ML23037A971
| ML23037A971 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  (NPF-057, DPR-070, DPR-075) |
| Issue date: | 03/09/2023 |
| From: | James Kim NRC/NRR/DORL/LPL1 |
| To: | Carr E Public Service Enterprise Group |
| References | |
| EPID L-2022-LLA-0092 | |
| Download: ML23037A971 (25) | |
Text
March 9, 2023 Mr. Eric Carr President and Chief Nuclear Officer PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GENERATING STATION AND SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 ISSUANCE OF AMENDMENT NOS. 233, 344, AND 325 RE: RELOCATE TECHNICAL SPECIFICATION STAFF QUALIFICATION REQUIREMENTS TO THE PSEG QUALITY ASSURANCE TOPICAL REPORT (EPID L-2022-LLA-0092)
Dear Mr. Carr:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment Nos. 233, 344, and 325 to Renewed Facility Operating License Nos. NPF-57, DPR-70, and DPR-75, for the Hope Creek Generating Station (Hope Creek), and Salem Nuclear Generating Station, Unit Nos. 1 and 2 (Salem), respectively, in response to your application dated June 22, 2022.
The amendments relocate the Salem Facility Staff Qualification and Hope Creek Unit Staff Qualification Requirements to the PSEG Quality Assurance Topical Report.
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
James S. Kim, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-354, 50-272, and 50-311
Enclosures:
- 1. Amendment No. 233 to NPF-57
- 2. Amendment No. 344 to DPR-70
- 3. Amendment No. 325 to DPR-75
- 4. Safety Evaluation cc: Listserv
PSEG NUCLEAR LLC DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 233 Renewed License No. NPF-57
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by PSEG Nuclear LLC, dated June 22, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 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.
- 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. NPF-57 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 233, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
The license amendment is effective as of its date of issuance and shall be implemented within 120 daysof the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 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: March 9, 2023 Hipolito J.
Gonzalez Digitally signed by Hipolito J. Gonzalez Date: 2023.03.09 08:46:07 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 233 HOPE CREEK GENERATING STATION RENEWED FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 Replace the following page of the Renewed Facility Operating License No. NPF-57 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 page of Renewed Facility Operating License No. NPF-57 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 6-6 6-6
reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4)
PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, 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; (5)
PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, 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 (6)
PSEG 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. Mechanical disassembly of the GE14i isotope test assemblies containing Cobalt-60 is not considered separation.
(7)
PSEG Nuclear LLC, pursuant to the Act and 10 CFR Part 30, to intentionally produce, possess, receive, transfer, and use Cobalt-60.
C.
This renewed 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 now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level PSEG Nuclear LLC is authorized to operate the facility at reactor core Power levels not in excess of 3902 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 233, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Renewed License No. NPF-57 Amendment No. 233
ADMINISTRATIVE CONTROLS 6.2.3 SHIFT TECHNICAL ADVISOR 6.2.3.1 The Shift Technical Advisor shall provide advisory technical support to the Senior Nuclear Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to safe operation of the unit. The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and controls in the control room.
6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications referenced for comparable positions as specified in the PSEG Nuclear Quality Assurance Topical Report.
6.3.2 The Operations Manager or Assistant Operations Manager shall hold a senior reactor operator license. The Senior Nuclear Shift Supervisors, and Nuclear Shift Supervisors, shall hold a senior reactor operator license. The Nuclear Control Operators shall hold a reactor operator license.
6.3.3 The Operations Manager shall meet one of the following:
(1)
Hold a senior reactor operator license, or (2)
Have held a senior reactor operator license for this or a similar unit (BWR), or (3)
Have been certified at an appropriate simulator for equivalent senior operator knowledge.
6.4 TRAINING 6.4.1 DELETED 6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Fire Protection Manager and shall meet or exceed the requirements of the SRP (NUREG-0800)
Section 13.2.2.II.6, 10 CFR 50 Appendix R and Branch Technical Position CMEB 9.5.1, Section C.3.d.
6.5 REVIEW AND AUDIT (THIS SECTION DELETED)
HOPE CREEK 6-6 Amendment No. 233
PSEG NUCLEAR LLC CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 344 Renewed License No. DPR-70
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by PSEG Nuclear LLC, acting on behalf of itself and Exelon Generation Company, LLC (the licensees), dated June 22, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 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.
- 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-70 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 344, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG 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 120 daysof the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Hipólito J. González, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License and Technical Specifications Date of Issuance: March 9, 2023 Hipolito J.
Gonzalez Digitally signed by Hipolito J. Gonzalez Date: 2023.03.09 08:46:27 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 344 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 RENEWED FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Replace the following page of Renewed Facility Operating License No. DPR-70 with the attached revised page as indicated. 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 page of Renewed Facility Operating License No. DPR-70 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 6-7 6-7 Renewed License No. DPR-70 Amendment No. 344 (4)
PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70 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; (5)
PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, 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 (6)
PSEG Nuclear LLC, 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 the facility.
C. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of 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 or incorporated below:
(1)
Maximum Power Level PSEG Nuclear LLC is authorized to operate the facility at a steady state reactor core power level not in excess of 3459 megawatts (one hundred percent of rated core power).
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 344, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications, and the Environmental Protection Plan.
(3)
Deleted Per Amendment 22, 11-20-79 (4)
Less than Four Loop Operation PSEG Nuclear LLC shall not operate the reactor at power levels above P-7 (as defined in Table 3.3-1 of Specification 3.3.1.1 of Appendix A to this renewed license) with less than four (4) reactor coolant loops in operation until safety analyses for less than four loop operation have been submitted by the licensees and approval for less than four loop operation at power levels above P-7 has been granted by the Commission by Amendment of this renewed license.
(5)
PSEG Nuclear LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety
ADMINISTRATIVE CONTROLS 6.2.3 SHIFT TECHNICAL ADVISOR 6.2.3.1 The Shift Technical Advisor shall serve in an advisory capacity to the Senior Nuclear Shift Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit.
6.2.3.2 The Shift Technical Advisor shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents.
6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications referenced for comparable positions as specified in the PSEG Nuclear Quality Assurance Topical Report.
6.3.2 The Operations Manager or Assistant Operations Manager shall hold an SRO license.
The Senior Nuclear Shift Supervisors and Nuclear Shift Supervisors shall each hold a senior reactor operator license. The Nuclear Control Operators shall hold reactor operator licenses.
6.3.3 The Operations Manager shall meet one of the following:
- 1)
Hold an SRO license, or
- 2)
Have held an SRO license for a similar unit (PWR), or
- 3)
Have been certified at an appropriate simulator for equivalent senior operator knowledge.
6.4 DELETED SALEM - UNIT 1 6-7 Amendment No. 344
PSEG NUCLEAR LLC CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 325 Renewed License No. DPR-75
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by PSEG Nuclear LLC, acting on behalf of itself and Exelon Generation Company, LLC (the licensees), dated June 22, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 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.
- 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-75 is hereby amended, in part, to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 325, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG 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 120 daysof the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Hipólito J. González, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License and Technical Specifications Date of Issuance: March 9, 2023 Hipolito J.
Gonzalez Digitally signed by Hipolito J. Gonzalez Date: 2023.03.09 08:46:45 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 325 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 RENEWED FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Replace the following page of Renewed Facility Operating License No. DPR-75 with the attached revised page as indicated. 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 page of Renewed Facility Operating License No. DPR-75 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 6-7 6-7 Renewed License No. DPR-75 Amendment No. 325 (3)
PSEG Nuclear LLC, pursuant to the Act and 10 CFR Part 70, 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 operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4)
PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use at any time any byproduct, source or 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; (5)
PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, 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 (6)
PSEG 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 renewed 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 now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level PSEG Nuclear LLC is authorized to operate the facility at steady state reactor core power levels not in excess of 3459 megawatts (thermal).
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 325, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
ADMINISTRATIVE CONTROLS 6.2.3 SHIFT TECHNICAL ADVISOR 6.2.3.1 The Shift Technical Advisor shall serve in an advisory capacity to the Senior Nuclear Shift Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit.
6.2.3.2 The Shift Technical Advisor shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents.
6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications referenced for comparable positions as specified in the PSEG Nuclear Quality Assurance Topical Report.
6.3.2 The Operations Manager or Assistant Operations Manager shall hold an SRO license.
The Senior Nuclear Shift Supervisors and Nuclear Shift Supervisors shall each hold a senior reactor operator license. The Nuclear Control Operators shall hold reactor operator licenses.
6.3.3 The Operations Manager shall meet one of the following:
- 1)
Hold an SRO license, or
- 2)
Have held an SRO license for a similar unit (PWR), or
- 3)
Have been certified at an appropriate simulator for equivalent senior operator knowledge.
6.4 DELETED SALEM - UNIT 2 6-7 Amendment No. 325
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 233, 344, AND 325 TO RENEWED FACILITY OPERATING LICENSE NOS. NPF-57, DPR-70, AND DPR-75 PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION AND PSEG NUCLEAR LLC CONSTELLATION ENERGY GENERATION, LLC SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-354, 50-272, AND 50-311
1.0 INTRODUCTION
By application dated June 22, 2022 (Reference 1), PSEG Nuclear LLC (PSEG, the licensee),
submitted a license amendment request (LAR, application) to the U.S. Nuclear Regulatory Commission (NRC, Commission) to change technical specifications (TSs) for Salem Nuclear Generating Station Unit Nos. 1 and 2 (Salem), and the Hope Creek Generating Station (Hope Creek).
The LAR proposes to eliminate the unit staff qualification requirements in the TSs for Salem and Hope Creek and replace these requirements with the unit staff qualification requirements contained in the PSEG Quality Assurance Topical Report (QATR) (Reference 2). While the unit staff qualification requirements in the current QATR remain unchanged, they do differ from the current requirements being eliminated from the TS as proposed in this LAR.
2.0 REGULATORY EVALUATION
The NRC staff considered the following regulations and guidance during its review of the LAR:
Paragraph (c)(5) of Title 10 of the Code of Federal Regulations (10 CFR)
Part 50.36, Technical specifications, describes 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.
NRC Administrative Letter (AL) 95-06, Relocation of Technical Specification Administrative Controls Related to Quality Assurance (Reference 3), contains guidance for relocating requirements from the administrative controls section of TS in cases where adequate controls are provided by other methods. AL 95-06 states that the QATR is a logical candidate for such relocations because of the controls imposed on the QATR 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.
10 CFR 50.54(a) contains 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, establishes the requirements for the design, fabrication, construction, and testing of structures, systems and components (SSCs) for the facility.
The pertinent requirements of Appendix B apply to all activities affecting the safety-related functions of those SSCs and include designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, inspecting, testing, operating, maintaining, repairing, refueling, and modifying SSCs. Criterion II, Quality Assurance Program of Appendix B to 10 CFR Part 50 establishes requirements for indoctrination and training of personnel. It states, in part, that The program shall provide for indoctrination and training of personnel performing activities affecting quality as necessary to assure that suitable proficiency is achieved and maintained.
Regulatory Guide (RG) 1.8, Revisions 1 (Reference 4) and 2 (Reference 5) 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 endorsed ANSI N18.1-1971 (Reference 6) with one exception. Revision 2 of RG 1.8 endorsed ANSI/ANS 3.1-1981 (Reference 7) for certain positions and ANSI N18.1-1971 for other positions, with exceptions, clarifications, and additions.
3.0 TECHNICAL EVALUATION
The proposed LAR would eliminate the unit staff qualification requirements in the TSs for Salem and Hope Creek and replace these requirements with the unit staff qualification requirements contained in the existing PSEG QATR for. While the unit staff qualification requirements in the current QATR remain unchanged, they do differ from the current requirements being eliminated from the TSs as proposed in this LAR. The current revision of the QATR is Revision 88.
3.1 Description of Proposed Changes The Salem TS 6.3.1 currently states:
Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the individual designated as the Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide [RG] 1.8, September 1975, the individual designated as the Operations Manager who shall meet or exceed the minimum qualifications of ANSI N18.1-1971 except as modified by Specification 6.3.3, and the licensed operators who shall comply with the requirements of 10CFR55
[10 CFR 55].
The proposed change will revise Salem TS 6.3.1 to read as follows:
Each member of the facility staff shall meet or exceed the minimum qualifications referenced for comparable positions as specified in the PSEG Nuclear Quality Assurance Topical Report.
The Hope Creek TS 6.3.1 currently states:
Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1981 for comparable positions, except for the individual designated as the Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, the individual designated as the operations manager who shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1981 except as modified by Specification 6.3.3, and the licensed operators who shall comply with the requirements of 10 CFR Part 55.
The proposed change will revise the Hope Creek TS 6.3.1 to read as follows:
Each member of the unit staff shall meet or exceed the minimum qualifications referenced for comparable positions as specified in the PSEG Nuclear Quality Assurance Topical Report.
3.2 Evaluation of Proposed Changes In deciding whether an amendment to a license will be issued, the NRC staff 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 changes to decide whether eliminating the unit staff qualification requirements in TS 6.3.1 for Salem and Hope Creek will continue to adequately define the unit staff qualification requirements sufficient to meet the requirements of 10 CFR 50.36(c)(5) and assure that the referenced unit staff qualification requirements in the QATR will adequately maintain the training and qualification programs in accordance with 10 CFR 50.120.
As discussed in Section 3.1 of this safety evaluation, the licensee proposed to eliminate the unit staff qualification requirements in TS 6.3.1 for Salem and Hope Creek and reference the existing PSEG QATR for these unit staff qualification requirements. In its request, the licensee stated that the amendment is consistent with NRC Administrative Letter 95-06 and would not change any current unit staff qualification requirements.
For Salem, the NRC staff reviewed the current Salem TS requirements and the QATR requirements for unit staff qualification. The Salem TS references standard ANSI N18.1-1971 for comparable positions except the Radiation Protection Manager, who shall meet or exceed the qualification of RG 1.8, September 1975, the Operations Manager, who shall meet or exceed the minimum qualifications of ANSI N18.1-1971 except as modified by Specification 6.3.3, and the licensed operators, who shall comply with the requirements of 10 CFR Part 55.
In the QATR, Appendix C, Section 1.3.2, Salem references standard ANSI/ANS 3.1-1981 for positions equivalent to shift supervisor, senior operator, licensed operator, and shift technical advisor, while it references ANSI/ANS N18.1-1971 for other positions. It also states that management position for operations shall either hold a Senior Reactor Operator (SRO) license or have held an SRO license for a similar unit (Pressurized Water Reactor (PWR)) or have been certified at an appropriate simulator for equipment senior operator knowledge. This is consistent with TS 6.3.3. It also states that licensed operator qualifications and training shall be in accordance with 10 CFR Part 55. This is consistent with TS 6.3.1 that is being eliminated. In addition, it also states that the management position responsible for radiation protection shall meet or exceed the qualification of RG 1.8, September 1975. This is consistent with TS 6.3.1 that is being eliminated.
The QATR also specifically notes that for Salem:
Section 6.3.1 of the Salem TS indicates that the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971. Actual staff qualifications, however, is governed by the Salem UFSAR and QATR commitment to ANSI /ANS 3.1-1981.
Because ANSI/ANS 3.1-1981 has more stringent and exacting standards than ANS N18.1-1971, the Salem TS requirements are satisfied.
For Hope Creek, the NRC staff reviewed the current Hope Creek TS requirements and the QATR requirements for unit staff qualification. The Hope Creek TS references standard ANSI/ANS 3.1-1981 for comparable positions except the Radiation Protection Manager, who shall meet or exceed the qualification of RG 1.8, September 1975, the operations manager, who shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1981 except as modified by Specification 6.3.3, and the licensed operators, who shall comply with the requirements of 10 CFR Part 55.
In the QATR, Appendix C, Section 1.3.1, Hope Creek references ANSI/ANS 3.1-1981 for positions equivalent to shift supervisor, senior operator, licensed operator, and shift technical advisor, while it references ANSI/ANS N18.1-1971 for other positions. It also states that management position for operations shall either hold an SRO license or have held an SRO license for a similar unit (Boling Water Reactor (BWR)) or have been certified at an appropriate simulator for equipment senior operator knowledge. This is consistent with TS 6.3.3. It also states that licensed operator qualifications and training shall be in accordance with 10 CFR Part 55. This is consistent with TS 6.3.1 that is being eliminated. In addition, it also states that the management position responsible for radiation protection shall meet or exceed the qualifications of RG 1.8, September 1975. This is consistent with TS 6.3.1 that is being eliminated.
The NRC staff reviewed the two standards ANS N18.1-1971 and ANSI/ANS 3.1-1981 and identified the following discrepancies:
For some positions such as Manager, Operations Manager, Maintenance Manager and Technical Manager, ANSI N18.1-1971 has a higher number of years of required power plant experience than those in ANSI/ANS 3.1-1981.
ANSI/ANS 3.1-1981 includes multiple positions and their associated qualification requirements, such as Training Manager, Senior Operator, Quality Assurance and Shift Technical Advisor that are not in ANSI N18.1-1971.
ANSI N18.1-1971 is endorsed in Revision 1 (1-R) of RG 1.8, while ANSI/ANS 3.1-1981 is endorsed in Revision 2 of RG 1.8.
The NRC staff recognizes that while there are differences between the two standards ANSI N18.1-1971 and ANSI/ANS 3.1-1981, these two standards are often used interchangeably and supplement each other. The NRC staff also recognizes that while switching from ANSI N18.1-1971 to ANSI/ANS 3.1-1981 for Salem, the number of years of required power plant experience for some positions is reduced, however, ANSI/ANS 3.1-1981 provides more specific positions and their associated qualification requirements such as Quality Assurance and Shift Technical Advisor. In addition, RG 1.8, Revision 2 endorses ANSI/ANS 3.1-1981 for the positions of shift supervisor, senior operator, licensed operator, shift technical advisor and radiation protection supervisory personnel, while all other positions remain with ANS N18.1-1971. Therefore, the requirements set forth in Criterion II of Appendix B to 10 CFR Part 50 will continue to be met, and the NRC staff finds that the licensees unit staff qualification requirements will not be reduced by eliminating these requirements from the TSs and referencing the QATR for these requirements for both Salem and Hope Creek.
The NRC staff concludes that the proposed change to eliminate the unit staff qualification requirements in TS 6.3.1 and referencing the existing QATR for these requirements for Salem and Hope Creek is acceptable because the licensees overall unit staff qualification requirements will not be reduced by this LAR. In addition, if the licensee makes future changes to the unit staff qualification requirements that are in the QATR, then these changes must be in accordance with Appendix B of 10 CFR Part 50 and 10 CFR 50.54(a).Any reduction in commitments associated with the licensees unit staff qualification requirements in the QATR will require NRC approval prior to implementation in accordance with 10 CFR 50.54(a)(4).
Therefore, the NRC staff finds that the proposed TS changes and referencing the QATR for the licensees unit staff qualification requirements are acceptable because the proposed TS continue to assure operation of the facility in a safe manner in accordance with 10 CFR 50.36(c)(5).
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the New Jersey State official was notified of the proposed issuance of the amendments on February 9, 2023. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change the format of the license or permit or otherwise make editorial, corrective or other minor revisions. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, as published in the Federal Register on August 9, 2022 (87 FR 48518), and there has been no public comment on such finding. 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), 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 Commissions 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.
7.0 REFERENCES
[1] Mannai, D, PSEG Nuclear LLC letter to U.S. Nuclear Regulatory Commission, License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to the PSEG Nuclear LLC Quality Assurance Topical Report, dated June 22, 2022, (ML22174A294).
[2] PSEG Nuclear, LLC Salem and Hope Creek Generating Stations Quality Assurance Topical Report (QATR) NO-AA-10, Revision 88, dated June 28, 2019, (ML20042D666).
[3] Administrative Letter 95-06, Relocation of Technical Specification Administrative Controls Related to Quality Assurance, dated December 12, 1995, (ML031110271).
[4] Regulatory Guide 1.8, Revision 1, Personnel Selection and Training, dated September 1975 and reissued in May 1977 as Revision 1-R, (ML12305A250).
[5] Regulatory Guide 1.8, Revision 2, Qualification and Training of Personnel for Nuclear Power Plants, dated April 1987, (ML003739928).
[6] American National Standards Institute, ANSI N18.1-1971, Selection and Training of Nuclear Power Plant Personnel, dated March 18, 1971.
[7] American Nuclear Society, ANSI/ANS 3.1-1981, Selection, Qualification and Training of Personnel for Nuclear Power Plants, dated December 17, 1981.
Principal Contributor: Y. Law, NRR Date: March 9, 2023
ML23037A971 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DRO/IQVB/BC NRR/DRO/IOLB/BC NAME JKim KEntz KKavanagh LNist DATE 2/8/2023 2/8/2023 1/25/2023 2/15/2023 OFFICE NRR/DSS/STSB/BC OGC - NLO NRR/DORL/LPL1/BC NRR/DORL/LPL1/PM NAME VCusumano KDowling HGonzalez JKim DATE 2/8/2023 2/23/2023 3/9/2023 3/9/2023