CY-13-007, Independent Spent Fuel Storage Installation - Report of 10 CFR 72.48 Changes, Tests, and Experiments from January 1, 2011 Through December 31, 2012

Independent Spent Fuel Storage Installation - Report of 10 CFR 72.48 Changes, Tests, and Experiments from January 1, 2011 Through December 31, 2012

ML13039A283
Person / Time
Site:	Haddam Neck  File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	01/30/2013
From:	Buerger B Connecticut Yankee Atomic Power Co
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
CY-13-007
Download: ML13039A283 (2)

Text

• CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD

• EAST HAMPTON, CT 06424-3099 January 30, 2013 CY-13-007 10 CFR 72.4 and 10 CFR 72.48 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 - 0001 Connecticut Yankee Atomic Power Company Haddam Neck Plant Independent Spent Fuel Storage Installation NRC License No. DPR-61 (NRC Docket Nos. 50-213 and 72-39)

Subject:

Report of 10 CFR 72.48 Changes, Tests, and Experiments In accordance with 10 CFR 72.48(d)(2), Connecticut Yankee Atomic Power Company is required to submit to the NRC a brief description of any changes, tests or experiments made pursuant to 10 CFR 72.48(c), including a summary of the evaluation of each. This report covers the period from January 1, 2011 through December 31, 2012. The attachment to this letter provides the summary of the changes and the evaluations made, during that time period pursuant to paragraph (c) of 10 CFR 72.48.

This letter contains no regulatory commitments.

If you have any questions regarding this submittal, please do not hesitate to contact me at (860) 267-6426 ext. 303.

Nstfully, Brantle Buerger, PE ISFSI lanager

Attachment:

Summary of Changes and Evaluations Made in Accordance with 10 CFR 72.48(c) cc: W. M. Dean, NRC Region I Administrator M. S. Ferdas, Chief, Decommissioning Branch, NRC, Region 1 J. Goshen, NRC Project Manager,,Haddam Neck Plant E. L. Wilds, Jr, Director, CT DEEP, Radiation Division

Attachment to CY-13-007 Summary of Changes and Evaluations Made in Accordance with 10 CFR 72.48(c) 10 CFR 72.48 Evaluation Number 11 Revision 0 Summary of Proposed Change The 15 kilowatt (kW) Propane Generator that provides backup power to the Haddam Neck Plant (HNP)

Independent Spent Fuel Storage Installation (ISFSI), Security Alarm Station (SAS), and VB-I Guard Shack will be replaced with a 49 kW Diesel Generator.

Summary of 10 CFR 72.48 Evaluation The change will improve the reliability of site power when a Loss of Utility Power occurs. The Diesel Generator will provide power to areas of the site in addition to the HNP ISFSI, SAS, and VB-I Guard Shack. The change does not affect:

• Any evaluations of accidents or malfunctions made in the NAC International (NAC) - Multi-Purpose Canister System (MPC) Final Safety Analysis Report (FSAR) (NAC-MPC FSAR).

• Creation of a new type of event not previously evaluated in the NAC-MPC FSAR.

• Fission Product Barriers as described in the NAC-MPC FSAR.

" Evaluation Methodologies described in the NAC-MPC FSAR.

10 CFR 72.48 Evaluation Number 11 Revision 0 Summary of Proposed Change The 10 CFR 72.212 Evaluation Report for the HNP ISFSI was revised to incorporate Amendment 5 to the NAC-MPC Certification of Compliance (CoC) No. 1025, regulatory changes to 10 CFR 72.212, correct typographical errors (i.e., correcting title for the Quality Assurance Program, restoring Attachment C to the 10 CFR 72.212 Report, and adding reviewer and approver signatures to the cover page of the 10 CFR 72.212 Evaluation Report), and historical errors (i.e. updating references to procedures, updating references to regulations in 10 CFR 73.55, and adding Attachment D to define NAC generated 10 CFR 72.48 Evaluations adopted for use at the HNP ISFSI).

Summary of 10 CFR 72.48 Evaluation The changes to the 10 CFR 72.212 Report involved incorporating an NRC approved revision to NAC-MPC CoC No. 1025, changes to NRC regulations, and administrative corrections (typographical and historical errors).

The proposed changes do not:

• Affect an accident or malfunction of a structure, system, or component previously evaluated in the NAC-MPC FSAR.

• Create a new type or event not previously evaluated in the NAC-MPC FSAR.

" Result in exceeding or altering a design basis limit for a fission product barrier described in the NAC-MPC FSAR.

• Result in a departure from a method of evaluation described in the NAC-MPC FSAR.

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