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| | number = ML15133A502 | | | number = ML15133A502 |
| | issue date = 06/10/2015 | | | issue date = 06/10/2015 |
| | title = Perry Nuclear Power Plant, Unit 1 - Issuance of Amendment Concerning Extension of Cyber Security Milestone 8 (TAC No. MF5557)(L-14-421) | | | title = Issuance of Amendment Concerning Extension of Cyber Security Milestone 8 (TAC No. MF5557)(L-14-421) |
| | author name = Green K J | | | author name = Green K |
| | author affiliation = NRC/NRR/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/DORL/LPLIII-1 |
| | addressee name = Harkness E J | | | addressee name = Harkness E |
| | addressee affiliation = FirstEnergy Nuclear Operating Co | | | addressee affiliation = FirstEnergy Nuclear Operating Co |
| | docket = 05000440 | | | docket = 05000440 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Ernest J. Harkness Site Vice President June 10, 2015 FirstEnergy Nuclear Operating Company Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097 SUBJECT: PERRY NUCLEAR POWER PLANT, UNIT NO. 1 -ISSUANCE OF AMENDMENT CONCERNING EXTENSION OF CYBER SECURITY MILESTONE 8 (TAC NO. MF5557)(L-14-421) Dear Mr. Harkness: The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 167 to Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant (PNPP), Unit No. 1. This amendment extends the completion date for full implementation of PNPP Cyber Security Plan (CSP) in response to FirstEnergy Nuclear Operating Company's (FENOC's) application dated January 9, 2015, as supplemented by a letter dated May 6, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML 15009A264 and ML 15127 A202, respectively)). Portions of the letter dated January 9, 2015, contain sensitive unclassified non-safeguards information and those portions are withheld from public disclosure in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390(d)(1 ). It should be noted that the NRC staff does not regard the CSP milestone implementation dates as regulatory commitments that can be changed unilaterally by a licensee, particularly in light of the regulatory requirement at 10 CFR 73.54. Thus, any subsequent changes that FE NOC may request to the NRG-approved CSP implementation schedule will be submitted for prior NRC approval under 10 CFR 50.90. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 10, 2015 Mr. Ernest J. Harkness Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097 |
| E. Harkness -2 -A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Docket No. 50-440 Enclosures: 1. Amendment No. 167 to NPF-58 2. Safety Evaluation cc w/encls: Distribution via ListServ Sincerely, Kimberly J. Green, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP. OHIO EDISON COMPANY DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 167 License No. NPF-58 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that: A The application for license filed by FirstEnergy Nuclear Operating Company, et al., (the licensee, FE NOC) dated January 9, 2015, as supplemented by a letter dated May 6, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 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 -2. Accordingly, the license is amended by changes to the Facility Operating License as indicated in the attachment to this license amendment, and paragraph 2.E of Facility Operating License No. NPF-58 is hereby amended to read as follows: E. FENOC 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 (61 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Perry Nuclear Power Plant Physical Security Plan" Revision 2, submitted by letter dated May 18, 2006. FENOC 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 FENOC CSP was approved by License Amendment No. 158, and amended by License Amendment No. 167. 3. This license amendment is effective as of its date of its issuance and shall be implemented within 30 days of the date of issuance. Attachment: Changes to the Facility Operating License Date of Issuance: June 1 O, 2015 FOR THE NUCLEAR REGULA TORY COMMISSION . el n, f Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation ATTACHMENT TO LICENSE AMENDMENT NO. 167 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 Replace the following page of the Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change. Remove License NPF-58 License NPF-58 Page 6 Page 6
| | ==SUBJECT:== |
| -6 -D. FENOC is exempted from: 1) the requirements of Section lll.D.2(b)(ii), containment airlock testing requirements, Appendix J to 10 CFR Part 50, due to the special circumstance described in Section 6.2.6 of SER Supplement No. 7 authorized by 10 CFR 50.12(a)(2)(iii) and 2) the requirements of Section IV.F., Full Participation Exercise, of Appendix E to 10 CFR Part 50, due to the special circumstance described in the Exemption dated November 6, 1986. These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The exemptions are hereby granted pursuant to 1 O 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 the Commission. E. FE NOC 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 (61 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Perry Nuclear Power Plant Physical Security Plan" Revision 2, submitted by letter dated May 18, 2006. FE NOC shall fully implement and maintain in effect all provisions of the approved cyber security plan (CSP), including changes made pursuant to the authority of 1 O CFR 50.90 and 1 O CFR 50.54(p). The FENOC CSP was approved by License Amendment No. 158, and amended by License Amendment No.167. F. Deleted G. The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1964, as amended, to cover public liability claims. Amendment No. 167 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 167 TO FACILITY OPERATING LICENSE NO. NPF-58 FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP. 1.0 INTRODUCTION OHIO EDISON COMPANY PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-440 By application dated January 9, 2015, as supplemented by a letter dated May 6, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML 15009A265 and ML 15127A202, respectively), the FirstEnergy Nuclear Operating Company (FENOC, the licensee) requested a change to the facility operating license (FOL) for Perry Nuclear Plant, Unit 1 (PNPP). The proposed change would revise the date of Cyber Security Plan (CSP) Implementation Schedule Milestone 8, and would accordingly modify the license condition in Paragraph 2.E of the FOL. The supplemental letter dated May 6, 2015, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination. 2.0 REGULATORY EVALUATION 2.1 Background The NRC staff reviewed and approved the licensee's existing CSP implementation schedule in a letter dated August 29, 2011 (ADAMS Accession No. ML 111920382), concurrent with the incorporation of the CSP into the facility's current licensing basis. Milestone 8 of the CSP implementation schedule concerns the full implementation of the CSP. 2.2 Regulations Section 73.54(a) to Title 10 to the Code of Federal Regulations (10 CFR) states that licensees must 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 described in 10 CFR 73.1. Pursuant to 10 CFR 73.54(a)(1 ), licensees must protect digital Enclosure 2
| | PERRY NUCLEAR POWER PLANT, UNIT NO. 1 - ISSUANCE OF AMENDMENT CONCERNING EXTENSION OF CYBER SECURITY MILESTONE 8 (TAC NO. MF5557)(L-14-421) |
| -2 -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. As further specified in 10 CFR 73.54(a)(2), these systems and networks must be protected from cyber attacks that would adversely impact the integrity or confidentiality of data and software; deny access to systems, services, or data; and adversely impact the operation of systems, networks, and associated equipment. Additionally, 10 CFR 73.54 requires licensees to submit a proposed implementation schedule, and further requires that implementation of the licensee's cyber security program be consistent with the approved schedule. It should be noted that 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." Thus all subsequent changes to the NRC-approved CSP implementation schedule will require submittal for prior NRC approval under 10 CFR 50.90. Section 13.6.6, of NUREG-0800, provides the review criteria for CSP security plans. In a letter dated October 24, 2013 (ADAMS Accession No. ML 13295A467), the NRC staff listed criteria to consider during evaluations of licensees' requests to postpone their cyber security program implementation date (commonly known as Milestone 8). The criteria in the guidance are as follows: 1. Identification of the specific requirement or requirements of the cyber security plan that the licensee needs additional time to implement. 2. Detailed justification that describes the reason the licensee requires additional time to implement the specific requirement or requirements identified. 3. A proposed completion date for Milestone 8 consistent with the remaining scope of work to be conducted and the resources available. 4. An evaluation of the impact that the additional time to implement the requirements will have on the effectiveness of the licensee's overall cyber security program in the context of milestones already completed. 5. A description of the licensee's methodology for prioritizing completion of work for critical digital assets associated with significant safety consequences and with reactivity effects in the balance of plant. 6. A discussion of the licensee's cyber security program performance up to the date of the license amendment request. 7. A discussion of cyber security issues pending in the licensee's corrective action program.
| | |
| -3 -8. A discussion of modifications completed to support the cyber security program and a discussion of pending cyber security modifications. 3.0 TECHNICAL EVALUATION 3.1 Extension Request As discussed above, on August 29, 2011, the NRC staff approved the licensee's CSP implementation schedule, which was based on an NEI [Nuclear Energy Institute] template submitted in a letter dated February 28, 2011 (ADAMS Accession No. ML 110600206). In Section 2.0 of the January 9, 2015, submittal, the licensee indicated completion of the first seven milestones of the Cyber Security Implementation Plan as of December 31, 2012. It was identified that on-going monitoring and time-based periodic actions provide continuing program performance monitoring. This monitoring combined with these interim milestones, ensure that PNPP is, and will continue to be, secure; and that digital computer and communication systems, and networks are adequately protected against cyber-attacks during implementation of the full program. Milestone 8 of the licensee's CSP requires FENOC to fully implement the CSP by July 1, 2015. FENOC requested to change the Milestone 8 completion date to December 31, 2017, to allow for support of required design changes and provide additional time to appropriately prioritize work. The licensee identified that additional time would be needed to implement certain activities in Section 3.1, "Analyzing Digital Computer Systems and Networks and Applying Cyber Security Control," of the CSP. More specifically, the licensee indicated that additional time would be needed to complete critical digital asset (CDA) assessment work which is resource intensive, as well as remediation activities, which must be carefully considered, change management challenges, and training on new programs, processes and procedures. In Section 3.0 of the January 9, 2015, submittal, the licensee noted there is a large volume of effort associated with documentation of the assessment and analysis for the 1300 CDAs given the amount of rework that has been identified. The licensee indicates that new tasks are being added to normal maintenance activities, which require significant verification, analysis and testing to ensure no adverse impact to plant equipment. Additionally, the CDA assessment process requires careful consideration of remediation activities given that security controls modifications are unique and new to the plant and suppliers and proposed modifications to the plant have to be evaluated to ensure that the modifications do not adversely impact plant safety and operation. The licensee stated that its methodology for prioritizing Milestone 8 activities is centered on considerations of safety, security, emergency preparedness (EP), and balance of plant (BOP) (continuity of power) consequences. The methodology is based on defense in depth, installed configuration of the CDA, and susceptibility to commonly identified threat vectors. Prioritization for CDA assessment begins with safety-related CDAs and continues through the lower priority nonsafety and EP CDAs:
| | ==Dear Mr. Harkness:== |
| * safety-related CDAs; | | |
| -4 -* important to safety CDAs (including BOP CDAs that directly impact continuity of power) and control system CDAs;
| | The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 167 to Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant (PNPP), Unit No. 1. This amendment extends the completion date for full implementation of PNPP Cyber Security Plan (CSP) in response to FirstEnergy Nuclear Operating Company's (FENOC's) application dated January 9, 2015, as supplemented by a letter dated May 6, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML15009A264 and ML15127A202, respectively)). Portions of the letter dated January 9, 2015, contain sensitive unclassified non-safeguards information and those portions are withheld from public disclosure in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390(d)(1 ). |
| | It should be noted that the NRC staff does not regard the CSP milestone implementation dates as regulatory commitments that can be changed unilaterally by a licensee, particularly in light of the regulatory requirement at 10 CFR 73.54. Thus, any subsequent changes that FE NOC may request to the NRG-approved CSP implementation schedule will be submitted for prior NRC approval under 10 CFR 50.90. |
| | |
| | E. Harkness A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. |
| | Sincerely, Kimberly J. Green, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440 |
| | |
| | ==Enclosures:== |
| | : 1. Amendment No. 167 to NPF-58 |
| | : 2. Safety Evaluation cc w/encls: Distribution via ListServ |
| | |
| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP. |
| | OHIO EDISON COMPANY DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 167 License No. NPF-58 |
| | : 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that: |
| | A The application for license filed by FirstEnergy Nuclear Operating Company, et al., (the licensee, FE NOC) dated January 9, 2015, as supplemented by a letter dated May 6, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 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 by changes to the Facility Operating License as indicated in the attachment to this license amendment, and paragraph 2.E of Facility Operating License No. NPF-58 is hereby amended to read as follows: |
| | E. FENOC 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 (61 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Perry Nuclear Power Plant Physical Security Plan" Revision 2, submitted by letter dated May 18, 2006. |
| | FENOC 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 FENOC CSP was approved by License Amendment No. 158, and amended by License Amendment No. 167. |
| | : 3. This license amendment is effective as of its date of its issuance and shall be implemented within 30 days of the date of issuance. |
| | FOR THE NUCLEAR REGULA TORY COMMISSION |
| | . el n, f Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
| | |
| | ==Attachment:== |
| | |
| | Changes to the Facility Operating License Date of Issuance: June 1O, 2015 |
| | |
| | ATTACHMENT TO LICENSE AMENDMENT NO. 167 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 Replace the following page of the Facility Operating License with the attached revised page. |
| | The revised page is identified by amendment number and contains marginal lines indicating the areas of change. |
| | Remove License NPF-58 License NPF-58 Page 6 Page 6 |
| | |
| | D. FENOC is exempted from: 1) the requirements of Section lll.D.2(b)(ii), containment airlock testing requirements, Appendix J to 10 CFR Part 50, due to the special circumstance described in Section 6.2.6 of SER Supplement No. 7 authorized by 10 CFR 50.12(a)(2)(iii) and 2) the requirements of Section IV.F., Full Participation Exercise, of Appendix E to 10 CFR Part 50, due to the special circumstance described in the Exemption dated November 6, 1986. These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The 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 the Commission. |
| | E. FE NOC 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 (61 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). |
| | The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Perry Nuclear Power Plant Physical Security Plan" Revision 2, submitted by letter dated May 18, 2006. |
| | FE NOC 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 FENOC CSP was approved by License Amendment No. 158, and amended by License Amendment No.167. |
| | F. Deleted G. The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1964, as amended, to cover public liability claims. |
| | Amendment No. 167 |
| | |
| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 167 TO FACILITY OPERATING LICENSE NO. NPF-58 FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP. |
| | OHIO EDISON COMPANY PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-440 |
| | |
| | ==1.0 INTRODUCTION== |
| | |
| | By application dated January 9, 2015, as supplemented by a letter dated May 6, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. |
| | ML15009A265 and ML15127A202, respectively), the FirstEnergy Nuclear Operating Company (FENOC, the licensee) requested a change to the facility operating license (FOL) for Perry Nuclear Plant, Unit 1 (PNPP). The proposed change would revise the date of Cyber Security Plan (CSP) Implementation Schedule Milestone 8, and would accordingly modify the license condition in Paragraph 2.E of the FOL. |
| | The supplemental letter dated May 6, 2015, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination. |
| | |
| | ==2.0 REGULATORY EVALUATION== |
| | |
| | 2.1 Background The NRC staff reviewed and approved the licensee's existing CSP implementation schedule in a letter dated August 29, 2011 (ADAMS Accession No. ML111920382), concurrent with the incorporation of the CSP into the facility's current licensing basis. Milestone 8 of the CSP implementation schedule concerns the full implementation of the CSP. |
| | 2.2 Regulations Section 73.54(a) to Title 10 to the Code of Federal Regulations (10 CFR) states that licensees must 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 described in 10 CFR 73.1. Pursuant to 10 CFR 73.54(a)(1 ), licensees must protect digital Enclosure 2 |
| | |
| | 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. |
| | As further specified in 10 CFR 73.54(a)(2), these systems and networks must be protected from cyber attacks that would adversely impact the integrity or confidentiality of data and software; deny access to systems, services, or data; and adversely impact the operation of systems, networks, and associated equipment. Additionally, 10 CFR 73.54 requires licensees to submit a proposed implementation schedule, and further requires that implementation of the licensee's cyber security program be consistent with the approved schedule. |
| | It should be noted that 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." Thus all subsequent changes to the NRC-approved CSP implementation schedule will require submittal for prior NRC approval under 10 CFR 50.90. |
| | Section 13.6.6, of NUREG-0800, provides the review criteria for CSP security plans. In a letter dated October 24, 2013 (ADAMS Accession No. ML13295A467), the NRC staff listed criteria to consider during evaluations of licensees' requests to postpone their cyber security program implementation date (commonly known as Milestone 8). The criteria in the guidance are as follows: |
| | : 1. Identification of the specific requirement or requirements of the cyber security plan that the licensee needs additional time to implement. |
| | : 2. Detailed justification that describes the reason the licensee requires additional time to implement the specific requirement or requirements identified. |
| | : 3. A proposed completion date for Milestone 8 consistent with the remaining scope of work to be conducted and the resources available. |
| | : 4. An evaluation of the impact that the additional time to implement the requirements will have on the effectiveness of the licensee's overall cyber security program in the context of milestones already completed. |
| | : 5. A description of the licensee's methodology for prioritizing completion of work for critical digital assets associated with significant safety consequences and with reactivity effects in the balance of plant. |
| | : 6. A discussion of the licensee's cyber security program performance up to the date of the license amendment request. |
| | : 7. A discussion of cyber security issues pending in the licensee's corrective action program. |
| | : 8. A discussion of modifications completed to support the cyber security program and a discussion of pending cyber security modifications. |
| | |
| | ==3.0 TECHNICAL EVALUATION== |
| | |
| | 3.1 Extension Request As discussed above, on August 29, 2011, the NRC staff approved the licensee's CSP implementation schedule, which was based on an NEI [Nuclear Energy Institute] template submitted in a letter dated February 28, 2011 (ADAMS Accession No. ML110600206). In Section 2.0 of the January 9, 2015, submittal, the licensee indicated completion of the first seven milestones of the Cyber Security Implementation Plan as of December 31, 2012. It was identified that on-going monitoring and time-based periodic actions provide continuing program performance monitoring. This monitoring combined with these interim milestones, ensure that PNPP is, and will continue to be, secure; and that digital computer and communication systems, and networks are adequately protected against cyber-attacks during implementation of the full program. |
| | Milestone 8 of the licensee's CSP requires FENOC to fully implement the CSP by July 1, 2015. |
| | FENOC requested to change the Milestone 8 completion date to December 31, 2017, to allow for support of required design changes and provide additional time to appropriately prioritize work. The licensee identified that additional time would be needed to implement certain activities in Section 3.1, "Analyzing Digital Computer Systems and Networks and Applying Cyber Security Control," of the CSP. More specifically, the licensee indicated that additional time would be needed to complete critical digital asset (CDA) assessment work which is resource intensive, as well as remediation activities, which must be carefully considered, change management challenges, and training on new programs, processes and procedures. |
| | In Section 3.0 of the January 9, 2015, submittal, the licensee noted there is a large volume of effort associated with documentation of the assessment and analysis for the 1300 CDAs given the amount of rework that has been identified. The licensee indicates that new tasks are being added to normal maintenance activities, which require significant verification, analysis and testing to ensure no adverse impact to plant equipment. Additionally, the CDA assessment process requires careful consideration of remediation activities given that security controls modifications are unique and new to the plant and suppliers and proposed modifications to the plant have to be evaluated to ensure that the modifications do not adversely impact plant safety and operation. |
| | The licensee stated that its methodology for prioritizing Milestone 8 activities is centered on considerations of safety, security, emergency preparedness (EP), and balance of plant (BOP) |
| | (continuity of power) consequences. The methodology is based on defense in depth, installed configuration of the CDA, and susceptibility to commonly identified threat vectors. Prioritization for CDA assessment begins with safety-related CDAs and continues through the lower priority nonsafety and EP CDAs: |
| | * safety-related CDAs; |
| | * important to safety CDAs (including BOP CDAs that directly impact continuity of power) and control system CDAs; |
| * physical security CDAs; and, | | * physical security CDAs; and, |
| * nonsafety-related CDAs and EP CDAs. The licensee stated PNPP uses the existing corrective action program (CAP) to document all cyber issues in order to trend, correct, and improve the cyber security program. Conditions adverse to quality are captured in the CAP database and tracked from initiation through closure. Adverse trends are monitored for program improvement and addressed via the CAP process. 3.2 NRC Staff Evaluation The NRC staff has evaluated the licensee's application using the regulatory requirements and the guidance identified above. The NRC staff's evaluation is below: The NRC staff finds that the actions the licensee noted as being required to implement CSP Section 3, Analyzing Digital Computer Systems and Networks, and Section 4, Establishing, Implementing and Maintaining the Cyber Security Program, are reasonable as discussed below. The licensee indicated that completion of the activities associated with the CSP, as described in Milestones 1 through 7 and completed prior to December 31, 2012, provide a high degree of protection against cyber security attacks. It detailed activities completed for each milestone, and provided details about the completed milestones and elements. The NRC staff finds that the licensee's site is much more secure after implementation of Milestones 1 through 7 because the activities the licensee completed mitigate the most significant cyber attack vectors for the most significant CDAs. The licensee stated that additional time is needed to conduct modifications and change management planning activities and execution. The staff recognizes that CDA assessment work is much more complex and resource intensive than originally anticipated, in part, due to the NRC expanding the scope of the cyber security requirements to include balance of plant. As a result, the licensee has a large number of additional tasks not originally considered when developing its CSP implementation schedule. The staff finds that the licensee's request to delay full implementation of the CSP until December 31, 2017 is reasonable given the complexity and volume of the remaining unanticipated work. The licensee stated that changing the completion date of Milestone 8 will provide sufficient time to methodically plan and schedule the implementation of the required design changes as well as provide time to prioritize work activities to avoid rework and scope changes. The NRC staff recognizes that CDA assessment work is much more complex and resource intensive than originally anticipated and that the licensee has a large number of additional tasks not originally considered when developing its CSP implementation schedule. The licensee has provided sufficient information to conclude that there are implementation issues with the large number of CDAs and the need to address security controls for each. Given this information, the NRC staff finds that the licensee's request to delay full implementation of the CSP until December 31, 2017 is reasonable given the complexity and volume of the remaining unanticipated work. | | * nonsafety-related CDAs and EP CDAs. |
| -5 -Therefore, the NRC staff finds that implementation of Milestones 1 through 7 provides significant protection against cyber attacks in the interim; that the licensee's explanation of the need for additional time is compelling, and that it is acceptable for FENOC to delay full implementation of the CSP until December 31, 2017. The NRC staff also finds that, upon full implementation of the licensee's cyber security program, the requirements of the licensee's CSP and 1 O CFR 73.54 will be met. Therefore, the NRC staff finds the proposed change acceptable. 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 for the following reasons: (i) the licensee's implementation of Milestones 1 through 7 provides mitigation for significant cyber attack vectors for the most significant CDAs as discussed in the staff evaluation above and (ii) the scope of the work required to come into full compliance with the CSP implementation schedule was much more complicated than anticipated and not reasonably foreseeable when the CSP implementation schedule was originally developed. 3.4 Revision to License Condition In its January 9, 2015 application, the licensee proposed to modify the license condition in Paragraph 2.E of its FOL to reflect the NRC staff's approval of an extension of the implementation date for completion of the CSP. The license condition in Paragraph 2.E of the operating license is modified as follows: E. FENOC 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 (61 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Perry Nuclear Power Plant Physical Security Plan," Revision 2, submitted by letter dated May 18, 2006. FENOC 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 FENOC CSP was approved by License Amendment No. 158, and amended by License Amendment No. 167. 4.0 STATE CONSULTATION In accordance with the Commission's regulations, the appropriate Ohio State official was notified of the proposed issuance of the amendment. The State official had no comments.
| | The licensee stated PNPP uses the existing corrective action program (CAP) to document all cyber issues in order to trend, correct, and improve the cyber security program. Conditions adverse to quality are captured in the CAP database and tracked from initiation through closure. Adverse trends are monitored for program improvement and addressed via the CAP process. |
| -6 -5.0 ENVIRONMENTAL CONSIDERATION This licensing action is an amendment to a 10 CFR Part 50 license that relates solely to safeguards matters, and does not involve any significant construction impacts. This amendment is an administrative change to extend the date by which the licensee must have its cyber security plan fully implemented. Accordingly, this licensing action meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(12). The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding (80 FR 18658; April 7, 2015). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment. 6.0 CONCLUSION The NRC staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributor: J. Rycyna, NSIR Date of issuance: June 1 O, 2015 E. Harkness -2 -A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Docket No. 50-440 Enclosures: 1. Amendment No. 167 to NPF-58 2. Safety Evaluation cc w/encls: Distribution via ListServ DISTRIBUTION: Sincerely, IRA/ Kimberly J. Green, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation PUBLIC RidsNsirCsd JRycyna, NSIR LPLlll-1 Reading File RidsNrrDorl Resource RidsOgcMailCenter Resource RidsNrrPMPerry Resource RidsAcrsAcnw_MailCTR Resource RidsNrrLASRohrer Resource RidsRg3MailCenter Resource RidsNrrDorllplll-1 Resource ADAMS Accession No. ML 15133A502
| | 3.2 NRC Staff Evaluation The NRC staff has evaluated the licensee's application using the regulatory requirements and the guidance identified above. The NRC staff's evaluation is below: |
| * via memo **via email OFFICE LPL3-2/PM LPL3-2/LA NSIR/CSD* OGC-NLO LPL3-1/BC LPL3-1/PM NAME EBrown SRohrer RFelts JHull** DPelton KGreen DATE 5/14/2015 5/14/2015 4/22/2015 6/03/2015 6/09/2015 6/10/2015 OFFICIAL RECORD COPY | | The NRC staff finds that the actions the licensee noted as being required to implement CSP Section 3, Analyzing Digital Computer Systems and Networks, and Section 4, Establishing, Implementing and Maintaining the Cyber Security Program, are reasonable as discussed below. |
| }} | | The licensee indicated that completion of the activities associated with the CSP, as described in Milestones 1 through 7 and completed prior to December 31, 2012, provide a high degree of protection against cyber security attacks. It detailed activities completed for each milestone, and provided details about the completed milestones and elements. The NRC staff finds that the licensee's site is much more secure after implementation of Milestones 1 through 7 because the activities the licensee completed mitigate the most significant cyber attack vectors for the most significant CDAs. |
| | The licensee stated that additional time is needed to conduct modifications and change management planning activities and execution. The staff recognizes that CDA assessment work is much more complex and resource intensive than originally anticipated, in part, due to the NRC expanding the scope of the cyber security requirements to include balance of plant. |
| | As a result, the licensee has a large number of additional tasks not originally considered when developing its CSP implementation schedule. The staff finds that the licensee's request to delay full implementation of the CSP until December 31, 2017 is reasonable given the complexity and volume of the remaining unanticipated work. |
| | The licensee stated that changing the completion date of Milestone 8 will provide sufficient time to methodically plan and schedule the implementation of the required design changes as well as provide time to prioritize work activities to avoid rework and scope changes. The NRC staff recognizes that CDA assessment work is much more complex and resource intensive than originally anticipated and that the licensee has a large number of additional tasks not originally considered when developing its CSP implementation schedule. The licensee has provided sufficient information to conclude that there are implementation issues with the large number of CDAs and the need to address security controls for each. Given this information, the NRC staff finds that the licensee's request to delay full implementation of the CSP until December 31, 2017 is reasonable given the complexity and volume of the remaining unanticipated work. |
| | |
| | Therefore, the NRC staff finds that implementation of Milestones 1 through 7 provides significant protection against cyber attacks in the interim; that the licensee's explanation of the need for additional time is compelling, and that it is acceptable for FENOC to delay full implementation of the CSP until December 31, 2017. The NRC staff also finds 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. |
| | 3.3 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 for the following reasons: (i) the licensee's implementation of Milestones 1 through 7 provides mitigation for significant cyber attack vectors for the most significant CDAs as discussed in the staff evaluation above and (ii) the scope of the work required to come into full compliance with the CSP implementation schedule was much more complicated than anticipated and not reasonably foreseeable when the CSP implementation schedule was originally developed. |
| | 3.4 Revision to License Condition In its January 9, 2015 application, the licensee proposed to modify the license condition in Paragraph 2.E of its FOL to reflect the NRC staff's approval of an extension of the implementation date for completion of the CSP. |
| | The license condition in Paragraph 2.E of the operating license is modified as follows: |
| | E. FENOC 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 (61 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Perry Nuclear Power Plant Physical Security Plan," Revision 2, submitted by letter dated May 18, 2006. |
| | FENOC 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 FENOC CSP was approved by License Amendment No. 158, and amended by License Amendment No. 167. |
| | |
| | ==4.0 STATE CONSULTATION== |
| | |
| | In accordance with the Commission's regulations, the appropriate Ohio State official was notified of the proposed issuance of the amendment. The State official had no comments. |
| | |
| | ==5.0 ENVIRONMENTAL CONSIDERATION== |
| | |
| | This licensing action is an amendment to a 10 CFR Part 50 license that relates solely to safeguards matters, and does not involve any significant construction impacts. This amendment is an administrative change to extend the date by which the licensee must have its cyber security plan fully implemented. Accordingly, this licensing action meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(12). The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding (80 FR 18658; April 7, 2015). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment. |
| | |
| | ==6.0 CONCLUSION== |
| | |
| | The NRC staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public. |
| | Principal Contributor: J. Rycyna, NSIR Date of issuance: June 1O, 2015 |
| | |
| | ML15133A502 |
| | * via memo **via email OFFICE LPL3-2/PM LPL3-2/LA NSIR/CSD* OGC- NLO LPL3-1/BC LPL3-1/PM NAME EBrown SRohrer RFelts JHull** DPelton KGreen DATE 5/14/2015 5/14/2015 4/22/2015 6/03/2015 6/09/2015 6/10/2015}} |
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[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
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EPID L-2017-LLA-0259) ML18179A4672018-07-30030 July 2018 FENOC-Beaver Valley Power Station, Unit No. 1 and 2; Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1 - Issuance of Amendments Request to Adopt TSTF-529, Clarify Use and Application Rules ML18157A0842018-06-25025 June 2018 Issuance of Amendment No. 181 Concerning Adoption of TS Task Force Traveler TSTF-306-A, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration (CAC No. MG0150; EPID L-2017-LLA-0286) ML18110A1332018-05-16016 May 2018 Unit No. 1 - Issuance of Amendment No. 180 Concerning Changes to Technical Specifications Regarding Implementation of the Alternative Source Term (CAC No. MF9818; EPID L-2017-LLA-0241) ML17325B6902018-01-18018 January 2018 Issuance of Amendment Concerning Adoption of Technical Specification Task Force (TSTF) Traveler 400-A, Revision 1, Clarify SR on Bypass of DG Automatic Trips (CAC No. MF9855, EPID L-2017-LLA-0246) (L-17-089) ML17257A0982017-10-19019 October 2017 Issuance of Amendment Concerning Revisions to the Environmental Protection Plan (CAC No. MF9652; EPID L-7017-LLA-0226) (L-17-043) ML17163A3542017-06-29029 June 2017 Issuance of Amendment Concerning Adoption of Tstf-501, Revision 1, Relocation of Diesel Fuel and Lube Oil Volume Values to Licensee Control (CAC No. MF8693) (L-16-236) ML17139C3722017-06-19019 June 2017 Issuance of Amendment Concerning Reduction of Steam Dome Pressure Value Specified in Technical Specification 2.1.1 (CAC No. MF8760) (L-16-179) ML17081A5092017-05-11011 May 2017 ISFSI, Davis-Besse ISFSI, Perry Nuclear Power Plant, Perry Nuclear Power Plant ISFSI - Issuance of Amendments Re. Application to Revise Technical Specifications to Adopt TSTF-545 Revision 3 ML17033A0142017-02-16016 February 2017 Issuance of Amendment Concerning Revision to Technical Specifications to Permit Installation of Upper Containment Pool Gate During Modes 1, 2, and 3 (CAC No. MF7476) (L-16-083) ML16158A3312016-09-14014 September 2016 Issuance of Amendment Concerning Revision to the Perry Nuclear Power Plant Emergency Plan ML16130A5362016-05-31031 May 2016 Issuance of Conforming Amendment Related to the Direct License Transfer of the Facility Operating License NPF-58 ML15307A3492016-02-23023 February 2016 Issuance of Amendment Concerning Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control (CAC No. MF3720) (L-14-106) ML15201A5292015-08-17017 August 2015 Issuance of Amendment Concerning Technical Specification 3.8.4 DC Sources - Operating (TAC No. MF5298) (L-14-271) ML15160A0282015-06-23023 June 2015 Issuance of Amendment Concerning Adoption of TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (TAC No. MF4791)(L-14-137) ML15141A4822015-06-12012 June 2015 Issuance of Amendment Concerning Changes to Pressure Temperature Curves (TAC No. MF4351)(L-14-150) ML15133A5022015-06-10010 June 2015 Issuance of Amendment Concerning Extension of Cyber Security Milestone 8 (TAC No. MF5557)(L-14-421) ML15075A1392015-03-30030 March 2015 Issuance of Amendment Concerning Full Implementation of Alternative Source Term (TAC No. MF3197) (L-13-306) L-14-325, Issuance of Amendment Concerning Safety Limit Critical Power Ratio Values (TAC No. MF5007)(L-14-325)2015-03-27027 March 2015 Issuance of Amendment Concerning Safety Limit Critical Power Ratio Values (TAC No. MF5007)(L-14-325) ML15075A0912015-03-27027 March 2015 Issuance of Amendment Concerning Safety Limit Critical Power Ratio Values (TAC No. MF5007)(L-14-325) ML14205A6192014-08-29029 August 2014 Amendments to Indemnity Agreements (TAC MF0701, MF0702, MF0703, and MF0704) ML13136A1432013-05-16016 May 2013 Nucelar Power Plant, Unit 1 - Re-Issuance of Amendment Regarding Adoption of TSTF-275 and TSTF-300 ML13051B1442013-05-0606 May 2013 Issuance of Amendment Regarding Adoption of TSTF-275, Clarify Requirement for EDG Start Signal on RPV Level - Low, Low, Low During RPV Cavity Flood-Up, and TSTF-300 ML13017A4312013-04-18018 April 2013 Issuance of Amendment Revise Technical Specification 3.10.1, Inservice Leak, and Hydrostatic Testing Operation ML12221A4132012-10-0202 October 2012 Issuance of Amendments Change of the Name of a Owner Licensee to Firstenergy Nuclear Generation, LLC 2024-03-01
[Table view] Category:Safety Evaluation
MONTHYEARML24225A0512024-09-13013 September 2024 Issuance of Alternative Request VR-9, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML23353A0012024-02-21021 February 2024 – Issuance of Amendment No. 202 to Adopt TSTF-276, Revision 2, Revise DG Full Load Rejection Test ML23292A2972023-11-17017 November 2023 Table of Contents LAR (L-2023-LLA-0111) ML23237B4302023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public) ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments ML23172A2852023-08-23023 August 2023 Safety Evaluation Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimate ML22284A1442023-02-0303 February 2023 Issuance of Amendment No. 200 Regarding the Revision of Methodology Used for Flood Hazard Analysis ML22348A1372023-01-0505 January 2023 Issuance of Amendment No. 199 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML22252A2212022-09-30030 September 2022 Authorization and Safety Evaluation for Alternative Request IR-063 ML22210A0102022-09-16016 September 2022 Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements ML22187A2592022-07-12012 July 2022 Issuance of Relief Proposed Alternative Request Vr 12, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML22136A1132022-06-21021 June 2022 Issuance of Relief Proposed Alternative Requests VR-10, Revision 0, and VR-11, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval (EPIDs L-2021-LLR-0096; L-2021-LLR-0097) ML21322A2602022-01-10010 January 2022 Issuance of Amendment No. 197 Regarding the Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystem, and TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Oper ML21270A1122021-11-16016 November 2021 Issuance of Amendment No. 196 Regarding Changes to the Emergency Plan ML21271A0782021-11-0505 November 2021 Issuance of Amendment No. 195 Regarding the Adoption of TSTF-230, Add New Condition B to LCO 3.6.2.3, 'Rhr Suppression Pool Cooling' ML21158A2122021-07-12012 July 2021 Issuance of Amendment No. 194 Regarding the Adoption of TSTF-002, Relocate the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control ML21123A2172021-05-0505 May 2021 Issuance of Relief Requests Vr 4, Revision 0, Vr 6, Revision 0, and Vr 8, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval (EPIDs L 2021 Llr 0010, L 2021 Llr 0011, L 2021 Llr 0012 COVID-19 ML21123A2892021-05-0404 May 2021 Issuance of Relief Request Vr 7, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML21081A0702021-04-27027 April 2021 Issuance of Amendment No. 193 Regarding the Adoption of TSTF-500, DC Electrical Rewrite - Update to TSTF-360 ML21063A2532021-03-0505 March 2021 Issuance of Relief Request SR-2, Revision 0, from Certain Requirements of the ASME OM Code (EPID L-2021-LLR-0005 (COVID-19)) ML21063A1572021-03-0404 March 2021 Safety Evaluation for Alternative Request SR-2, Revision 0 Related to one-time Extension Snubbers Testing to ASME OM Code for the Fourth 10-year Inservice Interval at Perry Nuclear Power Plant Unit 1, Docket Nos. 50-440 ML21035A1702021-03-0101 March 2021 Issuance of Amendment No. 192, Regarding Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20363A0062021-01-29029 January 2021 Issuance of Relief Proposed Alternative Request Associated with Fourth 10-Year Inservice Inspection Interval ML20311A6582020-11-10010 November 2020 Issuance of Relief Proposed Alternative Request Associated with Fourth Ten Year Interval Inservice Inspection Interval ML20279A4402020-10-0808 October 2020 Energy Harbor Fleet-Beaver Valley Power Station; Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant - Request to Use a Provision of a Later Edition of the ASME Engineers Boiler and Pressure Vessel Code, Section XI ML20266G2652020-09-24024 September 2020 Correction Letter for Relief Request IR-062 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval ML20252A0262020-09-18018 September 2020 Relief Request IR-062 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval ML20189A0032020-07-10010 July 2020 Relief Request PR-3 for Fourth 10-Year Pump and Valve Inservice Testing Program ML20154K7002020-07-0909 July 2020 Issuance of Amendment No. 190 Regarding Fire Protection Program Licensing Basis ML20099A1022020-05-22022 May 2020 Issuance of Amendment No. 188, Regarding Revision to Technical Specifications to Adopt TSTF-564, Safety Limit (Minimum Critical Power Ratio) MCPR ML20118C1672020-05-22022 May 2020 Issuance of Amendment No. 189, Regarding Special Heavy Lifting Device Nondestructive Examination Frequency ML19305B1312019-12-0202 December 2019 Firstenergy Nuclear Operating Company - Enclosure 6, Non-Proprietary Safety Evaluation, Direct and Indirect Transfer of Licenses and Draft Conforming Amendments for Beaver Valley Units 1 and 2, Davis-Besse Unit 1, and Perry Unit 1 ML19163A0232019-08-14014 August 2019 Issuance of Amendment No. 186 Concerning Changes to Emergency Response Organization ML19028A0302019-04-11011 April 2019 FENOC - Beaver Valley Power Station, Unit 1 & 2; Davis-Besse Nuclear Power Station Unit 1; and Perry Nuclear Power Plant Unit 1 - Approval of Certified Fuel Handler Training and Retraining Program ML19072A0122019-03-15015 March 2019 Correction to License Amendment No. 184 Related to Adoption of Technical Specification Task Force Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control ML19072A0852019-03-15015 March 2019 Correction to Request for Alternatives Related to Inservice Testing Program for the Fourth 10 Year Inservice Testing Interval ML19029A0902019-02-25025 February 2019 Request for Alternatives Related to Inservice Testing Program for the Fourth 10-Year Inservice Testing Interval (EPID Nos. L-2018-LLR-0092, 0093, 0094, 0095, and 0096) ML19022A3242019-02-25025 February 2019 Issuance of Amendment No. 185 Concerning Extension of Containment Leakage Test Frequency ML19037A0412019-02-25025 February 2019 Request for Alternative to Use ASME Code Case N-831 ML18292A8162018-12-12012 December 2018 Issuance of Amendment No. 184 Concerning Adoption of Technical Specification Task Force Traveler 542, Rev. 2, Reactor Pressure Vessel Water Inventory Control ML18199A2802018-08-23023 August 2018 Issuance of Amendment No. 183, Adopt Technical Specification Task Force Traveler TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement ML18179A4672018-07-30030 July 2018 FENOC-Beaver Valley Power Station, Unit No. 1 and 2; Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1 - Issuance of Amendments Request to Adopt TSTF-529, Clarify Use and Application Rules ML18157A0842018-06-25025 June 2018 Issuance of Amendment No. 181 Concerning Adoption of TS Task Force Traveler TSTF-306-A, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration (CAC No. MG0150; EPID L-2017-LLA-0286) ML18110A1332018-05-16016 May 2018 Unit No. 1 - Issuance of Amendment No. 180 Concerning Changes to Technical Specifications Regarding Implementation of the Alternative Source Term (CAC No. MF9818; EPID L-2017-LLA-0241) ML18023A6252018-01-29029 January 2018 Approval of Alternative to Use BWRVIP Guidelines in Lieu of Certain ASME Code Requirements (CAC No. MG0149; EPID 2017-LLR-0112) (L-17-183) ML18004A1222018-01-22022 January 2018 FENOC-Beaver Valley, Davis-Besse, and Perry - Alternative for the Use of ASME Code Case N-513-4 (CAC Nos. MG0120, MG0121, MG0122, and MG0123; EPID L-2017-LLR-0088) ML17325B6902018-01-18018 January 2018 Issuance of Amendment Concerning Adoption of Technical Specification Task Force (TSTF) Traveler 400-A, Revision 1, Clarify SR on Bypass of DG Automatic Trips (CAC No. MF9855, EPID L-2017-LLA-0246) (L-17-089) ML17257A0982017-10-19019 October 2017 Issuance of Amendment Concerning Revisions to the Environmental Protection Plan (CAC No. MF9652; EPID L-7017-LLA-0226) (L-17-043) ML17270A0302017-10-16016 October 2017 Approval of Alternative to Use ASME Code Case N-513-4 for Repair of Emergency Service Water System Piping (CAC No. MG0130; EPID L-2017-LLR-0080)(L-17-278) ML17193A3822017-07-18018 July 2017 Correction to Safety Evaluation for License Amendment No. 177 2024-09-13
[Table view] Category:Technical Specifications
MONTHYEARML23353A0012024-02-21021 February 2024 – Issuance of Amendment No. 202 to Adopt TSTF-276, Revision 2, Revise DG Full Load Rejection Test ML22210A0102022-09-16016 September 2022 Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements ML21361A2172021-12-20020 December 2021 Supplemental Information for Revision 22 to Updated Safety Analysis Report, Revision 13 to Technical Specification Bases TS Bases ML21271A0782021-11-0505 November 2021 Issuance of Amendment No. 195 Regarding the Adoption of TSTF-230, Add New Condition B to LCO 3.6.2.3, 'Rhr Suppression Pool Cooling' ML21307A1762021-10-28028 October 2021 2 to Updated Safety Analysis Report, Chapter 16, Technical Specifications ML21158A2122021-07-12012 July 2021 Issuance of Amendment No. 194 Regarding the Adoption of TSTF-002, Relocate the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control ML21035A1702021-03-0101 March 2021 Issuance of Amendment No. 192, Regarding Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20099A1022020-05-22022 May 2020 Issuance of Amendment No. 188, Regarding Revision to Technical Specifications to Adopt TSTF-564, Safety Limit (Minimum Critical Power Ratio) MCPR ML17325B6902018-01-18018 January 2018 Issuance of Amendment Concerning Adoption of Technical Specification Task Force (TSTF) Traveler 400-A, Revision 1, Clarify SR on Bypass of DG Automatic Trips (CAC No. MF9855, EPID L-2017-LLA-0246) (L-17-089) ML17305A2132017-10-23023 October 2017 Perry Nuclear Power Plant Revision 20 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML15307A3492016-02-23023 February 2016 Issuance of Amendment Concerning Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control (CAC No. MF3720) (L-14-106) ML15243A1532015-09-0202 September 2015 Correction of Typographical Error Incurred During Prior License Amendment No. 162 ML15201A5292015-08-17017 August 2015 Issuance of Amendment Concerning Technical Specification 3.8.4 DC Sources - Operating (TAC No. MF5298) (L-14-271) ML15160A0282015-06-23023 June 2015 Issuance of Amendment Concerning Adoption of TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (TAC No. MF4791)(L-14-137) ML15141A4822015-06-12012 June 2015 Issuance of Amendment Concerning Changes to Pressure Temperature Curves (TAC No. MF4351)(L-14-150) ML15133A5022015-06-10010 June 2015 Issuance of Amendment Concerning Extension of Cyber Security Milestone 8 (TAC No. MF5557)(L-14-421) L-11-338, Supplemental Information for License Amendment Request Regarding Offsite Electric Power System Acceptability Until December 12, 20112011-10-17017 October 2011 Supplemental Information for License Amendment Request Regarding Offsite Electric Power System Acceptability Until December 12, 2011 L-11-333, Supplemental Information for License Amendment Request Regarding Offsite Electric Power System Acceptability Until December 12, 20112011-10-13013 October 2011 Supplemental Information for License Amendment Request Regarding Offsite Electric Power System Acceptability Until December 12, 2011 L-11-322, License Amendment Request Regarding Use of a Delayed Access Circuit as a Required Offsite Circuit in Technical Specification 3.8.1, AC Sources - Operating.2011-10-0303 October 2011 License Amendment Request Regarding Use of a Delayed Access Circuit as a Required Offsite Circuit in Technical Specification 3.8.1, AC Sources - Operating. ML1116608152011-06-16016 June 2011 Correction Letter License Amendment No. 157 L-10-201, License Amendment Request to Revised Technical Specification 3.1.4, Control Rod Scram Times, to Incorporate TSTF-460, Revision 02010-12-15015 December 2010 License Amendment Request to Revised Technical Specification 3.1.4, Control Rod Scram Times, to Incorporate TSTF-460, Revision 0 ML1029804462010-10-21021 October 2010 License Amendment Request to Modify Technical Specification 2.1.1, Reactor Core Sls, to Incorporate Revised Safety Limit Minimum Critical Power Ratio Values L-09-025, ISFSI, and Perry, Application for Technical Specification (TS) Change for Adoption of TSTF-511 Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.2009-03-25025 March 2009 ISFSI, and Perry, Application for Technical Specification (TS) Change for Adoption of TSTF-511 Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. ML0824608772008-08-28028 August 2008 Tech Spec Page for Amendment 150 TSTF-476, Improved Banked Position Withdrawal Sequence Control Rod Insertion Process, Per the Consolidated Line Item Improvement Process ML0817503002008-06-19019 June 2008 TS Pages - Issuance of Amendment Revise TSs 3.6.1, 3.6.4 and 3.6.5 ML0811905752008-04-25025 April 2008 TS Pages - Issuance of Amendment No. TSTF-448, Revision 3, Control Room Habitability. ML0726808522007-09-18018 September 2007 License Amendment Request Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0725505472007-09-0505 September 2007 License Amendment Request to Revise Technical Specification 3.6.1, 3.6.4, and 3.6.5 for Containment and Drywell Isolation Device ML0721102792007-07-30030 July 2007 Tech Spec Pages for Amendment 147 to Clarify Technical Specification Requirements Related to Annulus Exhaust Gas Treatment (Aegt) System ML0719402902007-07-12012 July 2007 Technical Specifications, Issuance of Amendment ASTM Standards for Fuel Oil Testing ML0717704662007-06-22022 June 2007 Tech Spec Page for Amendment 145 Scram Discharge Volume Vent and Drain Valves ML0717202522007-06-14014 June 2007 Beaver and Perry, Technical Specifications, Issuance of Amendments Modification of Technical Specification Requirements for Inoperable Snubbers ML0713403922007-05-0909 May 2007 Technical Specifications (Ts), Revise TS 5.5.7, Ventilation Filter Test Program, to Correct Referenced Flow Units ML0712005032007-04-30030 April 2007 Tech Spec Pages for Amendment 142 Regarding Emergency Diesel Generator Surveillance Testing Voltage and Frequency Limits ML0712102912007-04-27027 April 2007 Technical Specifications, Issuance of Amendment Revise TS to Change the Frequency of the Mode 5 Intermediate Range Monitoring Instrumentation Channel Functional Test L-06-172, Units 1 and 2, License Amendment Requests to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2007-01-11011 January 2007 Units 1 and 2, License Amendment Requests to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process ML0700904852006-12-29029 December 2006 Application for a Technical Specification Improvement to Revise Technical Specification 3.1.8, Scram Discharge Volume (SDV) Vent and Drain Valves, Using the Consolidated Line Item Improvement Process ML0629704472006-10-13013 October 2006 License Amendment Request to Eliminate Unnecessary Reporting Requirements in the Operating License and the Administrative Controls Section of the Technical Specifications ML0618700962006-06-30030 June 2006 Technical Specification, Modifies the Existing TS 3.3.1.3, Oscillation Power Range Monitor (OPRM) Instrumentation, Surveillance Requirement 3.3.1.3.5 ML0615903492006-06-0101 June 2006 License Amendment Request - Revise Mode 3 Hot Shutdown Requirements to Add a Note Addressing Situations When Both Residual Heat Removal (RHR) Shutdown Cooling Subsystems Are Inoperable ML0615903292006-06-0101 June 2006 License Amendment Request - Revise Mode 4 Residual Heat Removal Shutdown Cooling Requirements to Add a Default Condition Addressing Situations When Condition a Cannot Be Met within Its Completion Time ML0605404392006-02-14014 February 2006 Amendment Request to Revise Technical Specification 3.3.1.1 Intermediate Range Monitoring Instrumentation Mode 5 Channel Functional Testing Surveillance Frequency from 7 Days to 31 Days ML0605306202006-02-10010 February 2006 License Amendment Request to Revise Required Action B.1 in the Emergency Core Cooling System Instrumentation Technical Specification to Be Consistent with the Improved Standard Technical Specifications ML0529903232005-10-14014 October 2005 Submittal of Technical Specification Bases, Revision 5 ML0522902522005-08-16016 August 2005 Tech Spec Pages for Amendment 136 Elimination of Monthly Operating Reports and Occupational Radiation Exposure Reports ML0512501942005-04-19019 April 2005 4/19/05, Perry - TS Pages - Issuance of Amendment Elimination of Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process ML0509600872005-03-31031 March 2005 Tech Spec Pages for Amendment 134 Single Recirculation Loop Operation ML0504505712005-02-10010 February 2005 Tech Spec Pages for Amendment 133 Testing of Safety/Relief Valves ML0503503642005-02-0303 February 2005 Technical Specification Pages Revision of the Minimum Critical Power Ratio Safety Limit ML0419401992004-07-0909 July 2004 Technical Specifications, Issuance of Amendment Regarding Primary Containment and Drywell Isolation Instrumentation to Increase the Analytical Limit for Detected Temperature 2024-02-21
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 10, 2015 Mr. Ernest J. Harkness Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 - ISSUANCE OF AMENDMENT CONCERNING EXTENSION OF CYBER SECURITY MILESTONE 8 (TAC NO. MF5557)(L-14-421)
Dear Mr. Harkness:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 167 to Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant (PNPP), Unit No. 1. This amendment extends the completion date for full implementation of PNPP Cyber Security Plan (CSP) in response to FirstEnergy Nuclear Operating Company's (FENOC's) application dated January 9, 2015, as supplemented by a letter dated May 6, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML15009A264 and ML15127A202, respectively)). Portions of the letter dated January 9, 2015, contain sensitive unclassified non-safeguards information and those portions are withheld from public disclosure in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390(d)(1 ).
It should be noted that the NRC staff does not regard the CSP milestone implementation dates as regulatory commitments that can be changed unilaterally by a licensee, particularly in light of the regulatory requirement at 10 CFR 73.54. Thus, any subsequent changes that FE NOC may request to the NRG-approved CSP implementation schedule will be submitted for prior NRC approval under 10 CFR 50.90.
E. Harkness A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely, Kimberly J. Green, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosures:
- 1. Amendment No. 167 to NPF-58
- 2. Safety Evaluation cc w/encls: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP.
OHIO EDISON COMPANY DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 167 License No. NPF-58
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A The application for license filed by FirstEnergy Nuclear Operating Company, et al., (the licensee, FE NOC) dated January 9, 2015, as supplemented by a letter dated May 6, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 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 by changes to the Facility Operating License as indicated in the attachment to this license amendment, and paragraph 2.E of Facility Operating License No. NPF-58 is hereby amended to read as follows:
E. FENOC 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 (61 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Perry Nuclear Power Plant Physical Security Plan" Revision 2, submitted by letter dated May 18, 2006.
FENOC 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 FENOC CSP was approved by License Amendment No. 158, and amended by License Amendment No. 167.
- 3. This license amendment is effective as of its date of its issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULA TORY COMMISSION
. el n, f Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License Date of Issuance: June 1O, 2015
ATTACHMENT TO LICENSE AMENDMENT NO. 167 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 Replace the following page of the Facility Operating License with the attached revised page.
The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove License NPF-58 License NPF-58 Page 6 Page 6
D. FENOC is exempted from: 1) the requirements of Section lll.D.2(b)(ii), containment airlock testing requirements, Appendix J to 10 CFR Part 50, due to the special circumstance described in Section 6.2.6 of SER Supplement No. 7 authorized by 10 CFR 50.12(a)(2)(iii) and 2) the requirements of Section IV.F., Full Participation Exercise, of Appendix E to 10 CFR Part 50, due to the special circumstance described in the Exemption dated November 6, 1986. These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The 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 the Commission.
E. FE NOC 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 (61 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Perry Nuclear Power Plant Physical Security Plan" Revision 2, submitted by letter dated May 18, 2006.
FE NOC 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 FENOC CSP was approved by License Amendment No. 158, and amended by License Amendment No.167.
F. Deleted G. The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1964, as amended, to cover public liability claims.
Amendment No. 167
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 167 TO FACILITY OPERATING LICENSE NO. NPF-58 FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP.
OHIO EDISON COMPANY PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-440
1.0 INTRODUCTION
By application dated January 9, 2015, as supplemented by a letter dated May 6, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession Nos.
ML15009A265 and ML15127A202, respectively), the FirstEnergy Nuclear Operating Company (FENOC, the licensee) requested a change to the facility operating license (FOL) for Perry Nuclear Plant, Unit 1 (PNPP). The proposed change would revise the date of Cyber Security Plan (CSP) Implementation Schedule Milestone 8, and would accordingly modify the license condition in Paragraph 2.E of the FOL.
The supplemental letter dated May 6, 2015, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination.
2.0 REGULATORY EVALUATION
2.1 Background The NRC staff reviewed and approved the licensee's existing CSP implementation schedule in a letter dated August 29, 2011 (ADAMS Accession No. ML111920382), concurrent with the incorporation of the CSP into the facility's current licensing basis. Milestone 8 of the CSP implementation schedule concerns the full implementation of the CSP.
2.2 Regulations Section 73.54(a) to Title 10 to the Code of Federal Regulations (10 CFR) states that licensees must 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 described in 10 CFR 73.1. Pursuant to 10 CFR 73.54(a)(1 ), licensees must protect digital Enclosure 2
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.
As further specified in 10 CFR 73.54(a)(2), these systems and networks must be protected from cyber attacks that would adversely impact the integrity or confidentiality of data and software; deny access to systems, services, or data; and adversely impact the operation of systems, networks, and associated equipment. Additionally, 10 CFR 73.54 requires licensees to submit a proposed implementation schedule, and further requires that implementation of the licensee's cyber security program be consistent with the approved schedule.
It should be noted that 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." Thus all subsequent changes to the NRC-approved CSP implementation schedule will require submittal for prior NRC approval under 10 CFR 50.90.
Section 13.6.6, of NUREG-0800, provides the review criteria for CSP security plans. In a letter dated October 24, 2013 (ADAMS Accession No. ML13295A467), the NRC staff listed criteria to consider during evaluations of licensees' requests to postpone their cyber security program implementation date (commonly known as Milestone 8). The criteria in the guidance are as follows:
- 1. Identification of the specific requirement or requirements of the cyber security plan that the licensee needs additional time to implement.
- 2. Detailed justification that describes the reason the licensee requires additional time to implement the specific requirement or requirements identified.
- 3. A proposed completion date for Milestone 8 consistent with the remaining scope of work to be conducted and the resources available.
- 4. An evaluation of the impact that the additional time to implement the requirements will have on the effectiveness of the licensee's overall cyber security program in the context of milestones already completed.
- 5. A description of the licensee's methodology for prioritizing completion of work for critical digital assets associated with significant safety consequences and with reactivity effects in the balance of plant.
- 6. A discussion of the licensee's cyber security program performance up to the date of the license amendment request.
- 7. A discussion of cyber security issues pending in the licensee's corrective action program.
- 8. A discussion of modifications completed to support the cyber security program and a discussion of pending cyber security modifications.
3.0 TECHNICAL EVALUATION
3.1 Extension Request As discussed above, on August 29, 2011, the NRC staff approved the licensee's CSP implementation schedule, which was based on an NEI [Nuclear Energy Institute] template submitted in a letter dated February 28, 2011 (ADAMS Accession No. ML110600206). In Section 2.0 of the January 9, 2015, submittal, the licensee indicated completion of the first seven milestones of the Cyber Security Implementation Plan as of December 31, 2012. It was identified that on-going monitoring and time-based periodic actions provide continuing program performance monitoring. This monitoring combined with these interim milestones, ensure that PNPP is, and will continue to be, secure; and that digital computer and communication systems, and networks are adequately protected against cyber-attacks during implementation of the full program.
Milestone 8 of the licensee's CSP requires FENOC to fully implement the CSP by July 1, 2015.
FENOC requested to change the Milestone 8 completion date to December 31, 2017, to allow for support of required design changes and provide additional time to appropriately prioritize work. The licensee identified that additional time would be needed to implement certain activities in Section 3.1, "Analyzing Digital Computer Systems and Networks and Applying Cyber Security Control," of the CSP. More specifically, the licensee indicated that additional time would be needed to complete critical digital asset (CDA) assessment work which is resource intensive, as well as remediation activities, which must be carefully considered, change management challenges, and training on new programs, processes and procedures.
In Section 3.0 of the January 9, 2015, submittal, the licensee noted there is a large volume of effort associated with documentation of the assessment and analysis for the 1300 CDAs given the amount of rework that has been identified. The licensee indicates that new tasks are being added to normal maintenance activities, which require significant verification, analysis and testing to ensure no adverse impact to plant equipment. Additionally, the CDA assessment process requires careful consideration of remediation activities given that security controls modifications are unique and new to the plant and suppliers and proposed modifications to the plant have to be evaluated to ensure that the modifications do not adversely impact plant safety and operation.
The licensee stated that its methodology for prioritizing Milestone 8 activities is centered on considerations of safety, security, emergency preparedness (EP), and balance of plant (BOP)
(continuity of power) consequences. The methodology is based on defense in depth, installed configuration of the CDA, and susceptibility to commonly identified threat vectors. Prioritization for CDA assessment begins with safety-related CDAs and continues through the lower priority nonsafety and EP CDAs:
- important to safety CDAs (including BOP CDAs that directly impact continuity of power) and control system CDAs;
- physical security CDAs; and,
The licensee stated PNPP uses the existing corrective action program (CAP) to document all cyber issues in order to trend, correct, and improve the cyber security program. Conditions adverse to quality are captured in the CAP database and tracked from initiation through closure. Adverse trends are monitored for program improvement and addressed via the CAP process.
3.2 NRC Staff Evaluation The NRC staff has evaluated the licensee's application using the regulatory requirements and the guidance identified above. The NRC staff's evaluation is below:
The NRC staff finds that the actions the licensee noted as being required to implement CSP Section 3, Analyzing Digital Computer Systems and Networks, and Section 4, Establishing, Implementing and Maintaining the Cyber Security Program, are reasonable as discussed below.
The licensee indicated that completion of the activities associated with the CSP, as described in Milestones 1 through 7 and completed prior to December 31, 2012, provide a high degree of protection against cyber security attacks. It detailed activities completed for each milestone, and provided details about the completed milestones and elements. The NRC staff finds that the licensee's site is much more secure after implementation of Milestones 1 through 7 because the activities the licensee completed mitigate the most significant cyber attack vectors for the most significant CDAs.
The licensee stated that additional time is needed to conduct modifications and change management planning activities and execution. The staff recognizes that CDA assessment work is much more complex and resource intensive than originally anticipated, in part, due to the NRC expanding the scope of the cyber security requirements to include balance of plant.
As a result, the licensee has a large number of additional tasks not originally considered when developing its CSP implementation schedule. The staff finds that the licensee's request to delay full implementation of the CSP until December 31, 2017 is reasonable given the complexity and volume of the remaining unanticipated work.
The licensee stated that changing the completion date of Milestone 8 will provide sufficient time to methodically plan and schedule the implementation of the required design changes as well as provide time to prioritize work activities to avoid rework and scope changes. The NRC staff recognizes that CDA assessment work is much more complex and resource intensive than originally anticipated and that the licensee has a large number of additional tasks not originally considered when developing its CSP implementation schedule. The licensee has provided sufficient information to conclude that there are implementation issues with the large number of CDAs and the need to address security controls for each. Given this information, the NRC staff finds that the licensee's request to delay full implementation of the CSP until December 31, 2017 is reasonable given the complexity and volume of the remaining unanticipated work.
Therefore, the NRC staff finds that implementation of Milestones 1 through 7 provides significant protection against cyber attacks in the interim; that the licensee's explanation of the need for additional time is compelling, and that it is acceptable for FENOC to delay full implementation of the CSP until December 31, 2017. The NRC staff also finds 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.
3.3 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 for the following reasons: (i) the licensee's implementation of Milestones 1 through 7 provides mitigation for significant cyber attack vectors for the most significant CDAs as discussed in the staff evaluation above and (ii) the scope of the work required to come into full compliance with the CSP implementation schedule was much more complicated than anticipated and not reasonably foreseeable when the CSP implementation schedule was originally developed.
3.4 Revision to License Condition In its January 9, 2015 application, the licensee proposed to modify the license condition in Paragraph 2.E of its FOL to reflect the NRC staff's approval of an extension of the implementation date for completion of the CSP.
The license condition in Paragraph 2.E of the operating license is modified as follows:
E. FENOC 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 (61 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Perry Nuclear Power Plant Physical Security Plan," Revision 2, submitted by letter dated May 18, 2006.
FENOC 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 FENOC CSP was approved by License Amendment No. 158, and amended by License Amendment No. 167.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the appropriate Ohio State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
This licensing action is an amendment to a 10 CFR Part 50 license that relates solely to safeguards matters, and does not involve any significant construction impacts. This amendment is an administrative change to extend the date by which the licensee must have its cyber security plan fully implemented. Accordingly, this licensing action meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(12). The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding (80 FR 18658; April 7, 2015). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
6.0 CONCLUSION
The NRC staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: J. Rycyna, NSIR Date of issuance: June 1O, 2015
ML15133A502
- via memo **via email OFFICE LPL3-2/PM LPL3-2/LA NSIR/CSD* OGC- NLO LPL3-1/BC LPL3-1/PM NAME EBrown SRohrer RFelts JHull** DPelton KGreen DATE 5/14/2015 5/14/2015 4/22/2015 6/03/2015 6/09/2015 6/10/2015