Letter Sequence RAI |
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MONTHYEARML0603807082006-02-0909 February 2006
RAI, 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
ML0818400612008-06-24024 June 2008
Request for Extension of Corrective Actions Completion Date for NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: Request
ULNRC-05521, Request for Extension of Corrective Actions Completion Date for NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2008-06-24024 June 2008
Request for Extension of Corrective Actions Completion Date for NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
Project stage: Request
ML0818503552008-06-27027 June 2008
Attachment, Summary of Telephone Conference Regarding Request for Extension of Completion of Corrective Actions for NRC Generic Letter 2004-02
Project stage: Request
ML0818503312008-06-27027 June 2008
Email Response from Scott Maglio to Mohan Thadani, Jack Donahew, Leon Whitney Generic Letter - 2004 - 02
Project stage: Other
ML0818406062008-07-0303 July 2008
Approval of Second Extension Request for Corrective Actions GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
Project stage: Other
ML0920101222008-12-18018 December 2008
Request for Additional Information, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: RAI
ML0920101192008-12-18018 December 2008
Email Re Request for Additional Information, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: RAI
ET 08-0053, Corporation Response to 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 Reactors2008-12-22022 December 2008
Corporation Response to 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: Response to RAI
ML0919704342009-06-22022 June 2009
Draft Request for Additional Information Generic Letter 2004-02
Project stage: Draft RAI
ML0919704232009-06-22022 June 2009
Email Draft Request for Additional Information Generic Letter 2004-02
Project stage: Draft RAI
ML0920306202009-07-31031 July 2009
Notice of Forthcoming Conference Call with Union Electric Company and Wolf Creek Nuclear Operating Company Re Draft Requests for Additional Information on Generic Letter 2004-02 for Callaway Plant and Wolf Creek Creek Generating Station
Project stage: Draft RAI
ML0920306282009-07-31031 July 2009
Request for Additional Information (RAI) Regarding Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (Tac No. MC4731)
Project stage: RAI
ML0922205722009-08-27027 August 2009
Request for Additional Information Related to Generic Letter 2004-02, Potential Impact of Debris Blockage of Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: RAI
ML0924607142009-09-28028 September 2009
Summary of Meeting with Union Electric Co., and Wolf Creek, to Discuss Draft Requests for Additional Information on GL 2004-02 for Callaway, Unit 1, and Wolf Creek
Project stage: Draft RAI
ML0928003162009-10-16016 October 2009
Notice of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02 Sent 7/31/0209 and 8/27/2009, Respectively
Project stage: RAI
ML0929300152009-10-20020 October 2009
Revised Notice of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02
Project stage: RAI
ULNRC-05668, Request for Extension of Response Date to NRC Request for Additional Information Re Responses to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at PWRs2009-11-24024 November 2009
Request for Extension of Response Date to NRC Request for Additional Information Re Responses to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at PWRs
Project stage: Request
ML0932903202009-11-24024 November 2009
Request for Extension of Response Date to NRC Request for Additional Information Re Responses to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at PWRs
Project stage: Request
ML0933805662009-12-17017 December 2009
Summary of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02 Sent 7/31/2009 and 8/27/2009, Respectively
Project stage: RAI
ULNRC-05989, Path Forward for Resolution of GSI-1912013-05-16016 May 2013
Path Forward for Resolution of GSI-191
Project stage: Request
ML13263A1682013-09-23023 September 2013
Request for Additional Information, Closure of Option 2 to Address In-Vessel Mitigative Measures for Potential In-Vessel Blockage; Related to Generic Safety Issue 191
Project stage: RAI
ULNRC-06045, Response to Request for Additional Information Closure of Option 2 to Address In-Vessel Mitigative Measures for Potential In-Vessel Blockage2013-10-31031 October 2013
Response to Request for Additional Information Closure of Option 2 to Address In-Vessel Mitigative Measures for Potential In-Vessel Blockage
Project stage: Response to RAI
2009-11-24
[Table View] |
Text
From:
Thadani, Mohan Sent:
Thursday, December 18, 2008 3:40 PM To:
Internet:; Internet:
Cc:
Leon Whitney; Scott, Michael; Harrison, Donnie
Subject:
FW: Callaway GL 2004-02 RAIs Attachments:
Callaway RAIs.doc Importance:
High Scott/Tom:
By letter dated February 29, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML080810491), Union Electric Company (the licensee) submitted a supplemental response to Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, for Callaway.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensees submittals.
The process involved detailed review by a team of approximately 10 subject matter experts, with a focus on the review areas described in the NRCs Content Guide for Generic Letter 2004-02 Supplemental Responses (ADAMS Accession No. ML073110389). Based on these reviews, the staff has determined that additional information is needed in order to conclude that there is a reasonable assurance that GL 2004-02 has been satisfactorily addressed for Callaway. The attached document describes these requests for additional information (RAIs).
The NRC requests that the licensee respond to these RAIs within 90 days of the date of the formal letter. However, the NRC would like to receive only one response letter for all RAIs with exceptions stated below. If the licensee concludes that more than 90 days are required to respond to the RAIs, the licensee should request additional time, including a basis for why the extension is needed.
If the licensee concludes, based on its review of the RAIs, that additional corrective actions are needed for GL 2004-02, the licensee should request additional time to complete such corrective actions as needed. Criteria for such extension requests are contained in SECY-06-0078 (ADAMS Accession No. ML053620174), and examples of previous requests and approvals can be found on the NRCs sump performance website, located at:
http://www.nrc.gov/reactors/operating/ops-experience/pwr-sump-performance.html.
Any extension request should also include results of contingency planning that will result in near term identification and implementation of any and all modifications needed to fully address GL 2004-02. The NRC strongly suggests that the licensee discuss such plans with the staff before formally transmitting an extension request.
The exception to the above response timeline is RAI 17 in the enclosure. The NRC staff considers in-vessel downstream effects to not be fully addressed at Callaway, as well as at other pressurized water reactors. The licensee's submittal refers to draft WCAP-16793-NP, Evaluation of Long-Term Cooling Considering Particulate, Fibrous, and Chemical Debris in the Recirculating Fluid. At this time, the NRC staff has not issued a final safety evaluation (SE) for WCAP-16793.
The licensee may demonstrate that in-vessel downstream effects issues are resolved for Callaway, by showing that the licensees plant conditions are bounded by the final WCAP-16793 and the corresponding final NRC staff SE, and by addressing the conditions and limitations in the final SE. The licensee may also resolve RAI 17 by demonstrating, without reference to WCAP-16793 or the NRC staff SE, that in-vessel downstream effects have been addressed at Callaway. The specific issues raised in RAI 17 should be addressed regardless of the approach the licensee chooses to take.
The licensee should report how it has addressed the in-vessel downstream effects issue and the associated RAI referenced above within 90 days of issuance of the final NRC staff SE on WCAP-16793. The NRC staff is currently developing a Regulatory Issue Summary to inform licensees of the staffs expectations and plans regarding resolution of this remaining aspect of Generic Safety Issue 191, Assessment of Debris Accumulation on PWR Sump Performance.
Please review the attached RAI, and let me know when you would like to discuss the RAI with the NRC's subject experts for any clarifications needed on the RAI. I will setup a phoncon at mutually convenient time.
Thanks.
Mohan C Thadani Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-1476 Mohan.Thadani@nrc.gov
