ML14190B342

Virgil C. Summer, Units 2 & 3 LAR 14-03S1, Supplement 1 to Request for License Amendment: Tier 2* Editorial and Consistency Changes

ML14190B342
Person / Time
Site:	Summer, Washington State University
Issue date:	07/09/2014
From:	Jones R A South Carolina Electric & Gas Co
To:	Document Control Desk, Office of New Reactors
References
NND-14-0393
Download: ML14190B342 (5)

Text

SCE&G New Nuclear Deployment July 9, 2014 NND-14-0393 ATTN: Document Control Desk 10 CFR 50.90 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Virgil C. Summer Nuclear Station (VCSNS) Units 2 &

3 Combined License Nos. NPF

-93 and NPF

-94 Docket Nos. 52

-027 & 52-028

Subject:

VCSNS Units 2&3 LAR 14-03S1: Supplement 1 to Request for License Amendment

Tier 2* Editorial and Consistency Changes

References:

1. LAR 14-03 Request for License Amendment: Tier 2* Editorial and Consistency Changes, Dated June 12, 2014 (Accession Number

ML14164A098) In accordance with 10 CFR 50.90, South Carolina Electric & Gas Company (SCE&G), the Licensee for Virgil C. Summer Nuclear Station Units 2&3, requested an amendment to combined operating license (COL) numbers NPF

-93 and NPF

-94 for VCSNS Units 2&3, respectively, in Reference 1. The requested amendment proposed editorial and consistency changes within Tier 2* information contained in the Updated Final Safety Analysis Report (UFSAR)

. On July 3, 2014 SCE&G became aware that Reference 1 misquoted the UFSAR in "Licensing Basis Proposed Changes

- Public (LAR 14-03)" of Reference 1 by omitting a small portion of the text. This misquote occurred on page 3 of Enclosure 2 in the section titled "UFSAR Subsection 3H.3.1, Governing Codes and Standards:" in which the title of American Concrete Institute standard ACI 349-01 was being corrected in the UFSAR to align with the actual title of the standard.

To correct this issue, SCE&G submits Enclosure 4 of this letter which revises page 3 of to include the UFSAR text that was omitted in Reference 1.

The information provided in Enclosure 4 of this letter does not change the scope of, nor affect the Technical Evaluation or the conclusions of the Significant Hazards Consideration determination of the LAR provided in Reference 1. In addition, it does not alter the initial requested approval date.

Ronald A. Jones Vice President New Nuclear Operations

Document Control Desk NND-14-0393 Page 3 of 3 Margaret Felkel Cynthia Lanier Rhonda O'Banion Christopher Levesque Joel Hjelseth Daniel Churchman Brian McIntyre William Hutchins Brian Bedford Tom Geer Michael Frankle Ken Hollenbach Alvis J. Bynum

Marion Cherry

Kathryn M. Sutton Curtis Castell Chuck Baucom AJ Marciano Sean Burk Susan E. Jenkins VCSummer2&3ProjectMail@cbi.com vcsummer2&3project@westinghouse.com DCRM-EDMS@SCANA.COM VCSNNDCorrespondence@scana.com

South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Units 2&

3 NND-1 4-0393 Enclosure 4 (Enclosures 1

-3 provided previously in Reference 1

) Supplemental Information Regarding Request for License Amendment 14-03: Tier 2* Editorial and Consistency Changes (LAR 14-03S1)

NND-14-0393 Enclosure 4 Licensing Basis Proposed Changes

- Public (LAR 14

-03S1) Page 2 of 2 hatch, and the access opening to the annex building. The electrical penetration area, trip switchgears, and other electrical equipment motor control centers occupy most of the floor at elevation 117-6. The floor at elevation 135-3 is used for the storage of main control room air cylinders and provides access to the annex building. The roof for these areas is at elevation 160-6. Areas 5 and 6 include facilities for storage and handling of new and spent fuel. The spent fuel pool, fuel transfer canal, and cask loading and cask washdown pits have concrete walls and floors. They are lined on the inside surface with stainless steel plate for leak prevention.

The Interior structural walls and major floors are constructed using concrete filled steel plate modules, steel form modules, or reinforced concrete. The new fuel storage area is a separate reinforced concrete pit providing temporary dry storage for the new fuel assemblies. A 150

-ton cask handling crane travels in the east

-west direction. The location and travel of this crane prevents the crane from carrying loads over the spent fuel pool to preclude them from falling into the spent fuel pool. Mechanical equipment is also located in this area for spent fuel cooling, residual heat removal, and liquid waste processing. This equipment is generally nonsafety

-related.]* UFSAR Subsection 3H.3.1, Governing Codes and Standards:

Revise Tier 2* information, as shown below:

ACI 349-01, "Code Requirement s for Nuclear Safety

- Related Concrete Structures Structure Steel" (refer to subsection 3.8.4.5 for supplementary requirements and subsection 3.8.4.4.1 for alternative requirements

). UFSAR Subsection 3H.5.2, Composite Structures (Floors and Roof):

Revise Tier 2* information, as shown below:

De sign o f co n c r e t e s l ab - T h e conc rete slab a nd the st e el r ei n fo r c ement of t h e c o mp o site s ecti o n a r e eval u at e d for n o r m a l and e x t r e m e env i r on m e n t a l co n d it i ons. T he s la b c o n c r e t e a nd t he r e i n f o r cement is des i g ned t o m e et the r eq u i r ements o f Ame rican C o nc r e te Inst i tute st a nd a rd ACI 3 4 9-01 "Code R e q ui r e m e nts for Nuclear S af e t y- Rel ate d C o nc r e t e S t ru c t u r e s."