ML24071A116

Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System

ML24071A116
Person / Time
Site:	Prairie Island
Issue date:	05/01/2024
From:	Ballard B Plant Licensing Branch III
To:	Conboy T Northern States Power Co
Kuntz R
References
EPID L-2023-LLA-0095
Download: ML24071A116 (1)

Text

May 1, 2024

Thomas Conboy Site Vice President Northern States Power Company - Minnesota Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089

SUBJECT:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -

ISSUANCE OF AMENDMENT NOS. 244 AND 232 RE: REVISE TECHNICAL SPECIFICATION 3.7.8, COOLING WATER (CL) SYSTEM (EPID L-2023-LLA-0095)

Dear Thomas Conboy:

The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendments No. 244 to Renewed Facility Oper ating License No. DPR-42 and Amendment No. 232 to Renewed Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2, respectively. The amendments consist of changes to the technical specifications (TSs) in response to your application dated June 22, 2023, as supplemented by letter dated January 2, 2024.

The amendments revise TS 3.7.8, Cooling Water (CL) System, required actions for Condition B from verification of operability of both CL pumps that supply the operable CL header to verification of the operability of a safeguards CL pump supplying the operable CL header. The amendments also remove reference to an expired one-time allowance for the completion time for TS 3.7.8 required Action B.1.

T. Conboy - 2 -

A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's monthly Federal Register notice.

Sincerely,

/RA/

Brent T. Ballard, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Docket Nos. 50-282 and 50-306

Enclosures:

1. Amendment No. 244 to DPR-42

2. Amendment No. 232 to DPR-60

3. Safety Evaluation

cc: Listserv NORTHERN STATES POWER COMPANY

DOCKET NO. 50-282

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 1

AMENDMENT TO RENEWED FACI LITY OPERATING LICENSE

Amendment No. 244 Renewed License No. DPR-42

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

A. The application for amendment by Northern States Power Company (NSPM, the licensee), dated June 22, 2023, as supplemented by letter dated January 2, 2024, 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. DPR-42 is hereby amended to read as follows:

(2) Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 244, are hereby incorporated in the renewed operating license. NSPM 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 90 days.

FOR THE NUCLEAR REGULATORY COMMISSION

Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications

Date of Issuance: May 1, 2024

NORTHERN STATES POWER COMPANY

DOCKET NO. 50-306

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2

AMENDMENT TO RENEWED FACI LITY OPERATING LICENSE

Amendment No. 232 Renewed License No. DPR-60

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

A. The application for amendment by Northern States Power Company (NSPM, the licensee), dated June 22, 2023, as supplemented by letter(s) dated January 2, 2024, 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 2

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-60 is hereby amended to read as follows:

(2) Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 232, are hereby incorporated in the renewed operating license. NSPM 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 90 days.

FOR THE NUCLEAR REGULATORY COMMISSION

Jeffrey A. Whited, Chief Plant Licensing Branch III-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: May 1, 2024

ATTACHMENT TO LICENSE AMENDMENT NOS. 244 AND 232

RENEWED FACILITY OPERATING LICENSE NOS. DPR-42 AND DPR-60

DOCKET NOS. 50-282 AND 50-306

Replace the following pages of the Renewed Facility Operating License Nos. DPR-42 and DPR-60 with the attached revised pages. The changed areas are identified by a marginal line.

Renewed Facility Operating License No. DPR-42

REMOVE INSERT

Page 3 Page 3

Renewed Facility Operating License No. DPR-60

REMOVE INSERT

Page 3 Page 3

Technical Specifications

Replace the following pages of the 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 INSERT 3.7.8-2 3.7.8-2 3.7.8-3 3.7.8-3 3.7.8-4 3.7.8-4

(3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NSPM 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;

(4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, NSPM 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 and equipment calibra tion or associated with radioactive apparatus or components;

(5) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility;

(6) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to transfer byproduct materials from other job sites owned by NSPM for the purpose of volume reduction and decontamination.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter l:

Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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

NSPM is authorized to operate the facility at steady state reactor core power levels not in excess of 1677 megawatts thermal.

(2) Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 244, are hereby incorporated in the renewed operating license.

NSPM shall operate the facility in accordance with the Technical Specifications.

(3) Physical Protection

NSPM shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains

Renewed Operating License No. DPR-42 Amendment No. 244

(3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NSPM 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;

(4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, NSPM 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 and equipment calibra tion or associated with radioactive apparatus or components;

(5) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility;

(6) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to transfer byproduct materials from other job sites owned by NSPM for the purposes of volume reduction and decontamination.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter l:

Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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

NSPM is authorized to operate the facility at steady state reactor core power levels not in excess of 1677 megawatts thermal.

(2) Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 232, are hereby incorporated in the renewed operating license.

NSPM shall operate the facility in accordance with the Technical Specifications.

(3) Physical Protection

NSPM shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains

Renewed Operating License No. DPR-60 Amendment No. 232 CL System 3.7.8

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

A. (continued) A.1 Restore one safeguards CL7 days pump to OPERABLE status. OR

In accordance with the Risk Informed Completion Time Program

B. One CL supply header ----------------NOTES---------------

inoperable. 1. Unit 1 enter applicable Conditions and Required Actions of LCO 3.8.1, AC Sources-MODES 1, 2, 3, and 4, for emergency diesel generator made inoperable by CL System.

2. Both units enter applicable Conditions and Required Actions of LCO 3.4.6, RCS Loops-MODE 4, for residual heat removal loops made inoperable by CL System.

Prairie Island Unit 1 - Amendment No. 244 Units 1 and 2 3.7.8-2 Unit 2 - Amendment No. 232 CL System 3.7.8

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

B. (continued) B.1 ------------NOTE------------

Opposite train diesel driven CL pump may be verified to be OPERABLE by administrative means.

Verify opposite train 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> safeguards CL pump OPERABLE.

AND

B.2 Restore CL supply header 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to OPERABLE status.

OR

In accordance with the Risk Informed Completion Time Program

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND

C.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />

Prairie Island Unit 1 - Amendment No. 244 Units 1 and 2 3.7.8-3 Unit 2 - Amendment No. 232 CL System 3.7.8

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

D. -----------NOTE------------ D.1 Restore fuel oil supply to48 hours Separate Condition entry 7 days.

is allowed for each stored diesel driven CL pump fuel oil supply.

One or both stored diesel driven CL pump fuel oil supply(s) < 7 days and 6 days.

E. -----------NOTE------------ E.1 Declare associated dieselImmediately Separate Condition entry driven CL pump is allowed for each stored inoperable.

diesel driven CL pump fuel oil supply.

One or both stored diesel driven CL pump fuel oil supply(s)

< 6 days.

OR

Required Action and associated Completion Time of Condition D not met.

Prairie Island Unit 1 - Amendment No. 244 Units 1 and 2 3.7.8-4 Unit 2 - Amendment No. 232 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION

RELATED TO AMENDMENT NO. 244 TO RENEWED FACILITY

OPERATING LICENSE NO. DPR-42

AND AMENDMENT NO. 232 TO RENEWED FACILITY

OPERATING LICENSE NO. DPR-60

NORTHERN STATES POWER COMPANY - MINNESOTA

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2

DOCKET NOS. 50-282 AND 50-306

1.0 INTRODUCTION

By application dated June 22, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23173A069), as supplemented by letter dated January 2, 2024 (ML24002A740), Northern States Power Company, a Minnesota Corporation, doing business as Xcel Energy (NSPM, the licensee), requested changes to the technical specifications (TSs) for Prairie Island Nuclear Generating Plant, Units 1 and 2.

The supplemental letter dated January 2, 2024, 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 Commission) staff's original proposed no significant hazards consideration determination as published in the Federal Register on September 5, 2023 (88 FR 60719).

The proposed changes would revise TS 3.7.8, Cooling Water (CL) System, Required Actions for Condition B from verification of operability of both CL pumps that supply the operable CL header to verification of the operability of a safeguards CL pump supplying the operable CL header. The proposed changes would also remove reference to an expired one-time allowance for the completion time for TS 3.7.8 Required Action B.1.

2.0 REGULATORY EVALUATION

2.1 Cooling Water System Description and Operation

The Prairie Island Updated Safety Analysis Report (USAR), section 10.4.1, Cooling Water System (ML20118D373), states that the CL system is designed to provide redundant cooling water supplies with isolation valves to auxiliary feedwater pumps, Unit 1 diesel generators, air compressors, component cooling water heat exchangers, containment fan coil units, and the

Enclosure 3

Auxiliary Building unit coolers. The preferred source of water to the containment fan coil units and some Auxiliary Building unit coolers is provided by chilled water. The CL system provides an alternate source of water to these components.

The CL system is shared between both units and takes inventory from the Mississippi River.

The shared CL system contains five pumps: two safeguard diesel-driven pumps, two non-safeguard horizontal pumps, and one motor-driven pump assigned to either safeguard or non-safeguard. Both diesel-driven safeguard vertical pumps (normal) and the one motor-driven vertical (standby) pump provide water to two independent supply headers (Trains A and B). The supply configuration for Train A includes one safeguard diesel pump, one non-safeguard pump, and the shared motor-driven safeguard pump and Train B includes a separate safeguard diesel pump, one non-safeguard pump, and the shared motor-driven connection to supply header.

The USAR states that a ring header which is shared by Units 1 and 2 can be isolated automatically to provide two redundant independent sources of cooling water for all essential services. One-half of essential services for eac h unit is supplied from each side of the isolable loop. Each side of the loop is designed to supply the needs for all essential services for both units. Thus, failure of one side of the loop still provides for the operation of all equipment required for the safe shutdown of both Units.

The USAR describes normal operation of the CL system as using two non-safeguard horizontal pumps with a vertical motor-driven pump as a standby. Two vertical diesel-driven pumps are provided for emergency operation. The diesel-driven pumps are used whenever an engineered safety features sequence is initiated when discharge header pressure drops below its setpoint, or on a loss of offsite power (due to loss of motor driven pumps and resultant low discharge header pressure). The vertical motor-driven pump also functions as a replacement when a diesel-driven pump is taken out of service.

2.2 Proposed Change

The amendment requests to include the following changes to Prairie Island TS 3.7.8, Condition B:

The application requests to replace the existing Required Action B.1 which states:

Verify vertical motor driven CL pump OPERABLE

With a new Required Action B.1 as modified by a note:

---

NOTE-----------------

Opposite train diesel-driven CL pump may be verified to be OPERABLE by administrative means B.1 Verify opposite train safeguards CL pump OPERABLE

The NRC staff reviewed the proposed deletion of Required Action B.2 which states:

B.2 Verify opposite train diesel-driven CL pump OPERABLE.

existing Required Action B.3 is proposed to be renumber to B.2.

The submittal also requests to delete an expired TS note related to maintenance that has been completed.

2.3 Regulatory Requirements and Guidance

Regulatory Requirements

Under 10 CFR 50.90, whenever a holder of a li cense wishes to amend the license, including technical specifications in the license, an application for amendment must be filed, fully describing the changes desired. Under 10 CFR 50.92(a), determinations on whether to grant an applied-for license amendment are to be guided by t he considerations that govern the issuance of initial licenses or construction permits to the extent applicable and appropriate. Both the common standards in 10 CFR 50.40(a), and those specifically for issuance of operating licenses in 10 CFR 50.57(a)(3), provide that there must be reasonable assurance that the activities at issue will not endanger the health and safety of the public.

The categories of items required to be in the TSs are provided in Title 10 of the Code of Federal Regulations (10 CFR) section 50.36(c). As required by 10 CFR 50.36(c)(2)(i), the TSs will include limiting condition for operations (LCOs), which are the lowest functional capability or performance levels of equipment required for safe operation of the facility. Per 10 CFR 50.36(c)(2)(i), when an LCO of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs until the condition can be met. The remedial actions must continue to provide reasonable assurance of public health and safety.

Guidance

NRC Generic Letter (GL) 80-30, Clarification of the Term Operable as it Applies to Single Failure Criterion for Safety Systems Required by TS, dated April 10, 1980, (https://www.nrc.gov/reading-rm/doc-collect ions/gen-comm/gen-letters/1980/gl80030.html )

provides information on single failure and required redundancy while in a TS LCO action statement. GL 80-30 states, in part:

The specified time to take action, usually called the equipment out-of-service time, is a temporary relaxation of the single failure criterion, which, consistent with overall system reliability considerations, provides a limited time to fix equipment or otherwise make it OPERABLE. If equipment can be returned to OPERABLE status within the specified time, plant shutdown is not required.

NUREG-0800, Standard Review Plan (SRP), chapter 19, section 19.2, Review of Risk Information Used to Support Permanent Plant-Specif ic Changes to the Licensing Basis: General Guidance (ML071700658), provides guidance on the use of risk information in review of non-risk-informed license amendment requests (LARs). This section states, in part:

Special Circumstances represent conditions or situations that would raise questions about whether there is adequate protection and that could rebut the normal presumption of adequate protection from compliance with existing requirements.

3.0 TECHNICAL EVALUATION

3.1 Evaluation of Changes to TS 3.7.8, Cooling Water (CL) System

The current TS Required Actions B.1 and B.2 require both a vertical motor driven CL pump and the opposite train diesel -driven CL pump to be verified operable if Condition B is entered (one CL supply header was inoperable). As described in USAR, section 10.4.1.2, and restated in the LAR, the capacity of the safeguards motor-driven pump and each diesel-driven pump exceeds the maximum flow required for a single pump serving one unit in hot shutdown and a second unit in the long-term post-accident condition. Therefore, one diesel-driven pump or one safeguards motor-driven pump is sufficient to meet all the CL system loads required for the safe shutdown of both units (accident in only one unit). NRC GL 80-30 described the NRC staff position that when in an LCO action statement, the single-failure criterion is temporarily relaxed.

In this case, when in Condition B, safeguards CL pump redundancy is not required. The changes to Required Action B.1 and deletion of existing Required Action B.2 would eliminate this restrictive single-failure TS requirement and require verification of operability of only one 100-percent safeguards CL pump while in Condition B. The staff finds that because a 100-percent safeguards CL pump on the operable header will be verified operable with the proposed TS change, there will be reasonable assurance that the plant may be safety operated during the time that the LCO is not met.

The NRC staff reviewed the proposed note to modify new Required Action B.1, which states Opposite train diesel-driven CL pump may be verified to be OPERABLE by administrative means. Addition of this note to Required Action B.1 does not change any current operational requirements and provides additional clarity and is, therefore, acceptable.

The NRC staff reviewed the proposed renumbering of existing Required Action B.3 to B.2, and the proposed removal of the expired note associated with Required Action B.1 and found them to be administrative and are, therefore, acceptable.

The NRC staff finds the operable train will remain capable of performing the CL system safety function of keeping both units in safe shutdown (in the case one has a design basis event). With the CL system able to perform its safety function, the staff finds the TS change acceptable.

3.2 Risk Insights

While this is not a risk-informed LAR, the licensee provided risk insights related to the proposed change in section 3.0 of the Enclosure to the LAR. Because this is not a risk-informed LAR, the probabilistic risk assessment model s used to derive risk insights were not reviewed by the NRC staff to determine their technical acceptability to support this LAR. The licensee did not provide quantitative results, nor did it provide qualitative analysis regarding the impact the proposed change would have on risk.

The NRC staff reviewed the proposed changes to t he TS considering the risk insights provided by the licensee, and determined that special circumstances, as described in SRP section 19.2, which would have necessitated additional risk information be provided, did not exist. As such, the NRC staff did not request any additional risk information associated with the review of this

LAR. As discussed in section 3.1 of this safety evaluation (SE), sufficient deterministic information was supplied by the licensee for the NRC staff to make a safety finding on the request.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations on, the Minnesota State official was notified of the proposed issuance of the amendments on March 1, 2024. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change the requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR, part 20, or change the surveillance requirements. 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 and there has been no public comment on such finding (88 FR 60719; dated September 5, 2023). Accordingly, the amendments meet the eligibility criteria for catego rical 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 Commission's 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 Contributor: J. Wilson, NRR H. Wagage, NRR J. Robinson, NRR

Date of Issuance: May 1, 2024

ML24071A116 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DSS/STSB/BC NRR/DSS/SCPB/BC NAME BBallard SRohrer SMehta BWittick DATE 3/8/2024 3/12/2024 2/27/2024 2/27/2024 OFFICE NRR/DEX/EEEB/BC NRR/DRA/APLB/BC OGC (NLO) NRR/DORL/LPL3/BC NAME WMorton SMakor DRoth JWhited DATE 3/12/2024 3/11/2024 3/26/2024 5/1/2024 OFFICE NRR/DORL/LPL3/PM NAME BBallard DATE 5/1/2024