ML17310B239

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and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Unit Staff Qualifications (CAC Nos. MF9545, MF9546, and MF9547; EPID L-2017-LLA-0195)
ML17310B239
Person / Time
Site: Monticello, Prairie Island  Xcel Energy icon.png
Issue date: 11/28/2017
From: Robert Kuntz
Plant Licensing Branch III
To: Church C, Northard S
Northern States Power Company, Minnesota
Kuntz R, NRR/DORL/LPLIII
References
CAC MF9545, CAC MF9546, CAC MF9547, EPID L-2017-LLA-0195
Download: ML17310B239 (22)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 28, 2017 Mr. Christopher Church Site Vice President Monticello Nuclear Generating Plant Northern States Power Company - Minnesota (NSPM) 2807 West County Road 75 Monticello, MN 55362-9637 Mr. Scott D. Northard Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota 1717 Wakonade Drive East Welch, MN 55089

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT AND PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2- ISSUANCE OF AMENDMENT RE: UNIT STAFF QUALIFICATIONS (CAC NOS. MF9545, MF9546, AND MF9547; EPID L-2017-LLA-0195)

Dear Mr. Church and Mr. Northard:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 195 to Renewed Facility Operating License No. DPR-22 for the Monticello Nuclear Generating Plant (MNGP) and Amendment No. 221 to Renewed Facility Operating License No. DPR-42 and Amendment No. 208 to Renewed Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2, respectively. The amendment consists of changes to the technical specifications (TSs) in response to your application dated March 31, 2017.

The amendment revises the PINGP, Unit 1 and 2, TS, Section 5.3, "Plant Staff Qualifications" and MNGP TS 5.3, "Unit Staff Qualifications," subsections 5.3.1 to add an exception for licensed operators from the education and experience eligibility requirements of American National Standards Institute N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel," by requiring that licensed operators comply only with the requirements of Title 1O of the Code of Federal Regulations (1 O CFR) Part 55, "Operators' Licenses." The proposed changes are administrative in nature and are consistent with 1O CFR Part 55, "Operators' Licenses." The submittal also proposes administrative changes to the PINGP and MNGP TS 5.0, "Administrative Controls," subsections 5.1-5.3 by making changes to standardize and align formatting to the extent possible between the TSs.

C. Church and S. Northard A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Robert F. Kuntz, Senior Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-263, 50-282, and 50-306

Enclosures:

1. Amendment No. 195 to DPR-22
2. Amendment No. 221 to DPR-42
3. Amendment No. 208 to DPR-60
4. Safety Evaluation cc: Distribution via ListServ

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 195 License No. DPR-22

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

A. The application for amendment by Northern States Power Company (NSPM, the licensee), dated March 31, 2017, 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.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Renewed Facility Operating License No. DPR-22 is hereby amended to read as follows:

Enclosure 1

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 195, are hereby incorporated in the license. NSPM shall operate the facility in accordance with the Technical Specifications.

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

FOR THE NUCLEAR REGULATORY COMMISSION j '

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David J. Wrona, Chief l)_,I Plant Licensing Branch 111 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License No. DPR-22 and Technical Specifications Date of Issuance: November 2 8, 2 O1 7

ATTACHMENT TO LICENSE AMENDMENT NO. 195 MONTICELLO NUCLEAR GENERATING PLANT RENEWED FACILITY OPERATING LICENSE NO. DPR-22 DOCKET NO. 50-263 Replace the following page of Renewed Facility Operating License DPR-22 with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.

REMOVE INSERT 3 3 Replace the following pages of Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

REMOVE INSERT 5.1-1 5.1-1 5.2-2 5.2-2 5.3-1 5.3-1

3

2. Pursuant to the Act and 1O CFR Part 70, NSPM to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operations, as described in the Final Safety Analysis Report, as supplemented and amended, and the licensee's filings dated August 16, 1974 (those portions dealing with handling of reactor fuel);
3. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NSPM to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;
4. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NSPM to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and
5. Pursuant to the Act and 1O CFR Parts 30 and 70, NSPM to possess, but not separate, such byproduct and special nuclear material as may be produced by operation of the facility.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations in 10 CFR Chapter I 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 or incorporated below:

1. Maximum Power Level NSPM is authorized to operate the facility at steady state reactor core power levels not in excess of 2004 megawatts (thermal}.
2. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 195, are hereby incorporated in the license. NSPM shall operate the facility in accordance with the Technical Specifications.
3. Physical Protection NSPM shall implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Renewed License No. DPR-22 Amendment No. 195

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The plant manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

The plant manager or his designee shall approve, prior to implementation, each proposed test, experiment, or modification to systems or equipment that affects nuclear safety.

5.1.2 The shift supervisor shall be responsible for the control room command function.

During any absence of the shift supervisor from the control room complex while the unit is in MODE 1, 2, or 3, an individual with an active senior reactor operator (SRO) license shall be designated to assume the control room command function. During any absence of the shift supervisor from the control room complex while the unit is in MODE 4 or 5, an individual with an active SRO license or reactor operator (RO) license shall be designated to assume the control room command function.

Monticello 5.1-1 Amendment No. 44&, 195 I

Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)

c. A radiation protection technician shall be on site when fuel is in the reactor.

The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

d. Not Used.
e. The operations manager shall hold an SRO license or shall formerly have held an SRO license. If the operations manager does not hold an SRO license, another member of plant management shall hold an SRO license and shall be assigned to the plant operations group on a long term basis (approximately 2 years). This individual shall not be assigned to a rotating shift.
f. 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. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

Monticello 5.2-2 Amendment No. 146, 163, 195 I

Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N 18.1-1971 for comparable positions, except for the following:

  • The radiation protection manager shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1, September 1975.
  • In addition, the operations manager shall be qualified as required by Specification 5.2.2.e.
  • The licensed operators shall comply only with the requirements of 10 CFR 55.

5.3.2 For the purpose of 10 CFR 55.4, a licensed SRO and a licensed RO are those individuals who, in addition to meeting the requirements of Specification 5.3.1, perform the functions described in 10 CFR 50.54(m).

Monticello 5.3-1 Amendment No. 44e, 195 I

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NORTHERN STATES POWER COMPANY - MINNESOTA DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 221 License No. DPR-42

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

A. The application for amendment by Northern States Power Company, a Minnesota Corporation (NSPM, the licensee), dated March 31, 2017, 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 1O 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 Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-42 is hereby amended to read as follows:

Enclosure 2

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 221, are hereby incorporated in the renewed operating license.

NSPM shall operate the facility in accordance with the Technical Specifications.

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

FOR THE NUCLEAR REGULATORY COMMISSION David J. Wrona, Chief

Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License No. DPR-42 and Technical Specifications Date of Issuance: N overnber 2 8 , 2 O1 7

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NORTHERN STATES POWER COMPANY - MINNESOTA DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 208 License No. DPR-60

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

A. The application for amendment by Northern States Power Company, a Minnesota Corporation (NSPM, the licensee), dated March 31, 2017, 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 1O 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 Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-60 is hereby amended to read as follows:

Enclosure 3

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 208, are hereby incorporated in the renewed operating license.

NSPM shall operate the facility in accordance with the Technical Specifications.

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

FOR THE NUCLEAR REGULATORY COMMISSION

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David Wrona, Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License No. DPR-60 and Technical Specifications Date of Issuance: November 2 8, 2 o1 7

ATTACHMENT TO LICENSE AMENDMENT NOS. 221 AND 208 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 RENEWED FACILITY OPERATING LICENSE NOS. DPR-42 AND DPR-60 DOCKET NOS. 50-282 AND 50-306 Replace the following pages of the Renewed Facility Operating License Nos. DPR-42 and DPR-60 with the attached revised pages. The changed areas are identified by a marginal line.

REMOVE INSERT Page 3 Page 3 Page 3 Page 3 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

REMOVE INSERT 5.0-1 5.0-1 5.0-5 5.0-5

(3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NSPM to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, NSPM to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 1O CFR Parts 30 and 70, NSPM to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility; (6) Pursuant to the Act and 1O CFR Parts 30 and 70, NSPM to transfer byproduct materials from other job sites owned by NSPM for the purpose of volume reduction and decontamination.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 1O CFR Chapter I:

Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level NSPM is authorized to operate the facility at steady state reactor core power levels not in excess of 1677 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 221, are hereby incorporated in the renewed operating license. NSPM shall operate the facility in accordance with the Technical Specifications.

(3) Physical Protection NSPM shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Renewed Operating License No. DPR-42 Amendment No. 221

(3) Pursuant to the Act and 1O CFR Parts 30, 40 and 70, NSPM to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, NSPM to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility; (6) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to transfer byproduct materials from other job sites owned by NSPM for the purposes of volume reduction and decontamination.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 1O CFR Chapter I:

Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level NSPM is authorized to operate the facility at steady state reactor core power levels not in excess of 1677 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 208, are hereby incorporated in the renewed operating license.

NSPM shall operate the facility in accordance with the Technical Specifications.

(3) Physical Protection NSPM shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 1O CFR 73.55 (51 FR 27817 and 27822) and to the authority of 1O CFR 50.90 and 1O CFR 50.54(p). The combined set of plans, which contains Renewed Operating License No. DPR-60 Amendment No. 208

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5 .1.1 The plant manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

The plant manager or his designee shall approve, prior to implementation, each proposed test, experiment or modification to systems or equipment that affect nuclear safety.

5.1.2 The shift supervisor shall be responsible for the control room command function. During any absence of the shift supervisor from the control room while the unit is in MODE 1, 2, 3, or 4, an individual with an active senior reactor operator (SRO) license shall be designated to assume the control room command function. During any absence of the shift supervisor from the control room while the unit is in MODE 5 or 6, an individual with an active SRO license or reactor operator (RO) license shall be designated to assume the control room command function.

Prairie Island Unit 1 -Amendment No. B-8, 221 Units 1 and 2 5.0-1 Unit 2 - Amendment No. -149, 208

Plant Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Plant Staff Qualifications 5.3 .1 Each member of the plant staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the following:

  • The radiation protection manager shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1, September 1975.
  • In addition, the operations manager shall be qualified as required by TS 5.2.2.e.
  • The licensed operators shall comply only with the requirements of 10 CFR 55.

5.3.2 For the purpose of 10 CFR 55.4, a licensed SRO and a licensed RO are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54(m).

Prairie Island Unit 1 -Amendment No. 188,205,221 Units 1 and 2 5.0-5 Unit 2 -Amendment No. 177, 192,208

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 195 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-22, AMENDMENT NO. 221 TO RENEWED FACILITY OPERATING LICENSE NO. DPR 42, AND AMENDMENT NO. 208 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-60 NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT AND PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-263, 50-282, AND 50-306

1.0 INTRODUCTION

By application dated March 31, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17090A201 ), Northern States Power Company (NSPM, the licensee), requested changes to the technical specifications (TSs) for Monticello Nuclear Generating Plant (MNGP) and Prairie Island Nuclear Generating Plant, Units 1 and 2 (PINGP).

The proposed changes would revise PINGP TS Section 5.3, "Plant Staff Qualifications," and MNGP TS 5.3, "Unit Staff Qualifications," subsections 5.3.1 to add an exception for licensed operators from the education and experience eligibility requirements of American National Standards Institute (ANSI) N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel," by requiring that licensed operators comply only with the requirements of Title 1O of the Code of Federal Regulations (1 O CFR) Part 55, "Operators' Licenses." The submittal also proposes administrative changes to the PINGP and MNGP TS 5.0, "Administrative Controls,"

subsections 5.1-5.3 by making changes to standardize and align formatting to the extent possible between the TSs.

2.0 REGULATORY EVALUATION

In Generic Letter 87-07, "Information Transmittal of Final Rulemaking for Revisions to Operator Licensing [Title 1O of the Code of Federal Regulations] 10 CFR Part 55 and Conforming Amendments," dated March 19, 1987 (ADAMS Legacy Library No. 8703190287), and in NUREG-1262, "Answers to Questions at Public Meetings Regarding Implementation of Part 55 of Title 10, Code of Federal Regulations, on Operators' Licenses" (ADAMS Accession No.

ML15198A217), published November 1987, the NRC indicated it would accept a facility's licensed operator training program if the facility certified in writing that the program was Enclosure 4

accredited and based on a systems approach to training (SAT). This certification would supersede the requirements of ANSI N 18.1-1971, "Selection and Training of Nuclear Power Plant Personnel." Facility licensees were advised to submit a request to the NRC for an administrative change to their licensing documents to conform to their accredited program status.

In January 1992, the NRC published its proposed rule 1O CFR 50.120, "Training and Qualification of Nuclear Power Plant Personnel." The proposed rule stated that, if adopted, the rule would supersede the Commission's Policy Statement on training and qualification of nuclear power plant personnel and would not result in any change to accredited programs. The Commission concluded that accredited programs, implemented consistently with industry objectives and criteria, would be in compliance with this regulation. In April 1993, the NRC published its final rule on training and qualification of nuclear power plant personnel. The rule at 10 CFR 50.120(b) requires nuclear power plant licensees to establish, implement, and maintain SAT-based training programs for nine non-licensed positions.

In January 2001, the NRC published NRC Regulatory Issue Summary (RIS) 2001-01, "Eligibility of Operator License Applicants," 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 1O CFR 55.31 (a)(4) allows the NRC to accept an application for an operator's license if the facility certifies that the applicant has successfully completed a Commission approved training program that is based on a SAT. In addition, RIS 2001-01 stated that: (1) a training program would be considered approved by the NRC when it receives accreditation from the National Nuclear Accrediting Board (NNAB); (2) accreditation of operator training programs suggests that facilities are implementing the education and experience guidelines endorsed by the NNAB; (3) National Academy for Nuclear Training (NANT) guidelines for education and experience (those that were in effect in 1987 or those that were issued in January 2000) outline acceptable methods for implementing the Commission's regulations in this area; and (4) the staff encourages all facility licensees to review their requirements and commitments related to licensed operator and senior operator education and experience and to update their documentation (e.g., final safety analysis report, TS, and training program descriptions) to enhance consistency and minimize confusion.

3.0 TECHNICAL EVALUATION

The March 31, 2017, license amendment request (LAA) proposed to revise PINGP TS Section 5.3, "Plant Staff Qualifications" and MNGP TS 5.3, "Unit Staff Qualifications," subsections 5.3.1, to stipulate that licensed operators are excepted from the qualifications described in ANSI N18.1-1971. In lieu of the ANSI standard for licensed operators, the operators will be explicitly required to comply with 1O CFR Part 55.

The LAA stated that the licensed operator training programs are based on a SAT and are accredited by the NANT. The regulation at 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 a SAT in lieu of providing details of the applicant's education and experience. Therefore, this change meets the 1O CFR 55.31 (a)(4) requirements to apply for an operator's license and ensures the facility licensee maintains administrative controls that assure the operation of the facility in a safe manner by properly qualified licensed operators.

The NRC staff reviewed the LAR for compliance with the requirements in 1O CFR Part 55. As explained in RIS 2001-01, "Eligibility of Operator License Applicants," 10 CFR 55.31 (a)(4) provides 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.

The LAR is consistent with 10 CFR 55.31 (a)(4) and does not adversely affect nuclear safety or plant operations. Therefore, the NRC staff concludes that the proposed changes to PINGP and MNGP TS 5.3.1 are acceptable.

The LAR also proposed changes to position titles and abbreviations in PINGP TS subsections 5.1.2 and 5.3.2 as well as MNGP TS subsection 5.1.2 in order to standardize and align the meanings of the positions between the plant's TSs. The NRC staff finds that these changes are administrative in nature and will have no adverse impact on nuclear safety or plant operations.

Therefore, the NRC staff concludes that the proposed changes to PINGP and MNGP TS subsections 5.1.2, 5.3.1, and 5.3.2 and MNGP TS 5.2.2 are acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Minnesota State official was notified of the proposed issuance of the amendments on November 1, 2017. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or change the surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding June 6, 2017 (82 FR 26133). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

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 amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: John D. Hughey, NRR/DRA Date of issuance: November 28, 2017

ML173108239 *memo dated **via e-mail OFFICE DORL/LPL3/PM DORL/LPL3/LA STSB/BC APHB/BC NAME RKuntz SRohrer VCusumano** SWeerakkody*

DATE 11/9/17 11/8/17 11/13/17 10/6/17 OFFICE IOLB/BC OGC DORL/LPL3/BC DORL/LPL3/PM NAME NSalgado** CKanatas NLO w/ DWrona RKuntz comments**

DATE 11/28/17 11/22/17 11/27/17 11/28/17

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