ML23082A350
ML23082A350 | |
Person / Time | |
---|---|
Site: | Nine Mile Point |
Issue date: | 04/17/2023 |
From: | Richard Guzman NRC/NRR/DORL/LPL1 |
To: | Rhoades D Constellation Energy Generation |
References | |
EPID L-2022-LLA-0075 | |
Download: ML23082A350 (16) | |
Text
April 17, 2023 Mr. David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT 2 - ISSUANCE OF AMENDMENT NO. 192, REVISION OF SURVEILLANCE REQUIREMENTS ASSOCIATED WITH EMERGENCY DIESEL GENERATOR TESTING (EPID L-2022-LLA-0075)
Dear Mr. Rhoades:
The U.S. Nuclear Regulatory Commission (NRC or the Commission) has issued the enclosed Amendment No. 192 to Renewed Facility Operating License No. NPF-69 for the Nine Mile Point Nuclear Station, Unit 2 (Nine Mile Point 2). The amendment consists of changes to the technical specifications (TSs) in response to your application dated May 24, 2022, as supplemented by letter dated October 28, 2022.
The amendment revises the surveillance requirements (SR) associated with Nine Mile Point 2 TS Section 3.8.1, AC Sources - Operating, to reduce the number of fast starts of the emergency diesel generators (EDGs). Specifically, TS SR 3.8.1.2 is revised to identify the Start Test testing requirements for the EDGs. In addition, a new SR is created to identify the Fast Start testing requirements for the EDGs.
D. Rhoades A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Richard V. Guzman, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410
Enclosures:
- 1. Amendment No. 192 to NPF-69
- 2. Safety Evaluation cc: Listserv
NINE MILE POINT NUCLEAR STATION, LLC LONG ISLAND LIGHTING COMPANY CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 192 Renewed License No. NPF-69
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Exelon Generation Company, LLC dated May 24, 2022, as supplemented by letter dated October 28, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I;
B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Enclosure 1
- 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-69 is hereby amended to read as follows:
2.C.(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 192, are hereby incorporated into this license. Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Digitally signed by Hipolito Hipolito J. J. Gonzalez Date: 2023.04.17 Gonzalez 14:57:56 -04'00' 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: April 17, 2023
ATTACHMENT TO LICENSE AMENDMENT NO. 192 NINE MILE POINT NUCLEAR STATION, UNIT 2 RENEWED FACILITY OPERATING LICENSE NO. NPF-69 DOCKET NO. 50-410 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Page Insert Page 4 4 Replace the following pages of Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages 3.8.1-6 3.8.1-6 3.8.1-18 3.8.1-18
(1) Maximum Power Level Constellation Energy Generation, LLC is authorized to operate the facility at reactor core power levels not in excess of 3988 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 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 192 are hereby incorporated into this license. Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Fuel Storage and Handling (Section 9.1, SSER 4)*
- a. Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high.
- b. When not in the reactor vessel, no more than three fuel assemblies shall be allowed outside of their shipping containers or storage racks in the New Fuel Vault or Spent Fuel Storage Facility.
- c. The above three fuel assemblies shall maintain a minimum edge-to-edge spacing of twelve (12) inches from the shipping container array and approved storage rack locations.
- d. The New Fuel Storage Vault shall have no more than ten fresh fuel assemblies uncovered at any one time.
(4) Turbine System Maintenance Program (Section 3.5.1.3.10, SER)
The operating licensee shall submit for NRC approval by October 31, 1989, a turbine system maintenance program based on the manufacturers calculations of missile generation probabilities.
(Submitted by NMPC letter dated October 30, 1989 from C.D. Terry and approved by NRC letter dated March 15, 1990 from Robert Martin to Mr. Lawrence Burkhardt, III).
The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report (SER) and/or its supplements wherein the license condition is discussed.
Renewed License No. NPF-69 Amendment 117 through 191 192
AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.2 - - - - - - - - - - -- - - -NOTES- - - - - - - - - - - - - - - -
- 1. All DG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.
- 2. A modified DG start involving idling and gradual acceleration to synchronous speed may be used for this SR as recommended by the manufacturer. When modified start procedures are not used, the time, voltage, and frequency tolerances of SR 3.8.1.19 must be met.
Verify each required DG starts from standby In accordance with conditions and achieves steady state voltage the Surveillance 3950 V and 4370 V and frequency 58.8 Hz Frequency Control and 61.2 Hz. Program (continued)
NMP2 3.8.1-6 Amendment 91, 152, 174, 192
AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.18 - - - - - - - - - - - - - - - -NOTE- - - - - - - - - - - - - - -
All DG starts may be preceded by an engine prelube period.
Verify, when started simultaneously from In accordance with standby condition, each Division 1, 2, the Surveillance and 3 DG achieves, in 10 seconds, voltage Frequency Control 3950 V for Division 1 and 2 DGs and Program 3820 V for Division 3 DG, and frequency 58.8 Hz for Division 1 and 2 DGs and 58.0 Hz for Division 3 DG.
SR 3.8.1.19 - - - - - - - - - - - - - - -NOTE- - - - - - - - - - - - - - -
All DG starts may be preceded by an engine prelube period.
Verify each required DG start from standby In accordance with conditions and achieves: the Surveillance Frequency Control
- a. In 10 seconds, voltage 3950 V for Program Division 1 and 2 DGs and 3820 V for Division 3 DG, and frequency 58.8 Hz for Division 1 and 2 DGs and 58.0 Hz for Division 3 DG; and
- b. Steady state voltage 3950 V and 4370 V and frequency 58.8 Hz and 61.2 Hz.
NMP2 3.8.1-18 Amendment 91, 152, 192
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE REVISION OF SURVEILLANCE REQUIREMENTS ASSOCIATED WITH EMERGENCY DIESEL GENERATOR TESTING AMENDMENT NO. 192 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-69 CONSTELLATION ENERGY GENERATION, LLC NINE MILE POINT NUCLEAR STATION, UNIT 2 DOCKET NO. 50-410
1.0 INTRODUCTION
By letter dated May 24, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22144A018), as supplemented by letter dated October 28, 2022 (ML22301A152), Constellation Energy Generation, LLC (CEG, the licensee) submitted a license amendment request (LAR) for Nine Mile Point Nuclear Station, Unit 2 (NMP2). The proposed amendment would revise the Surveillance Requirements (SR) 3.8.1.2 associated with Technical Specifications (TS) Section 3.8.1, "AC Sources Operating," to reduce the number of fast starts of the emergency diesel generators (EDGs). Specifically, the Start Test and Fast-Start test requirements currently in SR 3.8.1.2 would be revised to identify SR 3.8.1.2 as only the "Start Test" requirements for the EDGs. A new SR 3.8.1.19 would be created to identify the "Fast-Start" testing requirements for the EDGs.
The supplemental letter dated October 28, 2022,1 provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC or the Commission) staffs original proposed no significant hazards consideration determination as published in the Federal Register on September 6, 2022 (87 FR 54553).
1 The supplemental letter revises the written description of the proposed changes pertaining to the Notes for SR 3.8.1.2 and SR 3.8.1.19. Attachment 1 to the supplemental letter provides an updated Section 2.0 that supersedes Section 2.0 of the LAR in its entirety.
Enclosure 2
2.0 REGULATORY EVALUATION
2.1 System Design and Operation AC Sources - Shutdown The LAR Section 3.0 states, in part:
The Class 1E AC distribution system supplies electrical power to three divisional load groups, Divisions 1, 2, and 3, with each division powered by an independent Class 1E 4.16 kV emergency bus (refer to LCO 3.8.8, "Distribution Systems -
Operating"). The Division 1 and 2 (4.16 kV) emergency buses each have one separate and independent offsite source of power. The Division 3 (4.16 kV) emergency bus can be supplied by either offsite source. Each 4.16 kV emergency bus has a dedicated onsite DG. The ESF systems of any two of the three divisions provide for the minimum safety functions necessary to shut down the unit and maintain it in a safe shutdown condition.
The Division 1 and 3 (4.16 kV) emergency buses are normally supplied by the tertiary winding of reserve station service transformer 2RTX-XSR1A while the Division 2 (4.16 kV) emergency bus is normally supplied by the tertiary winding of reserve station service transformer 2RTX-XSR1B. Control power for the 4.16 kV breakers is supplied from the Class 1E batteries.
Each DG [diesel generator] must be capable of starting, accelerating to rated speed and voltage, and connecting to its respective ESF bus on detection of bus undervoltage. This sequence must be accomplished within 13.20 seconds. The 13.20 second start time includes the Loss of Voltage - Time Delay Function Allowable Value specified in LCO 3.3.8.1. Each DG must also be capable of accepting required loads within the assumed loading sequence intervals and must continue to operate until offsite power can be restored to the 4.16 kV emergency buses. These capabilities are required to be met from a variety of initial conditions such as DG in standby with engine hot and DG in standby with engine at ambient conditions. Additional DG capabilities must be demonstrated to meet required Surveillances, e.g., capability of the DG to revert to standby status on an ECCS signal while operating in parallel test mode. Proper sequencing of loads, including tripping of nonessential loads, is a required function for DG operability.
2.2 Proposed Change As stated by the licensee in the LAR:
The proposed change will revise NMP2 TS SR 3.8.1.2 to remove and relocate the "Fast-Start" test requirements for the EDGs into a separate SR. This proposed change will align NMP2 SR 3.8.1.2 with the "Start Test" described in section 2.2.1 of [Regulatory Guide (RG) 1.9, Selection, Design, Qualification, and Testing of Emergency Diesel Generator Units Used as Class 1E Onsite Electric Power Systems at Nuclear Power Plants, Revision 3 (ML003739929)],
and with SR 3.8.1.2 in [NUREG -1434, Standard Technical Specifications -
General Electric BWR/6 Plants: Specifications, Revision 5, Volume 1
(ML21271A582)]. The relocated "Fast-Start" testing requirements will be in a new SR (SR 3.8.1.19) and will align with the "Fast-Start" test [SR 3.8.1.7] as described in [NUREG-1434, Revision 5 and RG 1.9, Revision 3].
2.2.1 Changes to SR 3.8.1.2 The current SR 3.8.1.2 reads as follows:
NOTE--------------------------------
All DG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.
Verify each required DG starts from standby conditions and achieves:
- a. In 10 seconds, voltage 3950 V for Division 1 and 2 DGs and 3820 V for Division 3 DG, and frequency 58.8 Hz for Division 1 and 2 DGs and 58.0 Hz for Division 3 DG; and
- b. Steady state voltage 3950 V and 4370 V and frequency 58.8 Hz and 61.2 Hz.
Frequency: In accordance with the Surveillance Frequency Control Program SR 3.8.1.2 will be revised as follows:
NOTES-----------------------------
- 1. All DG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.
- 2. A modified DG start involving idling and gradual acceleration to synchronous speed may be used for this SR as recommended by the manufacturer. When modified start procedures are not used, the time, voltage, and frequency tolerances of SR 3.8.1.19 must be met.
Verify each required DG starts from standby conditions and achieves steady state voltage 3950 V and 4370 V and frequency 58.8 Hz and 61.2 Hz.
The frequency for this SR will remain as described in accordance with the Surveillance Frequency Control Program (SFCP).
2.2.2 New SR 3.8.1.19 The new SR 3.8.1.19 will read as follows:
NOTE--------------------------------
All DG starts may be preceded by an engine prelube period.
Verify each required DG starts from standby conditions and achieves:
- a. In 10 seconds, voltage 3950 V for Division 1 and 2 DGs and 3820 V for Division 3 DG, and frequency 58.8 Hz for Division 1 and 2 DGs and 58.0 Hz for Division 3 DG; and
- b. Steady state voltage 3950 V and 4370 V and frequency 58.8 Hz and 61.2 Hz.
The frequency for this SR will be in accordance with the SFCP [Surveillance Frequency Control Program].
In Section 2.0 of the supplemental letter dated October 28, 2022, the licensee states:
The proposed changes in this License Amendment Request (LAR) to separate the "Start Test" from the "Fast-Start" test will optimize the EDG testing strategy to minimize wear and tear on the EDGs. A modification will be implemented under the 50.59 process to support the testing changes. Until the EDG modifications are in place, EDG testing will continue with manufacturer recommended start procedures as defined in proposed Note 2 of TS SR 3.8.1.2.
In addition, the proposed change will delete a footnote related to current SR 3.8.1.2 on TS page 3.8.1-6 that reads, "*Following return to OPERABILITY of the HPCS System, the past due Surveillances will be completed by January 18, 2019," because the past due SR 3.8.1.2 was completed as part of the actions associated with the Emergency License Amendment No. 174 (ML18342A015, dated December 9, 2018) for a one-time extension to the Completion Time for LCO 3.5.1, Required Action B.2.
The supplemental letter dated October 28, 2022, provides clarification and addresses inconsistencies with the written description of proposed changes in Section 2.0 of the LAR to align with the proposed changes illustrated in the marked-up TS pages in Attachment 2 of the LAR. The supplement revises the written description of the proposed changes pertaining to the Notes for SR 3.8.1.2 and SR 3.8.1.19. Attachment 1 to the Supplement provides the revised Section 2.0 and supersedes Section 2.0 of the referenced document in its entirety.
2.3 Regulatory Requirements The following NRC requirements are applicable to the review of the proposed changes:
The requirements in Title 10 of Code of Federal Regulations (CFR) 50.36 Technical specifications, requires, in part, that TSs shall be included by applicants for a license authorizing operation of a production or utilization facility. The regulations under 10 CFR 50.36(c) require that TSs include items in five specific categories related to station operation. These categories are (1) safety limits (SLs), limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) SRs; (4) design features; and (5) administrative controls. The proposed changes in this LAR relate to the SR
category. The regulation under 10 CFR 50.36(c)(3) states that 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.
The following guidance documents are applicable to the proposed changes:
RG 1.9, "Selection, Design, and Qualification of Diesel-Generator Units Used as Standby (Onsite) Electric Power Systems at Nuclear Power Plants Revision 3, dated July 1993 (ML003739929), integrates the guidance of RG 1.108, Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants, Revision 1 dated August 1977 (ML003740376); RG 1.9, Revision 2, and GL 84-15, and it endorses, as appropriate, guidelines set forth in Institute of Electrical and Electronics Engineers (IEEE) Std 387-1984 "Selection, Design, and Qualification of Diesel-Generator Units Used as Standby (Onsite) Electric Power Systems at Nuclear Power Plants.
RG 1.155, "Station Blackout," dated August 1998 (ML003740034) discusses an acceptable method for determining the reliability of the diesel generator as one of the factors to be used to determine the length of time a plant should be able to cope with a station black out.
NUREG-1434, General Electric Standard Technical Specifications BWR/6 Plants Specifications, Revision 5, Volume 1, dated September 2021 (ML21271A582).
3.0 TECHNICAL EVALUATION
Section 2.2.1 in RG 1.9, Revision 3, provides the following test description for Start Tests:
Demonstrate proper startup from standby conditions, and verify that the required design voltage and frequency is attained. For these tests, the emergency diesel generator can be slow-started and reach rated speed on a prescribed schedule that is selected to minimize stress and wear.
Section 2.2.3 in RG 1.9, Revision 3, provides the following test description for Fast-Start Tests:
Demonstrate that each emergency diesel generator unit starts from standby conditions. If a plant normally has in operation, prewarm systems designed to maintain lube oil and jacket water cooling at certain temperatures or pre lubrication systems or both, this will constitute normal standby conditions for that plant. Verify that the emergency diesel generator reaches required voltage and frequency within acceptable limits and time as defined in the plant technical specifications.
Table 1 of RG 1.9 prescribes the test frequencies for the Start Test as a monthly surveillance, and for the Fast-Start Test at six month testing and every scheduled refueling outage period.
The proposed change will revise NMP2 TS SR 3.8.1.2 to relocate the "Fast-Start" test requirements for the EDGs into a separate SR. This change will align NMP2 SR 3.8.1.2 with the "Start Test" described in Section 2.2.1 of RG 1.9, Revision 3, and with SR 3.8.1.2 in NUREG -
1434, Revision 5. The relocated "Fast-Start" testing requirements will be in a new SR 3.8.1.19
and will align with the SR 3.8.1.7 as described in NUREG-1434, Revision 5 and RG 1.9, Revision 3. NMP2 SR 3.8.1.2 requires the EDGs to be periodically tested and currently includes both the "Start Test" and the "Fast-Start" testing requirements.
The NRC staff reviewed the proposed changes in the LAR that would revise SR 3.8.1.2 to describe only the "Start Test" requirements for the EDGs, moving the Fast-Start requirements to the proposed new SR 3.8.1.19. The changes to SR 3.8.1.2 include adding a second NOTE regarding modified starts. The NRC staff notes that there are no proposed changes to the voltage or frequency acceptance criteria for SR 3.8.1.2. The addition of Note 2 to SR 3.8.1.2 would allow for a modified, gradual EDG start in accordance with the manufacturer's recommendations. The licensee stated in the LAR that until the EDG modifications under the 10 CFR 50.59 process are in place, the EDG testing will continue with manufacturer recommended start procedures per proposed Note 2 of SR 3.8.1.2. The NRC staff finds the addition of Note 2 acceptable because the gradual start would minimize unnecessary stress and wear on EDGs due to testing, improving reliability so that the EDGs testing will assure the necessary quality of systems per 10 CFR 50.36(c)(3) and consistent with RG 1.9.
Additionally, the NRC staff reviewed the proposed change to remove footnote
- to SR 3.8.1.2 described above in section 2.2 of this safety evaluation. The footnote, added in License Amendment No. 174 dated December 9, 2018 (ML18342A015), was related to a one-time TS change for the Division 3 EDG maintenance, which supports the high pressure core spray (HPCS) system. The NRC staff finds the removal of the footnote, which expired in 2019, is acceptable because it is editorial in nature and clarifies the current requirements.
The NRC staff reviewed the proposed new SR 3.8.1.19 representing the Fast-Start test. The requirements in proposed SR 3.8.1.19 were relocated from current SR 3.8.1.2. The proposed changes to separate the "Start Test" from the "Fast-Start" test will allow the licensee to optimize the EDG testing strategy to minimize stress and wear on the EDGs. RG 1.9 prescribes a less frequent test interval for the Fast-Start test versus the Start Test. The NRC staff notes that there are no changes to the voltage or frequency acceptance criteria moved from SR 3.8.1.2 to new SR 3.8.1.19. The NRC staff finds proposed new SR 3.8.1.19 acceptable because other than the separation from SR 3.8.1.2, the new, less frequent EDG "Fast-Start" test interval (which will be performed in accordance with the SFCP) continues to meet 10 CFR 50.36(c)(3) and is consistent with RG 1.9.
Technical Evaluation Conclusion The proposed changes for NMP2 revise SR 3.8.1.2 to identify the "Start Test" requirements for the EDGs and relocate the "Fast-Start" testing requirements for the EDGs to a new SR 3.8.1.9.
These changes appropriately follow the guidance of NUREG-1434, Revision 5, and RG 1.9, Revision 3.
The NRC staff reviewed the NMP2 proposed TS changes and finds that NMP2 SR 3.8.1.2 and NMP2 SR 3.8.1.19 are consistent with the NUREG-1434, Revision 5 (SR 3.8.1.2 and SR 3.8.1.7, respectively). The proposed TS changes are in compliance with the requirements of 10 CFR 50.36(c)(3) and consistent with RG 1.9. Based on the above evaluation, the NRC staff concludes that the NMP2 TS proposed changes are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the New York State official was notified of the proposed issuance of the amendment on March 6, 2023. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on September 6, 2022 (87 FR 54553). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: H. Kodali, NRR A. Foli, NRR K. West, NRR Date: April 17, 2023
ML23082A350 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DEX/EEEB/BC NAME RGuzman KEntz WMorton DATE 03/24/2023 3/27/2023 02/08/2023 OFFICE NRR/DSS/STSB/BC NRR/DEX/EMIB/BC OGC (NLO)
NAME VCusumano SBailey KDowling DATE 03/31/2023 03/31/2023 04/05/2023 OFFICE NRR/DORL/LPL1/BC NRR/DORL/LPL1/PM NAME H González RGuzman DATE 04/14/2023 04/17/2023