CNL-15-164, Second Annual Update, License Renewal Application

Second Annual Update, License Renewal Application

ML15226A592
Person / Time
Site:	Sequoyah
Issue date:	08/14/2015
From:	James Shea Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CNL-15-164, TAC MF0481, TAC MF0482
Download: ML15226A592 (6)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-15-164 August 14, 2015 10 CFR Part 54 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328

Subject:

Second Annual Update to the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application (TAC Nos. MF0481 and MF0482)

References:

1. TVA Letter to NRC, Sequoyah Nuclear Plant, Units 1 and 2 License Renewal, dated January 7, 2013 (ADAMS Accession No. ML13024A004)

2. TVA Letter to NRC, Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application: RAIs B.1.13-4 and 3.0.3-1-3c, Commitment 9.G, and 2013 LRA Annual Update, dated April 22, 2014 (ADAMS Accession No. ML14113A208)

By letter dated January 7, 2013 (Reference 1), Tennessee Valley Authority (TVA) submitted a License Renewal Application (LRA) to the Nuclear Regulatory Commission (NRC) to renew the operating licenses for the Sequoyah Nuclear Plant (SQN), Units 1 and 2. The request would extend the licenses for an additional 20 years beyond the current expiration dates. By Reference 2, TVA submitted the first annual update to the LRA, as required by 10 CFR 54.21(b).

TVA has completed a review to identify any current licensing basis (CLB) changes made since the submittal of Reference 2, which have a material effect on the content of the LRA, including the Final Safety Analysis Report (FSAR) Supplement. The review identified one change to the CLB that materially affects the content of the SQN LRA. This change is described in the enclosed second SQN LRA annual update.

There are no new regulatory commitments contained in this letter. Please address any questions regarding this submittal to Erin Henderson at (423) 843-7170.

Nuclear Regulatory Commission CNL-15-164 Page 2 August 14, 2015 I declare under penalty of perjury that the foregoing is true and correct. Execute d on this 14th day of August, 2015 .

President, Nuclear Licensing RDW:EDS

Enclosure:

Sequoyah Nuclear Plant, Units 1 and 2 License Renewal Application Second Annual Update cc (Enclosure):

NRC Region alAdmi nistrato r - Region II NRC Senior Residen t Inspect or - Sequoyah Nuclear Plant NRC Project Manage r - Sequoyah Nuclear Plant NRR License Renewal Project Manage r - Sequoyah Nuclear Plant

ENCLOSURE Sequoyah Nuclear Plant, Units 1 and 2 License Renewal Application Second Annual Update Review Period May 4, 2012 (freeze date) is the date of record for documents used in preparation of the Sequoyah Nuclear Plant (SQN) License Renewal Application (LRA). December 31, 2013 was the cut-off date for documents that were considered as part of the first annual update report (Reference 2 of the cover letter). The review for this LRA update covers the period from January 1, 2014, through June 11, 2015.

Description of Current License Basis (CLB) Changes that Impact the SQN LRA Penetrations SQN-1-PENE-302-0026-S and SQN-1-PENE-302-0040-S were removed from the 10 CFR 50.49 environmental qualification (EQ) program as part of a plant modification. TVA originally purchased these penetrations for use in safety related EQ applications, added them to the EQ Program, and qualified these penetrations in accordance with 10 CFR 50.49. However, it was later determined that these penetrations do not contain any safety-related electrical equipment and that the sole safety-related function for these penetrations is to maintain containment pressure boundary integrity. Therefore, these penetrations have been removed from the EQ program. These penetrations will continue to be maintained in accordance with the 10 CFR 50 Appendix J leak rate program.

The LRA is affected because the LRA currently states: All SQN electrical and I&C penetration assemblies are in the EQ program (10 CFR 50.49). The aging effects associated with the electrical functions, not subject to 10 CFR 50.49 EQ requirements, are managed by the Non-EQ insulated cables and connections program and the aging effects associated with the mechanical functions are managed by the containment leak rate program. Therefore, the LRA is being revised to note that penetrations SQN-1-PENE-302-0026-S and SQN-1-PENE-302-0040-S are not within the scope of the EQ program and to clarify how aging effects are managed for these two penetrations.

SQN LRA Changes As result of the removal of penetrations SQN-1-PENE-302-0026-S and SQN-1-PENE-302-0040-S from the EQ Program, Section 2.5, Table 2.4-1, and Table 3.5.2-1 of the SQN LRA, are modified as shown with additional text underlined and deleted text lined through.

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ENCLOSURE Sequoyah Nuclear Plant, Units 1 and 2 License Renewal Application Second Annual Update Section 2.5 SCOPING AND SCREENING RESULTS: ELECTRICAL AND INSTRUMENTATION AND CONTROL SYSTEMS Commodity Groups Not Subject to AMR Electrical and I&C Penetration Assemblies All Primary Containment SQN electrical and I&C penetration assemblies, with the exception of penetrations SQN-1-PENE-302-0026-S and SQN-1-PENE-302-0040-S, are in the EQ program (10 CFR 50.49). SQN electrical and I&C penetration assemblies in the EQ program are subject to replacement based on their qualified life, so they are not subject to aging management review. Non-EQ cables and connections to electrical and I&C penetrations are evaluated in the insulated cable and connection commodity group. The pressure boundary function of penetration assembles SQN-1-PENE-302-0026-S and SQN-1-PENE-302-0040-S are included in the evaluation for the Reactor Building in Section 2.4.1.

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ENCLOSURE Sequoyah Nuclear Plant, Units 1 and 2 License Renewal Application Second Annual Update Table 2.4-1 Reactor Building Components Subject to Aging Management Review Component Intended Function Elastomers and Other Materials Lower inlet doors Direct flow Heat sink Insulation Missile barrier Shelter or protection Support for Criterion (a)(1) equipment Support for Criterion (a)(3) equipment Moisture barrier Direct flow Shelter or protection Support for Criterion (a)(1) equipment Primary containment electrical Pressure Boundary penetration seals and sealant Seal between the upper and lower Support for Criterion (a)(1) equipment compartments (divider barrier)

Service level I coatings Support for Criterion (a)(2) equipment E 3 of 4 CNL-15-164

ENCLOSURE Sequoyah Nuclear Plant, Units 1 and 2 License Renewal Application Second Annual Update Table 3.5.2-1 Reactor Building Summary of Aging Management Evaluation Table 3.5.2-1: Reactor Building Structure and/or Aging Effect Aging Component or Intended Requiring Management NUREG- Table 1 Commodity Function Material Environment Management Program 1801 Item Item Notes Service level I SNS Coatings Air - indoor Loss of coating Protective Coating II.A3.CP-152 3.5.1-34 A coatings uncontrolled integrity Monitoring and III.A4.TP-301 3.5.1-73 Maintenance Primary PB Elastomer Air - indoor Loss of sealing Containment Leak II.A3-1 CP- 3.5.1.33 A containment uncontrolled Rate 41 electrical penetration seals and sealants E 4 of 4 CNL-15-164