ML24047A042
| ML24047A042 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/07/2024 |
| From: | Mahesh Chawla Plant Licensing Branch IV |
| To: | Schuetz R Energy Northwest |
| Chawla M | |
| References | |
| EPID L-2023-LLA-0062 | |
| Download: ML24047A042 (1) | |
Text
March 7, 2024 Mr. Robert Schuetz Chief Executive Officer Energy Northwest 76 North Power Plant Loop P.O. Box 968 Richland, WA 99352
SUBJECT:
COLUMBIA GENERATING STATION - ISSUANCE OF AMENDMENT NO. 273 RE: RENEWED FACILITY OPERATING LICENSE AND TECHNICAL SPECIFICATION CLEAN UP (EPID L-2023-LLA-0062)
Dear Robert Schuetz:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 273 to Renewed Facility Operating License (RFOL) No. NPF-21 for the Columbia Generating Station. The amendment consists of changes to the RFOL and Technical Specifications (TSs) in response to your application dated May 1, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23121A294).
The amendment revises the Columbia RFOL and TSs, including editorial changes and the removal of obsolete information.
A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA - S. Lee for/
Mahesh L. Chawla, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-397
Enclosures:
- 1. Amendment No. 273 to NPF-21
- 2. Safety Evaluation cc: Listserv ENERGY NORTHWEST DOCKET NO. 50-397 COLUMBIA GENERATING STATION AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 273 License No. NPF-21
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Energy Northwest (licensee), dated May 1, 2023, 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 paragraphs 2.C.(2) and 2.C.(36) of Renewed Facility Operating License No. NPF-21 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. 273 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(36)
Deleted
- 3.
The license amendment is effective as of its date of issuance and shall be implemented within 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jennivine K. Rankin, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. NPF-21 and the Technical Specifications Date of Issuance: March 7, 2024 Jennivine K. Rankin Digitally signed by Jennivine K. Rankin Date: 2024.03.07 08:56:54 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 273 RENEWED FACILITY OPERATING LICENSE NO. NPF-21 COLUMBIA GENERATING STATION DOCKET NO. 50-397 Replace the following pages of Renewed Facility Operating License No. NPF-21 and the Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Renewed Facility Operating License REMOVE INSERT Technical Specification REMOVE INSERT 3.3.1.1-11 3.3.1.1-11 3.3.5.1-10 3.3.5.1-10 3.3.5.1-11 3.3.5.1-11 3.7.5-2 3.7.5-2 5.2-2 5.2-2 5.3-1 5.3-1
Renewed License No. NPF-21 Amendment No. 273 (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 273 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- a. For Surveillance Requirements (SRs) not previously performed by existing SRs or other plant tests, the requirement will be considered met on the implementation date and the next required test will be at the interval specified in the Technical Specifications as revised in Amendment No. 149.
(3)
Deleted.
(4)
Deleted.
(5)
Deleted.
(6)
Deleted.
(7)
Deleted.
(8)
Deleted.
(9)
Deleted.
(10)
Deleted.
(11)
Deleted.
(12)
Deleted.
(13)
Deleted.
Renewed License No. NPF-21 Amendment No. 225, 266 269 273 (34)
Deleted (35)
The licensee's FSAR, as updated with the license renewal FSAR supplement submitted pursuant to 10 CFR 54.21(d) and supplemented with Appendix A of NUREG-2123 with the exception of Commitments Nos. 55, 56, 57, and 71, and as revised pursuant to the criteria set forth in 10 CFR 50.59, describes certain future programs and activities to be completed before the period of extended operation. Energy Northwest shall complete these activities no later than July 20, 2023 and shall notify the NRC in writing when implementation of these activities is complete.
(36)
Deleted (37) 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Energy Northwest is approved to implement 10 CFR 50.69 using the processes for categorization of Risk-Informed Safety Class (RISC)-1, RISC-2, RISC-3, and RISC-4 structures, systems, and components (SSC) using:
Probabilistic Risk Assessment (PRA) models to evaluate risk associated with internal events, including internal flooding, internal fire, and seismic risk; the shutdown safety assessment process to assess shutdown risk; the Arkansas Nuclear One, Unit 2 passive categorization method to assess passive component risk for Class 2 and Class 3 SSCs and their associated supports; and the results of non-PRA evaluations that are based on a screening of other external hazards updated using the external hazard screening significance process identified in ASME/ANS PRA Standard RA-Sa-2009; as specified in License Amendment No. 269 dated December 15, 2022.
Prior NRC approval, under 10 CFR 50.90, is required for a change to the categorization process specified above.
RPS Instrumentation 3.3.1.1 Columbia Generating Station 3.3.1.1-11 Amendment No. 270 273 Table 3.3.1.1-1 (page 3 of 4)
Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
- 3.
Reactor Vessel Steam Dome Pressure - High 1,2 2
G SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14 SR 3.3.1.1.15 1079 psig
- 4.
Reactor Vessel Water Level - Low, Level 3 1,2 2
G SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14 SR 3.3.1.1.15 9.5 inches
- 5.
- Closure 1
8 F
SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14 SR 3.3.1.1.15 12.5% closed
- 6.
Primary Containment Pressure - High 1,2 2
G SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14 1.88 psig
- 7.
Scram Discharge Volume Water Level - High
- a.
Transmitter/Level Indicating Switch 1,2 2
G SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14 529 ft 9 inches elevation 5(a) 2 H
SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14 529 ft 9 inches elevation
- b.
Transmitter/Level Switch 1,2 2
G SR 3.3.1.1.8 SR 3.3.1.1.10(d)(e)
SR 3.3.1.1.14 529 ft 9 inches elevation 5(a) 2 H
SR 3.3.1.1.8 SR 3.3.1.1.10(d)(e)
SR 3.3.1.1.14 529 ft 9 inches elevation (a)
With any control rod withdrawn from a core cell containing one or more fuel assemblies.
(d)
If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(e)
The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Limiting Trip Setpoint (LTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable.
Setpoints more conservative than the LTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the surveillance procedures (Nominal Trip Setpoint) to confirm channel performance. The LTSP and the methodologies used to determine the as-found and the as-left tolerances are specified in the Licensee Controlled Specifications.
ECCS Instrumentation 3.3.5.1 Columbia Generating Station 3.3.5.1-10 Amendment No. 166, 169 225 238 251 270 273 Table 3.3.5.1-1 (page 1 of 5)
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
- 1. Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS)
Subsystems
- a.
Reactor Vessel Water Level - Low Low Low, Level 1 1, 2, 3 2(b)
B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6
-142.3 inches
- b.
Drywell Pressure -
High 1, 2, 3 2(b)
B SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 1.88 psig
- c.
LPCS Pump Start -
LOCA Time Delay Relay 1, 2, 3 1(e)
C SR 3.3.5.1.5 SR 3.3.5.1.6 8.53 seconds and 10.64 seconds
- d.
LPCI Pump A Start -
LOCA Time Delay Relay 1, 2, 3 1(e)
C SR 3.3.5.1.5 SR 3.3.5.1.6 17.24 seconds and 21.53 seconds
- e.
LPCI Pump A Start -
LOCA/LOOP Time Delay Relay 1, 2, 3 1
C SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 3.04 seconds and 6.00 seconds
- f.
Reactor Vessel Pressure - Low (Injection Permissive) 1, 2, 3 1 per valve C
SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 448 psig and 492 psig (a)
Deleted (b)
Also required to initiate the associated diesel generator (DG).
(e)
Also supports OPERABILITY of 230 kV offsite power circuit pursuant to LCO 3.8.1.
ECCS Instrumentation 3.3.5.1 Columbia Generating Station 3.3.5.1-11 Amendment No.238 270 273 Table 3.3.5.1-1 (page 2 of 5)
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
- g.
LPCS Pump Discharge Flow -
Low (Minimum Flow) 1, 2, 3 1
E SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 668 gpm and 1067 gpm
- h.
LPCI Pump A Discharge Flow -
Low (Minimum Flow) 1, 2, 3 1
E SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 605 gpm and 984 gpm
- i.
Manual Initiation 1, 2, 3 2
C SR 3.3.5.1.6 NA
- a.
Reactor Vessel Water Level - Low Low Low, Level 1 1, 2, 3 2(b)
B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6
-142.3 inches
- b.
Drywell Pressure -
High 1, 2, 3 2(b)
B SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 1.88 psig
- c.
LPCI Pump B Start -
LOCA Time Delay Relay 1, 2, 3 1(e)
C SR 3.3.5.1.5 SR 3.3.5.1.6 17.24 seconds and 21.53 seconds
- d.
LPCI Pump C Start -
LOCA Time Delay Relay 1, 2, 3 1(e)
C SR 3.3.5.1.5 SR 3.3.5.1.6 8.53 seconds and 10.64 seconds
- e.
LPCI Pump B Start -
LOCA/LOOP Time Delay Relay 1, 2, 3 1
C SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 3.04 seconds and 6.00 seconds (a)
Deleted (b)
Also required to initiate the associated DG.
(e)
Also supports OPERABILITY of 230 kV offsite power circuit pursuant to LCO 3.8.1.
Main Condenser Offgas 3.7.5 Columbia Generating Station 3.7.5-2 Amendment No. 149,169 225 238 273 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1
NOTE------------------------------
Not required to be performed until 31 days after any main steam line not isolated and SJAE in operation.
Verify the gross gamma activity rate of the noble gases is 332 mCi/second after decay of 30 minutes.
In accordance with the Surveillance Frequency Control Program AND Once within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after a 50% increase in the nominal steady state fission gas release after factoring out increases due to changes in THERMAL POWER level
Organization 5.2 Columbia Generation Station 5.2-2 Amendment 182,213 225 273 5.2 Organization 5.2.2 Unit Staff (continued)
- c.
An individual qualified to implement radiation protection procedures shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.
- d.
Deleted.
- e.
The Operations Director or Assistant Operations Manager shall hold an SRO license.
- f.
An individual shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.
Unit Staff Qualifications 5.3 Columbia Generation Station 5.3-1 Amendment 169,182 225 273 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI/ANS N18.1-1971, for comparable positions described in the FSAR, except for:
- a.
The Operations Director, who shall meet the requirements of ANSI/ANS N18.1-1971 with the exception that in lieu of meeting the stated ANSI/ANS requirement to hold a Senior Reactor Operator (SRO) license at the time of appointment to the position, the Operations Director shall:
- 1.
Hold an SRO license at the time of appointment;
- 2.
Have held an SRO license; or
- 3.
Have been certified for equivalent SRO knowledge; and
- b.
The Radiation Protection Manager, who shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1-R, May 1977.
5.3.2 For the purpose of 10 CFR 55.4, a licensed SRO and a licensed Reactor Operator (RO) are those individuals who, in addition to meeting the requirements of Specification 5.3.1, perform the functions described in 10 CFR 50.54(m).
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 273 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-21 ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NO. 50-397
1.0 INTRODUCTION
By application dated May 1, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23121A294), Energy Northwest (the licensee) requested changes to the renewed facility operating license (RFOL) and technical specifications (TSs) for Columbia Generating Station (Columbia).
The proposed amendment would make administrative and editorial changes to the RFOL and TSs, including removal of an obsolete operating license condition, removal of obsolete TS information, and spelling error corrections. The licensee stated that neither the proposed administrative changes nor the proposed editorial changes result in changes to technical or operating requirements at Columbia.
2.0 REGULATORY EVALUATION
2.1 Description of the Proposed Changes 2.1.1 Proposed TS Changes The licensee proposed the following changes to the Columbia TSs:
Correct Note (e) in TS table 3.3.5.1-1.
Correct typographical, spelling, and formatting errors on TS page 3.3.1.1-11 Note (d); TS page 3.5.2-5 Surveillance Requirement (SR) 3.5.2.7; and TS page 3.7.5-2. The alignment adjustment indicated on page 3.5.2-5 correcting the alignment in SR 3.5.2.7 was previously addressed in Amendment No. 272 and was inadvertently included in Amendment No. 273. Therefore, no clean page for 3.5.2-5 will be included in Amendment No. 273 as no other changes were made to this page in Amendment No. 273 and the page is correct in Amendment No. 272.
Revise title of Operations Manager to Operations Director in TSs 5.2.2 and 5.3.1.
2.1.2 Proposed RFOL Change The licensee proposed to remove License Condition 2.C.(36) related to core plate wedges.
2.2 Regulatory Requirements The U.S. Nuclear Regulatory Commission (NRC or the Commission) regulatory requirements related to the content of the TSs are contained in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, Technical specifications. The regulation in 10 CFR 50.36(b), states, in part, that [e]ach license authorizing operation of a production or utilization facility will include technical specifications. The categories of items required to be in the TS are provided in 10 CFR 50.36(c).
The regulation in 10 CFR 50.50, Issuance of licenses and construction permits, states, in part, that the Commission will issue a license in such form and containing such conditions and limitations including technical specifications, as it deems appropriate and necessary.
The regulations in 10 CFR 50.54, Conditions of licenses, specify, paragraphs and applicable requirements, that are conditions in every nuclear power reactor operating license.
Such conditions were placed on the operating license for Columbia, requiring the licensee to address outstanding licensing issues and facilitate issuance of the original operating license.
The original issuance of the Columbia operating license was subject to several additional requirements (license conditions). These additional requirements were incorporated in the license, as required, as a result of ongoing reviews via the license amendment process in accordance with 10 CFR 50.90, Application for amendment of license, construction permit, or early site permit. In some cases, subsequent license amendments removed certain license conditions when they were satisfied or no longer applicable. However, the majority of the license conditions have been left intact, including those that are no longer required.
The licensee is proposing changes to the Columbia RFOL to remove a license condition that no longer applies. Revision of the RFOL is being proposed to retain only those license conditions that remain pertinent to current Columbia operations.
The NRC staff reviewed the licensees application for changes to the TSs and License Condition 2.C.(36). The staffs evaluations and conclusions are summarized below.
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Change to Table 3.3.5.1-1 Note (e)
The licensee proposed to revise table 3.3.5.1-1 Note (e), to delete reference to Limiting Condition for Operation (LCO) 3.8.2, AC [Alternating Current] Sources - Shutdown, since the note is no longer applicable in Modes 4 and 5. The licensee stated that changes made by the adoption of Technical Specifications Task Force (TSTF) traveler TSTF-542 in Amendment No. 251 dated October 30, 2018 (ML18255A350), included the revision from automatic initiation to manual initiation of the time delay relays for the start-up transformer. Therefore, the specified equipment no longer supports Operability of 230 kilovolt offsite power circuits in Mode 4 and 5.
The NRC staff examined the licensees proposal to delete Note (e) and concludes that this change should have been included as part of the TS change to adopt TSTF-542 traveler. All the Modes 4 and 5 requirements were removed from TS 3.3.5.1. The reference to LCO 3.8.2 should have been removed as well. Therefore, the NRC finds this change acceptable.
3.2 Correction of Typographical Errors The licensee proposed to correct the following typographical errors in the TSs:
TS page 3.3.1.1-11 Note (d), the word predefined is misspelled.
TS page 3.5.2-5, SR 3.5.2.7 alignment of note and text in table.
TS page 3.7.5-2 contains a stray 5 in the word REQUIREMENTS.
The NRC staff reviewed the licensees correction of typographical errors and concludes that the corrections are editorial and are supported by the TSTF guidance in TSTF-GG-05-01, Writers Guide for Plant-Specific Improved Technical Specifications, dated June 2005 (ML060720511) and, therefore, are acceptable.
3.3 Change in Title of Operations Manager to Operations Director The licensee proposed to change the title of Operations Manager to Operations Director in TSs 5.2.2 and 5.3.1 due to a recent reorganization change.
The NRC staff reviewed the licensees change and concluded that the title was changed January 7, 2023, and the change does not affect reporting structure, but merely changes the job title. Since the title was changed January 7, 2023, and merely changed the job title, the NRC staff finds this change editorial, and therefore acceptable.
3.4 Proposed Change to the RFOL The licensee proposed to remove License Condition 2.C.(36) that relates to core plate wedges.
This condition was added to the license with NUREG-2123, Volume 1, Safety Evaluation Report Related to the License Renewal of Columbia Generating Station, dated May 2012 (ML12139A300). The licensee stated that it completed installation of the core plate wedges as reported in letter GO2-21-093, dated August 23, 2021 (ML21235A454). The letter documents the licensees completion of License Condition 2.C.(36).
The NRC staff reviewed the licensees proposal to remove License Condition 2.C.(36). The licensee stated that it completed the license condition and installed the core plate wedges on or before December 20, 2021, per the license condition and as indicated in the letter dated August 23, 2021. Based on the statement under affirmation that the licensee completed the license condition, the NRC staff concludes that it is acceptable to remove License Condition 2.C.(36) from RFOL No. NPF-21 for Columbia.
3.5 Summary The NRC staff finds that the licensees proposed changes to the Columbia RFOL and TSs are administrative and editorial and delete obsolete information. Further, the licensees proposed changes are consistent with the regulatory requirements and NRC guidance. Therefore, the staff concludes that the proposed changes to the Columbia RFOL and TSs are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Washington State official was notified of the proposed issuance of the amendment January 19, 2024. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes SRs.
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, published in the Federal Register on July 11, 2023 (88 FR 44165), and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and 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 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: Andrea Russell Andrew Siwy Date: March 7, 2024
- concurrence via email OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA*
NRR/DSS/STSB/BC(A)*
NRR/DEX/EICB*
NAME MChawla PBlechman SMehta FSacko DATE 2/14/2024 2/21/2024 1/12/2024 2/14/2024 OFFICE NRR/DNRL/NLRP*
OGC*
NRR/DORL/LPL4/BC*
NRR/DORL/LPL4/PM*
NAME LGibson RSiegman JRankin MChawla (SLee for)
DATE 3/6/2024 3/1/2024 3/7/2024 3/7/2024