ML083300152

10 CFR 50.46 - Annual Report of Non-Significant Changes

ML083300152
Person / Time
Site:	Sequoyah
Issue date:	11/24/2008
From:	James Smith Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML083300152 (3)

Text

November 24, 2008

10 CFR 50.46

U.S. Nuclear Regulatory Commission

ATTN: Document Control Desk

Washington, D.C. 20555-0001

Gentlemen:

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority (TVA) ) 50-328

SEQUOYAH NUCLEAR PLANT (SQN) - 10 CFR 50.46 ANNUAL REPORT OF NON-SIGNIFICANT CHANGES

References:

1. TVA letter to NRC dated November 14, 2007 Sequoyah Nuclear Plant (SQN) - 10 CFR 50.46 Annual Report Of Non-Significant Changes

2. TVA letter to NRC dated June 3, 2008, "Sequoyah Nuclear Plant (SQN) - 10 CFR 50.46 Day Special Report of Significant

Changes"

3. TVA letter to NRC dated June 4, 2008, "Sequoyah Nuclear Plant (SQN) - 10 CFR 50.46 Day Special Report of Significant

Changes"

4. TVA letter to NRC dated October 29, 2008, "Sequoyah Nuclear Plant (SQN) - 10 CFR 50.46 30-Day Special Report of Significant Changes

- Unit 1"

The purpose of this letter is to provide the current status of the calculated peak cladding

temperature (PCT) for the SQN emergency core cooling system (ECCS) evaluation model. This submittal satisfies the annual reporting requirements in accordance with

10 CFR 50.46(a)(3)(ii). The enclosure contains a summary of the changes to the

calculated PCT made and submitted to NRC in the references. No changes have

occurred since the special report that was submitted under Reference 4. There were no

further changes in the ECCS evaluation model for the 2008 annual reporting period.

U.S. Nuclear Regulatory Commission Page 2 November 24, 2008

There are no regulatory commitments in this letter. Please direct questions concerning

this issue to me at (423) 843-7170.

Sincerely, Original signed by James D. Smith

Manager, Site Licensing and

Industry Affairs

Enclosure

cc (Enclosure):

Mr. Brendan T. Moroney, Senior Project Manager

U.S. Nuclear Regulatory Commission

Mail Stop 08G-9a

One White Flint North

11555 Rockville Pike

Rockville, Maryland 20852-2739

ENCLOSURE TENNESSEE VALLEY AUTHORITY (TVA)

SEQUOYAH NUCLEAR PLANT (SQN)

UNITS 1 AND 2 10 CFR 50.46 ANNUAL REPORT OF NON-SIGNIFICANT CHANGES In accordance with the annual reporting requirements of 10 CFR 50.46 (a)(3)(ii), the following is a summary of the limiting design basis accident (loss-of-coolant accident) analysis results

established using the current SQN emergency core cooling system (ECCS) evaluation model.

Large Break Loss of Coolant Accident (LB LOCA)

PCT Previous Licensing Basis PCT 2197 degrees F

(Reference 1)

Reanalysis using AREVA realistic analysis - 195 degrees F methodology (References 2 and 4)

Updated Licensing Basis PCT 2002 degrees F

Net Change - 195 degrees F

Small Break Loss of Coolant Accident (SB LOCA)

PCT Previous Licensing Basis PCT 1162 degrees F

(Reference 1)

Reanalysis for revised ECCS pump +241 degrees F

performance and core power peaking

analytical input assumptions. (Reference 3)

Updated Licensing Basis PCT 1403 degrees F

Net Change +241 degrees F

The limiting calculated fuel cladding temperature for the LBLOCA was determined to be

2002 degrees Fahrenheit based on the Unit 2 analysis. This result represents a net reduction in

the calculated PCT from the previous analysis of record of 195 degrees Fahrenheit.