ML22294A150

Issuance of Amendment Nos. 284 and 267 Relocating Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program

ML22294A150
Person / Time
Site:	Susquehanna
Issue date:	11/17/2022
From:	Audrey Klett Plant Licensing Branch 1
To:	Cimorelli K Susquehanna
Klett A
References
EPID L-2022-LLA-0046
Download: ML22294A150 (19)

Text

November 17, 2022 Mr. Kevin Cimorelli Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard NUCSB3 Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 284 AND 267 RE: RELOCATING TECHNICAL SPECIFICATION UNIT STAFF QUALIFICATION REQUIREMENTS TO QUALITY ASSURANCE PROGRAM (EPID L-2022-LLA-0046)

Dear Mr. Cimorelli:

The U.S. Nuclear Regulatory Commission (NRC or the Commission) has issued the enclosed Amendment No. 284 to Renewed Facility Operating License No. NPF-14 and Amendment No. 267 to Renewed Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2, respectively, in response to Susquehanna Nuclear, LLCs application dated March 31, 2022. These amendments revise Technical Specification 5.3.1, Unit Staff Qualifications, by relocating the specific minimum qualifications for unit staff to the quality assurance program and referring to the quality assurance program for the minimum qualification requirements for comparable positions. Enclosed is a copy of the NRCs safety evaluation for the amendments. The NRC will include a Notice of Issuance in its monthly Federal Register Notice.

Sincerely,

/RA/

Audrey Klett, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 284 to License No. NPF-14

2. Amendment No. 267 to License No. NPF-22

3. Safety Evaluation cc: Listserv

SUSQUEHANNA NUCLEAR, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.

DOCKET NO. 50-387 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 284 Renewed License No. NPF-14

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

A. The application for the amendment filed by Susquehanna Nuclear, LLC, dated March 31, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 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 Commissions 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 Commissions regulations and all applicable requirements have been satisfied.

Enclosure 1

2. Accordingly, the license is amended by changes to the Renewed Facility Operating License and Technical Specifications, as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-14 is hereby amended to read as follows:

2.C.(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 284, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. Susquehanna Nuclear, LLC 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 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION Digitally signed by Hipolito Hipolito J. J. Gonzalez Date: 2022.11.17 Gonzalez 14:22:58 -05'00' Hipólito J. González, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: November 17, 2022

ATTACHMENT TO LICENSE AMENDMENT NO. 284 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1 RENEWED FACILITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 Replace the following page of Renewed Facility Operating License No. NPF-14 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 Page 3 Page 3 Replace the following page of the appendix A technical specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Insert 5.0-5 5.0-5

(3) Susquehanna Nuclear, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, posses, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed neutron sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Susquehanna Nuclear, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, posses, 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) Susquehanna Nuclear, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth 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 nor or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level Susquehanna Nuclear, LLC is authorized to operate the facility at reactor core power levels not in excess of 3952 megawatts thermal in accordance with the conditions specified herein. The preoperational tests, startup tests and other items identified in License Conditions 2.C.(36), 2.C.(37), 2.C.(38), and 2.C.(39) to this license shall be completed as specified.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 284, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. Susquehanna Nuclear, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

For Surveillance Requirements (SRs) that are new in Amendment 178 to Facility Operating License No. NPF-14, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 178. For SRs that existed prior to Amendment 178, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 178.

Renewed Operating License No. NPF-14 Amendment No. 284

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 referenced for comparable positions as specified in the Susquehanna Steam Electric Station Quality Assurance Program.

SUSQUEHANNA - UNIT 1 5.0-5 Amendment 178, 284

SUSQUEHANNA NUCLEAR, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.

DOCKET NO. 50-388 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 267 Renewed License No. NPF-22

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

A. The application for the amendment filed by Susquehanna Nuclear, LLC, dated March 31, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 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 Commissions 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 Commissions regulations and all applicable requirements have been satisfied.

Enclosure 2

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

2.C.(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 267, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. Susquehanna Nuclear, LLC 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 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION Digitally signed by Hipolito Hipolito J. J. Gonzalez Date: 2022.11.17 Gonzalez 15:07:40 -05'00' Hipólito J. González, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: November 17, 2022

ATTACHMENT TO LICENSE AMENDMENT NO. 267 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 RENEWED FACILITY OPERATING LICENSE NO. NPF-22 DOCKET NO. 50-388 Replace the following page of Renewed Facility Operating License No. NPF-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 Page 3 Page 3 Replace the following page of the appendix A technical specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Insert 5.0-5 5.0-5

(3) Susquehanna Nuclear, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, posses, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed neutron sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Susquehanna Nuclear, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, posses, 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) Susquehanna Nuclear, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth 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 nor or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level Susquehanna Nuclear, LLC is authorized to operate the facility at reactor core power levels not in excess of 3952 megawatts thermal in accordance with the conditions specified herein. The preoperational tests, startup tests and other items identified in License Conditions 2.C.(20), 2.C.(21), 2.C.(22), and 2.C.(23) to this license shall be completed as specified.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 267, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. Susquehanna Nuclear, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

For Surveillance Requirements (SRs) that are new in Amendment 151 to Facility Operating License No. NPF-22, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 151. For SRs that existed prior to Amendment 151, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 151.

Renewed Operating License No. NPF-22 Amendment No. 267

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 referenced for comparable positions as specified in the Susquehanna Steam Electric Station Quality Assurance Program.

SUSQUEHANNA - UNIT 2 5.0-5 Amendment 151, 267

November 17, 2022 Safety Evaluation by the Office of Nuclear Reactor Regulation for Amendment No. 284 to Renewed Facility Operating License No. NPF-14 Amendment No. 267 to Renewed Facility Operating License No. NPF-22 Susquehanna Nuclear, LLC Allegheny Electric Cooperative, Inc.,

Susquehanna Steam Electric Station, Units 1 and 2 Docket Nos. 50-387 and 50-388 TABLE OF CONTENTS 1.0 Introduction ................................................................................................................... 1.1 Background ............................................................................................................... 1.2 Description of Current Requirements ........................................................................ 1.3 Description of the Proposed Change ......................................................................... 2.0 Regulatory Evaluation ................................................................................................... 2.1 Regulatory Requirements .......................................................................................... 2.2 Licensing Basis .......................................................................................................... 2.3 Guidance ................................................................................................................... 3.0 Technical Evaluation ..................................................................................................... 4.0 State Consultation ......................................................................................................... 5.0 Environmental Consideration ........................................................................................ 6.0 Conclusion .................................................................................................................... 7.0 References .................................................................................................................... 8.0 Abbreviations ................................................................................................................ 9.0 Principal Contributor ...................................................................................................... Enclosure 3

1.0 Introduction

1.1 Background

By application dated March 31, 2022 [1], Susquehanna Nuclear, LLC (the licensee) submitted a license amendment request pertaining to the Susquehanna Steam Electric Station (Susquehanna), Units 1 and 2 technical specifications (TS), which are Appendix A of the Susquehanna Renewed Facility Operating License Nos. NPF-14 and NPF-22. The proposed change would revise TS 5.3.1, Unit Staff Qualifications, by relocating the specific minimum qualifications for unit staff to the quality assurance program (QAP) and referring to the QAP for the minimum qualification requirements for comparable positions. The licensees QAP and staff qualification program is in its updated final safety analysis report (UFSAR) [2]. The U.S. Nuclear Regulatory Commission (NRC or the Commission) staffs proposed no significant hazards consideration determination was published in the Federal Register on July 15, 2022 [3].

1.2 Description of Current Requirements TS 5.3.1 currently has the following requirements on unit staff qualifications:

1. Licensed operators and shift technical advisors shall meet the supplemental requirements in NRC Regulatory Guide (RG) 1.8, Revision 2, Qualification and Training of Personnel for Nuclear Power Plants [4].

2. The health physics supervisor shall meet or exceed the qualifications of RG 1.8, Revision 1, Personnel Selection and Training [5].

3. All other members of the unit staff shall meet or exceed the minimum qualifications of American National Standard Institute (ANSI) standard ANSI N18.1-1971, Selection and Training of Nuclear Power Plant Personnel [6], for comparable positions.

The QAP, as described in Table 17.2-1, Quality Assurance Program Description Compliance Matrix, of the UFSAR [2] states that the following standards apply to the listed positions:

1. American National Standards Institute/American Nuclear Society (ANS) Standard ANSI/ANS-3.1-1981, Selection, Qualification and Training of Personnel for Nuclear Power Plants [7], which the NRC endorsed in RG 1.8, Revision 2 [4], for the positions of shift supervisor, senior operator, shift technical advisor, licensed operator, supervisor of organization unit responsible for independent review, and staff specialist

2. ANSI N18.1-1971 [6], which the NRC endorsed in RG 1.8, Revision 1-R [5], for the position of radiation protection manager

3. ANSI/ANS 3.1-1978, Standard for Selection and Training of Personnel for Nuclear Power Plants [8], for all other positions except those listed in 1 and 2 above

1.3 Description of the Proposed Change The licensee proposed to revise TS 5.3.1 as follows, with additions underlined and deletions shown in stricken text:

Each member of the unit staff shall meet or exceed the minimum qualifications referenced for comparable positions as specified in the Susquehanna Steam Electric Station Quality Assurance Program of ANSI N18.1-1971 for comparable positions except licensed operators and Shift Technical Advisors who shall meet the supplemental requirements in Reg Guide 1.8 Rev. 2 and the supervisor-health physics who shall meet or exceed the qualification of Regulatory Guide 1.8 September 1975.

In its application [1], the licensee stated that the unit staff qualification requirements are already in Table 17.2-1 of the UFSAR [2].

2.0 Regulatory Evaluation 2.1 Regulatory Requirements Paragraph (c)(5) of Title 10 of the Code of Federal Regulations (10 CFR) Part 50.36, Technical specifications, has requirements for the content of the TS in the category of administrative controls.

10 CFR 50.54(a) has requirements for making changes to quality assurance programs.

10 CFR 50.54(a)(3) states, in part:

Each licensee described in [10 CFR 50.54(a)(1)] may make a change to a previously accepted quality assurance program description included or referenced in the Safety Analysis Report without prior NRC approval, provided the change does not reduce the commitments in the program description as accepted by the NRC. Changes to the quality assurance program description that do not reduce the commitments must be submitted to the NRC in accordance with the requirements of

[10 CFR] 50.71(e).

10 CFR 50.54(a)(4) requires changes to the quality assurance program that do reduce commitments to be submitted to the NRC and receive NRC approval prior to implementation.

10 CFR 50.120, Training and qualification of nuclear power plant personnel, requires training and qualification for personnel to operate and maintain the facility in a safe manner in all modes of operation and requires that each nuclear power plant licensee establish, implement, and maintain the training and qualification programs that are derived from a systems approach to training as defined in 10 CFR 55.4, Definitions.

Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, has requirements for quality assurance programs.

2.2 Licensing Basis Sections 13.4, Review and Audit, and 17.2, Quality Assurance During the Operations Phase, of the UFSAR [2] describe the licensees QAP and staff qualification program.

2.3 Guidance NRC Administrative Letter (AL) 95-06, Relocation of Technical Specification Administrative Controls Related to Quality Assurance [9], has guidance for relocating requirements from the administrative controls section of TS in cases where adequate controls are provided by other methods. AL 95-06 [9] states that the QAP is a logical candidate for such relocations because of the controls imposed on the QAP by regulations (e.g., 10 CFR Part 50, Appendix B, and 10 CFR 50.54(a)) and the existence of NRC-approved quality assurance plans and commitments to industry quality assurance standards.

NRC RG 1.8, Revisions 1 [5] and 2 [4] describe methods that the NRC staff finds acceptable for complying with the NRCs regulations regarding training and qualification of nuclear plant personnel. Revision 1 (1-R) of RG 1.8 [5] endorsed ANSI N18.1-1971 [6]

with one exception.1 Revision 2 of RG 1.8 [4] endorsed ANSI/ANS-3.1-1981 [7] for certain positions and ANSI N18.1-1971 [6] for other positions, with exceptions, clarifications, and additions.

3.0 Technical Evaluation In deciding whether an amendment to a license will be issued, the NRC is guided by the considerations that govern the issuance of initial licenses to the extent applicable and appropriate. The NRC staff evaluated the licensees request to decide whether the proposed change is consistent with the regulations, licensing basis, and guidance discussed in Section 2.0 of this safety evaluation. The NRC staff reviewed the proposed TS change to decide whether it meets the requirements of 10 CFR 50.36 and provides reasonable assurance that the continued operation of the units will not endanger the health and safety of the public.

As discussed in Section 1.3 of this safety evaluation, the licensee proposed to modify TS 5.3.1 by relocating the unit staff qualifications from the TS to the QAP, which is located in Sections 13.4 and 17.2 of the UFSAR [2]. In its request [1], the licensee stated that the amendment would not change any current staff qualification requirements.

The NRC staff confirmed that the current TS 5.3.1 requirements are the same as the current QAP requirements in the UFSAR [2] for the positions of shift supervisor, senior operator, shift technical advisor, licensed operator, supervisor of organization unit responsible for independent review, staff specialist, as well as radiation protection manager (radiation protection manager is the same position as supervisorhealth physics, as stated in the license amendment request [1]). Therefore, the guidance in RG 1.8, Revisions 1-R [5] and 2 [4] will continue to be met.

For other members of the unit staff, the current TS 5.3.1 requirement is ANSI N18.1-1971 [6],

while the current QAP requirement is ANSI/ANS-3.1-1978 [8]. ANSI/ANS-3.1-1978 [8] is a 1

The NRC originally published Revision 1 of RG 1.8 in September 1975 and republished it as Revision 1-R in May 1977.

revision to ANSI N18.1-1971 [6]. The licensee stated, and the NRC staff verified, that the qualification requirements in ANSI/ANS-3.1-1978 [8] meet or exceed the qualification requirements of ANSI N18.1-1971 [6] for all unit staff positions, as required in TS 5.3.1.

Therefore, the staff finds that licensees staff qualification requirements will not be reduced by these amendments because ANSI/ANS-3.1-1978 [8] in the QAP bounds ANSI N18.1-1971 [6] in the TS. Therefore, these requirements remain bounded by the guidance in RG 1.8, Revision 1-R [5], which endorses ANSI N18.1-1971 [6]. In addition, the staff also finds that the relocation of the licensees staff qualification requirements to the QAP is consistent with the guidance in AL 95-06 [9].

The NRC staff concludes that the requirements of 10 CFR 50.36 and 10 CFR 50.120 will continue to be met because the licensees staff qualification requirements will not be changed by these amendments. In addition, the licensee must make future changes to the licensees staff qualification requirements that are relocated to the QAP in accordance with Appendix B of 10 CFR Part 50 and 10 CFR 50.54(a). Any reduction in commitments associated with the licensees staff qualification requirements that are relocated to the QAP will require NRC approval prior to implementation in accordance with 10 CFR 50.54(a)(4). Therefore, the staff finds that the proposed TS changes and relocation of the licensees staff qualification requirements to the QAP are acceptable.

4.0 State Consultation In accordance with the Commissions regulations, on September 14, 2022 [10], the NRC staff notified the Commonwealth of Pennsylvania official of the proposed issuance of the amendment. The Commonwealth official had no comments.

5.0 Environmental Consideration The amendments relate to changes in 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)(10). Pursuant to 10 CFR 51.22(b), the NRC does not need to prepare an environmental impact statement or environmental assessment 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 amendment will not be inimical to the common defense and security or to the health and safety of the public.

7.0 References

[1] Cimorelli, K., Susquehanna Nuclear, LLC, letter to U.S. Nuclear Regulatory Commission, Susquehanna Steam Electric Station Proposed Amendment to Licensees NPF-14 and NPF-22: Relocate Technical Specification Unit Staff Qualification Requirements to Susquehanna Quality Assurance Program PLA-7883, March 31, 2022, ADAMS Accession No. ML22090A05.

[2] Cimorelli, K., Susquehanna Nuclear, LLC, letter to U.S. Nuclear Regulatory Commission, Susquehanna Steam Electric Station Submittal of Updated Final Safety Analysis Report Revision 70 and Fire Protection Review Report Revision 24, PLA-7935, October 12, 2021, ADAMS Accession No. ML21294A245. Section 13.4, Review and Audit, is at ADAMS Accession No. ML21294A228, and Section 17.2, Quality Assurance During the Operations Phase, is at ADAMS Accession No. ML21294A096.

[3] U.S. Nuclear Regulatory Commission, Monthly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations, Office of the Federal Register, Volume 87, Page 42510 (87 FR 42510),

July 15, 2022.

[4] U.S. Nuclear Regulatory Commission, Regulatory Guide 1.8, Revision 2, Qualification and Training of Personnel for Nuclear Power Plants, April 1987, ADAMS Accession No. ML003739928.

[5] U.S. Nuclear Regulatory Commission, Regulatory Guide 1.8, Revision 1, Personnel Selection and Training, September 1975 and reissued in May 1977 as Revision 1-R, ADAMS Accession No. ML12305A250.

[6] American National Standards Institute, ANSI N18.1-1971, Selection and Training of Nuclear Power Plant Personnel, March 18, 1971.

[7] American Nuclear Society, ANSI/ANS-3.1-1981, Selection, Qualification and Training of Personnel for Nuclear Power Plants, December 17, 1981.

[8] American Nuclear Society, ANSI/ANS-3.1-1978, Standard for Selection and Training of Personnel for Nuclear Power Plants, January 17, 1978.

[9] U.S. Nuclear Regulatory Commission, Administrative Letter 95-06, Relocation of Technical Specification Administrative Controls Related to Quality Assurance, December 12, 1995, ADAMS Accession No. ML031110271.

[10] Klett, A., U.S. Nuclear Regulatory Commission, email to Shields, M., Pennsylvania Department of Environmental Protection, NRC Notification to the State of Pennsylvania Re. Susquehanna Steam Electric Station, Units 1 and 2 Amendment - Relocating Staff Qualification Requirements, September 14, 2022, ADAMS Accession No. ML22257A194.

[11] U.S. Nuclear Regulatory Commission, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 13.2.2, Revision 4, Non-licensed Plant Staff Training, August 2016, ADAMS Accession No. ML15006A129.

[12] U.S. Nuclear Regulatory Commission, NUREG-0800, Revision 12, Operator Licensing Examination Standards for Power Reactors, September 2021, ADAMS Accession No. ML21256A276.

8.0 Abbreviations AL administrative letter ANS American Nuclear Society ANSI American National Standard Institute CFR Code of Federal Regulations LWR light-water reactor NRC U.S. Nuclear Regulatory Commission QAP quality assurance program RG regulatory guide TS technical specifications UFSAR updated final safety analysis report 9.0 Principal Contributor Yiu Law, NRR Date: November 17, 2022

ML22294A150 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DRO/IOLB/HFTL NAME AKlett KZeleznock BGreen DATE 10/27/2022 10/24/2022 10/25/2022 OFFICE NRR/DRO/IQVB/BC NRR/DSS/STSB/BC OGC - NLO*

NAME KKavanagh VCusumano LShrum DATE 10/24/2022 10/24/2022 10/27/2022 OFFICE NRR/DORL/LPL1/BC NRR/DORL/LPL1/PM NAME HGonzález AKlett DATE 11/16/2022 11/17/2022