ML090270057
| ML090270057 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 02/05/2009 |
| From: | Stang J Plant Licensing Branch II |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| Wright D, NRR/DORL, 301-415 -1864 | |
| References | |
| TAC ME0264, TAC ME0265 | |
| Download: ML090270057 (3) | |
Text
February 5, 2009 Mr. David A. Christian President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
NORTH ANNA POWER STATION, UNIT NOS. 1 AND 2 - ACCEPTANCE OF REQUESTED LICENSING ACTION RE: PROPOSED LICENSE AMENDMENT REQUEST ADOPTION OF TSTF-490, REVISION 0, REGARDING DELETION OF E BAR DEFINITION AND REVISION TO RCS SPECIFIC ACTIVITY USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (TAC NOS. ME0264 AND ME0265)
Dear Mr. Christian:
By letter dated December 17, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML083530982), Virginia Electric and Power Company (Dominion),
submitted a license amendment request for North Anna Power Station, Unit Nos. 1 and 2 (North Anna 1 and 2). The proposed amendment would replace the current North Anna 1 and 2 technical specification (TS) limit on reactor coolant system (RCS) gross specific activity with a new limit on RCS noble gas specific activity. The noble gas specific activity limit would be based on a new dose equivalent Xe-133 definition that would replace the current E Bar average disintegration energy definition. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff=s acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review.
The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application, including the supplemental information dated January 26, 2009 (ADAMS Accession No. ML090260528), and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed
amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the NRC staff to complete its technical review, you will be advised by separate correspondence.
If you have any questions, please contact Donna Wright at (301) 415-1864.
Sincerely,
/RA/
John Stang, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-338 and 50-339 cc: Distribution via Listserv
ML090270057 OFFICE DORL/LPL2-1/PM DORL/LPL2-1/PM DORL/LPL2-1/LA DORL/LPL2-1/BC NAME DWright JStang MOBrien MWong DATE 1/26/09 2/4/09 2/2/09 2/5/09