license condition for "Physical Protection" (Attachments 2 and 3). A list of regulatory commitments is provided in Attachment 4. The LAR also contains the proposed implementation schedule (Attachment 5) as required by 10 CFR 73.54.

to GNRO-2010/00047 Page 2 of 4 4.0 Regulatory Evaluation 4.1 Applicable Regulatory Requirements/Criteria This license amendment request (LAR) is submitted pursuant to 10 CFR 73.54 which requires licensees currently licensed to operate a nuclear power plant under 10 CFR Part 50 to submit a Cyber Security Plan as specified in 10 CFR 50.4 and 10 CFR 50.90.

4.2 Significant Hazards Consideration Entergy Operations, Inc. (Entergy) has evaluated the proposed changes using the criteria in 10 CFR 50.92 and has determined that the proposed changes do not involve a significant hazards consideration. An analysis of the issue of no significant hazards consideration is presented below.

Criterion 1: The proposed change does not involve a significantincreasein the probabilityor consequences of an accidentpreviously evaluated.

The proposed change is required by 10 CFR 73.54 and includes three parts. The first part is the submittal of the Grand Gulf Nuclear Station, Unit 1 (GGNS) Cyber Security Plan (Plan) for NRC review and approval. The Plan does not alter accident analysis assumptions, add any initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, modified, tested, or inspected. The Plan does not require any plant modifications which affect the performance capability of the structures, systems, and components relied upon to mitigate the consequences of postulated accidents. The Plan is designed to achieve high assurance that the systems within the scope of the 10 CFR 73.54 Rule are protected from cyber attacks and has no impact on the probability or consequences of an accident previously evaluated.

The second part of the proposed change is an implementation schedule, and the third part adds a sentence to the existing Facility Operating License (FOL) license condition for Physical Protection. Both of these changes are administrative and have no impact on the probability or consequences of an accident previously evaluated.

Therefore, it is concluded that the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

Criterion 2: The proposed change does not create the possibility of a new or different kind of accidentfrom any accidentpreviously evaluated.

The proposed change is required by 10 CFR 73.54 and includes three parts. The first part is the submittal of the Plan for NRC review and approval. The Plan does not alter accident analysis assumptions, add any initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, modified, tested, or inspected. The Plan does not require any plant modifications which affect the performance capability of the structures, systems, and components relied upon to mitigate the consequences of postulated accidents.

The Plan is designed to achieve high assurance that the systems within the scope of the 10 CFR 73.54 Rule are protected from cyber attacks and does not create the possibility of a new or different kind of accident from any previously evaluated.

to GNRO-2010/00047 Page 3 of 4 The second part of the proposed change is an implementation schedule, and the third part adds a sentence to the existing FOL license condition for Physical Protection. Both of these changes are administrative and do not create the possibility of a new or different kind of accident from any previously evaluated.

Therefore, it is concluded that the proposed change does not create the possibility of a new or different kind of accident from anyI previously evaluated.

Criterion3: The proposed change does not involve a significantreduction in a margin of safety.

The proposed change is required by 10 CFR 73.54 and includes three parts. The first part is the submittal of the Plan for NRC review and approval. Plant safety margins are established through Limiting Conditions for Operation, Limiting Safety System Settings, and Safety Limits specified in the Technical Specifications. Because there is no change to these established safety margins as a result of the implementation of the Plan, the proposed change does not involve a significant reduction in a margin of safety.

The second part of the proposed change is an implementation schedule, and the third part adds a sentence to the existing FOL license condition for Physical Protection. Both of these changes are administrative and do not involve a significant reduction in a margin of safety.

Therefore, it is concluded that the proposed change does not involve a significant reduction in a margin of safety.

Based on the above three criteria, Entergy concludes that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and accordingly, a finding of "no significant hazards consideration" is justified.

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

5.0 Environmental Consideration The proposed amendment establishes the licensing basis for a Cyber Security Program for GGNS and will be incorporated by reference into the Physical *Security Plan. This proposed amendment will not involve any significant construction impacts. The proposed amendment meets the eligibility criterion for a categorical exclusion set forth in 10 CFR 51.22(c)(12).

Therefore, pursuant to 10 CFR 51.22(b), Entergy concludes no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

to GNRO-2010/00047 Page 4 of 4 6.0 References

1. Federal Register Notice, Final Rule 10 CFR Part 73, Power Reactor Security Requirements, published on March 27, 2009, 74 FR 13926
2. NRC Order EA-02-026, Order Modifying Licenses, Safeguards and Security Plan Requirements, issued February 25, 2002
3. Nuclear Energy Institute NEI 08-09, "Cyber Security Plan for Nuclear Power Reactors,"

Revision 6, April 2010

4. NRC Letter to Nuclear Energy Institute, "Nuclear Energy Institute 08-09, Cyber Security Plan Template, Rev. 6," dated June 7, 2010 [ML101550052]

Attachment 2 GNRO-2010/00047 Proposed GGNS Operating License Change (markup) to GNRO-2010/00047 Page 1 of 1 (b) The first performance of the periodic assessment of CRE habitability, Specification S.5.13.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from March 2005. the date of the most recent successful tracer gas test, as stated in the June 30, 2005 letter response to Generic Letter 2003-01. or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.

CC) The first performance of the periodic assessment of the CRE boundary, Specification 5.S.13.d, shall be within the next 18 months, plus the 136 days allowed by SR 3.0.2, as measured from the date of issuance of this amendment.

D. The facility required exemptions from certain requirements of Appendices A and I to 10 CFR Part 50 and from certain requirements of 10 CFR Part 100. These include: (a) exemption from General Design criterion 17 of Appendix A until startup following the first refueling outage, for (1) the emergency override of the test mode for the Divislon 3 diesel engine, (2) the second level undervoltage protection for the Division 3 diesel engine, and (3) the generator ground over current trip function for the Division 1 and 2 diesel generators (Section 8.3.1 of SSER #7) and (b) exemption from the requirements of Paragraph III.D.2(b)(ii) of Appendix 3 for the containment airlock testing following normal door opening when containment integrity is not required (Section 6.2.6 of SSER #7), These exemptions are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest. in addition, by exemption dated December 20, 1986, the Commission exempted licensees from 10 CFR 100,11(a)(1), insofar as it incorporates the definition of exclusion area in 10 CFR 100.3Ca) until April 30, 1987 regarding demonstration of authority to control all activities within the exclusion area (safety evaluation accompanying Amendment No. 27 to License (NPF-29). This exemption is authorized by law, and will not present an undue risk to the public health and safety, and is consistentwith the common defense and security. In addition, special circumstances have been found justifying the exemption.

Therefore, these exemptions are hereby granted pursuant to 10 CFR 50.12.

with the granting of these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application as amended, the provisions of the Act and the rules and regulations of tle Commission.

E. The licensee shall fully implement and maintain in effect all provision 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 4 Safeguards contingency and Training and Qualification Plan,, and were subm tted to the NRC on May 18, 2006,

-with 10 CFR 2,390,

.16a Amendment No. V49 -}za Revised by-Leltefdaet 4ly-8-2007

Attachment 3 GNRO-2010100047 Proposed GGNS Operating License Change (typed final)

(b) The first performance of the periodic assessment of CRE habitability, Specification 5.5.13.c.(ii), shall be withi'n 3 years, plus the 9-month allowance of SR 3.0.2, as measured from March 2005, the date of the most recent successful tracer-gas test,, as stated in the Juhe 30,. 2005 letter response to Generic.

Letter 2003-01, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.

(c) The first performance of the periodic assessment of the CRE boundary, Specification 5.5..13.d, shall be within the next 18 months, plus the 136 days allowed by SR 3.0.2, as measured from the date of issuance of this amendment.

D. The facil'ity required exemptions from certain requirements of Appendices A and I tolO CFR Part 50 and from certain requirements of 10 CFR Part 100. These include: (a) exemption'feom General Design Criterion 17 of Appendix A until startup following the ffirst refueling outage, for (1) the emergency override of the test mode for the Division 3 diesel engine.

(2) the second level undervoltage pr6tection for the Division 3 diesel engine, and (3) the generator ground. over currentitrijp function for the Division land 2 diesel generators (Section 8.3.1 of SSER #7) and (b) exemption from the requirements of Paragraph IIID.2(b)(ii) of Appendix 3 for the containment airlock testing following normal door openipng when containment integrity is not required (Section 6.2.6 of SSER #7)' These exemptions, are authorized by law andwill not endanger'life or property or the common defense and security and are otherwise in the public interest. In addition, by exemption-dated December 20, 1986, the Commis'sion exempted licensees from :10 CFR 100.11(a)(1), insofar as it incorporates the definition of exclusion area in 10 CFR100.3(a), until April 30, 1987 regarding demonstration of authority to control all activities within the exclusion area (safety evaluation accompanying Amendment No. 27 to License (NPF-29). This exemption-is authorized by law, and will not present an undue risk to the public health and safety, and is consistent with the common defense and security. In'.addition, special circumstances have been found justifying the exemption.

Therefore, these exemptions are hereby granted pursuant to 10 CFR 5042.

with. the granting of these exemptions, the facility vill operate, to the extent authorized herein, itnconformity with the application, as amended, the provisions of the Act and the rules and regulations of.the Commission.

E. The licensee shall fully implement and maintain in effect all provision of the Commission-approved physical security, training and qualification,:

and safeguards contingency plans including amendments made pursuant to provisions ofthe Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the.authorityý 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, Safeguards Contingency and Training and Qualification Plan,." and were submitted to the NRC on May 18, 2006.

The licensee shall fully implement in accordance with an NRC-approved implementation schedule and maintain in effect all provisions of the Commission.ýapproved cyber security plan: submitted'.by letter dated July 22, 2010, and withheld from public disclosure in accordance with 10 CFR 2,390.

16a 3, Amendment No..b4,