ML20303A024
| ML20303A024 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/09/2020 |
| From: | Shawn Williams Plant Licensing Branch II |
| To: | Burchfield J Duke Energy Carolinas |
| Stone Z | |
| References | |
| EPID L-2020-LLA-0075 | |
| Download: ML20303A024 (19) | |
Text
December 9, 2020 Mr. J. Ed Burchfield, Jr.
Vice President, Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672-0752
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 - ISSUANCE OF AMENDMENT NOS. 419, 421, AND 420 RE: TSTF-272, REFUELING BORON CONCENTRATION CLARIFICATION (EPID L-2020-LLA-0075)
Dear Mr. Burchfield:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 419 to Renewed Facility Operating License (RFOL) No. DPR-38, Amendment No. 421 to RFOL No. DPR-47, and Amendment No. 420 to RFOL No. DPR-55 for Oconee Nuclear Station (Oconee), Units 1, 2, and 3, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated April 13, 2020.
The amendments revise the TS requirements for the boron concentration based on Technical Specifications Task Force (TSTF) traveler No. 272, Revision 1, Refueling Boron Concentration Clarification.
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commissions monthly Federal Register notice.
J.E. Burchfield, Jr. If you have any questions, please contact me at (301) 415-1009 or by e-mail at Shawn.Williams@nrc.gov.
Sincerely,
/RA/
Shawn Williams, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, 50-287
Enclosures:
- 1. Amendment No. 419 to DPR-38
- 2. Amendment No. 421 to DPR-47
- 3. Amendment No. 420 to DPR-55
- 4. Safety Evaluation cc: Listserv
DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 419 Renewed License No. DPR-38
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 1 (the facility) Renewed Facility Operating License No. DPR-38 filed by Duke Energy Carolinas, LLC (the licensee), dated April 13, 2020, 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.
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 3.B of Renewed Facility Operating License No. DPR-38 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 419 are hereby incorporated in the license. The licensee 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 120 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Digitally signed by Michael T. Markley Markley Date: 2020.12.09 08:25:48 -05'00' Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: December 9, 2020
DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 421 Renewed License No. DPR-47
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 2 (the facility) Renewed Facility Operating License No. DPR-47 filed by Duke Energy Carolinas, LLC (the licensee), dated April 13, 2020, 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.
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 3.B of Renewed Facility Operating License No. DPR-47 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 421 are hereby incorporated in the license. The licensee 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 120 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Digitally signed by Michael T. Markley Markley Date: 2020.12.09 08:26:27 -05'00' Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: December 9, 2020
DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 420 Renewed License No. DPR-55
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 3 (the facility) Renewed Facility Operating License No. DPR-55 filed by Duke Energy Carolinas, LLC (the licensee), dated April 13, 2020, 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.
Enclosure 3
- 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 3.B of Renewed Facility Operating License No. DPR-55 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 420 are hereby incorporated in the license. The licensee 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 120 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Digitally signed by Michael T. Markley Markley Date: 2020.12.09 08:27:01 -05'00' Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: December 9, 2020
ATTACHMENT TO AMENDMENT NO. 419 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-38 AMENDMENT NO. 421 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-47 AMENDMENT NO. 420 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-55 OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DOCKET NOS. 50-269, 50-270, AND 50-287 Replace the following pages of the Renewed Facility Operating Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert License License DPR-38, page 3 DPR-38, page 3 DPR-47, page 3 DPR-47, page 3 DPR-55, page 3 DPR-55, page 3 TSs TSs 3.9.1-1 3.9.1-1
A. Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2568 megawatts thermal.
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 419 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
C. This license is subject to the following antitrust conditions:
Applicant makes the commitments contained herein, recognizing that bulk power supply arrangements between neighboring entities normally tend to serve the public interest. In addition, where there are net benefits to all participants, such arrangements also serve the best interests of each of the participants. Among the benefits of such transactions are increased electric system reliability, a reduction in the cost of electric power, and minimization of the environmental effects of the production and sale of electricity.
Any particular bulk power supply transaction may afford greater benefits to one participant than to another. The benefits realized by a small system may be proportionately greater than those realized by a larger system. The relative benefits to be derived by the parties from a proposed transaction, however, should not be controlling upon a decision with respect to the desirability of participating in the transaction. Accordingly, applicant will enter into proposed bulk power transactions of the types hereinafter described which, on balance, provide net benefits to applicant. There are net benefits in a transaction if applicant recovers the cost of the transaction (as defined in ¶1 (d) hereof) and there is no demonstrable net detriment to applicant arising from that transaction.
- 1. As used herein:
(a) Bulk Power means electric power and any attendant energy, supplied or made available at transmission or sub-transmission voltage by one electric system to another.
(b) Neighboring Entity means a private or public corporation, a governmental agency or authority, a municipality, a cooperative, or a lawful association of any of the foregoing owning or operating, or proposing to own or operate, facilities for the generation and transmission of electricity which meets each of Renewed License No. DPR-38 Amendment No. 419
A. Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2568 megawatts thermal.
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 421 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
C. This license is subject to the following antitrust conditions:
Applicant makes the commitments contained herein, recognizing that bulk power supply arrangements between neighboring entities normally tend to serve the public interest. In addition, where there are net benefits to all participants, such arrangements also serve the best interests of each of the participants. Among the benefits of such transactions are increased electric system reliability, a reduction in the cost of electric power, and minimization of the environmental effects of the production and sale of electricity.
Any particular bulk power supply transaction may afford greater benefits to one participant than to another. The benefits realized by a small system may be proportionately greater than those realized by a larger system. The relative benefits to be derived by the parties from a proposed transaction, however, should not be controlling upon a decision with respect to the desirability of participating in the transaction. Accordingly, applicant will enter into proposed bulk power transactions of the types hereinafter described which, on balance, provide net benefits to applicant. There are net benefits in a transaction if applicant recovers the cost of the transaction (as defined in ¶1 (d) hereof) and there is no demonstrable net detriment to applicant arising from that transaction.
- 1. As used herein:
(a) Bulk Power means electric power and any attendant energy, supplied or made available at transmission or sub-transmission voltage by one electric system to another.
(b) Neighboring Entity means a private or public corporation, a governmental agency or authority, a municipality, a cooperative, or a lawful association of any of the foregoing owning or operating, or proposing to own or operate, facilities for the generation and transmission of electricity which meets each of Renewed License No. DPR-47 Amendment No. 421
A. Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2568 megawatts thermal.
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 420 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
C. This license is subject to the following antitrust conditions:
Applicant makes the commitments contained herein, recognizing that bulk power supply arrangements between neighboring entities normally tend to serve the public interest. In addition, where there are net benefits to all participants, such arrangements also serve the best interests of each of the participants. Among the benefits of such transactions are increased electric system reliability, a reduction in the cost of electric power, and minimization of the environmental effects of the production and sale of electricity.
Any particular bulk power supply transaction may afford greater benefits to one participant than to another. The benefits realized by a small system may be proportionately greater than those realized by a larger system. The relative benefits to be derived by the parties from a proposed transaction, however, should not be controlling upon a decision with respect to the desirability of participating in the transaction. Accordingly, applicant will enter into proposed bulk power transactions of the types hereinafter described which, on balance, provide net benefits to applicant. There are net benefits in a transaction if applicant recovers the cost of the transaction (as defined in ¶1 (d) hereof) and there is no demonstrable net detriment to applicant arising from that transaction.
- 1. As used herein:
(a) Bulk Power means electric power and any attendant energy, supplied or made available at transmission or sub-transmission voltage by one electric system to another.
(b) Neighboring Entity means a private or public corporation, a governmental agency or authority, a municipality, a cooperative, or a lawful association of any of the foregoing owning or operating, or proposing to own or operate, facilities for the generation and transmission of electricity which meets each of Renewed License No. DPR-55 Amendment No. 420
Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 Boron concentrations of the Reactor Coolant System and the refueling canal shall be maintained within the limit specified in the COLR.
APPLICABILITY: MODE 6.
NOTE------------------------------------------------
Only applicable to the refueling canal when connected to the RCS.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration not A.1 Suspend CORE Immediately within limit. ALTERATIONS.
AND A.2 Suspend positive Immediately reactivity additions.
AND A.3 Initiate action to restore Immediately boron concentration to within limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the limit In accordance with the specified in the COLR. Surveillance Frequency Control Program OCONEE UNITS 1, 2, & 3 3.9.1-1 Amendment Nos. 419, 421, 420
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR AMENDMENT NO. 419 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-38 AMENDMENT NO. 421 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-47 AMENDMENT NO. 420 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DUKE ENERGY CAROLINAS, LLC OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DOCKET NOS. 50-269, 50-270, AND 50-287
1.0 INTRODUCTION
By application dated April 13, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20104A384), Duke Energy Carolinas, LLC (Duke Energy, the licensee) requested changes to the Technical Specifications (TS) for Oconee Nuclear Station (ONS, Oconee), Units 1, 2, and 3. The application seeks to adopt the provisions of Technical Specifications Task Force (TSTF) traveler No. 272, Revision 1, Refueling Boron Concentration Clarification (ADAMS Accession No. ML993540010), and TSTF-421, Revision 0, Revision to RCP [Reactor Coolant Pump] Flywheel Inspection Program (WCAP-15666) (ADAMS Accession No. ML013390280). This safety evaluation addresses the proposed adoption of TSTF-272. The amendment to revise the Oconee TS requirements for the RCP flywheel inspection program based on TSTF-421 was issued on November 25, 2020 (ADAMS Accession No. ML20296A281).
The proposed adoption of TSTF-272 would modify Oconee TS 3.9.1, Boron Concentration.
Specifically, an applicability note would be added to TS 3.9.1, clarifying that the TS limiting condition for operation (LCO) only applies to the refueling canal when that volume is connected to the reactor coolant system (RCS). The U.S. Nuclear Regulatory Commission (NRC, the Commission) approved this change to NUREG-1430, Revision 1, Standard Technical Specifications (STS) - Babcock and Wilcox Plants, in a letter from William D. Beckner, NRC, to James Davis, Nuclear Energy Institute (NEI), dated December 21, 1999 (ADAMS Accession No. ML993630256).
2.0 REGULATORY EVALUATION
2.1 System Description The function of the refueling canal is to allow the flooding of the space above the reactor vessel with borated water during refueling operations. The borated water provides shielding and Enclosure 4
cooling and assures reactor subcriticality during the transfer of fuel between the reactor vessel and the spent fuel pool via the fuel transfer tubes. After refueling operations are completed, the reactor vessel is reassembled and the refueling canal is drained of water to resume normal reactor operations.
Additional information regarding refueling can be found in the Oconee Updated Final Safety Analysis Report (UFSAR), Revision 28, Chapter 9, Section 9.1.4.2 (ADAMS Accession No. ML20189A092).
2.2 Description of Proposed Changes The licensee proposed to revise Oconee TS 3.9.1 by adding a note clarifying that the TS LCO only applies to the refueling canal when that volume is connected to the RCS.
Current TS 3.9.1 states, in part:
LCO 3.9.1 Boron concentrations of the Reactor Coolant System and the refueling canal shall be maintained within the limit specified in the COLR [Core Operating Limits Report].
APPLICABILITY: MODE 6.
Revised TS 3.9.1 would state, in part:
LCO 3.9.1 Boron concentrations of the Reactor Coolant System and the refueling canal shall be maintained within the limit specified in the COLR.
APPLICABILITY: MODE 6.
NOTE----------------------------------------
Only applicable to the refueling canal when connected to the RCS.
2.3 Regulatory Requirements and Guidance Documents The regulatory requirements and guidance documents that are applicable to the review of the license amendment request (LAR) are listed below.
The Atomic Energy Commission (AEC) issued the construction permits for Oconee on November 6, 1967. The plants design approval for the construction phase was based on the proposed general design criteria (GDC) published by the AEC in the Federal Register (32 FR 10213) on July 11, 1967. The GDC, which constitute the licensing bases for Oconee, are those described in the UFSAR, Revision 28, Chapter 3.1, Conformance with NRC General Design Criteria (ADAMS Accession No. ML20189A074) and in applicable UFSAR sections. As discussed in the UFSAR, the licensee made changes to the facilities and committed to some of the GDC from 10 CFR Part 50, Appendix A. Based on its review of the UFSAR and the licensees submittal, the staff identified the following Oconee UFSAR criteria as being applicable to the proposed amendments.
UFSAR, Section 3.1.13, Criterion 13, Fission Process Monitors and controls (Category B),
which states, in part:
Means shall be provided for monitoring and maintaining control over the fission process throughout core life and for all conditions that can reasonably be anticipated to cause variation in reactivity of the core, such as indication of position of control rods and concentration of soluble reactivity control poisons.
UFSAR, Section 3.1.27, Criterion 27, Redundancy of Reactivity Control (Category A), which states, in part:
At least two independent Reactivity Control Systems, preferably of different principles, shall be provided.
UFSAR, Section 3.1.66, Criterion 66, Prevention of Fuel Storage Criticality (Category B),
which states, in part:
Criticality in new and spent fuel storage shall be prevented by physical systems or processes. Such means as geometrically safe configurations shall be emphasized over procedural controls.
The regulation in 10 CFR 50.36, Technical specifications, establishes the requirements for TSs. 10 CFR 50.36(c) requires, in part, that TSs include LCOs and surveillance requirements (SRs).
10 CFR 50.36(c)(2), Limiting conditions for operation, states, in part:
Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met.
10 CFR 50.36(c)(3), Surveillance requirements, states:
Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
TSTF-272, Revision 1, provides guidance for adding an applicability note stating that the boron concentration requirements on the refueling canal and the refueling cavity only apply when those volumes are connected to the RCS.
3.0 TECHNICAL EVALUATION
3.1 Licensees Proposal The Oconee TS LCO 3.9.1 provides the requirements for boron concentration in the RCS and the refueling canal in MODE 6. Specifically, LCO 3.9.1 requires that with the reactor vessel
head unbolted or removed, the boron concentration of the RCS and the refueling canal shall be maintained within the limit specified in the COLR.
Oconee converted to the NUREG-1430 STS via NRC-approved license amendments dated December 16, 1998 (ADAMS Accession No. ML012060036). In the LAR, the licensee explained that with this conversion, the Oconee TS 3.9.1 LCO wording did not include the term refueling cavity. The licensee stated that This deviation was taken because the ONS design does not identify a refueling cavity; the term refueling canal includes the area typically referred to as the refueling cavity.
The licensee proposes to add a note to the applicability that states that the LCO 3.9.1 limits only apply to the refueling canal when it is connected to the RCS. The licensee stated that when the refueling canal is isolated from the RCS, there is no potential for dilution to exist and that in this condition it is not necessary to place a limit on the boron concentration of water in the refueling canal.
3.2 NRC Staff Evaluation Oconee TS 3.9.1 limits the boron concentration of the RCS and the refueling canal during refueling to ensure that the reactor remains subcritical during MODE 6. For MODE 6, Oconee TS SR 3.9.1.1 ensures that the coolant boron concentration in all filled portions of the RCS and the refueling canal is within the COLR limits. The boron concentration of the coolant in each volume is determined periodically by chemical analysis.
The licensee proposed to add a note to the applicability that states that the LCO 3.9.1 limits only apply to the refueling canal when it is connected to the reactor coolant system. The NRC staff finds the proposed change acceptable because it is not necessary to place a limit on the boron concentration in the refueling canal when the refueling canal is isolated from the RCS. When the refueling canal is isolated from the RCS, no potential for a dilution event exists. Additionally, the proposed revision incorporates the generic changes of TSTF-272, Revision 1.
Based on the above, the NRC staff concludes that the proposed amendments meet the regulatory requirements and guidance documents in Section 2.3 of this safety evaluation and, therefore, are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the South Carolina State official was notified of the proposed issuance of the amendments on October 9, 2020. On October 28, 2020, the State official confirmed that the State of South Carolina had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve 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 amendments involve no significant hazards consideration, which was published in the Federal Register on July 14, 2020 (85 FR 42441), 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)(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 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.
Principal Contributors:
J. Wilson, NRR Date of Issuance: December 9, 2020
ML20303A024 *via e-mail OFFICE NRR/DORL/LPL2-1/PM* NRR/DORL/LPL2-1/PM* NRR/ DORL/LPL2-1/LA* NRR/DSS/STSB/BC*
NAME ZStone SWilliams KGoldstein VCusumano DATE 11/04/2020 11/04/2020 11/04/2020 10/20/2020 OFFICE OGC-NLO* NRR/DORL/LPL2-1/BC* NRR/DORL/LPL2-1/PM*
NAME JWachutka MMarkley SWilliams DATE 11/30/2020 12/09/2020 12/09/2020