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MONTHYEARML0426100722004-09-13013 September 2004
Plant Engineering Branch Closed Items Interim Safety Basis
Project stage: Request
0CAN030501, Units 1 and 2, 90-Day Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2005-03-0303 March 2005
Units 1 and 2, 90-Day Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: Request
ML0515202862005-06-0202 June 2005
Request for Additional Information (RAI) Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors
Project stage: RAI
ML0603805752006-02-0909 February 2006
RAI Re Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors
Project stage: RAI
ML0603806242006-02-0909 February 2006
Request for Additional Information, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors
Project stage: RAI
ML0726904102007-11-0808 November 2007
Staff Observations of Arkansas Nuclear One, Unit 2, Strainer Testing for Generic Safety Issue 191 During August 13-14, 2007, Trip to Fauske and Associates
Project stage: Other
CNRO-2007-00044, Unit 1 and Arkansas Nuclear One, Units 1 & 2 - Inservice Testing Plan2007-11-30030 November 2007
Unit 1 and Arkansas Nuclear One, Units 1 & 2 - Inservice Testing Plan
Project stage: Request
0CAN020803, Notification of Submission of Final Supplemental Response within 90 Days of Completion of Generic Letter 2004-02 Actions2008-02-28028 February 2008
Notification of Submission of Final Supplemental Response within 90 Days of Completion of Generic Letter 2004-02 Actions
Project stage: Request
ML0817202552008-06-17017 June 2008
/17/2008 E-Mail from N. Mosher, Entergy Operations, Inc. to A. Wang, NRR/DORL/LPL4 Enclosing Draft Request for Extension of Completion Date for Resolution of GL 2004-02 (GSI-191)
Project stage: Draft Request
ML0817202952008-06-17017 June 2008
Draft Request for Extension of Completion Date for Resolution of GL 2004-02 (GSI-191)
Project stage: Draft Request
0CAN090801, GL 2004-02 Final Supplemental Response2008-09-15015 September 2008
GL 2004-02 Final Supplemental Response
Project stage: Request
0CAN020901, Unit 2, Annual Radioactive Effluent Release Report, January 1 Through December 31, 20082009-02-26026 February 2009
Unit 2, Annual Radioactive Effluent Release Report, January 1 Through December 31, 2008
Project stage: Request
ML0911903222009-05-21021 May 2009
Request for Additional Information, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: RAI
2CAN050905, Response to Request for Additional Information for Alternative - PRR-ANO2-2009-12009-05-21021 May 2009
Response to Request for Additional Information for Alternative - PRR-ANO2-2009-1
Project stage: Response to RAI
ML0917508322009-06-26026 June 2009
Notice of Conference Call with Entergy Operations, Inc. to Discuss Draft Request for Additional Information for GL-2004-02 Sent to Arkansas Nuclear One, Units 1 and 2 on June 22, 2009
Project stage: Draft RAI
ML0923706572009-09-0303 September 2009
Summary of Conference Call with Entergy Operations, Inc. on Draft Response to the RAI for GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis
Project stage: Draft RAI
0CAN090901, Arkansas, Units 1 and 2, Generic Letter 2004-02 Final Supplemental Response to Request for Additional Information2009-09-24024 September 2009
Arkansas, Units 1 and 2, Generic Letter 2004-02 Final Supplemental Response to Request for Additional Information
Project stage: Supplement
ML0932004602009-11-23023 November 2009
Request for Withholding Information from Public Disclosure - 8/3/2009 Affidavit Executed by J. Gresham, Westinghouse
Project stage: Withholding Request Acceptance
ML1001903202010-01-26026 January 2010
Generic Letter 2004-02 Supplemental Response
Project stage: Other
2008-06-17
[Table View] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 26, 2010 Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 SUB~IECT:
ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 - GENERIC LETTER 2004-02 SUPPLEMENTAL RESPONSE (TAC NOS. MC4663 AND MC4664)
Dear Sir or Madam:
By letters dated February 28, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML080710544), September 15,2008 (ADAMS Accession No. ML082700499), and September 24,2009 (ADAMS Accession No. ML092720684), you submitted supplemental responses to U.S. Nuclear Regulatory Commission's (NRC's) Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors," for Arkansas Nuclear One, Units 1 and 2 (ANO 1 and 2). The NRC staff has reviewed your submittals with a process that involved a detailed review by a team of 10 subject matter experts, with a focus on the review as described in the NRC's "Content Guide for Generic Letter 2004-02 Supplemental Responses" (ADAMS Accession No. ML073110389). The review process also included, as necessary, a separate "holistic" review of your submittal 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.
We have no further questions at this time regarding your completion of corrective actions for GL 2004-02. In large part this conclusion is based on your September 24,2009, submittal, which addressed the NRC staff's request for additional information conveyed by letter dated May 21,2009 (ADAMS Accession No. ML071190322).
As you may be aware, we have not yet issued a final safety evaluation (SE) on Westinghouse Electric Corporation Topical Report, WCAP-16793-NP, "Evaluation of Long-Term Cooling Considering Particulate, Fibrous, and Chemical Debris in the Recirculating Fluid." Because your GL 2004-02 response refers to and relies on this topical report, we plan to defer issuance of a closure letter to ANO 1 and 2 for GL 2004-02 until the SE isissued for WCAP-16793 later in 2010 and we have assurance that the in-vessel downstream effects issue has been addressed for ANO 1 and 2. We request that you inform us, within 90 days of issuance of that SE, whether ANO 1 and 2 are bounded by the conditions and limitations in the topical report and the corresponding SE. If either ANO 1 or ANO 2 is not bounded by those documents, your submittal should describe actions you plan to take to satisfactorily address in-vessel downstream effects at the affected unit(s).
- 2 If you have any questions, please contact me at 301-415-1480 or via e-mail at kaly.kalyanam@nrc.gov.
Sincerely, q~
N. Kaly Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-313 and 50-368 cc: Distribution via Listserv
ML100190320 OFFICE NRRlLPL4/PM NRRlLPL4/LA NRRlDSS/SSIB/BC NRR/LPL4/BC NRRlLPL4/PM NAME NKalyanam
.IBurkhardt MScott MMarkley CFLyon for NKalyanam DATE 1/21/10 1120/10 1/21/10 1/26/10 1/26/10
