ML091350073
| ML091350073 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/28/2009 |
| From: | David Wright Plant Licensing Branch II |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| Wright D, NRR/DORL, 301-415 -1864 | |
| References | |
| GL-04-002, TAC MC4696, TAC MC4697 | |
| Download: ML091350073 (2) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 r~ay 28, 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, REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 2004-02 (TAC NOS. MC4696 AND MC4697)
Dear Mr. Christian:
By letters dated February 29,2008, and February 27,2009 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML080650563 and ML090641038, respectively),
Virginia Electric and Power Company (Dominion, the licensee) submitted supplemental responses to Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors," for North Anna Power Station, Unit Nos. 1 and 2 (NAPS 1 and 2). The Nuclear Regulatory Commission (NRC) staff has reviewed your submittals with a process that involved a detailed review by a team of 10 subject matter experts, with focus on the review areas described in the NRC's "Content Guide for Generic Letter 2004-02 Supplemental Responses," (ADAMS Accession No. ML073110389). The review process also included a separate review of your submittals informed by inputs from the subject matter experts that focused on whether you have demonstrated overall that your corrective actions for GL 2004-02 are adequate.
The NRC staff has no further questions at this time regarding the performance of the emergency core cooling system strainers at NAPS 1 and 2. This conclusion is directly attributable to the detailed and comprehensive information you provided to the NRC staff for review, and to your use of a testing and evaluation process that allowed the NRC staff to obtain reasonable assurance of your compliance with the applicable regulations.
The NRC staff needs one additional set of information to close GL 2004-02 for NAPS 1 and 2.
This information need, regarding in-vessel downstream effects and the use of Topical Report WCAP-16793, "Evaluation of Long-Term Cooling Considering Particulate, Fibrous and Chemical Debris in the Recirculating Fluid," is adequately captured in a commitment you made in the letter dated February 27,2009, referred to above. However, given that the draft WCAP-16793 Revision 1 is now available to licensees and it is the best available industry information of which the NRC staff is aware regarding plant susceptibility to this issue, please review NAPS 1 and 2 againstthe draft W CAP-16793 criteria if you have not already done so. Additionally, please inform the NRC staff of the planned actions if the results of the evaluation show that NAPS 1 and 2 are not bounded by the draft WCAP-16793. While the NRC staff has not yet issued a final safety evaluation for WCAP-16793, it is prudent for licensees such as Dominion who plan to rely on the topical report to evaluate their plant-specific conditions against the draft report.
D. Christian
- 2 If you have any questions regarding this matter, please contact me at (301) 415-1864.
pC:A_~~
Donna N. Wright, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket l\\Ios. 50-338 and 50-339 cc: Distribution via Listserv
'.. ML091350073 OFFICE NRRlLPL2-1/PM NRRlLPL2-1/LA NRRlSSIB/BC NRRlCSGB/BC OGC NRRlLPL2-1/BC NAME DWright MO'Brien MScott MGavrilas BHarris MWong DATE 5/18/09 5/18/09 5/18/09 5/19/09 5/26/09 5/28/09