ML110550768

and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Request for Additional Information Regarding License Amendment Request for Approval of Cyber Security Plan

ML110550768
Person / Time
Site:	Salem, Hope Creek
Issue date:	03/02/2011
From:	Richard Ennis Plant Licensing Branch 1
To:	Joyce T Public Service Enterprise Group
Ennis R, NRR/DORL, 415-1420
References
TAC ME4352, TAC ME4353, TAC ME4354
Download: ML110550768 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 March 2, 2011 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear P.O. Box 236, N09 Hancocks Bridge, NJ 08038

SUBJECT:

HOPE CREEK GENERATING STATION AND SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR APPROVAL OF CYBER SECURITY PLAN (TAC NOS. ME4352, ME4353, AND ME4354)

Dear Mr. Joyce:

By letter dated July 14,2010, as supplemented by letter dated September 28,2010, PSEG Nuclear LLC submitted a license amendment request for Hope Creek Generating Station (Hope Creek) and Salem Nuclear Generating Station, Unit Nos. 1 and 2 (Salem). The proposed amendment requested approval of the Salem-Hope Creek Cyber Security Plan.

The Nuclear Regulatory Commission staff is reviewing your submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). It is requested that your RAI response be provided within 30 days of the date of this letter.

Sincerely, Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-354, 50-272, and 50-311

Enclosure:

As stated cc wI encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION (RA!)

REGARDING LICENSE AMENDMENT REQUEST FOR APPROVAL OF THE CYBER SECURITY PLAN FOR HOPE CREEK GENERATING STATION AND SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-354, 50-272, AND 50-311 By letter dated July 14, 2010, as supplemented by Jetter dated September 28,2010 (Agencywide Documents Access and Management System (ADAMS) Accession Nos.

ML102080586 and ML102810304, respectively), PSEG Nuclear LLC (the licensee) submitted a license amendment request for Hope Creek Generating Station (Hope Creek) and Salem Nuclear Generating Station, Unit Nos. 1 and 2 (Salem). The proposed amendment requested approval of the Salem-Hope Creek Cyber Security Plan (CSP).

The Nuclear Regulatory Commission (NRC or the Commission) staff is reviewing your submittal and has determined that additional information is needed to complete its review. The specific information requested is addressed below.

RAI 1: Records Retention Title 10 of the Code of Federal Regulations (10 CFR) Section 73.54(c)(2) requires licensees to design a cyber security program to ensure the capability to detect, respond to, and recover from cyber attacks. Furthermore, 10 CFR 73.54(e)(2)(i) requires licensees to maintain a CSP that describes how the licensee will maintain the capability for timely detection and response to cyber attacks. The ability for a licensee to detect and respond to cyber attacks requires accurate and complete records and is further supported by 10 CFR 73.54(h), which states that the licensee shall retain all records and supporting technical documentation required to satisfy the requirements of 10 CFR Section 73.54 as a record until the Commission terminates the license for which the records were developed, and shall maintain superseded portions of these records for at least 3 years after the record is superseded, unless otherwise specified by the Commission.

The licensee's CSP in Section 4.13 states that Critical Digital Asset (CDA) audit. records and audit data (e.g., operating system logs, network device logs) are retained for a period of time that is less than what is required by 10 CFR 73.54(h).

Explain the deviation from the 10 CFR 73.54(h) requirement to retain records and supporting technical documentation until the Commission terminates the license (or to maintain superseded portions of these records for at least 3 years) and how that meets the requirements of 10 CFR 73.54.

Enclosure

- 2 RAI 2: Implementation Schedule The regulation at 10 CFR 73.54, "Protection of digital computer and communication systems and networks," requires licensees to submit a CSP that satisfies the requirements of this section for Commission review and approval. Furthermore, each submittal must include a proposed implementation schedule and the implementation of the licensee's cyber security program must be consistent with the approved schedule. Paragraph 73.54(a) of 10 CFR requires licensees 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 (DBT).

The completion of several key intermediate milestones (Items (a) through (g) below) would demonstrate progress toward meeting the requirements of 10 CFR 73.54. The NRC staff's expectation is that the key intermediate milestones will be completed in a timely manner, but no later than December 31, 2012. The key CSP implementation milestones are as follows:

(a) Establish, train and qualify Cyber Security Assessment Team, as described in Section 3.1.2, "Cyber Security Assessment Team," of the CSP.

(b) Identify Critical Systems and CDAs, as described in Section 3.1.3, "Identification of Critical Digital Assets," of the CSP.

(c) Implement cyber security defense-in-depth architecture by installation of deterministic devices, as described in Section 4.3, "Defense-in-Depth Protective Strategies" of the CSP.

(d) Implement the management, operational and technical cyber security controls that address attacks promulgated by use of portable media, portable devices, and portable equipment as described in Appendix D Section 1.19 "Access Control for Portable and Mobile Devices," of Nuclear Energy institute (NEI) 08-09, Revision 6.

(e) Implement observation and identification of obvious cyber related tampering to existing insider mitigation rounds as described in Appendix E Section 4.3, "Personnel Performing Maintenance and Testing Activities," and Appendix E Section 10.3, "Baseline Configuration" of NEI 08-09, Revision 6.

(f) Identify, document, and implement cyber security controls to physical security target set CDAs in accordance with Section 3.1.6, "Mitigation of Vulnerabilities and Application of Cyber Security Controls," of the CSP.

(g) Ongoing monitoring and assessment activities will commence for those target set CDAs whose security controls have been implemented, as described in Section 4.4, "Ongoing Monitoring and Assessment," of the CSP.

(h) Full implementation of the CSP for all safety, security, and emergency preparedness functions.

- 3 Provide a revised CSP implementation schedule that identifies the appropriate milestones, completion dates, supporting rationale, and level of detail to allow the NRC to evaluate the licensee's proposed schedule and associated milestone dates which include the final completion date. It is the NRC's intention to develop a license condition incorporating your revised CSP implementation schedule containing the key milestone dates.

RAI 3: Scope of Systems Paragraph 73.54(a) of 10 CFR requires licensees to provide high assurance that digital computer and communication systems and networks are adequately protected against cyber attacks, up to and including the DBT as described in 10 CFR 73.1. In addition, 10 CFR 73.54(a)(1) states that the licensee shall protect digital computer and communication systems and networks associated with:

(i) Safety-related and important-to-safety functions; (ii) Security functions; (iii) Emergency preparedness functions, including offsite communications; and (iv) Support systems and equipment which, if compromised, would adversely impact safety, security, or emergency preparedness functions.

Subsequent to the issuance of the cyber security rule, the NRC stated that 10 CFR 73.54 should be interpreted to include structures, systems, and components (SSCs) in the balance of plant (BOP) that have a nexus to radiological health and safety (ADAMS Accession No. ML103490344, dated November 19,2010). The SSCs in the BOP are those that could directly or indirectly affect reactivity of a nuclear power plant and could result in an unplanned reactor shutdown or transient and are, therefore, within the scope of important-to-safety functions described in 10 CFR 73.54(a)(1). Furthermore, the NRC issued a letter to NEI dated January 5, 2011 (ADAMS Accession No. ML103550480) that provided licensees with additional guidance on one acceptable approach to comply with the Commission's policy determination.

Explain how the scoping of systems provided by the site CSP meets the requirements of 10 CFR 73.54 and the additional guidance provided by the NRC.

March 2, 2011 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear P.O. Box 236, N09 Hancocks Bridge, NJ 08038

SUBJECT:

HOPE CREEK GENERATING STATION AND SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR APPROVAL OF CYBER SECURITY PLAN (TAC NOS. ME4352, ME4353, AND ME4354)

Dear Mr. Joyce:

By letter dated July 14, 2010, as supplemented by letter dated September 28, 2010, PSEG Nuclear LLC submitted a license amendment request for Hope Creek Generating Station (Hope Creek) and Salem Nuclear Generating Station, Unit Nos. 1 and 2 (Salem). The proposed amendment requested approval of the Salem-Hope Creek Cyber Security Plan.

The Nuclear Regulatory Commission staff is reviewing your submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). It is requested that your RAI response be provided within 30 days of the date of this letter.

Sincerely, Ira!

Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-354, 50-272, and 50-311

Enclosure:

As stated cc wi encl: Distribution via Listserv Distribution:

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DATE 2/28/11 11 3/2/11 OFFICIAL AGENCY RECORD