ML050960303

Evaluation Biennial Summary Report for 2003 / 2004

ML050960303
Person / Time
Site:	Yankee Rowe
Issue date:	03/30/2005
From:	Jesse Rollins Yankee Atomic Electric Co
To:	Document Control Desk, NRC/FSME
References
BYR 2005-027
Download: ML050960303 (5)

Text

YANKEE ATOMIC ELECTRIC COMPANY Telephone (413) 424-5261 49 Yankee Road, Rowe, Massachusetts 01367 YANAK.E March 30, 2005 BYR 2005-027 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

References:

1. License No. DPR-3 (Docket No. 50-29)

2. Docket No. 72-31

Subject:

10CFR72.48 Evaluation Biennial Summary Report for 2003 / 2004 In accordance with IOCFR72.48(d)(2), Yankee Atomic Electric Company (YAEC) herewith submits the enclosed 10CFR72.48 Evaluation Biennial Summary Report for 2003 and 2004. This report summarizes those evaluations associated with facility changes, tests and experiments implemented at the Yankee Nuclear Power Station (YNPS) without prior NRC approval as allowed under the provisions of 10CFR72.48.

Should you have any questions regarding this submittal, please contact the undersigned at (413) 424-2300.

Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY Jack D. Rollins Regulatory Affairs Manager

Enclosure:

10CFR72.48 Evaluation Biennial Summary Report for 2003 / 2004 cc: Mr. R. Bellamy, USNRC, Region I Mr. J. Kottan, USNRC, Region I Inspector Mr. J. Hickman, NMSS Project Manager Nrr 5ss 1

YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATION (YNPS)

(DOCKET NO. 50-29)

(DOCKET NO. 72-31) 10CFR72.48 EVALUATION BIENNIAL

SUMMARY

REPORT FOR 2003 / 2004

S -

10CFR72.48 EVALUATION BIENNIAL

SUMMARY

REPORT FOR 2003 / 2004 TABLE OF CONTENTS TITLE PAGE Table of Contents 1 A. Evaluation No. 03-01 (Rev. 0, 1 and 2), YNPS Demolition Phase I and Phase II (RCA) Design Change Record (DCR) 2 B. Evaluation No. 04-01 (Rev. 0), YNPS 72.212 Report, Revision 3 2 I

i 10CFR72.48 EVALUATION BIENNIAL

SUMMARY

REPORT FOR 2003 / 2004 A. Evaluation No. 03-01. (Rev. 0.1 and 2). YNPS Demolition Phase IA and Phase II (RCA) Design Change Record (DCR)

This DCR covers activities within the RCA including:

• SSC turnover and the above and below grade demolition of the Primary Auxiliary Building, Primary Vent Stack, Primary Vent Stack Monitoring House, PCA Warehouse, PCA Storage Buildings 1 and 2, Waste Disposal Building, Compactor Building, Waste Water Evaporator, Vapor Container, Fuel Transfer Enclosure (FTE), Spent Fuel Building, Turbine Building (use of explosives),

Safe Shutdown Building, Waste Tank Moat Area, Ion Exchange Pit, Diesel Fire Pump / Fire Water Tank, Service Building (portions in RCA), Yard Area Crane and Support Structure, Fuel Oil Transfer House, VC Access/Elevator Tower, Waste Transfer Pump Pit, Fuel Transfer Pit, Fuel Transfer Chute, Storage Tanks (TK-39 and 81)

• The handling, classification, storage, packaging, monitoring, disposal, and documentation of all radiological contaminated waste and mixed waste

• Phase H demolition of specified subsurface structures The controlled and limited use of explosives is included in the demolition methods utilized in this DCR. FSAR Section 200.3.3 (h) requires a specific safety review for use of explosives. This evaluation is limited to the use of explosives for demolition of the Turbine Building only.

The work performed by this DCR is part of the overall decommissioning of YNPS as described in the FSAR. The activities being performed have been determined to have no impact on the spent fuel that has been transferred to dry storage at the ISFSI. All SSCs affected by this change are NNS. Existing FSAR analyses bound all work that will be performed. These activities were determined to not require NRC approval prior to implementation.

B. Evaluation No. 04, (Rev. 0), YNPS 72.212 Report, Revision 3 This evaluation addresses Revision 3 to the YNPS 72.212 Report which was revised to:

• Adopt the NRC approved Amendment 3 of the NAC-MPC CoC and Rev. 3 to the NAC-MPC FSAR for spent fuel storage at YNPS going forward (also applies to plant procedures being revised to meet Amendment 3)

• Reflect completion of fuel loading activities

• Incorporate minor changes, clarification, or deletions of existing text to reflect current conditions This evaluation only addresses spent fuel storage activities going forward. Previous design and fuel loading, transfer, and storage activities were covered by Amendment I to the NAC-MPC CoC and associated exemptions. Revision 3 of the YNPS 72.212 Report 2

incorporates changes that have been previously approved by the NRC through the issuance of Amendment 3 to the NAC-MPC CoC. These activities were determined to not require further NRC approval prior to implementation.

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