ML24267A040

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Cycle 27 Core Operating Limits Report Revision 0
ML24267A040
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 09/19/2024
From: Marshall T
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
Download: ML24267A040 (1)


Text

l TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant, P.O. Box 2000, Soddy Daisy, Tennessee 37384 September 19, 2024 ATTN:DocumentControlDesk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 2 Renewed Facility Operating License No. DPR-79 NRC Docket No. 50-328 10 CFR 50.4

Subject:

SEQUOYAH UNIT 2 CYCLE 27 CORE OPERATING LIMITS REPORT REVISION 0 In accordance with Sequoyah Nuclear Plant (SQN) Unit 2 Technical Specification (TS) 5.6.3.d, enclosed is the Unit 2 Cycle 27 Core Operating Limits Report (COLR}, Revision O that was issued on September 3, 2024.

There are no new regulatory commitments in this letter. If you have any questions, please contact Rick Medina, SON Site Licensing Manager at (423) 843-8129 or rmedina4@tva.gov.

Respectfully,

~~

l-Jl~V\\,~~ ~f>VO_JCLk. :PtOJ-.t ~(

Thomas Marshall fo f' T. f\\lA.i S~ \\

Site Vice President Sequoyah Nuclear Plant

Enclosure:

Sequoyah Unit 2 Cycle 27 Core Operating Limits Report, Revision O cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - SQN

ENCLOSURE SEQUOYAH UNIT 2 CYCLE 27 CORE OPERATING LIMITS REPORT REVISION 0

QA Record SEQUOYAH UNIT 2 CYCLE 27 CORE OPERATING LIMITS REPORT REVISION 0 August 2024 Prepared by:

L36 240814 800 Sharper, Nathaniel Trevon Digitally signed by Sharper, Nathaniel Trevon Date: 2024.08.19 13:00:17 -04'00' I

N. Trevon Sharper, PWR Fuel Engineering Date Verified by:

E.

Digitally signed by Collins, Peter Eric

( O 11 in S, peter r I c Reason:, have reviewed this document Date: 2024.08.19 V3:23:17 -04'00' P. Eric Collins, PWR Fuel Engineering Reviewed by:

Ritchie, John Digitally signed by Ritchie, John A A

DN: dc=gov, dc=tva, dc=main, ou=Main, ou=Corporate, ou=Users, cn=Ritchie, John A, email=jaritchie0@tva.gov Reason: I have reviewed this document Date: 2024.08.20 20:26:45 -04'00' John A. Ritchie, PWR Fuel Engineering Manager Date I

Date Digitally signed by Hammargren, Benjamin Hammargren, Benjamin John John Date: 2024.08.21 08:.S7:00 -04'00' Ben J. Hammargren, Reactor Engineering Manager Date Approved by:

Hodge, James M.

PORC Chairman Plant Ma~er Date of PORC Affected Revision Approval Pages 0

See above All SEQUOYAH UNIT 2 Digitally signed by Hodge, James M.

Date: 2024.08.31114:00:57 -04'00' Date I

Date Reason for Revision Initial Issue Page 1 of 4 Revision 0

Unit 2 Cycle 27 SEQUOYAH Page 2 of 4 Revision 0 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Sequoyah Nuclear Plant Unit 2 has been prepared in accordance with the requirements of the Technical Specifications (TS) 5.6.3. This COLR is only valid for MODE 6 and restricted MODE 5. The MODE 5 restriction does not allow the control rod drive system to withdraw any RCCA. The COLR must be revised before the withdrawal of the RCCAs by the control rod drive system is enabled. The cycle-specific parameter limits for specifications 2.1.1, 3.1.3, 3.1.4, 3.1.5, 3.1.6, 3.1.8, 3.2.1, 3.2.2, 3.2.3, 3.3.1, and 3.4.1 are not applicable in MODE 6 or restricted MODE 5 and are not provided.

The Technical Specifications that are affected by this report are listed below:

TS Section Technical Specification COLR Parameter COLR Section 3.1.1 SHUTDOWN MARGIN (SDM)

SDM 2.2.2 3.9.1 Boron Concentration Refueling Boron Concentration 2.11 5.6.3 CORE OPERATING LIMITS REPORT (COLR)

Analytical Methods Table 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 27

Unit 2 Cycle 27 SEQUOYAH Page 3 of 4 Revision 0 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in the Technical Specifications 5.6.3.

2.2 SHUTDOWN MARGIN (LCO 3.1.1) 2.2.2 For TS 3.1.1, SDM shall be 1.0% k/k in MODE 5.

2.11 REFUELING BORON CONCENTRATION (LCO 3.9.1)

The refueling boron concentration shall be 2000 ppm.

COLR FOR SEQUOYAH UNIT 2 CYCLE 27

Unit 2 Cycle 27 SEQUOYAH Page 4 of 4 Revision 0 Table 1 COLR Methodology Topical Reports

1. WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, July 1985.

(methodology for Shutdown Margin, Refueling Pool Boron Concentration)

2. WCAP-10965-P-A, ANC: A Westinghouse Advanced Nodal Computer Code, September 1986.

(methodology for Shutdown Margin, Refueling Pool Boron Concentration)

3. WCAP-10965-P-A, Addendum 2-A, Revision 0, Qualification of the New Pin Power Recovery Methodology, September 2010.

(methodology for Shutdown Margin, Refueling Pool Boron Concentration)

4. WCAP-16045-P-A, Qualification of the Two-Dimensional Transport Code PARAGON, August 2004.

(methodology for Shutdown Margin, Refueling Pool Boron Concentration)

5. WCAP-16045-P-A, Addendum 1-A, Qualification of the NEXUS Nuclear Data Methodology, August 2007.

(methodology for Shutdown Margin, Refueling Pool Boron Concentration)

COLR FOR SEQUOYAH UNIT 2 CYCLE 27