ML102020199

Supplemental Information for License Amendment Request - LAR-04-02911 (Alternative Source Term)

ML102020199
Person / Time
Site:	Summer
Issue date:	07/16/2010
From:	Gatlin T South Carolina Electric & Gas Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RC-10-0095
Download: ML102020199 (3)

Text

Thomas D. Gatlin Vice President,Nuclear Operations 803.345.4342 July 16, 2010 A SCANA COMPANY RC- 10-0095 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 SUPPLEMENTAL INFORMATION FOR LICENSE AMENDMENT REQUEST -

LAR-04-02911 (ALTERNATIVE SOURCE TERM)

Reference:

1. SCE&G Letter (ADAMS Accession No. ML090720887) (LAR-04-0291 1) from Mr. Jeffrey B. Archie to USNRC Document Control Desk dated February 17, 2009, "License Amendment and Related Technical Specification Changes to Implement Full-Scope Alternative Source Term in Accordance with 10 CFR 50.67."

South Carolina Electric & Gas Company (SCE&G) hereby submits supplemental information pertaining to the Alternative Source Term License Amendment Request (Reference 1). The attached supplemental information was requested by NRC staff per telecon on July 6, 2010.

Should you have questions, please call Bruce Thompson at (803) 931-5042.

I certify under penalty'of perjurythatitheiforegoing-is true-and correct.

Executed on Thomas D. Gatlin Vice President, Nuclear Operations Virgil C.Summer Station

• Post Office Box 88 -Jenkinsville, SC.29065 - T(803) 345-5209

JHW/JBA/gr Attachments c: (without Attachments unless noted)

K. B. Marsh S. A. Byrne J. B. Archie N. S. Carns J. H. Hamilton R. J. White W. M. Cherry T. P. O'Kelley (w/ Attachment)

P. Ledbetter L. A. Reyes (w/ Attachment)

R. E. Martin (w/ Attachment)

NRC Resident Inspector K. M. Sutton NSRC (w/ Attachment)

RTS (CR-04-0291 1)

File (813.20)

PRSF (RC- 10-0095) (w/ Attachment)

Document Control Desk RC- 10-0095 Page 1 of 1 The accident source inventories for all accidents other than the fuel handling accident were taken from References 1 and 2 using the ORIGEN2 computer code. The major input assumptions used in those analyses are:

- Power level of 2,958 MWt.

- VANTAGE + fuel type.

- Three-region equilibrium core at end of life. The three regions have operated at a specific power of 45.40 MWt/MTU for 480, 960, and 1440 EFPD, respectively.

- Radial peaking factor of 1.7.

- A feed enrichment of 5.0 weight percent U-235.

Note that the same source inventories were previously submitted for Facility Operating License No. NPF-12 Amendment No. 119 in Reference 3 for steam generator replacement.

The accident source inventories for the fuel handling accident were taken from Reference 4 using the SAS2H-ORIGEN-S/ARP computer code. The major input assumptions used in that analysis are:

- Power level of 2,958 MWt.

- W 17x17 fuel type.

- Specific power of 45.00 KW/KGU.

- Fuel exposure ranging from 35,000 to 70,000 MWD/MTU

- Radial peaking factor of 1.7.

- A feed enrichment of 5.0 weight percent U-235.

- 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> cooling time.

Note that the same source inventories were previously submitted for Facility Operating License No. NPF-12 Amendment No. 160 in Reference 5 for spent fuel pool storage expansion.

References:

1) Westinghouse Radiation Analysis Manual for Virgil C. Summer (CGE), Revision 0, December 1992.

2) Westinghouse Radiation Analysis Manual for Virgil C. Summer (CGE), Revision 1, October 1998.

3) Letter from SCE&G to U.S. NRC dated April 30, 1993 "Virgil C. Summer Nuclear Station, Docket No. 50/395, Operating License No. NPF-12, Completed Safety Analysis Results to Support Steam Generator Replacement (REM 6000-7)."

4) SCE&G calculation DC00040-085, Rev. 2 (HOLTEC Report HI-2012648, Virgil C Summer Nuclear Station Radiological Analysis Calculation Package).

5) Letter from SCE&G to U.S. NRC dated July 24, 2001 "Virgil C. Summer Nuclear Station, Docket No. 50/395, Technical Specification Amendment Request TSP 99-0090, Spent Fuel Pool Storage Expansion.