ML16008B072

Issuance of Amendments Regarding Technical Specifications for Facility Staff Qualifications for Licensed Operators

ML16008B072
Person / Time
Site:	Turkey Point
Issue date:	02/25/2016
From:	Audrey Klett Plant Licensing Branch II
To:	Nazar M Nextera Energy
References
CAC MF6799, CAC MF6800
Download: ML16008B072 (16)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 25, 2016 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division NextEra Energy P.O. Box 14000 Juno Beach, FL 33408-0420

SUBJECT:

TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 - ISSUANCE OF AMENDMENTS REGARDING TECHNICAL SPECIFICATIONS FOR FACILITY STAFF QUALIFICATIONS FOR LICENSED OPERATORS (CAC NOS. MF6799 AND MF6800)

Dear Mr. Nazar:

The U.S. Nuclear Regulatory Commission (NRC or the Commission) has issued the enclosed Amendment No. 268 to Renewed Facility Operating License (RFOL) No. DPR-31 and Amendment No. 263 to RFOL No. DPR-41 for the Turkey Point Nuclear Generating Unit Nos. 3 and 4, respectively. The amendments change Technical Specification (TS) 6.3.1.3 in response to the application from Florida Power & Light Company dated October 12, 2015.

The amendments revise the qualification requirements for licensed operators in TS 6.3.1.3 by removing the requirement to meet American National Standards Institute (ANSI)

Standard 3.1-1981, "Selection, Qualification and Training of Personnel for Nuclear Power Plants," and ANSI N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel," and instead requiring compliance only with Title 10 of the Code of Federal Regulations, Part 55, "Operators' Licenses."

M. Nazar The NRC staff's safety evaluation of the amendments is enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, Audrey L. Klett, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-250 and 50-251

Enclosures:

1. Amendment No. 268 to DPR-31

2. Amendment No. 263 to DPR-41

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

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT NUCLEAR GENERATING UNIT NO. 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 268 Renewed License No. DPR-31

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

A. The application for amendment by Florida Power & Light Company (the licensee) dated October 12, 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 Title 10 of the Code of Federal Regulations (10 CFR),

Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Operating License and Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Renewed Facility Operating License No. DPR-31 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 2 6 aare hereby incorporated into this renewed license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Benjamin G. Beasley, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Operating License and Technical Specifications Date of Issuance: February 2 s, 2o1 6

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT NUCLEAR GENERATING UNIT NO. 4 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 263 Renewed License No. DPR-41

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

A. The application for amendment by Florida Power & Light Company (the licensee) dated October 12, 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 Title 10 of the Code of Federal Regulations (10 CFR),

Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Operating License and Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Renewed Facility Operating License No. DPR-41 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 2 6 3 are hereby incorporated into this renewed license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULA TORY COMMISSION Benjamin G. Beasley, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Operating License and Technical Specifications Date of Issuance: February 2 5 , 2O1 6

ATIACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 268 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-31 AMENDMENT NO. 263 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-41 DOCKET NOS. 50-250 AND 50-251 Replace page 3 of Renewed Facility Operating License DPR-31 with the attached page 3. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Replace page 3 of Renewed Facility Operating License DPR-41 with the attached page 3. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Replace the following page of the Appendix A Technical Specifications with the attached page.

The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Insert 6-4 6-4

3 E. Pursuant to the Act and 10 CFR Parts 40 and 70 to receive, possess, and use at any time 100 milligrams each of any source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactively contaminated apparatus; F. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of Turkey Point Units Nos. 3 and 4.

3. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect, and is subject to the additional conditions specified below:

A. Maximum Power Level The applicant is authorized to operate the facility at reactor core power levels not in excess of 2644 megawatts (thermal).

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 268 are hereby incorporated into this renewed license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

C. Final Safety Analysis Report The licensee's Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d), as revised on November 1, 2001, describes certain future inspection activities to be completed before the period of extended operation.

The licensee shall complete these activities no later than July 19, 2012.

The Final Safety Analysis Report supplement as revised on November 1, 2001, described above, shall be included in the next scheduled update to the Final Safety Analysis Report required by 10 CFR 50.71(e)(4), following the issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs described in such supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

Unit 3 Renewed License No. DPR-31 Amendment No. 268

3 E. Pursuant to the Act and 10 CFR Parts 40 and 70 to receive, possess, and use at any time 100 milligrams each of any source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactively contaminated apparatus; F. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of Turkey Point Units Nos. 3 and 4.

3. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect, and is subject to the additional conditions specified below:

A. Maximum Power Level The applicant is authorized to operate the facility at reactor core power levels not in excess of 2644 megawatts (thermal).

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 263 are hereby incorporated into this renewed license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

C. Final Safety Analysis Report The licensee's Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on November 1, 2001, describes certain future inspection activities to be completed before the period of extended operation.

The licensee shall complete these activities no later than April 10, 2013.

The Final Safety Analysis Report supplement as revised on November 1, 2001, described above, shall be included in the next scheduled update to the Final Safety Analysis Report required by 10 CFR 50.71(e)(4), following the issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs described in such supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

Unit 4 Renewed License No. DPR-41 Amendment No. 263

ADMINISTRATIVE CONTROLS 6.2.3 SHIFT TECHNICAL ADVISOR FUNCTION 6.2.3.1 An individual shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit and the opposite unit. This individual shall meet the qualifications specified by the 1985 NRC Policy Statement on Engineering Expertise on Shift.

6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for 6.3.1.1 The Health Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

6.3.1.2 The Operations Manager whose requirement for a Senior Reactor Operator License is as stated in Specification 6.2.2.i.

6.3.1.3 The licensed operators, who shall comply only with the requirements of 10 CFR 55.

6.3.1.4 The Multi-Discipline Supervisors who shall meet or exceed the following requirements:

a. Education: Minimum of a high school diploma or equivalent

b. Experience: Minimum of four years of related technical experience, which shall include three years power plant experience of which one year is at a nuclear power plant

c. Training: Complete the Multi-Discipline Supervisor training program 6.3.2 When the Health Physics Supervisor does not meet the above requirements, compensatory action shall be taken which the Plant Nuclear Safety Committee determines and the NRC office of Nuclear Reactor Regulation concurs that the action meets the intent of Specification 6.3.1.

6.3.3 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator and a licensed reactor operator are those individuals who, in addition to meeting the requirements of 6.3.1.3, perform the functions described in 10 CFR 50.54(m) 6.4 DELETED 6.5 DELETED 6.6 DELETED 6.7 DELETED TURKEY POINT - UNITS 3 & 4 6-4 Amendment Nos. 268 and 263

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR AMENDMENT NO. 268 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-31 AND AMENDMENT NO. 263 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-41 FLORIDA POWER & LIGHT COMPANY TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 DOCKET NOS. 50-250 AND 50-251

1.0 INTRODUCTION

By application dated October 12, 2015, 1 Florida Power & Light Company (the licensee) requested changes to the Technical Specifications (TSs) for Turkey Point Nuclear Generating Unit Nos. 3 and 4 (Turkey Point), which are contained in Appendix A of Renewed Facility Operating Licenses DPR-31 and DPR-41. The licensee proposed to revise the qualification requirements for licensed operators in TS 6.3.1.3 by removing the requirement to meet American National Standards Institute (ANSI) Standard 3.1-1981, "Selection, Qualification and Training of Personnel for Nuclear Power Plants," and ANSI N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel," and instead requiring compliance only with Title 10 of the Code of Federal Regulations (10 CFR), Part 55, "Operators' Licenses." The U.S. Nuclear Regulatory Commission (NRC or the Commission) staff's original proposed no significant hazards consideration determination was published in the Federal Register (FR) on December 22, 2015 (80 FR 79620).

2.0 REGULATORY EVALUATION

2.1. Description of the Turkey Point Facility Staff Qualifications TSs The Turkey Point TSs require licensed operators to meet or exceed the minimum qualifications specified in 10 CFR Part 55 and ANSI 3.1-1981 in addition to the qualifications in ANSI N18.1-1971. Turkey Point TS 6.3, "FACILITY STAFF QUALIFICATIONS," states, in part:

6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for ...

1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML15300A264.

6.3.1.3 The licensed Operators and Senior Operators who shall also meet or exceed the minimum qualifications of the supplemental requirements specified in 10 CFR Part 55, and ANSI 3.1, 1981.

2.2 Licensee's Proposed Changes In its application dated October 12, 2015, the licensee proposed to revise TS 6.3.1.3 to require compliance only with the requirements of 10 CFR Part 55 in lieu of providing details of the operator license applicant's education and experience that would meet the requirements of ANSI/ANS 3.1-1981 and ANSI N18.1-1971. The licensee proposed TS 6.3 to state (with deletions shown in strike-out text and additions shown in italicized text):

6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for ...

6.3.1.3 The licensed Operators and Senior Operatorsoperators, who shall comply only with the requirements of 10 CFR 55 also meet or exceed the minimum qualifications of the supplemental requirements specified in 10 CFR Part 55, and ANSI 3.1, 1981.

2.3 Regulatory Review The NRC staff reviewed the licensee's application to ensure 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 the activities proposed will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or the health and safety of the public. The NRC staff considered the following regulatory requirements, guidance, and licensing and design basis information during its review of the proposed changes.

The regulatory requirements related to the content of the TSs are contained in 10 CFR 50.36, "Technical Specifications." Section 50.36 of 10 CFR requires TSs to include items in the following categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; (5) administrative controls; (6) decommissioning; (7) initial notification; and (8) written reports.

Paragraph 50.36(c)(5) states that administrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner.

The requirements for issuing, modifying, maintaining, and renewing operators' licenses are contained in 10 CFR Part 55.

On March 20, 1985, the "Commission Policy Statement on Training and Qualification of Nuclear Power Plant Personnel" was published in the FR (50 FR 11147). This policy statement endorsed the Institute of Nuclear Power Operations (INPO)-managed Training Accreditation Program, which has developed the National Academy for Nuclear Training (NANT) guidelines.

In NRC Generic Letter No. 87-07, "Information Transmittal of Final Rulemaking for Revisions to

Operator Licensing - 10 CFR 55 and Conforming Amendments," dated March 19, 1987, 2 and in NUREG-1262, "Answers to Questions at Public Meetings Regarding Implementation of Title 10, Code of Federal Regulations, Part 55 on Operators' Licenses," November 1987, 3 the NRC indicated that it would accept a facility licensee's licensed operator training program if the licensee certified in writing that the program was accredited by the National Nuclear Accrediting Board (NNAB) and was based on a Systems Approach to Training (SAT). This certification would supersede the previously approved training programs of ANSI N18.1-1971 and ANSI/ANS 3.1-1978. Facility licensees could submit a license amendment request to the NRC for an administrative change to their licensing documents in order to conform to their accredited program status, if necessary.

The NRC revised its regulations related to operators' licenses in 1987. In accordance with 10 CFR 55.31 (a)(4), as amended on March 25, 1987 (52 FR 9453), an applicant for an operator license must provide, among other things, evidence that he or she has successfully completed the facility licensee's requirements to be licensed as a reactor operator or senior reactor operator. This must include either details of the applicant's qualifications and details on courses of instruction administered by the facility licensee or certification that the applicant has successfully completed a Commission-approved training program that is based on a systems approach to training. In conjunction with the rule change, the NRC issued Revision 2 to Regulatory Guide (RG) 1.8, "Qualification and Training of Personnel for Nuclear Power Plants,"

dated April 1987, 4 which provided guidance on an acceptable method of implementing the regulation. RG 1.8, Revision 2 endorsed ANSI/ANS 3.1-1981 with clarifications, additions, and exceptions; and ANSI N18.1-1971.

On January 7, 1992, the NRC's proposed rulemaking to 10 CFR 50.120, Training and Qualification of Nuclear Power Plant Personnel," was published in the FR (57 FR 537). The proposed rule stated that, if adopted, the rule would supersede the Commission's 1985 policy on training and qualification of nuclear power plant personnel and would not result in any changes to accredited training programs. The Commission concluded that accredited training programs, when implemented consistently with industry program objectives and criteria, would be in compliance with this regulation.

On April 26, 1993, the NRC's revised rulemaking to 10 CFR 50.120 was published in the FR (58 FR 21912). The rule requires nuclear power plant licensees to establish, implement, and maintain SAT-based training programs for nine non-licensed positions. Accreditation of these nine training programs is an acceptable means of meeting the requirements of 10 CFR 50.120. In its discussion of the revised rule in the FR, the Commission recognized the appropriateness of using this approach to training in its requirements for operator licensing prescribed in 10 CFR 55.31 (a)(4), and for operator requalification prescribed in 10 CFR 55.59(c).

2 ADAMS Accession No. ML031150669.

3 ADAMS Accession No. ML15198A217.

4 ADAMS Accession No. ML13350A382.

On January 18, 2001, the NRC issued Regulatory Issue Summary (RIS) 2001-01, "Eligibility of Operator License Applicants," 5 to familiarize licensees with the NRC's current guidelines for the qualification and training of reactor operator and senior operator license applicants.

RIS 2001-01 acknowledged that 10 CFR 55.31(a)(4) allows the NRC to accept an application for an operator's license if the facility licensee certifies that the applicant has successfully completed a Commission-approved training program that is based on an SAT. In addition, RIS 2001-01 states that (1) a training program would be considered approved by the NRC when it receives or renews accreditation from the NNAB; (2) accreditation of an operator training program suggests that the facility licensee is implementing the education and experience guidelines endorsed by the NNAB, which are outlined by NANT in its "Guidelines for Initial Training and Qualification of Licensed Operators"; (3) the NANT guidelines for education and experience outline acceptable methods for implementing the Commission's regulations; and (4) the staff encourages all facility licensees to review their requirements and commitments related to licensed operator education and experience and to update their documentation (e.g.,

Final Safety Analysis Report, TSs, and training program descriptions), to enhance consistency and minimize confusion.

3.0 TECHNICAL EVALUATION

The staff evaluated the licensee's proposed changes to TS 6.3.1.3. The licensee proposed to revise the education and experience requirements for an applicant for an operator's license to stipulate that licensed operators shall comply only with 10 CFR Part 55. The licensee stated in its application dated October 12, 2015, that the licensed operator training program at Turkey Point is SAT-based and accredited by the NNAB. The regulations in Paragraph 55.31(a)(4) specify how to apply for an operator's license and states that the NRC may accept an application for an operator's license if the facility licensee certifies that the applicant has successfully completed a Commission-approved training program that is based on an SAT, in lieu of providing details of the applicant's education and experience. Based on this regulatory language and the above regulatory review, the staff finds that there is no need to specify in the TSs additional education and experience requirements for licensed operators beyond what is already required in the regulations. The staff finds that the proposed changes are consistent with 10 CFR Part 55, do not adversely affect nuclear safety or plant operations, and provide reasonable assurance that the facility licensee maintains administrative controls for the safe operation of the facility by properly qualified licensed operators. Therefore, the staff concludes that the proposed changes to TS 6.3.1.3 are acceptable.

In addition, the licensee proposed to replace the words, "Operators and Senior Operators," in TS 6.3.1.3 with "operators." The term "operator" is defined in 10 CFR 55.4 as "any individual licensed under [10 CFR Part 55] to manipulate a control of a facility." Because this definition encompasses both "Operators" and "Senior Operators," the staff finds that the proposed change reduces redundancy, does not change the applicability of the TS requirement to both operators and senior operators, and does not reduce any requirements. Therefore, the staff concludes that this proposed change to TS 6.3.1.3 is acceptable.

5 ADAMS Accession No. ML003733003.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the NRC staff notified the State of Florida official (Ms. Cynthia Becker, M.P.H., Chief of the Bureau of Radiation Control, Florida Department of Health) on December 28, 2015, 6 of the proposed issuance of the amendments.

The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change the requirements with respect to TS administrative controls associated with qualifications of licensed operators. As such, the amendments relate to recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(1 O)(ii). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

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

Principal Contributor: Victoria V. Huckabay Date: February 25, 2016 6 The NRC staff notified the State official by telephone and by e-mail. The e-mail is in ADAMS under Accession No. ML15362A540.

M. Nazar The NRC staff's safety evaluation of the amendments is enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, IRA/

Audrey L. Klett, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-250 and 50-251

Enclosures:

1. Amendment No. 268 to DPR-31

2. Amendment No. 263 to DPR-41

3. Safety Evaluation cc w/enclosures: Distribution via Listserv DISTRIBUTION:

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