ML24071A098

NRR E-mail Capture - Audit Plan Related to Review of the Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce RHR Flow Rate

ML24071A098
Person / Time
Site:	Watts Bar
Issue date:	03/07/2024
From:	Kimberly Green Plant Licensing Branch II
To:	Hughes S Tennessee Valley Authority
References
L-2023-LLA-0152
Download: ML24071A098 (5)

Text

From: Kimberly Green Sent: Thursday, March 7, 2024 4:18 PM To: Hughes, Shawna Marie Cc: Wells, Russell Douglas

Subject:

Audit Plan Related to Review of the Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce RHR Flow Rate (EPID L-2023-LLA-0152)

Attachments: Audit Plan.docx

Dear Shawn Hughes,

By application dated October 30, 2023 (Agencywide Documents Access and Management System Accession No. ML23303A095), pursuant to Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), the Tennessee Valley Authority (TVA) submitted a license amendment request for the Watts Bar Nuclear Plant (Watts Bar), Units 1 and 2. The proposed amendments would revise Watts Bar, Units 1 and 2, Technical Specification Surveillance Requirement 3.9.5.1, Residual Heat Removal (RHR) and Coolant Circulation - High Water Level, to revise the current flow rate of 2,500 gallons per minute (gpm) to 2,000 gpm.

The U.S. Nuclear Regulatory Commission staff is reviewing the proposed change and has determined that a regulatory audit is necessary to aid it its review.

Attached, please find an audit plan containing the basis, scope, information needs, audit team, logistics, and deliverable for this audit.

If you have any questions, please let me know.

Regards,

Kimberly Green Senior Project Manager Division of Operating Reactor Licensing U.S. Nuclear Regulatory Commission 301-415-1627

Hearing Identifier: NRR_DRMA Email Number: 2425

Mail Envelope Properties (SA1PR09MB91639A37E70FC3E55F9A82408F202)

Subject:

Audit Plan Related to Review of the Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce RHR Flow Rate (EPID L-2023-LLA-0152)

Sent Date: 3/7/2024 4:17:55 PM Received Date: 3/7/2024 4:17:00 PM From: Kimberly Green

Created By: Kimberly.Green@nrc.gov

Recipients:

"Wells, Russell Douglas" <rdwells0@tva.gov>

Tracking Status: None "Hughes, Shawna Marie" <smhughes@tva.gov>

Tracking Status: None

Post Office: SA1PR09MB9163.namprd09.prod.outlook.com

Files Size Date & Time MESSAGE 1137 3/7/2024 4:17:00 PM Audit Plan.docx 32918

Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

REGULATORY AUDIT PLAN

BY THE OFFICE OF NUCLEAR REACTOR REGULATION

TO SUPPORT THE REVIEW OF LICENSE AMENDMENT REQUEST

TO REVISE TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT 3.9.5.1 TO

REDUCE THE RESIDUAL HEAT REMOVAL FLOW RATE

TENNESSEE VALLEY AUTHORITY

WATTS BAR NUCLEAR PLANT UNITS 1 AND 2

DOCKET NOS. 50-390 AND 50-391

1.0 BACKGROUND

By application dated October 30, 2023 (Agencywide Documents Access and Management System Accession No. ML23303A095), as supplemented by letter dated January 10, 2024 (ML24010A064), pursuant to Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), the Tennessee Valley Authority (TVA) submitted a license amendment request (LAR) to amend Facility Operating License Nos. NPF-90 and NPF-96 for Watts Nuclear Plant (Watts Bar), Units 1 and 2, respectively. The proposed amendments would revise Watts Bar Nuclear Plant (Watts Bar), Units 1 and 2, Technical Specification (TS) Surveillance Requirement (SR) 3.9.5.1, Residual Heat Removal (RHR) and Coolant Circulation - High Water Level, to revise the current flow rate of 2,500 gallons per minute (gpm) to 2,000 gpm.

The Nuclear Regulatory Commission (NRC) staff has determined that a regulatory audit of the supporting information for the LAR should be conducted in accordance with Office of Nuclear Reactor Regulation Office Instruction LIC-111, Regulatory Audits (ML19226A274).

2.0 REGULATORY AUDIT BASIS

A regulatory audit is a planned license-or regulation-related activity that includes the examination and evaluation of primarily non-docketed information associated with the LAR. An audit is conducted to gain understanding, to verify information, and to identify information that will require docketing to support the basis of a licensing or regulatory decision. An audit will assist the NRC staff in efficiently conducting its review and gaining insights to TVAs processes and procedures. Information identified during the audit that the NRC staff relies upon to make the safety determination must be submitted on the docket.

3.0 REGULATORY AUDIT SCOPE AND METHODOLOGY

NRC staffs objectives of the audit are the following:

• Gain a better understanding of the evaluation and supporting analyses performed in support of the LAR and confirm the NRC staffs understanding of the LAR.

• Gain a better understanding of the plants relevant design features and its implications for the LAR.

Attachment

• Identify questions and requests that may become formal requests for additional information (RAIs) per NRR Office Instruction LIC-115, Processing Requests for Additional Information (ML21141A238).

4.0 INFORMATION AND OTHER MATERIAL NECESSARY FOR THE AUDIT

The NRC staff requests access to the following documents:

Item # Audit Item 1 FSSE/CWBS-1145, RHRS Operation During Midloop at Watts Bar, December 7, 1989 2 Westinghouse Letter No. LTR-RES-21-76, Watts Bar Residual Heat Removal (RHR) Pump Motor Bearing Life, July 6, 2021 3 BUFFALO LMD Shop Order 74F2682, Seismic Analysis of Residual Heat Removal Pump Motors for Watts Bar No. 1 & 2 Nuclear Stations Tennessee Valley Authority Manufactured on S.O. Numbers 74F12184, May 30, 1975 4 Westinghouse Letter No. WAT-D-8252, Tennessee Valley Authority Watts Baur Units Number 1 and 2 Minimum RHRS Flow Rate During Midloop Operation Safety Evaluation (SECL-89-893), June 1990 5 Westinghouse Equipment Specification Number 678815. Revision 2 6 Westinghouse WNEP-8402, Generic Stress Report of 3 Loop XL Reactor Core Support Structures -Structural and Fatigue Analysis, September 2008

Additional information needs identified during the audit will be communicated to the designated point of contact.

The NRC will document the final audit items list as an enclosure to the audit report, which will be publicly available.

5.0 TEAM ASSIGNMENTS

The audit team will consist of the following NRC staff:

Team Member Division Area of Responsibility

Kimberly Green NRR/DORL/LPLII-2 Project Manager Kimberly.Green@nrc.gov Thomas om Scarbrough NRR/DEX/EMIB Technical Review -

Thomas.Scarbrough@nrc.gov mechanical

Jo Ambrosini NRR/DSS/SNSB Technical Review -

Josephine.Ambrosini@nrc.gov systems

Ahsan Sallman NRR/DSS/SNSB Technical Review -

Ahsan.Sallman@nrc.gov systems

Matthew Hamm NRR/DSS/STSB Technical Review -

Matthew.Hamm@nrc.gov technical specifications

Key TVA personnel knowledgeable in the areas of interest should be made available for interactions, on a mutually agreeable schedule, to respond to any questions from the NRC staff.

6.0 LOGISTICS

To support the review schedule communicated to TVA when the NRC staff accepted the LAR for technical review, audit activities will be performed remotely and virtually using Microsoft Teams and an internet-based portal made available by TVA.

The internet-based portal should be populated with the documents requested in section 4.0 of this audit plan. The following conditions associated with the portal must be maintained while the NRC staff have access to the portal:

• The portal will be password-protected. A separate password will be assigned to each member of the NRC staff participating in the audit.

• The portal should prevent the NRC staff from printing, saving, downloading, or collecting any information directly from the online portal.

• Conditions of use of the portal will be displayed on the login screen and will require acknowledgment by each user.

Username, password, and other portal access information should be provided directly to members of the NRC audit team. The NRC licensing project manager will provide TVA with names and contact information of the NRC staff participating in the audit (section 5.0 above). All other communications should be coordinated through the NRC project manager.

NRC information requests and communications with TVA staff will be coordinated through the NRCs licensing project manager.

The virtual audit will commence after the internet-based portal is set up and the documentation addressing the items in section 4.0 of this audit plan is made available to the NRC staff. The audit will be conducted from April 1 through April 5, 2024. The NRC project manager will coordinate with the NRC staff and TVA for any teleconferences needed after the NRC staff has reviewed the documentation. The NRCs licensing project manager will inform TVA of the entrance and exit call dates when they are established. The NRCs licensing project manager will inform TVA via routine communications when the NRC staff no longer needs access to the portal.

7.0 DELIVERABLES

The NRC staff will issue an audit summary report within 90 days of the audit exit call. The staff may request additional information needed to complete the review of the LAR but will issue any such RAIs separately from audit-related correspondence in accordance with NRR Office Instruction LIC-115, Processing Requests for Additional Information (ML21141A238).