ML14190B342

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:	Rosalyn Jones South Carolina Electric & Gas Co
To:	Document Control Desk, Office of New Reactors
References
NND-14-0393
Download: ML14190B342 (5)

Text

Ronald A. Jones Vice President New Nuclear Operations 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.

SCE&G New Nuclear Deployment P. O. Box 88 MC 800 Jenkinsville, South Carolina 29065 www.sceg.com

Document Control Desk NND-14-0393 Page 2 of 3 In accordance with 10 CFR 50.91, SCE&G is notifying the State of South Carolina of this LAR supplement by transmitting a copy of this letter and its enclosure to the designated state official.

Should you have any questions about this letter, please contact April R. Rice, Manager, Nuclear Licensing, by telephone at (803) 941-9858, or by email at arice@scana.com.

This letter contains no regulatory commitments.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on this ~~ay of -)IiiM!I~__ ' 2014.

DKiRAJ/dk : Supplemental Information Regarding Request for License Amendment 14-03: Tier 2* Editorial and Consistency Changes (LAR 14-03S1) c: Victor McCree Denise McGovern Ravindra Joshi David Jaffe Rahsean Jackson Jim Reece Stephen A. Byrne Jeffrey B. Archie Ronald A. Jones Justin Bouknight April Rice Dean Kersey Matt Kunkle Neil Haggerty Amy G. Aughtman

Document Control Desk NND-14-0393 Page 3 of 3 Margaret Felkel Cynthia Lanier Rhonda OBanion 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-14-0393 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 Licensing Basis Proposed Changes - Public (LAR 14-03S1) 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 Requirements 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:

• Design of concrete slab

- The concrete slab and the steel reinforcement of the composite section are evaluated for normal and extreme environmental conditions. The slab concrete and the reinforcement is designed to meet the requirements of American Concrete Institute standard ACI 349-01 "Code Requirements for Nuclear Safety- Related Concrete Structures."

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